IEEE 627-2010 en Qualification of Equipment Used in Nuclear Facilities《用于核设施的设备资格鉴定IEEE标准》.pdf

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3、9g72g81g88g72g3g49g72g90g3g60g82g85g78g15g3g49g60g3g20g19g19g20g25g16g24g28g28g26g15g3g56g54g36g3g34g3Juneg3g21g19g20g19g25g21g26g55g48IEEE Std 627-2010 (Revision of IEEE Std 627-1980) IEEE Standard for Qualification of Equipment Used in Nuclear Facilities Sponsor Nuclear Power Engineering Committee

4、 of the IEEE Power +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. Introduction This introduction is not part of IEEE Std 627-2010, IEEE Standard for Qualification of Equipment Use

5、d in Nuclear Facilities. The requirements for qualification of safety system equipment are mandated by regulatory documents including the Code of Federal Regulations (CFR) and various industry standards. Among them are the following: a) 10 CFR Part 50, Appendix A, General Design Criterion 2 (Design

6、Bases for Protection Against Natural Phenomena), General Design Criterion 4 (Environmental and Dynamic Effects Design Bases), and General Design Criterion 23 (Protection System Failure Modes). This requires that structures, systems, and components important to safety be designed to withstand the eff

7、ects of natural phenomena such as earthquakes, and to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant-accidents. b) 10 CFR Part 50, Appendix B, Quality Assura

8、nce Criterion III (Design Control). This requires that design control measures be established and that such measures provide for verifying or checking the adequacy of design. One of the methods of design verification is by the performance of a suitable testing program. c) 10 CFR Part 50.55a, Codes a

9、nd Standards, Protection System. This requires that the protection system meet the requirements set forth in 4.4 of IEEE Std 279-1971 B11. d) ASME BPV-III, ASME Boiler and Pressure Vessel Code, Section III B3. e) Clause 4.7, Equipment Qualification, of IEEE Std 308, IEEE Standard Criteria for Class

10、1E Power Systems for Nuclear Power Generating Stations B12. f) Clause 4.6, Equipment Qualification, of IEEE Std 603, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations. g) Clause 3.3, Equipment Qualification, of ANSI/ANS-56.7-1978 (withdrawn 1997), Boiling Water Reactor

11、Containment Ventilation Systems. h) Clause 3.3, Component Performance Requirements, of ANSI/ANS-56.6-1986 (withdrawn 1996), Pressurized Water Reactor Containment Ventilation Systems. i) Clause 4.6, Isolation Barrier Environmental Provisions, of ANSI/ANS-56.2-1984 (withdrawn 1999), Containment Isolat

12、ion Provisions for Fluid Systems. Efforts on this standard were originally begun in late 1975 at the request of the IEEE Nuclear Standards Management Board. In 1977 a joint ASME/IEEE agreement established responsibility for qualification and quality assurance standards preparation. ASME accepted res

13、ponsibility for Quality Assurance and IEEE for qualification. In accordance with that agreement, IEEE completed the generic qualification standard which is this standard in 1980. This document provided high level approaches, criteria, guidance, and principles for qualification of both electrical and

14、 mechanical equipment that at that time appeared in no other industry standard. IEEE Std 627-1980 was later reaffirmed in 1996. In 1986, ASMEs Board on Nuclear Codes and Standards directed its Committee on Qualification of Mechanical Equipment (QME) to develop a standard for qualifying mechanical eq

15、uipment. This task was completed in several parts during the time frame from 1992 to 1994. Partly in response to this activity, IEEE Std 627 was withdrawn in 2002. Later although withdrawn, it was found that IEEE Std 627 was continuing to be used and referenced by many entities both in the US and ot

16、her countries including in ASMEs QME-1-2002 “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants,” US NRCs NUREG-0800 Standard Review Plan Section 3.11 B38, at least one reactor vendors Design Certification Document (DCD), several iv Copyright 2010 IEEE. All rights reserved. in

