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

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

Status: C8:] New

Instructional Designer ADNHHO-TR Z#

Mary Beth Lujan 102295

Concurrence ADNHHO-TR Z#

William Freeman 205098 NCSDCSA-Q Z#

Alicia Salazar-Crockett 230272

Approval NCS Division Leader

Andrew Wysong

Classification Review

~classified

Name

Ernest Elliott

~Alamos NATIONAL LABORATORY - - u f.tua--

Z#

256333

D ouo

Z#

135267

0 Revision 0 Reviewed with no changes

Date:

11/15/l<o

D UCNI D Classified

Signature: Date:

1,/1:r. 'I

.t-Jwclear ~riticality Safety Division

TABLE OF CONTENTS

Qualification Standard: Criticality Safety Analyst (CSA) NCS-QS-001,RO

1.0 Purpose and Scope ........................................................................................................................... 8

2.0 Precautions and Limitations .................................................................................................... ......... 8

3.0 Analysis Methodology ..................... ....... ........................................................................................... 9

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

5.4 Prere<:Ju isite Requirements .... , ....... ,,..; ......... .' ........................................................................... 13

5."5 \ Medic'ar Examination ·Requirements ........................................................................ ... ... ....... 13

5.6 CSA-IT Qualification Requirements ............................................................ .... ..................... 13

5.7 CSA-Q Qualification Requirements ...................................................................................... 13

5.8 CSA-SQ Qualification Requirements ................. .................................................................. 13

5.9 Implementation Methodology ................................................................................................ 16

5.10 Authoring/Reviewing in Additional Duty Areas .......................... .. ....................................... 18

5.11 Mentoring ....................................................................................... .. ......................................... 18

5.12 Examination Requirements ... ................................................................................................ 18

5.13 Equivalencies/Substitute Credit ............................................... .. ...... ... .................................. 18

6.0 Maintenance of Qualification .................................................................................................... ...... 19

6.1 Initial Qualification Period ...................................................................................................... 19

6.2 Continuing Training ...................................................................... ........................................... 1.9

6.3 Requalification Requirements ................................... .................. .......................................... 19

6.4 Qualification Extension ............................................................. .............................................. 20

6.5 . ~os~ pf Qualification and Authorization .. : ............................................................................ 20

7.0 Records ............................................................................ .............. ................................................... 21

8.0 Acronyms .......................................................................... ................... ............................................. 21

9.0 References .......................................................................... .... .......................................................... 22

10.0 Appendices ...................................................................................... ................................................. 22

11.0 Attachments ...................................................................................................................................... 22

Appendix A: Competency Requirements by Qualification Level ...................................................... 23

Appendix 81: CSA-IT Task-to-Training Matrix (CU 1728) ..................................................... ........... 28

Appendix 82: CSA-Q Task-to-Training Matrix (CU 1729) ................................................................. 29

A Los Alamos NATIONAL LABORATORY --EST, 19 .. l'--

Page 2 of 60

...t-Jwclear "triticality Safety Division


Appendix 83: CSA-SQ Task-to-Training Matrix (Cu 1730) ............................................................... 30

Appendix C: Familiarization Activities .................................................... .. ............. ............. ..... ........ ..... 31

Appendix D: Facility Duty Areas (DAs) .. ........................... .. ............... .... ................. ............. ........ ........ 32

Attachment 1: Entry Level Education & Experience ................ ........... ... ..... ................... ................ .... 33

Attachment 2A: CSA-IT Record of Substitute or Completion (CU 1728) .. ..... ................................ 34

Attachment 28: CSA-Q Record of Substitutes (CU 1729) .. .......... .... ................... .. ...... ..................... 36

Attachment 2C: CSA-SQ Record of Substitutes (CU 1730) ............................................................. 38

Attachment 3A: CSA Task Qualification/Calculation Specialist (TQ/CS) ... .................................... 39

Attachment 38: CSA Task Qualification/Facility Specialist (TQ/FS) .............................................. .40

Attachment 3C: CSA Task Qualification/Independent Reviewer (TQ/IR) ...................................... .42

Attachment 30: CSA Task Qualification/Criticality Accident Alarm Specialist (TQ/CAASS) ...... .43

Attachment 4: Competency 10 Process and Facility Knowledge Duty Areas ... ............. .............. .44

Attachment 5: Record of Familiarization Activities ............................................................................. 58

Attachment 6: Record of Completion - Competency 6 CSED Requirement .................................. 59

Attachment 7: Request for Continuing Training Credit ...................................................................... 60

:QAlamos NATIONAL LABORATORY -- U f . )fO--

Page 3 of 60

Nuclear --~riticality Safety Division

History of Revisions

Document Number NCS-QS-001 ,RO

.. LosAlamos NATIONAL LABORATORY -- 1 \T~ ttn --


Action New S-604, RS.

Page 4 of 60

.l:Jt1clear ~r:iticality Safety Division

-QAlamos NATIONAL LABORATORY -- 1U .•MJ - -

Qualification Standard: Criticality Safety Analyst (CSA) NCS-QS-001, RO

1. Throughout:

a. Removed references to NCS/DDL.

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;

Page 5of60

wclear ~ritica lity Safety Division

-QAlamos NATIONAL LABORATORY - - tU. 1't•l--


new crosswalk of program requirements and courses.

16. Appendix D: Remove Duty Areas 10 (LANSCE) and 12 (Balance of Site); added "Waste Storage Areas" to TASS Basement/Vault duty area.

17. Attachment 1: Updated/reformatted table.

18. Attachment 2A:

a. Addressed Competency 10 changes (see Attachment 4 description below).

b. Added column for record of completion of NC SET requirements.

c. Added NCSET website.

19. Attachments 3A, 3B, 3C: renumbered, formerly Attachments 6A, 6B, 6C.

20. Attachment 3A: defined 3 codes (SCALE/MCNP/COG) and added UTrain numbers.

21. Attachment 3B: defined TQ/FS at facility level.

22. Attachment 3D: added new TQ/CAASS.

23. Attachment 4:

a. Updated instructions and signature block/column.

b. Removed "item" from table heading to avoid confusion with UTrain term "item."

c. Removed "Qualification" from Competency 1 title.

d. General Requirements: Moved RR to Att. 2A (CU 1728).

e. Updated requirements in duty area requirements (2.1.1, 2.2.1, etc.) and reformatting for clarification.

f. Removed "pass oral examination" signoff requirement for each DA as it is captured as an automated requirement in UTrain WQ for each DA.

Page 6 of 60

Nuclear ~riticality Safety Division

~A Los Alamos NATIONAL LABORATORY -- EST, 19 .. J - -


g. Added unique facility criticality safety implementing procedures (for example, TA-55AP-522) as ConT to Duty Areas.

h. Added requirements for STO and NNSS

1. Removed LANSCE and SMB

24. Attachments 6A, 6B, 6C: renumbered and resequenced as Attachments 3A, 3B, 3C.

25. Deleted Attachment 6D (TQ/PS).

26. Created new Attachment 3D (TQ/CAASS).

27. Added curricula and course numbers to attachments.

28. Added Attachment 7, Continuing Training.

Page 7 of 60

.,.t-.J u clear ~riticality Safety Division


1.0 Purpose and Scope

This qualification standard describes the training and qualification requirements for individuals working

in the position of Criticality Safety Analyst (CSA) under the Nuclear Criticality Safety Division (NCS) as

the Responsible Office (RO) at Los Alamos National Laboratory (LANL).

The scope of this program encompasses both LANS and subcontractor employees that are involved in

providing technical support to operations and programs as part of the implementation of the LANL and

Facility Specific Nuclear Criticality Safety Program (NCSP).

