Issue Date:10/26/11 C4-1 1246

APPENDIX C4

TRAINING REQUIREMENTS AND QUALIFICATION JOURNAL FOR 

FUEL CYCLE SAFEGUARDS - PHYSICAL SECURITY INSPECTOR

I. TRAINING REQUIREMENTS

A. Applicability

The training described below is required of NMSS program inspectors assigned to 

perform physical security inspections at fuel cycle facilities.

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/Regional Procedures.

(4) Regulatory Guidance.

(5) NRC Inspection Manual.

(6) Industry Codes and Standards.

(7) Inspection Accompaniments.

(8) NRC Management Directives.

(9) Review of significant security events at licensees

(10) Directed Review of Selected Site Security Plans and 

Procedures

b) Core Training. These courses establish minimum formal classroom 

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

these requirements.

(1) Fundamentals of Inspection Course (G-101) or Inspection 

Procedures Course (G-108)

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

(3) Effective Communications for NRC Inspectors (PDC)

(4) OSHA Indoctrination Course (G-111)

(5) Site Access Training (H-100)

(6) Physical Security Fundamentals Course (S-301) or 

equivalent

(7) Intro to Security Systems Course Self-Study (S-118S) 

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

(9) Hazards Analysis for DOE SARs and QRAs (P-404)

c) Specialized Training. Depending on the inspector's previous work 

experience and planned inspection activities, additional courses may 

be required in order to gain knowledge necessary for specialized 

inspection activities. Management will make this determination on an 

individual basis. For example, if an inspector is assigned activities in 

one of the areas listed below then that inspector should attend the 

appropriate training course or have equivalent experience as

determined by their management.

(1) Safety Officers Practical Training Orientation Course (S-105)

(2) Explosive Threat Recognition, Prevention and Response 
Issue Date:10/26/11 C4-2 1246

Course (S-106)

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

Training. This training will be determined by the supervisor and will depend 

on the individual's previous work experience and planned inspection 

activities in specific areas.

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

after initial certification. Refresher training will include the following courses 

and other courses, as determined by management:

(1) Fundamentals of Inspection Refresher Course (G-102)

(2) Safeguards Technology Refresher Course (S-402)

II. QUALIFICATION JOURNAL

Applicability

This NRC Inspector Qualification Journal implements NRC Manual Chapter 1246, by 

establishing the minimum training requirements for personnel assigned to perform fuel 

cycle safeguards inspection (physical security) activities at fuel facilities. 

The NRC Inspector 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 inspector.

The NRC Inspector 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 inspector's 

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

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

have direct application to an inspection discipline. The inspector is expected to 

demonstrate detailed knowledge of the inspection discipline specific references.

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

inspector'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 

inspector's management with the ability to tailor the qualification process to the 

experience and training level of the inspector, and to meet the inspection needs of the 

NRC. The use of specific real world material will reinforce the qualification process.
Issue Date:10/26/11 C4-3 1246

INSPECTOR QUALIFICATION JOURNAL

Fuel Cycle Safeguards Inspector - Physical Security

 

Name Title Branch Section

To complete your qualification as a Fuel Cycle Safeguards Inspector - Physical Security 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 Inspector Qualification Journal.

Signature When Complete Date

1. NRC Orientation _______

First Line Supervisor

2. Code of Federal Regulations 

First Line Supervisor

3. Office Instructions/ 

Regional Procedures First Line Supervisor

4. Regulatory Guidance 

First Line Supervisor

5. NRC Inspection Manual 

Chapters (MC) First Line Supervisor

6. Industry Codes and Standards 

First Line Supervisor

7. Inspection Accompaniments ________

First Line Supervisor 

8. NRC Management Directives 

First Line Supervisor

9. Review of Significant Fuel 

Cycle Security Events 

First Line Supervisor

10. Review of Site Security Plans

and Procedures ________________________ ________

First Line Supervisor

11. Formal Training _________________ ________

First Line Supervisor
Issue Date:10/26/11 C4-4 1246

Qualification Board 

Requirement Met 

Second Level Supervisor

or Board Chairman

Recommended as a qualified inspector 

Second Level Supervisor

Certification Memo Issued 

Second Level Supervisor
Issue Date:10/26/11 C4-5 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 C4-6 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 

