opý 10. Site Reclamation Cost Estimate for Plant Located in Metropolis, Illinois Revision 0 June 2000 Prepared for: Honeywell Metropolis, Illinois Prepared by. GTS Duratek Radiological Engineering and Field Services 628 Gallaher Rd. Kingston, TN 37763
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opý
10.
Site Reclamation Cost Estimatefor Plant Located inMetropolis, Illinois
Revision 0
June 2000
Prepared for:HoneywellMetropolis, Illinois
Prepared by.GTS Duratek
Radiological Engineeringand Field Services
628 Gallaher Rd.Kingston, TN 37763
HONEYWELL
Site Reclamation Cost Estimatefor Plant Located inMetropolis, Illinois
Revision 0June 2000
Prepared by:
Reviewed by:
Approved by:
Pau C.Ely •f
Principal Radiologicý/Engineer
Robert HombeckOperations Manager,Radiological Engineering and Field Services
Date 6&k/o
Date _"__,,-___
Date 00Roafi ShultM6ager, ByproductsRadiological Engineering and Field Services
Prepared By:GTS Duratek
Radiological Engineering and Field Services628 Gallaher RoadKingston, TN 37763
EXECUTIVE SUMMARY
EXECUTIVE SUMMARY
The Radiological Engineering and Field Services division of GTS Duratek, Inc., has providedan independent cost estimate for the site reclamation of the Honeywell Plant located inMetropolis, Illinois. This estimate was prepared at the request of Honeywell to provide for anindependent estimate for financial assurance purposes. This cost estimate was developed usinga systematic approach. Release levels were identified and historical contamination data for thisfacility was reviewed. A site characterization survey was not performed. Specific and generalinformation regarding equipment and structures was used in determining decontamination anddemolition methodologies in order to minimize overall decommissioning costs.
This estimate includes itemized costs for manpower and equipment resources, radioactivewaste volume reduction, packaging, shipping and burial activities, and the performance of finalstatus surveys for buildings and structures. The estimated decommissioning cost is$99,535,489 in terms of 2000 dollars. This estimate is for budgetary purposes only and is nota proposal for GTS Duratek, Inc., to perform the decommissioning work.
A significant portion of the overall decommissioning costs is attributed to the processing orburial of radioactive waste. The radioactive waste disposal rate used for most of the waste inthis estimate was based on shipping to Envirocare of Utah and upon negotiating a favorablerate with Envirocare of Utah based on a large waste volume and low levels of activity. Theremay be another opportunity to dispose of this waste as 1 l(e)(2) material, defined in Section11(e) of the Atomic Energy Act as the tailings or wastes produced by the extraction orconcentration of uranium or thorium from any ore processed primarily for its source materialcontent. The cost for disposal of wastes at a facility authorized to accept 11 (e)(2) materialcould be significantly less than for a facility licensed to accept regular radioactive wastes under1OCRF61. The cost for disposal of the calcium fluoride pond sediment was based on disposalunder 1 I(e)(2) regulations.
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TABLE OF CONTENTS
TABLE OF CONTENTS
PROPRIETARY STATEMENT .............................................................EXECUTIVE SUMMARY................................................................... iTABLE OF CONTENTS.....................................................................iii
LIS OF APPEND)ICES...................................................................... ivLIST OF FIGUTRES .......................................................................... ivLIST OF TABLES ............................................................................ v
Figure 2-1 Honeywell Facility..................................... 2-5Figure 2-2 Plan of Honeywell Facility .............................. ....... ...... 2-6Figure 3-1 Honeywell Uncontrolled Area Survey Data .................. 3-6Figure 3-2 Honeywell Controlled Area Survey Data ........... .......... 3-7Figure 3-3 Honeywell Environmental Soil Sample Data ........ .............. 3-8Figure 3-4 Honeywell Environmental Mud Sample Data......................................... .3-9
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TABLE OF CONTENTS
LIST OF TABLES
Table 3-1: Acceptable Surface Contamination Levels ........................................................ 3-3Table 3-2: Interim Screening Values' (pCi/g) of Common Radionuclides for Soil Surface
C ontam ination Levels .................................................................................................. 3-4Table 4-1: Decommissioning Cost Summary - Honeywell Facility ................................... 4-1Table 4-2 Personnel Protective Equipment Protection Summary ....................................... 4-2Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work ......................... 4-3Table 4-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work ........................ 4-4Table 4-5: Honeywell Unprocessed Radioactive Waste Summary .................................... 4-5Table 4-6: Decontaminhation Methodology Comparison ..................................................... 4-7Table 4-7: Volume Reduction Methodology Cost Information .......................................... 4-8Table 4-8: Decommissioning Estimate Selected Unit Cost Factors .................................... 4-9Table 5-1: Planned Rem ediation Activities ........................................................................ 5-2Table 5-2: Typical Final Survey Instrumentation ............................................................... 5-5
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INTRODUCTION
1.0 INTRODUCTION
1.1 Purpose-
The Radiological Engineering and Field Services (RE&FS) .division of GTS Duratek(GTSD) has prepared this document for the purpose of providing a cost estimate for sitereclamation of the Honeywell Plant located in Metropolis, Illinois. This estimate wasprepared to provide for an independent estimate for financial assurance purposes.
The estimate includes only activities and cost factors necessary to reduce residualradioactivity to levels that will permit release of the associated structures, buildings andgrounds for unrestricted use.
Costs associated with the demolition and removal of non-contaminated equipment orstructures are not included in this cost estimate unless such activities are required tosupport decommissioning. An actual date to perform the site reclamation has not beenprojected. The cost estimate provided by this report is in terms of 2000 dollars.
1.2 Scope
The scope of this report is to present the estimated costs derived for site reclamation ofthe Metropolis Plant. The specific areas covered by this estimate include:
• Feed Materials Building• ION Exchange Building* Sodium Removal Building* KOH Mud's Building* Uranium Recovery Building0 FM Building Pads* Sample Plant0 Ore Storage Building* Bed Material Filter Fines Building* Pond Mud's Filter Calciner Building* Cylinder Wash Building* Drum Crusher Building* Fluorine Plant• Liquid Fluorine and Nitrogen Facilities0 Calcium Fluoride Building* Administrative Areas0 Ore Storage Pads* KOH Mud's Storage Pad• Waste Storage Pad
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INTRODUCTION
* Settling Ponds* Drains & Sewers* Calcium Fluoride Ponds• Outdoor Areas• Discharge Ditch to River
Decommissioning costs are directly related to the degree of remediation required andthe amount of radioactive waste generated. The extent of remediation is based onradiological data, proven decontamination processes and data from similar projects.The volume and weight of radioactive waste was estimated based on data obtained fromsite drawings, vendor documents, and direct measurements in the facility.
1.3. Assumptions and Bases
The following assumptions and bases were utilized in developing the cost estimate.
Some of the older more contaminated buildings will be removedcompletely. The office buildings, and other buildings with minimal orno contamination. will remain in place after decommissioning. They willbe decontaminated if required and free released but they will not berefurbished if required to make them useable.
Uncontaminated processing equipment can have high intrinsic values andwill be utilized at another location or sold during decommissioning.There was no cost included for decommissioning this equipment and nosalvage value credit taken for this equipment.
Contaminated equipment will be decontaminated on site, processed at avolume reduction facility prior to disposal, or sent directly to a licensedradioactive material disposal site. The waste processing facility isassumed to be the GTS Duratek facility located 295 miles away in OakRidge, Illinois.
Radioactive waste with low specific activity will be sent to Envirocare ofUtah. It was assumed that partially decontaminated equipment,protective clothing wastes, removed concrete, miscellaneous DAW andsoil would qualify for disposal at Envirocare of Utah.
Radioactive waste not suitable for disposal at Envirocare of Utah can besent to the Barnwell, South Carolina disposal site. However, all wastequalified for disposal at Envirocare of Utah under their current licenseand waste acceptance criteria.
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INTRODUCTION
The site remediation contractor will provide most of the demolitionequipment and survey instrumentation at prevailing rates.
Local decontamination technicians and supervisors will be utilized tostaff this project and no travel and living funds are included for them.Health Physics technicians and supervisors and project managementpersonnel will not be local hires and funds for travel and living expenseswere included.
* Construction labor rates were obtained from 2000 RS Means BuildingConstruction Cost Data for Paducah, Kentucky.
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GENERAL FACILITY DESCRIPTION
2.0 GENERAL FACILITY DESCRIPTION
The Honeywell Plant is located on U.S. Highway 45 approximately 1.8 miles northwest ofdowntown Metropolis, Illinois. The plant and Metropolis are both situated on the north bankof the Ohio River. The Honeywell property consists of an 862-acre tract bounded on thesouthwest by the Ohio River and by U.S. Highway 45 on the northeast. A section of thesoutheast property boundary is contiguous with the town limits of Metropolis. The restrictedarea containing the plant occupies an area or about 31.6-acre site within the property boundaryas shown in Figure 2-1. The plant contains about 20 principal buildings, including anadministration building and a laboratory. It also includes five large settling basins for whichretain the calcium fluoride sludge and two small settling and treatment ponds
Major site facilities include the administration building, the laboratory, the fluoride productionfacility, the UF6 manufacturing facility, the waste treatment plant, and a large UF6 cylinderstorage area.
The Metropolis plant was designed to convert uranium ore concentrates into uraniumhexafluoride, which is then shipped to U.S. and foreign plants for enrichment of the 235Uisotope. The facility, which uses the fluoride volatility process, has the capacity to convertapproximately 14,000 tons of uranium per year from ore concentrates into UF6. The oreconcentrates feed assays approximately 75% uranium, and the distilled UF 6 product containsless than 300-ppm impurities.
The plant receives uranium ore concentrates in 55-gal drums. Each drum of ore concentrate isweighed and then stored on storage pads until accountability procedures and the uranium andimpurity analyses are completed.
Some ore concentrates and all uranium compounds from the uranium recovery process containundesirable amounts of contaminants, principally sodium, that must be removed. Thepretreatment consists of a four-stage countercurrent decantation treatment with ammoniumsulfate solution. The uranium solids discharge into the ore calciner in the ore preparation area.
Incoming ore concentrates are charged into the system through a drum-dumping station. Theconcentrates either go directly to the calciner or through the pretreatment area to the calciner.Following the calciner, the ore concentrates are blended, agglomerated, dried, crushed, andsized to a uniform particle size. Dusts and fumes from this process are controlled by a seriesof dust collectors.
The sized U30, enters a fluid-bed reactor termed the reductor. In the reductor the uranium isreduced to the dioxide form utilizing hydrogen and nitrogen as the fluidizing gas, which isobtained from the dissociation of ammonia. The reductor off-gas (principally hydrogen,
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GENERAL FACILITY DESCRIPTION
nitrogen, water vapor, and hydrogen sulfide) is passed through filters to remove particulateuranium, and the residual gas is incinerated to convert the H2S to SO 2.
The uranium dioxide from the reductor is fed into two fluid-bed hydrofluorinators operated inseries. A countercurrent flow of anhydrous HF fluidizing gas converts the uranium dioxideinto uranium tetrafluoride (UF4). The off-gas is filtered to remove particulate uranium andscrubbed with water and potassium hydroxide solution to remove HF before being vented tothe atmosphere. The HF scrubber liquors are neutralized, and the fluoride is removed beforebeing discharged with the main plant effluent.
