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Pelimhwy Criticaifty Analysis of Degraded SNF Accumulations External to a Wate Page (SCPB: NIA)4. TOTAL ?Ac

BBAOOOOOO-01717-0200-W016 REV 00 SLTOTAL ATTACHMENT L1ATTACH&ENT KUM= BELS O1.F PAM IN I

154 See Section 9 . 309 Total Pages_____________

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CRWMS/M&O I Design Analysis Revision Record

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2. DESIGN ANALYSIS TITLE

Preliminry Criicalfty Anahyss of Degraded SNF Acmulaons External to a Waste PackageI. DOCUMENT IDENTIFIER Indutding Rev. No.)

BBA000O00-0 1717-0200-00016 REV 00

4. Revision No. S. Deauiption of Revhlion4

00 . Issued for Release

OAP.3S IElJaeZh, O1�3JI5J 0457 R.v. 12)14053OLU49(IESCOVS 01AW95 ow7 VW. sayJs)

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l. Purpose ............................... .4

2.Quality Assurance .................... ;.,.4

3. Method .................... 4

4. Design Inputs ................... S4.1 Design Parameters .................... S4.2 Criteria ................... 74.3 Assumptions ................. : ; 84.4 Codesand Standards ................. 9

5. References ................................ 9 9

6. Use ofComnputerSoftnare . ............................... 106.1 Scientificand Engineering Software ................................ 106.2 Computational Support Software ................................ 11

7. Design Analysis ................................ 117.1 Background ................................ 117.2 Evaluation Procedure ................................ 127.3 Material Composition Generation ................................ 12

7.3.1 SAS2H Calculations .............................................-. 127.3.2 U(Np)0 Isotopic Compositions ....................................... 157.3.3 Tuff/WateriUO Mixt=e Number Densities .............................. 18

7.4 M CNPCriticality Cases ............................................ 227A. I Optimum Mixtures of Tuff/Water 2 .................. ............... 227A.2 Optimum CriticalSizesand Masses ........................... I ........ 287A.3 NominalCtical Sizesand Masses ..................................... 377A4A Modertor Volume Fraction Effects .................................... 427A..S Additional Cases . ................................................... 45

8. Conclusions ............................................ a

9.Attachzniuts ............................................ 50

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1. Purpose

This study is prepared by the Mined Geologic Disposal System (MODS) Waste Package DevelopmentDepartment (WPDD) to provide input to a separate evaluation on the probablility of criticality in the far-field environment. These calculations are performed in sufficient detail to provide conservativelybounding configurations to support separate probabilistic analyses. The objective of this evaluation is toprovide input to a risk analysis which will show that criticalities involving commercial spent nuclear fuel(SNF) are not credible, or indicate additional measures that are required for the Engineered BarrierSegment (EBS) to make such events incredible. Minimum critical volumes and masses of UOH2 O6Otuffmixtures are determined without application of regulatory safety limits. This study does not address ordemonstrate compliance with regulatory limits.

2. Quality Assurance

The work performed for this analysis is covered by a Waste Package Development (WPD) QualityAssurance Procedure (QAP)-2-0 work control Activity Evaluation entitled '"erform Criticality,Thermal, Structural, and Shielding Analyses" (Ref. 5.1). The QAP-2-0 evaluation determined that suchactivities are subject to Quality Assurance Requirements and Description (QARD) (Ref. 5.2) controls.Applicable procedural controls are listed in the activity evaluation. The waste package is on the Q-List(Ref. 5.3) by direct inclusion by the Department of Energy (DOE) as are the natural barriers of the.Topopah Spring Welded (TSw) Hydrogeologic Unit, the Calico Hills Nonwelded (CHn) HydrogeologicUnit, and the Saturated Zone (SZ) barrier, a QAP-2-3 evaluation has yet to be conducted.

The work reported in this document is part of the neutronic analysis for the preliminary design; thus,design inputs include unqualified data and unconfirmed assumptions. These design inputs will requiresubsequent qualification (or superseding inputs) as the waste package design proceeds. This documentwill not directly support any construction, fabrication, or procurement activity and, therefore, does notrequire initiation of a TBV (to be verified) number for tracking purposes. However, use of any data oroutput from this analysis for-input into documents supporting procur=ent, fabrication, or constructionis required to be controlled as TBV in accordance with appropriate procedures.

3. Method

The SAS2H sequence in SCALE 4.3 (Ref. 5A) is used to calculate the isotopic composition, as afunction of time, for the pressurized water reator (PWR) criticality design basis fuel assembly. Theprime module of this sequence is the ORIGEN-S code. This code does a point depletion of a selectedfuel type with user specified Irradiation conditions. At the completion of the depletion calculation,decay of the irradiated fuel with user specified time intervals is computed.

Number densities for subsequent MCNP cases are calculated using LOTUS 1-2-3 spreadsheets using theORIGEN-S output.

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The multiplication factor (kff) of the fissile materal accumulations is determined using the Monte Carloneutron transport technique implemented in the MCNP (Ref. 5.5) computer program Thie resulting k.fvalues for a variety of configurations are then provided for subsequent evaluation of the criticalitypotential of the disposal package and the aoceptablility of the design in meeting design requirements andcriteria using probabilistic methods.

4. Design Inputs

The design inputs identified in this document are for preliminary design and shall be treated asunqualified data; these design input will require subsequent qualification (or superseding inputs) as thewaste package design proceeds. This document will not directly support any construction, fabrication, orprocurement activity and therefore is not required to be procedurally controlled as TBV.

The dimensions listed in this section and throughout this analysis are in the metric units used directly inthe neutronics codes to facilitate checking and preclude rrors in input.

4.1 Design Parameters

The composition and characteristics of the far-field tuff are shown in Table 4.1-1 (Ref. 5.7, p. 16 unlessotherwise noted).

Table 4.1-1 CALICO HELLSPROW PASS NONWELDED-ZEOLITIC TUFFEarame lcrMean Density 198 samples 1.746 g/cm3*Mean Porosity 127 samples (Max 0.470) 0.306*SiO2 Wt.-frac. 69.17O 2 Wt.-frac. 0.11A120, Wt-frac. 13.4Fe20 WL-frac. 1.13MnOWt.-frac. 0.05MgO Wt.-frac. 0.94CaO WL-frac. 3.22Na20 Wt.-frac. 1.23K20 WL-frac. 2.64P205 Wt.-frac. 0.01LOI (volatile) Wt.-fErac. 8.90Total Wt.-frac. 100.7

* Ref. 5.6, p. 7-1 1

In addition to the above major-element concentrations, 25 trace-element concentrations were identifiedby parts per million by weight (Ref. 5.7, Appendix C). Some of these trace elements have highabsorption cross sections, for example, Eu, Hf, Sm, etc. The impact of these trace elements wereevaluated for possible incorporation into the Tuff concentrations. As noted in Section 7.3.3, it was

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judged that no element contained sufficient concentrations with an adequate confidence in the nominalvalue to be included.

The atomic weights of isotopes used are listed in Table 4.1-2 (Ref 5.8, pp. 941-978).

Z ElemenI Hydrogen

6 Carbon

8 Oxygen8 Oxygen11 Sodium12 Magnesium13 Aluminum14 Silicon19 Potassium20 Calcium22 Titanium25 Manganese26 Iron92 Uranium

93 Neptunium94 Plutonium

SymxHDTCC00NaMgAlSiKCaTiMnFeUUUUUNpPuPuPuPuPuPuAmAmAmCmcmcm

Tab

a

le 4.1.2 LIst o(Ref S.

H-1H-2H-3naturaC-120-16naturalNa-23naturalAl-27naturalnaturalnaturalnaturalMn-55naturalU-233U-234U-235U-236U-238Np-237Pu-238Puz-239Pu-240Pu-241

*Pu-242Pu-243Am-241-Am-242mAmn-243Cm-243Cm-245

*Cm-248

f Isotope'Atomic'8, pp. 941-978)

MCN ID21001.SOC1002.55C1003.50C6000.50C6012.50C8016.50C

1 1023.50C12000.50C13027.50C14000.S0C1900.0.SC20000.50C22000.50C25055.50C26000.55C92233.50C92234.SOC92235.50C92236.50C92238.50C93237.55C94238.50C94239.55C94240.50C9424 1.50C94242.50C94243.35C9524 1.50C95242.50C95243.50C96243.35C96245.35C96248.35C

Weights

1.00782S192.014102223.0160497112.0111512.000015.99491515.999325*22.989770724.31226.981538928.08639.10240.0847.954.938050355.847233.039522234.040904235.043915236.045637238.05077237.048056238.049511239.052146240.053882241.056737242.058725243.061972241.056714242.059502243.061367243.06137245.065371248.0722

95 Americium

96 Curium

* Calculated fiom atomic weights and abundances shown below.

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In addition, the atomic weights of 0-17 and 0-18 are 16.9991314 and 17.999160, respectively (Ref.5.9). The atom percent abundances of 0-16,0-17 and 0-18 are 99.76,0.04 and 0.20, respectively (Ref.5.9).

The atomic weight data listed above comes from handbooks and textbooks (Ref. 5.8. Ref. 5.9) that areutilized industry-wide. ITe data is taken to be established fact that requires no additional qualification.

The theoretical density of UO is 10.96 glcm' (Ref. 5.4, Table M8.2.1).

Avogadro's Number [NA) = 0.602252 (g-mol)Yx1I& (Ref. 5.8, p. 933). A physical constant is taken tobe established fact that requires no additional qualification.

4.2 Criteria

This design analysis provides input for consequence analyses which evaluate whether waste packagedesigns meet the repository criticality control design criteria from requirement documents. TheEngineered Barrier Design Requirements Docunent (EBDRD, Ref. 5.10) has rquirements whichpertain to criticality analyses. These requirements apply to accumultons of fissile material in the far-field because far-field consequences can have an impact on the WP design. The WP is the source formaterial in the far-field and mitigation of significant consequences in the far-field may require somemodification of the WP (Engineered Barrier) design. The requirements cited in Reference 5.10 that havebearing on this analysis include the following:

4.2.1 From the EBDRD (Ref. 5.10);"3.2.6 CRITICALITY PROTECTION

A. The Engineered Barrier Segment shall be designed to ensure that a nuclear criticalityaccident is not possible unless at least two unlikely, independent, and concurrent orsequential changes have occurred In the conditions essential to nuclear criticality safety.Each systemashall be designed for criticality safety under normal and accident conditions.The calculated effective multiplication factor must be sufficiently below unity to show atleast a five percent margin, after allowance for the bias In the method of calculation andthe uncertainty in the experiments used to validate the methods of calculation.

[MGDS-RD 3.2.2.6.A][10CFR60.131(b)(7)J

B. To mitigate the potential for nuclear criticality, the Engineering Barrier Segment shall bedesigned and constructed to comply with the nuclear criticality requirements specified byDOE order 6430.1A, 1300-4.

[MGDS-RD 3.2.2.6B] [DOE Order 6430.IA. 1300-4]"

The present DOE and Civilian Radioactive Waste Management System (CRWMS) Management andOperating Contractor (M&O) management position is that the requirements cited in the above criteriabased on 10CFR60.131(b)7, being primarily of a deterministic nature, is not appropriate for postclosure

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disposal criticality analysis. Instead, the probability or risk based approach has been recommended tothe U.S. Nuclear Regulatory Commission (NRC) in the following two letters:

4.2.2 From Ronald A. Milner, Director, Office of Program Management and Integration, Office ofCivilian Radioactive Waste Management (OCRWM), to the NRC, Docketing and ServiceBranch, dated June 16, 1995 iRef, S.I1), which included the specific recommendation to applythe above requirements only to preclosure, and create the following new requirement forpostclosure criticality:

"Postclosure criticality safety. The engineered barrier system shall be designed such that theprobability and consequences of nuclear criticality provide reasonable assurance that theperformance objective of §60.112 Is met." (Ref. 5.11)

4.2.3 From Stephan J. Brocoum, Assistant Manager for Suitability and Licensing, OCRWM, toMichael J. Bell, Chief, Engineering and Geosciences Branch, Division of Waste Management,Office of Nuclear Material Safety and Safeguards, NRC (Ref. 5.18), which referred to the abovereferenced letter, and specifically commented as follows:

"The DOE, therefore, requests that consideration be given to the DOE's proposed revision to1OCFR60.131(b)7 that would allow disposal criticality to be evaluated with risk-based methods."(Ref. 5.18)

The analyses in this document are intended to provide input to consequence analyses whose output willbe used as part of TSPA-VA to demonstrate compliance with the performance objective of §60.112.This study focuses on supporting a probabilistic analysis which will evaluate the probability of criticalityof these accumulations rather than conformance with regulatory limits. Therefore, no regulatory safetymargins are applied in calculating critical parameters in this study. This document will not directlysupport any construction, fabrication, or procurement activity.

4.3 Assumptions

4.3.1 Principal Isotope (PI) burnup credit is an acceptable criticality control mechanism for the wastepackage. (CDA Key 009) (Ref. 5.12). This assumption is used throughout Section 7.

4.3.2 Water infiltration has provided the mechanism for waste package and SNF degradation, as wellas the mechanism for actinide transport to the far-field environment This assumption is usedthroughout Section 7.

4.3.3 Only uranium and neptunium oxide accumulations are investigated. The transport of materialfrom the waste package will likely occur over hundreds of thousands of years in which time theplutonium would have decayed to uranium or neptunium and an unknown fraction of the fissionproducts would have been stripped away. This assumption is used throughout Section 7.

4.3.4 The fresh fuel bias and uncertainty for MCNP is approximately 0.015. This uncertainty was usedin a prior unqualified analysis (Ref. 5.13, p. 6-221) and is appropriate for application toaccumulations of U(Np)02 . This assumption is used throughout Section 7A.

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4.3.5 The material compositions for tuff in the far-field Is assumed to be represented by the majorconstituents of Calico HillsfProw Pass nonwelded-zeolitic tuff taken from References 5.6 and5.7. Portions of these formations fall within the saturated zone. This assumption is usedthroughout Section 7.

4.3.6 The accumulation of U02 in saturated tuff is assumed to be rersnted by a sphericalhomogeneous mixture of UO0uffwater. This is a reasonable geometry given that fracturedistributions and densities in the tiff, size and density of potential uranium deposits, andpresence and composition of reducing zones within the tuff are unknown. This assumption isused throughout Section 7.

4.3.7 The U(Np)0 is accumulated at the thoiretical maximum density of UO (natural U) of 10.96g/cn? (Ref. 5A, Table M8.2. 1). This is conservative because the least amount of other material isdisplaced. This assumption is used throughout Section 7.

4A Codes and Standards

American National Standard on Criticality Safety Criteria for the Handling, Storage, andTransportation of LWR Fuel Outside Reactors", ANSJ/ANS4. 17, 1984.

5. References

5.1 "Perform Criticality, Thermal, Structural, and Shielding Analyses," Document Identifier (DI) #h.BBOOOOOOO-01717-2200-00025 REV 02, Civilian Radioactive Waste Management System(CRWMS) Management and Operating Contractor (M&O).

5.2 "Quality Assurance Requirements and Description (QARD)," DOE/RW-0333P Rev 5, U. S.Department of Energy (USDOE) Office of Civilian Radioactive Waste Management (OCRWM).

5.3 "Yucca Mountain Site Charactizaton Project Q-lst," YMP/90-55Q, REV 3, Yucca MountainSite Characterization Project

5A SCALEA 4.3 RSIC Computer Code Collection, CCC-545, Oak Ridge National Laboratory,October 1995.

5.5 MCNP 4A - Monte Carlo N-Paticle Trnspt Code System, RSIC Computer Code Collection,CCC-200, Oak Ridge National Laboratory, February 1994.

5.6 'Total-System Performance Assessment for Yucca Mountain - SNL Second Iteration TSPA-1993)", Volume 1, Michael L Wilson, et al., SAND93-2675, April 1994, pp. 7-11.

5.7 "Chemistry of Diagenetically Altered Tuffs at a Potential Nuclear Waste Repository, YuccaMountain, Nye County, Nevada", David E. Broxton, et al., LA-10802-MS, October 1986, pp. 16,52.

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5.8 Nl Mnical FnginQ, 2nd Edition, Manson Benedict, Thomas H. Pigford, and Hans W.Levi McGraw-Hill Book Company. New York NY, 1981.

5.9 Nuclides and Ism=, Fourteenth Edition, GE Nuclear Energy, 1989.

5.10 Engineered Barrier Design Requirements Documewn, YMPICM-0024, REV 0, ICN 1, YuccaMountain Site Characterization Project.

5.11 Letter, RA. Milner to Secretary, U.S. NRC Docketing and Service Branch, Transmitting DOEcomments regarding NRC-proposed revisions to 10 CFR Part 60 Regulations for Design BasisEvents, June 16, 1995.

5.12 "Controlled Design Assumptions (CDA) Document," DI#: BOOWOOODO17174600-0032 REV03, CRWMS M&O.

5.13 "Initial Summary Report for Repository/Waste Package Advanced Conceptual Design," DI#:BOOOOOOO-01717-5705-O00015 REV 00, CRWMS M&O, p. 6-221.

5.14 "SCALE4.3 and MCNP4A Installation," Interoffice Correspondence LV.WPJWD.06/96.135, J.Wesley Davis, June 11, 1996, CRWMS M&O

5.15 American National Standard on "Criticality Safety Criteria for the Handling, Storage, andTransportation of LWR Fuel Outside Reactors", ANSIIANS-8.17, 1984.

5.16 "SAS2H Generated Isotopic Concentrations for B&W 15x15 PWR Assembly," DI#:BBA0000-01717-0200-00012 REV 00, CRWMS M&O.

5.17 "Probabilistic Exteal Criticality Evaluation," DI#: BB0000-01717-0200-00037 REV 0O,CRWMS M&O.

5.18 Letter, SJ. Brocoum to MJ. Bell, Providing DOE acknowledgment of receipt of NRC commentson the Annotated Outine for the Disposal Criticality Analysis Topical Report, April 12, 1996.

6. Use of Computer Software

6.1 Scientific and Engineering Software

SCALE 4.3 has not been qualified according to QA procedures. The results of this analysis, therefore,shall be treated as unqualified data. SCALE 4.3 was run on HP Series 735 Workstations.

SCALIE 4.3 is an appropriate tool to be utilized to determine the composition and characteristics of PWRspent fuel and has been demonstrated to run correcty on the HP 735 Workstations (Ref. 5.14).

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MCNP4A was not qualified when this analysis began but was in the process of being qualified. Theresults from MCNP4A shall be treated as unqualified data. MCNP4A was run on HP 735 Workstations.

MCNP4A is utilized to determine the criticality potential of fissile material accumulations in the far-field environment external to the repository and is an appropriate tool for this purpose (Ref. 5.14).

There are biases and uncertainties associated with a criticality calculation. How these biases anduncertainties are treated in criticality calculations is covered In the American National Standard on"Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel OutsideReactors" (Ref. S. l5). The fresh fuel bias and uncertainty for MCNP is approximately 0.015. The freshfuel bias and uncertainty is appropriate for application to the external accumulations of fissile materialinvestigated in this analysis.

6.2 Computational Support Software

LOTUS 1-2-3, Release 4.01 for Windows was used to calculate the isotopic number densities for thetuff/water/U0 2 mixtures investigated. Details of the equations used in the spreadheet are provided inSection 7.3.3.

SLIDEWRIGHT PLUS V. 3.0 for WINDOWS was used for plotting the results. The plots withcurvefitting are included in this report

7. Design Analysis

This study was performed to determine the critical masses and concentrations of actinides released frombreached waste packages in the far-field environment. This study will provide input to a risk analysiswhich will show to what extent the SNF waste package concept, in conjunction with the rest of theEngineered Barrier Segment (EBS), meets the regulatory requirements or indicate additional measuresthat ar required for the EBS.

7.1 Background

The modeling of the SNP for evaluations of criticality and reactivity in the far-field is integrated with thescenarios for transport and deposit. The scenarios for SNF transport and deposit begin with theparameter of time. For SNF transport, the WP and fuel cladding must be breached and the fuel releasedfrom the repository with the transport mechanism. As noted in the assumptions, the time frame for theanalysis is 100,000 years or more, after closure of the repository. In the 100,000 year period, it isassumed (Assumption 4.3.2) that water in some form has completely degraded the fuel container anddegraded the fuel into elemental (molecular) forms. The water that causes the degradation of thecontainer is assumed to be the transport mechanism that carries the fuel to the far-field. The water isalso assumed to provide the mechanism for separating the actinides (uranium and neptunium) from thestable fission products and daughters of fission product decay.

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7.2 Evaluation Procedure

The evaluation procedure Is broken into two major tasks, with subtasks in each. The general procedureis as follows:

1) Material Composition Generationa) SAS2H Casesb) U(Np)02 isotopic composition calculationc) Number density calculations for Tuff/Water/U0 mixtures using spradsheet

2) MCNP Criticality Casesa) ;.. cases for various burnup/enrichment pairs in various Tuff/Water/UO2 mixtures

which are plotted to identify the optimum (highest k..) mixtreb) k., cases for optimum mixtures identified in previous subtask which ar plotted to

itify minimum critical sizes and masses of mixturesc) k,, cases for nominal mixtures identified in previous subtask which are plotted to

identify nominal critical sizes and masses of mixturesd) lk and kff cases for highest porosity tuff which ar plotted to identify optimum

moderator volume fiactions and indicate magnitude of any positive effects due toreducing water volume fraction

e) k. and ka cases specifically requested to support a separate probabilistic analysis

The results of task I and task 2 ar listed in Sections 73 and 7.4, respectively.

73 Material Composition Generation

SAS2H calculations were first run on six fuel burnuplenrichment pairs to generate compositions in theform of gramstassembly. The six burnupenrichment pairs were chosen to provide an indication of theeffect of reduced effective enrichment on the critical masses to be calculated in this study. The actinidesfrom the SAS2H calculations were then converted to the uranium or Np-237 isotopes into which theydecay and number densities for the resulting oxide were calculated. Tbese fuel number densities alongwith the compositions for tuff and water were then entered into a spreadsheet which was used tocalculate homogenized number densities for the waterhuff/U02 mixtures to be investigated.

73.1 SAS2H Calculations

The base input for the SAS2H cases was taken from a previous QAP-3-9 analysis (Ref. 5.16) for a B&W15x15 fuel assembly with 3% enrichment and 20 GWd/MTU burnup. The burnup conditions used arethe most stressing in order to produce the most reactive burned fuel. Only the minor changes to the basemodel will be discussed in the current calculation.

In order to cover a wide range of the SNF inventory, six different bunup/enrichment pairs (five differentenrichments) were run. The isotopic distribution of the uranium is determined by the given initial

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enrichment and the following empirical relationship (Ref. 5.16):

wt%n, = 0.007731(wt%=s)'m",wt%236= O0.046wt%ns,wt%2 3 = 100% - wt%234 - Wt%US - Wt%2M

Using this formulation, the fresh fuel isotopics for selected Urn enrichments were calculated as shown inTable 7.3.1-1.

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Table 7.3.1-1 Istonic Makeup of Uranium of Selected U-235 Enrichments

U-235 3.0% 3.5% 4.0% 4.2% 4.5%

ISOTOPE

U-234 2-54E-2 3.OOE-2 3.47E-2 3.66E-2 | 3.95E-2

U-236 1.38E-2 1.61E-2 1.84E-2 1.93E-2 2.07E-2

U-238 96.9608 96.4539 95.9469 95.7441 95.4398* The base case in Ref. 5.16 had a minor enror in the U-234 and U-238 wt% calculations - actual valuesused in Ref. 5.16 and this analysis for consistency are 2.40E-2 and 96.9622 for U-234 and U-238,respectively.

Block 4 of the input has Zircaloy-4 entered as an arbitrary material rather than using the predefinedzircaloy as listed in Reference 5.16 because the 44-group cross sections used with SCALE4.3 does notsupport this predefined material.

The EFPD entered in data block 8 (bun=) of the input is a function of burnup as indicated by thefollowing equation:

EFPD = Burnup (MWdJMTU) x (MTU/Assembly) / (MW/Assembly)

From Reference 5.16. the MTU/Assembly is 0.464 and the MW/Assembly is 7.25. The EFPD calculatedfor each burnup is shown in Table 7.3.1-2. All other input is the same as that developed in Reference5.16.

The input and relevant output from each of the six burnup/enrichment pair SAS2H cases are listed inAttachments II-VIL

Table 7.3.1-2 Burnp and Associated EFPD

BURNU 20 30 40 41 53GWd122U

IEFPD 1280 1920 2560 , 2880 3392,

A simplistic identification of the fuel characteristics is expressed by the weight fractions of U-235 andPu-239 relative to the total amount of metal (versus oxide) fuel material. The expression fordetermining the weight fraction of an isotope (1) of the metal fuel is:

Weight Frsction(I) = Atom Fraction(I) * Atomic Weight(Ai) / Metal Atomic Weight

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Table 7.3.1-3 below gives the weight fractions of U-235, Pu-239 and (U-235 + Pu-239) after 1826.25days of decay for three of the six SNF fuel burnuplenrichment pairs. The atom ractdons are calculatedby dividing the "gm-atoms" for a given isotope by the total "gm-atoms" from the SAS2H outputincluded in Attachments JI-VIL

Table 7.3.1-3 U-235 and Pu-239 Weight Fractions

Weight Faction in Fuel Metal

Fuel Characteristics U-235 +1g26.25 Day (5 Yar) Decay 1-235 PE-239- Pu2lh39

3.0 Initial U-23520 GWd Burnup 0.01397 0.00541 0.01938

3.5 Initial U-23530 GWdBurnup 0.01242 0.00631 0.01873

4.0 Initial U-23540GWdBurnup 0.01122 0.00699 0.01821

73.2 U(Np)02 Isotopic Compositions

The uranium and neptunium isotopic compositions in the far-field originate with the six fuelburnuplenrichment pairs that are described above in Section 7.3.1. Attachments II-VII give the SAS2Hresults for the actinide isotopic fractions after decaying for 1826.25 days (5 years). For time periods of100,000 years, the actinides decay to the asymptotic daughter products as shown below in Table 7.3.2-1.The decay chains shown in Table 7.32-1 were constructed from data in Reference 5.9. Atomic weightsare not required in construction of the decay chains so isotopes may appear in Table 7.3.2-1 which arenot listed in Table 4.1-2.

The resulting atom fractions of U-234, U-235, U-236, U-238 and Np-237 for each fuel-burnup type aeapplied to the constant atomic concentration of cubic crystalline U02 to determine the appropriatenumber density for each fuel Isotope as shown in Table 7.3.2-2. The atom fractions are calculated bydividing the "gm-atoms" for a given isotope by the total "gm-atoms" for 5 years decay from the SAS2Houtput included in Attachments IU-VII. These calculations are shown in the spreadsheet included inAtnachment L

The fuel characteristics when deposited in the far-field are modeled as a cubic cystalline U0 2-NpO2structure at 10D% U02 density (10.96 gfcm3 ) in solid solution (molecular mixture) with the tuff material.Only the uranium and neptunium are included in the transport modeling. This provides a simplistic andmore reactive fuel material but eliminates the complexity and the requirements to develop the model andprobabilities that various amounts of other materials will be transported with the fuel. The reactivity ofthe fuel material is limited by the assumptions that (1) the fuel is a molecular mixture (homogeneousmixture, Assumption 4.3.6) with the tuff and not a particulate mixture, and (2) it does not contain water

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in any physical or chemical form, only the tuff contains water (Assumption 43.7).

Table 7.3.2-1 Aecinide Transmrtation Chains

U-234 - Pu-238 - On-242a a

II - 1YD-238

P- Am-242

U-235 -Pa-239 -On-243a a

t - Np-239P

-Am-243 -Pu-243 -On-247 '"q-251a P, a a

U-236 -a

Pu-240 - On-244a

I o Mp-240O U-24DPP

-Pu-244 -On-248 -q-252a a a

U-238 -a

Pu-242 - Qn-246 - q-250a a

Np-237 - Am-241 - Bk-245a a

II -Pu-241 - On-245 - q-249

P a a

The density of the ful deposited in the far-field is bounded by the maximum cubic crystalline density ofU02, 10.96 g/cm' for natural uranium concentrations. Lower fael densities are assumed not to have anyopen porosity. Therefom, the modeling parameter for fuel density is simply fixed at 100% theoreticalfor cubic crystalline U02. Under these conditions, lower density fuel only includes voided space whichdecreases reactivity for finite systems and has no effect on infinite systems.

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___________Table 7.3.2-2 Isotopic Concentrations In The Far-Field

Asymptotic Trnsmuitatons (a 100,000 Years)Fuel Type Cubic Crystalline Concentrations

U-234 U-23S U.236 U-238 Np-237

3.OE-20GWdAtom Fraction .00024 .01956 .00468 .97440 .00112Number Density 5.868062 - 6 4.781608 -4 1.144148 - 4 2.381875 - 2 2.728657 - S(atoms/barn-cm)3.SE-30GWdAtom Fraction .00036 .01893 .00653 .97239 .00179Number Density 8.691609 -6 4.628167 -4 1.597173 - 4 2.376949 - 2 4.37650 - 5

4.OE-40GWdAtom Fraction .00051 .01847 .00825 .97035 .00241NumberDensity 1.246889-5 4.515723 -4 2.017600 - 4 2371969 - 2 5.898417 - 5

4.2E45GWdAtom Fraction .00060 .01791 .00902 .96977 .00270Number Density lA63431-5 4.378063-4 2.204533-4 2.370558 -2 6.599715-5

4.OE-45GWdAtom Fraction .00059 .01676 .00881 .97114 .00270Number Density 1.444231- 5 4.097444 -4 2.153653 -4 2.373895 - 2 6.597651 - 5

4SE53GWdAtom Fraction .00076 .01704 .01012 .96895 .00313Number Density 1.865720-5 4.164425 -4 2.473902-4 2.368540 -2 7.658723-5

NOXC uMi MC numOer IensiuCs were eUcwIuatu vwn Mnc spreadsheet values (no roundon) for atomfractions.

The cubic structure of U02 results in the atomic concentration (atom / barn-cm) being a constant withthe maximum value for 100% teo tical density. The 100% theoretical density and atom fractions ofnatural U02 are used to determine the maximum (constant) atomic concentrations as follows:

NAbtraI U02 (100% Theoreical Density - 10.96 gm/ cm's)

Atom Fracdons

U-234 = O.O00055U-235 - 0.0072U-238 - 0.992745

Atomic Weights (ZInmle)

A234 = 234.040904A2m - 235.043915A2M - 238.05077

.*

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The molecular weight for U0 is calculated from te atomic weights of U and 0 (x 2).

Molecules Atomic Weights (f/mole)

U - 1.0 AU - 238.0289000 = 2.0 A0 = 15.999325

U02 - 1.0 A vo = 270.02755

Mimum Mober Density U0 (N (U0 2 )) = 10.96g/cm' * 602252 m uokles/mole2aximum A~mb Desity ,IND WOO270.02755 glnole

Maximum AD (UO2) = .0244444758 molecules/b-cm

lD (0) = .04888895 atoms/b-cm

ND (U-234 + U-235 + 17-236 + U-238 + NP-237) = .0244444758 aoons/b-cmn

The U02 number density (ND) and atomic weight are used in Attachment I calculations.

7.3.3 TffWater/U02 Mixture Number Densities

As discussed above in Section 7.3.2, the composition of the fuel is uranium dioxide and neptuniumdioxide. This composition does not exist as an independent material in the far-field but as a solidsolution (molecular mixture) with the tuff.

The far-field characteristics that involve increasing reactivity as fuel is deposited in with the tuff are (1)the composition of the tuff, and (2) the open porosity for water saturation. The far-field is composed ofProw Pass nonwelded-zeolitic tuff from the Crater Flat group of the Calico Hills formation (Ref. 5.6 and5.7). The average density and porosity of the tuff along with the weight percent of the compounds arelisted in Table 4.1-1. In addition to the average porosity of 30.6%, upper bounds of 47% (which may beanomalous datum) and 40% porosity are included as nodeling parameters for the tuff. These increasesin porosity are modeled with the appropriate reductions in density. The water that could saturate the tuffhas a maximum density of H2 0 (1.0 glcm') and is modeled to fill the 47% and 40% of the open porosityin the upper bounding porosity models. The nominal porosity is modeled to be saturated with 30% ofthe total volume filled with water (0.6% left void). Evaluations of tuff dry-out were evaluated with 20%of the total volume filled with water (10.6% left void) in the nominal model. and a range of water from47% to 15% in the bounding porosity model.

The atomic concentrations of hydrogen and oxygen in the water are determined as follows.

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molecules

H = 2.0

0 a 1.0

120 - 1.0

Number Disty 120 {IND ( 2 0)} =

Atomic Weights (C/mo&eJ

A R - 1.0078251940 - 15.%99325A51" , 18.014975

1.00 g/CM3 * .6022S2 molecudalmole18.014975 glmok

ND (H) - 6.686126 - 2

N D(0) = 3.343063 -2

Tbe nominal density and porosity of the tuff in the far-field are shown in Table 7.33-1 along with theweight fractions (Wt.-frac.) of the major constituents. The weight fractions of the constituents wereconverted from Table 4.1-1 by eliminating minor and volitile constituents and renolizing. Thisconversion was performed in the sreadsheet included in Attachment L

Table 7.3.3-1 Far-Field Dry Tuff Model(Converted from Table 4. 1-1)

ParameterMean Density (Dry)Porosity (Mean)

SiO2A1203Fe2O3MgOCRONa.0K V20

(Wt.-frac.)(WL.-frac.)(Wt.-frac.)(Wt.-Erac.)(WtL-frac.)(WL.-frac.)(Wt.-frac.)

Value1.746 g/cm!0.306

0.7540.1460.0120.0100.0350.013om2s

0.999Total WtL-fRac.

The number densities for the isotopic concentrations of the dry tuff were performed in the spreadsheetincluded in Attachment I and are evaluated as follows:

Numnber Density x (ND(x)) = 1.746 * Wt.-frac.z * .602252-Atomic Weight (Al)

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Number Denisity (atonulb-omL Atomic Weights (dtormlmole)

AND(O)

MD (SM)

= 2.638683E-2- 1.319341E-2

AN (Si 02) = 1.319341E-2

AD(O)

MD (Al)

- 4.523081E-3= 3.015387E-3

AOA "V

4AJ0 3

A403

AF A

= 15.999325

= 28.086

= 60.08465

= 15.999325- 26.9815389

a 101.9610528

- 15.999325x 55.847

= 159.691975

ND (A40 3 ) = 1.507694E-3

AV(0)AND(Fe)

= 2.43533SE-4= 1.623559E-4

ND(FC20 3) = 8.117793E-5

ND(O)AD((Mg)AD (Mg 0)

- 2.675121E-4= 2.675121E-4= 2.675121E-4

AOA M:

= 15.999325= 24.312

a 40.311325

* hD(O),ND(Ca)AD (C0)

= 6.587122E-4= 6.587122E-4

- 6.587122E-4

40

A C&

A reo

s 15.99932540.0856.079325

JD (O)ND (Na)

ND (Na2O)

ND(O)AD(K)

- 2.276691E-4- 4.553382E-4

- 2.276691E-4

A0AKa

A°'%4 0

Ar

A41;

= 15.999325= 22.9897707

= 61.9788664

15.999325= 39.102

= 94.203325

- 3.2 14995E-4- 6.429990E-4

AD (A0) = 3.214995E-4

In addition to the above major constituents, tmce elements of thorium, samarium, europium, et cetera,were noted to also be constituents of the tuff. These tace elements would reduce the reactivity of thetuff. However, evaluating the effects of 20 parts-per-million (ppm) of thorium and S ppm of samariumwith engineering judgement indicated that the negative reactivity effects were too snall to accuratelyquantify. Tlerefore, the trace lements were not included in the tuff model.

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When the porosity of the tuff is increased to 40% or 47%, the density is reduced. For example, with adensity of 1.746 glcrm and a porosity of 0306 for nominal tuff, a porosity of 0.47 has a density of

Deeity (.47 porosiy no = 1.746 gm/cma * (i.o - .47)1.0 - .306

Delsity(.47 porosity PM) = 1.3334 gm/n 3

The (heterogeneous) isotopic concentrations computed above for the tuff, water and fuel (Section 7.3.2)are for each material as if it existed separately in the far-field. The U03 - NpO2 fuel however isdeposited with some resulting (molecular) mixture volume fraction with the tuff-water. The(homogeneous) isotopic concentrations for the mixture of far-field fuel and tuff-water are determinedusing a LOTUS 1-2-3 spreadsheet (Attachment VM). An example of the spread sheet expression tocompute the isotopic concentrations follows assuming (a) a fuel volume fraction of 0.185 O(b) with acomplementary tuff-water volume fraction of (1.0 - 0.18 ) 0.815 ,and (c) a tuff porosity of 0.47 thatis completely saturated with water.

Far - Fid AD(U 2 -Np0 2)b, =,, = .185 * ND (UO2 A0 2)Raerot

Far-Field AD(TffMaterl)S,, ¢,,,, = .815 * AD(luffMateris),,,,,e,,,,

Far -Feld ND (Water),.,,, = .815 * .47 * ND(Water),,,,,,,

The spreadsheet listing all of the mixtures analyzed is included in Attachment VI.

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7A MCNP Criticality Cases

The analytical modeling of SNF in the far-field has the objective of determining the reactivity and theminimum critical mass. To determine the most reactive conditions and the configurations with theminimal critical mass, the analytical modeling employed separation of spatial and spectral variables.MCNP was used to determine the most reactive fuel and water-tuff conditions for the various fuel-burnup types in an infinite configuration. These optimal conditions of fuel-tuff-water were modeled invarious MCNP configurations to determine the minimum critical mass.

The results from MCNP cases are reported as Off * 2a. kl, is the final estimated combinedcollisionlabsorptiontack-lenghi kd reported in MCNP. 2a is twice the standard deviation of thecalculated value and approximately represents the 95% confidence interval of the result

All material fractions or percents reported in this Section are by volume unless otherwise noted.

7A.1 Optimum Mixtures of TufWater/UO0

Optimum mixtures of tuff/waterlUO% for various burnup/enrichment pairs are identified by running k.cases (reflected sphere) for the mixtures and plotting the results. A curve is fit to the points and the peakis identified from the curve.

Pour water volume variations as described in Section 7.3.3 were run in the MCNP model for the 3.00%enrichment/20 GWdMTU fuel form. The case inputs and relevant outputs are included in AttachmentsIX-XXXM. These case descriptions and results are listed in Table 7.4.1-1. The results are plotted inFigure 7.4.1-1. Three cases for an additional mixture of 30% water and 35% C (50% of tuff replaced byC) were run to demonstrate the reactivity effect of the C. The results for the three additional cases areincluded in Table 7.4.1-1 and on Figure 7.4.1-1.

The optimum U0 2 volume percent for each of the four water volume variations was determined byreading off the U0 2 volume percent corresponding to the peak kIc value from the curves on Figure 7.4.1-1. The optimum U0 2 volume percents are 18.5, 17.0, 15.0, and 11.6 for 47%, 40%, 30%, and 20%water in tuff, respectively.

Nine additional cases were rui to identify the minimum water volume fraction required for criticality tooccur. Criticality was defined as fellows:

CRflICALE I - 0.015 - 2a

Three cases each for 12%, 10%. and 8% U0 2 in a Tuff/Water mixture were run with the results listed inTable 7.4.1-2 and shown Figure 7.4.1-2. In the lower water volume fraction range the 10.0% U03 casehas the highest values of k, Using the relation listed above to define criticality and reading off Figure7.4.1-2, 16.4% water is identified as the lowest volume percent for criticality for 30.6% porosity tuff.

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-

Table 7.4.1-1 Results of 3.00% Enc GWdMTU Fuel Form M ixture Variation k. Cases47% Water 40%water 30% Waer 20% War 30% Water/ 35% C

U02 Ait. taLc 20 AL k. t 2a A. k.t±20 U02 Aut kt2a U0 At.# k.8 2a

S DC 0.8805 t XV 0.8932 a XX1 0.9072 t 5 XXVI 0.9285 a 3.6 X=C O..970 t.002S .0026 .0017 .0019 .0022

8 X 1.0096* XVI 1.0155t 8 * XXVI 0.9950* S OCKI 0.9848.0023 .0027 .0031 .0028

10 XI 1.0559 * XVI 1.0580t XXII 1.0371* 10 XXVMII 1.0057* 8 XXMI 1.0704t.0029 02 .0021 _0_ .0035

15 XU 1.1070t I 102* m 465 11.6 X- X l.09.0036 .0033 A0023 .0041

20 xm 1.11122t N 1A93 t 1.0393 * 15 X 0.9w t ..0029 .0034 .0024 .0030

25 XIV 1.0988 t XX 1.0694 t XXV 1.0073 f .I .. 1 .0039 I__ l0028 .0024

Table 7.4.1-2 3.00% Enrichment 20 GWd/MTU Minimum Water Volume Fraction For Criticality(k_) in with 30.6% Parosi

20% Water 18% Water 16% Water

Uo% At. kt2a At. Lt 20a At. k.L 2a

S XXXIv 0aM96 * t OV11 0.9904 t L 0.9777 a.0021 .0022 1XJ23

10 ICXKV I0078 t Xa X 0.9948 a XU 0.9803 *.0022 A0022 A023

12 XXXVI 1.0089*t XXOC1 0.9931t XILI 0.9729*.0023 .0023 A23

- - = - -_

Far-Field External Criticality Analysis I3.0% / 20 GWdIMTU U02 in Tuff/Water

0o30 HO a D'O4 0 47% P VSO%H14P3%C.1J40% 10 .

1.12~~~~~~~~~~i01.0- __

1.04 k._.

3 4 5 6 78 1011 12 13 14 15 16 17 18 19 2 21 23 24 25

Volume % UO2in Tuff/Water Mixture

FIGURE 7.4.1-1

Far-Field External Criticality Analysis3.0%/ 20 GWd/MTU UC In Tuff/Water Mixture (Poroslty-.306)

0 12% UO, In TuWa* A 1C00 UO, I Turawer 0 l% W. I TINWr

IF.0I.-

a

las

itI

IE

I 1-JlA2.

l0.974

0.97016.00 16i50 17.00 17.50 18.00 18.50 19.00 19.50 20.00

Volume % Water In Tuff/Water Mixture

FIGURE 7.4.1-2

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Optimum mixtures of Uffwater/U0 2 were identified using the method described above for.

3.5% enrichment, 30 GWd/MTU, for 30% and 20% water,4.0% enrichment, 40 GWdlMTU, for 30% water,and 4.2% enrichment, 45 GWd/MTU, for 30% water.

The remaining burnup/enrichment pairs discussed in Section 7.3.1 were not run because these caseswere sufficient to establish the reactivity trend of these results and the trend indicated that the last twopairs would be subcritical at all U0 2 volume percents at the nominal water concentration of 30%. Thecase inputs and relevant outputs are included in Attachments XIL-LXL These case descriptions andresults ar listed in Table 7.4.1-3. The results are plotted in Figure 7.4.1-3.

The optimum U0 2 volume percent for each of the four burnup/enricbment/water volume variations wasdetermined by reading off the U)0 volume percent corresponding to the peak k. value from the curveson Figure 7.4.1-3. The optimum U02 volume percents are 14.0, 12.0, 15.0, and 15.0 for 3.5%enrichment, 30 GWdIMTU, 30% water in tuff; 3.5% enrichment, 30 GWd/MTU, 20% water in tuff;4.0% enrichment, 40 GWd/MU, 30% water in tuff; and 4.2% enrichment, 45 GWdMTU, 30% waterin tuff, respectively.

Table 7A.41-3 Results of Lower Reacti Fuel Form Mixture Variation k. Cases3.5% U-23S/ 30 GWdTMJ 3 SU-2351 30 OWdIMTU 4.0% U-235/40 GWd/MTU 42% U-235S45 GWd/MIU

30%Water 20%Water 30% Water - 30% Water

UO2 AtL k.t 2a UOj # 1. AMt 2a A)02 k. *2a UO, At k.L* 2c

S XLM 0.8872 * .0033 5 IL 0.9065 *.0026 5 LM 0.8689* .0023 10 L1X 0.9809 t.0023

8.8 XL1V 0.9990 t.0034 10 L 0.9794 * .0031 10 LAY 0.9966 * .0027 15 LX 0.9935 t .0026

10 XLV 1.0125 *0040 12 L1 0.9861*.0040 12 LV 1.0058*.0030 20 L .9744.0022

14 XLVI IM016*.0037 t4 LE 0.9804 t0032 14 LVI 1.0091tt A03M - .

15 XLVII 1M09* .0031 .. 16 LVII 1.092 t OO5 _

16 XLEvm t.02685.0037 _ _ 18 LVM 1.0034±.09 _ -

Far-Field External Criticalit'y AnalysisUO in Tuft/Water Mixture

0SM306 VU 20% 045O Wy43D% HO ~ ~~~30HO30% HO

bI-0

w

coi

By

I

Ii Iit81loof

SE

9a-a!I

CT,

a.

0.880 ..... L L I L A L l L I6 6 7 8 9 10 11 12 13 U 16 16 17 18 19 20

Volume % UO2 In TuffjWAter Mixture

FIGURE 7.4.1-3 BIU,

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7A.2 Optimum Critical Sizes and Masses

Multiple k,, cases were run for each of the optimum U02 volume percents identified for the four watervolume variations of the 3.00% enrchmentP20 GW&IMTU fuel form. These cases were run in order toidentify the minimum sphere radius (and conresponding mass) at which these mixtures would be critical.These cases were modeled with an inner spherical region containing the tffwater/U0 2 mixture and anouter reflector region of at least 60 cm thick containing a tuffwater mixture. The results for these casesare shown in Table 7.4.2-1. The source distribution for these cases (large themal systems) take a largenumber of cycles to reach equilibrium. As a result, most of the cases were run two or more times usingthe SRC1TP file from the prior run until the statistical check in the output indicated the sourcedistribution had reached equilibrium. The initial run of most of these cases used a starting sourcedistribution from a SRCIP file for a case of similar size.

The minimum radius and associated minimum U0 2 mass are determined by plotting the results andfitting a second order polynomial to the results as shown in Figure 7.45-1 through 7A.5-4. The criticalradius value is then determined by identifying the point on the curve that meets the following relation:

CRMTICAL m I-O.05-2a

The corresponding critical mass is calculated by multiplying the volume of the critical sphere (4/35x) bythe density of U0 2 (10.96 g/cm3) and the volume percent of U02 in the mixture. The critical radii andU0 2 masses are shown in Table 7.4.2-2.

Table 7.4.2-1 Results of 3.00% Enskbt/2O GWdlMTU Fuel Form Optimum Mixture I Cases47%Wazer/185%UO, 40% Water 17% U0 30%Waterl 15%UO 20%Waterl L6%U0 o

47- 40% Poro6ity _P__s 30c6

r At. ka 2O r At. kt 2a r AIL kf 2a r At. k 2(cm) # (cm) 1 (m) # ()

57* LNUI 0.9787 t.0029 60 LXVI 0.9578 t.0014 59 LXXI 0.8980tDQ018 180 LXXVM 0.9755t.0019

61 LXM 0.9950 t .0027 65 LXVII 0.9747 .0014 97.16 IOM 0.9846 t .0018 220 LX 0.9849 t.0017

70 LV 1.0202 t. 032 70 LXM 0.9873 t.0015 103 UOCIV 0.9893 t.007 250 LOc 0.9887 t.019

77 LXV 1.0290t.0024 75 LXIX 0.9986 t.0014 113.15 LXXV 0.9985* tAM02 300 LX=I 0.9952 t.0019

80O C i 1.0100 t .0014 1143.1 XXVI 10.9993 t 0 325 LOO 0.9975.t0019

. - - 85 LXG lOIS8 t .0014 123.15 1.0088 at OO03 345 XOMIH 1.0004*.0017

. - - - - - - 365 LSDOV 0.9987 a002C

_ _ _ _ _ - . - - 385 L-XXV I.00 t8

Far-Field External Criticality Analysis3.0% Enriched, 20 GWd/MTU, 18.5 vol% UQ

+ 47% Waor I Tuff

.Icv~

1.030

1.025

1.020

1.016

1.010

1.005

I I l-IL~L ll_ I ttt MIT I l T1 l r rl ~I< I-_, _ _

11 . 1 . .1 - -- " i 3

I I

IiIfiita9E

4

vanla

0

1.000 . . . . . .T~ T . . .7 . .- . . T .

0.985

0.9800.975

0.9705

I I I

T I l. I-l I I_

pLL I1 ' V I__H i 4 ' _ _ _ _5 56 57 58 69 60 61 62 63 64 65 66 67 68 69

Sphere Radius (cnm

FIGURE 7.4.2-1

70 71 72 73 7475 76 77 78

Far-Field External Criticality Analysis i,3.0% Enriched, 20 GWd/MTU, 17 vol% Uq i

+ 40%WATe. inTuff

1.00i--l-

W1.020--.--…o.0g

~0.97 5-- --

x0 ., 7 5 ..… … -… .L

64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 0 81 823 84 65 8 8

Sphere Radius (cm)

FIGURE 7.4.2-2 cm

Far-Field External Criticality Analysis3.0% Enriched, 20 GWd/MTU, 15 vo1% U02

+ 30% Water In TO

1.010

I ImW 1.006

0 1.000

Ez 0.995

£O 0.990

x 0.9

IIii

I*

f

2.

0laa

On

In

0.980 _90 95 100 105 110

Sphere Radius (cm)

FIGURE 7.4.2-3

116 120 125

Far-Field External Criticality Analysis3.0% Enriched, 20 GWdIMTU, 11.6 vo1% Uq

+ 20% Water In TO

1.005

U 1.000

4) 0.995

E o."os

_ 0.85

,s 0.980t

II I T

7- -+-. > "Oo Jr- " -rI

I L7- 0-10 . .

.�P' --.40

I

- - I I - - I i . . . . . . .

ii10

I

h.-J

0_ 5 _ U _ U . U . U ._. L .E U W U_ U WI .W U. W _ U _ E W U U I E U U J _ IU E- _. . ..... .... E... . .. J.E .L l _. .. - -09766..

180 190 200 210 220 230 240 250 280 280 290 300 310 320 330 4 0 0 370 So

Sphere Radius (cm)

FIGURE 7.4.2-4

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Table 7.4.2-2 Critical Parameters for 3.00% Enrichment/20 GWdWMTU Optimum MixturesCrtical Parameter 47%Water/ 15% U 4 Water/17% 0 0% Water/ 15% U %Water/ 1.6%UO

47* Pori 30.6* }ty 30.6% Porosity

Radius (cm) 57A 68.5 98 218

mass(MT) _1.6 2.5 6.5 55.2

In order to demonstrate that the optimum compositions identified in Section 7.4.1 are applicable to thecurrent calculations, two additional cases were run for the 61 cm radius sphere containing 47% waterwith 15% and 20% U0 2. The results are shown in the Table 7.4.2-3 with those for the optimum case at18.5% UO.2 These results indicate that the optimum UO volume fraction identified in the infinitecalculations is applicable to the finite calculations.

Table 74.2-3 Confirmation of Optimum ua, Volume Percent, for Icf Cases.47% Water/R=61 cm

47% Porosity30EqnchmestMDDGWYdMll

U02 AM. kf*2aol% * _

15 LXXOVI 0.9479 t .0030

185 Lx 0.99I50 *I.027

20 1 WOMM 1 0.992mt.0031

Multiple lc, cases were also run for each of the optimum U02 volume percents for the followingburnup/enrichment pair and water volume percent cases to demonstrate increasing critical massrequirements:

3.5% enrichment, 30 GWd/MTU. for 30% water,4.0% enrichment, 40 GWd/MTU, for 30% water.

The results for these cases are listed in Table 7.42-4 and the results are plotted in Fgus 7.42-5 and7.4.2-6. The method described above was used to detennine the critical radius and calculate the criticalmass. The critical parameters are listed in Table 7.4.2-5.

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Table 7A.-4 Resuls of Lower Reactivitv Fuel Form Odtimum Mixu Ic Cases3.5% U-235/30 GWd/MTL 4.0% UV235S/40 GWdrMU

30% Water 14% UOS 30% Wuatd 15% U02_ 30.6%Porot _ 30.6APos

r ~At. kt2a r A. 2(CM) (cm) _

120 LXXVM 0.9821* *.O09 160 XCV O.906 t001

130 LJCIXX 0.9877t.0021 187 XCVMII 0.9873 $.001

134 XC 0.9901 $ .P02S 21908 0.9943t .001

140 XCI 0.9946 t .026 27535 C 0.9987 t .001

150 XCII 0.9971t±.030 280 a 0.9989a.0014

151 XCMI 0.9970 f.0041 28432 Ca 0.9993 t.D01!

152 XCIV f9 9 MU34 293.22 c 1.0012 t .02

153 XCV 09M94 t.0037 310 CIV 1.0017 $.OD1

IS4.9 1.0013 * lX40 - _ I

Table 7A.2-S Critical Parameters for Lower Reactvit Fuel Form Optimum MixturesCOical Parmeter 35% U-235J 30 CGWd&MTU 4.0% U-235 40 OYd1MTU

30% Water/ 14% UO, 30% Water/ 15% U02

I__ _ __ 30.6% Porosit 30.6% Pdrosiy

Radius(cm) I 120 165

Mass(M) [I 11.1 30.9

Far-Field External Criticality Analysis3.5% Enriched, 30 GWd/MTU, 14 vol% U02

+ 30% Waer I Tuff

1.005

.IF.0 1.000

0.95

k 0.990

I 0.98la

iiIIti9.

Owt

E

"I%

Sat

0

to

0

I.

0.980 I"116 120 125 130 135 140 145 150 155 160

Sphere Radius (cm)

FIGURE 7.4.2-5 In

in

Far-Field External Criticality Analysis4.0% Endched, 40 GWd/MTU, 15 vo1% UO2

+ 30DWaterhITu .TO

.0 0

T~~~~~~~~~o0 1.0

FIGURE 7.4.2-6 t

0.99,5~~~~~~~~~~~~~~~~~~~U

O.M 8~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I

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7A.3 Nominal Critical SiZeS and Masses

The optimum U02 volume frions identified previously are much higher than could lIcely be achievedby natural processes. In order to demonstrate the effect of less conservative assumptions, lower volumepercent U02 cases (nominal) were rmn for the tuffwater mixtures rum for the 3.0% cnrichmentf20GWdIM{TU fuel form. Multiple k..ff cases were run for each mixture to demonstrate increasing criticalmass requirements from the optimum mixture results.

The results for these cases are listed in Table 7A.3-1 and the rsults are plotted in Figures 7A.3-1through 7.4.3-4. The method described in Section 7.4.2 was used to determine the critical radius andcalculate the critical mass. The critical parameters are listed in Table 7.4.3-2.

Table 7.43-1 Results of 3.00% Enrichmentl20 GW MU Fuel Form Nom inal Mixture kCas es47% Water I 8% U02 40% Water I 8% UO2 30% Water I lo% 112 30% Water 8* 1 U0_ 47*1 oit 40%1 t 30.66 sir 30.6*

r AIL kat2 r Am. kat 2o r At. kf t 2a r AIL. kf ta(cm) # I (cm) I # I (cm) I . (cm) _

115 CV 0.9684 t .0022 140 CXM 0.9819 t .0016 115 CXID 0.9791 : .0032 180 CVI 0.9833 t .0020

150 CVI 0.9855 t .0021 150I C v 0.9867 t .0015 125 CQ03 0.9909 t .0035 220 CXXCYV 0.9905 t.002

160 CVII 0.9908t 0020 160 CXV 0.9892 a.0016 140 CX0M 0.9997 .009 280 CXXVM 0.9963 M .002

175 CVM 0.991St .0018 175 CXVI 0.9901 t .0017 155 CXO V 1.0046 t .0028 300 OO C O.9978 a .002

190 CIX 0.9967 a .0017 190 CMVII 0.9976 a .0013 170 CXXV 10096 .0031 335 OS 0.9995 a .028

205 CX 0.9979 t .003 205 0 .9960 f .0018 . 345 C000 0.9981 a .0029

220 CXI 0.9974 a .0015 220 CXX 0.9991 a .0014 - 355 0 1 1.0020 a A0

235 CXI 1 202035 Cn 2 1.0035 * 016 _ = . A 365 - 1.0021a.002

Table 7A.3-2 Critical Parameters for 3.00% Enrichment/20 GWd/MTU Nominal Mixure CasesCIical Parameter 47%Water/2% UO) 40%Wazter/ 1810 30%Wazer/ 10%1UO2 30%Water 8% UO,

I _____ _0_3 P1 Posity 30t E

Radius (cmn) 140 1 140 Jli7 [ 170

10.1 10.1 7A 1 1.0

Far-Field External Criticality Analysis3.0% Enrched, 20 GWd/MTU, 8 vo1% U02

+ 47% Water Tuff

1.00

0.9-5 l…

0.975-

'0.970

0.965100 110 120 130 140 160 160 170 160 190 200 210 220 230 240

Sphere Radius (cm)

FIGURE 7.4.3-1

toIIr

wI?I0

*a fs.

Far-Field External Criticality Analysis3.0% Enrched, 20 GWdIMTU, 8 vol% U02

+ 40% Water hi TO

1.005

I 'Ca 1.000.0

q) 0.995

Xa 0.90

E 0.985

a 0.m0080

itI

I

IflaL

a

I

I.

F0

0.975 ..130 140 150 14

.

BO 170 180 190 . 20 210 220 230 241

Sphere Radius (cm)

FIGURE 7A.3-2

Far-Field External Criticality Analysis3.0% Enriched, 20 GWd/MTU, 10 vol% UR2

+ 30% Water I Tuff

1._%

Im

I

k

IlaC:

R.,.1.11

1.10

1.005

1.000

0.995

0.990

0.985

0.980

0.975

O C7M *'�� JLLL *�*� LLLL"" ±�L± �LL� �J�L �LL WL **��

Ifw

:IU

I

U~is

91.IA

10 115 120 125 130 135 140 145 150

Sphere Radius (cm)

FIGURE 7.4.3-3

155 160 165 170

Far-Field External Criticality Analysis if g3.0% Enriched, 20 GWdIMTU, 8 vol% U02

+ 30% Water hI Tuff

& 0.985….wD I:L Efi3c 11S Q985 LL.- S_'.//i_ ___a

0.980 . ..I III liftRl t 1LLI W. .... .... _._ ... .. ..

170 180 190 200 210 220 230 240 250 260 270 290 290 300 310 320 330 340 350 380 370

Sphere Radius (cm)

FIGURE 7.4.3-4

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7A.4A Moderator Volume Fraction Effects

The results shown in Table 742-1 indicate that there are various far-field combinations of (a)asymptotically transmuted SNF without fission products or fission product daughters, and (b) tuff withwater that would be critical. In addition, the results shown in Table 7A.1-1 indicate that there is areactivity dependency on the water moderation. Depending on the volume fraction of U0 2 -NpO% that isassumed to be deposited in a combined mass of fuel and tuff with water, increasing the water volumefraction in the open porosity of the tuff can both increase and decrease reactivity. Consequently, it isfeasible that a positive moderator void coefficient would exist in a subcritical mass of UO2 -NpO2 fuel.The evaluations performed to determine the combinations of fuel, tuff and water necessary to have apositive moderator void coefficient are explained in this section. The conclusions are that (1) thenominal tuff with 30.6% porosity will not have a positive void coefficient, (2) the most porous tuff(47%) could possibly have a positive coefficient, and (3) the effects of the positive coefficient couldhypothetically produce a dynamic fissioning system and a limited neutron - thermal transient. heconsequences of the hypothetical transient and dynamic system are not addressed in this document.

Figure 7.4.4-1 and Table 7.4.4-1 summarize results which show that large configurations (infinite) havea very positive moderator void coefficient if the tuff contains the maximum porosity (47%) that has beenobserved, and the open porosity is completely saturated. The magnitude of the moderator voidcoefficient is increased by having both the greatest amount of water, and the least amount of U0 2-NpOAin the fuel-tuff-water mixture.

Table 7A.4-1 Positive Reactivity From Moderator Voids

3.00 Wt. % Initial Enrichment 20 GWd/MTU Burnup8% U02 - NpO2 92% Tuff-Water 47% Tuff Porosity

Water% Att.# K_.,±2a Att.# | ,frt2a

47 OCKXIV 1.01025 ± .0018 CXLI .98706 ± .0013

40 CXXXV* 1.0854 : .0018 CXL .9964 * .0014

35 CXXXVI 1.03566 *.0019 CXL 1.00242 *.0015

30 COOXVII 1.04272:t.0019 CXLIV 1.00163±t.0016

25 CXXXVI 1.04320±:.0020 CXLV .99189 *.0016

20 CXXXIX 1.03318 ±.0022 CXLVI .97117±t.0016

15 CXL 1.00676 .0022 CXLVII .93067 ± .0018

Figures 7A.41-1 and 7A.3-1 indicate that 8% U0 2-NpO2 by volume with the 47% saturated tuff wouldbe around the lowest practical amount of fuel. The reactivity (p) increase with these optimal conditions

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of maximum water and minimum fuel is 0.0025 A p per percent void in an infinite configuration.Consequently, only 2% to 3% voiding would result in a prompt critical system

For configurations with the minimum size, and minimum amount of fuel that would achieve criticality inthe far-field, the leakage effects on reactivity produce a large reduction in the positive moderator voidcoefficient A 150 cm radius sphere was found to have a leakage of 2.35% in reactivity. The lzff forthis high leakage configuration is 0.987 as shown in Figure 7A.4.1 and Table 7.4.41. The leakageeffects reduce the positive void coefficient to 0.0014 Ap per percent void. While this is a significantreduction from 0.0025 A p / % Void the positive void coefficient still needs to be addressed in the futurebecause 4% to 5% voiding could create a prompt critical system, although the magnitude of a powertransient would be extremely limited in the unlikely event that one started in the first place. It should benoted that for a finite system the k.& drops sharply from the peak of the cue as the water volumefaction is reduced. This would tend to quickly shutdown any transients which may be started.

In order for a significant increase in power to occur, a mechanism for Introducing the reactivity increase(moderator volume percent decrease) instantaneously would be required If the reactivity is inserted(water removed) over a time scale of seconds or greater then the temperature feedback effects ofincreasing power would likely compensate and keep the system relatively stable and at low power.

Far-Field External Criticality Analysis3.0%1 20 GWdI/MTU U02 In Tuff/Water Mixture (Porostty-0.47)0 6.%u1,. wif 4 8.%UO,,15 RadusSpm

1.050

1.040

S 1.030

a 1.020

1.010

k 1AX0.99

B0.980

C 0.970

so 0.960,,;0.950

0.940

0.93010

Ii

'I

WI

-I

15 20 25 30 .3 40 45 50

Volume % Water In Tuff/Water Mixture

FIGURE 7.4.4-1

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7A.5 Additional Cases

Several cases were specifically requested to support separate probabilistic analyses. These cases aredocumented in this section. All cases in this section are based on the 3.0% enrichmentl 20 GWd/MTUactinide isotopics. These cases include:

2 fuel zone cases to demonstrate the effect of reduced density U02 in second zone,cylindrical configuration (log simulation).

Two sets of cases were requested to demonstrate the reactivity effect of a secondary fuel shell around theprimary sphere in support of methodology development for probabilistic analyses (Ref. 5.17). Theprimary fuel zone contains 18.5 volume percent U0 2 based on the 3.0% enrichment/ 20 GWdMU pair.The tuff porosity is 47% and is assumed completely filled with water. The secondary shell is twice theradius of the primary sphere. The average (two region) UO volume fraction specified for the two sets ofcases is 9.2% and 4.6% with corresponding volume fractions in the outer shell of 7.87% and 2.61%,respectively. The volume fractions in the secondary shell correspond to approximately 3/7 and In of theprimary sphere volume fraction, respectively. The mixture number densities are calculated in aspreadsheet as described in Section 7.3.3 and included in Attachment VEL Multiple Ld cases were runfor each of these two mixtures in order to Identify the minimum sphere radius (and corresponding mass)at which these mixtures would be critical. The results for these cases are shown in Table 7.4.5-1. Theminimum radius and associated minimum U 2 mass are determined by plotting the results as shown inFigures 7A.5-1 and 7A.5-2 and performing the operations previously described in Section 7A.2. Thecritical radii and U02 masses for the inner spherical fuel zone ar 39.4 cm (0.52 MT) and 54.2 cm (IAMT) for 9.2 % and 4.6% U03, respectively. The total critical mass for the primary and secondary zonesis 2.1 MT and 2.7 MT for 9.2% and 4.6% U02 , respectively. The minimum critical mass for the singlefuel zone case calculated in Section 7.4.2 is 1.6 MT.

Table 7A.5-1 Results for 2 Fuel Zone Cases to Determine Critical Radii9.2 Avuge Volume for U,4.6AvraeVOW=m %fort1

Inner Attachtnent k0 i 2a Inner AMactament kff * 2aRadius Radius

(CM) _____ (CM)

40 CXLVM 0.9847 .0018 53 CI 0.9762 t.0017

50 CL 0l14O .0015 55 CLf 0.9870t.00l8

57A CL 1.0301 a .D19 57A I 11! 0.9939*.0018

I

Far-Field External Criticality Analysis i a

3.0% Enriched, 20 GWd/MTU, 47 vol% Water In Tuff+ 2 Zanes, tvo U, Cterd 9.2 Vol% Avemrge

co.0 0-02-

1.01I

& cm s T- - -__,_-____- __

3839940 41 42 43 4445 4647 48 49505616 63 64ES655867 68

Sphere Radius (cmn)

FIGURE 7.4.5-1 i

1410~~~~~~~~~~~~~~~

* Far-Field External Criticality Analysis3.0% Enriched, 20 GWd/MTU, 47 vol% Water in TufO

+ 2 Zones. 18.6 v% UO. Contsrl4.6 Vol% Average

1.000

. ID 0.995

* 0.990

iE 0.985

c'9- 0.975

0.970I

T

1-1�-I--,

,.Io I

. I . I-LA-LA-L." I I 4 . . .I t . I . . . . . . I . . . . I

iiIP..*

F.A

52 53 54 55 58

Sphere Radius (cm)

FIGURE 7.4.5-2

57 58

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The highest local uranium ore concentrations in the United States are found in the Uravan Mineral Beltin southwestern Colorado and southeastern Utah. These are up to 21.5% U30i by weight and are foundin fossilized logs along pre-historic riverbeds (Ref 5.17, Attachment I). The maximum values of logparameters were determined to be:

radius=61 cm.length= 24.4 m (80 ft),U02 weight fraction= 0.215 (4.6 volume %).

These parameters (Ref. 5.17) were used for a 40% volume percent water in tuff mixture to demonstrate alow k;ff for this configuration (infinite length). This resulting kff for this case is 0.7926 :t .0015. Theinput and relevant output for this case is included in Attachment CLIV.

8. Conclusions

The results of this study should be teated as unqualified data and not be used for procurement,fabrication, or construction unless properly identified, tacked as TBV, and controlled by the appropriateprocedures.

The major results are summarized below:

CRITICALITY DEFINED as kdr,{1.0 - .015 (bias and uncertainty) - 20) from Curves

The water volume percents quoted throughout this report have been the volume percent water in atuff/water mixture. The UO volume percent quoted displaces the tuf/water mixture such that the watervolume factdon in the tufflwater/U02 mixture is reduced by the factor (1-U02 volume fraction). Thevolume fraction of water in the tufflwater/U0 2 mixture is reported next to the UO, volume fraction inthe mixture.

3.0% Enrichment/ 20 GWdItMU47% water in Tuff

Minimum critical radius/mass at 18.5 vol% U02 / 38.3 vol% water - R=57.4 cm,U0, mass= 1.6 MT. U02 p=2.028 glm'

8 vol% UO, /43.2 vol% water - R=140 cm, U02 mass=10. 1, U02 p=0.8 77 glimcMinimum U02 vol%/density for criticality (k. =.982) - 7.2 vol% /0.789 /cm'

40% water in TuffMinimum critical radiusAnass at 17 vol% UO2 /33.2 vol% water - R=68.5 cmUO% mass=2.5 MTW. U0 p=1.863 g/cmn

8 vol% U2 / 36.8 vol% water - R=140 cmn U02 mass=I0.I, U0 p=O.8 77 gicm'Minimum U0,2 vol%/density for criticality (k.. =.982) - 7.1 vol% /10.778 gicm'

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30% water in TuffMinimum critical radiushnass at 15 vol% UO2 / 25.5 vol% water - R=98 cm,U02 mass=6.5 MT. 1102 p=1.6 44 g/cm`

10 vol% U02 127.0 vol% water - R=1 17 cm, UO2 mass=7A MT,U0 2 p=1.096 g/cm?

8 volU%11 //27.6 vol% water - R=170 cm, U10 mass=18.0 MT.U02 p=0.877 g/cme

Minimum U02 vol%/density for criticality (k. =.982) - 7.0 vol% / 0.767 g/cm3

20% water in TuffMinimum critical radius/mass at 11.6 vol% UO0 /17.7 vol% water - R=218 cm,

U0 2 mass=55.2 MT, U02 p=1.271 glcm3

Minimum U0 2 vol%/density for criticality (k. =.982) - 7.2 vol% /0.789 g/cmn

s 16A% water in Tuff- subcritical

3.5% Enduchmentt 30 GWd/ MTU30% water in Tuff

Minimum critical radius/mass at 14 vol% U020125.8 vol% water - R=120 cm,U02 mass=1 .LIMT, U0 p=1.534 glcm

Minimum U02 vol%/density for criticality (k. =.982) - 7.6 vol% /0.833 g/cmn

s20% water in Tuff - subcritical

4.0% Enrichmentl 40 GWd/ MTU30% water in Tuff

Minimum critical radius/mass at 15 vol% U0 2 / 25.5 vol% water - R=165 cm,UO2 mass=30.9 MT, U10 p=1.644 g/cm3

Minimum U10 vol%/density for criticality (k. =.982) - 8.6 vol% / 0.943 g/cm'

s20% water in Tuff- subcritical

3.0% Enrichmentf 20 GWdM IWU, 47% Porosity, 8.0 volume% U02Peak k. =1.044 at 27 volume% water, Ak from 47% water = 0.034Peak kr =1.003 at 33 volume% water for 150 cm sphere, Ak from 47% water = 0.017

The evaluations performed to determine the combinations of fuel, tuff and water necessary to have apositive moderator void coefficient provide the following conclusions: (1) the nominal tuff with 30.6%porosity will not have a positive void coefficient, (2) the most porous tuff (47%) could possibly have apositive coefficient, and (3) the effects of the positive coefficient could hypothetically produce adynamic fissioning system and a limited neutron-thermal transient. The consequences of thehypothetical transient and dynamic system are not addressed in this document

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9. Attachments

The following Attachments are case output files as listed. The name of the file is listed in parenthesis.

I. LOTUS 1-2-3 Spreadsheet for Base number densities (atomden.wk3 sheet A), 9396,2 pages

Cases for Section 7.3.1II. SAS2H Case - 3.0% Enrichment, 20 GWd/MFU (o3020.res), 415196, 6 pagesm. SAS2H Case - 3.5% Enrichment, 30 GWd/MTU (o3530.res), 415/96,5 pagesIV. SAS2H Case - 4.0% Enrichment, 40 GWd/MTU (o4040.res), 4/8J96,6 pagesV. SAS2H Case - 4.0% Enrichment, 45 GWdMTU (o4O45.res), 41/596, 6 pagesVL SAS2H Case - 4.2% Enrichment, 45 GWdNMTU (o4245xes), 4/5/96,6 pagesVII. SAS2H Case - 4.5% Enrichment, 53 GWdJMTU (o4553.res), 4/5/96,6 pagesVm. LOTUS 1-2-3 Spreadsheet for Mixture number densities (lespher2.wk4 sheet.B), Sf27/96,

11 pagesCases for Section 7.4.1

IX. MCNP Case - 3.0% Enrichment, 20 GWdLMTU, 47% Water, 5% UO2 (i30O2md.sum),615/96, 1 page

X. MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 47% Water, 8% UC3 (i302zf sum),Sf21/96, 1 page

XL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 10% UO2 (i302Ome.sum),f521/96, 1 page

XIL MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 47% Water, 15% U02 (i3020ma sum),5121/96, 1 page

Xm. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 20% U 2 (iOOmb.sum),5121/96, 1 page

XIV. MCNP Case - 3.0% Enrichment, 20 GWdfMTU, 47% Water, 25% U02 (i3O2Omcsum),521/96, 1 page

XV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 5% U02 (i3O2Ooasum),5121196, I page

XVL MCNP Case - 3.0% Enrichment. 20 GWdIMTU, 40% Water, 8% U02 (i3020Ob.sum),5/21/96, 1 page

XVII. MCNP Case - 3.0% Enrichment, 20 GWdMTU, 40% Water, 10% U02 (i3020Oc.sum),5S21/96, 1 page

XVI3L MCNP Case - 3.0% Enrichment, 20 GWdlMTU, 40% Water, 15% U0 2 (i3020Od.sum),5/21/96, I page

XX. MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 40% Water, 20% U02 (i3020Oe.sum),5/21/96, 1 page

XX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 25% UO2 (i3020Of.sum),5/21/96, 1 page

XXI. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 30% Water, 5% U02(11-3.0E-20OWd-30WOSU), 5/20/96, 2 pages.

XXIL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 30% Water, 10% U0 2

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(12-3.02OGWd-3OW1tU), 5120/96,2 pagesXXI. MCNP Case - 3.0% Enrichment, 20 GWdMTU, 30% Water, 15% U02

(13-3.OE-20GWd-30W 15U3), S1296, 2 pagesXXlV. MCNP Case - 3.0% Enrichment, 20 GWdMT, 30% Water, 20% U02

(14-3.OE-20GWd-30W20U), SW96,2 pagesXXV. MCNP Case - 3.0% Enrichment 20 GWd/MU, 30% Water, 25% U0 2

(IS-3.OE-20GWd-30W25U), S/2096,2 pagesXXVI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 5% UO0

(11-3.0E-20GWd-20W05U), 120196, 2 pagesXXVIL MCNP Case - 3.0% Enrichment, 20 GWdMTLJ, 20% Water, 8% U02

(12-3.OE-200Wd-20W08U), 520/96, 2 pagesXXVM. MCNP Case - 3.0% Enrichment, 20 GW dMTU, 20% Water, 10% U10

(13-3.OEB-20GWd-20WIOU), /20/6, 2 pagesXXiX. MCNP Case - 3.0% Enrichment, 20 GWdMU, 20% Water, 11.6% U10

(14-3.0O20GWd-20W12U), 5/2SY96,2 pagesXXX. MCNP Case - 3.0% Enrichment, 20 GWdMU, 20% Water, 15% U02

(I5-3.OE-20GWd-20W15U), /20/96, 2 pagesXXXL MCNP Case - 3.0% Enrichment, 20 GWdMU, 30% Water, 35% C, 3.6% U0 2

(i3020of.sun), 6/5/96, 1 pageXXXIL MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 30% Water, 35% C. 5% U02

(i3O20of.sum), 6/5/96, 1 pageXXXI. MCNP Case - 3.0% Enrichment, 20 GWdlMTU, 30% Water, 35% C, 8% U02

(i3020Of.sum), 6/5/96, 1 pageXXXIV. MCNP Case - 3.0% Enrichment, 20 GWdCI/MT, 20% Water, 8% U10

(IMW-3.OE-20GWd-20W08U), 6r7/96.2 pagesXXXV. MCNP Case - 3.0% Enrichment, 20 GWd/MU, 20% Water, 10% UO2

(IMW-3.OE-200Wd-20W1OU), 617/96,2 pagesXXXVL MCNP Case - 3.0% Enrichment, 20 GWdMtU, 20% Water, 12% U02

(IM-3.OE-20GWd-20W12U), 617/96,2 pagesX=VI MCNP Cae - 3.0% Enrichment, 20 GWdIMIU, 18% Water, 8% UO%

(IMW-3.OE-200Wd-18W08U), 6t7/96,2 pagesXXXVm. MCNP Case - 3.0% Enrichment, 20 GWdlMTU, 18% Water, 10% UO,

(IMW-3.0E-200Wd-18WIOU), 6n796,2 pagesXXX . MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 18% Water, 12% U02

(IMW-3.OE-20GWd-18W12U), 6/7/96,2 pagesXL. MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 16% Water, 8% U0 2

(IMW-3.OE-20OWd- 16W08U), 67/96, 2 pagesXLI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 16% Water, 10% U02

(DMW-3.OE-20GWd-16WIOU), 6t7/96,2 pagesXUL MCNP Case - 3.0% Enrichment,.20 GWd4lMU, 16% Water, 12% U02

(RMW-3.OE-20GWd-16W12U), 6n7/96,2 pagesXLII. MCNP Case - 3.5% Enrichment, 30 GWd&MTU, 30% Water, 5% UO1 (i3530fsum),

5296, 1 page

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XLIV. MCNP Case - 3.5% Enrichment, 30 GWCVMTU, 30% Water, 8.8% UO2 (i3530e.sum),5/21/96, 1 page

XLV. MCNP Case - 3.5% Enrichment, 30 GWd/MU, 30% Water, 10% U02 (i3030d.sum),5121/96, 1 page

XLVI. MCNP Case - 3.5% Enrichment, 30 GWd/TU, 30% Water, 14% U02 (i3530c.sum),5/21/96, 1 page

XLVIL MCNP Case - 3.5% Enrichment, 30 GWd&MTU, 30% Water, 15% U0 (i3530asum),5/21/96, 1 page

XLVI. MCNP Case - 3.5% Enrichment, 30 GWdMTU, 30%o Water, 16% U0 2 (i3530bsum),5/21/96, 1 page

IL. MCNP Case - 3.5% Enrichment, 30 GWd/MTU, 20% Water, 5% U0 2 (i3530j.sur),5/296, 1 page

L MCNP Case - 3.5% Enrichment, 30 GWd/MTU, 20% Water, 10% U02 (i3530isum),5/22196, 1 page

LI. MCNP Case - 3.5% Enrichment, 30 GWd/MTU, 20% Water, 12% UO2 (i3530g.sum),52296, 1 page

Lll. MCNP Case - 3.5% Enrichment, 30 GWdlMTU, 20% Water, 14% U02 (i3530hsum),5/22196, 1 page

Lm. MCNP Case - 4.0% Enrichment, 30 GWd/MTU, 20% Water, 5% U2O (i4040fwSUm),5/22/96, 1 page

LIV. MCNP Case - 4.0% Enrichment, 30 GWdlMTU, 20% Water, 10% U0 2 (i4040d.sum),5/22/96, 1 page

LV. MCNP Case - 4.0% Enrichment, 30 GWd/MTU, 20% Water, 12% U02 (i4040b.sum),5/22/96, 1 page

LVI. MCNP Case - 4.0% Enrichment, 30 GWd/MTU, 20% Water, 14% U02 (i4040a.sum),5/22/6, 1 page

LVII. MCNP Case - 4.0% Enrichment, 30 GWd/MTU, 20% Water, 16% U0 2 (iA040c.sum),5/2296, 1 page

LVI. MCNP Case - 4.0% Enrichment, 30 GWd&MTU, 20% Water, 18% UO (i4040e.sum),52296, I page

LIX. MCNP Case - 4.2% Enrichment, 45 GWd/MTU, 30% Water, 10% U02(i4245amum), 8/27/96, 1 pages

LX. MCNP Case - 4.2% Enrichment, 45 GWdrMTU, 30% Water, 15% UO2(i4245b sum), 8/27/96, 1 pages

LXL MCNP Case - 4.2% Enrichment, 45 GWdWMTU, 30% Wat, 20% U02(i4245c.sum), 8/27/96, 1 pages

Cases for Section 7.4.2LXI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 18.5% U0 2, r=57

(s3020me.sum), 5/23/96,2 pagesLXH MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 18.5% U0 2, r=61

(s3020md.sum), 5J23/96,2 pagesLXIV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 18.5% UO2 , r=70

(s302Omb.sum), 5/23/96,2 pages

Waste Package Development Deladan Analvsis,, S

Tte: Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste PackageDocument Identifier. BBAOOOOOOD01717-0200-016 REV 00 Page 53 of 57

LXV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 18.5% U02, r=77(s320ma.sum), Sf2396, 2 pages

LXVI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 17% UO, r=60(s30O2oa.sum), 5123196,2 pages

LXVI MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 17% UO2, r=65(s30200b.sum), 5296,2 pages

LXVHL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water. 17% U02, r70(s3020oc.sur), 5/23/96, 2 pages

LXIX. MCNP Case - 3.0% Enrichment, 20 GWdMTU, 40% Water, 17% U0 2, r-75(s3020od.sum), 5123/96,2 pages

LXX. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 40% Water, 17% U02, r=80(s30200e.sum), 5/23196, 2 pages

LI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 17% U0 2, r-85(3020of sum), 5/23196, 2 pages

LXXII. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 30% Water, 15% U02, r-59(C1-3.OE-20GWd-3OWISU), 5120196,2 pages

LXI . MCNP Case - 3.0% Enrichment, 20 GWdlMTU, 30% Water, 15% U02 , r=97.86(C2-3.OE-200Wd-30WSU), 5117196,2 pages

LXXIV. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 30% Wate, 15% U02, r=103(S3020a.sum), 6/10/96,2 pages

LXXV. MCNP Case - 3.0% Enrichment, 20 GWdCMTU, 30% Water, 15% U02 , r-l 13.15(C4-3.OE-20GWd-3OW15U), 5/20/96,2 pages

LXXVI. MCNP Case -3.0% Enrichment, 20 GWd/MTU, 30% Water, 15% U02 , r=1 14.51(CS-3.OE-2OGWd-30WISU), 5120/96,2 pages

LXXVIL MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 30% Water, 15% U0 2, r=123.15(C6-3.OE-20GWd-30W1SU), 5120/96,2 pages

LXXVIIL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 11.6% U0 2, r=180(s30el2h.sum), 67M96, 2 pages

LXXIX MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 20% Water, 11.6% U 2 , 1=220

(s30e12g.sum), 617/96,2 pagesLX. MCNP Case - 3.0% Enrichment. 20 GWdIMTU, 20% Water, 11.6% U02 , r=250

(s30el2fsum), 617/96,2 pagesLXXXL MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 20% Water, 11.6% U0 2. r=300

(s30el2e.sum), 6/7196.2 pagesLXXXI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 11.6% UO, r=325

(s30e12b.sum), 617/96,2 pagesLXXI MCNP Case - 3.0% Enrichment, 20 GWd/gU, 20% Water, 11.6% U 2 , r=345

(s30e12a.sum), 617/96,2 pagesLXXXW. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 11.6% U02 , r=365

(s3Mel2c.sum), 6MM96, 2 pagesLXXXV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 11.6% U02, r-385

(s30el2d.sum), 6f/796, 2 pagesLXXXVL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 15% U02 , r=61

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(s302mh.sum), 6/96,2 pagesLXXXVII. MCNP Case - 3.0% Enrichment, 20 GWd&MTU, 47% Water, 20% U02, r=61

(s302Omi.surn), 6/6/96,2 pagesLXXXVM. MCNP Case - 3.5% Enrichment, 30 GWdIMMU, 30% Water, 14% U 2 , r=120

(s3530i.surn), Sf2496, 2 pagesLXXXDX MCNP Case - 3.5% Enrichment, 30 GWdIMTU, 30% Water, 14% U%2, r-130

(s330bsurn), 5124/96,2 pagesXC. MCNP Case - 3.5% Enrichment, 30 GWdMTU, 30% Water, 14% UO2, r=134

(s3530g.sum), 5124196,2 pagesXCI. MCNP Case - 3.5% Enrichment, 30 GWtJMTU, 30% Water, 14% U02, r=140

(s3530f.sum), 5/23196,2 pagesXCII. MCNP Case - 3.5% Enrichment, 30 GWdtMlV, 30% Water, 14% U02 , rl150

(s3530b.sum), 5/24/96, 2 pagesXCII MCNP Case - 3.5% Enrichment, 30 GWdIMATU, 30% Water, 14% UO2 , r-15 1

(s3530c.sum), Sf23196, 2 pagesXCIV. MCNP Case - 3.5% Enrichment, 30 GWdfMTU, 30% Water, 14% UO2, r=152

(s3530d.sum), Sf2396, 2 pagesXCV. MCNP Case - 3.5% Enrichment, 30 GWdJMTU, 30% Water, 14% U02, r-153

(s3530c.sum), 5123J96,2 pagesXCVI. MCNP Case - 3.5% Enrichment, 30 GWdM, 30% Water, 14% UC2, r=154.9

(s3S30asum), 5123196,2 pagesXCVIL MCNP Case - 4.0% Enrichment, 40 GWd/MTU, 30% Water, 15% UO%, r=160

(CI-4.OE-40GWd-30WlSU), S121196,2 pagesXCVIIL MCNP Case - 4.0% Enrichment, 40 GWd/MTU, 30% Water, 15% U02, r=187

(C2-4.OE-40GWd-30W151), S/2 6, 2 pagesIC. MCNP Case - 4.0% Enrichment, 40 GWdwrU, 30% Water, 15% U0 2, r-219.08

(C3-4.OE-40GWd-3OWISU), 5121196,2 pagesC. MCNP Case - 4.0% Enrichment, 40 GWdlMTU, 30% Water, 15% U02, i-275.35

(C4-4.OE-400Wd-30W15U), SJ21/96,2 pagesCI. MCNP Case - 4.0% Enrichment, 40 GWd/MTU, 30% Water, 15% U02, r=280

(CS-4.OE-4OGWd-30W1511), 5121/96,2 pagesCII. MCNP Case - 4.0% Enrichment, 40 GWd/MTU, 30% Water, 15% U02, r=284.32

(C6-4.OE-40GWd-30WY15U), Sf2/96,2 pagesCmI. MCNP Case - 4.0% Enrichment, 40 GWd/MTU. 30% Water, 15% U02, r-:293.22

(C7-4.OE-40GWd-30W15U), 5121/96,2 pagesCIV. MCNP Case - 4.0% Enrichment, 40 GWdMU, 30% Water, 15% UO, r=3 10

(C8-4.OE-4OGWd-30W1SU), 5/96, 2 pagesCases for Section 7.4.3

CV. MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 47% Water, 8% U0 2, rIl 15(s302Onh.sum), 5124/96,2 pages

CVI. MCNP Case - 3.0% Enrichment, 20 GW&/MTU, 47% Water, 8% U02, r=150(3O2Onsum), 5124/96,2 pages

CVII. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 8% U02, r=160

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(s3020nb.sum), 5/24/96,2 pagesCVIII MCNP Case - 3.0% Enrichmcnt, 20 GWd/MTU, 47% Water, 8% UO0, r=175

(s302nc.sum), 5124/96,2 pagesCMX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 8% U02 , r=190

(s3020nd.sum), 524t96,2 pagesCX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 8% U0%, r=205

(s302One.sum), 5/24/96,2 pagesCXI. MCNP Case - 3.0% Enrichment, 20 GWtMTU, 47% Water, 8% U02, r=220

(s3O2Onf.sum), 5/24196,2 pages 0CXIL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 8% UO1, r=235

(s3O2Ong.sum), 8/27196,2 pagesCXM. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U0 2, r=140

(s3020ph.sum), Sf24196, 2 pagesCXIV. MCNP Case - 3.0% Enrichment, 20 GW&d/U, 40% Water, 8% U02 , r=150

(s302pa.sum), 5/24196,2 pagesCXV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U10, r=160

(s3020pbsum), 5/24196,2 pagesCXVL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U0, r=175

(s3O2Opc.sum), 5/24196,2 pagesCXVII. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U02, r=190

(s3O2Opd.sum), 5/24/96,2 pagesCXVII MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U0%, r=205

(s3020pe.sum), 5124/96,2 pagesCXIX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% U02, r=220

(s3O2Opf.sum), /24196, 2 pagesCXX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 8% UO,, r-235

(s302Opg.sum), 5/24196,2 pagesCXI. MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 30% Water, 10% U0%, rz1 15

(s3020be.sum), 5/24196,2 pagesCXXII MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 30% Water, 10% U10, r=125

(s3O2Oba.sumn), U24M96, 2 pagesCXXM. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 30% Water, 10% U02, r=140

(s30203Ob.sum), 5/24196, 2 pagesCXXIV. MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 30% Water, 10% U02, r-155

(s3020bc.sum), 5;24/96,2 pagesCXXV. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 30% Water, 10% U02, r=170

(s3020bd.sum), 5/2496, 2 pagesCXXVI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 30% Water, 8% U02, r=180

(s3020ah sum), 5/24196,2 pagesCXXVIL MCNP Case - 3.0% Enrichment, 20 GWdAMTU, 30% Water, 8% U12, r=220

(s3020ag.swn), 5/24196,2 pagesCXXVIIL MCNP Case - 3;0% Enrichment, 20 GWdMTU, 30% Water, 8% UO%, r-280

(s3020af.sum), 5/24196,2 pages

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CXXIX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 30% Water, 8% U02, r=300(s302ae.sum), 524196, 2 pages

CXXX. MCNP Case - 3.0% Enrichment, 20 GWd&MTU, 30% Water, 8% U0 2, r=335(s3020ad.sum), 5/24/96,2 pages

CXXL MCNP Case - 3.0% Enrichment, 20 GWdlMTU, 30% Water, 8% U02 , r=345(s3020ac.sum), 5/13/96,2 pages

CXXXIL MCNP Case - 3.0% Enrichment, 20 GWd/MU. 30% Water, 8% U13, r=355(s3020ab.sum), 5/496, 2 pages

CXXXM. MCNP Case - 3.0% Enrichment, 20 GWdWMTU, 30% Water, 8% U0 2, r=365(s3020aa.sum), 5/24/96, 2 pages

Cases for Section 7AACXXXIV. MCNP Case - 3.0% Enricbment, 20 GWd/MTU, 47% Water, 8% UO, k,-

(P4717-3.OE-20GWd-47W08U), 5J21/96,2 pagesCXXXV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, 89% U02, k,.

