NEI 06-13A - Template for an Industry Training Program Description Revision 2pdf

8/3/2019 NEI 06-13A - Template for an Industry Training Program Description Revision 2pdf

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NEI 06-13A [Revision 2]

Template for an Industry

Training Program

Description

March 2009


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NEI 06-13A [Revision 2]

Nuclear Energy Institute

Template for an Industry

Training Program

Description

March 2009


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

of this guideline.


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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document reflects draft guidance provided by the NRC and industryNRC discussions ontraining-related issues.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, orconsultants 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, anyinformation apparatus, methods, or process disclosed in this report or that such may not

infringe privately owned rights.


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TABLE OF CONTENTS

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

1 TRAINING PROGRAM DESCRIPTION ......................................................................... 11.1

LICENSEDOPERATORTRAINING ........................................................................2

1.1.1 Licensed Operator Initial Training Program ..............................................21.1.2 Continuing Training for Licensed Personnel ...............................................2

1.2 TRAININGFORPOSITIONSLISTEDIN10CFR50.120 ......................................31.2.1 Non-Licensed Operator (NLO) Initial Training ..........................................31.2.2 Shift Manager Initial Training ......................................................................31.2.3 Shift Technical Advisor Initial Training Program ......................................41.2.4 Instrumentation and Control (I&C) Technician Initial Training ..............41.2.5 Electrical Maintenance Initial Training Program .......................................41.2.6 Mechanical Maintenance Initial Training Program ...................................51.2.7 Radiological Protection Technician Initial Training ...................................51.2.8 Chemistry Technician Initial Training .........................................................51.2.9 Engineering Personnel Initial Training ........................................................61.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120 .....................6

1.3 GENERALEMPLOYEETRAINING(GET)PROGRAM ......................................71.3.1 Plant Access Training .....................................................................................71.3.2 Radiation Worker Training Program ..........................................................71.3.3 General Employee Requalification Training ...............................................7

1.4 SELECTEDOTHERTRAININGPROGRAMS .......................................................81.4.1 Fire Protection Training ................................................................................81.4.2 Emergency Plan Training Program ..............................................................81.4.3 Physical Security Training Program ............................................................81.4.4 Station Management Training Program ......................................................8

1.5 TRAININGEFFECTIVENESSEVALUATIONPROGRAM .................................91.5.1 Supervisory Review for Training Effectiveness ...........................................91.5.2 Trainee Review of Training Effectiveness ....................................................91.5.3 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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NEI 06-13A (Revision 2)

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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 aredeveloped 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 foreffectiveness. 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 employeeexperience, 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, simulatortraining 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 totraining (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 includingpreoperational 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 initialtraining are presented in Table 13.4-1.

1.1 LICENSEDOPERATORTRAINING

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

including initial and requalification training, provide the means to train individuals in theknowledge, 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 forRO 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 usedfor 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 theNRC 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 demonstrateunderstanding 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 participatein continuing training.


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Program content, course schedules and examination schedules comply with 10 CFR55.59 (Reference 13.2-13). Continuing training for licensed personnel is conducted in

accordance with administrative procedures.

1.2 TRAININGFORPOSITIONSLISTEDIN10CFR50.1201

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 laterthan 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 andcomponents 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 abroader 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 themwith 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 fromnuclear 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 classroomunder 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 thefollowing 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


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

radiation protection equipment and use of procedures under the guidance of experiencedtechnicians. 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 reiteratingselected 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 withactual 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 totraining 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 GENERALEMPLOYEETRAINING(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 radiologicallycontrolled 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 requalificationtraining. 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 qualityassurance requirements. As applicable, training is conducted on industry operating

experiences, Licensee Event Reports, and personnel errors.

1.4 SELECTEDOTHERTRAININGPROGRAMS

This subsection addresses training for positions not specified by 10 CFR 55 (Reference13.2-7) 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. Personnelassigned 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 PhysicalSecurity Plan, which is a separate document.

