Issue Date: 10/26/11 C1-1 1246

APPENDIX C1

TRAINING REQUIREMENTS AND QUALIFICATION JOURNAL FOR 

FUEL CYCLE TECHNICAL REVIEWER

I. TRAINING REQUIREMENTS

A. Applicability

The training described below is required for all fuel cycle technical reviewers assigned to 

perform safety reviews of fuel cycle license applications.

B. Training

1. Required Initial Training.

a) Self-Study and On-The-Job Training:

(1) NRC Orientation.

(2) Code of Federal Regulations.

(3) Office Instructions.

(4) Regulatory Guidance.

(5) Fuel Cycle Licensing Branch Manual.

(6) Industry Codes and Standards.

(7) NRC Management Directives.

(8) Review of significant events at fuel cycle licensees.

(9) Directed Review of Selected Licensing Case Work.

b) Core Training. These courses establish minimum formal classroom 

training requirements. Refer to Section 1246-09 for exceptions to 

these requirements.

(1) Root Cause/Incident Investigation Workshop (G-205)

(2) OSHA Indoctrination Course (G-111)

(3) NMSS Radiation Worker Training (H-102) or “Site Access 

Training” (H-100)

(4) General Health Physics Practices for Fuel Facilities Directed 

Self-Study Course (F-102S) or equivalent

(5) Fuel Cycle Processes Directed Self-Study Course (F-201S) or

(6) Uranium Enrichment Process Directed Self study Course

(F-204S)

(7) Integrated Safety Analysis Course (F-103) or Hazards Analysis 

for DOE SARs and QRAs

c) Specialized Training. Depending on the fuel cycle license reviewer's 

previous work experience and planned reviewer activities, additional 

courses may be required in order to gain knowledge necessary for 

specialized licensing activities. Headquarters branch management 

will make this determination on an individual basis. For example, if a 

license reviewer is assigned activities in one of the areas listed 

below then that reviewer should attend the appropriate training 

course or have equivalent experience as determined by their 

management.

(1) Nuclear Criticality Safety Directed Self-Study Course (F-101S)

(2) Air Sampling for Radioactive Material Course (H-119)

(3) Transportation of Radioactive Materials Course (H-308)

(4) Environmental Monitoring for Radioactivity (H-111)
Issue Date: 10/26/11 C1-2 1246

(5) Fire Protection for Fuel Cycle Facilities Directed Self-Study 

Course (F-206S)

2. Supplemental Training. Additional training beyond that identified as Core 

Training. This training will be determined by the individual's supervisor and 

will depend on the individual's previous work experience and planned 

inspection or licensing activities in specific areas.

3. Refresher Training. Refresher training will be conducted every three 

years following initial certification. Refresher training will be determined by 

management on a case-by-case basis.

II. QUALIFICATION JOURNAL

Applicability

This NRC License Reviewer Qualification Journal implements NRC Manual Chapter 

1246, Appendix A, by establishing the minimum training requirements for personnel 

assigned to perform license reviews for fuel facilities. 

The NRC License Reviewer Qualification Journal serves as a guideline for the 

development of a Qualification Journal, and establishes the minimum training 

requirements consistent with NRC Manual Chapter 1246. The Qualification Journal must 

provide traceable documentation to show that minimum requirements are met for each 

license reviewer.

The NRC License Reviewer Qualification Journal consists of a series of qualification 

guides and signature cards. Each signature card is used to document task completion, 

as indicated by the appropriate signature blocks. The corresponding qualification guide 

establishes the minimum knowledge levels or areas of study that must be completed for 

each signature card. 

Most of the qualification guides are divided into sections. The review sections of the 

qualification guides identify references with general application to the license reviewer's 

qualification. The license reviewer is expected to have a general familiarity with these 

references. Other sections of the qualification guides identify specific references that 

have direct application to the license review discipline. The license reviewer is expected 

to demonstrate detailed knowledge of the license review specific references.