This standard is implemented in accordance with:

• DOE Order 420.lC, Facility Safety

• DOE-0-426.2, Personnel Selection, Qualification, and Training Requirements for DOE Nuclear

Facilities.

• P 781-1, Conduct of Training Manual

• SD130, Nuclear Criticality Program

Additionally, technical content was derived from:

• ANSVANS-8.26-2007, Criticality Safety Engineer Training and Qualification Program

• DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer Training and Qualification

In accordance with DOE-0-426.2, Criticality Safety Analysts are categorized as "Technical Support

Personnel." This position is alternately referred to as "Criticality Safety Engineer" in ANSVANS-8.26-

2007.

The requirements of this qualification standard are effective when implemented and supersede previous or

conflicting policies, requirements, and procedures. The one exception is that current CSA-ITs may

continue their qualification under the requirements of the active plan that existed when the qualification

process began or any revision thereafter (Appendix B2, Criticality Safety Analyst-Qualified (CSA-A)

Task-to-Training Matrix (CU 1729).

2.0 Precautions and Limitations

Completion of the program does not implicitly authorize a worker to perform CSA activities in a facility.

Additional site, facility-specific access, and on-the-job requirements may be required by the functional

organization before a CSA candidate is authorized tu perform activity-specific operations; facility

specific access and on-the-job requirements are identified by the owning facility or organization.

A worker pursuing initial CSA qualification is considered a Criticality Safety Analyst In Training (CSA

IT). The CSA-IT may not make decisions independently or take actions that could affect facility safety

and shall be under the supervision of one or more qualified CSAs. However, a CSA-IT may

,--QAlamos NATIONAL LABORATORY --EST.190--

Page 8 of 60

.r;..J ~clear ~rlticality Safety Division


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)

3. Criticality Safety Analyst: Senior Qualified (CSA-SQ)

The competencies are:

1. Nuclear Theory 2. Criticality Safety Calculation Methods

3. Critical Experiments and Data

4. Hands on Experimental Training 5. Rules, Standards, and Guides

6. Nuclear Criticality Safety Evaluations

7. Safety Analysis and Control 8. Criticality Accident Alarm System (CAAS) and Criticality Detection Systems (CDS)

9. Accountability Practices

10. Facility Knowledge

QAlamos NATIONAL LABORATORY --nt.,110-- Page 9 of 60

.t-Juclear ~riticality Safety Division


The qualification levels are designed to accommodate varying levels of knowledge, experience, and

expertise (Sections 5.6 -5.8). The overall structure is progressive:

• The CSA-IT includes entry-level requirements, including DOE training modules available

complex-wide and LANL NCSD requirements. CSA-IT is prerequisite to CSA-Q;

• The CSA-Q includes site-level competency requirements categorized as core and facility specific.

Competencies 1 through 9 address requirements common to all CSAs, therefore they are the core

of the program, while Competency 10 addresses facility-specific knowledge requirements,

segmented into unique duty areas (DA) that may be assigned individually. CSA-Q is prerequisite

to CSA-SQ.

• The CSA-SQ includes expanded requirements applicable site-wide.

A graded approach is applied to the definition ofDAs. For example, for high-risk facilities such as TA-

55/PF-4, multiple DAs are identified to provide a robust qualification process and thorough understanding

of fissile material operations. For lower-risk and less complex areas (e.g., EWMO, STO), many facilities

are bundled into one DA under a single Facility Operations Director (FOD).

There are, and may continue to be, fissionable material operations that exist outside of any DA (one such

example is an operation at the Los Alamos Neutron Science Center [LANSCE]). These operations are

typically low hazard, disparate, and few in number and thus it is impractical to make them a separate DA.

Furthermore, qualification in any of the existing DAs would enable a CSA to have the knowledge and

background necessary to support these operations.

Task qualifications (TQ) are used in accordance with DOE-0-426.2, Personnel Selection, Training,

Qualification, and Certification Requirements for DOE Nuclear Facilities, and P781-1, Conduct of

Training, to incrementally qualify analysts to perform work for which he/she has completed training

while pursuing full qualification. A CSA-TQ/x is a CSA that has completed task qualification for task

"x." For example, a CSA-IT may complete requirements for Calculation Specialist while pursuing CSA

qualification, allowing for independent performance of those specific tasks.

The Utrain assignment/tracking structure implements the program design: entry-level training (CU 1728)

is followed by core training (CU 1729) which is then followed by specific DA requirements. Continuing

Training (CU 4260) is assigned to all CSAs. The combination of all curricula comprise qualification.

For example, a CSA assigned to TA-55/PF4/Area 300 completes the following to achieve qualification:

Entry Level

DOENCSET + cu 1728

LANL

Core

cu 1729

Facility DA

+ TA55/300 WQ 2513

Figure 1 demonstrates the full qualification program structure.

~Alamos NATIONAL LABORATORY --EH. 1941--

Continuing

+ Training

cu 4260

Page 10 of 60

Nuclear ~ritical ity Safety Division

-QAlamos NATIONAL LABORATORY - Uf,1t4J-


CSA T

CSA..Q

16---~ - - - - - - JWCMS

I '-----~-------..-·--- -.

CSA-SQ

Figure 1: CSA Qualification Structure

Page 11of60

~t:Jclear ~riticality Safety Division

5.0 Program Elements


5.1 Entry-Level Education and Experience Requirements

• Education requirement: B.S. in nuclear engineering, physics, or a related science field from an

accredited college or university.

• Experience requirement: two (2) years minimum of job related experience, one of which must be

nuclear.

5.2 Alternatives to Entry-Level Education and Experience Requirements

A completed Entry Level Education and Experience Form (Attachment 1) is submitted to the NCS

DL for verification and approval. Alternatives to education and/or experience are evaluated on a case

by-case basis and approved and documented in accordance with P781-3, Exceptions to Training,

Education, and/or Experience Requirements for Nuclear Facility Workers.

Alternatives to education:

• Professional Engineer's license or successful completion of Engineer-In-Training (EIT)

examination may substitute for the B.S. in science or engineering, or

• When combined with related experience, completion of 80 semester hours of technical portions of

an engineering, engineering technology, or related science program, may substitute for the B.S. in

science or engineering, or

• Related experience may substitute for education at the rate of 6 semester hours for each year of

experience, up to a maximum of 60 credit hours. The remaining required credit hours

(approximately 68), must be met with relevant course work.

Alternatives to experience:

• Where course work is related to job assignment, post-secondary education may be substituted for

up to 50 percent (one year) of the "Job Related" experience requirement.

• Job related training may qualify as equivalent to nuclear experience on a one-for-one basis up to a

maximum of one year.

5.3 Exceptions to Training Requirements

Criticality Safety Analysts may satisfy some criteria in Appendix A with academic training and/or

experience; this is processed as an exception to the requirements of this standard, and is documented

on Attachments 2A, 2B and/or 2C (as applicable) and Form 2136, in accordance with P781-3,

Exceptions to Training, Education, and/or Experience Requirements for Nuclear Facility Workers.

~Alamos NATIONAL LABORATORY --Ut. t'f •l--

Page 12 of 60

~uclear ~riticality Safety Division


5.4 Prerequisite Requirements

There are no prerequisite training requirements for this qualification.

5.5 Medical Examination Requirements

There are no medical examination requirements for this qualification.

5.6 CSA-IT Qualification Requirements

The CSA-IT requirements include:

• DOE Nuclear Criticality Safety Engineer Training (NCSET) requirements

• LANL NCSD general program requirements

• Task Qualification

While in CSA-IT status, the CSA-IT shall perform tasks only under the supervision of one or more

criticality safety analysts, or as allowed by task qualification (Section 4.0 Program Design).