safeguards physical security

inspection program _____________________ _____

First Line Supervisor
Issue Date:10/26/11 C4-7 1246

Qualification Card 3

Office Instructions/Regional Procedures

Initials Date

A. Familiarization with office/

regional policies and procedures _______________ _____

Employee

B. Discussion completed on

office/regional

policies and procedures _____________________ ______

First Line Supervisor
Issue Date:10/26/11 C4-8 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 safeguards physical 

security inspection program _____________________ ______

First Line Supervisor 
Issue Date:10/26/11 C4-9 1246

Qualification Card 5

NRC Inspection Manual Chapters (MC)

Initials Date

A. Review of appropriate NRC

MCs completed __________________ _____

Employee

B. Discussion of NRC MCs

and their relation

to the fuel cycle safeguards

physical security

inspection program _____________________ _____

First Line Supervisor
Issue Date:10/26/11 C4-10 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 safeguards physical

security inspection program _____________________ _____

First Line Supervisor
Issue Date:10/26/11 C4-11 1246

Qualification Card 7

Inspection Accompaniments

Initials Date

A. Inspections completed

1.____________________ ______________ ______

Facility Employee

2.____________________ ______________ ______

Facility Employee

3.____________________ ______________ ______

Facility Employee

4.____________________ ______________ ______

Facility Employee

B. Discussion of inspection and 

employee's role

1._________________ _____________________ _____

Facility First Line Supervisor

2._________________ _____________________ _____

Facility First Line Supervisor

3._________________ _____________________ _____

Facility First Line Supervisor

4._________________ _____________________ _____

Facility First Line Supervisor
Issue Date:10/26/11 C4-12 1246

Qualification Card 8

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 safeguards 

physical security

inspection program _____________________ _____

First Line Supervisor
Issue Date:10/26/11 C4-13 1246

Qualification Card 9

Review of Significant Fuel Cycle Security Events

Initials Date

A. Review of selected significant

historical fuel cycle security

events __________________ _____

Employee

B. Discussion of the importance

of these events and lessons

learned _____________________ _____

First Line Supervisor
Issue Date:10/26/11 C4-14 1246

Qualification Card 10

Review of Site Security Plans and Procedures

Initials

Date

A. Review of selected portions

of site security plans and 

procedures _______________ ______

Employee

B. Discussion of site security

plans and procedures and their

relationship to the fuel cycle

safeguards physical security

inspection program _____________________ ______

First Line Supervisor
Issue Date:10/26/11 C4-15 1246

Qualification Card 11

Formal Training

A. CORE TRAINING: Initials Date

1. Fundamentals of Inspection

Course (G-101) or Inspection

Procedures (G-108) ________________ _____ 

Training Coordinator

2. Root Cause/Incident Investigation

Workshop (G-205) ___________________ _____

Training Coordinator

3. Effective Communication for 

NRC Inspectors ___________________ _____

Training Coordinator

4. OSHA Indoctrination Course (G-111) ___________________ ______

Training Coordinator

5. Site Access Training (H-100) ___________________ _____

Training Coordinator

6. Physical Security Fundamentals

Course (S-301) or equivalent ___________________ _____

Training Coordinator

7. Introduction to Physical Security 

Systems Self-Study (S-118S) ___________________ _____

Training Coordinator

8. Fuel Cycle Processes Directed

Self-Study Course (F-201S) ___________________ _____

Training Coordinator

9. Hazards Analysis for 

DOE SARs and QRAs(P-404) _____

 Training Coordinator
Issue Date:10/26/11 C4-16 1246

10. SPECIALIZED TRAINING

Other training courses required for inspectors performing inspections 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 C4-17 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

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

reference material, supplies, office equipment, 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 C4-18 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 inspector in that mission.
Issue Date:10/26/11 C4-19 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 25 Access Authorization for Licensee Personnel