The UF4 is fed into two parallel fluid-bed fluorinators that also contain inert bed material.Elemental fluorine used as the fluidizing gas converts the UF4 to UF6 that is volatilized fromthe fluorinators. Residual uranium and nonvolatile uranium daughter products remain in thebed material, which is recycled and reused until the buildup of contaminant levels prohibitfurther use. The bed material is then retired for radioactive decay and recovery of the uraniumcontent. The volatilized gas containing UF6, excess fluorine, and HF is passed through aseries of filters for particulate removal and through a series of cold traps for UF6 collection.
The bulk of the UF6 is condensed in a series of primary cold traps that are operated atapproximately -20'F. The secondary and tertiary traps operate at lower temperatures andremove the residual UF6. Following liquefaction crude UF6 is removed intermittently fromthe cold traps by heating and is then transferred to still feed tanks to await purification byfractional distillation.
Uncondensed gas from the cold traps consisting of F2, HF, air, and traces of UF6 is passedthrough scrubbers where contact with aqueous potassium hydroxide solution removes fluoridesand traces of uranium prior to release to the atmosphere.
The potassium diuranate precipitated in the off-gas scrubbers is settled from the KOH solutionand transferred to the uranium recovery facility for recovery of contained uranium. Thescrubbing solutions are processed for regeneration of KOH that is subsequently reused in theprocess scrubbers.
Crude UF6 from the still feed tanks is fed into a low boiler distillation column. The UF6 thathas been stripped of low-boiling impurities is then fed into a high boiler distillation columnwhere high-boiling impurities are eliminated. The product is condensed and packaged into 10-ton' or 14-ton cylinders that are shipped to gaseous diffusion plants. There are no off-gasesfrom this process.
Potassium diuranate from the cold trap off-gas cleanup system, fluorinator filter fines,contaminated fluorinator bed material, miscellaneous recovered dust, and scrap ore are finely
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GENERAL FACILITY DESCRIPTION
ground and leached with a sodium carbonate solution to solubilize the uranium as thetricarbonate complex. The leached material is filtered, and the insoluble material (principallyinorganic fluoride containing residual uranium and uranium daughter products) is dried anddrummed for disposal at a licensed radioactive waste disposal facility. The uranium in thefiltrate is precipitated with NaOH; the recovered uranium is then charged to the head end ofthe process via the pretreatment facility.
The uranium recovery leach liquors are recycled to permit reuse. Less than 10% of theseliquors are withdrawn, treated, and then discharged into the plant effluent.
Periodically, UF6 product cylinders, must be washed and pressure tested to assure designintegrity. The cylinders are washed with sodium carbonate solution to leach the uranium fromthe residual solids. The leach liquors are then filtered to remove the unleached solids andtransferred to the uranium recovery facility.. The remaining solids containing daughterproducts of uranium principally 234Th and 234Pa, are stored onsite in drums and areeventually disposed of at a licensed waste disposal facility.
Fluorine, which is one of the raw materials required for the UF6 process, is produced onsiteby electrolysis using hydrogen fluoride as the source. A portion of this material is transferredto the UF6 operation, and the remainder is used to produce materials that are soldcommercially.
2.1 Main Production Buildings
The Main Production Buildings include the Feed Materials Building, the FeedsMaterials Building Pads, the Ion Exchange Building, the Sodium Removal Building, theKOH Mud's Building, the Uranium Recovery Building, and the Sample Plant. Thesebuildings incorporate the primary processing activities as listed above.
2.2 Miscellaneous Production Buildings
The Miscellaneous Production Buildings include the Ore Storage Building, the BedMaterial Filter Fines Building, the Pond Mud's Filter Calciner Building, the CylinderWash Building, the Drum Crusher Building, the GF2 Plant Building, the South GF2Plant, the SF6/IF5/SbF5 Building, the Liquid Fluorine Facility, the Liquid NitrogenFacility, and the Calcium Fluoride Building. These building incorporate supportprocesses for the uranium processing facilities above and non-uranium processingactivities.
2.3 Drum Storage Pads & Ponds
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GENERAL FACILITY DESCRIPTION
The Drum Storage Pads & Ponds include the five (5) Ore Storage Pads, the KOH MudsStorage Pad, the Waste Storage Pad, and Settling Ponds #3 and #4.
2.4 Outdoor Areas, Drains & Sewers
The Outdoor Areas, Drains and Sewers include the Employee Parking Lot, the pavedroads on site, the Railroad spurs #1 through #4, the land between two parallel propertyexclusion fences, the company owned land outside the fenced property, the DischargeDitch to River, the UF6 Cylinder Storage Area, the Long Term Cylinder Storage Area,site drains, site sewers, and all other land inside fenced area.
The Discharge Ditch handles the discharge from several sources. The effluent streamfrom the calcium fluoride settling basins has a pH of approximately 12 and isautomatically adjusted to, a pH of approximately 8 using H2SO 4. This stream iscombined with treated sanitary waste and is continuously monitored. This combinedstream is mixed with the uncontaminated cooling water and the effluent for the uraniumsettling ponds and again monitored before being discharged via the ditch into the OhioRiver.
2.5 Administrative Areas
The Administrative Areas include the Administration Building, the Lab and OfficeBuilding, the Shop/Stores/Ofrice Building, and the Power House.
2.6 Calcium Fluoride Ponds
The Calcium Fluoride Ponds include the five ponds, Ponds "A" through "E". Thefacility process uses calcium hydroxide to precipitate fluorides as insoluble calciumfluoride. Precipitated solids are separated in settling basins and are retained onsite.
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GENERAL FACILITY DESCRIPTION
Figure 2-2 Plan of Honeywell Facility
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RADIOLOGICAL CONDITIONS
3.0 RADIOLOGICAL CONDITIONS
The Honeywell Facility in Metropolis, Illinois was visited in February of 2000 to gatherphysical and nuclear data for this site. Facility sketches, building sketches, andradiological data for affected areas were obtained. On site staff members wereinterviewed to determine the radiological history of affected areas and the site ingeneral.
3.1 Radionuclides of Concern
The radionuclides of concern at these sites are naturally occurring and originate fromthe processing of uranium ore concentrates that also contain natural thorium notremoved in the milling process. Natural uranium contains the two principal isotopes U-238 (99.3%) and U-235 (0.7%). Natural uranium also contains minute amounts of U-234. The other radionuclides of concern include Th-230, Th-231, Th-234, Pa-231, Pa-234m, Pa-234, and Ra-226.
3.2 Radiological Criteria for License Termination
The NRC Radiological Criteria for License Termination is given in 10 CFR 20. Inorder to release a site for unrestricted use the two separate and independentrequirements contained in 10 CFR 20.1402 must be met. A 25 mrem per year doselimit and the levels of residual radioactivity must be ALARA. There are at least three(3) methods to demonstrate compliance with the license termination ALARArequirement: 1) the quantitative method in DG-4006 (Demonstrating Compliance withthe Radiological Criteria for License Termination, including the D&D code, August1998), 2) by reference to other appropriate analyses (e.g., the Generic EnvironmentalImpact Statement, NUREG-1496); and 3) qualitative judgements (e.g., good practice,engineering judgement, unreasonable expense). For the purposes of this report it wasassumed that the quantitative method in DG-4006 would be utilized.
The current NRC guidance for acceptable activity levels for specific radionuclides ispresented in Supplemental Information on the Implementation of the Final Rule onRadiological Criteria for License Termination, the Federal Register (63 FR 64132,11/18/98). However the NRC declined to provide specific guidance for alpha emittingradionuclides (U-nat included), but during a two-year interim period the NRC plans tocontinue to develop the approach for alpha emitters. In the meantime the Policy andGuidance Directive FC 83-23 still applies for release of equipment and other materialsduring operations. For license termination during the interim two-year period the NRCencourages the use of site-specific dose assessments based on actual site conditions.The acceptable surface contamination levels used for this estimate are as given in Policyand Guidance Directive FC 83-23 Guidelines for Decontamination of Facilities and
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RADIOLOGICAL CONDITIONS
Equipment Prior to Release for Unrestricted Use or Termination of Byproduct, Source,or Special Nuclear Materials Licenses. These acceptable levels are presented in Table3-1, which was excerpted from the above referenced document.
The current NRC guidance for acceptable surface soil contamination levels for specificradionuclides is presented in Supplemental Information on the Implementation of theFinal Rule on Radiological Criteria for License Termination, the Federal Register (64FR 68395, 12/7/99). These acceptable levels are presented in Table 3-2, which wasexcerpted from the above referenced document. The surface soil screening value for U-238 with its decay progeny present in equilibrium is 0.5 pCi/g. This is much lower thanpreviously utilized release limits for U-238. The NRC criterion for residual depleteduranium (DU) in soil was 35 pCi/g ("Disposal or Onsite Storage of Thorium orUranium Wastes From Past Operations", 46 FR 52061, October 23, 1981. It isanticipated that applying the a site specific release criteria and the quantitative ALARAmethod in DG-4006 will result in a release criterion in excess of 35pCi/g based onpreviously performed evaluations. For example for the Gore, Oklahoma SequoyahFuels Corporation Decommissioning the site specific DCGL for uranium was calculatedto be 110 pCi/g using the RESRAD code at the 25 mrem per year dose limit. A DG-4006 ALARA evaluation indicated an ALARA action level of 4,780 pCi/g uranium.Therefore the 110 pCi/g DCGL would not have to be reduced further to be ALARA.For the purposes of this report it was assumed that a site-specific release level of35pCi/g could be established.
Beta-gamma emitters (nuclides with decay modes other than 5,000 dpm /100 cm 2 15,000 dpm /100 cm 2 1,000 dpm /100 cm 2
alpha emission or spontaneous fission) except Sr-90 andothers noted above.
'Where surface contamination by both alpha- and beta-gamma emitting nuclides exists, the limits established for alpha- and beta-gamma emitting nuclides should apply independently.hAs used in this table, dpm (disintegrations per minute) means the rate of emissioh by radioactive material as determined by correcting the counts per minute observed by an appropriatedetector for background, efficiency, and geometric factors associated with the instrumentation.
'Measurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area, the average should be derived for each such subject."M'e maximum contamination level applies to an area not more than 100 cm2
.
"The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, andassessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined,the pertinent levels should be reduced proportionally and the entire surface should be wiped.
-'he average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at I cm and 1.0 mrad/hr at I cm,respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
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RADIOLOGICAL CONDITIONS
Table 3-2: Interim Screening Values' (pCi/g) of CommonI Contamination Levels
deemed in compliance with the 25 mrem/y (0.25 mSv) unrestricted release dose limit in 10 CFR 20.1402.For radionuclides in a mixture, the "sum of fractions" rule applies; see Part 20, Appendix B, Note 4. Referto NRC Draft Guidance DG-4006 for further information on application of the values in this table.2 Screening values (pCi/g) equivalent to 25 mrem/y derived using DandD screening methodology (SNLLetter Report for NRC Project JCN W6227, January 30, 1998). These values were derived based onselection of the 90th Percentile of the output dose distribution for each specific radionuclide (orradionuclide with the specific decay chain). Behavioral parameters are set at the mean of the distributionof the assumed critical group. The Metabolic parameters are set at Standard Man or at the mean of thedistribution for an average man.3 "+C" indicates a value for a radionuclide with its decay progeny present in equilibrium. The values areconcentrations of the parent radionuclide, but account for contributions from the complete chain ofprogeny in equilibrium with the parent radionuclide.