5.7 CSA-Q Qualification Requirements

The CSA-Q qualification requirements include:

• CSA-IT requirements

• ten competency areas, including core and facility specific requirements. Initial qualification ,

requires completing the core requirements for Competencies 1-9 and at least one of the duty

areas identified in Appendix D. The specific duty area to be completed for initial and

subsequent additional qualification is assigned by the NCS-DL.

Additional DAs should be mastered as the CSA gains experience throughout the Laboratory and are

assigned at the discretion of the NCS-DL.

5.8 CSA-SQ Qualification Requirements

The CSA-SQ qualification requirements include:

1. all CSA-Q requirements;

2. CSA-SQ curricula;

3. Facility Knowledge for the following six (6) Duty Areas:

• TA5S 400 Area • One (1) additional TASS duty area • EWMO • NNSS • Two (2) additional duty areas listed in Appendix D

4. "CSA Task Qualification/Independent Reviewer (CSA TQ/IR)"

S. instructor training and serving as an instructor (for example, in the Fissionable Material

Lo~Alamos NATIONAL LABORATORY --UT, IUJ--

Page 13 of 60

I

I

I

Nuclear ~ritica lity 3afety Division

Handler certification program);


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 ~

Specialist.

~Alamos NATIONAL LABORATORY --UT. tUJ--

Page 14of60

11

11

~ticlear "'Crlticality Safety Division


Table 1. CSA Qualification Structure - continued

Lcvd Work Scope

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

Page 15 of 60

II

[,I

i,I

I I

..r;:.J uclea r ~riticality Safety Division


Table 1. CSA Qualification Structure - continued

Level Work Scopr Traini11g l~cquirrmcnts

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

~Alamos NATIONAL LABORATORY --Ut . t• •J--

Page 16of60

uclear e:riticality Safety Division


qualified criticality safety analysts (CSA-Q/CSA-SQ). As allowed by DOE 0 426.2, when qualified and

authorized to perform specific tasks, the CSA-TQ may perform those specific tasks independently.

Throughout the qualification and requalification process, continuing training is required.

Table 2 defines the CSA qualification program implementing instructions, roles, and responsibilities

T bl 2 CSA I a e . f I t f mp cmen m2 ns rue ions an dRI o es an dR "b"li . espons1 1 ties Step Action

1 The NCS-DL formally assigns the worker to the CSA qualification program.

2 The newly assigned CSA candidate completes the Entry Level Education & Experience form

(Attachment 1) and submits it to the NCS-DL for verification and approval.

3 The NCS-DL performs a technical review of the completed Attachment 1; determines training and

qualification needs for the individual worker using substitutes forms (Attachments 2A, 2B, 2C);

and requests exceptions using Form 2136 for alternatives to experience and/or education, and

training substitutions based on worker's education and experience.

4 The Training Specialist assigns the appropriate UTrain curricula/worker authorization activities.

5 The newly assigned CSA candidate completes the Criticality Safety Analyst - In Training (CSA-

IT) requirements (CU 1728).

6 The NCS-DL and the CSA candidate develop a proposed path/schedule for qualification, including

the assignment of mentors (CSA-Q/SQ) and task qualifications. The NCS-DO and CSA candidate

meet periodically to discuss the CSA candidate's progress.

7 The CSA candidate completes the assigned knowledge requirements (TQs and CSA-Q/CU

1729/1730 as applicable).

8 A CSA-Q/SQ provides the CSA candidate with oral knowledge checkouts, mentoring, and

oversight on performance requirements, ensuring that the candidate has the requisite knowledge

and/or demonstrated satisfactory performance for each item (TQs and CSA-Q/CU 1729/1730 as

applicable).

9 The NCS-DL ensures completion of the qualification standard requirements and signs the required

forms as applicable.

10 The Training Specialist records all completed requirements in UTrain.

11 The NCS-DL authorizes the qualified worker in the UTrain Worker Qualification and

Authorization System (WQAS) to perform CSA activities.

12 Steps 6 through 11 are repeated, as applicable, for additional qualification assignments (such as

Duty Areas) or advancing to the next qualification level.

~A • LosAlamos

Page 17 of 60 NATIONAL LABORATORY --01,19.0--

~uclear ~citicality Safety Division


5.10 Authoring/Reviewing in Additional Duty Areas

The qualified CSA may author a CSED for a process anywhere on the site as long as either the author

or reviewer is qualified on the facility duty area where the process is resident.

In the case where the author is a qualified CSA but not qualified in the duty area, the reviewer serves

as the qualified oversight for the author to satisfy the DOE 0 426.2 requirement. This function does

not compromise the ability of the reviewer to provide unbiased technical judgment of the adequacy of

the evaluation.

If the CSA is qualified in TA55/PF-4 Areas 100, 200, 300, or the Basement, Vault, and Waste

Storage Areas, then the CSA may author CSEDs in any of those areas independent of the

qualification of the independent reviewer.

The operations in TA55/PF-4 Areas 100, 200, 300, and the Basement, Vault, and Waste Storage

Areas are similar enough that qualification in one provides a sufficient technical basis and

understanding of the facility to act as the author in any of those areas.

5.11 Mentoring

Mentoring is essential to developing the knowledge, skills, and abilities required for this program. It

provides guided practice on any program-related topic, thereby enhancing the qualification of the

CSA or providing professional development for more experienced CSAs. It is an expert- and

experience-based element of the qualification program that complements formal Systematic

Approach to Training (SAT) based instruction; it does not replace the formal training and

qualification program. Mentoring is completed in accordance with P78 l. l, Conduct of Training, and

NCS-AP-003 Training and Mentoring.

5.12 Examination Requirements

When needed, examinations are developed in accordance with P781-1, Conduct of Training. An oral

examination is administered for Competency 10, Process/Facility Knowledge per CT-SB-CSA-OBR-

631, "Criticality Safety Oral Board Requirements. "

5.13 Equivalencies/Substitute Credit

The NCS-DL may grant equivalency for specific competency areas, based on education, past

experience, and/or training obtained either locally or at other sites/facilities. Substitution for

Competency 6 should be carefully evaluated to ensure LANL requirements are adequately satisfied.

These equivalencies are documented in the UTrain System as "substitutes" using Attachment 2A, 2B,

2C and Form 2136 in accordance with P781-3.

NATIONAL LABORATORY -- IU.111AJ--

Page 18 of 60

.tluclear ~riticality Safety Division


6.0 Maintenance of Qualification

6.1 Initial Qualification Period

Upon completion, the qualification for the CSA-Q or CSA-SQ is valid for 2 years, whereupon

requalification requirements apply.

6.2 Continuing Training

After a CSA has been qualified and authorized to work, the CSA must maintain all continuing

training requirements. The continuing training program is designed to maintain and enhance the

knowledge and skills required to perform assigned duties, and may occur through required reading,

briefings, attendance at seminars and lectures, etc.

Continuing training addresses the following elements, as applicable:

• significant facility system and component changes

• applicable procedure changes

• selected fundamentals, and

• applicable industry operating experience

Continuing training is tracked in UT rain and is conducted throughout the qualification period. If all

continuing training requirements are not completed during the period, the worker is considered

unqualified for the position and is not allowed to perform tasks associated with lapsed qualifications

until they are successfully completed. However, the worker may continue to independently perform

job tasks/assignments for which still qualified.

The continuing training program consists of the following elements at a minimum:

• Required reading, briefings, or other NCSD sponsored assignments;

• Periodic lectures, training seminars, or other professional development events - minimum of

12 per year (Attachment 7, Request for Continuing Training).