(P4716-3.OE-20OWd-40W08U), 5/21/96,2 pagesCXXXVL MCNP Case - 3.0% Enrichment, 20 GWd/MTM, 35% Water, 8% U02, k,.

(P4715-3.OE-20GWd-35W08U), 5/21/96,2 pagesCXXXVII. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 30% Water, 8% U0 2, kw

(P47W4-3.OE-20GWd-3GW08U), 5/21196,2 pagesCXXXVI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 25% Water, 8% U2, k,.

(P47I3-3.OE-2OGWd-25W08U), 5/21/96,2 pagesCXIX. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 20% Water, 89% U02, k..

(P4712-3.OE-20GWd-20W08U), 5f21J96,2 pagesCXL. MCNP Case - 3.0% Enrichment, 20 GWd .l"U, 15% Water, 8% UO2, k.

(P47Il-3.OE-2OGWd-15W08U), 5/21/96,2 pagesCXLI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 8% U2, R=150

(P47C7-3.OE-2003Wd-47W08LU), 5/21/96,2 pagesCXLIL MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 40% Water, 8% U02, R=150

(P47C6-3.OE-200Wd-40W08U), 5/21/96,2 pagesCXLIl. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 35% Water, 8% U%2, R=150

(P47C5-3.OE-20GWd-35W08U), 5/21/96,2 pagesCXLIV. MCNP Case - 3.0% Enrichment, 20 GWdMTU, 30% Water, 8% UO%, R=150

(P47C4-3.OE-20GWd-30W08U), 5/21/96,2 pagesCXLV. MCNP Case - 3.0% Enrichment, 20 GWd/MT, 25% Water, 8% U32, R=150

(P47C3-3.OE-200Wd-2SWO8U), 5/21/96,2 pagesCXLVI. MCNP Case - 3.0% Enrichment, 20 GW&/MTU, 20% Water, 8% U0%, R=150

(P47C2-3.OE-200Wd-20W08U), 5/21196,2 pagesCXLVII. MCNP Case - 3.0% Enrichment, 20 GWdIMTU, 15% Water, 8% U02, R=150

(P47C1-3.OE-2WGWd-15W08U), S/2196,2 pagesCases for Section 74.5

CXLVM. MCNP Case - 3.0% Enrichment, 20 GWdJMTU, 47% Water, 2 Zone 9.2% AverageU2, r=40(80) (s3020mzsum), 6J7196, 2 pages

CL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 2 Zone 9.2% Average

Waste Package Development Design AnalysisTite: Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste PackageDocument Identlfler: BBAOOOOO-01717.020040016 REV 00 Page 57 01 57

U02, r=50(100) (3O20mysurn), 6t7/96, 2 pagesCL MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 2 Zone 9.2% Average

U0 2, r=57.4(114.8) (s3020usum), 67/96, 2 pagesCLI. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 2 Zone 4.6% Average

U02 , r=53(106) (s3020ms.sum), 6f7/96, 2 pagesCLII. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 47% Water, 2 Zone 4.6% Average

UO2, r;55(1 10) (s3020mr.sum), 6t7/96,2 pagesCMIII. MCNP Case - 3.0% Enrichment, 20 GWdtMTU, 47% Water. 2 Zone 4.6% Average

U02, =S7.4(l 14.8) (s302mq.sum), 61796,2 pagesCLIV. MCNP Case - 3.0% Enrichment, 20 GWd/MTU, 40% Water, Cylinder, 4.6% U02,

r=61, (c3020nb sum), 6/7/96,2 pages

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1. For-FeW Crlticality Study * J3.63 20 Sn/at * 302 1201 52 132 (1i320ud)2- C nlo misllte Tuft 1.1S7 u/cc .470 poreesty reftlected mphere3- C CILL SPiEciri1*731s4- C IN*11 UATER 3418035- I 1 9.54553-2 -1 INW.e-I6- C WUIHE IWORLO7- 2 6 .1 Z1PseYD

9- C SURFACE SPECIFICATIOS10* 1* to so S INEl FUEL 201E

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1- nOOO.S190.c 4.66496 4 20000.Oc I.t 795-4 26000.15. 1.1771994-22- 92294.SCc 3.93031 7 92235. .90W04-S 226.1Oc S.720740-623- 92238.50c 1.7109C33 953237.sc 1.3329-624- .21 tutr.6lt25- PRINT

Initial eauree free kare card. print table 90lkeff results fePs Far-field Criticality Study * 3.2 L 20 61D1/t - 302 3201 32 UD2 (13020od) probid * 0412616 14" 49

the nitel fislesn neutron source dIstribution used the 14 source points that were input en the tkre card.the criticality Problem ws echeduled to ekip 7 antles and rui a tetal of SJ ealpt with nminatlly 4000 neutrons per tce.thie proble, has run r Inactive eycles with 2791 nautren hieterie and 30 active cycles with 12Cn75 mautron histeri.ss

this calculetien km completed the reqstd _ I r of taft eycls using a total ofell cells with fissienable *aterial were saupled and had flessin neutron source points.

141069 ftlerin neutren seurce hietories.

the results of tho r test for rrality cpplied te the Individual oellisien. ebaarptien. and tract-leneth teff eycle vatura ere:

the tt eraltels on)y V t alues appear mrmstatly dIstriuted at the 5 gpercent centldencn levelthe leabsorpti n) cy ce almas appear norm Ily distributed at the 93 preent ecnt denee ltvethe Wtrk Imlgth) cycle values appear normally dletrlbuted at the 9S percent aenfidonce level

................................... ................................................................................................

the final estimated e obined eoltsionlaboerptlenitract-tength ha * .6U050 with an estimated standard deviation of .C0125

the estimated , 9 persent taft ontfidence Intervals ere .6723 e .6o177. .7 te .6837. and .67704 to . ?97

the estimated ettialen/absorptien noutren reaoval lifetime e 1.19E1-4 eaconda with an estimated standard deviation of 4.UE-O7

................................................................................... .............................................

R 21 13156 1996 ole Names 13020d.su. UV5 tl A4tI-0200 ISV EY *0 TTACINENT X P Page-I

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I- Fa-Fil Critllml:1 St 3.01 20 in olt * 301 1201 1502 X(3020f)2- C Cat i BIlts f1 7 Vsc. .470 porosity - relected spisare3- C CELL SPECIPICATItiU4. C INNER VATuI 100

1- I I 1 IIP.0 I6- C uWIScrE WO~RLD 7C

la so 6 JJO tI FUEL TiIIIE0I-

12- ROOE kIs- IEcoD 4000 1. T 3714- C t 0t 1 0 0IC0 0020 0e29 9a5 00 a5 -10S -101s- C I 0s -w20 -1to 0-13 a 1 1 a 1 -S -10-5-6 5 a IC* so IT01U- C MATIEIAL SPECINION?2CSIt- a I4? ,l1 sar 1n olio. KIllto tuft) x .90 13 wets U021t. * 3.01 0.-telt sal gssriohont/ N0611 I d /ml de to Uranlum ttepetIt- el 1001.5Cc cold012 060 4.129133.2 t@30 ~9i2 12 000C .SOr 97n2}4 13027. Cc . 18592-314000.50c 9606-521- 19000.5c S .* 76704 20000 e 623070-4 000. 1.140702-422- 9224.50c 4.494450T 223X. 2.t252e6-5 92236.50c 9.153184-623. 9223s.5c 1.9l 03003 93237.1Cc 2.12926-624. itl lutr.1t25- PRINTI Initial sousce flea file oftat

1kcf results Fors far-Field Critila ity Study * 3.0S /20 tD71t - 30S 120/ U U102 (13020sf) prebid a 04/26/96 1l3s19

the Initial fissian neutron source dtstrlbutlan was reed fros the eretp fit nAtad erctpthe sritieellty prublem as scbaduled teo ip s cTlras and run a total d1 37 aycles with nominally 4000 neutrons per aLae.thle problam aM run T InactIve ccles ofth 30 nautrsn historIes and 32 active syclas will 120009 neutron hlletoris.

this calculatien has seo leted the raPusted maser of kff les. uuinh a total *f 148015 fission Neutron sourse histories.all calls wIth fissionable material were empted asd hId iesion neutran aure. pintse..

the results of the a test for normality applied to tbe IndIvidual eItlies1n mbseeptlanend t b ttack-la th koff cycle votws orms

the c oallislon) *ycle values peeaerrmally distrlbutad at the 95 merent me nte latbe Utbareptlan) eycle v Ime appe r normally distributed at Itb 95 reent ent nd11cU owlthe tttrk ltntth) cycle vmlus ppear normletl distrlbuted at thc 95 percent conflidnce tevat

...................................................................... ................. I .........................................................................................

the fInal estImated obined seltialean/bserptimn/trmck-ltal tb Raft * 1.0957? with an aetleated standard dovietian *f .90116

t.e estimmtad 68. 5. 4f "'percent ksff Pentfidente Interymls re 1.tO40 to 1lT1075, 1.00719 te 1.11196. and 1.00633 to 1.0127

the emtlmated eeltislen/abeorptiln nautran rotenal lifetlime * .4513 seconds with an astimated *tmnderd deviation of 1.95t-07.................................................................................................................................

way 21 13:54 196 Fite laws 13020ae.sum R5AoCCCO-61?1e200. u 5EV 00 ATTACNENT XI - Pee I

.c wro l dn 4/ tt1 .... *- "26/96 150*33 probl * 66/26/t 16:50.33

iMP1.302Cs. WuTV-i3C2f.O

1- For-iFeld Cr1tiheslty elm 3.61 /fC 0/mt 0 SOX 10e In 02 11302M")2- C Cels. a Its TM f .1 7 e .*O porosity - reffected sphere31- C CELL SPECIFICATIONS6- C WKERE VAINR 0E63035S I 1 t .462700-2 -1 IUsINNI6* C 6U7i8E WORLD

9: SINCPE 6PEClF3CATIONSle: ~ ~ tt' so 0 INNER FlUEL IMZII-12- NOE S13- KCreDE OCN 1. 7 371C- IBRC 0ee 061a0 e @ 0 629I to 00-5 -100-10IS- -5 -t -10 e -13 I10 1e U a -15. -5 -165 s e10le It1114- C lATIEEAL PECIfPCATWONIT- a £7 le water fa ellee oIfto tuff) a .1r 1e volt U02I1- . O I sal a grldmant 20 IOM/ml decayed te Uranim fatepas19- el la1.C I .023- 1416.10 1.165AS1- 11023 .5gc 3.129430-420- 120 0.c 1.36 I- 1 027.30. Do 6733-3 14000.3Cc 9.6680M-321- t9e00 ec4.619460-4 30000. 36000.5c 1.5904-422: 92234.50 : 5 602r 922 .SJ .l16181S 92236.50. 1.c 1!143533- 922.1c .1671-3 93J7.5Cc 3.723657-636- altl Iwt.6t25- PRINTI isftitel asuree fuse hare card. print table.90

Ikoff results f*rs Par-Plotd Criticality Study - 3.6n /20 MOMt - 30 320/ 10M 6102 (13020") robid a 4/26/96 160.3

the Initial fIssion neutren sourse distributien used the 14 source points that were Input en the hare csrd.the eriticality problem was scheuled te skitp r ccles and run a 6.t1l ef 57 "yeles uith ntnatly 46000 neutrons r eyge.this preblem has run 7 Inactive "cles sith 261t1 neutron hieter as end 30 active cycles 0ith 119743 neutron leterfia.

this eeleuiatien has eompleted the requested maber of htft eyeisa vsi a tetal ofall eeloe awth fissionable materiel were empled and had fission neutron eeuree points.

45674 fPlass neutron asuree histeries.

the resulte of the w test fer normality applied to the individual ellision, abserption, and trnck-tength hef1 cycle wevalu ersMthe It2 sellislen) cycle Wela oppe r normally dis ut d at the 9 pergent eonfidence tevtthe kt rptlon) eycle v es appear normally distributed et the 95 poernt eenf dence tentthe cttrk iugth) cycle values appear normally distributed at the fS percent *onfidence level

...................................................................................................................................

the final estimated eombined eelilsein/abharptlon/track-ertnth k2ff e 1.n35n3 with an estimated etandard deviation of .0I"

the estimatad 3, V5, £ n9 percent Oaff scnfidence Intervals *re 1.664? to. 1.e5nt. .5297 t 1.45888, and 1.65103 to 1.05n2the estimated eItlIslenabseorption neutron removal lifetime a 7.871-63 *ecsnds with on estimated stendard deviation ef 1.60E-67

..................................................................................................................................

iL

gay 2 1340 I 996 fle Is: s 3020". X NEWao6 strtr e2eo-eoot t£1t 00 ATIACuENT Xi * page I

Imne versain WOd1010193 6412u19 13347 d*** ***** * ****** ** ** *** *&**** ** ** prbebd a 04/U/96 13:13W~

IMP-13020m eUTP.-1020m"O

t- fer-Fglld Crfleallty tud * 3.04 120 VWmat - 47Z 0ISM 1102 SMOZOa)2a- C callco Ut Is f . l if .7 ee .470 porosity ret eeted sphere3- C CELL 6PIC31`3C*TIONS

I- I 1 8.41994 -2 1 IllPA-16- C OUTS1CE VOiRL7. 2 S 1 IUtiU.0

9- C MFTeI rSECSFICATIOS1C. it so30 a 1 *EME FUEL ZOREI1-12. 300E s

13 £00 4000 1 7 3714. C KREC 06 O s lo I 6 .200 I29 0 2 S 00o - 1 0lo 0 -13. C e *O1C-13 I- U e I I.15 *t0 * 16 3 0 0 la1IC IT16. CC 11AW112AL PRECSICATIINS17. a s 4472 lt Vsat r inoeli lcf t da .13 .13 vat% WO21S. a .6 IrIgIl Sr lh ntl W t/N decayd to Uranium reotara¶9. -01 Soo,.3C f.6T107. IT.3I 4.S9l 1023.I:c .:11420. 12000.c .736516. 1. I 0 8 3 1.9 5 9 40003C 31032l 1900.Oac 4.173 9 4 3000. 3Cc 4794.4 26000.33. 1.03910.422. 92234.3Cc 0 so20ss r 2S5 7.172412- 26 .SOc 1.716222.3233 922303C 3.721. 3 9323s 7.3Cc 4.092986.6U'. *ntl lwtr.0gt23. PalM? t. I

I Initial Idre Ue f rie .rgtIaff result.l for~: Fr-Field iticalf ty Study - 3.05 /20 aD/mt - 472 9/20/ 131 302 (1302m) prabd * 04/26/9 11:13,47

the Initial flasien neutrrn aurra distributian was read frem the arctp file named erctpthe criticality problee scheduled ta ktti I cets and run a tetel f St7 actes with nmnalty 4000 nautrans per tcle.this prcblem hia run I inactive eyesit 94 neutran histories erd 30 active altes wIth I19319 nrutren leteries.

this seltulatien has seaplettd the requested _mber ef hoff ca tes using a tetal of 14823 fisson neutrn eeuree, histories.all sells with fissienable material ware sampled and had f 9asn neutran source points.

the rcmutte of the w test for normatity applied te the individual ectlltte. absrption. and track-tongth hatf qeyla Vtes era sth:e tt ecttialen) cycl alue appear normally tistr buted at the 93 percent *enfidance levelthe te rpton) yc a vayele appear nrm ll tr buted at tha 95 percent confidence tevelthe ttrt tl th) ysle valuee p"eeer nmally ditr ibuted at the IS percent confidence level

...................................................................................................................................

the finat estimated ceebined ealtlelsn/aerptlenJtract-ianoth haff a l.tO6 with n estimated standard deviation of .6013

the estimated 68. n. £ 9 perent haff aenfidnce Intervals are .1S012 to 1.10879. 1.10324 to 1.11067. and 1.10194 e 1.11197

the estimated *eletlien/abaorption mnutron rement lifetime a 4.UE0 - eaceda with an estimated *tndard deviation of 1.24E-Is... . s.*....... ...... ... ................. ... .......... ..... ... .... ........... .

Ray i1 13:44 1996 File Nomet 13030db.smu SA00.17.S0S0 REV 90 ATTACRItEET XIll - Page 1.

Inr. jersiun 4a td-10/02i9 f424/6 1313J,19**a*a*-*eaee ..-eaeea*aeae-ee-ao-eeea ePeea-.-a---.- - prebid a 04/26fS6 13:3019IDP-13020ob WTPsiSD20omb

1- rer-Fteld Critleesft Studk - S.2 /t3 gun/et 471 920( tO tl02 (10320abI2- C callee ittae TV t 1. a t Vec .470 porosity - ref ected sphere3- C CELL SPECIPICAUCIOS4. C INNER MATER 1182w5. I 1 6.3549342 -1 1NPs"-'*- C tUTtlDE llORLD

6.9 e SURrFACE PECIFICATIONS

10- 1- so 70 S 3ItEI FUEL ZONE11-12- IIOE a

.13- (0001 0 314. C 40S0 I 6 -02 I 0 eS 203 3 0 6 .1 -10 I -101U- C -8O -100-130 -C * 14 e 0 -l5 l0 - -16 5 5 S 1@101716- C lATERIAL SPECIFICATI0NS17- a I7 volE nater In eaelee IlItI tuft) a .60 tO vets U02U- e J.63 Orignat Itnrhmentl 20 610/IT decaed to Uranium lasotpes19- el 108i.10 35111- 100l6.WD4 .jU023 p g0 :, 1.70

81an 4

20- 12000.10: 1.t34U 4 13027. 1. 3254L 4 0200 C1c .06052731t1: t1900.10C . 0-4 0000.10 c4.024409-4 26000.155 9.199110.1

22 9234.0a t.1n612 923s. Se 9. 3216-5 ,2236.5Cc 2.2SS296-23- 92238.50: 0.;7-3 93337.50: 5.411314-4

24- atl tr.SOlt

IhnftF resultste Var-Pla Crit6e St d - 301 /2e 61/.t - 471 R20f 30 6302 (6302b) prebid * 04/26196 1s3s319

the initial fisston neutron source dietributien was read from the eretp tile named eretptihe eriticallty proabmm -s ecleduted to stil 7 too VWd ino a tatal of 37 Mtcea with nominelly 4000 neutrons acm cYcle.this problem kaa run 7 mactiv eyclet with E339 flutron b1iteries end ' 30 ective e ls with 120266 neutron eteres.

this cetluletion has completed th reqted amber f eoff spictes using a total of 1U605 fison neutron source histories.atl eIlte with tlessinable materiel were sampled end bed t salon neutron sourceo pinte.

the results of the u test ter nermatity applied to the individalt *etlieien. aebrption. erd track-length efct *ycle values ares

the I solttlilen) eyete volus: appear normally distributed at the 95 percent confidence levelthe h~abearptitan Vs Ic v l.a appear normally ds1trlbuted at the percent ontdeies lenvtthe katik length) ele values appear nomally distributed at the 9f percent eonttdonce evat

...................................................................................................................................

the tinal estimted estined tclsliion/abserptlen/tracklongth Reff a 1.11122 with en estimated standard deviation ef .N6Othe estimated 48 9n, A 9t percent hift cff infdonce Intervals ore t.1093 to t.ll2t7l t..1021 to 1.11423, and 1.14715 te t.oiSZ9

the estimated eolliolen/ebsorption neutron removal lifetime a 3.601-03 escondt with en estimated *tandard devietion of 9.11S31

................................................ ................................................................................

;

any 21 13,4 1996 File owes D30206c.uu 1A000000-01r71020v0.0Ol6 REV co ATTACMUEET Xsl * Palo I

ve.N wrolon 48 l~l8Elm . **-* *'$a"9""" "prabid * 5126/9 13314 M 4

IMP-i3020.cWm elZec

1- For-filld Eritsll ty St 3 J. S7I CUD/at 3 4n 20x 2S UD2 gl 3020mc2 C o ttle tIuti TVft 1.UI7 flat .U0 .cresty reflected sphere3 CELL SPECIFSCAT2011R4: to INER a lATES 2eEU

5. I 1 .31140-2 -1IiNF:E-i~* C OUTSiaE OIIOLD7- 2 * 1 isrsi.0

11 a M1.9- C SMRACE S1PICIFICATIONS10 *1 so S0 S INNER FUEL1 ZONE

12- XOOE S13- CC=0 6000 1. 7 314- E°iC 3 0 1 0 0 0 6 3.20 5 6 290 3to 55 I .5 *0S laIS. 0-S-to -10 I-13 0.10 14 05I-15 -t0 - -16 35 iS IOI?16. 1 MAIERIAL. SPECIFICATIONS1T e j 4F vtEs water In atic Eills tutff * .n 25 volt U02

is- 6 Ax~.0 Sriginal Esiehaeess to 20swimdcee to uraniumn Isotoesto- ~~12000.I0c 1.132220-! 112. 71. 4090.I De *554741.3

2100* 3feD J. c28E33 8 26000.c55 9.21M993-122- 92n.2 b4:10 U:t6u0i: I 10t 1.1954326 IZ536.50c 2.8603?7-323- 1238.50c 5.54638-3 91237.S10c 6.U1643-624- *sl lwtr.SltZs. FAMR

i nitial source free_ are eard. print table 90Ikeff resultt fore Jr-Fietld Criticality Study - 3.0e AG MM/at t 475 120J 25S U02 I302011c) prebid * 4/26/96 13056:54

the initial fiscion neutron source distributien used the 14 source points that were Input en the hare card.the criticality prebln wass scheduled to skip 7 *yclsa and rPM a tOtal of 37 cycles with nomialtty 4000 neutron se r le.this problee Mas run 7 Inactive "cties with 28533 neutron histsries and 30 active eyclcs with 120454 neutren blotare

this cetculetin hkas emeaieted the requsted nwmber tf heff ecles using a total ofatl ieett It f lesetblo steriel were apled nd had fleare nnutrcn cource points.

149239 fission neutron cource historiec.

the resuts of the e test for nortality epplied to the Individual collision, absorption, and track-length eftt cycle velues eras

the kt celliieni erele values appear nermaly distributed at the 95 preent confidence levelthe tebsorlet on) aeycle v s appear nor y distributed et the n tereent entfidence tlevthe Mtirk leth cycl values pper normally dtributed at the ff Erent confIdence lten

..... ...... .. ...... .. .. .. ...................... ............................. ... ...

the final *etimated combined kelisienlabsorpttroch-length heff * 1.09134 with n estimated stndard deviation of .

the estimated ", 95, I n pertent haff confidence Intervals cre 1.09686 to 1.10082. 1.948 to 1.1028D and 1.S9343 to 1.10625

the ecstleted cellietin/obesrptien nsutrn rmevat lifetime a 2.81 E-5 secends with en estimated ttendard deviatisn of 6.141-8..... _. .. .. _ .. .. .__.. . ... . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .

lay 21 14s33 1996 F Le Names 3020oo.jum KEYo0e0e.en1?e2w S u eo ATTACONEXT Irv N Pej, I

ladc verso n 4a IdOC0 SC3.p96 o9t:929*-- probid * 5s3s96 69:39s29iSpsl302008 eutpU no200ro

It Fer-Fleld Crftfeestif t 3.tl 120 lWtt 401 1207 S1 t102 ((50200..A. C 9Calec gis l.s TVtt 1 l5 Vea .4 porosity ref tooted sphereS. C CELL SPECIFICATIONS*- C phEt WEATO AUICEtlS. I 1 8.3639362 *1 IP:EI-6- C UITSICZ VOELSr- 2 o I IeUo

9* jSpRAC9 SPiCIFICAiONs10- 1~ 10* 30 S INNER FUEL 201E11- X 113- ECoCE 1000 I 7 3714- C EEC iaI 6010 0620 6329 t205 o S S -S -0-lIS- C * -20 -10 0 -136 - S 14 S -1s -I S -S16 5 0 10 10 I16- C MAT9E2SIA IPECiF3CATIONS1?- c (40 vell weter In ellee Elitts tut) .9e 5 wet% ue210- 3. Sriginel nrichment/ 20 e110/3 ccyd to Urenium Isotopes1t- *1 1001. Oc .5402J 2 oldOc .14- ; 1023.5Oc 3.n7O9s94N0- 12000.JOcg.197143-4 1027. Oe 2.4741S Xe0.5Oc 1.33609-221- 1900C.S c S.231 6-4 10000.5Oc. 4 07. 1W000.SSc 1.333471-422- * 2234. Cc 3.934 1-7 223S.5Wc .390004 236.5Cc 5.720740-423- 9n23 SOc 1.190938-3 93237.SOc 1.34329-424- *tl lutr.i t25- PAINTI initicl source free file Ortp

Ikeff reaulto fort F r-tleld Critio tIty study - 3.0% no /e * 401 *os 120/ SS U02 (l3020..) prblid * 05/63/96 09:39t29

tte Inttlel fisslon neutron source distributlen wee read from the sretp fite named eretpthe critieelity prebtm a scheeduted te skil cTye, nd run a tetel of 37 actes ufti& nominelly 400 noutrons, rr cyce.tIle preblehin run o livctve cyctes it 2h71 feutren histories end 0 eative cycles with 120059 neutron leterles.

this enctuletien hiae e teolted the requeste d _mber of teft ercles aing a totel *ftl cell. itth flel cebu -aterilt were espted nd had flectin neutron sourse points.

147675 fission neutron source histories.

the results of the w Sest for normality epplied to the Individual eolleleon ebserptlon, end track-lenth Ieff eylet values ores

'he hi oeileo1nj "rcle values Mesr nermelly distributed et the IS perent oonfldence levlthe Itebsorptlon eyspt vs luwa 'Spper nermel 17 Itrbuted *t the 9S persent eenf sdeic: I owlthe kttrt length) ec"e values eapper nermally distributed et the 95 pe rent eonf dence levet

...................................................................................................................................

the finit estimeted seobired ettlielon/ebssrpt1iwtrsck-ternth haff * .89315 ultl on etiemted etanderd deviation of .00131

the estimated U. 93 & 9 percent heot eonfidence Intervals ere .29182 to .N9448 .n99o to .39384. end .68952 te .73967

the estimated eolleelonlabsorptlon neutren reoevnl lifetlme * 1.201-S4 eeconds wIth on *stletted standard deviation of 5.92-07............................................................................................................................................................................................... .

I

Ray 21 14M35 1996 file same i3020Ob.es tum 0000-0l1l1 0200 -001 t£1r 60 ATtAUrEET xNl * Paes 1

1wcl version 4. Id:10101193 03/03/96 10.231!1 pr1bid s r s 10:23,15

I4wi3020ob eutpuiS020cbO

1- Par-Felod Criticalityr 8Iwal 3.61 /20 Slifflt - 48s e20/ 83 U02 ti3020.b)2- C tCtico Nlitta To t.5 Iec .4 porosity reflected sphere

C UPELL IMCFICATIC1S

5- 1 1 6.335845-2 -1 INP,5m1

$: I ws-V I 1FACE SFCCItPCTIONS

le 1- ~ ~~to in IatltI;210. C~~'o 3 UE FUEL 2"1t12 IOWE 913- Kt=E 4000 1. r 3714- C 1s51 01 610 66sI.20 06.89 .05 0.3 s o10 - 31015 1 S11 !20 10 6-136I-i0 1466-5.1I5- a55 10101IT1I C. IAIUR1AL gCIPEiICAIOII17- a 140 Vel% water In *eallee sIle "uof) x .9 a vet 218. e 301 origInal Urithont/ t0 1=N? daced teo Iren1 1ertepec120 SI lee. 0 .460494-2 6O1.1c 4. 16420-2 11023. 0c 1.217l1 4'IC 12000:18 Z1. 0127762 l:027.54:ct 8.109425e 14000 nc 49339-2

fi 19000:500 3:1143044e4I j00:C2P @00.50. i.EP31i 4-23- 92232.50a 1.9055100-3 9237.50c 1.162926-424- 113l lwrtr.1t25 PRINT

Initial source free filte ortItefl results fort far-Pflad CritIa tity Study 3.0t 20 1/at - 40Z 520/ 11102 413i20ob) prebid * 05/6396 10:28.15

the initial fissien neutren esoure distribution pas read fro the serctp file named arctpthe aritisality preblem ma echeduled to skip * rycls end run a tetlt of 7 sCtee withl milall 4000 nutren per ele.this problem has rnm 7 inactive sycles with 2203 neutren histerle and 30 a ctiv cyclet with 120109 neutrsn nistoril.

this eealculetin has coepteted the requested mber of ktef Tycles uting a ttal of 143143 fissien nwutren source histerie.all eetle a th flisleab a material _rs esamped end hd Iassion nutren source points.

the results ot the w test for iormelity epplied to the individual aellisien, ebserptien. and tract-length heft eycle values res

the s eettle on) ercte valms eppear mrestly df at ruted et the 95 p:rc:nt eonftdance leveltbe tHebsortln I ple was app~ea normaly etletr uted et tbe 9S pe reent *enfle~nce tevelth trk length) *cle values appear norenity distributed at th 95 percent centlince level

...................................................................................................................................

the final estimated combined eottlelen/aberptiwn/trec-lteneth heft a 1.01547 with an estimated stanrd deviation of .0137

the estimated ". 95, I n percent heft eonfidence Intervae era 1.0140 to Cams, 1.02i5 to 1.61328. and i.61167 to 1.61926

the esatleated eettliaenlebserptlen neutren remvat lifetime a 6.419-6 ascends with an estimated standard deviation of 2.E41-7j.................................................................................................................................

Kay 21 14436 1996 fits laws I3020m.em SAO0000-617i7-6200.601I REV 60 ATTACIISNt XVII - Page 1

rlp wversion 4. t1d0l/0/93 65/03/96 11,4WS23probld * "3/0/9 11844J23

Inp-1302ite Z utp-1S020Co

1- par-Fietd Crtliatigt Study - 3.61 /N20 JAlmt * 4OS 120J/ 10 1102 (130200c)2- C Ca il. ea I at Igt i5 95 tec .4 peorsity - rfleted sphere3- C ILL SPRCIFICTZhS13t

4- C NNER WATER SENIORI 1 0.314052-3 *t INPslui

6- C OUTIDE WORLD7- 2 * 1 IESO-.

9- C SURFACE UPECIFICA1ONSIC- - t0 so * INNER FUEL 20E11-12- NIOe IIs- ECWE 4000 1. 73714- C ISC 6 1 6 6 10 6 0 0o * I 2 025 6 6 -5 -106 a 1013- C I * -tD -10 I -13 0 .10 14 t-O *15 -to -S i 1 I IC le r1716. C MATERIAL. SPEIFZICATIONS17- a 140 vIS ustEr ingalle. EI to ffll) a .90 10 veIl U020- 0 3.6s erigi4W tmantl W 61lltT d eayd to Ursnum leotw19- m1 1001 D.407003.3 0016.0. 4. 312.- 3.5429077420- 1 0 c 0 0o.8130-4 15027.50. 3.2. 7 14 00.S0c 1.626577.221: 19000. 0e ..031-4 30000.50. 5.12542464 36000.e 1.362U-4II: 922~OZ34.50. .664006. Cc23. 4j 16 I:$ 92236. 50. 1.1:M4461,-

92236 salSO e 3.3015 93231.50e 2. 57-.t1 lustrN It

*5. PRINTI Initial source from file eretoIkeff resutts fort far-Fietld Crtissllty Study - 3.63 /20 W1/t 4 D z40/ 16 V002 113020..) prabId * 63163196 11s44.23

the initial fission rbutron sourse distribution wa read from the sretp file named grstpthe eriticality problem was echaduled to sipt 7 cycles and run a total of 30 tclea wish nominstlythis problem lies run I Inactive sycles sith 33172 neutron higstries and la active antles with

4600 neutros per cye.120097 Neutron letories.

this eateutet im hia cempleted the requested Imaber of Ruff te es using a total ofall selte with fierisnable materlat mare sampled and had fiesan neutron sourse points.

148269 fission meutron sourse historles.

arning, there appeare to be dacreasing trend In the avercse .t1/abestt kaff estimater ever the test 10 active cycles.tho renulte of the a teat fer normality epptled to the Individualet * felon. sbeorption. nd trackt-lmth atff gycle values are

the t ceollision) evcl values appear epoely distributed at the 9 persent s*nftidncee lovel, but not at 95 percentthe tteabserpttoil s 5 values aear mally dietifel ad Ie thae 95 *oront senftidnce lewl

warning. the httrk lengtht ctcl valuoe do nest ppear nrma ty distri b d a the " percent *entfidnec level

tbe final eatlasted ombined *eetlsl Jebeerptiontneck-ltenath heff f 1.650 with on eatimated *tsndard deviaten *f .143

the outlated 63. 9 A, S 9 pereant Roff confidence Intervals aen 1.8365? te l.65941. 1.65S9 to 1.66097, end 1.1340 to 1.16200

the oetlated setllsion/ebeerptlon neutron ezo,,t lifetime * 7.643-U5 seconde mitt an estlasted standard deviation of 1.3SE-07

........................... ................................... .................................

May i1 14 t9 n96 File Imm. 1O20ed.um SSAOOtOOO-61717-0200-00016 RtV o lCAItACERt jVIII * Paea I

lee rslen 4& IdwIC101031d * 66 131 1s32

Inp-0i20od outposI020od.

1- fer-Field CrItleality St& - 3.61 /20 S4WIol 405112Z/ 15S U02 glO02Ood)2- C Calito SIlls Wu V .5 5 isec .4 pores ty - reflected sphere3. C CELL SPECIFICATIONS4. c INKER VATIR UNIez

I I S ia. S5iu-2 -1 I apFu.WS C 1UT 0EWC LO

7- 3 t 1 IN~tCE.0

9- e SURFACE DPECIMATIONS10- I go 30 S ItKER FUEL 201E

12,: MODE aIT- 9COODE 4000 1. 7 f14- C ECKS40 t; r 0 I -0 063 a 1 t 9 0 20 3 00 - .100 -101s-. C e S- -20 S Se13 e -IS -10 14 a a -1 -*0-5 16 10 17U&- C MA ME:AL SPECIPICATIONS1T- * (40 volE ter in ntle11 Sillt tuft) x.tS 1S volt% U0218- a M nC iI is Caihent/ 30 6D10/T decayd to gronlum loot19- la la01.10. IjmzO

3. gol.0c t:I¶mVZ tte23.Ic 4

30- 12000t.S. Oss666- 1 1 S- P 14000. OC X.R5445-3'19000.f9 10950C.0 .4080-4 26000.15c 14;93105.422i 92238A0 .126012 93237.SOc 54241265 92s^° Cc t 16222-5

26- m1 lwtr.Oit1 e- PRINTI initial aource f re ie [Itts

theff results Fero fer-Field Criticality Study 3.61 /20 am/mt 40 1120/ 151 '802 (i3020.d) probed 1 6303/96 1248:12

the Initiel fissien neutron souree distributien mu road from the sretp Vile naed enrtpthe rIttalellty, problewasa sceduled to skil 7 seles nd run a tetl of 27 Cycles with lm lly 4000 neutrens er "eCe.tlhis prebl e harun r Inactive *eclt mith 10 neutron histerips end 30 active "Ce itA 11919 neutron literles.

tise eeleuletien hes ee.Pleted the re ted _mber of Ralf aelee in a tete of 147953 fisseon neutron eeures hiseterle.all cells with fleosleab e materilt *nr smpled end had lmaeel neutren snoure points.

the results of tse v teat for normality applied te the Individusl cellisien. ateorptiln end treck-leth teVV eycle vth ues eres

the RI selisien r yle was appear inermally distributed et the 93 percent *enfidence levelthae Itebsrptien) ert:e vlueas ep r nermt ly ditrlbuted at the 95 percent entICdense levelthe httrk ientl) cyl values e per normally distributed et the 93 reent eenfidence level

...................................................................................................................................

the fiVal estimated ceabined eelelen/lboaerptietreck-lenuth tett - 1.09023 with en estimated *tanderd davietlen *t .tOU5

the estimated 4 I t5 pereent heft centidenee intervals are 1.6lS36 t 1.09190, 1.U63"e to 1.9361. and 1.63367 te 1.09479

the estimated celllaenlabserptlen neutren removal lifetim a 4.171-03 secends with en estimated standard deviatien of 1.325-57,.................................................................................................................................

I,

o t 0 %AI PitWr GMLnO= M -mD=E IM *W Km-h I

wuM Wdo kw*Om GYAI W% p6d 1499

I-

4- Iummmrmum5 1 IILZM%4 *I mP*46. C 6R3UVW7. DP"~g~

v S. TV 69 RLW

9 MC C lo SSU 004603 035 GM614 MO51

UD- Id W044.US.US49.064-U5416

21- ad bi3Utr jamt

&1 mitI k g~lm=m*ifilteorbxfit .. W 9i a-Ph&Idk 1Wt~aI'I*-LCAID * OWYn~M Utn * w

dds stadan Go mavs7 bt1w de IV u a" wtv a Odof IV* k"Lm-=kf

ft vmintto IN .3 W tw ,mUw~r ohd miGO iIrdUW sdtkisai ~tit ad We-.o kf cs sWAm su

G U3 edliwS qcgs *= m pw vedtydN&§km*3 U miwimmoAVs tUta i~tWQOAdam qwme~dm*AWi U pwt iniut"

#s kul -PI I -Ut mm lAmdmst Am~

is '~I O U. A S9 pwmfW -if igfIm th3Ms sy IASI ia I.SM 1I fa 1P Ord 1=5M IANW

is - ledlis aowpttfmuu mpm .iUfmftm~ft 535 %inV mtbmbagVsdfgwbm U L

i.

May 21 14i42 196 Pites Keai * 30204f.sum e3A00O-00117-S200-Oo16 REV 90 ' ITACUIENT xx * Page 1

1nex v=****rsn 4s . ldos/01/93 .eS/3196 15:25319 prebW * es1596 15:2 19

i1W3020of eutpsol52lOuo2: ^e xor d Cl /2l t0 G/mt 401 t20/ 253 t102 13020of)

- t t feett I a I t . S sloe .4 porosity reflected sphere3- C CELL SPECIFlCATIONe4. C INN1 WATER UNION35. t 0 8.1546400-2 -1 IMP l31

7. 2 S 1 IUURE P o

9. c SrURFACE SPECIF 104A7T010- tl so 30 a I83CR FtEL SOMEII.12. moDE I3- ECcoo 4000 I 1 374.- C I .5 U 0C -t 41 .'510 99 1. 2 099 s 8120 5 . 5 * 1t 10-I

1. Ct IhAThhUAL SPECIFICTIONS17- a 140 otZtat Ite r. "tie to1 turff a JS 2S vt%1 U02la- a Se g0 rill I deca nd ts Uranl_ iaoseota

- Si l e t14.340e43S 1e 2S.0c 11214820. 12000.S~e Ccn459 * 13027. Ct 1.935222-3 14000.1Cc 341OS3-311. 190C0.0 c 4. 9p0 Ito" 00.: 4.7194 00 c 1.C32T0-

23- 2234.5Cc %.4 1 04.9 t 2233. Sc '.I 9502U 4 12236.0c .96030-S3- ~~~92238.5c S.9368-39337.1C 6.321943-4

14. *tl tutr.olt

I initial source frau file sortIIkeff results flar Far-plald Critlcatlty study - 3.X 120 GWD/wt - 401 320/ 23x U102 i3020of) prebid * a $5/93/6 15123:19

the Initial fission neutron meor. distrihutian ws rood from the aretp file named *rctp .the criticality prebtm wcs echduteed to ski 7 let and ran a totat * 7 ycleas uith noInalty 4000 nautrens per teethis probloem ist rn 7 Inactive ycecs stt gt1 neutron histories and 30 actlv eyCelA uith 120514 neutron Siatorleo.

this lotulatln has s*mtoted the requested -1br of keff Tles using a tetal of 143U5 fission neutron eourc. histories.atl eoll with fiissinab *oterilt wore sopted antd had fl tean neutron soureo points.

the results of thoeu test for normality epptlad to the indivdtual eolision. bcorptiln, and track-length tefI cycle values rer:

the hi ehlisianl syclt: value appear normally distributad at the 93 *oreent eonfidenco levelthe i aberptInl "ycle values appear normatly distributed at thb 95 rCent eonflidnce leoylthe tttrk lenoth) eyl values appear normally distributed at the n percent cenfidence loeal

...................................................................................................................................

the final estimoted *eobined setisin/abaorptlinltrack-longth keff * 1.96938 with an estimated ctendard deviation of .J0142

the estimated 43. 95. & 09 pereont koff bnfidence intervals ere 1.06794 to 1.97062. 1.86647 to 1.67230. ntd 1.e6545 to 1.37332

the estimated esltislon/absorption nautren rseevov tlfetime * 2.71£-03 s*cends with on estimnted *tandard deviation of 6.731-03, :. . . . . . . . . .. . . .. . .. . . . . . . . . . . . . .. . . . . . . . . . .. . . .. .. . .. .. . .. . . . . . . .

Ray 20 07:60 1996 File asme 11-3.OE 205W 0W-30I U REV O00- A71-200-oo REV e0 AITANItNET lXI - Food I

1.¶ version 6a Id1 ol00l" 64120196 *22t 1g0 p.* ee e.. eo.*.O .. *. e. .rob.d *o4ee20.9& 22Me. eOMMR~S.04105 OUIPBSO 0.10wI-ees forfle o0%Voer52 - 0

1- FarField Critieelitry Sphere of Trensmuted 3E E 300 hater 5S U-Sp 022- C hInf OptimizIoe3. tC St6- C SNINES5- 1 I s.0nx1m4l6-2 -1 glUPall S Urenium/luffllater6 t C 31 .11121144000-2 1 *2 INPaN-c S Tuff/Winter Reflector

1: CC WUtDE WORL9- C INP IaO S VoidI1S so I NP~U.0 S Void

12-: C on PAOES13- 10 3 OR 1t.114.1 Ifniteht 935311 SPECIE

1- C a 0 0 1 REFLJCTOR

earning, thle surfiee has been replaced by a surface of type so16-17- NM0I I'Er KORE 2000 1 33 15I12. 0060 1 6 0 -1 I 0 1 010 0 1 00120- * s -1 o I*I I 0 -1

2** ' ¶ 0 t ' 1 -t ' ' *t |24- 922St .10c .93403i-7 9223. 1 0C 1 2236.50C 5.720740-6 S Pi25- 9223J8.C .19093-3' 9322357 .c 894329-6 9016.50 4.29695Y-2 S At

16: IOIOC1035an14000 w 3 250744:j 13027.50C a 864618-3

at- 26~~~000 n3c 1.531-4 12000:510c 2a141565-4 2000.50C 6.25?M-64 I1129- 11023.90C 4.323713-4 1900CC 11.1 084l1-4340- N11 LVT4.01731 p ' 3 10M .me 2.0053-2 14000.30 I.S1S941-2 13027.90c 3.001S3&- '32- C 20016.500C 6.2635802:133: 8 26000.5s0 1123 559I 9 12000.50C .675121-4 20000.50C 65.57122-4

3 I 11023 50 46553382.5 19000.1500 6.429990-635- C ITS TIlVAMTS6- PtJUT

I Initial :ourse free kare card. print table 90

1koff results forg Ferileld Criticality - Spher of Transmuted 3.61 200W0 30% Water 5S U-lp 02 prebid a 64/20/96 M2OM

tic initial fissin neutron course distributifen eed the 23 source petnts that were input on the Raeceard.the eriticatity problem was scheduled to klI I3etlee 1 run a total of 155 eteas with nominally 2000 neutrons Par "Cle.this problem has run 3 Inactive *cyles ui 65542 nutren histories and 125 ectivo ecyes uith 253830 neutron histories.

this ealculctlan has cm btetd the restd aber of koff ccler using a totat of 316392 fission neutren saurce hIletries.all cells wIth. tfe inable aterial were sampled and had fissien neutron source points.

the results of the u test for normality appled to the Individual colliIlon, absorption, and track-length keff cycle values ore:

the hIf ceolisen) sycl walues appear ntrally distributed at the 95 percent confidence l1elthb labeorptienl *"le vwluas appear normally distributed at the 9S percent cenfide c 1lotthe kItrk tengthl sycle Values appar normllty di tributed at the 99 persent confidence level, but not at 95 percent

May 20 e745 l9 file lamet I1-3.61-20Gl0*30OSU IACOOCOoo-1717-S200-0001gtry 1o £"tACiEXIT I l * Pse a

...................................................................................................................................

the final eatimated cebtind edllist nl/abarptletreck tenath keff * .90721 with an eatimated Standard deviation of .O53

the estimated , 95 9 percent klof cenfdme. intervels are .90634 to .MI .s48 to .90394 and .90491 to .995

the estimated eillsien/ebosrptln neutron omweval lifetime - 1.323.54 eacende sith on estimated Standard deviation of I.3 -87

...................................................................................................................................

*ay t3 07138 l996 pift EaNw 12-ME.s-20CUO-3SuIOU 0S1ACCOOO-S171?-200-00016 REY 00 £TTaCRENT XXI : - Pas 1

1m . ve** rsion * * td-10101193 *s***4*,*** 1*20/36 ens!IbOM i~/s ss02probid 4 4/20/96 33.1029IhP- .Shi: OUP.T3E10.10

I. FarFtetd tritiseit * Sphere of Trnrmuted 3.61 201CD Jim Water 1C% U-Jp 323- C kI Optim as IonS. C4. C 313! E:EI S rnislufWE ~1S I 1 9.83342432112.3 *1 111P:K-I S UraniuW~uff/Vater4. C * 3 s.11121U4000-1 I -2 31311 S tuff/Water 'tsfecter

S t EUSIVE lOlU17- so S a t£p"-o I VONe- e £17601 W e Md

2 ~ ~ 3 e 2 2Ntu;OSeesII.t2- s suaFACE:So en emf 3 5P10113 i -i a e a .e. e S1*Ininfte FI RMS MERE14- C a * * 6e s 4.11 S EEFLECICR11- C

warning. this surface hs baeen replaced by a eurface of type so16-1T- ROD3 Iis- lC£1 wo00 1 33 s1119- IS1C a 0 160 -t 1 61 e - 0e e 1 0 0-

20-e 1 1 1- 10 e -1e-22- 1 I 1 1 I 11 I 123- I I -1 I1 . .1 I 4:1 :134. RI 62234.1 CC J.630621j ;2235.10C 4.:$Ifl:- 112336.50C 1.1"S4 84 1 S PE5s 62218. CC . 1875- 3237.50: 80MS 16. Ceee I @.C 4.3L2 - S AtEs- 1001 .10C 1.305254-2 S an

I- a40ooo 1sse 1 a100.0 .027.5C s .713848-3 S es26000.55C 1.401203-4 10.CC .407609-4 20000.1CC 11.928416-4 * WI

- tt'11023.oC 4.63044-4 19000. see 'r786991-4 ' so30- ElI LUTE.O1T S Vs31- C 33 1001.30C 2.405m836 14000.5CC 1.319341-2 13027.1CC 3.611387-3

R SC 123:539-24 12000.10C 3.675121-4 30000.1CC 6.587122-434- C 11023.3CC 4.5153332-4 19000.50C 6.429990-435- C N73 LWRe.6e136- PRINT

n lnstit eurce fro kare cord, print table 90

Ikeff results fOrt FerField Criticality *- tphere of Trnauted 3.03 30010 SO0 Water 102 U-Kp 62 prebld * 64130/96 23.S0.39

tie initial fission neutron source distribution used the 33 souree points that were input on the bare serd.the crttieelity preblem wa scleduted te sk*p 33 eyciee and run a total of 118 rycles with nominally 3000 neutrene pr ercletthie problem has run 13 Inective eye wsith 46233 neutren hietortes and 1US activ e elee with 250174 neutron Iele eIs.

this ealculetten has empteted the requested rnmber ef teff res using a tetlt of 31640T ftesien neutron oure liseteries.all cella with fisslenable esterlel were sapld nd had flet en neutron source pointe.

the eutts of the w test fer normality 6ppled to the Individual cellisien, ebs rptlien nd treck-tength Reft cycle values ore,

the ki etllielen) eycle vetoe eppear normally distributed at the 9 percent eenfldence levet, but not at 9 percentthe ktaaerptienl ee y t v e aear nr ly distributed at the 9f percent confidence levelthe tik tentht ycle wV e ppear ormal y distributed at te percent onfidence level, but not et 9 percent

lAY 20 0712 1996 Fi. Boost 2-3.IE-OCUOD-bS1COU BaAyO-S U So8 00 ATTACKUENT 1I2 - Peg* 2

...................................................................................................................................

the final estimated ombined ccliiein/aebeorptienltreck-tength keff * 1.63712 with an estimated standard deviation *f .10104

the estimated 3. 9S. e 9 poercent koeff eanfidence intervals ere 1.03608 to 1.63316, 1.03506 to 1.03919. nd 1.64333 to 1.8396

the estimatod eollislerVabsurptlon neutron removal lifetime a 6.863E3 Secende with an estimated standard deviation of 1.27?*S7............................................................................................................................ i......

ray 20 07O0 1996 Fite ame: 13-3.ME-201UD-IMSU ERAUOOOO0017.-0200-00016 EW S0 *TTACOMIT 31Ill * Pge I

1 cnp ... vrelen 4* Utd-COIJ3 US11896 11a16agA** e -,***-oeo oe#eoeeee ooeo **-e .- ee-e.eue-.--o*e--ee probeid * 4/18V96 MUM IaaSOPd.3.1: E UIP-3.OE.10

f- PerField Critiesity - pAar* of Transmuted 3.E 201 30X Vater 152 U-Np 02a- * k Inf3- C4- C 5733315. I I 7."45311i4353i2 -i INPlIl S Uranieanuff/Vater6- C 3 I i.1I121144000-2 1 -2 *KPsUI81 1S Tutvat e fetor 1floe7. C*- C UISflE WORL9- C 30 S I IMPaled 2 Vold

10- so 1 IlNlIO $ Void11-12- C SUIRACIS13- 1* t S * a 1t. E *inlIntite HU8 E SPIEl!14- C 2 8 C0 0 183.1t e16PL11VTOis- C

warnine, this surface has beon replaced by a surface of tvpe as16-tJ- IIDE ItJ- COCIE 2000 1 13 1319- 1t53C SOS 15 -1501 @ e15 S-* 55 @ 1 So-020- 1 I S 1 -1 * 1 I 1 *-121- * 1 * 1-15 -1 -1t -122- S@ S-1 1II S-23- 11 I 1- I t-1-IU4- Xi 92234.30C e.02z93- 92235.0C 7.172012-5 92236 SC.71222-3 8 Fl25- 92238.50C 3.S72313-3 93Z37.S5C 4.092986-6 S016U.O0 .359266-2 e At26- 1a01.50C I.YC4U621 San2?- 14000.5CC Ido21440- 13027.301 2563079-3 t n28- 2600I.5C .0025 000.0C 33731S3-4 20000.101C 5S99056-4 S 6I29. 11023.e0C . 70375-6 1000. c0 . 6592-4 S 3030 IITI LWITE.OlT 6 Vs

I1- e 3 1001.30C 2.058331-2 14000.5CC 1.319341-2 1S027.3CC 3.015387-332- C 016.10C 4.265502-233- C U4000. SC 1.623559- 120003SC 2.7l21-6 20000 SOC 6.587122-631.- C 1I0Z3.JC 4.553382-8 19000.50C 6.429990-435- C IT3 18TN.O1T36- 9231T

i nitial soeur frs kre card. print table 90

I.9ff resulta fors Pereltd Crftiletity - 6phere of transmuted 3.0E 20UD0 3Z Voter 15S U-4p 02 probid * 416/96 ISi1aM

the initial fission neutron eoure. distribution wesd the 23 source points that were Input on the bare card.the criticslity preblee was scheduled to skip 13 cycles end run a total of 138 cycles with nominally 2000 neutron r cycle.this problet has run 13 inactive cycles with 2373S neutron hietories end 125 active cycles with 251201 neutron Isoterie.

this celulation hoc e"tpeted the requsted uber of Iaff e 1ea using a total of 2936 fission neutron eurce histories.*It sells with fissionabl maeteriel were saepted and hed fl1ee neutron sourbe points.

the resutte of the u test for normality epplisd to the individual selttlieln ebeorption. end treck-length .hff *ycle values se:

the hi sollisien cycte valwue eppear aermelty distributed at the 95 percent sonfidence levelthe kttbserption) eyc s le. epper normatly distributed *t the nS percent oenfidence levlthe kitrk length ycle vl appe brnormally distributed et the 95 percent *onf dene lev

May 20 I7WO 1M9 Ie rtsait 13-3.051E01YO.SMM15U JCA500D0-DS171742B0.S0016 EV so ATTACOltEnT XXIII - Pas 2

..................................................................................................................... ..............

the fital estimated embined eeIttisen/abesrptientrk-letongth keff a 1.05135 wIth an eatimated standard davietlon of .90113

the erstmted 4, 9, 9 9 percent keff smnfidence Intervals ere 1.05351 te 1.057. 1.5239 to 1.05691. Vnd 1.6515 te 1.74

the estimated settlleenjobtorptlon mutran rmovat lifetime - 4.569-65 aftends with an estimated standard deviletln of 9.273-48..................................................................................................................................

Nay 2 M727 1996 file lese 14-3.SE-20CU0-XoD10U 1ACCOCODC-S1717-0200-00016 REVY60 ATTACININE XXIV - Paloe

Imem.cfi. rolon 4a .1.tIelC 93 P120.96 22619:59* ~~~~~~~~~~~~~prebld U 64/10/96 22:09:69

I117.3.11201 OU1P.30E2C.30

1. ParFli!d Critieslity- Sphre, of traneuted M1E 20cUD 3O0 Water 02n U-lp C22. C hI In# optimization3. C4- C SPIERE

15- 1- t 731 6614.D .1 3I1N7.1 S UraniuIE luff/vater14 C 3 9.1 IIII 000-2 I 2 CIM110 S Tuf f/Mter Reflector7- C

9- C 3 200 1 WORL D

tO 1 e 1 8 *3 § ; ~INFI lea, Vold e ee1

is o so" " i nRP:1..o I

12- C SURFAChS13. 10 5 a 00 I¶0.00 S `*Inftnite PZSSILI SPHERE14- C a I 0 a 0 -17.1 S 1 E1LaCYoa13. C

warning, this surface has been rsp sced by a surface of type so16.1D- NMl UaIS. 30001 l000 I 33 13819: 50

31 1: 1 :1 11 l: -6 6 1 6 .

51 xi #22U.CC e. 73l22.492223 .3CC 9.5332164 92236.15C C .28 5W- S15. 92238. 1 CC 4. 4375-l 93237.1C0C 3.43M14.4 504.5CC 4.390421-2 S Ata2- tol 1. . oeSt650 2an27- 14000.11CC 1.34731- 1027.jCC .411 10-1 5 CB

28- 2~~6000.35C 1.26854?.1 120. .1 :9809?:4 205.6C3 96981-4 S VI89 11023.10DC 3.442706-4 ItS55552 C 5 so30- NIt LVtA.C7 a VA31. C 113 1001.13CC 2.003338-2 14000.9CC 1.319341-2 13027.9CC 3.613387-332- C 10516.354 4.265302-333- C 26000.13C0 1.623539-4 12000.11CC 2.673121-4 110C00.50C 6.337122-4h5: c ~~1,1023.3fC 4.3353382-4 19000.5OC 4.4*9990-4

I -Initial source frem bars eard. print table 90

lheff4 results fore FPrileld Criticelity Sphre *of Transmuted MSE 20510 3S0 Water 202 U-Op 02 probfd a 54/20/96 22:69:09

Ie Initial fisslin neutron souren distribution med the 23 saure. points that ware input sn the bare said.tle eriticality preblem usa acheduled to sklp 33 cycles and run a total of 158 cyclea with nominally 2000 neutrons car cycle.thte prebia baa" run 33 Inactive *Yalte .Ith 66069 nautron histories snd 125 active eycle with 25014 neutron teo ria.

this salculstien has completed the requested --mbor of keff Iy le wine a total of 31488 fission neutron source histories.sit salle with fasaeinable material war. sacpled and had faaTlon utron source points.

the results of the u teat fer normality pptled to the Individwal aellisen, abdsrption, end treetklsnth keft eyle values areo

the hI Molliston) ynle values appsr norally di"tributed at the IS percent confidence levelthe hi erptlon) xycle valews appear Normally distributed *t the 95 percent cnftdence leveltbe r length) ye valeus appear nermulv distributed at the $S pereent eotnidence level

Nay 30 17? 19e file am: I14-.01-.3W-D-30U REVDCtO-4l1 200 B EV 60 £lAUIUENT XXIV - Page 3

.................................................................................... f' ...... ...........................

the fIrat estimated unibined eetllsien/abs rptluVtreek-lenath Lvtt k 1.13934 Bit an eatnatad standard deviatlen of . 1O22

the estIasted J. *S3 9 9 percent haff en idance Intervals are 1.03812 to 1.thd 1.3691 to t1.0&177 and 1.1612 to 1.6b.2

the estimated estliseieoebsorptlen naut remoal lifetime * 3.311563 scond. with an estimated Standard deviation of &.79143

..................................................................................................................................

lay to 67?2s 199 Filt 9as tI-3.S-20,1U00-30U2MU S3A5OODo0-1717-0200-50014 BuV Se ATTACMIIT SXV - Pae. I

4nn ~~~~~~~~~~~~~~~~~~~~probid. 05114/96 195:9312

11P0393SV2 UUTP*313M02S.

I. Far is!d CritilcIII;.Sphere of Transmuted I.BE ZOCWU 3es Water 32 U-Up 022 C h-mtff optimizTene

4. C MIE1S- t 1 T.1674411150-3 -l lltsU-1 t Urenim/Tuff/Veter6- IC 37.st r1292024004 1 Z NlPSNMI s luff/aeter Reflector7. rS- e UITSISE WORLD

IS- 3 0 e il wsU 1 S SVoiIt.l2- C SURFACES13- 1e I a ISC ee 00 8 *.ninito FIRMS 1 13 SPIERK14- C 1 * * n 74.,1 S REFLECTOR

u'Sisw. this surfce has been replaced by a surface of type so

- WODE IIIs- KCODE IS 1 3 100319- KUAC BBS I a a -1 BIB B-S1 B t e I * 1 B-

2l ~ f *1 r .1:r 1 * 1' 1 atelo- I I~~B I22- 51 1 BI I S - --2E- 1 1 I -1 1 1 -i- 1 - In- ml 922 DC 14716-6 92233.50C i.1s 4024 922is.SeC 2.560375-5 B pi

as- 92233.5CC s .Xss'ua-s 93237.52C 6.21643-6 51016.550 4.4215f-2 , At

n7- I4500.555119 -c 5104378 Is527.SC 3.261340-3 s Ca

O0- 71110 SC t Ma 1301- eC 1 ee0 1.50 C 1.337225-a 14000.SDCS.319341-2 1i327.5C 3.051317-32-: C 11516.5413319-I3 c a' ieo6000sc 1.M6259-42 12000.55c 2.67S121-4 20000.35C &.587122-4

34- C 1152L 11C 4.15332-4 1900..sDC 6.429995-43s- C IT3 LUTI.OIT36- PRINT

I initial source from kare cerd. print table

Ikeff results fort FPr~leld Criticality - Sphere of Trenasutod 3.61 25c0 3S0 Meter 23s U-tp 02 prebld a 05214/Jf 16:5012

the Initialt fliseIn neutron *ruree dlctributin vied the 23 sourse points that were input on the tare card.the criticality problem was scheduled to ckf p 3yclss and rum a total of 1003 cycles with nominatly uo neutrons r cycle.this preblem has run S inactive cylets th 71 neutron histories end 150 active e"ctie with 251306 neutron blateres.

this ealculetian has eampleted th req teWd mmber of heft cycles using a totel of 332017 flselon neutren source histories.all cells with tissienabte material. were sampled and had fleasion neutren souroe points.

the results *f the v test for normatity applied to tkc Individual, etlision, abserption. and treck t-ngth haff cycle valuns oreS

the khi aellieln) cycle velues appear normally dtitributed at the 95 percent canft dnce levettte (bsertucy s appear normally distributed at the 95 ercent centidence levetthe tkth lengthi) cycle vetus. appear nerest ty dietrigbuted atthe 3 argent seonfidence towel

I

nay X3 6725 9M UIte Names 11_t 52!3O0SUSU IAOeOOo-S171?-0a00-00016 I ATTACUIDT XX7 * Page a

...................................................................... 6.............................................................

the final estimted ewined ecltilcnJ/aberptientrmckt-et nthbft * 1.60732 mith an estimated atandard dviatien of .0121

the *stimted U. 95, & 9 percent taft confidence Inttrvals ore 1.10611 to 1.00353. 1.10492 to 1.60972, and 1.00414 to 7.1051

the estimated ctlilsfen/abaorptten neutron removal lifetime * 2.49-15 seconds aith en estlated standard deviation of 5.371-61...................................................................................................................................

Rey 20 14Us, 19n6 Fil a ws *11-3.09-20dI -2M0SU u a0o0o0-01717-200-40016 RV 00 A"TACUtENT XVW * Past 1

Wmn r 04/30196 11S3230s........arn .ss.ce.sse.ce.a ... eaea.ssa..s..es..e..m..a.. prebid * 04/30/96 MUM11tSJINP.3E20VCS1 OUTP42s0n5 .

1- farpleld iriticalt Soaphere of transmuted 3.6E ZOCUS 20t VYtcr 5* U-Up 022- e ritn t3- C4. C SPRERE3. I I r.1i9344?1^6-2 -1 IN1is1 S Uranlmuxlufffvater6-. C I 3 7.10392240003Z I -2 INPU-1 IS Tuf f/Mter Reflector7- C aS. C GUT1130 "Rio59. C 30 0 E111iKC SyVold

lC- 30 a i INP41ESS S Vold

I" I 0 00 @ G 10.60 4 S Infinlte PIESIEE 5IE3E1t: C a a e e S 14.1 SIFLETaitIs- C

warning. this surface has been repLoced by a surface of type ao16-17- I00F N18- 1000 500 1 3 S0319- "1 e'0 10 I -100 I* I 0 -1 10 a 1 6 61

lo, z1* 1- e: 19 lc 11 -1

14. ml 92

23c .5340314 923.1 0 9 2 1 32 * * PI

25- *9223.S 1.t909J3 93237.S0C .3 329-4 t0t40 .t:936e-Z 2 lU- 101. DC 1.270364.2 ' n

2T. 14400 c.C 1.233742 13027. te 2.e a CaU8- 2500t SSC 1.542381-4 1tOoUoc 2.341365-4 20000.30c 6.25rr 6-4 V I29- 11023.5C 4.325713-4 1000. CC 6.108491-4 s3030- 3t1 Eti.e1T .. $ UM31. 1 U3 1001.50t 1.33722S-2 14000.5Cc 1.319341-2 13027.30C 3.815387-332- e 8016.5tC 3. 396-233- C 26000.55C 1.23539-1 12000.9OC 2.673121-4 20000.50C 6.587122.414- t 11023.5SC 4.51333Z-4 19000.SDC 6.429990-4

36- PAR1TI Initial source free terc eerd. print table 90

Ikoff results for: ParFtlod Criticality - Sphere of Transmuted 3.0t 20C1 201 later SS U-llp 02 prbeid * 54130/96 11MU30

the initial fissien mautren source distribution used the 23 source points that were input n tte hare eardtecrIticality problem was scheduled to skit 3 acdes end run a total of 503 yclce mith neinatly 500 neutrons per *c Io.this problem late run 3 inactive eyles th 14U? nautron histeries end 500 active eycc Ult 250104 neutren iltories.

this calculation "a* tcotied the requestod *Ambr of hoff criles using a total of 25159I fission neutron source hfetorles.Otl celts with fissinal"et material wre stpled and had fslee n * neutron source points.

the resulte of the u teat for nermality apptld to the Individual cellisien. absorption, ad track-length hoff cycle values ares

the ki etllision) c vaus appear noralttV distributed at the 95 Ere nt enftldence levethe ht absoption) cycle velwus appear normally distributed at th 9f pecnt enfdence lvthe t trk length) cyce values appear noratl w ditr buted at the 95 reent eeoifdone levct

"By 20 1ev01 1996 Fit* SMI 31 3.1RE!2UOD-20IMO5U SAODOOGO.01717,0200.0016 REV s8 ATCIENNIT XVI . *pag e

...................................................................................................................................

the final estimated eriabld eellitlencabserptlatrgcktlerngth kaff a .9254 with an estimated standard deatien of .09the estimated U. 95, & 9 pereant kaff enflidence Intarvele are .927s1 to .92941. .92657 to .9355. Nd .9295 to .93096

the estimated etetlelon/Absorptian moutron removal, Mietin * 1.26 *34 casnds with an estimated standard deviation of .m121. sA..................................................... ...............................

Nay 20 1359 1196 ril. eam1s 132-3.CE200-t0D-2CM8u 91AOCOCOG-St171I?200-42016 tHN 60 ATTACNOW? XXVII -. Page 1

prebid * 34423191 MIMSI-s3.0etess =Fl.303. 101

1- farzeilJdCrittielitr * Sp-tare of Tranuted 3.01 bUmC 205 Water XI U-lp *22- C lnf OptIinIoen3. C'. C "KingE54 1 ?.12629630 2 -1 ItPsf I S UraniunTut iter6- C S .10s29224000-2 I 4, tKPs111 S luffllater aeflecterT. CS- C OUTSItD MILI: 3c , S0 2 IlU0. t a oi Veld10* so @ s IRPIK-O S Vold

12- C SURFACE&13. I* 0 ° go 16.00 S *Infinite FIISILI SPNERE16. C at 0 174.51 S REFLECTORIs. C

ur6ng. thsle surface hae been replaced by a surface of type me

15S MOC e 000 1 13 43t9- Ni1 0 6 a 1 a 0 t a t I I a -10 0 0 I t a 1 -

21 it :1 61 1 I S a -1 S122 e -1 t I e 11 S1 -124. Pi 92234.CC 4.69450.-7 92235.5C 3.825286565 92236. CC 9.15314-. S rl25- 9223.50C .0ssoo-3 93237.5sC 1.1SZ - 50S6. OC 4.0osz0- S tA36- 1001.5eC 1.23027-2 * en27- 1U000.50C 1.213793-2 13027.r00 .741563 S C2s0 26000.55C 1.49n6764- 1200 6111 20000.5sc 6.060152-4 S ill29- 11e23.SCC 6.1091114 19000. C 45311-4 S,5O30. KTI LMIFU.011' a Me31. C la 1001.50c 1.337225- 14000.1CC 1.319341-2 13427.50C 3.015387-3

32. C 6~~016.300 3.931696.233S C 2t6:000. S .235059 4 12000.1CC 2.675121-4 20800.500 63587122-434- C 11c23.50C 4.5153382- 19000.50C 4.429990-435- C tT3S LIR.01T36- Pr317

I initial source from tere aerd. print table 90

Ikeff resulte foer FerFlotd Criticality - Upher. of Treusmuted 3.01 20Cfu0 20X Iater 103 U -1p 02 prebld * 041231296 1991968

the Initial fiesion neutron source dietribution used the 23 seurce alsts that wyre Input an the hkre card.the criticality problem u echeduted to skip 13 ltee cnd rmn a tetal tf 43 crcles rithrnominalty 4000 neutrons per cyclethie preblem ais run 13 Inactive cyales uith 51n9 utren histories end 30 acive r ter with 119762 neutren eisterles.

this aeleuletien er teoted the requested number of eaf cycles using a tetel of 1t1601 fission neutren saurce hieteries.ell clls uuith fiaafenabla material were templed and bad fission neutren esurce points.

elms resulta *1 theu tv t for neraaliSty applled te the IndivIdwl collision, absepte end trackt-lawth keff cycle values ars*

the ni ealltlen) cycle vtues appear normally distributed at tme 95 persant confidence levettlbe k aerptlen) cycle Il appear omall diceritbuted at the 95 creent confidence leveltie kitrk length) ctycl ntres appear "arcall dvetributed at the 95 *areent confidence lene

Nay 20 IMF59 199l fi t e Ssa 32-1.LE- 209 1210WU ISAOOOO trz717.O20-SO0t SW (tt o An TUCINE En l VII * pagea

...................................................................................................................................thr final estimated ecbined eAllaeloneabasrptieontrace-tlnath off * .M902 with ean estimated stendard devietien of .00156

the estimated 1, 9. A 99 penrent ff cenfidence Intervals are .M944 to .99n 0, .99183 te .99521, end .9971 te .n93s

the estimated eolliesin/abserptlen neutren removat lifetime - 6.223 05 aeconds wilt en estimated standard deviation of 2.1me-7...................................................................................................................................

Key 20 7S1? I"6 Pile ees 13-3.SE-20Md0-211O U NA8003000-0.17l7*200-SO016 REV go AUtAfCxKl XX1321 - Pie. I

I versin 4a 14-10 "0119 64/2296 l~tStal4prebid * S4/2Z/9& 14l3S,14

IEP.3.9110Z 0UIP-SIE10.10

1- errield CrltiFel ty * Sphere of Transmuted 3.01 20um 2es mater 10 U-lp 02- cC k-tnt Optimismt len

3. C4. c Spam85- T t ?.13sann12- -*1 IUPasu 2 Uranigu./ ffr/vter4. C 1 3 7.1042922 000e 2 1 -2 uepIUll S Tufft/eter SeafIctor7- C6. C SUTSIDE VORLD9- C so a 2 117,.0 s efid

10- 30 S I INaINSO S VoidII.12- C SUEPACIS13- I- £ 1 O 10.00 S 'infinite *112U1 37NER814- C 2 S 000 174.11 n PRI.E CT03

"M int th1e surface has been replaced by * surface of type so16-I1- lloO I18s- 1001 8000 1 13 4319- *1 1 11 .*1 I I I10 01-10 0aI 0-1all e.1 I .11 A 1- 1

34- Ml 1234.10C 1.868062 1r 23S.10C I.;140805 25I&6.seC 1:1$"I pi25- 2s5 seC J.3s1s7- 237. OC .r 6375r so 80 C 4 $ At26- GO1.10C 1.2030S-2 5 *n27- 14000 1.107407-1 13027.50C 2.7138483 $ Ce2S- 26000eo C 1.41203-4 120050.c 2.407609-4 20000.D5CC 9.9281@-4 lVI29- 11023.10C 4.0988444 19000.1CC 1.T76991-4 S so30- WT1 11173.0111 S VA3Si- C M3 'O0.JOC 1.33722532 14000.10C 1.519341-2 13027.10C 3.8153'7-3

32- C 80160 10C .42314 6 12DO.90C 2.675121-4 20000.10C 5.187122-434- t 11023.10C 4.S33S32-4 l9000.10c *.429m-435- C 3T3 11UTC.11T36- 112R17

1 lltit source free tare cerd. priat table 90

Ikeff results fer: eriteldl Criticsllty - Sphere of Trenemuted 3.01 bin 2an Ueter 101 U-Up 02 prebld * e/22/96 1U3MsU

the initial fission neutron source distribution used the 33 source points that more Input en the kerc cerd.the criticelity preble. was Scheduled t skip 13 cyclee nd run a totet of 43 eyele utwth nominally 4500 neutrene per cye.this proble heas run 13 Inetlve cycles wIt 1 51 neutron histeros eWd 30 etlv eyelet with 1193"4 neutron blt rIee.

this ceetulete2 n has ooepleted the requsted umber of half e es usings a tetel of 1713 fission neutron source histeries.*il cells with fissioneble msteriel were usepted end had fisoen neutren source points.

the results of the u test for normetity appltid to the Indivldual collision. eabsrption. end trec-tlength helf cycle values Mre:

the kt cellis n) ryele valuss eppeer normelly dietributed et the IS percent confidence levelthe ktebssrptien) sycle sluwes appesr normally distributed at the n perent s Idenct lenlthe kttrk leth) aycle e aeppe r normuaIV diostributed at the 93 percent confidence level

Mey t0 M:ST 116 file Samov 13-3.02.309 YOIlMIJU nSAOO C0-07i170200Z-0016 SKY T0 ITUACKMEKI XXVIII Palo 2

...................................................................................................................................

the final estimated eaobined .otltilen2jabooption/track-laenth keff a 1.005n with an estimated standatd deviation of .I,014

the estimated 6, 93, & 9 petcent koff eanfidence Intervals are 1.041t2 to 1.00717. 1.00274 to 1.006?, VW 1.60173 to 1,60970

the eatimatad eolilIsolhabeorption neutron removal lifetime a d.Sn-s5 aecolde "ith an eatilated standard deviation of 1J.0-E7

..................................................................................................................................

Pay to 07:51 1996 File asms 16-3.L0fROCU8 -280M8u RIAOOOOO01717-I20-0016 IUVY 00 ATTACKRZEXT XX1 - Page I

Im .... vcrelen As Id-10/2119i e4/23/96 11:14658*of-*-*--***----* * *-*---* * * * * prbld * a 1123/96 11s16sS8IMP-3.01121 WJTP312.10

1- Uerfiel CrIticaltf t- Sphere of Traneutad 3.ME 20YO 202 Mater 1.16 U-Kp 022- C k-1nf Optiml" Ion3* C4- C tilEtES- 1 1 7.13439813085-2 *1 3i,-1 1 UruuiunlwuTuff/Water6. C S 37 .10829224000-2 1 -2 11tU.-1 4 TuffltaIsr ReflectorT* CS. C r1tlE bOLW*- C 0 a 2 IP81.0 1 Voldl0- 38 * 1 137P.80 S VoldII.128 C CLIRWACISU3- i* t 0 e 0 10.00 1 OInfinite UiSStI U11IEIE14- C a S 6 0 0 174.51 S 11ngoCtO-Is. C

warning, this surface has been replaced by a surface of type so16-17- NMI I18- iOca 6000 IS 13 619- iitC 0 0 * 1 e e *1 e a e 10 eS -1 e0 - a I 1 S-1

82- 6 1 1 0- I *1*'.1~23- 1 1 1 -1 1 1 | l 1 -126- Ml 92234.310C 4.606952-! 9223340C 5.546663-5 92236.950 1.327212-5 S PI25- 92238.50C 2.762975-3 93237s.OC 3.1652422- 8016.54C 6.042554-2 s At86- iO0l.10C 1.102107-816a27- 14008.50C 1.16297-3 13027.50C 8.663602-3 S Cag3- 26000j50 .4352266 i1000.SOc 1.366807.6 20000.50C 3.S23016- St VI29- 11023. 0c0 4.02590-4 I o00.50c .684111- a sSo30- 1T1 LMTLOItT S. VA31- C 33 1001.*CC 1.337225-2 14000.10C 1.319341-2 13027.0c 3.31538 7-332. C 89016.100 3.931496-133- C S S000.C50 1.623559-4 12000.50C 8.675121-4 20000.50C 4.5S7122-436- C 11023.50C 4.533382-4 19000.50C 6.429990-43- C INTS LMTA.OlT36. PRIE?

