NRC INSPECTION MANUAL NMSS/FCSS

MANUAL CHAPTER 1247 APPENDIX C6

FUEL FACILITY NUCLEAR CRITICALITY SAFETY INSPECTOR TECHNICAL PROFICIENCY 

TRAINING AND QUALIFICATION
Issue Date: 06/11/14 i 1247 Appendix C6

Table of Contents

Introduction................................................................................................................................ 1

Required Fuel Facility Nuclear Criticality Safety Inspector Training Courses:............................. 1

Refresher Training (as needed): ................................................................................................ 1

Required Rotational Assignment................................................................................................ 2

Fuel Facility Nuclear Criticality Safety Inspector Study Guides................................................... 3

(SG-NCS-1) Regulatory Framework ....................................................................................... 4

(SG-NCS-2) Regulatory Guidance.......................................................................................... 5

(SG-NCS-3) Generic Communications ................................................................................... 7

(SG-NCS-4) Industry Codes and Standards ..........................................................................10

(SG-NCS-5) Fuel Cycle Events .............................................................................................12

Fuel Facility Nuclear Criticality Safety Inspector On-the-Job Activities ......................................14

(OJT-NCS-1) Criticality Safety Inspections ............................................................................15

(OJT-NCS-2) Criticality Safety Codes....................................................................................18

Fuel Facility Nuclear Criticality Safety Inspector Rotational Assignment....................................19

(ROT-NCS-1) Rotational Assignment to PORSB/NMSS........................................................20

Fuel Facility Criticality Safety Inspector Technical Proficiency-Level.........................................22

Form 1: Fuel Facility Nuclear Criticality Safety Inspector Technical Proficiency-Level 

Equivalency Justification ...........................................................................................................23

Revision History for IMC 1247, Appendix C6 ......................................................................Att1-1
Issue Date: 06/11/14 1 1247 Appendix C6

Introduction

Consult with your supervisor prior to beginning the activities or completing the courses in this 

qualification journal. In most cases, you will need to complete the Basic Inspector Certification 

Journal prior to beginning the activities in this Appendix. You may complete the General 

Proficiency requirements contained in Appendix B together with the Technical Proficiency 

requirements outlined in this journal.

Several of the topics have both an individual study guide and on-the-job training. You must 

complete the individual study guide before beginning the corresponding on-the-job training.

Before signing up for any course, be sure that you have checked and have met any 

prerequisites.

Required Fuel Facility Nuclear Criticality Safety Inspector Training Courses:

 F-206S, Fire Protection for Fuel Cycle Facilities Self Study

 (40 hours) SCALE Training Course

Completion of one of the following:

 (80 hours) Hands on Nuclear Criticality Safety (NCS) Program (or equivalent) –

[Note: This class is normally offered by the DOE]

 (40 hours) University of New Mexico – Nuclear Criticality Safety Short Course

Refresher Training:

(To be completed every three years)

 (8 hours) OSHA HAZWOPR Refresher Course or iLearn Health and Safety Training 

Suite as identified in Memorandum dated May 7, 2010, from Catherine Haney to NMSS 

Branch Chiefs (See ADAMS Accession No. ML100200563 for details of equivalent 

iLearn training modules).

 (16 Hours) Refresher Technical Training Seminar as approved by supervisor

 (40 hours) SCALE or MCNP Training (As needed)

Continuing Training:

These classes are suggested for continuing training for inspectors. You may propose alternate 

courses in additional topic areas to your supervisor. 

 NQA-1 Training

 (32 hours) ANS Criticality Safety Meetings

 SCALE or MCNP Training Courses

 University of New Mexico Assessments and Criticality Safety Evaluations 
Issue Date: 06/11/14 2 1247 Appendix C6

Required Rotational Assignment:

Successful completion of the Nuclear Criticality Safety Inspector (NCSI) qualification program 

requires collaboration between Region II and NMSS to ensure the NCSI completes the program 

with sufficient knowledge and skill to be successful.