In order to support the review of upper tier documents, programs, and policies, the license 

reviewer's immediate supervisor will assign one or more specific fuel facilities as 

reference facilities. The selection of a reference facility is intended to provide the license 

reviewer's management with the ability to tailor the qualification process to the experience 

and training level of the license reviewer, and to meet the needs of the NRC. The use of 

specific real world material will reinforce the qualification process.
Issue Date: 10/26/11 C1-3 1246

LICENSE REVIEWER QUALIFICATION JOURNAL

Fuel Cycle License Reviewer

 

(Name) (Title) (Branch) (Section)

To complete your qualification as a Fuel Cycle License Reviewer you are to complete the 

following signature cards. All signoffs shall include the signature of the responsible reviewer 

and the date. Maintain these cards in a notebook along with any background or written 

material required by the program. This notebook will comprise your NRC License Reviewer 

Qualification Journal.

Signature

When Complete Date

1. NRC Orientation 

First Line Supervisor

2. Code of Federal Regulations 

First Line Supervisor

3. Office Instructions 

First Line Supervisor

4. Regulatory Guidance 

First Line Supervisor

5. Fuel Cycle Licensing Branch

Manual 

First Line Supervisor

6. Industry Codes and Standards 

First Line Supervisor

7. NRC Management Directives 

First Line Supervisor

8. Review of Significant Fuel 

Cycle Events 

First Line Supervisor

9. Directed Review of Selected

Licensing Case Work _________________ ______

First Line Supervisor

10. Formal Training _________________ ___ ___

First Line Supervisor
Issue Date: 10/26/11 C1-4 1246

Qualification Board _______________________ _________

Requirement Met Second level supervisor

or Board Chairman 

Recommended as a qualified _______________________ _________

license reviewer Second Level Supervisor

Certification Memo Issued _______________________ _________

Second Level Supervisor 
Issue Date: 10/26/11 C1-5 1246

Qualification Card 1

NRC Orientation

A. Site Orientation Initials Date

1. New employee processing ___________________ _____

package completed Employee

2. Facility tour and introduction ____________________ _____

First Line Supervisor 

B. NRC Organization

1. Review of NRC headquarters

and regional organization ___________________ _ _____

Employee

2. Discussion of NRC organization

____________________ _____

First Line Supervisor 
Issue Date: 10/26/11 C1-6 1246

Qualification Card 2

Code of Federal Regulations (CFR)

Initials Date

A. Familiarization with selected

CFR parts completed _______________ _____

Employee

B. Discussion completed on CFR

parts related to the fuel cycle

license review program 

_________________ _____

First Line Supervisor
Issue Date: 10/26/11 C1-7 1246

Qualification Card 3

Office Instructions

Initials Date

A. Familiarization with office

policies and procedures _______________ _____

Employee

B. Discussion completed on

office policies and procedures _____________________ ______

First Line Supervisor
Issue Date: 10/26/11 C1-8 1246

Qualification Card 4

Regulatory Guidance

Initials Date

A. Review of regulatory guidance

1. Regulatory Guides __________________ _____

Employee

2. Information Notices

/Bulletins __________________ _____

Employee

3. NUREGs __________________ _____

Employee

4. Generic Letters __________________ _____

Employee

5. Federal Register Notices

__________________ ______

Employee

6. NRC Branch Technical

Positions __________________ ______

Employee

B. Discussion of regulatory guidance

with application to the fuel

cycle license review program __________________ _______

First Line Supervisor 
Issue Date: 10/26/11 C1-9 1246

Qualification Card 5

Fuel Cycle Licensing Branch Manual

Initials Date

A. Review of appropriate 

portions of Licensing

Branch Manual completed __________________ _____

Employee

B. Discussion of Licensing Branch

Manual and its relation

to the fuel cycle license 

review program ____________________ _____

First Line Supervisor
Issue Date: 10/26/11 C1-10 1246

Qualification Card 6

Industry Codes and Standards

Initials Date

A. Review of selected codes

and standards completed _________________ _______

Employee

B. Discussion of the application

of codes and standards in the

fuel cycle license review

program __________________ ________

First Line Supervisor
Issue Date: 10/26/11 C1-11 1246

Qualification Card 7

NRC Management Directives

Initials Date

A. Review of selected portions of

the NRC Management Directives 

completed ________________ _____

Employee

B. Discussion of the application

of the NRC Management Directives

to the fuel cycle license review

program

 

