NEI 06-13A [Revision 2] 

Template for an Industry 

Training Program 

Description 

March 2009 
NEI 06-13A [Revision 2] 

Nuclear Energy Institute 

Template for an Industry 

Training Program 

Description 

March 2009 
ACKNOWLEDGEMENTS

This program description document, Template for an Industry Training Program Description, 

NEI 06-13A, Revision 2, was developed by the NEI New Plant Training Task Force. We 

appreciate the time, efforts and expertise of the individuals who contributed to the development 

of this guideline. 

EXECUTIVE SUMMARY

NEI 06-13A, Template for an Industry Training Program Description, Revision 2, provides a 

complete generic program description for use with combined license (COL) applications. The 

document reflects draft guidance provided by the NRC and industry–NRC discussions on 

training-related issues. A main objective of this program description is to assist in expediting 

NRC review and issuance of the combined license. 

NRC approved this generic template guidance in a Safety Evaluation Report dated September 5, 

2007 (see Appendix B). 

NRC approved Appendix A, Cold License Training Plan, in a Safety Evaluation Report dated 

December 5, 2008 (see Appendix C). 

NOTICE

Neither NEI, nor any of its employees, members, supporting organizations, contractors, or 

consultants make any warranty, expressed or implied, or assume any legal responsibility for the 

accuracy or completeness of, or assume any liability for damages resulting from any use of, any 

information apparatus, methods, or process disclosed in this report or that such may not 

infringe privately owned rights. 

iii 

TABLE OF CONTENTS

EXECUTIVE SUMMARY ....................................................................................................... i 

1 TRAINING PROGRAM DESCRIPTION ......................................................................... 1

1.1 LICENSED OPERATOR TRAINING ........................................................................2

1.1.1 Licensed Operator Initial Training Program ..............................................2

1.1.2 Continuing Training for Licensed Personnel ...............................................2

1.2 TRAINING FOR POSITIONS LISTED IN 10 CFR 50.120 ......................................3

1.2.1 Non-Licensed Operator (NLO) Initial Training ..........................................3

1.2.2 Shift Manager Initial Training ......................................................................3

1.2.3 Shift Technical Advisor Initial Training Program ......................................4

1.2.4 Instrumentation and Control (I&C) Technician Initial Training ..............4

1.2.5 Electrical Maintenance Initial Training Program .......................................4

1.2.6 Mechanical Maintenance Initial Training Program ...................................5

1.2.7 Radiological Protection Technician Initial Training ...................................5

1.2.8 Chemistry Technician Initial Training .........................................................5

1.2.9 Engineering Personnel Initial Training ........................................................6

1.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120 .....................6

1.3 GENERAL EMPLOYEE TRAINING (GET) PROGRAM ......................................7

1.3.1 Plant Access Training .....................................................................................7

1.3.2 Radiation Worker Training Program ..........................................................7

1.3.3 General Employee Requalification Training ...............................................7

1.4 SELECTED OTHER TRAINING PROGRAMS .......................................................8

1.4.1 Fire Protection Training ................................................................................8

1.4.2 Emergency Plan Training Program ..............................................................8

1.4.3 Physical Security Training Program ............................................................8

1.4.4 Station Management Training Program ......................................................8

1.5 TRAINING EFFECTIVENESS EVALUATION PROGRAM .................................9

1.5.1 Supervisory Review for Training Effectiveness ...........................................9

1.5.2 Trainee Review of Training Effectiveness ....................................................9

1.5.3 Review for Effectiveness of Instructional Techniques and Materials ........9

1.6 REFERENCES ............................................................................................................10 

APPENDIX A – COLD LICENSE TRAINING PLAN......................................A-1 

APPENDIX B – FINAL SAFETY EVALUATION REPORT NEI 06-13.............B-1 

APPENDIX C – FINAL SAFETY EVALUATION REPORT NEI 06-13A...........C-1 

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TEMPLATE FOR AN INDUSTRY TRAINING PROGRAM 

DESCRIPTION (TPD)

1 TRAINING PROGRAM DESCRIPTION 

Training programs incorporate instructional requirements to qualify personnel to operate 

and maintain the facility in a safe manner in all modes of operation. The programs are 

developed and maintained in compliance with the facility license and applicable 

regulations. The training programs are periodically evaluated and revised to reflect 

industry experience and to incorporate changes to the facility, procedures, regulations, 

and quality assurance requirements, and are periodically reviewed by management for 

effectiveness. These training programs are described in site and/or corporate procedures, 

as appropriate. Sufficient records are maintained and kept available for NRC inspection 

to verify adequacy of the programs. 

The Training Department provides the required training based on individual employee 

experience, the intended position, and previous training and education. Training 

Department personnel may be supplemented by other personnel such as subject matter 

experts, contract staff, and vendor representatives. Formal instruction may be presented 

through a combination of classroom lectures, e-learning, assigned reading, simulator 

training and evaluations, and other delivery techniques. 

For reactor operators, senior reactor operators, fuel handlers, fire protection personnel, 

and positions specified in 10 CFR 50.120 (Reference 13.2-4), programs are developed, 

established, implemented and maintained using a systems (or systematic) approach to 

training (SAT) as defined by 10 CFR 55.4 (Reference 13.2-8) and ANSI/ANS-3.1-1993 

(Reference 13.2-14), as endorsed by Regulatory Guide-1.8 (Reference 13.2-16). 

Initial and continuing training programs accredited by the National Academy for Nuclear 

Training (NANT) provide personnel with the skills and knowledge to perform assigned 

tasks. Accredited training programs include the following: 

 Non-licensed operator 

 Reactor operator 

 Senior reactor operator 

 Shift manager 

 Shift technical advisor 

 Continuing training for licensed personnel 

 Instrument and control technician and supervisor 

 Electrical maintenance personnel and supervisor 

 Mechanical maintenance personnel and supervisor 

 Chemistry technician 

 Radiological protection technician 

 Engineering personnel 

The results of reviews of operating experience are incorporated into training and 

retraining programs in accordance with the provisions of TMI Action Item I.C.5, 
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Appendix 1A. Training programs encompass all phases of plant operation including 

preoperational testing and low-power operation in accordance with the provisions of TMI 

Action Item I.G.1 (Reference 13.2-19). Before initial fuel loading, sufficient plant staff 

will be trained to provide for safe plant operations. Implementation milestones for initial 

training are presented in Table 13.4-1. 

1.1 LICENSED OPERATOR TRAINING 

The Reactor Operator (RO) and Senior Reactor Operator (SRO) training programs, 

including initial and requalification training, provide the means to train individuals in the 

knowledge, skills, and abilities needed to perform licensed operator duties. The licensed 

operator training program includes the requalification program as required by 10 CFR 

55.59 (Reference 13.2-13). Collectively, ROs and SROs are referred to as Licensed 

Operators. Before initial fuel loading, the number of persons trained in preparation for 

RO and SRO licensing examinations will be sufficient to meet regulatory requirements, 

with allowances for examination contingencies and without the need for planned 

overtime. 

The site employs a simulator in accordance with 10 CFR 55.46. This simulator is used 

for training licensed personnel, and for the administration of the operating test. 

1.1.1 Licensed Operator Initial Training Program 

The Licensed Operator Initial Training Program prepares RO and SRO candidates for the 

NRC license exam. This program is implemented in accordance with administrative 

procedures. 

1.1.1.1 Reactor Operator 

Reactor Operator candidates receive training in the topics listed in 10 CFR 55.41 

(Reference 13.2-9). RO candidates receive plant simulator training to demonstrate 

understanding and the ability to perform the actions listed in 10 CFR 55.45 (Reference 

13.2-11). 

1.1.1.2 Senior Reactor Operator 

In addition to the Reactor Operator topics listed in 10 CFR 55.41 (Reference 13.2-9), 

candidates for the Senior Reactor Operator license receive training in the topics listed in 

10 CFR 55.43 (Reference 13.2-10). SRO candidates receive plant simulator training to 

demonstrate understanding and the ability to perform the actions listed in 10 CFR 55.45 

(Reference 13.2-11). 

1.1.2 Continuing Training for Licensed Personnel 

Continuing training for licensed personnel consists of regularly scheduled formal 

instruction, evaluation, and on-the-job training. Training material is developed using the 

SAT process, and includes Operational Experience (OE). Licensed operators participate 

in continuing training. 
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Program content, course schedules and examination schedules comply with 10 CFR 

55.59 (Reference 13.2-13). Continuing training for licensed personnel is conducted in 

accordance with administrative procedures. 

1.2 TRAINING FOR POSITIONS LISTED IN 10 CFR 50.1201

This section addresses training programs for the positions listed in 10 CFR 50.120 

(Reference 13.2-4). The systematic approach to training (SAT) process is used to 

establish and maintain training programs. Course duration and content are determined by 

the SAT process and by administrative procedure. This program will commence no later 

than eighteen months prior to initial fuel loading.

1.2.1 Non-Licensed Operator (NLO) Initial Training 

Personnel employed as NLOs receive instruction on operation of plant equipment and 

components under normal and emergency conditions. This program is a combination of 

formal instruction and on-the-job training. Training is given in: 

 Fundamentals of mechanical and electrical components 

 Operation of equipment and systems 

 Operating procedures 

 Surveillance requirements 

 Operation of systems important to plant safety 

In-plant training includes system walk downs, which emphasize the use of procedures, 

the proper operation of equipment, and safe operating practices. 

1.2.2 Shift Manager Initial Training 

Shift managers have been trained as Senior Reactor Operators and receive additional 

training that addresses higher-level management skills and behaviors, and provides a 

broader perspective of plant operations. Initial training includes such topics as: 

 Application of Operating Experience 

 Problem-solving skills 

 Planning and managing evolutions 

 Maintaining a broad view of plant operations 

 Application of observation skills 

 Operating philosophy 

 Shift team management 

 Application of design bases to plant operations 

 Emergency Plan 

 Transient and Accident Analysis 

 Systematic Approach to Training 

 Work controls 

 

1

 10 CFR 52.78 (Reference 13.2-6) requires that Combined License applicants demonstrate compliance with 10 CFR 

50.120. 
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1.2.3 Shift Technical Advisor Initial Training Program 

Shift technical advisors provide engineering expertise on-shift. Training provides them 

with the skill and knowledge to monitor equipment and system operation, and assess 

plant conditions during abnormal and emergency events. Initial training for individuals 

who fill the position of shift technical advisor includes instruction in the following areas: 

 Responses to accidents and analyses of plant transients 

 Application of engineering principles to protection of the core 

 Mitigation of plant accidents 

 Basis of plant and systems design 

 Reactor theory, thermodynamics, heat transfer, and fluid flow 

 General Operating Procedures, Technical Specifications, and Administrative Controls 

 Operational transient and accident analysis 

 Simulator training, including exercises in the following situations: 

 Plant or reactor startups to include a range such that reactivity feedback from 

nuclear heat addition is noticeable and heatup rate is established 

 Plant shutdown 

 Manual control of feedwater during startup or shutdown. 

 Significant (10 percent) power changes due to manual changes in control rod 

position. 

 Accident response training 

1.2.4 Instrumentation and Control (I&C) Technician Initial Training 

Initial training for I&C technicians includes instruction in the following areas: 

 Fundamentals of instrumentation and control 

 Pneumatic systems and equipment 

 Electronics 

 Fundamental systems training 

 I&C and other job related procedures 

 Surveillance requirements 

 Mitigating core damage training commensurate with their responsibilities during 

accidents that involve severe core damage 

 On-the-job training 

On-the-job training allows I&C technicians to practice the skills learned in the classroom 

under the guidance of experienced and qualified I&C personnel. 

1.2.5 Electrical Maintenance Initial Training Program 

Initial training for electrical maintenance technicians includes instruction in the following 

areas: 

 Print reading 

 Use of electrical tools and test equipment 

 Fundamental systems training 

 Electrical components and equipment 

 Electrical maintenance practices 
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 Maintenance procedures 

 On-the-job training 

On-the-job training allows Electricians to practice the skills learned in the classroom 

under the guidance of experienced and qualified electrical maintenance personnel. 

1.2.6 Mechanical Maintenance Initial Training Program 

Initial training for mechanical maintenance technicians includes instruction in the 

following areas: 

 Print reading 

 Use of hand tools, power tools, and measurement devices 

 Fundamental systems training 

 Mechanical components and equipment 

 Mechanical maintenance practices 

 Maintenance procedures 

 On-the-job training 

On-the-job training allows Mechanics to practice the skills learned in the classroom under 

the guidance of experienced and qualified mechanical maintenance personnel. 

1.2.7 Radiological Protection Technician Initial Training 

Initial training for radiological protection technicians includes instruction in the following 

areas: 

 Principles of radiation 

 Radiation protection and safety 

 Use of survey instruments 

 Use of analytical equipment 

 Radiation Protection procedures 

 Emergency Plan procedures 

 ALARA practices and procedures 

 Fundamental systems training 

 Mitigating core damage training commensurate with their responsibilities during 

accidents that involve severe core damage 

On-the-job training provides the trainee opportunities to practice actual operation of 

radiation protection equipment and use of procedures under the guidance of experienced 

technicians. Further information on training for radiological protection technicians can 

be found in Section 12.5. 