I nitilet aourse from bere cerd. print table 90

Ikeff resutto fort PerFietd Criticelity - Spher etf trensmuted 3.01 I0D0 20 Mater 11.6% U-sp 02 probld * 04/23/96 11:14:S

the initial fission neutron *ouree dietrlbutlsn weed the 83 soureo pointo that wars Input on the here eard.the oritical tiy probtes was scduled to skit 13 ctae nd run * stao sf 63 cycles with nominally 4000 neutr gr eyclo.this probtel has run 13 inactive eytea ith 52 24 neutron historice end S0 active ycees with 119149 nsutren ia eries.

this cectuletlen htas ramptted the requested numbr tf lf cy olce using a total of 17175 fissioen neutron source histories.all oltle with feienabl m*torslt ere sr ptded en had fission neutran source points.

the results of the u teat for noroclity applied to the Individual eollislion sorption. and treck-lenth kef cycle veluos srpo

the RI collision) syle vltues appear normally distributed ct the 95 percent confidence levelthe aborptin) cyVle values appear noruelly distributed *t the 9S pereent eanfidence levelthe Ittrk tanhth ee to values appear uorwel i distributed at the 93 pereont confidence level

KIay 20 67151 *M Fate Ft oa 14-.0. M2-12U UVA oCo*?t7S2oaOO1 6 Ci *0 nACWENT xx:: - Post a

...................................................................................................................................

the final estimated seabiowd seililsionaborptien/track-length hoff - 1.094 with an estimated standard deviation of .0204the estimated 03. 95. & IN percent koff confidence Intervals are 1.0697 to 1.61111. 1.80483 to 1.61323. and 1.00338 to 1.61469

thb estimated atlisiion/abMrption neutron rtmeval lifetime * aS9.679-olsconds with an estimated standard deviation of 1.9t1ffC...................................... ............................... :.............................

May 20 0748 199 #11 Namets RE-3.S E-0iA-ZCVU S3AoC0 AAl?17-T200-0OOU ISV ee aeCEi iI * Pset I

IS= version 4& UVIC/Olm ~~~04/22/96 15:23:31 praobd a 14/22/94 1523a31

1- Fsrflaed Criticality S 1phere *t ofIrenuted 3.ME 20CC 205 mater 15S U-ip 022. e Critical Radius

5- II 7.1420491357480200.i NPE. S Urenium/Vuf f/uster6- C S 37 .'08292240 I2 .2 INP:11.1 S Tuf f/Mater Reflector7- C6- C UftSIOE WORLD9' 5 It K I 1t Veld

IC 30 i0 0l IKPUS.* S Void11-12- C 31MPACES1s- I* a S I I 10.00 e *Infinite PIURIhE tilE!E14- C 2 C 06 6 174.51 S REFLICCt15- C

warning, this surface has been replaced by * eurfece of type ea146

16- C1i001 4000 1 1 4319- 131C 06 0 160 -1a0 0 0. 1 0 0e 0 6 a t -1

20-22- I 71 e l1 al I2'3 1e -1 -1I -1 :- 1.71622e.524- mi 922344c ..802093-7 2235* 0 7.172412-5 92236.50C 1S 7:222-5 S I25- 92233.50 5C .572813-3 93237.5CC 4.*P2986-6 8016.50C 4.075156-2 S At

1111-100. CI. an127. INDIAN Cc 1 1440-l 13027.S0c 2.13079. ea25- C00254 3-4 20000.C S.OO04-4 * Wi29- 1IC3:CC 3:870375.4 19000.50CC 54492-4 S 30

0 KTI 1.01t.S11' * MaC. M3 10.C .3233 14000.0C 1.319341-2 13027.5CC 3.015387-31 2- C "'1".C 3.931496.

3- * 000.51UOO 1. 23s3-9 12000.50C 2.475121-4 20000.5W C 4.9 ?122-4S:Z C MT311023.1CC 4.533382-4 19000.5sC 6.4999-4

C Ut LitR.7.1T36- PRINT

I Initiel course freom erse erd. print table 90

lttt f resulte far: PerFIeld Criticality - 1phere of tranasuted 3.0E lUtiD 20 Motor 131 U-op 02 prebid a 64122/96 152S3

the Initial fission neutron source dlstrihution used the 23 source points tbet Mere inpr n the tare eard.the crit ietity preblem was scheduled te eks 13 eYctes ed ru a total t 43 eylet wth nominatty 4000 neutrena Or ycle.this problem has run 13 Inactive cycles t 52 neutren hiseterie n ad 30 active cycles with 12027 neutron hieteries.

this saleulatisn hose ampleted the reqsted rwaber of teff sycle usaing a total f 17270 fissien neutron Meurge histories.all cells with fissionable materiel were sampled and had fission neutron asurse points.

the resutte of the w test for normality applied to the individual eolliesien absorption, end trech-loneth kef cycle vaslues er*a

the tt ' sllison) cycte Values appear normally distributed at the 95 persent eonfidence levelthe htabserptieni cycle values appear normally disetributed et the 9n percent cenfidence levelthe kttrk Ietathi syci values appear normally distributed at the 95 percent confidence level

Key 30 61s48 1996 File 1181S* 135 .St.20M-0VISU 33"00000 -1717?-2oo.OOo16 lEV 00 AtTACfWET Xxx e Pge. 2

...................................................................................................................................

the final estimated esmbinet fbrtoetme4.lonhth lf * .99656 with ai eatimated atendard deviatin of .012

the etimalted 8, 95. & In porernt lkeff enfidenee Intervals ore .994" to .98s0. .9361 to .n996, 6 nd .99231 to 1.60076

tbe estimated cotlisienldboorptien feutron euoal lifetime * 4.13E3-5 oeends uith an eatimated standard deviation of 7.92E*

...................................................................................................................................

Jun 03 15149 199 File ames. 301"es.em *A000000eS171?-200-00016 UV 60 *TIAZ11XET SXSI * Page I

1r~ version La Id.10/91193 94/23/46 1s484:09R~n~e~s** w **n..............|oe.eev9 .... ee.e.... unsee .ee.ee.ee.e ...ee.e.ee..e.... prebid a 04/23/ft 16:4or09Ill ls3tags iUTPu3Ole so

1- For-Filtd CrI9l~tt Ctudy.1 * 0 *.tX CWie Ct t O e *^ 2z sa)"21- t tea tteTt .U il/ec: . wts reft ct d sphere3- C cELL SPECIFICATIONS4- C 13311 VATES 11G3103- I 1 .330641-2 *1 1lP1118i6- e OVTTSID 1E013.L7. 2 0 t lEigioC

9- C SURFACE SPECIFiCATION,IS- 19 3O 30 C 3313E EUEIL 203111-12- NOMI £13- RZODC 4000 1 7 3714- C iSC I Ii 600 lo II.20 6 0 g203 03. .5 -100.10Is- e -5 -to -10 0.13 I-10 14 6 13 -10 -5 -1635010 l 1017.1U- C RATERIAL SPECIPICAUtIOSI1- a (30 vatl ueter In tuft C) A .9U4 3. .v 1ts W021o- e .61 srigina Crihent0 20/Il decsyod to Urenlu Ieute&OS19- ml 1001.3Cc 1.9362- 3016.30c .nssu 11023.S0 c494720 420- 12000.3Cc B.2tJ940-4 1327Cc .4534.0 140.5 so 139224-321- 19000.30 .69255 4 2003040.3 17493- 3000.55 7.32554-s22' 02236.g. 2.1C2?aZ 3 .C~llO 23.0 4.112933.423- 92238.c .7470-45 9 7t 21- 4000.30.c 2.7048114-224- *tl ttr ilt

initial saTre tram tile st eep1teft mut.te tos Per-Field Critieelity Study * 3.Si120 n W /t - 3o0 320/ 3.B3 W02 OlOatca) prsbld a ur23/94 164,

the Initial tiesien neutrOn souree di tribution Lps read free the eretp tile named reptpth eriticality problem was scheduled to akip Fegltes and run a total *t 37 ls. mIti neInally 4000 Metrc r a tythis problae hbe non 7 Isctive ycl uth 27671 neutron histories end au active Mces Kith 120210 neutren filstries.

this *ilculetitn hes eleted the requested unber of heft Iacles usIng a tttcl ot 1470 tission nsutren source hieteriea.elI 6.11. with fissienable materiel wera gampted and bad tissie neutron saurce points.

the resulta ot the w test ter narmailty epplied to the indIvidual collielen, absorption. Snd trectIength iseft cycle values ores

the t solllsimn) cycle vetlus appear normally distributad at the f percent esnfidence levelthe htebeorption) aycle valuesaeppear normally distributed at the f percent cnfidencs levelthe httrk length) cycle valuss appear normalty distributed at the percent eenfldance tevel

......_.......................................... ................................................................................................................. ___

the tinal estimated cebined etteislo/abeerptien/treck-length keft a .39704 with en estimated stenderd deviation ct .60111

the estimated Al. 95. A 9 percent heft centidence intervcse are .n9592 to .M1. .89477 to .931. end .n9397 to .90011

the estimated emitieen/absberptien neutron neuevael liftime * 1.691-06 secends with an estimated etandsrd ievistin of 4.973-07..__. ____..... . .. .. . . .. . .. .. .. .. .... ... . . .. _ .. ... . . .. .... . ... .. ... . . . .. . .. .

4

It

Jun 05 11:12 M99 fit RMeS IlOleaC.Swt 31DA00000061?17.-e200-00016 Bay 00 ATTAC£tENT mcxi * page I

X en**** *probid 6 .4/24/96 77*23TsUinp.13it *Ce outp-i0l9ogcC

1. For-Field SrilicalM .tud- *.6% /t gubjeno Wat * 30 O 20/ 5S M02 (i3Oteg)2- C Call ,0 Elitl Tlu 0.563 fNcc . 5 vetS C- reflected ephere3- C CELL SPECIFICATIONS4. C lINNER VATEI REGIONS- I I S.316157.2 *1 INPIN16- C OUTSIDE VORWL

12-12- UWE0 a13- 1000 6000 1. 7 314- C 13C 6 61 e0 66:: .20 2 0 2 0 I o 5 II-S * 10 0 .101 .. C 6I-S -20 -10 0 -13 6 -10 14 6 6 -15 C. 5 -16 5 S 101 C 1716- C NA1*13A1* IPECIFICAT3011317- * 0v6 Sti Iats Is tuf 0 Cx .93 5 vets101I- a .I01Slle l Er hn We d tc 0 a I MhopeUranl.topes19- *1 100161 04 1 OSSU tt * 0 67037 I 1023.1c 2 jXIS6r0o 12000. 0e 2. Cc 230 4000c S 3:0FlII- 19 Oc .S4245-4 :CO.O4 26000.55c 7.31905-5

Z2~ 223650c~.93C31 Z2.jczsI4 5 9=26.SUc 3.n0740-41n2- nzM O oarZ5 o wSos Xs 0eSn,23- 9S2.1Oc .193 1323?. Uc .34329-6 6000.1SOc 2.8S005-224 *t1 lmtr.0ltRs- PRINT

i 1nitial rsoure. fr_ fle f rstcSkoff results fear Far-PFlad Critle gty Study 3.0S no w0at * so3 320/ 51 ktw (isOltc) prdblid 4/24/9 7s7,s173

the Initial fission neutron eurce dlStributien pas read from the eretp file named aretpthe eritialeity rbi ha olkduted to ski, 7 jea and run a totat of 37 cycles with nmanatlly 4000 neutrens re ey to.this procbtes run t wr nective sysles sit 85 noutron h ltories end 30 actwiv eycles wilt 1209S mutr.n iaet ri..

this eeleulation has ecuteted the raquested br of taff cyles using a total ef 148330 flislen neutron eaurse histeries.tl selle sith tlissioneble materiat were sapled end had les en noutern sourec points.

the rmultts thm u test far normality applied to the Individual ollitaien, ebserptlen. and tract-length helf aycle velus ae st

tbe t ecllistien) oynte velus appear Mnrmatlly EStrbuted at the 9 percent confidence levetthle tl orpt ion) oynet values appeir normalty iitr bhuted et the 95 percent eonfidencle vetthe trk length) cycle values appear normtly di stributed at the 9 percent eonfidence levet

...................................................................................................................................

the final estiested sadtbfind Soltilsnlobserption/treck-tenoth talf a .98470 wilt en estltated standard deviation of .6013

the estimated eS. 95. I 9 percent hall confidence Intervals are .9T333 to .14. .98109 to *98761. and .ARM to .!933

the estlated settlelan/absorptien neutron removalt Mleting a 1.3E3104 eseconds Ith an estimated standard deviation of L.31K-6..................................................................................................................................

Jun 65 1551 199 file Iames I30L65b.en £3800000-11?71.0200.00016 REV 60 ATTACKNEXT XXIII - Peas I

tn version 4. W4101l93 04/123/96 MU M 43 43fE "|, .. . t~l2etMiU*/*s/96*1415 ........................... probid * 4i/13/94 t1914359

33-11301ugb STPAlSloesbO

i1 Pr-fleld Critleatit tud * 3.6X /2:06 /t 50$ 1201 / US 2 (13Olsb)2* Ce g1. lilts Tl f 6. a5 /ce .n volet C *eftected sphere3- C CELL SPECIFICATIONS4 e ItOEN WATER RtEION5. 1 1 0.265121-2 -i INP:-16- C W3TSt8E VORLD7- C e~ac i tapumo

9 C SURFACE PECtF3CATtONl10 1. 60 so S INNER PRI.EL 205iEI1.12. NMI1 U3- 9CODE 4000 I. 7 37

14- C ISIC 06 a6010 06I.20 602 60to5 060-5 -106. 10IS- C e *.S .30 .E@613 2 6. 14 e e 1 15 -10 -5 451 S 10 10 17

1- C a INR:AL 6EIV CATIONSITT e (30'l^'t'S'a vets mater In eml. tuff lel X .92 a vplzUOiis- a . OIinot $nrieI.t/ 50mITdcYed to Uranium loetepos,19 el 1I0.5. I. *0l6.Pc 14723-3ti023.50c 8.6 S:145320 12000. QcS 1.330156-13026.S:1 l 073-314000.c 6.66916-3

19000.50. e 2.937794 2 DQ.50e .GM 4 850 00.55. t.4"5371-522- 92234. c 6.694430 ? 92255.50e .E25236 5 12236.5C6c 9.153184.6

9 238.5c 1.OSS00-3 9U3.50c .182929 6000.50c 2.583265.22i5- P1NT

Initial sour. from file srctvIkeff results tfrI Per-Field Critical ty, Study - 3.6l 120 SGO/at D30 120/ XI Ui2 (130tegb) prebld * 64123/96 M1U14:9

the Initial flesion neutron source distribution ews read from the aretp ftII noved aretpthe criticality preble. wae echeduled to skit 7 vecle end run a total of 37 eyclee stih nominally 4000 neutroa per cycle.this probt_ has run 7 Inactive "yclr with 102 neutron historie and V 0 e ctive "yes Site 120123 neutron histories.

tOle ceslutl tiens h b oop eted tlbe requ.sted numbor of kaff Ics using e total ofatl eeIe ul tb fiolemioble material were saepled and had f *eTe neutron source points.

14t25 fitten neutron source histeries.

the resulte Of the a teet for normatity applied to the Individuel celliston. ebeorptlon, end trtc-loneth toff eycle nvluos, ores

the ht celtel on) cycle vela W"ppear normally distributed at the 93 percent cenfidence levettits tt sborption) eycle velues appear normally distributed et the 95 pereent eonflidne levelthe kntrk lengeth "vile tulues appear normally dietributed ct the 95 percent eonfidence tevel

...................................................................................................................................

the final estimated geebfned oelttiion/abeorptlntrtck-tlength ketf a *I.6M039 with on estimated stenderd deviation of .60114

the estimated Ui 95, I " prernt teff cet idence Intervals are 1.68636 to I.6216. 1.6U82 to 1.i7397. end l.ussr to 1.7322

the estimated eelteilen/ebsarption neutron removel tifetlee * E.911-63 *seends with on estimated stendard deviation of 3.46.67'

..................................................................................................................................

Jun 67 6:19 9196 1it Isme 1v S.O00ID 20VO *3OOOOZO S ?1 t2CD OD16 E O ATTACUIESIT xxtiv Prse I

lm.n . version 4* tldt010/193 *S12416 60168:17I*?-oE20oXeo.Oeeesteeeoele eeoteoooeeO.~Oeuooo.O*OeO agoe * -e-*-eaoe piobld * 61126196 00:03:17

ISPBUZ0108 6iUTPu320hdO.0

. Faild Sriti .alitr - S ere of Trna'ted 3.6E IOuiD 30S Water 1s Ui-p 023. C h-fSGP asimz Ion InImus Water3. C4. C SPUEt£3- 1 1 T.1263963C2643 2 1 INIPuS1 0 UraniuefTuffjtater6. C I 37.1829224000-2 1 -3 1INP: S Tu/ffloator Sf lector7. CJ. c antiso macaw9* C 30 6 a IMtPtUO S Veld° s3o I 1 tNP:t-D I Vold

II: C SUFACts13J 1 * S S 10.60 S dInfinit, FISSIL7 SMERE14- C I 5 O60 114.51 S REFUCTOR15- C

warning. thie surface haa been replaced by a surface of type so16*17 IIODE t-

t9 ttC 71 es j I A22- * I 6 * 1 -1 6 -1 -125- 1s -i I .1. 1 .1-1-124- R1 2234.stC 4 694430? 9223S.10C 3. 232866S 92236.SCC 9.153144-. S pias O2238.110C 1.90SD73 9323?.5C .1926.6 O016.50C 4.00oDU-2 * At

34. 1001.30"" 13302.... $1io sctnmsO en27. 14o SOC 1213794- 13027.500 3.774156-J ' ce38- 36000.130 1.493674-f 12000.10C 14641111:4 20000.3Cc 6.060152.4 S lei39- 1123.30C 4.119111. 1900 C0C . 215591 '30. 521 LUTKASH S Wa

1- C' 3 1001t.SDC 1.3325 14000.S0C 1.31931.3 13027.50C 3.015t37-332- C 801.100 59 i"'33* C 3400.Sc .U O 2 59- 2800 0.500C v.63m114 ta000.SDC 6.3sm7z2.434. C 3102.500 4.353392-4 19000.300 6.429910433. C 123 iVT1.6IT36. 7710T

i Initial eourse free kare card. print table 90

1keff results fort Sarrlied Crittolity - sphere of Troweuted 3.0! 20lD V0S Water UI Utop @2 prebHd a S126196 60o Ot7

the initial fissien neutren source distribution usted the 33 source pnto that were input en the harm card.the eriticlity problem me scheduled to skip I ctles end run a tetal of 1003 o tc*1 with Nominally 350 neutrons cyle.this preblos baa run 3 Inactive cyclcs with 16 neutren hieterica enid 1000 active cycles With 34999 neutron Ist esic.

this calculation ha csompleted the Pequated Number of hoff sycles uaing a tetel of 350710 fissien neutron seurce histories.all cells with fissionable materiel mere sapled end had fissio n neutren course pointe.

the resulte of the w test for Normelity applied to the Individual collieon. aboerptlien. end track-length toff cycle values ores

the ht littllon onc wa appear normatty diatributed at the IS percent *enfidence levelthe h eaborptieon 1e a s apper Normally d tributod at the 95 crent a cfidence levelthe hi tl egt)c a values appear normatly dIstributed at the 93 areent confidence lovel

Jun 0? t6ut9 11*6 Pil to am:s Imaw3.SE.28mmIJCmll0u SIACOCCO-S1717-0200.SOOI4 UVEW 00 £rrACKNEXT xxxiv - page a

the. final estimated cobned ka16nB*rtt~tclfibhft v .99598 With an estimated standard deviation of .00106

thse estionted ". 95. I& 9 persent koff .inI idmsce Interstst are .99492 to .9974. .MIT3 to .M93, and .99316 to .M98

thse estimated sa.lalmen/abserptimn neutron removal tifetime * 3221.05 seconds with mn estimated standard deviation ml .Uil4?

Jun 67 16.20 196 file Baa., 1113.61.3001I4D2V1OU Rlaooo .200 l EV 60 ATTACKMENT -11 - se I

ves rslo n4a 1 I$/10m H~t/ 9 0ttt a.;g**---*- --- - -probid * 6526/96 604?aS11e1E21OW1@01 UT118320f0.8 N

1- aFr~Ield Criticality * 6phere of Tranamuted 3.6! 3601 20s VIter 163 V-1P 022- C k-ldW Optillast ln Ialnum Vter3- C4. C

7.13079731632-3 -1 ONa~ renlus/uffflaterCC 3 T.COZ40- I .3 iN1ual tf/Miator Relect l or

*1- t OUTSIDE 01ORL

@: C r0 11:. 2 IlMZ old10: lo So ST a 31U1,1.6 I V1 VoidII-12. C SIUIACES13- 1- t 6 I 16.60 t *Infinite MIKIE DSPERE14- C a S 6 6 8 174.51 S REFLECTOR

1- Cwarind, this surface has been replaced by a surface of typo so

1E- KCO0E 250 1 100319- 3630 6 6 I 1 6 -1 I 1t 6 t a t1 6 O * 1 0 *-1

t0- ~1 1 *: 1- 1* |1 1 6-1

22- e238. l.6:31 1 -1 e. :3:24- 11 92234.60C . 8062- 92235.500 4. 781605- 92236.5CtC 144148-9 5as-0251173-3 9 237. CC 2.7657-6 6016.50C 4.627236-8 a At26- 1001.30 1.303503- an27- 1400. sec 1.1376874- 13027.50C 2.713848-3 5 Cs28- 360eo .ssc 1.461203-4 13000.10C 3.407609-4 20000.56C 5.92546164 S VI29- 1123 .OC 0.98044-4 19000.50C 5.786991-4 6. 3030S NII LVT2.6*T S We3t2 C t 3 1001.38 1.237n2-2 14000.10c t1.31934132 13427.50c 3.01338731

53- C 36000.150 1623SS396t 12000.50c 2.675121-4 20000.00C 4.187132-434- C 11023. 510C 4.5533324 19000.SOC *.429990-435. C 373 LWIA.61136- PRINT

1 i nitisl soure. from hare card, print table 90

Ikeff results fort Forfleld Criticclity - Pcerc of Tronemuted 3.61 26010 30S Mater 10 U-#p 02 prebid * 652696 60:47:15

the initetl tileson neutron Source Eietrlbutien geed thc 23 source points that ere Input an the Itsre card.the Cr Ica ttty problem was scheduled to ekip leclee and rnm a ttot of 1003 eyIle with nominally 330 neutrona pr ysi.this problem as run I inactive cyste with 7tO'utren histories Vad 1000 *ctive cycles with 831465 neutron hiatorIe4.

this ealculatlen has completed the reuested rAbqr of keft ces using a totet of 252135 fession neutron source historles.elt eella with fissionable materiel mere sampled and had 1i s n eutron source eoints.

the results of tbhe test for normality apptied to the Individusl eollieion. absorption, end treck-length keff cycle values rer

warning, the tt eotiaion) eotle valueatdo nat appear normatt dietributed at the 9 percent confidance leveltheo httsorptlen) eycle vaues appeor neormIF distributed at the 5 precent conf Idnce levelthe lengtht) ccle vlues appear normal dieti buted at the ercent cont idnce level. but not at 9 percent

Awn @7 16:30 1996 File Names IMM-3.Sl-200M-32hIOlU [email protected] UVi U ATTACu! IN y *M Pass 2

the final estimated eumbined keallen/dbrrpt let etk keff * 1.0833J 11th an estleated standard deviation of .01t2

the ostleated 48, 95. " pe rent hat contfidenca interval. a?* 1.t0671 to 1.t0895. ,OS5 to 1.11007, and I.M0U to 1.010

the esttiated attlliiontebserptten neutron removal lifetime a 6.37 35 scaendc with an estimeted standard deviation of i.aZst-....... ............................ ............ ....................

I

a

Jun 07 16:39 1M9 Pile Name u1 E-3.2oto 20oogwa Au 3At000000-01717-0200-oO0O6 REV 00 £TlACMrt 1vl * Pegr 1

l eP .verilen *e tidO110193 05/2696 0123:13 d

1UP.3E20W122 OUTPO320uW2.0

1- PerField Criticalitr * SPhere of Transmuted 3.1E 20RO 20S water i2n iU-p 022- C k-aln Optimization Ilnlu I Wter3. C4* C SmNERtS- I 1 7.1352933393iC *1 I KPSA-1 S Urniur/Tuff/Vater6- C 3 3 7.d029224000.2 1 *t INRPI.I * Tuff/Vater Reflector7- CS- C SUt8301 WORLDJ: f 30 I 2 111108.0 IIVl

la IC 0 1 INPI.0 Tyold11-12- C SUPACIES13 15 I I0 0 16.00 1 eo 1nfiite FISZILI SPlRE1U- C 2 £ 600 174.1 a REFLECTOR15- C

.srning. thie surface has been replaced by a surface of type so16-17- IIODE U1S- 9CCOE IS0 t 3 100319- S1t1 000 I o -1* I 0 1 .10 0 0 1 o e -20- I 1 01 1 1 121- -110 .1:12 .121 1~ .132- e1 a - 1 01-1 .1123- 1 1 1 -1 1 1 *1-1 1 *1-124 rl 92234.110C 7.041674-7 92235.s SOC s.7no-s1 92236.OC 1.37293-3 A Fl25- 922315tSC 2.553250. 53S97. OC 3.274316-6 0016.1 4634-3 S At

267: ARIASl 5 : 1.61020N 13027.10C 6M41-3 6 ea2e- U6OOO.S$C 1.423732-4 12000 C03.354106-4 20000.S0C 3.79617-4 S W29- 11023.50C 4.006976-4 1000.50OC .65301-4 8 3030- NTI 1.113.01 S Ma31- C 13 1001.5ft 1.33722S-2 140OO.SOC 1.31941-2 13027.50C 3.613337-33 2-C 1~~016.30C 3.931496-33- C 2C0c IC 1.623559.4 12000.58C 2.675121-4 20000.10C 6.537122-4

4: C ~~1123 COC 4.35336-4 19000.300 6.429990-4sS e rn LUVt.AlT

56- P:111inItial ourse from hare card. print table 90

Ikeff results fort :Prfild Critiaslity - Sehere of Transutotd 3.0E 2001 201 Water 121 u-tp 02 probid a 05/26/96 01,23s3

the Initial fission neutron saurce distribution used the 23 source polnte that wre, inut an the harc eard.the criticalIty problem wsc scheduled to Ok p l l aDOS rclec uith nomminlly ISO autrena *et cycle.this problem hee run I InactIve cycles Wit 1 neutron histores ad 0o actl p as ith 25074 neutron histerile

this eelculetion lhas eomplettd the requested muber Of koff cycles using a total oftIl soils with fissimisb e materiel ,wer e spled and had fission neutron source points.

2#5105 fistion neutron acure, historis.

thoe rsults of the u test for normality applied to the individual coltlsion, absorption, nd track-length hNff cycle values ares

the hi collisIon) cycle values separ normally distributed at the 95 percent confidence levelthe hiebsorptien) cyce veluss appear normtlly distributed at th 5 percent confidence leiethe htrk toneti) cycle valu e pp"r normally distributed at the 95 percent confidence level

I

I

Jun .? lM 1996 Pit. Eaws M-3.SE-2ODc6*202U IIIA000040-8OTlT-S1? OO-10g REV *0 £ATTANIU 10XXX - Pase 2

...................................................................................................................................

the final stimated seebin d e talen sptlttrsck-l th keff . 1.00535 with an estimatad standard divIation of .6011?the estimated ". IS3 A 9 percent keff eonfidence tntervale are 1.8074 to 1.01002. 1.60652 to 1.11113. and 1.60576 to .611U94

the estimated sattislen/abserptlen mutren removat tifetIme * S .446I5 .scends with an estimated standard deviation of l.U1117...................................................................... ......................................................... ,

-

Jun 07 TM12 t6 lle hla s INl M E-20CU0-16 U0u 1AC000009-6717-020C-80016 tEV tO ATACINET KX Il * Pass I

Ion . version 4;. .d.IC0/0/93 03125/96. 2014:43 prehid * 05/259 20.1445

*ertlele Critieetity * Sphere of transmuted 3.61 ZOCYD ItS Mater n U-Up 02C k I~f Optimization lini. Mater

3. 1 I 4.94175922S56S- *t INPoI S Urenium/Tuf f/ater4. C 3 3 7.102922 D0- 2 I .3 IlMPalt C luftf/ater Reflectery. Ce. e OUTDE WORLD9: e 0 6 2 a11penD C Vold

I: C * 1 lP3 S Yeid11-12- C VJUPAU313- t* 6 6 10.60 I *Infinite PISSILK PUEt14* C a t a I e 174.11r C ULCCTORis- c

.rrnlng. this surfece hea been replaced by a surface of type so16-t7- IONE t15- KCOUK 250 I 3 100319- MtC 660 16 6 -1 6 0 * 1 6 -1 6 0 t 1 * C -120.I I 110 1.6 10 1 .21- -1 6 -1 -1' g 1a I l, :123- * * t* I

2 llt 92234.C 4.;94450-7 92235.5DC M.5M226- 92236.50C 9.514-S1 C 6 Ft25- M2Z5.50C 1.90500- 93237.50C 2.1SZ926-6 6016O.5C 3.946575- C At26-1l D 2 }210t C 72t S 2 *1 an27- IISSONIC 1:2I1i19.1 130127.56C 2.71141346-3 snC2S- 26000.53C 1.493674.4 1200D.50C 1.461111t4 20000.50C 4.060152-4 " l29- 1I0Z3.I0C 4..19111 4 tS1000.1C 5.915591-4

inlLUTLOIT 1400VsC5t- C N3 3001.9C 1.'S3225Z 2 4000.150C 1.519341-2 13027.50C 11.81n57 312: C 101.3C 14962

36 C 4 .5C 423559:4 192000.:3sgC . 121:-4 20000.3CC 4&.18T22-431.- C 11023.C 453332.4 9000.3C 4.29990435- C XT3 LVTL.OIT

I initial source freo hare card, print tabte 90

lkefo results fort FPrField Criticality - sphere of Treneauted 3.E 20CWD 13a Vater S% U-cp 62 probid'- 05/25/96 2C:14s43

the Initial fission neutron source dietributlen used the 23 *ource points that were input en the here card.the criticality problem wes scheduled to skip S aycles end run a totel of 1003 cycles with nonally 250 aeutrens rr cycle.thie preblea has run t Inactive cycles ml n212t neutron loterses

thie calculation hea ealeted the requested raber of khaf cycles using a total of 251958 flelen neutron source histeries.ell cells with fleaionable materiel were ea pled and had fission neutron source pointa.

the results of the w teat for normality epplied to the Individul eeollisieen. asorption. eand track-length kaff cycle values ares

the kt collision) cycle values sweer normally distributed at the 95 persent confidence lvelthe htabsrrptlen) cycle values appear normally distributed et the 99 percent confidence l l but not at 3 percentthe ettrk length) cycle values appear normal y dItributed at the 95 percent cenfidance lewt

w -

Jun 67 1Utt2 1996 Fit*L ese INA.3.gE.3OWD uOW I0A0000-67 0200-S0016 gly S0 ATIAMINT IXXXIL Paso a

.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Cho final estimted cobined aslilel n/a rptl - Jtraek-lergti kof a * .1O44 with On stimated standard deviation of .00110

the "tlret d U3 tS a perennt luff confidence Inwtervals are ."9S5 to .11ts4, ."3z6 to .s263, and AMs to ."Sthe estiurt d coliaeft/inbsorptln nemutron removal lifetime a tlSE-OS * eonds with an *etl-ated standard deitlo of I.&R-07

.................................................................................................. 6...............................

- - -

jun ST 16.14 1996 Filt Same 1fV-3.SE-2000D.18VIU uA0oD0eD-61717-200-40016 REY CC ATTACENEI YIlyVi Post I

Iease version 4& Id.l0I..i9 SS.25.96 22S3t e * .2263:2probid 529 2134

IUP.33I3101a 6uTP3IUUIO.6

1- t arIloId Criticality - "here of Trenuted 3.81 200VO 1ES Water 101 U tp 622 C IC-lntf ptimisatlen Iirl later

3- C SNR5- I 1 6.95027191632-2 -1 IN11-1e S UrenriuaTuftf/aterA- C S 3 ?TJ521224000-2 1 -2 Im IN-1 II Tuff/Mater St lector7. CI. C P1UT151 VOILS9: to so a IKP.U.0S a Vldr1-

12- C SURIACIS1T- 1e S I 0 a 10.60 * *Infinite tlU ,LE SPNElE14- C 2 a S 6 5 174.S1 S REFLECTOR

earning. this surface has been replaced by a surface of type so16-17- MODE U18- 1CM1 2s5 1 3 100319- SC 06a 16 -16 0 a 10 6 -1 6 61 0 I -1

21- 11 1 e 1 @1 1 1220- 11 S 16

24- t1 92234.60C 1.861062- 92235.1Cc 4.81608-5 92236.sec 1.144148-1 S Ft25- 9223.00 C .381675-1 93237.0C 2.Tn857-6 6016.50c 3.967060-2 S At26- IOCIOC1.0835-2$a2n- 14000.100 1.St76T012 13027.0C 1.713143-3 £ Ce28- 6000.SSC 1.41203-4 12000.10o c.407601-4 20000.10e s.923410-4 S lI29V 11023.1O0 4.693044-4 19000. DC .57691-4 S 3030- 511 LVTR.61t a Ws1°- C N3 1001.11C 1.33725-2 14000.1DC 1.319341-2 13027.9Cc 3.S11T-33732- C 5014.c 391696-33- C 26000.15C 1:933S964 12000.10C 2.675121-4 20000.50C 6.587122-6I4: C 11023.10C 6.15233192.4 19000.910C 6.429990-4

ZS- C 513 4,01.01.T36- PRINT

I Initial esoure free hare card print table 90

hkett results far: FarField Criticality - sphere of Transmuted 3.63 200GW 131 Water 101 U-Up 02 probid a *1252n96 2U232

the Initial fission neutron scurce distributlen used te U23 eur-e points that were Input on the here card.thc rIticality reobtlem wa scheduled to ski p I cyetas *nd run a ttat of 1003 cyclce with numlnally 250 neutrons gr cye.this proble has run 3 Inactive cycles oth S neutren histeries and lpD active erctee uith 250120 neutren astoes.

thic celeulatien bas ecmpleted the rqueated mmber at heft eycles using a total *t 25s07s fisseon neutron eource histeries.all cells with fiasltuable material uere sampted and had fiee in neutron sourcepoints.

the results of the w test far normality applied te the individual celllsiun, n beorptlen and track-length heft cycle vatlem cre

the tI selllsion) cycle valms appear normalty distrIbuted at the 95 percent eontidance levelthe httbeerptin) cycle velwme appear normally distr1butd at the 95 rcent eontfidnce levelthe hitrh legth) cycle veluea appar normal y d stributed at the 95 percent confidence level.

-

Jun ?7 16.14 1996 PILe Name INU-3.0E-l11D0l9lfU 11AOOODO-31T77- 200- 016 KEY SO AT1tEENIIT 3Xiv113 - Pa3 2

..................................................................................................................................the final estimated eeubined celtileen/ebserptleon/ttck-length eff * .993 wIth an stimatetd Standard deviation of .01

the estlmated U8 95, 99 pereent keft eentidente Intervals are .9375 to .592. .M28 to .99699. and .99197 to .M7

the estimated e.Ilisienebeerptlen mnutron removL lifetime a 6.4BE1-5 seeends with en estlated standard devletlin of 1.311-67...................................................................................... ....................................................................................................... _

a

Jun C7 16:6 19m Fit Urn. BCS.e0-2001lN12U uo00000-ClriT-0200*SOO16 NEW 00 TTIACMSENI 812X - Paet

1K np version 4a td.1001193 0es25s6 MU2M.. eoaeme~ee.ame.,aee.aa~eea*.a~eeea.a..a.e~eee...eproblid * 025//96 MUM4.2

IMP-SE16 21 OUTPmS3Ifl2.0

1. ParField Criticality - dre of e ranemuted M.6E 1OGUD 181 Water 12S U-4p 022- C -Sfi OptIM a .on I U "ter31- C4- C IP3131S. I 6.9581146tn382 *1 IlIRIil S Urensm/Tuffi2ater6. C 5 3 7.11121224P000-2 * . INFIN-i a Tuft/moter Reflectorv- CS. t OUTSIDE UOitO

IC 3IHFtU.0 0 V oidlo SO | 1 ' 111 tl!'mP.U.0 t V eid

13- Ce I 0 00 10.00 a *Infinite 11USS1IL. SPHERE14- C 2 I 060 174.51 2 REEICTOt

M5eng.' thle surfeco has boen replaced by a surface of type ma16-I? XME H 1na- 9001 2S 1 3 1003

13- el 1 1 1 -i 0 1 * 1

2- HI 92234.1CC 7.041674-7 92235.1C I.7930 5 M36.$CC J.Mr -11 8 Pis238. CC .158250- 3237. CC*3W.Sc .u37271s4 S At

1001.100 1.0390310C :GM2-5j aIT 14000. J 1.161020 13027.SCc 2.6734-s to t2a 2600.5 1.6*3732-4 2000 C 2.s5410 20000.10 5.79647-4 S29- 11023.1CC 4.0069176.4 900C8.1 0CC 319 * so1-4

30 1 U3TS _JyO1.c 1.33252- 14000.5Cc 11942 13027.10C 3.015387-332- C 9~~016.C .931496-233- t 4~2000.155 1.623539-4 12000.50C 2.675131-4 20000.11CC 6.587132-4

112 CC 4.553382.4 19000.50C 6.429990-4

I 6- intil sourre. from~t kgecrd. print tabte 90

kof rultei fort ErileM I Criticailty Sphere of Transmuted 3.6E 2C0A 18S Vater 12n U-4 e2 pr0b2i a t5123/96 MUM

the Initial fiessen mautren soure distribution wsed the 23 eource pointe that ere Inuut en the ke.. card.the eriticellty preblem ws scheduled te skitp 3 eyces and run tetal of 1003 eycles with seminally 250 mutrens pr "ycle.this preblee has run 3 Inactive stebs of I 1I mautron hleterie sWd 0se0 active eyles uitk Mtsoo nautren Ileteries.

this eeleulatien has *pteted the requsted muber of koff eples using a total of 230700 fission nautran source hlsteries.slt eelle with fissienable materiel were sapled end had fission neutron eource points.

the results of thoe test for mormatity applied to the Individual eallielin, absorption, end track-lemth koff cycle values ores

the it etlislenn) "eta values appear normally distributed at the 95 percent eonfidence levelthe htabserptinl syttle values appear normally diltributed *t the " percent eonfidence levelthe its-h l ength cle values appear normally det ibuted It tIhe 5 percent enfidence level

Jun @7 ttsI6 ,,,9 file lawh *KW.3.SI.3OSV-11U BSOCOO.01717.200-S0016 REV 00 ATTACIMIUT mWIX * P336 2

................................................ ........................................................ .............................. , , ..

the final estfeated eoabinad eoltielen/abeorptiedtrack-et ngth kaff.- .99307 with an estimated standard 4dviatlen of .01S11

the estimated 8, 9. a 9 percent keff gonfidence Intervals are .91o to .1423. .9MT to .9M33, and ."90C to .n913the estimated eoltlleien/bsorption neutren removale ifetime. 9.331-OS 5scends with an estimated standard deviation of 1.111-t7

....................................................................... ............................................ '.....:..

Jun 67 1?U63 19 File somev IN-S."48911D.IdiI08U REV u s -g200-g0 E TTCENTET n - nae I

mene version 4a 4d-10/011 ISM/% MIMS 9 d 1 8t

lUt-SE16iIO5l i~TP416iws.e

1- Parrleld Cr1ItcltialtSbere of Transuted 5.ME 2OCU 16S Water I% U-Itp 622- t t-lnt gpttoias WanIr vbter3- C tPIE6- C SPNERES I1 &.7512214746-S -1 mP0S11 S Uranlu-/Tufft/ater6. e S 3 .103292Z os0-2 1 - SySol S tuff/water Iaflecter

9. e 3TSlC E L-. 9 s Xe 2 INF&I-0 9 Void

16- 30 0 1 IKPtlIt e Veod11-12- 1 2SIN ACE13- lI I 6 I a 160 S S *Infinite FISSILI SPNERE14- 1 2 S 9 I a 174.11 S REFLICTOR15- C

warning this surface has bean replaced by a eurface of type so16*17- 300E a16- KCO0E 20s 1 1CC519 nc 9 1-6 -19 61 6-ee16 69 *1 e09-1ll- KSI~a1 16 1 16 1 I 1 1 9 -1

Z2- 61 1 e-1 1 6 1-1 6.1-1

24- 11 92234.500 4.69445. 92235.5CC 3.625286.5 92236.SeC 9.153154-6 t pi2S- M238.50C 1.905500-S 3 93237.5ZC 2.1S2926-6 e016.seC 3.U85063-2 t At26- t001.5CC 0.114197a-n27- 1000 .Cc 1.213794 15027.50C 2.774156-3 s C28- 26000.55C 1.693674-4 16000.SC 2.661111-6 20000.5OC 6.960152-4 S VI29- 11023.50c 4.189111-4 19000.5Cc 5.915591-6 t 3e30- WTI LWSi.6 7SVA31- 1 C 33 1001.SC 1.33722S-2 14000.5CC 1.319341-2 13027.50C 3.81M5M37

38- C ~~~6St6.jCC 3.931496 -S33- 8 2|6000.o550 '.623359-4 12000.50C 2.67511 -4 2et000.sc 6.57122-434- C 11623 5Cc 6.55332-4 19000.S0t 6.4291990-35- C0 113 tTR.&IT36. Palo?

I Initial source from kare card.print table 9

Ikeff rmuttl fart FarFIltd Criticality - Sphere of Transmuted 3.01 A2V1D 162 Water n2 U-Ip 62 prabld * 65/35/96 1M8UM

the Initial fiasien moutron sourse dletributlen used the 23 source points that more input on the kare card.thle critical ty preblee wa scheduled to WC "r__" *nd run * total of 10O5 *rclec ulth neoll, ISO neutro er cyclIthle prcblen bc run 3 Inactive sycles 3 ctes and rm n toterlu edrt 100scycles sndlth iacive 250n neutron. 1c csle .this problem his nm 9 futrfi hatnaestivde0CC cli sscewitth 56378 neutron histories.

thle eatculatlen has empltted the requested umber of eoff yactes using a total of 25117T flerlon neutron seurce hiateries.att celtt with fielaensbi* esaterial mer expltd end had flea in neutron *oure points.

the results of the a test far noreality applied to the Individual colliesln. n bserption. end track-length kcff cycle valuee erptthe tt collision) cycle values appear normally distributed at the 95 percent centfhence levalthe tbrptlon) wycle vatwes appear noros IV distributed at the I5 percent enfidence levalthe httrk length) cWy values appear norse IV ditlbuted at the VS percent confidence level

Jun or 1803 1f6 i, l r *itelass I NU-3.SE USMIAWVOSU SIACOODO-S1717.S200-001 UV S0 £T1ACINESt m. - pre a

........................ .......................................... ,,,,,.........,,,..... ,,,,.........._,,,............._...............

the final ntlmated coubined csltisleVdsbeorptlen/traek-tengtb koff a .977 with an estimated stenderd deviation of .30102

the estimated ". S. I 99 percent hefft ontnidence Intervals are .9761 to .975 .756" to .A774, d .9dM00 to .9040

the estimatd eoltltioVebserptlen neutron removal lifetime * m.-OS matends with an estimated standard deviation of 1.Su4-m7

..................................................................................................................................

Jun 07 16:0? 1996 Fit* rnst OYA-E.03t00 lii/l0U S3AOOOCOO-01717-200-0e016 Ray g0 ATTACUII? XLI * Ps.e I

I.c" version os 1oIC09i/93 02/25/96 Iv80is i* ee*- o - o*- e-- oooo oe- * o-o-*ooeoooeooe*a-ooo-o-* eo*-epjrobid * 05/23/,4 106tg9

l1Po3E6Uiz WTIP.31610.0

1. Farplild Critiesllt Ir. tof trsnszutod 3.0E 20MC t16 Moter 102 U-op 022 C l-Inf Optfilsa Ion Matnleoter

5. e I 6.7697431432-2 -t 1 117:111 5 Uranism/Tufflu ater6. C 5 S 7.10829224000-2 1 t3 INfill-' S Tuff/Mater sfrlector7- C8e e W/23303 UCELSs- C I309 C 2 WIORLDw S Vid: so so I Ifwl igO $ V oilII.12. C SUtFACES12S C WA S 10.00 S *Pnfinite fIStLE 37E3E14* C I E 0 06| 174.51 S StKFLeICTCeis. C

warning. this surface has bean replaced by a sutface of type mo1i.17- HOCE 5li. 02003 ISO i 3 1003t9 n e * ee e-t e e s te -to e u e0 t * -120-: 1 s 1 : .1 S 1 -1 e 1 .1 e

222 I 11 el e1 ItI * 023- 1 t t1 I 1 -24- MI 92234.10C 5.1S6062-? 9232.50e 6.7816085 92236.0CC 1 l"l485 S Ft25- 235 3 .301175-3 93237.00 3. 7265716 6014.5CC 3.90638-52 8 At26- It,.1.5C 9.628021 - an27. 14000.103 1.161407-3 13027.10C 2.1`21316c8-3 r CIt9- 11623.10C .46.09804. 12004.1C 1.iii4nCO$C592404 Sl28- 26000. CC 1.46800 -1 2000. CC 2406 91-4 280.C 5931-*2 t XT TB.617 S go31- C 393 1001.50c 1.33fl25.2 14000.560 1.319341-3 13027.11cC 5.015387-3

3 t t4000. SSC .i2 355 12000.SOC 2.675121-4 20000.5OC 6.57122-44- C 11023.50C 4.353332-4 19000.10C 6.429990-4

Ps: C n LVT".6IT36- 10ER11

i lnitial Dource free tarc card. print table 90

lteff results fort ForField Critleality - Sphere of Transmuted M.0E ROOM10 162 Mater M10 U-Up C2 prebid a 05125/96 1t*6t59

the nintiat fission meutron source distribution resd the 33 soures, points that wore input en the bare card.the criticality probltm ass scheduled to skif *et ycla end run a total of 1003 cycles with nominally 250 neutrons per cycle.this problee has run 3 inactive syeoe with 713 neutron hiatories end IPO0 active cvces with 250152 neutron histries.

this calculation has completed the requested mber of betff cale using * ttet of 25e363 fission neutron source histories.all colle with fit sinable materale were oampled and hed fission noutron soure points.

the results of the w test for normality epptled to the Individual collielon. absorption. and track-lengt hfof cycle valtues ros

the kt ollielon) cycle -les eppear noreolly dietriluted at the 95 pereent confidence 1evethe ljobsorptin) cycle values rppear normally dietributedd t tth 95 pre t sonfidance levelthei trk lengfth) "cisl value. eppeer ormrally dietribute at "he "5 Parce: confidence level.

Jun 67 tO7 tO 9 IM Ie N.mot 83.C E 200-OCOtd REV 00 oTrCUINU7 MEL *- page 2

............................................................................ ......................... ;

the fimat estimated eeblned etlilaon/abeerptWl~track-tength khff *a 3U with an stimated standard deviation of .00113

the estimated 1, 9, 9 " percent keft confit dence int e as .97919 to .98149. . S to .26, Vnd .9M to .33

the estimated setilaionfabgrption meutren removal lifetime a 6.3E-CS secends with an estimted tetndard deviation of 1.31-47.................................................................................................................................

a

Jun 07 1lilO 1996 Fit Uarn. 9I11-3.IE-2011m-l12U 3A0O0O-0171?-0200-1 6 REV 60 AIACNEllT XL1I - page

mCnr wversion 48 tdIslas9 i450196 13:608

IVP.316"1f22 SIT18316U112.p

1- FarF~ieE Iriticai otf * gphsr et lrensauted l.tE 20CD 16S Water 12S U-hP 02- C finf eptimize Isn Irnoi Voter

3- C4- 0 PRERS5. 1 1 6.7e22701111Z-2 .1 ilPaEul I 1ecniuclvuff/vater6* C S 7 .10329224000-2 I *2 INPIN1 I Tuff/lveter Reflector7. C

91 C GUI0 D WOL 2 llth0t I E tw9et ° *O 1 Ill3110 S Weid

12. t SURFACTS1S- 1- S 00 to so C eInfinite FISSILI 2pillE14- C 2 e e0 e 174.11 * REFUCItOIs- - C

warning: this surface has been replaced by a surface of type so14-17- IODEIU. ICODE 250 I 3 180319- IIRC t I 166 .*1 6 60 8 I I 0 -16 0 1 0 0 -1

2Z1° 1 16 .1:1C .1 Si .161!22- .11 1 0.1 I .1.1

2S9Itl 2234.0: rv 1474-r z9s22c3 S n :s 9206.dOC t37297r-e $ f2S 62238. 6,215e250.3 9237 5ec 2U -6 &016. CC .9257-2a I At

26- IO~100.SO 9.414045-3 Sa27- 14000.500 1.161020-1 13027.5CC 2.673S41-3 0, t21l- 16000.530 1.4231732-4 124001.CC 2.34106-4 20000.30C 5.796467-4 a nI29- IIO2S3.JC 4.606976.6 19000.14C 5.58n391-4 S 3030- KI1 LUU.610T, IM31. C It3 100O0 1.237225-2 14000.50C 1.319341-2 13027.5CC 3.0158-3 t32- C gold.5CC 5.931496-233J C 6000.:5sC I 23559I-4 12 00.50C 2.65121-4 20OOO.SOC 6.517122-434. C `1023 .1C 4.553382-4 19000.11C 6.529990-435- C ITS WTiNT.OlT36- PRINET

I Initiel source fr_ hors ctrd. print table 90

tietff resulte fort rFiltd Criticlity - Sphere of Transmuted 3.0R 20W 146 eater 125 U-tp 62 prebid * 052252U6 11:4:5

thc initial flesion neutron source distribution used the 23 sours. points that ware Input en the tbae card.the critiesltty problem "sa scheduled to skit I entcs sd mun a tctalote les yustea with nominelly 250 neutreni pr *rlte.thi probism has run 3 inactive cycles Mltt 94 neutron histories and 100 ativw cycles with 2310S6 moutren histties.

thi aelculatimn huas aspltetd the requested tumber of keft cyctse usIng totel of 251760 fiselen neutron source hieteries.all Icis with fissionabi materist wer sampled nd had fission neutren scurce points.

the results ot the u test for normality sppIled to the individal cellision, ebserptton, cnd track-tength heff cycle viluse sret

the hti sellisin) *pcle velues appear notraltl distrbuted t the 95 percent *enfidance levethe 11aboerption) -yt1 enthe trht letngthcycle value:s sppsr normall dIstubutod et th ff percent enfdncre levethei t I yengtha pt etwo ppar narmaly ietrlbuted et the Ps Mercent contidane teavt

* ~~Jun 07 10:10 1996 file Vowes INV-3.0I.EOGW-16V1 *UA000000-G1?1T-0200-g0016 IFV S0 ATTACINEN1 3MII * Page I

the final estimated eemaInod ooleoiboto/rc-oshkoff.. .97294 with Omi estimated Standard d6viation of .60113

the estimated 08. 95, 9 99 perceunt hoff consfidensce Intervelo are .97161 to .97404. .9764 to .9710. and .9699 to .9791

thme estimated ctll~alonvabsorptlen mautra., removal liftimea . 5.191-05 attends; with an estimated otessdard deviation of 1.111-I7

May 32 13i11 1996 File nae.: 13533f.em ISAOCOCooo-1717-n200-90016 UV W0 ATTIACNENT XLIII atle 1

1a,,=rjnsa-,id.10*O1I9 S4I3*:¢i. ........ -4-!9-6 ttuss ................... prebid * 6/130,66 214:11

InpI3S301 elutpISSOfO

1. rt Faettl CrIffealit Sttu 3.3 n C~lDfmt - 301 3201 SE 1102 (ISS30f)C Caulic dIIts 8rf 1.r 6 fee .06 prosilty ref lcted sphere

1e CELL SPECUIFIUTIONS

3- 1 I G.072311.2 -I Naa*- C 8UT831 WORlDL

: at 1 *.ensle 1 I *P11a

9- C SURFACCE SPECIFtATICA S10- 1* to so S INNER FUEL ROMEII.It. KOE S15* 1cE001 000 1 7 ST1$. C "SAC i aI 010C 061.20 0 St I 5 20 00. . la00-tIs. C * *S S tO S 100 e 13 * * 14U e 6 1 -1 - U16 s 5 e 10 10 IT16- C MERIAL SPECIFICATIONS17- a £3p wll ater in oalt I AIe t ttuff) .95 ettlsUO216. a .3 rigtoal larielmsentl C SIONT deeaye to U~ranium ,sotopa19. .11 101jc NO 4544&469 US2.Cc 6. 237 6SC- 1 I20C. Cc 1302?. Cc * 61 00.C . 33 4-22tl 19900.Sc 08491.6 2 ot.see :.j5774-. SCCC:35c 1.54 1-62-22234 C 130s- ~ 23S Cc 9 c2" 70. :9358 65

9 2232.5Ce 1.1 3475-3 93237.5Cc 1.1882 5 e6M8t al lu tr.61t

as. PRINT1 initial anurce from fit. ortIkaff roaulte fur, Par-Plaid Critlea Ifty Study S. 3.S% /30 ne ti1 * 30% 12O / 5 1102 (13530f) prebid * 6 /0O9 12 l6ul

the initial flssion nMutr n sour.e distrilbtlon rus read From the eretp file _mod eretpthe critliallty problem ua Mcheduled to aslI 7 0ca4 amd r al inally 4600 noutrona pe rthis problem bas run 2 fnectIve .eylas it 2 N t Ktiaterle and C acthi qclea rith 120234 nutron hiastorie.

this ealul ltian has ompleted the raueated umbr of kff Ocler uIaln a total o 147615 fission neutron eource hietories.all eette rith fissinablO m* taratd ware sampled and bad fIoreu, nnutrin soure po nts.

the result. of the W teat for normality applied to the Individual. eolltlein. absorplion. and track-lenth taft erelo volues ores

the tI *otleln) ewle : valmea appear nralty eistributed at the " percent cenfiance tenelthae kaborpt an) oycl vlma appear normal ty ditributed at lb. 9s preant *ailfica lthe kttrk leng th olno valuew appear normally dit ributed at the 9 pereant cenfidoneii 1oa

...................................................................................................................................

the finml estimated oe binod *lttielon/ebsorption/trock-linglb ktff * .83719 with on astimatad standard deviliei, of .0"

the etltiated 8. 93. £ 99 pareant taft eonfidnic intorvnl a"ro .88532 to .88885. .838Z to .89C5. and .U244 to .174

the ostimated coaliteilonabaerption nautren removal tilfetife a 1.3E144 Uocnda with an estimated tansdard deviation of 4.63E-67

.................................................................................................................. ................................................................ , .,:

Kay El 14145 1"6 its,~ gams. 1333o..... UV000-11.00-0h l 00 LTACXUNU? XIV Palls I1

14. veolan 4A l£d.II01I33 0411719L 12a22116- --- 0 Ord

IMp-3320e *utpo1iS3000

1. Par-Field Critleelty Ste * SX.S 0 elm/ut * I30 1120W S.SS 2 (12530.)C: e ical C. 1.Jf1.? Uee 0 porltry * ruflected sphere

4U C INNER VATEI LESIGN5 1 1 *.042759- *1 IMPI1316. C OUTSIDE WORLD

7. 3 6 I IN PI u.0

4: M*SI7.CE SPECIFICATIONS

12- "eMt11 4000 1 7 3714. I te *0 i i 6I6I IC I 0 *5I * -

16- C 1AT EIAL SPECIGICA71017 el Iwt eetle ate t ft) x .912 6.5 welt UO017- * 2.SSOr. l nt EriIlaefX06P Scad to Uranl Isotope.

19 *1 l100.50e .6n 924 2 61 6.50e 4. 063 -3 11023 .58. 4.5261 420. 120001N.5 3.4 1-6 13027. O . 003 - 14000.S0e 1. 29-I2 i. 1 9 0 0 0. 5 0 8 4 5 . 0 0 .5 . 0 3 4 2 0 0 . 5 3. .4 80 6 1 6-4222 92234.50 7. 4 61 . I.- 3 3 . 0 1.40331S2-

U?, 92235.5 . 2S .09 171. -3 923 7 . 0 3. 13 20-614-. stl ae~25- 10:11'e11 te re

Initial au..rs from file srat -Ikeff rusults far. Per-Field Critisal Sty study - 3.52 is0 twisO t - 30x uz0/ 6.31 U2 (13330.)

bid a 64/417/96 1222s10

Probid a 64/17/96 12s22.1

the Initial floaten nautrn esurce distributian ms read frae the arntp fite rn"d *retp .the criticality pr blem n e.tedultd to *t 7 1ela and r*n a total of 37 eycles With alillY 4000 seutranc r cylethis prublem has run TInctiva ycles 9it 2766 esutrn hlitories and 30 actlv "yetin with 120679 gautrun loterles.

this seleuletien has .aupletad the reuutud pushr of ff e e uing a total of 15U33 fesion mautran auwre. hlsteries.all collt mith fiessiwabla material nar. sapled and bad flesa n neutren soUrc peints.

the resulte of the uI test fr normity applied to the Individual .oltisisn. absrptien, and track-lenath Isff eyed. watwa *arS

the tt etlel on cycle walwe. appear mormally distributed at tea s pareent ent fdeane laveltile k*abaauptian) sycla matms appear normal ty diulslbuttd at thie 99 par rt aunf hence lovsl but not at 95 persanttie tttrk length) pycle wvtues appear *ormally elstributed at the 9n poreent sent fienet ltve

...................................................................................................................................

tM- final estimated *e iblesd Realil /erptintraet ltb t tta .9900 with an estimated standard deviation ot .671the estimated 63, 9. r5 9 percent keff confidence intervals are .99727 to 1.10073. .9s to 1.e0230. and .n9429 te 1.e0373

the estimatod eotleleintabserptlen nautrun rmoevt lifetime * 7.79e-S5 *eceid. with an estimated standard deviation ot 2.671-07

r t

Nay 21 14.04 1996 Fite Eaws 13530d.ow EIAO OOO l-61717-0200-00016 KEV 60 ATTACIET 3LV * pass I

prehid * 416196 l6s30:0SInp.1353d outpi 303d

1. fPr-Field Critlcality StudY - 3.XI n10 Mit * 301 E20lOS 101 2 WE M30d)2- C Cacico Nillt TV T e.7l6e e .306 porobity - reflected sphere3- C CELL SPECIFICATIOeN4. C lINER MATER "Gle0n- 1 6.033424 *1 INP:E-16- 6 61UT1ID1 aLOW7- t 6TI I IMP $SE

9- C t1113ctA 1PECIMFICATIOUI10- l to 0 S INNER FUEL 2011II.12- I*Io13- 310O0 4000 17714- C ESc C 11 a 6 0 -o 0 06 29 6 2 6 6 1 -10 6*1015C- * . *-20 -10 I -136 0 1666 e I l -10* 5 -165 1 6 10 lo 1716- C 37A1WAL SPWIFIU110I1tr- C ISO vats gttr In Noit a tElls tuff .90 .10 Veit WO21t- C .55 1rJi0 garhe nt/ 0 61O T dcay d te Unituxm Ieotoee19- El l .Oc1 O. c1001*.c I - 2n1-' 1 22. O "80-40: 12000 Oe .6060 1 027. Oc 1 c 1.:17407-21- 11e0o Oc"Tb- 200 c5 6042 0.S 1205-422- 023 1." .6 10-I 7 22353 c 4. III67 9 2226c 1.977-1

a5 193223.50c 2.576949-5 9227.5c 4.376500-6

i initial our. free file creetIkeff results fort For-Field ErItiiftY Itudy S.51 /20 6/mt - 30% S2O/ 10 11 02 (13330d) prebid * P16196 1,3:O0l3

the Initltl fission neutron source dIstribution was tad freo the *retp file md gratpithe ortticality problem we scheduled to Wtp 7 sris end nm * tetal Of 37 c"clves witO nesnlI 4000 meutren. per cycle.this problem has run 7 Inactive cycles sith Itn neutron histories end 30 active cycls with 120460 neutron nlteries.

this caleulation hag eepleted the requested nauber of keft eyles usin$ a total of T4WO fiction neutron *eure histories.all cello with flee enable a*sterlel were easpled an had f st in neutron source pointe.

the results of the u test for normality applied to the Individual *ellielon. abeorption and track-length koff eyeln values ores

the hI esslielon) ytcle tvelma aspear norm. v iatributed et the 5 pereent eonfidence lentthe kebsorptlen) eyc va wle apper nermatly Sitributed at the IS ereent eonfldene levelthe httrt tength ey*cle valuees appesr normatll distributed at the 95 percent cenfidonce Vael

...................................................................................................................................

the final Estimated oembined .eetllen/ab erptien/trock-lemnth keff a 1.11325 with an estimated standard develetin of .AM19

the estimated 63 95, * 99 parsent koff *enfidence Intervels are 1.t1051 to 1.01454. 1t.dJ0 to 1 n161 ard 1.90701 to 1.61O04

the estimated eslsllienjabasrptien neutron removal lifetims a 6.911-OS seconds with en estimated otandard devlition of t.93E-07..................................................................................................................................

May 21 14M0 1996 FIle lame, iS383c.sum SEV00-077600006U 00 £TIACAXENT XLVI - Pose I

locri ve reign Os ld-1@01W9 64/14196 15157211talwil e.,e..eeee....eeeeeeeteP..e13e*..e*eCeeeeprbeid * 116"/6 15317M1

1. fasr.fald Crtietfol 231 M /1 CM/at * SOX 920/ 168 1502 (1253Cc)cal Ca *16Ill1t T ?Zf 7 Ilcc *306 pores ty . reflacted sphereg UtL VAPUC sICmTI NS :*

6. C WT3JISUS WORLD

1: 2 I0 10811i090.- C 6UNFAE SPECI FICATIONS

10. it so30 S1 1IB1l FUEL ZONE11-12- NOCE UII- IC0001 6000 I. 7 17

1 C 11S 66 a~ 100a.20t 0 69 205 60a-5 .1C00-1015: C 0A.51-20.i00. 1113 0.10'1 I00-i5 0 -5 *16 S5 810 10 7

KATLE11AL SPCIFICATUCIS,.?: It water n seltee Nittatuff) a .66 .14 vet% UQOa IN IST~at 9tori ~~U 0 SUDIT dae to Urenism stoeet

L0 1200.Cc. 180201- izz rigD 313

23: OZ9223.5C 3. 27729.2 132? Oc 6.127100-426. Ott tutr St21. PAMEI iflitlel *wei 6fusm file grotp

Ikof 6 results forts Pr-Field Critiesl ity Study 2.51 /30 613/at -201 120/ 143 1502 (123S3c) prebid * 64/14/96 15,57o11

the initial fission eutro n source dietribution wes read freo the sretp file med sretpthe !rbi tieitpr Sey s Vnd run s tetel of 2 tcyles with fominallY 4e00 neutrons Pr gycI.this problem bat run 7 inectlve eyles. Sith 2815 Neutron histories enW 3 active cycles with 120342 neutron histories.

this slevuletion has gospleted the requested lumber of khaf emies Winse t tat ofall cells with fissionable mterial wore sampled nd had i o n eutron souree points.

166477 flssien neutron souree histories.

the rsults of the u test for normelity applied to the Individual eollision, abeorption, end track-length hlf eyee vulues orse

the it eellisienl gycle vasls apr normally istrut d et the OS pereent eenfldence 1evelth t1eerpin Wyl sus appear noruui y LIstrihteod at the 95prcent confidence level,the kti legrth) ccte vatlws 4ppoar nmH tly distributed at the 05 percent tnfidonce level,

...................................................................................................................................

the fInal estimated cuebined oetlltlen/cebeorptlentroch-longth ketf a 1.0CSlS with n estimated standard deviation of .601e4

the estimated 6. 95. * 9 pereent helf confidence intervls sre l.62972 to1.s45. 1.0274 to 1.5. end 1.62649 to l.03t6

the estimated eslleiolnlabserptlon neutron removal lifetime a 4.9-C5 etcnds with an estimated *tendard deviation of 1.251-07.................................................................................................................................

may as113:39 1996 File EaN:3 iSS304.6u§ Irv000I?1-20. 1 tE o ATIACENINEE MITV * page I

&= ""ts . ; 4- t *0£.=.. . . .............................. 4 .a£# lsl~ts. ............ prebfd 04/16/96 14:56:57Inp-i3530a outp-i3330a0

1. froField 6riticalitT 6ludv - 3.3 /IW UOW/mt - 303 1E20( 153 UDt (13S3C)2 C Calf.. Vitt* Tv f 1.7 /ce .306 porosity - tlected cphere3* C CELL SPICIFICAUGNS4* C CEU U1lATIA. 911O85* I 1 7.994331-3 -1 IltPitEl. C eT11013 WOILD

7- t a~t i mpacll"TeWRPALS EPECIPICATI0MS

10 to 0 30 * lEINNER EL 3011

12- ERo a33- 1te03 4000 1. 7 3734. .120 601 66 lo 06-20 603c @a 05 IS-I e 100 10Is. *. 1 s 20 6e i Z3t 6 o It 6 4 3 t e -5 -i6 S I * to 10 IT

1 C MARAT~La SP FKiATIONS17- * SATERIAL3PECA0 vit i ter rl eeee Itf a .03 .15 volt 1102Ui. e .SS Oriointl 2 len hnt/ W U I t deced to Urenl nite!es9- I OMCI a. 704962. 1 60 Oe4.592n6 3112 3 * 3m.763 7Io* 12000 a50 (.7834 107 319-34000. 0c 1.31 440-317: 55g 1950.'0 465 . 20000. 9a 0 4oa54-4 34000.55s0 *.38025.4

32. M2234 50. .304 I 9i235 De9 4 *221-5 22316.0 339?"30-523- 223 S.t 3.U56 -.3 932370. te4.544 0-34- itl iutr.it35- PRINT

i nitial source from 3cre card, print table 90Ikeff results Ir: for-field Criticality Study - 3.53 /30 uWt t - 30s t20/ 15 U102 (13530c) prrbid * @4/16/94 MUM56:

the Initial ficaii n eutren sourae dietribution wood the 14 cource points that were Input en the kare card.the criticaltity probles me scheduled to skit 7 cycles e,, rn a tet, of 37 cyetas with nominally 4000 neutreon r oynte.this prble hase run 7 inactive cyclas hie 46 gbsutrn hietories and 30 active sycls with e t1199 tm autrn histeries.

this caleuletin has cepleted the requested nmber af half clest using a total of 147942 fission neutran eourse histories.al1 colta with fissionable materiel ware sompted nd had fission neutran asurce points.

the results af the u test fer normallty applied to the individual eellielen, ahaarption, oud track-tength khaf eycle valses ores

the ht selilen) eyele lus appeer normtly Itriuted at the n percent cenfidence level, but not at OS percentthe abserpt len ysle values appear nrmel ly stributed at the IS pereent aenflidoce lovtlthe 0ttt length) oente values 4aper normally distributed at the 95 percent eeifdonct level

............................. ......................................................................................................

the final estimated cobined klts erptintrclnth hff - 1.63aio with an estimated standard deviation of .61S5

the estiated 6t. 9, 9 perent Wf *onfidanae intervale are 1.82931 to 1.63243. 1.S2M to 1.3402. and S.t661 to 1.63513

the estilated eallisienlabsorptien neutron removal lifetime a 4.623-it seconds with an estimated standard deviatien of 1.24E167..................................................................................................................................

4 I

Nay 31 14.00 1996 Olli Name: 1ZSS0b.eaue nAAC000000-1`?17-11200-00M UEV 90 ATTACXENET ZLVIII P elt I

tmeer vnerin 42 t1- 5 10101lMstt* - -***-*--*-e****-* -***-**-- w~~~~~~~rebid * 04s16/9 15sRI: 131ipsl3530b outpl3301b1

1- Fr-ield Critisite tld 5.31 /30 ne aDt - 30e K aO 46 U02 (13530bl3- C Ce tlls Kill. EM f 1.7 sie .306 porsity - reflected sphere3 C CE L IiCAT 2 S"4* C KINNE WATER REGIONS- 1 1 7.9867524 -1 -I P:K1-i. 0 OUTSIDE WORLDT_ 3 0 1 IKPuK.-OJ* C suaaes 1PECI FICAtTles10- 1- to so0 S KIKs FUEL ROME111Z- MOVE S1s3 IcOE 4000 1 5 Is

14- C 1"530 I II IC a01 6 20 -toI29a 203t S 06-S -I100-I01S- C e S 20 -10 e -15 0 10 4 0 e1-S -10-5 163 0 e 10 10 1?18. C KATIRIAL SPECIFICATIONS1? a 00 v4ae l water c*in salloe Sllto tft A .U4 .14 v.11102

19t . 10ISc .490- g1. c 44549 d 1102345C420. 12000D Sae ule2 1 027.c 12925. 1 a000.oc 11012I24621 nooo~sec . 2eeoo19000. . 4 . 3182-4 36000.53.2z- 92234.0c .S90 65 Lzsu.ocr. S0os7: 9m6.5c s233 I2Z33.50c 3.e03u3 93237. c J.t2600-824. atl lwtr.Slt25- FAINT

I Initial seurws fro file Bretptheff results fors Far-field Criticality Ktudy 3.n /30 11/ut *M 102o 1S 1102 (13330b) probld . e4/16 MUsM312

the initisl fission neutron sourae distribution ucs read from the oretp file notad erctpthe eriticality problan was scheduled ts shl 5 3 sctos and run a total *f IS eCcles wmth cmthally 4000 eutrens r sycle.this prebile Ias run S Iractive sples wits I" neutron histories and 30 Rctlv e ces with 120160 nutron Istorlss.

this ealculation has *mpleted the requsted obar of keft acles uaia a total f 140146 fission neutron source histories.al sIotle wIth fleimbtle material ware esaplod and had f cecn .isutren *suree points.

the results af the u test for oranlity sppIled to the individual sollisien absorption, mnd track-tlngtk koff oycle values eros

the ht solltieln) onlo valun s ppar noroally distributed t the 5 Cargent * nfidance tlthe ttabesrptl) n l ales appar noreatly diatrlbutsd at the n peront oit i ce levlthe tktrk lenthsye values wccr normall dlitributad t the IS persent sonfidance Ileve

the final estimated coabined matlltl ainbsorptin/trsckiloneth heft a 1.4l268 with an *atlrated standard deviation at .0183

the estlated 43. 95, & n pereont heff Ronfidance Intervals are 1.02494 to 1.02866, 1.02305 te 1. 54. an 1.0217 to 1.6C18

thb ostilated ellieeanl'obaorption sutron reval lifetime a 44.32E-0 eocanda with an estlated stsndard deviation of 1.lCE-07

.................................................................................................................................

ear 32 14100 1996 Fit.le iN 1135303.Sum u 7o ooo e sy e00 eTT*CKMEN0 1 L - Pae I

I version 4a t~~~~~~~~~t-101MI 93pahi m 04/5096 :MUM3i-W3530j outpOiSSOJOa

I. | sPar-U loid Criti , Ithhif 3.* /S 0 /so /at * 30 1120 51102 NM 3330J)- C U ias gals" 1 1.7 /se * 06 I .I..posragIty - re- f Oted sphrre3. C CELL S1PICIFiCATIi01I4. 1 111111 KAThR RE6105- 1 1 7.1195451- -1 ils l,. C UTIIDIEkLOr a *t * u a .09. e SU3RFCE UECIPICatIoNS

10- 1 so so INNERP WEL ZME

12- 1000 I15- c 0t C4000 5 I 7 6 e lt e e *20 e 9 O 20 5 7 a 7 10 I 10

11- C I. T5 -230 -1 -13 0 l 10 14 -10 U e e*-10 - 1 -1 6 * 01010 116- C KAISRIAL IPECIFiCAIIONS17- e (3 wel wter In soleo Elitts tuff) a .ff 5 vots U02Ua- a 3.11 Irinal Enricaent/ 30 4iD/IT deca 1ed te Uranium haoto*e19- Si 1I 00.0 1.370364-3 6016.510 r979366- 1023.50c 4.32571 -430- 12300 W .54136S4 13027.10. 3.66U1-3 14000.30. 1:.53374-3I1- 19nooe .10491-4 300OO.5e .:57766-4 26000.15. ;."4231*422- 922.. S 4.05401-7 93235. 54034 S 92236. Cc .985361-0

35- F~lET 9223.1.1.183471-2 93237.110c 3.163250-6Z a stl lwtr.Slt25- FAINlT

Initial temrea frm file artIkeff result. fort Far-Field Critical tyatudy * .X ne0 Wi/ s 02e 120/ 01 Ui02 O jori vr 01e0196 M13:3:39

the Initial fisnlen neutron soure. dietributten was read from the *retp file sed *retpthe aritical ty problem was echeduled to skit 7 r eletend run * tetal *t *7 'petes with ominlltty 4000 mautreen g etethis problem has run 7 Inartiv cycles with 2m neutron histories and *0 activ ey"leo with 119857 neutron iMterioa

this calculation has eempleted the requested raber of atet eyctes using a toetal teat cetts with tiauionable matserial war. empled nd had tficion neutron sour. points.

147613 fissen neutron souree histories.

the results of the w teat for normality applied te the individual eellision, absorption, end track-length ksnf rycle volues ares

the tt cellision) acye valuee awear normally distributed at the 95 prcent onfidence levelthe ktabaorptiln) cycle values ppear normally distributed at the 95 percent onfidence tentthse kitk length) cycle valume appser normally distributed at the 91 percent confidence tevel

................................ ..........................................................................................

the finst estimated ecobined collclsnlsbsorptl treck-tength teft - S.0652 with en estitted standard dv1cstten et .00130

the estated 6 9 S 9 percent atof gonfdenec intervals ere .9ZSN tos .784. 90355 to .90919. end .90252 to .S1C13

the estleated oeltitlen/sbsorptlen neutron removal tifetime - 1.31E3-6 sacwnda with an estimated standard deviation of 2.371-67...................................................................................................................................

Kay 22 13:16 1996 Fite KlOM i3530.1-M SUACOOOCO-6i717-0200-0D014 NEW 00 ATTACINIET L * Paeg I

loci vrsioln * . Id.10J01.93 J66/17/* 1 5,56,27Im".531o"eer..eee1eeeeeeeeeeeeeees probid * 04/17/94 15t54.27

2: t tj5 tU IU/a -lr 2Oe 52f0( tOZU02 (135301)3- C CIEL SPECIFICATIONS4. C INNER WATI EG6I6O05- I i 1.130717-3 .1 l11PU16- C OUTtIiE WORLD

' ' '~ 1 Illpoed

,le: Vc so so s INNER FUE 20111II-

12- lloE IlJ. 1CODE 4000 *. 7 J71U. I 131C 61 6I10 c 020 a a29 6 203 6e .- 10I1015- C .s 20 *106-3600 14 I 15 -10 -5 -16 5 5 * 10 10 1716- C NA1t3IA3 6IPCI ICATIZCUIT- a N20 vots matr in calu, lile tuft) C .AG 10 volt U0210. e J.55 Orilinl Enrichent/ 30 aniU duemeyd to looter.19- *1 101.ec 1.150054-2 s1. 12c 4.55Z2 103Sc 4944420- 1200.5Cc 1.407609-413027. Cc 3. 1364- 000 c 1 187407-22St 19000.5Oc .9991.-4 0000. OcS.9 Z17 4 W0O6 g5e 1.441203-422- 2234.5Cc 9U609.7 225. c 4.621 75 Z236. 0c 1.97173-S23- 9223 S0. 2.O 74949.3 93237 Oc 4.376500-424- *tl Itnr.ilt25'- PRNTI Initial source, ren ftsl greto

tkeff resultt taori er-Foild Critical1 ty Study 3.5S /30 gVD mt 2es 320 1o0 UN2 (135301) prebld a 64/1T 15,l5:2?

the initial fissien neutren source distribution Lss read freo the eretp file m md erctpthc eriticlilty preLm was scheduled to skt 7 etaes and rin e totat of 57 cycles with nmnally 4W00 neutrons pr gycle.this preblee m s run 7 Inactive mycles with 27322 neutron histerle end 30 activ eyelos with 120249 _mutren hetories.

this celculetimn bes eomleted the requested number ef keff cycles using a total o 14123` fission neutren ecurse hlsterle.all celle with fiesnebe materiel were eampled end had fies in neutron source points.

then sultts the t test ter normality applied to the individual mellision, absorptlien, nd treck-length keff cycle values are:

the ht e1lelnl eyerm values ppear or tly dlitrilbuted at the 95 percent cenf'dlnce vtthe kgobsarptihn n c va s a:;ppear ner:elty di tibuted at the 95 perent :onfdee evetthe k(trk length) cyclo valus appear normatty distributed at the 95 percent onidmence lvetl

...................................................................................................................................

the finat activeted eebined ealtiselenabsorptienlntracc-lmngth t a .9734 Kith en estimated standard devietion if .10014

the estimated 4t 95. I n percent heft senfidence Intorveal are .97785 to .961102 .97623 te .9264. and .97511 te .93377

the estimated eolliaienlocborpti neutron renealt lifetile a 6.561-65 secenda with en estimated standard devitlien of 1.4e.................................................................................................................................

Noy 22 13:16 1996 *11e mans 13530K.euem KEAW0000-tt7e200-0001 v 00 ATIACUNIEUT Li Page .1

lne~c., version 4 Idal8/14 .1 n93

Inp-lS530 eutps 0ala331

1- Far-fIeld Critiselity Study * 3.5% /so 0Mat * 2es S2ao 12S U02 (155301)2. C Call. 3e11t TVuff 1.78 eoer .306 porsity - ref cted ephere5. C CELL SPECIFICATIOUS4* C "Ilt VATER REGIO01. 1 1 7.5ss29b2 .1 IUPIUUI

6- SU1SUE01 WOL7- to e E 1PSC e6-ra- NNE S SPECEPIC*7f01Ses- Sot 000 70 213 S I *tlEL 203_

13 Mclte 6000 1. 7 3714- C 5C0 ee I etl ee-ac 6029 020S ee-S *toe-toIs. C 0 .5.320 I CS 13 a -t0I 14 6 a*I -1 S * 16 5 5 1010 I16- C S&116 CplcEFICArIONS17- e t20 ,t Meter In sellce Kils tuft) x .8 12 ae l U0216- e J.5S Orilnal n Chownt/ 30 IWNT deced t rnfum leatepes19- Gt tOl.50c .6758 1016.IO c 4.646384 24 1123.3c 4.60697 4420. 12000.50c3.3541 4 13027. :c .453541-S uoee.so. 1.1660204

12- 92286. .0' 144299387 *3 . -S32 19000. Coe.589- 10000. Cc .7946720 D60.C 1.428752-6

92213. Cc 2.35393 93 so50 1.25t800.6Zs. PRITI Initial esurge free file rt

Ikeff reaultt for: Fer-Field Critte:eLfty Study 3 *.51 30 CW/.t 201 120 I2n ue2 (1353) prebld * $4117196 15:03:47

the Initlat flealen neutron source dietributlen wes read free the erctp file need cnrtpthe erltitellty preblem usa scheduled to ekIt 7 ties aend run a total of d 7 *Ctles with Nominelly 4000 mautrens prr Cycle.this preblem has run 7 inactive eycles with 27656 neutren hiatertc end 38 actIve cycles wIth 1197l 1 neutron Illterles.

this *alculetlon has oleted the requested mber et keft cycles using a total ofelI sells with fIss ibl a materiel ware sampled andl had f lss ln neutron souri* peinta.

147409 flesien neutren course histarios.

the resultc et the w teat for normalIty applied te the Individual eallialon. abserptlon. nd track-length ketf cycle veluas apes

tle tt *ellialon) *rtle votlum vpeerr normally 1 strlbuted at the V5 percent cenfidence levetthe Oebs rptlnl otcle vlues ppear nermal l dlctrlbuted at the Pertent sentfidnce level but not at 95 percentthe Stur tength) cycle values appeer Normally ditrbuted et the phrrent confidence levet

,...................................................................................................................................

the final estimated eambined eellieion/ebserptlen/trc-ength halft a .98612 with en estimated standard deviation ot .e0200

the estimated ". 95. A 9 percent talf confidence interval. are .91840 to .MU4. .n1202 te .9021, and .059 to .69165

the estimated eolifelenJebsorptlen neutron removal lifetime a 5.50E-C5 seconds with an estieted standard deviation of 2.311-07

............................................................. ...........................................................................................