1.4.4 Station Management Training Program

Station supervisors receive Fitness for Duty (FFD) supervisory training in accordancewith 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 RegulatoryGuide 1.8 (Reference 13.2-16).

The qualification requirements for managers and middle managers include training orexperience 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 TRAININGEFFECTIVENESSEVALUATIONPROGRAM

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 contentof 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 assuminginstructional duties. The educational specialist conducts periodic seminars in instructional

techniques, discussing areas where group performance could be improved andrecommends 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 Duty13.2-3 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 forUse 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 RadiationExposure, 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 FIRSTREFUELING 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 operatorselection, training, and qualification cannot be met.

Cold licensing of operators provides the method for operations personnel to acquire theknowledge and experience required for licensed operator duties during the unique conditions ofnew 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 orequivalent as required by R.G. 1.8 Revision 3.

Candidates for a Senior Reactor Operator license shall have at least one of the followingqualifications:

Previously held a Senior Reactor Operator license for an operating nuclearpower plant

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

Bachelors 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 theNRC.

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 forthe new nuclear plants adheres to current industry guidance for operating plants withexemptions 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 toentering a licensed operator training program. Experience and plant evolutionrequirements that have not been met at the time the licensed operator examination isadministered shall be met prior to issuing the individuals NRC operator license. In sucha case, the Licensee will notify the NRC when the candidate meets the experience andplant evolution requirements.

The methods listed below provide the licensed operator candidate with meaningfulexperience on the reactor for which the license is sought. Methods for gainingmeaningful experience include completing systematically designed training courses, andparticipating in practical work assignments such as preoperational testing, proceduredevelopment and validation, human factors engineering activities, task analysisverification, or conducting licensed operator classroom or simulator training.Additionally, for these activities to be considered meaningful, they must be associatedwith 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 onselected non-licensed operator tasks. The selected non-licensed operator tasksare those tasks that are important to plant operation with regard to nuclearsafety, defense-in-depth, or that are risk significant.

Participate in practical work assignments for a minimum of six months thatincludes 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 trainingimplementation

Senior reactor operator cold license candidates will complete a site-specific reactoroperator and senior reactor operator training course.

Senior reactor operator cold license candidates without hot plant experience willcomplete a plant operational excellence course that is conducted in a plant simulator orthey will observe control room activities at an operating nuclear plant for at least sixweeks. The course and the observation activity are designed to familiarize thecandidate with the operational interfaces encountered by decision makers in a nuclearplant control room.

Hot plant experience is defined as performance of senior reactor operator duties for atleast 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) andsubcritical

Startup preparations following a fueling or refueling outage

The startup, shutdown, and startup preparations may have been performed at anoperating plant or a plant simulator.

Table 1, Comparison of Hot and Cold License Guidance , shows the current experiencerequirement and the associated cold license experience method. Table 2, Illustration ofCold Licensing Plan by Candidate Type, shows education and experience methods foreach licensed operator candidate type.

1.2 Crew Experience Requirements during First Year of Operation

Each operating crews cumulative nuclear power plant experience shall be > 6 years;and the crews cumulative power plant experience shall be > 13 years.

The crews cumulative nuclear power plant experience is gained by working at nuclearpower plants and military nuclear propulsion plants, conducting licensed operatortraining, participating in new nuclear plant construction and testing, and completingacademic degree requirements. The cumulative crew nuclear power plant experience isthe sum of each individuals experience after applying weighting factors and maximumcredit limits in Table 3, Cumulative Nuclear Power Plant Operating Crew ExperienceEquivalencies.

When determining cumulative nuclear power plant experience, all 6 years shall not beattributed from one crew member.

The crews cumulative power plant experience is the sum of each individuals powerplant experience. Power plant experience, for example, is experience gained by workingat nuclear power plants, conventional power plants, and military propulsion plants.Cumulative power plant experience does not involve weighting factors or maximumcredit limits.