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RADIOLOGICAL CONDITIONS
3.3 Characterization Data
The characterization data available and experience with similar sites was used todetermine the extent of remediation required during decommissioning. The siteavailable characterization data included removable activity survey data andenvironmental sampling data. The cost for a detailed characterization of the facility isincluded as part of this decommissioning estimate. This characterization would assist indetermining exactly how much remediation would be required in each plant area.
The site removable activity survey data was utilized to help determine which buildingsand indoor areas required rem'ediation. Fixed activity data was not available. The siteremovable activity survey data is shown graphically in Figures 3-1 and 3-2. Theaverage and maximum activity levels measured are shown for each building. The limitfor removable activity for natural uranium is 1,000-dpm/100 cm 2.
The site environmental sample survey data was utilized to help determine whichoutdoor areas required remediation. The site environmental sample data for soil andmud is shown graphically in Figures 3-3 and 3-4. The activity levels measured areshown for each area. For the purposes of this report it was assumed that a site-specificrelease level of 35pCi/g could be established.
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RADIOLOGICAL CONDITIONS
jAverage M Ma~dmum I7
Lab Library
HP Respirator Fit Area
Capital/CLC Engineers Office
GF2 Office Trailer
Fluorine Plant North C.R.
Fluorine Plant South C.R.
Production Foreman Office
Powrhouse Control Rm
CFx Bldg Control Rm
E.P.F. Control Rm
SF6 Control Rm
FM Bldg Control Rm
NaR U-Rec. Control Rm
KOH Control Rm
Const. Guard Bldg
Sampling Plant Lunch Rm
Laundry
Clock Alley Locker Rms
Maintenance Engineering
Maint. Forman Office
Reliability Office
Inst. Electric Foreman Office
Stores
Purchasing
Lunch Room
Eli
E•
,3A
U _______
53
I].
Iit*.1
500
4
0 100 200
Removable Activity
300 400
(dpm/100 sq. cm.)
Figure 3-1 Honeywell Uncontrolled Area Survey Data
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RADIOLOGICAL CONDITIONS
m Average m Maxirrum
FMBACn 6hRorI- --
FM Bilding 6th Foor
FMBUldng4th Floor r ---- -
FM Bulding 3r Foor- L J}!FM Idlcng nd lcRot • .. . . . .. •
Figure 3-3 Honeywell Environmental Soil Sample Data
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RADIOLOGI ALRADILOGIAL ONDITIONS
Effluent Dit1400'
Effluent Diti700'
Oak Glenn
ch @
ch @
Lake
I j
I.
Lindsay Lake
Joppa Power Plant
Brookport Dam
Plant Site Outflow
147
10
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Lamb Farm
0 2 4 6 8
Uranium Activity (pCi/g)
Figure 3-4 Honeywell Environmental Mud Sample Data
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RADIOLOGICAL CONDITIONS
3.4 Main Production Buildings
The Survey data for the Main Production Buildings (Figure 3-2) indicates that ingeneral these buildings are contaminated and will require remediation. Specifically theFeed Materials Building, the Uranium Recovery Building, the KOH Building and theSampling Plant exceeded the smear activity release levels.
3.5 Miscellaneous Production Buildings
The Survey data for the Miscellaneous Production Buildings (Figures 3-1 and 3-2)indicate that in general these building are not contaminated and will not requireextensive remediation. Based on prior history the Pond Mud's Filter Calciner Buildingis assumed to require remediation.
3.6 Drum Storage Pads & Ponds
Based on history, the Drum Storage Pad,.the KOH Mud's Storage Pad, the WasteStorage Pad, and the Ore Storage Pads 1 through 6 are assumed to require remediation.Settling Ponds #3 and #4 will also require remediation based upon data from ponds #1and #2 that were recently remediated and filled in.
3.7 Outdoor Areas, Drains & Sewers
The Discharge Ditch is contaminated and will require remediation as indicated in Figure3-4. The only other area that has significantly elevated soil activity levels is around theFeed Materials Building as indicated in Figure 3-3. Specific data is not available formost of the other areas and therefore assumptions were made based on productionactivities in the area and plant history. The Employee Parking Lot, the on site pavedroads, the four Railroad spurs, the land between two parallel property exclusion fences,the company owned land outside the fenced property, the UF6 Cylinder Storage Area,the Long Term Cylinder Storage Area, and all other land inside fenced area are assumedto mostly uncontaminated any only a small fraction of these areas will requireremediation due to localized elevated activity. The site drains and sewers are assumedto be moderately contaminated-and they will require some remediation.
3.8 Administrative Areas
The Administration Building, the Lab and Office Building, the Shop/Stores/OfficeBuilding, and the Power House are not contaminated. Radioactive materials have beenused in laboratory area and some remediation in this area will be required.
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RADIOLOGICAL CONDITIONS
3.9 Calcium Fluoride Ponds
The Calcium Flu 'oride Ponds contain calcium fluoride and some uranium. The pondsediment is a RCRA waste due to pH but there is a license exemption in place thatpermits this material to be disposed of at up to 212 pCi/g of uranium, A remediaitioinplan presented to the EPA includes remove of this material by 2020.
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ESTIMATION METHODS
4.0 ESTIMATION METHODS
The estimated cost to decommission the licensed areas at the Honeywell Facility is$99,535,489 not including the On-Site Disposal Vaults or waste disposal costs. This section ofthe cost estimate report provides an overview of the considerations and factors that influencedthe decommissioning cost estimate. Table 4-1 provides a summary of the costs associated witheach area of the facility.
There are modifying factors that significantly affect the overall cost for remediation.One of these factors is an adjustment for productivity related to personnel protectionrequirements and working temperatures. The degree of protection required dependsupon the extent of contamination and specific activities to be performed in a given area.As the level of personnel protection increases, so does the impact on individualproductivity and task duration. Adjustments were made to account for theimplementation of personnel protective measures where applicable. This estimateutilized standardized levels of personnel protection, along with the associated impacts isprovided in Table 4-2. The Productivity Factors related to these levels of personnelprotection are provided in Table 4-3 for Light Work and in Table 4-4 for Heavy Work.
Level A: The highest available level of respiratory, skin, and eyeprotection
Level B: The highest level of respiratory protection, but less skinprotection than Level A. Level B is the minimum levelrecommended for initial site entries, or for other entryconditions dealing with unknown hazards.
Level C: The same level of skin protection as Level B, but a lowerlevel of respiratory protection.
Level D Modified: Skin protection similar to or the same as Level C, withoutI respiratory protection.
Level D: Standard work uniform suitable for construction work: noI respiratory protection and minimal skin protection.
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FQTMATInIV X4V YTnnQ
Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work
Level A Level B Level C Level D Modified Level DVariables Ulm
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.. .... ... .reaks:ti . ii.ist , - :*%-Io k .... ................... ................. .............. .......... ........... K ... ...... ... .... .. I. I= ........ ...... ........... I ........ I ........ ............ ................. - , .................. ......................... .Dexterity losses are Ws* *&1:6hiiýýjebUý6..bpim*pq'4.'-p*f:ithi ..... = fi..g ........ ... d&xfi:q:ii ctorswsm . , s disco t-iplt ýý'Wcighgp e tý 6ýthk:PPEslmvi oft1w .... .. , , - .... .1 ..... - 14- .... IM& - timinq :b& it& 6f N ' - h .... . ..... ...... .......... .. ............ .... ...... ...............
or.. a PPEJrcstn4cted.liwtWng.an-d t zlmof.minaeýsacftidll- * fted, 1-c6d Ah:-:`-' -nk: 4 ,-.. ..... .... !ca iomýý elnurri y.) r ..t xepreýdnting. ý-Ayerv ýFev t part- W............... .. ...... .00 ý...... ....... .. ......Values fýrw,-.B, andC.Ai,ýji derived'by ed fib . ..... .......spongd or 046h. PPE 16 61, R '*** " - - " " ... t ........ ........ .... ..0- WO! OMISSIMOU...............author's dISCtetiOIL
........ ......................... ......... ..........................ýI wi ..................................... ....... ................................................... ....... ................... ............ : ............................ .......... i:::: 7: . ........................ ........... ........... fth ... ....... I i t he'y":, a-5 q-re' ........... -I'A fiqVs'ituatlons o fl wmDolad'e"d:::: -,:: .............. ggý... actors.- orL6-e1A-A6ifld be, wi taftow. .......... .......................... . ........................... ........ ............. ............................... ....... ...... ..............
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ESTIMATION METHODS
4.2 Radwaste Volume Estimates
The volume of radwaste requiring treatment and disposal can be a very significantmodifying factor due to the high cost for radwaste disposal. For the Honeywelldecommissioning, the cost for radwaste processing, shipping, and disposal is anticipatedto be about 73% of the total decommissioning cost. This is a much higher fraction thanis normally seen for radioactive facilities because of the large volume of contaminatedsoil, pond sediments, facilities and equipment. Radwaste volume estimates arediscussed in the following section. Table 4-5 provides an unprocessed waste volumesummary for each area of the Honeywell facility.
A significant portion of the overall decommissioning cost is generally attributed to theprocessing or burial of radioactive waste.
For many sites the material to be disposed of is first processed to the maximum extentpossible. This can result in a significant reduction in the final cost for waste disposal.Current GTSD rates were used for these calculations. However there was no benefit toincorporating volume reduction processes. For example the cost to metal melt or
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ESTIMATION METHODS
decontaminate a contaminated tank was more than the cost to cut up the tank and ship itdirectly to Envirocare of Utah for disposal at a $42.45 per cubic foot disposal rate. Thecosts to transport waste to the Envirocare of Utah disposal site are based on a transportdistance of 1985 miles, at a rate of $1.95 per mile.
4.4 Remediation Methods
The goal in choosing remediation methodologies is to select the minimum cost option toaccomplish a task. There are many factors which need to be considered when selectinga methodology such as contamination levels, degree of penetration of contaminationinto substrate material, equipment cost, support equipment costs, material and chemicalcosts, the generation of secondary waste volumes (waste in addition to the removedcontaminated material), processing rates, labor requirements, and applicability tovarious tasks. Typical decontamination processes are summarized in Table 4-6. Thistable shows the decontamination methodology used, application information, theprocess cost per square foot of area decontaminated, and the amount of secondary wastegenerated. These unit factors are applied to specific areas or equipment requiringremediation to determine the most cost-effective process.
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ESTIMATION METHODS
Table 4-6: Decontamination Methodology Comparison
Penetration Process Secondarydepth Crew Cost Waste Volume
The volume reduction processes analyzed for use are summarized in Table 4-7. Thistable shows the volume reduction methodology used, application information,transportation charges, the process cost per unit weight or volume, and the total processcost per unit volume. These unit factors are applied to specific items of equipmentrequiring disposal to determine the most cost-effective process. The waste generated atthis facility will include ventilation systems, process equipment, concrete, steel, soil andsecondary waste generated during the decontamination work such as protective clothingand materials used during manual decontamination work.