Nay 22 1317 19 FPiI t a me: 13330h.sum 3AOD0D000-61717-0200-60016 REy 60 ATTACNlIRE LII * Pale 1

fmnat ... version 4a td-10101193 64/17rebid a04/17/9615,,6:3

Inp1i3530h tpoISS 0ho prabad a iSM 5.2 bO

1. Far-Fled Criticality It -'- .52 Ino 1/mt ' 201 520 142 1102 (13530hl2. e Calicoe N uVf t.J * 6 at ppersuy n1ecetd sphere

C* CELL SPECIFICATIONSI e 1I1R WATER t110Y

n. 1 I 7.1397-a2 *1 lEPNtF-11 C oursiTE 11010D

tS- t e. *s 2e *e a -13 0 *le 14 a e -1S *te *S -tG S * I le la 179- e IIATCtIA SPEOIFICATICU

1I (2 vetX water rIn *eatse atl at I ) .f6 .14 vott UDZ12- 30PX oriSinal Kerich U e 20td to Uranium Iotopes12- l1 ISO, a Ilo- 2e4000:0 1. 7 OD600-4 I? 1 1 5U0 2Il- C 9003.066 S61 65- 20 602916205 66.:9 0Za 2U005 .10146202216-234 So 1. 1682TA, 6P7SI F21- a 2M.110e ster 92n37 s. Si f .1271f e v 0Pt 1v tttr.olt16It- s .2 r l hdT from f nt rr19-eff resutst f 100 F .r-f0td CrI t.c5ffty St1dy 013.5 X nD1t - 2ex 12.0 14. uOZ e15eh) probfd * 9/17t6 MUM

the 12nitial.mt *source d06st tit n road fr10 t7e .r5 t 25 33le n1000.0 d * rctpthe criticaltity pt! bten wastscehettuletd to *litp 7 *tees atnd run a tetat of ST *r tes wthlt nominatlt 4000 netutrons re ethle pnobtttt has run r Inactive cycles attl 27S6s nttutrttn histories and So aciettt cyctes ulth 120155 nweutttn hh.ttttlyttst

tble ceetr n bcm teesletd the rtettt &d Aimer of kaff eS ing atwt total ttf 141023 fissiotn neutron soturce histories.at1 *9tml plot wre sampl9d and tt0td . le. 2e6utr000n . euree po.nts

the rttwlte of the wt test f tr ner ality * ppl ed to et Indlvidua I tetlel sn, *bserptittn. ttwa tnetk tengthl keff 't"'e vteutest are

tbe tt eettlelttnl yete vatttts *Ppperr normally dltelbtei~id II thda*tntetnftce leveltheIa l car epear morms dl sr but t the te tieent lenfidene lertlthe n titi l fiteien nutr e twee ppear ourctly distributthe ed at the nm peent ersnfitnce tevtt

...................................................................................................................................

the ritict atl-ptebec mbined sedtleld e aeiptle tcyck-tleanth t ff - . 34e0 with nomn iti ated sltand0rd e etiron rf .eyle.

the esultsofhe a t etd V.tA ercnrmitf confietoe intival en .9lle. 202r .tl 0 end . t755 tok t h a yce vue aoes

the estimated eotilslien/beorptien neutran rencml lifeti * me 04.621-S seconds with en asimated standard deviation of 1.241-07..................................................................................................................................

Say 22 141 1996 File MUNI 1404CtSfR *m O6100-61717-1200-10014 REV *0 ATTACMNIT Lill - Page I

t eeip version 4a C.1../93 #4/30/96 5.135156*.~~~~~~14~~~~~~1t ~~~~~~~~ ~~~rbid * 4/30/96 13:31:16

1: fr- i t Pf e clity /-U 140 s 0n O t * 3OS 120/ SZ UD2 (1604Sf)2- Ce Gs. lilts IV f 1.rb 910 .11 o fsity - rf ated sphere

3- C tELL SPECIFICAtION4. C INNER WATER RESIGN5- I I SAM21S-2 -I 1,.4- C OUISIGE WORLD1- a I I iN s.G6a.9- C guargaC SPECI FICATIONS10. 1' 50 s0 * INNER FUEL 2WEtI-12- NODE U13* ICONE 4000 I 7 ST14- t Kic i 0 7 0 to I 66-0 -t tI 9 025 a °-5 -10 I -Is- C ,,0. , -106-t13 8 -1S 14 1 5 -1 O -tO 5 -16 i 5 5 10 10 1714- C MATIRIAL SPECI ICAUIONSI7- * ISO veot wat r In caleoe lilt tuft) e .n t vels t12

- e 4.50 Origt Inrl hunt/ VA UO/T ecye0d teurgInlm lestopes19- *t toet.soe t.rs544 6014.. c 4.j49S7 1023.5Cc 4.32573 -420D 12000.S~e C 41345.5 13027.0. 3. t 418- 14000. Oc 1. 3374.t

S4 7664 2600.5.1 438 1.22: 122°3I 1 7 255 5 1 5 5 .5la".42.3 223.c 1.603500.313- 9223 50e 1. 55985-3 93237.5ec I. os-24- stl Iltr.Oit2- 912317

iwitisi *Du?** ft.. file ritheff results ren for-field Critlie ty Study - 4.Z S40 MODMt * 307 1120/ SN U02 (40f t prebld * 04/30/96 1331:54

the initIal fission neutren eaurse dietributien was read frem the *retp file nmed sretpthe criticality problem Was schaduted to skit 7 cycles Nd nm * tetet of 37 sylta with nominally 4000 nautrene er *evle.thiu problee has run 7 inactive cytes with 2313 neutron hieteries and 30 mctive eyclee with 12024 neutron litet lee.

this calculation has etpleted the reested number of heft cycles et ins a tetelt 1f 477 tiesien neutron soure hiseteries.all cells with tisslenable msterisl were ceapted end had tiessin neutron source Pints.

the results of the u test for normality applied te the individuel cellielen. ebsorptien. nd track-length heft eycle value, sre:

th:e i collision) cycle velues appear nermelly dietributed at the 95 Sercent eenftlence lenethe hbeorptisnl cyce we les appear normally distributed at the ff bcr.ent snf ind e .vtethe (tlrh length) cycle wovues eppr normally itribwted ct the *5 pereent nfidence ltet

...................................................................................................................................

the final estimated eembined keliaien/sbscrptintrschlength heft a .86893 with en estimated ctendard deviation of .50117

the esetimated 4. 93. & 9 percent t ft confidence litersts are .864 toe 37012. .U6653 to .87134, and .S643 te .7219,

the estimated oettoliionlbssrptlen nutron removal lifetime * I.23E-04 esconds wilt en estimated *tenderd deviation ct 3.609-07.................................................................................................................................

Mey 22 14012 tn6 Fite gea.o 14040d.smm SIA000000-017T.0200-00016 REV 00 ATTACNKEXT LIV Pean 1

l c:C vrere'n 4. Id-itO/i/93 S4iSt/96 0 F:152.*OO*- *[email protected]**O5**-~~~e~ *eeO*te-* *-*ee**-**e*-**------*--.ee.eO*............................ piotd * 04e111,9 07:15 sO

Imp-14040d *utp i4040dO

I- far-fleld Cr4 tisetity SjudY 4.0- 140 SIDm 2 3020t i0C Ut02 (I4045d)2. C Cs t tie Tu f .7 6 S/cc .306 porosity reflected sphere3- C CELL SPECIFICATIONS4 & INNER WATER ItE st05- I I .633424-2 1 '"'-'6. C OUTSIDE MOULO87 2 0 1 111PsU.0

9* C SURFACE SPECIFICATIONIS10. ' So 30 S INNER FUEL ZONE

12- M!E U13- KcoE 4000 1. 7 3714- C KIRC e 0 1 6 010 0 0 -20 I 0 29 6 20 5 0 0 - .10 0 1015- C 0 -5 20 -10 0-15 0 -i14 0 0 15 -10 -3 -lI5 0 1010 1716- C MATERIAL SPECIFICATIONS

a7 3 v.11 water in callco Nlits tuff) x .90 .10 vats U021tt c 4.01 Original Enrichment/ 40 SW/NT decayed to Uranium tset e s19- ml 1t50cc t1052542 S06.5Dc 4.32311-2 11023.5C 4 .09303 420. 12000. 0c 2.407609-4 1027.5c 1.713848-3 14000.5Cc 1.187407.221- 19000.50c 5.76991-4 20000.50c .92410-4 2S000.91c 1.4412 3-422- 92234.30c 1.244889-6 9223s 5.c 1.515723-5 92236.50c 2 S1IMM0S23S 92238.54c 2.5171969-5 93237.5Cc 5.619417-624- itt lutr.61t25- PRINT

I Initiel seurce froe file oretekheff results tfr: fer-Felod CritlicTlty Study - 4.OS 40 CllD/Mt - 3 120/.10S U02 (14040d) probid * 04iO /96 07.15:02

the Initial filesin neutron source distributian was read froa the srctf fil, named srutpthe criticallty pretlm wuee schedultd to siD 7 Wyles nd run a total of 37 cycles with nominally 4000 r utr me prr cycle.this probltm has run 7 Inective cycles with 27997 neutron hlstorios end 30 ective cycles with 120178 meut an histbre.

this celculeuton has csplotoed the requestad nuebar of heft cycle using a total of 148173 fission neutron court r histories.all cells wIth fiesioneble material were soePId end hod fi seon neutron esurce points.

the results af the w toet for noreality spplled to the Individual eollieIen ebsorptlion and treck-length heff cycle tlues Arcs

the kg collision) cycle values sppear formally distributed at the 95 percent confidence levelthe kteaborption) cycle vtlues eppear neor tly distributed at the 95 percent confidenc leethe kctrh length) cylel values eppoer nrmer ly distributed ot the 95 percent eonfidanco level

the final estimated combined cellilson/bsborptiontrackLlength koff a .99"2 with en estimated standard deviation .f .00134

the estimated 9 n *9 percent keff confidence Intervals ore .99526 to .99799. .mt37 to .9m99. end .99291 to 1.0003S

the estimated collision/absorptlon neutron removal lifetime * 6.97£-05 seconds with en estimeted standard deviltieo af 1.33E-07............................................................................................................................ ................ .............................. . ...............................................

Nay 22 14,10 1996 file Sem 1040b.eu BilAOCOCOO-171?7-.200.W0016 ttV 60 £Uta3n1 LV * Pate I

.. e.vaersio 4. ld-10C1O193 "6411119 ml,03e probid * "117/96 17ail1s6

EU). 4C4Ob 0111`0i4840bo

l- Par-Field Critceelity Stum * 4.n2 /40 Mt - S05 120/ 12S U02 414040b)2 C Calias fillt Tv f I.? l/ee .106 peresty - re fected sphere3- C SILL IPECIFICAIIOIS

4- C 6OUtSID NOWO L7. 6 1 IZINOEC8-9. C WuFAtE SIPCIFICATIEONS

1C 1* so s0 S INNER FUEL Z03311-12 IIODE als- xcci 4O00 1. 7 714- e 3A1 a 561 66 6 IC I -t0 669 6 205 06 e 5 -10 0 -10is- c *I .-5 10 * I -t * -10 14 6 * -1S -10 -5 -t I I a to la I?16. C IATltZAL SICIFICATIONSI?- e Ot votS voter In catice, IIse tut1) x ." 12 vt& ue021- e 4.6 original enrlhment GM/WT doe id to Uraniui lotepes19- .1 1001.e l.7653137-2 8016.10c 4.3 7sn3t 11623.30c 4.00697 T420- 2I a.5Cc .3S l466 13027. 0c 2.653541- S14000. Oc 1.161020-321- 19000. Cc .SS391-4 000. Oc .79667-4 36000.3. e 42s32-422- 92234.1Oc 1.496267-41 Z235. Cc MG4168S 2236. Oc 4211203SI: n92233 50 e.-463S3 S93237.50c e.073160-6

24 etl ltr .6 1t23- P33W1

i Initialse fer- fle 'C'lt'fty Study * 6.es/ r4e D/ft iOS gi2t 125 ue2 C140 Ob) prebt a "ilyn 17811 esIkeff results fort For-field CWiicl t td .3/638/t-3330 2 52i4CS)rad 6419 7116

the Initial fission moutren source dtatributien was read free the aretp file named satpthe griticalltV wprsebm assamciduted to skiCp 7 sles end runi a ,tott of 37neyls with nominally 4S700 neutron. pr eyeye.this problem Pa ro 7 nctive cycles Bitt 27a73 nutran hkIteris and o0 actwi cycles with 122S9 neutron hlstories.

this9 catculstetn has to. eted time requcsted nueber of tef eles using e total of 142237 fIssion neutron source histertos.all etlls with flssionable material nare sopled and had fissien neutrsn sounre points.

warning. there appears te be decreasing trend In theea *r *etl/absft alof eastimator evr tme last 1a actIve scete.the results of thc a teat for normality applied ts the Ind vi eel at slen. absorption and treck-legth i eff cycle values re.t

the kb collision) "scl vatulu appear normally distributed at tbe 9 psreent enfidente levelthe btabrerptien) yclv appear normally dstrilbuted at tbe 95 pesent een11dence levelthe kltrt length) cycle values appear normally dletrlbuted et the ff perent enfidence level

...................................................................................................................................

the final estlacted sosbinod oeltltlon/absorptlon/treck-longth kaft * M.O6ST with an estimated standard deviation of .e0152

the estimated 8. 95. A 9 percent koff seonfidence Intervale are 1.60424 te 1.00732. 1.60267 te 1.6089 and V 1.60158 to 1.60995

the estimated eattlelesnbsorptien neutron resovat lifetime * 5.631-1 seeasndr WIt an estimated Standard deviation of 1.921-67..................................................................................................................................

Noy 32 14.e04 196 Fita Name: l4OS4aO.tm SSAOOCO ?17.-02004-0016 KEY 00 ATTNONEIT LV - Pgs I

IUfl veson ld. oiO!l9 041 1961637:131n d tO 5**e@OsoOOO*@,,@O*e4ta aee.*,*6 *a prebid * 05117196 16:37:13IUNP404a iTlPaI4040ae

I- For-F.ild Salteaity 9tud. * 4.03 14C LUD/mt 301 / (t20/ 14 UO2 (1400)2. 0 Calis. I tl Tu f 1.7 Ileg .306 porielty - r flacted sphereS. C IELL SPICIUISAtIOIS4. 5 INNER WATER SION10- I 1 t .MOZs31i-2 -1 IRPSIEW

| t wt~msasc wisslcz exI 4 I IMP8108

9. C SURFACE VPECIFSICAMS-C is go t * INNER tUEL WSOE

10. 1c 50 30t 1 I RUIL21: NMDE I13- 9CODE 4000 I. 7 1714- C 21C I 601 e e lo I 0 0.0 0 0 2 0 e 0 -e 5 -10e 0 10IS. C I -1*St *010 e .13 0 10 14 0 -.15 0 -5 -14 5 5 0 1d it I16* S NA3SALSPCIFISAITOIS17- e 430ols water In satIle Nitls tuft) a .66 .14 sot% I002IS. a 40..01SIgInst 2nrlshaent/ 40 £/N Ieae to Wrenlum loot sa19- at a001.1Cc I .25021t 0 c 4.j33035 211023.1Cc 3.119 -420- 12000.1Cc 2.300604. 13027. 3c . 9Z333-3 I40.Ic 1.134S33.2I- 19003.5Cc .1299-4 300.5c 1."4925-4 16000.. 1.:396241422- 92235.5Cc 1.765645-6 92233.1Cc .:322012-S 2236.5Dc 2.8640.523- 2ZZ36.%Cc 3.320757-3 93237.soc 6.35746-24. *tl lutu.O~t2#- PillT

1 Initial cure- fre fIle srotcIkeff results I rs for-Field CrIticallty Study * 4.0* 140 eW0/mt - 302 u20/ 142 wz02 (1 400) probld a 04/11/96 1473

the Initial fistion moutran *suree distrIbutlan wos read from the eretp fit* nosed s*ctp Ithe criticslity prebim vsa scheduled te skip 7 *ecte and run a total ef 37 ecclet with seminally £000 neutrs pr eclthis preble. has run 7 Inastive sycles Yth 8071 neutren hitterlas and 30 active eycis with 119"29 Mautrtn neterise

this celouletlen hats copleted the requested ember o eft k lea usIng a tetal ef 1,4000 fission neutron souree histeries.atl cella with fissionable m*teriel were "pled and had fler en eutren esuree pointe.

the results ef the v text for nortaity applIed to the individual eolleisin. abasoptlin. and trect-lnetb heft eyete valuet ares

the k( esllielen) eycle values appear normally dlstributed at tha 93 percent senfidenee levelthe htabserptlan) syule values ppear normally distributed at the 93 parent *snfIdtnce lavelthe UtIrk tength) cycle values appear normally distrlbuted et the 95 pereant eonfidence lavel

...................................................................................................................................

the final estimated esablead eellialolnabearptlen/track-tength atof a 1.00910 with an estlmated standard deviation of .00174

thte estimated U. 93, I 99 pereent haf onfidance Intervta aee 1.a0eMO te 1.0107. .1.0353 te 1.01267. and 1.00427 to 1.61392

the astlmated setitelen/abaDrptlen eutron removal lifetime * 4.973-05 seeonds with an estlasted standard deviation of 1.0Ec-07..................................................................................................................................

lay 22 14.11 IM Pile Sames t4040c.s 61A33OtOOO-1717-6200-00016 9tv 00 AltACHI605 T LvI - pase I

1U=e*fl vertion -4 id-10t01/93 I te Itr32S17 *robi * 6t4196 17:32:17i37,i43430c SUTP0i404M rbO I1C6 3O1

1. Per-Peldt CrIt caflty tw * 4.3 140 610/ot 0 S is *20 16X U02 (1M40Cc)I* C Calittce stil uf 1.74 V/ac .36 porosity * ref lected sphere3. 3 CELL SPECZFICATIORS*- C INNER WITER REGION1- I I 7.9847322 *1 tNPFIUi

7. 2 6 1 IUlPiK.0

1- 1- W tO 6 WOR 1 LUDL 201111-12- IlOf a13- 10301 40030 1 314. C 5IC0 I I 0 0 I 620 0629 I t2o I 0 t5 *10 I *13is- C aS. -20 i360 I -136 j-10 14 a 0 -15 .1 *5- 16 S 1 a I6 10 l716* C NAIIRIAL SPECIPZCATIOUSIT- a t30 vt% water In ealico Ii a tuofI a .84 .16 vote ue2U41 a *.Xe~ t gartehn 0 tlT 1caewd to Uraclum ee te aeIt ml * 00c1 04S 4 l4.to- 12000 :e :2 247l02 130 ~ ~ 2.S22 4 OO.60e3l-lOS24 2UUll: ItoO. :#e11n4 2004 t6000.U5c i.U3to -4

23- P2236.5Cc 3.79 11 1. P323?.3c 9.437447.624. stl lutr.Sit23. P:311T

I Initial surce frem fite , rctpIheff results fort far-Field Crm1Xti tyStudy * 4.33 /40 6WP/t - SO 12/ M SMW2 (i4SCAM) probed * 64/ S 1T:32.1?

the initial fission neutren source distributien ws read free the rretp file named *retpthe criticality problem was scheduled to skip 5 p yclese nd run a total of 2 yles with nominally 4000 neutrens per sycle.this problem has run S inactive cycles with 3362 mneutren histories end ectwive cycles with 120608 neutron isteries.

this calculatien h:as comleted th equ ested numebr of koft c"yls using a total of 140670 fission neutron source histories.atl cells with i ilenable materiel were *ipled end had f slon neutren eource polite.

the resulte of the u test for normelity ailied to the Individual eetllisin ebaorptien. end treck-tlanth toff cycle vawues are:

the hI melieleen1 *ytcl valams appear normally distributed at the 95 percent eenftidnce levelthe Nobeorpt on' cycle values appear normal i d rib the 9S peroent senffdne Ieethe hltrk length) cycle velwes oppear normally dietributed t the 93 percent confidnc leVel

...................................................................................................................................

the final estimated cobined eelleision/aberptien/tracktlength koff - 1.69093 with an estimated *aundard dvictien f .124the estimated 68, 95. t 9 percent hoff confidence Intervals ere 1.MOM to 1.61048. 1.60469 te 1.61177. and 1.O5CH to 1.6125

the eetiuated ellisienlbserptien neutron removal lifetime a 4.29165 *uec with on estimated *tcnderd devietien of 9.741E8

fay t2 14s14 tn I Fte lame 14040e. e KEAYoooB eOt7tr-uoo 1V * TTACeENIU LVIII * page I

tmcng Irdnn a.telO/1/93 mtJUS W 17:556

Inp14040e *utp..4040e0 probid a S411196 O Ol0:5

t- Fer-Field Cr1 eeality Stuy* 4.62 1t0 610/at - 302 0201 1US 302 t14040o)3- t C Calo as U a a luTf 1. Wec .J06 porosity reflected spere

C. CU ectSPECIFClulczlS4 C I1211Et WATER REGION

5. 1 1 T.971195-2 -1 INPIN-16U C SuISio MuLte7- 2 * 1 IW~sO

9- eC *UFAC SPECIFICATIONS10- 1i s0 so S INNER FUEL MEII-12- 9001 113. KO=a 4000 1. 7 3714 " C K3RC 6 1 ' e 0S1oo e -t I6e9 6 20 I 1 -10 -1015. e C a S -to . 0O I-13 a 6.i 14 6 I -15 -10 66 l101?16- C UAT91U2* SPECIFZCATIONUI7- * (30 well aoter i caIli Ills tuf) i2 1 vaI U0218- . 4.6s Srigln C"raet entl 60 e KT drecnd to Urunium isotes1U- El I SacSOc 144477t 016.Stc 4'*7795'* 11023.50c 1.T3773-420- 12000.D0. Uc.l9 9 4 1027.1Cc 3.4617.4 14000.0Sc l.S11860-221- 191000.10C I.Z.72192- 4 0000.sc .40440-4 26000.SSc 1.331316-422- 92234.Oc 3.14400-6 :225.S0c .. 281-S 923136.11 3.631410.123 P21 t 6 see 4.269144-S 93237.5. 1.175-524: Istl" tutr~i~t25- Fail?

I Initial ource *fre file sroti1keft results tors Far-Fleld Criticality Study - 4.s 140 6310.t D30 11201 16S U02 (14040e) prebid * 64/18196 67.056

the Initial flsalen neutron source dietributlin "a sed from the oretp file moed eretpthe criticality problem me *cheduled to skl 7 eyles end run a total f 37 eylea with nominally 4000 neutrone pr ytyte.this problem has run 7 Inactiv es cles with A7979 neutron histories and 30 acti eystem with 19975 neutron hietories.

this caelclatlen hea flplted the requested tuaber of ketf cyclea using a total atet l ells with IFilonle moeterlel were eoseld end had fleeis neutron seuree points.

147954 fleteen eutron source historfes.

the results of the u test for normatity tpptled to the individual eollieion. ebsorptlon, end track-length keff cycle vtlues ares

the hI collisn eyncycle volwes ppecar normally dStribut d at the IS percent confidence levelthe blabsorptten) cycle velwes sp r normalty distributed *t the 95 percent confidence levelthe Witu tleth) cycte velues Pi" nor m ly distributed at the IS pereant cant danee level

..................................... !..............................................................................................

the final estimated ecebined caltlsaivabsorptienltrck-tlength keft a 1.00143 with an estimated etdrd devietion of *00i45

the eostieted dJ IS. A 96 percent toff cenfidence Intervale ore 1 9o016 to 1.50491. 1.60045 te 1.50641 end .9946 te 1.0744

the estimated eeltlolon/mboorptlen neutran removel lifetime a 3.m Ss- * esonds with en estimated standard deviatien of 1.82647

Aug z? 13.8 1#94 file gare i4243ahs eI1AM400-t1rtr-9200-90016 SKY O0 nTa23NEXT LII - Pose t

"121/96 1111061668Z~f4 5.0:6- . version 4e Id111w, C."........ ,>......§ robtel 01141196 111i"6s63EP0i243a sIITP-4245*0

1. farFied CrIeitalcty tu.I%- 4.21 145 MSD/t * 305 l20D t0S W02 M1M&5s)C C llee ali I f t at Vcc . peresity - ref ected *phere

C SELL SPECIAlSITOlN

6. C IUStOE WORLDn- 2 e I ~-9. C $11FAtE SPECIFICATIONS

tc to to 10 a INNER FUEL ROSEt ID12- pool I13- not 40001. t; e f7 1 .o a I g *C 0 I .,C

.14- C 106 oae-a01 390. 16115- C *S- *-to 0 0 - -10 14 I I -15 10 - 1 S e 10 10 IT14- C MATERIAL SPECFI ATIOIt7- * 'o vetil ter in stiae sills lufi e .90 .10 wtl Ul02t9. .1 001.50. .0SS4" 1 0e |' - dla 1023. e Urnim a0topIt. ml 4oo.2 ccgns ri 1 Sli. 1de 230 *se.0904

12000.10. j.A07409.4 1302?.0a I.1840?-321otl:O 190c38,s 1: 34 W000.e 2 4 00.1 5. 1.441203-422- 92234. 1.4443.4 922. lOe Cc* 125 .10.5 2.04 333.523- 92238.50. 2.s7e5s-3 9323.C0. I.715.24- .1 It0t25. FIET

I Initial seuree from file srcretheft results fort Far-fieid Criticality 8tudy * 4.31 145 CM/at 30 51201 n6 Sue2 5i42411) Probld * 8/1/96 1:tf.e9"

thc Initial fiesion neutron source distribution was read from the Cretp f1ie med arcep ."hc oriticalty cprblm was scheduled to 6k:C r _Yls *and run s teta of *7 cyelcc wtith i tily 4000 r rr *"t0 .this problm tas ru e Inertlve eV a "utran iter es VWd 40 active sycles with 239404 neutron Istorles.

this caltuletion has e toted the aqusted - Irr of keof vktles using a total of 3721? fission neutron saurwe histories.sil ccete Wil fisinale coteriat wre sasted nd had fission neutron course points.

the results of the u teat far normality epptlid ts the IndivIdual aellision. aboerptiln. oe track-length koff cyelc vatles epee

the It eltlision) Cycle values spear normally Distributed at the ;5 percent enfi danc: levethe tIoarptant cycle vatues appear normaly Istrbuted at tla n percent cantfdewnc lovalthe RttM lenth eyete vtaes appear ereotly distributed at the 95 porcent oonfidence level

................................................ ...............................................................................................................................

the fin estimated cobined ealelfls nfheorptien/trsck-loneth heff a .U9OU mitk an estimeted standard deviation of .Nt7

the estimated 8. 9f percent koff eanfidenee intervals are .97969 to .98103* .97152 te .98320. and .97r7 to .98397

the estimated eettislen/lbasrption mnutren removal tietite * a7.67-0U seconds with an estimated standard deviatioen f 1.421-D7................................................ .................................................................................

AM 3 1330 1996 Pile EKam: 4243b. se 33000eelli?-0200-50016 REy *0 ATTACUKNEXT L - Pger I

vtreo 4 M W=15,48:98

ltt-1;2 b NTPs14265bO *0-*-*-**-* ........................................... a. sUP.i S ... wprebid a e8u21/s6 MS4u:s1j: P or.ld r.11 sloaits tud - 4.21 /45 6wimt * 301 1120( i5 U02 416245bi

9 i Iti' Ito tTlutt 1. Vate .6 porosity ref acted sphere3- CELL 9PKCIFiCAtEONS

4- 1 S9 AR 16203O- I i T"4531i.2 -1 IKPaE.

6- 1 C ToiDE WOILD7. 3 e I INPIU.C

9- C SURFACE 8112CIFICACTUNSIC- 1* to 3o S INNER FUEL ZONE11-1t- NOOK 5s3- SC=0r %c0o 1. 7 47

14- C Ilc set sets ea *@ o I 53 o05 0 0 -5 10 I610Is* C L -130 -105 .13S .I10 145 8 6 -5 10 -5 16 5 5 5 10 1 171U- C SATER3IL. EPICZFICAIONS17- C 130 volt "a1tr In salles ais tuff) - .6S .1S voet U102i8- a 4.n ,Islas Eneleh nt/ 4 610/MT cad to Ureni Isotopes19- *1 001. De1.7049623 606.5Cc 4.!5nu 2a 11023. Oc 3.87C3n430- 13000. Cc .3738534 1327.5Cc 6.3U07S- 14000. Oc 1.14402

19000.0 so 649- 100.0. 90 4 26000.55. 1.380025.42'2 9223. 3.' 5 A147 St *.327095.5 92236.1Cc 3.s30630-5

92338.50I 3.383S 937. c9.899S73-A

75. PURNTInitial source fre file srctr

lkdff results for Far-Plald CritialKty Study -4.23 14 5MM/at - 1n 120D ISS 152 Ct4245b) prabld * 08/21/96 15.s68;

the Initala fission nautron source distribution was read free the etetp file namd arctp,he 7ritic,,ity prebim bt_ shedu led to ship I eyclsa and run a tatal of 67n aid wits h e neinsuly 4000 nautrsn per cte.this prablem has nom 7 inactive syties with 2139 meutren histories and a0 actiVe eyia" as 1 3ih 39713 feutran RioteIas.

this c"tcutletin h1s etaxted the requested suber of Sell aye la weans a tetal ofa*t cltte lh fiasienable amterilt nre ampled end had fiasien mautran *acris points.

267612 f1eaIsn neutron esurce hiaterlee.

the rrsults of the a teet far nrertaity apptled to the Individual etolliion. abserption, end track-length kbff cycle values ares

the ki etllisien) wale values appear normally distributed *t the 95 percent eenf dance vttthe h abs. rtien} retc vlur a4pear nermalty diltrbuted et the 9S percent eant~dalne oaltthe RItr length) ocnet vaes appear ormally datributed at the 95 per ent sentt dnre te

...................................................................................................................................

the finat astimatsd Ooabined otifilen/abaerptionltrack-leonth ketff .934 with on estimated standard deviation of .01

the estimated N. 9S. A S9 percent haff senfidance intervals t re .99217 to .9479. .noST tod "n. VW 90ooo tK .969

the estimated aottiicintabserptlon neutron rmcoevl lifetiae * 4.68K-S5 *eeonds with an estiaterd standard deviation of 1.63E-47

.................................................................................................................................

Aug 27 lSt2 19 Pllt ENes 14245c.am V AA000000-01"7.200-001& UY 00 £ N7EXN LtI - Page I

| =-*** 4 * *1s.=5*.*.t~~a2 M prebld a *u68n1o21|1961s I

INPai4245a SIJIP.14243c0

fo tr-Fieldit iei titt 1S1uMs* 4.n J45 601mt * 3JO SI20J 2DX U02 (14245U )3: ~ Eli e C Is le lus 1.7u 4 Ieat .306 porosity reflected spher3- C ELL SPeCIPICAIIOES4- C tMEN ifAlt; UNIO03- 1 I .9S s72 -1 -1 EEI4- C 0411902 VI aLD

9 3 t IFACE SPtCIICATICS1C- 1- EO 30 5 33313 FUEL 2011E

13- CCODE 4400 1.714- 9 K1C '' I a lo60.20 60a29 620 toI -3 -IOU8-IS

"4- * 133I -to 'to65 06130 O C 15 ,16 -3 - 5 I o lo16- t NAU73AL SPECIFICATION S

17- £ (30 v~IS ae ia Gmiles, Ni to tuff) a.0 20vei 10s2- * .n1 rilna EnriesUont 45 CUtj7 deaed te Urani stopes

7Oc 9 1 10c °'j123210-i 1l : 000. OcX 90DO. Oc .U 2 4 DODO. Oc. I000.55c 1:298547

5i T2255 o . 1; 93237. .3199355e24- *t r. t25- PlaiT

1 Initial cure i frou f ree etlkeff results fort r-fleld Criticalfty Study 4 4.21 4S OMD/at 301 t201 01O 1102 tU4245c) prebid * 63211 16i23t15

the initial fission neutron seurce disteibution was read free the arcmp file named eretpthe criticality problem was scheduled to skip eycles And run a total of 67 sycls with nominally 4500 neutr" r alo.this problem has run 7 Inactive cycles with rrn neutron histories and 60 active eycies with 211642 neutron steno..

this eulculatlen has templettd the requested mber of koff cycles uasin a total of 247614 fission neutron eourse hiatorles.all tells with fissionable material wmre sampted And dW fission neutron course points.

the result. of the w teat for normality opplied to the Individual ealltmion, eboarptiln, and track-lenth heft aycle valmas are*

the Itcllso) "yVI: Velma appear normally distributed at th. 95 portent emifidence 4javollb: kLabset~)e c apr a per f mkptl on) ec V taes aspea nomelt diatrihutad at the 9 meant ooIene leelthe ttr tngth) aycle Vlua appear normally distributed at the n percent emnfidance tevel

fc final estimated aembined eellielonfabeotptionltrack-tsngth efct a .97J2 with on estimated standard deviation of .60110

the estimated ". 95. & 9 poreant hftf sontidonce intervals are .91332 to .552. .97222 to .97661. and .971r0 to .9 4

Ues estimated falilsenlnabsorpti1n neutron removal lifetime a 3.351-05 seconds with an estimated standard deviatien of 4.401-01..................................................................................................................................

Way 23 10:4Z 199m Fite UNae: 0s02om.m3 *t3A000500-41T1r7-0200-0016 REV 60 AT4A3EWI LKII - Palg 1

laIn esa . dl/1 64/30196 ItsaO51 = . ."tIn~s~d-le1011.3 .. . ........................ . *- --- *probid a 61430194 16*60.32

lP-.3S"se UWTP"3O2mo

I- par-Plot P lro1 ataty 01 - stn W3mmt * 471 320/ 18.5% uOZ *. 2e. C tca lec Bllts TM f l U 5ce .47 porosity sphere aurrend by tutf

S3 C CELL SPIECiFJICAIC5 tC lIVNER ATER "at1o1S. 1 1.74149-1 -1 I37.3.16- It 3 5.61040- 1 .3 [Krivoi7 O 10T IDN OLUNa a a eR7,1.09.

10W C URFACE SPECIFICAThONStl- I 8017 S0 5 IER FUEL OtE1t2 3a to It e I1I FUEL 2ONE1S-14- 'N0I U15- SSCE 4000 1. Is 518* C cslC ; 3|1 6610 6 6e * 30 6 26 23015 n * 5 -10 e e40

17- C -*So -*o *30 Is -13e -S 40 e -35 .30 -15 *S 5 5 610 3017le C RlatIAL 9PEC1 ICATIOUS19. a £47vtZ Nso nsl. In I Its luff x .815 18.5 v.11 y0232- e 3.61 Original 2arlehoetl ZO 300/1 decye d to Ursnls ,sstsooIto .t aor, St.X e ^0l2 a l2 ~el.lt |^ 8¢g"^4*i l~o81001.1Cc .56121- 1. 4.315845 t11023.15c t.634544

2s e. 1.la5t sZ3 O - 4000.5Cc 6.311662.3

35- 9323S8e.1 4.4C6443 s 3237.5oc 5.646015-826- stl tutr.Slt27- * Jo .wSt:rIn aleesIllttuf38- .2 1001 0. 3 424792 61 * c 4 0 11023.50c 3.4YM?-4772v. 13oo100. : 3.842960-4 13027.50c 3.302817-3 14000.5UO c 1.607su30- 1D00u.5c 4.91511-4 30000.50c 5.630511-4 26000.55. 1.3989-431. eta lutr.ol132- PsaiTI Initial source fr.. file, oft 3 W. 7 30 85 J2(320 poi 43/41:03

Ikcff rosultt fart For-faiold CrIticalfty 82.dy 38 10WO nRwimsoCM ae ob a 431 860z

the initial fission nautron source distribution Mas read frau the sretp file nesed spetp . .the sritisslity problam was schodutad to skit asou;ss awe run a Mtoa of 75 ancles with nominally 4000 neutrons prccethis problem has run 35 Inactive aycles sit I VT nautron histories and IS eclivo Cycles with 194M neutron histories.

this .sleulatisn fias ssilted the rsquatatod nmmbor of Neff eycles, vsins a total of 399773 fission neutron source histories.Olt celts with fiessioabl material Mar. coupled and bad fi ssion neutron asurso points.

the results of the m tast for normality applied to the individual sollision. absorption, and treck-longth kaff sOnto values are:

the lit sotlelson) oycte valurn appear normally distributed at the 95 porcent sonflilencot levelthen ksbaorptlon) s"el: values appear normally distrihutod at the 95 prcant confidence levalthe h(trk lentih) sycl values appear normally distributed at the9 prsont confidence loyel

~the finaL astimated soobined kelaolbspio/ro~ogh3f f a .973170 with an estimated standard deviation of .80143

Nay 23 toag 1W9 UII f le o. Is s *00oZ waaeS lBO S1?S2 1 IRV So ATIALIMMIT LX11 Page I

the estimated 48, 95, & 99 Poreoft hoff Oonfidance intervals SPS .97726 to .93014. .97182 to ."I",9 and .97448 to .taS I

th t estmted cotleftin/absorption autt~n remval lifetidi a 7.341-S5 socanda with en stestomtd standard deviation of 3.91o-S7

May 23 IW4o 1996 file lame: o3izond.smm 35A00v0 so 61 200-00016 SEW 6o *ACUIENT Llt! - P ose 1

lecnr ldulfersn e I1019 3 tW26/96 tU3S2257

-.- 5ecee~O~eseses~eeer Wee5 prebid m 04/26/96 1l1112.57ISP-s3020d OUTF daO2 dO

1. for-field CriticalIty 6tu * 3.1S /20 61W0Dst - *7S 1120/ 1.3S U02 1aO2ac25 C Caei Sfilles TV f I.33 I /cc .U porosity sphere surrounded by tuWf3- C UCEL SPECISICAIOX14. C "malt1 WAT9REGION301S 1 0 S.4i49, -I 3NPs3.6- 2 2 6.610406-3 1 -2 IFsIb

?- U~~StSISE MIIOI

11 C0 61 * IRWIS FUEL 20XEa3 tO 121 * INERS FUEL ZOE

14 NMIE I15- 1000 4000 1. 25 7516 : C £530 1; @610I a I 0 e.0 6 62 a? I t0 iS 6 6 5 -10 6 40I7 C 50 -20 -30 13 e -10 6 0 .25 u30 .1S *S3 S a lo 30 7T18- C IA7E2Ml. SPECIFICATIONS19- 147 vt ig w ater In matlee lilts tuft) a .t15 16.3 vnlS U0230 .s riginal Inrichment/ t0 Co/mYOl de' oed to uranium toetepas21 *1 1001.50c 2.36113 6016.50. 4.21 5-I 11023.10. 2.63405 -422- 12000.S~c 1.650134 13027.50. 1.76796- 14000U.S0 1.62-3PI- 19000.50c 4.002067-4 P20o000.Sc 4.0119964 26000.55. 1.610513-4

92234.30° 1.05 '916 92235. C0 1.6459755 92236.30c c.11"674-525: 922 D.50 4.406469-3 93237.50c, 5.646015-626- all lrtr.6lt27- a 30 weIt water In calleo mll t tuf23W .2 1001.30c 3.142429-2 8016.10c 4.043067 11023.50c 3.47367-429 12000.50 2.t42960-4 13027.50.c 2302017.3 14000.10c 1.6075"6.230- 1SOO ~c .t@Sl4ZOOO.~c%.9000.50. 4.9010511-4 20000.30 0I1 2 .31 t- 2 tutr.olt32- Valli

I Initial source frem file fit'Ikeff results fari ear-Filel CrItIsl1 ty ttudy - 3.61 /20 6D /mt - 471 X20/ l13.3 SS 2 (.020.c) prebed a t4n26/96 16,S23S7

the initial fisslen nautren seurce distribution was read free the aretp file named eretpthe crit iality problem was ocheduled to skit 25 ccls and ram a tettl of Sey el wilth nominally 4000 reutrane per cycle.this problem has run 25 inactive cycles wit 100232 neutron histerle and 50 activw eyele with 199265 neutron h stories.

this calculation has topleted the requeted number of kaft cycles using a total of 299497 fission neutron source hieterles.all cells with fissalnable materiel were sxpled and had fles in neutron source palate.

the results of the w test for normelity applied to the individual collislen. absorption. nd track-ltngtb Ruff cycle values aret

the tt collisien) cyce values appear normally distributod at the 95 percent centidence leVelthle ttebeorptlen cye, values pear nrasml y dletr buted at the 95 percent centidence lVesthe kltrk tlngth) cyce Vals appear Normal y distr buted a* th 9S Percent senfidenco level

...................................................................................................................................

|the final witimated ee bblmd *oltiilnftbsorption/track-tength koff * .n 96 withB an estilsted *tendard deviattln *f .tO1S?

Nay 23 tO:4@ I9 Pit* Samet *302*md.gium BIRADOoOVOO-SI71 o-*20.S0 LIV SO ATTACKNEIN LXIII * tvag U

the eastluted 68. 9. £, II percent kiff eanfidanea Intervals are .99359 to *9904. .992 to .""I.1 and *99129 to ."

Ithe estimated eeltilon/aebsorptlen ueutro Ponevat Lifetime a 6.9161-95 seconds vith an estimated standard devietien of 3.581-S7I

kI

May 23 10.37 1996 Flte *N_: s3O20sb. AOOOOO R1n7V 020D ODI REV eo ATtACIMENT LXIV Page 1

imc .jersion 4& t-d10101I93 64126/96 17: 10b56prebid a 64/26/9 I'iT.135Iht-dDO2D b etTy-dD2D mbD

1- for-Field Critiesti 6-I /2D no ut *Swin - 20J U .55 U02 *302Oebl2- t COalic li sl tM f tI 7 V" .47 persity sphere surrounded by tuft3- 5 CELL SPECIFICA11011S4- C tINER WATER R11101

5- 1 ~~~~1 6.3741494 1 IUlu*- ~ ~~ ~~ tI Itii tiNQtst

r- 2 2 6.611106-7 1 -2 369.3.1O UTSIDEWOL

10- t SURFACE SPECIFICATIONSI1- I to 70 S t3DEt FUEL ZONE

12. 2 to 130 t IUeER FUEL ZONEis-14- awlE U15s- 1K0 4000 1. Is is16- C IntRC I I *I o 0 6 -20 0I 29 e 201S 06 . 55 -10 * -40IT- C S -50-2 0 1 0 -10 o I O -25 30 15 *56t S 5O la S 17IS- C NATERIAL IPEHIFSCAIIONS19- a 4 , ter In 84ico Iug touf) . .315 16.5 v tt 8O220- c 5.0 originat Serichoont/ 0 D/UT d Ureant i Isototes

1- tu 1001.o Oc S61121 los c~^Sc 4 1S" $C12 D 2.8DSW4-Deo.1hI6 Oe 12-f 13027:5Cc 1791 T e00 CM 8.11i642 3

1900.50. O4.60Z67-4 20000 c 4. .9 46-4 26000. Ic 34PI4 92234.50c 1.Ol5591.6 9223S.S0e t.6t975S 9223 6D. 2.:164-5aS tHt2SL.54c 4.406469-3 93237.50 5.648015-626 t tl lutr.@lt27. * 30 Ta tat lttcC lle UItjo tUtu23- .2 lD01.S0e .1U *2 001. c /.. 3067-3 11023.50. 3.477367-429- 12000.0. 8.642960-4 13027.3c f.302317.3 16000.50.c 1.607956230 19000.50c 4.910511-4 2000.OOc O .30511-4 26000o.5c 1.239894 431- att lutr.Slt32- PRINT

initial source free fitl ertetty Study * 3.pt n GM/at n tl2D lt StJ2 ( probld a tJ26J9 1731246tkeft results fort for-Field Cr1 ticetySdy-36 2610t 67 211.160CeOmbp-eie 140/67a:S

tho Initial *issic n neutron eource distribution wse resd free the erctp file arned *rctpthe criticelity problee was sceeduled to ski p 25 eyle and arn a tetal of n actes with ninslly 4000 neutrons rr oeyclthis problee has run 25 inctive "etles with 100201 neutron histories end 50 active cycles with 199091 neutron sltoIeas.

this eelculetin hes ceopleted the requsted mbor of hetf ylets using a total of 299292 fiesion neutron source histories.aIt colts with fissionable Material were saepled and had flesen neutron source Points.

the results of the u test for normality applied to the Individuel collision. absorption. nd track-length kot cycle values ores

the hX coilelisin cycl vslue eppecr normoaty distributed at the 95 Pereent confidence levelthe hsbetxorptlen) yc wslhsue: appot normally 1ditrbuted at the 95 percent sent idence tentthe kitrk Length) cycle ia Me ppear normally distr buted et the percent eontidence toeel

.............................................f.....................................................................................I tbo f net *stlmted ee btwet oettialan/aosrptlettrack2 teneth k20tf * 1.012021 ulth an eetinaetd standard dviteton of .oonS8 I

may 2 1Cs37 199 Pit Masa i 02ob.ioum BREVtO@Ohi uov 09 ATTACKINT LXIV * Pass 3

Ii. estImated 63 95. & 99 percent kff cenfidence IntervI are 1.01862 to 1.02179. I.61 to I.-233S. .nd V .W 91 tts toIJ 4

llte estimated sellstjwrabaorptlen neutren regave Itfetla * 6.3819E9 eaeeda with an astimted standard devlstien of LST.17|..................................................................................................................................

May 23 10012 I96 fIle Nam: eO20m.sum 32A00oo0o-0171740200-00016 KEW eo ATTA3ENIT LXV Pagte 1

.==*-**-----m -- -- version --- Id--01- " 1prebid * P1626/ 16,36:62

11"32OaS UTPaa3020Ca0

l- fer-Field Criticallt *tudv -3.6 /30 GO/at *r7 20/ 1S.5S 1102 (3.020ma)2- C Cal1co lit TMu I1.1 i V7g .67 porosity - sphere surrmuded by tuft

CEULL SPECiPICITtCUSI e I33f WATER RIElol

5 1 11.374141:2 *1 IOP.s1a6. 2 016402 1 t ia I17- C GUISIOI WORLDS. 3 9 a 90M~.8

13- 2IA- "ODEis: COCE 4000 1. tS 75Is- C ESRC 061 6 6 I @ .20 939 62015 I e -55 10- 40r7- C I -50 D -s1 5 e le0 * * 0 25 IS -SS S5 6 10 30 171S- C MATERIAL SPECIFICATIOSC19- c t4J wolN water In ealle. Bill, tuft) r .t15 11.5 veN UD0230- a h.6 rignal gnrlcbantl 20 60/NT decayed to Uranim isotoesII- al 100O4Cc t.561121-2 016.S1c 4.315 45-3 11023.50c .34054 422- 12t0t.SCc 1 .tUS02-1 5027.5Oc 1. 76796-3 14000.5Cc .21162-3U2 lawote4¢a506T^ 2~oS ¢ sg .62 T 1: tr23- 19000.5Cc 6.602067-6 30000.5Cc 6.699866-4 26000.15: 1.110513-6264- 912234.15Cc 1.015591-6 92023S.5Cc 1.565975-5 92236.5Cc 2.116474-512S- 9223.50c 4.40619-3 93237.5Cc 1.645i5-626- .nl lncr.;1t27- a 30 votE aoter in calico slills tuff

2S- .2 1001.50c 3.162679-3 3016.50 c .063o67-2 11023.soc 36.7n67.6g- ttotsee U296-4 1027.50c SZSI3 S 4000.1Oc 1.007566-2

30- 110o00tJSoc 1: 1S11-4 20000.50c 5.B30511-4 26000.5c I.2RM9 4-3ii eta lutr.Olt32- P313

initial awrce frau file oretekaff results fars Far-PlaLd Criticality Study - s.n /210 6a/. - 6*n nor/ 1S.53 Uo2 (03020ma) prebid * a 4n6/6 16:36s62

the Initial fassen neutron eoure. ditributlan uws read fram the eretp file aed arcetpthe ariticality probl. wass scheduled to skitp 5 eIS let end rw * a tota of a sle with nominally 6000 a tr per cycle.thle problem has run 2S Inactive "tcles with 100226 neutron hlatariand a e aycls with 199837 neutran histries.

this aelculmtiln has ecopleted the requrcted r eo half cycles waIn a tetal af 300063 fIsslon neutron source histories.aIt aella with fissionable material were apled and bad fiesson neutron source peints.

the reaulte of the u test for normality applied ts the individual cellielon, absorption, and treck-length hoff cycle values are:

the k( eallielon) cycle values appear normally dltributed at the 95 percent confidence levelthe ktabaorption) cytle values appear rctmally distributed at the 95 percent confidence levelthe kttrt length) yec valusa appear normally distributed at the 95 percent confidence level

................................. .................................................................................................

I the flmat *etlsted cobin d oettlelonlabscrptlntracktanlth Raft - 1.028" wlti an e tl-aetd *tendard dt~evitl of .St119 |

May 23 13.13 1996 FiI.laetos *3020".avm 3AUOOg7-SCSO1 Iv~ go ATTACmIWIT tv * page I

the eatimated 688 95, & 99 percent kaff confidence intervals eF* 1.02M7 tO 1.03013, 1.02660 te, 1.63i38. and LongoS to 1.132131the estimated celttislnlabsorpttifn neutron removat lifetime a 685.0535 ascends Hith an estimated standard Devlotiot. of 2.611.S7 I

Ray 33 10:1 194 PFtie Nea: B3O20o.sue UACCO O l-017`1-0200-00016 REV 60 S TTACKIERT &XVI - Page 1

version 4e ldloo/01j93 .5/03196 16393124* --e- - *-e-e--*eee~e~eeeee~eeeeesee..ee~e~eeeeee~eseeeeeetee-e* ee-se e prebid a 05/03/94 l64:9s24r-PuS302o @1eTFsSC2OoaO

1. Far-1leW Critteetity ISty - L.n /tO to0/at * 40X 1120N in1 U02 u e32Ooe)t- C al Ie ltl suff 1.V095 ice .40 porosity sphere surrctmded by tuff5* C CELL IPECIFICT I NON

10- a tsa 1e4019, ,lult 1e :1t4- C TSIDIE VO tILE 61*14. 3 3 5.2301- 1- lam

70-10 51113ACE SPECtIUTICATSO

I1 50 40 S 310E3 FUEL ZONEI2. 3 so 120 S INNER FUEL ZONE'3.14 PDDE U15- eOWE 400t 1 40 340

14- C 1530 ISI 0610 61.20 0539 0305 0S117 tC 0-c,5 iAe !*I0U-13.10 go-114 I 0 5 ,1 5.10 .5 15 5010 a IT1S- C MATERIAL SPIECIFICATION19- a v40 tl voter In calls. lto tuff) N .13 IT woat U0230- e .63 SJX Orlet £nrlchaent/ tO 10/Il e W TDed .t Urenium leott

21. m 100.50.f~lafl,: 0t.04 a 1U. 1it23j.0c114n- *t B~l.S~ .t197 U!". ae *.tO"- 3 lC43 HIM ~l32. 12000.50e 7 5611 1 I23- 190D00.50 4.14027-4 30000.5. 4.72467324 26000.55e 1.145032-424. 92234.50. 9.975705?- 92235.0c 6.123754-5 92236.50c 1.945052525. 92238.50c 4.049185 93 237.10. 4.48717-34. Ontt lutr.Iit27. a 40 vole water In calico ittte tuft35t *2 1001.50c 2.476450-3 W014.50c 4.1511S2-2 11023.50c 3.966t414

29 12000.50a 3 1275-4 1527.50. 3.406963.3 14000. 1.140641-t10. 19000.50c 5.159069-4 30000t.50 5.449163 63t000.554 1.453-431- ;S2 utr.41t32- PRINTI initial source from file rstat

hteff results Feur for-Field Criticetlty Study . no 1mt * os 0 - 4021201 173 11 02 0oe) prebld a 0l1C3/U 14329i24

the Initlil fleslsn neutron sourse dietribution us recd from the crtp fitse named eretpthe ert teellty problem wee scheduled te skip 40 celesend rVPn a total of 240 etlee wulth n nalty 4000 neutrons pr cycle.this problem has rn 40 Inactive cycles with 14015 neutron hietories end t00 ective yectle with S01227 neutron nteterle.

this celculetten has completed the roqcSted rIbr of heff cycles ustne a total of 961642 fissiun neutron source histories.sit cells wtth flelenabte materiet were sampled end had fisesen neutron source points.

the resulte st tthe teat fur normelity applied to the Individual collision absorpetoen. nd trach-longth heft cycle velwcs are:

the hl eeltlelon) cycle valwus appear normally dietributod at the 93 percent confidence lelthe h ebeorpt1in) cycle welues appear norma-lly strbeu d *t the 95 percent onfidene tlevthe h ti length) yle velee aW er rem lly distl buted at the 95 percent oonftidnce level

. ................................................................................ w.................................................

|the tint l *tlmted cobin d setfll~elser/pti nttr ct leretb kaff - .9534 withl an stlmat d stadrd deviation of .soon l

my23 103S1 19M File smog 632"o.an Rtz:e 1~r|0-X EY 00 AlTAtCKIET UXI - * cc I

the estimated is. 95, & he percent koff confidecne Interingt are .9s.72 to .955ISS, .ff4s1 to .n5er; And .nss4 to .nm7' I

I the cstlmated votticion/cbsorption mautt root r tov l fcttze * 9.0lc S escccnds with an rst1"ted stcrdard devirticn of 1. u9-c I

......................................................... 1......................................;....................................

Nay 23 1053 1996 file Cames e3020eb.sue S1ADOOODO-0tI-0200-000I6 IEt *0 AITACSNET LIVII Pegs I

1ecne veelen 1.5 1d.41010S 3 6S/031956 194601'" e*"e*eeeee ***e-e--e l probid S/03/94 191.6.17IN;s30200b QeUTta3O2OobO

1- Fer-1ele grl:ieelltvaadyS - 3.0Z /20 11Dmt * i40 320/ IXZ W02 (.3020Db)3. C Calleo Nitltl Tut 1.5 S tsee .40 porosity sphere eurreunded by tuft35 C CELL SPtECIICATICON4. C 13131 WAT1R RlICO*- | 1 i.23774-2 *1 ln~rnu.1

- Z 2 1.423019.2 1 -2 iMPu31s7- C OJT13111 1OILO* 3 Z ltSP*U09

10 C UtFACE 3PICIFICuTIlS 211 I " US 425333 FtUEL 2053

12 a tO 125 * 33333 FU L 201E13-

15: 1000 4000 1. 40 240165 C In1cI0 I toe so a: 00 020 0 29 3ICSa 00 5 -100 -10IT: C a -5 -20 .0IOS.13 a-10 14 00a.15 10 .5 1 5 5 Ia10 I?is t SATitAL 1 PCIFCAT IONS1t e (10 Volt vater IF calle Nils tfta a .83 17 vel W0220- * 1 Oarigal Snritiant/ 20C d0ifT ecaned te uraniu iote21. II 001 o. c 2.219 -2 0015.5Cc 4.23236 211023.5Cc 3.371.11-.22- 12000100.5C .15 113270 .577 d 11000.5Cc 9.46573I7.323 19000.5Cc 4.514027.4 20000.5 026.5 2 .1 24000.65e 1 . '11032-434. 92234.5Cc 9.9750. 2251c6.2745 92235.11Cc 1.944052.5

92233.58c 4.3491314 93235 7.c *4.3817-5NMItl utr.it

2 . ~~~40 vet& aster fen gaffe lIsuf2' *2 ° t1001 .5Cc 2.571"450-32 180615c4.'158162.2 11023.5Cc 31.51641-4

29- 12000.10. 2.3273.1 13027.5Cc 12.506963.3 14000.5Cc 1.140641.2308 hieT 19000C 5.559069.4 20000.5JC 52594918t4 26000.ssc 1.403653.4

_1 K l2tr.01t

I Initial sursg frt. file tr a 4 * 20/ 1TZ 1t02 CeSOlOob) prebid * 05/03/6 191.:1Iheft results fern: for-Field Grit eel ty study - 3.0l ISO 1*101/mt17 O C32eb rbe 313%It40

the Initial fission neutren eource distributien was read frm the *retp file nad sretpthe eriticality problem wag schoduled to skip 40 sycles and run a total of 240 cycles With omInally 4300 neutrens Pr cycle.thie problem hts run 40 inactive cycles with 150174 neutren histories and 200 active eyclee wlth 793926 neutron hlsteries.

this eLculeotien has eueleted the requested tuber ef teft acles using a tetel ef 959100 fissioen neutron euree hieterlie.ell eelts with fisslenab e materiel ure seepted and hsd tles en neutron seuree pointe.

warning, there appcare te be deoreasine trend In tFe average etlaebartl toff estimator ever the lost 10 active crles.the results of the u test fer normality applied te the Indlviuslt collisein, oberptlien, end track-length keft cycle veluas ret

the kC esellilen) eycle valims eppear normatty dtitrlbuted at the 95 percent aenfjdence levelthe k(ebsorpti en eycle vlues appear normally istributed at the 95 peent aent dence levelthe kttrk length) ccle valve eppear normally distributed at the 95 pereent centf dnce level

I the final e*timated eeobbied eelitlenrabsorptieen/trace-lengt, betf * .'ru uhit an estimated *andard de vatlen of .069 |

Nay 23 IM,3 1996 MUIIsKmat sW2Cb.smm £IU0000004fl1?.S20O-S0014 REV SO ATTAUMENET LXVII * Page I

the: estimated ", 93, & "perbenlt kaff cmflgunc. itflrvmls are M979 to .97538. .97331 tat .97607. and *97286 to .97652theasimte cllsinlbsrptenmuro mva lfeim a7.9C 03seons ft a etimte sa.55 dvitln f ?

may 13 tiMS 1 n file Nome: 35Z200Cc.eum REV Co AtTAZCNEEI LVUSII * Pase I

I" version 6. id.10/01I93 63/03 196 22323:22200*.***.rtl.*n** td 17tl95 ***-*--*-****- s!5=*21 S2*2prebid * 65303/96 22:25:22

INPaeO20c:c GUTPna3Ze

3. Far.P f 6rFel! CrilllalUsit 3.#1 120 goiat * 60% 320/ 173 102 (0320cc)C at ceKitts t t .S S gee .40 porosity - sphere surrouded by tuft

- e CELL SFEc10 0ATSISe4 e INtNtER ATER REGiON5- 1 1 8.2 m a77- -1 OWPK-t6- t It 8.L3019 Z 1 -t :uPIN-1

e0- S SURFACE SPECIFICATIOKS11- ¶ 10 70 SIUIErFuELCRE12- I t3 1o 0 T uitaR FuEL lent14. IIE 11r4 aw o-s 2 o ws-es cs 1 ss ll15. D10R 4000 1 40 3406: C sic 6@ @61 a0 IC 0-'30t a3 620Ito5 06-5 .10 .1017. C a -5 20 -10 I.136- 10 16690 -I-10 -5-1 5 5 6 l o17011t- C MATERIAL SPECSFICATlE0NIF- a (60 veit waetr in gealifoKl tuft) ..63 1? WI U502

20- c 3.62~e C191noa Enriehen MUD/U deceyed to Uiraniumigte2l~~ ~~~~ 1 I t5474a-8s8t**6dso"~ec§l4421- El 1001.3c 3.r06 I~ 2336.; 11023.1Cc .l~

22- 1200.3c 1 7. Oc t. 6379 14000. Sc . n23- 19000.1Cc 4.61027-6 00.50c 6.n26 2- 36000.55C 1.165032-424- 92234.5Cc 9.973707 I223.5Cc 9.12873 -5*2236.50c 1.93505245ns. *2230. 4.0491381- 93237.5Cc 4.4 3 .II: ati wr2y e t40' Iti6 S te 1cr In calls* Sitl tluff51- 10IGO Go 2.674450-2 8016.5Cc 4.153162-2 11023.5Cc; 3.934441-4

29. 12000 Cc 2. IS-4 13027.5c 3.606963-3 14000.5c 1.16041-230- 19000 .5Dc 5.539069-4 3t0000Cc 5.694916-6 26000.13c 1.603613-3S1 atz iwtr.olt32. PRINTI .n2t11 source from file rt

Staff rmsultl ftor far-Field GCrlit Ieeity Study - 31.5 /20 S o 0A/t 4s01 2zo/ 173 1002 U .3020cc) probid * S1303196 22s23

the Initial flssion meutron enure. dlstribution wes read from the *rstp file named orctpthe criticality problm wee schedutld to ekim 40 cctes nd rim a total of 2U0 crcls ulith sceinay 4000 nfutrmn cr cycle.this prebleo has run 40 Inactiv, eele t with9 15913 neutron hietorlee tnd ISC aetive cycles with 60036 noutron alaterle.

this calculation hs completed the requested nmber o kefft cycles using a total of 960277 fisslon neutron source histsries.It colla with tisoatl aerlel wre eampted end had fitsion neutren sourtr points.

the results of the u test fer normality applied to the Individual eolilsien, abserptien. end track-length htff cycle values eres

the It collison ) ycle values appear normally distributed at the 95 percent eenftince levelthe ktaterptmn) syee vauces appear normally distributed at the 95 psreent confidence levelthe kttrt le "Lth) values "pear normally distributed at the 95 percent confidance level

................... n................................e...ine. .eiiie.en.....r.......sck-....t h.t..7.ite.ainldsa rd eiaon f.0007

| the fincl estleoted soublisd sollileln/asorptin/track-leth t ttf - .nn72 with an ectinct d stadrd deviation of .100o4 1

MY g3 USIS: 1996 PIt. Ameee. uiO200C.GUi StAee0c-S117.7-1o200-S016 UV SO £TTAUNEUT ielltt - Pog. a

the aetivated 68, 9, 9 9 percent keff confidence intervals Ste .9863? to .98806u .955r3 to .MU , and .98535 to .9SM I

the estimated eollieien/absorption neutron removl lifetim, * T.AlE-85 Seconds with an estimated Standard deviation ef t.?4t.O?

................................................ ............ ...................................................... ....... ......... . ........

May 2S 1I5 t996 IIto lose: cSOZood.ean K3AOOOOCC-0?1T60200-00014 UEV e0 ATTACKIEKT LIx - Page 1

ltac version 4e td-101J/V93 6S304/96 101ttO:16*- *-**** **** --- * *--* *---*** .- plr bed * 5/0419 41 4061

I P-3S02tod GUTP-s1c020odO

1. ter-Field tri e St udy- 3.6n /20 6IWO/at * 40S 0201 17 1102 (ASO28d)2. C iticeEs I a *I 1.5 5 f) c .40 porosity - sphere surrounded by tuff3. C CELL SPICIF CATIRnS4. C INttl WATER 19301203*.- I I 1.2=7741 2 a 111Pag-:- 3 3 S 423019- 1 -3 INUK.

OUTSIDE WIRLD' * 2 te10W t BURFACE SPECIFICATIONSii. I *o n5 $ INNER FULL 30Y11a 2 tO 135 S InttE FUEL awlE13.14- 11001 K1. loosE 4000 .40,34010- C WC C_';a123 6 O lt 0 29 0'0 0 ' '. 10' 101?- C * .5 20 .t@ a *13 0 -to I I5 -i -S -i0 I 5 0 l to trIIS- C. MATERIAL 2PEtlFICATIONIa19- e t40 e1l noter In eellce ill, tuff) * .S lt 2U0220. a 3."0 Origina Inriesmnt 20 "DI0N3T deced ts Uranium iestsp21- *1 c001.5Cc 2.219794j 6010.51c 4.262136 11023.S9c S.UT41r24#-. 12000.$0cl .919511 183027.51c 2.163779 14000.1Cc .447317-32S- 1900.co c I .4eZT4 e00C.1Oe 44 782-' 3oe.5sc t.16S4532424- 92234 SOc 9.9TS7057 92235. O . 27341 5 .5c 1.945052-52S- 92233.1Cc 4.4916 S3 93237.50c 4.371-636- .11 iwtr.Olt3? a 40 v.t3 water in smRie Oillie tuft23. e2 10el1.1C 2.6744so-2 6010.Cc4.'15"62.3 11023.1C0c 3.96041-429- 12000.eoc 2.3127.4 13027.50c 2.09033 14000.10. 1.140641-23SO 19000.5Cc 1.559069-4 20000.5D c .0694914-4 26000.15. 1.403633-431. etta ltr.0lt32. PRINTI initial source fuss file art

lkeff results fort For-Field Criticalfty Study - 3.0S Se0 W/sit . 403 t20/ 173 U102 (.3O20od) prebid * 15)04/96 01.80010

the Initial fission neutron *suree distributien wus read from the aretp file I n d *retpthe riti cality problem was scheduled to skis 40 ercle and run a total of 40 cycles with nominally 4000 neutrons pr *ctthis proble has run 40 Inalctves cycles mlk 140073 ntutren histerie snd 300 o ctive system with 799513 neutron tlstories.

this eelculation has cmp teted the requested nmber of haff e usinR a total of 959591 fission neutron eeurce histories.sll cells with fiesionable *ateribl wore sampled End had fitFn n eutron souree points.

the results of the test for normality applied to the individual collision, obsorptien, and treck-length half cycle values ores

the hi sollision) eycle values appear normally dtstributed at the 95 percent confidence levelthe k(aserptisn) ycle values appear normally dIstlbuted at the 95 pereent onfildence lovilthe kitet toth) syc l values appear rnrmalty dEstrbuted at the IS percent ;inf idenc leVs

the final estimated seebinod *ettlieionlbserptiontrsck-tenUth kaft * .n9ss5 with an estimated standard devlatfot of .010072

Nay 23 11:65 1M6 FitU EN.: s3OZOd.em K3UOOOOtS117.2t-6OO6 REV 68 ATTACEXT LUXl *Pabe I

the estimated F,, 93. I 9 pertn t keff eonfidence Intervets are .97" to .19927. .9711 to .9M99, and .164 to 1.8046 |

the estimated eolliseion/asorptien neutron removat lifeti.e a 68.7165 secends with an estimated standard deviation of 1.63E 4

.......................................................... !...................................... !...................................

May 23 11i6 1596 Fite Noe: a30o2cs.esu 3ACGOCCO-0171?-0200-S001A REV SC e TTAC1C1T LII * Peos I

Ceersin 4 I =...e 93 !o.e..ea.. . 7 O * 4/96 633703a0

imP.e3020 WuTPes320o"

1- fer-Field Crileaityi Stu S - S.ta /20 Wlu/t 401 120/ In U02 .3020e.)2- C ctale a Ilt gm f I.S095 Vec .40 poresity phere surreunded by tuff3- C CELL SPECIFICAeIIIS6- C INNtE YATet REG12N

I 1 W t:267174 !I IIP.%Nl@ 2 X $.a423019- 1 *t Ill I

10- C SURFACE 8PECIFICATIONS11. 1 ee s0 I IIER FUlEL 23E12 a 2 so 140 S IYYEt uWL ZD03C13..46. NMCI 3Is; C00DE 4o00 1. 40 24016- C 353C 0e1 a00o 00-20 a 09 205 00-5 10 6-1017- C e -5 *20 -10 0 -13 O 10 14* 0 -1510 S -16 5 5 10 10 1718- C MATERIAL SPECIFICATIONS19- e 60 volt mter In eatlee itta Cuff) e .a3 17 vot U0220 ' 2.01 Original Enrichment/ 20 3WD/R decayed to tiranim lsotepesEl- dl 10.5c 2.2197V4-2 U016.c 4.a52336 102"J50c 3 26741-46

12000.4c 1.919611.4 13027.5Cc 2 3.coo7- 4000. S 497317-3I a00 0Cc n.61r027.6 3000.1c 6.726732.8 2o000.55c 1.165032-4

2: 922 35Cc 9.97S 5707 m2233.5Cc 0.128734.5 92234.3Sc 1.945052-592232.5Cc 4.069138-3 93237.S5c 6.638717-6

26 gl tuttr. It2J- e 40 veot water In sattes D Cutf

28- At 1801.50a 2.0"5s0 2 80s &*l162. . c3.6X-ts IW~~200 *Oc 1.1127J5 4 lsn.o0 2 0*U 14 00D5cl"~r1- 12 t9000.Cc

Ott*~ lmrtf.elt1 fnitial ccuree frem file aretDlkeff results for: For-Field Criticller ty ttudy - 3.61 /0 Sublat - 61 120/ 1T S02 (3020oe) prebid * 0 4/0/96 03:37:02

the InItlat f issen nutron source distrlbution ass read frem the rep fie named *artpthe rit salty proilm mae scheduled to skip *0 eyclie nd run a tetal of U40 eyclsa with petty rD0 nrutre r ,ctethis preblem has run 40 Inactive eycles with 160532 neutron histories and N00 active y"eIs with 799503 neutron I I res.

this *alculetion hsi e teoted the requested mumer *f teff eyelea using a total tf 960035 fiesion neutron source histoeree,all sell witil fiIslenabte material wire seapled and had fission neutren seurce olnte.

the resultc of them lost far normality applied to the Indiv1dual eolliien, "eorptien, nd track-langth I off cycle values ore:

the kg etlleis n) ece, ve wmee appear norealir distributed at the 95 percent *enfidanee levelthe kbserptionl cycte vein s appear normally distbtd tt the 99 pere nt sefidnca ltvet but net at 93 percentthe Istrk length) eycte values appear normctly distrbuted at the 9 prcnt sntidence ae

...................................................................................................................................| the fine st * ate~td cobin d cetttet o Jebcerption/tract engtk tett * 1.eloJ with an ostlted *tndrd d vrtct{ o f .eoore I

l

KEY 23 tt.U6 WAt Fite 119e, e3Ot2ee6eiM REOOO-*?76OO@t i 60 ATACUNEET INK h ae 2

the: esleu cattleonab/~eptIlin aeuran recant tifeti~.JiSmea .11 scnds with. an estimmted standlard Ud avlagenof

Nay 23 118 1996 Fils Names 3020of.eum SgEWOOOOtO-1 .200-314 R 00 ATTACKNEXT LXXI - page I

In version *a ldWl01193 6504196 06,06:23.. sse. ee.. e. *- p esee*Oeee --- a -- -*s praobid * 05111"94 tt16.2s3

IX-es30200t WtPc3020ofe

*- For-Fitld CrIl eettj Stu - .* 120 * SI/mt - 40x 2za/ in U02 tS30200f)2. 8 t tlle a it Tu t 1.5 geao *40 porosity Sphere eurraunded by tuff4- C SELL SPECIFICATIONS4. C trUEK VATER S1l1095- .2Xm- 1 -1 IKPI

10 C StURFACE *PECIFICAT20uS11- 1 to es a IPIER FUEL ZONE12 2 XO 145 * 1IXER UEL 205t

14 ME b15. 0801DE 4000 1 40 240t76 t eiC iS I 1 0a e a I .20 aU 2 0 20 5 0 -5 5 e 100lrIT C 0 .5-.20 -I0a-is a-la14 a I-is -10-3-.16 IC1so0ITI5 C RATERIAL BDECIPICAIIES19 t a40 valic ater in settee Sillt tuff) x .e3 IT vets Ul0220 e 3.05 prigunal Enrilehent/ 10 MDIMT decaed to Uraniua m atepoc21t *2 1001.30.r 2.34"19794-2 0014&. 0c 4.132386.3 1023.50 3.741*2I 12000.50c 1.0196114 13027.SOc 2.163779-3 1400.0 9.46731-223- 19000.10. 4.6140274 20000.50c -.736722-4 26000.15. 1.165032-424- 92234.50. 9.973705-7 9223.510. 5.12573-5 92236.3C 1.945052.52a- 92238. 50. 4.549103-3 93237.54o 4.638717-426- totl tet .IIt

40 vets water n Ostal. (liSleetuff 3 2 12.3.3964-39. ~~~12000.30. 1.3127354 13027.50. 2.404963-3 14000.50. 1.140641.2

PI0,. 19000.30. 11.559069-4 210000.50.c 5.494918-4 24000.55. 1.413653-41 8nll 2 lutrn t

I in.itiel source from fite rertvltefH results faer Par-Field Critisalty Study * ex /20 S0lOat - 40X n20/ 17n 1102 aSO2eaf) prebed * 3/0t4/9;6 6432S

the Initial fisalon neutron eource dlstributlen was read from the sretp File uood *retp,the criticality problem was scheduted to skip 40 cyles and run a tetal of 240 aytes with suminatiy 4000 nautrn pt eyOne.thlei prablem has run 40 Inactive etle wit.h 160496 neutrn hiateries and 200 sctiva ceyles lth 00373 Neutron hlstories.

this caleulatin has ompteted the requested saber of koff swtess using a tetal of 960849 fission neutron sourse histerles.*ll celte with tlselonable material wer sempted end had feasion neutron bouree points.

the results o thUe w teat far nartulity applied to the Individual eatlisian, absorption, and track-tength kelf cycle values ares

the kh eallisienn eycle walwea appear n urtally distributed et the 95 percent eenfidence leveltha hlebcerptien) *ycle alwe uwe t appe nrsttay distributed at the 95 pearent confidence levelthe I(tr Length) yle vatues Oppesr nerm all drt rbuted at the 95 percent cenfidonce level

...................................................................................................................................

| thle fInel estimated comebined setllelenlbserptlentr ck-longth tett - 1.11583 with on estimated stdrd eviationl of .eoorl I

Nay 33 u11N 1996 Pit* IaSMS 302Ctf.se E3AOONOO-SC11?t.2OO-SO016 lfV So LITACKUIUI "XI Page It

the estlmted OS. 95. & 9 "pereent hof Senfidence Oftervatl Ore 1.01312 to 1.41654. 1.61442 to 1.01124. Vd 1.013,4 to 1.617m 1the estinted .ellleienalabsrption euteon maevat lifetime - 6.UE-S eends with am ostimted standard deviation of I

..................................................................................................................................

Ray t0 MU I99 Pilt Eames, CI-3.S-.200OIo30WISu 3AO0OOOr-817176200-00014 m *o AT1AC1R053 LXXII p F I

I" vrsin ! Ide10/@l193 4396*36019PRU 0.9. CLIT1183s3.94 .0 td °!u!" .. *.* e4.d bJ6|5prabid * 614/0/96 M0UM:5

1. Farflead 6ritioity 6 gp*r of transmuted M.E0 206U0 US water tSS U-10 022- C .90 k-f Cr t ct adiveS. S

5- 1 1 .994531143S53: *1 tin!a$t S UrIniumituflf/aterA* S t 6.111216440004 1 .2 lP,11 S Tuft/ Vter 31 lctier

1 so OI IIS INp:EO S Vold10-11: 615ACES£ S 6 S 39.00 S F1laiL, SPIRES

yarning. tiii srftaco hasben rsplscsd by a surfaca of type so12- 2 S S 6 1C9.00 * REULECIOE

warning. this surface bas bean repltcsd by a surface of type ao

ies ea CUI loe -56- e00 1 Ule ee20- t00 500 I 3 100316- e *15 00 0 a -1 610 6.16 0 1 a I

143 xi 92234. CC 6.602093-? 9223s.5CC 7.172412.5 92236.100 1.75222.5 f125- oanl ec .04 * n

26- 1 oo~~O SC :|21 0e- 13027'.38C 2.963orw-3 eaar- 00:11ss 1:111111:t 11t11o:10C j:1&jfss-: 20000.S5C S.599054-4 ~21- ROO IT 1T$"IILVTE.01T 4V30- 33 1001.50C 2.00583-s 14000.5CC 1.319341-2 1302?.SD0 3.015387-3 S SC

-60 uoo Is 2sss 12000.10C 2.6n721o4 20000.50C 6.58r12-4 I so33- 11023.50C 4.55332-4 19000.30C &.421190-4 S34- h73 LNE.0i? S Na

.Initial sure frau file sretp

ltetl rasulte f letr ParFld Critiaality Sphere ot Transouted M.6E lo0Iw 30J Water 156 9-E1p 02 prabid * 64/30/96 20M36:50

thu initial fitsien noutren course distribution ws read from the *retp file eamsd *rctpthe eritisal ty problem was schduled to skip 3 syclses and run a tetal of 1003 syctes vitk nominally S00 neutrens per vyce.this problem ua run 3 inactiva sycl$a vito 14td neutron bisteriec and 1000 active cycls with 499866 neutren lsteriese.

this e"tcutltien baa s ted the tequested ber at kl eYcter usaing at otal of 501213 flealsn nsutron euire, histeries.alt Sells lith f*isiale materia wlra spled and bad fiaIIen neutron ourae points.

the results of the a test for normality applied to the Individual eollision. absorption, and track-twth kaff eyetu vetues aretthS kI *etionl gyce v e swear nmay distrlbuted at th. S persent aenfidence Isvalthr5 k(sbaorption) gycd values appear "armall dist rbuted at tte 5 srent * ntidenes lsvtthca Uth Icnutbh syc slus appear normeaty distributed at th. 95 perecnt cst idencr lsvsl

Ray 20 to :S 196 file *a_ CI-lSE*2041D-3WISU S000000-Sl1717-S2000016 KEY to ATTACKIEET LXXII - Fage 2

.................................... ...............................................................................................

the final estimated subiried ectlisiulabsorptlmnitracktrenath khef - .89801 vith en estimated standard eatien of .60092

the estimated U8 9. & percnt taff menfhence intervals are .19709 to ..8939 .9611 to .993. gm .S959 to .903the estimated *collieenlJbsebrptin mAutron rsemval lifetime * T.M-03 aecmnda with an estimated standard deviation otf 2.msI

................. ................................................................................................................

Nay 17 1436 1996 Filc Nams C2-3.S-20CIID-SItSU IA0OOODO-61717-6200-0016 EIV 00 * ATACUENET LIZZII * peal I

Ie verson 4a ledIl010193 8/11096 11135 51**. *O- *-*O*OOMOO 5 p0*b4d a 101/96 2tMSS

lEPaSESO tC IUTFDSE.tC.O

t- Partield Criticalatf - Sphere of Transmuted 3.6E iCCD SOX oItcr 152 u-Up 02t- S .953 k-elf CrH Icl Radius3. C4- C MIKEE5- 1 t 7.9145t1 4353- IXPSsIm S Uranium/Tuf fVater*- * S 5.l1ttt11DDI Z1 -1 Ittr.t- I Tuf fluter Rftlecter7r CS. t OUTtlOt WORLD9. 30 0 2 INPsE-0 a Vo1d

1C-II- C SWIRPACI12- I £ O e a 97.66 S FSS PEIKER!

warn!ng. this surface has been replaced by a surface of type so15- a S 06 S 137.56 REFLICI0E14- C

marmin. this surface bas been replaced by a surface of type se

t6 MlODE a15-1?- scoo" '8° 1 ' 3 t * * t 1 a a 1 I * t 1 0

9- C I I I I -1 0 1 a I 1 -1l0- C -1 I S *1 -1 0 -1 6 1 1 -122- C 11 t 6-1 I 6 1-1 .1 I

23- El 92234 .oC6.102013-7 92235.0sc 7.1r 412-S 9236.9Sc 1.71622-5f I PI24- 1223 S.C357 3-3 93237. C0c 46129 6 - SoIL.SOC 4.339 -2 tas- la1.CC1.0962- an26- 1400.C 1 121440-1 13027.3C to6307r- 5 Ct

260 5ssc 1.3300223-6 1000.50e3.2?135 34 20000.SOC 3.99054-4 9 VI112 S Ls7037S 1.952 00003o8Cc 5.463492-4 3

29- IT~t 1 LUT I VA30-: M3 1005CC 3.605336-1 14000MCc 1.319341-3 13027.11Cc S.13337-3 69 Ca

II1: 26 0.SC 1.62333949 120oo.110C 2.675121-4 10000.110C 6.1157132-4 III33- 11023 CC 4.553332-4 1900035Cc 6.4399964a34- ElI LWTR iT a Vs

Initial source fr fie Arstp

kef 9 results forp ParFelod Criticality tSphere of Trananuted SME 20eO 30 Water 11% U-Up 62 probid * 65/1119 I1s335I

the Initial fission neutron source dictributien Uas reed f*es the sectp fie named *rctp nthe criticiVty problm was scheduled to skip 3 eycl nd run a tctcl d 1003 sycles uith 1t 500 neutrn er cyc.this prbtMn run 3 inactive cycles Itfth 1762 nauten hiiterias ad 1000 acticvse lev ulewth 4993 meutren lbieteria.

this calculation bas e Leted the requested number f katf a uI- uing a total of 101725 fission neutron *surce histories.all cIlls with fiee tlar latril wera sampled And had fleaIs neutron source pointa.

the results of the w test fer normality applied to the Individual cellisien. Masrption, end track-length keff cycle values srei

the it cellislin) ycle values appear mormatly distributed at the 95 percent confidance levelthe ktabsoeptien) cycl values 4pcr mormatly distributed at the 5 "prernnt cnf donce lvelthe kttek lngth) enc value appear normally distributed at the 9 paercent ecnfidance level

Nay It 14a3 1996 filke Rams C2-3.65.8O GI30e SU IVAooCooelrlre2oo14 Sty ArTTACUNEn 1x3121 * Pal a

.............................................. ............................................. :...................

the final estimated eo embd eatttnle ebaorprtiil trenc-longth kofft * .a61 Mith an estimated Standard davtatien of .0039

the estimaetd ". 95, I 99 poreent hoff onti dence intervals are .982 to .98549, .9M to .SU37. and .98226 to .9895

the estimated ceitlloien/esrptien neutron removal lifetime a 6.953-85 sacends with en estimated standerd deviation of 2.153-S7...................................................................................................................................

