LA-UR-17-20127 Approved for public release; distribution is unlimited. Title: Criticality Safety Analyst (CSA) Qualification Standard Author(s): Lujan, Mary Beth Intended for: 2017 American Nuclear Society (ANS) Annual Meeting, 2017-06-11/2017-06-15 (San Francisco, California, United States) Benchmarking request from Savannah River Nuclear Solutions Issued: 2017-01-10
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CoverSheet - TAMU College of Engineering...NCS-QS-001, RO 1. Throughout: a. Removed references to NCS/DDL. b. Replaced term "module" with "competency" to avoid confusion with DOE NCSET
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LA-UR-17-20127Approved for public release; distribution is unlimited.
Title: Criticality Safety Analyst (CSA) Qualification Standard
Author(s): Lujan, Mary Beth
Intended for: 2017 American Nuclear Society (ANS) Annual Meeting,2017-06-11/2017-06-15 (San Francisco, California, United States)Benchmarking request from Savannah River Nuclear Solutions
Issued: 2017-01-10
Disclaimer:Los Alamos National Laboratory, an affirmative action/equal opportunity employer, is operated by the Los Alamos National Security, LLC forthe National Nuclear Security Administration of the U.S. Department of Energy under contract DE-AC52-06NA25396. By approving thisarticle, the publisher recognizes that the U.S. Government retains nonexclusive, royalty-free license to publish or reproduce the publishedform of this contribution, or to allow others to do so, for U.S. Government purposes. Los Alamos National Laboratory requests that thepublisher identify this article as work performed under the auspices of the U.S. Department of Energy. Los Alamos National Laboratorystrongly supports academic freedom and a researcher's right to publish; as an institution, however, the Laboratory does not endorse theviewpoint of a publication or guarantee its technical correctness.
~wclear ~riticality Safety Division
Document Number:
Effective Date:
Supersedes:
Next Review Date:
NCS-QS-001,RO
OD\Juu.Gv t 5, .J-0( ~ CT-NCS-CSA-QS-604.R5
~t:doe v- I S- . ;J0/6 )
Criticality Safety Analyst (CSA) Qualification Standard
4.0 Program Design ............................................... ........................................ .............. ............................ 9
5.0 Program Elements ....................................................................... .. ............. .................................. ... 12
5.1 Entry-Level Education and Experience Requirements ...................................................... 12
5.2 Alternatives to Entry-Level Education and Experience Requirements ........................... 12
5.3 Exceptions to Training Requirements .................................................................................. 12
b. Replaced term "module" with "competency" to avoid confusion with DOE NCSET program use and for consistency with ANSI/ ANS 8.26-2007 and DOE-STD-1135.
c. Miscellaneous terminology and acronym updates.
2. Section 1: Updated revision number from DOE Order 421.B to 421.C
3. Section 2:
a. Added Task Qualification.
b. Added subsequent document revision applicability.
4. Section 4.0:
a. Added Section; added Figure 1.
b. Added narrative addressing LANSCE and Balance of Site duty areas.
5. Section 5.6 - 5.8: Revised; added Table 1.
6. Section 5.6.3.b.2: Deleted CSA IQ/Process Specific
7. Section 5.9: Revised.
8. Section 5.11 : Added mentoring plan reference.
9. Section 6: Resequenced.
10. Section 6.2: Updated continuing training narrative.
11. Section 7: Added requirement for original NCSD qualification records.
12. Appendix A: updated.
13 . Appendix BI - B3: Updated to include new UTrain requirements.
14. Appendix Bl: added row with LANL/NCSD-specific requirements.
15 . Updated Appendix B2: Added UNM Short Course and DOE Hands-On course as primary requirement for multiole modules;
independently perform specific tasks or job assignments for which trained and authorized; this qualification approach is referred to as "task qualification."
All listed documents are current at the time of this publication; subsequent revisions and updates should
be used as applicable.
3.0 Analysis Methodology
This program was developed using DOE-STD-1135-99 as a guide, and is consistent with national
consensus standard ANSl/ANS-8.26-2007.
Various analysis methods were utilized in development of this program, including needs, job, and task
analysis; document reviews; and expert interviews. Analyses were performed for facility and process
knowledge elements, including operations, equipment, material processes, physical plant/systems, and the safety authorization bases.
The program is comprised of an institutional core program augmented with facility specific modules and mentoring; together they constitute a comprehensive qualification program for the specified facility.
4.0 Program Design
Consistent with ANSI/ANS 8.26, this program is designed to address three levels of qualification and ten competencies.
The levels of qualification are:
1. Criticality Safety Analyst: In Training (CSA-IT) 2. Criticality Safety Analyst: Qualified (CSA-Q)
6. at least ten years (10) experience as a qualified CSA with at least five years (5) experience as a CSA-Qin the LANL NCSP.
A senior CSA-SQ has broad experience in criticality safety and related fields, including
independent review of CSEDs, mentoring CSA-ITs and CSA-Qs, and oversight of operations
with criticality control materials (e.g., fissionable materials, moderators, absorbers). The CSA
SQ has demonstrated a robust understanding of criticality safety principles over diverse
operations, and as a result, a CSA-SQ may perform all activities, including independent reviews,
in all areas of the Laboratory. Based on a CSA-SQ's knowledge and experience, they may be
asked to provide guidance/opinions in areas that are covered by the LANL NCSP and each of the
Facility Specific NCSPs.
Table 1 defines the levels of qualification, work scope, and training requirements.
