1、 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations Sponsored by the Nuclear Power Engineering Committee IEEE 3 Park Avenue New York, NY 10016-5997 USA 19 October 2012 IEEE Power and Energy Society IEEE Std 577-2012
2、 (Revision of IEEE Std 577-2004) IEEE Std 577-2012 (Revision of IEEE Std 577-2004) IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of the IEEE Power and Energy Society
3、Approved 30 August 2012 IEEE-SA Standards Board Abstract: The minimum acceptable requirements for the performance of reliability analyses for safety systems when used to address the reliability considerations discussed in industry standards and guidelines are set forth in this standard. The requirem
4、ent that a reliability analysis be performed does not originate with this standard. However, when reliability analysis is used to demonstrate compliance with reliability requirements, this standard describes an acceptable response to the requirements. Keywords: IEEE 577, nuclear facilities, reliabil
5、ity analysis, safety systems The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2012 by The Institute of Electrical and Electronics Engineers, Inc. All rights reserved. Published 19 October 2012. Printed in the United States of America.
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19、ed from the IEEE Standards Association. Copyright 2012 IEEE. All rights reserved. vi Participants At the time this IEEE standard was completed, the Nuclear Power Engineering Committee had the following membership: John D. McDonald, Chair Satish Aggarwal, Vice Chair Ijaz Ahmad George Attarian George
20、A. Ballassi Farouk D. Baxter Mark Bowman Daniel F. Brosnan Nissen M. Burstein Robert C. Carruth John P. Carter John Disosway Dennis Dellinger Stephen Fleger Robert J. Fletcher Robert B. Fuld James Gleason Dale T. Goodney Daryl Harmon Dirk C. Hopp David A. Horvath Paul R. Johnson Thomas Koshy Harvey
21、C. Leake J. Scott Malcolm Alexander Marion Michael H. Miller James Parello Mansoor H. Sanwarwalla Glen E. Schinzel James E. Stoner, Jr. James E. Thomas Marek Tengler Paul L. Yanosy, Sr. David J. Zaprazny At the time this IEEE standard was completed, the NPEC Operations, Surveillance, Aging, Reliabil
22、ity, and Testing Subcommittee (SC 3) had the following membership: Glen E. Schinzel, Chair Mansoor H. Sanwarwalla, Vice ChairGopal Aravapalli George A. Ballassi John Beatty Tom Crawford Alireza Daneshpooy Rachel B. Gunnett Hamid F. Heidarisafa Sharon Honecker David A. Horvath Peter J. Kang Jacob Kul
23、angara Robert Lane James K. Liming G. Singh Matharu Kirklyn Melson Joseph Napper James Parello Ted Riccio Owen Scott Craig D. Sellers Barry Sloane John A. Stevens John H. Taylor Yvonne Williams Kiang Zee At the time this IEEE standard was completed, the Nuclear Power Engineering Committee (PE/NPE/WG
24、_3_3) Working Group had the following membership: James K. Liming, Chair John A. Stevens, Vice Chair Gopal Aravapalli George A. Ballassi John Beatty Tom Crawford Alireza Daneshpooy Rachel B. Gunnett Hamid F. HeidarisafaSharon Honecker David A. Horvath Peter J. Kang Jacob Kulangara Joseph Napper Jame
25、s Parello Ted Riccio Mansoor H. Sanwarwalla Glen E. Schinzel Owen Scott Craig D. Sellers Barry Sloane John H. Taylor Yvonne Williams Kiang Zee Copyright 2012 IEEE. All rights reserved. vii The following members of the individual balloting committee voted on this standard. Balloters may have voted fo
26、r approval, disapproval, or abstention. William Ackerman Stan Arnot George A. Ballassi Robert Beavers William Bloethe Wesley Bowers Daniel Brosnan Robert Carruth Suresh Channarasappa Tom Crawford Alireza Daneshpooy John Disosway Gary Engmann Stephen Fleger Dale Goodney Ron Greenthaler Randall Groves
27、 Ajit Gwal Daryl Harmon Hamid R. Heidarisafa Werner Hoelzl David A. Horvath Peter Hung Paul Johnson James Jones Piotr Karocki Yuri Khersonsky Chad Kiger Joseph L. Koepfinger James Liming Greg Luri Gary Michel Michael S. Newman Julian Profir Ted Riccio Bartien Sayogo Glen Schinzel Gil Shultz James Sm
28、ith Rebecca Steinman John Stevens Gary Stoedter Marcy Stutzman S. Thamilarasan James Thompson John Vergis Robert Waters Yvonne Williams David Zaprazny When the IEEE-SA Standards Board approved this standard on 30 August 2012, it had the following membership: Richard H. Hulett, Chair John Kulick, Vic
29、e Chair Robert M. Grow, Past Chair Konstantinos Karachalios, Secretary Satish Aggarwal Masayuki Ariyoshi Peter Balma William Bartley Ted Burse Clint Chaplin Wael Diab Jean-Philippe Faure Alexander Gelman Paul Houze Jim Hughes Young Kyun Kim Joseph L. Koepfinger* David J. Law Thomas Lee Hung Ling Ole
30、g Logvinov Ted Olsen Gary Robinson Jon Walter Rosdahl Mike Seavey Yatin Trivedi Phil Winston Yu Yuan *Member Emeritus Also included are the following nonvoting IEEE-SA Standards Board liaisons: Richard DeBlasio, DOE Representative Michael Janezic, NIST Representative Michelle Turner IEEE Standards P
31、rogram Manager, Document Development Malia Zaman IEEE Standards Program Manager, Technical Program Development Copyright 2012 IEEE. All rights reserved. viii Introduction This introduction is not part of IEEE Std 577-2012, IEEE Standard Requirements for Reliability Analysis in the Design and Operati