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In addition to the experience requirement mentioned above, each operating crew shallbe staffed with a senior reactor operator with hot plant experience (previously defined in1.1, Licensed Operator Experience Requirements Prior to Commercial Operation). If asenior reactor operator with hot plant experience is not available, then a shift advisormay be substituted. The shift advisor will have at least one year of on-shift licensedsenior reactor operator experience at a similar type (PWR/BWR) operating plant, and willhave completed a training program on the design for which they are advising. Whileobserving crew performance, the shift advisor will make recommendations to the shiftmanager only, and will not interfere with the licensed responsibilities of the operatingcrew. The shift advisor will have direct access to plant senior management to resolveissues. Shift advisor duties include, but are not limited to the following:

Monitor procedure adherence

Observe the conduct of prejob briefs, shift turnover, plant evolutions, non-licensed operator rounds, plant tours, and post job debriefs

Monitor overall station risk

Weighting factors and maximum credit limits for determining cumulative nuclear powerplant operating crew experience are shown in Table 3, Cumulative Nuclear Power PlantOperating 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-jobtraining include discussion, simulation, and use of mockup equipment and virtual realitytechnology

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 thefirst operator license. Continuing training content is systematically determined tomaintain 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 amulti-unit site.

Cold license guidance items 1 through 9 on Table 1 will apply to any licensed operatortraining class started prior to initial fuel load.

Cold license guidance items 3 through 9 on Table 1 will apply to any licensed operatortraining class started after initial fuel load and before completion of the first refuelingoutage. Items 1 and 2 cold license guidance are no longer allowable after initial fuelload.

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

As plant systems, components, and structures are completed, and as integrated plantoperations begin, the systematic approach to training process will be used to adjust coldlicense class training methods and settings used to implement the guidance in Table 1items 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 priorto fuel load.

2 REFERENCES

2.1 Nuclear Energy Institute (NEI), Technical Report on a Template for an IndustryTraining Program Description, NEI 06-13A


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Table 1Comparison of Hot and Cold License Guidance

Current Hot License Guidance Applicable Position References C

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 mont

Com

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.


2.10.


Six mont

Com

Comple

operator

no

A-7


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3. Pre-requisite experience

requirements must be met to

enter training program.All


Section D.

Applica

shall b

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


2.10


Six mont

Cumulat

5. Reactor operator license

actively involved in the

performance of licensed

duties for at least one year.

Senior reactor operator

(Non-degreed)


2.8


Com

Comple

operator

no

Comple

rea

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6. At least three years of

responsible nuclear power

plant experience.


(Degreed)


1.3

2.8

Com

Comple

operator

no

Complete

react

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

212F) and subcritical, and

startup preparations

following a fueling or

refueling outage.

Shift Supervisor

(Shift Manager)

ANSI 3.1-1993:

4.4.1

Cumula

Complet

Cours

A-9


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8. At least six weeks of

operation above 20% power.

Senior reactor operator ANSI 3.1-1993:

4.4.2

Cumula

Complet

Cours

9. Three years power plant

experience and three years

nuclear power plant

experience


ANSI 3.1-1993

4.4.1

4.4.2


2.8


Six mont

Cumulati


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Table 2

Illustration of Cold Licensing Plan by Candidate Type

License Candidate Education

Site

Layout

Course

NLO Task

TrainingRO Training

SRO

Training

Reactor operator High school diploma Yes Yes Yes N/A


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


previous license or

military equivalent

High school diploma Yes Yes Yes Yes


certified instructorHigh school diploma Yes Yes Yes Yes

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

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

(2): No, if candidate has hot license experience

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Table 3Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies

Type of Experience Weighting Factor Max Credit

1. Commercial Nuclear Plant RO/SRO on same type

plant (PWR/BWR)1.00 No Limit

2. Commercial Nuclear Plant RO/SRO from different type

plant (PWR/BWR)0.75 No Limit

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

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

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5. Reference Plant Simulator 5.00 12 months