First Line Supervisor
Issue Date: 10/26/11 C1-12 1246

Qualification Card 8

Review of Significant Fuel Cycle Events

Initials Date

A. Review of selected significant

historical fuel cycle events __________________ _____

Employee

B. Discussion of the importance

of these events and lessons

learned _____

First Line Supervisor
Issue Date: 10/26/11 C1-13 1246

Qualification Card 9

Directed Review of Selected Licensing Case Work

Initials Date

A. Review of selected licensing

casework _______________ _______

Employee

B. Discussion by first line supervisor of directed review of the

selected casework and its relation to the fuel cycle license

review program ________________ _______

First Line Supervisor
Issue Date: 10/26/11 C1-14 1246

Qualification Card 10

Formal Training

A. CORE TRAINING: Initials Date

1. Root Cause/Incident Investigation

Workshop (G-205) __________________ _____

Training Coordinator

2. OSHA Indoctrination Course (G-111) ___________________ _____

Training Coordinator

3. NMSS Radiation Worker Training 

Course (H-102) ____________________ _____

Training Coordinator

4. General Health Physics Practices for

Fuel Facilities Directed Self-Study

Course (F-102S) or equivalent ____________________ _____

Training Coordinator

5. Fuel Cycle Processes Directed 

Self-Study Course (F-201S) or 

Uranium Enrichment Process Directed

Self study Course (F-204S) ____________________ _____

Training Coordinator

6. Integrated Safety Analysis Course

(F-103)or Hazard analysis for DOE SARs

and QRAs ____________________ _____

Training Coordinator

B. SPECIALIZED TRAINING

Other training courses required for license reviewers performing licensing actions in 

specific areas:

Course Title Course # Initials Initials Date

________________________________ ___________________ _ ______

Supervisor Training Coordinator

________________________________ ____________________ _______

Supervisor Training Coordinator

________________________________ ____________________ _______

Supervisor Training Coordinator

________________________________ ____________________ _______

Supervisor Training Coordinator
Issue Date: 10/26/11 C1-15 1246

Qualification Guide 1

NRC Orientation

A. Site Orientation

1. The qualifying individual should read and complete, as appropriate, the following 

forms for processing into the NRC:

a. Personnel information

b. Health insurance elections

c. Retirement plan elections

d. Savings elections (e.g. U.S. Savings Bonds, TSP, etc.)

e. Fitness for Duty requirements and physical examination

f. Any other forms which may be required by NRC Office of

Human Resources

g. Forms for issuance of tagged, controlled NRC equipment

h. Payroll forms and time cards

i. Regulatory Information Tracking System (RITS)

2. The First Line Supervisor should orient the qualifying individual to the facility as 

follows:

a. Tour the facility and introduce the qualifying individual to the staff

2. Indicate to the qualifying individual the location of controlled documents, 

reference material, supplies, office equipment, classrooms, etc.

B. NRC Organization

1. The qualifying individual should review and become familiar with:

a. Organizational charts of division, NMSS, regions and headquarters and 

overall NRC organization (NUREG-0325)

b. Role of Headquarters in policy and interpretation of regulations

c. Role of NRC General Counsel

d. Role of NRC Inspector General

e. Role of NRC Public Affairs

f. Role of NRC Office of Investigations
Issue Date: 10/26/11 C1-16 1246

g. Role of NRC Office of Enforcement

h. Physical location of NRC offices and regions

i. Role of NRC as a regulatory agency 

(1) 10 CFR Part 1 (Organization)

(2) Atomic Energy Act of 1954, as amended

(3) Energy Reorganization Act of 1974, as amended

(4) NRC Enforcement Policy (NUREG 1600)

(5) Incident Response Plan (NUREGs 0728 and 0845) 

(6) Energy Policy Act of 1992

2. The First Line Supervisor should discuss NRC organization and role with the 

qualifying individual to ensure the qualifying individual has a full understanding of 

NRC's organization and mission and the role of the license reviewer in that 

mission.
Issue Date: 10/26/11 C1-17 1246

Qualification Guide 2

Code of Federal Regulations (CFR)

A. A selection of currently applicable CFR Parts should be made by the First Line 

Supervisor. The selection should include the references listed below and be documented. 

