NUREG-0800

(Formerly NUREG-75/087)

4F NA G'P A U.S. NUCLEAR REGULATORY COMMISSION

STANDARD REVIEW PLAN

OFFICE OF NUCLEAR REACTOR REGULATION

13.2.1 REACTOR OPERATOR TRAINING

REVIEW RESPONSIBILITIES

Primary review branch - The branch responsible for human performance

Secondary - None

I. AREAS OF REVIEW

The applicant's licensed operator training program, as described in the safety analysis report

(SAR), is reviewed. This section of the SAR should contain the description and scheduling of

the training program for reactor operators and senior reactor operators. The licensed operator

training program also includes the requalification program as required in 10 CFR 50.54(i)(i-1)

and 55.59.

A. Construction Permit (CP) and Combined License (COL)

The training program descriptions should contain the following elements:

1. A description of the proposed training program, including the subject matter of each

initial licensed operator training course, the duration of the course (approximate

number of weeks personnel are in full-time attendance), the organization teaching

the course or supervising instruction, and the titles of the positions for which the

course is given. The program descriptions should include a chart showing the

proposed schedule for licensing personnel prior to criticality. The schedule should

be relative to expected fuel loading and should display the preoperational test

period. The submittal should contain a commitment to conduct formal licensed

operator, on-the-job training, and simulator training before initial fuel load.

Rev. 2 - November 2005

USNRC STANDARD REVIEW PLAN

Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the

review of applcations to construct and operate nuclear power plants. These documents are made available to the public as part of the CommIssion's policy to inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance wih them Is not required. The standard review plan sections are keyed to the Standard Format and Content

of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan.

Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect

new Information and experience.

Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D.C. 20555.
2. The subjects covered in the training programs should include, as a minimum, the

subjects in 10 CFR 55.31, 55.41, 55.43, 55.45, and Regulatory Guide 1.8 for

reactor operators and senior reactor operators as appropriate. The training

program should also include provisions for upgrading reactor operator licenses and

for licensing senior reactor operators who have not been licensed as reactor

operators per Regulatory Guide 1.8. The training should be based on use of the

systems approach to training (SAT) as defined in 10 CFR 55.4

3. The licensed operator requalification program should include the content described

in 10 CFR 55.59 or should be based on the use of a systems approach to training

as defined in 10 CFR 55.4.

4. Applicants should describe their program for providing simulator capability for their

plants as described in 10 CFR 55.31, 55.45, 55.46, 50.34(f)(2)(i), and Regulatory

Guide 1.149. In addition, the applicant should describe how it will ensure that its

proposed simulator will correctly model its control room. Applicants should submit,

prior to issuance of construction permits or other submittals, a general discussion

of how the requirements will be met. Sufficient details should be presented to

provide reasonable assurance that the requirements will be implemented prior to

the issuance of a license.

5. The means for evaluating training program effectiveness for all licensed operators,

in accordance with a systems approach to training.

6. For COL, applicants provide implementation milestones for the reactor operator

training program.

B. Operating License (OL) or COL holder - verification through the Construction Inspection

Program

The training program descriptions should include the following elements:

1. The licensed operator training program descriptions should delineate clearly the

extent to which the training program was accomplished at the approximate time of

submittal of the SAR. Contingency plans for additional training for individuals to be

licensed prior to criticality should be described in the event fuel loading is

subsequently delayed until after the date indicated in the SAR.

2. Reactor operations training using nuclear power plant simulation facilities shall

comply with Regulatory Guide 1.149. The applicant should provide the details of

the program for simulator training, including length of time (weeks) and a

description of the simulation facility as required by 10 CFR 55.45(b) and 55.46.

The applicant should also provide details of the program to meet experience

requirements for applicants for operator and senior operator licenses as required

by 10 CFR 55.31 and 55.46.

3. The SAR should describe the applicant's plans for requalification training for

licensed operators and senior operators.