The rotational assignment (ROT-NCS-1) is the capstone project in the NCSI qualification 

program. This rotation is expected to be performed after the inspector has completed all 

required NCS training courses, a majority of the qualification card and participated on several 

NCS inspections. The inspector will develop a work plan by selecting one or more licensee’s 

processes or activities for in-depth modeling and analysis. The work plan will be reviewed and 

approved by Region II and NMSS management prior to initiating the rotation. Additionally, a site 

visit may be conducted to facilitate the inspector’s understanding and support reconstruction of 

the selected process(es). Thus, the inspector’s rotation should be viewed as a culmination of 

activities performed during the course of several previous inspections.

The cognizant NMSS Branch Chief for NCS will document successful completion of the work 

plan at the conclusion of the rotation. The rotation to FCSS does not apply to NCS inspector 

qualification program candidates assigned to the NMSS branch that is responsible for NCS.
Issue Date: 06/11/14 3 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guides
Issue Date: 06/11/14 4 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guide

TOPIC: (SG-NCS-1) Regulatory Framework

PURPOSE: The purpose of this activity is to acquaint you with the regulations that 

specify the requirements for all aspects of Domestic Licensing of Special 

Nuclear Material. This SG will help you to understand the content of 

nuclear criticality safety portions of the regulations.

COMPETENCY 

AREAS: REGULATORY FRAMEWORK

LEVEL OF 

EFFORT: 80-120 hours

REFERENCES: 1. 10 CFR Part 70

2. 10 CFR Part 76

3. Safety Evaluation Report (SER) for your reference facility

4. License Application for your reference facility

5. ISA summary for your reference facility 

EVALUATION

CRITERIA: Upon completion of this activity, you should be able to do the following:

1. Describe the criticality safety portions of 10 CFR Part 70.

2. Describe the criticality safety portions of 10 CFR Part 76.

3. Describe the purpose of SERs.

4. Describe the interaction between criticality safety licensing and 

inspection.

TASKS: 1. Read and discuss with a qualified NCS inspector or reviewer the 

criticality safety portions of 10 CFR Part 70.

2. Read and discuss with a qualified NCS inspector or reviewer the 

criticality safety portions of 10 CFR Part 76.

3. Discuss the SER for your reference facility with a qualified NCS 

inspector or reviewer.

4. Discuss with a qualified NCS inspector or reviewer the difference 

between inspection and licensing.

DOCUMENTATION: Fuel Facility Operations Inspector Technical Proficiency-Level

Qualification Signature Card, Item SG-NCS-1
Issue Date: 06/11/14 5 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guide

TOPIC: (SG-NCS-2) Regulatory Guidance

PURPOSE: The purpose of this is to familiarize you with the regulatory guidance 

available for NCS inspectors for fuel cycle facilities.

COMPETENCY 

AREAS: REGULATORY FRAMEWORK

LEVEL OF

EFFORT: 60 hours

REFERENCES: 1. NUREG-1520, “Standard Review Plan for the Review of a License 

Application for a Fuel Cycle Facility,” Chapters 2, 3, 5, and 11.

2. NUREG-1513, “Integrated Safety Analysis Guidance Document.”

(ML031340285) 

3. NUREG-1718, “Standard Review Plan for the Review of an 

Application for a Mixed Oxide (MOX) Fuel Fabrication Facility.” 

(ML003741461 and ML003741581)

4. Regulatory Guide 3.71, ‘NCS Standards for Fuels and Material 

Facilities.”

5. FCSS-ISG-01, “Methods for Qualitative Evaluation of Likelihood.”

6. FCSS-ISG-03, “Nuclear Criticality Safety Performance 

Requirements and Double Contingency Principle.”

7. FCSS-ISG-10, “Justification for Minimum Margin of Subcriticality for 

Safety.”

8. FCSS-ISG-12, “Reportable Safety Events per 10 CFR Part 70 

Appendix A.”