32、on of Safety Systems for Nuclear Power Generating Stations. This standard was first published in 1976 to standardize the application of reliability techniques in the design and operation of nuclear power generating station and nuclear facilities. This standard is intended for nuclear generating stat
33、ions and other facilities related to the nuclear fuel cycle, from fuel processing to reprocessing and waste facilities, all referred to as “facilities” in this standard. The standard was revised in 2004 to delete obsolete information and to update the standard to current references and practices wit
34、hin the nuclear industry. This revision, IEEE Std 577-2012, has been prepared to continue the updating of the standard to current references and practices within the nuclear industry, and to conform to the revised style manual and formatting for standards. The standard is directed towards those syst
35、ems in the nuclear facility that performs protective functions and falls within the scope of IEEE Std 603 and IEEE Std 308. However, the requirements of this standard may be applied to other systems within a nuclear facility if appropriate. This standard may also be used as a guide to establish peri
36、odic testing programs. This revision also has modified the wording applicable only to nuclear power generating stations to reflect its use for other nuclear facilities as well. IEEE Std 352 supplements this standard by providing guidance in the application of reliability techniques. IEEE Std 338 req
37、uires that programs are established for periodic testing that are based, in part, upon the minimum acceptable analyses described in this standard. Reliability analysis is a method that can be used to demonstrate compliance with reliability requirements stated in industry standards and guidelines. Wh
38、en reliability analysis is used for this purpose, this standard describes an acceptable response to the requirements. The requirement that a reliability analysis is performed does not originate with this standard. IEEE Std 379-2000 B36adescribes the application of the single-failure criterion. aThe
39、numbers in brackets correspond to those of the Bibliography in Annex A. Copyright 2012 IEEE. All rights reserved. ix Contents 1. Overview 1 1.1 Scope . 1 1.2 Purpose 2 2. Normative references 2 3. Definitions 2 4. Requirements 2 4.1 General 2 4.2 Qualitative analysis 3 4.3 Quantitative analysis 4 4.
40、4 Evaluation 6 Annex A (informative) Bibliography 7 Copyright 2012 IEEE. All rights reserved. 1 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations IMPORTANT NOTICE: IEEE Standards documents are not intended to ensur
41、e safety, health, or environmental protection, or ensure against interference with or from other devices or networks. Implementers of IEEE Standards documents are responsible for determining and complying with all appropriate safety, security, environmental, health, and interference protection pract
42、ices and all applicable laws and regulations. This IEEE document is made available for use subject to important notices and legal disclaimers. These notices and disclaimers appear in all publications containing this document and may be found under the heading “Important Notice” or “Important Notices
43、 and Disclaimers Concerning IEEE Documents.” They can also be obtained on request from IEEE or viewed at http:/standards.ieee.org/IPR/disclaimers.html. 1. Overview 1.1 Scope This standard sets forth the minimum, acceptable requirements for the performance of reliability analyses for safety systems w
44、hen used to address the reliability considerations discussed in industry standards and guidelines. The methods of this standard may also be applied to other systems, including the interactions, if any, between safety and non-safety systems. The requirements should be applied during the phases of des
45、ign, fabrication, testing, maintenance, and repair of systems and components in nuclear power generating stations. The timing of the analysis depends upon the purpose for which the analysis is performed. This standard applies to the facility owner and other organizations responsible for the activiti
46、es previously stated. IEEE Std 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations Copyright 2012 IEEE. All rights reserved. 2 1.2 Purpose The purpose of this standard is to provide uniform, minimum, accepta
47、ble requirements for the performance of reliability analyses for safety systems found in nuclear facilities, but not to define the need for an analysis. The need for reliability analysis has been identified in other standards (e.g., IEEE Std 379-2000 B361which describes the application of the single
48、-failure criterion). IEEE Std 352 provides guidance in the application and use of reliability techniques referred to in this standard.22. Normative references The following referenced documents are indispensable for the application of this document (i.e., they must be understood and used, so each re
49、ferenced document is cited in text and its relationship to this document is explained). For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments or corrigenda) applies. IEEE Std 338, IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety.3, 4IEEE Std 352, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems. 3. Definitions For the purposes of this docu