The qualifying individual should be expected to have a general knowledge of the topics 

addressed in the references. This review may be accomplished by self-study, 

study-quizzes, briefings, or discussions. 

1. 10 CFR Part 1 Statement of organization and general information

2. 10 CFR Part 2 Rules of practice for domestic licensing proceedings and 

issuance of orders

3. 10 CFR Part 9 Public Records

4. 10 CFR Part 19 Notices, instructions and reports to workers; inspections

5. 10 CFR Part 20 Standards for protection against radiation (includes selected 

Questions and Answers, Q & As)

6. 10 CFR Part 21 Reporting of defects and noncompliance

7. 10 CFR Part 30 Rules of general applicability to domestic licensing of 

byproduct material

8. 10 CFR Part 40 Domestic licensing of source material

9. 10 CFR Part 51 Environmental protection regulations for domestic licensing

10. 10 CFR Part 61 Licensing requirements for land disposal of radioactive waste

11. 10 CFR Part 70 Domestic licensing of special nuclear material

12. 10 CFR Part 71 Packaging and transportation of radioactive material

13. 10 CFR Part 73 Physical protection of plants and materials

14 10 CFR Part 74 Material control and accounting of special nuclear material

15. 10 CFR Part 75 Safeguards on nuclear material

16. 10 CFR Part 76 Certification of Gaseous Diffusion Plants

17. 10 CFR Part 95 Security facility approval and safeguarding of national security 

information and restricted data

18. 10 CFR Part 170 Fees for facilities, materials, import and export licenses and 

other regulatory services under the Atomic Energy Act of 

1954, as amended

19. 10 CFR Part 171 Annual fees for reactor operating licenses, and fuel cycle 

licenses and materials licenses, including holders of 

certificates of compliance, registrations, and quality assurance 

program approvals and government agencies licensed by 
Issue Date: 10/26/11 C1-18 1246

NRC

20. 29 CFR Part 1910 Occupational Safety and Health Standards

21. 40 CFR Part 61, National Emissions Standards for Hazardous Air Pollutants

Subpart I

22. 40 CFR Part 190 Environmental Radiation Protection for Nuclear Power 

Operations (Uranium Fuel Cycle Standards)

B. Following completion of the qualifying individual=s self study of the listed 10 CFR Parts, a 

discussion will be held with the qualifying license reviewer by the First Line Supervisor to 

test the qualifying license reviewer=s knowledge of these Parts. To the extent possible, 

recent application of various sections, new regulatory initiatives, and current industry 

issues should be emphasized.
Issue Date: 10/26/11 C1-19 1246

Qualification Guide 3

Office Instructions/Regional Procedures

A. Office/Division Policies and Procedures

1. Read the applicable Policy and Procedures Manual

2. The qualifying individual should review the office/division/NRC policies and 

practices on:

a. Travel, including Management Directive 14.1 Official Temporary

Duty Travel

b. Telephone use

c. Policies on use of annual, sick, and excused leave, including Bulletin 

4135, Leave Administration

d. Work schedule, including NRC Appendix 4136, Hours of Work and

Premium Pay

e. Use of government equipment, including computers (NUDOCS and 

ADAMS) and Management Directive 13.1, Property Management

f. Union activities, including Management Directive 10.102, 

Labor-Management Relations Program for Federal Employees

g. Communications outside NRC

h. Policies on outside employment and acceptance of gifts

i. Participation in political activities

j. Routing of mail and procedures for sending mail and materials (via U.S. 