Rev.2 - November 2005 13.2.1-2
a. The subject matter of each course, including a syllabus or equivalent course

description, the duration of the course (approximate number of weeks

personnel are in full-time attendance), the organization teaching the course

or supervising instruction, and the titles of the positions for which the course

is given. The program should distinguish between classroom, on-the-job,

and simulator training, before and after the initial fuel loading. It should

include provisions for training on modifications to plant systems or functions.

The organization teaching the course or supervising the instruction and the

qualifications of the instructors in the training program should be provided.

The subjects covered should include, as a minimum, those contained in 10

CFR 55.41, 55.43, 55.45, and Regulatory Guide 1.8 for reactor operators

and senior reactor operators as appropriate. The training program should

also include provisions for upgrading reactor operator licenses and for

licensing senior reactor operators who have not been licensed as reactor

operators per Regulatory Guide 1.8. The training should be based on the

use of SAT as defined in 10 CFR 55.4.

b. The licensed operator requalification program should include the content

described in 10 CFR 55.59 or be based on the use of a systems approach to

training as defined in 10 CFR 55.4.

c. The means for evaluating training program effectiveness for all licensed

operators, in accordance with SAT as defined in 10 CFR 55.4.

C. Design Certification

The development of training programs will be designated as the responsibility of a COL

applicant.

D. Review Interfaces - None

11. ACCEPTANCE CRITERIA

A. General Guidance

The SAR should demonstrate that the training provided, or to be provided, for reactor

operators and senior reactor operators will be adequate to provide assurance that all

reactor operator qualification requirement items will be met at the time needed, i.e., prior

to operator license examinations, prior to fuel loading, or prior to appointment or

reappointment to the position. :

Criteria for acceptability, as they relate to licensed operator training and retraining

programs, are:

1. The training and qualification requirements and guidance set forth in the following

regulations and regulatory -guides should be met or acceptable alternatives should

be presented:

13.2.1-3 Rev. 2 - November 2005
a. 10 CFR 50.54, items i through m

b. 10 CFR 55.4, 55.31, 55.41, 55.43, 55.45, 55.46 and 55.59

c. 10 CFR 50.34(f)(2)(i)

d. Regulatory Guide 1.8, "Qualification and Training of Personnel for Nuclear

Power Plants"

e. Regulatory Guide 1.149, "Nuclear Power Plant Simulation Facilities for Use in

Operator Training and License Examinations'

f. NUREG-071 1, "Human Factors Engineering Program Review Model"

g. NUREG-1021, "Operator Licensing Examination Standards for Power

Reactors"

2. Training programs shall be developed, established, implemented, and maintained

using a systems approach to training as defined by 10 CFR 55.4. Training

program development will be evaluated by the staff using the guidance in

NUREG-0711 and training program content, and effectiveness will be evaluated

using NUREG-1220.

3. Formal segments of the initial licensed operator training program should be

substantially completed when the preoperational test program begins.

4. The number of persons trained in preparation for licensed operator and senior

operator licensing examinations prior to criticality should be sufficient to ensure that

applicable regulatory requirements for shift staffing can be met from the time of

initial fuel loading, with allowances for examination contingencies and the need to

avoid planned overtime.

5. The licensed operator requalification training program should adequately

implement the requirements of 10 CFR 55.59.

B. Technical Rationale

The technical rationale for application of these acceptance criteria to reviewing licensed

operator training is discussed in the following paragraphs:

I1. Compliance with the relevant requirements of 10 CFR 50.54 items i through m

requires the licensee to have licensed operators or senior operators present at the

controls and responsible for manipulation of the controls or directing the licensed

activities of other licensed operators, as appropriate.

The reactor operator and senior reactor operator training programs, including initial

and requalification training, established by the applicant provide the means to train

individuals in the knowledge, skills, and abilities needed to perform licensed

operator duties.

Rev. 2 - November 2005 13.2.1 -4
Meeting these requirements provides assurance that only trained and qualified

individuals will be licensed and assigned to carry out or direct operational activities,

including manipulation of the controls and other activities affecting reactivity or

power level.