8. 10 CFR Part 30 Rules of general applicability to domestic licensing of 

byproduct material

9. 10 CFR Part 40 Domestic licensing of source material

10. 10 CFR Part 51 Environmental protection regulations for 

domestic licensing

11. 10 CFR Part 61 Licensing requirements for land disposal of radioactive 

waste

12. 10 CFR Part 70 Domestic licensing of special nuclear material

13. 10 CFR Part 71 Packaging and transportation of radioactive material

14. 10 CFR Part 73 Physical protection of plants and materials

15. 10 CFR Part 74 Material control and accounting of special nuclear material

16. 10 CFR Part 75 Safeguards on nuclear material

17. 10 CFR Part 76 Certification of Gaseous Diffusion Plants

18. 10 CFR Part 95 Security facility approval and safeguarding of national 

security information and restricted data

19. 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
Issue Date:10/26/11 C4-20 1246

20. 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 NRC 

21. 29 CFR Part 1910 Occupational Safety and Health 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 inspector by the First Line Supervisor to test 

the qualifying inspector=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 C4-21 1246

Qualification Guide 3

Office Instructions/Regional Procedures

A. Office/Division Policies and Procedures

1. Read the NMSS Policy and Procedures Manual

2. The qualifying individual should review the NMSS policies and practices on:

a. Travel, including Management Directive 14.1 Official Temporary Duty 

Travel

b. Telephone use

c. Policies on use of annual leave and sick leave 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 Personal 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 C4-22 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 inspector'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)

3.71 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)

5.7 Entry/Exit Control for Protected Areas, Vital Areas, and Material 

Access Areas

5.11 Nondestructive Assay of Special Nuclear Material Contained in 

Scrap and Waste

5.12 General Use of Locks in the Protection and Control of Facilities 

and Special Nuclear Materials

5.13 Conduct of Nuclear Material Physical Inventories

5.15 Tamper-Indicating Seals for the Protection and Control of Special 

Nuclear Material

5.21 Nondestructive Uranium 235 Enrichment Assay by Gamma Ray 

Spectrometry

5.26 Selection of Material Balance Areas and Item Control Areas

5.31 Specially Designed Vehicle with Armed Guards for Road Shipment 

of Special Nuclear Material

5.37 In Situ Assay of Enriched Uranium Residual Holdup

5.43 Plant Security Forces

5.52 Standard Format and Content of a Licensee Physical Protection 

Plan for Strategic Special Nuclear Material at Fixed Sites

5.59 Standard Format and Content for a Licensee Physical Security 

Plan for the Protection of Special Nuclear Material of Moderate or 

Low Strategic Significance

5.61 Intent and Scope of the Physical Protection Upgrade Rule 

Requirements for Fixed Sites
Issue Date:10/26/11 C4-23 1246

5.62 Reporting of Safeguards Events

5.65 Vital Area Access Controls, Protection of Physical Security 

Equipment, and Key and Lock Controls

5.67 Material Control and Accounting For Uranium Enrichment 

Facilities Authorized to Produce Special Nuclear Material of Low 

Strategic Significance 

8.1 Radiation Symbol

8.5 Criticality and Other Interior Evacuation Signals 

8.7 Instructions For Recording and Reporting Occupational Radiation 

Exposure Data

8.10 Operating Philosophy for Maintaining Occupational Radiation 

Exposure As Low As Is Reasonably Achievable

8.13 Instruction Concerning Prenatal Radiation Exposure

8.29 Instruction Concerning Risks from Occupational Radiation 

Exposure

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

IN 89-24 Nuclear Criticality Safety

IN 90-09 Extended Interim Storage of Low-Level Radioactive Waste by Fuel 

Cycle and Materials Licensees

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

Supplement 1 NRC Operations Center

IN 94-73 Clarification of Criticality Reporting Criteria

IN 96-71 Licensee Response to Indications of Tampering, Vandalism, or 

Mischief

IN 98-05 Criminal History Record Information

IN 98-35 Threat Assessments and Considerations of Heightened Physical 

Protection Measures

IN 99-16 Federal Bureau of Investigation=s Nuclear Site Security Program 

BL 91-01 Reporting Loss of Criticality Safety Controls

Supplement 1

Bulletin 38 Necessary Penetrations of Material Access Area Barriers (issued 
Issue Date:10/26/11 C4-24 1246

by Licensee Safeguards Guidance Group, LSGG)

