1、Corrected EditionISBN 0-471-60205-1Library of Congress Catalog Number 87-045994Copyright 1987The Institute of Electrical and Electronics Engineers, Inc.345 East 47th Street, New York, NY 10017 USANo part of this publication may be reproduced in any form, in an electronic retrieval system or otherwis
2、e, without the prior written permission of the publisher.ANSI/IEEE Std 352-1987 (R2010)(Revision of ANSI/IEEE Std 352-1975)An American National StandardIEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety SystemsSponsorNuclear Power Engineering Committ
3、eeof theIEEE Power Engineering SocietyReaffirmed 25 March 2010Approved June 13, 1985IEEE-SA Standards BoardReaffirmed 24 March 2005Approved November 21, 1985American National Standards InstituteIEEE Standards documents are developed within the IEEE Societies and the Standards Coordinating Committees
4、 of theIEEE Standards Association (IEEE-SA) Standards Board. The IEEE develops its standards through a consensus develop-ment process, approved by the American National Standards Institute, which brings together volunteers representing variedviewpoints and interests to achieve the final product. Vol
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19、 rights in connection therewith. The IEEE shall not be responsible for identifying patentsfor which a license may be required by an IEEE standard or for conducting inquiries into the legal validity orscope of those patents that are brought to its attention.iiiForeword(This Foreword is not a part of
20、ANSI/IEEE Std 352-1987, IEEE Guide for General Principles of Reliability Analysis of NuclearPower Generating Station Safety Systems.)This document is basically tutorial and has been prepared to provide the user with the basic principles that are neededto conduct a reliability analysis of safety syst
21、ems. It is not expected or intended that any individual or organizationwould need all of the principles that are presented. For example, an organization may be concerned with quantitativeanalysis and mathematical modeling as discussed in Section 5. The very important problem of failure data is discu
22、ssedin Section 6.; the material on probability distributions, estimation, and condence intervals may be used by those whoare concerned with analysis and evaluation of failure and repair rate data that will be accumulated as nuclear powergenerating station operating experience is accrued. The materia
23、l on established data programs may be of moreimmediate use to those who make reliability or availability predictions on current safety system designs.This document was originally prepared to provide a common and consistent means of reliability analysis for protectionsystems covered by IEEE Std 279-1
24、971, Criteria for Protection Systems for Nuclear Power Generating Stations. In theintervening years, Standard 279 has been superseded by Standard 603, and in March, 1984, Standard 279 waswithdrawn. This standard has been expanded in revisions since 1971 to include many technical areas as they havebe
25、come important. In accord with the current version of Standard 603, IEEE Std 603-1980, it has been generalized toapply to safety systems.The general principles presented in this document, and further information given by the references, are sufcient toconduct the reliability/availability analyses of
26、 safety systems, but not every analysis will necessarily employ all of thegeneral principles that are presented. Furthermore, the principles contained herein are not necessarily limited tonuclear power plant safety systems. They may be applied, as applicable, to the analyses of other systems. The us
27、ersmay select those parts of the document that apply to their particular problem.The current revision of this document contains much updated information and clarication, but adheres to the generalprinciples put forth in previous editions.The IEEE will update this document as the state of the technol
28、ogy changes. Comments and suggestions for additionalmaterial to be added should be addressed to the Secretary of the IEEE Standards Board.This document was prepared by Subcommittee 5, Reliability, of the Nuclear Power Engineering Committee of theIEEE Power Engineering Society. The members of the wor
29、king group and other major contributors were as follows:R. L. Olson, Chair F. J. BalohR. G. EasterlingW. C. GangloffS. H. HanauerI. M. JacobsH. T. MartzE. NommJ. R. PenlandF. RosaB. M. TashjianM. I. TemmeI. B. WallJ. J. WroblewskiAuthorized licensed use limited to: IEEE Standards Staff. Downloaded o
30、n July 15, 2009 at 14:32 from IEEE Xplore. Restrictions apply.ivAt the time this guide was approved, the members of the subcommittee were follows:W. C. Gangloff, Chair P. F. AlbrechtA. BarchasL. E. BoothF. ChamowK. ComerW. I. CrowleyD. FinnicumJ. R. FragolaJ. F. FussellP. HassW. HannamanB. W. LoganW
31、. J. Luckas, Jr.R. MilesS. P. MitraP. K. NiyogiR. L. OlsonE. S. PattersonJ. W PegramJ. R. PenlandJ. PittmanS. ReizensteinF. RosaB. M. TashjianM. I. TemmeE. WittryJ. J. WroblewskiAt the time this guide was approved, the members of the Nuclear Power Engineering Committee were as follows:R. E. Allen, C
32、hair B. M. Rice, Vice Chair G. R. Leidich, Secretary J. T. Bauer, Vice Chairman and Standards CoordinatorJ. F. BatesT. M. Bates, Jr.F. D. BaxterR. G. BanhamJ. T. BoettgerD. F. BrosnanW. BuxtonD. G. CainF. W. ChandlerC. M. ChiappettaR. P. DaigleE. F. DowlingJ. J. FerencsikE. P. FogartyJ. M. Gallagher
33、W. C. GangloffJ. B. GardnerL. HanesI. M. JacobsR. F. KarlicekA. LairdD. C. LamkenP. G. LyonsL. C. MadisonT. J. McGrathW. E. ONealR. W. PackM. PaiA. PetrizzoE. S. PattersonJ. R. PenlandN. S. PorterW. S. RautioH. V. RedgateA. R. RobyW. F. SailerW. G. SchwartzA. J. SpurginL. StanleyD. F. SullivanP. Sza
34、badosL. D. TestJ. E. ThomasT. R. VadaroF. J. VolpeThe following persons were on the balloting committee that approved this document for submission to the IEEEStandards Board:R. E. AllenJ. T. BauerF. D. BaxterR. G. BenhamD. F. BrosnanW. E. BuxtonF. W. ChandlerR. P. DaigleE. F. DowlingJ. J. FerencsikE
35、. P. FogartyJ. M. GallagherW. C. GangloffJ. B. GardnerL. C. GonzalezB. GrimR. E. HallL. HanesG. K. HenryR. F. KarlicekJ. T. KeiperT. S. KillenA. LairdD. C. LamkenG. R. LeidichP. C. LyonsW. E. ONealR. W. PackM. PaiJ. R. PenlandC. A. PetrizzoN. S. PorterW. S. RautioH. V. RedgateB. M. RiceA. R. RobyZ.