1.2.8 Chemistry Technician Initial Training 

Initial training for chemistry technicians includes instruction in the following areas: 

 Chemistry procedures 

 Laboratory practices 

 Conduct of analytical tests 
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 Operation of laboratory equipment 

 Fundamental systems training 

 On-the-job training to include actual operation of analytical equipment and the use of 

procedures 

 Mitigating core damage training commensurate with their responsibilities during 

accidents that involve severe core damage 

 Power plant chemistry 

On-the-job training provides the trainee opportunities to practice actual operation of 

analytical equipment and use of procedures under the guidance of experienced 

technicians. 

1.2.9 Engineering Personnel Initial Training 

Engineering personnel complete orientation training on topics such as those listed below. 

The topics are chosen to familiarize engineering support personnel with various aspects 

of nuclear technology in an operating plant environment. Training topics include: 

 Records management and document control 

 Applicable industrial and nuclear regulations, codes, and standards 

 Procedures and drawings 

 Applicable programs such as corrective action, configuration management, work 

control, and the QA program 

 Technical Specifications 

 Fundamentals such as reactor theory, heat transfer, fluid flow, properties of materials, 

and chemistry 

 Plant systems, instrumentation, and components 

 Plant operations 

 Introductory review of accidents 

 Design processes 

1.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120 

Non-licensed plant personnel specified in Subsection 13.2.2 [i.e., personnel listed in 10 

CFR 50.120 (Reference 13.2-4)] receive continuing training to maintain qualifications 

and enhance proficiency. Continuing training reinforces initial training by reiterating 

selected portions of the material. Continuing training also addresses new and modified 

procedures and plant design changes. 

Operating Experience (OE) is included in continuing training, providing personnel with 

actual examples of good practices and lessons learned. OE topics are selected from 

Licensee Event Reports, corrective action databases, industry groups, and other sources. 

Continuing training material is developed in accordance with the systematic approach to 

training and is conducted in accordance with administrative procedures. 

STA qualifications are maintained by participation in continuing training for licensed 

personnel. 
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1.3 GENERAL EMPLOYEE TRAINING (GET) PROGRAM 

1.3.1 Plant Access Training 

As part of the GET program, members of the station staff, contractor workers, and 

unescorted visitors participate in Plant Access Training, which consists of the following 

topics, prior to being granted unescorted access to the plant: 

 Station organization 

 Station facilities and layout 

 Station administration 

 Nuclear plant overview 

 Industrial safety 

 Fire protection 

 Quality assurance and quality control 

 Plant security 

 Emergency planning 

 Radiological orientation 

 Appropriate portions of 10 CFR 26 (Reference 13.2-2) 

 Appropriate portions of 10 CFR 19 (Reference 13.2-1) 

1.3.2 Radiation Worker Training Program 

Personnel whose job duties require them to have unescorted access to radiologically 

controlled areas of the plant receive instruction in the applicable aspects of radiation 

protection. Topics include the following: 

 Sources of radiation 

 Types and measurement of radiation 

 Biological effects 

 Limits and guidelines, including Reg. Guide 8.13 (Reference 13.2-18) 

 Concept of As Low As Reasonably Achievable (ALARA) 

 Radiation dosimetry 

 Contamination 

 Internal exposure 

 Radiation work permits 

 Radiological postings 

 Radiological alarms 

 Radioactive waste 

 Rights and responsibilities 

 Protective clothing 

1.3.3 General Employee Requalification Training 

Personnel with unescorted access to the plant participate in annual requalification 

training. Requalification training includes those topics in 13.2.3.1 and 13.2.3.2, as 

applicable to access requirements. Emphasis is placed on significant changes to the plant, 
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plant procedures, government regulations regarding the operation of the plant, and quality 

assurance requirements. As applicable, training is conducted on industry operating 

experiences, Licensee Event Reports, and personnel errors. 

1.4 SELECTED OTHER TRAINING PROGRAMS 

This subsection addresses training for positions not specified by 10 CFR 55 (Reference 

13.2-7) or 10 CFR 50.120 (Reference 13.2-4). 

1.4.1 Fire Protection Training 

Initial fire protection training is completed prior to receipt of fuel at the site. Personnel 

assigned as fire brigade members receive formal training prior to assuming brigade 

duties, and regularly scheduled retraining. Fire brigade training complies with NFPA 

Standard 600 (Reference 13.2-15). 

Training appropriate to the assigned work is also provided for the fire protection staff, 

fire watch personnel, and the general employee. FSAR Section 9.5.1 includes additional 

information regarding fire protection training. 

1.4.2 Emergency Plan Training Program 

Emergency Plan training meets the requirements of 10 CFR 50 Appendix E Section IV.F 

(Reference 13.2-5) and the standards of 10 CFR 50.47(b)(15) (Reference 13.2-3). Further 

details of the Emergency Plan training program can be found in the Emergency Plan, 

which is a separate document. 

1.4.3 Physical Security Training Program 

Training of security personnel is discussed in FSAR section 13.6 and in the Physical 

Security Plan, which is a separate document. 

1.4.4 Station Management Training Program 

Station supervisors receive Fitness for Duty (FFD) supervisory training in accordance 

with 10 CFR 26.22. The remaining definitions and recommendations in this subsection 

are taken from ANSI/ANS-3.1-1993 (Reference 13.2-14) as endorsed by Regulatory 

Guide 1.8 (Reference 13.2-16). 

The qualification requirements for managers and middle managers include training or 

experience in supervision or management. Training for supervisors develops their skills 

in the following areas: 

 Leadership 

 Interpersonal communications 

 Management responsibilities and limits 

 Motivation of personnel 

 Problem analysis and decision making 

 Administrative policies and procedures 

 Observation skills 
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 Coaching 

1.5 TRAINING EFFECTIVENESS EVALUATION PROGRAM 

The program to evaluate the effectiveness of training programs is based on three 

independent inputs or perspectives: the supervisor of the trainee, the trainee, and an 

educational content evaluation. Each of these reviews is discussed below. 

1.5.1 Supervisory Review for Training Effectiveness 

The purpose of this review is to monitor the content and effectiveness of training 

programs as related to the duties and job responsibilities of the trainees. Reviews may be 

performed by supervisors of employees meeting with appropriate Training personnel, by 

designated oversight personnel, or by observing subsequent job performance. 

Observations are discussed to determine topics that may require additional training or 

subjects that may be removed from the training program. 

1.5.2 Trainee Review of Training Effectiveness 

Following selected courses, or training cycles, trainees have the opportunity to provide 

comments regarding the effectiveness of the instructional methods and content relevancy 

to their jobs. These comments are used in the evaluation of both instruction and content 

of the training program. 

1.5.3 Review for Effectiveness of Instructional Techniques and Materials 

Training material and instructional aids are assessed for clarity and applicability. 

Observations of instructors in the teaching environment are conducted by this qualified 

individual to monitor classroom performance. Full time instructors receive basic 

indoctrination in instructional techniques as soon as practicable after assuming 

instructional duties. The educational specialist conducts periodic seminars in instructional 

techniques, discussing areas where group performance could be improved and 

recommends innovative techniques observed at this or other power stations. 
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1.6 REFERENCES 

13.2-1 10 CFR 19, “Notices, Instructions, and Reports to Workers; Inspection and 

Investigations” 

13.2-2 10 CFR 26, “Fitness for Duty” 

13.2-3 10 CFR 50.47, “Emergency Plans” 

13.2-4 10 CFR 50.120, “Training and Qualification of Nuclear Power Plant Personnel” 

13.2-5 10 CFR 50 Appendix E, “Emergency Planning and Preparedness for Production and 

Utilization Facilities” 

13.2-6 10 CFR 52.78, “Contents of Applications; Training and Qualification of Nuclear 

Power Plant Personnel” 

13.2-7 10 CFR 55, “Operator's Licenses” 

13.2-8 10 CFR 55.4, “Definitions” 

13.2-9 10 CFR 55.41, “Written Examinations: Operators” 

13.2-10 10 CFR 55.43, “Written Examinations, Senior Operators” 

13.2-11 10 CFR 55.45, “Operating Tests” 

13.2-12 10 CFR 55.46(c), “Plant-Referenced Simulators” 

13.2-13 10 CFR 55.59, “Requalification” 

13.2-14 American National Standards Institute, “Selection, Qualification, and Training of 

Personnel for Nuclear Power Plants,” ANSI/ANS-3.1-1993 

13.2-15 National Fire Protection Association, “Standard on Industrial Fire Brigade,” NFPA 

Standard 600, 2005 Edition 

13.2-16 U.S. Nuclear Regulatory Commission, “Qualification and Training of Personnel for 

Nuclear Power Plants,” Regulatory Guide 1.8, Revision 3, May 2000 

13.2-17 U.S. Nuclear Regulatory Commission, “Nuclear Power Plant Simulation Facilities for 

Use in Operator Training and License Examinations,” Regulatory Guide 1.149, 

Revision 3, October 2001 

13.2-18 U.S. Nuclear Regulatory Commission, “Instruction Concerning Prenatal Radiation 

Exposure,” Regulatory Guide 8.13, November, 1980. 

13.2-19 U.S. Nuclear Regulatory Commission, “Clarification of TMI Action Plan 

Requirements”, NUREG-0737, Revision 3, June 1999 

13.2-20 U.S. Nuclear Regulatory Commission, “Policy Statement on Engineering Expertise 

on Shift”, GL 86-04 
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APPENDIX A – COLD LICENSE TRAINING PLAN

1. LICENSED OPERATOR TRAINING PROGRAM PRIOR TO COMPLETION OF THE FIRST 

REFUELING OUTAGE 

Prior to operation, plant experience requirements specified in Regulatory Guide 1.8 (Revision 3) 

and ANSI/ANS 3.1-1993 cannot be met. Additionally, other standard guidance for operator 

selection, training, and qualification cannot be met. 

Cold licensing of operators provides the method for operations personnel to acquire the 

knowledge and experience required for licensed operator duties during the unique conditions of 

new plant construction and initial operation. 

Persons eligible for the cold license process shall meet the following requirements: 

• Candidates for a Reactor Operator license shall have a High School Diploma or 

equivalent as required by R.G. 1.8 Revision 3. 

• Candidates for a Senior Reactor Operator license shall have at least one of the following 

qualifications: 

− Previously held a Senior Reactor Operator license for an operating nuclear 

power plant 

− Previously held a Reactor Operator license for an operating nuclear power plant. 

− Bachelor’s Degree in engineering or science as defined by R.G. 1.8 Revision 3. 

− Experience as a licensed operator training instructor with an SRO certification. 

This experience will be evaluated and approved on a case by case basis by the 

NRC. 

− Two years military experience in a position equivalent to a reactor operator. 

The provisions in this section are applicable to each unit of a multiple unit site separately. 

The cold licensing process for the selection, training and licensing of Operations personnel for 

the new nuclear plants adheres to current industry guidance for operating plants with 

exemptions and alternatives in the following areas. 
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1.1 Licensed Operator Experience Requirements Prior To Commercial Operation 

Licensed operator candidates need not satisfy the experience requirements prior to 

entering a licensed operator training program. Experience and plant evolution 

requirements that have not been met at the time the licensed operator examination is 

administered shall be met prior to issuing the individual’s NRC operator license. In such 

a case, the Licensee will notify the NRC when the candidate meets the experience and 

plant evolution requirements. 

The methods listed below provide the licensed operator candidate with meaningful 

experience on the reactor for which the license is sought. Methods for gaining 

meaningful experience include completing systematically designed training courses, and 

participating in practical work assignments such as preoperational testing, procedure 

development and validation, human factors engineering activities, task analysis 

verification, or conducting licensed operator classroom or simulator training. 

Additionally, for these activities to be considered meaningful, they must be associated 

with safety significant, defense-in-depth, or other major plant components or systems. 

All cold licensed operator candidates will: 

• Complete a systematically designed site layout course. 

• Complete a site-specific non-licensed operator on-the-job training program on 

selected non-licensed operator tasks. The selected non-licensed operator tasks 

are those tasks that are important to plant operation with regard to nuclear 

safety, defense-in-depth, or that are risk significant. 

• Participate in practical work assignments for a minimum of six months that 

includes preoperational testing, and one or more of the following: 

− Procedure development and validation 

− Human factors engineering activities 

− Task analysis verification 

− Licensed operator classroom presentations or simulator training 

implementation 

Senior reactor operator cold license candidates will complete a site-specific reactor 

operator and senior reactor operator training course. 

Senior reactor operator cold license candidates without “hot” plant experience will 

complete a plant operational excellence course that is conducted in a plant simulator or 

they will observe control room activities at an operating nuclear plant for at least six 

weeks. The course and the observation activity are designed to familiarize the 

candidate with the operational interfaces encountered by decision makers in a nuclear 

plant control room. 