Table 1. CSA Qualification Structure
Le\ el Worl, Scope rrai11inc l{l:'qt1in·mcnh
Performs tasks only under the supervision 1. Prereguisites: None of one or more qualified criticality safety 2. Training: Defined on Att. 2A, NCSET on-
~ analysts (CSA-Q/CSA-SQ). line modules and general requirements O' = E-< ~ 3. Continuing Training: as applicable
4. Exam: None
Allows CSA-IT to author and review 1. Prereguisites: ! -; calculations for the purposes of informing • CSA-IT requirements (CU 1728) 't:l a Criticality Safety Evaluation Document • CSA-Q (CU 1729) subset, see Att. 3A ~ s:i. (CSED). These calculations may become 2. Training: Defined on Att. 3A O' 00
f: E-< .§ part of a CSED directly, or be documented 3. Continuing Training: as applicable
~ ....
in a Technical Document which could then 4. Exam: None OS
= ~ be referenced in one or more CSEDs. OS u
Allows CSA-IT to act as the NCS 1. Prereguisites: i representative during Fissionable Material • CSA-IT requirements (CU 1728) ";j Operational Reviews (FMORs) and • CSA-Q (CU 1729) subset, see Att. 3B ·2
O' s:i. perform NCS review of work authorizing 2. Training: Defined on Att. 3B E-< 00 and NCS control implementing documents 3. Continuing Training: as applicable g
·c; for facilities in which he/she has 4. Exam: None OS additionally completed the TQ/Facility ~
A CSA-Q has completed requirements in all ten competency areas including the Calculation and Facility Specialist Task Qualifications and demonstrated understanding of the physics of nuclear criticality and the program elements that make up the NCSP at LANL.
A CSA-Q may independently complete the Cl.I following work tasks: o=
!-; ~ • Fissile Material Operational Reviews (FMORs)
• Procedure Reviews
• Event Response
• Author CSEDs (see Section S.9 Authoring/Reviewing in Additional Duty Areas for more information)
A CSA-Q may begin the CSA-SQ curricula (CU 1730) if assigned by the NCS-DL
~ Allows the CSA-Q to perform as the loo independent reviewer for CSEDs written for
~ Cl.I it; processes in facilities where the CSA-Q has .9:! ;.. completed facility qualification. Additionally, ~ the CSA-TQ/IR may review CSEDs for
0 .... processes anywhere on the site as long as !-; ~ -= either the author or reviewer is qualified on = Cl.I the facility where the process is resident (see c. Cl.I Section S.9 Authoring/Reviewing in -= = Additional Duty Areas for more information) . ....
Prerequisite to CSA-SQ.
! c;; Allows the CSA-Q to perform Criticality «I rl:J Accident Alarm System Evaluations. <~
The TQ/CAASS is assigned by the NCS-.... u = ._ DL/DDL as needed and is not a prerequisite Cl.I ....
-= "' O' ..... = for CSA-SQ. E-- t .SS < ~ c~ = rlJ 5 e .: $ ·c "' u~
NATIONAL LABORATORY -- or ... 1.,,.J --
Training Hcquircml•nh
1. Prereguisites: • CSA-IT (CU 1728) • TQ/CS • TQ/FS
2. Experience: two (2) years minimum job related experience, one of which must be nuclear
3. Training: Competency areas in Appendix B2 (CU 1729)
4. Continuing Training: as applicable 5. Faci lity Knowledge: at least one (1) duty
area identified in Appendix D 6. Exam: Oral Board
1. Prereguisites: • CSA-Q (CU 1729) and assigned Duty Area
(see CSA-Q) 2. Training: Defined on Att. 3C 3. Continuing Training: as applicable 4. Exam: None
1. Prereguisites: • CSA-Q (CU 1729) and assigned TASS
Duty Area (see CSA-Q) 2. Training: Defined on Att. 3D 3. Continuing Training: as applicable 4. Exam: None
A CSA-SQ has demonstrated a robust understanding of criticality safety principles over a diverse range of operations, and as a result, a CSA-SQ may perform all activities, including independent reviews, in all areas of the Laboratory. Based on a CSA-SQ's knowledge and experience, they may be asked to provide guidance/opinions in areas that are covered by the LANL NCSP and each of the Facility-Specific NCSPs.
They also may be asked to deliver criticality safety training to operations as directed by the NCS-DL/DDL.
A CSA-SQ meets all the requirements of a CSAQ and has either been qualified as a CSA-SQ at another facility or completes the following NCSD requirements:
I. Prerequisites:
• CSA-Q (1729)
• Task Qualification IR
2. Experience: Ten (10) years, at a minimum, experience as a qualified CSA with at least five (5) years in the LANL NCSP
3. Training:
• CSA-SQ training curricula (CU 1730)
• Qualified instructor (TSQP 3247)
4. Conrinuing Training: as applicable
5. Fac.ility Knowledge:
• T A-55/PF4/400 area
• One other T A-55 Duty Area
•EWMO
• NNSS
• Two (2) Additional Duty Areas listed in AppendixD
6. Exam: No formal examination; instead a capstone event Management Review is required
5.9 Implementation Methodology
This program uses a comprehensive, yet flexible methodology benefitting both the CSA and the programs
supported. Once a candidate has been formally selected, the NCS-DL screens the candidate's previous
education and experience and determines this program's applicable core training requirements. The NCS
DL then determines the DA assignment, including TQs, for the CSA candidate based on the organization
and emergent needs.