EVALUATION

CRITERIA: Upon completion of this activity, you should be able to do the following: 

1. Understand the guidance that the NRC has for criticality safety in 

fuel cycle facilities.

TASKS: 1. Read and discuss with a qualified NCS inspector or reviewer the 

criticality safety portions of NUREG-1520 and NUREG-1718.
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2. Read and discuss with a qualified NCS inspector or reviewer the 

ISA portions of NUREG-1520, NUREG-1513, and NUREG-1718.

3. Discuss Regulatory Guide 3.71 with a qualified NCS inspector or 

reviewer. What standards has your reference facility committed to?

4. Read and Discuss and discuss with a qualified NCS inspector or 

reviewer the criticality safety portions of FCSS-ISG-01, FCSS-ISG03, FCSS-ISG-10, and FCSS-ISG-12.

5. Discuss with a qualified NCS inspector or reviewer the requirements 

for fuel facilities to have criticality accident alarm systems. When 

are criticality accident alarm systems needed?

DOCUMENTATION: Fuel Facility Operations Inspector Technical Proficiency-Level

Qualification Signature Card, Item SG-NCS-2. 
Issue Date: 06/11/14 7 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guide

TOPIC: (SG-NCS-3) Generic Communications

PURPOSE: The purposed of this is to familiarize you with the NRC generic 

communications that have been issued for fuel cycle facilities.

COMPETENCY 

AREAS: REGULATORY FRAMEWORK INSPECTION

LEVEL OF

EFFORT: 80 hours

REFERENCES 1. Bulletin (BL) 91-01, “Reporting Loss of Criticality Safety Controls”

2. BL 91-01, Supplement 1, “Reporting Loss of Criticality Safety 

Controls”

3. Information Notice (IN) 11-06, “Erroneous Criticality Alarm 

Monitoring Signal Caused By Incorrect Data Acquisition Module 

Configuration”

4. IN 10-16, “Failure To Disable Unsafe Geometry Bandsaw Reservior 

Results In Criticality Safety-Related Alert”

5. IN 10-15, “Fuel Cycle Facility Configuration Management Errors”

6. IN 08-14, “Criticality Safety-related Events Resulting from Fissile 

Material Operations under Procedures Not Reviewed by Criticality 

Safety Staff”

7. IN 08-08, “Maintenance Procedures Compromise DoubleContingency of UO2 Powder-Handling Equipment at Fuel Cycle 

Facility”

8. IN 07-30, “Radiological Controls Create Criticality Safety Accident 

Scenario for Fissile Solution Container Transport at Fuel Cycle 

Facility”

9. IN 07-13, “Use of As-found Conditions to Evaluate Criticality-related 

Process Upsets at Fuel Cycle Facilities”

10. IN 06-10, “Use of Concentration Control for Criticality Safety”

11. IN 06-07, “Inappropriate Use of a Single-Parameter Limit as a 

Nuclear Criticality Safety Limit”
Issue Date: 06/11/14 8 1247 Appendix C6

12. IN 05-31, “Potential Non-Conservative Error in Preparing ProblemDependent Cross Sections for Use with the Keno V.A. or Keno-VI 

Criticality Code”

13. IN 05-28, “Inadequate Test Procedures Fails to Detect Inoperable 

Criticality Accident Alarm Horns”

14. IN 05-22, “Inadequate Criticality Safety Analysis of Ventilation 

Systems at Fuel Cycle Facilities”

15. IN 05-13, “Potential Non-Conservative Error in Modeling Geometric 

Regions in the Keno-V.a Criticality Code”

16. IN 05-12, “Excessively Large Criticality Safety Limits Fail to Provide 

Double Contingency at Fuel Cycle Facility”

17. IN 05-05, “Improving Material Control and Accountability Interface 

with Criticality Safety Activities at Fuel Cycle Facilities”

18. IN 04-14, “Use of less than Optimal Bounding Assumptions in 

Criticality Safety Analysis at Fuel Cycle Facilities”