6.3 Requalification Requirements

Requalification is conducted upon completion of the qualification period and includes:

• Completion of requirements formally identified as a refresher or retraining occurrence

• Completion of continuing training as specified in 6.2 Continuing Training.

• Continued satisfactory execution of CSA duties, as determined by a review of work product.

The NCS-DL documents in the WQAS that the qualified CSA has continued to satisfactorily perform

criticality safety duties and has completed all training requirements of this program.

-QAlamos NATIONAL LABORATORY --UT.11143--

Page 19 of 60

..t-Jwclear ~riticality Safety Division


If additional requirements are identified for CSA qualification, these requirements will be evaluated

for implementation in the initial or continuing training phase (see 3.0, Analysis Methodology).

6.4 Qualification Extension

Qualification extensions are handled in accordance with P781-2, Qualification and Certification

Extensions.

6.5 Loss of Qualification and Authorization

The NCS-DL may revoke or limit a CSA's qualification for the following reasons:

• performance deficiencies,

• unfit to assume duty,

• failure of requalification requirements (including examinations),

• medical disqualification,

• failure to maintain proficiency,

• failure to complete required training, and/or

• extended absence from duties.

Qualification and authorization to perform work may be regained after all training requirements have

been met and the NCS-DL reauthorizes the CSA.

The NCS-DL must determine when qualification will be revoked or limited to specified work

activities/tasks. The NCS-DL must document the revocation or limitation in a memorandum to the

CSA, the CSA's direct management (if outside NCS), and the worker's training record. The

memorandum must specify the reasons, the restrictions, and the conditions for reinstatement of

qualification. The Training Specialist and the NCS-DL develop a remediation plan to correct the

deficiencies. The CSA regains qualification upon successful completion of the remediation plan

(reinstatements are recorded as UTrain 27947).

When a CSA has been absent from this qualification program's duties, the following requirements

apply:

• Greater than three months, but less than 12 months: selected retraining (e.g. required

reading, written examinations, oral examinations and/or performance evaluation, as deemed

necessary by the NCS-DL) must be completed prior to reassigning duties for which

qualification is required. The two-year requalification date remains the same as it was before

the absence.

• Greater than 12 months: comprehensive examinations and performance evaluations must be

given to determine weak areas. Retraining and reexamination must be required in areas of

weakness, and upon successful completion, a new qualification date may be established.

-QAlamos NATIONAL LABORATORY --l!ST,1943--

Page 20of60



• 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

Page 21of60

Nuclear riticality

Safety Division Qualification Standard: Criticality Safety Analyst (CSA)

NCS-QS-001,RO

9.0 References

1) DOE-0-420.lC, Facility Safety

2) DOE-0-426.2, Personnel Selection, Training, Qualification, and Certification Requirements for DOE

Nuclear Facilities

3) DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer Training and Qualification

4) P781-1, Conduct of Training

5) P781-2, Qualification and Certification Extensions

6) P781-3, Exceptions to Training, Education, and/or Experience Requirements for Nuclear Facilities

7) SD-13 0, Nuclear Criticality Program

8) ANSl/ANS-8.26, Criticality Safety Engineer Training and Qualification Program

9) ANSI/ ANS 8.3, Criticality Accident Alarm System

10.0 Appendices

Appendix A: CSA Competency Requirements by Qualification Level

Appendix B: Task-to-Training Matrices

B 1: Criticality Safety Analyst-In Training (CSA-IT) Task-to-Training Matrix (CU 1728)

B2: Criticality Safety Analyst-Qualified (CSA-Q) Task-to-Training Matrix (CU 1729)

B3: Criticality Safety Analyst-Senior Qualified (CSA-SQ) Task-to-Training Matrix (CU 1730)

Appendix C: Familiarization Activities

Appendix D: Facility Duty Areas (DAs)

11.0 Attachments

Attachment 1: Entry-Level Education & Experience

Attachment 2A: CSA-IT Record of Substitutes or Completion (CU 1728)

Attachment 2B: CSA-Q Record of Substitutes (CU 1729)

Attachment 2C: CSA-SQ Record of Substitute (CU 1730)

Attachment 3A: CSA Task Qualification/Calculation Specialist (CSA-TQ/CS)

Attachment 3B: CSA Task Qualification/Facility Specialist (CSA-TQ/FS)

Attachment 3C: CSA Task Qualification/Independent Reviewer Specialist (CSA-TQ/IR)

Attachment 3D: CSA Task Qualification/Criticality Accident Alarm Specialist (CSA-TQ/CAASS)

Attachment 4: Competency 10 Process and Facility Knowledge Duty Areas

Attachment 5: Record of Familiarization Activities

Attachment 6: Record of Completion: Competency 6 CSED Requirements

Attachment 7: Request for Continuing Training Credit

A Los Alamos NATIONAL LABORATORY --Uf.t••,--

Page 22 of 60

uclear ·~riticality Safety Division


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.

Page 23of60

uclear ~riticality Safety Division


Competency

3. Critical Experiments and Data

4. Hands-On Experimental Training

5. Rules, Standards, and Guides

"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

and Response.

Page 24 of 60

Nuclear 10riticality Safety Division


Competency

6. Nuclear Criticality Safety Evaluations

QAlamos NATIONAL LABORATORY -- EST~ l9<1J --

Training Level

Training Content 00 00 0 u ~

I

-... < 0 0 rJ)

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

Page 25 of 60

uclear ~riticality Safety Division

Competency


Training Level

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.

8.1.6. Discuss LANL NCS Emergency Response procedure

8.1.7. Participate in Criticality Accident Response (Tabletop, Exercise, or Actual)

8.1.8. Discuss LANL NCS Potential Process Deviation response procedure

8.1.9. Participate in Process Deviation Response (Tabletop, Exercise, or Actual)

Page 26 of 60

x

x

x

x

x

x x

x

x

x

x

x x

x

x x x

x x

x x

x x x

x x x x x x x x

...r;Juclear ~riticality Safety Division


Competency

9. Material Accountability Practices

10. Process and Facility Knowledge

A Los Alamos NATIONAL LABORATORY --tJT.lllUJ--

Training Level

Training Content rL!. rL!. O' ~ ~

I

< O' O' rL!. Eo- Eo- u

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

Page 27of60

~uclear ""Criticality Safety Division


Appendix 81: CSA-IT Task-to-Training Matrix (CU 1728)

Competency (Training Con(ent

Reference>

1 Nuclear Theory (1.1, 1.2, 1.3)

Criticality Safety 2 Calculation Methods

(2.1, 2.2)

Critical Experiments 3 and Data

(3.1 , 3.2) Hands on

4 Experimental

Training Course (NA)

Rules, Standards, 5 and Guides

(NA)

Nuclear Criticality Safety Evaluations

6 (NCSE) (6.1)

Safety Analysis 7 and Control

(NA) Criticality Accident

Alarm System (CAAS)

8 and Criticality

Detection Systems (CDS) (NA)

Accountability 9 Practices

(NA) Process/Facility

10 Knowledge (NA)

LANL and NCSD specific procedures,

policies, etc., as applicable

-QAlamos NATIONAL LABORATORY __ ,,,, ... . q --

l:ITraln # Perform111nce

(substitute#.) Item Title Requirement Evaluatton

(substlll!te1 NCSET Modules

19171 (20056) 1: Introductory Nuclear Criticality 19172 (20057) Physics

NA NA 19174 (20058) 2: Neutron Interactions 19176 (20059) 3: The Fission Chain Reactions