Consistent with Section 5 of ANSVANS 8.26, a CSA-IT is actively training in the CSA-Q curricula (CU
1729). During this period, the CSA-IT shall perform tasks only under the supervision of one or more
• If a CSA has been absent from duties in their assigned facility, but has been able to maintain
proficiency by performing equivalent operations elsewhere, the CSA may be reinstated to full
qualification at the discretion of the NCS-DL.
7.0 Records
The NCS-DL, as owner of this program, assures maintenance ofrecords of all training and qualification
requirements in accordance with P781-1, Conduct of Training. The CSA is required to submit original
records originating from this qualification program to the Training Specialist (records from external
employment/qualification programs demonstrating prior achievement may be duplicates). All completed
components of this program are entered and maintained in the institutional training records system,
UT rain.
8.0 Acronyms
CAAS CAASS CDS CMR CSA-IT CSA-Q CSA-SQ CSA-TQ/(x) CSED cu DA EWMO FMOR DOE LANL NCS NCS-DL NCSP NNSS PF SAT STO TA WQAS
QAlamos NATIONAL LABORATORY --UT. 1to--
Criticality Accident Alarm System Criticality Accident Alarm System Specialist Criticality Detection System Chemistry and Metallurgy Research Facility Criticality Safety Analyst: In Training Criticality Safety Analyst: Qualified Criticality Safety Analyst: Senior Qualified Criticality Safety Analyst: Task Qualified (task 'x') Criticality Safety Evaluation Document Curricula Duty Area Environment and Waste Management Facility Operations Fissionable Material Operational Review Department of Energy Los Alamos National Laboratory Nuclear Criticality Safety Nuclear Criticality Safety - Division Leader Nuclear Criticality Safety Program Nevada Nuclear Security Site Plutonium Facility Systematic Approach to Training Science and Technology Operations Technical Area Worker Qualification and Authorization System
Appendix A: Competency Requirements by Qualification Level
Competency
1. Nuclear Theory
2. Criticality Safety Calculation Methods
~Alamos NATIONAL LABORATORY
--tn.•••:11--
Training Level
Training Content 00 00 01 ~ ~
I
< 01 01 00 E-- E--o u
1.1.1. Define the following terms: Excitation energy, Cross Section, Fissile material, x x x Fissionable Material, Fertile Material.
1.1.2. Sketch the fission cross section for both U-235 and Pu-239 as a function of neutron energy. Label each significant energy region and explain the x x x implications of the shape of the curves for criticality safety.
1.1.3. Explain why only the heaviest radioactive nuclear are easily fissioned. x x x 1.1.4. Explain why uranium-235 fissions with thermal neutrons and uranium-238 x x x fissions only with fast neutrons. 1.1.5. Characterize the fission products in terms of mass groupings and x x x radioactivity.
1.1.6. Define sub-critical, critical, super-critical, nu, and beta. x x x 1.1.7. Define reactivity and describe how it is measured. x x x 1.1.8. Explain the Six-Factor formula and the terms used therein. x x x 1.1.9. Explain how delayed neutrons affect reactivity. x x x l .1.10. Explain the effects of the following factors relevant to criticality safety of
operations: Mass, Interaction, Geometry, Moderation, Reflection, x x x Concentration, Volume, Neutron absorbers and Enrichment.
1.2.1. Describe the interactions of the following with matter: Alpha particle, Beta x x x particle, Positron, and Neutron.
1.2.2. Describe the following ways that gamma radiation interacts with matter: x x x Compton scattering, Photoelectric effect, Pair production
.3.1. Describe the use of neutron poisons. x x x
.3.2. Explain the absorption characteristics of the following elements in terms of x x x their cross-sections: cadmium, boron, chlorine, gadolinium, and hydrogen.
.3.3. Explain the purpose and use of Raschig Rings as a neutron poison. x x x 2.1.1. Identify and discuss the application of several common hand calculation x x methods. 2.1.2. Select one hand calculation technique (buckling, solid angle, or areal density) x x and prepare an example of its use.
2.2.1. Describe how cross section data impact Monte Carlo and deterministic codes. x x 2.2.2. Describe the importance of validation of computer codes and how it is x x accomplished. 2.2.3. Describe the methodology supporting Monte Carlo codes and deterministic x x codes.
2.2.4. Describe the pitfalls of Monte Carlo calculations. x x 2.2.5. Discuss the strengths and weaknesses of Monte Carlo and Discrete Ordinates x x codes.
"A ..-,. LosAlamos NATIONAL LABORATORY --EST_l94l--
Training Level
Training Content 00 00 0 u ~
I -- < 0 0 00 E-- E-- u
2.2.6. The diffusion theory model is not strictly valid for treating fissile systems in which neutron absorption, voids, and/or material boundaries are present. In x x the context of these limitations, identify a fissile system for which a diffusion theory solution would be adequate.
2.3.1. Perform three practical MCNP models under the guidance of a qualified CSA- x x Q/CP or CSA-SQ
3.1.1. Describe the types of data derived from critical experiments and their use in x criticality safety.
3.1.2. Participate in a criticality experiment or subcritical experiment demonstration x (Covered by Terminal Objective 16).
3.2.1. Discuss previous criticality accidents and their causal factors, including parameters involved in solution and metal critical accidents.
x
4.1.1. Attend Hands on Training Course (Sandia, DAF, LLNL, etc.) x
5.1.1. Discuss ANSI/ ANS-8.1, Nuclear Criticality Safety in Operations with x x x Fissionable Materials Outside Reactors.