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ESTIMATION METHODS
Table 4-7: Volume Reduction Methodology Cost Information
Transport Total VR CostVR Methodology Applicability Container Type ($/Ib)
Super Compaction Dry active waste, 20 B-25 for Envirocare $7.52Ib/ft3
DisposalIncineration DAW B-25 for Envirocare $5.88
Disposal
Metal Melt' Metal Custom $0.84
Metal Decon Metal Custom $0.94
Survey & Release 2 Dry Active Waste 55 Gal Drum $1.53
i. . n, cYcks ft proomwd nater so fthm is no cien wato for disposa].2 Dispose is Imai b-.ud in omt
4.6 Unit Costs
There are a number of.unit factors used to generate this cost estimate. They are listedhere so project costs can be updated when required and the effects of changing unitcosts can be evaluated.
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ESTIMATION METHODS
Table 4-8: Decommissioning Estimate Selected Unit Cost Factors
Unit Cost Factor Unit Cost Rate Units
Radioactive Waste Disposal at Envirocare of Utah *$42.45 cubic foot
Waste Transportation to Envirocare of Utah $1.95 mile
Transportation Distance to Envirocare of Utah 1,985 miles
B-25 Waste Disposal Container Cost $460.00 each
Management and Supervision $91.59 hour
Engineer $67.16 hour
HP Supervisor $67.16 hour
Laborer Foreman $38.15 hour
Admin Assistant $26.91 hour
Instrument Technician $50.08 hour
HP Technician $44.67 hour
Laborer $25.46 hour
Illinois sales tax 6.25%
Fee 15%
4.7 Final Surveys
Final survey cost estimates are based on the methodology presented in Draft Regulatory GuideDG-4006, Demonstrating Compliance With the Radiological Criteria for License Termination(August 1998) (Ref 6.8). This methodology requires the determination of the number of samplepoints for the various areas being surveyed and the type of survey being performed. The time toperform each of these surveys is determined, and the product of these two items is the labor timeto perform the surveys. Equipment and material cost to perform the surveys is added along withstaff support costs to determine a total cost. The survey requirements are based on NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Ref 6.7). Aspreadsheet was developed which incorporates facility dimensions, labor rates and support costratios to estimate the final survey cost. Facility survey labor estimate is summarized inAppendix A-5 and the open land and miscellaneous area survey labor estimate is summarized inAppendix A-6.
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DESCRIPTION OF THE DECOMMISSIONING SCENARIO
5.0 DESCRIPTION OF THE DECOMMISSIONING SCENARIO
Decommissioning of the Honeywell Facility requires that residual radioactive materialsbe removed from the site to allow removal of the decommissioned facilities from theirIllinois Radioactive Materials license. For the purposes of this cost estimate, once theHoneywell Facility has been remediated to release limits, no further decontamination ordemolition is required. Upon acceptance of the final radiological survey report andtermination of licenses by the NRC, no restrictions will be imposed upon the site due toits prior use as a radioactive material processing facility. Numerous non-radioactivestructures will remain standing for an undefined period of time. No non-radioactivebuildings or structure will have their structural soundness compromised by thedecommissioning activities.
5.1 Characterization Survey
A characterization survey will be conducted in all areas of the facility that have ahistory of radioactive materials use or storage. The results of the survey will be used todetermine -the extent of remediation required prior to release of these areas forunrestricted use. Characterization surveys are normally performed in such a mannerthat if no contamination is found, the results may be used as, or to augment final surveydata.
5.2 Remediation
Following the removal of all source materials and waste, it is assumed that noremediation will be required in administrative areas. The following is a brief summaryof the anticipated remediation activities, with applicable assumptions and bases, in theremaining areas. The remediation activities are summarized in Table 5-1 below.
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DESCRIPTION OF THE DECOMMISSIONING SCENARIO
Table 5-1: Planned Remediation Activities
Ara Bidngo rmRemedisition Activities jMain Production Buildings
FM Building All equipment and structure will be removed from the site. Basement 8"concrete walls and 6" concrete floor slab will be removed. Soil 12" deepbelow floor slab will be removed and a 50' wide by 12" deep buffer zoneof soil will be removed from around the building.
KOH Mud's Building, All equipment and structure will be removed from the site. 1/2" ofSodium Removal Building, concrete will be removed from the floor slabs and they will be left inU Recovery Building, & place.Sample Plant BuildingFM Building South Pad All equipment will be removed from the site. 6" concrete floor slabs willEast & FM Building South be removed, 18"x24" footings will be removed, and 2'x3' equipmentPad West footings will be removed. Soil 12" deep below floor slabs will be removed.
Miscellaneous Production BuildingsCalciner Building All equipment and structure will be removed from the site. 1/2" of
_ concrete will be removed from the floor slab and it will be left in place.Ore Storage Bldg., Bed Decontaminate buildings and leave them in place. 1/2" of concrete will beMaterials Filter Fines removed from the floor slabs and they will be left in place.Bldg., Cylinder WashBldg., Hazardous WasteStorage Bldg., & DrumCrusher Bldg.Miscellaneous Waste BM/FF Bldg. LLRW Trash in drums -338 tons, LLRW Trash in B-25
boxes - 227 tons, LLRW Trash in Blue boxes - 27 tons, Waste PadMaterial-1.2 tons, "Scrap Metals Pad - 4,830 tons, New Scrap Metal - 73tons, 16*x16"x&" Metals Pad Cubes - 22 tons, Imhoff Sludge in Crusher
_Building - 73 ton, & Outfall Material in Crusher Building S. I ton.Drum Storage Pads & Ponds
Ore Storage pads 1 through 1/2" of concrete will be removed from the concrete pads and they will be5, Drum Storage Pad, left in place.Waste Storage PadSettling Ponds #3 and #4 Excavate 3' from pond bottoms, backfill ponds with 9' thick clay.
Outdoor Areas, Drains & SewersDrainage Ditch to River Excavate 6'wide by 3' deep by 1.600' long expanse along ditch, backfill
_onds with 5' thick clay fill.Drain & Sewer Pipe Excavate and remove 3'x5'x2000' of drain pipe and 3Yx5'xx000' of sewerpipe, remove 8 manholes/catch basins, and backfill excavations.Drain & Sewer Pipe Excavate and remove 500' of embedded drain and sewer pipe.Site Soil Areas Excavate 2 acres, 12' deep and backfill the excavations with clay.
Administrative Areas Removeand replace roofing material at Laundry Area over a 20'x50' areaCalcium Fluoride Ponds Excavate and remove 50,000 tons of material from the sediment ponds andI ship off site for disposal, backfill ponds with clay fill
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DESCRIPTION OF THE DECOMMISSIONING SCENARIO
5.2.1 Main Production Buildings
The entire Feed Material Building and structure, the concrete slab, the buildingpads, 12 inches of soil from under the slab, and all of the equipment wasconsidered to be contaminated and would need to be demolished and removedfrom the site for processing or disposal at a licensed radioactive waste disposalfacility.
The Ion Exchange Building, the Sodium Removal Building, the KOH Mud'sBuilding, the Uranium Recovery Building, and the Sample Plant will be treatedin a similar manner. The structures and all of the equipment was considered tobe contaminated and would need to be demolished and removed from the sitefor processing or* disposal at a licensed radioactive waste disposal facility. Thebuilding concrete slabs will be left in place after being decontaminated usingsurface removal methods.
5.2.2 Miscellaneous Production Buildings
The Ore Storage Building, the Bed Material Filter Fines Building, the PondMud's Filter Calciner Building, the Cylinder Wash Building, the Drum CrusherBuilding are considered to be contaminated and will be treated accordingly. ThePond Mud's and Filter Calciner structures, and all of the equipment wasconsidered to be contaminated and would need to be demolished and removedfrom the site for processing or disposal at a licensed radioactive waste disposalfacility. The Ore Storage Building, the Bed Material Filter Fines Building, theCylinder Wash Building, and the Drum Crusher Building will bedecontaminated and left in place. Building concrete slabs will be left in placeafter being decontaminated using surface removal methods.
The GF2 Plant Building, the South GF2 Plant, the SF6/IF5/SbF5 Building, theLiquid Fluorine Facility, the Liquid Nitrogen Facility, and the Calcium FluorideBuilding do not require remediation.
5.2.3 Drum Storage Pads & Ponds
The five (5) Ore Storage Pads, the KOH Muds Storage Pad, and the WasteStorage Pad are considered to be contaminated and will be treated accordingly.The concrete slabs will be will be left in place after being decontaminated usingsurface removal methods.
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DESCRIPTION OF THE DECOMMISSIONING SCENARIO
The Settling Ponds #3 and #4 are contaminated and will be remediated byremoving the pond sediments, pond liner, and contaminated soil under the pondsfor disposal at a licensed radioactive waste disposal facility.
5.2.4 Outdoor Areas, Drains & Sewers
The Employee Parking Lot, the paved roads on site, the Railroad spurs, the landbetween two parallel property exclusion fences, and the company owned landoutside the fenced property do not require remediation.
The sanitary sewer and site drain system are contaminated and will beremediated by removing the drain pipes and any contaminated soil surroundingthe drains for disposal at a licensed radioactive waste disposal facility.
The Discharge Ditch to River is contaminated and will be remediated byremoving the ditch sediments and surrounding contaminated soil for disposal ata licensed radioactive waste disposal facility.
The UF6 Cylinder Storage Area, the Long Term Cylinder Storage Area areanticipated to be slightly contaminated and some soil removal will be requiredwith the removed soil shipped for disposal at a licensed radioactive wastedisposal facility.
The graveled area to the east of the Hazardous West Storage Building waspreviously used for uranium storage and in anticipated to be contaminated. Thisarea will require that some soil be removed and shipped for disposal at alicensed radioactive waste disposal facility.
There is a small, contaminated soil pile by the employee parking lot. This soilwill be removed and shipped for disposal at a licensed radioactive wastedisposal facility.
The land area to the southeast of the Ore Storage Pads Hazardous West StorageBuilding was previously used for uranium storage and in anticipated to becontaminated. This area will require that some soil be removed and shipped fordisposal at a licensed radioactive waste disposal facility.
5.2.5 Administrative Areas
The Administration Building, the Lab and Office Building, theShop/Stores/Office Building, and the Power House do not require remediationexcept for the roof above the laundry in the Administration Building. The
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DESCRIPTION OF THE DECOMMISSIONING SCENARIO
roofing material is expected to be contaminated and it will be removed andshipped for disposal at a licensed radioactive waste disposal facility.
5.2.6 Calcium Fluoride Ponds
Calcium Fluoride Ponds "A" through "E" are contaminated with radioactive andhazardous materials and they will be remediated by removing the pondsediments, pond liner, and contaminated soil under the ponds for disposal at alicensed waste disposal facility.
5.3 License Termination Surveys
License termination surveys, or final release surveys, will be performed in all areas ofthe site using the guidance provided in NUREG-1575, Multi-Agency Radiation Surveyand Site Investigation Manual (MARSSIM), (December 1997). The surveys will beperformed in accordance with specifically developed plans and procedures.
5.3.1 Survey Instrumentation
Selection and use of instrumentation will ensure sensitivities are sufficient todetect the identified nuclides at the minimum detection requirements. A list oftypical final survey instrumentation, radiation detected, and calibration sourcesare provided in Table 5-2.