Others as selected by the First Line Supervisor

3. NUREGs (latest revision, where applicable)

NUREG 0674 Security Personnel Training and Qualification Criteria

NUREG 0845 Agency Incident Response Actions

NUREG 1189, Assessment of the Public Health Impact From the 

Accidental Vol. 1 and 2 Release of UF6 at the 

Sequoyah Fuels Corporation Facility at Gore, Oklahoma

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

Supplement No. 1 Sequoyah Fuels Corporation Facility: Lessons-Learned 

Report

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 1520 Standard Review Plan for the Review of a License 

Application for a Fuel Cycle Facility

NUREG/BR 0006 Instructions for Completing Nuclear Material Transaction 

Reports

NUREG/BR 0007 Instructions for Completing Material Balance Reports and 

Physical Inventory Listings

NUREG/BR 0096 Instructions and Guidance for Completing Physical 

Inventory Summary Reports

NUREG/CR 2078 Handbook of Nuclear Safeguards Measurement Methods

NUREG/CR 4604 Statistical Methods For Nuclear Material Management

Others as selected by the First Line Supervisor

4. Generic Letters(GL)

GL 88-19 Use of Deadly Force by Licensee Guards to Prevent Theft 

of Special Nuclear Material

NMSS Letter Letter to CAT-I Licensees, Night Firing Light Levels, dated 

November 22, 1988

GL 89-20 Protected Area Long Term Housekeeping

GL 91-003 Reporting of Safeguard Events
Issue Date:10/26/11 C4-25 1246

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

None

B. The application of these guidance documents to the fuel cycle safeguards physical 

security inspection program should be studied in detail by the qualifying individual and 

covered by the First Line Supervisor in discussions, interviews, or oral quizzes. 
Issue Date:10/26/11 C4-26 1246

Qualification Guide 5

NRC Inspection Manual Chapters (MC)

A. A selection of currently applicable NRC MC and Inspection Procedure (IP) references 

with direct application to the fuel cycle safeguards physical security inspection program 

should be identified by the First Line Supervisor. The application of the specific 

references to the fuel cycle safeguards physical security inspection program should be 

studied in detail by the qualifying individual. 

1. REPORTS/COMMUNICATIONS/FOLLOW-UP 

MC 0030 Policy and Guidance for Development of NRC Inspection Manual 

Programs

MC 0230 Morning Report

MC 0610 Inspection Reports

MC 0620 Inspection Documents and Records

MC 0720 NRC Bulletins and Information Notices

MC 0730 Generic Communications Regarding Materials and Fuel Cycle Issues

MC 0801 Inspector Feedback

MC 1120 Preliminary Notifications

IP 92701 Follow-up

IP 92703 Follow-up of Confirmatory Action Letters

2. INSPECTIONS

MC 0300 Announced and Unannounced Inspections

MC 0312 Technical Assistance for Radiation Safety Inspections at Nuclear Fuel 

Cycle Facilities and Material Licensee's Sites

MC 0630 Analysis of the Impact of Noncompliance with Physical Security 

Requirements

MC 1246 Formal Qualification Programs in Nuclear Material Safety and Safeguards 

 Program Area

MC 2600 Fuel Cycle Facility Operational Safety and Safeguards

Inspection Program

MC 2681 Safeguards Inspection of Fuel Facilities, Transport of SNM and Irradiated 