6. Limited Scope Simulator 3.00 9 months

7. Actual nuclear plant experience during construction 0.25 12 months

8. Actual nuclear plant experience during pre-operational

testing0.75 12 months

9. Actual nuclear plant experience during fuel load and

startup testing1.00 12 months

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10.License Classroom training 0.25 9 months

11.Participation in operator duties at another commercial

nuclear facility. This includes nonlicensed operator

duties

0.75 12 months

12.Other Nuclear Plant experience 0.25 12 months

13.Licensed operator instructor 0.50 12 months

14.Bachelors Degree in an Engineering, Science or

Technical fieldn/a 24 months

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rience Weighting Factor Max Credit Type of Expe

15.Associates Degree (technical) n/a 6 months

(1): Weighting factors and max credit values based on those in Industry Evaluation of Operating Shift E

J.H. Miller Jr. 2/24/1984, and endorsed by Generic Letter number 84-16, Adequacy of On-Shift Operatin

Operating License Applicants, except for shaded rows which are added experience types based on new

analysis.


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APPENDIX B

FINAL SAFETY EVALUATION REPORT

NEI 06-13, REVISION 0


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UNITED STATESNULCEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

September 5, 2007

Adrian P. Heymer, Senior DirectorNew Plant Deployment NuclearGeneration Division Nuclear EnergyInstitute 1776 I Street, NW, Suite 400Washington, 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. NuclearRegulatory Commission (NRC) staff review its proposed Template for an Industry TrainingProgram, Revision 0.

Enclosed is the staffs safety evaluation (SE) which defines the basis for acceptance ofNEI 06-13. On the basis of its review, the NRC staff finds that for combined licenseapplications, 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 ourreview of the acceptable material described in the NEI 06-13. When the NEI 06-13 appears asa reference in regulatory applications, our review will ensure that the material presented appliesto the specific application involved. Licensing requests that deviate from NEI 06-13 will besubject 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 theaccepted version of NEI 06-13 within three months of receipt of this letter. The acceptedversion should incorporate this letter and the enclosed SE after the title page. Typically, theaccepted version would also contain historical review information, including NRC requests for

additional information (RAIs) and your responses; however, that is not necessary for NEI 06-13because RAIs were not issued. The accepted versions shall include a "-A" (designatingaccepted) following the report identification symbol.

If future changes to the NRC's regulatory requirements affect the acceptability of NEI 06-13, NEIwill be expected to revise NEI 06-13 appropriately, or justify its continued applicability forsubsequent referencing.


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A. Heymer - 2 -

If you have any questions, please contact Michael Canova at (301) 415-0737, [email protected].

Sincerely,

Stephanie M. Coffin, ChiefAP1000 Projects BranchDivision of New Reactor LicensingOffice of New Reactors

Project No. 689

EnclosureSafety Evaluation

cc w/encl: See next page


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SAFETY EVALUATION REGARDING THENUCLEAR 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 anIndustry Training Program," Revision 0 (NEI 06-13) for Nuclear Regulatory Commission (NRC)review and approval. The topical report provides a complete generic training programdescription for use with combined license applications. NEI 06-13 was developed by the NEINew Plant Training Task Force, which includes representatives from the four design-centeredworking groups, to assist in expediting NRC review of the combined license and issuance of thecombined license. NEI 06-13 is not applicable to the review and issuance of constructionpermits 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


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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, attributesand level of detail. In evaluating the adequacy of the format, attributes and level of detail, thestaff followed the guidance of the Standard Review Plan (NUREG-0800), Section 13.2.1 (SRP13.2.1), "Reactor Operator Training" and Section 13.2.2 (SRP 13.2.2), "Training for NonlicensedPlant Staff." SRP 13.2.1 outlines the training and requalification program guidance for licensedreactor operators and senior reactor operators. SRP 13.2.2 outlines the training and retrainingprogram guidance for nonlicensed plant staff. SRP 13.2.1 and 13.2.2 apply to constructionpermit, operating license, and combined license applicants.