Mail, Federal Express, etc.), including Management Directive 3.23, Mail 

Management

k. Ordering of documents (e.g NUREGs)

l. Emergency and evacuation procedures

m. Employee appraisal system and Individual Development Plan (IDP)

(1) Employee trial period (Management Directive 10.14 

Employment and Staffing)

(2) Employee appraisals (Management Directive 10.67, Non-SES 

Performance Appraisal System)

n. Differing Professional Views or Opinions (Management Directive 10.159, General 

Personnel Management Provisions)

B. The First Line Supervisor should discuss these policies and practices with the qualifying 

individual to ensure that the qualifying individual has a full and complete understanding.
Issue Date: 10/26/11 C1-20 1246

Qualification Guide 4

Regulatory Guidance

A. A selection of currently applicable regulatory guidance should be identified by the First 

Line Supervisor. It should be noted that not all of the referenced regulatory guides will be 

applicable to each license reviewer's area of responsibility. These references should be 

selected from those listed below and should be documented. The qualifying individual 

should be expected to have a general knowledge of the topics addressed in the 

references. The review may be accomplished by self-study, study-quizzes, briefings, or 

discussions. Note that many Regulatory Guides reference or endorse industry codes 

and standards listed in Qualification Guide 6. Study of corresponding and subtier codes 

and standards is recommended. 

1. Regulatory Guides (use latest revision)

3.2 Efficiency Testing of Air-Cleaning Systems Containing Devices for 

Removal of Particles

3.3 Quality Assurance Program Requirements for Fuel Fabrication Plants

3.7 Monitoring of Combustible Gases and Vapor in Fuel Fabrication Plants

3.10 Liquid Waste Treatment System Design Guide for Fuel Fabrication Plants

3.12 General Design Guide for Ventilation Systems of Fuel Fabrication Plants

3.16 General Fire Protection Guide for Fuel Fabrication Plants

3.21 Quality Assurance Requirements for Fuel Fabrication Plants

3.34 Assumptions Used for Evaluating the Potential Radiological 

Consequences of Accidental Nuclear Criticality in a Uranium Fuel 

Fabrication Plant

3.52 Standard Format and Content for the Health and Safety Sections of 

License Applications for Fuel Cycle Facilities

3.55 Standard Format and Content for the Health and Safety Sections of 

License Renewal Applications for Fuel Fabrication

3.71 Nuclear Criticality Safety Standards for Fuels and Materials Facilities 

(Draft DG-3013 published 1/98) (Guide Withdraws RG 3.1, 3.4, 3.43, 

3.45, 3.47, 3.57, 3.58, 3.68, 3.70, and 8.12)