36、SabriW. F. SAilerA. J. SpurginL. StanleyD. F. SullivanP. SzabadosW. G. SchwartzL. D. TestJ. E. ThomasT. R. VardaroF. J. VolpeAuthorized licensed use limited to: IEEE Standards Staff. Downloaded on July 15, 2009 at 14:32 from IEEE Xplore. Restrictions apply.vWhen the IEEE Standards Board approved thi
37、s standard on June 13, 1985, it had the following membership:John E. May, Chair John P. Riganati, Vice Chair Sava I. Sherr, Secretary James H. BeallFletcher J. BuckleyRene CastenschioldEdward ChelottiEdward J. CohenPaul G. CummingsDonald C. FleckensteinJay ForsterDaniel L. GoldbergKenneth D. Hendrix
38、Irvin N. HowellJack KinnJoseph L. Koepfinger*Irving KolodnyR. F. LawrenceLawrence V. McCallDonald T. Michael*Frank L. RoseClifford O. SwansonJ. Richard WegerW. B. WilkensCharles J. Wylie* Member emeritusAuthorized licensed use limited to: IEEE Standards Staff. Downloaded on July 15, 2009 at 14:32 fr
39、om IEEE Xplore. Restrictions apply.viCLAUSE PAGE1. Introduction and References .11.1 Introduction 11.2 References 12. Definitions.43. Objectives and Methods53.1 Consideration of the Human Factor . 53.2 Qualitative Analysis. 63.3 Quantitative Analysis. 63.4 Applications of Reliability Methodology 74.
40、 Qualitative Analysis Principles.94.1 Failure Mode and Effects Analysis (FMEA) . 94.2 Fault Tree Analysis 144.3 Reliability Block Diagram . 194.4 Example . 214.5 Extended Qualitative Analysis for Common-Cause Failures 225. Quantitative Analysis Principles.285.1 Mission Definition . 285.2 Mathematica
41、l Modeling . 315.3 Tabular Reference to Popular Logic Configurations . 455.4 Trial Calculations. 465.5 Credibility Check of Results 466. Guides for Data Acquisition and Use .486.1 Input Parameters 486.2 Probability Distributions, Parameters, and Estimation 506.3 Established Data Programs 566.4 Devel
42、oping Field Data Programs. 607. Application of Reliability Methods.657.1 Introduction 657.2 Numerical Goals 667.3 Selection of the Modeling Technique 677.4 Fault Tree Techniques 687.5 The Markov Process as a Reliability Model 697.6 Equipment and System Testing 728. Annex (Informative) .77Authorized
43、licensed use limited to: IEEE Standards Staff. Downloaded on July 15, 2009 at 14:32 from IEEE Xplore. Restrictions apply.Copyright 1987 IEEE All Rights Reserved1An American National StandardIEEE Guide for General Principles ofReliability Analysis of Nuclear Power Generating Station Safety Systems1.
44、Introduction and References1.1 IntroductionThis guide was prepared to provide the designers and operators of nuclear power plant safety systems and theconcerned regulatory groups with the essential methods and procedures of reliability engineering that are applicable tosuch systems. By applying the
45、principles given, systems may be analyzed, results may be compared with reliabilityobjectives, and the basis for decisions may be suitably documented.The quantitative principles are applicable to the analysis of the effects of component failures on safety systemreliability. The principles are applic
46、able during any phase of the systems lifetime. They have their greatest valueduring the design phase. During this phase, reliability engineering can make the greatest contribution towardenhancing safety.These principles may also be applied during the preoperational phase or at any time during the no
47、rmal lifetime of asystem. When the principles are applied during either of these two phases, they will aid in the evaluation of systems,in the preparation or revision of operating or maintenance procedures, and in improving test programs. Although notinherently limited, these principles are intended
48、 for application to systems covered in the scope of ANSI/IEEE Std603-1980 511.2 ReferencesThe following publications shall be used in conjunction with this standard:1 ANSI/ANS 51.1-1983, American National Standard for Nuclear Safety Criteria for the Design of StationaryPressurized Water Reactor Plan
49、ts.2 ANSI/ANS 52.1-1983, American National Standard for Nuclear Safety Criteria for the Design of StationaryBoiling Water Reactor Plants.21The numbers in brackets correspond to those of the references listed in 1.2.2ANSI/ANS publications can be obtained from the Sales Department, American National Standards Institute, 1430 Broadway, New York, NY10018, or from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60525.Authorized licensed use limited to: IEEE Standards Staff. Downloaded on July 15, 2009 at 14:32 from IEEE Xplore. Restrictions appl