NEI 06-13 is organized into five areas, licensed operator training, training for positions listed in 10CFR 50.120, general employee training, selected other training programs, and the trainingeffectiveness evaluation program. Other training programs selected for description include fireprotection, 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 theknowledge, skills, and abilities needed to perform licensed operator duties. The reactor operatortraining program description includes a description of the 10 CFR 55.59 required licensedoperator 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 andTraining 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, asimulator will be used for training licensed personnel and for the administration of operatingtests.

NEI 06-13 further states that prior to initial fuel load, the number of licensed ROs and SROs willbe sufficient to meet regulatory requirements, with allowances for licensing examinationcontingencies, 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 forthe NRC license exam. The program will be implemented in accordance with licenseedeveloped administrative procedures.

2. Reactor Operator candidates will receive training in the topics listed in 10 CFR 55.41. ROcandidates will receive plant simulator training to demonstrate understanding and theability to perform the actions listed in 10 CFR 55.45.

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3. In addition to the RO topics listed in 10 CFR 55.41, SRO candidates will receive trainingin the topics listed in 10 CFR 55.43. SRO candidates will receive plant simulator trainingto 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 formalinstruction, evaluation, and on-the-job training. Training material will be developed usingthe SAT process in accordance with licensee developed administrative procedures. Alllicensed operators will participate in continuing training.

5. Licensed Operator Requalification Program content, course schedules and examinationschedules will comply with 10 CFR 55.59 and will include industry operating experiencetraining. Licensed Operator Requalification training for licensed personnel will beconducted in accordance with licensee developed administrative procedures.

Based on the staff's review of the "Licensed Operator Training" section of NEI 06-13 outlinedabove, the staff concludes that NEI 06-13 clearly and sufficiently describes, in terms of scope andlevel of detail, the RO and SRO training programs to enable a reasonable assurance finding ofacceptability for issuance of a combined license with verification of the RO and SRO trainingprograms 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 trainingprograms 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 thefollowing 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 usingSAT methodology and will follow licensee developed administrative procedures. The 10 CFR50.120 training programs will be implemented and maintained no later than eighteenmonths prior to fuel load.

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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 acombination of formal instruction and on-the-job training. In-plant training will includesystem walk downs, which will emphasize the use of procedures, the proper operation ofequipment, 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 anSRO. The Shift Supervisors will receive additional training that addresses higher-levelmanagement skills and behaviors, and provides a broader perspective of plantoperations. The Shift Supervisor training program will be a combination of formalinstruction and on-the-job training. Initial shift supervisor training will include topics suchas:

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 withthe skills and knowledge to monitor equipment and system operation to assess plantconditions during abnormal, off-normal, and emergency events. The STA trainingprogram will be a combination of formal instruction and on-the-job training. STA initialtraining will include instruction in the following areas:

Responses to accidents and analyses of plant transients

Application of engineering principles to protection of the core

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Mitigation of plant accidents

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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 andon-the-job training. Training for I&C technicians will include instruction in the followingareas:

Fundamentals of instrumentation and control

Pneumatic systems and equipment

Electronics

Fundamental systems training

Instrument and Control and other job-related procedures

Surveillance requirements



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

3.2.5 Electrical Maintenance Personnel (electricians)

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

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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-jobtraining. 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 inthe classroom.

3.2.7 Radiological Protection (RP) Technician

Initial training for RP technicians will be a combination of formal instruction and on-the-jobtraining. Training for RP technicians will include instruction in the followingareas:

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 protectionequipment 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 on-the-job training. Training for chemistry technicians will include instruction in the followingareas:

Chemistry procedures

Laboratory practices

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Conduct of analytical tests

Operation of laboratory equipment

Fundamental systems training

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



Power plant chemistry

On-the-job training will permit chemistry technicians opportunities to operate analyticalequipment 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 ofnuclear technology in an operating plant environment. Initial training for engineeringsupport 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 theskills 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 maintainqualifications and enhance proficiency. Continuing training reinforces initial training byreiterating selected portions of the material. Continuing training also addresses new andmodified procedures and plant design changes.