19. IN 94-73, “Clarification of Criticality Reporting Criteria”

20. IN 93-60, “Reporting Fuel Cycle and Materials Events to the NRC 

Operations Center”

21. IN 92-14, “Uranium Oxide Fires at Fuel Cycle Facilities”

22. IN 91-84, “Problems with Criticality Alarm Components/Systems”

23. IN 90-63, “Management Attention to the Establishment and 

Maintenance of a Nuclear Criticality Safety Program”

24. IN 89-24, “Nuclear Criticality Safety”

25. IN 82-21, “Buildup of Enriched Uranium in Effluent Treatment 

Tanks”

EVALUATION

CRITERIA: Upon completion of this activity, you should be able to do the following: 

1. Identify criticality safety problems that have occurred in fuel cycle 

facilities.

2. Identify how licensees can use as found conditions to evaluate 

events at their facilities.
Issue Date: 06/11/14 9 1247 Appendix C6

TASKS: 1. Discuss with a qualified NCS inspector or reviewer how licensees 

can use as found condition to evaluate significant issues at their 

facilities.

2. Discuss with a qualified NCS inspector or reviewer recent problems 

experienced at fuel cycle facilities with their criticality accident alarm 

systems.

DOCUMENTATION: Fuel Facility Operations Inspector Technical Proficiency-Level

Qualification Signature Card, Item SG-NCS-3. 
Issue Date: 06/11/14 10 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guide

TOPIC: (SG-NCS-4) Industry Codes and Standards

PURPOSE: The purpose of this is to familiarize you with NCS industry codes and 

standards that are used by the NRC and fuel cycle facilities.

COMPETENCY 

AREAS: INSPECTION

LEVEL OF

EFFORT: 60 hours

REFERENCES: 1. Regulatory Guide 3.71 Nuclear Criticality Safety Standards for Fuels 

and Material Facilities.

2. ANSI NQA-1 Quality Assurance Requirements for Nuclear Facilities.

3. LA-10860-MS, “Critical Dimensions of systems Containing 235U, 

239Pu, and 233U.”

4. LA-12808, “Nuclear Criticality Safety Guide.”

5. LA-13638, “A Review of Criticality Accidents.”

6. R. A. Knief, “Nuclear Criticality Safety – Theory and Practice,” 

American Nuclear Society.

7. ARH-600, “Criticality Handbook,” W.A. Blyckert, Atlantic Richfield 

Handford Company.

8. NUREG/CR-6698, “Guide for Validation of Nuclear Criticality Safety 

Calculational Methodology.” (ML050250061)

9. TID-7016, “The Nuclear Safety Guide.”

EVALUATION

CRITERIA: Upon completion of this activity, you should be able to do the following: 

1. Describe the significance of the ANSI/ANS 8 standards on the 

criticality safety community. Discuss the involvement of NRC staff 

on the ANS working groups.

2. Describe how the fuel cycle licensees use and commit to the 

ANSI/ANS 8 standards.

3. Discuss ANSI NQA-1 and how it is used in the nuclear criticality 

safety community.
Issue Date: 06/11/14 11 1247 Appendix C6

TASKS: 1. Read and discuss ANSI/ANS-8 Consensus NCS Standards with a 

qualified NCS inspector or reviewer.

2. Discuss with a qualified NCS inspector or reviewer how licensees 

meet the double contingency principle. Discuss the history of the 

double contingency principle and how different organizations have 

different views on the implementation of the double contingency 

principle.

3. Read and discuss ANSI NQA-1.

4. Read and discuss reference 6 (Nuclear Criticality Safety – Theory 

and Practice) the Knief book with a qualified NCS inspector or 

reviewer. Try to identify things that have changed since the book 

was published.

5. Discuss with a qualified NCS inspector or reviewer how single 

parameter limits are used at facilities. Describe the conservatism 

that is established as part of the single parameter limit as compared 

to a calculated limit.