5.1.2. Discuss ANSI/ANS-8.3, (ANSI N-16.2), Criticality Accident Alarm System x x 5.1.3. Discuss ANSI/ANS-8.5, (ANSI N-16.4), Use of Borosilicate-Glass Raschig x x x
Rings as a Neutron Absorber in Solutions of Fissile Material. 5.1.4. Discuss ANSI/ANS-8.6, Safety in Conducting Subcritical Neutron- x
Multiplication Measurements In Situ. 5.1.5. Discuss ANSI/ ANS-8. 7, Guide for Nuclear Criticality Safety in the Storage of x x x
Fissile Materials. 5.1.6. Discuss ANSl/ANS-8.9, Nuclear Criticality Safety Criteria for Steel-Pipe x x x
Intersections Containing Aqueous Solutions of Fissile Materials. 5.2.1. Discuss ANSI/ ANS-8.10, Criteria for Nuclear Criticality Safety Controls in x x
Operations with Shielding and Confinement. 5.2.2. Discuss ANSI/ANS-8.12, Nuclear Criticality Control and Safety of
Plutonium- Uranium Fuel Mixtures Outside Reactors. x x x
5.1.7. Discuss ANSI/ ANS-8.15, Nuclear Criticality Control of Special Actinide Elements.
x x x 5.1.8. Discuss ANSI/ ANS-8.17, Criticality Safety Criteria for the Handling, Storage x x x
and Transportation of L WR Fuel Outside Reactors. 5.1.9. Discuss ANSI/ ANS-8.19, Administrative Practices for Nuclear Criticality x x x
Safety. 5.1.10. Discuss ANSI/ ANS-8.20, Nuclear Criticality Safety Training. x 5.1.11. Discuss ANSI/ANS-8.21, Use ofFixed Neutron Absorbers in Nuclear x x x
Facilities Outside Reactors. 5.1.12. Discuss ANSI/ ANS-8.22, Nuclear Criticality Safety Based on Limiting and x x x
Controlling Moderators. 5.1.13. Discuss ANSI/ANS-8.23, Nuclear Criticality Accident Emergency Planning x x
E- E- u 5.1.14. Discuss ANSI/ANS-8.24, Validation ofNeutron Transport Methods for x x
Nuclear Criticality Safety Evaluations. 5.1.15. Discuss ANSl/ANS-8.26, Criticality Safety Engineer Training and x
Qualification Program. 5.1.16. Discuss ANSI/ANS-13.3, Dosimetry for Criticality Accidents. x 5.1.17. Discuss DOE Order 420. lC, FACILITY SAFETY, Section 4.3, Nuclear x x x Criticality Safety 5. l .18. Discuss DOE-STD-3007-2007 Guidelines for Preparing Criticality Safety x x x
Evaluations at Department of Energy Non-Reactor Nuclear Facilities. 5.1.19. Discuss LA-10860-MS, Critical Dimensions of Systems Containing U235, x x x
Pu239,and U233, 1986. 5.1.20. Discuss TID-7016, The Nuclear Safety Guide, June 1978. x x x 5.2.3. Discuss 10 CFR 830 Subpart B; 830.204, Documented Safety Analysis. x x 5.2.4. Discuss 10 CFR 830 Subpart B; 830.205, Technical Safety Requirements. x x 5.2.5. Discuss DOE-STD-1135-99, Guidance for Nuclear Criticality Safety x Engineer Training and Qualification. 5.2.6. Discuss DOE-STD-3009-94, Preparation Guide for U.S. Department of x
Energy Nonreactor Nuclear Facility Documented Safety Analyses. 5.2.7. Discuss DOE-STD-3011-2002, Guidance for Preparation of Basis of Interim x x Ooeration (BIO) Documents.
6.1.1. Develop contingency analysis, limits and controls. x 6.1.2. Describe key personnel needed to assist in preparation of criticality safety x
evaluations and determination oforocess upsets.
6.1.3. Describe how subcritical margins and limits are determined. x x 6.1.4. Describe when validation and bias estimates must be considered. x x 6.1.5. Describe typical criteria to consider when evaluating various fissile processes,
inclu<ling common process upsets: Aqueous, Metal, Recovery, x x x Fabrication/Foundrv, Mixed Waste.
6.1.6. Describe criteria to consider for evaluating material storage: Pits, Waste, Fuel elements, Solutions, Metal parts.
x x 6.1.7. Discuss the industry reference material used in determination of critical mass:
LA-10860, LA-12808, and TID-7016. x x
6.1.8. Discuss the effects and applications of the following factors relevant to criticality safety of operations: Mass, Interaction, Geometry, Moderation, x x x Reflection, Concentration, Volume, Neutron absorbers, and Enrichment.
6.1.9. Discuss the influence of the presence of non-fissionable materials mixed with, x x x or in contact with, fissionable material on nuclear criticality safety. 6.1.10. Discuss the concept of contingencies for checking the validity of criticality x x safety limits and controls. 6.1.11. Discuss the methods used in the calculation of criticality safety, source term, x x
environmental transoort, and dose assessment activities including commonly
Training Content r:l1 r:l1 Cl u ~ I ..._ < O' O' r:l1
Eo- Eo- u used computer models.
6.1.12. Demonstrate familiarity with the published histories of criticality accidents
7. Safety Analysis and Controls
8. Event Response & Criticality Accident Alarm Systems (CAS)
NATIONAL LABORATORY --EST.194)--
with emphasis on the control failures, terminating mechanisms, and resulting x radiation hazards/health consequences to nearby personnel.