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Operating Experience (OE) is included in continuing training for all programs. OE trainingprovides personnel with actual examples of good practices and lessons learned. OE topics willbe selected from Licensee Event Reports, corrective action databases, industry groups, andother sources.

Continuing training programs will be developed in accordance with SAT principles and will beconducted in accordance with licensee developed administrative procedures.

Shift Technical Advisors (STAs) will maintain their qualifications by participating in licensedoperator requalification training.

Based on the staffs review of the "Training for Positions Listed in 10 CFR 50.120" section of NEI06-13 outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes,interms of scope and level of detail, the training programs for positions listed in 10 CFR 50.120 toenable a reasonable assurance finding of acceptability for issuance of a combined license withverification 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 threecomponents, Plant Access Training, Radiation Worker Training, and General EmployeeRequalification Training.

3.3.1 Plant Access Training

Prior to being granted unescorted access to the plant, members of the station staff, contractorworkers, and unescorted visitors will complete Plant Access Training. Plant Access Training willinclude 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 theplant will receive instruction in the applicable aspects of radiation protection. Radiation WorkerTraining will include the following topics:

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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 tomeet access requirements. Emphasis will be placed on changes to the plant, plant proceduresand procedure changes, government regulations, and quality assurance requirements. Asapplicable, training will be conducted on industry operating experiences, Licensee EventReports, and personnel errors.

Based on the staff's review of the "General Employee Training" (GET) section of NEI 06-13outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes, in terms ofscope and level of detail, the training programs for general employee training to enable areasonable 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 notspecified by either 10 CFR 55, "Operators' Licenses" or 10 CFR 50.120, "Training andQualification 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 becompleted prior to receipt of fuel at the site. Personnel assigned as fire brigade members willreceive formal training prior to assuming brigade duties. Fire brigade members will also receiveregularly scheduled retraining. Fire brigade training will comply with National Fire ProtectionAssociation Standard 600, "Standard on Industrial Fire Brigades."

Training appropriate to the assigned work will be provided for the fire protection staff, fire watchpersonnel, and the general employee. Final Safety Analysis Report (FSAR) Section 9.5.1, "Fire

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Protection Program" will include additional information regarding the fire protection trainingprograms.

3.4.2 Emergency Plan Training Program

NEI 06-13 states that Emergency Plan training will meet the requirements of 10 CFR 50Appendix E, Section IV. F, "Training" and 10 CFR 50.47(b)(15). Additional information about theEmergency Plan training program will be found in the Emergency Plan, which is a separatedocument.

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 with10 CFR 26.22. The qualification requirements for managers and middle managers includetraining or experience in supervision or management. Training for supervisors develops theirskills 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 06-13outlined above (fire protection, emergency plan, physical security, and station managementtraining programs), the staff concludes that NEI 06-13 clearly and sufficiently describes, in termsof scope and level of detail, the training programs for fire protection, emergency plan, physicalsecurity, and station management training to enable a reasonable assurance finding ofacceptability for issuance of a combined license with verification of the programs during theconstruction stage.

3.5 Training Effectiveness Evaluation Program

NEI 06-13 states that the program to evaluate the effectiveness of training programs will be basedon three independent inputs: the supervisor of the trainee, the trainee, and an educationalcontent 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 asrelated to the duties and job responsibilities of the trainees. Reviews may be performed by the

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supervisor of the trainee (former student) meeting with appropriate Training Departmentpersonnel, 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 requireadditional 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 providecomments 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 trainingprogram.