4.15 Quality Assurance for Radiological Monitoring Programs (Normal 

Operations) - Effluent Streams and the Environment

4.16 Monitoring and Reporting Radioactivity in Releases of Radioactive 

Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing 

and Fabrication Plants and Uranium Hexafluoride Production Plants

8.1 Radiation Symbol

8.2 Guide for Administrative Practices in Radiation Monitoring
Issue Date: 10/26/11 C1-21 1246

8.4 Direct Reading and Indirect Reading Pocket Dosimeters

8.5 Criticality and Other Interior Evacuation Signals 

8.6 Standard Test Procedure for Geiger Muller Counters

8.7 Instructions For Recording and Reporting Occupational Radiation 

Exposure Data

8.8 Information Relevant to Ensuring that Occupational Radiation Exposures 

at Nuclear Power Stations Will Be As Low As Reasonably Achievable

8.10 Operating Philosophy for Maintaining Occupational Radiation Exposure 

As Low As Is Reasonably Achievable

8.11 Applications of Bioassay for Uranium

8.13 Instruction Concerning Prenatal Radiation Exposure

8.14 Personnel Neutron Dosimeters

8.21 Health Physics Surveys for Byproduct Material at NRC Licensed 

Processing and Manufacturing Plants

8.24 Health Physics Surveys During Enriched Uranium 235 Processing and 

Fuel Fabrication

8.25 Air Sampling in the Workplace

8.29 Instruction Concerning Risks from Occupational Radiation Exposure

8.30 Health Physics Surveys in Uranium Mills

8.31 Information Relevant to Ensuring that Occupational Radiation Exposures 

at Uranium Mills Will Be As Low As Reasonably Achievable

8.33 Quality Management Program

8.34 Monitoring Criteria and Methods to Calculate Occupational Radiation 

Doses

8.35 Planned Special Exposures

8.36 Radiation Doses to the Embryo/Fetus

8.37 ALARA Levels For Effluents From Materials Facilities

10.10 Guide for the Preparation of Applications for Radiation Safety Evaluations

2. Information Notices(IN) and Bulletins (BL)

IN 82-21 Buildup of Enriched Uranium in Effluent Treatment Tanks

IN 87-26 Cracks in Stiffening Rings on 48-inch-diameter UF6 Cylinders

IN 89-24 Nuclear Criticality Safety
Issue Date: 10/26/11 C1-22 1246

IN 90-27 Clarification of Regulatory Requirements for Packaging of 

Uranium Hexafluoride (UF6) for Transportation

IN 90-63 Management Attention to the Establishment and Maintenance 

of a Nuclear Criticality Safety Program

IN 91-84 Problems with Criticality Alarm Components/Systems

IN 92-11 Soil and Water Contamination at Fuel Cycle Facilities

IN 92-14 Uranium Oxide Fires at Fuel Cycle Facilities

IN 92-58 Uranium Hexafluoride Cylinders - Deviations in Coupling

Welds

IN 93-60, Reporting Fuel Cycle and Materials Events to the

Supplement 1 NRC Operations Center

IN 94-73 Clarification of Criticality Reporting Criteria

BL 91-01 Reporting Loss of Criticality Safety Controls

Supplement 1

Others as selected by the First Line Supervisor

3. NUREGs (latest revision, where applicable)

NUREG 1198 Release of UF6 From A Ruptured Model 48Y Cylinder at 

Sequoyah Fuels Corporation Facility

NUREG 1198, Release of UF6 From a Ruptured Model 48Y Cylinder at 

Sequoyah Supplement No. 1 Fuels Corporation Facility: 

Lessons-Learned Report

NUREG 1189, Assessment of the Public Health Impact From the

Vol. 1 and 2 Accidental Release of UF6 at the Sequoyah Fuels Corporation 

Facility at Gore, Oklahoma

NUREG 1324 Proposed Method for Regulating Major Materials Licensees

NUREG 1450 Potential Criticality Accident at the General Electric Nuclear 

Fuel and Component Manufacturing Facility, May 29, 1991

NUREG 1513 Integrated Safety Analysis Guidance Document

NUREG 1520 Standard Review Plan for the Review of a License Application 

for a Fuel Cycle Facility

NUREG 1600 General Statement of Policy and Procedures for NRC 

Enforcement Actions
Issue Date: 10/26/11 C1-23 1246

Others as selected by the First Line Supervisor

4. Generic Letters (GL)

GL 95-001 NRC Staff Technical Position on Fire Protection For Fuel

Cycle Facilities

Others as selected by the First Line Supervisor

5. Federal Register Notices

U.S. Nuclear Regulatory Commission, "Guidance on Management 

Controls/Quality Assurance, Requirements for Operation, Chemical Safety, and 

Fire Protection for Fuel Cycle Facilities," Federal Register 54 (No. 53), 

11590-11598, March 21, 1989

U. S. Nuclear Regulatory Commission, "Guidance on Fire Protection for Fuel 

Cycle Facilities," Federal Register 57 (No. 154), 35607-35613, August 10, 1992

Others as selected by the First Line Supervisor

6. NRC Branch Technical Positions (BTP)

None

7. Policy and Guidance Directives

FCSS Policy and Guidance Directive FC 84-14, "Radiological Contingency 

Planning Requirements and License Application Review"

NRC Policy and Guidance Directive 83-23, "Termination of Byproduct, Source, 

and Special Nuclear Materials Licenses"

Others as selected by the First Line Supervisor

B. The First Line Supervisor should test the qualifying individual's knowledge of 

application of the selected regulatory guidance documents to the fuel cycle 

license reviewer program by discussions, interviews, or oral quizzes.
Issue Date: 10/26/11 C1-24 1246

Qualification Guide 5

Fuel Cycle Licensing Branch Manual

A. A selection of portions of the Licensing Branch Manual with direct application to the fuel 

cycle license review program should be identified by the First Line Supervisor. The 

application of the specific sections to the fuel cycle license review program should be 

studied in detail by the qualifying individual. 