0

Jun 10 lOs!? 196 Flit. Ean s3020a.wei UE500000-l017i A2t0D016 tElr S AtIACeENT LXXIV - Peag I

I"o version 4a Id-1010*m 0t216 ls..r P1mcn* l.-d*X-1~u~m .- W prebid * 6 2/96 13s44:1TIn - 3020se utp..302a0t

3: Crilaarl-lFe y eVu * J.6 /is golMt O 30%20/ 12SS UO2 s3020a)IC CEll e £t PIC I £1 * 6 porosity sphere eurreunded by tuff

* IKIER lU RE IltO#S. I 1a 7.894531-2 ,! 01 11

J 2 t l~e~st42 2 -2 1W 1s"mre t IID WuseORLD6. 3 6 2 137:3.0

10 C URFACE SPECIFICATIOSII: 1 O0 103 I1Et FWUEL 20E312 2 0 163 EKEIE FUEL 20D113-

IS. 11U 44000 1. 20716. e jIeC 1 0610 3e.20 062 e 20 15 -51 t 10 * *40rT. c e-I o0 - 30 I 136 .l 1 o 253 0 1S- S S S1 301

ii. NATEXIAL" IECIFICATE8ESla C 1 ml Spll~lx19- P o0 velX Mecr In eet1ee lilts tuff) a .05 .1S vetl ue220- c .6 erigins Enrichaent/ 20 VDIMT dec d to Ur niw lastepe421- *1 1001.50c 1.704962 2 P016.50. 6.55926 211023.50. J.S7037s 422U 12000.S0. 2.27315334 1027.50c 2 5J3079-J 14000.50. .121440.223 190 0SOe S. o5492.4 10000.5 ..59"054-4 26000.15C 1 .38025-424. 92235 1S102093:7 92235.. e 1772412565 92236.50c i.7I6222-S25. 92231.10. 3.5728113.3 93237.10., 6.092956-626- .11 lutr.41t27- a s0 v.13 water In calico Ellis luff25. .2 1001.50. 3.142479-2 6016.3Sc 3.d95585-2 11023.0.c *.9U442.4

n1W200.58 1.741675-4 3027 .e0 1.963209-3 14000.s0. 8 509752.s50 19000. De 4.1163344 20000.10. .35537-4 26000.55. 1.65T741 431. *tt istr.61t32- PRINTI Initial s"urce free fII ret

Ikaff rasults fort For-field Criticaty study - 3. 30 S CAMt - 30 120/ 153 802 (3020) probld * 65162/96 15as417

the Initial fission nautron seure, distribution usc read fram the aretp file rased *retpthe criticality problm mac acheduled to skiP 20 oyc ls and run a etotl of 75 ycltes wifth nominally 4000 neutrenc Nor cycle.this problem Me no O Inactive cycles with 60438 neutron hiaterlas and S5 active cycles with 21U449 neutron hlletries.

this celculetlon Ms completed the reqastod number of keff cv.lee using a tetal of 299837 fisleon neutron source histories.sil calls miltk fisalinable material were coupled and had fIt.ian neutron source points.

the resutts of the I test far noruality applied te the IndividOul collision. sbserptlin. tnd track-lanith keff cycle values ereo

the t( eoslision) tyclo values eppear normally distributed at the 95 poroent confidence levelthe w~obaorptten) eycle lwes ppear Rarelt H dietributed et the 9 preet onfidnce e1the Ptrk length cycle values appser norma sl dietributed et the 95 proe nt GMnfidnce *1

I the final estimated a*ebiod *ellelonleberptlon/track longth eftf ea 914 vith an salatod standard deviation of .00137 |

Jun 10 10:37 19096 File laws, 93320a.sus t3~OC-11-200 1V K 00 AIUC1KEN? LXXIV Page 2

Ot etimated "8* 9S, & 9 percent katff centfidene Intervals are .Al79 to .199071. .93353 to . O999 aNW .9367 to .9930 I

the estimated cattfolsn/abuerption neutr.n removal lifetime a 6.49E-05 seconds Mlith an estimated standard deyletien of 24-'

say 20 07s1 t996 Pile Name C643.oE 20XUD3CVtSU R3AODO0oo 01?4200.0016 2EV 60 4TtCttEnT LWxX * Page I

1I version 65 IdelDCOt1199 64110/6 1317:26l~t-S.;EC e~tt-X.BE.CDwprobid a 0411/94 1M1MI2

l- perFileld tritiality - Sphere df tramuted 3M1E 200 30X Water 1tS U-hp 022- C Crit cat Radliu3- C4. C SPRERES- I I 7.99 143I63s3-4 .1 11,P.e1 * Uranilusuf f/Vter6- ' 3 ' .11121144000-1 1 -2 11:1.l S luff/water Ref teter7. C*. C MTIIDCE VORLD9- 30 S a IlP111.0 S Vold

lo-II- C 6112FACEa12- 1 6 66 113.15 S ItSUCS UIERE

MArnnGe. this surface Ias been retaced br a surfece of tie so1s 2 6 e a 173.15 5 SEFLICTOR14- C

warning, this surface has been replaced by a surface of type asis.16- OOC a1T- EC00E 2000 I 1S 138IS- C gltM 0* * 1 0 -1 0 e l I 0 D-l 1 a19- C 116 1-16 101 1 C-I20- C l 1 6 l S 1 l -l l 1221- C 0 1 0- *S 1 *: :1

23 RI 92234.500 1 .02093-7 .9223..C T.172412- StaUm. .716222-5 S el24- 2238.50 SO 3.72313-3 93237.50C 4.s92986-6 11016.Cc *.35926-2 * At25- 'a""'1.096- Sa26- 14000.1oo'U 14 021 13027.30C 2.583079-3 soC272 2000. TC 1 40025-4 12000500 I I2M4S3-4 20000.3CC s.599054-4 i28 11D23.50C 3t70375-4 19000.SDC 6.45462-4 0

l9 IITl IlVeIIONIC 2.00518-2 14000.0C 1.319341-2 1027.1SOC 3.015357-3 S eV1 6016300sod c 4 26S802-2 S WI

12 2'00'0 SC 1.62355 -4 12000.SC 2.6n121- 20000.Stc 6.U87122-4 $ so11023 SOt 4.153382-4 19000.S0C 6.42M0-4 t

VI3 LWTE.1

1 Is, v.35 PFll?

Initial seures free file sretp

Iteff reaulte fort Far-Fled Criticality - sphere of Tronuted JMDE 2oe JM Water 1SX U-1p 82 prebid a 04/18/t MiMI2

the initial fission neutren esurce distribut in use read freo the *retp file named aretp -the oritlestrty preblem *as scheduled to skip 13 reyee Wad run a total of 1 cycles with nomInatly 2000 neutrena per ccleothis problem hae rim 13 mactive epels with 254S2 neutron histories and 12S active aices with 010Stl neutron hitoriee.

thiso celeulation has compltesd the requested mbor of koff aeylee using a totel of 275ru fislon neutron seurce hietories.a11 eolle uith fiasianab le ateriat ware sampled end had fission neutron source points.

the results of the v test for uormality applied to the individual eollision, abaorption. and track-length kftt cycLe values arec

the ht eolk iwiont yle vlue appear normlty dItrilbuted at the 95 percent cenfid-en laveltlbs ttebrorptlen~ sYcle values appea normIly isltributed at tbo 95 percent confidame levelthe tbrk Iilth3 ye.lo valus piesar normlly itrbuted at ti S 9S percent confidane tlvel

Ray 20 7:16 1996 fit zs BLACO.3O O1fu IOOOOO01717-9200.00016 REV to ITACKnEIT Xtw - .js 2

...................................................................................................................................

the ftear estlmated onbined eeotigien/absorptienItrack-Iength keff * ."8t7 witt en estimated Standard deviation of .6

toie estimated £1. 9. £ 9 percent ke confidsnce Intervals are .992 to ."M9. .99SS to 1.6002. anId .1153S to 1.60159

the estimated ootioiolobsorptlon fAutrun removot lifetime * 6.441s-0 secnds with an estimated standard deviation of 2.631-S7...................................................................................................................................

may 20 *rs19 1996 Pits ES. CS-3.SE-10603-O34SU SADOCOOC-011-0200-80016 CIV 00 ATIACSUKNT LXXVI - Pos 1

verin 4s kdel 00(9aIV 4/89 150:9**".36e * f probfd * 4/18/96 15:5:39

1. PFrfeltd Criticality - Sphere of Transmuted $.0E Z0CcD S30 Water 152 u-Up 022- C Critical Radius

5 1 '1 7*I433111:31.M A Uranism/TuffjUater6- 5 3 a.121144000- 1 -3 131,1.1 S Tuff/Water Reflector

9 so I a IM.I-C S Vold10-11. C SINFACES3- 1 5 a 06 * 114.5l s rSSIL UllERE

warrnin, this surftae has bon colated bI a surface of tpse ae13- a S 6081 REFLECTOR14-

Noiins, tliks surfece has been replaced by a surface of typo as

16- IIOD I17- 5CCD1 2000 1 13 1INaI- C ESIU *S I S t -1 8 6 I1 6 0 -1 0 I 0 1 S

19- C I I6 I-.1 I0 0a 10a-110- C 1 I .1 .10 -1 0 1 1 0-12D e 11 I41 1:

3 ml 92234t C 1 1 3-9235 Cc 4.192486.5 3026.5C 1.35926-3 : pi36- 92233.5CC I.572S13-3 922S5.CC 4.91241-5 92236.5CC 111926-22- 5 At35- e 001.5 1104962-9 S an

36- ~~14,0000.:50CC 1.121460-2 13027.5CC 1.563079-3 Is CS37- 26000.55C 1.380025-4 13000.50C 3.3383- 30000.50C 5.599054-4 Il3s- 11023.5CC *.70375-4 19000.5CC r .z6c492- A s 339- 171 LUTESIT A Ws2U- IS 1001. SDC L.805832-3 1600.5CC 1.319341- 13027.5CC 3 e 15387-3 8 C*31 2016.50C 4.30802 s o2r 36000.55C 1.623559-4 12000sC 2.615121- 230000.5CC 6.587132- I

33- 11023.SO0 4.553312-4 19000.5CC 6.439990-4 *36- IT13 LUTtJIT W U.

initial sours. fri. file oretp

ikeff results fors Farfield Uriticality - Sphre of Transuted S.0E 23000 30 water 155 U-4P 02 prsbld * 04/18/96 tun S3

the initial fission neutron sourw dstribution was road from the scalp file nmoed Scalptho criticality problem ws achaduld to skit 13 aa138 syclec with nominally 2000 noutrsns pr sycle.thli problem has rm 13 nactIe e"etas sith 35772 neutron histories end 135 active sewms with 369934 mutren istorit.

this calcutetla n has cempleted the requested nmber of hoff cyces using a total of 75706 fission neutron *eurce histories.slt selle uith fissierabte *aterift were Sampled and had fission neutron sours. points.

the results of the a test for normality appl1ed to the Individual coiticion, sbsorptlen. end treck-tength t1ff cycle values are,

tho It collision) cycle velwrs appear normtly distributed at the 95 percent confidence levelthe tt(asorptisft) Oc IC valwes *ppear oremelly dirtrlbutod at the 95 percent cenfidence ie"etthe kttrk length) eyecV waus ppear noraaty distributed at the 95 percent eutfidence level

- .

may to0S7u19 199% Pits Names CS-3.4110C-SOODflWIU SIACONOCO-01717-0200-S0001 REY 00 ATIACONITI LXI I Post I

the final estimated eebined settleien/abserepti.track-tength koff a .n9925 with an estimated standard eviaetion of .0117

theeestieted "l 9n, 1 9 percent toff erfidentce Intervals ere ."798 to .LOO53 . MT2 te 1.o01n9. and .99s90 to 1.2u1

the estimated oltiesionebeereptien neutrnn eevel lifetime * 4.413-8S aecends uith an estimated standard deviation of 2.531-47

.............................................................. .................................................... _,.......

I

may 20 6713 t996 itle *ame: C6-S.S.200110C30fl SU UAD00000D-61717-D200-DD0016 KEY00 £DATTCHMEN LXXVII - Pagt l

l * en verseln 4- tdad10/0193 04118/96 [email protected] *a.50*O -o**** eeeo* eee pr-bld * 4/ 94 12:22:24

Ilp-3.01C UTtS. BE.CO

P^rtetd Criticality - tSphere of treansuted ME.6 2DUD 3 u water 15 U-bp 822 C Critical. Radius

4- CC £PUiRI I -1 IMP11a1 S Uranismfluf f/iVateC r ;.t94 .le55.2 .. 1". . t UtNluattu f ftf/ter

7- C

9- so 6 a IMPsUSO VoidIC-11. t pau otet12 1 t 066 123.15 * 1It31 ttPREtt

warning. this surface has been roqlaced a surface f type so1- 2 * 0 6 183. 5 REFLECTOR14 . 1

srning. this surface has been rnpleced by a surface of type soIs-16- 1017- 9ICOE 2000 13 01381C- c nc I 0 653_ 66a1I -l S 1 06 6 6_ 1 S19- C I S 1 1 S-*EC 12 .1 * 11 2*1 la 1 .1 S-121- 1 1 a -1 I 1I -1 S-1 -I22- C 1 1 -1 I -i -1 -1 -1-23- Hi n2234.50C 0.802093-7 92235.50C 7.17241i2- 92236.5cC I.714222.5 S pi24- 92238.3CC 7Z2A13 93237.SCC 4.S92986-6 W016.S5C 4.3592SS-l S at25- 1001.50C 1.749&2-3 Sean26- 140..o5DC 1.121t440- 13027.5DC 5563079-3 I to27- 6000 55c 1IJ30025-4 2000.D5C 1.273153.4 20000.50C 5.599054-4 * VI23- llDZ3.5DC 3.370375 4 19000.5DC .eS5492-4 It S29- Ii I TE01 S VA30- 113 100.CC 3.6053D5U22 14D0D.50C 1.319341-2 13027.5tC 3.0155387- S Ce

1- 6~~11016.5CC 4.265302-3 1;3112. 2 D60000 S 1.23U59-4 1200D.5CC 2L675121-4 D0000.5CC 6.537122-4 * 3033- 11023 5pC 4.553382-4 19000.50CC 642mD-4 S34- NTS ,113.41T , Wm35. PRIIITI initial source from file aertp

tetff results tfrt ForFteld Criticality - Sphere of Trens uted 3.01 20IDG6 30 Water 15 U-1lp 02 prebid * 04118/96 I1Z2::34

the Initiel fission nmutren souree distribution usa read tree the erctp file aeed *retp .the eritteelity peroblem wa scheduled to skip 13-waey aznd ru a tetel of 135 eyteln with rnominlly 20OC n utrens rr yele.this preblee Us run 13 Inetve syelas with uesr neutron hioterle mid t25 ativeycls wth 24947 nutron teter.

this eelculution hen seoplated the requested umber of off cycles ueing a total of 275974 fission neutron source histeries.Ott sells e ith f I sienable materiel were eseptld end uad fiesien neutron seuree points.

the results of the u test for normality applied to the IndIviual eeollision, eaborption. and treac-length hff cycle values ero:

the i cellli n etyle values epp'Wr normally distributed at the 95 percent confidence levelthe ttebeerptlon) erle values appenr ortially distributed at the 95 percent confidence lewlthe trk lonith) osnle values appeer normally distributed at the 95 *ercent confidence level

-

Nay 10 MU,13 1996 File laws C6*3.01208WD-30eISU IA00000.1r 7?.200go51 60 AITACNNEUT LXXVII page 2

...................................................... ........................................................................................ --...-

the final etimated embined eettlslen/daorptimiVntrct-tenets kaff-- 1.60875 aith en * timted standard deviatlen of .00116

the etimated "3. 95. 9N peent koff cenfidenee Intervals are 1.60739 to 1.60992, 1.006" to 1.0i107. mnd 1.00563 to 1.61183

the estimated eeliilmenJbserptlen eutron reeoval lifetime a 6.17343 eaconds with an eatimted etandard deviation of 23.&-67

., ..... ........................... ......................... ....... !.................... .................. ...... ..................

Jun e7 10310 1996 fits Ka m 30a12h1.e-UM 3A0oo0D0-1717-0200-00014 UEV SO ATIACKNET UxvlZ * Pass I

I"cn version 45 14.10/01/113 03102/96 07s39s43osa*.eee .a .td-s~l~omee .e e.oee.sa............... .. .029 e...e. prehb * 65/021, 071A9S43iPS30c12h utpasSOc1zho

1- aFrFistd Critlesllty - Sphere of Transmuted S.OE 20D 201 Water 1t.&1 U-tp 022- C Crt1eels Size Optai stlen Cenfirmatien3. C4- C 173E11

I 1 134398I1 S-2 *t 037:31 S. Uranfuntuff/Utsrt S S r.~~~10112M24000-2 1 *t INIMs-1 S TuffVacter Refl etor

7- C WTSIOE IOtU

10-

12- 1 toISOI S R1ILEtO. UER13s a to 2 0 S ngeFLet54- C

56: Ig a17- 0001t 4000 1 30 130Is- C CSIC 0 60 10 e _1 a0 010 a -15 0 0 a 1 019- e I i 10 1 01 a I a I I -120- C -1 0 -i1 I -1 @ 1 -1 0-121- C S 1 1 0 1 0 1-1 *1-122U C II 1 -1 I I 1-11 -I -1-123- E1 92234.50C 6.10692-? 92235.50C .34W55 92236.5CC 1.327`212 S *24- 9223S.S0C 2.76295-s3 93237.0 .143242- 6 014.50C 4.042554-2 S At25- 00 O 9.310. an26- 1 8000. 01 1662972 13027.0SC 2.66S6023 S Cs27. 36000.15C 1.435226-4 12000.10SC 3.3407-4 20000.300 5.323016-4 S VI23- 11023.J0C 4.025190-4 19000.30C 1.184111-4 S 3029- ItT1 113.01T t 1130S II ICONIOC 1.337225-2 14000.S0C 1.319341-2 13027.30C 3.01337-3 S C eII: U0i6O .931496-2 a VIi2 2402000.35H .423559-4 12000.0C 2.67512i-4 200.050C 6.57122-4 5 30

33- 11023 SOC 4.533382-4 19000.50C 4.429990-4 S34- KT3 LVL 61T S Vs35- PRINT

I InitIal sourcc fre file erctp13kff resultt fors ,FrField Critiality - Sphere of Transmuted 3.01 200 01D Z water 11.61 U-tp 02 prebid * 05102196 O7:39s43

the Initial fission neutron sourcs distribution us read from the cretp ftle namd aretpthe criticality pr ooblemas schsd.led to skti1 30 cyc le and run a total of 130 "tiles withi nominally 4000 neutrens ser cycle.this problem has run 30 Inactive sycles VI 120473 neutron histories and 100otlive clets with 3981 neutron histories.

this calculation has sou leted the requested ubr of heff cva la ing a total of 51926 fission neutron cource historise.all sells with fissionable materiel wmre sompled end bed fisain neutron source points.

tlh results of the w test for normality applied to the individual sollisien. *berption. end track-lenth koff cycle values *re:

the RI aeltielen) *yVte valuss appeer nermally distributed at the 9S percent confidence leveltm kt(bsorpt in) cycle valwes eeppc nrmaltly distlbuted at the 9f percent confidence levelthe tr lenth) eycla Vlues ppe r rma lly distributed at the 95 percent confidence level

.............................. ....................................... :...........................

jum 0? 1010 196 teFile Nano 30e12h.seu IUACOOOC-U1?1r-?0200-00016 rIV So AfACEMT uLXlIul * Page I

tie final estimated embined etilfelaea wrpti n/tra ength heft * . fith an estimated standard daetvia t .of CW?

the estimated CS, 95, £ " percent koff eonfidetne intervals are .97451 to .97M4. .915S to .97742, aNd .Jr to .M65

tie estimated cotliesin/absorption neutron Presval lifetime * a7.04z3S escends with an estimated standard deviotion ot 1.3-47..................................................................................................................................

I

Jun 07 10160 1996 File now: e*30e12g.ue SA0COCCOC-01?17-6200-00016 REV 00 C AITACUNET LXXIX - Pate I

1ecnp vdreiCn 4e /1o 63 196sl 6 69.39:4I out-*-8-**--**1--_*- pr*00o0*- - p.* *-*OR*-- prebid * 63102/96 69:3 0

1rn eSOe15s outpva3Cet~gO

1- aFrtleld Criticmlitp ofer o Transmuted 3.61 20 X 303 twater 11.64 U-tp 622- tC Critalet Rsie ptl ugti on Confirmation

4. C SPNER!. I S IINT 73S43931S01532 .1 INPtiUU S Uranlue/Tuff/Iator4. S 7 10392U4000-2 1 *2 PtEutl $ Tuff/Utetor tetoleterr- C

9 30 O 2 1aP:WOO .8 Void10-11- C 5WItACES12- 1 to 320 S FS9l1L tPtEXE13 2 Wt 2S0 * EFLECTOR14 C15-16: 800 a11, IGC0E 4000 1 jO 130Ia 1 I 0 0.,',- C'°vs IU °° "°' : ' '19- C 1 I 6 .0 161 a I I 160-120- C 1 6-1 -1 -1 -121- C*ll - 1 e o 11

222 ml 92234.50C 6.e069S27 n2si 922U.soe 1..2.212.5 S Ft24- 922531.0C 2.76297S-3 323750c .16524246 041.5*C 4.04235642 * At25- 1401.1CC 1.1U107-1 an26- 14000.SCo 1.14429- 13027.WCe 2.665602-3 S to27- *6000.1SC 1.43S226-4 1200001C 13.36,607-4 20000.50C S.123016-4 D ti25* 1103SoCC 4.023190-4 1 C000.5CC 6.t4111-4 * so

I1T1 LlflR.G1lStiJ0g: t3 1001.50C 1.337223-2 14000.5CC 1.319341-2 13027.SCC 3.013367-3 S Im

32- 26000 SC .3IS9- 12000.S0C 3.675121.4 20000.5C 6.587122-4 I *033- 11022 SGC 4.533282-4 19000.0CC 4.429990-4 s34- IT3 1*TE.61T a Na35- IilKTI initial asur.. from file $r619

Iteft reault For$ PorFtietd Critltstity - 6phere of Transmuted 3.0E 20GCU 201 Weter 11.6 u-Utp 02 probid * 5/0296 9:39:40

the Initial fission noutron source diltributlon was read from the eretp fit mnmtd *rstpthe .riticelity preblem was scheduled to skip 3e my teo red run a total of 130 eetee with noeintlly 4000 nutrrens per cycle.this problem has run 30 inactive eyetem mIuk 120371 u rutn historie and 100 active ovsem uilt 399911 neutren tleterite.

this omleutation aM setotetd the requested umber of d off cyclk e using a totet of 520232 fIssion neutron soure historlies.sit salle with fissionable urteriel were sampled and hind fislesn neutron eoureb pointe.

tIe reaoute of the * tete for normality applied to tIe Individual setoliion. absorption, and trsk-tensth haff cycle values ores

tIe h( eettlelen) eycl values appear normally dlmtrfbuted at toe 95 percent confidence leveltbe htebtaorption) mycle atims atppear normally deitrbuted at tte 95 percent onf Idence love,tke Mark tlonth) eyet values appear normally distributed as the 95 percent oenfIdance level

........................................................................................................ 7...........................

Jun 67 10:S8 M9 file lanes *34s12g.osu IIAeoooOU-01717-0200-O0001 REV S0 AtCMNENT 12X1 - Pago 2

the final esttlated combined eeltloeenlabsrptien/track.Iength keff a .93419 with an estimated standard deviation of ."000 |

the estimated ii. 9, £ 9 percent koff confidence intervals are .93403 to ."71. .9331 to .93460, end .9U62 to .9371

the estimated coliielsn/obesrptiln neutron removal lifetime * a6.9E-03 seconde with an estimated standard deviaetin of t.3f9-e7

..................................................................................................................................

- * .

Jun n7 tcil I6 pile aNow a3oaIf.au 0 *s1717.20010016 REV 10 aTACINENt1 LXXI page I

1:e.cn .yersion al d-10ne1f93 63/01/96 14,081.3lon rel n *agleoeo. .oeoe.e .. .e..e.e.......... tscBss~us~o, prebld * 5/01/96 l4sOM5Inp-s3Oiltf .utp-530aI21'a

1- Pareltd Critluallt-Spt ere ot Trenasuted MIE 20YWD 201 Water 11.61 Ul-1p 022- C Critical Slat aptial~atfn C1nfIrmation3- C6- C OF51*1

1- 1 1.13639813085.j *1~ IMPalel S Uranium/Tuff/Mater6 I 6~~~~U M000- 1 .2 1171, I Tuft/Mater Sef lecter

CID3 I it Il~ipthC £ voidla-II. C 111UKACES12. 1 30 330 S P133111 37PI1113. 2 s0 10 S FLICTOI146 C

£- SY01E I17. iceo= 4000 1 3J 130le- C 150 e*t 100 .1 0 0o1 010 o e 1 e1It C 1 10 1.10 101 1 0-1

2 C12- C st * 1 *1* .1 *1

22* 111MOC 022694 C31 0C 1146653. 922!36SOC 1.27212-.1 S F126 *2tS tC . 297- r.o 7.10 .13524-26 3016.50C 4.042354- I AtIs- 1001.1CC t.1221073 S, an26- 16000.I5C 1.16297 13O27 .OC .663602-3 S Cn27- 26000.13C 1.433226-6 1 oo 8ec .364s07 20000.10C 1.I23016-4 I I2s- 11023. IC 6.1253190- 1 .OOO0 .6 l S64111-4 6029- III LM1h CIT usM30- KS 1I00 *C 1.37225-2 16000.5CC 1.319341-2 13027.1cC 3. 11317-3 S ct31: 1016.5CC 3.n31962'32- "000.Isc 1.6233559- 12000.50 2.673121-4 20000.50C 6.537122.4 I io33- 11023 CC 4.13332-6 19000.0C 6.4299o-4 a36 1173 LVSIT S was3- P1RNT

I Initial source fre fite *reteIkeff resulta tar, Forfield Criticalit a phre of Tranmuted M.1E 200 205 Mater 1.1" M-1p 02 prtbid * 05301/9 161 350T3

the Initial ftlea1n nautren source distrIbution wsa read fram the r*ntp filte naed *rctpthe eriticelity preblen was scheduled to skip 30 cycle. and rum a total of 130 veclr with yominelly e000 neutrons ir *yclo.thIs problem has rn 30 inactive eyclea with 12090I heutron histories and 100 active sycbos with 398167 neutron istories.

this calculetion Mas capleted the requested ntuber of katf tea aina a tetal of 118232 fissin neutron source hstteries.all gotls with f oalenable eaterist were somlsid and had fle Iaon neutron source points.

the results of the a test for neroeity applied to the findfvlwd l collelon, aborptien. and treck-lengtih keft cycle values sreo

the kt eallisien atcle vw.r* appear nuormlly d etributed at the 9n parsent centidence telthe Utebs rptlon acle vae appear unral y distrbuted at the It percent emitIdsnce leelthe hItrI snat l r velwss apPear Zoruallt distributed at the 955 perent *enfit dnce level

...................................................................................................................................

Jun I7 18CI0 1996 FIle Bases e3012f.M UVAOCCoo*61mIe208-l016 I 0 SO A1TTC*NEIt LZU Pogo I

the final estimated combined eliel/erptienjtractetth keff a .93870 with n estimated standard dovitin .94

t, estimated a. , 5 9 percent kaff eonfidence Intervale are .977T to .98964. .9141 to .0537. id .92 to .9

the estimated eSltislon/sbsorptlon mnutron removal lifetime a 4.11221- Seconds with an estimated standard deviation of 1.9111-7..................................................................................................................................

jun 6? tenv IOW PIN. Hamel s30o126.su.g 63AODOO0-C1f-4200-DOCIS REV DO ATTACUNENM LUXXI P as I

lcce vrelon 64 probld e /0316196 .e.:43:e8

Inp-830*128 otp.8e3 12.0

1- FrFliets Criticalit spere of transmuted 3.61 260lU 202 Water I1.Z U-Up 02Ce Critical Sme, Optei-atlot Canftirmatien

4. C SPhaE5: 3 1 r1uu XSS-2 *s . 19Psl-l * UranuaIuff/ater

e I MIGIMMODO-1e I t t INF IN-1 S ruff/nte Re fleto7- C

8 eC 61u1TMOE WORLD9- s0 0 2 11913 - S Vold1I-11- C SURFACES12- I so 300o FISSILK SPRE3113. 2 to 360 S 4CPLCCIal14- C

II: OWE 11tr- lOCE 4000 i t0 130tC- C 913c 6 a I a I -t * 6 1 C-a t e 1 a a a I a19- C e 116 1- I6 1 1 I0-I- C -t .1 1 1 *J 0.1

21- C I I 1 011I 61. 1 01122- C t 1 .1 1 1 1i I .1e 1123- Ml 92234. cc l.o069s2-7 92233:.50c 1.3466513 62236.sc 1.327212-3 rt24- 9223s.s0c 2.76297s3 .93237.10 3. 6S242- 6016.50C 4.6424-2 S At25- 1001.300CC.152107. St n,26- 140000 0C 1.1"6697:. 1t3027.30 2.463602-3 Ca27- 26000.33c 1.435226.4 12000. o0 1.3 074 20000.SCcOC 3.623014-42S- te2os.soc 4.62s130.4 inooo. 0c .634111.4 a U29- T LIR.6 a maso 33 1001I.5c 1.3372253 t14000.10C t.S193412 13027.0sc 3.61J387-3 S Ca

I2: 2Se0:15HC U S;9 4 12000.50C 3.65121-4 20000se.c 4.537122-4 I so4: Dn 1102|3,5C 4.553SZ 4 I40 .SOC 4.42MOS04 11

33LWTA. IT 4.338.4S Vs33- PR311

I Initial asurce fre file eretIkeff results fort F.rFietd CritIeslty - spiere of Irensuted J.OE 20C1o 20s Water 11.45 U-Up 02 probld * 65101196 884316

the initial fiuslen neutron souree dletribution wsa read from the erctp fite named erctpthe critialtity probt_ usa atheeled toII sip30 les and run a toal of 130 ycles with nominally 4000 neutrens er *le.thie prebto hts rino 3o inactive Yclen mIth tt6t neutron itistories end 100 active "ycies with 39903 neutran Isleterfes.

this calcutetion aas completed the requested number of kff eIel using a* tctal 3f 8M4 ftleaon neutron source hiastorio.atl ello with fIssionable *ateriel wre sampled end had fleon neutren ource Into.

the results of the u teat for normality applied to the Indivlidul callislen, abserption. end track-length koff cycle values ores

the th collision) cycle velues appear noreally distr buted at the 95 percent confidence lthe bcserptien) cycle we ue ppear normal y dIstributed at the f3 percent * nf dence lowthe k(trk tleilth) cycle vates appear normally dietributed at the 9S Marcont eonfidence level

......................... ..........................................................................................................

Jun 07 M0109 1996 Oltt goae: s 3oeI e.su l3ACCUOAOA17T-S2f-CO0t* REV 60 £tCKNEIT LIl I Page I -

the final estimated aemblend mlttilen/abearptlal~traek-tensth ka ff * .99516 uIlth an estimated Standard deviation of .00095

the estimated 48. 95. £99 percent kaff onfidenace intervals are .9V421 to .996I .997 to .MS. and .M265 to .976?

the estimated oeliaonlebsorption neutron removat lfethe - 6.¶63.0S aseends with an estimated atendard deviation of 1.7E-07. . . . . . . . .. . . . . . .. . ... . . . . . . . . . . . . .. ._ . . . . . . . .. . .. . .... . . . . . .. . . . . . .

awn 67 1:6 1996 Pits gUms Msael2b.gsu BAO00000-0.17170200-6001O REV to AITACe£XT LXXXII * Pasg 1

1mcnP vergiMn 4a ld.02/193 *4/26/96 12.SS39I n....e** eeeer ee.ee..~e...ee~e~~~eee.e.eprbeida 044/ sSItr43el2b outpos30el2bo

1. PerField VIt I tita spere of Trenhmuted 3.ME 2n6 20S Water 11.61 U-kp 022- C Stit tal ptimitien Confirmation3. C4. C polls3

s 1 1 r~136

398133

S-j es MM % Uronfustff/ater5: s : r0le29z2 ea00 1 -8 ,IRPI-I S Tuft#vater Itaftcter7- C8- C 6UTSIO WORLD9. 3o 6 2 ImPIU.0 S Void

10.II. C OWUACES12- 1 to 325 S FISSILIS S71RE13- 2 go 3ss S REFLECTOR1S. C15.16- NMI0 I1t- 100 4000 1 0SOit- C 1510 5 0 e -166 e 1 e -1 e 01 619- C 110 1.1 161 1 .. 120- C -11I0 .1.1 I .16s1 -1 3*121- CSI I SI I 1- 1-

23- ml 92234650e 6. 36952-7 9223S. J1Cc .546665-S 92236 1 327212-s 'pi3i.- 92238.50C 2.76297-3 93237.50C 3.16S242-6 MAINJ0 4.642534.2 5a~t25- 1001.00c 1.162107- con26- 14000.C0C .166297sr 13027.50r 2.665602-3 * Ca2n- 6000.55c 1.431226-6 12000.e00 2.364807-4 20000.56e 5.s23016-42s- I1023.50c C.23190-4 1900000.5 5.634111-4 *29- NTI LMTS.G1T S Mas0- 113 1001.S00 1337225-2 14000.110 1.319341-2 13027.50c 3.01538-73 St C31- 8016.110 3.931496- 232- 26000.SSC 1.623559-4 12000.0C 3.675121-4 20000.100 6.1387122 *-433. 11023.900 4.553382.4 10OO.S00 4.429o0-4 S36. 1113 LW?5.61 S Vs3S- PINT

I initial source fre_ fi.c aretpIkeff results fort forrield Critlesli t-Sph.re .f Transmuted 3.01 $000 202 Water 1.61% U-Up 02 Prebld 041241/9 12:55:39

the inItial fsslion noutren source distribution was read free the shctp file smod eretpthe criticality preblee wase sceduled to skit 3Occ ent nd run a total of 130 cyctes ulttt nomlnaty 4800 feutrons per cycle.this preblem has rcm 30 Inectiva cycles wit 120156 neutren histories end Iso active eycles with 400694 neutren histerisa.

this cgleutltn has s topted the requested mimber of kff aeye suIng a tot#l of S208S0 flIaten neutron source hiestorie.all tells sith fisena= mterigl were salpted and had fissIon neutren source points.

the reeutte ef the u test fer normality spplied te the Indivljdul estlilalon abnorpteon and track-length tetf cycle values aerg

the hi gollislen) eyct values appear nfrmatty dIstributed at the ff percent confidence tlevlthe ktebeorption) *ycle vatug appear nermalty di tributed at the 9f prent enfidonce levethe Uttrh length) cycle veluss eppear normally distributed at the n prer nt cenfidefnce level

.......................................................... ............................................. ?.............................. --'''-'''''' '''''T''''''''''''

Jun 07 [email protected] 1996 file ""mes a30*12b.sum SSOOOOCO.917T1-0200-10016 IRv Co LTTACMUMI L. tl * page a

the final etimated canbined eelliuionabsorptien/treck Lenth koff * .99753 with an estimated standard deviation of .00095

the eastlated 4, IS, & II percent keff cenfidence interval. ore .U996S to .19914, ."S&4 to .99942. *nd .n502 to 1.00004

the *stimated coltaleonabsorptien mutran removal Lifetime * 6.1SE-05 ascends with an estimated standard deviatlon Of 1.52E3.7

................................................................................................................................

I

JMn 07 10.93 1996 PIIS laMe: o30a128e-tm ORA0DDDD-01717-0200-90006 REV 00 *TTACIEIT LXXIII * page I

Ihnn verlto *a IdNII X§a 821^ @" O*.- *-*--****-- -**-**-*- ***-aprebid * 64/24/96 10:46tO6IWSe30*12n eutp-eOelzaO

1- crfletld Crtticelity-Sphort of Transmuted 3.0E locuD 20S Yater 11.65 U-lp 022- C Critical Me Optimizatlen tenfireation3. C4- C 3P3311

5: I I r:I134813 :S- -1 IX~tIM:j S liranium/luff/Uater

-: et OUTSIDE WOaLt9- so a 2 l1.PIN-o a VoYd

11- C 3UINFAC5512: 1 to0 345 ISSILE I*sUltIS- a sto 40 C IEFLECTOR14- t

'16- J0IM U'T.- 10E 4000 1 30 13D1I C 1ttI 0 0 1 1 0-10 0 0 1

20 e ~~~~~~1 1 * I 1 .1 0 119- C 1 I e .I:1 e 1-06-1

22 CC 11 1 .11 1 .1.1 1 1-1,13: 111 9223 04.0 o9s26 y 92235.c 01.4C6663. 922.50 1.327212-5 S FI9223C.50 262975 93237 .Oc 1.I152424 H0016.51 1.042554-3 At25- .1001 De 1.162107-2 a n26- l DC140000 1,1 6297-2 13027.90C 2.65602-3 t Ca27- U4000j0 C.U3522646 1200D.5D0C J36407-4 2t000.50C 5.23016-4 92S- 1102S. 00 4.025190 4 l9000.50C 4.64111-4 go9- N71 LMTI.S11 S Wm30- 3 1001 OCI.500 .S33 14000.1.0C 1.319341-2 13027.50C 1.015357-3 S at

31- 8016.100 .931496-j32- 26000. 1S .623559- 1300O.1OC 2.67121-4 20000.50c 6.567122-4 1 I33- 11023.50C 4.553322-4 19000.110C .429990-4 s34: 11Ni LWlL 611 M35- PRINT

Initial soIrce fees file .troI'eff results fort Perflld Criticallty - Sphere of Treneauted 3.0! 20O1D 202 Mater 11.65 Ui-Up 02 probld * 4124/96 146"s:06

the Initial flesien neutron source distribution uas read from the eretp fite naed eretp -th eriticality preblte was scheduted to skip 50 aelas and run a total of 130T ycles with nominally 4000o nutrons erryleths problem has run 30 Inactive cyce witI 1227Z neutron histories and 100 active yct wles th 39955 nrutren hIstori a.

th~s eelculetlen las sleeted th s rquted ruiber of "ff cr tes using a total of S19227 flesion neutron source histories.ell eelia With f Iealmab a. materl mere *rted and had fission neutron source points.

the results of the t test for normality applied to the individual collieien. absorption and trsck-length toff cycle vatues ares

the hI ctllslon) *eclto values appear normally distrlbuted at the 9 percent cnfidence level. but not at tS percentthe hibsoerption) eycie walves apear norm ay dstrbuted at the 95 pereent ent fiance level

morning. the khtrk lengthl cycle values do not appear normally dietributed at the 99 percent confidence lIvel

...................................................................................................................................

Jun I? 10:15 1996 Pit*Ilme: soal2sa.m uIAOOCOOO-G17T1-0200.S001m elE S ATWACNeT LXIMIII n wa ge 2

the final estimated .omined selttlalen/aborptaiVtractlensth keft a 1.00036 with an astimated standard devlation of .30054

the estimated ". I5. I 9 Percent eft nenfidenct Intervals are .19952 to 1.00120. .n9e69 to 1.3203. and .99l: te 1.30256

the stimated eanlelealabsorption hutrn rnovat liftiml a 6.09E-05 *conds with an eatiuted standard deviation of 1.491-0.................................................................................................................................

Jun er 10:07 1996 file Rames a3Ol2c.m 4U3ODOD-S11Te-0200-00014 IEl 00 ATTAMCKEeT LDXIW Page 1

1acnp verieon 4a SId-i/011 442/ 14.10,50amOO*O*-SOO---ee*OOOOO* eO55O5-O*5OOOOOOOOO,*OamOOO*O-g- prbid * 4/24/96 14s50.50

IW&aS30*12c autpus30allce

1- FerField Criticality - Sere ot Traneauted L.IE ZOsiD 20D Vater 11.65 U-Sp t22- C Critical $ize Optim satian Confirmation3- C4. C SPMECIS. 1 1J43913BS-2 -1 f1112Plu1 S UranIum/TTuff/Water4- 5 s ;.t12,224000.2 I -2 gIRpsol a luff/Water Ref lecter7- C5- C OITSIZO WbRL1. J O IKPII-0 a Vold

11- C SURt*CES12- I to 365 * FISSILI IPN7E313- a t 425 I IEFLECTIOR14- C15-16- IODE KIT- ICDD0 6000 1 0o I5016- C 9120 0664 100 -166 10 5 0-15 66 1 519- C I 1 I I 0 1 e t 1 I20- C t1 a 11 * 1 I I -1 oI21- C01 1 -1 1 0 1 0I-22- C 1 1 i : -1.1 123- ttl 9224.soc 4646952-J jZ5 tJOC j.S46645.5 n2236s50c 1.3272124 Sp e26- 9228.5 2.1295- . 0C I021n c .1U52422-6 0 £14C 6.66s2s55-2 AtZs- loci50 Ia6104Sn26- 14000.100 1. :14429I 7'- 2 130127.50C 2.645602-3 SCe27- tO00 .SC 1.435224.6 12000.300 j.64807 4 20000.DO C 5.t23016-4 V I28- 110253 p0 4.0251904 19R00.500 .64U111-4 $ 3029- 311 LUTE~ IS we30- 33 1001.5DC 1.337225-2 14000.50C 1.319341-2 13027.0c S.015387-1 S Ca

2- 2 '600055SC .46523559- 1O s00.50c 2.7S021-4 20000.SOC 6.507122-4 6 lo33. 11C23.30c S .*S3332-4 19000.50C 6.42mo94 S34- IITS L.lTlbIT I 1135. PRINTI initiel soure froe fl rt

lkeff results fars PerField Criticality Sphere of Transmuted 3.6E 20411 20D Vater 11.43 U-Up 02 probid * U424/96 14s1C se

the initial ftisaen neutron eource distributlin wae read free the eretp fite d erctpthe eritleality problem was echeduled t ip 30 eelea end run a total of 130 e wuth nomInally 400 neutrons per cycle.this problem ba run 30 inactive cycles uilt il neutren hieterie and 100 actiWv cyclec uith 60391 neutren isterles.

this calculation haa completed the requsted nhbr of *off cycles using a total of 521672 fis*len Meutrn euree hieteriee.*l1 *ette with fiessienble material were sampled end had flee in neutren source points.

the resutte of the a teat for normattty applied te the individual eelllaisn. absorption, and track-tength heft cycle values ares

the NC aellale n) ctyce values appear normally distributed at the 93 percent cenfidence levelthe *(ebaerptien) cycle values appear normaIly distributed at the 95 percent confidence levelthe tark tength) ycte values appear normally distributed at te 95 percent enfltience level

,,. . . . . . .. . . . . . . ;. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .

Jun 07 tOnr 1f File Ham: 43Oe12c.sw tIAOOO@@@.ll7I?.SZO@401 1EV SO ATr*Nflt tmIV - Pge A

the final estimated emoblind Geetioi cabsteption/trock-tenith koff * .69 wlit a estimated standard Eeviattcn of .00a98

the estimated U. 9, I 9 pereent koff cenf dence Interals are .9M to .9967. .9674 to 1.00061. Nd .9610' to 1.50127

the estimated cttlelon/abaerption neutren removal ltfetim a s6.041-OS sacends mith n estimated standard deialtlon of 1.441-07

..................................................................................................................................

Jun 07 100 1996 Fl Itolmet o0.2d.oum S3AOOoOO-1717-1200-00016 lSV 60 ATTACIMEMT LUnY page 1

iseno version 4. 1d-10101/93 642496152349*e.s3r O*u04c200 . prebid * 64/24/96 15i2349Inp-sS~el2d euepes3el2do

1- araleld Criticality -sepre of Transmuted 3.03 2001 20S Water 11.5S U-tp 02a- t Critical Olte Optimisztion Confirmation3- 24- C SFEtE

3 1 .13439813033-2 *1 INIU-1 S UranluTuffiftter1: g 3 r.1032922 4000Z I -2 Imtum S Tuftf/uater lefuctor7. C8- C GITSIOE WORLD9. 30 0 2 ilPlN-O S Void10-II. C SISJACES12. I to 35 5 FISSIL9 SF53132- t' go gst * tlEtF l tC k13. 2 *0 445 4 *3FL50t0114- CIs-16- wOol t17* SCDD3 4000 1 10 ISO1l e KSIc Ie O 13 e 1 0 e _1 I I I I a C_1 0 0 et I 0

2D e 1 1 160 1 1 --0 121 6 e I 1 -1 1 1 I at2- CIt I 1 1 .1 * .1 1 1 1S24 ml 223.5 0 .406952.1 91r sc.50C 1 3272112 9P *t

2C 762.47S 911r.SOC 6.165242.4 O1 m- At25- 1001: 10C 1 .162107.1 Sa26- 14000. 0C .1"297- 15027.30C 2.656502-3 S Ce27- 36000.55 .435226-4 120001O0C 8.3648074 20000.50C 5.323016-4 m *l25- n1o :.300 *.25190-4 19000.5 C 5.45111-4 0 SO29. NTI LMIS.81T S Mat9- 53 1001.CC 1.337225.t 14000.50C 1.319341.2 13027.50C 3.615387.3 * Cm31- 201.50 3.931496- V I32- 2J000.55 J23559 4 12000.50C 2.475121-4 280000.0C 6.567t224 , 3O33- 11023050C 4.553382-4 19000.500 4.42999O-4 S34- MT3 LUTI.SIT I V.33- PRINT

i Initial sourse from fit., orIkeft resulte ft Prtield -ri: * ree of Transmuted 3.eE 20C0 20S Water 11.65 Y-tp 62 probid * 6/24/96 15t20 4

the Initial fission neutron source dietribution was read freo the rretp file Rooed oretpthe eriticolity problem was scheduled to skit 30 cycles *rd rum a totcl *f 1O yes with norinrlly 4600 neutrons eote.this problem has run St inactive yctleo it* 120407 eutr'n lhstories erd C0 active *ycles with 399728 neutren histories.

this olcuwletiun has eemlted thec requested number of keff cycles uine a total of 520135 fission neutron source histories.*1i cglle with files eb * ateorel mere stapled and had fission neutron soureb points.

the results of the 1 test for normality pnlted to the individual collision, abterptlen. end tracktlesnth htaf cycle values erem

the tkg erpllisin) h'ct: velus appear norallty distributed at the 93 percent enf ldenc levelth ha Vtpisn) sycl vatus epper normally distributed at the 95 porte t snf Idante level

the kttrt length) oyclo we us appear normally distributed at the 95 percent *lnfidence level

............................................................................................................................................... T..........................._

Jun 6 10MS 1996 File dame e elld.rsm vUDOOtDZ t0010-SZO-IW 6l 6 ATTACRENT LXXIV - Pege I

the finel estimated eobined eoltitioebshuritlintreck-longth ktff - 1.80193 with an estimated stendard deimtiun of .00092

the estleated ", V5, I 9 percent tiff confidence Intervls ar 1.00106 te 1.00290. 1.Z0015 to 1.00330, end .M56 to 1.0040

the estimated celtlelonlebserptien neutren rmovel lifetime a .990 seend with en estleted etanderd deviation of 1t34-07

..................................................................................................................................

4

Jun t6 13106 1996 file Earer 9S02WA.Sm R3AOO00 0001717-020- 60016 REV *0 £TT*CKNEXT LXXNVI * Pae I

**- **********ne****- ***-*- ******-*-** * *-*** se- probid * OS2996 MUZMsRIinp-e3020mh eoutp - 7OMO

1- For-Filtd CriticatI Gtudo - 3.OS /IC tiff0/t * 47 11201 15n U02 (so20Oh)a3 C Cateios Ilfl.? Ir S 111*e I porosity e sphere ur d tut5- C CELL EECIFICCATlOS14. C IUEER tATER 1REION

iuE0406gt~ ~ I 1:11"1 '°!a 11M'"!

1S U IACE ttERLtlD lC 9nFACg SPECIFJEATiCUE

1- W 1 St NEtE FUEL 301E2 tO 21 * Itil SUER FUEL oltE13-14- e£E15 "C0 %000 I. 3575

C ERIC a ' 51 50 6 6 I -to I I 39 I 201S 00-55 e 10 -40IT- C e -s50e - 30 -13 -1e 60 e -25 -30 -15 -S 5 S e I5 301 ?It C IATERIAL SPECIFICATIONS19- * 7 vets woter In eetlleo ille tuftf r .5 .15 vol1 Ue30 a 3.n OrIginat Enricehent/ 30 6MIT deceyed to Uranium soteep$E1 *i 1001.lCc 3.471107 - 6014.5Cc 4.186941- 11023.50c 3. 55762 432- 12000. INc S * s,15164 1027. cc 1. $7395 34000.50c e.564310-3U3- 1900.50c 4.173934- 300e.5Cc 4.27534-4 36000.55 1.653910.42U4 92234.50. S . 020937 92235.5Oc 7.172412-S nu236.sCc 1.716222-525 92236.50c 3.572613-3 93237.5Cc 4.99296-626- atl ltre.lt27- a 0 vt1 water In cmlige mills tuff233 e2 II.JOc 03.142479*- 1016.5Cc 4.63067-2 11023.5Cc 3.47767-429- 12000.5Cc 2.642960 4 13027.5Cc 3.02817-3 14000.5c 1.607566-230- 19000.5Cc 4.910511-4 20000.5Cc 1.630511-4 36000.15 1.339694-31- Eta twtr.olt32- P:tIT

I initial surce tree tile eretOIkef n result fort Wer--Field Critical ty Study - L.6s /n0 6/e t - 4 11 20/ 15s UC2 s3C020) prebed a 65/*9/96 12t5S:tl

the initial ilesson neutron source distribution vie reed freo the sretp file ared a"rtp"thecriticatlity problem was echeduled to skip t5 cycles emd run a total of 75 *ycw s Ith nominally 4eCo neutron pr cycle.thi problem has run 35 Inactive cycles witt 100223 neutren hietoreee end SO active "yces with 300748 neutron h 9etarlee.

thile celcutatien has coateted the requested number of kot cycles using e total of 300971 ftesion neutron source hiutoris*.all sells with fissionable Smateriel ware sptld end had fission neutron erurce points.

the resultt *f the u tect for normality appiled to the Indlviduel collieien, ebsorption, end track-tlngth teff t ycle vatles are:

the hC collision) cycle vatues appeor normally distributed at the 95 percent confidence levelthe ttabsorptlen cycle values appear normally distributed at the 95 percent confidence levelthe *tr a-h length ccle values appear normally distributed at the 95 percent confidence wle

................................. .................................................................................................

I the final e t1"ated mombined WIioerptnt atlnt t * 987r uuthi an *stt-cted standcrd dwevition of COIs I

Jun It 13:16 t96 fil Uaces sSC2zah.sum REAVooao- A1717-S200*@0016 at TatilxT "hvI - p a& a

the ostImated 48, 9, & 9 percent keff confidence intervals are .933 to .96939, .981 to .9092. ad .M7 to .9194

the estimated soltlslen/abserption neutron removsL lifetime a 7.801-5 aseonds with on estimated standard eviatien of 2.u4e7............................................................................................................ ..............................................:

jun 0e 13.17 1996 ftie Earn: SO20-ai.sa BIeAOCOOO-0-1717-0200-00016 REV 0 ATTACNENIT LXXVII * Page 1

t ern * egts en 4c e,4dsiO~!l/3

,,**te 05/29/ 16:44.20 Fprebid * 5129/96 14144320

m"psO0zom eutpeSoz208lO

1- F r-Ylc~d Criticality study - 3.tS /20 6110/mt * 47$ N20/ 30 U502 CsS02001132 C Ctlieo Sills Taff 1.117 Wee .47 porosity sphere surrounded by tuff3. C CELL BFICIFiCATIOU1S4- C I0E3 IATUE REEIOI5- 1 6.35499-3 1 327:3.16 2 2 *.610406-2 1 -2 iN1PsE-17- C OWTJZSCMWORLD* 3 a a IMPIN-09

C e URFACtE SECIFICATIEL ROI t 61 S Int1PHl 33

2 to *21 II Itht FUES 2tit

14 MOOG a1S- KCcOO *eoo 1 IS nS1- c esIc ie I I a e0 let0 * 0 . a29 0 g is 415 -5S -le e -4eI?- C e *s0 -to *30 e -13 a *lB e0 I a -2s *s0 -15 *S6 S I e le So IT1S C SATEEAL PECIFICATIONS19e 47 etI water In catico gillt tueff) x .t0 30 volt It0230 e 1J.t0K n melt Inrnichunt/ 20 6i0mT yad to m n eter21 El 100 .50. j.513963 2 016. 50. '.Z2UU2. 2 llO2.Se 2.731393-422 13000.50J 1.C43684 13027.0.c 1.64254- 14000.5C0c 6.060527-3U33 19000.50c .9 09-4 50000.10. 24"0-4 26000.55e. 9.19150-S24. 92234.50. I.I612. 2235. 0c 9. 3216-5 92236.50c 2.23296-535. 92236.50c 4.743750-3 93257.50. 5.457314-626- itl lutr.Clt27. a 30 vot% water In calice Mills tuft2e. *2 1001.50c 3.142479-1 6016.50c *.t63067r2 11023.0a 3.4M767-429- 13000.50. 2OU960-4 13027.50c 1.302317-3 14000.50 .607564-230- l19OO.%l000a 10511-4 20000.50c 5.030511-4 M6000.55. 1.259694-431. Mt lwtr.Sz t32- PRINTI Initial source from f Ile oretp

Ikoff reaulte for for-flield CrlticaItty Study 5 3.0e ne r/t - 4 It 20/ 20S 1U02 (53020.1) probid * 05/39/96 14:44:20

the Initial fission neutron source distribution was read from the erctp file wood cretpthe criticelity preblee mamu cheduled to ski p 25 cyes eW run a total of IS syetee with minimalty 4000 neutrons per eycle.this problem has run 35 inactive cycles with 100130 neutron hietories and 50 active cylegs with 19972 neutron isterlec.

this calculation hal cr pleted the reqsted amber of hoff cycles using a total of 299848 fission mcutron *surce histories.alt l Itcl ith teneble materiel were amtld and had fiasion neutron source points.

the results of the w teat for normality applied to the Individual collleionn absorption, and track-length koff cycle value. oreX

the RC scticion) cycle values appear normally distributed at tha 95 precnt enfidence levelthe Mtabsterptin) sycle values appear normally distributed at the 95 percent confIdence levelth trk length) cycle values appear normally distributed at the 95 percent confidence l1vl

...................................................................................................................................

|the finat *sti-eted combtned cctiolel a~cptlmtecelwicngtb keff - .n925 with an * tlcat-d st nderd deiation of .0015r |

Jun 06 ISO? I99 fle N11ao s3020ne .uaa RSAOOOEOS17?SZOO.SO:1 32 09 £TTACUNET LXXXVII - page I

the estimated 68. 95. & 9 percent kaff cenfidmnce Intervals are .99087 to ."402. .98929 to .99560. and .9824 to .99W66the estimated cettislemtueborption neutron removal lifetime * 6.729-GS seconds with an estimated standard deviation of SA2E.E-7

................................................................................. ....................................................................................................

May 24 67015 1996 file Sams SSId5Sl.oum A UAD00 -1717-200-00016 UV 10 A1 C05M35T 11LXUVII Page 1

Icng versien 4a d.10t1093 05/01/96 16i2431iprobid * 15161196 1624,13

IqesS530i outpesSsoio

1. for-Fislo Crtlicatity Stlud * J.SA /30 go /at . SoX 181/ 141 U02 (935301)2- C Cal tc tlls Tlf 1.746 stea .306 porosity - ophere surrounded by tuft5- C CELL 3PECIVICAIIOIS4. C INNER 114111 RESIGN

I 1 e-1 1 i8I '!

4: 11P C uT 1oteo

10: C SURFACE SPECIFICAt1ION11- 1 o 120 1 1Et FUEL 2=C72 2 o too * IEIIEt WEL ZONE

14 OW0E IIS SCOO 4000 1.116 C BEC 66 1s 6610 6e -to e29 6 I05 6 0 e5 .106 -e1T- C e *S 20 -10 e13 I 610 14U e e 6 .5 . .16 I 5 10e le I1J C MATEIAL SPECIFICATIONS19- 6 130 votX uter in ealie MI.tl uff) * .6 .14 votS U0220- e S.55 Cre1 n el Crrlentr 30 6 decayd to Uranium Isoteoes21 T 1 1001.S0c .725021-2 601.5Cc 3035.2 11023.5Cc .915909-422- 12000.50c3 .30060 4. 1J027.5Cc .932R3- 1400U.5 1.13463-223. 19000.5Cc 5 * 2094 p000 5Cc .66n5-4 26000.55c 1.396261.424- 922S 4 c 1.21125. *9223S.1c 4.4794 S35 92236.50c 2.236042.1253 92233.1Cc S.327M-3 93237.15Cc 6.127100-626 mntl Iutr.4It

267 .2 1001.5C0c 26053-2 6016 c .65102-2 11023.5Cc 4.553332-429- 12000.5Cc 2.673121-4 13027.00cc 1.615367-3 14100I50c1e.319341230 t 19000.5c *.2999- 20000. c6.537122-4 5 68eo Sec 1.O 63559-31. .22 lutr.61t32- PZImt

1 Initial ource few file aretIkeff weaulte few: Far-Field Critiliathy Study - 3.1 D /30 W81t - 30s 1120/ 141 U02 4,35301) probid a 635I1I96 14:24:18

the Initial flttin neutron source distribution read from the gratp is1f saged eretpthe criticality problem Was acbedulod to ahip 20 syal nd run a tot1 an 7 pyes with nominally 4000 nutrene peryclthis proble-n has run 20 inactiv, cycle uith 791 neutron histories and 55 active cycles Kith 219362 noutren histerl a.

this calculation hbs *espleted the requested umber of keft aylean usIng a total Af 29343 fission nsutren asree histories.al csells with fig ilonabe materiel usre sampled and abd fled en nutron ecure poInt.

the results of the u test for nortality Applied to the Individual collision, absorption, end treckhtongth heft veiae values ares

the hIt solelesn) cycle values appear normalty detributed ot the 95 per:ent sonfidence levelthe htebaorptlen) eyle valws appear neormlly dis:ltributed at the 5 parcant een idenco leveltho ttrk leWNthW cYtc valugs appear normllty ditributed at the 5 percent cenfdednce level

...................................................................................................................................

|the MNet stlmted combinod eottielen/absorptloa~treck-lengtb Ralf a .2207 with an estiel ted *tendsrt devletion of .e0147|

Pay 84 "705l t996 File ine:t aSS30i.esu UACCCCOO8OOt 0l740200.OD01 itE S0 aTyACINEm L3XNVIII * Page 2

Ithe estUited a. 95, II 9 percent toff eonfidence Intertvsl are MMe to *35, .97913 to .9ss2, nd VW MIs to .e360

the estimated seLtiain/absorptien neutren renval. tlifetime * a6.40E-5 ascends with en ealtiated standard devilaton of I.63E-8 I....................................................................... U..........................................................

may 24 07112 1M Fite Dea e3SS30h.sui SA8800C 0-01717-S280-S0816 REV O0 ATTAuNNENT LXXXIX Pase 1

I" version 4a td-10/01193 0310! *Mo*O*O5*eee 15:1S*M*ee probid * 6/6196 11:33:40iuipsea330h eut tSS3Oho

1- For-Field CrItieatl Study * 3.51 In gy/pt S3X 120/ 14X u02 (S3330h)a- C cettee wilfts tuff I.ru g/e .306 poreslty - sphere surrounded by tuff3- C CELL IPECIFiCATiOXii.- C iNNER WATER REGION

7. C OUTSIDE SOILS7- 3 * a mlOtt <9.

l0- e SUFA1 e 6SF38C6ICAT901211- 1 so I38 6 INNER FUEL ZONE12- a2 t Its 19 INNERMEL SOlE

14- NODE 111- 18601 48008I1.0 I'16- C SE IIC a 16 01 2 * 26 0 26 I a I -100 e1017- C C -* t-0 -IC I -13 e 10 14 e I 15 -1C -S -14 5 S O 0 10 IT1U- C JIEAAL SPECIFICATIONS19- a wa0 it water la cealfa ai|le x .6 .14 veat uo220- * I.2 Ori Inal Enriehmet/ 0 nWn a deayed to Uranium 1eoter21- el 10 0 2S02i. 516Sc 4.*33035-Z 11023.S0e 3.91989-422- t; oo.30c: 1 0604- I 027.SCc 2 S923S3* 14400.165 1.13433-2

23 §~~908.0 5.- ' i2979 230500.c *644925-4 456000ja ee 1.39261 4s134: Mae223.3cI.125 I2333c :493i5 2306. 0,: 3.336042-152S- c221. . r2m9-3 93237. c 6.127100-426- itl tltr.61t

27- Vel% water in ntle. MI*lt luff21t *2 1001.50. .c05138-2 1016.Sc 4.263302-2 11023.50c 4.133332-4

2V: 12000.58. 1.673131.4 13082718 .0e 533 73 14080.0.0o 1.319341-30- 1900-.30e 4.4219904 0o00 C S .37122-4 2600a a. 1 623S9-431. ut2 tutt.01t32- PRINTI initial esource ft.. file spotp

lkeff results ferl Far-Ieltd Critleeathy Study * 3.31 /no 5W/ut - 30s *20/ 141 U02 CS3330h) prebhd * 6S101/9 15:33.40

the initial flee.io nNutren eouree dietributien ne read fre. the eretp file named sretpthe criticle ty preblem me scheduled to skip 2 cyles and run a totat of n cycles VIAth omInaty 4600 neutredw pr ycle.this problem has run 30 inactive cycles with 1134 neutron tle orles and 53 aetl cysles with 31968 neutron laetereI.

tfis celeuletien has empleted the requested number of ketf cyclee uin a toteael 29904 flesIen neutren *eure Ietertes.all eelle wlth lesienablo material were Sampled end had fleeiin neutren ouree pointe.

the results ef the u test for normatity epplied to the Individuel celliien, n beerptiern and treck-teeth keff cycle vaelue area

the hl *eticien) cycle Valwas appeer normally dietributed at the 93 percent tenfidcnce levelthe hi Iaeorptlen) cycle valvs appear normally dietributed at the f percent eenftdence levelthe kitIrk ltngth) yele vlwes ppear normally distributed at the 9f percent confidence level

f..................................................................................................................................

|thwe f $net estimted eabind settislt aorptlen/track-tengtil kof f a .n8tr wit1 an estimated standa devietien of .00107

Nary 24 0712 1996 fits cams *.53.h.s B3AOttttO.S171?-S200-.001C REUV 00 LTTACIREUIT EIz z Page I

I the estimatod 68. 93. I 9 perent kelt .enfidenee Intervals are .95u6 to .9As2, .9559 to .99. eW .954 3 to .9060 1the estimated elilelenlabserption leutron removal lifetime a 6.40k-.O seconds with an eatimated atuaerd deviation of 2.653.071

...

-

Kay 24 0711 199 file I1mes 3SIOg.stm UAOOOOCC-6ll7I7200.O0016 KEY CO ATIACNEST 30 * Page I

1.ene version 4a l 14o10/9m3 03 /e6 14:19:2*-* *- *---*-----*-@ **- -e ***-**--*-*--2**-*- probid * U/Ol,'0 14:19:521W.eX35og outpeaSS30to

I. for-pfltd eritlieelty Stud - I /30 go iat - o 0 IoI 1 0a wz e3530s)3- S CaIle ISE s tu f 1.r7 lge .306 poreslty * sphre surrouned by tuff3- C CELL SPEUCIICATIC114. C SINER WATER 355301S. 1 1 S.:023102 *1 IIIN186. 3 3 8.111311.2 1 -2 lIfs~r- e ~mtsuuio WtUL

lo- C VUPACE SPECIVICATII0S11 I SC 134 S IlEtR MEL tWE12- 2 to 194 S IllEt FWL 200E13-14- MEC U15- MCCC 4000 116- C ZINC 6 101" 0 la I .-20 I t 29 6 205 6 - -10 I 1017- C e-S -to -10 I 613 6 - 1 t 0 -15 *10 - -16 S5 6 1010 l18- C IRATR1AL SPECEUICATIOIS19- * vt% vaster ln .. ll.. Bills tuff) S .1U .14 volt u0220- .S original nrlukhMntl 30 310411t docad to Uranium motorxs21- *1 101.5 cc 1.1so21-2 a016.5Cc .333035- 1023.50c 3.91590 -422- 120001.5c M.300604-4 13027.10c 1.593233-3 14000.50c 1.134433-a33- 19000.Cc 5.29791-4 20000.50c 5.664925-4 26000o.5c 1.:9261.4234 9ZZ34.10c 1.216825-S 9223S.50c 6.4794345 z236.c 2.S 6042-52S- 223S.sCc 3.312772-s 93237.1Cc 6.127100-636- tl laetr.6lt27- a 30 v.2X water In calio. M111 tuff25. m2 1001.5Cc 3.005853-2 g016.10c 4.236502-2 11023.50C 4.553332-429. 12000.5Cc 3.6n11-4 1S027.5Cc 3.01537-3 14000.C c 1.319341-230- 19000.5Cc .449990-4 20000.10c 6.537122-4 26000.5e 1.623SS9-431- NO lmtr.Slt32- PRINT

I Initial source fri_ fIII strIkeff rmsults fori far-Fi1ld CitIol 1ty Stud -y 3.5 /30 mm/at - 302 N201 14 12 (530a) pnrobld * 051019 14.9:52

the Initial flsson neutron source distribution esr road from the erstp fite nosed aretpthe eriticality preble. we scheduled to skit 20 c leV end rum a total of I5 ivlep with inoinelly 4000 neutrons pre rycl.this problem has rum 20 Incetlve oycles lth I 794 feutren histories Vd S5 active eyceas moth 219457 nutron ht raes.

this colculetlo has completed the re ted trubor et hft e aing s total of *29929 fission neutron *oure histeolres.elt *cllo cub fissionabl matorlel wer. sepld and had fl son neutron soure points.

the result. of the u test for normality applied to the individual eollIslon, *borptlon. and track-length hoff cycle values acot

the RI solliolon) cycls values ippaor norfally dletributed et the 95 peruent confidenco tevetthe Riebaorptlon) cycl values eppeir normally distrlbuted at the 95 scruent onfideneo levtthe Bttrk Wenth) syc an slam ppeor norm lly distributed at the 5 rernt onfidenc lvt

...................................................................................................................................

| the f*1M1 estiuaetd oemblmd cattilelJonbsorptiontraek-longth koff * ."010 with an estimated otadrd devition of C0127 |

iv 1 ~~~~~~~~~~~~~4Xay 24 07,11 1"6 File usual s.535g.smm 3111000000.l11767-200-1SSO16 REV SO A11*C3NE31 XC -Pago a

Key 23 16.t3 I9 Fite Ktnee SS3Cf.6ue E5AOO0OO-17174-200-S0016 KEY aC nTAIACNIEIT 3Cl * Pege I

Imen? verslen lea 18.s10/0093 @5/01196 11.12.55"*neeoin . .m4Omem..............*S "m'-m- * prebid * CS/01/96 11.321SMInp-d3S30t outp-M35310

1- far-Field Critlleilt, Study - 3.SX O W1 1t * 30X 32/ 14S U02 1e3530f)2- t Cellco llis luff ..746 m/ss .506 porosity * sphore surrounded by tuff3- t CELL SPtCIFiCAIZOES4- C w3ill WATER UNION35- I 1 S0302 . N..S- 2 2 a .:11211-2 1 -2 IPEt7. C wIit il1ORLD5- 5 5 teo2-C S.9.

tO. C VJIFACE SPECIFICATIONS11- 1 to 140 S ItNER niEtIOIE12- 2 *0 to 0 to * INNER FUEL 313-14- K001 51S- tecD0 4000 1. 20 7n16- C nSi S a I e e0 I I 0 -to e n9 * 20 OS e -S -106 e oIT- C I -S -2D -10D -1* I -1 14 0 e *1S -1 - -16 s s e IC la IT12- C 14A130I1L SPECIFICATIONS19- a invotvotertoer b Bn 5t11, EIte tuft) x .36 .14 velt 110220- c PSS Orgllnal lnrllhentl SD tPY02rT deyed to Urani Isotopeas21- ml 1013 Cc 1.725021-2 *016 c S :55.j 11023.5Cc 5.9159 9422- 12000.130c 2.300604-4 13027.1Sc 2. - l4000.50c 1.134633-223- 19000.1Sc S.129791-4 20000.SeC S.444925-4 26000.55e 1.96261-424- 92234.S0c 1.216825-6 92235.SCc *.4t9U34-5 92236Cc .2S042-I25- 92238.Cc, 3.327729-3 9323.1Cc 4.127100-626- *tl Iutrp.1t27- c o vtl P9 tcr In catlco Kiltl tuft28- e2 1001.1Cc 3.6058382 016. 50e.24S02-2 11023.9Cc 4.153332-429- 1 S000.1c 2.675181-4 13027.1c 3.1S37-3 14000.1Cc 1.319341-230- 19000.SCc .429990-4 *000. Cc 6.517122-4 26000. 5Sc 1.23559-431- *t2 tltr.6lt32. P1131

inItial 4ource trom tile cret7tefft results tort r-Fisld Critiscl ty Study - 3.53 /30 £0mD t - 30e $20/ 143 002 0e3S3 prabid * 1/I/96 M1.32UM

the Initial fission neutron *curec distribution was rad tre- the Brctp tile naed *rctpthe citleslity problem es *scheduld ts ski 20 s *s end run t totl of n Clc Ith nominally 4000 neutrons per cyce.thim problem hbs rn 20 inactive ycles mt 7630 neutron htortes and S ectlw eyclee with 21922 neutron listorlee.

thle alsulatlon has cemleted the requested umber of holf trcest using a tltel of 398872 ttssen 1 eutren source histeriee.stl tells with fissIonable material were tampled and had tisson neutron source points.

the results of the v test ttr normality applied to the Individual sclllsien, aseorptin. and trect-longth heft cycle values ares

the hI collision) tyclc values eppeor normally dietributed at the 95 percent confidence lteelthe Itabtorptlon) cycl values appoer normally distrIbuted *t thIa 9 porcent sentf bne lel hut not et *5 percentthe Wit rlenteth) eyce values apper normally distributed et the 95 percent sentidtenc leve

............ ...................final etmaed .ledae...../.s..l..trch-enthhef - *94.. il. an e.timated atondrd atie of .6130

|tbe final estimated ce bteled *ctitlonlenbeorptlenltraek-lonoth t tt * .nA4 Owdth an estlmated stadrd debviation of .eols3

May 33 l6g39 199k file Urng $3530f.at. 13A000000.0171?40200-S00016 REV SE *TTAZUKUIT SCI IPalo a

the estimated Ul. 9S. II IN PO-~ft &;ff bconfidence intereas, are .9932 to .9sm1 .9919 to .99721 am~ .9911 to ."9305

I isestimated caltieienfabasrption MAUtlef remova.t tifetime a £.2314S3 macends With an est tested standard dewlatien of aIt.7

Ney 23 16:29 1996 File lam*e d3530b.e. UAODOOO0-0171l .200-00016 StY eo ATTACINIIT ICII Page I

Inpa931133b outp-&3530bo prebid a 64117/96 68 4:32

InpeaSXlb *vtpnaS3CXb0

1. Fer-Field Srilealiti St 3.52/0 nSe Wtt - 30S 320/ 14 t UQ2 ta3530b2 t talle Ut s a uttte T 1 .46 1 /ee *36 peresity *phere vurrundad by tuff

4. C 133111 WATER 1E343031- 1 1 e.002310- I1 IlPl1el6- 2 2 S.ltt2tt 2 1 3 l - "-'

' s *S IntuE.07: uT 101 WORLD

10 5 51.15160 IVICIFISATIONSI1 I SooIICa 110 13311 FUEL go31I-14 NMIt *15- ScODE 40001I7ST16 5 IC O 0 6 e010 e 0 0 *a I9 e 20S 0e a 5 -10 I tItr C * -S-*2-0 IOe e-I36- l0 14 0 * - S 10 - 16 S S e 10 10 IT1i C . ATNIA itIAL IC CAT1301V IO v&30 wela ter In calice Ctlls tuff) x .06 .14 weIt U022D- e S.SS original I." rhn nt/ SWIt de!ejd *e Uranium lotpes

120000.1c I. 00604- 13027. 1 93233. 3 14000.soc 1.13U6 219000.S0c 1.S29791-4 w000 Oc .64925 4 26000.15. 1.396261-492234.ScOc1.314825. . 479436- 92236.10c 2.336042-S

-i: 9233.C Sc 3.327729r 237 c 6.127100-*26. it lt.Olt

2tter in saelet te I euf*2 o10la.I0. OSU5t 2 9011 Jc 4.365802.2 11023.30. 4.1533-4

29. 120.0:c 7.675121.4 13027.10c 3.115387J3 14000.10c 1.3 1P41- 2

305 12 9000. 0. .4m904 20000. Dc 4. 87122-4 26000. Se .62 559-431. ez lutr.Olt32- P133x

1 initial source free file oretptheff esulta far: Far-eletd Criticalitv Study - 3.51 no gSW/mt - 30h 020J 14U U02 (e3S3Ob) pirbid - 66/1T/96 061s432

the Initial fsston neutron source distributlen wae reod fr-e the 5rsip fi * med eretpth criticaltyt Y olame wa e aduled to eki p enlee and run a teltal o 37 cycles witi nominally 4500 neutrons ger cycle.thIa problem he run r Inactive cycles It 37939 foutren histeries nd 30 active sycles withl 119653 neutren ihsteries.

this calculation has cmpeteod the retquestd nutber of keff cyc les lna a total of 147597 flasser neutron course hieteries.all *ells with flsaloable miterial were sampled and had fission neutron eource points.

the resultt of the " test far normality &ppled to the individual etllielon. abserptlion and track-eenlth keff 9ycte vatues eros

the kC eollisien) cycle vlwues appear normally distributed at the 9S percent eonfidance levelthe k(abaerption) cyete vaue eppear normally dit i1buted at the 95 percent *enfidenco eelthe bitrk length) ceye wvas appear norma ly distrbuted at the 9 percent conf dence lev

. ........................................................................ 4.........................................................4

|the fin l *tatimted ceubined *dttile n/aeorptl nttnektenttth koff * .91714 itb an *estlmttd standard deviation of .0o149

May 23 tdt29 1996 Fits leaest s35Sfb.eiin SR COO-10171?-0200990016 UVW 0 ATTACKNEXT flIl - Paes I

Sbe eatieeted 6U. 95, & II Pr'Cent klff 0,enfidence latele ats .f99563 to .19"65 .9,403 to 1.60020. arid .99300 to 1.10123

~the estimated settiteolanbsorptlen meutmrenseavel lifettme a 6.153405 seconds mith an estimated stendard deViation of 3.643.y17

may 23 16:31 1996 file laws *3s30c.se 33BIAO00-001717-0200-00016RE4 81 tO ATcAUNIT cil - Pa"S I

Seeng version 4&id-l0/0i13 64/17/96 10:64:2?*-O,--..-es-5O-- ---- @**§ @-5---s**-*-p*rO pobid * 64117/9 l0:9a427

IrpessS3Cc eutp.3330O

1- Per-Plot Criticalitrt tud% - /1n 60/at O0 320/ 14S w02 035330.2- C Ca les Nilt. Tu f 1. g/ee .06 poreity - sphere surrounded by tuft3 C CELL USCIFICATIONS4- C Uf1EI MATER RESION1- 1 1 .e602310-2 -1 11:1pst4- r 2 6.11t211 1 -23l 7: l. I

OU0113113WOL

10. C e 3rFAcE SPECIFICATIbOSt1- ~ ~~~ ~~~ 112 tO Jl It ft 203Z1t

e1- 1002 4001.7316 C 31t3 61; e 0 10 a -t20 0 2 29 0 205 0s -* -10 I -101- C S -20 -10 -130100 14 * e -15 -10 -S -16 S 10 10 1718- C MAER2IAL SECIFICATIONS19- . £30 veIl water in s1IIe Nitt tuft) a .96 .14 vltX w0220- * JS Sriina Enrichment/ 30 63/11T decayed to Uranim. leete21- a1 1001.10. 1.125021-2 010.1c 4.153035j- 11023.10c L915909-422- 12000.S0" j.30604-4 1302 0. 3 - 14000. 0.c .1333-22s- 19000.50c 5.529791-4 20000.10. .c 0649z5 26000.15 1.396261-4

4- -n92234.10c 1.214625-4 9223S. Cc 6.479434-1 92236.50. 2236042-S2S- 92232.50c 3.32m9-3 93237.3Cc 4.127100-626- otl tute.41t27- c:2 Mater In enlice 1t1t. tuft28 .2 101.10. 2.905838-2 016.10.c 4.165302-2 11023350C 4.533382-429- 120e.10 2.475121-4 13027.10j 3.s15317-3 14000.10. .11

9341-2

So- 19o0o.so0 0.429990-4 20000. 0c 4.87122-4 2s000. Sc 1. 1s9-4

32- 73137I Initial surce frau fi1t *rtDlkff resultt fors fer-Pletd Crittcl try Study - 3.5130 MMW/mt - 301 N20/ 14 ue12 s35S0c) probid * 16/17196 10:16:27

thc Initlal filsion neutron saurce distribution Ves read frUe the aretp file named sretpthe critieelity problem was cheduted to skip 7 cyctes end run a total of 37 c*cles lt"ilk Incttr "O neutr er cce.thi problem h run 7 Inactive cycles with 28110 neutron historiaes nd 30sect iv e elms mith 120590 eutrmn ltsore.

this cealculatin has eooytc ted the requected nber of keft eyces. using a total of 14700 fislesion neutron source hiotetres.sll sellt with fislonab le materiel wore sampled end bad flesen neutron seuree points.

the resulta of the u test for noruaity eatlied te the IndIvidual collision. absorptlin, end track-length kefJ cycle t leass erpo

the kl ellisien) eete values eppeer nornally dletributed at the 95 persant cenfidsnce levelthe h1obsrptien Ccl values uppecr nermelly distributed at the IS percent cenfidence levelthe k(trk Iangthl erete values appear normally distributed at the 95 percent eonfidsree lsvel

...................................................................................................................................

|tbc f*11 estimated eobir d * tetpl tekeohkef * ns99s with an estimated *tendrrd dcvietl n of U0205M

Key 33 Us13I 1996 pit* sames 63S30..ust U000O8O61?17.O2O0-O0di6 IREV to aIACkNWIl XCIII * Palo 3

:h etmae ::::Z ;S. 9 pecen keff confidence Intrnewts or* .91489 to..9900, .99279 to 1.00110. and .99133 to 1.O02S6 11te stmte cltoonaboptennotonreoallietm v6.2-G scod wtha etiatdstndr .v9tono 3.1I-

may 2a 1ieS3 1996 file 11us. e530d.ssm U8IACCCCO-S1717-0200-0CC06 REV eC ATTAKiNEXT XCIV - poet

m . .. ars a4. ld.*10/0l/93 64117/96 110251sI

Ir sS330d outp-sSSSedO

1. far-Field CM ilse ' .ll v tS tu%-L5 I /0 eo/ - 305 o20/ 141 UD2 COMSSOd)2. C Cteo llt.tl TV f I I v lee .306 porosity - sphere surrunded by tuff3. C tELL 9PEeCFICaT3011s4. C INNER WATER 1161054- t t .eoi.a.... I-t lKTE.1EC~a- 2 a 111211-i~ 1-2 IRP~stmI7- C OUTSIDE WOiLS*- 3 * t 1 U :U-0

10- C URFACE SPECIFICATIONSII- 1 t0 152 S IhtER FUEL 201E12- 2 so 212 S INER FUEL 20hE13-14- DOOR I15- WcOeE 4000 1. 7 3714- tC ISC 601 6010 Ic-20 s 9 * ac to ec-s -los-o0

7- C * -5 -20 *10 *-135 -t14o e 1 5 -. 5 16 as la lo lIS* C MATERIAL SPECIFICATIOWS19- 0 55O vl; meter it callse tit taff) a 6 .1U volt UDZ20- e SP orIginsa enriclhentj 30 Cl Dn MeeMdte lestoerc21* *l loIo is. tICS 11023.5Cc 3.91590 -422- 12000 cc 2. a 00604- 0 2S7.5 9 1 c 1.1U3633-223- l900005Wc S.29791-4 30000.5Cc 5.649p-4 25000.35s 1.:92641.424- 223C5 c 1.216825-4 92235.50c 4ru54-s 92236.50c 2.2362-52U- *2Z3.C0c 3.527729-3 93237.5c .127100-525- mel Imtr.Slt2?- eJ w0 wlmater In aIlse lills tuft28. 2 1001 .3c 2.505831-2 4016.5Cc 4.255802-2 11023.50c 4.553382-4

12000.5D c 2.43121-4 3027.50c S.915387-3 14000.50c 1.31913412lSOO19000.5Cc 4.429990-4 20000.5Cc 4.587122-4 26000.S5c 1.423559-4

'2 at2t lutr.Slt32- PRINT

I Initial *ource from file *reteItef F results fort Far-Fleld Crtleel1ty Study * 3.55 10 RWom - 30 E20J 14U U02 (ce3SOd) prebid * S/1l1/S4 M1,UM.

te Initial fleslen neutron murce distribution Was reed free the cretp fIt' med retpethe criticailty prsblem wae scheduled to skitp Feylec and rmis a tctel of 37 cycles with nInetty 4000 heutrene or eyl.thi problea has run 7 Inactive erces with 2810 neutron histeries nd 30 active cycles lk 119T67 neutron histories.

this elcsulction has eepleteod the reumsted nmber of hetf cycles using a total of 1475 flesion neutron csures histories.*1I cells with f9 einabt* metertl were Csepled and had ftes on neutron source points.

the results of the u test ter normality applied te the Individual eellieien, obsorption. end trtck-Itonth koff cycle vetlus rtes

the kt eollsion) eyle valles appoer noruslly dietributed at the 9S percent confidence levelthe k(tbsorpt n cyle wuss 4peor nmrmlly distributed at th 95 percent confidence levelthe tt-k lenth) eyete ve max appCer normalty distributed at the n percent eontidsnc tevel

...................................................................................................................................

|the fIncl actlmted combined cotialoln/absrptlen/track tath keff a .n331 with an *rtl-cted st ndrrd deviation of .t0169

May 3 1Us33 1996 file HAemt 355d.av BIAOODOOO-61717-620-60016 IEW SO £13*UTIIIxM XCIV Page a

the estimated o. 93. & 9 percent keff confidence tntervas are .9930 to .m2. .9920S to .987. ead .9033 to 1.93018the estimated coltiolonabsorption mutren rmovat lifetime * 6.931-93 Seocdas fith an estimated standard deviation of I

...................................................................................................................................