Hot plant experience is defined as performance of senior reactor operator duties for at 

least six months including: 
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• At least 6 weeks of operation above 20 percent power 

• A startup from subcritical to 20 percent power 

• A shutdown from above 20 percent power to cold (less than 212°F) and 

subcritical 

• Startup preparations following a fueling or refueling outage 

The startup, shutdown, and startup preparations may have been performed at an 

operating plant or a plant simulator. 

Table 1, Comparison of Hot and Cold License Guidance, shows the current experience 

requirement and the associated cold license experience method. Table 2, Illustration of 

Cold Licensing Plan by Candidate Type, shows education and experience methods for 

each licensed operator candidate type. 

1.2 Crew Experience Requirements during First Year of Operation 

Each operating crew’s cumulative nuclear power plant experience shall be > 6 years; 

and the crew’s cumulative power plant experience shall be > 13 years. 

The crew’s cumulative nuclear power plant experience is gained by working at nuclear 

power plants and military nuclear propulsion plants, conducting licensed operator 

training, participating in new nuclear plant construction and testing, and completing 

academic degree requirements. The cumulative crew nuclear power plant experience is 

the sum of each individual’s experience after applying weighting factors and maximum 

credit limits in Table 3, Cumulative Nuclear Power Plant Operating Crew Experience 

Equivalencies. 

When determining cumulative nuclear power plant experience, all 6 years shall not be 

attributed from one crew member. 

The crew’s cumulative power plant experience is the sum of each individual’s power 

plant experience. Power plant experience, for example, is experience gained by working 

at nuclear power plants, conventional power plants, and military propulsion plants. 

Cumulative power plant experience does not involve weighting factors or maximum 

credit limits. 
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In addition to the experience requirement mentioned above, each operating crew shall 

be staffed with a senior reactor operator with hot plant experience (previously defined in 

1.1, Licensed Operator Experience Requirements Prior to Commercial Operation). If a 

senior reactor operator with hot plant experience is not available, then a shift advisor 

may be substituted. The shift advisor will have at least one year of on-shift licensed 

senior reactor operator experience at a similar type (PWR/BWR) operating plant, and will 

have completed a training program on the design for which they are advising. While 

observing crew performance, the shift advisor will make recommendations to the shift 

manager only, and will not interfere with the licensed responsibilities of the operating 

crew. The shift advisor will have direct access to plant senior management to resolve 

issues. Shift advisor duties include, but are not limited to the following: 

• Monitor procedure adherence 

• Observe the conduct of prejob briefs, shift turnover, plant evolutions, nonlicensed operator rounds, plant tours, and post job debriefs 

• Monitor overall station risk 

Weighting factors and maximum credit limits for determining cumulative nuclear power 

plant operating crew experience are shown in Table 3, Cumulative Nuclear Power Plant 

Operating Crew Experience Equivalencies. 

1.3 Conduct of On-the-Job Training (OJT) 

Until plant construction is completed, acceptable methods for the conduct of on-the-job 

training include discussion, simulation, and use of mockup equipment and virtual reality 

technology 

1.4 Use of Part-Task/Limited Scope Simulators 

Part-task or limited scope simulators may be used during licensed operator training. 

1.5 Licensed Operator Continuing Training 

Licensed operator continuing training begins within 90 days following the issuance of the 

first operator license. Continuing training content is systematically determined to 

maintain operator knowledge of plant operation. 
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1.6 Cold Licensing process Applicability and Termination 

The cold licensing process described in this document may be applied to each unit of a 

multi-unit site. 

Cold license guidance items 1 through 9 on Table 1 will apply to any licensed operator 

training class started prior to initial fuel load. 

Cold license guidance items 3 through 9 on Table 1 will apply to any licensed operator 

training class started after initial fuel load and before completion of the first refueling 

outage. Items 1 and 2 cold license guidance are no longer allowable after initial fuel 

load. 

The cold licensing process will terminate after completion of the first refueling outage. 

As plant systems, components, and structures are completed, and as integrated plant 

operations begin, the systematic approach to training process will be used to adjust cold 

license class training methods and settings used to implement the guidance in Table 1 

items 1 through 9. The purpose is to optimize student learning using actual in-plant 

training and experience opportunities as they become available. 

1.7 Initial Licensed Operator Examination Schedule 

Administration of licensed operator examinations begins approximately 18 months prior 

to fuel load. 

2 REFERENCES 

2.1 Nuclear Energy Institute (NEI), “Technical Report on a Template for an Industry 

Training Program Description,” NEI 06-13A 

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Table 1 

Comparison of Hot and Cold License Guidance 

Current Hot License Guidance Applicable Position References Cold License Guidance 

1. Six months on-site at 

reactor for which license is sought. All 

ANSI 3.1-1993; 

4.4.1 4.4.2 4.5.1. 

Regulatory Guide 1.8 Rev 3: 

 2.8  2.10. 

NUREG 1021 Rev 9 ES-202 

Six months practical work assignments 

and 

Complete a site layout course 

2. One year on-site at the 

reactor for which the license is sought with six months as a nonlicensed operator. 

Reactor operator 

ANSI 3.1-1993: 

 4.5.1. 

Regulatory Guide 1.8 Rev 3: 

2.10. 

NUREG 1021 Rev 9 ES-202 

Six months practical work assignments 

and 

Complete a site layout course 

and 

Complete a site-specific non-licensed 

operator training program for selected 

nonlicensed operator tasks 
NEI 06-13A (Revision 2) 

March 2009 

A-8 

Table 1 

Comparison of Hot and Cold License Guidance 

Current Hot License Guidance Applicable Position References Cold License Guidance 

3. Pre-requisite experience 

requirements must be met to enter training program. All 

NUREG 1021 Rev 9 ES-202 Section D. 

Applicable experience requirements 

shall be met prior to NRC license 

issuance. 

4. Three years power plant 

experience at least one of which should have been at the plant for which the license is sought. 

Reactor operator 

ANSI 3.1-1993: 

4.5.1 

Regulatory Guide 1.8 Rev 3: 

2.10 

NUREG 1021 Rev 9 ES-202 

Six months practical work assignments 

and 

Cumulative operating crew experience 

requirements apply 

5. Reactor operator license 

actively involved in the performance of licensed duties for at least one year. 

Senior reactor operator 

(Non-degreed) 

Regulatory Guide 1.8 Rev 3: 

2.8 

NUREG 1021 Rev 9 ES-202 

Complete a site layout course 

and 

Complete a site-specific non-licensed 

operator training program for selected 

nonlicensed operator tasks 

and 

Complete a reactor operator and senior 

reactor operator training course 
NEI 06-13A (Revision 2) 

March 2009 

A-9 

Table 1 

Comparison of Hot and Cold License Guidance 

Current Hot License Guidance Applicable Position References Cold License Guidance 

6. At least three years of 

responsible nuclear power plant experience. 

Senior reactor operator 

 (Degreed) 

Regulatory Guide 1.8 Rev 3: 

1.3 2.8 

Complete a site layout course 

and 

Complete a site-specific non-licensed 

operator training program for selected 

nonlicensed operator tasks 

and 

Complete a reactor operator and senior 

reactor operator training course 

7. At least six weeks of 

operation above 20% power, and startup from subcritical to 20% power, and shutdown from above 20% power to cold (less than 212°F) and subcritical, and startup preparations following a fueling or refueling outage. 

Shift Supervisor 

 (Shift Manager) 

ANSI 3.1-1993: 

4.4.1 

Cumulative Operating Crew Experience 

requirements apply 

and 

Complete a Plant Operational Excellence 

Course or plant observation activity 
NEI 06-13A (Revision 2) 

March 2009 

A-10 

Table 1 

Comparison of Hot and Cold License Guidance 

Current Hot License Guidance Applicable Position References Cold License Guidance 

8. At least six weeks of 

operation above 20% power. 

Senior reactor operator ANSI 3.1-1993: 

4.4.2 

Cumulative Operating Crew Experience 

requirements apply 

and 

Complete a Plant Operational Excellence 

Course or plant observation activity 

9. Three years power plant 

experience and three years nuclear power plant experience 

Senior reactor operator 

ANSI 3.1-1993 

4.4.1 4.4.2 

Regulatory Guide 1.8 Rev 3: 

2.8 

NUREG 1021 Rev 9 ES-202 

Six months practical work assignments 

and 

Cumulative Operating Crew Experience 

requirements apply 
NEI 06-13A (Revision 2) 

March 2009 

A-11 

Table 2 

Illustration of Cold Licensing Plan by Candidate Type 

License Candidate Education 

Site 

Layout 

Course 

NLO Task 

Training RO Training 

SRO 

Training 

Plant 

Operational 

Excellence 

Course or 

Observation 

Activity 

Six Months 

Practical Work 

Assignments (1) 

Reactor operator High school diploma Yes Yes Yes N/A N/A Yes Senior reactor operator – degreed manager or degreed nonlicensed operator or technical staff 

Bachelor of Science or equivalent in engineering, engineering technology, or physical science 

Yes Yes Yes Yes Yes Yes 

Senior reactor operator – previous license or military equivalent 

High school diploma Yes Yes Yes Yes Yes (2) Yes 

Senior reactor operator – certified instructor High school diploma Yes Yes Yes Yes Yes Yes 

(1): practical work assignments includes activities such as participating in preoperational testing, procedure development and validation, 

human factors engineering activities, and task analysis verification, or conducting licensed operator classroom or simulator training 

(2): No, if candidate has hot license experience
NEI 06-13A (Revision 2) 

March 2009 

A-12 

Table 3 

Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies (1) 

Type of Experience Weighting Factor Max Credit Justification 

1. Commercial Nuclear Plant RO/SRO on same type 

plant (PWR/BWR) 

1.00 No Limit 

Task Analysis for same type plant are essentially the same

2. Commercial Nuclear Plant RO/SRO from different type 

plant (PWR/BWR) 

0.75 No Limit 

Task Analysis demonstrates that 75% of PWR/BWR tasks are similar 

3. Military Nuclear Propulsion Plant Experience 

(Propulsion Plant Watch Officer, Engineering Watch Supervisor, Reactor Operator, Engineering Officer of the Watch, Propulsion Plant Watch Supervisor) 

0.5 36 months 

For these military nuclear propulsion plant watch qualifications, approximately 50% of the job tasks are similar 

4. Military Nuclear Propulsion Plant Experience (Other 

than watch qualifications in 3 above such as Machinist Mate, Electricians Mate, Engineering Laboratory Technician, or Electronics Technician) 

0.25 36 months 

For these (other) watch qualifications, a range of similarities between job tasks (25-75%) exists, so a conservative value of 25% is credited 
NEI 06-13A (Revision 2) 

March 2009 

A-13 

Table 3 

Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies (1) 

Type of Experience Weighting Factor Max Credit Justification 

5. Reference Plant Simulator 5.00 12 months 

Industry analysis demonstrated that activities completed in a simulator, compare to an operating Control Room, occur in a ratio of approx. 400/1 

6. Limited Scope Simulator 3.00 9 months Similar to Reference Plant 7. Actual nuclear plant experience during construction 0.25 12 months 

Approximately 25% of the tasks during construction testing in preparation for system turnover to operations is similar to an operating facility 

8. Actual nuclear plant experience during pre-operational 

testing 

0.75 12 months 

75% of tasks during preoperational testing are similar to an operating facility 

9. Actual nuclear plant experience during fuel load and 

startup testing 

1.00 12 months Tasks during initial startup 

are similar to operating facility
NEI 06-13A (Revision 2) 

March 2009 

A-14 

Table 3 

Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies (1) 

Type of Experience Weighting Factor Max Credit Justification 

10. License Classroom training 0.25 9 months 

Theory of ops and specific plant design knowledge is critical to an operator’s success 

11. Participation in operator duties at another commercial 

nuclear facility. This includes nonlicensed operator duties 

0.75 12 months 

Task similarities 

12. Other Nuclear Plant experience 0.25 12 months 

Procedure writing, facility operation (water plant and other support facilities, etc) 

13. Licensed operator instructor 0.50 12 months 

Instructors will have participated in a train-thetrainer program that includes simulator, classroom (systems, theory). 

14. Bachelors Degree in an Engineering, Science or 

Technical field 

n/a 24 months 

College work (in these fields) gives student an understanding of the fundamentals of plant operations 
NEI 06-13A (Revision 2) 

March 2009 

A-15 

Table 3 

Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies (1) 

Type of Experience Weighting Factor Max Credit Justification 

15. Associates Degree (technical) n/a 6 months Student gains knowledge of fundamentals (1): Weighting factors and max credit values based on those in “Industry Evaluation of Operating Shift Experience Requirements” By: 

J.H. Miller Jr. 2/24/1984, and endorsed by Generic Letter number 84-16, Adequacy of On-Shift Operating Experience For Near TermOperating License Applicants, except for shaded rows which are added experience types based on new technology or additional analysis. 