6.2.1. Read and discuss three CSEDs under the guidance of a qualified CSA-Q or CSA-SQ.
6.2.2. Perform three CSEDs under the guidance ofa qualified CSA-Q or CSA-SQ.
7.1.1. Identify and discuss essential elements of deterministic and probabilistic risk assessment techniques.
7.1.2. Identify and discuss the methods used to determine and analyze failure modes.
7.1.3. Discuss the methods used to identify and categorize the hazards associated with DOE nuclear systems.
7.1.4. Define the following terms with respect to probabilistic risk assessments: Probability, Reliability, Availability, Unavailability, Risk, Safety, Accident sequence, Dominant contributors, and Minimal cut set.
7.1.5. Define the following terms and differentiate between the associated processes: Event tree and Fault tree.
7.1.6. Describe the content of the sections ofa safety analysis report (SAR) per the local DOE site office expectations.
7.1.7. Explain a hazard analysis techniques and how Technical Safety Requirements (TSRs.) are derived.
7.1.8. Identify criticality safety controls that are required by the facility safety authorization basis documents.
7.1.9 Explain Threshold values and the Graded Approach used in hazard classification.
7.1.10. Explain how natural phenomenon events are evaluated in NCS.
8.1.1. Discuss LA-13638, A Review of Criticality Accidents, 2000 Revision
8.1.2. Define the following terms: Criticality accident, Minimum accident of concern, and Process area.
8.1.3. Discuss the general principles associated with the use of criticality alarm/detection systems including: Installation, Coverage, Detection, Alarms, Dependability, Surveillance, and Maintenance.
8.1.4. Discuss the requirements for testing the criticality alarm/detection system.
8.1.5. Discuss how an exemption for CAS/CDS must be prepared.
9.1. l. Explain how nuclear materials accountability relates to criticality safety. x x 9.1.2. Discuss how the accountability system is conducted at their facility. x x 9.1.3. Discuss Non Destructive Assay (NDA) and sampling techniques used at their
facility including the limitations and pitfalls of the methods relative to x x criticality safety.
9.1.4. Discuss container and material labeling practices and fissile material area x x postings.
10.1. l. Describe the physical system/facility. x x 10.1.2. Describe the material flow and throughput. x x 10 .1.3. Describe the normal operating conditions. x x 10.1.4. Describe credible abnormal conditions. x x 10.1.5. Describe interfaces and interactions with other processes/facilities. x x
Familiarization Activities supporting the facility requirements for Criticality Safety Analyst Task Qualification/Facility Specialist (FQ/FS) include:
Familiarization Activities
1. Author or co-author a CSED supporting a new or significantly changed operation.
~ Primary author initials Record of Familiarization Activities
2. Review or co-review a CSED
~ Primary reviewer initials Record of Familiarization Activities
3. Participate in an FMOR. An FMOR consists of three general steps; I) review the documentation to be used for the review, 2) observe the work performed (if applicable), and 3) document the review and comments.
~ Primary CSA conducting FMOR initials Record of Familiarization Activities
4. Tour the area with a qualified CSA and discuss how criticality safety is implemented into the various operations.
~ CSA conducting tour initials Record ofFamiliarization Activities
5. Observe performance of fissile material handling operations. This must be conducted in concert with Operations (ORM, ORS, CSO, or FMH), and focused on gaining/maintaining familiarity with operations.
~ ORM, ORS, CSO, or FMH initials Record of Familiarization Activities
6. Participate in a Procedure Review
~ Primary CSA conducting Procedure Review initials Record of Familiarization Activities
7. Participate in the review of a Criticality Safety Posting (CSP)
~ Primary CSA conducting CSP review initials Record of Familiarization Activities
8. Participate in a Process Deviation Response and Resolution
~ Primary CSA for Process Deviation initials Record of Familiarization Activities
9. Support facility self-assessments, NCSC/B reviews, and DOE/DNFSB reviews related to criticality safety issues.
~ Lead of assessment/review initials Record of Familiarization Activities
Attach supporting documentation for all responses to Education and Experience Requirements. Submit form with supporting documentation to the NCS-DL for verification and approval.
Position: Criticality Safety Analyst (CSA) UTraln NT #21512 Name (print) I Signature I Z Number Date
Education Requirement: BS In nuclear engineering, physics, or related science field Undergraduate Graduate Doctorate
Degree:
Institution:
Year Completed:
Experience Requirement: Two (2) years }ob-related, one (1) of which must be nuclear
1. How many years of nuclear criticality safety experience do you have? Years: Months:
2. How many years of nuclear experience do you have? Years: Months:
3. Have you been qualified as a CSA, meeting the requirements of:
• DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer D Yes D No
Training and Qualification?
• ANSllANS-8.26, Criticality Safety Engineer Training and Qualification D Yes D Yes
Program?
If yes, cite Facility name:
4. Have you been qualified as a SENIOR CSA, meeting the requirements of:
• DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer
Training and Qualification?
• ANSl/ANS-8.26, Criticality Safety Engineer Training and Qualification
Program?
If yes, cite Facility name:
Describe experience applicable to the position (attach additional pages as necessary)
The TQ/CS allows the CSA-IT to: • author and review calculations in support of criticality safety evaluations • to include authoring of technical documents
To be completed by CSA candidate and approved by NCS-DL Name Z#
D MCNP D SCALE D COG WQ: 3035 WQ: 6897 WQ: 6898
Section A: Prerequisites
D Completion of CSA-IT (Cu #1728) and assigned to CSA-Q (CU 1729)
Section B: Theoretical Knowledge UTraln#
Appendix A elements( or approved substitute):
D Competency 1 : Nuclear Theory 34550 (sub 19109) or 19063 (sub 19109)
The TQ/FS allows the CSA-IT to: • perform NCS reviews of and concur with criticality safety implementing documents, and • lead FMORs.