DOCUMENTATION: Fuel Facility Operations Inspector Technical Proficiency-Level 

Qualification Signature Card, Item SG-NCS-4. 
Issue Date: 06/11/14 12 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Study Guide

TOPIC: (SG-NCS-5) Fuel Cycle Events

PURPOSE: The purpose of this is to familiarize you with previous accidents in fuel 

cycle facilities and how these have impacted the regulatory framework and 

the criticality safety community.

COMPETENCY 

AREAS: INSPECTION

LEVEL OF

EFFORT: 80 hours

REFERENCES: 1. NUREG/CR-6410, “Nuclear Fuel Cycle Facility Accident Analysis 

Handbook.”

2. NUREG-1450, “Potential Criticality Accident at the GE Nuclear Fuel 

and Component Manufacturing Facility, May 29, 1991.”

3. NUREG-1198, “Release of UF6 From a Ruptured Model 48Y 

cylinder at Sequoyah Fuels Corporation Facility: Lessons-Learned 

Report.”

4. NUREG-1189, “Assessment of the Public Health Impact From the 

Accidental Release of UF6 at the Sequoyah Fuels Corporation 

Facility at Gore, Oklahoma.”

5. F-206S, “Fire Protection For Fuel Cycle Facilities Self-Study Course 

Manual.”

6. LA-13638, “A Review of Criticality Accidents.”

7. NRC INSPECTION REPORT (IR) NO. 70-1151/2004-001

8. NRC IR 70-143/2006-006

9. NRC IR 70-143/2006-011

10. NRC IR 70-143/2006-012

11. NRC IR 70-143/2006-019

12. NRC IR 70-27/2009-006

EVALUATION

CRITERIA: Upon completion of this activity, you should be able to do the following: 
Issue Date: 06/11/14 13 1247 Appendix C6

1. Understand how previous accidents in fuel cycle facilities have 

impacted the regulatory framework and the criticality safety 

community.

2. Understand how to apply lessons learned from previous criticality 

safety accidents to what to look for when inspecting.

TASKS: 1. Read and discuss how NUREG/CR-6410 applies to criticality safety 

with a qualified NCS inspector or reviewer.

2. Discuss the NFS HEU spill event in 2006 with a qualified NCS 

inspector or reviewer. Discuss the inspection reports (IR) IR 70-

143/2006-006, IR 70-143/2006-011, IR 70-143/2006-012, and IR 

70-143/2006-019, and enforcement actions that were taken.

3. Discuss the Westinghouse Incinerator event in 2004 with a qualified 

NCS inspector or reviewer. Discuss the IR 70-1151/2004-001 and 

enforcement actions that were taken.

4. Discuss the B&W bandsaw event in 2009 with a qualified NCS 

inspector or reviewer. Discuss the IR 70-27/2009-006 and 

enforcement actions that were taken.

5. Discuss with a qualified NCS inspector or reviewer the Sequoyah 

fuels accidents in 1986 and 1992 after reading NUREGs 1198 and 

1189. 

6. Discuss with a qualified NCS inspector or reviewer the GE Near 

criticality event in 1991 after reading NUREG-1450. 

7. Read the UO2 fires portion of the Fire Protection for Fuel Cycle 

Facilities Self-Study Course Manual (F-206S), and discuss with a 

fire safety inspector UO2 fires, and then discuss with a NCS 

inspector or reviewer how fire safety and criticality safety interact.

8. Review LA-13638 and discuss with a NCS inspector or reviewer the 

United Nuclear- Wood River Junction accident in 1964.

9. Review LA-13638 and discuss with a NCS inspector or reviewer the 

Y-12 accident in 1958.

10. Review LA-13638 and discuss with a NCA inspector or reviewer the 

fuel fabrication accident in Japan in 1999. Be able to discuss 

common failures that happen in all of the events. 