2. Compliance with the relevant requirements of 10 CFR 55.4, 55.31, 55.41, 55.43,

55.45, 55.46, and 55.59 requires that the applicant for an operator's license and for

requalification successfully complete written and operating examinations which

demonstrate that the applicant possesses the knowledge, skills, and abilities

needed to perform licensed activities.

The reactor operator and senior reactor operator training programs, including initial

and requalification training, established by the applicant provide the means to train

individuals in the knowledge, skills, and abilities needed to perform licensed

operator duties.

Meeting these requirements provides assurance that only trained and qualified

licensed individuals possessing the required knowledge, skills, and abilities will be

assigned to, and will conduct, licensed activities.

Ill. REVIEW PROCEDURES

Preparation for the review of Section 13.2.1 of the SAR should include familiarization with

10 CFR 50.54 items i through m; 10 CFR 55.4, 55.31, 55.41, 55.43, 55.45, 55.46, and 55.59;

10 CFR 50.34(f)(2)(i); Regulatory Guides 1.8 and 1.149; and NUREGs-0711 and -1021.

The reviewer should ensure that whenever the applicant has committed to follow the position of

a regulatory guide, industry standard, or other reference document, the specific revision being

referred to is identified. Similarly, whenever the reviewer is using a position in a reference

document as a basis for acceptability, the revision being used should be identified.

The reviewer then determines, based upon the foregoing, the overall acceptability of the

applicant's licensed operator training plans.

For design certification reviews under 10 CFR Part 52, the subject review will be identified as a

review to be performed during COL application review.

IV. EVALUATION FINDINGS

The reviewer should verify that the information presented in the review supports an evaluation

finding statement of the following type, to be used in the staff's safety evaluation report:

The staff concludes that the training program for licensed operators and senior operators

is acceptable and meets the requirements of 10 CFR 50.54 items i through m and 10

CFR Sections 55.4,55.31, 55.41, 55.43, 55.45, 55.46, and 55.59. This conclusion is

based on the following:

13.2.1 -5 Rev. 2 - November 2005
A. For CP or COL

The overall conduct and administration of the licensed operator training programs is the

responsibility of the Plant Manager. The Training Manager is responsible for

development, implementation, evaluation, ar)d documentation of the licensed operator

training programs.

The applicant states that a training program will be established [for COL add: in

accordance with the implementation milestones] to provide licensed operators with

sufficient knowledge and operating experience to start up, operate, and maintain the

plant in a safe manner. The licensed operator training program, derived from a systems

approach to training, is to be developed by the applicant and will meet the regulatory

guidance of Regulatory Guide 1.8. 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 should meet the guidance of Regulatory Guide 1.149.

The information submitted relative to these subjects is satisfactory for the preoperational

test program, for operator licensing, and for fuel loading.

B. For OL or COL holder - verification through the Construction Inspection Program

The overall conduct and administration of the licensed operator training program is the

responsibility of the Plant Manager. The Training Manager is responsible for

administering the licensed operator training program and monitoring program

effectiveness. The applicant states that the licensed operator training program will

provide reasonable assurance that decisions and actions by licensed operators and

senior operators during all plant conditions will be made consistent with plant safety

procedures and operational limits established to protect the public health and safety. The

licensed operator training program has been designed to meet the individual needs of the

participants, depending upon their backgrounds, previous training, and expected job

assignment. The program will meet the guidelines of Regulatory Guide 1.8 and 10 CFR

Part 55. Simulation facilities used in the training program shall meet the requirements of

10 CFR 55.31, 55.45(b), 55.46, and 50.34(f)(2)(1), and the guidelines of Regulatory

Guide 1.149. Over [state specific number provided by the licensee] candidates will have

completed the entire training program prior to the fuel loading so that a sufficient number

of licensed operators should be available to meet the requirements of 10 CFR 50.54.

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.