For initial qualification in one facility (e.g. TA55 or CMR), complete Sections A, B, and C. To qualify in additional facilities, complete only B.2, B.3, and C.3.
To be completed by CSA candidate and approved by NCS-DL Name Z#
Facility D TA55 D CMR D EWMO D STO WQ7340 WQ 7341 WQ7347 WQ 7348
Section A: Prerequisites
D Completion of CSA-IT (Cu #1728) and assiqned to CSA-Q (CU 1729)
Section B: Theoretical Knowledge
1. Appendix A elements( or approved substitute):
D Competency 1: Nuclear Theory
D Competency 5: Rules
D Competency 6: Criticality Safety Evaluations
D Competency 7: Safety Analysis and Controls
D Competency 8: Criticality Alarm System
D Competency 9: Material Accountability Practices
D Drill/Role Play: NCS-AP-012, Nuclear Criticality Accident Emergency Planning and Response
D NCS-AP-010, Potential Process Deviation Briefing
2. Read and discuss the facility criticality safety implementing procedure with a CSA-Q.
D TA55 D CMR D EWMO D STO
D NNSS RR 28005 RR 22824 RR 23991 Area G
RR 14631, TA35 RR 35117
3.
RR 23991 , WCCR RR 23991 , RANT
RR 14631, NISC
RR 23991 , RWL RR 14631, Sigma
RR 32603, TWF RR 14631,TA66
Read the facility Documented Safety Analysis (Chapter 6), the Facility Safety Plan, or Safety Assessment Document (as applicable) for the facility. Discuss interfaces and key requirements related to criticality safety (e.g. TSRs) with a facility safety basis SME.
n TA55 RR 35125
NATIONAL LABORATORY --Ufw1•0--
lJ CMR RR 35126
D EWMO/TWF OSTO D NNSS RR 35127/35185 RR 35128 RR 35129
1. Participate in 5 Fissionable Material Operational Reviews (FMOR), as approved by the NCS-DL, under the guidance of a CSA-Q.
FMO# Title OJT 24957 FM01 CSA-Q Date
FM02 CSA-Q Date
FM03 CSA-Q Date
FM04 CSA-Q Date
FM05 CSA-Q Date
2. Review 5 procedures under guidance of a CSA-Q as approved by the NCS-DL.
Procedure# Title OJT 24959 Procedure #1 CSA-Q Date
Procedure #2 CSA-Q Date
Procedure #3 CSA-Q Date
Procedure #4 CSA-Q Date
Procedure #5 CSA-Q Date
CSA-Q Date
Using Appendix C as a guide, conduct Familiarization Activities in the facility as
3. approved by the NCS-DL (these are in addition to the procedure reviews and FMORs) . Document on Attachment 5. (Note: these Familiarization Activities may count toward full Competency 10 completion)
# Competency 10: Process and Facility Duty Areas for CSA-Q
FAC TA-55 DA PF-4, 100 Area (OJT 25082)
1. Describe this area's physical systems and layout.
2.
3.
4.
For each room, conduct walk-downs and discuss the following to the satisfaction of the ORS/CSO/CSA: • types and quantities of material in each room • material flow once it is already in the room • how material flows into and out of the room from other areas. • describe the normal operating conditions and credible abnormal
conditions for each room: discuss typical chemical/physico-chemical/electro-chemical/ metallurgical processes used in fissile material operations and typical off-normal conditions of such processes that can potentially Im act the safe basis of a NCS evaluation.
Room 105
Room 106
Room 113
Room 114
Room 115
Room 120
Room 121
Room 124
Room 125
Room 126
Conduct at least 3 general tours with a qualified CSA. The CSA-IT should discuss issues of importance to criticality safety to the CSA-Q/SQ's satisfaction.
Using Appendix Casa guide, conduct at least 15 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.
# Competency 10: Process and Facility Duty Areas for CSA-Q
FAC TA55 DA PF-4, 200 Area (OJT 25083)
1. Describe this area's physical systems and layout
2.
3.
4.
For each room, conduct walk-downs and discuss the following to the satisfaction of the ORS/CSO/CSA: • types and quantities of material in each room • material flow once it is already in the room • how material flows into and out of the room from other areas. • describe the normal operating conditions and credible abnormal
conditions for each room: discuss typical chemical/physico-chemical/electro-chemical/ metallurgical processes used in fissile material operations and typical off-normal conditions of such processes that can potentially im act the safe basis of a NCS evaluation.
Room 201
Room201A
Room201B
Room 201C
Room201E
Room 201F
Room206
Room207
Room208
Conduct at least 3 general tours with a qualified CSA. The CSA-IT should discuss issues of importance to criticality safety to the CSA-Q/SQ's satisfaction.
Using Appendix Casa guide, conduct at least 15 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.
# Competency 10: Process and Facility Duty Areas for CSA-Q
FAC TA55 DA PF-4, 300 Area (OJT 25084)
1. Describe this area's physical systems and layout
2.
3.
4.
For each room, conduct walk-downs and discuss the following to the satisfaction of the ORS/CSO/CSA: • types and quantities of material in each room • material flow once it is already in the room • how material flows into and out of the room from other areas. • describe the normal operating conditions and credible abnormal
conditions for each room: discuss typical chemical/physico-chemical/electro-chemical/ metallurgical processes used in fissile material operations and typical off-normal conditions of such processes that can potentially im act the safe basis of a NCS evaluation.