B. The First Line Supervisor will hold discussions, interviews, or oral quizzes to test the 

qualifying individual's knowledge and understanding of the application of the selected 

sections to the fuel cycle license review program.
Issue Date: 10/26/11 C1-25 1246

Qualification Guide 6

Industry Codes and Standards

A. A selection of currently applicable industry codes and standards should be identified by 

the First Line Supervisor. These references should be selected from those listed below 

for the specific area of the license reviewer's responsibility and be documented. The 

qualifying individual should be expected to have a general knowledge of the topics 

addressed in the references. This review may be accomplished by self study, study 

quizzes, briefings, or discussions. 

1. American National Standards Institute (ANSI)

ANSI/ANS 8.1 Nuclear Criticality Safety in Operations with 

Fissionable Materials Outside Reactors

ANSI/ANS 8.3 Criticality Accident Alarm System

ANSI/ANS 8.5 Use of Borosilicate-Glass Raschig Rings as a Neutron 

Absorber in Solutions of Fissile Material

ANSI/ANS 8.7 Guide for Nuclear Criticality Safety in the Storage of 

Fissile Materials

ANSI/ANS 8.9 Nuclear Criticality Safety Criteria for Steel-Pipe 

Intersections Containing Aqueous Solutions of Fissile 

Material

ANSI/ANS 8.10 Criteria For Nuclear Criticality Safety Controls in 

Operations with Shielding and Confinement

ANSI/ANS 8.12 Nuclear Criticality Control and Safety of 

Plutonium-Uranium Fuel Mixtures Outside Reactors

ANSI/ANS 8.15 Nuclear Criticality Control of Special Actinide 

Elements

ANSI/ANS 8.17 Criticality Safety Criteria for the Handling, Storage, 

and Transportation of LWR Fuel Outside Reactors

ANSI/ANS 8.19 Administrative Practices for Nuclear Criticality Safety

ANSI/ANS 8.20 Nuclear Criticality Safety Training

ANSI N13.1 Guide to Sampling Airborne Radioactive Materials in 

Nuclear Facilities

ANSI N13.2 Guide for Administrative Practices in Radiation 

Monitoring

ANSI N323 Radiation Protection Instrumentation Test and 

Calibration

ANSI NQA-1 Quality Assurance Requirements for Nuclear Facilities

ANSI NFPA Standards as selected and documented by the First Line Supervisor 

(NOTE: a list is provided in Section 8.4.2 of NUREG 1520).
Issue Date: 10/26/11 C1-26 1246

2. NRC Accepted HP Computer Codes

PC-DOSE

Varskin

RASCAL

REMIT

3. U.S. Environmental Protection Agency (EPA)

EPA Federal Guidance Report No.11

4. Committee on the Biological Effects of Ionizing Radiation (BEIR)

BEIR Reports (As selected by Supervisor)

5. American Society for Testing Materials (ASTM)

ASTM C986-89, Developing Training Programs in the Nuclear Fuel Cycle

6. Other

LA-10860-MS, Critical Dimensions of Systems Containing U-235, Pu-239, and 

U-233, H.C. Paxton and N. L. Pruvost, Los Alamos National Laboratory, Los 

Alamos, NM, 1987

Draft Regulatory Guide, DOE/NCT-04, A Review of Criticality Accidents, W. R. 

