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)

(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.

1246, APPENDIX B	VII-2	Issue Date: 01/05/01

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

 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	

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         

Qualification Card 1

	NRC Orientation

A.	Site Orientation			InitialsDate

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 

	Qualification Card 2

	Code of Federal Regulations (CFR)

InitialsDate

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

Qualification Card 3

Office Instructions

InitialsDate

A.	Familiarization with office

policies and procedures			_______________		_____

Employee

B.	Discussion completed on

office policies and procedures		_____________________	______

First Line Supervisor

	Qualification Card 4

	Regulatory Guidance

InitialsDate

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 

	Qualification Card 5

	Fuel Cycle Licensing Branch Manual

InitialsDate

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

	Qualification Card 6

	Industry Codes and Standards

InitialsDate

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

	Qualification Card 7

	NRC Management Directives

InitialsDate

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

	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

 Qualification Card 9

Directed Review of Selected Licensing Case Work

InitialsDate

A.	Review of selected licensing

casework				_______________	_______

Employee			

B.	Discussion by first line super-

visor of directed review of the

selected casework and its rela-

tion to the fuel cycle license

review program			________________	_______

First Line Supervisor

	Qualification Card 10

	Formal Training

A. CORE TRAINING:			InitialsDate

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 TitleCourse #InitialsInitialsDate

____________	_________	___________	___________________	_       ______

Supervisor	Training Coordinator

____________	_________	___________	____________________	_______

Supervisor	Training Coordinator

____________	_________	___________	____________________	_______

Supervisor	Training Coordinator

____________	_________	___________	____________________	_______

Supervisor	Training Coordinator

	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

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

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.

	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 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 individuals 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 reviewers knowledge of these Parts.  To the extent possible, recent application of various sections, new regulatory initiatives, and current industry issues should be emphasized.

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)

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.

 	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

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

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

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.

	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.

	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).

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.

	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.

	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.

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.

	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.

Attachment 1

Revision History for IMC 1246, Appendix C1

Issue Date 10/26/11	Att1-1	1246