Table 5-2: Typical Final Survey Instrumentation
Ludlum Model 2350/43-68 Gas-flow proportional Alpha or beta "'Tc () Direct measurements(100rcm 2 ) "Th () and smear counting
Ludlum Model 2350/44-2 Nal scintillator Gamma '"Cs Gamma exposure rateLudlum Model 2350/44-40 Shielded GM Beta 9'Tc () Direct measurements
(15.5cm 2)Ludlum Model 2350/43-5 ZnS scintillator Alpha MTh () Direct measurementsTennelec Model LB5100- ZnS scintillator Alpha/Beta 11 () Smear counting2080 __c () _
Gamma Spectroscopy HPGe Gamma Mixed Nuclide identificationSystem Gamma and quantification
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REFERENCES
6.0 REFERENCES
6-1 NRC Policy and Guidance Directive FC 83-23, Guidelines for Decontamination ofFacilities and Equipment Prior to Release for Unrestricted Use or Termination ofByproduct, Source, or Special Nuclear Material Licenses.
6-2 Code of Federal Regulations, 10 CFR 30, Rules of General Applicability to DomesticLicensing of Byproduct Material
6-3 NRC Regulatory Guide 3.66, Standard Format and Content of Financial AssuranceMechanisms Required for Decommissioning Under 10 CFR Parts 30, 40, 70 and 72.
6-4 Means Building Construction Cost Data, 58th Annual Edition, 2000, R.A. MeansCompany, Inc.
6-5 NUREG/CR-1756, Technology Safety and Costs of Decommissioning Reference NuclearResearch and Test Reactors, March 1982
6-6 NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual(MARSSIM), (December 1997)
6-7 NRC Draft Regulatory Guide DG-4006, Demonstrating Compliance with the RadiologicalCriteria for License Termination (including the D&D code), August 1998
6-8 NRC, Final Rule on Radiological Criteria for License Termination, the Federal Register(62 FR 39058)
6-9 NRC, Supplemental Information on the Implementation of the Final Rule on RadiologicalCriteria for License Termination, the Federal Register (63 FR 64132, 11/18/98)
6-10 NRC, Supplemental Information on the Implementation of the Final Rule on RadiologicalCriteria for License Termination, the Federal Register (64 FR 68395, 12/7/99)
* Notes:I Decon Waste Volume: This is the volume of waste generated directly by a decontamination
process (this Includes such Items blasting grit, treated chemicals, etc.).2 Generated Waste Volume: This is the volume of protective clothing waste generated by all operations on site and
I Main Production Buildings 993.1 15.0 2995.52 Miscellaneous Production Buildings 103.3 1.6 311.53 Drum Storage Pads and Ponds 240.0 3.6 724.04 Outdoor Areas, Drains & Sewers 315.9 4.8 952.95 Administrative Areas 1.3 0.0 4.06 Calcium Fluoride Ponds 1.2 0.0 3.6
TOTALS: 1,655.0 26.0 4,992.0
Notes:I The number of waste shipments Is rounded up to next full shipment.
Estimated waste loading operator time :Estimated HP Tech time per rad or mixed waste load:Estimated HP shipper time per rad or mixed waste load:Estimated railroad shipment limit:
1 Main Production Buildings 0.0 02 Miscellaneous Production Buildings 0.0 03 Drum Storage Pads and Ponds 0.0 04 Outdoor Areas, Drains & Sewers 0.0 05 Administrative Areas 0.0 06 Calcium Fluoride Ponds 0.0 0
0.0 00.0 00.0 00.0 00.0 00.0 0
TOTALS: 0.0 $0 0"Notes:
I The number of waste shipments Is rounded up to next full shipment.
88 hr per load88 hr per load16 hr per load66 20' Rolloff
CAWy - , g-n- a fted --a -b I e-4- -. wb 3 Pg fi0 6- .......... -.-Page 4 of 4 . ............ WJ-u-rW, M A ýF46 M
APPENDIX A
APPENDIX A- 5 Building Area Survey Cost Estimate
A-5 Revision 0
UNAFFECTED BUILDING AREA SURVEYHoneYWell MetFo O alS FacIlItyTable A-5
ofro Suwvf Emm mENTE ENTE cmos ENTEsnLow molue ENTER ENTER PACKAGAE AMA AREA AREA _______ PLOORt* U.tLLS" ENTER ROAR. U.WALJ.. SIVBT DRCT
PMII sBw.Dam BOOM AREA M ~ WQTH LENGTH U)GAOT L WALL CER.DAO EAXv. LWALL CIS.W RO TOAL PAO(AM "MRWLOC HAMW MNflwER DEECRFTIOU ? BEOW BELOW BELOW ROM TOTAL S*VEY SURVEY %k@0W" =.VB IUWY LY rM L~RPW IAS~
CODE BELOW BELOW BELOW Avom an ah on I.% .1- COOFT CC"l A..l -.r -OT !!RTPTR A.
TOTALS yl."41 "t 1.025 227 2.02S I? 475
Pý~ I d I P~g. I A AL.ASMc 035 ru-
APPENDIX A
APPENDIX A- 6 Outdoor Area Survey Labor Summary
A-6 Revision 0
AFFECTED BUILDING AREA SURVEYTable A-6 Honeywell Metropolis Faclifty
OERSVEY ENTER ENTER ENTER ENTER ENTERr GAIABELOW ETER ENTER MDETER PACKAGE AREA AREA AREA FLOOR. U. WALL+ fDETER FLOOR. MM WALL SURMVEY wM.Y DRECTOPTN. BULDN ROOM AREA REORD WIDTH LENGTH HEIGHT L WALL. CEILIPG =, L WALL L WAL. CIlUW RI. PA PAGE,*IJMV
LOC NAME ANUMBER DESCRIPTION ? BELOW BELOW BELOW SURVEY SURVEY sWC*W B.5wY W wET W M aY .RWY 2W PRV LAsmCODE BELOW BELOW BELOW (YomE mlfl mI ml CODE CODE 1es5h, BLoCs P ERAm PACTI .- h.- -1 ,,
C A" fE P t O .p- 'o ,
UNAFFECTED OPEN LAND UNPAVED AREA SURVEYHoneYwell Metropolis FacilityTable A-6
DA1~
OPTIOMdALOC
eforSURFACETYPES
RNsAREA
CESCRFTIMMkElow
SUVE, OFjes ENTERPACKAGE AREA AREAREWO WIDTH LENGTH
? BELOW mo.w MR%%Y f1 ft- E- SW SW. 11" 0E
RandomIehor O..
Su PACA BRL Bowl
TOTALS 1,564 1671 1.7 il7 2.11 Ill 75.6 27- 8 06.
....... .W ' .. fP..... .... ....oý", 03*%"* -**
UNAFFECTED OPEN LAND PAVED AREA SURVEYS Honavwmfl Mefronolls FacilltyYk3O Aa
!Table A-6 Honevwell Metro olls Facilltv
BELOW ENTRaOPT11ONL MLMFAD
LOC TYPOCODE BELOW
EoNTfAREA
oEsmroBELOW
SURVEYPACKAE
REORD
flyW1
ENTERt ofDTAREA AREAWIDTH LENGTH woe wf10 or woeBELOW BELOW W. bdl. 9,o-
MI MRI ý S-., Sc
ENTER
.f Em-., XX5WyEmRM. RM. Met"
Rd,ý UOWY 10%S-V~ PA•CKA05 SURVEY
S0ý PRE L800(
0 33 4 4
033 4 44
033 4 44
1.0 12 1.TOTALS 9 19 0.3 9 0.1 3
C 'ay 30030301o1011I 0'w a.01S.0.0030.P- I . OcJuO" O3 5,; ý
AFFECTED UNPAVED OPEN LAND AREA SURVEYTable A-6
Hone ell Metro lis FacilibiENTERBELOW
OPTIONALLOC
CODE
ENTERSURFACE
TYPESBELOW
ENTERAREA
DESCRIPTIONRELOWn
SURVEY ENTER ENTERPACKAGE AREA AREA
REORD WIDTH LENGTH? BELOW BELOW
(Y/N1 (ft) 1111
SUBSURFACEACTIVITY
DEPTHIfti
ENTERRandom
Sketch$Isechl
SRVEY DIRECTS.., ACKAG SUM
er PREP LABOR
TOTALS: a 24 3-979
C~Iy Ooowwofs~obbk OEW Eqg I of I 05 ~Wý, 6. pm
AFFECTED PAVED OUTDOOR AREA SURVEYHoneYwell Metropolis FacilityTable A-&
~~NJ. ~ OA AURVW M4 4 00 AL S~*VENUMBER PIAL ALTERNATE IEiWUgN1' NQW.UENITEMS PROJECT mohTMVy LEWS LEA3E
REQUIRED D4JRAIION DURAION COST COST
I l N2 &320
y Y 064 SM
N I 1Z206
1 Y 1162 10
TOA.E UNT 0ESECST $19784 26
1-10, P~q.IS N-1 #, 0U0 Pt.