4: Neutron Scattering and Moderation NCSET Modules

19629 (20061) 6: Introduction to Diffusion Theory 19630 (20062) 7: Introduction to the Monte Carlo 19633 (20065) Method

13: Measurement & Development of NA NA Cross Section Sets

19631 (20063) 19632 (20065) 8: Hand Calculation Methods Part 1

9: Hand Calculation Methods Part 2

NCSET Module Item 19628 (20060)

5: Criticality Safety Limits NA NA

NA NA NA NA

NA NA NA NA

NCSET Modules 10:Criticality Safety in Material

20183 (20187) Processing Operations Part 1 20184 (20188) 11: Criticality Safety in Material NA NA 20185 (21050) Processing Operations Part 2

12: Preparation of Nuclear Criticality Safety Evaluations

NA NA NA NA

NA NA NA NA

NA NA NA NA

NA NA NA NA

Per Per Per Per Attachment 2A Attachment 2A Attachment 2A Attachment 2A

Page 28of60

Nuclear t:riticality Safety Division


Appendix 82: CSA-Q Task-to-Training Matrix (CU 1729)

Qualification Standard Requirements Based on Program Evolution

NCS-AP-002, RO CT-NCS-CSA-QS-604, Revisions 0-5 (December 2012- October 2016) Requirements*

(November 2016+)

Competency UTraln Item Performance UTraln Item"* Evaluation Requirement* (Training Content) (substitute)

(substitute) (substitute)

1 Nuclear Theory 19043 (19109) Exam 19043 NA 34550, 35047, and 19063 (1.1, 1.2, 1.3)

Criticality Safety Exam Perform 3 calculations

19048 (19111) 19048, 19422 with a mentor. 2 Calculation Methods 19422 (19423) Practical Evaluation: Item# 19124 34550,35047, and 19063

(2.1, 2.2, 2.3) 19124 (19125)

Participate in a criticality

Exam: experiment or subcritical

19049, 19480 experiment Critical Experiments

3a: 19049 (19112) demonstration covered

3 and Data 3b: 19480 (20194) Participation NCSP as part of NCSP hands 19063

(3.1, 3.2) Course 19103

on Functional Area 4

3c Item# 19103 (19138)

Hands on Participation NCSP Attend the DOE Hand-

Experimental Training On Training Course 4 Training Course

19063 Course 19063 Item# 19063

19063

(4.1) (19113) Rules, Standards,

5a: 19096 (20196) 5 and Guides Exam 19096, 19662 NA No change

(5.1 , 5.2) 5b: 19662 (20195)

Read and discuss three (3) CSEDs (Level 3) with

Nuclear Criticality Exam 19052 a mentor Item# 19061

6 Safety Evaluations 19052 (19114) Practical Evaluation (19199, per Att.5) 34550,35047,and 19063 (NCSE)

(6.1, 6.2) 19061, 19101 Perform 3 CSEDs with a mentor.

Item# 19101 (19137, per Att.5)

Safety Analysis 7 and Control 19055 (19115) Exam 19115 NA No change

(7.1) Criticality Accident

Participate in 1 criticality Alarm System (CAAS) 8 and Criticality 19057 (19116) Exam 19057

incident exercise 34550

Detection Systems (may be table-top)

(CDS) (8.1) OJT 35258

Accountability 9 Practices 19058 (19117) Exam 19058 NA No change

(9.1)

Process/Facility 10 Knowledge 19060 (21049) Oral board Per Attachment 4 No change

(10.1)

. . • Performance Requirements from previous rev1s1on CT-NCS-CSA-QS-604 remain valid for NCS-AP-002 **34550 = UNM Short Course 35047 = UNM Assessments Course 19063 =DOE Hands On Course

~Alamos NATIONAL LABORATORY Page 29 of 60

tJclear ~rlticality Safety Division


Appendix 83: CSA-SQ Task-to-Training Matrix (Cu 1730)

Competency (Training Content)

1 Nuclear Theory

(NA) Criticality Safety Calculation

2 Methods (2.4)

3 Critical Experiments and Data

(NA) Hands on

4 Experimental

Training Course (NA)

Rules, Standards, 5 and Guides

(5.3) Nuclear Criticality Safety Evaluations

6 (NCSE) (6.3)

Safety Analysis 7 and Control

INAl Criticality Accident Alarm System (CAAS)

8 and Criticality Detection Systems (CDS) INAl

9 Accountability Practices

(NA)

10 Process/Facility Knowledge

(NA)

Management Review

-A Los Alamos NATIONAL LABORATORY -- Hf1lto4I)--

UTraln Item Perfonnahce Requirement Evaluation (Substrtute) (subsUtute)

NA NA NA

9129 (19130) Review 3 calculations NA

NA NA NA

NA NA NA

19144 (20237) NA Exam

19131 (19132) Review 3 CSEDs with a mentor NA

NA NA NA

Participate in 1 criticality incident NA exercise NA

OJT 35259

NA NA NA

NA Per Attachment 4

Oral Board Duty Areas

21471 NA NA

Page 30of60



Appendix C: Familiarization Activities

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

QAlamos Page 31of60 NATIONAL LABORATORY

--UY, \.,_.1--

~uclear 'l'triticality Safety Division


Appendix D: Facility Duty Areas (DAs)

Duty Area Number of Faclllty Complexity Famlllarlzatlon

f Crltlcalltv Safety) Activities*

1 TA55/PF-4: Area 100 Medium 15



4 TA55/PF-4: Area 400 High 20

5 TA55/PF-4: Basement, Vault, and Waste Storage Areas Medium 15

6 CMR Low 10

7 EWMO Low 10

8 STO Low 10

9 NNSS Medium 15

* The NCS-DL may change the number of required familiarization activities based on the candidate's experience.

~Alamos NATIONAL LABORATORY __ .,,,,,, ... __ Page 32of60

.r;Juclear ~riticality Safety Division


Attachment 1: Entry Level Education & Experience

To be completed by CSA candidate:

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)

Approval and Records NCS-DL Approval Signature

Training Records Signature

~Alamos NATIONAL LABORATORY -- c,ir. t•4i - -

- u

n

Z#

Z#

D Yes 0 No

D Yes D No

-.~ .,_

Date

Date

Page 33 of 60



Attachment 2A: CSA-IT Record of Substitute or Completion (CU 1728)

Section A: To be completed by NCS-DL for substitute credit (attach Form 2136)

OR CSA candidate for completion credit

DOE Nuclear Criticality Safety Engineer Training (NCSET) http://ncsc.llnl.gov/trainingMain.html

Substitute Credit Completion

Accepted Objective Evidence Completion Date NCSET Substitute Module Modules (to be completed Attached (to be completed

bvDLJ (to be completed by DL) by CSA)

NCSET Module 1 #19171

Modules D Education D Degree

Nuclear Theory D Experience D Training and qualification Module 2 #19172

NCSET Nuclear 1-4 1 Theory Item #19171

Item #20056 record from approved

Modules 1-4 Item #19172 Item #20057 organization Module 3 #19174

Item #19174 Item #20058 D Certificate

Item #19176 Item #20059 D Other Module 4 #19176

NC SET NCSET

D Degree Module 6 # #19629 Calculation

Modules D Education D Training and qualification

Methods Monte Criticality Safety D Experience

record from approved Carlo organization Module 7 #19630

Modules 6, 7,13 Calculation Item #20061

D Certificate Methods 6, 7, 13 Item #20062

D Other Item #19629 Item #20065 Module 13 #19633

2 Item #19630 Item #19633

Module 8 #19631 ------------------

Hand ---------------- --------------ltem#19631 Item #20063 Calculations

Item #19632 Item #20064 Module 9 #19632 Part 1 & part 2 Modules 8 & 9

NC SET NCSET Module D Degree Module 5 #19628

Critical Critical D Education D Training and qualification

3 Experiments Experiments D Experience record from approved

Module 5 Item #19628 Item #20060 organization

D Certificate D Other

Module 10#20183

Nuclear NCSET Criticality Safety D Education D Degree

Nuclear Criticality Evaluations D Experience D Training and qualification Module 11 #20184 4