Room305
Room306
Room 308
Room309
Room 317
Room 318
Room 319
Room327
Room 333
Room329
Conduct at least 3 general tours with a qualified CSA. The CSA-IT should discuss issues of importance to criticality safety to the CSA-Q/SQ's satisfaction.
Using Appendix Casa guide, conduct at least 15 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above re uirements.) Document on Attachment 5.
# Competency 10: Process and Facility Duty Areas for CSA-Q
FAC TA55 DA PF-4, 400 Area (OJT 25085)
I. Describe this area's physical systems and layout.
2.
3.
4.
For each room, conduct walk-downs and discuss the following to the satisfaction of the ORS/CSO/CSA: • types and quantities of material in each room • material flow once it is already in the room • how material flows into and out of the room from other areas. • describe the normal operating conditions and credible abnormal
conditions for each room: discuss typical chemical/physico-chemical/electro-chemical/ metallurgical processes used in fissile material operations and typical off-normal conditions of such processes that can potentially im act the safe basis of a NCS evaluation.
Room401
Room420
Room429
Room433
Room409
Conduct at least 3 general tours with a qualified CSA. The CSA-IT should discuss issues of importance to criticality safety to the CSA-Q/SQ's satisfaction.
Using Appendix Casa guide, conduct at least 20 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above re uirements.) Document on Attachment 5 .
# Competency 10: Process and Facility Duty Areas for CSA-Q
FAC TA55 DA PF-4 Basement, Vault, and Waste Storage Areas** (OJT 25086)
1. Describe this area's/room's physical systems and layout
2.
For each room/area, conduct walk-downs and discuss the following to the satisfaction of the ORS/CSO/CSA: • types and quantities of material in each room • material flow once it is already in the room • how material flows into and out of the room from other areas. • describe the normal operating conditions and credible abnormal
conditions for each room: discuss typical chemical/physico-chemical/electro-chemical/ metallurgical processes used in fissile material operations and typical off-normal conditions of such processes that can potentially im act the safe basis of a NCS evaluation.
Competency 10: Process and Facility Duty Areas for CSA-Q CSA-Q/SQ or Date CSOorSME
(unless otherwise noted)
CMR (OJT 25089) TS
Complete the Facility Specialist task qualification (CSA-TQ/FS) for CMR
Read the CMR status document (NCS-MEM0-09-026). Discuss with a qualified CSA
CSA. Describe the overall facility layout, including where common systems are located Facility Ops Manager! SME
and how systems interact between areas. Demonstrate understanding of the following systems/devices in CMR, in particular a. how they could impact criticality safety: b. a. MC&A LANMAS, LIMS b. Ventilation c.
c. Vacuum System d.
d. Chilled Circulating Water System e.
e. Industrial Waste Water f. f. Waste Drain g. g. Process Gas Supplies (Nitrogen, Argon, Helium, etc.) h. h. Dri Trains i. I. Compressed Air systems j. Cart/hand carry process
j .
k. Fire suppression system k.
l. Sumps (in the basement) l.
m. SAFE-4 m.
Discuss unique fissionable material operations with a CSA-Q qualified in CMR or i. operations equivalent. Demonstrate understanding of
ii. a. major equipment; b . . fissile operations at each location including material amounts, types, and flow; iii.
c. normal operating conditions and credible abnormal conditions of such IV.
processes that can potentially impact the safety basis of a NCS evaluation. v.
I. Container Vessel Disposition (CVD) Project (CMR-9141-03) vi. II. Vault (CMR-S021-00) vii.
Competency 10: Process and Facility Duty Areas for CSA-Q
CMR (OJT 25089)
Walk down all other fissionable materials operations in Wings 3, 5, 7, and 9 with CSA-Q qualified in CMR or operations equivalent. Demonstrate understanding of
- major equipment; - fissile operations at each location including material amounts, types, and
flow; - normal operating conditions and credible abnormal conditions of such
processes that can potentially impact the safety basis of a NCS evaluation a. Wing3 b. Wing5 c. Wing7 d. Wing9
Using Appendix Casa guide, conduct at least 10 Familiarization Activities in the in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5 .
Competency 10: Process and Facility Duty Areas for CSA-Q
EWMO (OJT 25090)
Complete the Facility Specialist task qualification (CSA-TQ/FS) for EWMO
a. Demonstrate understanding of flow-down from SD130 to EP-DIV-AP-0111 off-normal event responses for operators, Ops Center, and CS staff including AOP-411.
b. Demonstrate understanding of applicable Safety Basis (DSA or BIO) sections and associated TSRs impacting CS concerns
c. Discuss Material Flow in EWMO i. Source, condition and storage of waste containers I items
a) Drums b) FRPs c) Tanks d) Higher FGE items
ii. Waste Matrix types a) Sludge & Cement b) Size reduced items c) Items from processing (gloves, wipes etc.)