APPENDIX A
APPENDIX A- 10 Demolition Estimate
A-10 Revision 0
.Appendix A-10, Demolition Estimate
TASK BASED DEMOUTON COSTS42M Hazardous & Tosdc Waste Producttyty Fador Level C. Heavy WoM TO - •5'f
Pewc.l4 Labor Cost 65.00% MATERIAL LABOR EOL6PMENT MATERIAL LABOR EOtAPM6ITLOG m Average Noal Labor Rage UN14SIT UNIT UNIT TOTAL TOTAL TOTAL TOTALCOOE N0. AREA QUANITY UNIT PRCE PRICE PRICE PRICE PRCE PRICE PRICE
I FM BW.bWD-WNI 370,440 CF $.09 $0.10 387.86 $11,200 $106,681t FM rt r F ow Slab 0 6146 3F $324 10.00 $41 479 $7,300 $48,81I FM 6ddin r Co0,lee w•el Dw-O. 301 LF $8174 $1.08 $8r406 $1r136 $7,S4!I Ped l'SoIM o R ewe 191 CY .0 5.75 Z310 o $20; 8,010I FM 94 s9 W BUR V W Ramoed1 868 CY $5.09 $.7 0704 $08976 $16i,9
KOMi De ek O-6awm 608,00 CF $0.01 $0.10 $109804 $14,250 P5.1FM Bkclf Smh PW E.t0r Flow Omb wcheo 3,08 SF $3.31 000m $31,346 S6.64 s.m ,0CFMOWI f Sco,* Pad KE.l 19v4* Coeseal Fo*eo eleon 262 LF 06.70 03.06 93422 S2.316 10730FM S 0 So P4 Pad E &2 EqE . CoeoFt D-en oloe 202 LF $.15 $S.SO $4, $3,300 ISI
I FM 8" 3. Pad EE'.9Sol Rftmel 144 CY $6.01 $6.75 $1.748 $1,71 $7711I FM O Son UL Pad 90.0,S' FIo, Deae 38544 SF _S338 $0.60 $20,733 S10011 s3m21.I FM 60., PaId W0tt Iro24° C..af F OFemeDo0 240 LF ,5.70 $3.46 $3,269 $2,208 06ý4641 FM Bo Ss Pod We9 27.W Eg*P Cweoft Fo=w D.ebe 240 LF $8.16 $6.76 P4666 $3,290 $7 941
, FM So Pod VVW* "16Sol Roow 132 CY $8.01 6.75 1,600 14607 ,3,407I 8.d86. R.eme &W O.,eeeA. 033240 CF $0.01 $0.10 $16.9w $22,200 $39104
TASK BASED OEMOLUTON COSTSM Hazwrdous A ToXk Waste Prodmlvlvt Faror. Level C. Heaw Worlk 70 UMF
Percent Labor Cos 65.00% MATERIAL LABOR EOU.P6ENT MATERIAL LABOR EOUIPMENTLOC a Avenage Hourly Labor Ride ;, • . •• UNIT WNT UWT TOTAL TOTAL TOTAL TOTALcoaE 110 AREA UAI WET PRICE PRICE PRICE PRICE PRICE PRICE PRICE_
steS..- Ty" M-75 0.7 1t $462.81 S776 SO $77Behe 0*4,.. O-ee Sly UF702 01 on $452.61 $63 so $6B .,.l,.h .~4 064 ANsw $462.81 $62 soS0-1. 2.1 n $42.61 $20 00 $26IOei1 .6.612Sd_2 Ion 037030 $11s06 $0 11i0ULIF C Cnd a 30 n $452,61 $32247 $s 03.24UF4 OD-e 0,...•. 2.1 ton $462.61 $2,260 so $2.26
, A M . 0.1 AN. 6410 13$ 1$- 6 8i11 Nto $462.51 $102391 $0 $10.351 LI.6 .W"d I'. AN $462.61 $1 391 $0 t010'0
I P-non,.l Fs.,, Co, Ow Ab... 03 An $42.41 $291 $0 0201 10C000•6•M.Uemlld. ILnA- 1.0 $462.81 $11103 so $1,10:I 2.0006C -Mo l So.d R6 A.,. 0.2 AN $452.61 $167 $0 $161 4,,000 C.9 -M . "A" S60~ .a. Al- 0.1 An $452.61 "04 $10 ;,
9,60010 MW.4 ed. O.E. D0vot. R.6.6, 03 ANe $462.61 $252 so SU5,5 4so0006Cp. 1Mo11 .-*A'0.S.6A- 0.1 AN. $462.61 $117 so p1
4,0006 Cap -*Mo0r •l.R A.. .V w 02 An $462.61 $244 $0 $24,62 V- Pup 03 An $452`1 $326 $0 $s12
0.0• A $462.61 $31 $0 1Cb Ak III&- -.V,*g 00 Aon $452-61 ;3 so $31I Cl. Pp.a,.. B4- 03 AN $452.01 6212 $0 $31.R- 123 Clea A.i. 0 P-9 0.0 AN $452.61 $30 so S3
11a wa,160,,,,. 02 Aon $402.01 100O0 so SI 000FM BFM EWL Fm 11.0 AN $37030 $9,711 $0 $01711..bVera.,, 0.5 AN $46241 $526 $32
I E*,a 'm-DF...0.W 06 AN $462.61 01,000 $0 0000~STo-. Vea.,, Pup- 2d Fl- 03 AN $452.61 $226 so $325E.4M F .- Soulh Ceram 0CA 1452.61 $1,000 $) $1,000E*..M F. . Wet 02 Aon $462.61 $1000 $0 $1,000E . l4FM - Wet- Are- 0.8 ton $462.61 101000 $0 $1S000B.,..-d E.d F.o- ho.I 0.9 tN $45261 $1000 $0 $1,000&W H&,. k6 Air CE;ý F- 73 AN$462.41 $7660 s0 $7.100Ufn - C-.Ail1 06 AN $452.11 $444 so $044
I*- Fi. -S-P,$. 0.9 AN $402.01 $1,000 $0 $1000Re. Vs 8I 0.6 $452.01 01,000 so $1000vWiw Coal-. 02 AN $45241 $1S so $100I Pota.bel.Akior ond 0.7 A $452.41 $781 o $7601I R6123 5 W 23.5 AN $370.30 $20,762 $0 $20707
R-123 l 11.9 AN $37030 $10,478 so 0101476R-134. LPOk UI. AN $370.30 10,470 $0 $10,476R1e 6 S 0.7 t. $462.61 70$ 0$70R-123 Hig E0f. Pur E Ld 0.2 A $S42.1 $225 s $22W 5 -40,6Awo 3.2 AN $462.61 $53499 $0 $3469
3.2 AN $402`.1 $3,406 NO 3,406O.L *6 32 AN $452.61 $53498 $0 3,46
I C "'**. 52 A $462.61 t.6246$ $5406317 Pb. T- R.at 0A $462-61 $438 so $432O"t 04 $452.61 $469 so $4601 . 0.4 A $4C211 $40 $0 $409O-M 0A tAN $452.61 $469 so $406O -d. - Id IA AN $402.61 $1s000 $0 $100S46h Board. NE 0.7 AN $452.00 $760 $0 $7.0swhBoad. E - Ca 0.7 AN $452.61 $760 $0 $7.0&MBo rd d. E - S 0.6 An $452.61 $653 so 650
6g B.o 82 AN $462.61 $8,060 so $S6e4Low s• . i.9 .oN $402.61 $7,416 $0 $7,41SO 2 Swrp" Vc.. Puny Ak.mi,. Too. 0.6 AN $462.01 $"61 so $051#1 1 V.. lPw Ah. To- 01 AN $462.,61 61 $0 $6010 2 P--" Fod N w 19.2 AN $370-30 $160g35 $0 $16092I t1 Pvd F.d H6pp.2 $270t30 0062$1 8 $0 $086902TeO y WTd 5W.6 AN $462.01 ,52 0 $3,63293 -- ,. Feed H,",2 AN $37030 $1659n $0 000039
T6. 1, Ch. Addft" PW 0.0 AN2 $4021 $49 $0 $40Kok Q Put 03 AN $46•211 $261 0 210R-134Aa. euw, 1.6 AN $452.61 $10572 $0 $1.672R-1.4.1 o 0.0 AN $452.61 01,079 so $100790 0h Cy.w. Sp:de 0.0 N 4.0i $0 so $00O UFO SS .•5.0 AoN $4620,31 so $0.301
P'loP- T-. R..oot, 0.1 An $4S2.61 $103 $1026RQ V6- D-s Col. 0.0 AN $46211 031 so $31R0 6 Vad.e-DoOlOfL ,.6B.mL• 0.0 AN $452A1$ $34 $0 $3RO6 Va"W *A* 8W Wt. D0.0 AN $4162.0 $291 so $2
,.Vds .. M-410 0r6 AN0 $462.01 $21 $0 $021 6 y V.1- Bd F-s M Do.- v. 0.0 AN S45261 $31 $0 $31Rat V&8% " Bo6 d F DOis 0.0 ton $452.01 620 to $31DI, D06h. WI N .44 OF-4S. 0.0 AN $W42.61 $611 so $516CMW.A, EB.. 0i.. So-w 02 AN S4628 1 $219 so 020
I Pr* Fed Hopper Fod. S-,ey 0.7 AN $462SI $711 so $710I Ur.ndF F-d 4MStera 1S ANA $45201 $1.474 so 01.47
TASK BASED DEMOLITON COSTS4n% Hazardous & Toxic Waste Producflvky Fador, Level C. Hearv Work. 70-85
Pmwcas Labor Cos 65.00% MATERIAL LABOR EOUIPUG4T MATERLAL LABOR EOUPMENT':Average Howrl Labor Rate g :: T WNT UIT TOTAL TOTAL TOTAL TOTALCO AREA QUANTITY WAIT P FUCB PACE PRCE PR=C Pri PRIC
Ch4" Te 24 16e $462.61 $2,64 $0 $2,64dt Ak,' A 2A4 4 $462A S25,$44 $0 S2,6t 94 N.L WFer 0J4 Io, $452.61 $031 $0I SO Tw OEFf 04 W. $462.61 $831 $8311 60 Top W Few 0,0 U4 $452.61 $t $0so
0 1 68 &.0e W4 Few, 0J 1 $452.61 $831 so $6311 Wddw..d.: 0.2 14 $452.01 $209 $0 5201 Weld.e. Ide 0.2 b6 $4S241 $200 $011 HIA@ -. ColTr E-444-tASe. 140 14 $462-41 $106c to $10011 H.o,-.. -C Tv E-413-2A S-. 1.0 t1o $452.66 $11059 so $1,061tHot • -Cold Trp 64t1-tA T.. 1.0 14 f/2.611• 1,060 ¢ $1 061I 6t 0. I 1.0 ft. $462.41 $1060 $0 $1,008
1 640 8-- CodM Yn - E-412.2A Tel 1.0 In 452.61 $106S $s $106I HM Se. Co Trip - E-447-.1 0Sa. 1 A 5462. 11.06 1$06$ 1I Ha•w l CoCld Trp E-446-26 S0 . 140 W4 $452A1 $1t060 so $1,066I H O•-a. Cold Try- E-472-1 T,6 1.0 1- $462.41 $1,060 so $1,06I H1 6- . Cad Tray • E-473-20 T.t 1A W. $462.61 $1,069 $0 $1.06
H Her B 1.0 Io S462.81 $1.060 so $10'I H.1 Bw - Co Trp - E-41 1.0 ton $452.61 $1 06 $0 $1,06it H610.,ColdTray602 1.0 14. S2A1 $1060$ $16061I MW - Co..Cld Tn - E-403 1.0 6, $462.81 $1,060 so $1r066I PabbleHaol..6MhIAE.L 0.0 ton $462.01 $1M $8 $60
I HM al.6 O,.0 AA & AS Wl F01 0.1 t4 $452.61 Sal so S6140000 ohi & TI" O- 93 W2 ft 0.1 14 $462.61 $79 so $7010000. HoW. ROWyVa. Shwaga 0,0.4 14 $462.61 $40 $0 $481 1000 .CaPb. HOW 0.0 1n $462.61 US $8 $461006 cap- . Hw 0.0 ton 1452.6$ $46 $ $460 200000 M.,.O - 0 Cold T 20 Tot 04 ,n $452.61 $1005 $8 $10 O
I 20,0000 M-.- Ovn COd Trap 2A & 1B Sec. 1.6 4 $452.61 $$1,670 so $106701 20,00 Moo-C*d Trap MA S & 2A Tw. 1.6 W4 $452.61 $1,679 so $106761 I 11.a000 .al. -Over W . OW A4 0& t14 $452.61 $300 $200
S70000 M1 *x - Oo WH FR-•84LA 02 ton $452.01 $266 so $2661 6,00006M-o.,od - 0- W Ffto, 02 14, $452.01 $222 so $222
1,0000 o0- W A OiAS 0.1 14 $452461 $139 $0 $1i9
1,000I O ol-*OA'G.A- 0.1 ton $452.61 $132 $ $MeI MO-4 1 Mal. -0-I C-4 19) Me Fed E.ý, 0.2 b.n $452.61 $160 so $1I61 600-4201 r00O M-.0- RO V.. 9,Ares 0.1 t14 $4S2.61 $03 so $931 V m Pa$ 0.1 ton $452.01 $72 $0 $72$ 1 " Re,,clo Co.6 Ak ow 0.2 1$ W2.61 0$76 $0 76$ Pke.,Co0.2 t4$ $4524U 1 $375 $8 $3751 Ea.ad Fan - 3o.,h Med. W A- 0. t1o $4.62.61 $tI000 so $ 000$i E4, d F,,,V.9W WV.1 - , W A ton S45241 64,02$00$ 1,060ot $ E Fan 14 W. 1462.61 . $ 000 $8 $2000I ., .1 Fen 0.6 b14 $462.61 $31 so 631
IF W JW l * o. b.l. - West 0.1 Ion $452.61 $04 so $941 -W W S- .y Jet Scrnba. EW 0.1 w, 1452.61 $94 $8 $94$ *F Reducawo Air Ck Fe, Fh. W4 $452.61 $0160 $810I Ed-at Fam 0.0 bon $42.61 $1 000 $8 $ $60I Was. Coa., 0,0 tn $45211 $45 so $45I 6-402 A R•t•"W * Swfic. Cobt. 0.3 ton $45241 $80.47 $8 $80,47I R400W "Akda. 0.3 14 $452.61 $09047 $0 $0.947
RoS- R.I.. s- 0.1 14, $452A1 W-4 $8 $84I E*6.64 0.dad Ca. 5;2 (F41$) 0.1 14 6452481 Sa1 so Sol
I F.0 Fan .624) 0.A I4n $452.61 $84 $8 $041 Ea.. Fan 039 -0.1 14 $452.61 $84 $4 $84S E.,- Fan (P-) 0.1 . $46241 $84 $ 0O41 3,616 0I Me 10.2 14, $452.61 $10,038 $8 $1 0091 6Ao Cwanm COr M 42 n 646S2.61 S4.500 so $4,000I In Co p.per(-) 1.4 e.. 1452A41 $10lo so $1 04I *AW R.dot Fe F- Ho - 0.1 i4 $452.61 $103 so $102t U2Caex. *2C- So (E- a Cn. 1.9 t4n $452.61 S1,969 $8 $51.