Safety (NCSE) Item #20187 record from approved Evaluations Item #20183 Item #20188 organization

Modules 10 - 12 Item #20184 Item #21050 D Certificate Item #20185 D Other Module 12 #20185

CSA Candidate (if requesting completion credit) Signature Z# Date

NCS-DL Approval (if requesting substitute credit) Signature Z# Date

Training Records Signature Z# Date

<Q Alamos NATIONAL LABORATORY - - l!oT. l o!i 1U--

Page 34 of 60

.,.t.Juclear ~riticality Safety Division


Attachment 2A: CSA-IT Record of Substitute or Completion (CU 1728) - continued

Section B: To be completed by CSA candidate for completion credit

This list is includes NCSD Guides and Administrative Procedures current at the time of this document's publishing.

Upon each use: 0

0

Verify and update the list using the NCSD webpage or shared drive "Common" Document the title and latest version of the required document

Name Z#

Signature & Z# General LANL NCSD Requirements (OJT 19060) CSA-Q/SQ

Demonstrate through discussion with and to the satisfaction of a CSA-Q/SQ, understanding of the followin 1 documents:

1.1 SD 130, Nuclear Criticality Safety Program

1.2 NCS-QS-001,Qualification Standard: Criticality Safety Analyst (CSA)

1.3 NCS-AP-003, Training and Mentoring

1.4 NCS-AP-004, Criticality Safety Evaluations

1.5 NCS-AP-007, Criticality Safety Evaluation Review

1.6 NCS-AP-008, Document Review

1.7 NCS-AP-009, Fissionable Material Operational Reviews

1.8 NCS-AP-010, Potential Process Deviation Response

1.9 NCS-AP-012, Criticality Accident Planning and Response Procedure

1.10 NCS-AP-0014.01, FMO-ID Prescription

1.11 NCS-AP-0014.04, Worl< Request Entry

1.12 NCS-AP-0014.05, Internal Worl< Acceptance

1.13 CT-SB-CSA-OBR-631, Criticality Safety Analyst (CSA) Oral Board Requirements

1.14

1.15

1.16

1.17


Date

Q Alamos NATIONAL LABORATORY --C:U , 1'1111.) --

Page 35 of 60

uclear ~ ritica lity Safety Division


Attachment 28: CSA-Q Record of Substitutes (CU 1729)

To be comoleted bv NCS-DL for substitute credit (attach Form 2136J Name Z#

Com~eney Acc.-d&ifJa't!Me ObJective E'fldent&"(QEJ ~tac~ment Reaulred

D Education D Degree Nuclear Theory D Experience D Training and qualification record from approved

1 Item #19043 D DOE-0 1135 Compliant organization Program D Certificate

Item #19109 D Other Criticality Safety D Experience D Training and qualification record from approved

Calculation Methods D DOE-0 1135 Compliant organization 2 Item #19048 (MCNP) Program D Certificate

Item #19422(Hand Item #19111 D Other

- - - - - - - -~~!~~La_t!q~~l- - - - - - - Item# 19423 ,. __ ... _ ... ------------------------------------- -----------------------------------------------------Performance Requirement: D Experience D Training and qualification record from approved

3 mentored calculations D Other organization Item #19124 Item# 19125 D Other

Critical Experiments and D Experience D Training and qualification record from approved Data D DOE-0 1135 Compliant organization

3 Item #19049 Program D Certificate Item #19480 (Criticality ltem#19112 D Other

Accidents) Item# 20194 -- ... --- - i:>eifomiari&;-Req-uiremerif: - - • ci - E"xiierieiice - - - - - - - - - - - - - - - - - - - - - • o-·-r;:ainiii~laiicf Ciuaiific-atTori -reccircffrom-aiii>rCiiiecf - ---Participate in a criticality D Other organization

experiment demonstration D Certificate Item #19103 (NCSP) Item #19138 D Other

Hands on D Experience D Training and qualification record from approved

4 Experimental Training D DOE-0 1135 Compliant organization

Training Course Program D Certificate Item #19063 (NCSP) Item #19113 D Other

Rules, Standards, D Experience D Training and qualification record from approved

5 and Guides D DOE-0 1135 Compliant organization

Item #19096 (ANSI/ANS 8 Program D Certificate

---------~t~~~!:l!~~l- ------- Item #20196 D Other ... ---....

Rules, Standards, - ·o - E"xiierienc:e - - • • • • • - - - --- • ---- - - - • o • ·-r;:ainiii9-aiicf CiuaTific-atiori -recorci- irom -aiii>rCiiieci- - • - • and Guides D DOE-0 1135 Compliant organization Item #19662 Program D Certificate

(DOE Requirements and D Other National Standards) Item #20195

Nuclear Criticality Safety D Education D Degree D Experience D Training and qualification record from approved

6 Evaluations (NCSE) D DOE-0 1135 Compliant organization

Item #19052 Program D Certificate

Item #19114 D Other ------ - - - - -Reaci-anc:f ciiscuss _3 __ -- --o - E"xiierian·c-e ·· • -- • --- --- • --- • • ·- • · c:i- ·t;:arn-in9-aii<f Ciuaifricatfori .record"fro·m-aiii>roiiaci· • • • • CSEDs with a mentor D Other organization

Item #19061 D Other Item #19199 ------ - i:>eifomiciri&;-Raq·u-iremerif: • • ·o - E"x?erian·c-e - - - -- - - - - - -------- • • - • o • ·-rr:arn-in9-anci-Ciuaiificatfori -recorci- irom-aiii>rCiiieci· • • - -

3 mentored CSEDs D Other organization Item# 19101 Item #19137 D Other

.QAlamos NATIONAL LABORATORY --H1~1!!11Al --

Page 36of60

Nuclear Criticality Safety Division


Attachment 28: CSA-Q Record of Substitutes (CU 1729) - continued

Ci>bjectlve Evidence {OE) " Competency ACC8P;,ted Sut$tltute Attachment ReauJred .:

Safety Analysis D Experience D Training and qualification record from approved

7 and Control D DOE-0 1135 Compliant organization Item #19055 Program D Certificate

Item #19115 D Other Criticality Alarm System D Experience D Training and qualification record from approved

8 (CAS) and Criticality D DOE-0 1135 Compliant organization

Detection Systems(CDS) Program D Certificate Item #19057 ltem#19116 D Other

D Experience D Training and qualification record from approved

9 Accountability Practices D DOE-0 1135 Compliant organization

Item #19058 Program D Certificate ltem#19117 D Other

Process/Facility D Experience D Training and qualification record from approved

10 Knowledge D DOE-0 1135 Compliant organization

Item #19060 Program D Certificate Item# 21049 D Other

ADDroval and Records NCS-00 Approval Signature Z# Date


Q Alamos NATIONAL LABORATORY -- n1 ~ 1 ot.1.J --

Page 37 of 60

Nuclear e::riticality Safety Division


Attachment 2C: CSA-SQ Record of Substitutes (CU 1730)

To be comoleted bv NCS·DL for substitute credit (attach Form 2136J Name

Competency

1 Nuclear Theory

Criticality Safety Calculation Methods

2 Performance Requirement: Review 3 calculations

Item# 19129

3 Critical Experiments and Data

Hands on 4 Experimental Training

Trainina Course

Rules, Standards,

5 and Guides

Item# 19144 (ANSllANS-8.23, 8.24)