Ray 23 1636 1996 Pte Fit g * 5so 0ewso * 0OOOO 4174 e200401 sEeo N ATACNUIET XCV - eas I

lacig..,ereim, 6. ld.1o0J1/93 04/17/96 13v6btG&Imp-s~~~~a outpna3338oC ~~~~~~ptgbld 8 161/96 1360:06

iu f- S33 ee *utpatc30 O0

I: Fsr.pleld elfeeita t aUtr.M- * 3.12 /30 n volat - 3o0 320 14a re 2 (d5305)C CELL ltECshe.m1 . ales .306 porosity - phre surrounded by tuff

C- C INNER WATER IRE6I01

: I a, 1:11211:1 .1 iN33I*1OUTSIDE LO 233 .

10 C fUUACE SPECIFICATIOIStl: 1 O MIXIXt FUEL WYCE

12 2 fO 210 *1 IXEIUEL ROEIS:14- IOE II- 3CODA 4000 1. 7 116. C Rc OS lo Si 6029 0a *20 0 ° -10 I 1017- C 0 4. 2 *l0C I *S-13, 00-I01H IV1A 10- 1- *16 1 0 I IC 10 1IUI- tC MATERIAL SPECIFICATIONS19- e t3% yolt water In alsco Ntlise tuff) a .t6 .14 volX UO220- ea Z 5X trlofa g riienlt/ 30 SVCIMT decayed to Urenio Isotopes

EI .1 loci.1el1I12021-8 6016.100 6.333033-1 11023.10. 3.15909:422. *1 12000 g l.t300604-6 13027.50.8 2.593233- 1COO.0 '1.134633 225 19000 .10 :1.29791-4 2000050c 1 t64925-4 6000.S5c 1.396261-4

92234. 0c 1.21"256 22553.10I .9434-5 92236.50. 2.236042-125- 92238. 1. 3.32m 3237.0. .127100-626- *ntl ivtr.Stt

30 vol water In sellee Elift tuff20- :2 1001.10c 2. 0832-2 8016.50 6e.16302-2 11023.30. 4.553382-429- l2000.50c f. 675121-4 33027.10. 3.g13 14000.30c 1.319341:309 19000.10. 6.429990-6 0000.10. 6. I 2- 60.3 . 3930- [email protected] Xm9 JR ooo.o . l22-4 UO000.5Sc l &ZI35931- it2 lutr.olt32- P3167

inttial tcaurse free file srtIknff results tfr * ser-FIeld Iritier tlty Study * 3.15X/30 JfOIb t - 30 C 120/ 142 1102 (I530e). prebid * 4/I176 15,60106

the Initial fissien neutren soures dietribution *as read frem the sretp fits gaied erstpthe eritislcity preblem das echoduled to skip 7 tlee end run a tetsl of 37 vies witth noinlnelly 6000 nsutren pr ecyle.thls peblem boo run 7 Inactive sycles with 28463 eutren hibterier end 30 active cycles with 119992 neutren histerers.

thie seleuletiln cas pleted the reested mnaber of keff e lee usIng a tetal of 146455 fleseln neutren ceuree iletories.Ott sell. with ftesionbl materlal mare sampild and bed flee en neutren coure pointe.

the results of the w test for normnlty epplled ts the Indlvidual selislln. absorptien. end track-length Neff *yel- values ores

the ki eollleitn) syele valucs spear ernally dletributed at the n percent confidence levelthe tteeberptin eycl e walus appar norasity dletributd at the 95 perent enfidence levelthe ttrk length) cyle values eppear normally distributed et the 9 pereent eenfidance level

...................................................................................................................................

|thle final *ctlmat d obined settision/abortption/track-lanth koff - .ne999 with an estimated stadrd deviatlen of .001tX

Way 13 1 it 96 Fil Erns f33308-Sin USAOOOt-?1717?-200-00016 REV 00 £TUCOENUT Xcv PAIE 2

the estimated ", 95. & 9 percent koff confidene InterTals are .9752 to 1.60125. .M95o to 1.60317. And .9n9a to 1.F49

Ithe etimated cotilsilnJrbsarption moutren removal lifetime a 64.2EIS secends with en eatimated standard deviatln of 3.I2E.07 I

......................................................................................................................................................................................................................

lAy 23 16.27 1996 9lle Ise: d3530cgw eu A3A0 000 S171t-S200-t0016 REV 0t A1TACENEXT CVI * page I

version 4a ltoiC/in9 0117196 140212.3Inp B30 *O t* OtS4n * *te .5@ *O *b*@ ": prebid * 04117/96 14:t3:23inpcseS30 .utp-e5530 0

1- Per-fieI teld ltuy /n t I os z 14% Ul2 (*353a2- t at tle Bit a Tu~t 1.716 f .306 poroity *spere surraamded by tuff3- CELL SPECFICTIONS4- C IEV13 WATER RIS1U*- I 1|1~ t~sIae*- 1 1 a.60231C.2 -1 IKP.Ugi-6* 2 3 *.111211-2 1 -3 I, .3.lT. t OUTSIDE 3ORLD

l- a SURFA4E SPECIFICAtIONS12- I XI0 1 33-1 l,111F MEL 3031E12: a to 25s I 11 xltUEL to!e~13-14- IODE I15- scECg 40001.r 71I C 1:310 6 01 6-0 63 35 00-I .100-IC17 t S-5-33 4' . 0 3 0-IC 6146 1-2195 - -I 1605 5 a 10 10 ?IS- C UAII3IAL SPEIFiICATIONSI, 30v9 wtrI .. li.. alll tuff) a .6.14 vets Wu030- a 3.3Oignl ehmieont/ 30 6110/T decaye tO Uenis ioea

21- El s10 r15Cc 021-3 l0.c 4o53 - 1023.SCc 1:915904912: 1200.SCc .s29n-t 1302e7.5c 3.5X93233-3 14000.S0c 1.13463333- I9005Ccoo29- 30000C 3.6649?5-4 36000.53. 1.396261-4

34- 92234.10. 1.31Z51254 n2335s.sc .479434-5 92z33.Soc 2.3342-S25- 9223.1Oc 3.327729-S 1327.3Cc 6.127100-636- atl ivtr.o~27- e 30 vall water In eatie. 31fi1 tuft3S- *2 1001.5Cc 2.605838-3 D016.5Cc 4.265302-3 11023.50. 4.553332-429 12000.Sec 2.675131-4 13027.S0c 3.5387-3 14000.1Cc 1.19341-130- 19000.Cc 6.42990 -4 10000 .c 6.5n0122-4 36000.13c 1.23559-3' ME2 tute.4132- P1131FI initial sa-roe frs le art

Ikeff reaulte fors elr-ild Critil-l I1ty itudy- 351 /30 1 ut * 301 320/ 141 tl02 0e3S3s) prebld a 04/17/96 14112R3

te Inittle fission neutron eeurce diatrlbutlin was reed free the cretp filt named erctpthe ariticality prable. sas acheduied to skip 7 as and run a tetal of 7 icses with noaltty 400o neutrons poe cycle.thia problem has run 7 inactive ycete with 2314 nautron histories end 30 active syctep with 131022 neutren histeorie.

this calcutation has aempleted th. requested mubbr of keff sycies using * tetal of 14836 fislen neutron saurce kitetrihe.eil celts with fiaeminable materiel ware esapled end had Ftsson neutron source pointe.

the rsulte of the w teat for Normality epptld to the individual eollisien. ebserptlin. and track-length keft ceyle values oree

the SC *ellitaon) eycte values appear norealtty distributed at the 95 percent confidence le"lthe ktabeorption ecleo valwes epper normally dtr buted at th 5 percent ent fidence levelthe htrk tengthl ants values n ppeaW normatly d iatr iuted at the f persent enfidence tevel

....................................................................... ; 1.0......ith.an...timated.at.n.a....a...t..n.o....

I the finst *ct10attd sobind etitisfeeobseristlentratis-Ingti kaff a 1.00132 wIth an *estimated stadrd leftlen of .tD201 I

Noy 23 uSr2? t9 lc Ae it laws s320.s.m *3AOO000000-6 7-0200-00016 REY S0 ATACINENT 8V e Page 2

the estimated 68 95, I 9 percent keff confidence Interls are .9928 to t.00336, ."720 to 1.30544. and .997 to 1.3068

Ithe estimated eatlilion/absorption feutern remonal lifetime w *.*4E105 Seconds with an estimated standard deviation of I.7E-.071

May1 10.33 196 Fite naow C0-4.01-406O-SOUiSU flA000000-1717-1C200-00014 REV 00 AITACMu T xCVII - Pose I

lncn, version 4a..ii I /0.0z6.3! prabid * 63103106.. 10a39s355

-IP-4.361C QTP-41C.0

1. Fazletl friteality * Sphere of Transmuted 4.6 406UO 50X Water 1SX U-Sp 022- C Cr t callty.- C

4- C SPHERE5- 1 1 7.994331071001 *1 IN.P:2:1 * Urenu m/Tuff/Vater6- * 3 * 111i11i 000- . I i IP S Tifuttvatera Reflector7- CS C 14TSIDI WORLD9- 30 * INP:E-0 S VTold

10-11- C CUUIAC!S12- 1 S 6 S * 130.60 s FISSXi. 57513

uarning. this surface lba been eleced b a surface f type so1S- a S I96 I no. 0. U L0CtO14- C

warning. this surface has been replaced by a surface of type so15-16- NMIO a17- ECOOI SOO 1 3 10031S- C 0C a66 1 0 -1 I I * 1 0 -1 6 6 e1 019- C 1 1 * 1-1* 161 16-120- C - 10 - 16 - 6 -1 131- C 6 -1 9 - --32- C 1 1 Il - -i ---23. tEl 223£41C 1 2 554- 92239.50C .126400.- S i34- 92236:& 1 3.53 .3 6237.0 sa 6"26-3 6016460C . 59266- S AtI5- 1001a00 1 932-3 ean32- 400CUO C 1131440-3 13227.40C 2.so63079-s S27- 2 O 5 13000400 3.173553-4 20000.SCC S595054-4 S I1- 11033.10 1Ii 7037 cc l000 1100 L S49 4 * 309 Nil LWTt.lT Vs

IO- 113 16100 * .6es8O8- SC 1.3193412- 13027.S60C Sl1533? S ee1. I1S 0 OC 346802-3 S VY

S2 36000. 3C 1.623559- 120000.0C 2.675121-4 2e0000.60C .57123-4 VS l33- 11023 400 4.5332 19000.10C s .422990-434 XTS LWITlIT * nV33- TalE

1 InitiaL surce fro, file Snip

lkdff results fort FerField Criticality - Sphere of Transmuted C.IE 4O00i 3OX Water 132 U-Op 02 prbid * 65103196 10419t3l

the Initial eision neutron aouree diatributien was read free the eretp file named eretpthe criticellty problem we scheduled to skie 3 yclaI afnd run a tetel d 1003 eycles ith ninally 00 neutrana per aisle.this preblem bee run 3 inactive anlts wit 1S10 neutron histories and 1000 active cycles with 499301 neutron hseteries.

this calculation asl seslewted thel requested nrber of keff cyces sine a tettd of 01011 fiesion neutron source histeries.all getta with fieel m aterial wre pld nd had flea in neutren sure points.

the resulta of tbe v teat for normality applied to the fndividul collision. absorption. end track-length kbot ptce values are:

the kt eallision) ane Values mppear normally diatributed at the 9f percent confidcnce levethe kabeserptlon) aete va s npp r r ly dietributed at the n pereent * nfince lvethe kitrk eth) eycle valVe appear normalty distributed at the S percnt cantidance tvel

aY as 10.28 1998 file least C1*4.CI.40SC 0WIID IOU REV OOOO-g17-0200.0018 33? So ATTACINEXT XCI P page a

...................................................................................................................................

the fgnat estimated eCobined eLielen/abeorptlen/ttrck-tength kotff a .9060 wIti an estineted stendard deviation of .Ooou

the estimated ", 95, I 9I pernt otff confidence Interyal* ere .97T to .9816. .978U4 to .2S, and .97M2 to .98293

the estimated ceillsion/abaorptien neutron removet lifetime a 548Ee1$5 sconds with an estimated stendard deviation of 1.10c107

...................................................................................................................................

may 0 1M.11 19916 Pits *as, 02.t4JE4001d0.30f115u IUOOOOOO-01717.0200-00016 UVt 00 ItAOINE!T XCVIII page 1

Ir***rln tleS s0.............. **...... v**ersion 492aW rld-1/1 * ....................SUCH 19821229probtd es 05 J96 19,21&29

lEOw4SC.93 ?.4S I.

1- FarField Crticliti - Sphere of TOaniuted 4.0E 40SUD 30 Water In U-0p 023- C .983 h-etf Ref actor Savinar3- C

:- f 1 t.99633107100.3 *1 INP1l . Uroaniumluffjvster6- 5 S 8.1112144000 1 1 11-3 Iau S Tuft/Mater Ref ector

WTSIU OR aLDI- so IS a 1110sll S VoidTo-

11- C19 I° t I ll17.0 SFadSSI d llel

"tn!aq. this surfcebeee n *; tace byO at sufce ftyea

ri1r. thts surface has Wen rplaed by a surface of typ as

Is-~~~~~~~~~~~~~~~aIT- KcCDE $5 I 1 0 1005

I a I-1 I I I I e-1 * a a I 1

21 e t~~ 1 1 0-1 1 e - -1-192- .

33* 5001.070~~~~~334.6 92233.100 6.77&3383-3 92236.50C 3.026400-3 S II26- 92235.50 1c3.7954-3 93237.lca. S726-6 8016.30C 4.33926-2 a At

23- ~~~~1001.100 1 704962.j o26. 14000. 00 .1214402 13027.50 3.3079: 2 -3IC27. U6000.55C n l 3002S34 000 3.3753-6 20000.Sc 5.59904-6 VI

ss ~ ~~~~ 112920 U06-* s O.1C *.JR1153

15. 11023.500 3.70375-4 9coo.5 DC £ 92.6 a 3039- 1 U1 t.OIT W ea30. 13 00.50C 2.10503438 14000.500 1.319341-2 13027.50C 3.015387.3 Ca31. 8016.5001 4:1458021 a WI32. 36000.53 1 23539- 12000.500 3.6711121.61 20000.500C 1.587132-4 a30

3- ~~11023 C00 4.553382-4 1900.500 6.439990-4MIS117 LVTIRiT a Na35- PRINT

initial sourc from fitl aretp

Ikeff results for: Ferlaetd Critloality - Sphore of Iranmuted 4.01 4*oMe 30 Vater 152 u-1p 02 probid * 05/01/96 19:31,9

the Initial fiasion neutron ouroe distributian wa roed frau the araep filt named erntpthe eritical ity probdoa as tehaduied to akit I vectes and rnn a total of 1003 aynte with nomInally 500 nautrona ae rsle.this preblem has run 3 Inactive cyles sitn 1U62 neutron hiatories end 1000 actlv cytes with 300649 neutron nlteriee.

this *ateulttin has caleated the requaeted wAiber of kaff ce isa us1in a total of 50191t fleasen nautrn source histories.a1, caetl with fisleonabl material wre, sapld and had fls ion neutron seurce points.

the resuita of the e *atn for nomatity applied to the Individual eelilien. obsorptlln. and traet-length koff yclte valvas area

the &i soltiaten) eyds vatwas appear asroalty distributed at the 9S pertent cenfidence lewelthe tabsorption e ete ue appear ormaly Di stributed at the 9 peroent aenfidonoe levelthae trthl length) rel" valum appear comally istributed at the 93 pereant cenfidanto level

NOy 30 16,t1 1996 File laws. C24.SE-409W-SOVISU BA0U.O?0280O RLEV SO ATTACNNEWT 3XCVIII * Post I

the final estimated combined e~tl#*eie/sbcerptfm./trsct-(wgtk keff a .9873 vit anI *f stiawtod standard deviation of .0008

the estimated "8. 95. £ 99 pereewnt hoff confidence interval. are .98343 to .9581. A9854 to .98901. and .98512 to .9M56

the estimated eotelloee.,abserptlen neutron removal tlfetime a 5.411-S5 secands with an estimated atandard deylatian of 1.84*-U?

KaY 21 10:19 19 Fits Imei: 93-46.6-4000-OSiaISU RAECCC0-617-0200-00016 V eo ASC CllMENT IC * Fast I

1inp version 4a td-10C1111/ 04120/96 15:32.53a Tbssss .sosa .* .*moo-.- prebid * 64/20/96 13:32:58in; 4.;Ce W t-4.0£.ee

1- farfletd fpitlaity - Sphere tf Tranamuted 4.6E 4Q0D 3St water lSX U-lp 62S C MI:rlt l tY

6- C "pifnES. 1 1 7.145S107100-2 -1 Ui|i-1 S Uraniusfluff/Mater6- 5 3 S.1112i144000-2 1 -2 I lmi S tuff/Mater ef lector

* 7. C*- C OUTRIDE WOiLD9. S0 0 2 IllPStO b Vold

10-II- C IUPA"eS12- 1 S 6 0 21t9.t3 S P3lSILE 5thEt

nrnler. this surface haseen retete bi tnr surface af tp e13- 2 t O 0 9 *EPLgCICIMine C

arni this surface has bharn replated by a surface of type soIs.16- 601V CCZ0R 2000 1 33 233lt C C0tC e a 0 1 6 -o 1 6 0 e 16 0 -1 * S * 1 *to- C 1 1 1 * 1 1 0-1

21- C' 6 I I .1:1 e1 *I 1 I 1 *.

28- 1'102.5Cc I I3I I75- 10 I.C I I 6I49'24 2t Ca27. m 9236000.5 .3605.6 10.CC . 53- 9223000.CC S.59400-1 S29- 671 LUU O 9T2I. 01.9C0I52T aA

30- 3 110t010i.5C 3.00583-1 16020.1c 1.319S41-2 1so27.5CC 3.6n338-3 t31. 8316.10C 6.285302-i SS2 26000.5t S .C 61559- 12000.3CC 2.67S121-4 2RooM.sc= 6.37122-6 S l053 11023 HsC .1333382-4 19000.5cC 6.429990 S4Si- 613162.07 Vt Initial source fro fle argtp

1keff results fort FerField Crittiesity - tphore ef Tranrsuted 6.61 660110 301 Water 151 U-tp 02 prebld a 64/20/96 13U253

the initial fission neutron source distrilution was read from the erctp fits named eretpthe crIticality proble was scheduled to skip 33 eScls and run a tetal ot 233 eswls with nominally 2000 neutrons per cyet.this problem has run 33 inactive yelts with t046 neutron hiatotes end 200 active *yVel with 3907 neutron Sistreras.

this ealeutetin a ecpteted the rqueeted Iue r of keft ertes using a tetal of 465973 fission neutron source histeries.Olt Setls wIth fssInable material were sampted and had flea on neutron esurce points.

the results of the u teat for normality appiled to the individual collision, absorption, nd tract-length koff sOts values aer

the kt collision) enle values Wpear normaly dIstributed at the 95 percent e nfidonce levelthe habsorption) yte wolves apar normaly dlstributed at the n pereent onfidence levelthe httrh legth) tle values appear normally distributed at the 95 ereent *onfidence level

may 21 roste tP99 ait. eam:t Ci-t.".g * JV-3S4V5u 9o0 oooo-g170-0e20o-1ooI6 REu 0 ATTACHMENT Ie F- a g

..................................................................... i...............................................................................................

the finet estimated combned ealielen/ beoptl1traektenth uft .9, with an estimated steandard devietion of .000

the estimated U. 9* & 9 percent heff gontidance Intervels are .993r40 to .952, .9924 to .9619. anid .99187 to .9:96

the estimated eolhfelen/absarptein moutron removel lifetime - s.1sE-OS m*cends with en estimated standard deviation of 1.291e 7...................................................................................................................................

Nay 21 10:22 1996 Fit Sams CA-4.4E 4001D-3soDsu 63A4o0o000-01717-0200-00016 REV eo AnTACOEMI C - Pa 1

lucia vursien 'a ld1 &I@119 66129 14:4:2e6*lncrs Urcicn 6e tolsq5. ............. probid 4 U/N2/96 14o5M26ftP0.4.02 1TIP-4 .01.60

l. Farflcld ritlealtIty * Sphere of Transmuted 4.6E 400We 301 Water 1M1 U-Up 02

IC 8 13 goity

1. 1 ltiI 1 F.J53107l00.1 -1 1lPUtul S UrenitumTuff/later1S 3 6.11121144"000 1 -3 OlPStel S 1uffiUates Reflectcr

7. C: so W a .151301 WORLD

2 2 INPsU.0 A Voldlo-IT: M1 ACE1 S 275.35 5f513533

varning, this outface has been liced bi a surface of tpeo ao13 2 a *SS33 5 SUILIEOTOI14-asing. tshis surface has boon replaced by a surface of type sois-16. NO0E l17- 80001 2000 1 33 23315- C '13c0000 166 -16a0 610 6I-1 0 51 519- S 11 1-IS 101a IS-I20- S1 -1 -I a -1 6 1 - a 0-i

*s- Cc @1 1 S" I 1 I-I 1-1

26- :11CC IM U201 13027.50C 2.563079-3 Stt6000.sc |1.s3300254 12000.1o0c a.27353-4 20000.90C s *.5*9054-4tte1023.s0e .7037n-4 9000.50C s.45492-4 e

TI TS I S Vs109: 013 10 11.1002..905313-2 14000.SOC 1.319341-2 13027.50C 3.015367-3 SCto6016.300 4.265602-2 a la

21: a~26000.15 1.623as9-4 l2000eJC 2.675121-4 20000.5sC 6.*87122-4 io33- 11023.500 4.553382-4 19000.500 6.429O-99.34- S IS LbTS SIT S Vs

I Initial courts frau filt arctp

Ikeff raute frts ForField Criticality - Sphere of Trenamuted 4.6t 40WD 301 Water 1ns U-Up 02 prebld * 64120196 14:41.26

the initial fatiein neutron sourte dietribut en wea read from the arcetp file cnad *retpthe critical ty pi-ebta. ua tul t 33 cycles end run a total of 2n 3 etea with rrt h n

thi problem has run 33 Inactive ayclea with 66122 neutron histories and 200 active a"clee mith 398971 neutron aet $le.

thie eatculatlen has empleted the rqueeted nber of *off a a ueIne a total of 45093 fis*len neutron eouree histeries.atl eettI witSh fasenabLe materalet were saepled and had f1seeo neutron sousre points.

the resulta of the v teat fer normality epptled to the individual eollisien, aboerption, and track-length Steff ote o evlu er o

the hI *elli n eycl valmue appear normally dietributed at the 9S percent confidence levelthe kh abarption) cle sin appear nerally dI tIbt tedd t the percent eonfidence 1evelthe hk trk lenoth) sycle va mgo appear normally ditrhuted at the 95percent aenfidence oeval

way 21 l tU 1996 II aIt lam: Ct4.E4OCCYD.ZVW1SU nS A$eOOSI1tO2sO 6 SY l: TT uT e - Pp 2

...................................................................................................................................

the final estimeted eebhed eeoteiuuefe aptian/tnetk-enth huff .""9 with en estimated stendrd deviation of .00094

the estimated U, 95, & " percent keft confidence Interv e are .75 to .m994, .99631 to 1.00057, end .99620 te I.to119

the estimated eoltlision/bserptien Neutren removel lifetime * 3.@1-i eseends with an estimated stenderd deviation of 1.1fl.0?

..................................................................................................................................

lay 21 10:31 1g, File New: CS 4.0E-400W.S0111U UUAOOOORT-81`17-O20-00016 REV 00 ATTACKNEXT Ct * sts 1

1mc v-r-len *ald sl0 *@i*93 S4Ii9*96 0'O2:56 prebld * 4O1996 67302M3I1e*4 1s OUTIP4.8I.ss0

1. Parpst1 Cuitiality - Sphere of transmuted 0.0E u00e Su Watsr 135 U-tp *22 ~C Re lector Sav ale

C4. C ... ...S 1 U lSO O 2 *1 IMs1 C Uraimu/tuff/Water0. 3 .1112110002 1 *t IRI7:31 S Tuft/Woter Reflecter

9. 30 6 t ItIR-u0 * Vold

t2- 1~ m a C 2no.6 S ISSUIU SPIEREming, thIs uOfit. l Caee n n¶lsced ly a surface of type so13S- 2 5 t s e e . EFLECTOR

warng. thtee surface has bhin replaced by a surface of type so15-16: MOVE I

1T ItCoOE 2000 33 3 233I. e utRc e 13 e .1 e e e 1 a11. e 1 S-1I I " e 1S 1eI 023- e -1 1 e *-1.1 e 10e1 .10.121- C * 1 -1 1 -1 6 a-I 0.1-1

|2- e 1 1 1 1- 1 1 1-1 .1 I -1 -1 1232 Il 92234.30C 1.670334-6 ;2Z3S.50C 6.773515S5 9223U.50C 3.626400-5 S Pl24- 9223.50C 3.l57954-3 93237.54C 1.64762-0 5016.90C 4.339266-2 * At

25. 14000.30 1T 21442012 13027.50C 2.523079-3 S to7 coo 60S0C51.380025-0 12000.1Cc 2.271153.0 20000.500 1.3911054.4 a VI

11023.80C .670375-4 1900l.50C 3.6 5 092.4 30 s

P0: N3 leoioIC 2.103113I t 14000.SOC 1.319341-2 13027.50C 3.*1537-3 S Cs

12. 16000.5501.623550 12000.00C 2.5`121-4 20000.t00C 6 37122-4 s 333- 11023.S5C 4.353332.4 19000.50C *429990-4 534. 17 VCT.~ S We35- UIU

I Initial souree from fil eretp

Ikesf results fer FirFileld Critlcality - Sphere of Transmuted 4.01! 480D 30S water 151 U-kp 02 prebld * 40119/96 6702:56

the Initial fiassen neutren source distributlen uti read from tihe eretp file rowed *retpthe criticelity preblem was scheduled to skip 33 eyclea end run a t:tal of 233tcyctes wit; nominally 2t000 neutreon *rcytle.thile problem his run 33 InactIve *eypls with 6S532 nutron Ileteriee end 200 active sycles sith 39374 meutren Iatorela.

this eIetutetiln has oepleted the equeated nmmber t kit ta leu sing e total ef 465296 fisalen neutren source hiaterisa.all *ette With fsIleoble materIel ume e": ptde end had fuaen nmutron source pointr.

the resulte of the u test for normalilty applied to the Individual eellisien, absurptien, and track-leneth keff sycle velue are:

the kt etllislen) sycle vtelm eapewr normally distributed st the 95 percent sontidence leveltIhe tteb erptlen) yctle velma appear foetry distributed at the 95 percent eonftdence levelthe ItrP length cycle wlmes apear mormetly distributed it the 95 percent confidence level

Ray E1 10:31 196 wile ose: cS4.t c40401SOVISU e5aeoo000*S177-0200-60016 REV SO LoTAnKMT Ca - Page a

.. _................................................................................................................................

the finel estimated Aobied seltisWaebeorptlen/traesktoeth buff * .J8M wIth en estimated standard deviatlen of .00091

the estited ". 95. I " percent kbff eonfidence Interval. are ."9Sol te .993 .99710 to 1.00074. and .99650 to I. eSA

the estimated eolsleion/abscrptien Mutron removel lifetime a 4.983.s5 asconds wib en estimated standard deviation of 1.393.07

..................................................................................................................................

Nay 21 I102S 1996 Filt lames C6-4.0E-400WD-SOUISU UVO-6 -0200 OU (tY 60 ATTACNREET CII - Page I

"'e a " es n* *cprobid m 813096 14,09:06

IUP4.E1C WU1PU4.6E.CO

. forfltold Criticality - Sphere of Transeuted *.0C 4001W 3S Voter 15S V-Up 023- C Criticauity3. C

4. C 21PI1ES5- I 1 .9"453S10100-1 -1 IUPaII-1 S VraniumTuff/lter*. * 3 6.11121l44000-2 1 32 IIfa1E S Tuft/oater Ref fctor7. C11* C STSIDE WORLD,. so I a it.*.@0 S Vold

10-II. C SUIFACSl123 1 t 0 6 284.32 S FIRSILS SIERE

morn!ng. th2s surface Isa been roplocod by o surfsac of type no13 - a a 00654.32 S SEILECICS16- C

warning. this surface leu beon reploced by * surfaee of type so13-16. tOE I17- ZCOCE 3000 1 73316. C MC 01 10 -10 0 1. a aI0 a0-1 66 I19- C6I30- C * I .1 2 1 1 . -aiI C Si I I1 11 01 .121: C I I I -11 1 -1-1 1-1-123 II 92234.1 0C 1.670334-1 92233.5SC $ 583-S 9223U.OC 3.024400-S S f34 92238. oCC 3. 1s3S4-3 9U237.1C .64 762.4 1014. 4c 6.3592663 S Alt233 100.5C 492 3R2t 11SOJO.CC 1440-3 13027.50C 2.5430795-3 a3T 23000.:3C 0025-4 11000.CC 1: 3-4 20100.50C.S.599954-4 I2S 11023.5MC * I703T7 4 1oo cc 4 a C0

190 Nt LTAIfT V.1113 100i.5CC 2.905338-2 14000.5CC 1.31934i2 13027.54C 3.51387-3 e a

32 1200.1°gC .4I73121-4 30000.182 *.5S7122-4 so33: 12.0 4.553382-4 1005C64M -3s- LPRI TLIT

I Initlel sourc ro tr fit* *rctp

lketf rowlts fops Fotflold tilllity * Sphere of Transeuted 4.63 *t60D 30S Votor 155 111p 62 prebid * 04/20/96 149s6

the Initial fission neutron source dietribution was road from the *retp fi* namod oretptho prrticollty prblem -sa sehedulod to skip 33 rdee and run a total of 333 sycles with misally 2000 neutrons pr eyo.tbie preblem has run S5 Inactive ycles with "Dg19 Neutron hietories and 200 active "elos with 399041 neutren hltories.

title calculetion bat rtpeted time requested rber of ofef eV*les using a total of 44560 fission neutron source histories.ett colle with Fisslonable materilt wnre sapled and had fiseien neutron sourrs points.

tihe results of tho v teat for normality applied te the Individual sollision, absorptlion. nd track-lenegth bktf cycle values ares

the i eoLlieion erclo values appear Narmally dietributed at the 95 percent cenfidonce l1veltho I eb erptlenl sycla w e Wo r 'nrally distrlbuted at the 95 percent tenttdonce leolthe khtrk t nsth ae" Ives 4ppeer nors ll dVetributed ot the 95 pereent eonfidnce level

may 21 10.25 1996 FiGe 11am.: C6-4.01-46VOn-SOWiSU *3AO0OCC8O-O11?S200-S0016 REV 00 ATTACREM i~t -I rose I

the final eastited ecobined celtisl n/eaborptfeitreek-Ilenoth eft * .n3 with an estimated etandard deviation *f .1tt9

the estimated 68, 95, £ 99 persent kaef genfidenee Intervals are .9184 to 1.00026, .9974 to 1.00118, and .99618 t i.0017`9

the estimated sottiosln/absurptien mutron rovavl lifetime * a 94.E-S secenda with an estimated standard deviation of 1.24 T7

...................................................................................................................................

k

May 21 10:13 1996 Pit* ment CT-4.GE3400Q0-UOUlSU S1A300000-C1T7T-S200-SO016 RlE so ATIACNtET Cgilt Page 1

leeng**"rsl .n.4.4 ................ !dgl~v¢|" P....... 84a~tt .... 6 115595s~t probid a 04/24/96 11:59:37lin NI0C snp04.ug1.go

2- PerFtied gritecaity * 9phero of transmuted 4.0E 40ect 301 Ueter 152 Ullp Cz.- t ritical ty

3- t "£5. 1 1 7.994S3l47100:- *1 137 IN :31 5 Ureniu/Tuff/Uster6- S 3 S.11121t4000 2 l -2 INPaU.1 S 2uttN tor Reflector

11. t .t~~1a- g * e 22LO9n g U10 0ufs 3s trn oecd trr O * rtc oidtpe*II- g IIMACES

13- I2 a 0 1593.32 0 FISSILS SPflUwarning. this surface hae bean replaced by a surface of type so

13- a 6 0a a 353.32 S *RFLCTOR14. 5

warning. this surface has been replaced by a surfae of type asIs.14. IIbE tI?- C0DE 2000 1 33 233IS- C SC 060 1 0 .1 0 S 16 0 .10 00 1 019- t 110 1- 01 10*1

20- t *-1 1 e .1.1 e *1 0 I *1 0.1

22 'e t H V I * .a.*,' ::Is: 1X 92234 9i : 1.870341- 922S A . 5854 92236:100 &:gi:Iu:1

24- ~~~2US seeC 3.S57S4-3 93237.e 0 9rrsz6Z sold.e CC 4. 9244-2 * Aas- IC01i30C 1.704962.3 S an24- 140000.1100 1.121440-U 13027.0cC 2.563079.3 S Ca37- 26000.'5SC t 13002S-4 128000. 7j3 34 20000.s0c 1.5990s4.4 S WI2r- 11023.OCC 3.670375-4 19000. cC 5492. *0

2Zo 3 TGR I Rc.00S33-2 14000.10C 1.319341-2 13027.50C 3.01373 Sa Ca

32- ACHUSK sTS~t 1:f' t:. 120In .1Oc 2.75121.4 20000.5OC 6.5171224 '$llo33- 11023.10C 4.553332-4 19000.10C .429990.4 S34U II3 LiUt.OIT S Vs35- PRINT

i nitial souree free file *retp

theftf results fore Serfrtod Criticetaity Sphere of Traneautod 4.08 40Bhp 3OX tter 151 u-Up 02 prebid * 0420/96 11,937

the Initiel tfissin neutron source distribution wee reed tree th eretp tile naed orctpthe eriticality prebles was scheduled to ship 33 cacles ad run a total of 233 sycles with noinally 20e nautrener sclothis problem has run 33 inactive syclas with 46055 neutron histories and 300 active cycles with 399655 nutron histories

this ealculatlen has eompleted the re asted amber of Ta"f eyelee using a total of u5710 fiaslen neutren souree blatories.al celes with tfissenable *ateriel wars sampled and had tfisleo neutron source points.

the results of the w test tor noreality aplied to the Individual ceilisian, absorpltin, end trech-Iesnth khft Cyler values ares

the ht eklliston)l eyel u s appeur noermlly distributed at the 95 percent s*ntafdnce lovetthe hi absorption) cyc'e wvas appear normally di'tr buted at the I perrent sentIdenca leveltheh trk lenth) cyc mc values appear mormally diatributed at the 5percent sont idone* olme

Nay 21 1013 1996 File now: CT-6.SZ.40901SWISU 3ACO*oCO-eOr1T7e-2001oo16 REV SO £TTTACINT C1I - Vage 2

...................................................................................................................................

the final estimated cembined eslltelensebsarptien/treck-length hlef - 1.60119 with an estimated standard daletlen of .0009

the estImated 8. 93. £ " percent kaff confidence Intervals Ire 1.0020 to 1.60219. M9lI to 1.6031?, and .MS to 1.e0032

the estimated .e8iilIeIanJ/bsrption neutron reova lifetime a -4.E9035 seznd with an estimated standard deviatlln of 1.33E-0?..................................................................................................................................

NaY 20 16:16 96 fito U111, CS-1A.E-409c-30V1Su BUOCCOOC-61717-0200-800l. USV 60 £TTACUINI tlV * page I

loc~ veraisn 4a Id-110/0193 63/02/96 13:11.07*e eeeeeeeeee** eeee-ae-e- -- eeee-eee..- e-a-eeeeeee.- ,e-s.ee - prabid * 03/02/9& 613a7lIP.413015C ouJt 63C.O

1- Fai ritiseltt§..ity - Sphere of t'enseut d 6.6l 40cSM 3 Water 155 U.Up 622- C e-tff Crrtifl Cedlum3. C4. C SPIER[3. 1 1 7.9 3010."43:L1 1 *1 INPE.1 a Urnfus/TWfffWater6 Is Is .112114000-E 1 -2 IIi IlaI Z Tuff/Nater efl ector

S. C OUTSIDE tVoRL9- so 6 2 619:.0 * ioTd

1I: C StURFACES12- 1 t I 6 310.60 e * 6311 SSIU F2EE

MNor tA surface "I's been replaced bya surface of typeoi3- a 5 666 370.60 S SIPLECICI16-n~ C

war" thils surface has been reploced by a surface of type so13.1S5- KxE a17. 9CODE SOC I 3 100318. C WeC 66 1 6 e e 1 0 e e 1 e 0 -1 6 0 e 1 e19 C 1 t102e C .1 .e1 :121: C I I1 1 1 ewl t -1 n vlU2 C. I -1 I I1 1-1 1 1 .111

2S RI 92234:.5CC 1.673346 92 :1.3Cc 6.177333-3 92236n 3C.626 CC-S S Cp5 t o922's C 365c 379545 T 3 eC 6.647626-6 6016. 4. 39266.2 6 At

F. l4toeec l.uilio-f l3027.5oc 1.563079-3 17WO0. CC .70496- I Ienn7. 2600.33C 3 a01234 12088. C .127333-6 24006.5CC 5.59084-4 * VI

IS I C lle7se s ~~n 4 19e00. c .465^92-4

H.t N3 10eUCc t2.603338.2 1400.NCc 1.SM193 1302-.5eC i 0s537-3 | e31. 6C8'C4258. VI32- 26000.13C :1 ... 9.6 12000.NC 2.6n5214 2ooe0.CC 6.S5r122-4 so33 11023.5CC 4.533S32-4 I900C. CC *.4290. s34- 173 LWTI.IifS33. IT

Inititl osuree free fite Iretp

Ikeff results fore Farfield Criticality * sphere of Transmuted 4.1 *0OWD 30 water 15 Ul-p 62 prebid a 65/62/96 e813867

the Initial fiesien neutren soure. distribution se roed free the eretp fit ranaed aretptl criticality problem use scheduled to ekitp eTes nd r m a total of 1063 eycles with nominally seo meutren r eperthis probl hts run S inative os ultr 14 feutron histories end 1000 active #ycto* with 499832 mutren fsterfes.

this ealculetlan has seeptoted tbh equetead Waber of koffs le umins a total of 501291 fieslon seutren earue hieteories.all eels uith flslen *terlot we e" pled end had fIIsien neutron touree points.

tbe results of the v test for normality applied to the Individual *olltieon. absorptien, *nd track-length eftf eycle Walues sres

the tC sollie en) eycle values appear normally distributed at th peC nt enidence levetthe klabserpt1 lenl eyeI valuees apear neormtall distributed at tie 9 perent enflidencethe Rtrt tlngth anle vles Wee normally dilstrbuted et the a3 re nt cenfI dnce level

*Sy AZ I&IsI 196 tile lea.: CS4.S14[5-DCVOWISU RC 8 ?I D OO 1S Itin D ATTACUnENT CmV Pe- r a

...................................................................................................................................

the filat estimated cobined retlelen/eberptioltrae--lamth keff a 1.0017D *itb an estimated Standard deviation of .006

the estimated U. YS, £ 9 pereant tat f anfidanca Intervals are 1.0008 to 1.602S6, .119 to 1.0341. and ."943 te 1.C0037

the estimated ettilelelabseruptinn meutrnn removal lifetime a 4.S91SDS seconds with an estimated Standard deviation of i.1SEeT7..................................................................................................................................

Ray 24 M1I 1996 File laRws S020nh.stu SJADOOt 001717t2009 0016 REV *0 ATTVCKI1EXT tv - Pogs 1

1incne version 4. t~d.10/0/93 so. e4/3Cno 30:14:20 prbebd a 04/30/96 MUM114,3

I1Pxa3O2Gnh UTFa&3O20nhO

1- Far-Felod Criticltity ttudv * 3.es 10 M/Mt - 47 120I/ 9n U02 (e302Or)2. C Calico title Iu f 1.t 7 V/ac .47 Porosity sphere surrounded by tuff3* C CELL PEtCIFICAI71GN4. C IUNER VAIEt AE6ttt. I*

2 2 .14e - w07- C OUTSIOE MOULIP*. * S 3 IRPIR-09.

10- C mURItCE SPrUFICAmZUS11- I to 115 * INtER FUEL tOIoE12- 3 tO 235 S INNER FUEL ZONE13.14- IngDE15- KC00 4*0 1. 0 751U t ntc e C tRO 9 0 091C 0 e20 9 * t9 93015 00.55 .109.401?- C 9* -S * *S. 009*U**0*0* 23*30-15 .565 5103017INU C RATIIAL SPECIVICAITEON19- o £r ll water In *ttee Itl tut .92 9 votX U0230 e .t ri tnrihant W06 /tT doe d to Uraniume otpe

IT Mt 1: 31.92903 1 143S- 11023.50c *.1"91T-410 .879523-4 13027.1 c 11SS92 14000.50c 9.36960-3

19 *oc 4 *506j Cc 8o2r070-4 26000.55. 140702-4PE 2234 ffi1c I ^9U50 r *22SS 50ce S226. 92236.50. 9 153194-6is: 22S.50c 1.1033003 93237.5Cc .18296-436- *tl twtr.61t27 e 30 well water In catle Nittae tuff31. *2 1001.50c t.142479-2 9014.90c 4.963047-3 11023.5C0 3.477347.29- 12000. 1 Oc 2.0429S0-4 1302.590c .302817.3 14000.50c I.907569-230J 19000. 0 4.110S11.4 t0000.50c .630511-4 26000.55.e 1239894-431. *t2 Iwtr.I1t32- FRIll

I mnitlel source free fite *retIkeff reaulte ftor Fer-Plets Critical ty Study - 3.n /120 no/t - 47 20 91 uo0 (o3oh) prrbid * 4/3096 MUM

the initial fission mnutron *surce distribution a" road from thb eretp if ie named orcthe oriticelIty prebles wes cseduled to otI 200cs nd run e tetet f 7 r les Uth nminally *00 neutron per sct*.thie problem has run 20 Inective eycles ith 797 neutron hieteries and SS active antes with 320592 nsutren blot erIe.

thlectrutetlen hbee sopteted the requested umber of keft Mles usiw e total of 300459 fiesien neutron source histories.ett Ieas with fissionabis material wes amopted Wd ha fission neutron sour.e points.

the resutts of the u test for nertiaity applied to the individual cotleteon, eabsrptlin. and trect-length heff sycle vealus otes

the Ik eollisien) cycte vales sppear normalty dietributed at the 9 percent confidence levelthe htebsorption) cycle values ppear normally distributed at the 93 percent confidence leveltbe l(trL lngth) cycle veiwos appear normally distributed at the 93 percent senfidance level

................................... ....... .............................................................................9 3

|the fIn t catlmtod somisned *etttciol bserptlen~tnse tength koff a .968tJ with an ativated stendard devletl n of .4O105

Nay 24 131S4 1994 File Names s3020nh.sum 3A00o0Do00-1?17-e200-000a1 REV S0 ATTACeKENE cv * Page I

the estlomted 4, 95. £ 99 percent kWtf confidence Intervals are .9675 to .96951. .9627 to .9059. end .6555 to .971311

Itoh estimated eallislooecborptlen neutron removal lifetiam a 9.39E15 seconds with an estimated standard daviatlen of 2.66 I'...................................................................................................................................

May 26 1M1T 1996 F1le elow MZn1M.sum SuoooooREV S ATTACNNEXT nl rPage 1

1couzon, e sett*r {fnv *s30t2MIG a*OOOO.OSO196o OO O.tOl prebid a 6/1819 MasUh

issp dezflnl eutpi53020n10

1- Par-Field criticality Btu * 3.62 13e sue/T- 6n 7 z20/ h 12 Wu 3020ni)2 C entlle gIlis TufV 1.157 g/ce .*7 porosity sphere surreunded by tuft3- C SELL SPECIFICATIONS4- T 1 t.S0U1 a * WATER1801- 1t I 1.:1032611 2 1 IlPlt-l

'. a a .15060 1 31 iMP31a7- 5 WUIS111 WORLD8- 3 0 2 IMP11aO

1I- C- SuFACtS PECIFICATIONS11- 1 80 1IC SS333t8 FUEL ONE1

12- 2 to 210 NN * 111 FUEL ZONE13-1'- Mo0E K11- gem01 4000 1.807TS16- 5C r31 I01 1 1 08.20 0629 0201 * -Ss -*tO g -IT* C I 0-20 -30 0 13 *10 0 e 0t -25 -30 -1 36 10 30 17la: C. MATERIAL SPECIFICATZOUS19- C (47 vet l t or In etales eiels tuff) a .92 t vat% 130220- a OI Srist l gniea"ntn el2 6101 2 decoyed to ltranium Isa toes21- El MI01.Sc j.891S81-1 0016.10c

4 .1l 9113: 11823.10c 5.I991 -4

22- 12000.S0c .579323. 1I027.1Cc 2. 1592 16000.10. 9.359406.323- 19000.10. .1670 4 20000.30c 6.628070-6 2600.O1s. T.lo0702.424- 92234.10. .94410.7 223310 .5211- 2365.9u3184-625- 92233.30. .903300-3 93237510. 2ISe29-U *626. Intl tutr.St27- 30 v.11 "ater Ini esalle Bil1s tuft2- Z 1001.30. 3.142479-2 3016.10 4.063067-2 11823.10a 3.4M67-429- 12000.10. 2" 429604 103027.S10 2.302117:3 14000.50. 1.807566-230- 1900US1c 4.910511.4 20000.Oc .030311 2U000.55. 1.239Z14-431. at2 tutr.01t32- PEREZ

iknft results fore Far-fiel d Crt IeI" t ty Study - 3.02 /20 SW/1mt n US 9201 52 VO02 (eiO20ni) prebld * 63/1/96 12MU8M01

the Initial tfesion neutron source dletribution s read free the *rstp tile reed sretpthe crit eality problem me at*aldted to ski p to aytea and run a tetal et 73 syncts with fominatly 4000 neutrens par cycle.thie problem bea run 20 Inactive ylet astE 007 neutron histeries end 55 ctive cycles with 220019 neutron hiateries.

this celeuletien bee eompleted the reqsted rmber of koff stae le using a total of 300091 flecion neutron *oure. histeriesall telle With fiesienable material were sampled and had fission neutron source pointe.

the results ot the u test for ewrmlity applied to the Individual colliseion absorption. and track-tenth keff oycle volume srpo

the RC solliefen) cyele values ppear normall disetributed at the 93 percent confidence levelthe kaborptlen) cycle aue appear maritlly distl buted at the 9S percent eenfidante levelthe itnrk length) cycle values appear norsl ly dinesr uted at the 93 percent confidence level

...................................................................................................................................

| th- fIrul estlmted combined settieolan~b erptle~treck-lengtil koff a M$SS3 ultb an estimated standard devwltien of .00104 1

Ray a4 1sst1 196 Ins, saw: Ac 020n1.sem BRAOA0ODO* Y7S26-0001A UIV Yo ATTAMENT CVI * rage 2

tie estimted 65, 95, A 99 percent left cenftdane. intervals are .98443 to .9865T, .933" to .14762. and .98t274 to .JW3

Ithe estimated celilsiienebsorptlen neutron removal tifetime a 9.62E-01 secends with Am estimated standard daviatien of I.j991.,?................................................................ ..... ....... ....................................................

May 24 13: 1996 Pit, laws dD2Dnb.tm R5AOO000D t1?.6200-680I6 CEV 00 ATIACIREUT CVII * Pass I .

tCI"D vnerin 4e Ideleo/oms 4416/ 17:370s45*5 5** **. .** *.***d* * * *** *.d* 64/26/96 l7.3s&54

1NP-s3O2Onb UTP 320nbo.,

1. Far-fletd ritlclIlt Study * 3.01 /2D0 6i/t 47% 320/ S2 UZ2 (S3020nb)2. C Callc S1ills tuff 1.1u7 /ec .47 porosity * sphere surrsmdsd by tuff3. C CELL SPECIFICATIe S

*- 2 2 *. 10606-2 1 -2 ItFUKm

10- C SURFACE SPECIF3CATIONS11- 1 s0 160 S INiER FUEL 2ONE12- 2 to 220 5 INNER FUEL ME1s-14- N0DE KIS- 9COOE 4800 1 2714' C ESIC i iil @ 10 @ -20 6 3 29 0 2015 e * -I -to * 0-01?- C a * .0 -to *30 a -1U e 1 g e e -25 -30 -15 *51 5 * 1e So 17IC- C MATERIAL SPECIFICATIONS1t- * i7 oil water In latlee Ellis tuff) a .n2 a weI U1022D- e I0% tl27 lnest 2nriclM1nt4 20 6I/5T dec; ad to Urenlm lootEl- ml 1001.5Cc 2.891I03-2 a)J.5Cc 4. "1l3- 1023.5Cc .199137-622- 12DD.5e 1c.279523-4 13027.1 3. 118592- 4100.50c .269606-323- 19000Cc. 4.517670-4 20000.C0c 4.628070-4 2W600.1t 1e.140702-424- 92234.50c 4.694 50-? 92235 c 5.625286-5 92236.s c .13164-625 OZZ38-.5c 1.903500-3 13237.sCc 2.162926-626- *tl Iutr.Slt27- s so Veil motor In sill.. volts tuff28- mZ 1001.1Cc $.142479-2 60M.50c 4.063067-2 11023.5Cc 3.4?73-429- 12oCo.* ".429604 15027.5Cc 2.302n73 140003Cc 1.S075l -iSC- 19:~000.c 4.910511-4 20000.5Cc I.03011-4 26000.c 1.2Ss, 94-j stZ lutr.61t

Initil sours. fros flserotoIkeff results for, sri-Field Cr"CHIMaIty study - 3.01 /20 SD/at - 47* 320/ SE UOZ 0esO20db) prebid * 6/26/96 17s3Ts54

the Inititl flssion nnutren source dlstrlbutlen was read from tIe sretp ftIs "se-d *retpthe eritlesllty pr-blem was scheduted to skip 20 ecler and run a total of 7s cycles with nomnatty 4000 nsutrona psr eyVet.this probllem ho rn 20 Inactive sycles mIkilk WU uutren hlterll and 55 aive eycles with 220167 nutrn hi terlIs.

theis ealuletlen has ompletd the requsetd number of kff syplse uslns a tetat of 300230 fissin neutrmn source hlsterles.all cells Mtil flssleonble *sterlt mere ampled and bad ftee en neutron sours. points.

the resuits of tIe v test for normilty pptiled to tIe Individul ceIllseln, absorptlen. end tnrck-tomth kaff sycle vua *resis

II,.tt essllelenl plets vstus sppccr normally distrlbuted at the 95 percent esnfidence Isvstthe hiabserptlen) cycie vatum sppasr normally d strlbuted at the 15 preent eenlfdsnce levsttIke t rk lensth) ares *p t pps noremally dlstributed at the 5 percent *enftlince 1svt

.......................................................................... .........................................................

I the final etlmted eabirad collislen/bserptlen/traet tength tett a .99Dtl wlth an estimated stend rd deviation of .Doon I

Nay 24 13,09 1996 Fite lan, *020Sb.w *IAOOO00-0*1717.-200-40016 a1W 60 UTfl XUNET CV1i * PeP. Z

Ith estimated ii. 95. & 9 percent tkff eonfidenee Intervls are .98981 to .9911 .32 to .9280. and .91u to .9947

the estimated sgllislonlabsorptien neutron remvoal lifetime a 5.9t43.5 Oehula with an estimated standard deviation of 2.3-3 7|........................................................ ?........................................................................

i

I

May 24 1309 1996 File asr c320nc.scu IUAOOCCOCO-1177-0200-00016 REV 00 AtTAChEINT OWIZI Page 1

J.1crf version 4m lIdwI010193 04/26/96 13:61:03 probid OVUM 13A6 l:032P.83020Anc OUTFP-5020ncO

1. Fer-Fild Criticolity 8jud * 3.S J130 6D21. 47S b20/ X1 U02 0e3020nc)2- C Catic *Illa Tu t .1 7 Wes/ .pres ty sphere surreundcd by tuft3- C CELL SPECIFICATIOSN4- C 113At VAATR RE1IO0

I 1 6.303241-2 *1 INPa"-l5- I6- a a a 618"6-2 1 -2 111P0"T- t QUTSIE WORLD

9.10- C SURFACE IECIZICATIONS~11 1 30e 17S 2 13 FUEL 20E

2 235 6 IIII3EI EC 201EIs-14- N0MI I

C0D3E 40001. W0 75156- ea nac o 0 1 a lo e 020 a e 29 I 201f 06e 55 C -SS 104017 e- C a-5020 -30 a -13 a -10 60 0 -25 -*S -15 -5 5S01C3017186 C IATEIIAL SPECIFICATIONS19- c OT voX water Ir ccileV Il ll ulf s .92 6 v IU0220- c 3.01 OrIginat Inrlcentl 2610/ 3 daeY d t UranLU IsottesC21. *1 ICCIJ* c 2.691081-1 101. Ie .29133. 11023.50c 3.199177-422U 1200.Cc 1.89523 6 1327.5Oc 16592-31400.3Cc 9.2606.3

19000. O .54 S670-4 0000. jOe .12607 4 26000.55e 1.4C70264*- *rnS. Cc .69440- 2n5 Oc. 25216 5 92236.5Csc 9. 53184.

25- 9223.Cce 1.tO5500-t 93237.5Oc 2.12926-628- aint twtr.Olt37- a 10 volt water In ealice Nitta tuff23. .2 1001.5Cc 3.142479-2 8016.50c 4.063067-2 11023.5Cc 3.47TU67429- 12000.51C 2.042960-4 130027sOCc .323187-S 140030.5Cg 136075"6.30. 19000.5Cc 4.910511.4 2000005Cc 5.0S305 1. 26000 55 1.2 94-4$I- eta lutr.elt

I initial source free ll rtIkeff results fe:r Faor-FieldCrelticlty Study * 3.0 tS20 A G/at - 47% 20/ nM 110 (mSO20nc) prebid * 1286 1S 1M03

the Initial fissien meutran *surce distribution was read free the *rctp file mord erctpthc critIeallty preblem was scheduled to skip 20 e leaed rg a tstl of 75 cycles with nominally 8600 neutrons rr cycilethi prble hs rn 20 Iactive cycles wilt C0323 5 utr i htree and 5 active cycles wilt 219166 neutren Iloriea.

this celcutetlen as corleted tIe rcquceted number of keff cycles uwsng a totl of 299509 fission nautron ecurce historiec.all celtl with fiesnable aeterlel were seapled end bad fleeIen neutron source points.

the rmultt of thIe lest fer noiulity applied to the IndIvidual celllsien, ebsorption. end track-length haff cycle values esp

the k( cllision) cycle veua cppeer ormaly ditributed at tha 95 percent *onfidence levelthe kttbsorptln) cycle veuss eppeer nor V distrbuted at the 95 percent cenfidanee levelthe kttrk length) cycle ve mIe appeer normal y distributed at the 95 percent *enf denc- let

I the final estilwted cdbined kliec/arpti track ngth heft * .99147 with an estimated standard deviatien of .0090 I

May 84 13s4 1996 Fite *ame. 0024nc.ca GIAOODCOO-0I1?-0200-60016 REV S0 ATTAUNEMT CVIII * Pash I

the estimated 48. 95. * 9 percent keff eonfidence Intervale Ar .9056 to .J9T .93966 to ."323, and .98906 to .99131|

the estimated setilionlabsorptln neoutrmn removat lifetime a 3.92t-15 mhends "ith an estimated standard deviation of 2.ES7I.................................................................................................................................

Ray 24 MIT1 1996 file Immat a3020nd.umii REVOOC077-20001 i co AIThACNRET ONE - Past I

-Icnnm.rm r ona .... version .. ...0101.93 64/2619 .. 92.... proba196 19:57:54

IEP-m3o2Cnd wJT n&3020ndO

1- Far-Fl.d C tSll Et Judy -3.E /28 go/mi . 672 120/ PE U02 (.S020nd)2- C Calto Sllt6 lff 1.137 /ee .47 ares lty - pher. surrwunded by tuft3. C SELL SECIF ICATIOIS'- C lost& MAThR REGION5 I II:bE I 1 IN EECIOI

I: I ' 2 0"Il00II

10- C SURFACE CPICIFICATIlSttt- I so 190 * 11111 FUEL ZONE12- 2 s0 250 * Oltil FUEL game15-(4- NOtE U

IS: KCO 14 01c aI75 6 1 10 I I - 06 e 9 e 015 0 055 -s 1 0 0I?. C *.S0 *20 30s e 13- -0lo 4l *D C 6 . 30 .15 -5 5 S0 1030 1TIt- C NATPI1AL UPCICFICATIOiS19- ' 4 wa12termIn callco miltt tufluf .92 * vrtX U0220- e l.CX Oil inmi rnrlelcmnt 10 t 1o N d c d to Uraniunm loottp,21- * 1001.S0c m.39101-3 016.Snc 29133 2 023.5Cc82- 1200t.SCc 1.679523 4 11027.5Cc 211D592-T U4000 .SCc 9 W9 023- 19000.S0c 4.31767 -4 20000.3Cc 4.42800704 26000.53c 1.140702-424- 92234.50c 4.69450-7 92235.5C0 3.625216-1 92236.5 c 9.153184-685- 92230.50c 1.905500-3 93237.50c 2.162926-626- atl lvtr.olt2- e 10 ve cr In mail. Ill IS lutt23. u2 to1 .5Cc 3.14249 2 016. SOc 7-2 11023.50c .4TM77429- 12000.15c 8.342960-4 13027.1Cc 1.302817-l 14000.30c 1. 7S646230- ,9oo.Cc 4. 91031-4 20000.5C J .030ft1-6 26000.35c 1.29894-431S *t2 tutr.1t132- PRINT

I Initial surre fre file *retetheft r"ultt tori for-pelad Critce ritb Stud * 3. Xf0 113/mt *72 t282 X 02 tm02Cnd) prdid * 04126/96 l97a04

(heIniielflmlmnnegtrwn sauic. distribut ion was read fr.. tb. orclp file, nSeed ail(k rtlmlt p1111:1,18Imbete m us aftduled to skip 80 3ries mand runa titlem of 73 5ow mitplk nc]alriyths problem aMs run 20 Inactve "visa with 60408 nmutrmn histomries end 55 active cyclm. mith

64000 nmutrenm per ontom.8(9217 umutimnfistolries.

thls attcuieltin bme ecplet d thk reqStu d mber of kcft eyclec sing e tetet oltl cell. with 11emelable mtaleali nmre eseted mnd bad tlee on eulltrmn moure polnts.

2996251 fission neutron socurce hisleries.

the results of the u teal ter normality Smiled to the Individuml ceitlmlmn ebmrpttoen. and track-length koff cycle values arse

thi hI mollil en) mycle vatues appesr normally dlftrlbuted it the IS percent cwnfdmnc. levelhle lesborptl sen) cyet values ipprcr normally d irlbuted et th k S percent cenflidncm levt

the rk lengthi3 "clt v tes appear normtaly distrlbuted at tlh VS precnt centidence level

.. ................................................................................................................... ............

|the finlN *tst mtd eembtn d eetllislan/boorptlenfirack-longth half * ."67n with an *rtt-rted stadrd deviation of .tODO8

Ray 24 MM1 19s6 file laws b 020nd.sam ggVnooN O1717-6250*S0014 CE 0 aTTAcIMNET SIX- Pace a

the estimated ". 95. 8 9 perent keff sean hence Intervats ore .nSU to .m 9. .9S9o to ."43. and .9S43 to .9902

the estimted eattllalmvasorption matren removal tiftise * a.ME05 seconds eith on estlmated stendard deAyltten of I.644.s7|.................................................................................................................................. "I

I . I

may 24 13:12 1996 F1te Jame, e5302ne.atm BIAOOOOO-1S1176-200-60016 REV 30 ATTACONEVt e - Page 1

inr. version As td.101@1/93 64126196 20:39148t . ".asten5*55*5 e.mO.e2 ....... e.e .e.e.ee.ee..*.e.e.e...0 ...e ..... prebid a 04/2/96 t0839840IMPes3020ne SUTPOSSO2MneO

1- 90? Field CiitiSetlj3 ti - 3.6 Sm 20 ., cu 4n hz20t ax U02 (S302*ne)2 c Calic Ktiltlt I /ce .47 pres ty * sphere surrounded by tuftf

3- C CELL SPECIFICATIONS4- C INNER WATER SENIOR5- 1 1 0.508241-2 *1 INPEIBI6. 2 2 S.6lD406-2 1 -2 ISP-1.

6- 3 9 2 llNtiU.09-

10. C SURFACE SPECIFICATIONS11- 1 50 S lItEt FUEL W E12- 2 Sa o S SIXIEU FUEL IZon13-14- NODE I1S- ICODE 4000 1. *0 7516- C CIOC e e 1 0 10 6 . 20 0 * 29 0 2015 0 e .o10 4 -401?. S a -se 020-30 *13 s -10 0 6 -25 X0 -15 6 SC10 301s1S. C MATERIAL SPECIFICATIONS1t- I 14 w vetX mter In salle. Nittl tuftl a .92 I v.ll U022t- c J.tS Orginal Snriehnt2 20 MUOJIT des ad to Uranium Ieotow

24 2254.~ ma4.9 St-T 1 ZZ55 It. II 52t-S 4005 Sc :151t ON2S *2Z5.00 c l.@OSSOO 00 0m50 93 69406-i

as: e2 12001.05e3 e290 j 2 1*°1 lJ~le ,L-. 4129I33t 1l23.50 5. 3.1991

132e 19000. 4.517 -4 0 OOO.SH 26070.4 26000.ssc 1.F14072.44: ;,20,34010,6C4.69450.792Z233 526. 9230.10. 9.91314 6

25- 92236.0 J 1c905500.3 93237.0c 2.162Y926.26- *ti tltrt.lt27e a 30 volt watr In stelsl. ue*Is tuf t

.l 1001.O S.142479.2 6014.50. 4.063067-2 11023.50a 3.4772U7-412000.50. 2.642960.4 13027.50. 1.302617.3 14000.50. 1.07566-219000.50t 4.910511t4 20000.50. 530e114 26000.o55 1.l239n94-4

I initial source from file sratotheff results fror Fer-Field Criticalfty Study - 3.62 120 tWist - 472 NZ0/ 51 iIOZ (s3O20ne) prebid * 6412&196 203940

the initlel fission neutron source dlatribution was read free the srctp file nembed sretpthe eritisslity problem mwascahsduted to skip 20 cyeles end run a total of 755cyclets with sominally 4000 neutrone mr owrls.this problem has rn 20 Inactive esylea with 60Z19 neutron histories end SS ctiv cycles with 221T7 neutron I Ieter as.

this calculation has tompleted the requted umber of keff sycles using a total of 30406 fission neutron source histories.eil colts with fleslso ble wateriel were sempled end had Iel on nutr on souree points.

the rncults of the t ost for normality applied to the Individual cellision. absorption, and track-length hoef eycle velwss ores

the hi eollieion) cycle values eWear normally diSetributed at the 95 percent *onfiden.e levelthe h(elbsrption) sycl values w et ar nermatly diStributad at the 95 porent confidence ltvelthe k(trt length) ayc tVlue appeer normally dfstributed *t the 9 poreent *onfidence lewvl

.......................................................................................................... ..d.....................

|the flmal stieated combined eeitiolelnzeasrptlei~traeet legth kaff a ."M9 wltb an estimated stadre' de'etletn of .80114 |

May 24 lutZ 1994 Fit* Noses *=OZns.sum R~~OOS77SO.O1 EV S ATIACKMENT 0 - Pave 2

the estimated a,* IS* A 9 percentt eff confidence Intervals arm .9967? te .919956. .99563 to I.0002, GM .9948? to 1.0009?

1the estimated cullisien/abaorption neutroni remevat lifetime a 11.111-43 seconds with en estimated standard devietien of II?11

may 24 13M14 1996 Fllt Names a0lnt.sim ISAOOOt1717-t200-00016 REV *0 AITACN!ENT ClI Pae I

1ene. wversion n Id-10/81/93 /9 296 C i S07119*-- -***** --- *----**-- **-**--*-*** *- *---probid * /29/96 MMg"s

in4*O2Dnf outpea320ntO

1- Fer-Field critIcality ttud* -. S It0 ogoiat * 475 Y201 U1U02 d(oO32nt ,2. C Calico slits t.uft 1 S e .41' porosity - sphere surrounded by tuft2. C CELL SPICIFSCA?2a11l4- C 1131E MATh1 1E10305- 1 1 3.5032413 2 *1 04U-I

T2 6.10408W 1 t2 INP:ULD

I I @ to U S nn"M LOlo

12- a t0 IN0NER UEL WOt13-14- 1ME IIs- SC=3 4000 1. C71' C 9tC 13 3 l066 6610 I.20 0 69 e30 15 0 -i -16 0 4017 C S -* C -S0 a -13 a -10 o a -Ss .30 -15 *4 5 5 I la So IT1S C IAtEIiAL SPCUIFICATIOS19- c (7 voeI water In galte 1lIlt, tuft) x .92 S vets WO220 e .tS Original Inrichaent/ 20 1/NlT deed to Urenlum Ietepes21 el 100.5c f.891081-2 SOc.SOc. 4.129133 11D23.50e 3.19m1 .422- 12000.50. .S79523-4 1 027. 0. 2.11U592 14800o.0c 9.3496043

23- ~~19000.S0c 4 Sl767O 4 00001" OcWUl" UO." ' ee-23- 190.0 .1804jO O. ~0 .28070.4 26000.55c 1.140702-424- 92234.50c 4.694450-7 2235. 0c 3.62523-5 92Z34.50. 9.113164-6325 92233.50c 1.905500.3 9327.50c 2.182926-.24. ati lutr.S0127. a 30 WIt: water In, esllam Sli1s tuft26- .2 1001.50. 31.142479.2 8016.0c: 4.063067-2 11023.5Cc 3.4M6T-429. 12000.50c 2.642940.4 13027.50. j.102817-3 14000.5Cc 1.607e4-3'0- 19000.50. 4*910511-4 30000.30. .030511-4 34000.55. 1.3339-4-31- eta lwtr.01t32- 913YT

1 ihtiat asurce trta file spotsIkeft results fort far-Field Critictlity Study - 3.61 /2O iM - 47* 320/ 6U U02 (a)O20n) prebid * 64//9/96 71172089

the initial fitceln muutren source diatributien was read ftrm the aretp t named arctpthe eritigality prables m e dutld to skip i0 evotes n rusn a tota of n aeylea aith nominalS 4880 mautrana s* "ya.this problem hea rn 10 inactive revok with 60579 nnutren histories and 55 actliv cyclet with 319949 nautron lateries.

thisceleulttlon habaempteted the reuted number f ketf cyclea uain a total *t 300323 fission neutron souree historie.*lt cellc with fiseioable materal aera sapled and had tfisien neutron source points.

the results of the W test for normality applt d to the individuat *ellielonn abserption. and track-length hbeft *yet valuae are:

the hi callialn) eycl vte wal appear normally diatributad at the 95 percent confidence levelthe tt *bsorptlo cy* Icl values appear normally dstrtibuted at the 9 paeent senf 1dence levelthe ar trlength *rete Vales appeaernormally di truted th 95 pcent conf denc level

...................................................................................................................................

|tbe fiNtl estimted Cffmbined settiolon/bserptlen/tracetongth t ff a .9113S with an estlimted st ndard deviation of .0007T

gay 24 13:14 1996 aitelaIM$ t sS2 nft.ei *IACOOCOO01717.6200-08016 KEW Go ALIACKSltT CaI * Peas I

,tI e stimted J8 9, . Al 9 pereent koff eanfidnce Intervals aoe .99657 to .9 2, ."579 to ."1g9 . and ."S92 to .9992 I

the estimated melttlen/aebserptien fehtufn .emat lfetim a 3.74E.ES macends with en estlmated atnderd "eletlen of 1. 6.1|...................................................................................................................................

Aus 27 14:16 1996 Ft to EROW &UMN-Gum REVoo0-1? 20 -000 ATIACUMENT CxI - Poe. I

Imcng, Version 64s tld1001/93 03/19/96 19,14:4*OO~ieesseO*Oesei***esO~eiCesOO55*so*OOO~.5m~i4*i~OOO*prbebd U 1/19/99 09:54&45

4npsesO420n eutp-4020neO

1. Fai*fr old CriIticality fU7 S.IX /20 GM/at - 47Z 1201 IX e2 (s3020ng)St t lls Nitta lue h.7 Stec .7 porosity sphere surrounded by tuff

1 C CELL SPECIFICATIONI4 t C lelt WATER. 13841055- I 1 .0822461- I INPtINs6. a S.610406.1 1 -3 IMPuNsi7 O 2 *.^le404UTSIDE 180115

10- C SIUtMACE SPECIFIEAIIKStl- t 10 NS S ItEtV MUEL tOIE- It 30 aO * lVER ML ZOIE

15 Itl°Ce 4000e e17S to eIs*o|@ 9*2 s§ 5 eeXsit: I 9KC 9 a soI -t .003a 0a 0 15 I0a-15 .10 0 -0I?- I-S .t0 -to -30 I -13 * 10 60 I* 5 a 30.s *s56 5 I la 30 Ila. Et AIR AL sECtFuIaCtAIOs19- a 14 7 s meter In entie EKitt tuff) A .92 £ v.t1 U0Z

v e 3.XSrig r nsal Inriochent/ t0 GO1IST dceysd to Uronum isotopes1001.1Co c 3.191031.2 1016. *c 4.129133- 1 123.50 3.19917 -12002.5Cc I.17r523s4 13027. oe 3.118592-I 1800.50e i.269606-319000.5Sc 4117610-4 000.5Cc .628070-4 6000.13e 1.460702-492234.SCc 4.69440-7 r 2235.Wc 5*25286-5 2236.530 .9531U

051 1 2231oc s1.905500-3 93237. SCc 2.132926-6

27- 9 z ~~~ter In livls.mitise ufff56 *2 0 -." 142479-,42 °0214.5Cc 4.063067-2 11023.0c 14M73-4

29- 2000 .842960-4 13027.S : .302817.3 14000.50c 1.t075"6-30- 1000oo .910511-4 3OO0000.c s.03011-4 26000.53. 1.239094-4U: .t2 Iwtro.t

.f tesults fo ret erFel ti t Studr - 3.1 n o /mt *s671y/n go0tat e 2 153z20na/ as uoz c o prebid a b2/1919 0UM63

the Initial flesion neutron s*ureo distribution Was r od from the aretp file nmed sretpthe orit act ty preblem we ocheduled to skip St orces and run it total of n eces with Inounslty 4*C0 neutrons per esto.this problem has run 20 Inctive $yeclos with 80182 neutron hietorlies nd 55 actlws oycoe with ttu839 noutron hietories.

thIs seeluletion has ae Ptetd tls requcsted muber of koff etves msing a tetel of 300021 flesion neutren source histories.*1I *elaS with flealonabie ostealel were spled end ad fission neutren sourso points.

the results of the u test for normalIty epplted to she 1ndtv1i eld *llIsion. ebeerptlon, and treac-leneth tuff ycle veawes eret

the th etlliehin) antsV ulus appear normally distributed et the 95 percent centidence levelthe thcbeerptlsn) sycie vsIwewa appear normall detribut d et the 95 pereent sonf iodnce tevewthe ttrk tength_ [ctetwes appear normally dlstrbuted st the 99 percent cefidence level, but net et 95 percent

....................................................................................................................................

|Ithe fIrst estimated combined kcoeenepfut t-t tf * 1.00196 rith an estimate et ndard dlevitl n of . OllS |

Au$ IT 14,16 t9A Fite KM.. $3020no.unm SBA00003-S717.-1200-0S016 KEY 00 AIAHNRExT all Peage I

the estimated 62 5. & 9 pereent keff sonfidmee Iltervee oare 1.00083 to 1.80308 .9m 1 to 1.08420, Vd .9197 to 1.08494

the estimated Cetltilenjeboriptlen noutrn removal tifetime * 3.47E105 seconds with en estimated etendard devietien of 1.81-07..................................................................................................................................

May U4 13233 1996 ile Banat e3028ph.sun 1 SY 00 AflaCHUNEM? 31531 Pogt 1

I" flversien *e Idl101C 1)" 15/aI 9IV6 S p7 3.55*** *-**--**-@--*-*--* *""-****-@* * I *** prebd a es0719 ~s 4?eS5Inpes3020ph eutpas!1020p1o

1. For-Field CrItceatIt studl * 3.01 /to mist 401* S201 62 U02 (e3OZOch)3- C Callco Kiltlts f . . 9$ ec .40 porsity sphere surrounded by tuff51- C CELL CPECIFIC*?IONS.: . INIER VATCR R161ON5- 1 1 1.53645-i -I IUswI"S. I 3 .3091 1 10PIUP.K.* 2 2 "* MUSer- e CTSiIC WORLD1 * * es-9-

10- C SURFACE SPCCIFICATIONSIi: to 140 Ill KI FUEL M0EI2- I tO too s It1t FUEL MYE13I14. NODE 1115- ICCVg 4000 I s0 1301- C IS 1:3ic l 00 la I 0 C0 29 0 a05 0S e -10 e -10

- C 0e -1 0 -10 o 13 e -1014 U 0 -1o -10 -5 -16 s s 10 10eIs- C KATEKIAL CPECIFICATIONS19 a 140 voet wtEamter In ste e Kills tuft) x .92 C vets V0230. c 3.6 Orlsgial garcment/ 2e W11AIT decayed to Uenmum tlest

22 ~~~~10eos..m - sZ o .3980So 11oo.sec 3l6e11,11-233. s~o19000.50 111.344-4 to00.1C 339325-4 344=000 5.55. 1.2991s1-434. 92234.oc 4.Ces4o-7 92235.51c z3226-5 92233.5. 9.1531e4-sZ5- 92233.50: 1.90ssoo-3 93237.10: 2.162926-626. si tWr.Oltn7- a 40 voLS mater In Calic. Kills tuff36- 2 1001.110: 3.474450.3 8016.10C 4.113162-2 11023.50: 3.92441-439- 1 2.500040: 1:15.4 1302T.S0 :3.606963.3 14000. cc 1.140641-2'O- 19"00.30 :.9069-4 230000.30 1.694918-4 26000.5e 1.403653-4I1: .t1 lutr.Slts2 PRINT

I Initla, smurce fre fils retheft raults Fort Per-Field Critlsslty Study * - /. 0 no 10 SI. - 401 32/ 6s U02 4e.020ph) prebfd * 05/0796 15 :4U5

the Initil fslsalen neutren source distributien was read free the eretp file named *rctpthe eriticelity prebtem as scheduled to skip 30 stdes and run a tota of 130 ysclee u1th nominalty 4000 neutr s per eyle.thie problem has run 30 Inactive cycles mitE 119955 mnutren hliteries and 100 active uwles mith 400160 Asutren ileterles.

this calculetielsn hee s letsd the requested amber of keft cycles ucing a tetal at 520155 tfissin neutron source histeries.Olt *seltl ith fleetlt * uateriel were sampled mid had fisioen neutron source points.

the results of the u teat ftr normality epplied te the Individual aellisien, ebsorpltin. and trsck-length kaff cycle values aers

the tt stllisien) cycle valSue appear normally dietributed at the 95 percent cotnidence levelthe tIabserptlen) erle vlues ppear nrmatly distributed et the 95 percent sentd en:e level

warning, the bttrC length) cycle Vals Co not appear ncrmaIly distributed et he 9 percent eonfidence level

...................................................................................................................................

| tbe fina1 estimated c*_bired o*elttsien/ebrptlen trackelth koff a .1191 with an eetlcated stadrd deviatio of .8on1 I

Way 4 IMs3 1996 File Eae ,3O20ph.sm I 00000061717-UO.e200co4 O E 00 so AAcEIET CXIII - peae Z.

jthe astiated A. 95. 99 " pereent heff coenfidence intervals are A.112 to .8269. .98035 to .36. end .794 te .9397 |

the estimated eeltIleINVebsrptlen neutron removal lifetime * 9.271-15 Seanda with an estimated standard deviation of J.92.T6|................................................... . ...............................................................................