NEI 06-13A (Revision 2) 

March 2009 

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APPENDIX B – 

FINAL SAFETY EVALUATION REPORT 

NEI 06-13, REVISION 0

NEI 06-13A (Revision 2) 

March 2009 

B-3 

Adrian P. Heymer, Senior Director 

New Plant Deployment Nuclear 

Generation Division Nuclear Energy 

Institute 1776 I Street, NW, Suite 400 

Washington, DC 20006-3708

SUBJECT: FINAL SAFETY EVALUATION FOR TOPICAL REPORT NEI 06-13, 

"TEMPLATE FOR AN INDUSTRY TRAINING PROGRAM" 

(PROJECT NO. 689; TAC NO. MD3406)

Dear Mr. Heymer:

By letter dated October 30, 2006, the Nuclear Energy Institute (NEI) submitted for U.S. Nuclear 

Regulatory Commission (NRC) staff review its proposed Template for an Industry Training 

Program, Revision 0.

Enclosed is the staffs safety evaluation (SE) which defines the basis for acceptance of 

NEI 06-13. On the basis of its review, the NRC staff finds that for combined license 

applications, NEI 06-13 provides an acceptable template for describing reactor operator and 

nonlicensed plant staff training programs.

Our acceptance applies only to material provided in NEI 06-13. We do not intend to repeat our 

review of the acceptable material described in the NEI 06-13. When the NEI 06-13 appears as 

a reference in regulatory applications, our review will ensure that the material presented applies 

to the specific application involved. Licensing requests that deviate from NEI 06-13 will be 

subject to a plant- or site-specific review in accordance with applicable review standards.

In accordance with the guidance provided on the NRC website, we request that NEI publish the 

accepted version of NEI 06-13 within three months of receipt of this letter. The accepted 

version should incorporate this letter and the enclosed SE after the title page. Typically, the 

accepted version would also contain historical review information, including NRC requests for 

additional information (RAIs) and your responses; however, that is not necessary for NEI 06-13 

because RAIs were not issued. The accepted versions shall include a "-A" (designating 

accepted) following the report identification symbol.

If future changes to the NRC's regulatory requirements affect the acceptability of NEI 06-13, NEI 

will be expected to revise NEI 06-13 appropriately, or justify its continued applicability for 

subsequent referencing.

UNITED STATES 

NULCEAR REGULATORY COMMISSION 

WASHINGTON, D.C. 20555-0001 

September 5, 2007 
NEI 06-13A (Revision 2) 

March 2009 

B-4 

A. Heymer - 2 -

If you have any questions, please contact Michael Canova at (301) 415-0737, or 

mac6@nrc.gov.

Sincerely,

Stephanie M. Coffin, Chief 

AP1000 Projects Branch 

Division of New Reactor Licensing 

Office of New Reactors 

Project No. 689 

Enclosure 

Safety Evaluation 

cc w/encl: See next page 
NEI 06-13A (Revision 2) 

March 2009 

B-5 

SAFETY EVALUATION REGARDING THE 

NUCLEAR ENERGY INSTITUTE

TOPICAL REPORT 06-13

"TEMPLATE FOR AN INDUSTRY TRAINING PROGRAM" 

REVISION 0 

1.0 BACKGROUND

By letter dated October 30, 2006, the Nuclear Energy Institute (NEI) submitted Template for an 

Industry Training Program," Revision 0 (NEI 06-13) for Nuclear Regulatory Commission (NRC) 

review and approval. The topical report provides a complete generic training program 

description for use with combined license applications. NEI 06-13 was developed by the NEI 

New Plant Training Task Force, which includes representatives from the four design-centered 

working groups, to assist in expediting NRC review of the combined license and issuance of the 

combined license. NEI 06-13 is not applicable to the review and issuance of construction 

permits or operating licenses. 

2.0 REGULATORY EVALUATION

The NRC staff verified that NEI 06-13, Revision 0 complies with the following regulations, 

regulatory guidance, NUREGs, and industry standards: 

• 10 CFR Part 19, "Notices, Instructions and Reports to Workers: Inspections and 

Investigations" 

• 10 CFR Part 26, "Fitness For Duty Programs" 

• 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities" 

• 10 CFR Part 50, Appendix E, "Emergency Planning and Preparedness for Production 

and Utilization Facilities" 

• 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined 

Licenses for Nuclear Power Plants" 

• 10 CFR Part 55, "Operators' Licenses" 

• Regulatory Guide 1.8, Rev. 3, "Qualification and Training of Personnel for Nuclear 

Power Plants" 

• Regulatory Guide 1.149, Rev. 3, "Nuclear Power Plant Simulation Facilities for Use 

in Operator Training and License Examinations" 

• NUREG-0711, Rev. 2, "Human Factors Engineering Program Review Model" 

• NUREG-0800, Rev. 2, Standard Review Plan, Section 13.2.1, "Reactor Operator 

Training" 

• NUREG-0800, Rev. 2, Standard Review Plan, Section 13.2.2, "Training for 

Nonlicensed Plant Staff 

• NUREG-0800, Standard Review Plan, Section 18.0, "Human Factors Engineering" 

• ANSI/ANS 3.1-1993, "Selection, Qualification, and Training of Personnel in Nuclear 

Power Plants" 

ENCLOSURE 
NEI 06-13A (Revision 2) 

March 2009 

B-6 

• NUREG-1021, Rev. 9, "Operator Licensing Examination Standards for Power Reactors" 

• NUREG-1220, Rev. 1, "Training Review Criteria and Procedures" 

• Generic Letter 86-04, "Policy Statement on Engineering Expertise on Shift," 

February 1986 

3.0 TECHNICAL EVALUATION

The staffs review concentrated on the proposed training program description format, attributes 

and level of detail. In evaluating the adequacy of the format, attributes and level of detail, the 

staff followed the guidance of the Standard Review Plan (NUREG-0800), Section 13.2.1 (SRP 

13.2.1), "Reactor Operator Training" and Section 13.2.2 (SRP 13.2.2), "Training for Nonlicensed 

Plant Staff." SRP 13.2.1 outlines the training and requalification program guidance for licensed 

reactor operators and senior reactor operators. SRP 13.2.2 outlines the training and retraining 

program guidance for nonlicensed plant staff. SRP 13.2.1 and 13.2.2 apply to construction 

permit, operating license, and combined license applicants. 

NEI 06-13 is organized into five areas, licensed operator training, training for positions listed in 10 

CFR 50.120, general employee training, selected other training programs, and the training 

effectiveness evaluation program. Other training programs selected for description include fire 

protection, emergency plan, physical security, and station management training programs. 

3.1 Licensed Operator Training

The "Licensed Operator Training" section of NEI 06-13 states that the Reactor Operator (RO) 

and Senior Reactor Operator (SRO) training programs will provide individuals with the 

knowledge, skills, and abilities needed to perform licensed operator duties. The reactor operator 

training program description includes a description of the 10 CFR 55.59 required licensed 

operator requalification program. The RO and SRO training and requalification programs will be 

developed, established, implemented and maintained using a systems approach to training 

(SAT) as defined by 10 CFR 55.4 and as endorsed by Regulatory Guide1.8 " Qualification and 

Training of Personnel for Nuclear Power Plants," ANSI/ANS-3.1-1993 "Selection, Qualification, 

and Training of Personnel in Nuclear Power Plants." In accordance with 10 CFR 55.46, a 

simulator will be used for training licensed personnel and for the administration of operating 

tests. 

NEI 06-13 further states that prior to initial fuel load, the number of licensed ROs and SROs will 

be sufficient to meet regulatory requirements, with allowances for licensing examination 

contingencies, and without the need for planned overtime. 

A summary of the RO and SRO training programs follows: 

1. The Licensed Operator Initial Training Program will prepare RO and SRO candidates for 

the NRC license exam. The program will be implemented in accordance with licensee 

developed administrative procedures. 

2. Reactor Operator candidates will receive training in the topics listed in 10 CFR 55.41. RO 

candidates will receive plant simulator training to demonstrate understanding and the 

ability to perform the actions listed in 10 CFR 55.45. 
NEI 06-13A (Revision 2) 

March 2009 

B-7 

3. In addition to the RO topics listed in 10 CFR 55.41, SRO candidates will receive training 

in the topics listed in 10 CFR 55.43. SRO candidates will receive plant simulator training 

to demonstrate understanding and the ability to perform the actions listed in 

10 CFR 55.45. 

4. Licensed Operator Requalification training will consist of regularly scheduled formal 

instruction, evaluation, and on-the-job training. Training material will be developed using 

the SAT process in accordance with licensee developed administrative procedures. All 

licensed operators will participate in continuing training. 

5. Licensed Operator Requalification Program content, course schedules and examination 

schedules will comply with 10 CFR 55.59 and will include industry operating experience 

training. Licensed Operator Requalification training for licensed personnel will be 

conducted in accordance with licensee developed administrative procedures. 

Based on the staff's review of the "Licensed Operator Training" section of NEI 06-13 outlined 

above, the staff concludes that NEI 06-13 clearly and sufficiently describes, in terms of scope and 

level of detail, the RO and SRO training programs to enable a reasonable assurance finding of 

acceptability for issuance of a combined license with verification of the RO and SRO training 

programs during the construction stage. 

3.2 Training for Positions Listed in 10 CFR 50.120

The "Training for Positions Listed in 10 CFR 50.120" section of NEI 06-13 states that the training 

programs for the positions listed in 10 CFR 50.120 will be designed, developed, implemented, 

and maintained using the SAT process. 10 CFR 50.120 requires training and qualification of the 

following categories of nuclear power plant personnel: 

• Non-licensed Operator 

• Shift Supervisor 

• Shift Technical Advisor 

• Instrument and Control Technician 

• Electrical Maintenance Personnel 

• Mechanical Maintenance Personnel 

• Radiological Protection Technician 

• Chemistry Technician 

• Engineering Support Personnel 

Course content and duration for each 10 CFR 50.120 training program will be determined using 

SAT methodology and will follow licensee developed administrative procedures. The 10 CFR 

50.120 training programs will be implemented and maintained no later than eighteen 

months prior to fuel load. 

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NEI 06-13A (Revision 2) 

March 2009 

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3.2.1 Non-licensed Operator (NLO) 

NLOs will receive instruction on operation of plant equipment and components under 

normal and emergency conditions. The non-licensed operator training program will be a 

combination of formal instruction and on-the-job training. In-plant training will include 

system walk downs, which will emphasize the use of procedures, the proper operation of 

equipment, and safe operating practices. Areas of training will include: 

• Fundamentals of mechanical and electrical components 

• Operation of equipment and systems 

• Operating procedures 

• Surveillance requirements 

• Operation of systems important to plant safety 

3.2.2 Shift Supervisor 

Prior to entering the training program, the shift supervisor will have been licensed as an 

SRO. The Shift Supervisors will receive additional training that addresses higher-level 

management skills and behaviors, and provides a broader perspective of plant 

operations. The Shift Supervisor training program will be a combination of formal 

instruction and on-the-job training. Initial shift supervisor training will include topics such 

as: 

• Application of Operating Experience 

• Problem-solving skills 

• Planning and managing evolutions 

• Maintaining a broad view of plant operations 

• Application of observation skills 

• Operating philosophy 

• Shift team management 

• Application of design bases to plant operations 

• Emergency Plan 

• Transient and Accident Analysis 

• Systems Approach to Training 

• Work controls 

3.2.3 Shift Technical Advisor (STA) 

STAs provide engineering expertise to the on-shift crew. Training provides the STA with 

the skills and knowledge to monitor equipment and system operation to assess plant 

conditions during abnormal, off-normal, and emergency events. The STA training 

program will be a combination of formal instruction and on-the-job training. STA initial 

training will include instruction in the following areas: 

• Responses to accidents and analyses of plant transients 

• Application of engineering principles to protection of the core 

• Mitigation of plant accidents 

- 4 - 
NEI 06-13A (Revision 2) 

March 2009 

B-9 

• Basis of plant and systems design 

• Reactor theory, thermodynamics, heat transfer, and fluid flow 

• General Operating Procedures, Abnormal and Emergency Operating 

Procedures, Technical Specifications, and Administrative Controls 

• Operational transient and accident analysis 

• Accident response training 

• Simulator training, including exercises in at least the following situations: 

- Plant or reactor startups to include a range such that reactivity feedback 

from nuclear heat addition is noticeable and heatup rate is established 

- Plant shutdown from greater than 50 percent power 

- Manual control of feedwater during startup or shutdown 

- Significant (10 percent or greater) power changes, in the power range, 

using controls as defined in 10 CFR 55.4 

3.2.4 Instrument and Control (I&C) Technician 

Initial training for I&C technicians will be a combination of formal instruction and 

on-the-job training. Training for I&C technicians will include instruction in the following 

areas: 

• Fundamentals of instrumentation and control 

• Pneumatic systems and equipment 

• Electronics 

• Fundamental systems training 

• Instrument and Control and other job-related procedures 

• Surveillance requirements 

• Mitigating core damage training commensurate with their responsibilities during 

accidents that involve severe core damage 

On-the-job training will permit I&C technicians to practice the skills and knowledge learned 

in the classroom. 

3.2.5 Electrical Maintenance Personnel (electricians) 

Initial training for electricians will be a combination of formal instruction and on-the-job 

training. Training for electricians will include instruction in the following areas: 

• Print reading 

• Use of electrical tools and test equipment 

• Fundamental systems training 

• Electrical components and equipment 

- 5 - 
NEI 06-13A (Revision 2) 

March 2009 

B-10 

• Electrical maintenance practices 

• Maintenance procedures 

On-the-job training will permit electricians to practice the skills and knowledge learned in 

the classroom. 

