Regulatory Guide 1.149
| ML12305A245 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1981 |
| From: | Office of Nuclear Regulatory Research, NRC Region 1 |
| To: | |
| References | |
| Task RS 110-5 RG 1.149 | |
| Download: ML12305A245 (4) | |
4" U.S. NUCLEAR REGULATORY COMMISSION April 1981
~REGULATORY GUIDE
0' OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 1.149 (Task RS 110.5)
NUCLEAR POWER PLANT SIMULATORS FOR USE IN OPERATOR TRAINING
A. INTRODUCTION
exist between a simulator and the facility that the operators are being trained to operate, is addressed in 10 CFR Part 55, Appendix A, "Requalification Programs for Licensed Oper- "Operators' Licenses." This issue, the similarity that must ators of Production and Utilization Facilities," to 10 CFR exist between a simulator and the facility that the operators Part 55, "Operators' Licenses," permits use of simulators for are being trained to operate, is not addressed in the guide and operator training. should not be confused with the guidance provided that speci- fies the similarity that should exist between a simulator and This regulatory guide describes a method acceptable to its reference plant.
the NRC staff for specifying the functional requirements of a nuclear power plant simulator to be used for operator
C. REGULATORY POSITION
training.
The requirements established by ANSI/ANS 3.5-1981, The Advisory Committee on Reactor Safeguards has "Nuclear Power Plant Simulators for Use in Operator Train- been consulted concerning this guide and has concurred in ing," for specifying the functional capability of a simulator the regulatory position. and for comparing a simulator to its reference plant are acceptable to the NRC staff, subject to the following:
B. DISCUSSION
1. The standard identifies at the point of reference The need for improvements in operator training in the areas (Section 1.1, "Background Data") other documents to be of response to abnormal and emergency situations was high- included as part of the standard. The applicability of these lighted as a result of the operator errors noted in NUREG-0585, documents should be determined by referring to the latest
"TMI-2 Lessons Learned Task Force Final Report."' Use of revision of the following regulatory guides and the version the actual plant for training operators to respond to accidents of the standard the guide endorses:
would result in additional challenges to the plant's protective
2 features and is therefore undesirable. Thus, the additional ANS Standard Regulatory Guide training required to improve operator performance should be performed on simulators. In order to maximize the effective- 3.1 1.8 ness of this training, the simulator must be kept current with 3.2 1.33 changes in the reference plant and lessons learned from operating experience. Recommendations of instructors and 2. Section 3.1.2, "Plant Malfunctions," lists the abnormal operator trainees for improving a simulator should be encour- and emergency conditions that must be performed by the aged. ANSI/ANS 3.5-1981, "Nuclear Power Plant Simulators simulator if applicable to the reference plant. A simulator for. Use in Operator Training," 2 in conjunction with this should also be able to perform diesel generator failure.
regulatory guide, provides guidance in these areas.
3. Appendix A, "Procedure for Documenting Simulator The use of simulators for operator training, including Performance," to the standard should be considered an the requirements which specify the similarity that must *integral part of the standard.
ICopies are available for public inspection or copying for a fee at the 4. The simulator performance test discussed in Sec- NRC Public Document Room, 1717 H Street NW., Washington, D.C., tion 5.4, "Simulator Performance Testing," of the standard or copies may be purchased for $2.50 directly from NRC by sending check or money order payable to the Superintendent of Documents to the Director, Division of Technical Information and Document Con- 2Copies may be obtained from the American Nuclear Society, trol, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555. 555 North Kensington Avenue, LaGrange Park, Illinois 60525.
USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Regulatory Guides are issued to describe and make available to the Attention: Docketing and Service Branch.
public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech- The guides are issued in the following ten broad divisions:
nidues used by the staff in evaluating specific problems or postu- lated accidents or to provide guidance to applicants. Regulatory 1. Power Reactors 6. Products Guides are not substitutes for regulations, and compliance with 2. Research and Test Reactors 7. Transportation them is not required. Methods and solutions different from those set 3. Fuels and Materials Facilities 8. Occupational Health out in the guides will be acceptable if they provide a basis for the 4. Environmental and Siting 9. Antitrust and Financial Review findings requisite to the issuance or continuance of a permit or 5. Materials and Plant Protection 10. General license by the Commission.