I,

Ray 24 12:14 199& Fite Nases s3020pe.omm 8 ADOO000-O1?17-020000016 REV *0 "fACUMENT CXIV * Pael I

tIR wrerin 4& Id*I0/Ct/93 65206/94 56:1S 57*." p**.O.--O-- *--- 0-------* *, -e prebid B. 6/06196 16:18:S720P-sS02Ops uJWP.eS0p eO

1. Fer-fi Il Critfeeltyr Study - 361 t 20 no /mDt 601 320/ 81 U112 (s3020r)2- C Colic. Mil tuff I I5.95 Stec A4 porosity - sper surrounded b tuff5. C CELL IPECIFIUCTIUSi4. C 18313 WATER RESION5 I I NP33:45.3 -t 117:-.6. 2 a 4230193- 1 -2 *IE1s7- C CUT8101 WORL

3 It a 2113.0

16- C SURFACE SPECIFICATIONiSIs- 1 go 150 S £3311 FUEL 20NE12- 2 tO t1 a INNER FUEL ZO31is14- OWE 11Is CO0E 4000 1 30 W1016- e at1c i Ia01 0ee-20 8629 2s05 e0-s -I0I-I0I?- C - -20 -to e *- -tO 14 a 8 -S 0 .14 s I*0 la to IFI1- C RAI3RIAL SPECIFICATIONS19- e 40 wel weter It *etiles 3l11 tuft) a .92 S uve e 10220- e 3.1 " riginal Rnrichmentl 20 cc/I? decc2d ts Uen1i Soot a21- E1 100.50c 2."0494 2 1016.506

4 .*J1 OA! 110iz23.5s0. 12lrl22- 12000.510 2.127762-4 1 027.5. .l98406- 4000.50. 1.649389-223- 1900eo50c 5.1143-4 200. S0c 9321-4 28000.55e 1 291361-424- 92234.50c 4 .69u50-7 2350 S 252U6-S 92236.50. 9.153184-625- 9223S 50c 1.905500-D 93 23.30 2.U926-626- *sl Iwtr.e1t7- e *40 wlSl watr Il esalt. Mill, tuftU- *2 D1001.50a 2.674430-2 8016.50c 4.15162-2 11023.50c 3.936641-4

9o20eo 5Dc 1278594 5r D 69i-i 14000.5D0. 1.1461-2O- ~~~~9D00t S5c .1:5390a§- Z0003.5Dc 4Y49/1S * 26DDD 515c t 4US53-4

31- eta ltr.it32- PRINT

i 'nitial source fre_ fle scitheff results fort Usr.FIeid Critiemaity Study - 3 .6S20 S1D0ct - 4 * 120/ n1 W02 CaSO20pa) prebid * n2D06n96 16:18:5?

the Initiel fission neutron souree distribution wee read freo the arctp il* named Jretp,the criticellty proble- wet echeduled to ski *0 Occles end run a total of 10 *rctec with minlly 4000 neutron per eycle.thie problem hoe run 30 inactdive ley with 12001 mutren histories end 00 Ictiw tea with 399469 neutron istories.

this ceteulatlon has sempleted tAe requested umber of heff e cles using a totel of 519870 fissin neutren source histories.eli cells with fiscienabe usterlt were sapted end had fissien neutron souree points.

the results of the w test for norma1ity epplied ti the individual collision, *sorption, end track-length khef cycle Velnee ore:

the ht collision) cycle values appear normally distributed et the 95 pereent eonfidence levelthe lkshsrption n ole vsluces VePr normally distributed et the V5 percent confidence levelthe *yirk length) Cycle Values epper lrmally diStr buted at the 95 percent eonfidence level

the final estimated cembimed eelilcein/ebsorption/treck-lonoth taff a .98670 with on estimated setndard deviation of .0075|

May 34 MU,1 1994 Fit*Isaias s3020pa.rm B5A000000-01717-O200-00014 REV GO AITACNNERT CXtIV Past I

t Ia th stimated £, 91. & 99 percent kalf eonfldnce Interval. are .98395 to .98745, .98520 to .93319. amd .9471 to *W8L

thme esttlated calislaenlabsorptlen mautren removat lifetime a 9.301.fl Saconds withi an eatloated standard deviation of 1A.6S-7~

I

Nay 24 12116 1996 File Games *2Cpb.eue tTAOOMODOO.17l7-200-.0016 REV 00 ATIAciNERI CltY Page I

1I version 4a dIdll001193 0/106/96 T1716:04/*** s*****w*******************@***********-*****s--* robld * 3069 * 178"3 * 8

IUP-o5020pb OUTPa&3020pbO

1. For-Flod crttiolity study - ..n 20 /g 0/at - *0 320/ IS UW2 (e0020ob)2- C calico gilte ?u f 1.5e95 glee .40 porosity - phere eurrdod by tuft5- C CELL SPCCIPICAI1CIS4- C IbtfEER VT4E1 REGION1* 1 t ..s3SS-2 -1 iIPuE1I*- a 2 .42301 t | -it Imp|I: oUT53DE UOILD

IC- C SURFACE SPECIFICATIONS11- 1 to 160 S INER FUML totE12- 2 to 220 S IbOt MEL 31

14 IIO0E 1t5- . CC00E 4*000 . 30 IsO16 C 1C3 501 0 1 0 C 0 020 P9 6 20 0 0 O 10 0 1017- C S -1-20 -10 0-1 0 -10 14 6 I 5 10 % 1-411 0 i010 IF1- C IUATit1AL SPECIFICATIONS19- c a44 voS wter in gstice gills tuft) x .92 W v. U0220. e T.S Or1inet Enrichment/ 20 6WD/31 decayed to Uranium Isotope21- *1 1001.5I c 2.440494 a 04.1Oc 4.21:20- 11023.sCc 3.G2113 1:22- 12000.SCc 2.127742-4 13027.5 0406 14000.50e 1.0439-223- 19000.10 1.114304 fCCCO.C .29325.4 26000 I 5 1 9 15 6

l.U4- 92234.Sc 4.494450-U 223S.54c, 42286 2C23 0.Sc * 19136-625- 9223.sSCc 1.905500-3 927.Sc 2.162926-6

27- 62 0 voill water In cellos Kill. tuff20- 1001.50. 2.67 540-2 "016.10c 6.153162-2 11023.50 3.9641-429- 1200810.5 2.371514 13027. 0c 1.606963-1 16800.9Cc 1 .14641-230- 19000.5c 5.159069-4 20000.5e ".694911-4 260o8.15e 1.463U3-431- *t2 lu"tr."'12-: P81927S r-

-heft rculte ourUe tr tFieldCr1 tice lty Study - 3.01 /210 GD/mt - 40t N20/ U1 1102 s3020p) rebid * 95/06/ 17,56

the Initial tiesien twitren soures distribution No& read from the erctp tile mood *rctpthe criticality problem was echeduled to ekip 30 cycles and run a toteal of 130 cycles with nOmtially 4000 neutrons per cyele.this problem has run 30 mactlv. cycles with 119827 neutren hloteries end 100 ective cycles uith *00132 neutron iseterles.

thlo ealuletlin has ecupleted the rquested fi*ber ef half cycles uming a total of S20CO9 flisson neutron source histeries.all sells with fiesionable materiel Mrs sampled and had Mesln neutron oeur" palante

the results ef the e teSt for normality pPlled te the Individual cellision, eaebrptien. and treck-lentth Self ytcle vales are:

the ht collision) yetle values appear normally #istributed at the S pereent confidence levelthe khaboorptien) cycle values epper normally distributed et the 9 perent confidence evelthe ktrk length) cycle velums appe"r normally distributed et the 95 percent confidence level

................................................................................................. .................................

|tb- fInal *rtilted esombind eelltelenieboarption/track-tentl half - .uno2 ultb en1 etit"ted standarre devletlen of .eewo

R&Y 24 12116 1996 Fit. Nross SC20pb.6S IIA0OOSO-01717-O200.60016 RIV 00 ATTACKNEXT CXV - Piae I

the estimated "8, 95, £ percrenct h1ff *onfIdence Intervals are .9U40 to .99000. .9&7" to .990, nod .S97S to .00132

the "tinmted clelsionfabsorptilon mutrsn removl tifeAtim a 9.1119-05 socands mit an acstivated standard deviation of 1.6It.S |................................................................................................................................... I

lay 34 1MIT 1994 m it, Keon *aS020pc.am UsA0ooooo-4i717-0200-90016 REV So ATTACMEMN CXVI - Page I

1*n vdr.n d Id%10Is/93 OS/o6/U 19.23:33

l*3020pc OUTP-s3OZwpcO

I- Per-FIeld aritlslityi Studr- 3.01 /o0 4n/mt * 40X 20/ a1 NOR2 (aS020pc)3- C a Is * Il 1.1095 gtec .40 porosity *espherc urrumdad hy tuft3. C CELL 3PICIPICATIiOI4- C 35r3 VA1Et U e16l01 333345-1 6.335845 1 WWI* a 3 2 423019- 1 -3 IfUtt-l7- C OUTSIDE 115L.6- 3 0 a INP.E.O9.lo- C SURFACE1 SPECIFICATIONS11 1 su3r~rS wtl0 175N3 PUElL RO3E13- 3 30 33S S 13331 PAL ZONE13-14- NO01 a11- RZ001 4000 I. so IS01£- C ERIC i 3 0 1 30il 00 20 a 0 t 3 20 S -5 -10 0-17- C I o- -0 -1 0 -13 0 -10 0 * o -1*ts 1 i -161 S 5 o 10 10 1710- C MAtERIAL OPKCIu3CA?0S119- c 40 vol meter in calls. lilts tuft) a .92 I vott U0230- * 3.0 Orig~nal Inrichnt/ 30 61l10/N? d tcd to Urranium iote1- el 1001.50c '.410494-3016. 5 4.3120-i 1023.50: 3.4z21710

13000o.soe :.12 772413027.0: 3.39406-3 14000.110c 1.049309-ts- 19D00.fOc 1.114344.4t000. 0: 5.33932-4 34000.S 1.291561-4

2X- 2ZNX soo450 4 -7 5: s P.52 - 92236.30. 9.133134-635- -92231.5Cc 1.95500-3 93237.1Oc 3.132926-I36- Itl lmtr.OIt37- . 40 volE Mater In Galtla s*1ls tuft238- m2 1001.1tc 3.67440.3 601.10 4.113162-2 11023.50: 3.936441-4Z9- 12000.10: .31278-4 13027.50c .6069463-3 14000.S0. 1.1641-30. 19000.10: .5$9069-4 20000.0c 1.694918-4 26000.55. 1.40653-4S1- at3 lutr. It32- PRINET

I Initial source free tile *rctIkoff results fore For-field CrItieal ty Study - 3.6 S20 n 1M/t - 40S 020/ e1 M 02 e ISsozpe) prebid * 05/06/9 19.33:3

the Initial hasd.. mautren sours, distribution was road fee. th.....tp file amoed aretpthe critleelity problem was scheduled to in tatal of 1IS Syls r wIth meminally 4r00 neutrrns pr eycle.this Ir blm hasn run 0 insctiv sytes mith 130259 eutren hist*ies and 100 active Syces with 39"71 neutron hstories.

this ealculation has completed the requested number ot huff Teles using e total of 11198D fission neutron seurce histories.etl esell with fislsnbl* moterilt mare Sampled and had file on neutron esurce points.

the results of the w test for normality applied to the Individual tollisisn, absarptlen and track-length haff sycle values ares

the I ecollisisn) cycI: vatles smPear normally distrbluted at the 95 percent confidence levelthe ttnbsorptln) sycle vtlu ppcer normll dIatrjhuted at the 95 pre nt sentidence levelthe kttrk length) rle valwe sppsr ormal ly dlste tad at the S9 percent sentidonce level

.................................................................................................................................

|the fin t estimt d *eo bf d eettileleb erptlwjtract- tth Raft a ."014 with an *stlmted steandrd devletl n of .tO056 |

i

t

Ray 24 12IT 1996 File Ines. s3020pc.sua £lO9RO1142OOO1 l S0 AITACKUET CXVI * Page I

"ai ottileted 63. 9. 9 99 psercent tell confidence Interval. are AMU92 to .99101. .933 to .99136, end .9375 to .99242Ith. estimated eattla1.u/absorptimn neutron rmovat lifetime a 9.041-OS somarde Otis en estimated standerd devietien of 1.6n-71.

may 24 12hi l99i File Itaes s3OZopd.sUm REVoo0 tonr CU17 0 Sl tSo tTTACtXtT CXVIl p aige 1

I" versien It lId1/01/93 05/06 2 al.l 42* * *** -***-i*- *****--********-*--* ~~~~~~probid * 41sI06/6 2141:42

lU-Ps3*2Cpd OUTPvs3C2OpdO

1. For-Pit Crittl iyel Stuysr - .ex /IC GM/nt * 401320/ S ue2 ( 2S320pd)C c al asO E~lfis T 1 .5 u/s .40 porosity - sphse' aurrnd y tuftC- C CELLC*SpECIPCATIOIS1

4* C IMENNS WATER 11.300s- 1 1 . 5341-2 .1 IMPIE

*. a 3 8.412309-a 1 -2 MM

10- C SURFACE UPECIFICATIONS11- 1 40 190 S I3bEI FUEL 20ii12- a So 20 S I'tEI FUEL ZONE13-14. UWE KIS 1C001 450001 01301a C S1t 6 0 10 I -e20 a e 2I 0 20 5 I e S1 -1

Cs t .5- 20 -IO a S1 I -101 0 5 . -1 -1 -I -1S 1@10 la to 1IE C £ATMIZAL SPECIFICATIOeS19 e 4 40 velX water in Salle. Bills tuffl x .92 a volt U02at- 01 Whet *nrieh4entls 0 MINT de9 ad to Ursnium Isotopes1801.C 4444 4016.1Cc 4. 116620.j i1023.50c 3.021710-4

19000.j0c 1.114344-4 1000 :0.c Os 25.54 26000.155 1.291361-4Ul M .225.O 1.905500-32 37.S1c ZJM6-

2?- 2 40 volt motor In galls. K111. tuff28. .2 ~~1001.10c 3.674430-2 61016.1Cc 4.11162-2 11023.54c 3.936044.

29. 12000. 1C .312735-4 13027.5Cc j.0646963.3 14000.10s NUNNC041-30 19000.1Cc 5.159069-4 20000.1Cc .694919-4 260008. c .0343-41. at52 lutr.SOt1 -initial TRY. re ie rt

Ikeff results for: Wa-11eld Critt.cal1ty Stud)' - LU6 /20 0/MM - 40%1 320/ USD 02 (e3020pd) prebld 85/056196 It1s1SIM

the Initial fission neutron touree dlitributlin was tred from the aretp fite meod eretpthe eritlecalty preblem was scheduled to skil 30 aysles end run a tMet of 130 eycles with nominally 4000 neutrene per eycl.thie problem has run 30 Inactive eycles .ith 120110 neutron historIec end 100 active cycles with 400181 neutren bleterles.

this celculation has cc apleted the rquested number of keff sacns using a total of 120297 flesion neutron source hletorles.all cells with fissisnabl* materel ware templed end had flssion neutron source points.

the reaults of the a test fer mortality applied to the Individual eslllsisn. beserption end trcsk-lsngth eeff eyele valume arer

the tt eel tion)l *yele values appear normally distributed at the 95 pereent confidence levelthe i ebscrption) cycle values appear normally dtstrlbuted at the 95 percent eonfidence levelthe kitrk tlength epte values appear normally dfstributed at tha 95 percent confidence lovel

...................................................................................................................................

|the f1nal estlimited ee mblnd totlisiv~ebsorption/troekt-erntth teff * ."7o wtith tan estliuited *uirdard deviation of .eeo66 |

May 24 I2W1 1996 fiale *Bas s3O2pd.*m 3UO0000004171?.11M-00016 REV VA £TTACKMENT CIVII - Faes

Ithe otiated "68, 9S. I 99 pereant koff cenfidence intervals are .99694 to .9986 .99628 to .99392, and .9 A to .9S935 Ithe estimated cetItlIelnabarption mutron removal lifetime * 8.90345 secAnds with an estimated standard deviation of t.' 37SI

..................................................................... .....................................................................

II

way 24 12.30 1996 rile Rus 83020pe.esu *3A00OD06 Ct-t0-S0016 CCY 60 aTTACUIEUT aCYIji - Pass I

crne .version 4a ld.I10/193 s5e/9 3213518probld * 05/06/9 22:33:58

INP86302Cpe 4UI1PwdO20peO

t. For-1ield Cr.tleetity ttudy *. 20 i WMit * - 03 120/ a W12 *3020pCl2* c Celfo Util eI If 1.5 glee .60 porosity - sphere surrounded tq tuft3. C GELL SPECIFICATIONS*- C 111ER MATES REGION

I t t .35345-2 *1 INPalI.6- 2 5.623 a 0 19-2 1 *2 iUIHaE9

I0 C e URFAcE SPECIFICATIONS11 I 90 N05 I15 IN ERPL ZONEII a so 205 * INNER P"EL 20YE13-14- ODE I1S- 10003 6000 1 30 13016 C5 15 0 0 ' 1 3e a 10 I e -20 6029 I205 a eSS e-it1r- c * e -to *10 0 -s I t-O 14 e 1-s *t - S a ete lIs C MATERIAL PECIFICATIeOs19 I 60 vtS water Ir Calste 11ils tuff) s .92 S wetl 110220 e 3.CS Original Inrighaontl/ W CVET doed to Ureni10 isotorar21 ml 1001.30c 3.60494-2 1I16.5oc 4.16420 11023.10c 3.621714 *22- 12000. 1.262 130 27.30c 9."8 -3 d146000.50. 1.9*493392

II 323 23 4 3600.551 11.c J1.1911:4a 19000.SOc * 13M 003 2O0 .5sc o 9 32 ~~~~2234.SCc 94650.7 93235.5Cc .25286.5 92236.0e 9.153114-6

as- SZZ3LS.1eC t.95500.3 "23 .50c I 2526 .626- ett lutrO tt2?- * 40 vetS water In c.lleo N111. tuff

S Z. tttO2 1001.50. 2.674450-3 9016.Soc a.150162-l 11023.10. 3.536641-429. 12000.5Cc 178- 13027.c .606963.5 14000.50. I1:1

4 0 6 41:f

30- O19200.5c S 90S9-4 2000. Sc .694918-4 26000.55c 1.401653-

II: P11VT lutr eltI initial courec;from file aret,

Ikeff results form ar-ield Critleaitty Itudy - 3.3A 20 BUD/mt * 60% UZO/ a 1102 (s02Ope) prebid * 15/06/96 M2U3M158

the Initial fissien neutron sourec distributicn as read free the aretp file nmaed eretpthe criticality problem was acheduled to skip 30 eyc ls end run a total of 130 cycles uith Ineally 6000 nautrn per cyle.this problem has run SO Inactive cyctes with 120Z11 neutron histories and 100 active cycles with 3994u3 neutron hnitmries.

this calculation hba copltetd the requted rber of hoff eye lea gig * tetal of 519674 fission neutron eource histories.all cello with fissionable matsrial ware sampled and hed fisslen neutren source points.

tho results of the a teat for normality eppliod to the Individual collilion, absorption, and track-length Neff cycle values ears

the kC ctiall"n) ycIS vIaes appear normally diotributed at the 9 prcoent sonfidence 1evelthe k ebsorptlion) eycla wltes appear normally distributed St the 95 prceent *onfidence levelthe kftir length) eyc wewas appear neral ly distributed at the 5 percent confidence level

...................................................................................................................................

| the final *stlmated cobined setisioln/abserptlenttrack-l ngtb Raft a ."397 ultb an cstinrted stadrd deviatln of Aeoon I

gay 24 IW,3 1996 Fit* Banat as302pa.sum SBAOCCOOO-Sl717-O2OC-gO16 nV o AITAdENEXT CKVIII Peroe 3

Ith ::ti:matd catislein/abserptien neuatron ramovat tifetlues .0394145 ~secnds with an estimated standard deviation of 1.63E-S7 I

-

nay 34 12:2 1996 Pile game oSf2opf.sum KEY000 gon 1 00001 E 00 aTTACKNEIT 50 1 Paoe 1

1Kng verston 4 Id-101e/93I Pscn 4.0.6. 2prebid * 3/0716 00,6632

21P1-S5Z820pf 0TP-83020p oF r -Fleild Criteticall *tudr ~ esI~ o 2J"W .eqf3: Far~i~ida~celi~S.u - .O /to SiD/Ut * 40 1120/f (a4024302040~t Caic Kit lle f1z@1 .s s 95 We . e porosity * sphere surne twff

3. C tELL. 6PECIFICATIINS4- C INNER VATEC 3161011- 1 1 *i iNFle*- 2 2 £.42301-92 1 .2 IMPI.1417 C SUIj1DE VOILEa 3 a a IPI373O9-

10C c SURFACE SPECIFIATIONS11- 1 tO 220 S INNERF UEL 201t7l2 2 tO 3SO * INER FUEL 20311314. NOE O15 "OeE e4000 1. 30 13016 C 9SRC 3 01 @0 06 la .B 20 6 0.29 162015 66 -15 o * 16-1017' c @.5 -20 -10 6.13 6-10 14 a I11 -10 -5-16 55 @10 101?16 C MATERIAL. SPECIFICATIONS19- 40 vlS water In ealle INie tutft * .92 6 vetl WO220 . sOrliginOr l inriehant 20 nloD/NT dec ed t. Urn, um Ieetepes21- *1 1001.30o 2.46*494-26 01.1; ".266ZO 11023 S1c 3.621710.422- 12000.50. 2.127762-4 13027.10 2.I90000- 14000.10 1.049339-223- 19000. 1.11434-4 FITo0 5.339323-4 26000.1.S 1.91361.424 92234.50 4.694410-7 2231. o .5236-1 92236.0 9 131" 621- 922 3.10. 1.903500-3 93237.50. 2.1 2926-626- met twtr.61t27- a 40 wel water In eall"e Ellis ttff2-. m2 1001.C0c 2.674450-2 6016.10c 4.113162-2 11623.10. 3 .6641-430. 12000'Oa1.: I:Ug5-4 13027.l: 1.g:06963-3 14600:0:50 1.1t4130. 19000:54 .8 5 s069- 230000. aC s2 9g49134J 2 o88 s5s0 1.403 53-431- at utr.61t32- PilNtI Initial source frau file arets

Ikff result. far: Far-Flaeld Critifealty 6tudy - 3.61 /20 Sleet - 401 320/ 31 102 (teOOp) prebid * 65/07/96 60.6:2

the Initial flesien neutren soure diSetributien was read freu the eretp file named erctpthe eriticelity Problem wee sChedhled te ekip 30 eyeles end Pun a total of 130 uclce with I.natly 4000 oeutreon oar cycle.this preble_ has run 30 Inactive eyclea with 120304 neutren histerle and 100 active eyclos with 400035 neutran hieterles.

this caleuleatien has cempleted the reqiuested number at, ki11y e uigattla 20339 fission neutren *surce hiateries.all cellul ith fiaseonable materiel mdre sampled end had te s t nuren aure poients.

the resulte of the u test for naruality applied te the Individual teilieien, abserption, Wnd track-length heff cycle values are:

the kg aellilsen) eycle values eppear normattl distributed at the 93 percent eotnidence leilthe taberptien) eyle ve luas appear norma lly ditributed at the 95 ercent tentidence levelthe kCtrk length) cycle values appear normally distributed at the 93 pecent etnfidence level

...................................................................................................................................|the fin l estimted seedelnd setiolenlenbserptle/rSarck-tengthl koff a .1011 with an eatimatod *tenidard deviation of .t00r1|

may 24 1221 1996 fite aomet e3020pf.su, 2AOCCONO-S1t-0200-S§016 UV ni AIACSNcNT m x12 * Page 2 .

the estimated 4t, VS. I 9 percent keff eetdidenee Interalts are .9840 to .9982, .99M to e.0oos3. and .nn 4 to 1.50099

the estimated collilalabsorptlen neutron tenaet tifetime a *.St-1.S seconds with en estimated standard deviatten of I............................ ......................... ,......,... , ,,,,,,:.......................

01ay 24 12222 1996 File lames *02Cpo.usa BAOOO-elClr071T7-0200-01 a ItEv Do £TACUNUT CXX * Pase I

I" rco I ld-tC01 931 ,1 65107/296S1837i43lI .. v rs n X ....... ld. SO2O ........ .tee.§.t2.6.SOZ~psOl:5T prdebd *u............................................. 03/27/9&6 0137#42IV-cs3C2pg0111'Pe<o.20ptO

1* FWr-FUeld Crt Icolity 11M * 3.03 S20 611D/mt * 40% no/ aS U02 (.3020o2- C Call" lilts Tu 6 I 0095 I/ec.40 pOrosity s ephere ourremuded tuff3- t CELL SFPECFMCATIONS4- C INNER WATER RE10305. 1 t 6.s33 5- 2 -1 IKPsI-16- 2 3 6 .423019.2 1 .2 I11P1a1l

10- C SURFACE SPECIFICATION11- 1 NO I3 S IXIIEt MUEL WIIE12 t O 90 9 I5S IEE 20LhOUE13-14- NODE I14- 32001 40CC 1 50 iSO16- C SIC Ie 0 0 la a I -20 0 I I 2to 0 e -10 101?- C I *- 2-10 a -13 e 10 14 6 a 5 .1o 0s - s16 5 6 101011s- C 36AThRI sPECIPICATIOS19- c t w veal wter in cll Kitll touf) x .92 £ volZ U0220- c .0s gelnlnlt nrlthment/ go tD/3 decaead to Uranium Isotopes21. S1 1 I.sc 1.4604194 2 6016.5Cc .21e620 2 1123.5Cc 4.6211 422U 12000.Cc .127762-4 13027.50e .zgs4t6-3 180006S~c 11.9039-2a lt0.S c 1.1144-4 20000.5Sc .33925.4 26000SSe 1.291361-424- 922X.S 4.49450- 92235.5Cc 3.62236 9S22365c 9S.1531t8425- 3.Oc 1.90500-3 o o 23T.5Cc .112t26-26. Ott ltr .t27. e 40 veol nmter In eallee Nills tuff23- e2 10 Cc.5Cc 3.474450-2 t 014.5Cc 4.1531 2-2 11023.5Cc 3.936641-429- lWOO.S0c 731S25-4 15027.10c 2.460696331I 1005CO c 1.140641.230- l9000.50c 5.559069-4 20000. Wc .4913-4 26000.5 a 1.403653-451 et2 lwtr.olt32- P1Il?

1 Initlal tource free flts orctikeff results feri Far-ieled triticelfty study -. S.0 /2W 6110at - 0Z tc20/ ai 1102 eSo2Cpg) prebid a 05/07/96 S1uM42

the InitIal fissien neutron sourss distributien was read free the oretp file named orstpth critical Ity prdblee ws scheduled te skip 30 7e tnd run :.: ,l of 130 c with nolminally 4000 neutrons per es.this problem %as run 30 inactive cycles with bl.e neutron isteories oad 100 activs cycles uith 3997308 neutron risteries.

this calculetion has c peepeted tle reuested number of kostf etesl using a total of 520082 fiterln neatron esorce hiseteries.oil e-ttl with fissitenble Materiel were eampled and had flecin nsautrmn source points.

the results of the u teet for normality applied te the Individual cellosien. bsorptien, end track-length koff cycle vlues ores

the tI oetlielen) cycle vtluee eppear normally distributed at tbe 95 percent oenfidenes levelth k(abeorptitn) cycle valuers epper ormcalty distributed at the 95 percnt env 3Ine level.the k~trk length) eyele values appear normally dietr1 td at the 95Perct confidenc evel

......................fi..l........ed............... .../...a....en.hoff . 00334 u. d1, an Oe standard..ti ............................6|the final e timeted sooubod eelitscienlosorptfltr ct longth toff * 1.eo03U wlth an estimated standard deviation of .eoorw9

Ney 24 12t22 1116 Pilt Name: o3020U".mm UIAUOOOOOet?717?0200-00016 REV Se ATIMMUENT OEX * Page 2

1the estimated , 95, 99 " pr"uI t eft etidefc Intervate are 1.60275 to 1.604, 1.80197 to 1.60512. and 1.10145 to 1.60563

the estimated eolttisain/aborpti.. meutran removal lifetime u 8.M706 scends ith on estimated stendard aietion of 1..t-07 I... _...............................................................................................................................

may 24 13852 19`6 Pile me: elO2Dbe.eau UAW000000-6171?*6200-80016 VEY 00 A£TACDUhENT CXII - Page 1

I*..a ... .. .eeeeeese--e.... .. ........ eees. preble * 64/30/90 19:42:51ItPta-52Cbe WUTP-aS20boa

1. far-plets! Critleali ttud * -5.tS 1I2 61mt * 305 1201 101 U02 e3020be)2. C Calls. HSU TV f 1. a ttee .J 6 perseety *phbre *urrsmded by tuff3. C CELL SPECIFICATIONS4 C UNNR VAUtE RECIONS S I X~X t -2344- *1 iIteU

J- e a 35 2I -2

te C SUtFACE SPECIFICATIUNSII: go Is sts I P1UE L ZoNE32 S0 TS 621511 MUEL ZONE13-14- R W0 IIS- . CODCI 3000 1. 14 5415 C 1SIC 66 1 00 10 I 0 020 0 3 29 0 2015 J0-55 -10 I-41T- C -S0 -20 -305 a 1S a -10 I I-2S o 0-15 *S 5 * * 10 so IT1S- C KATIRIAL IPECIFICATIONS19- e (30 I% water In meltce Itllo tufft .90 la vel W220 * 3.0 Original Enrichment/ 20 6110 dveyed te Ureni so betsy..21- at 1001.S% c I803254 4t1c4.32811- 123.Sc 6.6980422- 1200C.SOc 207609-4C27.3Cc 2.7la U14000.50c 1.137407.223-100Ie 786991-41 I00C 26000.5.i461203-423;24 X-92234Cc 6827 235 SOC 608-5 92238.500 1.14418-

9232.SoC 2.381975-3 93237.5C 2.728657-616- mitl Itr.61t

23- m2 100I.0eX 3a.14279-24 "60Ot16.c 3.69555-2 11023.50c 2.94542-429- 1 0Z.15c 1.34l75-4 13e27. fc 1.963209-3 16000.5ac 8.589752.330 19000. Cc 4.6134-4 20000.0 c 4.285637-4 26000.55. *.657041-45I 2 t2 l7tr.l4t32- PRIOTI Initial insure. free tUl ofet

Ikeff results :;,; Per-Fietd Cr1t215 Ity Study - 3.0120 l/mto SO-3 20/ 101 102 (e3020be) prebid * 6430/9 19.42M51

the Initfel fission neutref source dtatribution mas rerd from the eretp ft a moed *aKtpthe *ritisllity problem wse scheduled to ekig 14 eisa and runs ttetal d 54 sycle. with nhminelly 3000 neutron. W sle.this preblm baa run 14 InactIve ulh *0s Bit utron hleterles end 46 active *yelet with 119399 meutren Istoriee.this calculation hm eompleted the usquseted nmber of hff ay e usIng a totel of 161407 fiesion neutren esource hsterors.ell eelle with flesienable mteriel mre sempled end had fle en nutron sourse points.

the results of the K test tor norsellty applled te the Indlvidual tgolieein, ebsorptl, end track-length teff yecle values ens

the U( ollieten) eycle veues appoer nersally dIstributed et the 95 pereent eoofdenCe levelthe h(ebrorptlon eycle Vs mlue: e normaly e11trikuted t Che pereent eonfidence levlthe ktork length eycle value appear ra8l yi delSrtr buted et the 9S percent contideoce level

................ ..................................................................................................................

I the fIn l estimated combined colialsiebsoroptlentract longth lxtt a . C 79e iuth an *rtl-eted standard devitiotn of .10159 |

Nay 24 13S2 Ins Uite iEma, *3020tb..em S3AOOOo-o1717.o2oo0oo16 REV e0 ATUaCNENT CXXI - PefAt

the estimated 48, ". 9A percent kuff eonfidence Intervits ore .9745 to .9806 .983 to .98227. and .974n to .U9337:the estimated eottlelluonbsorption neutron smovet lfetime - 6.42E1-5 seconds with en estimated stadard eavistlon of 4.sCE4T II.... ................................................. ..................................................................

may 34 13:47 1996 Pile lRout 3020ba.sum UV00000 001? -200001 XN 60 AlTACIXET CXXII * Page I

lecLg version 4- t.10/01193 4t23196 63.:*151:0~~~~~~~~~~~~ ~~~~~~~~~~~prebida 12/ ntioInpas3020be outpesSO201bo

1- Fr -Field Critleality Mtud- S.6 120 Mt - 302 n 20J 10t 1102 3020b )3- C Calls. Ettls tuvtf 1.76 g/ee .306 porosity *phere surreouded by tuff3- C CELL SPECIFICATIONS4- C INNER WAtER tE010Y5- 1 1 1.633424- *1 N1w1"1.6. a .635743-3 1 impWs

16- C $URFACE SPECIFICATIONS11- I *0 125 INNER FUEL Z0E12- a e0 S t, INNER fUEL RtOE'3-14- gloE IIs- SCOOT 3000 1 14 S41U- C 133c 1*1 a I 10 a 6 -20 6 69 a 20 15 0 - -10 6 -40ITr C a *50 -t SS ee-30 I-13 a -10 o 0 25 -30tS -56 5 I e 1 S0 T171S- C IlATKRIAL SPECIFICATIuNSIt e st30 v.11 water In satice Yltts tuft) a .90 10 voS U102

20- e 3.lS r i .In. Enrlehmnt/ t0 VD1T cey te Urenul IsotopesII- El 1c01. c 1.S05254-3 S016. 1 .c 32ll-t 11023 *0c 4.*99044o

22- 12t 5c :4076n94 1so27 $0c nss-s 3 14o0'sOa 1.1sw4e7 a2X- 1te0C~ 50 O"9914 t00W0.10e I:.25,104 26000.S5c 1 .61203 4

24 2 c s96,406oa r223. . 7 SW::i;0 :.:: : S n2s.6sc 1148S*S- ~~~1223 5c Essisn-i 9357.115c 2.72sMs

6- intl Iutr. t7- a so vetS water In salle. Xllts tuf

2S: e2 101.50 3.142479-1 3 016.50e 11693335 2 11023 50c 2 6 S42 42- 13000. 0. 1.741475-4 13027.50e 1.963209-. 100050c e 589n2-30. 16000.0c 4.166334-4 20000.50 4.28soa7-4 26000.55c 1.0570414

31- *t2 Itr.e1t32- PRNI ItIal nourn'ree frm fl *ret

Ihoff results fort ferset- d CritIeathy Study - 3.61 In VAZn/Ut 301 X20/ 16C W02 C.3020b.) probed * u6n41396 64515:0

the Init fi fcssion neutron source distrlbutlsn wa read from the *rctp fit* nard *r3tp sthe crititellty preblee was scheduled to skip 14 ewtet end run a sett. of 54 "ycves with noinlly Zooo routr per r ece.this preblm asc run 14 InactIve etyes wIth 41724 neutron hlsterles nd 46 ative cycles with 120165 neutren hestores.

this oaleulatetn tNC cempleted the requesled rumber of t1ff ceyles uaing a tetel of 161189 fieslen nautren eouree hleteries.*tt cetll wuth fIsstenable moterist Sara mpltd end had flai en neutron sourse points.

the results of tbe u teat otr horeallty applied to the individual ottlelen. absorptIon, and trect tengtb toff "via values are:

tle tt collIslon) yole values cppeer normally distributed et the 95 P rent aent ln.. lewtthl clborptlen r te valwe 'ppear normally distributed at the 9 percent sentflen,. toyathe titrt leneth) ontle valuse ppear normally distributd at the 95 jerent cenf lenec le t

I the fIant estlmated eoebined.ltllen/abserptl trsck-lngth hat f * ."9093 with on estlemtad standard devIatlon of .60177

May 24 13.4 1996 fil to mez o3CZObs.sm U3OO9-11?60S16IV SO A£TIAUNI? SXIZE * Page a

teestfmated 48. #S. &f9percnt kafoftf ofid~e Intervals er: #iSV4 to .992n2..9 33 to .99413. and .93611 to.95theestmatd mttllonmbsrptonneuronrowvolifftim m 111o1S"ed iha stimated standard deviation of 3.23I.S7

May 24 13%43 1996 Filte gse *3O20bb.eu 3U000eOl717-0200-501tEW SC e ITACNINEMT CXX22 1 Page I

1 e..cn varsteh 'a ld4t/010193 64/22196 14:4431-;'°***** eeeeeee ee * oeeese:eceeeeeee eeeeeeeoeeee'-ee..44e" prebid * 64122196 1444:31IEPwsSO2Cbb 0UTPvs3O2ObbC

1- for-VFiad crillegIl St * 3.- 6 2/O S1go t - 302 120/ 102 U02 (3O2Cbb)2 C C lle Ite 1i T f pcc .S06 porsity - sphere surrouded by tuf1

*: C SELL SPECIFICATI2114. e IOEEE VllaE EEScle

5. I ~~1:8.33424 -3 -1 ium4- 2 2 S8u35742 2 *2 DiNPa1Tr C eUTSlCZ WORLD

* 2 IMPIRSO9

10 5 SURFACE SPECIFICATIONSII I S0 146 SUE 111131 20!ZON11 to to Sr INNER FUEL 2en12 2 tO 200 SEEKER~ IIELECIt

13-14 50E S1S IWE 3000 1. 14 54I C UIC S 5015 to I I 29 I 2015 I 6 55 .10 4017 c .Se *20 I300 t13 is5 !10 60 I I -S . 56 5 0 1030 171it I CTRIAL SPEClFI fagsTe19 e (0 volE vater In cellee Stits tuff) x .90 1t ,lt U10220e c 3.62 Grill Enrlchaent/ 20 V10/31 decayed to Uranitu Isotopes21- *1 1001.50c 1.S05254.2 6 e016.3c 4.3281-1 11023.Cc 4.n98044 422. 12000.1Cc 3.40760-4 1027.SCc 2.71SU 14 .0c 1.15e 7407-223S 19000.1c .n6nt4 2000::.1Cc 1.HS4104 26t0O.0 S 1.46"13-42S 92234.50C 5.665067 92235S CC 4 76108-5 92236.500 1.144148-525- 92238.10C .31075-3 93237.1cC 2.7286s7-6I6- intl Wur.lt27- a So vat% veter In s*Ill* s11t. tuff25- *2 1001.50c 3.142479-2 1016.Ccd 3.495515-2 11623.Sc 2.96542-429- 12000.u c 1.741675-4 137.c .32093 14000.5Ctc 1.59a2n-30- 19000.5ec 4.186334-4 2000D0:.c 4.288637.4 26000.5eo 1.037041.431- .02 lutr.Slt32- P1lE?

initial four.. free fil* eretsIkeff results forte Fr-PleitW CritIcal ty Study - 3.62 120 tolat - SCE 520/ 16 102 (o3020kbb) probld * 64122196 16.44s:3

the Initial fledson neutron eeuree distributlen was read free the ertp tfile named *retpthe eritlcelity problam was scheduled to skip 14 cycles end no a tetal of H acyler 1i0th omurlAly 30O0 neutrane per *y*cl.thle preblem has rn 14 inactive cycles wIt I 446 neutren hletorles and 40 cctve cycles with 120232 nutrtn hieteries.

this calculatetn has completed the reucested maker ef koff cycles using e tetel of 1427O fission mautren source hlstorlesell eelle with ilesienable materIlt were seapled nd had fleetn n utran source points.

the results of the u test for nersa1ity eppieed to the Individual cellisien. absorption, and track-tlegth hlkf ctele values are:

the tt celtieslal cycle va lus appear mrmaclly distributed at the 95 percent confidence le"Ithe k(absorptien) cycle vatles appear normally distributed et the 95 pereent :enfilee lethe k(trk length) cycle values appear cremally i1 trlkbuted at the 95 percant canfidenc level

...................................................................................................................................|tbe, finel estimated combined oelateln2 bsorwetlentrock-tonth t tt * ."M9 With an estimated standard dlevition of .0DtU

Ray 13.48 19M FfIs lam: *3020bb.ma RVA000000-S1717-6200 0 mE 0 ATtACIMENT CXXIII * Page I

.1 the estimated , 95, I99 percon: ken f oentfidence intervals are M928 to 1.00119, ."681 to 1.U26. and .9951 t 1.0US65

the estimated celliamnlebsorption neutron removal lifetime * 7.92t-S asend' with an estimated standard devietien of S.4 0E-0|

..................................................................... ........................................................ :.

eay 24 1S3 1596 file el3ss0d2tbc.seu REVOOOto-0 -e2004001 REV 0 £TTACINENT Xx1EV * Prse I

IaNOT version 4a d-1=/1I93 04j22l96 170010:1e~e*O.*OeOOO,**~eee*O~OeO~ceOOO@O~O*,ece~eO~ce~eee.probid Ga 64/2/ 17:16:1

ItP-dt2tbe OUITPeS20tbc0

1- far-Field SritielItyI Sly, - 3.01 se l0et - SOS 120/ 1CS ue12 4i320bc)2 t t L twC Call.. title TV f .7 elee porosity sphere surreunded by tuft31. c CELL SPICE FICATICU4- C INNER WATEREGION1. 2 1 i6.6t42II - t1 tM9n" t

~~ U~gISEWOILIO7 t OUTttOI WetLD

10- C intFACt 8PE0CIFICATEONS11. ' *0 153 S SUER FL 2E12- * 5to 15 ISNE EFICL 3ONE13.14- NOOK I15. IECODE 3000 I 14 5416 C 1E c j ' 1 06 10 I O -20 I 6 29 * 20 15 -S5 -10 -4017- c * - *020 -30 I 13S 10 60 6 -2S n-15 -56S 5 100 a17i8- I RAT11IS SPECIFIC&TIONS19 t 430 wtt Mater in ""l". "2"ll' tuff) x .90 10 woll 110230. POO6 Iriginat Smrfchaant/ 04 MA/T dieccad to ilranium loot'21- el 10t OC e0254- 6016.itc 26111.31 1023.54c 4.898C4 422. 12000.SOe 3.4076094 13027.5Cc 584.5. 14000.50c 1.117407-223- 19400 Stc 76991.3 20000.jc :928410- 1260to.nt 1.1203-424 223SOC .U5062- 92235. cc .73160- 226.C 1.44148-525- 9223S.cSC 2 1.3875-3 93237.50C 23.23637-621. mitl lutr. it27- a 3o0vyo% water IncaioIltt2i. *2 1001.5Oc 5.142479-2 0016.1Se 3S695553-2 11023.50c 2.96342-6

2 2000:5o c 1.741673:4 13027:.1c 1.963209.3 140005.5c 9.529c52-3109- 1006.5ft 44.134 4 toooo.50c 4.28 n7- 26000.55is 1.65741-431- nt2 tutr.Slt32- PRINTI Initial scurce frern fIm I re

tkeft resulta tori tar-F ideldCritlestty ONtud - 3. S 6)101.: 301120/ 1OS U02 1e3O20b.2 probld * a 4/R/96 M7,O10R

the initial fission neuttrn source distribution wen roed from the creep tile vmed *rstpthe aritleelity problin vat esciduted t i WC 14yrdes and run a total of 54 antes uIth Nominally 3000 nautrans per yecle.this problem has run 14 inactive scles with n51 neutron histeries and 40 active antes with 11"32 nautren hleterlis.

this calculeatin has sinptlted the rqicetd ewber of beft cycles using a tetal at 162133 te"ien neutron source hieteries.aIt eeels with fiasieneble materiel were usampld end had fle ion nautrmn souree paints.

the results of the u test for normality applied to the individual collision. abesrptlin. Nd track-length keff cycle Values are:

the it *ellition) eonl vfuese appear normally distributed at the 95 percent sonfidence levelthe tb prptiton) eyce wves a ppear nrmelly dietributed at the 95 percent confidence levalthe itrk tlength) etcle valus eoper ntollo Viat r buted t tha 95 percent c*nfidonce level

.............................. .....................................................................................................

I the fInat estimacted cobind aelialolnladbsorptiontracktoterth keff a 1.10046 with an estimated standard 1 1viaton of .40139 |

May 24 IWO5 1996 FitsIm.eas 95020bc.ma 11A000000-U1?17-0200-00016 REW SO A?1AillEUT CXXIV Page 2

the estimated 68, IS. & 99 percenft keff canfidance intorvets are 1.00320 to 1.00601. 1.00173 to 1.00743. and 1.800SZ to 1 .0839

the estimated setitsion/absorptien neutron resevat lifetime a 7.73-OS saencins with, an estimated tatndard doviation of 3.1 607

may 24 13S51 196 Fit* ItKae *3020bd.srn U AOOOOZ-01717-6200-MIOi U2W 00 ATTACNEIT CXNW Page I

n'2ep verson 4 Id1.= *. .ld~t0 l. 6dl /22/46 17135:19e..aea.e.....e..aa.....eaaae....a~ae~eaaeaa~~e..eeaa..ee.probid G4162216 MUM5:1

Ifu-a3020bd VUTPwa3e2tbdO

1. Far-fiehl CrIfcalit Study .es /20 IWO/mt * 305 1/ 12 U02 (e3020bd)2- t C lieo Xllt Tutt t /eg .306 porosity - soereourr ud d by tuft5- e CELL SPECIFICATIONS4. C INEI WATER 1t1362015. 1 1 033424-2 -I IM11:6- 2 2 3:.035762.2 I 2 IMP.17. C OU~illW WORLDI. 3 0U 337:3.0zb9-

tw- C SURFACE SPECIFICATIONSII- 1 to 170 C 3311E FUEL ZOE12- 2 30 230 S ISNER FUEL ZONE13-16- PO0PE15- CODE 3C00 1 14 5C14- C src iS1 0 00 0 0-20 I 029 20 15 C0 10 -401T- C .50 -20-0 0 -13 e -1 60 C 0e-25 -30 15 *56 5 1 to 30 1?Il1- C *S&L14 CIPECIMSATIONS19. 3 wl watae? In salt.. Kills tuffl .90 10 Weis U0220- e . Orinal grlichantu 20 lOT dec;yd t° UranI. Isotops21- *1 001.5Cc 1.C05254-2 1016.5c U5ZC111- 11023.50c 4.99804-422. 1000.5Cc 3.4076W9 13027.35c 8143.3 16000...c 1.187607.223- 990 00 3.7U914 20000e.sc .23410-4 26000.55c 1.461203-424- 92234. OC 92235.305 431608-5 92236.CC 1.16143-S*5- 9223 .SC 2 81375-3 93237.50C 2.765T-626l- Mal1 l trl27- e t0 weSeter in calico Notts tuft23- *2 100.5Cc 5.142479-2 s016.50c 3.695535-2 11023.5Cc 2.96452-42V- I 10 0 1.761673-4 13027.50c 1.963209-3 14000.lCc 8.589752-35D- 19000.a c.136 34-4 20000.5Cc 4.28337-4 260D00S. l.057061-4

Skeff results tars Fer-Field Critleeflty Study - 3.0s /20 NtnO/t - 302 320/ 101 Utl2 (302Obd) F"Ibd * 0422/96 1T75:19

the i1nitial tterl n moutron *our" dietrlibutlen wa r~ed free the eretpa 11$ ntd *retpthe criticality problim was scheduled to skip 14 leas ad run a total a 54 gycles mIth minatly 3000 "autr. per svte.thile preblt has run 14 Inactive cycles with 41T73 neutron histories and 40 teye *pts mitt 120050 mutren hlatortes.

this ealeulatin has momplated the req2etd - *t r of ett t usain a totel at 16172 fissl n neutron source histories.all cello with tMMsienabl material, were sapled end had fl n an ute-n source points.

the resulta at the u test far mormality appold to the individual etolialen. ebsorptlion, nd track-lensth eff epclo values reas

the tt collision) cycle values appear normally dietributd at the 99 percent confidence level. but not at VS percentthe ktebsorptian) ycple values appear normally dritrIbutod at the 9S percent eonftdence tlthe hktek tonth) eycle vles eppear normally istributed t the 95 percent cant dane lveI

...................................................................................................................................

|tho fin l e timatod ezbin d *ellteslontaorpt1 nttreck tleoth keff - 1.00961 with an *estleeted standard devletien of .eot55

.

gay 24 133SI 1196 Ulo Sum: a3O2Obd.wo UAOOV Os 1?7tO2tOOOOl 1Y So ATTIACIIT CXXV * age a .

the estimated ". 95. & 9 percent hoff eonfidence Intervals are 1.00804 to 1.0111Y. 1.006" to 1.01276. end 1.00539 to l.0l133 Iti, estimated etltloeienebeorption neutron remoyat lifetime a ?.5SE-05 seconds with en eatluated standard devietion of 2. 071

...................................................................................................................................

Noy 24 1:34 1996 File lams 6S020ah.su e3620eD041717200.016 V 00 ATACENT CXXVI Pgse I

*.tmce version CS 1#001 S102/96 19:23119

inp-s3020ah sutp-SZOpb a S 6

1. Par-Plisd Criticality *Stuyt 3.01 Ia0 "DA/t - 30U 320/ IX U02 (a3C20sh)2. C calte I i touff 1.7 gVee .S06 porosity sphere surreunded by tuff31- C CELL SPECIFICATIONS4* C INNER VATES 31EMOS. 1 1 .48912-2 -1 EPal t-l1: S a 1 :65 2 -2 Imp$

7 t eUVT5I1 OC IDLO

10 a antc sINeF luneO10 C 11131AE3 IPECIFiCATIOCI11- 1 10 J0 * HOUR lWL 301W12- 2 SO 40 SUEUSP WEE 20I13-14- MADE K

16- C 4000j Ij 750 01 6 e .30 @0 29 6 20 1n I 5 -106 .401?- C se5 -t0o 30 13 0 1e 60 I *- S-30 -15 -565 S a 10 seTIs- C MATERIAL PECIFICATIONS19- Po vtes water In entice 3S1te tuff) .92 6 vetX U02

2.6O original nrishln7 go W30 delcawd to Uranium iootsperm1 1001.1Cc 1.45m371 2 6016.Cc 4 15449 1 o023 *c 4.18911-

22 12000.0cc .461 1 t3027 .5

c a n i : 4000. 1.e13794-313- 19000.SCe 3.9155S9-4 0oo00. cccO .66152 4 UOOO SSe 1.49364

92234.5Cc 4.494450-? 9223S.Se 50 .2522 6 92236.1Cc 9.1531674S. 92238 I5c 1.90355CO- 93237.5ce 2.182926-4

16- Mlt Introwit37 e SO vetS water in all l 3 a t111. uff0 .2 100t.5Cc 3.142479-2 6016.gOc S.6955?- 2 023.*Oc .9542-4

29-I .. 0.sc le1.. 715.4 13027. Cc 1. 209S 14000.5Cc 1.52M952S19000 .Tc 4.1 6334.4 20000.50c 4.*8 27 4 26000. Sc 1.057041S4

31- .13 IPtr.SIt32- PTI

I initial ouree fra file rikoff results fors 7er-Field Criteat ty Study - 3.nZ J20 S/at - 30s t207/ 8J 902 (sSC2Oh) probld * 5/02106 123:19

the initial fission neutran source distribution was read from the *retp file nsed ""etpthe oritiality probsla was scheduled to skip 20yacles *nd run a total of 7n5ecls with neinatty 4000 neutrons rr ye.this problem has run 30 inactive cycles vi So neutrn histories and 55 activ eyces wilth 219827 neutron bieters.

this calculation hae eepletted the rested umber of keff cles using a total of 29977 fission neutron esures historiec.all etlls with fissionable material. mere eopled and ad fison neutron source points.

the results of tbe w teat far normality applied to the Individual coltision. ebnsrption. nd track-length t St cycle values aes

lbs h collision) cycle values epprar normally distributed at the IS peent confidence teett1he kibeerplo)gce auseparnral diatr buted at lhs r~ erent confidence Le"etlbsh I~rk length) eycle vluss appear normally distributed at the 9 percent sonfidence tle

...................................................................................................................................

|Oth fINIt *etteted combined eeliflcln/eborprtlen/tract lergth t ff a .U927 with an estimated standard deviation of .eo0e01

-

KaY K4 12384 1996 M11 Names $3OZtaiijms aISCNS?7O0-0 16Iv so ITACKN!II CXXVI * Paes a

the ustimated 48. 95, 8 99 percent koff conf Wifnce Intervals are .98224 to *98129. .93125 to .98530 and .98058 to .S915

the estimated cotisioniwabsojption weutrmn rmoavl Ofetime a 9.031-fl euctwde with an estimated standard doviatiofio .2.7

0

a

way 24 1U141 1996 Ile Renta 8S0 0agl.sum SIAOeOOOO0 11T7-0200.W0016 UV so0 AIACNIHST CXXVII * Page 1

lucnr wrele 4e t - 10/! " 5t§V 16346sU*-c 3 ld---/-* 9 1510119 14a2a4. prbebd a 65101/96 14,4t:48

IeyweO2Oag autpse3020at

1. per-Fied ritletitv Stuy 1.9 10 CWM/t * S C20/ X1 U02 13020a62i- C Cal lee l Kilts Tv f ee *4 porepo ity * phere surrouded by tuft11- C CELL 1S1ECIFICATICON'. C 1111A VATER .110U15. I I 8.6441182- -1 INP8UPI1 a 63 742- I -2 Rk1:::le: C UrIT 1U0SLD

82- 2 'O 22 t. It a

9.

t4- C SUjRFAC SPIC P01 * 9 t t 2O1II- 1 10g 320 5 1111111 FUEL 205!

la- 2 to 0 01151 FlaiL 20NE13-14. NMI a

10- ac 05E !knont 0 011T d cd te Ur4nium00 1e2t02t: ml 1l01.5D 0 6-2 0c 4652 90 15 23550 4-129111-422 12eI0 a 11 - 1021710c I. 41S Doc c 1 213?94 223- 19000. c 5591. 20000.10c 1.160152.4 24000.15c 1.495474-424- 92234.10 6.9 07, 922O3S. 50. 3.8251-5 92234.58. 9.1113164-025 VMS. 1c .9 03 9)237.50c 2.102926U-:3 *It a nte n e l

28s o2 r001.3c 31.'D4479-2 6014 3.495ss 52 11023.50. 2.944542-49. ~~~12000.50. 1.741475-4 13027.10. 1.943209-S 14000.50. 6.589712-3i: t19000.e50, .116633-4 20000.50c 4.124$37.4 24000.f5e 1.63754 3

312 it2 tmtr.@lt32- FINT

Initfal Seune tra, tile ensteIkeff results for. Far-Fietd eritleatity Study - S.6 /2 OWlat . 301. 120/ t1102 ( 3O0eg prid * 6r/1/9 10:8448

the Initlet Ilesi.n Mutrn seurce dietritbutlen was ad frau the enrtp file amed aentethe or t ceto ' prebt_ e scheduled to skiep - arees and rn a total of n acltes wlth nomnalty 4000 autrona per *r tl.tis problem hia run InSO ttive syclas with 9475 feutron histerl end 35 active syces Kith 220024 mutton bistories.

this eatlcutatin has momplted the requested nmer of heff "ycles usinw a tetet at 29970 fIssion neutron sourse hieterles.alt nelle with fissconable _aterial were espted end had fisaIen neutron mure psInte.

the results of ths v test for normality apptled to the Indivdual ntllision. aeborptlen. ad track-tlngth taff oytc values resr

the hI aetileienj pycle vanues swear normally distributed at the I5 percent anftidence levelth hietbtersption le ntlues appear rmally distr buted at the 91 percent eantidence levelt Irk tk lenth) ytle value * "pear norm distr buted at the 5 percent eo nfidnce lvel

...................................................................................................................................

|the finat ectlwated coblmd * tilel - # - rpitlontreckt lnotti kat a .9905e with an estilat d standard dbvietln of .90111 |

.

gay 2a 12:41 1996 fls, Nese3020a.ua S3AODMOD10n71?I-O O-00016 REV SO lTTACINEXT CXXV! - Page 2

the estimated "8 95. & 9 percent laft confidence intervals are .93935 t. .11162, .91127 to M73. vnd .9973 to .9934 1

ithe estimated cotlislon/absorptien mutran removal lifetime a -$.S1-5S secends with an estimated standard dewvitien ef 1. 9ES7?|.... .... ........... .... ..;........... ........... .... .... !...... ....... ... '.... ... .... .. '. ... .... .... ...

May 24 13u40 19m Fite sats a30200f.su RAOOODOO 7-6200-00i 3EV e0 ATIAeEN? exxSIII page I

le e verslon 4*r- Id-1O* S10/135l I d5u e 5212

ir OZsf wtp-a3020a1f

1. for-Field e rit iC litr studY * 3.3X /20 sub/lt * 0 1N201 61 U02 (a3o2zoa)2- C eall. 11llts Tuf 1.7T gl/e .306 poresity sphere aurrsutded by tuft3. C CELL IPECZFICATIONS4- C IERIK WATER 316201

' ¢ ~~~1","4^"'2 *t 1e IM

X 2 2 l:|a35742 t 1 -2 INIPt"-1T7 C GUTZZOE lUL6- 3 6 a 11PM10I.

10- C SURFACE SPCiFICATIONS11- 1 30 JC S I33f FUEL 20E12- 2 0 6 tIYItUL NYE13-14- 11001 I15- 13 0001 071_ C5 1330 61 * g ge-Nc 6629 6 20 1S 6 1 6 *S 4 0 e i I

T. C *50 -- 30 0 -13 IS 1 60 I e-2 -30 15 -54 S I e 10 30 1T

19- C (30 volt uter In *asl. Itl Iuf a .92 £ vetI U0230. a 3.61 Grlislna tnrolrnt/ Ng Io/r e3 d to Uronlu teot a21- .1 1001.50. 2 10 Oe 4.ml f 49-o 11023.50c 4.18911-*422 t20CO.IOc .1 111 027.90I 41O. OOa 1.213794-323- 19000.Oc .915s 1-4 I 0000.SO:.1?6012- 26000.55. 1.493674-6

24- 234.5 Oc.9 o I 2255.Oc .25256-5 92236.50c 9.153184-625- 9 5s.soc 1.903500-3 93237.10 2.122926.62d stl ltr.St2?- " t0 vol ter in csalle 1I ls tuff23 .2 1001.50c 3.142419.2 SOlO. 3.693165-2 11023.0.c 2.964542429. 12000.10c 1.741673-4 27. 10Sc 1.963209-3 14000.10. 4.519731.130 19000. O. 4.166334-4 20000. cc .23637 - 26000. Se 1.e6t41 -31. *t2 latr.6lt32- PttlT

i nitial source fre *tie rstoSksff results Fert Fsr-Fie Critiatidt y * 1.61 120 n Wo /t 3-o 12 X/ 3I02 (Ws320et) prebid * 63101/96 l3.s46

the Initial tissien neutren Sourec dItribhutlen was read frem the erstp file named erctpthe critical it probtee me stheduled to ski 20 to s a and ru C total of " "elel Kith nominally 4000 neutrns pr mele.this problee has run 20 Inactive ols Ml 1 80313 neutron hietories snd SS active scles. with 21910 emutren ieteras.

this aloulatlen has see pleted the nequertsd _uber f heft awl.e using a totat of 299495 fission neutron eouree histerri.all celle uith tiassenable Material were empled end had fieslen neutron source poInts.

the results ot the v teat ter noraity applied to the Indivldual collision. aboarption. nd trect-length teft cycle vluw: qret

the t( sollison) ytcle value appear normally distributed at the 95 percent centfldene ltvelthe I orptln) arcl vae appear noral ly dltributad at thl 9 pereent senfidenca levelth rk length) tcl values appeaeromatl dstrilbuted at the 95 perecnt astldence lewl

............................... ...................................................................................................

th fictnal salivated obinod ootisloen/sbrptlen Jtreet tengti tf tt *~u .n ,,, a~ln estleated stadrd drvletl n of .1otes

may 84 12:40 199 Fii.le Vwe 83O20 f.sum IIV00.07?00001 E @0 AIIAtENEI CIXXIIE - Page f

teestimated dl. vs. A 99 percent keff Sonfidence Ontetwate are .99523 to .99740. .9415 to .9914. and .934 to .99919I

th stimated sa.Itls.nlabserpdtou, mautten iemovat tfetlue a 8.7215-esacenda with an estimated standard deviation ofI 7-..... .

say 24 13438 19 Pile la e s* O20ce.anm 63AOO0 001* 0200-0014 IREV 00 ATTACN2l i? CXXIX - Pao I

l=.*s! version 4a ld-10101193 64/30/94 15246:22S-* n " t:|°a~a25 .............. o !soeu 1ga44s2 pt ebd * ............. 64/30196 1.6:2

IKP-sSC20ac OUTPaa3324caa

arUPetil rtit~ctiltt . * 3.00 10 s1D/St - 3S% N20/ X tOZ s6le2Dc)2- t ar-FleW C iti l title I T 1l. r I . porosity - sphee s rreundid by tuft3-* C CILL 5EPCIPIATII0S4- C ININER ATEE 3EEtJ

^- 2 a *."570429 a1 -1 INPOIS"r X e~~UTSIDE WORLOI: I I 2:f~ : 111111,1:

10s t tUnFACE SPECIlMATltNStl- tO 00 61IEA1t WEL RUE12- 1 ! tO 6*0 * lltYt lEL 2011E13-14- IMCC UiS. 10001E 4300 1. 30l1 2

14- C lsa1c sI 6I I66-20 6629o t 62011 a-53 -1060-40IT- C I .50 20 -S0CS.13 6-1C0 60 II 25-0 -11 *&5 5 510 30 171T: C VATERZAL PIECIMAICl 035S19- (30 vatl Mater In *elee. mitls tuff) C .92 a vel tle220- a 3.601 Griul l E iehmt/ 20 a lel deca yd to Uran Isotopes21- *1 1001.SOc 1. 6 371-3 016.56c 4.315649 11023.50c 4.19111-432- Se12000.C 2.641111-6 13027.50c .774t56-3 14000.50c 1213794-2

1l000.50c 5.915591-4 20000.5Cc .660152-4 26000.5. 1.4347?4-4j3. 92234.5Cc 4.494 T- 92235.5Cc I.82126-5 92236.10c .153164-

f223.1C0c 1.901100 93237.50C 2.16926-62- tl Imtr.t1t

27- a go volS mater In altic Eisle tuff23 *2 1001 Sc 5.162419-2 6514.50c 3.49538 -2 11023.50c 2.94442-429- 12000C Oc .76T1675-4 13027.5Cc 1.96209- 14000.5Cc 8.569752-3W0. 19000.5Cc 6.1U5634-6 0000.5Cc 4.31637-D 2000. 55 1.057041-4

31- NtZ lutr.61t32- P5131

inItialt soure free Itil s dDltef reaults fors For-Fl Id Crit 1.11ty Study - 3.6S no 6t1at - 301 320/ 1 1102 .3020..) probfd * 4/30/96 1446

tlb 1n.t2at fissten rutrn sourq. distrlbstAin was read free the cretp file mixed Kretpthe ritia tttyr prblo pas scheduted to skim 20 cntes and run a tatt of 75n ctes with misally 4000 weutren a a sye.this probtle has run 20 Isactive cycles with 79804 seutren histreIe and 55 actis cycles wIth 21913 meutran Iattercs.

this celculstion bag aoted the requested number of heft cyces weisU a total of 214424 flssion ncutren sourse hieteries.all cells with thsfeable aterlal were ampted and bad tisl en stren sowure points.

the results of the w test fsr normality applied ts the Individual esilielen, abeorptln. and tracktlenth taft cycle valws. cres

the kg selllen) eys values appear normally dIstributed at the 95 pierent *entI dcncs lesvlthe t Ib etptien sclova appear nernatly dfotributod at the r9 osucent annf nce Ivthe k trk length) *ye values 1 ppsar ors T distr buted at the 95 perent ent dene le

........................................................................................................... ........................

|the float estimated *eebtrd *ettiloelabeerptl oJtracktolnstil kiff . ."77 with an etimated *tend rd devitet1n of .tO1BS

May Z4 13:33 1996 Fit. Name: 630204t..min S3AODOODO-S1?17-02OO4OO016 KEY SO A1TTACKElu O5111 Pe"a 2

the astimated 68. 95. A 99 pergent keff conifidenice Initervals art .99675 to .9352, .M957 to ."991. and M9953 to 1.00054

I te estimated suIlisiem/absetptien neutran remove' lifetime a 6.661705 secends with on estimated standard deviation of 2.IU.S?

May 24 13S7 1996 Fite Siate *3020&d.su 11OOOOCel?.6200-50016 3EV eo ATTAiiEiitt CXXX - Page 1

Inc. e00ersiodn 4a 110 tG93 S4/22I96 14.69:3*I#W1*3O2Md ~eeseeee.eeuetpe..es.eeeedopeeprebid a 64/22/96 14:6M3

t- Fer-tled Critlcality Study - 3.8 1 2 30/at * 30t i20/ d1 U02 (s30208d)2- C Calico ill Tuft 1.7! Ivec * .J06 porosity - sphere surrounded by tuff3* C CELL SPECIFICATIONS4- C INNER MATER 1251031 U4982-1 1 I*iti~lnlI: I 1 1*1-2 ERPtIlsI: I .J2391OL

IS- C SURFACE SPECIFICATIOIStl- I So 130 I t IN C UH L 01YE12- 9 50 95 S MEtE PUEL 20131s-14- NODE SI5: 1C0OE 4000 1.7

6- C ERIC i 17 6 0 a I a 0 .20 0 029 20E5 iS a .55 *10 I *4017- C S.-530 .20 -30 SOS13 I-10 600 -e *25 '°30-15 635 3 0 10 30 1718- C MATERIAL SPECIFICATIONS19- e 0 welt water In .. lle. lills tuff) a .92 I volZ Lo220- e .0e Original Enrichment/ 20 MINWOT decayed te UraniumlIote21- m1 1001.5ec 1.643371-2 201650ce 4 *15U 9 11023.50c 4.16911 -422- 12 0. s .o611114 1 275Cc a . 4156- 16000.50. 1.2134-2

1 9000.SCe .915391-4. 10000.0. *6 60152-4 26000.55 1. 49r4:4.922234.15C 4. 69450? 9 S23.50e 31226-: 922U..Cc 9. 153164-6

25- 92238.10c 1.603300-3 9.50c 2.t129 6-61- *t2 tltr.Slt

17: ie §lS: .4 2 O Sc 9si- lion C~c 2 .6XS42 429- ~~~~12eoe.ec 1:1'&4075-* 1Xo _0c 1.1U209- 14000OO SOc 1.59972-5

log 2 ts9O;~ *.e 4 000 CODOZc . "ir 7in 26000. Soe 1.esr0 4

2 PRINTI Initial soce *fr fi 11e IrpIkeff results fors For-Field grit s ta i ty Stud l 3s 2; Si/et * It3 i20/ 81302 (s020ad) prebid * 642296 16,49.34

the Initial fiaseln twutren source dietribution Ps read froe the sretp file named rctpthe eritical Ity preble was t cit eduled te ekip Wise Aen rtun a tetal of 37 cycleswitti; _nminaly 4000 esutrens rr cle.this probtem tut run I Inactive cycles with 3 7 nautrttn hbeteries end 30 active erctes with 120000 nl aren letries.

this slsulatien has semptet*d the rquested tder of kaff sctes using * tsl of 16794 fiesien neutron source tiusteriss.all calls with ffsslonabl Ic ateriel were samled end had fission neutron source points.

the results of the t lest fer normality spplied to the individual erllislon, absorption. end track-length laft eyees values *res

the i collision) eycle values eppeer normatiy dlstrlbuted at the 95 percent cenfidence levelthe Itebserptlion) eyce values appear nermally distributed at the 93 percent sonfidence levlthe khurk length) eyce values* eppar nereally distributed at the 9S percent confidence tentl

...................................................................................... ............................................

|the final estimated eeocbined ceLttolel~bscrptien/trecktengttt koff * .ffl4 with at n estimaited *tadrd dwevition of 0013 l

May 13.37 1996 File News: s3020ad.mn *1ANO00-1f7-420C-0012fl Y RE ATAMetNT 0CXX - Page I

th estimated ". 95. II.9 percent keff confidence Intervalste .1r * 01 to 1.9900 , .9 1SS to 1.00231. and ."SS9 at 1.00331

the estimated settlolenJebsorptlen neutren remva lifetime * 6.S51t-S seconds with an eatimatod etendard deviation of 2.59-0|

Iay 13 15:51 1996 Fite Sel S302scD.s4u tUAD OCO-01717-0200-00016 REV 00 ATTACIRINt CXXXI Page 1

l cn verOrsion 4. 1-d1101193 0422/96 13*243:28..so0* otos.em Oae asrnO eeooe*~a m.s.o~eeprobid * 04122196 13:48:21

InpesSOZ0uc eutpea302Csc0

1- far-ield Cri` llty Sludy - 3.6 f20fWC_/0t D30 X205 St U102 03020Ucs2- t C cc Elc Tuff 1.7U / Iee .30V porosity sphere eurretuded by tuft

4- t X11£2 WATER REGION5 I 43l942-1 1 INP:11:16- 2 _115742--2 2NPs31

WITSIDE WORLD .

10. C SURFACE SPECIFICATIO3SISO 345 6 33311 FUEL01

S. t 05 so 74S H lEI FUEL 2031lis14- II1E I15- 300 4000 1 7 3?IS: e rx 1530 ei e 6 e o -20 60 2 26 12 e 655 -10 C 4017- C 650 -.20 -300 e 130 1 0 e-25 .30 -15 -56 S 5 e 10 30 171C- C MATIAL SPECIFICATIONSI9 I pD vtU nter In ealice Xillt tuff) a .92 t volt U0220- .L I 0cS rt l chamnti 20 60IT dacs d to vrsl" Itst I e21- el :41C .657- 6016.JCc 4.315649.3 123.5Cc 4.18C1¶i-422- 1200D2S7e 441111-4 i3027JSc 2.774156-2 14000.50c 1.215794-223- 100D0.WCc Z 1 20000.Sac .060152-t 26000.55c I.493674-4246 234.5Cc 9440 7 2235.53 c .82526 92236.50c 9.1531644625- 922.5Cc 1.905500-3 93237.0Cc 1E2926-626- V21 lutr. 1tI7- c 30 v.13 uster In calico 31110 Cuf

8Z *2 1001.5Cc s.t4utn2 6016.5Cc 3.695585-2 11S23.50c 2.944542-t29- 12000.3Cc 1. 67-4 13027.5Cc 1.963209-3 1U000.5Cc 1 9752:30- 19000.SCc *.18334-4 t2DO0.Sc .288637-4 26300.SSe 1.957041-431- atz Iutr.Glt32- PFUT

1 Initial source from file eretp

1keff rqaulte fort Fer-field CritIcality Study * 3I.t /20 Mismt - 30S 120/ IS U102 0e320ac) problI * a /22JUn 13:48.21

the initial tisalen neutren eeurse distribution uer read froe the eretp ft11* used eretpthe critielltty preble_ us scheduled to skip 7 cyeles and run a total of 37 "yles uith nominally 4*00 neutrons r eyethis problem has run r inactlve cycles Ith 28023 neutr n Ileteriele nd P tiv cyles dith 120580 neutron alterlgo

this calculetion hs ,lIeted the requested umber of keff c ie usine a total of 148608 fission neutron source historles.all selts uith faiss al e mteril ware sampled end had flaecn neutron ecurce points.

the results of the v test for normality applied to the Individual eallilesn, absorption, end treck-leneth toff cycle vslues are.

th t o k llslo) n yVle vsluss appear normally distributed at the 95 percent aentidonce levelthe k ebeorptn tyle values appear norm lty dilstributod at the 95 percent eonfidence levelthe kttrk length cycle values appear normally distributed t the 95 percent centdence level

............................................................................................................................... 9..

I the fInel *stt-tt d eenbin d'eelifleln2 b erptlenttrecS-lencth koff a .9no06 with atn *stiueted st nderd deviation of .tDIU

nay IS 1SlS 199% Mote sact e0202&c.m ISANCOOOO-S1TIT-O200*Ot REV SC ATTACKENT R XURIS * ta 2.

the estimated ". OS. S " percent teff sonfidence interval. are .9960 to .99952. ."911 to 1.S101, Nd .19467 to I. 205the estisated sietfaloen/bsorptfen mnutron rsovsl iffeti.. * I."l15 seconds "ith en estimated standard deviation o 2.91-67 |

..................................................................................................................................

may 24 135 1996 FIte Remeis cl020b." isAOoo00-S1olm-o2000u04 XE No @@ Tiltoki ezxnIx - Pag* I

te versien 4s tlsOt01/93 64/24/96 08.54100aesaomeeee*eeesa-eeeee*- eeaeeeeoeee- -e- ee ----. ---@.. prabfd * U24//96 905400

lmpsSO20ob outp-9020abO

1- Far' pVia Cll2e0 lltJalult 3.01 20 S t t S30 120/ SE W2t 63O020ab)2- t catI o wllis T f 1.t A I/, .306 porosity - sphere surreonded by tuff3- 1 CELL SPECIFICATIONS4- 6 IN3ER WATER REG1IOS: I 1 I1ifl5I.. 1et tn2 .11

7. C IIUTUBE tlOAL*- 3 e 2 zinpsuOd

10 C SUlFAtE SPECIFICATNIOS11- 1 W 15*5 * IlhEt VUEL 20E12- 2 o 15 I aIn A FUEL WIE13-14* MO0R a1s Yc0oE 4000 1 20 7116- a nat i a6 01 0-20 002 62013s i 00a-55 -lo0 .4;17- C 0 -50 20 30 -13 -10 60 * 0 0 25 -U D15 -54 5 5 0 1l 50 0IS. C EAIERIAL PEtuCIFI aTaONS19 a 130 vo.1 water In smile l uf) a C .92 8 vetl U0220. I .Z Orignl Ra nri hdj 2 l~lf ea eds Uranium isotoeps21- el UiaoiUSoS. k"1.471-31 6065.4354- 1023.50. 4.16911-422- 12000.50e i.66111i-4 13827.50. 42.771596- 14000.50. 1.*13794-2IS- 19000.50. 5.913591-4 20000.50c 0.060152 4 26000.55c 1.493674-424- 92234.50 4.69.450-5 I2255.50. 3J5236- 92234.50. 9.153164-S5. 9223t.SOc t.90S500-W 93237.Soc 2.1t2926S6- intl tlv.0tr.

Z . 3O v.1Z ustar In sails.o litt luff27t *12 l a1.5c0t 3.14479-2 6016. 0c 3.693385-2 11023.O0I.e u95u42.42V 12000 50 1.41675.4 13027. 0c 1.963209-3 140DO00 S .#9752-3

19000.Sc 4.11833 4 20000. DO .288637-4 6000.53.5c 1.870414I O2tt tulr1 lt12- VIII?

1 1noff c *curse fre fis Orele111.f rrleforg for 0ei ertelytuy-3e n , o 1D SU02 t.Xe~oh) prebid a UJU^41 11t4400

the InItial fissien neutron source dlstribution was road from the erstp ftIte namd srctptilh ertlicallty problem wae scheduled to stip 20 p yclea and run a total of 3 cycles with emInally 4000 nsutrena per *ycte.tbis problem has rum 20 InactIve sycles with 80504 neutren hIstorIes and SS ctive eyeler with 220090 nsutren slsterec.

tlis ealculatlen has completed the rquested isxber of keff ciales using a tIoet of 300594 fleslsn nrautreh esurce hlsterle,.all eells with fisslenab * materil ucre sampled end had fission neutron soure points.

the results of the m test fer normality applIed to the Individual acllislen, absorption, and treck-lenth bhff cycle valum sis

the kh sellislon) :cyte value appear nermally dIstrIbuted at tie n pesnt aenfldnee1the hi obsoaptlen) yple valuse appear nermatly distrIbuted a thb pere*e snf n lelthe h ta lengthk cycle values appear =rmally dislrlbuted at he S percent enf Ider lel

..................................... n..........................hff.....2......h.en......a.. d.... ndard.............. .. 0.99|Oth fInel *stlit d eomblmd 9eiedepllntlnt et-1e21ut rltd*r clt t.09e |

May 24 1335 I9M file Nms 3023ab.00 biA000000-t?17-4200-0016 RIV SO ATTACIRES? CXXXII Page I

I the etimated 48, 9. & 9 percat Jeff cenfidence itervasto are 1.00101 to 1.00301, 1.00002 to 1.60401. and .9935 to 1.0 I

the estimated oesilatenlabsorption aeutren removal lifetime * 0.543-65 seconds with an etImatod standard deviation of 1.23E07|................................................................................ !..................................................

Nay 24 13:23 1996 OIlf ews: *3Od20eca.a 18AO00OD-0?T1?-0200-O0016 REV 00 AtTiMikaIt CXXXIII Page I

InM"" wfnln c dtOOtB f 96 1t169ttD*- -- *-* **-*** ***"*--*****e-*- ******** prePbfd * 4/22/96 14:09s:1lnp-aOR208a outpt83020toa

t. Far-tield SrriticalitBtud * 3.02 fi0 ofit0ut- 30S 120/ li U2 Iz 3020aa)2. C Calle Ellls 1u f 1. 6 /c .306 porosity sphere eurrounded by tuft3- C SELL SPECIFICAtIOwS4- C INNER WATER E11101': . g.04898s24 -1 ! IUvsiI:7. e C u OIDIE 1011.05- 3 0 3 IKP:1O

10- C MIRFACE SPECIFICATIONIS1I- I to 365 t IXY1X U£L 20EIZ- 2 itD 625 0 1El PUlL 2011N13.14- Pool E

400 1. 10 40id - IC, I OelO 0 620 6 0 29 0 2015 0 0 -5 10 - 40IT e * *SD*250 -20 0 13 a -1D0 6D I a 25 .3* 15 -56 S 5 3 l 0 SO 17

is- 9 MENIAL SPECIPICAZ02S3:: a 0 ,OvatS wat et saCll.C t1itle tuff) a .92 a veIl W0220- a* 139. Sriealest Setrlshment 0 go MINT deca d te UrsntIu 1e.t21- ml tDel.Sca t. USt1 2 O1601.5Dc 1.J15649- 11023.0 tnt

22 t2D00.50c 2.161ttl-4 3SD27.5 2. 1151:S t OOO.1Srct.t7t23- 1900D.50c *.tl5551-4 2DooO. c .:|60tS2.6 26000.S1 t 4"6S4 424- 9223.50c 4.494450- 1 20235. Dc .|S21 2236.50C 9.153184-62S- 32313Sce1.905500 3 3237.90c 2.l829Z6.426- itl tutrslt27- c 30 vot mter In calico llts tuft2S- .2 t000I.Sc 3.142479.2 1016.50c 3.495565-2 11023.50. 2.94542-429- 12D00 Oc 1.741675-4 13C27.50c 1.063209-3 1480j0.5c t : 9r52-330- 1000. .Oc 4.106334-4 20000.c 4.n634 200055. 15. 741430- t2 txttr.@ttj21 all lutr~lt5in2il source fIite f _ fit It

theftr ul tfrt for-Field Crlt.aty study - 3.0e /20 wc /t sox 12 61 11 U02 4*3020mm) prsbld * 04/22/96 14:09:18

the Initial fission noutran sourts dlstributlin was read from the aretp itl e amed sretpthe eriticality problem wsa schaduled tc skIp 10 myclsa sid run a total of 40 yletra with nominally 4080 neutrona per clthis problem has run 10 Inactive ycle. with 40180 nsutren hlitoris and 30 active eyitsa with 119m esutron Istorlet.

this clctulstisn has cmpleted the requetod unber V eft bW s uaing a total of 15995? fieslcn neutron soure. historie.all lltct with flesrable ma* terial ware sampled and d flea en feutren source points.

the results of the u teat for normality applied to the IndivIdual cellilson, absorption. end treck-lt th hafft eryte vawels cens

the kt ceitlelen) "yle vatues eppear ornmally distributed at the 99 percent cs t idence level. but not at VS percentthe k4ebsorptl n) ryc w vele appeaet rnally distrIbuted at the VS parcent confidence teet

marnlng. the kctyc leethe valuey do not eppear notrally distributed at the 99 p remit scntfdence level

f..................................................................................................................................

|tbu tlmal estimated cobired hats~bcptitekln ft a 1.80209 witth an estimated studard deiatrle n of . D0141

may 24 13:22 M&9 File. Names &3020aa.iua [email protected]??OC-S REV SU AITAiii"UT ezizam * page a

th., estimated 688 95 It 99 percent koff confidence Istervata are 1.60066 te 1.90353. .9919 to 1.60499. and .99A18 to 1.960011 th estimated seltiLonla~bscritless neutron romoval tifetime a 16571.65 seconds wifth an estimated taterdard davletion If241.

Nay 21 143 1996 file uaset P47?-3.2abi1O-47WoU u3o000eo-el7lr.2eo iv Ei £ITTACKEKT CXXXIV Page I

1.c w relen 4a Id.-10/0I/93 4/2996 10955.36.. **-*"*-*-***---*9*-****Xs-*-*-*----*** *" probid a 54/29/96 1:55M6

1- ferfield erit Itty Srsre of Trenrsuted 3. 061 "ONO U Veter t1.9 U-tp 02. 3C t-ln Optimite en or Pesiti,* miter Ceeffl ient

'- C 39035- I I .50624092506-2 *1 IIINPoll * U1ranium/tuff/Water6- C S S .61040596000-2 1 2 iNP1 * Tuf f/Mater Reflecter7- cI- c eunleE0 VOLDa- c IleNF wa a woieo0- so e 1 IMM-0 S Voeld

1I-12- C SURFACSS. 1* S 9 e * 10.00 S *Infinite FISSILK SPNE3E

34- Kc 2 * 0 6 174.51 5 UILRKIOR

warng thes surface ties been repleced by a surface of type asIS.17- NOODE1g- I0CCE0 500 1 3 50319- a K 6 6 1 0 -1 0 0 0 0I 0 1 06-1

22- 011 0-1 1 61 s1 .1 -1

23- 1 1 .I - I 1 .1.1 I -1-1-124- t 92234.c0c 4.694450-7 WIN7.=K 5.623236-S 92236.50C 9.153164-6 s VI25- 9223.SOC 1.905500-5 337.KOC 2.1629 -6 I 016.50C 4.129133- S At2 1001. Sac 291081 Sen2- 14000: .5CC 9.69607-5 13027.50C 2.111392-3 * Ct23- 126000.s° 55KC 1.14002s4 12000.50K 1.S79F23-4 20000.50C 4.623070-4 4

29- 110~~23C 1.199178- 419000.54K 4.517670-4 450- NT LVTM.8I9 S Vs

51. K N3 1001.10C 31.12479-2 14000.50C 1.007566-2 13027.5sC 2.302817.332- e $01.0KC *.0630U -233- K 36000.5Sc 1.239694-4 12000:50C 2.042960-6 20000.30K 5.630511-434 e C 11023. C S4m767-4 19000 o.c 4.910511433- I X73 1MTI.01T36- FPRET

I initial seurce r_ bare sard. print table 90

Ikeff results for Frtir7eld Criticality - sphere of trenmeuted 3.3K 2010 *rx ater 6.t U-4p e2 prebid a 04129/96 lMu55:36

the Iiftlal fission neutren euree diestrlbutten ued the 2 sourse peintc thet wre Input on the toe card.the sritleelity preblee ase scheduled to skIl 5 eaves and run a tatal of 0 sytes with ominally 500 neutren r M yele.this problem bsa run 3 Inactive eyeles with 1553 neutron hlesterle end 5VW ective tcles with 250071 _eutren a Ierae.

this elouleatien has spleted the reqsted number of Ithff ccles ucing a tetel of 21624 fessaen neutron suree hisettes.a I otlle with fissianable materiel were seepled and had fiesTen neutron course peints

the results of the u teat for neatlity applied to the IndIvidual cellialon, abeorptlon, and trackttength kofl cycle velues ares

the l coellsleln) *ypte ns Is appear Normally distributed at the 9S percent eanfldence levetthe taboerpt1e eycle waluse appear mutally distributed *t the 95 percent enfjdsnce lee tthe trk length *ete values appear normt eY dlstributed at the 95 percent enfi dence levt

pay 21 1St3 1996 FtMe Names P4TIT?-3.dE-kC t-?UV 3AOOOOO-81717-6200-00014 REY SO ATTACKNENT ANYJV * Past a

...................................................................................................................................

the final estimated seabined *ettilin/laberptieitrack-tlenth kif ta *1.0102 wIth en estimated standard devietlen of .60091

the estimated 68. 95, A 9 peorent keft sontIdence Intervals are 1.1o93. to 1.61114. 1.60864 to 1.0126, ed 1.607 to .612563

the estimated settieiojebesrptlen mutatn removal lifetime a £."E-3 *eaonde uith en estimted etandard deviation of 1.4t -67...................................................................................................................................

nay 21 1T 96 Fite Name: P4716-3. E. 0 6.4VU 1S3AOC000-01717-0200-00016 RttEf d AtTAUKIENT 02Uv Page 1

prebld * 0412796 1554:54

1- felaie CrVititalit* -Dhere ot Transmuted $.E 20tiYD 40S Water 0.82 U-SD 022- C falt Opt mtsstIn or Poiltive Water Coefficient3S C5- I 1 7.M63 115346-2 -1 tal S, Vrani~u.sf f/Vaters- C s 3 0.61040396000-2 a .2 P1.1 S /WatutlWster letlecter7- C01- C SUWIICI WORLD9- C 30 0 2 IMP11U.8 OVoid

1'- s0 a 1 itPmIE. S Void11-12- C OUPFACES13- 1- a 0 10.00 S 'I.inite EttSIEE 17P3ERE14- C 2 S I 00 174.51 * RIPLECTlO15- C

Mareni.g this surface has been replaced by a surface *t type as16-1?- MOCC ais- I=1 'se 1 3 50319- *t C 0 0 0 1I0 100 0 8 0 - 1 O0 1 e-120- 1 1 0 1-10 1 l 1 1 0-121- -1 10 -1-10 -101 -10-122- 01 I 0II I I -I 0-I-I :23- °. 1 I . . 1 -1- '1 .1 124- El 9234.SCC 4.694450-7 92235. CC t.22526S-5 92236.5C 9.153134-6 4 Fp25- 02233.t50C 1.j05500-3 93237.4CC 212926-6 6016.9CC 3.01S334-2 S At26- 18l 0SC 2a 60494 S an27- INRUS SOC 9*269607-a 13027.5CC 2.11i592-3 S co

26000.J5C .14002-64 12000.5SC 1.879523-4 20000.5WC 4.620070-4 S W19-: 123.S0C .19913-4 90CC.OJC 4.517T6704 S 6C- STI LtTR.OlT a Vs

St- e 10 lOl.SCt 3:1424-2 14000U.SC 1.007566-2 13027.5CC 2.302317-3$2 e Ol4.1C 4 S6.063 -2

t 21000.%SC t.239394.4 120ZO. CC 2.042960-6 20000.5CC .130511.434- C 1t 1.5C SUM773 4 * 0r07-6 I0C00JC .105-t 433- C R13 LVT3.01136- FRlNT

I 1nitial meunle trem hare eard, print table 90

theft msuttl for: FarFleld Criticelity - Sphere *f Transmuted 3.01 20CM 402 Water i.02 V-Up 02 pretd a "4J27196 15:54.54

the Initial fission utren ource dietributin wsed the 23 source points that were Input on the hare card.the sriti.elity preblam was *cheduled to skit 3 * lee and run a teetal * n 3 cr"ces it noenell tly neutrena per yetle.this prebleo hea run I inactive cycles wilt 1592 neutrn histories *nd SOO a Ve a"cles WIth 2IS06 neutren histeres.

this celculatien has aepleted the requested nmber of keff e les wing at tete of 2519t ftesin neutren souree hieteries.Olt sells with figslen ble materiel mare sampled end had fleassn utr s esurce pointe.

the results of the u test fer normalty applied to the Individual col1isien. abasrptlin. and track-tlength keftf yctle values ere

the ( eolliaeln) cycle value ppeer normelly distributed at the 9 percent et fidenee 1elthe h esrptien) cycle vales epper normally distributed at the 95 perent cent dnce levelthe kttrk length eycle values appear normally dIstributed at the f5 jersent aentidene level

mhy aI ISS? 1996 fit, Name: Ptrl3-6.11thifiU-4V0U ISaflOioOlV1?-S20040016 Uti £ ATU WNlET CXV - Page I

...................................................................................................................................

the final estloated cambined cetitcionlabsarptinftrmckctonth koff a 1.03854 wIth an eatiosted standard deviation of .00090the estimated ". 95. £ " percent hoff sonfidene* Intervals are 1.W764 to I.Sf44, 1.0675 to 1.1113, end 1.02616 to 1.01309

the estimated gottlilenlsbsorptln neutron removal Itfetime * a.6ll-S seconds with en estimated standard deviation of i.501-67...................................................................................................................................