Stratton, Revised by D. R. Smith, U.S. DOE, March 1989

Nuclear Criticality Safety - Theory and Practice, R. A. Knief, American Nuclear 

Society, La Grange Park, IL, 1985

Underwriters Laboratories, Inc. (UL) Standard 555, "Standard for Fire Dampers 

and Ceiling Dampers"

B. The First Line Supervisor should test the qualifying individual's knowledge of application 

of these codes and standards to the fuel cycle license reviewer program by discussions, 

interviews, or oral quizzes.
Issue Date: 10/26/11 C1-27 1246

Qualification Guide 7

NRC Management Directives

A. A selection of currently applicable NRC Management Directive (MD) references should be 

identified by the First Line Supervisor. These references should include those listed 

below and be documented. The qualifying license reviewer should be expected to have 

a general knowledge of the topics addressed in the references. This review may be 

accomplished by self-study, study-quizzes, briefings, or discussions. The selection 

should include:

1. NRC MD 9.1 Organization Management

2. NRC MD 9.29 Organization and Function of Regional Offices

3. NUREG 0325 USNRC Functional Organization Chart

4. NRC MD 3.2 Privacy Act

5. NRC MD 3.1 Freedom of Information Act

6. NRC MD 10.130 Safety and Health Program Under the Occupational Safety 

and Health Act

7. NRC MD 10.131 Protection of NRC Employees Against Ionizing Radiation

8. NRC MD 14.1 Official Temporary Duty Travel

9. NRC MD 10.159 Differing Professional Views or Opinions

10. NRC MD 10.42 Hours of Work and Premium Pay

11. NRC MD 10.43 Time and Attendance Reporting

12. NRC MD 10.67 Non-SES Performance Appraisal System

13. NRC MD 10.101 Employee Grievances

14. NRC MD 8.3 NRC Incident Investigation Procedures

15. NRC MD 8.8 Management of Allegations

B. Application of the selected NRC Management Directives to the fuel cycle license review 

program will be discussed with the qualifying individual by the First Line Supervisor to test 

the qualifying individual's knowledge.
Issue Date: 10/26/11 C1-28 1246

Qualification Guide 8

Review of Significant Fuel Cycle Events

A. A selection of significant historical fuel cycle related events should be identified by the 

First Line Supervisor. These events should be studied in detail by the qualifying 

individual. Such events would include the following. Other events may be chosen but in 

any case the events chosen should be documented.

1. Sequoyah Fuels accidents in 1986 and in 1992

2. Potential criticality at the GE Wilmington plant in 1991

3. Y-12 criticality accident in 1958

4. UO2 fires at fuel fabrication plants

5. United Nuclear - Wood River Junction in 1964

6. Japan fuel fabrication nuclear criticality accident in 1999

B. The First Line Supervisor should discuss the selected events in detail with the qualifying 

license reviewer and go over recommendations made, lessons learned, and changes 

identified to prevent recurrence. The relevance of the event to the overall fuel cycle 

license review program should be stressed.
Issue Date: 10/26/11 C1-29 1246

Qualification Guide 9

Directed Review of Selected Licensing Case Work

A. The First Line Supervisor will select documents from the file of a licensed facility and 

direct their review by the qualifying individual. The qualifying individual will study in detail 

the selected documents. The selection should be documented. Such documents would 

include:

1. Initial license application and facility description

2. NRC Safety Evaluation Report

3. Associated licensing correspondence (NRC staff comments and licensee 

responses)

4. License renewal applications and associated NRC correspondence

5. Copy of the license 

6. Integrated Safety Analysis (ISA), if available

7. Facility pre-fire plan, if available

B. The First Line Supervisor will discuss in detail with the qualifying individual the selected 

documents and their relation to the overall fuel cycle license review program.
Issue Date: 10/26/11 C1-30 1246

Qualification Guide 10

Formal Training

The standards for each Training Course are provided in the NRC Technical Training Division 

Course Catalog and will not be duplicated in the Qualification Guide.
Issue Date 10/26/11 Att1-1 1246

Attachment 1

Revision History for IMC 1246, Appendix C1

Commitment 

Tracking 

Number

Document 

Accession 

Number and 

Issue Date

Description of Change Training 

Needed

Training 

Completion 

Date

Comment Resolution 

Accession Number

N/A ML11230B319

10/26/11

CN 11-022

Revision history sheet 

added. Combined 

Appendix A7 with Appendix 

B7 and renamed as 

Appendix C1. Added 

“training requirements” 

section from Appendix A7.

None N/A ML11235A674