iii. Venting operations (DVS and Remote Venting) iv. NDE & NDA operations (HENC, ISSOCS, gamma spec, RTR, etc.) v. Tracking systems for FGE & MAR & interaction with CS concerns
a) De-inventoried from LANMAS when declared as waste b) WCATS used instead ofLANMAS to track waste type, FGE &
MAR loading, container, and location c) Differences between MAR and FGE limits
vi. SSSR operations a) Parent-daughter rules b) Repack c) Sludges d) Gloveboxes e) Other items processed f) Operation locations and applicable CSED/CSLA controls and limits
for SSSR facilities vii. Transport between processing areas
a) Within an area (e.g., between domes) i. CSLA controls for movement spacing
b) Between area (Area G to RANT or AREA G to WCRR) i. Need to coordinate CS controls with DOT rules
viii. Shipping to WIPP (RANT) ix. LL W disposal in pits and shafts /or NNSS (esp. fissile or moderating
materials exceeding the LL W Waste Acceptance Criteria (WAC)
Competency 10: Process and Facility Duty Areas for CSA-Q
EWMO (OJT 25090)
While touring the designated facilities below, demonstrate understanding of: a. major equipment used in operations that can impact CS and equipment with no
credible impact to CS b. fissile operations at each location including process description, material amounts,
types, describe material flow thru processes at that location and required CS control points
c. handling of higher FGE items or unusual types (e.g. , pencil tanks) d. normal operating conditions and credible abnormal conditions of such processes
that can potentially impact the safety basis of a NCS evaluation, including fire suppression, potential hold-up points (such as DYS) and associated controls
Area G (while touring, demonstrate knowledge of:) a. Dome 231 b. Dome49 c. Bldg 412 d. Dome 375 e. High Efficiency Neutron Counter (HENC)/ Pad 10 f. Other storage areas g. Dome 283 assay h. DYS & Remote Venting l. LLW Pits j. LLW Shafts
While touring RANT, demonstrate knowledge of the loading area and storage yard
While touring WCCR, demonstrate knowledge of the Waste Characterization Glovebox and the Staging area While touring RLWTF, demonstrate knowledge of: a. Liquid Waste Discharge Process from PF-4 b. Concentration and Geometry Controls Protecting Safety Margin While touring TWF, demonstrate knowledge of: a. CSED b. Waste Storage Buildings c. Storage & Characterization Building d. Source Storage Building e. Characterization Areas Discuss hazards and limits usually associated with processes in the EWMO a. Spacing based on FOE content b. Parent-daughter rules (includes holdup prevention rules) c. Equipment and operations that are exempt (non-FMO related) d. Liquids control e. Recognition of off-normal situations or process deviations Using Appendix Casa guide, conduct at least 10 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.
Date Competency 10: Process and Facility Duty Areas for CSA-Q CSA-Q/SQ orCSO
STO (OJT 25092)
Complete the Facility Specialist task qualification (CSA-TQ/FS) for STO TS
SIGMA a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in
STO or Operations Equivalent. b.
b. Discuss Material Flow. c. c. Demonstrate understanding of CSEDs/CSLAs. d. Demonstrate understanding of hazards and limits. d.
T A-35, Buildings 2 and 27 a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in
STO or Operations Equivalent. b.
b. Discuss Material Flow. c. c. Demonstrate understanding of CSEDs/CSLAs. d. Demonstrate understanding of hazards and limits. d.
T A-66. Building I a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in
STO or Operations Equivalent. b.
b. Discuss Material Flow. c. c. Demonstrate understanding of CSEDs/CSLAs. d. Demonstrate understanding of hazards and limits. d.
NISC a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in
STO or Operations Equivalent. b.
b. Discuss Material Flow. c. c. Demonstrate understanding of CSEDs/CSLAs. d. Demonstrate understanding of hazards and limits. d.
Discuss STO Less than Significant Quantity (LSQ) facilities and demonstrate understanding of their operations, material, and potential hazards with a CSA-Q qualified in STO or Operations Equivalent.
Demonstrate understanding of"Nature of Process" and nature of process CSEDs.
Using Appendix Casa guide, conduct at least 10 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.
Competency 10: Process and Facility Duty Areas for CSA-Q
NNSS (OJT 25095)
Complete the Facility Specialist task qualification (CSA-TQ/FS) for NNSS Attend LANL portion of the 2nd week ofNCSP hands-on training for criticality safety practitioners a. Complete approach to critical operations b. Complete critical operations Participate in at least one Radiation Test Object (RTO) construction activity atNCERC a. Attend pre-job b. Understand relevant criticality safety controls and procedures for
conducting this work c. Observe the operation d. Attend the post-job Participate in at least one fissionable material move at NCERC a. Attend pre-job b. Follow fissionable material move, including from/to vault location
to/from building c. Observe shelving/retrieving process d. Understand relevant criticality safety controls and procedures for
conducting this work e. Attend post-job Serve as a primary author for at least 3 CSEDs for NCERC operations, including: a. Understanding the CCR process b. Follow procedure for recommendation of controls c. Attend a CCR meeting d. Follow-up on
Serve as a reviewer on at least 3 CSEDs for NCERC operations.
Participate in annual operating reviews for NCERC operations a. Conduct review b. Complete required documentation in database
Understand administrative practices for criticality safety at NCERC.
Using Appendix C as a guide, conduct at least 15 Familiarization Activities in this DA. (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.
Attachment 7: Request for Continuing Training Credit
To be used for any continuing training event not recorded on a LANL roster.
Training Activity or Event Title
Date(s) of Training Activity or Event
Location D LANL site/facility (specify) D DOE site/facility (specify)
D Other (specify)
Continuing Training Topic Area D Significant facility System and Component Changes (31601)
D Applicable Procedure Changes (31603)
D Applicable Industry Operating Experience (31604)
D Selected Fundamentals, emphasis on seldom used knowledge and skills (31606)
D Other (30095) (specify)
Instructor Name(s)
Training Method D Preplanned classroom type training D Emergency Response Drill D Required Read D Briefing D Other (specify)
Required Supporting Materials D Supporting materials are attached and are listed below. D Supporting materials are not available; a detailed description is provided (additional sheets are attached if needed).