KRy 21 13t43 1996 File Same P4m71-i.0*teciaoossuoau Sa fooOC-1717020 0 x i e a0TIAcUHEi cxmVI * pas

I"n version 4a Id-.10I 093 04/27/96 16.47007prebid a 04127/96 140

IKlr-I3SVO8i tOUTP.313503.

1- PerfieCd Critfiaestt a Shere of Trasmuted ME tecse ss5 Water s.n U-Xp 023- C k-In. Optlslt ion oer PeaI i Ycter Coefflcent3. C6- C "maClt5. 1 1 r u.401645946-2 1 IUP.-l * llUranIufTvuffWater6* C I 35 104059600042 1 -2 RRPU.1 S luf/Water Ref lecter7- CS. C 41T310E WORLDf- t so O a IMPs11 e Voild

ia- s0 o I iIP81.0 e VoldII-12- C SURPACES1- I'* S 0 S .00 S *Infinite S931,S1 57U3E114- C a 5 000 174.51 S RELECTOR

earning. thle surface bas been replaced by a surface ef type so16-17- NOE IIC- 1101 Soo 1 3 50319- nc I I0 0 0 -10 010 0-lI 0 0 1 0 1

2i- - 1 0 -1 - 0 -1 S 1 1 0 -132- I1 1 I-* 1 61.1 S-I-i2s I I- 1 I *1 -1I 1 -1 -1 -14. Ml 92234 e

0 9223S.1CC e .125216-3 922360 10531141 0 F126- 1001.100 r152933-3 22Sn oc o nz37. ec 3un 6 At

226r 14000 CC 9.269607 1302750C 2.118592-3 a ea6000.55C 1.140702 4 100 10 c 79S23-4 20000.50C 4.628079-6 5 VI

Igo 11023.:0C 3.1919 4 19:0"0; oo -6 4.3160 a4 i 4J0- hT1 LVIRIT * VASt1 C la 1CO1.50C 3.1424U9-2 14000.50C 1.607566-2 1WZ2.50C 2.302t-3132: t S8016.S0C 46.63067-2i. ~C 26000.5C 1 213989:4 12000.110 C S 2.9429-4 2OO.5oc 5.630511.4

IO t 103.SO 3* 140 7 19000.50v 4s0 11-1: CC 173 LWIR.I1T

56- PRINTI Initial source free fte c"rd. print table 90

Ikeff results fars PerFleld Critieality - Sphere of Treanusted 3.01 301D 352 Water t.0 e -spS 02 prebtd a 04/27/96 16s47:80

the Initial fission neutran course distribution Weed the 33 source points that ere Input en the kere card.the crItIcality problem was acheduled to sekl S les and mmn a teOtl *f 5e5 cltes with nocinally 500 neutrens rrcyle.this problem has run I Inactive "yletls it 5 nautren hleteries and *e0 ctive cytls with 25 001 neutron I Iteraes.

this ealculetion hasC ecpleted the rquesd umber of kef cctles Using a total of 852147 fisesln neutren acurce histories.tl eetll Ith fi nebl teriel wre sampled end had fierson neutron source points.

the results of the u teat for normality epplied te the Individual cellitlen. cbsorption. and track-length keff cycle vlues Orel

the RI cllisien) eycle values appear normally distributed *t the 9 percent confidence levetthe k(eboeMptien) eyc v waues appear normally 1 etr buted at the 95 percent confidence levelthe kttrk tl th) gycle veluas appear normally dIctr buted et the 95 percent confidence tlvel

may 21 MU14 IMP file lames P47TIS.fi~bGlU D-3SVClu *IICO-11. O ni4 it~ Al1*CKREW CZXXM * Palo I

the final eattlutad combined I~saVboplntatLn th faf a 1.63544 with an estimated standard Ewiatten of .60694

the astilutad ",89. S & 99 percent katff confidence Inmtervals are 1.03473 to I.S366. 1.03373 to 1.03754. sand 1.63317 to I.M631

the outlmated col~lisionjasorption neultron rsemovl lifetlmea .*6.313-3 seconds with an outmasted standard daviatisn of 1.541-67

Nay 21 1hZ? 1996 I w ile Na4mes li.3.f iouD.301C08 12A0000-01717.200-600 L 8 TTACUXEU? 611 Y1t - Paew I

probid 0 1427/94 17332114fP6.3ngS0oae euQP.3ESCAo.C

1* FarFl.!d Cr:tleilt - aere of Troneauted l. EO2CUC 302 aIter *.0e U-lp t22: C Inf Optiinsetlen for Peattive Vater Coefficlent4- C MPINES- 1 7I5462396n^5U_ -1 INP#N.l I Urenlum/luff/Ustert: - t J .61040516000-r I -2 IRF Mal S Tuff/Uster Reflecter11. C 6U15101 VORnL

9: la so I a 1RPslmO S, VoldI: I J 1 I2IU t-0$ Vold11-12- C 'UrFAC1913- 1' S 6 16.60 S *lnfitl UESUILS SIOHERit- t 2 e 0e 17e.3 e R.51 * EItC

warning, this *urfece has been replaced by a surface of type so

17 ROCE t13- CCODE 5DD 1 % 3 0319-' KCtC 60 6 16 * 1 3 1 1 I -1 * s 1 o -12D l 1 6 1 i1 *I - 0 -1' -*1

l 912234.JCe 4. 450 12233.3c J.t25266-5 92236.50C 9.153164-6 a fl92233.ICC ,0,1 'H173112:1,92. 045C .0M2 AIT 1.03 5300- 13237.1nC 2.112924- ; 014.coC Le6m-2 t nZS: 2600e.xs 1 1407024 12000 *OC 1It7921 4 2ZDOO 50C 4.128Dr 4 * llt29. ltD23. U J lPtS 4 19U08.5DC *.5t 70 4 * 4J30- MTLT , tW31- " 3 1601.3CC 3.142479-2 u400.50C 1.4073"-Z 13027.50C 2.30217T-332- jcc 4.1306?- 333- e 4000. SC 1 239894-4 12000.36C 2 .2940-4 20000.11CC 3.630511-4

S- t6l2.C cC 3.477367-4 l 000.3CC 4.910511-4D5- t T LTw .tr -I Initial soure frn arre card print tab e 90

1keff reuites fers rfild Crtl saltty - Sphere of Transmuted 3.0! 206110 302 JXter 6.6X U-Up 2 6 r2bld a 9 MUM

the initial V n neutren orse dIstribution wed tir 23 source points that ses Input on the hare card.tle criticality prbtlem was scheduled to ekip e als end runt a totsal t d 03 cycles Ute nominally 00 neutrens per ccis.this problem has run 3 inactive cycles viti 140 neutr n eilsels snd ID0 active cyles with 249500 neutron htatar es.

tl elcutien s completed the requested mber of tetf cries uwsig a total of 251290 fisslen neutron *surce hlsterles.atl cells utIth fissisnblO *eterisl aere sampled end had fiction neutron source points.

the results et tIe w test far normality eplied to the Individual cellirlsn, beserption. and treck-longth tetf cycle wvlues ores

tiec AI collision) cryle weles eppwer rmsally dlstrlbuted at the f plercent esnfifcnce lIvel, but not *t 9 percentthe 1eibserptien) cecle vles appear norma ly dstributed *t the 9 percent eenfidance Ilethe hrk leonthi cyle vales appear aeelly distributed et the n percent eant denc evl

Ray II 13:3? 1996 file ants,763OE*S3V3 UAOOOOC~o-S1717.0200-60016 Ift M AflAWOMIT ezziVIa rate I

the final estimated eombined eel-Isienlebeelpplen/traek-length keff a 1.64M7 with en estimated etandard davietien Of .6009the ectimated 41. 93. a 99 pereent kalt cenfidence Interval. are 1.64175 to 1.64363. 1.64079 ts 1.6444. end IMAM11 to 1.614327the estimated eellisienjabserption neutron removal, lifetime * 9.671-OS secends with en estimeted satndard devitien of 1.533167

way n 13.I 1 1996 file Ramse. FP43-3A0Ei0CMd-2SVo03U 1IADOCOC-.1717-0200.60016 3Ei0 Ad ATtACeENT eX=ViIl * page I

Io version 4a ldel0/0l/l eS MU pMed 1

*-* *- -***--***-*-s-**-"*-********* **- * --*****-*prdbed a n"12/6 16014MZIUP.3125VC31 WuTP-SE1s08.C

1. ParFeled SitislecitY * Soberes*t Trefisutad 3.63 320110 t5S Vater 8.63 U-Up 023. C k-Inf aptlrizt n 6r P. . I'm V.t r Cott efficient

S I * .4733307146-2 *1 IfPs1-1 S Uranium/Tuffliator. C S 3S .6164 059000-2 1 -2 U081 S1 S tUaf/MVter Refleter

7- CI- C suIGio MCRLINSPI*- t rtlt ttVoilo to 50 *I 1 INP21.0 Vel V id

3- C £ 1IIFACt*is. i* s I * * %11, 1 -infinite OPISUM 1731RI314. 9 2 1 . ViL.s, S 1ECTCAIS- C

aniing, this surface has been reploted by as urface f typ' *s

tr- 1003 x6e 3103E 500o I3 503i9- KUSC 066 I60 .1 0 616 6I1 001 061

Z1 1-10 161 16 121-:* 1 6.1* .10X -16e1 *16*-123 0 1 0. - 1 I 1-1 *-1 1

a24 II 92234.cc 4.694450? 9223'.SCc 3.625236.5 9U36.seC 9.1S3134-6 S WI35- 9223.5CsC 1.905500-3 93237.SCC 2.16292.6 9016.3Cc 3.452497-3 a At26A 1001.4C 1i.57309- I anZ- 14000.5Cc 9.269607-3 1307.:5CC .111592-3 t o35t 2 OOO.S5C 1140702- 13000.5C 1.729523.4 20000.9SC 4.628070-4 S VI29- 1023.5c 319917-0 19000.1CC 4.5i7670.4 54730- 7 LZTE.0I1 u s317 t 33 iCOI.SCC 3.142479-2 14000.5CC 1.607566.2 13027.5CC 2.302617.5323 C 1014.50C 4.6630667.33 C 360003 5C 1.3398944 12000.1CC 3.642940.4 310000.5C S.630511-434. C 110235 CC 3.47M764 19000.50C 4.610511-435- C IT3 I5TI.61736- P11K?

i6-1itl&L esuree fre hare card. print table 90

Iteff results fete FerField Crititclity sphere of transauted *.6E 201 3S3 Mater 0 eI U-sp 62 prebid * 04/27/96 I8mt4Z33

the Initial fiesion neutren cource distribution used the 233 ourse points that were Input en the etre card.the criticality problem wsa schedulcd to skip 3 *rles and ru total of S03 cycles with nominally 50 neutrene per sycle.this probles has run 3 inactIve lVc les with 1500 neutron histeries nd O active cycles with 350102 neutron histories.

this ececulttisn has sompleted the requsted nuber of kaff ayele ueing a total of g31602 fisalen neutren csurce histepies.all *clls with fissinable material Mer: eampled end had fiesion neutron sourtc points.

the results of the a test for normality applied ts the Individual cellitlonn absorption, end track-length koff cycle values arcs

the tt etlaiien) cyce lal appea r normally dtatributed at the 95 percnt confidec levethe Sbsorptieni reclc values appear ormal tdistributed at the 95 percent eonfidence ltevlthe ttrk tnth) cycle values appear normally distributed ct the 9n percent confidetnce level

Kay 21 ISM 199 file Ilas.: P47:3-3.6-khCUU4vOBU * C oooo-Sl?17-O2OO-@0 h1 6 ATTACINET CxxxViII - Page I

...................................................................................................................................

the filmt estimated cembined eollaenerp ntrct ettuuth haft * 1.34320 with an estimated standard deviation of .10102the estluted 43, 95. 9 9 percent keff eanfidence Intervals are 1."217 to 1.04422. 1.84114 to 1.t3523. and 1.U00 to 1.0419the estimated eeitisleo~sbaorptien neutron remeovt lifetime a 1.443-63 Secends mlth an eativated stusadrd deviation of 1.4*-S

.................................................................................................................................

may 2I 13.25 199 Fi11, lam., PAIZ3.3.i AMBMu.3Uv [email protected] Ith "U ATTAC3NICES CXXh2 * Palo I

the V gnal estimated combInod .otleiaonlab~erptianftrack-longth koff.. 1.83311 .itt an estimted standard destietn of .000

the estimated 48, 95, IL 9 percent koff ecrnfidonce Intervoto are 1.03ZIO to 1.83424, 1.63103 to 1.03S33, and 0.6303 to :1.6300603

the estimated eettlaloilabsoiptien neutron removal lifetime a £.494-05 ecacnfds with an estimated s-tandard deviation *f 1443.417

ray 21 13:25 M99 File 118e. Pll2i.3 bcvo-nuVOJu SBAOOOOCO.61717.6200.60016 SEV id a uTzCKNpT CXaX - oge 1

1ecnn 0rsion e td.101611964/27196 1:54226,.c. .*.. --- **** version*-* 4 I= eaprobid * P 1/96 11154S26

UP-M2CO11081 MUI-P.2008.

1- Perrield Criticalit * Sphere of ZenamMd 5.tC 20610 20X Mater s. ex U-p 622 e k-inf ptimtza Ien or Pe lt bter Coefficient3- C4- C SPECIE5- I 1 4.81699037746-2 -1 IlMNl- s Uronint/Tuff/Vater- C s * *.6104059000-2 1 2 IalS-l S Tuff/ltate Raf betor

7- C: C OUTSIDE WtRLU9- C 30 I 2 l1 U-d S Voide0* so 6 1 IKPI-C S Veld

1: 1C U * S 16.60o *infinlte FPSSILE SPHERE16- C 2 s **6 174.51 s6 tEFICTOR15- C

uarning. this surface has been replaced by * surface of type so16-IT- NODE al1- RCOOE ao0 1 3 503S9- iSXC I I56 16a -lOS4 a 610 5 I16 66 I 66a.120- 1 16 -1

21- 1 1 | 1 .1 I I .1 .1 1:124- 92234.1C 4.69l450-1 9223S.50c 1.825286-5 122M36.SOC 5 .6! sl A25 92233. OC 1.90SS000 13237.5Cc 2.u1126-6 8016.11C s I26- 180 01.0C 1.1j3 t-0 2 an2. s

s2~~~~~u eeas~ .~s^

MOO C :.1 2M- c 20000.50C 4.622070-4 S

ss C~~~1 10zssc s.1rrt r * ls`oo:1 oc 3.^1si

0123.C 1917-4 "O 6.176;0-4 Os 147l

1 : ~ 1 as 0 1 *5 SO 3.14247.2 16000.50C 1.607564-2 13027.5wC t.302817-332- C 60116.C 4.6,63067.233- C 26000.5CC 1.239891.4 12000.5CC 2.642960-4 200011.500 5.630511.4

ISO .CC3.47737-4 19000.50C 6.9110311.4134- CC 03 IVTZR36159

36- P661TI Initial source frne harc card. priat table 90

Itaff results fert Parield Criticality - Sphere of Trenamuted S.E 2091VD NOS Water S.6X U-xp 62 pred a 64mn96 1MU14M2

tbe Initial fission neutron seours distributlen used the 23 scurme points that ware input en the kore cerd.the criticality preblen we scheduled to AMC 3 cyles and run a tetal of 503 rycles with nomlilly 500 neutrons per eyclo.this problm has non I Inactive cycles Alt 1 13 neutron histories And *0 e ctIv eycelS with 1508187 neutron histories.

this calculation has eltated the requested nmber of ktff nctes using a total of 2300 fission neutron *euree histories.all *1e1s with fissionable sateriat were aspled end had fission neutron osures poihts.

the results of the u test for norality applied to tho Individual eollialon, sbaorption. ad track-length keff cycle values *re3

the hi esilisien) *rye vlalues Appear normally distributed et the 95 percent confidence levelthe ktebortien) eyel was eppwr normally distributed at the 95 percent onflidence levelthe MItPt length) cycle values apper normlly dietributed t the 95 percent onfidence level

Stay n J132 1m 6 rtte C_.e PEwe s 1 .eOE*2eelatSMWu OACCOO0O-amr--200-0oid gSi 0 AAC63IX CX * Page I

Isna version 6. ldwlIOI/.193 01427/96 19:32,521 - r**"=etn * leile~e~n . e~n7.n6 tss2|5 probtd * 04/2r796 193252ItP.3115U081 WuTP.32503.0

1. FsrFled Cit ll .. 1t- * Sphere of Tr sauted 3.1E 20MM 151 Water 1.61 U-Sp 022- t k int Opt I i nt Fr Pte itlve Water Coefficient3. C4- C spHEtis- t 1 5.1.356476s346-2 1 INPalul 6 Uranium/Tuff/dster~* C 3 3 8.6104859eo00.2 1 *2 lWPM-1t S Tuff/wUter sefl cter7- CS11 C Sf1lSUE WORLD

12- e SFACEII13- .* * SI 10.0 tee *nfifnite FtTZILE SPUIERE14- C 2 3 SO o 174.51 s EFLeCITOIs- Ca'!'4- this surface has been replaced by a surface of type so16-17 IIOO tlIsU 1cco sea 1 3 50319- EIC 0 i 1°0 1 0 0 e 0-1 0 0 0 1 0 0.1

pi : .1 11 :0 1 1 0.

23: ..1 *1 1 .11 .1: .124- 111 922341CC 4 6959-7 922r D3.C M.86- 92236.50i 9.153184-16 5 ts35- 9223.5cC 1.905500.3 93237. CC I.u2s26- 1016.9C 3.1t4935-2 S At4S~kI00 :1W4:I '13027.500 M11692-3 CaS27- Sro Ccs6^7s s~~o 2lag2s 26000. sct60762-4 12000.14c 1.1 36 210000.500 c.62074 8 WI29 11023.5c 3.191S 1900. 5DC 4. 17- 4?30 R71 LWTE.4IT S Vs

C 13 1001.30C 3.142179-1 14000.50C 1.07566-2 13027.500 2.3.302317.3C U1014.5C .93067-1C Uoo6000.C 1. 5594- 12000.53C 2.e42960.6 20000.50C 5.630511-4

34- C 1023S OC M6767-4 1900.s3Cc 4.910511-.31 . P6 11 LWTR.GIT print tsble 90

Initial source from barn serd. pittbe9Iteff results for: Fsrield Critieality S phere of Transmuted 3.6E 208W 153 Water 5.6X a-Up 02 prebld * 14/27/6 1MU3M

the Initial fission nautren source distributiWn qu d rte 13 souree points that wore input on the hare ae"d.the aritiesllty preblo wass scheduled to sip Ye3 T *nd run a total of 543 eytes with nanlily 500 neutrons rr cycle.this prebtes has n J3 Inctive cycles ith 1t64 neutron tisttores nd 500 ective "vies afti 351063 neutren istorrls.

this celeulftlen has cuoptsted the reuested onber of taff cycles using a total of 2352327 flesin nrutren souree histeerit.etl ells Iu tb flesicnable materiel wre reapled and bad fission neutron scurce points.

the resulte of the a test far normalty applied to the Individual cellisien. ebseroptio, end track-tength td1 cycle values are:

the t collision) st:le wlueme appear ormtally Istributed at the 9 paercent confidence lenlt but not st f percentthe tt rtlnl yctle vles appear nomally dItributed et the 95 pore nt eonfidnce lewelthe kltrt lenethi oey evs ue eppear normally dlistributed at the f percent *onfidence laws

pay E1 13122 1996 Pita los O7CA2.2C@&m.15UC3'0 S3AUOODO-n1717-82OO-Sf011 Ri V aTTKITACUNEUT UL PIg I

...................................................................................................................................

the finat estiated cembined retilee/abaerptlenttreck-tengtt keff * 1.M6r6 with an eatimatod standard deviation of .00109

the estimated ", 93. £ 99 pareont koff enfidence Intervals are 1.00347 to M.6OMu. 1.00459 to 1.1008. and 1.0038 to 1.009"4

the estimated .otilaion/ebsorption noutron removal lifetime * 6.211-63S *arod wIt en eatlmted standard deviotion of 1.51380?..................................................................................................................................

may 21 14:1 1996 file Raewl P4?67-3.-iERhO D.41M J 3AgD000t0-S1?17-0200-00016 REV 80 ATIACMEXT tXLI - Post I

1Re ro 1n 4& Id.101/93 4127/96 12238:3r

iIPaSE4708C IITP.3C4701.0

- PFar~leld friticallt * tpere a Trenouted *.6E ! D 4*n valter 3.0! U-Up a22- C h-ef OptiftaX alen Por stiv mater VYtme Coefflelmnt3- C

4- C SINERES. I 1 6tSC024092506j -* impiE1 S UranimumTuff/Waterr t ' *.6A 40596000- 1 -2 MP I., S tuftfeater Ref lecter

7. Cg- o OUTSIDE WOULD330 0 6 05.l3.0 S Void

lo-l1: C SURPACES12- 1 S OS t 130.s0 a FISSIE SKeItE

warniln. this surface bee ben reptaced by a eurfece of type so13- 2 S e090 210.60 S ItRECTOR14- C

uarnipg. this surface has been replaced by a surface of yp sIs-14- or. Kl17- ECODE S00 1 10031I- C EtIc I 0 1 I0 -1 I S 0 1 0 e-i I 00 1 S99- C I -i20- C III -: 1 t . -1121- C @1 I - -3S 1-122 C 11 ' . I S -1. 1 - 31-23- 111 92234jC 4.:4050 r 25s.soc 3.15226-1 92238.1C0C 9.153154g S I24- 9223s.s c I."500-3 93237.C 2r18sc 2-41 4016.56C 4.129133- Al t25- 1001.S0C 1.591051- S en26 14000.S0C 9.269607-3 13027.50C 2.118592-3 0 es27- 26000.5C 1.140702-4 12000.50c 1.8T9523-4 20000.10C 4.A28070-4 6 1II20 1102S.S0C 3.19917l-4 19000.10C 4.517670-4 47

9- Nil LWYA1 el MaVIC:8 M13 101iC.5JC 3.142479-2 14o00.soC 1.80756s-2 13027.1oC 2.302317-3 5 Ca31- 0016 0C 306- 0 II32- t6,100eH SC.2svg3,94-4 12ee.o90c 2.642960-4 20000.50C 5.030511-4 a 47

11023S*OC 3.47767-4 19000.1C0C 4.915l1-4 SI! 113 LI tr.I1f - a W.35- PRINT

Initial source free file sretp

ikeff results fart forFaltd Criticality - sphere of Transmuted M!E CbWD 4?n Water 2.0x U-Up 02 probid * 04127196 12M33

the Initial fission n utren source distributlien W read ftre the orctp tfile amed *retpthe criticlity preblee ues scheduled ttoSkip 3*rcle aend rVW * total of 1003 ctcles with nolnl tly 5m0 nautrne per ycl.thbs problm has run 3 Inaetive eycle uith 149 nsutren histories and 1000 t aIve cycles with 500461 neutrn hiateroies.

this calculotien has eap loted the reested unobar of kef cycles using a tetel af S01959 fission neutron seureo hlotories.all ltls uiltk fissienable materirl ware eampled and had fission neutron seurce points.

the remultt d the v test for noreallty applied to the Individusl *eltliaen. ebsorptlin. end track-lenUth heft cycle values are:

the kt eollialon) sycle Values eppear nornatty distributed at the 9S percent centfidnce levelth hteborplien) cycle values appear norel ly distributed at the 9 pereent confience levlthe kitrk leugth syc valwes appear netralt1 distributed et the 93 percent sent dence level

may II 14.o 1996 File Names Mit C36 iA.ieJoAru EIToo@oo-61?L7-6200-a0016 SE s6 £acmIEE? SELl - se 2

the final estimated eombined geatlelenbserptlen/track-Iength koff * .t 6 witth an estimated stendard deviation o .90067

the estimated OS9 5 99 percent keff confidence intervlae re .933 to .9a8 . te * and .93528 to . 4

the estimated sogl isleno/borptien feutlen rmoval lifetime a 9.611-U5 sconds with an estimated standard deviation of 1J"l.67.. e ..... X@... e.w*@e........... .............................. ....... .................

Nay 21 U3t52 1996 fit Race: P4TC6-3S.fI'I0U0-4CW03U RE4000000-0177-6200-6X16 RIV t1 AtTAClgExT CxCII * Page I

t"'-'e4o.0 eeomet m.40Sa-e--ao~tt' *-*****- *-- .S~oout sehop probfd * 94/27/9A 14115:37Iur.3!40i1080 OUTP-lc408.e

1-d Clitetality -11hare of Trnmmuted 3.6E 21WC 40Z Water t.n u-4 62t~ k-Off Optimiat Ion or Positive water Vetsl. Coefficient

5. 1 1 ;.t6Z$615346.3 - iEP.i S a UrripmTuffjyater6 I .41040596000-. * -2 INhsE. * Wu flmater Reflecter

OUTSID3E WORLD32: i1 a t s O PINE1 S Vold

I1: C URMACE0XI a "

warning. this urtface kca been rplaced by e surface eI typo ao13- I aC S D a 210.e0 1 eE°9e 1 tOe14- Cwarning.- this surface kea bean replaced by a surface ef type so

16- KOOK II17- 10001 S00 I 10031I- C £323060 0 1 060-10I0 69 I 0&-1 0 60 1 0

a4 * . sc t.eS - 15. DC co- t112- l3C 6C 199I * 1 I I .1 -.11

II 1 225 c.c0 4494450-7 92235.S0C lt75266-2 12236.10C 9.153184-1 S FtX1-3: zmJ30 190S506- 93237. Ooc C6 5016. cc 3.913840-3 A At

32 tt6lg01 00 460494' $ ea26- 14000 0tT .26980. 11127.5Ca27. 00 40702-4 12000.0012 II14?2952:34 20000.500 4.423070-4 S6 VIall 1102 3:51 3I:199173-4 19000.500 65 17670-4 $ 47

1 n it?, Lur V" Sir use*rt

SC- K3 too oC 3142479-3 14000- 40 1.*07566-3 13027.5C00 2.30281Y-3 t CeSI: 6016.I5OC 4.5063067-3 S WI32- 26 000J5C 1 .239894 12000.110C 2.642960-:4 20000.560 3.6030511-4 5 4733- 110230 3.737-4 19000.500 4.910311-4 S134- N15 LMIR.O1T I Ma

I Initial source from file sertp

Ikaff9 result. fots Farfie~Ld Criticality - Spirer of Transmuted 3.8C 20401 4031 Water 6.61 U-Up 62 probid * 4127196 14.13:3

thb inlticl fiss1c n neutron ource diotribution was road from the eretp file named oretp,the oriticality probloc was scheduled to skip lvoes and run a totol of 1003 eyso ul witb minally NO neutrons per aycle.thlo preblm bas run 3 inactive "aclec sIh 1w33 noutron histoeris and 1000 active cycles with 500377 neutron bletoris.

this oaleultatin has eompleted tha rquested mber of kaft cycles using a tota of S0910 fission neutron soureo histories.*11 sIell wiuth 1e fIsenabo material were ampled and bad fission neutron seurce poInte

the results of the w test for nrmatity, oppliod to the Individual collision. sorptlino end track-length koff cycle val er ars

th a coillision) ycl vals appear orallty dIetrbhuted at the 95 percent c nfidence levelthe bItb onpti nw a vales appear normally doctnr iutd at thC pereont onfiden levelthe ht~rk longthi syc a values appear normally dietributed *t thb percent confidane* level

NAY R1 13152 199 Fikelae ISMS .S-ZSV*6118 *AClODOOO-S17I?-1200-60016 REV SO ATTAUHENT CX1.II - Feet 2

the final matimated combined eettlsien/abserptfientreck-Iength kaff a .9M8 with an estimated standard davatien of .80069

the oatimated 68 83 89 percent heff ..nfidence Intervals are .99615 to .99753. M994? to ."9921. and .99502 to .9986

the estimated setlisien/abasrptlen neutron removal. lifatlee a 9.291-fl mascnda with an estimated standard deviation of 1.533-87

.......................... *......... .I..... ............. I............

mar 2I l3t40 1996 File Owmes p4rtsC-3 .UE-R -35WS0U RUOOOOOO-3Wrt3200-0i REV l0 A£TTacIEut Mill flage 1

1men vrsisn 4a d11193112 13:25.45t ;P~ue..e ... ........ . ee*1 eeae..... prabi * 6510C"O.... *P*4219£ 13325 45

1- larpild Cit 1 ltj * 1puer of tranamuted 3.E 2090 35 Water 5.es U-bp 02. Ct k-itl Optic at I n or VosatI Water Coefficient

3. C*- C SPHEtRI 1 1 7 401011343946-2 t- I6 -.1 S UrAfium/Tuff/Water

31 3 l £1040596000.2 1 -2 IitN 01 S TufflVater SRfl etor

't t UWnSICE WORLO11- 30t a 2633.0 S Vold

i. C WCPAO!312- 1 I aS 0 150.*0 * PeISI1 SPHERE

warning. this surface has been replaced by a surface of type *13s 2 I a 0 210.60 e REFLECTOR

w5Ir.ming. ths surface has been replaced by a surface of type *s15-16- 600 S17- 2000! *00 1 3 10031S t 31CC 00 e 16 a e 1 I 0 I 10 0 .1 6 0 * 1 019- t 11 * :1 1 10 1 .1 120. C .21t C 11;22 t'I I -' .1 *t1 * :3:2l. Ml 1 2235. C4..?4:01:- U34o 9.153134-4 * Ft24- 111 m4.soC *.^suo r n2 15so0C 3.125286-5 n2: o cc2233.C 1. o- * S C3r SZC 2.182926-6 406.50C 3.7400592 * At25. 101.3C1C 529SON.3 STSc 152- 1an26- t 69607.3 13027.50C 2.118502.I Ca

c000 C 8 640T02I 4 It000.35C 79723-4 20000.5SC 4.628070-4 9 VIRO10 .00 :1191T4.4 19000.3CC 4.17670-4 S 47

29- 0171 LWTR.SIT OW.50 63 i001.COC 3.142479-2 14000.10C 1.60756&-2 13027.5CC 2.302817-3 ' co

31. 8~~016.5500 4.86306?"SW32- 16000 ~~094-4 13000.3CC 2.042960-4 200*00.50 5.430511.4 S 1471

5'~ ~ ~ I~ nsYU5:;''.5m'4 319o0o.soc 4. s91411-4 200-eCseoil* $*4 WTR.OIT I~~~~~~~~~~~~~~~~~ Va

Ss PONTI Rnitilt esure* fre file oratp

lkodt results fori For~ield Criticality * tphere of Transmuted ME.E 2o00 3ns Water *.0o U-Np 02 prsbid * 65162/96 13.s25.

the Initial fission neutron source distribution was reed fre. the sretp fii. maod eretp .the eritieallty preblm was scheduled to skit 3 yctes and nota total of 1003 cycles with nroinally W00 reutren per eycle.this problee has run 3 Inactive yclee willt 1S3 neutren hisltrles and 1000 active eycest Mith 30031 mutran hteteries.

this eeleulelion has ae teted the requseted number of keff *cLeot using a total of 501301 fission neutron source hiteries.atl eeits with f1esielnb* materiel were sempled and had fiesson neutron source points.

the rerutts of thb v test for neraellty pplied to the Individual cellisien, abrerption, and track-length keff cycle values *res

t:e kl *olelsion) cycle values appear normally distributed at the 95 percent confidence tevtthe kiabsauption) cycle values t ppeer rally diteributed et the 93 pereent *enfidnce Ilthe Mitrk length) yete values appear mrm tty distributed et the pereent confidence tvel

Ray 21 134Se 1996 Pito cameg P6?C3. 3.SI tiD.3ZSWU SIAOOC-0OO1717O200C0S0016 tt *0 A£TACINENT CXLIII Page 2

......................... !.......................................................................................................

the final eatimated soubined eolttiion/abeerptiotlreek-tlength hoff * 1.00242 with en estloatad standard deviation *f .00073

the estimated t, 9, 99 POreOnt Itff confidence Intervals are 1.00167 to 1.10317. 1.00e to 1.00391. nd 1.0oo0 to 1.004o3

the estimated cellielen/absorptlon neutron revet lifetime a 9.45143 seconds atth an estimated standard deviation of 1.017..................................................................................................................................

Iby at I33S 1996 File lase, P47C41-1.SE* 10VOSU Sty0-ocooo 0noo0016 lv 0o ATTACuXTn CXLIV - page I

va~g rrsin An 141-108R1/93 8312"s6 141"84*- ' **-*-**-*@-s-s**--*@-*-*--@--**-e***--* **-***-*-* probld * S02/96 14:S0:47

1. Feried Critieulltt * Shere of lranamuted S.01 200W 3o0 Mater .1 U-*11p 022 C k-eff Optmistt 1in or Peaitive VUter Coeffticent3- C~- C SpECR1S t INni~h 3967SI65" *t . Ursnifm/Tiuff/aterG'* ST 5 1:! "104° 60001 1| -2 111; *- , Tuff/Water BC fect0r7. C6- C OUTSIDE WORl9- so e a IllFt-0 * Vold10-

Ia- c tS .. so50... , FISSILE 6P1warn!ng. thCi surface has been replaced by a surface of too so

13- a a I a a aio.a0 a REFLECTOR14- C

warning. this surface hea been replaced by a surface of type ao15.'6 MODE K

1T- r c0c£ Soo I 3 100312- C 5831000 00 -1 6 0 *01 a e a

22: '. ' I 0 .S 3 1, .:.3: 1 .'1:.:.12 C ¶ 16

233 Ml 92234.5CC 4.694430- S2-2:1 ac 2.tszia * c24- 9223.c 1.90550- 93203007DC1 92- 016.50 3.6020273- 6 AtIS. 1001.8Cc 1.645371-3 Sa26. 14000.50C 9.3696 0- 13027.500 2.1165924 I Ca27- 0ftS:U51C 1:14i :41 Ii0SS10 1.179513:4 20000.550 4.628070-4 5 WI29- NIt LMT5.1 S VA30- 13 100 i50c 3.142479-2 14000.50" 1.0046-2 13027.50C 2.302817-3 t C

to16.Cc 4.0306- 5V2- 26000 55c1 120DD944 130.50C 2.t42960-4 20000.50C 5.630511-4 t 47

33- fi02e toc 3r7737-4 i9000.500 4.9t051114 634- T3 LUT .1 t W.3S- PRIlE

initlel source free fil. *rotp

Ikoff reaultts er Feroild Criticality * Sphere of Transmuted 3.6E 203W 301 lleSr A0s UV-p 02 probtd a 6S/0D196 14,50747

tie initial fission neutren sourse distribution was reed free the eretp file rued aretptethe eriticality problem was scheduled to ski I leylets and rim a total of 1003 cycles wtth nominatly SO0 neutrons par cycle.thie problec has run I Inactive ycles t 1441 neutron histories end 1000 active epycla with 99950 _cutron istories.

this ealculatlen ha esolt ud thie roquct d saber o eaf t syclc mint * tatel of 301391 filclon neutron saurce historloc.all calls witIh tleslnabe materfl were semplod end ahd flecien neutron eourKeeolte.

the re ulte of the v test for normality applied to the Individual collision. abserptien. end track-length hetff cycl values are.

the hi .ollision) sycle values appear normally distributed at th. 93percent eanfidence levelthe ktsolilionn eycl aletws appear normally diatributed at the 95 ercent confidence levelthe bltrk engthi sve ecP appear normally di tr buted t the 95 percent confidence level

flY 21 13X$5 1996 Ft. Nm.es P4TC4.3.GE-200UDU-30UOS1U SlA0v0so0-l7 e20 O e Eo S ATTAMEsj CXLI- Page I

.............................................................. i.............. .............. ................................................................................. _

the finl estimated emibined etltilne/aboorptlen/tracktlength heft * 1.00103 6Ith an *atimated-standard deviation of .00

the estimated S 95. p 9 pertent koff cenfidence Intervals t re 1.C0O0U to 1.00242, 1.00006 to 1.00320, end .9m55 te 1.00371

the estimated eetsleionlsbsarption feutron remol lifetime * 9.t6E-S *scends hIth en estimated standard deviation of 1.61-C7..................................................................................................................................

a

Nay 21 13:28 1996 Otle lNaet P47c03.09-202025K113u BI3AOOCOCC.1717.16200.0001d IEV *0 *TTACmnUT 0xLV - Valk I

e.l. ..verson 5 la.2 9IO.61/93 p5/02196 164SC3probid m 65/102/96 '16.18:C3

I1P.IE2SWGOOC CUTPO3!2S0.0

1. FarFiltd Critlelity * Br, of dTransmuted 3.0! 206DM 25S Mater 0.62 U-bp 022 e f nft Optimize ton or Positive Water Coefflicent3. C4. C splintI. Ie ' 4~a.47333307146-2 -1 1UPais $ Vraniu./1uff/tor6* 3 3 * .61040596000-2 1-2 . I3Pl. S Tu f/Uster Re looter7- Ct. C OUTSIDE VOtLU9. 30 t 2 SIN-0 S Wlid

IC.11- C CURFA!CE12- I S 0 S' 110.00 S UESSILE SPIERE

warning. this surface hea baen *eplaeod by a surftce of type as13. a £ 000 21 .00 S RESLgCTC14 .warning. thie surface hae been replaced by a surface of type toIs-t' N:MeE aSe1Xlz2e- ecu! Sa0 1 3 1003I2- C *53C 6 0 100 610 6 -1 0 *061 a

Cc .16 1.0 01 1

22- III 92234.50C 4.694430:e 9 235.%C |3.123286-1 922i36.5C 9.113184-6 I pF26. 92238.1CC 1.905500-3 9323.jC .18292&-& 3016.50C 3.412497-2 S At

*5. ~~~1001.5CC 1.37509 -302.Sen.139-26- 14000. CC .3679607-3 1302co1C .11392 S Csn-~~~~~0 ISeo sse 40?0t2 4 12000.S0C 1.8795254 20000.0 see aae7e 4 $Y

Nf: ll,2X.S3: C 1:1991711 4 ISS:CS.5ee 800.5C-4 e 439- II LUT .OI S Vs

38- 13 'l00.ol Cc 3.142479:3 14000.5CC 1.113 6-32 13027.50C 2.302817-3 5 Cs

12-2 300StC 1.339994. 12000.10C 2.02960.4 280000.5C S.030S11-4 5 4733- 11023.1CC see.7m67.4 19000. C .910511-4 -34. XTS LMtI.01S S Ms3 5-t ttlTET _ §I Initial source free fils aretp

Iktff results fors farrteld Criticality - sphere f transmuted 3.!E 2010 n5s Woter 3.02 U-Xp 02 "rabid 05n/296 1610e0

the initial fimsibn neutron course distribu ion us read free the aretp fits named aretpthe eritlelity problem us scheduled to *tip 5 cee end run * total of 1003 *ypes with nemelnolly SOD neutrens pr oelo.thie problem bee rmm 3 Inactive yte oitS 148 neutren histories and 10C active ccles with 100779 neutron hstories.

this ealculation has *ceptoted the requested tmuber of eff cycles using a total of 02267 fission neutron oure histaries.all gollo with floeanabtlo moterisl were sampled and had fioeion neutron sourse points.

tha results of the I test for normality applied to tha individuel sollision absorption, and treck-length hoff eyule valume ore:

the hI mellisien) *ycle vtueus eppoer normally distributad at the 95 percent enfidence ltoelthe httbsorption) sycle velus weppoer normrlty distributed *t the OS precent confidence levetthe tltrt lentChS qycle eluses apparr ormrtlly dtr trIbuted at the 95 poreent confidence level

may 21 1328 1ma file 1Sa1 P47CSt3ay.E-10MM1ID2SVOBU 3IAC0OO-61717.200-40016 aYv et ATtAChExT CZLV - Pege 2

....................................................................................................................................

the final eStMAted e.bInmd eelleientabseerptieltrachklength beif a ."U99 with an estimated etanderd deviation of .6al00

the estimated ",-93, & IN percent koff confidence Intervals are .991S to .9n. .902? to .11331. and .49974 to .9404the estimated celtialenlabsorption neutron removal lifetlm a 9.&E1-5 ascends ulth en estlated standard davietien of 1.7n2-7

Key SI 13,21 1916 PIl e t IMAD7CZ-3.20-20 OO000-91717-0200-1001d SEr 0K A1TACK117 CXLVI - Page I

Vnc. ver ion 4. tl-t10/0i93 13102/96 18,10,203*...15.*....Oee 0ea..e -*.-. *1-0eaeeee - e**----***-- prebid * nte02t6 18.1.20iEPa3IZOVOCSt ufl-a3200U.0

1- Ferpied Iptieat * Sghearee t rensuted 3.6t 20oCII 20X Vat.r a.0 UV-p 022- C ktelf Optin D1 ln er Postiwelleter Cotffetent3. C4- e SBEE1S- 1 1 *.01699037746- *-1 INP,:m1 S Uraniumnflff/Vater6- 3 .4 040596000- *2 INP8a1I S Iaffiator Reflector7- CS. C OUSIDOE WORLD9- so 0 2 11PsI.0 t Voldle-11- e SURFACES12- I t ae0 o 30.0 e 913S1Lg SF1211

wornlnh. this surface b hebren replaced by a surface of type so1s3 a t 0 0 1 2e10.00 s RFLEOlt

rnine. thiT urf ace hes been replaced by a surface of type so1!-16- ODC 117 steDE Soo 1 I 10031a- C cut 5 0 0 1 0 -1* 0 010 a a -10 00 1 019- C 1 0 11 e0 1* *1to C 2 X.1 0 .1 . so .1 .1

- 2234.50t 4:.9440? 922333.0C j.62s26-5 92236.50C 9.153134-6 S PI124- 92233U50C I.90SS30I 93237.5CC 1.1 2926-6 c016.seC 3.298716-2 At24. 1001.50C 1.230247-S Seana$- ugo 14000.530 .269607-5 13027.3CC 2.113592-3 S ca27- 26000.33C 1.150702-4 12o000.1C 1.87 23-4 20000.50C 4.628070-4 S u22S 11023.300 3.3 9178-4 000. DC 4.51r 70-4 * *r29- 371 IVTSW.30. A3 1001I30C 3.1424N-2 14000.5CC 1.007$6.2 13027.1CC 2.302017-3 Ca

0016:300 4.1063067.200. St V12 *2600.30 S1 .39594-4 12000.3CC 2.042960-4 20000.D0DC S.30511-4 * 47J3- D1023.1C 3.477367-4 19000.30c 4.910511-4 t*43 - I xn VITR.*IT $ u35. PaRl

I Initial source frm fite eretp

Ikeff results far. ParF~lod Critiesllty - Sphere of Trenamuted M.0E 20CM 20x Vat r s.ex V-Up 02 prebid * 03/62/96 iss2

the Initial fiessin neutron esurce dletrlbutiln ms, read trom the oretp file namd *retpthe critleality problem was scheduted to skit I Ties Vnd run a tetal of 1003 syleg mith nominally *00 nautrens per 62c10.this problem hs rmm 3 Inactive eycles uit I141 neutren histories end 1000 active cycles with 4990s neutron istorles.

this salculatian bce completed herequstod umber of kaf cletes using a total d S301W26 flexlon neutron eource hibterlee.ltl sells with fissionable materi were sampled end bed fee ion nautron *ourse points.

the resultt at tthe test for normality applied to the ladtviduelt sollielon. aborption, and treck-length keff cycle vetum eors

the tt acllielon) ctl weWuo appoer wormatly Vditrihuted at the 95 percent ment fance loveathe kiabaerpitlton) "ye wluees appear normatly distributed at the 95 ,eant ef ane levethe kitrk leoth) sycl veswae oppear normatty distributed at She 5 peret nt Nnfiance evt

ma El t3sn In File Naes P4702-3.6i'SCUV-f3mV UVOOOOO-6t717-82OD4OO SP aTTACUNEuT Lt&V1 * Page a

the finst estimated eebised etIlelentebearptIeNVtrack-Lenith kfeft * .97117 with an estimated etendard deviatien of *00082

the estimated eS 95. t n Percent koff eanfidance Interval. are .9736 to .97199, .U955 to .972se. ed .949f 2 to .97=

the estimated seltlolonlabserption neutron removal ltfetina a 9.*SE.4S seconds with an estimated standard devlatlen of 1.1717-..................................................................................................................................

may 1111S5 l 996 Fit. Imes P4?CI-3.oE-200l0-1S sU S O0 0000 REV So ATTACINENT CXLVII Page 1

iac VersiEt-onn 60 1d-10101/9 63102/6. 19.261.6prebid * S/"I6 19UM:1

IsPaS11SWO&C IR1114E15018.0

1. MMe rior.oftT* te ransted MEJ2CIt 1fl Water q.83 U-1p e2I: c heA SptIimasnionor Piltive Water Ceeffiernt4 S PUERE

3. te 1 Il.t33 35 76-5346 1 INix:ul S UraniumlTuff/VaterI 3 3 .61C4I40soooC 1 -2 MiP:. S TluffWater Rsflector

I CC UITSIDE WORi.09. so I a INPSK-O S Void

lo-II: @ * tSURFACESi2 I I * S S 110.15 $ FIRIE SPHERE

morning, this surface bas besn rteled by * *urfe of type so43- 3 5 555 21a.60 * REFLECTCR

14.warning, this *urfsce has been replaced by a surface *f type so

3s-16. moot K1r. K50o0 *00 1 3 100313- C E IC S I I* 1 -105 I t ee 1 e

t9. C 1 10 * *1 a -1 O 1 1 I-121- C 01 1 -1 e1 SI -132- C 1 1 I .1 I - 1. 11 1 1-23. Ml 92234.oCC 4.494430-7 9223S.SOC 3.823286-5 92236.SCC .153184-6 S FP24. 9223s. cc 1.33500-3 93237.3SC 3.182926-6 a016.u C 3.1493S-2 s At23- 1001.3CC 9. 326034-1 S on

.224 14000. 5C 9. 49607- 13027.S0C 2.116312-3 I co27- 26000.3C 1.140702-4 eroz l2000o01.e79s23-4 020O.SCC 4.62070-4 It VI23t- 11021 S5C 3.199"17*4 19000.00 e .37670.4 S 47

29 IR1LIR6TS WaT

30. I ca8. CC 1.142470-2 140oo.sCC 1.607366-2 13027.10c 2.302817-3 * ea9016.13C 4.93067-3 ,0 II VI

12: 2600o0.sc 1. ,a94- 12000.3c 2.842960.4 200o0.S0C 5.330511-4 I 4733: 11023.30C 3.477367.4 19000.30c 4.910511.4 534* l LWTR.IT $ usIs. PRINT

Initial source free fite aretp

Ikoff results fore ForFiltd Critialsity - Sphers of Transmuted S.5E 2011 1S% Wlter 5.33 U-Hp C2 prebld * OS/6 19:3.16

Ohs Initial Iiaslon neutron curce dietributisn s r ead free the cretp filt named sretplb criticality proble was sclicauled to StK §T~s, and run * tatot* eof C0 "ewc wth stnoinl SOD Muro per o"Is.this Problem has run 3 Inactive "ules Hith U nautron hiotries 1and 1900 ctie cyce i wit 00761 neutron lstorios.

this celculation has crmplted the requested rmber of toff cycls using a tstal of 502216 fission neutron source historie.satl easl. xith fissionibla maetriel ware "opted end had fission neutron sourcepoints.

ths results of the u test for normality appie d to thc Individual cellision, besroptian. end track-length ksff ictle values are:

ths t( liionl c Hl a ales appear normally di tr buted at th 9 t softdthc hto tien) cycle val appear normally distributed at tha 93 barcent conf idn1 c cevel

th itrh lngth) syc I values appsr normally distributed at the 95 ~arcent sonfidonme level.

hay 21 IISS 1996 91t. lsmt. P47C143.qEf2OMJDM.ISWU SIAODOCCOO-171T7O200-S0016 BEV 60 ATtACKNIET CXLVII - Ptag a

...................................................................................................................................

the final estimated cmbined eettlsieiVabsorptien/truck-igrn ttf * .9a *th an eats ated aat&atd ddviatin io .o 08

the estImated 8. 95. £ 99 percent kuff confidence intervals I rm .92979 to .93ISS, .92892 to .93243, and .92835 to .933

the estimated enttlelon/abserption nautren roaval lifetime * 1.IE-64 ascends wilth n estimated *tndard deviation of 1.3t-U7...................................................................................................................................

I

Jun 07 W0M31 1996 PIR lama 83O20ez.6m UIoVooOOO~e20 1 fEY 0o ATTACUIEUI CXLVIII- Page I

1" version 6. t..10/01193 05/16196 11:06244.. *. prbed a -5/16/96 MM t 44,ms.3020ez stpsOa020azO

I- Far-Fluld 0rittlasitrltudr ' 3.02 e 20 GM/at * 47 S201 l.SAR U02 0s020az2. C Cellt Eile iu ft 1.17 g/ce .4? poroaity ehel a eurre by tuft3- C CELL SPECIFICATIONS4- C ICKER 413TElR algDC

s 1 1 . r~~~7414-1 *l 301I-1

7- I ".60406-2a -S 28PS1o16T- C W1S IW tRLD9- e s 3 NPE0

l10II. C SuRFACE SPECIFICATIOISIl- 1 g0 40. S 1t1Y1 MEL 01l1ls: j 20 INYEt FEL &OI14 650 S 4O14. S INNE1 FUEEL Z3E15-16- NODE UI?- 100 4000 1 30 130iS- C 02350ie1 I I 0 0l e 20313 0 -55 -100 . 4019. e S -S e-3 36-1060 1 e -2 0 -S s -545 5 1C So 1Taz- C KATU0aL SPECIFIAeTIONS21- e 1 I ater ln alt lce51 tut) e .X15 16.5 velt U1022 s 3.01 Origtnl Enrilhmnt o 0 D/T decayed tI utnI lactate23 ml 10 0 18c 1 , 5 1e S 424 t s 1 I 1.6 I02c 1 ee7o96 S 14000. 0. * 1.0162-324 12000. ~. 8.561121-2 801 d 0. 4I

5 45. 20.1*.11023.jo426 92s34.50. 1.015591.4 y223s.soc 6.684s9755 92236. 5c . I" 5

27 92233 S~~c 4.40 9393237.50. 5.043015.628 Otl lttr.t29 a (67 .lS uter In Galles Kill. ta ) 3 .9213 7.37 wall U0255t a 3.01 etrfginel ichant/ 20 00M7I ad to UponheI

31- 62 ~ 1 015c.6162 1.Ic.109- 11023.5Cc 3. 20369 .432- 12000.50.1 .62179-4 1302r7.. D .1215853 14oo.SOc 9.28M7 3Ss 1 oee so 4.5240 - 0000. .c .634610.4 26000.53a 1.142314-4

4: t923. Cc 4.6163-v r 2 235. Cc .7312-1 S 2236.50. 9.004s5-635 92238 SC. 1.67534-3 93237.50 .1675-636 at2 tutt37- a 47 elt sae $to u all lit $38- .3 1001.118c .14249-3 6016.50. 4.66,3067.2 11023.50. 3.477347-439- 12000.50.1.042960.4 a 027.50c 2.302817-3 14OO0e00o 1.007366.4*- 19000.30c 4.910S11-4 20000.5c 5.030511-4 24000.55. 1.239894-4

41. mIS Iu~~~~~tr.O1lt42. PRINTI Initial *ource frin fits Grstt

Ikeff resulte for Fr-fleld Critleel ty Study - 3.02 120 4OWD/t - *7T 320/ 18.5 U02 (.3020.:) problid 05116/96 11206:44

the Initial flelen neutron source dletrlbution uwe reed from the ertp file omed *retpthe criticellty problem was scheduled to esip 30 cyles end run a total of 130 vcles with nem I1lty 4000 neutrone per "ela.this problem has rmn s Inectiv epcles with 120411 nmutron liletorles and 100 active ycles wIth 39"932 eutron hnstorIes.

this ealculation has comteted the requested number of koff cyclos useng a total of 519943 fiesion neutron source hietories.oll golle with fioslseeblo material erte ompted oand bed fiss on neutron wourco poiato.

the rosulte of the w test for normality applie d to the individuol collision, ebsorption. and troc-longthl koff cycle values or.:

Jaun 7 10.31 6 MS tM Ruse, 83020a1.m- 11A0OOOO1-S1717-6200S-0016 3!V 00 AACMEIT CXLVII - Page a

thi kt ceollsien) eyete values appear NormalIV distributed at the 95 percent confidence Itvelth kberptien) cycle values appear mormsll distributed at the 9 percent cenfidence levelthe k(trk length) eyele Values appear eermaltt distributed at the v5 percent enfidence level

..................................................................................................................................

the final estimated embined <elleonlehoarptienltrack-tength keff * .8472 with an estimated standerd deviatien of .eo0904

the stimated 68. 95, & 9 percent keff cenfidence Intervale are .953R2 to .9U562. .98 to ."651. d .tI3S to .92709

the estimated eolteilonfabeorpt1en neutron removal lifetime a 2.371.05 second with an estimated standard deviation of I.3In-07...................................................................................................................................

Jun 87 10:30 196 Pile tlmn 0sC20my.sum U5A000000017-0 OOOU REV eo ATTfCdMENT CIL * Page 1

I = ** ..version 4e tld1/01/9 0./16/96 07:29:34probld a 05/16/96 07:29:34

Inprem2Oy eutp-43OZcyO

1- Per-7etld gritleallty StudY 3.0S 120 gmtet t 47X 20( 1.SS UO2 {o320.)2- C Calico YIlia Tuff 1.157 Stee .47 poresity - ohells surroundd hy tu3* C CELL SPECIFICATIONS4* C INNER VATEI REGIO63 1 1 9.1741491 *1I 1:11:1.

7* a 2 .610406-2 1 * INFI* C OUTSIOE uORLD9. 4 a I 11P9IK

Ill C SURFACE SPECIFICATIONSt5- I to 90. S INNER FUEL ZONE13- SO loc. e INNER UEL ZOIE14- to5 ISO. I INNER PUEL ZONE

16S- ICE I17- C0ODE 4000 1 30 1301s- C 132C ; 1 *61 0* -0 29 0 20 15 6 0 _ _10 0 -40I1- C * -0C -0 30 0 13 * -160 I * 25 30 -15 -56 5 S I 15 1 0 1720. C KATERIAL SPECIFICATIONS21- a j47 veIl "ter be Calice Ulits tutf) a .613 10.1 V.it U0Z22 * .0 Original Enrrlhmant/ 20 00/1T decoyed to Uranium Isoto23 m 1001.30. 3.61121-2 e1016.0c 4.3135452 110203.0c 2.130M5-424 12000.0l .I 5012-4 13027.50c 1. 76796-3 14000.5. S.211662-325- 19000.50. 4.002067-4 2000.1*c 4.9866-4 2600015 1.610513-42- 9234. 0. 1085s1-6 92235.30c SM4ON75- 92236. Oc 2.1166,74-

7. 92238.10a 4.40669-3 93237.10c 5.648015-S25- at1 lmtr.6lt9- a I 7 V "11 ter In eelleo Gill, tuft x .13 7.67 vls U02

O e 5S OrlginaEnrichment/ 20 S/IIT deceyd to llrenium iotope10 *2 ll.6 c Ortnelni 2 016.*Oc 4. UWS ;tg 11023.50. 3.203695.431. .2 12001.50. 1Sftb 30Z273 Cc 0 2s a'l4

32. Z 12005C .21 - I .1 I5 140.0 9. 3270-3333 19000.10c 4.324054-4 tO £6104 2l000.15. 1.14314.454. S2234. 0. 4.61616 57 9223. 4c 9 2315 a 6.50 9.0043635 92230.11c I.174536-3 93237.30c 2.147453-636- .t0 lmtr0lt37. e 47 ve4 M mieter in ecll.e illc tuftFs: *3 100M.50 5.142 T7S2 6016.50c 4.063067-2 11023.50c 1.4M67439- 12000.SOc 2.642960-4 13027.0. 2.302817-3 14000.50c 1.007566-240- 190000. De .910511-4 25000.50.c .30511.4 26000.55. 1.2S994-441 ots lutr.@lt

1 Initial eoureo tfre tlle rertntheff resulta fors For-Field Crit callty Study - 3.01 /20 go/at - 471 020/ 16.51 U02 (a3020.y) probld * 05/16/96 67:29:34

tse lntialt fisslin nhutren source diatribution wsa read tree the aretp file mood sretp .tha eritialilty prebla me scheduled to kip 30 eycles lnd run totetal of 130 cycles mwtit nomlnaly 4e00 neutrons per to.this Problen bes run 305e ictive sycies mith 120414 Nautrn histories and 100 activ eyelna with 400502 neutron histariesathis calculatlon has epleted the requested umber of taft e etes using a total *t 320916 tfislon neutron oouree historles.all calls with teisioneble moteriel wmre esapled end had t lesion neutrn cource points.

the results ef the I teat for hormalIty applied to the IndivIdual elisolen, abesorption. and troct-lensth Rftf cycle values eres

Jun 0? ISiSO l"U fPlu same, e0ZOuy.sum U3AUOOc01i717-*Soe-S0016 *£Y eo AITAtCKNXT CIL Patge 2

th:e i aellielen) eyce valwes appear norma Iy distributed et the 95 percent confidence lavelthe abe rpten? cycle Valves eppear normally distributed at the n prcent enf denee levelthe tytrt ltb cycle values ppear normally distributed at the prcent *nf dance level

......................................................................... ..... .................................................

the final estimated cobined setaialanabserptlenjtrack-lensth hef i 1.14602 with n stimated standard deviatien of .1009

the estimated 68, 95n, I " percent huff sonfid#=9 Intervala are 1.01315 te 1.U1491, 1.0122 to 1.01510, end 1.1167 to 1.91638the estimated eollioelVebsorption neutron removal lifetime * Mn05 aecew. s with an estimated standard deviation of I.53367

..................................................................................................................................

Jun 67 10.28 1996 II. 1le. 030201x.eue ESAooOO O-l1717-62e0o00016 8 REV 0 AtItACNENT CL - Peeo 1

18cm Vereien 6a Id.010J1/93 6SIIS/96 56u51a53'*a Proebid * 65/96 16,SUS13iwne502omx utpe53020.xO

1. Far-Ptetd CrHltIstIt mSc 3.* no10 U01t -* 75n l 6.n 1102 s3020 x$2- t talice* lte Turt 1.17u/e .$ 7 poresity- Shelsee urr d by twtf3S C tEUL SPECIFICATION;6- 1 1111 1A4 RE GSION

1: I *I 090 112 1'11P "17. I 6.64006-2 a .3 267:3.1*- C OUTSIDE WOiLD0- 4 0 3 1 6t3 .0

10-: 6USFAC1 SPICIPICATIOUS

12. 1 to 57. * INNER MUEL 20E13.: 2 30 114.6 S IN3E1 M~L lOll1 3 60 174.3 s INNER FUEL 20Y11s-16- HOSE U17- COO 6000 1. 30 13016- C gone a6 a 66G010 660.20 602 a 21566IF.60ts c nxc e e t @ le * e * 0 Is t a -51 * -teo -4o19- C 50 -20 -30 -13 a *10 60 0 t-a 30 15 56 I 5 5 10 3 1T20- C KATxIlAL SPICIPISAIIOUSz e 147 v.,1 water In seatt. Ellik tufft a .t15 1l.5 vetl 110222- el *es-trt10, I Enrichment/ 20 51AIM deed to Uranium leateaee11 :1 ~~~10011.50h. H.5610161- 6016.50. .14545.1 11023.50. 2.63405 .626 12000 L665012-6 13027. So .t"76116- '1000.90a 6.211662-523- 19000n10o 4.02067-4 80000.50c n.699966-4 26000.1se l6t10S;3.626- 92234. e0 1.68591.6 92235.50c 6.45975-5 922236. Se 2.1166 4-527- 92233.0c 4.406469.3 93237.50c. 5.648015628- st1 lutr .Slt29 a I7 l "ter in Gatos 2" tuft) * .9213 7.67 velt 0230 c 3.6 origInal Sarieuetl a0 COINYU decayed to Urenim. Isatepes31- Uz2 001 .50. 171911 C0c.0 6:11059 1023. 0. 3.30 9368432 12000.30 1.1121796 13027.54c0 1 5 8S14000. Cc 9.* 1705-S33 19000.500 524S6-4 000 c 4.13"16-1 26000.e.e 1.1623146434 9226.0 6.616S65-7 1 102231.50c 3.r63125 92236.50Cc 9.6064i46

9 228 50. 1.07536-3 93237.50. 2.164 3-4I- *t2 lhttr.ilt1767 Vets metor in cello~l5 uf

[email protected] U142479- 0 0o s .l'6. 63 -2 11023.50c 3.477367.639. 120 0:.50. 2.e04296-4 13027. 0c .3028 73 6000.50. 13.075"66-4U- 19000.50. 4.910511-4 20000. 0. o .6305 . 16000.556 1.239894-461- ot3 titr.61t42 Fall?

I Initiel sourte frae file *rctrItetf recutat foer Va-Fietd Critteality Study - 3.1 /20 XoW/t * 67X 3201 11.51 1102 es320x2 probled * a 6515/96 16351153

the In toel fission neutren source diestributien was rad fren the eretp fite ned *rctpthe sri teal ty problem was scheduled te skip SO cye s and run a total of 130 eyels with nominalty 4000 neutrens er cicke.this preblem has nn 30 Inactive eetse with 120424 neutren hietertes and to 10 c tiv yles with 460360 neutren hIsterIes.

this celculetien hba cempleted the requsted umber of tetf cycles uing * teotl of 520s04 fis.o neutren source histeries.el cellt witth fleesioable *atertel tere sampled and had astsen neutron eource points.

the resutte of the u teat fer normality applied to the Individual estlltlen, absorptien. and treck-tenth eft1t cycle valuxe ores

Jun 6 t7lDs 1996 File knot d3020mx.ea *3AO00 06lTt -0200-S0016 REV SO ATTACHINENT CL page 2

the kt celliasen) eyla values appear noreally dietributed at the 9 pareent centidence tlvntthe taborptien) cet values appear neoerlly dit Irbuted at the 95 pereent eont dance lentthe kltrk lenth) cycle vYlu eapper nfrmallv dlstributed It the 95 percent cent e neve

...................................................................................................................................

the fInal estlated aeablned aeltlelensbsereptientreck.teneth ke ff * 1.63012 with an eatimltd *tandsrd deviatlen of ."I'mthe estlated * 9n. p 9 perent keff ea idenee istervele are 1.02916 to 1.63108. 1.02325 to 1.63204. and 1.027s1 to 1.MsU3the estiasted eattleleniabserptlen meutren removal lifetime * 7.10E10 eseends, with en estiltted standard deviatlen of 1.A22*e7

...................................................................................................................................

sun 67 6sl2 196 roile Ears a3020D . KEY00000 G-61? V6200-60 C o 0 TTAI NT CLI - Pate 1

1&C0 ,0 version 4a Id.10a/093 63/16/96 12u66z131=*OeO* "t.* OernO*Sac**-ffi~n ....................... -*O ** -" ea.# ~4 l .......prebtd * 65016196 12,66

fnpe3CZss eutpeai20Ds

1. farpleot Critieality tudy - 3 t6 /2D tisWt * E202 1.5S UD2 (3O art2- C Colel lIls Tutf I.137 Cec .6?porosity s*aha surrounded by tuft3J C tELL SPECIFICAITZOU4. e INR E WATER RECGIO

I 2 2:I t l:'s1'rt~t9 ,1 !, 3l

r- * S ..61C402 4 -6 IpS C ~~OUTSIDE WORLD

9 6X eu5sle 3 inUon

11 C C~URPACII SPCICFICATIONS12. 1 so 53.6 6 INNER FUEL 2D01

- tt: I I .1EI3 1 URL 1011

156 NM I17 1V00D 4000 1101ISOit C IIC le v. 10 o t @ 20 0 6 29 0 20 15 I 60 5 le0D 0

19. C e *se -20400.1. so a * e 30-15 eae*20 so 1720l CC MAIIIAJ.L SPCFICATIONS

21-t rt w Utt rn eIitem2ls tuft) a .515 18.1 ,.ll U02I *g I 1ng anrIT den cad to UrtnIum foet*

t~~v t leoX~~~soc a."lla net-2 1o soc uDNsu- Z!S0 _parsst3. .1 :~~10:1.::: 0016:30. 4.259434 HOC3 2.834054424 12000.50c 1 3t027.S0c 1.676796s 16000.50c 6.211J62-3

19002 . 0 oo 4 .002660 26067.-54 1.etD5t-s2n1u4s .685 916 12o235.sn^ 6.45975-5 9-233.500 2.11664-S

27- 92231.50c 6.6064693 93237.10: 5.648015.6

29- at (67 vi w at r in ga lls. 3iI tuft) x .973857 2.6163 volt U10230. e 3.61 eclrs 'gina seh9 nri / SOT dcaeVd to unim Ieotepes

1- .2 101.1 D s.e6032S-36016.IOc *.6 565 11023.50. S.3W645212. 12000. 1c $.9"SS1. I 02.50. a.242615.3 1400.50. 9.612251-3

19000.50: o 4 0 4.M O.6S3998.6 25D00.55c 1.2D07479143; 22:j : IF r 2235:IOC;:230056: 92236.50. 2.9,9116-6

I I:*tZ~~~4 I33 3 100-19.50.2.1426792 68016.10 ."9 3067.2 11023.50: 3.6773 4.

59 2000.10. *1.42960 4 13027.10. 16100.50: 1r507566.266- d 9000.sec 6 * 91051.lO~l.4 2000.5t0.1e 1 20511 26000.55C 1.23399-4661- at! lwtr.Olt62. PRINTI inItial asreta 11 Crtet ty-SU10Gfiit-4 8/1.Z 2I00r

Ike ft raulta fa"'r"tFar-Motd Cr1 eatY Ity t .3 D /2 D6/t 67 *n 11 .51 12 a300r prebid * 65611696 12i6s61

tbo InitIal tlssion neutron eoureo distrlbut 1n was read fr_ the oretp file wood sretptie aritleelIty problee was scheduled to ski 30 sycles and run a total of 130 *yeles with mnl tty *t00 neutrons per oeIl.thle problm has run SO Inactive eycles with 11975 neutren bletorIlo *nd 100 active oycles with 399641 neutrln histories.

tble alculati n hae eompleted the requested nuaber at ttft aye s using a totel at 319616 fission noutron seuree ,hitarioes.ail calls with flsienabl *stetortel are sampled and had tl on neutron oeuree points.

the result. *t the u test tfr norm1ity applied to the individual collision, absorption. and trct-length tett *yetle values oroe

Jun 67 11l92 99 9ie 1. lam s e*3020 ..ia eIAeoooCoe0171?-4200-0001 REV ee ATTAUENT CLI - Page 2

the tt eeltisren) Cycle wlues appear nermally distributed at the 95 percnt e enfidence longthe k abserptiln) cycte walwes peecr normally dlet.ibuted at the 95 percent cenfidence le 'lthe kttrk length) "cse values ppear normal di etr buted et the 95 pereent eonfidence level

........ .............. ... ..... ... ..... .... ... .. _......... ... .. ...... .......

the final estimated ea elned cellisten/abuerptlen/treck-length keff * .97422 with oh estimated etanidard deviaetin of .00687the estimated 48. 95. I 9 percent ktft aenfidance Intervals are .97SS5 te .9m7 . .979 to .O9M. end .9739 te .9MSthe estimated celtialei^ebsorptien autren removal lifetime a 7.513-65 secends with en estimated standard deviation of 1.9K-Sto

. . .. . ... . .. . ... . .. . .. ... ... ... ... ... ... ... .................................................. .....................................................................................................................

Jun 07 GM0 1996 file UNes a3020ur.snm AUO0oOo-017tI-0200-000i MEV 0 £t1TACKNI CLII -Pase 1

wri:4. td1410/1/93 65/16/96 11:67:55protud * 15/16M9 11:07:15

up.s.02e..r etp-O2Omre

1. PerotS-Fle rittemiti c lst i gl S /e I l0 tw/it * *n aln/ 1S.sx 1o2 0ar12- CC al tter otes t I.1 7g gce .? porosity siatle o b fur by II: S ~~~~~~~CELL SPECIFICATIOMS*- C 161111t F~ISMS WTERt REIONl

10o~ ~ ~~~~~~-7 1 1 8.376149-~~~~I *1 Ilipgts

C. UTS30 WOALO91 6 0utrats 6 3 INWs8u11

11 ~~SURFACE SPECIFICATIONSIS: ES '0J CtiElt agt#ii I 3~~0 33.0$ Il PEM UEL SOMEts- t oIllo I NNERFUEL SOME

16 alOC IIT- 9E 400 16 I1¶S ugouz.oso, 0

19- a ''-5e -to -30 0-1 !le -1 de ta 5 ,3 -S , 56 5 s 5 ts IC So20C C IATERIAL CPECIFICATIOS1- * Is votx rter tIn sell Ittttt tutf) * .915 U1.S wtlX ta221- . J *S IW223. *1 1001. *oc *.51122 016*S0e 4*315345* 11023 4c * .s360^24- 12080.0e C. . 2w501 r I ec 027C. I 14000 .5C 1.21U1662-

2sv 1v~~~000.10c 4. 10067 4 00OO.%O 0999s6 2600.s .@0126 2234 so. B 1-6 235.s0. 6.6457-5 223.50. 3.1166h-5as. :m:s 94fT 3~0i 975q~ 5 SC112233.5Cc 6.40669-3 93237.3. C .048015-6

9: oi~~l utp.41ht29: 147 Mat er In eetlee oll Cuff x .973557 2.6143 IS 1o232 e . J1o1C.8 Ernr1.ehntJ 20 SUIIT Tc; c to Itrnt SiteInc. *2 :Ica 0: 12000.00. C. 0r %2. 'C }426s5- 40oe.50. * 122513. n o o *n1 2eo~ eV :4a 6ee MIsc IW1 ie 4nIS: . .1011. O . 4 16237. Cc .014656. 123.50. j I6 1S*j

36 at. t0tr.09.ST: I923. c1.II*- 925.C tuff 565923.0 *16-:3 1900. *ewtr# "60

41- NO ~lu~t.61t38- 47 eie l 479-tl 60"l':1 * Cc 4.063047. 11023.1Cc 3.47t7367.

- Initi 000.ur5e I am 200e e tetheff resultst fir: tF Xniia eferele Ct i ty Study - 3.611, nt Swit - 41 R20/ 18.SX tl02 aS320mr) prebod * 05/196/ 11:17:55

the Initial f lattn peautrrn aute. distributien s reatd free the etetp fi e q ethe eriticality probegiwi mm edduted to stop I3yleed 0 oa of 13 earms mlii smuinally 4000 neutreni pr evcio.tis problem befrun s " nactive yeytes .ith 1200T neutrtn hlsterisa and ICC active oYces with 400573 feutrn hutis.r

this eelmulatlon has eoleted tShe reuested nmber of heft cycles using a totl . 520620 fission neutron esurce hletorles.elt *elie with fiesioaeble materiel were Weopd end had fission neutron eruree peinte.

the result. of the u teat for ortality eppliod to the individual oolililen, ebsrptlen, and trackee ongth keff scl.e vlues ores

Jun 67 G9M 1996 Fle lsae: d3O20r.smm SUAOOOCO-1171?-0200-00016 REV S0 AITACIEIT CI * Pases 2-

tb- tt rellision) eveloe ue appear normally distributed et the n percent eonfidence leveltbe ttobrorptl n) "els valvs Ippea nr eruy ditritbuted at the ffS pprsnt confidence. levelthe tttrk tolnth) cycle va!S yppebr normallt distrited *t tho 9f percnt confidmnce 1evel

..................................................................................................................... ............

the finoa estimated cembined eetllielon/bserptiwtrack-tlongth 1f t * .98701 wIth en estimated standard deviation of .C0091the estimated 8. rs, 9 repercent 1sf sonfideoca istervele era .9810 te .98792, .9520 to . 8 and .9841 to .19842

the estimated aetlislonjobaorptien meutron removl lifetime a 7.62E-05 scends with an estimated standard deviatit n of 291E-07...................................................................................................................................

jun or ffs:6 1996 Pie olaes s eOZQ.#= R3A00000S17 C0016 1EV 00 ATTACKNEEt CliI Page 1

lcn version 4c t.WGII 61e<.= $8............. .. t.n.su........2 rbd*118/127 o~l prbd a flh1616 Pu 5Ct37ts.a3OZeq anptaS32OmqO

1. Par-Fleld CrI tIlIty Stu 3.0t IC 60t * 4n 1v2o 5 ISM UoZ t 302*m)l3- C oo lle T 1fI .I711.. pereaity- shells * urrundd by tf3- C CELL SPECIPECATIOIS4- C IE WATER 2(63CM

!g.S74149. 2 I IEPallE| ^ s~~171 02 I wIi I 3 S.6104061 2 CMPI U .

1- C 0SlIT0E VaILD9 4 S I sEUC

lo:11 C SURFACE PECIFICATIONS12 1 So 174 % *IUEl ML MlIE1 90 1)19SD m S NKES PURL ZONEIr to 4.1 9~~~ 11VR PML ZONE

1': ROD, I1IT 9C00E 4000 1. 30 13018. C c3 * 01 OSlO 6 6029 O 205 go5 as a I g I IO t19- C I-so 20 -S 3I 03 136I;040 1 3IS 430- .5650 030120 C IUTCl4L SPECI ICATIOIS21* e 47 t1 nater In sali.e Uitcl tuft) a .615 18.5 wets 11222- * 0 Cxrgl~lna a? lesent/ t0 6/RIT dced te Urnila lests233 ml 1001.5C .411 06C . 4.ZI43 .2103.5 2 834.054424 12000.1Cc 1.4501 I 13O27.5E0 1.S76796- 316000.Sc 8.311662.3

190.5c 1.006. 30000.1Cc 4.09986- as00 :5 81.010513.4as 40ODs. Oa w .620 20D e g 4^ 2 000 GS. 3~lsiZs:2203.C 1.08591-I 92235.ZSC 3.43973 9 2235. c 2.1O s

27 *~~~~2ZSI.S0 c .406469-1 9323.110c 5.1748015-6S8. intl Intr.111t

29. o Ie ter tn gal..c Sle tuft) a .9738ss 2.6143 t1 U02SO- I 1W@ Irgm Snllt 0gnl bcdt rcnl e c

3': 1084g0 "Ig o 9e5ral a Si-2 7580 2 .842s1SS 1400.1c9812231-8e333S 14eoo. o. *.nns 2oooo. o. 4.698998-4 26000.55.c 1.2eT4nSt *22ss. e. l3ss r Zzsee o. 1.200056 5 92236.5Cc 3.9916.S5 nue. GS:,.De 133523.736- at2 Itr.O~t37. c 47 VIS, Water In g*tiee s oil tuff39: 8 1 l 3oo. U2479-2 001.1k 6.063067-2 11023.5C0 3.477167.439 12eooc .u9 e n .302817 14000:.1. 1. 07TSUa40 19" 000 .91 * c .030511. 236000. 5 1 1.239394-41 at3 lgtr.Ot42. PRIM?I Initial aurs tram fits Irat

Ikdff results fore ar.PItd Cr1itseatty Study * 3.05 /10 M/mt * 472 h20/ 1S.SS 1102 (930205q) probld a 05116/9 58:15:27

the InItlal fleseon neutron esurse dietribut n tp file neaer shetppltjd *retV ,the *rutmeet ity prel_ ws scbaduled to sk P leie * nd ri M a total of 130 cycles utb nmily 600nutr pr sclthis problem Ue rum W0 inactive ycles w11th 120333 Neutron histeries end ICC ative sycles p iuth 31U19 neutron Nistories.

this calculetimn kee emletwd the requested asber ef efft sctles using a total of 519157 ftissin nautrn swi ure histeriee.all eslls with Ifielalbe teral wore suptld and had fleesin neutron wurce points.

the rsutts f the a test for notrmlty aplted te the indtvfal eolllsien. abesrptfmn. and track-length kaff cytle values ares

Jun nT Cgs" 19196 1 Fl o Ise: aC2Omq.u SIACOCOOOO-g1?77-S200-SOOIS UIV I0 ATTACKIEN CLIKI - Post a

the hti cealllr1n) sycle Vtelm appear normatty dletibuted at the IS perent m1,dm levelthe ktaerpti n) *rele na s pear normally ditrIted p tbe 9 r:nt *enfiden levt. but met at VS percent

tb r t let) cycle ws m Oppear nomial diatribtred *t the S Prcent e nfidance level

...................................................................................................................................

the flet cstfa td ciemed eoiefi/abaerptlJtracIenhh ht tf * .n3U Mith On eatizated entdrd devietien f .00092the Ostlutad e. ff, A 9 percent hUff anfidence Intervals are . 93 to .94n. .9202 to .mn. eWA .1914Z ts .99d34

th <estimated eeltiolen/mbeorptlen nautren raetvl 1ifetim * 'T.41-65 secends With an estimated *tauard deviation of 1.631-07..................................................................................................................................

Jun 67 1t0.7 1996 Pite Ism: dt020Mnb.cum UVA00t0D0-0717 -20-CtOI4 EV *0 ATUACMENt CLIV - Past I

I" vesion4. td.10/01/93 33/23/96 1MOM8pebd* 0/3/4luSSI~ . In4...1ttO . ** *- 2 9 Is5 probld a 0542UM M2UM

ta.pc320nb eutp-e3020nb0

1- fer-Pletd Criticelty 3g 3.1 n20 6W/st - 41 120/ 4.61 U02 teS02Cebi2- C Catfee Nitta tuvf 1.PS 95Vc .40 porosity lsf eytindor ref ected by tuff3- C CELL EFECIFICAIIONS4- C 3123R VAlUE- 313101S. I I * 9. -1 3-4 I,.4- a Ipul1"J . - 13.1l1

9 4 I 25-384 11M1ledl

II- C 3ISI3CE 3PECIFICATIOIIS13 I as 1 * INNER FUEL Z0313 U Oa 121 a reflector14- 5' pz U I center". 4' PF 335 t and16 5 p 445 S reflector

19- 9LOE %000 I. as 1231M e cnc e I 16 0 e10 6 9 It 0 2 96 I 15 e0 0 SS -10 I 40E1 C -5120 -30113 0-10216 S 9025 ;123-15 16 53 010 30 17322 C I6 co00 0 go0 332 0 90 02to010 065 a -103a 4013:r. C * U20 -30 0 313 e -10 20 3-30 325 -3 15 33 I Ss0 ItN1724 C E A TIONSL pECAIUOE3

* 1 4~~~1 ~Xuater In eesliceo Utol Iuf a .934 44 .111s . tuOuul l Enharcnt 2t 01t011T doeed to Ureni eotwe

27- E .1 C100 oe 0. a.54- 305450 .19173- I10235. 75564426- I 20: 0c 1:106391-4 it 027.Ic 3.4t ,3 14000. 0. 1.;1

29 W~~~000.5Cc 5 j0332-4 20000.30. 5.429524 6000.55. 1 J390S5.41200 to T ~~~~~~1231- n92234.0c 9930-r7 2235.3CcL19954- * soc *.343s51.31- 92233Cc 5 .195633 93237.3c .312-6

32 all t40 wil ate ol531.tf33: *t 40. l

S * Itgo:5' 0 .312735-4 1 027. Ic .406963-c 1.140641.119to0. 0. .559089-4 20000. 101.494915 4 S000.s. 1.40C453-

37- intl lntr0tt atial soure, frefe I r

Ikeff reults fors For-riel Strttlty stufy * B.01 no 10.t - 40e 202/ 4.61 X02 10zenb) probld * 05/28/9 MsUM

the Ititalt fleattn neutron scuree dietribution nc reed free the eretp file nred oretp .the spit eality probl. us scheduled to skip 5 eyeL rum a tetel of 125 syclas with newtinstl 4000 meutrns er Iec:t.this problem has nim f8aactive te witt 9996 neutn hivstries ed 10e ey" et wIth 399700 _eutron hist r"s.

this celcutetien ats eoaleted the requested umber of keff syclee using a totel of 49949 fission neutron souree iletories.eit seale with flesleneble materlel were sampled end tad flexien neutron source pinte.

the resutts of the u test for norselity appliod to the individul soutleilon, ebeorptlen, end treek-langth keff svle values apes

the tt esllislon) sycte vaelas appeer Nermlly disetributed at the 55 preant :enfidefce levelthe ktebserption) se values *opper Nermally istributed at the Ps pereent enfidenee levelthe httrt tenstho gytloe lwas ep"or mrml ly distributed at the 95 reent eenfI dene& tee

Jun 67 19u4? 1996 P to. laws: .OZOnb.sun ICNO677SS.01 REV SO AWIACKNENT CLIV -Palo 2

the final eatimated cembined oeltleijjbearption/track-tlngth kadf- .79262 with it iitlsated standard deviation of .6007?

the istimated u, 93. Al 9 percent eff ncotnnfider Intervals are .79183 to .7919 te .79414. and .79059 te .n944

the estioated * ttiaenloabserption eutron essavat Ufetime a 1. IS-S4 Socans with en estimated standard deviatien of 3.&3-ST...................................................................................................................................

I*,