DOCUMENTATION: Fuel Facility Operations Inspector Technical Proficiency-Level

Qualification Signature Card, Item SG-NCS-5. 
Issue Date: 06/11/14 14 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector On-the-Job Activities
Issue Date: 06/11/14 15 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector On-the-Job Activity

TOPIC: (OJT-NCS-1) Criticality Safety Inspections

PURPOSE: The purpose of this activity is to familiarize you with the proper method for 

inspecting criticality safety documents and organizations.

COMPETENCY 

AREA: INSPECTION REGULATORY FRAMEWORK

LEVEL OF

EFFORT: 128 hours

REFERENCES: 1. IP 88003, “Reactive Inspection for Events at Fuel Cycle Facilities 

Program.”

2. IP 88015, “Nuclear Criticality Safety Program.” 

3. IP 88016, “Nuclear Criticality Safety Evaluations and Analyses.”

4. IP 88017, “Criticality Safety Alarms.”

5. IP 88020, “Operational Safety.”

6. IP 88025, “Maintenance and Surveillance of Safety Controls.”

7. IP 88070, “Permanent Plant Modifications.”

8. IP 88071, “Configuration Management Programmatic Review.”

9. IP 93800, “Augmented Inspection Team.”

10. IP 98312, “Special Inspection.”

11. ISA summary for designated facility.

EVALUATION

CRITERIA: Upon completion of the tasks, you should be able to do the following:

1. Identify the hazards (nuclear criticality safety, radiation protection, 

chemical safety, and fire protection) associated with your 

designated fuel cycle facility.

2. Identify the IROFS and management measures for a designated 

operation or process to ensure that process operations remains safe 

during normal and credible abnormal conditions.
Issue Date: 06/11/14 16 1247 Appendix C6

3. Identify the controlled parameters and controls, and safety limits for 

a specified process. 

4. Describe the differences between the general types of NCS controls 

used an LEU facility and an HEU facility. 

TASKS: 1. Review the ISA summary for your assigned facility and select a risk 

significant area or process based on the potential safety significance 

as described in the ISA.

2. Review the License Application and procedures used by the 

licensee at your designated facility to review, revise and approve 

procedures. Discuss this process with your mentor or a qualified 

fuel facility inspector.

3. Review the License Application and procedures used by the 

licensee at your designated facility to implement the Corrective 

Action Program (CAP). The License Application requirements for 

the CAP may vary between fuel facilities.

4. Review the License Application and NCS procedures used by the 

licensee at your designated facility to implement the NCS program. 

Discuss the information with a qualified NCS inspector or reviewer. 

5. Obtain a copy of an internal and external audit of NCS. Discuss the 

information with a qualified NCS inspector or reviewer.

6. Identify the existing safety controls and the associated Management 

Measures for Nuclear Criticality.

7. Review the facility’s Operating Procedures for the selected process 

or area. Identify if specific safety limits or criteria for IROFS or 

Management Measures have been translated into the Operating 

Procedures or Postings. 

8. Participate in NCS inspections at a minimum of an enrichment 

facility, an LEU fuel fabrication facility, and an HEU fuel fabrication 

facility. Walk down the areas to observe the implementation safety 

controls. 

9. Discuss the operation and maintenance of the safety controls with 

the workers. Discuss normal and emergency operational 

requirements.

10. Discuss procedural compliance with the workers.
Issue Date: 06/11/14 17 1247 Appendix C6

11. Review the maintenance and surveillance requirements for the 

safety controls as listed in the Management Measures. Review a 

sampling of maintenance records for the maintenance and 

surveillance testing for specific controls.

12. Discuss your evaluation of the operability of the safety controls with 

your supervisor or the qualified criticality safety inspector or 

reviewer person designated as a resource.

DOCUMENTATION: Fuel Facility Criticality Safety Inspector Proficiency-Level 

Qualification Signature Card, Item OJT-NCS-1.
Issue Date: 06/11/14 18 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector On-the-Job Activity

TOPIC: (OJT-NCS-2) Criticality Safety Codes

PURPOSE: The purpose of this activity is to familiarize you with the criticality safety 

codes that you may encounter at licensee’s sites.