Copies of issued guides may be purchased at the current Government This guide was issued after consideration of comments received from Printing Office price. A subscription service for future guides in spe- the public. Comments and suggestions for improvements in these cific divisions is available through the Government Printing Office.
guides are encouraged at all times, and guides will be revised, as Information on the subscription service and cur*rent GPO prices may
.appropriate, to accommodate comments and to reflect new informa- be obtained by writing the U.S. Nuclear Regulatory Commission, tion or experience. Washington, D.C. 20555, Attention: Publications Sales Manager.
should include as a minimum all the provisions of Appen- described in this guide will be used in the evaluation of all dix.A to the standard. simulators placed in operation after August 1, 1984, that are used for training nuclear powerjplant 6operators and others
5. Sections 2.1, 2.2. and 2.3 of Appendix A to. the whose. duties require an- operator's or senior operat6r's- standard require documentation of equipment lineup as Aicense. In addition, all simulators currently in use or placed part of the simulator data base for steady state operating in use prior to August 1, 1984, for training nuclear power conditions, transient operating conditions, and significant ,plant operators and others whose duties require an operator's plant-occurring events. Equipment lineup documentation or senior operator's license will be evaluated in accordance need only include equipment that may have an observabl'e with the following schedule:
'effect on the expected plant response being considered.
I. The requirements of Section 1, "Simulator Informa-
6. Item 2 of Section 3.2, "Abnormal Operations," of tion," of Appendix A to the standard should be complete Appendix A to the standard should be taken to mean that by August 1, 1982, or by the time the simulator is placed in although Section 3.1.2 of the stafidard requires that a operation for training, whichever is later.
minimum of 75 malfunctions be simulated, each simulator will most likely be capable of simulating more than the 2. The requirements of Section 2, "Simulator Data Base,"
minimum; therefore, every malfunction that can be intro& of Appendix A to the standard should be complete by duced into the simulator by the instructor should be tested. August 1, 1982, or by the time the simulator is placed in operation for training, whichever is later.
7. The terms "transients," "abnormal conditions,"
"abnormal operations," and "abnormal evolutions" used in 3. The tests discussed in Section 3, "Simulator Tests,"
the standard should be considered equivalent to "anticipated of Appendix A to the standard shouldbe conducted and the operational occurrences." initial documentation should be complete by August 1, 1983, or by the time the simulator is placed in operation for training, whichever is later.
D. IMPLEMENTATION
4. Deviation from the data base should be corrected and The purpose of this section is to provide information the simulator should be in full compliance with the require- to applicants regarding the NRC staff's plans for using this ments of ANSI/ANS 3.5-1981 as modified by this guide by regulatory guide. Except in those cases in which an applicant August 1, 1984, or by the time the simulator is placed in proposes an acceptable alternative method, the method operation for training, whichever is later.
.1.149-2
VALUE/IMPACT STATEMENT
1. ACTION Plant Personnel" uses the adjectives "suitable" (Paragraph
5.2.1) or "appropriate" (Paragraphs 5.2.4 and 5.5.1.2.2)
1.1 Description when describing reactor simulators used for training person- nel. The value of this action to the NRC is the availability Prior to issuing an operator's license to an applicant, the of guidance on what is a "suitable" or "appropriate"
Commission regulations require that evidence be shown that reactor simulator against which to review licensee training the applicant has learned to operate the controls in a compe- programs for adequacy. The impact of this action on the tent and safe manner. In accordance with ANSI/ANS 3.1-1978, NRC will be that of the time spent in developing the
"Qualification and Training of Personnel for Nuclear Power guidance, reviewing the licensees' proposals to comply with Plants," and Regulatory Guide 1.8, "Personnel Selection and the guide, and verifying implementation of the proposals.
Training,"* reactor simulators may be used to partially fulfill this requirement. In addition, Appendix A to 10 CFR 1.3.2 Other Government Agencies Part 55 describes the use of simulators for requalification programs, and NUREG-0094, "NRC Operator Licensing This action should not impact other government agencies,.
Guide,"*
- describes the use of simulators for initial licensing. unless the government agency is an applicant, such as TVA.
This action provides guidance on the acceptable character- istics of reactor simulators used for operator training as 1.3.3 Industry, described in the above references.