Nuclear Criticality Safety Evaluations (NCSE)

6 Performance Requirement: Review 3 CSEDs with a Mentor

Item# 19131

7 Safety Analysis

and Control

Criticality Alarm System (CAS)

B and Criticality Detection

Systems (CDS) Item# 19135

9 Accountability Practices

10 Process/Facility Knowledge Per Section 5.8



~Alamos NATIONAL LABORATORY --Of1l'IO--

Z#

Accepted Subs.tltute Objective Evidence (OE)

Attachment Re1Julred

NA NA

D Experience D Training and qualification record from D DOE-0 1135 Compliant Program approved organization D Other D Certificate

Item #19130 D Other

NA NA

NA NA

D Experience D Training and qualification record from D DOE-0 1135 Compliant Program approved organization D Other D Certificate

ltem#20237 D Other

D Experience D Training and qualification record from D DOE-0 1135 Compliant Program approved organization

D Certificate Item #19132 D Other

NA NA

D Experience D Training and qualification record from D DOE-0 1135 Compliant Program approved organization

D Certificate Item# 19136 D Other

NA NA

D LANL Experience D LANL Qualification

Z# Date

Z# Date

Page 38of60



Attachment 3A: CSA Task Qualification/Calculation Specialist (TQ/CS)

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)

MCNP: 19048(sub19111)

D Competency 2: Calculational Methods SCALE: 35262 (sub 35336) COG: 35263 (sub 35337)

D Competency 5: Rules, Standards, and Guides 19096 (sub 20196) and (ANSI/ANS 8 and DOE Requirements and National Standards) 19662 (sub 20195)

Section C: Practical Knowledge/Demonstration

D D SCALE D COG MCNP OJT: 34367 (sub OJT: 19124 (sub 19125) OJT: 34365 (sub 35096)

35099)

Perform 3 calculations under guidance of a CSA-Q who is also qualified to the same code. Briefly describe or list the document suooorted.

1)

2)

3)



-;Q Alamos NAl"IONAL LABORATOR Y -- !ST. 1943 - -

Date

Date

Date

Z# Date

Z# Date

Page 39 of 60



Attachment 38: CSA Task Qualification/Facility Specialist (TQ/FS)

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.


Facility D TA55 D CMR D EWMO D STO WQ7340 WQ 7341 WQ7347 WQ 7348


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

D NNSS WQ7349

UT rain#

34550 (sub 19109)

19096 (sub 20196) and 19662 (sub 20195)

34550 (sub 19114)

19055 (sub 19115)

34550 (sub 19116)

19058 (sub 19117)

33343

NT 34372

CSA-Q Date

CSA-Q Date

Page 40of60

..._~uclear ~riticality Safety Division


Attachment 38: CSA Task Qualification/Facility Specialist (TQ/FS)continued

Section C: Practical Knowledge/Demonstration UTrain #

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




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)

D TA55 OJT 35151



Q Alamos NATIONAL LABORATORY -- IJT. lt4;1--

D CMR OJT 35152

D EWMO D STO D NNSS OJT 35153 OJT 35154 OJT 35155

Z#

Z#

Dale

Dale

Page 41 of 60

Nuclear --~riticality Safety Division


Attachment 3C: CSA Task Qualification/Independent Reviewer (TQ/IR)

The Independent Reviewer Task Qualification allows a CSA-Q to perform independent reviews of CSEDs.


Section A: PrereQuisites

D Completion of CSA-Q (Cu #1729 and assigned Duty Area WQ)


Read and discuss DOE-STD-1134, "Review Guide For Criticality Safety Evaluations" CSA-SQ Date

with a CSA-Q, TQ/IR.

Section C: Complete: 1. Previous CSA-SQ qualification -OR-- UTrain # 2. Practical Knowledge Demonstration

D 1. Prior Qualification: The CSA was previously qualified as an IR; objective evidence is attached or on file.

Qualification Site: Date:

D 2. Practical Knowledge Demonstration

a) Complete 5 CSEDs as the author. FMO# Title

CSED 1

CSED2

CSED3

CSED4

CSED5

b) Review 3 CSEDs under the guidance of a CSA-Q TQ/IR or CSA-SQ (list NCS database#/title)

Procedure# CSED 1

CSED2

CSED 3

Approval and Records NCS-DL Approval Printed Name

Training Records Printed Name

A Los Alamos NATIONAL LABORATORY --or.,,.,., __

Title

Signature Z#

D WQ 3164 Signature Z#

OJT 25077

OJT 25078

Verification

Date

Date

Page 42 of 60

,.J:Juclear e:riticality Safety Division


Attachment 30: CSA Task Qualification/Criticality Accident Alarm Specialist (TQ/CAASS)

The Criticality Accident Alarm Specialist (CAAS) allows a CSA-Q to perform Criticality Accident Alarm System Evaluations.



D Completion of CSA-Q (Cu #1729 and assigned Duty Area WQ)

D Completion of CSA TQ/CS (select software used)

D MCNP D SCALE WQ: 3035 WQ: 6897


D Competency 2: Calculational Methods: SCALE, 35262 (sub 35336) -- OR--

D CSA TQ/CAAS MCNP Transport Code, 35346

Section C: Previous CAASS qualification -- OR--Practical Knowledge Demonstration

D Prior Qualification: The candidate was previously qualified as a CAASS.

Qualification Site: Date:

Practical Knowledge Demonstration

D Perform an exercise based on a given analysis/task, to be selected by the NCS-DL, and verified by a CSA-Q/SQ also qualified as a CAASS (same code).

Title

Approval and Records

NCS-DL Approval Printed Name

Training Records Printed Name

~A .. Lo sAlamos

NATIONAL LABORATORY - - CST. 19-43--

D WQ 7422

I Date

Signature Z#

Signature Z#

'

D COG WQ: 6898

CSA-SQ Date

UTraln #

OJT35333

OJT 35334

CSA-SQ Date

Date

Date

Page 43 of 60



Attachment 4: Competency 10 Process and Facility Knowledge Duty Areas

Competency 10 is divided into "duty areas" where a specific facility/FMO area constitutes a duty area;

Section S. 7 describes how this competency fits into the overall qualification construct.

This competency is administered as follows:

• Attachment 4 is completed as requirements are met; signature requirements are specified.

• The duty areas may be completed concurrently or independently of each other.

• All TASS facility duty areas require Common/Overarching Infrastructure and Ancillary Systems

upon initial qualification only (for example Area 300); it is not repeated for additional TASS duty

area qualification .

.. LosAlamos NATIONAL LABORATORY --tu. 1 .... 1--

Page 44 of 60

Name

#

FAC

DA

1.

2.

3.

4.

5.

6.

Nuclear ~~riticality Safety Division


Z#

Signature & Z#

Competency 10: Process and Facility Duty Areas for CSA-Q CSA-Q/SQ or Date

CSO I ORS I SME (unless otllerwise noted)

TA-55

T A-55, Common: Overarching Infrastructure and Ancillary Systems (OJT 25081)

Complete the Facility Specialist task qualification (CSA-TQ/FS) for TA-55. TS

Describe the overall facility layout, including where common systems are located and how systems interact between areas.

a. Demonstrate understanding of the following systems/devices in PF-4, in b. particular how they could impact criticality safety:

c. a. MC&Asystem b. Ventilation (Zone 1, Zone 2, and Zone 3) d.

c. Wet Vacuum System e.

d. Nitric Acid Distribution System f. e. Central Chilled Water f. Positive Pressure Chilled Circulating Water System

g.

g. Negative Pressure Chilled Circulating Water System h.

h. Industrial Waste Water i. i. Process Gas Supplies (Nitrogen, Argon, Helium, etc.) j . j. Caustic Waste Drain k. Acid Waste Drain k.