3.2.6 Mechanical Maintenance Personnel (mechanics) 

Initial training for mechanics will be a combination of formal instruction and on-the-job 

training. Training for mechanics will include instruction in the following areas: 

• Print reading 

• Use of hand tools, power tools, and measuring devices 

• Fundamental systems training 

• Mechanical components and equipment 

• Mechanical maintenance practices 

• Maintenance procedures 

On-the-job training will permit mechanics to practice the skills and knowledge learned in 

the classroom. 

3.2.7 Radiological Protection (RP) Technician 

Initial training for RP technicians will be a combination of formal instruction and on-the-job 

training. Training for RP technicians will include instruction in the following 

areas: 

• Principles of radiation 

• Radiationprotection and safety 

• Use of survey instruments 

• Use of analytical equipment 

• Radiation Protection procedures 

• Emergency Plan procedures 

• ALARA practices and procedures 

Fundamental systems training 

• Mitigating core damage training 

On-the-job training will permit RP technicians opportunities to operate radiation protection 

equipment and practice the skills and knowledge learned in the classroom. 

3.2.8 Chemistry Technician 

Initial training for chemistry technicians will be a combination of formal instruction and onthe-job training. Training for chemistry technicians will include instruction in the following 

areas: 

• Chemistry procedures 

• Laboratory practices 

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March 2009 

B-11 

• Conduct of analytical tests 

• Operation of laboratory equipment 

• Fundamental systems training 

• On-the-job training to include actual operation of analytical equipment and the 

use of procedures 

• Mitigating core damage training commensurate with their responsibilities during 

accidents that involve severe core damage 

• Power plant chemistry 

On-the-job training will permit chemistry technicians opportunities to operate analytical 

equipment and practice the skills and knowledge learned in the classroom. 

3.2.9 Engineering Support Personnel 

Engineering support personnel complete orientation training on the various aspects of 

nuclear technology in an operating plant environment. Initial training for engineering 

support personnel will be a combination of formal instruction and on-the-job training. 

Training for engineering support personnel will include instruction in the following areas: 

• Records management and document control 

• Applicable industrial and nuclear regulations, codes, and standards 

• Procedures and drawings 

• Applicable programs such as corrective action, configuration management, work 

control, and the Quality Assurance program 

• Technical Specifications 

• Fundamentals such as reactor theory, heat transfer, fluid flow, properties of 

materials, and chemistry 

• Plant systems, instrumentation, and components 

• Plant operations 

• Introductory review of accidents 

• Design processes 

On-the-job training will permit engineering support personnel opportunities to practice the 

skills and knowledge learned in the classroom. 

3.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120 

Personnel in positions listed in 10 CFR 50.120 will receive continuing training to maintain 

qualifications and enhance proficiency. Continuing training reinforces initial training by 

reiterating selected portions of the material. Continuing training also addresses new and 

modified procedures and plant design changes. 

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Operating Experience (OE) is included in continuing training for all programs. OE training 

provides personnel with actual examples of good practices and lessons learned. OE topics will 

be selected from Licensee Event Reports, corrective action databases, industry groups, and 

other sources. 

Continuing training programs will be developed in accordance with SAT principles and will be 

conducted in accordance with licensee developed administrative procedures. 

Shift Technical Advisors (STAs) will maintain their qualifications by participating in licensed 

operator requalification training. 

Based on the staffs review of the "Training for Positions Listed in 10 CFR 50.120" section of NEI 

06-13 outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes,in 

terms of scope and level of detail, the training programs for positions listed in 10 CFR 50.120 to 

enable a reasonable assurance finding of acceptability for issuance of a combined license with 

verification of the programs during the construction stage. 

3.3 General Employee Training

The "General Employee Training" (GET) section of NEI 06-13 states that GET consists of three 

components, Plant Access Training, Radiation Worker Training, and General Employee 

Requalification Training. 

3.3.1 Plant Access Training 

Prior to being granted unescorted access to the plant, members of the station staff, contractor 

workers, and unescorted visitors will complete Plant Access Training. Plant Access Training will 

include the following topics: 

• Station organization 

• Station facilities and layout 

• Station administration 

• Nuclear plant overview 

• Industrial safety 

• Fire protection 

• Quality assurance and quality control 

• Plant security 

• Emergency planning 

• Radiological orientation 

• Appropriate portions of 10 CFR 26 

• Appropriate portions of 10 CFR 19 

3.3.2 Radiation Worker Training 

Personnel whose job duties require unescorted access to radiologically controlled areas of the 

plant will receive instruction in the applicable aspects of radiation protection. Radiation Worker 

Training will include the following topics: 
NEI 06-13A (Revision 2) 

March 2009 

B-13 

• Sources of radiation 

• Types and measurement of radiation 

• Biological effects of radiation 

• Limits and guidelines, including Reg. Guide 8.13 

• Concept of As Low As Is Reasonably Achievable (ALARA) 

• Radiation dosimetry 

• Contamination 

• Internal exposure 

• Radiation work permits 

• Radiological postings 

• Radiological alarms 

• Radioactive waste 

• Rights and responsibilities 

• Protective clothing 

3.3.3 General Employee Requalification Training 

Personnel with unescorted access to the plant participate in annual requalification training. 

Requalification training will include those topics in 3.3.1 and 3.3.2, as applicable to continue to 

meet access requirements. Emphasis will be placed on changes to the plant, plant procedures 

and procedure changes, government regulations, and quality assurance requirements. As 

applicable, training will be conducted on industry operating experiences, Licensee Event 

Reports, and personnel errors. 

Based on the staff's review of the "General Employee Training" (GET) section of NEI 06-13 

outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes, in terms of 

scope and level of detail, the training programs for general employee training to enable a 

reasonable assurance finding of acceptability for issuance of a combined license with verification 

of the programs during the construction stage. 

3.4 Selected Other Training Programs

The "Selected Other Training Programs" section of NEI 06-13 addresses training for positions not 

specified by either 10 CFR 55, "Operators' Licenses" or 10 CFR 50.120, "Training and 

Qualification of Nuclear Power Plant Personnel." 

3.4.1 Fire Protection Training 

NEI 06-13 states that the training programs for fire protection personnel will be designed, 

developed, implemented, and maintained using the SAT process as defined by 10 CFR 55.4 

and as endorsed by Regulatory Guide-1.8. In addition, initial fire protection training will be 

completed prior to receipt of fuel at the site. Personnel assigned as fire brigade members will 

receive formal training prior to assuming brigade duties. Fire brigade members will also receive 

regularly scheduled retraining. Fire brigade training will comply with National Fire Protection 

Association Standard 600, "Standard on Industrial Fire Brigades." 

Training appropriate to the assigned work will be provided for the fire protection staff, fire watch 

personnel, and the general employee. Final Safety Analysis Report (FSAR) Section 9.5.1, "Fire 
NEI 06-13A (Revision 2) 

March 2009 

B-14 

Protection Program" will include additional information regarding the fire protection training 

programs. 

3.4.2 Emergency Plan Training Program 

NEI 06-13 states that Emergency Plan training will meet the requirements of 10 CFR 50 

Appendix E, Section IV. F, "Training" and 10 CFR 50.47(b)(15). Additional information about the 

Emergency Plan training program will be found in the Emergency Plan, which is a separate 

document. 

3.4.3 Physical Security Training Program 

NEI 06-13 states that training of security personnel will be discussed in FSAR Section 13.6, 

"Physical Security" and in the Physical Security Plan. 

3.4.4 Station Management Training Program 

NEI 06-13 states that station supervisors will receive Fitness for Duty training in accordance with 

10 CFR 26.22. The qualification requirements for managers and middle managers include 

training or experience in supervision or management. Training for supervisors develops their 

skills in the following areas: 

• Leadership 

• Interpersonal communications 

• Management responsibilities and limits 

• Motivation of personnel 

• Problem analysis and decision making 

• Administrative policies and procedures 

• Observation skills 

• Coaching 

Based on the staff's review of the "Selected Other Training Programs" section of NEI 06-13 

outlined above (fire protection, emergency plan, physical security, and station management 

training programs), the staff concludes that NEI 06-13 clearly and sufficiently describes, in terms 

of scope and level of detail, the training programs for fire protection, emergency plan, physical 

security, and station management training to enable a reasonable assurance finding of 

acceptability for issuance of a combined license with verification of the programs during the 

construction stage. 

3.5 Training Effectiveness Evaluation Program

NEI 06-13 states that the program to evaluate the effectiveness of training programs will be based 

on three independent inputs: the supervisor of the trainee, the trainee, and an educational 

content evaluation of the instructional techniques and materials. 

3.5.1 Supervisory Review for Training Effectiveness 

The supervisory review will evaluate the content and effectiveness of training programs as 

related to the duties and job responsibilities of the trainees. Reviews may be performed by the 

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March 2009 

B-15 

supervisor of the trainee (former student) meeting with appropriate Training Department 

personnel, by designated oversight personnel (Quality Assurance or instructional technologists), 

or by observing employee performance in the job setting. 

Management observations of training will be discussed to determine topics that may require 

additional training or subjects that may be removed from the training program. 

3.5.2 Trainee Review of Training Effectiveness 

Following selected courses or training cycles, trainees will have the opportunity to provide 

comments regarding the effectiveness of the instructional methods and content relevancy to their 

jobs. These comments will used in the evaluation of both instruction and content of the training 

program. 

3.5.3 Review for Effectiveness of Instructional Techniques and Materials 

The effectiveness of instructional techniques and materials review assesses the clarity and 

applicability of training material and instructional aids. Management observations of instructors in 

the teaching environment will be conducted by an educational specialist qualified to monitor and 

evaluate classroom performance. Full time instructors will receive basic indoctrination in 

instructional techniques as soon as practicable after assuming instructional duties. The 

educational specialist will conduct periodic seminars in instructional techniques, discussing areas 

where group performance could be improved and recommends innovative techniques observed 

at this or other power stations. 

Based on the staffs review of the "Training Effectiveness Evaluation Program" section of NEI 

06-13 outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes, in 

terms of scope and level of detail, the training effectiveness evaluation program to enable a 

reasonable assurance finding of acceptability for issuance of a combined license with verification 

of the programs during the construction stage. 

4.0 CONCLUSION

Operator Licensing and Human Performance Branch (COLP) staff used the acceptance criteria of 

SRP 13.2.1 and 13.2.2 as the basis for evaluating the acceptability of NEI 06-13, "Template for 

an Industry Training Program Description," Revision 0. The COLP staff has determined that NEI 

06-13, "Template for an Industry Training Program," Revision 0 is consistent with the training and 

qualification requirements, guidance, and industry standards for licensed and nonlicensed plant 

staff as outlined in Section 2.0 of this evaluation with verification of the programs during the 

construction stage. 

The training programs for licensed and nonlicensed plant staff described in NEI 06-13 will 

incorporate instructional requirements to qualify personnel to operate and maintain the facility, in 

a safe manner, in all modes of operation. The training programs will be developed and 

maintained in compliance with the facility license and applicable regulations. The training 

programs will be periodically evaluated and revised to reflect industry experience; to incorporate 

changes to the facility, procedures, regulations, and quality assurance requirements; and by 

management to determine overall program effectiveness. The training programs will be further 

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B-16 

described in site and/or corporate procedures. Sufficient records will be maintained and kept 

available for NRC inspection during construction to verify adequacy of the programs. 

The results of reviews of operating experience will be incorporated into the training and 

retraining programs in accordance with the provisions of TMI Action Item I.C.5, Appendix 1 A. 

Training programs will encompass all phases of plant operation including preoperational testing 

and low-power operation in accordance with the provisions of TMI Action Item I.G. Sufficient 

plant staff will be trained prior to fuel load to provide for safe plant operations. 

The licensed operator training program, to be derived using SAT principles, will be developed by 

the applicant and will meet the regulatory guidance of Regulatory Guide 1.8 and 10 CFR Part 

55. Licensed operators and senior operators will receive training in security procedures, 

radiological emergency plans, administrative procedures, and radiation protection. Simulation 

facilities used for the licensed operator training program will meet the guidance of Regulatory 

Guide 1.149. The licensed operator requalification training program conforms to the 

requirements of 10 CFR Part 50 and 10 CFR 55.59 and follows the guidance in Regulatory 

Guide 1.8. Sufficient licensed operators will have completed the training program prior to fuel 

load to ensure that the minimum shift staffing requirements of 10 CFR 50.54 will be met. The 

licensed operator training program will be verified during the construction stage. 

In accordance with the requirements of 10 CFR 50.34(a) and (b), the applicant has provided 

information related to its training program for nonlicensed personnel. The training and retraining 

of nonlicensed plant staff will meet the guidance of Regulatory Guide 1.8. The applicant has 

committed to establish, implement, and maintain training programs that will utilize a systems 

approach to training as required by 10 CFR 50.120 and as defined in 10 CFR 55.4. All initial 

training of the nonlicensed plant staff is scheduled to be completed prior to fuel loading. Training 

programs for personnel listed in 10 CFR 50.120 will be verified during the construction stage. 