COMPETENCY 

AREA: INSPECTION

LEVEL OF

EFFORT: 80 hours

REFERENCES: 1. SCALE Criticality Safety Calculations Course (via ORNL)

2. LA-UR-04-0294, “Criticality Calculations with MCNP5: A Primer.”

EVALUATION

CRITERIA: Upon completion of the tasks, you should be able to do the following:

1. Understand how input/output decks are set up.

2. Be able to identify conservative practices when modeling systems.

3. Understand what the licensee’s go through during an inspection.

TASKS: 1. Have a criticality safety inspector or reviewer assign to you different 

parametric studies to investigate the effects that moderation, 

interaction, enrichment, and geometry can have on a system.

2. Have a criticality safety inspector or reviewer assign you a practice 

criticality safety evaluation to do. Your evaluation should include 

physically measuring your system, creating controls, and defending 

your evaluation to a criticality safety inspector.

3. Review criticality calculations and the validation report for your 

reference facility. Discuss with a qualified criticality safety inspector 

or review your observations about the facilities calculations and 

differences that are observed from facility to facility. Also discuss 

areas in which you determine that licensee may have weak areas 

that need focus during inspections.

DOCUMENTATION: Fuel Facility Criticality Safety Inspector Proficiency-Level 

Qualification Signature Card, Item OJT-NCS-3.
Issue Date: 06/11/14 19 1247 Appendix C6

Fuel Facility Nuclear Criticality Safety Inspector Rotational Assignment
Issue Date: 06/11/14 20 1247 Appendix C6

NCS Inspector Rotational Assignment

TOPIC: (ROT-NCS-1) Rotational Assignment to PORSB/NMSS

PURPOSE: The purpose of this assignment is to help the NCS inspector to become 

thoroughly familiar with the operation, analysis tools and techniques, 

including criticality safety codes, used by the Programmatic Oversight and 

Regional Support Branch (PORSB) at NRC Headquarters. Those 

permanently assigned to PORSB are not required to complete this 

rotation, but should still complete the tasks. 

COMPETENCY 

AREA: TECHNICAL AREA EXPERTISE 

LEVEL 

OF EFFORT: Length of rotation is 6-8 weeks. 

(Duration is dependent upon successful completion of rotation tasks.)

REFERENCES: None 

EVALUATION 

CRITERIA: Upon completion of the tasks, you should be able to: 

1. Demonstrate proficiency in using criticality safety computer codes 

such as SCALE or MCNP to calculate the keff of configurations. 

2. Identify lead technical experts in NMSS, who can provide 

information on issues affecting NCS. 

3. Demonstrate an understanding of fuel facility licensing and how it is 

related to inspection and enforcement activities.

TASKS: Note: The tasks are designed to be accomplished as part of a single 

integrated project1. They do not have to be completed in strict sequential 

order, but all tasks should have been accomplished at the completion of 

task 4. An individual work plan should be completed prior to beginning the 

rotation. This includes selecting a process or activity to focus the project 

on: 

1. Obtain information related to the selected process or activity and 

facility that will be needed to complete the project. This will include 

site specific information from the licensee (e.g. system and process 

 

1

Project examples include examining criticality safety evaluations or analyses for a particular fissile 

material process. Other projects may include examining the licensee’s criticality code validation or CAAS 

detector placement calculations.
Issue Date: 06/11/14 21 1247 Appendix C6

information, NCS evaluations and analysis, NCS program 

documents, etc.) and licensing basis documents (e.g., license 

application, amendment request, staff’s safety evaluation report, 

etc.), from the Project Manager. 

2. Construct and run models using SCALE or MCNP and interpret the 

results to confirm that processes will meet the applicable regulatory 

requirements and commitments (e.g.: be subcritical under normal 

and credible abnormal conditions for a process analysis).