I 1E FtA 8,,l Tat 0.6 6M $462.01 $817 to $897I L 7. & 6"Tark 5.1 14, $462.61 $85622 $ $0,722S -1 r Rod1 kMet Fl-eps 0,3 ton $452.6$ 0221 $" $331
t 23 Com. H -P . Weal I A ton $465241 $10, so $,091 Vlblo. . 9 W. Od6 Da'at Co.. Hl . (E) 0.0 t1n $452.61 $7 $0 $7I ' .1 a 1 W.1 O6,4dd. Dod Cxl Hp f 00 t14 $452.91 $7 so $7
.2 ~2 0 6.0 D0 , Coo. Hop. Cx u 0.0 b $452.01 $7 0$7-2 VOW O.. 4. C.I. aIa.M 0.. 0 ton $452461 $7 $H
Il~b 604 FltawA *1F4 Dihd.ILb. 0.0 t. 14524$ $7 so I7I Vbta- W Fib,"A. fF.4071 TO LW. 0.0 4, $452.61 $7 $0 $7
VbI -W. FIewA3 C-41$ O. d, 1.8n. 0.0 1, $452.61 $7 $s $7t V tw rW Flaw *Ar (F-443) DOich Lne 0.0 t1 $452.01 $7 so $7I Vb. "UM P,. D.0C4l -(F42M Hw. 0.0 t. $452.41 $7 $8 $7I S0rWA- A2 PA. FP1,, FIta (F-432 0.0 t. $45261 $7 so $7
TASK WAED DEMOLgTO COSTSin HAazudOUS A Toxk Wagte Productvity Factor Layll C. Heavy WOIL' 7U . S5*F
Pwtut Labor Cost 66.00% IATERLAL LABOR EOUIPMET MAXTERIAJ. LABOR EQUIPMENTAverag Hourly Labor Rate uw UNIT tUPT TOTAL TOTAL TOTAL
ARM QUANTITY UNIT PRICE PRICE PRICE P15CE PRICE BELOC 14 TOTAL
I
I
....... ... o ~ I. k .P .~g -- ....... IM J.O
........... . Pug. 7 o( g OW-,00,O 04:13 IPM
Appendix A-1 0, Demolition Estimate.. P•.. ....
TASK BASED DEMOUTON COSTSi hazowftu & Toxic Wast. Pmducllvt factor Level C. Heavy Work, 70 - 85?F
Port,,ALbOr Cost 0&.00% IMTERLAL LABOR EoL0PU6NT MATERIAL LASOR EOLUIMPI40TLOC vM AvwnV. Hourly Labor Rat. u we UWu 66T TOTAL TOTAL TOTALcowC up AREA QUANTITY UWT PRICE PM=E POCE PUCE PIUC PUCE
I H-AB Fft.~ 0.0 0. 0462.01 $42 toI WW dM& A21 HF .. 0.0 6.n $462.91 $42 $0I HW-I.W R.&xW9JU.. 0.0 lo. 5462.61 $42 soI Md- A2 I'M& SU FUooFilm 0.0 Ion $42.01 P42 $0
-1 od 1BU Flogon Fiber& AdHF F 010 0. 34S2.81 042 $01 WM -Ash Dud Ca. 0.004 $452.61 $42 so
.. .. .. .... .. ........ -- -CýWy Do-wftW*"l.OPW Palge $ of C~y oo.,.onole*OI 8W ~o. .1006-J-0.0. 04.13 PU
Appendix A-10, Demolition Estimate
TASK BASED DEMOLUTON COSTSUS Ha•ardouw & Toxic Waste Procductlvtv Factor. Level C. Heavy Wodt 10 85EY
PW'Cli Labor Cost $5.00% MATERIAL LABOR EQUIPMENT MATERIAL LABOR EOUIPMENTLOC Averagel Hourly Labor Rd* i UNIT UeT NRT TOTAL TOTAL TOTAL TOTAL
CODE Ms AREA QUAHNTTY UNI6T PCe PRCE PR=C PRCE PRUCE PICE PR=E4 Caftm*wd ODbit . Swoo 8 P.t RaloaM Tldr I j ton 5452.61 $100q7 s0 516172 BMOFF bdd.a LLRW Tr-e I, d- 337.5 A $452.61 to..,707 so0 363.7073 Md.W CW W e-WPId 1.2 10N $412.61 W. 126 $0 $1,2932 BMiFF b LLRW Trsh I W-2S B•o 227,3 tn 5462.61 s244 060 $0 5244 110
-2 668FF bkd&re LLRW T.rh 51.8. Bf.B s 27.3 AN $o2.61 $29,3403 S-p MAW on Mo6 Ped 46430A An $370230 54.256,W2 $0 $4,260,6623 N.w. Sa Meon M. PId 7"2.9 AN $452.61 $78614 $0 17066413 1"r r6 r -oh. dq, p.j - M kee Pad 21.6 An S462.S1 $23.277 $0 $23.2772 koAN sawa. 1. Rtw &o 73.2 AN 4S2.61 $7.,924 50 $79,262 oadl W a 1., C..t• &,"v 5.1 A2.61 $554 so $5,45
WP(IT #~J UAPS/ ffiT 0V2M -ý ^ PROCEI~RIEDWAMAM DIIPOIN.AP. VA METHODOLOGY ARA ITM ITE _____________CONTAINCOO Cd NO. VOLUME SL^v-Vm~ T ~SOl""A - m W WCCOSD OR ENwTY WEIGHT DISO&AL COSFT COTT Pwoucr voLubm WEIGHT COST
p^;] -b 3 t~o.) .So. IIIL. FACO F X f .JbL L
I I 0
CCST sAoUPS
AP. VA WrloOOLOGV AMA IS. mom well COPPTAM. -L Amy~ WU *COOS SQ. VOL OSUTY WIRQHT D ASOL COST COST 7 Omm SHV CS
M AO WA
o FA 0
NOE V04
0-•J O..t -
a.~.a. et
alk.•Q •bO ID •f•
APPENDIX A
APPENDIX A- 12 Decontamination Costs
A-12 Revision 0
T5*6* A-1lDECO14TAMINAT'1OI c¢0
C9C -WACO9 fRMVA.• COST Ytf WITH BARIA- - - - -
- - -m~trmwr INU INPUT INPUT INPU INPU IMU ,r Av -PfDMCG €o? LIu6-I LOC vm CONT. CONTAM. SURF;M COST BARNWELL DECTAPP 6-T6<CD0OY AREA ITEM CODE No. &*FACE MATERIAL TOTAL R1EOVAL WASTE CONA. COtAk mo w COST 6 RELEASE10TCODE
GRAfIK voie ro ~~PO~0 6. CMO RA1E FILRIALCODE __ AREA T)*CK VOLUME. DENS" VO.U6 WET SHP & SURY COST COST TOTAL (m) SvIS &
APT IP IU Now INPUT IUT IUT w ITCOTPUA-40AET LOC V.6S Co0000. C!r AM, -IMt0C.R11W A LCO SRPCE COST E20PCE •C7CODE ITEM CODE No. SURFACE MATERIAL TOTAL. REMOVAL WASTE CONTA4M CONTM. BURSAL P OCE00 RELEAS GRAND RATE 0U6I.LAREA TWICK VOLE OM D VO0mIw W Sw & Ooio cosy COST COST TOTAL CW• 504P a.
