RG1.169 核电厂安全系统中使用的数字计算机软件的配置管理计划 1997

美国核电法规和导则

U.S. NUCLEAR REGULATORY COMMISSION

September 1997

REGULATORYGUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 1.169

(Draft was DG-1055)

CONFIGURATION MANAGEMENT PLANS FOR DIGITAL COMPUTER SOFTWARE

USED IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS

A. INTRODUCTION

In 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," paragraph 55a(a)(1) requires, in part, that systems and components be designed, tested, and inspected to quality standards commensurate with the safety function to be performed.I Criterion 1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," of 10 CFR Part 50 requires, in part, 1 that appropriate records of the design and testing of systems and components important to safety be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 describes criteria that must be met by a quality assurance program for systems and components that prevent or mitigate the consequences of postulated accidents. In particular, besides the systems and components that directly prevent or mitigate the consequences of postulated accidents, the criteria of Appendix B also apply to all activities affecting the safety-related functions of such systems and components, such as designing, purchasing, installing, testing, operating, maintaining, or

lln this regulatory guide, many of the regulations have been paraphrased;

see 10 CFR Part 50 for the full text.

.2

modifying. A specific requirement is contained in 10 CFR 50.55a(h), which requires that reactor protection systems satisfy the criteria of IEEE Std 279, "Criteria for Protection Systems for Nuclear Power Generating Stations."2 Paragraph 4.3 of IEEE Std 279-19713 states that quality of components is to be achieved through the specification of requirements known to promote high quality, such as requirements for design, inspection, and test.

Many of the criteria in Appendix B to 10 CFR Part 50 contain requirements closely related to the configuration management activity. Criterion III, "Design Control," of Appendix B requires measures for design documentation and identification and control of design interfaces. The same criterion also requires that design changes be subject to design control measures commensurate with those used in the original design. Criterion VI, "Document Control," requires that all documents that prescribe activities affecting quality, such as

2

Revision I of Regulatory Guide 1.153, "Criteria for Safety Systems," endorses IEEE Std 603-1991,"Criteria for Safety Systems for Nuclear Powfying the NRC's regulations with respect to the design, reliability, qualifi

er Generating Stations," as a method acceptable to the NRC staff for satiscation, and testability of the power, instrumentation, and control portions of the safety systems of nuclear power plants.

3

1EEE publications may be obtained from the IEEE Service Center, 445

Hoes Lane, Piscataway, NJ 08854.

USNRC REGULATORY GUIDES

Regulatory Guides re Issued to describe and make available to the public such Informabon as methods acceptable to the NRC staff for hmplementing specific parts of the Com- mission's regulations, techniques used bythestaff inevaluating specific problemsor pos tulated accidents. and data needed by the NRC staff in Its review of applications rper.- mits and licenses. Regulatory guides ae not substitutes foregulations, and compliance withViem Isnotrelred. Methods andisolutions different from thosesetoutinlheguldes

they provide a basis for the findings requisite to the Issuance or oonwill be acceptable If

tinuence of a permit or cense by the Commission.

This guide was issued after consideration of comments received from the public. Corn- mens and suggestions for Improvenents In these guides re encouraged stall tines, and

to reflect new inguides will be revised, as eppropriae. to accommodate comments :nd

Ion~on or experience.

Written comments may be submitted to the Rules Review and Diectives Branch DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washington. DC 20555-0001.

The guides are issued in the following ten broad disions: 1. Power Reactors

2. Research and Tost Reactors I Fuels and Mateials Facilities 4. Environmental end Siting 5. Materials and Plant Protection

6. 7. 8. 9. 10.

Products

Trarsportation

Occupational Health

Anitrust and Financial Review General

Single copies of regulatory guides may be obtained free of charge bywrlilng the Printing, Graphics and Distribution Branch, Office of Adminisation. U.S. Nuclear Regulatory Commission. Washington, OC 20555-0001; or by fax at (301)41515272.

Issued guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.

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