The applicant will meet the requirements of 10 CFR 19 by developing and implementing a 

training program that will inform and instruct personnel regarding radioactive materials and 

radiation, health protection problems associated with exposure to radiation, the means and 

responsibilities for the protection of workers from radiation, and the availability upon request of 

radiation exposure reports. The training program includes initial training and periodic retraining 

for categories of employees and nonemployees whose assistance may be needed in the event of 

a radiological emergency. The GET program will be verified during the construction stage. 

The applicant will meet the requirements of 10 CFR Part 26 by having a training program to 

ensure that personnel are adequately informed regarding the fitness-for-duty policy. Supervisors 

and persons assigned to escort duties will be trained to ensure that they understand their roles, 

responsibilities, and procedures for the fitness-for-duty program. The fitness-for-duty training 

program will ensure supervisors and escorts will possess knowledge and skills necessary to 

recognize behavioral changes, drugs, and/or indications of the use of drugs. The fitness-for-duty 

training program will be verified during the construction stage. 

NEI 06-13 states that training will be provided based on individual employee experience, the 

intended position, and previous training and education of the individual. Training Department 

personnel may be supplemented by other personnel such as subject matter experts, contract 

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March 2009 

B-17 

staff, and vendor representatives. Formal instruction will be presented through a combination of 

classroom lectures, e-learning, assigned reading, simulator training and evaluations, and other 

delivery techniques. 

On the basis of its review, the staff concludes that NEI 06-13, "Template for an Industry Training 

Program," Revision 0 adequately provides guidance for establishing the licensed operator and 

nonlicensed plant staff training programs. Accordingly, the COLP staff concludes that NEI 06-

13, "Template for an Industry Training Program," Revision 0 complies with the applicable NRC 

regulations, guidance, and industry standards and can be utilized by applicants for combined 

license applications. 

5. REFERENCES

5.1 Heymer, A. P., Nuclear Energy Institute, to the U.S. NRC, NEI 06-13, "Template for an 

Industry Training Program Description," October 30, 2006. 

5.2 NUREG-0800, "Standard Review Plan," Section 13.2.1, "Reactor Operator Training," 

and Section 13.2.2, "Training for Nonlicensed Plant Staff" 

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NEI 06-13A (Revision 2) 

March 2009 

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NEI New Reactors Mailing List List #35 

cc: 

Ms. Michele Boyd 

Legislative Director 

Energy Program 

Public Citizens Critical Mass Energy 

 and Environmental Program 

215 Pennsylvania Avenue, SE Washington, DC 

20003 

Mr. Marvin Fertel Senior 

Vice President 

and Chief Nuclear Officer 

Nuclear Energy Institute 

1776 I Street, NW 

Suite 400 

Washington, DC 20006-3708 

Ms. Leslie Compton Kass 

Senior Project Manager 

Nuclear Energy Institute 

1776 I Street, N.W. 

Suite 400 

Washington, DC 20006-3708 

Mr. Brian Smith 

Nuclear Energy Institute 

1776 I Street, NW, 

Suite 400 

Washington, DC 20006 

Mr. Ed Wallace 

General Manager - Projects 

PBMR Pty LTD 

P. O. Box 9396 

Centurion 0046 

Republic of South Africa 

Edward G. Wallace 

Sr. General Manager 

U.S. Programs 

PBMR Pty. Ltd. 

PO Box 16789 

Chattanooga, TN 37416 

Mr. Gary Wright, Director 

Division of Nuclear Facility Safety 

Illinois Emergency Management Agency 

1035 Outer Park Drive 

Springfield, IL 62704 
NEI 06-13A (Revision 2) 

March 2009 

B-19 

NEI New Reactors Mailing List 

Email

APH@NEI.org (Adrian Heymer) 

awc@nei.org (Anne W. Cottingham) 

bennettS2@bv.com (Steve A. Bennett) 

BrinkmCB@westinghouse.com (Charles Brinkman) 

chris.maslak@ge.com (Chris Maslak) 

cwaltman@roe.com (C. Waltman) 

david.lewis@pillsburyiaw.com (David Lewis) 

dlochbaum@UCSUSA.org (David Lochbaum) 

frankq@hursttech.com (Frank Quinn) 

greshaja@westinghouse.com (James Gresham) 

jgutierrez@morganiewis.com (Jay M. Gutierrez) 

jim.riccio@wdc.greenpeace.org (James Riccio) 

JNesrsta@cpsenergy.com (James J. Nesrsta) 

John.o'neil@pillsburylaw.com (John O'Neil) 

Joseph.savage@ge.com (Joseph Savage) 

Joseph_Hegner@dom.com (Joseph Hegner) 

KSutton@morganlewis.com (Kathryn M. Sutton) 

kwaugh@impact-net.org (Kenneth O. Waugh) 

lynchs@gao.gov (Sarah Lynch - Meeting Notices Only) 

maria.webb@pillsburylaw.com (Maria Webb) 

mark.beaumont@wsms.com (Mark Beaumont) 

matias.travieso-diaz@pillsburylaw.com (Matias Travieso-Diaz) 

media@nei.org (Scott Peterson) 

mike_moran@fpl.com (Mike Moran) 

nirsnet@nirs.org (Michael Mariotte) 

patriciaL.campbell@ge.com (Patricia L. Campbell) 

paul.gaukler@pillsburylaw.com (Paul Gaukler) 

Paul@beyondnuclear.org (Paul Gunter) 

phinnen@entergy.com (Paul Hinnenkamp) 

pshastings@duke-energy.com (Peter Hastings) 

RJB@NEI.org (Russell Bell) 

RKTemple@cpsenergy.com (R.K. Temple) 

roberta.swain@ge.com (Roberta Swain) 

ronald.hagen@eia.doe.gov (Ronald Hagen) 

sandra.sloan@areva.com (Sandra Sloan) 

sfrantz@morganlewis.com (Stephen P. Frantz) 

VictorB@bv.com (Bill Victor) 

waraksre@westinghouse.com (Rosemarie E. Waraks) 

G:/DNRL/DNRL Mailing Lists (Revised 9/7/07)

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NEI 06-13A (Revision 2) 

March 2009 

C-1 

APPENDIX C – 

FINAL SAFETY EVALUATION REPORT

NEI 06-13A, REVISION 1

NEI 06-13A (Revision 2) 

March 2009 

C-3 

Mr. Russell J. Bell, Director 

New Plant Licensing Nuclear 

Generation Division 

Nuclear Energy Institute 

1776 I Street, NW, Suite 400 

Washington, DC 20006-3708 

SUBJECT: FINAL SAFETY EVALUATION FOR TOPICAL REPORT NEI 06-13A, 

"TEMPLATE FOR AN INDUSTRY TRAINING PROGRAM DESCRIPTION," 

REVISION 1 

Dear Mr. Bell: 

On September 5, 2007, the U.S. Nuclear Regulatory Commission (NRC) accepted the Nuclear 

Energy Institute (NEI) 06-13, "Template for an Industry Training Program Description," Revision 

0 as an acceptable template for describing reactor operator (RO) and non-licensed plant staff 

training programs for combined license applications (COLAs). By letter dated March 28, 2008, 

the NEI submitted NEI 06-13A, "Template for an Industry Training Program Description," 

Revision 1, for NRC review and approval. The change to NEI 06-13A is the addition of Appendix 

A, "Cold License Training Plan." The change to NEI 06-13A, Revision 1 is exclusive to the 

addition of the Appendix A and the remainder of the template has not been changed. NEI 06-

13A, Revision 1 provides a generic training program description for use with COLAs. In addition, 

Appendix A to NEI 06-13A, Revision 1 provides licensed operator cold license eligibility 

guidance. NEI 06-13A, Revision 1 was developed by the NEI New Plant Training Task Force, 

which includes representatives from the four design-centered working groups, to assist in 

expediting NRC review of the combined license (COL) and issuance of the COL. 

Enclosed is the staffs safety evaluation (SE) which defines the basis for acceptance of NEI 06-

13A, Revision 1. The NRC staff finds that for COLAs, NEI 06-13A, Revision 1, provides an 

acceptable template for describing the licensed operator training program, the licensed operator 

cold license eligibility requirements, and the non-licensed plant staff training program. 

Our acceptance applies only to material provided in NEI 06-13A, Revision 1. We do not intend to 

repeat our review of the acceptable material described in the NEI 06-13A, Revision 0. When NEI 

06-13A, Revision 1 appears as a reference in COLAs, our review will ensure that the material 

presented applies to the specific application involved. Licensing requests that deviate from NEI 

06-13A, Revision 1, will be subject to a plant-specific or site-specific review in accordance with 

applicable review standards. 

In accordance with the guidance provided on the NRC website, we request that NEI publish the 

accepted version of NEI 06-13A, Revision 1 within 3 months of receipt of this letter. The 

accepted version should incorporate this letter and the enclosed SE. The accepted version 

should also contain historical review information, including NRC requests for additional 

information and your responses. The accepted versions shall include a "-A" (designating 

accepted) following the report identification symbol.

UNITED STATES 

NULCEAR REGULATORY COMMISSION 

WASHINGTON, D.C. 20555-0001 

December 5, 2008
NEI 06-13A (Revision 2) 

March 2009 

C-4 

If future changes to the NRC's regulatory requirements affect the acceptability of NEI 06-13A, NEI 

will be expected to revise NEI 06-13A appropriately, or justify its continued applicability for 

subsequent referencing. 

If you have any questions, please contact Sheryl A. Burrows at (301) 415-6086 or via email at 

Sheryl.Burrows@nrc.gov. 

Sincerely, 

William D. Reckley, Chief 

Rulemaking, Guidance, and 

 Advanced Reactors Branch 

Division of New Reactor Licensing 

Office of New Reactors 

Project No. 689 

Enclosure: 

Safety Evaluation 

cc w/encl: See next page 

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March 2009 

C-5 

SAFETY EVALUATION

REGARDING THE NUCLEAR ENERGY INSTITUTE 

"TEMPLATE FOR AN INDUSTRY TRAINING PROGRAM DESCRIPTION" 

NEI 06-13A (REVISION 1)

1.0 BACKGROUND

On September 5, 2007, the U.S. Nuclear Regulatory Commission (NRC) accepted the Nuclear 

Energy Institute (NEI) 06-13, "Template for an Industry Training Program Description," Revision 

0 (Agencywide Documents Access and Management System (ADAMS) accession no. 

ML070950479) as an acceptable template for describing reactor operator (RO) and nonlicensed 

plant staff training programs for combined license applications (COLAs). By letter dated March 

28, 2008, the NEI submitted NEI 06-13A, "Template for an Industry Training Program 

Description," Revision 1, for NRC review and approval. NEI 06-13, Revision 0, "Template for an 

Industry Training Program Description," was previously reviewed and approved on September 5, 

2007 (ADAMS accession no. ML070950479). The change to NEI 06-13 is the addition of 

Appendix A, "Cold License Training Plan." The change to NEI 06-13 is exclusive to the addition 

of the Appendix A. The remainder of the template has not been changed. In addition to 

providing a generic training program description for use with COLAs, NEI 06-13 provides 

licensed operator cold license eligibility guidance. The template and revision was developed by 

the NEI New Plant Training Task Force, which includes representatives from the four designcentered working groups, to assist in expediting NRC review of the combined license (COL) and 

issuance of the COL. Changes to NEI 06-13 were discussed at public meetings held on May 24, 

2007, September 13, 2007, January 8, 2008, and March 5, 2008. 

Prior to obtaining an operating license from the NRC and prior to entering a licensed operator 

training program, an applicant must satisfy certain nuclear power plant (NPP) experience 

requirements and perform specific operating plant evolutions as described in the Title 10 of the 

Code of Federal Regulations, Part 55 (10 CFR Part 55); "Operators' licenses," 10 CFR 

Section 50.120; "Training and qualification of nuclear power plant personnel," Regulatory Guide 

(RG) 1.8, Revision 3; "qualification and training of personnel for nuclear power plants, 

"NUREG-1021, Revision 9; "Operator Licensing Examination Standards for Power Reactors," 

and ANSI/ANS-3.1-1993; "Selection, Qualification, and Training of Personnel for Nuclear Power 

Plants." 

In 1984, an Industry Working Group met to "define components of operating shift experience 

and establish acceptable methods of meeting this experience." On February 24, 1984, at a 

meeting before the Commission, the industry presented the industry position on the level and 

type of operating shift experience required for the safe startup and initial operation of a nuclear 

generating plant. This industry position has come to be known as "cold license eligibility." 

The industry position for the licensed shift positions (shift supervisor, senior operator, and 

licensed operator) required power plant experience, nuclear plant experience, and "hot" 

operational experience. The experience requirements were derived from ANSI/ANS-3.1-1981, 

"Selection, Qualification and Training of Personnel for Nuclear Power Plants," and required 

additional hot plant shift time within each crew. 