Fuel, and SNM Imports and Exports

MC 2682 Technical Assistance for Safeguards MC & A Inspections at Fuel 

Facilities

MC 8800 Fuel Facility Inspection

IP 88102 Surveillance Observations

3. INTERACTIONS WITH OTHER FEDERAL AGENCIES

MC 1007 Interfacing Activities Between Regional Offices of NRC and OSHA

IP 93001 OSHA Interface Activities

4. INCIDENT RESPONSE

MC 1300 Incident Response Actions - Responsibility and Authority

MC 1301 Response to Radioactive Material Incidents that Do Not Require 

Activation of the NRC Incident Response Plan

MC 1302 Action Levels for Radiation Exposures and Contamination Associated 

with Materials Events Involving Members of the Public

MC 1360 Use of Physician and Scientific Consultants in the Medical Consultant 
Issue Date:10/26/11 C4-27 1246

Program

IP 88003 Reactive Inspection for Events at Fuel Cycle Facility Program

5. WASTE MANAGEMENT

MC 8400 Radioactive Waste Management

6. FUEL CYCLE SAFETY PROGRAM

MC 8100 Physical Security

MC 8500 Material Control and Accountability

MC 8800 Fuel Facility Inspection

7. RADIATION PROTECTION

MC 8300 Radiation Protection

8. OTHER

MC 1100 Notification of Significant Meetings

MC 1201 Conduct of Employees

MC 2900 Performance Appraisal Program

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 

references to the fuel cycle safeguards physical security inspection program.
Issue Date:10/26/11 C4-28 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 inspector'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 N15.15 Nuclear Materials - Assessment of the Assumptions of 

Normality (Employing Individual Observed Values)

ANSI N15.18 Nuclear Materials - Mass Calibration Techniques

for Control

ANSI N15.19 Nuclear Materials Control - Volume 

Calibration Techniques

ANSI N15.20 Guide to Calibrating Nondestructive Assay Systems

ANSI N15.22 Nuclear Materials - Plutonium-Bearing Solids - Calibration 

Techniques for Calorimetric Assay

ANSI N15.28 Nuclear Materials Control - Guide for Qualification and 

Certification of Safeguards and Security Personnel

ANSI N15.37 Guide to the Automation of Nondestructive Assay Systems 

for Nuclear Material Control

ANSI N15.41 Derivation of Measurement Control Programs -

General Principles

ANSI N15.51 Nuclear Materials Management - Measurement Control 

Program

- Nuclear Materials Analytical Chemistry Laboratory

ANSI N15.54 Instrumentation - Radiometric Calorimeters - Measurement 

Control Program 

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
Issue Date:10/26/11 C4-29 1246

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 NQA-1 Quality Assurance Requirements for Nuclear Facilities

Others as selected and documented by the First Line Supervisor

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).

Institute of Electrical and Electronic Engineers (IEEE) standards 

associated with security and analysis equipment

2. American Society for Testing and Materials (ASTM)

ASTM F792-82 Standard Practice for Design and Use of Ionizing Radiation 

Equipment for the Detection of Items Prohibited in 

Controlled Access Areas

3. General Service Administration (GSA) 

W-A-450C/1 Federal Specification Components for Interior Alarm 

Systems, Balanced Magnetic Switches

W-A-450B Federal Specification Interior Security Components 

for Alarm Systems

4. Sandia National Laboratory (SAND)

SAND 87-1927 Entry Control Systems Technology Transfer Manual

SAND 87-1926 Access Delay Technology Transfer Manual

SAND 89-1924 Video Assessment Technology Transfer Manual

SAND 78-0400 Security Seal Handbook

5. Underwriters Laboratory

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

and Ceiling Dampers"

6. NRC Accepted HP Computer Codes

PC-DOSE

Varskin

RASCAL

REMIT
Issue Date:10/26/11 C4-30 1246

7. Other Draft Regulatory Guide, DOE/NCT-04, A Review of Criticality Accidents, 

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

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

application of these codes and standards to the fuel cycle safeguards physical security 

inspection program by discussions, interviews, or oral quizzes.
Issue Date:10/26/11 C4-31 1246

Qualification Guide 7

Inspection Accompaniments

A. Each inspector should accompany certified inspectors on at least four inspections. At 

least two of these inspections should be performed at a facility other than the 

designated lead plant.

