IEEE-577-2004.pdf
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1、IEEE Std 577-2004 (Revision of IEEE Std 577-1976) IEEE Standards 577 TM IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities 3 Park Avenue, New York, NY 10016-5997, USA IEEE Power Engineering Society Sponsored by the Nuclear Power E
2、ngineering Committee IEEE Standards 30 August 2004 Print: SH95241 PDF: SS95241 The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2004 by the Institute of Electrical and Electronics Engineers, Inc. All rights reserved. Published 30 Augus
3、t 2004. Printed in the United States of America. IEEE is a registered trademark in the U.S. Patent +1 978 750 8400. Permission to photocopy portions of any individual standard for educational classroom use can also be obtained through the Copyright Clearance Center. NOTEAttention is called to the po
4、ssibility that implementation of this standard may require use of subject matter covered by patent rights. By publication of this standard, no position is taken with respect to the existence or validity of any patent rights in connection therewith. The IEEE shall not be responsible for identifying p
5、atents for which a license may be required by an IEEE standard or for conducting inquiries into the legal validity or scope of those patents that are brought to its attention. Copyright 2004 IEEE. All rights reserved. iii Introduction (This introduction is not part of IEEE Std 577-2004, IEEE Standar
6、d Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities.) This standard was first published in 1976 to standardize the application of reliability techniques in the design and operation of nuclear facilities. This revision, IEEE Std 577-2004, has b
7、een prepared to delete obsolete information and to update the standard to current references and practices within the nuclear industry. The standard is directed towards those systems in the nuclear facility that perform protective functions and fall within the scope of IEEE Std 603 -1998 a and IEEE
8、Std 308 -2001. 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 periodic testing programs. IEEE Std 352 -1987 supplements this standard by providing guidance in the application
9、of reliability techniques. IEEE Std 338 -1987 requires that programs be 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
10、 stated in regulations and other standards. When reliability analysis is used for this purpose, this standard describes an acceptable response to the requirements. The requirement that a reliability analysis be performed does not originate with this standard. IEEE Std 379 -2000 describes the applica
11、tion of the single-failure criterion and also states in 6.3.2: “A probabilistic assessment shall not be used in lieu of the single-failure analysis.” Notice to users Errata Errata, if any, for this and all other standards can be accessed at the following URL: http:/ standards.ieee.org/reading/ieee/u
12、pdates/errata/index.html. Users are encouraged to check this URL for errata periodically. Interpretations Current interpretations can be accessed at the following URL: http:/standards.ieee.org/reading/ieee/interp/ index.html. Patents Attention is called to the possibility that implementation of this
13、 standard may require use of subject matter covered by patent rights. By publication of this standard, no position is taken with respect to the existence or validity of any patent rights in connection therewith. The IEEE shall not be responsible for identifying patents or patent applications for whi
14、ch a license may be required to implement an IEEE standard or for conducting inquiries into the legal validity or scope of those patents that are brought to its attention. a Information on references can be found in Clause 2. iv Copyright 2004 IEEE. All rights reserved. Participants This standard wa
15、s prepared by the Human Factors, Control Facilities, and Reliability Subcommittee (SC5) of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The following SC5 members participated in the development and approval of the standard: T. J. Voss, Official Reporter The followin
16、g members of the individual balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. When the IEEE-SA Standards Board approved this standard on 12 May 2004, it had the following membership: Don Wright, Chair Steve M. Mills, Vice Chair Judith Gorm
17、an, Secretary *Member Emeritus Also included are the following nonvoting IEEE-SA Standards Board liaisons: Satish K. Aggarwal, NRC Representative Richard DeBlasio, DOE Representative Alan Cookson, NIST Representative Savoula Amanatidis IEEE Standards Managing Editor John P. Ahlbrandt Karen D. Arcisz
18、ewski Harold S. Blackman Dennis C. Bley James Bongarra, Jr. Ronald Bradford Raymond J. Christensen Andrew A. Dykes Robert C. Evans Joseph R. Fragola Hamilton C. Fish Robert B. Fuld James R. Gallman Robert E. Hall Bruce Hallbert G. William Hannaman Daryl Harmon Sam Heuertz Jeffery A. Julius William R
19、. Klein Jeffery A. Mahn William Mangiante P. Glenn Marshall William C. McQuiston Thomas Shedlosky Anthony J. Spurgin Robert L. Starkey Dawn Starrett Tommy Wall Robert Waters John Wreathall Satish K. Aggarwal Stan J. Arnot Farouk Baxter Wesley Bowers Daniel Brosnan John Carter Robert Copyak John Diso
20、sway Amir El-Sheikh Hamilton C. Fish Stephen Fleger James R. Frysinger Robert B. Fuld Ajit Gwal Britton Grim Randall Groves Robert E. Hall Wolfgang B. Haverkamp Peter Hung James H. Jones James Keiper John MacDonald Richard Meininger G. Michel Brian Newell James Ruggieri James Thomas T. J. Voss Li Zh
21、ang Chuck Adams H. Stephen Berger Mark D. Bowman Joseph A. Bruder Bob Davis Roberto de Boisson Julian Forster* Arnold M. Greenspan Mark S. Halpin Raymond Hapeman Richard J. Holleman Richard H. Hulett Lowell G. Johnson Joseph L. Koepfinger* Hermann Koch Thomas J. McGean Daleep C. Mohla Paul Nikolich
22、T. W. Olsen Ronald C. Petersen Gary S. Robinson Frank Stone Malcolm V. Thaden Doug Topping Joe D. Watson -,-,- Copyright 2004 IEEE. All rights reserved. v Contents 1.Overview 1 1.1 Scope 1 1.2 Purpose. 1 2.References 2 3.Definitions 2 4.Requirements. 2 4.1 General. 2 4.2 Qualitative analysis 3 4.3 Q
23、uantitative analysis 4 4.4 Evaluation 5 -,-,- -,-,- Copyright 2004 IEEE. All rights reserved. 1 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities 1. Overview 1.1 Scope This standard sets forth the minimum acceptable requirements
24、for the performance of reliability analyses for safety-related systems when used to address the reliability considerations discussed in the standards listed in Clause 2. The methods of this standard may also be applied to other systems, including the interactions, if any, between safety-related and
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