The result of this action is expected to be the addition
1.2 Need for Action of required functions to simulators that may now be in use for specific nuclear, power plants. The impact on industry
- The need for improvements in operator training in the areas will, likely be that of increased cost as more complex of response to abnormal and emergency situations was high- simulators are. required. An alternative to simulators is the lighted as a result of the operator errors noted in NUREG&0585, use of the actual power plant for trainin
g. This use results
"TMI-2 Lessons Learned Task Force Final Report." Use of in lost revenue because the power plant is not available to the actual plant for training operators to respond to accidents produce electrical power and also results in additional would result in additional challenges to the plant's protective challenges to the plant protection systems. The value of the features and is therefore undesirable. Thus, additional train- action to industry should be (1) more efficient operation of ing required to impr6ve, operator performance should be the power plant by better trained operators that would performed on simulators. A recommendation to require result in a cost savings when the power plant is put on line simulator training for initial and requalification training was in an expeditious manner and (2) a reduction in operator made to the Commission and accepted. The simulators used errors that might cause plant downtime or equipment for current training and proposed future training should damage. The value is based on using simulators that more have characteristics that allow the objective of training the accurately reflect the power plant they represent and that operator to operate the controls in a competent and safe simulate additional accidents, transients, and evolutions in a manner to be met. The action discussed in this value/impact more complete manner than can safely be performed on an statement is e.xpected to ensure that the objective stated actual plant.
above will be met.
1.3.4 Public
1.3 Value/Impact of Action The value to the public will be that better trained
1.3,1 NRC operators should reduce the possibility of improper operation of nuclear power plant equipment or systems that could Section 5 of ANSI/ANS 3.1-1978 (endorsed by Regula- endanger public health and safety. The impact will be that tory Guide 1.8) "Selection and Training of Nuclear Power of slightly higher electrical rates caused by higher costs as explained in Item 1.3.3.
1.4 Decision on Action Second proposed Revision 2 to Regulatory Guide 1.8 entitled This guide is being issued to .provide recommendations
"Personnel Qualification and Training" was issued for comment acceptable to the NRC staff on acceptable characteristics of in September 1980.
nuclear power plant simulators for use in operator training.
Copies are available for public inspection or copying for a fee at the NRC Public Document Room, 1717 H Street NW., Washington,
2. TECHNICAL APPROACH
D.C., or copies may be purchased for $4.00 directly from NRC by sending check or money order payable to the Superintendent of Documents to the Director, Division of Technical Information and The decision to use simulators for training of operators Document Control, U.S. Nuclear Regulatory Commission, Washing- ton, D.C. 20555. has been made by the Commission.
1.149-3
3. PROCEDURAL APPROACH 4. STATUTORY CONSIDERATIONS
3.1 Procedural Alternatives 4.1 NRC Authority
1. Regulation Authority for this guide is derived from the safety
2. Regulatory guide
3. National standard, endorsed by a regulatory guide requirements of the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974 through the
(
Commission's regulations; in particular, 10 CFR Part 55
3.2 Value/Impact of Procedural Alternatives applies.
The value of alternative 1, a regulation, is that it would have the full force and authority of a law. The impact of 4.2 Need for NEPA Assessment alternative 1 is that it would lack flexibility in implementa- tion. The value of alternative 2, a regulatory guide, is that it An environmental impact statement is not required since would achieve the desired result with suitable flexibility for this guide is not a major action that may significantly affect innovation by licensees. The impact of alternative 2is that the quality of the human environment.
it may not take full advantage of the work performed by industry in the area the guide addresses, which may result in a longer development period prior to issuing the guide. 5. RELATIONSHIP TO OTHER EXISTING OR PROPOSED
The value of alternative 3, a standard endorsed by a regu- REGULATIONS OR POLICIES
latory guide, is that it would achieve the desired result while taking advantage of the work performed by industry Regulatory Guide 1.8 and Appendix A to 10 CFR Part 55 in its development of ANSI/ANS 3.5-1981, "Nuclear Power make reference to simulators used in the training program Plant Simulators for Use in Operator Training." The impact for operators. In these documents, only general.statements of alternative 3 is that effort would have to be expended by are made concerning the characteristics of acceptable simu- the NRC in preparing, reviewing, and issuing the regulatory lators. This guide is consistent with existing and proposed guide. It is estimated, however, that the effort spent on the requirements and guidelines for simulators.
action would be greater if alternatives 1 or 2 were chosen.
3.3 Decision on Procedural Approach 6. SUMMARY AND CONCLUSION
The action has been accomplished by publishing a Regulatory Guide 1.149, "Nuclear Power Plant Simulators regulatory guide endorsing ANSI/ANS 3.5-1981, "Nuclear for Use in Operator Training," has been prepared. It endorses, Power Plant Simulators for Use in Operator Training." with certain exceptions, ANSI/ANS 3.5-1981. (
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
1194060020CL I QPISIR
LS NRC REGION I
CFFICE Of INSPECILON & ENFORCE
R J BORES
631 PARK AVENUE
REGION I
KING OF PRUSSIA PA 1940C
1.149-4