3.5.3 Review for Effectiveness of Instructional Techniques and Materials

The effectiveness of instructional techniques and materials review assesses the clarity andapplicability of training material and instructional aids. Management observations of instructors inthe teaching environment will be conducted by an educational specialist qualified to monitor andevaluate classroom performance. Full time instructors will receive basic indoctrination ininstructional techniques as soon as practicable after assuming instructional duties. Theeducational specialist will conduct periodic seminars in instructional techniques, discussing areaswhere group performance could be improved and recommends innovative techniques observedat this or other power stations.

Based on the staffs review of the "Training Effectiveness Evaluation Program" section of NEI06-13 outlined above, the staff concludes that NEI 06-13 clearly and sufficiently describes, interms 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 verificationof the programs during the construction stage.

4.0 CONCLUSION

Operator Licensing and Human Performance Branch (COLP) staff used the acceptance criteria ofSRP 13.2.1 and 13.2.2 as the basis for evaluating the acceptability of NEI 06-13, "Template foran Industry Training Program Description," Revision 0. The COLP staff has determined that NEI06-13, "Template for an Industry Training Program," Revision 0 is consistent with the training andqualification requirements, guidance, and industry standards for licensed and nonlicensed plantstaff as outlined in Section 2.0 of this evaluation with verification of the programs during theconstruction stage.

The training programs for licensed and nonlicensed plant staff described in NEI 06-13 willincorporate instructional requirements to qualify personnel to operate and maintain the facility, ina safe manner, in all modes of operation. The training programs will be developed andmaintained in compliance with the facility license and applicable regulations. The trainingprograms will be periodically evaluated and revised to reflect industry experience; to incorporatechanges to the facility, procedures, regulations, and quality assurance requirements; and bymanagement to determine overall program effectiveness. The training programs will be further

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described in site and/or corporate procedures. Sufficient records will be maintained and keptavailable 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 testingand low-power operation in accordance with the provisions of TMI Action Item I.G. Sufficientplant 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 bythe applicant and will meet the regulatory guidance of Regulatory Guide 1.8 and 10 CFR Part55. Licensed operators and senior operators will receive training in security procedures,radiological emergency plans, administrative procedures, and radiation protection. Simulationfacilities used for the licensed operator training program will meet the guidance of RegulatoryGuide 1.149. The licensed operator requalification training program conforms to therequirements 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 fuelload to ensure that the minimum shift staffing requirements of 10 CFR 50.54 will be met. Thelicensed 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 providedinformation related to its training program for nonlicensed personnel. The training and retrainingof nonlicensed plant staff will meet the guidance of Regulatory Guide 1.8. The applicant hascommitted to establish, implement, and maintain training programs that will utilize a systemsapproach to training as required by 10 CFR 50.120 and as defined in 10 CFR 55.4. All initialtraining of the nonlicensed plant staff is scheduled to be completed prior to fuel loading. Trainingprograms 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 atraining program that will inform and instruct personnel regarding radioactive materials andradiation, health protection problems associated with exposure to radiation, the means andresponsibilities for the protection of workers from radiation, and the availability upon request ofradiation exposure reports. The training program includes initial training and periodic retrainingfor categories of employees and nonemployees whose assistance may be needed in the event ofa 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 toensure that personnel are adequately informed regarding the fitness-for-duty policy. Supervisorsand 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 torecognize behavioral changes, drugs, and/or indications of the use of drugs. The fitness-for-dutytraining program will be verified during the construction stage.

NEI 06-13 states that training will be provided based on individual employee experience, theintended position, and previous training and education of the individual. Training Departmentpersonnel may be supplemented by other personnel such as subject matter experts, contract

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staff, and vendor representatives. Formal instruction will be presented through a combination ofclassroom lectures, e-learning, assigned reading, simulator training and evaluations, and otherdelivery techniques.