Enclosure 
NEI 06-13A (Revision 2) 

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The power plant experience requirement provided assurance of a minimum of 13 years per shift 

crew. The nuclear plant experience requirement could be met using experience equivalencies 

derived from ten categories of experience, with specific weighting factors and maximum time 

credited to each category and required a minimum of six years equivalent experience per crew. 

Each crew was required to have hot-participation experience within the crew. Hot participation 

was defined as direct involvement in reviews and discussions leading to decisions relative to the 

operation of a commercial nuclear plant, or, direct hands-on operation as a trainee at a 

commercial NPP. Hot participation included six weeks participation in senior reactor operator 

(SRO) and RO duties at an operating plant of the same type (commercial boiling-water reactor 

(BWR) or pressurized-water reactor (PWR)), Shift Supervisor participation in reactor startup and 

shutdown at the same type plant, or six weeks participation as an SRO-Licensed STA 

participation at an operating plant of the same type. 

In addition, if any hot participation experience requirement was not satisfied by either the Shift 

Supervisor or Senior Operator, a "Qualified Advisor" must be on shift. 

Generic Letter (GL) 84-10, "Administration of Operating Tests Prior to Initial Criticality" informed 

licensees of actions to take for all applicants for RO and SRO licenses at facilities prior to initial 

criticality who did not have extensive actual operating experience. The Commission authorized 

the staff to grant exemptions to those individuals who have completed a cold license training 

program for their facility. The program must have included: (a) nuclear fundamentals, including 

ten reactor startups at a nuclear reactor, (b) observation training on shift at a comparable 

operating reactor, (c) training on a simulator and (d) training on the actual system design of the 

candidate's plant. An exemption request was not needed for individuals who completed a cold 

license training program that included the four elements. The necessary exemption was to be 

granted as part of the issuance of the operator's license, provided that the individual's records 

clearly indicated satisfactory completion of a program. 

GL 84-16, "Adequacy of On-Shift Operating Experience for Near Term Operating License 

Applicants" discussed a June 14, 1984 letter sent to J. H. Miller, President, Georgia Power 

Company from the Chairman of the NRC, N. J. Palladino. The June 14, 1984 letter accepted, 

with some clarifications, the Industry Working Group proposal presented to the Commission on 

February 24, 1984. It was noted in GL 84-16 that "acceptance of these experience requirements 

by the NRC does not alter the guidance for eligibility, included in RG 1.8 and NUREG-0737, for 

RO and SRO licensing examination candidates." 

RG 1.8, Revision 2, "Qualification and Training of Personnel for Nuclear Power Plants" 

discusses cold license applicants. A cold license candidate is one that uses cold license 

eligibility guidance to sit for the operator licensing examination. Licensed operator candidates 

utilizing cold license eligibility guidance are examined using a cold license examination. Cold 

license examinations are defined as those examinations administered before the unit has 

completed preoperational testing and the initial startup test program. Hot examinations are 

those administered after this condition is attained. 

10 CFR Part 55, "Operators' licenses" states "The Commission shall use the criteria in 

NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," in effect six 

months before the examination date to prepare the written examinations...and the operating

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tests... The Commission shall also use the criteria in NUREG-1021 to evaluate the written 

examinations and operating tests prepared by power reactor facility licensees..." 

ES-202, "Preparing and Reviewing Operator Licensing Applications" of NUREG 1021 states 

"Regulatory Guide 1.8 (Revision 2 or 3) and the guidelines for education and experience 

promulgated by the National Academy for Nuclear Training (NANT) outline acceptable methods 

for implementing the Commission's regulations in this area. In addition, methods different from 

those set forth in Regulatory Guide 1.8 (Revision 2 or 3) or the NANT guidelines may be 

acceptable if a facility licensee provides an adequate basis for using such methods," Appendix 

A to NEI 06-13 is a different methodology for determining experience for new reactor licensed 

operators. 

On May 24, 2007, NRC staff met with representatives of NEI, the nuclear industry, and new 

reactor vendors in a public meeting (ADAMS accession no. ML071220329). The purpose of this 

meeting was to discuss issues related to the NRC operator licensing program for COLAs. The 

industry proposed to use limited-scope simulators for operator training because of the 

aggressive timelines leading to fuel loading. In addition, plant-referenced simulators are not 

projected to be available for reactivity manipulations and reactor startup until eighteen months 

prior to fuel load, in time for the licensing examination. Existing licensed operator eligibility 

requirements and anticipated problems with 'cold licensing' of operators were discussed. NEI 

proposed to have the industry develop alternative requirements that leverage technology. Cold 

license examinations are administered before completion of pre-operational and initial startup 

testing. Anticipated difficulties include conducting systems training prior to construction of the 

systems, reactivity manipulations without a plant or plant-referenced simulator, and meeting 

operator experience guidance. 

On September 13, 2007, NRC staff met with representatives of NEI, the nuclear industry, and 

new reactor vendors in a public meeting (ADAMS accession no. ML072770067) to discuss the 

operator licensing white papers (ADAMS accession no. ML072420450) submitted by NEI on 

August 21, 2007. The operator licensing white papers discuss cold licensing and training of the 

estimated 450 licensed operators which are projected to be necessary to operate the new NPPs. 

Meeting participants agreed that existing regulatory guidance addresses the training and 

qualification needs of licensed operator candidates for operating reactors but does not address 

the situation in which the plant is not operational (i.e., under construction). In addition, guidance 

related to the cold licensing of operators needs to be developed so that clear, appropriate, and 

achievable training commitments can be documented in each facility's COLA. It was also 

agreed that any process should follow current operator licensing guidance for operating plants 

with additional guidance in the areas of experience requirements, training program 

implementation, job performance measures (JPMs) and on-shift on-the-job training (OJT) during 

construction, simulator training using a limited scope simulator, continuing training for license 

candidates, and licensing examinations. 

Concerns expressed by the NRC during this meeting included documentation of individual 

experience, documentation of experience obtained while an individual is in a training status, 

consistent calculation of time spent obtaining experience prior to licensing, activities that count 

toward meeting the experience guidelines must be meaningful, and, operating crew overall 

experience levels. 

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On January 8, 2008, NRC staff met with representatives of NEI, the nuclear industry, and new 

reactor vendors in a public meeting (ADAMS accession no. ML080290034) to discuss the 

operator licensing white papers (ADAMS accession no. ML080150100) submitted by NEI on 

December 13, 2007. It was agreed that time spent obtaining experience prior to licensing must 

be meaningful and consistently calculated and the final determination of meeting the experience 

requirements rests with the NRC. Consensus was reached in the areas of training program 

accreditation and implementation, in-plant JPMs and on-shift OJT during construction, simulator 

training using a part task/limited scope simulator, continuing training prior to and following NRC 

licensing exams, and scheduling of licensing examinations. The NRC noted that additional 

guidance needs to be developed in the areas of documentation of individual experience and, 

operating crew overall experience levels. 

On March 5, 2008, NRC staff met with representatives of NEI, the nuclear industry, and new 

reactor vendors in a public meeting (ADAMS accession no. ML080910315) to discuss the 

operator licensing white papers submitted by NEI on February 29, 2008. Consensus between 

the NRC and NEI was reached in the areas of training program accreditation and 

implementation, in-plant JPMs and on-shift OJT during construction, simulator training using a 

part task/limited scope simulator, continuing training prior to and following NRC licensing exams, 

scheduling of licensing examinations, documentation of individual experience, and, operating 

crew overall experience. 

2-0 REGULATORY EVALUATION

The NRC staff verified that changes to NEI 06-13 comply with the following regulations, 

regulatory guidance, NUREGs, and industry standards: 

- 10 CFR Part 50, "Domestic licensing of production and utilization facilities" 

- 10 CFR Part 52, "Licenses, certifications, and approvals for nuclear power plants" 

- 10 CFR Part 55, "Operators' licenses" 

- RG 1.8, "Qualification and Training of Personnel for Nuclear Power Plants" 

- RG 1.149, "Nuclear Power Plant Simulation Facilities for Use in Operator Training and 

License Examinations 

- "NUREG-0800, Standard Review Plan (SRP), Section 13.2.1, "Reactor Operator 

Requalification Program; Reactor Operator Training" 

- NUREG-1021, "Operator Licensing Examination Standards for Power Reactors" 

- ANSI/ANS 3.1-1993, "Selection, Qualification, and Training of Personnel in Nuclear 

Power Plants" 

- GL 84-10, "Administration of Operating Tests Prior to Initial Criticality" 

- GL 84-16, "Adequacy of On-Shift Operating Experience for Near Term Operating License 

Applicants" 

3.0 TECHNICAL EVALUATION

The staffs review of Appendix A, "Cold License Training Plan" to NEI 06-13A, "Template for an 

Industry Training Program description," Revision 1 (NEI 06-13), focused on the "cold licensing" 

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NEI 06-13A (Revision 2) 

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process for the selection, training and licensing of operators for the new nuclear plants. Specific 

areas of review included: 

A. Experience Requirements for License Candidates 

B. Crew Experience Requirements during the First Year of Operation 

C. Training Program Accreditation and Implementation 

D. In-Plant JPMs and On-Shift OJT during the Construction Phase 

E. Simulator Training Using a Part Task/Limited Scope Simulator 

F. Continuing Training for License Candidates Prior to NRC License Exams 

G. Scheduling of NRC License Examinations 

H. Initiation of Licensed Operator Continuing Training 

3.1 Licensed Operator Training Program Prior to Completion of the First Refueling Outage

The "Licensed Operator Training Program Prior to Completion of the First Refueling Outage" 

section of NEI 06-13 states that persons eligible for the "cold licensing process" will be required 

to meet the following requirements: 

RO candidates shall have a High School Diploma or equivalent 

SRO candidates shall have at least one of the following: 

Previously held an SRO license at an operating NPP 

Previously held an RO license at an operating NPP 

Have a Bachelor's Degree in engineering or science as defined by RG 1.8, Revision 3. 

Two years military experience in a position equivalent to a RO. 

NEI 06-13 states that experience as a licensed operator training instructor with an SRO 

certification is acceptable as experience for SRO candidates. As is the current NRC practice, 

the eligibility of licensed operator instructors to sit for the licensing examination will be evaluated 

on a case-by-case basis. 

The requirements of this section are applicable to each unit of a multiple unit site. 

The guidance in this section is equivalent to the guidance of RG 1.8, Revision 3, "Qualification 

and Training of Personnel for Nuclear Power Plants," ANSI/ANS 3.1-1993, "Selection, 

Qualification, And Training of Personnel for Nuclear Power Plants," and GL 84-16, "Adequacy of 

On-Shift Operating Experience for Near Term Operating License Applicants", and is acceptable. 

The cold licensing process for the selection, training and licensing of operators for the new 

nuclear plants adheres to current industry guidance for operating plants with exemptions and 

alternatives in the following areas: 

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3.1.1 Experience Requirements for License Candidates

Licensed operator candidates do not need to satisfy all of the experience requirements prior to 

entering a licensed operator training program or sitting for the operator licensing examination. 

Experience and performance requirements that have not been met when the operator licensing 

examination is administered shall be met prior to issuance of the individual's license after 

notification from the licensee that all experience and performance requirements have been met. 

The NRC will determine the acceptability of experience for those candidates utilizing the 

alternative experience guidance. 

The methods listed below are an acceptable method of providing the licensed operator 

candidate with meaningful experience on the reactor and at the site for which the license is 

sought. Methods for gaining meaningful experience include completing systematically designed 

training courses, and performing work assignments such as preoperational and startup testing, 

procedure development and validation, human factors engineering activities, task analysis 

verification, or conducting licensed operator classroom or simulator training. Additionally, for 

these activities to be considered meaningful, they must be associated with safety significant, 

defense in depth (DID), or major plant components or systems. 

All cold licensed operator candidates will: 

Complete a systematically designed site familiarization course. 

Complete a site-specific non-licensed operator OJT program on selected non-licensed 

operator tasks. The tasks selected will be those tasks that are important to plant 

operation with regard to nuclear safety, DID, or that are risk significant. 

Participate in work assignments for a minimum of six months that includes preoperational 

testing, and one or more of the following: 

Procedure development and validation 

Human factors engineering activities 

Task analysis verification 

Licensed operator classroom presentations or simulator training implementation 

SRO cold license candidates will complete a site-specific SRO training course. SRO cold 

license candidates that do not have "hot" plant experience will complete a six week plant 

Operational Excellence course that will be completed either in a full scope plant simulator or 

through observation of control room activities at a similar type operating nuclear plant. The 

course will familiarize the candidate with the operational interfaces encountered in a nuclear 

plant control room. 

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C-11 

"Hot" plant experience is defined as performance as a SRO for at least six months which 

includes: 

At least 6 weeks of operation above 20 percent power 

A startup from subcritical to 20 percent power 

A shutdown from above 20 percent power to cold (less than 212°F) and subcritical 

Startup preparations following a fueling or refueling outage 

The startup, shutdown, and startup preparations may be performed at an operating plant or on a 

full scope plant simulator. 

Table 1, "Comparison of Hot and Cold License Guidance," lists the current experience 

requirement and the associated cold license experience method. Table 2, "Illustration of Cold 

Licensing Plan by Candidate Type," lists the acceptable education and methods of obtaining 

equivalent experience for each type of licensed operator candidate. 