1. Reagent Transfer Devices I.

m. Limited Volume Chilled Circulating Water Systems m. n. Ori/Ni Trains

Dry Vacuum n.

0.

p. Compressed Air systems, including Instrument Air and Process Air o.

q. Cart and hand carry process p. r. Fire suppression system

Sumps (in the basement) q.

s. t. Trolley r.

S.

t.

Tour the Radioactive Liquid Waste facility . Understand the relationship and material interactions with PF-4.

Tour PF-5.

Tour the RLUOB Radiological Areas and understand the NCS interface.

-QAlamos Page 45 of 60 NATIONAL LABORATORY

-- UT. lt•J--



Name

# 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.

-A Los Alamos NATIONAL LABORATORY --u•~ttO--

Z#

Signature & Z# CSA-Q/SQ or CSOorORS

unless otlrerwise noted

CSA-Q!SQ

CSA-QISQ

CSA-QISQ

CSA Candidate

Date

Page 46 of 60

..t:-J uclea r 'l:"triticality Safety Division



FAC TA55 DA PF-4, 200 Area (OJT 25083)

1. Describe this area's physical systems and layout

2.

3.

4.


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



QAlamos NATIONAL LABORATORY --l!ST. 19-4)--


unless otherwise noted

CSA-Q!SQ

CSA-Q!SQ

CSA-Q!SQ

C.'iA Candidate

Page 47 of 60

Date

..JNuclear

...-Criticality Safety Division


Name



1. Describe this area's physical systems and layout

2.

3.

4.



Room305

Room306

Room 308

Room309

Room 317

Room 318

Room 319

Room327

Room 333

Room329


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.

~Alamos NATIONAL LABORATORY --u•,10--

Z#



CSA-QISQ

CSA-QISQ

CSA-Q!SQ

CSA Candidate

Date

Page 48 of 60

..!:Nuclear ~riticality Safety Division


Name



I. Describe this area's physical systems and layout.

2.

3.

4.



Room401

Room420

Room429

Room433

Room409


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 .

.. Q Alamos NATIONAL LABORATORY -- 1.u.1w.u--

Z#


unless otlierwise noted

CSA-QISQ

CSA-QISQ

CSA-QISQ

CSA Cand idate

Date

Page 49 of 60

Nuclear ~rlticality Safety Division


Name


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


RoomB05

RoomB13

RoomB40

RoomB56

Room B57 I B58

RoomB35

RoomB38

Vault Room A

Vault Room B

Vault Room C

VaultRoomD

Vault RoomE

Vault RoomF

VaultRoomG

VaultRoomH

..... Q Alamos NATIONAL LABORATORY --ESTl943 --

Z#



Date

Page 50 of 60

"'-N.uclear · riticality Safety Division


Name Z#

Signature & Z#

# Competency 10: Process and Facility Duty Areas for CSA-Q CSA-Q/SQ or Date CSOorORS

(unless otllerwise noted)

FAC TA55 DA PF-4 Basement, Vault, and Waste Storage Areas** (OJT 25086)

Vault Room I

Vault Room J

Vault Room K

Vault Room L

Vault Room M

TRU Waste Pad

High Efficiency Neutron Counter (HENC) Pad

Shipping & Receiving pad outside PF-4

Conduct at least 3 tours of the general basement/vault and waste storage CSA·QISQ

3. areas with a qualified CSA. The CSA-IT should discuss issues of importance CSA ·QISQ

to criticality safety to the CSA-Q/SQ's satisfaction. Using Appendix Casa guide, conduct at least 15 Familiarization Activities CSA Camiidale

4. in this DA, (Note, these Familiarization Activities are in addition to the above requirements.) Document on Attachment 5.

* * Vault entry may require respirator qualification

,A .. LosAlamos

NATIONAL LABORATORY -- E5T1 194l --

Page 51of60

Name

#

FAC DA

1.

2.

3.

4.

5.

. Nuclear ~~riticality Safety Division


Z#

Signature & Z#

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.

lll. Non-Destructive Assay (NDA) (CMR-S 103-00) Vlll.

IV. Packaging, Unpacking, Shipping & Receiving (CMR-7112-00)

v. LEU Solution Staging (CMR-BSMT-00) VI. Hot Cell Operations (CMR-9133-00, CMR-9163-00)

Vil. Analytical chemistry (Various) Vlll. Waste Services (CMR-WS-00)

NATIONAL LABORATORY

--ur.••".J-- Page 52 of 60

Name

#

FAC DA

6.

7.

,.[:Juclear ~riticality Safety Division


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 .

.. QAlamos NATIONAL LABORATORY --Ui T'. 19.0 --

Z#

Signature & Z# CSA-Q/SQ or Date CSOorSME


a.

b.

c.

d.

CSA Candidate

Page 53of60

Name

#

FAC DA

I.

2.




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)

~-A • LosAlamos

• NATIONAL LABORATORY __ ..,,,,,.,,., __

Z#


Date

(unless otlierwise noted)

TS

FOD or designee

a. SB-GLEWMO

b.

C.l

c.ii

C.lll

C.IV

c.v

c.vi

c.vii

c.viii

c.ix

Page 54 of 60

Name

#

FAC DA

3.

4.

5.

6.

7.

8.

9.

10.




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.

Q Alamos NATIONAL LABORATORY --01. 11 .. 1--

Z#

Signature & Z# CSA-Q/SQ or Date CSOorORS


a.

b.

K:;.

<I.

a. b. c. d. e. f. g. h. i.

j .

a. b. c. d.

e.

a.

b.

c.

d.

e. CSA Ca11dida1e

Page 55 of 60

#

FAC DA

1.

2.

3.

4.

5.

6.

7.

8.

I;Juclear ~riticality Safety Division


Signature & Z#

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



T A-66. Building I a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in



NISC a. a. Walk down fissile material operations (FMO) with a CSA-Q qualified in



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.


;QAlamos Page 56 of 60 NATIONAL LABORATORY

--UTt,,._, __

Name

#

FAC DA

l.

2.

3.

4.

5.

6.

7.

8.

9.

Nuclear ·~ riticality Safety Division



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.

NATIONAL LABORATORY

-- tn,,t•• - -

Z#

CSA-Q/SQ Date

orCSO

TS

Page 57 of 60

J;.Juclear ~Criticality Safety Division


Attachment 5: Record of Familiarization Activities

Name:

Facility/ Area:

Brief Description of Familiarization Activities

~Alamos NATIONAL LABORATORY - - 1n11to--

I Z#:

Hrs Signature Date

Page 58of60

Nuclear -~rltica lity Safety Division


Attachment 6: Record of Completion - Competency 6 CSED Requirement

Name

Item# 19061 :

1.

2.

3.

Item# 19137:

1.

2.

3.

-QAlamos NATIONAL LABORATORY --EST0 19.43--

Z#

Read and discuss 3 CSEDs with a mentor Document Title and Number Date Mentor's Signature & Z#

Perform 3 CSEDs with a mentor Document Title and Number Date Mentor's Signature & Z#

Page 59of60

NLJclear ~ritica l ity Safety Division


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).

Submitted CSA Name

Appraval and Records NCS-DL Approval Signature


Q Alamos NATIONAL LABORATORY -- i ) t , t • -0 --

Signature Z# Date

Z# Date

Z# Date

Page 60of60