On the basis of its review, the staff concludes that NEI 06-13, "Template for an Industry TrainingProgram," Revision 0 adequately provides guidance for establishing the licensed operator andnonlicensed 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 NRCregulations, guidance, and industry standards and can be utilized by applicants for combinedlicense applications.

5. REFERENCES

5.1 Heymer, A. P., Nuclear Energy Institute, to the U.S. NRC, NEI 06-13, "Template for anIndustry 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 New Reactors Mailing List List #35

cc:

Ms. Michele BoydLegislative DirectorEnergy ProgramPublic Citizens Critical Mass Energy

and Environmental Program215 Pennsylvania Avenue, SE Washington, DC20003

Mr. Marvin Fertel SeniorVice Presidentand Chief Nuclear OfficerNuclear Energy Institute1776 I Street, NWSuite 400Washington, DC 20006-3708

Ms. Leslie Compton KassSenior Project ManagerNuclear Energy Institute1776 I Street, N.W.Suite 400Washington, DC 20006-3708

Mr. Brian Smith

Nuclear Energy Institute1776 I Street, NW,Suite 400Washington, DC 20006

Mr. Ed WallaceGeneral Manager - ProjectsPBMR Pty LTDP. O. Box 9396Centurion 0046Republic of South Africa

Edward G. WallaceSr. General ManagerU.S. ProgramsPBMR Pty. Ltd.PO Box 16789

Chattanooga, TN 37416

Mr. Gary Wright, DirectorDivision of Nuclear Facility SafetyIllinois Emergency Management Agency1035 Outer Park DriveSpringfield, IL 62704


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- 2 -NEI New Reactors Mailing List

Email

[email protected] (Adrian Heymer)[email protected] (Anne W. Cottingham)[email protected] (Steve A. Bennett)

[email protected] (Charles Brinkman)[email protected] (Chris Maslak)[email protected] (C. Waltman)[email protected] (David Lewis)[email protected] (David Lochbaum)[email protected] (Frank Quinn)[email protected] (James Gresham)

[email protected] (Jay M. Gutierrez) [email protected] (James Riccio)[email protected] (James J. Nesrsta)John.o'[email protected] (John O'Neil)[email protected] (Joseph Savage)

[email protected] (Joseph Hegner)[email protected] (Kathryn M. Sutton)[email protected] (Kenneth O. Waugh)[email protected] (Sarah Lynch - Meeting Notices Only)[email protected] (Maria Webb)[email protected] (Mark Beaumont)[email protected] (Matias Travieso-Diaz)[email protected] (Scott Peterson)[email protected] (Mike Moran)[email protected] (Michael Mariotte)[email protected] (Patricia L. Campbell)[email protected] (Paul Gaukler)[email protected] (Paul Gunter)[email protected] (Paul Hinnenkamp)[email protected] (Peter Hastings)[email protected] (Russell Bell)[email protected] (R.K. Temple)[email protected] (Roberta Swain)[email protected] (Ronald Hagen)[email protected] (Sandra Sloan)[email protected] (Stephen P. Frantz)[email protected] (Bill Victor)[email protected] (Rosemarie E. Waraks)

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


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APPENDIX C

FINAL SAFETY EVALUATION REPORT

NEI 06-13A, REVISION 1


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UNITED STATES

NULCEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555-0001

December 5, 2008

Mr. Russell J. Bell, DirectorNew Plant Licensing NuclearGeneration DivisionNuclear Energy Institute1776 I Street, NW, Suite 400Washington, 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 NuclearEnergy Institute (NEI) 06-13, "Template for an Industry Training Program Description," Revision0 as an acceptable template for describing reactor operator (RO) and non-licensed plant stafftraining 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 AppendixA, "Cold License Training Plan." The change to NEI 06-13A, Revision 1 is exclusive to theaddition 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 eligibilityguidance. 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 inexpediting 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 anacceptable template for describing the licensed operator trainin

Documents

NEI 06-13A - Template for an Industry Training Program Description Revision 2pdf