KAISER MATERIAL PERCIENT EISWROM ROL eOOESCRIPTION LOG OF OF BLK LIMT UNIT TOTAL TOTAL DIRECT DISPOSAL DISPOSAL
CODE UUTS UITS CONSTRUCT. DENSITY IT VOLUME WEIGH104 VOUM & URY WEIGHT VOL.1MI llb1 061 W03 "6 r %) O bi% em 133
EW.pmeadl Average Ove, Etir Base Bademvt I *q* led 6,134 FM-S.e-eeR-123 Refigerermnwazer I s FM.tIFbeoR-123 Refrigeranut Analit I FI.ld Floo
Corege BeWV I Es FM-1 Flee,Prepared Feed Elevator I Ea I FMId Fleer
A UF4R evilor I E I FM-I stFrBed Recycle BElveor 'I E. I mIRFle
Mied Feed Elkvuor I 6. I FIUldFlwPassenger Elevalor E I FM-lw Flee
FruightE vUtor I I. 1 FM-leel.*UF4 Feed Srew-3rdFloor I Ek I F.IdtFloo
Gren Sal Feed Screw- 2nd Floor I E I FM-ItFloewGrow , MDIspear 2nd floor I Re I FMIdtFlooe
Ore Blnder Disc. Screw I RE I M-.itFlor"W UF4 Elevator i Ea I FW-IdFIob
Prepered Feod Drum Inveswtr Discharge Screw I RE I Flee,UF6 Col Hd. Cram - R ray & Bridge I RE I FM.IdFleoe
Cne Troley Car E, FM-Ill Feeifting Betern for Slen lan Crane e FM-Il Floer
"W HF Prehsieeer I E* I Ft Id~loe"A" Bol. Ifydoftiorinaeor Heeler I E. FIMid Fleo
4 SIe. Chase I RE FM-I lefo03 Set;l Chaed E I FM.lst FIl
Tempered WalerTank Cooing Coil I Re I FM-IdFleSemple Col Trap I Re I FIoI-Floe,
UF6 hb. ,errlees Cyt Empt.q Manifokl I E. FM-Id FleeSenle Cold Trap t Ea I FMIoFle
Unk Hower I E I FM-IItFloor09 Coole held -E•changer E FM-IeIFb
Glycol heW Eriagr e FM-le FlowOver Fed Bri Cooler I Re I F&6.IwFlee,
Econom.izer I E I FMil FlkeeR-134& Condenser e FM-I I Fe,1:
R-134a UqLid Suction in HeOWedlnge Re F&-I FloorCondeexr-R-123(Top) I Ea I FMsIdFloor
Condumer- Cooler- R-123 &R-1S4a (Sodon) ER I FM-I Flee,Cordendar- R-134 Pwrnp Doan E I FM-t Floor
12 Steam Chem I E I FMIstl Floee1 Seter Chest i E I FMldlFle
'B" HF PFteter I RE I FLO.IdtFloo"E" Bobtom IydroFwb-uor Heelem I Rs I FMIltl Fr
Flame Tower Prehleder ( Former WA) I E I FUluFlee,stiv Hoalers. Upper Seclton Cr. I E. I FM-Id Flee,Strip Heelers Upper Sedion CU. I R. I F-lltFi-,Cooklg Cols - Lower Section Cr. t ER I FM-ll FleCooing Coibs- Lower Sectdio Mr. I Es I FM-Ll Fle•,Mitt Elimnator for Vacuau Pu, I EI I FMI~d F1le,
Oxide Ve ln Fliter I E. I Fhl- I-1,UF4 VscumFI Filer Re F.. laFloor
Aslh Vac•al Clee ner Re I FM-ls FleoUF4 Vacoau e Clenus.er i RE I FW-IlFIlAshl V lCm Clesnr I R Es FM-II Floor
Oxide Vow"Clos C nom.- Dusl Colletor I RE I MIdl FloerOdd Va.cuurn Clener - Dust Colledor I E I FIM-Id Floe
UF4 Vecuum I Re I FM-IwFleeSpar Filer Fines Onxm, Durypr I E. FI IFM-ll Fle•
HotBox (East) I Ea I FIa FloHot Box (West) I E. I FMI&IFle
500 M6-E-LU, Portable Hoist I eA FM-I FleteCrae Troley Cas 1 E I FM-Is Flee
Lilfng Beem lor Sharinfhan Crane I E I F1-ll FleUF4 Mi4l- 3rdFor I E. I F%- I IsFlA
Store Saw- Type M-75 I E. FM-I:FloeBench Grinder -Omen Sky UF792 I R I FI-IM Flo
Bench Grinder - Slnl I E I FM-Ill FleeDnrumtk eeor I E I FM-1 i'l.l,
Ore Corncrete Blainder I RE I F",-Il FleerUF6 Cylinder Cart I E I FMI oFle
UF4 Drum invw or I ER I FM-IdtFleA6JtiJcdled arm foro r eors I Re I FM-Id Fl.e
5mra-l - ast I E FM.Il 6loorM -" Weo I .E I FMI Ii Fleoor
Personnel Funnel Com for Above I E I FM-I FIleo10,0010 Cap _Mo -oreil Meki Are I e I F-IlM Fi-,
2O0CoCap -Monoral. Spw Recycle Are* I r. I Mi lFle4,500 Cop-Monor-l. A" Green Area I E. I F-llt Floo,
9,500i Cop- Mononed- G.E. Dissoc. Retorts I E I FMI.lFIee,4,50 Cop- Monoral- -A- Green SalArea I e I Fls llMFIo
4,0006 Cap - Monorail - r" Refrigeraion Area I E I FIMId Flte,#2 Vacu Puwrp I Re I FM-IiFloe
Cooing•Aikr lower. Earst I RE FIM-Ist Fl-,Coing Air Slower - West I E FI dltt For
G(ycoI C-c. Puwp - Basement I RE I F-ll FlR-123 Getr Au.Oi 01 Pwi I e FM-IEM Fi-e
Bottom HyKrofjorinleor Blow t Ea I FM-IlFME•idg. Eh. Fan I FR FM-Ienl-e
Sernple Vao• m FPam I E. I FM-Id Flee,Riuus Fen - Distllation R. FM-IlFlee
Flswne Tortar VctAsmn Plmlp - 2 Id FR I FM.M FleoExRtidi Fan -.Soul Carter I RE I FM-,l Floo,
El6udl Fan"- Wod I E F-Il"r Fluordus Fan M- nlanemrce Area I E I FM. 1d Fleoo
Basemenxhalu Fan - Hollowel I E. I FM-ll FleBottomn Hydrofjorwl(or Ai Ckirueon Fan I e FM-IlFle
NUMBER MATERIAL PERCENT ENVIRO ENVIRODESCRIPTION LOC OF OF BULK UNIT UNIT TOTAL TOTAL DIRECT DISPOSAL DISPOSAL
CODE UNITS UNITS CONSTRUCT. DENSITY W0EIGHT VOLUME WEIGH4 VOLUME BURY WEIGHT VOLLMEMA ) ) 31m Wel%) Ob) f93)
2000O Monorai. Ash Dust Col Blower Motor I IE I PM4-8 Floor1000O Monoral I Ea I FM l Flow10000l Monorai I Ea I FOrM- FIo
Monorail F-496 & F-497 Fluo01efor Flter Es I FM-U, PlwMonoral - F-463 & F-494 Forjotor Flter I Ed I FM-WG&P
SOlencer - Ash Vo¢ Ct Eah. I Es I FM01t FloorA UF4 D.C. Exhisuster I E. I PUU Floor
Wet Odde Dust Col Slower I E I FM-P4 PiewUF4 BU D.C. BlOhw I E. Fm4P 1 Fbs
"A* Reduclon Ex Coolng Blower I E I FMUM FleAsh Vac. CL Ex.mmuen I Ea I F1M-U Flee
Dry Oxide D.C. Bwr I -. I FM-U, FloorA HF Pri. Je Scnlber-Emst I Ea I P'M41-U .Fl
Ash D.C. Eimstler E. FM-fl FP..A HF Sec. Jet Scnuber .WedI Es I 8& Fle
Draw H&V Unit 0 1 FI I FM-, FloorDmvo H&V Ul2 1 Es I FM-U FlwDraw H&V UnI414 I E. FI-eI Floor
Draw Weol~d Drall Fern I E. I FM-U, Floe,Drawo Iduced Draft Fan i E. I FM-, FloorDraw kiduoed Draft Fen I E. FIaM-t Flow
Root E-os Blower No. I Es I FM-m FnRoof E.iavouit Blow Hoist Wei I Es I FM-U. Floe,
Trans Verd LSt No 317-1 E. 1 FM-U, FlowTnn. Vent U No 222-1 1 Ea I FM-ft 1oM
Ej~sual Fen - Sow I E. I FM-U, Floe,Exdheu Fa- Wo Es I FM-ll Fl.oExhaust Fe-)m I Es I FM4-U Fn_
Faen- Man Cooler I Es I FM-U, FIerVeto Fem I Es I FO-UFlow
" Redutor Ext Gas Coo• lw I Ea I FM-el P:oorDurilteg Waer Cooler I Es I FM-U, Floe
Scrnuber. A Green SoI Dust Coleclor I E I FIMost FP-Scruber, B Green Sal Dust Collect• I Es I FM-U, P
SW-22 Swtcboowd - See Dwg MTW-A0029 I E. I FM-U, loSW`-23 Switchoard - Sea Dwg MTW-A030 I Es I FM-rN, Pn
UF4 Hopper I E. I FU.Uh FI-pt Decay Hopper I E. I FMW-r, Fle
Air Blow Back Sege Te* I Es I FM-rFlo'A* Redjdoo Feed Hopper I Es I FM-U, Floe*B Reductor Feed Hopper I Es I FM-rn, F•
Vb&br-O, No2 Dry Ox Dust Coil HppIF412) I E. I FM-rn FiP-Vilbrtor - On'A*Sac UF4 DOus Cog I Es I PM-r, Foe
Vitor - On*B*Sec UF4 Dust Col(F450) I Es I FMU, Floe,Vbrtor - OnrA" Red Exl Ges CooiesE625) I Es I FM-h FIPV'brJaor.- On'Bl•ed ExI Gas Cooler(E632) I Ea I FM-ft Floe
VIbrator- On (F-450) Es FP1.-b FloeRotay VFVo--A'UF4 Sec D.C. Disch Es FM-rnhJp4ss
Rotar yVleve-9 UF4 Sec D.C. Disch I Ea I FM-U, FleCounlo,*ued Sol of Sespin Plear Railroad Trawis 4 f 3.5680 Sol
Conrtssled Soil M Samrping Plort North Feame 4 cf 132 SaoCorntarmsleod Debis at Serming Plant Ralkoad Tradc 4 O 6 .1
BEIMFF buildig LLRW Trash In drums 2 d- ,250 DAWMatereal on Weale Pad / Other 3 ds B DAW
SMIFF bildrVg LLRW Trash in B-25 Boxes 2 B-25 b- 129 DAWBMfFF builing LLRW Trai, In Blue Boxes 2 ble bex 20 DAW
Scrap Metal an Metals Pod 3 f 96,1602 MesHew Scrap Me•tl I oMa Pod 3 cf 1,408 M.
I"xI"7x cubes for disposal on Mestas Pad 3 d 432 M.tw.8,',off - In CnO, Bihig & 2 &M 217 Sludge
Otf as Mateoral in Crusher Bldlng 2 2 d- lB 16 s",gVEqipmert Sodim Rernovalllon Ew•i1o Bldg I er l-o 3,600 .SI ResIX 1stEquppwr Sodurt Renoveaon Excharge Bldg I luvre lo• 3,20 ,S4 R-inX Mar
Eqpmert KOH Muds Buidng I n lost ,Z34 KOH MkEql•pfft Uranium Recovery Buifn I eq- ls 4.680 U Rees. 1.Eqiprwt UrvaNIau Recovery B-ildnig I wo les 1.100 U Re.w. Me"Eq~Lpes FM Buhing SoAhest pad I qu- f.st 3,980 FM-Bts..,nEquLmdpn FM Budig Southwest pad I -q- les 3.584 F-B- -e- A
Epuipmest Sa~rsple Peari I eq- lost 4,484 FM&-6.4,.iEquipment Pond Muds Fite8r Calciner Bldg 2 .1,- fes 1,126 FM- Bs• oel
FM Building Denoklon Debrs I ,Ak les 10o.0o43 DebrisFM Building Dermoilon Concrete Rumbble I .6k les 61048 s.,st 5NH Removal BL~dkV Doenloon Debris I ob flet 13.796 0DebAU Recovery Bul• n Demo4flo, on Debris 1 .. lest 14,141 0..
KOH Muds BUlg Demornotion Debns I cu lest 1,1923 .1%Savpls Ped BUIsg Dernosilon Deets I ubk lest 14,231 0.d1
C._aok BU11ng Dernolltion Debris 2 oe es g0 D.6,1.FM Pads Desnollion Conoreate Rubble I lost Z3%8 s• , l n,.e
EBca•slod Pipe 4 bk 1- 1.058 SstRoofn Over Lawssry Area 5 sMe lest 600 A%*s.hu-eel