3. Discuss NCS questions and issues related to the project with the 

lead technical experts in PORSB/NMSS, other branches and the 

licensing Project Manager as needed, especially in the following 

areas: 

a. Applicable regulatory requirements and commitments 

b. The application of the double contingency principle

c. Validation (Benchmarking, Area of Applicability, etc.)

d. Techniques used for CAAS detector placement

4. Demonstrate (as a written report described below) how the 

licensee’s analyses and calculations comply with the regulatory 

requirements and license commitments. Justify their acceptability.

If they are not acceptable, identify issues that should be followed up 

on in subsequent inspections or licensing actions. Identify the 

issues to management promptly if they constitute an immediate 

safety concern.

a. Develop Safety Evaluation Report (SER) input, utilizing 

Chapter 5 of NUREG 1520 as a reference. The focus should 

be on applicable SER sections that relate to the project topic. 

b. Develop an inspection plan for the process or activity 

evaluated in this project that can be used in a future 

inspection. 

DOCUMENTATION: Proficiency Level Qualification Signature Card Item ROT-NCS-1
Issue Date: 06/11/14 22 1247 Appendix C6

Fuel Facility Criticality Safety Inspector Technical Proficiency-Level

Signature Card and Certification

Inspector Name: 

__________________________________

Employee 

Initials/Date

Supervisor’s 

Signature/Date

A. Training Courses

SCALE or MCNP training class

Hands on Criticality Safety Course

UNM Nuclear Criticality Safety Short Course

F-206S, Fire Protection for Fuel Cycle Facilities Self Study

B. Study Guides

SG-NCS-1 Regulatory Framework

SG-NCS-2 Regulatory Guidance

SG-NCS-3 Generic Communications

SG-NCS-4 Industry Codes and Standards

SG-NCS-5 Fuel Cycle Events

C. On-the-Job Training Activities

OJT-NCS-1 Criticality Safety Inspections

OJT-NCS-2 Criticality Safety Codes

D. Rotational Assignment

ROT-NCS-1 Rotational Assignment to PORSB/NMSS

Supervisor’s signature indicates successful completion of all required courses and activities 

listed in this journal and readiness to appear before the Oral Board.

Supervisor’s Signature: _____________________________ Date: __________

The appropriate Form 1, Fuel Facility Operations Inspector Basic-Level Equivalency 

Justification, must accompany this signature card and certification, if applicable.
Issue Date: 06/11/14 23 1247 Appendix C6

Form 1: Fuel Facility Nuclear Criticality Safety Inspector Technical Proficiency-Level 

Equivalency Justification

Inspector Name: 

__________________________

Identify equivalent training and experience 

for which the inspector is to be given credit.

A. Training Courses

SCALE or MCNP training class

Hands on Criticality Safety Course

B. Individual Study Guides

SG-CRT-1 Regulatory Framework

SG-CRT-2 Regulatory Guidance

SG-CRT-3 Generic Communications

SG-CRT-4 Industry Codes and Standards

SG-CRT-5 Fuel Cycle Events

C. On-the-Job Training Activities

OJT-CRT-1 Criticality Safety Inspections

OJT-CRT-2 Criticality Safety Codes

D. Rotational Assignment

ROT-NCS-1 Rotational Assignment to 

PORSB/NMSS

Supervisor’s Recommendation Signature/Date ______________________

Division Director’s Approval Signature/Date ______________________

Copies to: Inspector

Human Resources Office

Supervisor
Issue Date: 06/11/14 Att1-1 1247 Appendix C6

Attachment 1

Revision History for IMC 1247, Appendix C6

Commitment 

Tracking 

Number

Accession 

Number 

Issue Date

Change Notice 

Description of Changes Description of 

Training Required 

and Completion 

Date

Comment and 

Feedback Resolution 

Accession Number

N/A ML14051A526

06/11/14

CN 14-012

New inspection manual chapter 

appendix to specify qualification 

requirements for NRC criticality 

safety inspectors. Researched 

commitments for four years and 

found none.

None ML14084A483