The guidance in this section is equivalent to the guidance of RG 1.8, Revision 3, "Qualification 

and Training of Personnel for Nuclear Power Plants," ANSI/ANS 3.1-1993, "Selection, 

Qualification, And Training of Personnel for Nuclear Power Plants," and GL 84-16, "Adequacy of 

On-Shift Operating Experience for Near Term Operating License Applicants" and is acceptable. 

3.1.2 Crew Experience Requirements during First Year of Operation

The cumulative NPP experience for each operating crew shall be greater than six years. The 

cumulative power plant experience for each operating crew shall be greater than 13 years. 

Operators obtain NPP experience by working at NPPs and military nuclear propulsion plants 

(performing activities equivalent to those performed by licensed operators), conducting licensed 

operator training, participating in new nuclear plant construction and testing, and completing 

academic degree requirements. Cumulative crew NPP experience is the sum of each 

individual's NPP experience after applying weighting factors and maximum credit limits in Table 

3, "Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies." When 

determining cumulative NPP experience, the entire six years experience shall not reside in one 

crew member. 

The crew's cumulative power plant experience is the sum of each individual's power plant 

experience. Operators obtain power plant experience by working at NPPs, conventional power 

plants and military propulsion plants (performing activities equivalent to those performed by nonlicensed operators). Cumulative power plant experience does not utilize weighting factors or 

maximum credit limits. 

In addition to the experience requirements described above, each operating crew shall be 

staffed with at least one SRO with hot plant experience. If a SRO with hot plant experience is 

not available, a shift advisor will be substituted. The shift advisor will have at least one year of 

on-shift licensed SRO experience at a similar type (PWR/BWR) operating plant and will have 

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C-12 

completed a training program on the design/plant for which they will be advising. While 

observing crew performance, the shift advisor will make recommendations to the shift manager 

and will not interfere with the licensed responsibilities of the operating crew. The shift advisor 

will have direct access to plant senior management. Shift advisor duties include, but are not 

limited to: 

Monitoring procedure adherence 

Observing the conduct of pre-job briefs, shift turnovers, plant evolutions, non-licensed 

operator rounds, plant tours, and post job debriefs 

Monitoring overall station risk. 

The guidance in this section is equivalent to the guidance of GL 84-16, "Adequacy of On-Shift 

Operating Experience for Near Term Operating License Applicants" and is acceptable. 

3.1.3 Conduct of OJT

Until construction of the plant is complete, acceptable methods for the conduct of OJT include 

discussion, simulation, and use of mockup equipment and virtual reality technology. 

Selection of the instructional setting is an integral part of the systems approach to the training 

process as defined in 10 CFR 55.4, "Definitions." The guidance in this section meets the 

requirements of 10 CFR 50.120, "Training and qualification of nuclear power plant personnel" 

and is acceptable. 

3.1.4 Use of Part-Task/Limited Scope Simulators

With the exception of the Operational Excellence course, which will utilize a full scope plant 

simulator, part-task or limited scope simulators may be used during licensed operator training. 

RG 1.149, Revision 3, "Nuclear Power Plant Simulation Facilities for Use in Operator Training 

and License Examinations," allows the use of a simulation facility for RO and senior operator 

training. 10 CFR 55.4 defines a simulation facility as one or more of the following components, 

alone or in combination: used for either the partial conduct of operating tests for operators, 

senior operators, and license applicants, or to establish OJT and experience prerequisites for 

operator license eligibility: 

(1) A plant-referenced simulator; 

(2) A Commission-approved simulator under 10 CFR 55.46(b); or 

(3) Another simulation device, including part-task and limited scope simulation devices, 

approved under 10 CFR 55.46(b). 

This guidance in this section is acceptable for those part-task or limited scope simulators that 

meet the requirements of 10 CFR 55.46(b). 
NEI 06-13A (Revision 2) 

March 2009 

C-13 

3.1.5 Licensed Operator Continuing Training

Licensed operator continuing training will begin within 90 days following the issuance of the first 

operator license. Continuing training content will determined using a systems approach to 

training methodology to maintain operator skills, knowledge, and abilities. 

10 CFR 50.54.1 (i-1) requires that within three months after either the issuance of an operating 

license or the date that the Commission makes the finding under § 52.103(g)of this chapter for a 

COL, as applicable, the licensee shall have in effect an operator requalification program. The 

operator requalification program must, as a minimum, meet the requirements of 10 CFR 

55.59(c). The guidance in this section meets the requirements of 10 CFR 50.54.1 (i-1) and is 

acceptable. 

3.1.6 Cold Licensing Process Applicability and Termination

The cold licensing process may be applied to each unit of a multi-unit site. 

Cold license guidance items 1 through 9 on Table 1 of NEI 06-13 will apply to any licensed 

operator training class started prior to initial fuel load. The cold licensing process will terminate 

after completion of the first refueling outage. 

Cold license guidance items 3 through 9 on Table 1 of NEI 06-13 will apply to any licensed 

operator training class started after initial fuel load and before completion of the first refueling 

outage. Items 1 and 2 of the Table 1 cold license guidance will not be allowed after the initial 

fuel load. 

As plant systems, components, and structures are completed and made operational, and as 

integrated plant operations start, systems approach to training methodology will be used to 

modify the cold license class training methods and settings. These modifications will optimize 

student learning using actual in-plant training and experience opportunities. 

The guidance in this section is equivalent to the guidance of GL 84-16, "Adequacy of On-Shift 

Operating Experience for Near Term Operating License Applicants" and is acceptable. 

3.1.7 Initial Licensed Operator Examination Schedule

Administration of the initial licensed operator examination will be approximately 18 months prior to 

initial fuel load. 

10 CFR 50.120 requires NPP operating license applicants, by 18 months prior to fuel load to 

establish, implement, and maintain training programs based on a systems approach to training. 

The guidance in this section ensures licensed operator examinations are developed from 

training programs that meet the requirements of 10 CFR 50.120 and is acceptable. 

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C-14 

4.0 CONCLUSION

Operator Licensing and Human Performance Branch (COLP) staff used the guidance and the 

acceptance criteria in the documents listed in Section 2.0 of this evaluation as the basis for 

evaluating the acceptability of NEI 06-13A, "Template for an Industry Training Program 

Description," Revision 1. The COLP staff has determined that NEI 06-13A, "Template for an 

Industry Training Program description," Revision 1 is consistent with the training and 

qualification requirements, guidance, and industry standards for licensed plant staff training and 

eligibility as outlined in Section 2.0 of this evaluation with verification of the implementation of the 

cold license training plan during the construction stage. 

On the basis of its review, the staff concludes that NEI 06-13 A, "Template for an Industry 

Training Program description," Revision 1 adequately provides guidance for establishing the cold 

licensed operator eligibility guidance. Accordingly, the COLP staff concludes that NEI 06- 

13 A, "Template for an Industry Training Program description," Revision 1 complies with the 

applicable NRC regulations, guidance, and industry standards and can be utilized by applicants 

for COLAs. 

5.0 REFERENCES

5.1 Roe, J. W., NEI, to the U.S. NRC, NEI 06-13A, "Template for an Industry Training 

Program Description, Revision 1," March 28, 2008. 

5.2 NUREG-0800, SRP, Section 13.2.1, "Reactor Operator Requalification Program; Reactor 

Operator Training." 

5.3 Miller, J. H., Jr., "Industry Evaluation Of Operating Shift Experience Requirements," 

February 24, 1984. 

5.4 Summary of May 24, 2007 Category 2 Public Meeting with NEI to Discuss New Reactor 

Operator Licensing Initiatives. 

5.5 Summary of September 13, 2007 Category 2 Public Meeting with NEI to Discuss Issues 

Related to Implementation of New Reactor Operator Licensing. 

5.6 Summary Of January 8, 2008 Category 2 Public Meeting with NEI to Discuss New 

Reactor Operator Licensing Initiatives. 

5.7 Summary Of March 5, 2008 Category 2 Public Meeting with NEI to Discuss New Reactor 

Operator Licensing Initiatives. 

5.8 GL 84-10, "Administration of Operating Tests Prior to Initial Criticality." 

5.9 GL 84-16, "Adequacy of On-Shift Operating Experience for Near Term Operating License 

Applicants." 

5.10 RG 1.8, Revision 3, "Qualification and Training of Personnel for Nuclear Power Plants." 

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NEI 06-13A (Revision 2) 

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C-15 

5.11 NUREG-1021, Revision 9, "Operator Licensing Examination Standards for Power 

Reactors." 

5.12 ANSI/ANS-3.1-1993, "Selection, Qualification, and Training of Personnel for Nuclear 

Power Plants." 

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NEI 06-13A (Revision 2) 

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DCWG - Combined (All) (Revised 09/29/2008) 

cc: 

Mr. Glenn H. Archinoff 

AECL Technologies 

481 North Frederick Avenue 

Suite 405 

Gaithersburg, MD 20877 

Mr, Ray Aycock 

Field Supervisor 

U.S. Fish and Wildlife Service 

Mississippi Ecological Services Office 

6578 Dogwood View Parkway 

Jackson, MS 39213 

Mr. Richard L. Baker 

Bechtel Power Corporation 

5275 Westview Drive 

Frederick, MD 21703-8306 

Scott Bond 

Callaway Plant 

P.O. Box 620 

Fulton, MO 65251 

Ms. Michele Boyd 

Legislative Director 

Energy Program 

Public Citizens Critical Mass Energy 

 and Environmental Program 

215 Pennsylvania Avenue, SE 

Washington, DC 20003 

Ms. Cindy Brizes 

U.S. Department of Energy 

P.O. Box A 

Aiken, SC 29802 

Mr. Barton Z. Cowan, Esquire 

Eckert Seamans Cherin & Mellott, LLC 

600 Grant Street, 44th Floor 

Pittsburgh, PA 15219 

Director 

Division of Compliance & Inspection 

Bureau of Radiation Control 

Texas Department of State Health Services 

1100 West 49th Street 

Austin, TX 78756-3189 

Mr. Ray Ganthner 

Senior Vice President 

AREVA, NP, Inc. 

3315 Old Forest Road 

P.O. Box 10935 

Lynchburg, VA 24506-0935 

Mr. Eugene S. Grecheck 

Vice President Nuclear Support Services 

Dominion Energy, Inc. 

5000 Dominion Blvd. 

Glen Allen, VA 23060 

Mr. Jay M. Gutierrez 

Morgan, Lewis & Bockius, LLP 

111 Pennsylvania Avenue, NW 

Washington, DC 20004 

Ms. Sophie Gutner 

P.O. Box 4646 

Glen Allen, VA 23058 

Mr. Brian Hastings 

Public Utility Commission 

William B. Travis Building 

P.O. Box 13326 

1701 Noth Congress Avenue 

Austin, TX 78701-3326 

Mr. Tim E. Herrmann 

Vice President, Nuclear Engineering 

AmerenUE 

P.O. Box 620 

Fulton, MO 6525 
NEI 06-13A (Revision 2) 

March 2009 

C-17 

DCWG - Combined (All) 

Mr. Ronald Kinney 

South Carolina DHEC 

2600 Bull Street 

Columbia, SC 29201 

Dr. Regis A. Matzie 

Senior Vice President and 

 Chief Technology Officer 

Westinghouse Electric Company 

20 International Drive 

Windsor, CT 06095 

Mr. Norris McDonald 

President 

AAEA 

9903 Caltor Lane 

Ft. Washington, MD 20744 

Dr. Masanori Onozuka 

Mitsubishi Nuclear Energy Systems, Inc. 

2300 Wilson Blvd. 

Suite 300 

Arlington, VA 22201-5426 

Dr. C. Keith Paulson 

Mitsubishi Nuclear Energy Systems, Inc. 

300 Oxford Drive, Suite 301 

Monroeville, PA 15146 

PBMR Pty. Limited 

Lake Buena Vista Building 

1267 Gordon Hood Avenue 

PO Box 9396 

Centurion 0046 

Republic of South Africa 

Charles Peterson 

Pillsbury, Winthrop, Shaw & Pittman, LLP 

2300 "N" Street, NW 

Washington, DC 20037 

Mr. Ernest Reed 

Living Education Center 

 for Ecology and the Arts 

P.O. Box 2612 

Charlottesville, VA 22902 

Mr. David W. Sutherland 

Chesapeake Bay Field Office 

U.S. Fish and Wildlife Service 

177 Admiral Cochrane Drive 

Annapolis, MD 21401 

Mr. Robert E. Sweeney 

IBEX ESI 

4641 Montgomery Avenue 

Suite 350 

Bethesda, MD 20814 

Mr. Ed Wallace 

General Manager - Projects 

PBMR Pty LTD 

P. O. Box 9396 

Centurion 0046 

Republic of South Africa 

Mr. Gary Wright, Director 

Division of Nuclear Facility Safety 

Illinois Emergency Management Agency 

1035 Outer Park Drive 

Springfield, IL 62704 

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NEI 06-13A (Revision 2) 

March 2009 

C-18 

DCWG - Combined (All) 

Email

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March 2009 

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