B. The following is a guide for material that should be studied and discussed with the 

inspector in charge during these inspection accompaniments. The First Line 

Supervisor will discuss these items, as appropriate, following each inspection 

accompaniment.

1. The Inspection Program

MC 2600 Fuel Facility Inspection Program 

MC 2681 Safeguards Inspection of Fuel Facilities, Transport of SNM and 

Irradiated Fuel, and SNM Imports and Exports

MC 2681/05 Physical Security Inspection for Category I Fuel Cycle Facilities

MC 8100 Physical Security

IP 81000 Physical Security Procedure series

White Paper Risk-Informed and Performance-Based Regulation

2. Scheduling and Preparation for Inspections

MC 0300 Announced and Unannounced Inspections

3. Scope of Inspection

4. Entrance/Exit Interviews

5. Conduct of Inspection, Accumulation of Data

6. Post-inspection Activities of Inspectors

MC 0610 Inspection Reports

MC 0630 Analysis of the Impact of Noncompliance with Physical Security 

Requirements

MC 1100 Notification of Significant Meetings

7. Morning Reports

MC 0230 Morning Report

8. Non-routine Licensee Events

MC 1110 Potential Abnormal Occurrences

Management Directive 8.3 NRC Incident Investigation Program
Issue Date:10/26/11 C4-32 1246

Management Directive 8.9 Accident Investigation

9. Preliminary Notification

MC 1120 Preliminary Notifications

10. Bulletins/Information Notices

MC 0720 NRC Bulletins and Information Notices)

11. Use of Consultants of NRC

MC 1360 Use of Physician and Scientific Consultants in the Medical 

Consultant Program

Management Directive 10.6 Use of Consultants & Experts

12. Allegations and Investigations

Management Directive 8.8 Management of Allegations

13. Communication outside NRC

Management Directive 5.5 Public Affairs Program

Management Directive 3.6 Distribution of Unclassified NRC

Staff/Contractor-Generated Reports
Issue Date:10/26/11 C4-33 1246

Qualification Guide 8

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 inspector 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 0335 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 Program

15. NRC MD 8.8 Management of Allegations

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

physical security inspection 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 C4-34 1246

Qualification Guide 9

Review of Significant Fuel Cycle Security Events

A. A selection of significant historical fuel cycle security-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

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

inspector and go over recommendations made, lessons learned, and changes 

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

safeguards physical security inspection program should be stressed.
Issue Date:10/26/11 C4-35 1246

Qualification Guide 10

Review of Site Security Plans and Procedures

A. The inspector should become generally familiar with several site security plans and 

procedures as selected by the First Line Supervisor. The inspector's review should 

include the safety analysis and security plan associated with the license application with 

special emphasis in the following areas, as appropriate.

1. Site characteristics 

2. Process systems

3. Safety features

4. Electric power systems 

5. Quality assurance 

6. Material control systems

7. Radiation protection and radwaste 

B. Each selected site security plan and procedure should be reviewed with an emphasis 

on its application to the fuel cycle safeguards physical security inspection program. 

After reviewing the selected documents, the inspector will be able to specifically 

address its application to the fuel cycle safeguards physical security inspection 

program. The inspector may demonstrate knowledge through discussions, interviews 

or quizzes. These discussion activities should be conducted by the First Line 

Supervisor or alternatively, by senior inspectors to illustrate recent application of 

regulatory guidance to the fuel cycle safeguards physical security inspection program. 

Completion of the discussion activities must be documented.
Issue Date:10/26/11 C4-36 1246

Qualification Guide 11

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 C4

Commitment 

Tracking 

Number

Document 

Accession 

Number and 

Issue Date

Description of Change Training 

Needed

Training 

Completion 

Date

Comment Resolution 

Accession Number

N/A ML11230B339

10/26/11

CN 11-022

“Training Requirements”

section from IMC 

1246A04 has been 

merged with IMC1246 

B04 and renamed IMC 

246, Appendix C4, 

“Training Requirements 

and Qualification Journal 

for Fuel Cycle 

Safeguards - Physical 

Security Inspector.” 

Revision history page 

added. 

None N/A ML11235A854