C. For Design Certification

The development of the reactor operator training program is identified as a COL action

item.

V. IMPLEMENTATION

The following is intended to provide guidance to applicants and licensees regarding the NRC

staff's plans for using this SRP section.

This SRP section will be used by the staff when performing safety evaluations of license

applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except

when the applicant proposes an acceptable alternative method for complying with specified

Rev. 2 - November 2005 13.2.1 -6
portions of the Commission's regulations, the method described herein will be used by the staff

in its evaluation of conformance with Commission regulations.

The provisions of this SRP section apply to reviews of applications docketed 6 months or more

after the date of issuance of this SRP section.

Implementation schedules for conformance to parts of the review plan discussed herein are

contained in the referenced regulatory guides and NUREGS.

VI. REFERENCES

1. 10 CFR Part 50, "Licensing of Production and Utilization Facilities."

2.* 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined

Licenses for Nuclear Power Plants."

3. 10 CFR Part 55, "Operators' Licenses."

4. Regulatory Guide 1.8, Qualification and Training of Personnel for Nuclear Power Plants."

5. Regulatory Guide 1.149, "Nuclear Power Plant Simulation Facilities for Use in Operator

Training and License Examinations.'

6. NUREG-071 1, "Human Factors Engineering Program Review Model."

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

8. NUREG-1220, "Training Review Criteria and Procedures."

13.2.1 -7 Rev. 2 - November 2005
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(9-2004) (Assigned by NRC, Add Vol., Supp., Rev.,

NRCMD 3.7 and Addendum Numbers, It any.)

BIBLIOGRAPHIC DATA SHEET

(See hIstnuctions on the reverse) NUREG-0800

2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED

NUREG-0800, Standard Review Plan MONTH YEAR

Chapter 13, Conduct of Operations Section 13.2.1, Reactor Operator Training December 2005

Revision 2 4. FIN OR GRANT NUMBER

5. AUTHOR(S) 6. TYPE OF REPORT

R. M. Pelton

7. PERIOD COVERED (Indusive Dates)

8. PERFORMING ORGANIZATION -NAME AND ADDRESS (IfNRC. provide vsion, officeorRegion US. NudearRegultoyCommissibn, andmaffing address if ontracor,

provide name and madn address.)

Division of Inspection and Regional Support

Office of Nuclear Reactor Regulation

U. S. Nuclear Regulatory Commission

Washington, DC 20555-0001

9. SPONSORING ORGANIZATION -NAME AND ADDRESS (fNC type Some as above '.fcontat r promvideNRCD0ion, OfficeorRegion, U.S. NudearRegulatoryCommissron,

and mafti address.)

(Same as above)

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 wods orless)

This document provides review guidance for NRC staff Ao evaluate licensee's or applicant's licensed operator training program.

Its purpose Is to ensure that the training provided to reactor operators and senior reactor operators will be adequate to provide

assurance that all reactor operator training and qualification requirement Items will be met at the time needed, i.e., prior to

operator license examinations, prior to fuel loading, or prior to appointment or reappointment to the position. Reviews

conducted under this plan should ensure that licensed personnel will be trained and qualified in accordance with applicable

regulations, regulatory guidance, and appropriate industry standards.

.

12 KEY WORDS/DESCRIPTORS (it wonds orphrses that eassist rseareher In scate the report)

Licensed Operator, Senior Operator, Reactor Operator, Training, Operator Qualification,

Requalification, Simulator, On-the-Job Training, Reactor Operations Training, Systems Approach to

Training, SAT, Ucensing Examination

13. AVAILABILITY STATEMENT

unlimited

14. SECURITY CLASSIFICATION

{this Page)

unclassified

(This Report)

unclassified

15. NUMBER OF PAGES

16. PRICE

I

NRC FORM 335(9-2004) PRINTED ON RECYCLED PAPER

NRC FORM 335 (9-2004) PRINTED ON RECYCLED PAPER
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NUCLEAR REGULATORY COMMISSION

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