17、ternational licensing documents, and elsewhere. As a result, in 2007, the IEEE Standards Board authorized Working Group 2.10 of Subcommittee 2 (Qualification) of the Power and Energy Societys Nuclear Power Engineering Committee to resurrect and update IEEE Std 627-1980 (R1996). This revision has inc

18、orporated the following improvements to reflect current practices and user needs: The resulting standard is an upper tier document to both IEEE Std 323TMand ASME QME-1. Allowance for Owner discretion to apply this standard to other safety system equipment and to facilities other than nuclear power g

19、enerating stations. The term design qualification has been replaced by equipment qualification or just qualification (because the term design qualification is not widely used). Deletions, additions to and updates in several of the definitions have been made (such as design qualification, equipment q

20、ualification, common mode and common cause failures, DBE Period of Operability, and margin). Minor changes in the names of Clause 5 and Clause 6 and rearranging of wording to match the clause titles have been made to facilitate future reference. An informative block diagram has been added to clarify

21、 the relationship between this standard and other qualification references. An informative annex clarifying various terms related to safety for possible use by facility Owners in determining when qualification should be invoked has been added. An informative bibliographical annex with a comprehensiv

22、e list of qualification references has been added. This standard was written and continues to serve as a general standard for qualification of all types of equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing speci

23、fic equipment standards. Guidance for qualifying specific types of equipment may be found in various equipment-specific qualification standards (see Annex B). Equipment in nuclear facilities with required functions are required to meet or exceed performance requirements throughout its installed life

24、. This is accomplished by a disciplined program of qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the qualification section of the program only. Normal production testing and preoperational testing (i.e., functional testing

25、) performed after installation and acceptance of the equipment is outside the scope of this standard. Qualification is intended to demonstrate the capability of the equipment design to perform its required function(s) over the expected range of normal, abnormal, design basis event, post design basis

26、 event, and in-service test conditions. Inherent to qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade the equipment from its ori

27、ginal design condition to the point where it cannot perform its required safety function(s) upon demand. The above requirement reflects the primary role of qualification to provide reasonable assurance that design- and age-related common cause failures will not occur during performance of required f

28、unction(s) under postulated service conditions. Notice to users Laws and regulations Users of these documents should consult all applicable laws and regulations. Compliance with the provisions of this standard does not imply compliance to any applicable regulatory requirements. Implementers of the s

29、tandard are responsible for observing or referring to the applicable regulatory requirements. IEEE does not, by the publication of its standards, intend to urge action that is not in compliance with applicable laws, and these documents may not be construed as doing so. v Copyright 2010 IEEE. All rig

30、hts reserved. Copyrights This document is copyrighted by the IEEE. It is made available for a wide variety of both public and private uses. These include both use, by reference, in laws and regulations, and use in private self-regulation, standardization, and the promotion of engineering practices a

31、nd methods. By making this document available for use and adoption by public authorities and private users, the IEEE does not waive any rights in copyright to this document. Updating of IEEE documents Users of IEEE standards should be aware that these documents may be superseded at any time by the i

32、ssuance of new editions or may be amended from time to time through the issuance of amendments, corrigenda, or errata. An official IEEE document at any point in time consists of the current edition of the document together with any amendments, corrigenda, or errata then in effect. In order to determ

33、ine whether a given document is the current edition and whether it has been amended through the issuance of amendments, corrigenda, or errata, visit the IEEE Standards Association web site at http:/ieeexplore.ieee.org/xpl/standards.jsp, or contact the IEEE at the address listed previously. For more

34、information about the IEEE Standards Association or the IEEE standards development process, visit the IEEE-SA web site at http:/standards.ieee.org. Errata Errata, if any, for this and all other standards can be accessed at the following URL: http:/standards.ieee.org/reading/ieee/updates/errata/index

35、.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 standard may requi

36、re 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 is not responsible for identifying Essential Patent Claims for which a license may be required, fo

37、r conducting inquiries into the legal validity or scope of Patents Claims or determining whether any licensing terms or conditions provided in connection with submission of a Letter of Assurance, if any, or in any licensing agreements are reasonable or non-discriminatory. Users of this standard are

38、expressly advised that determination of the validity of any patent rights, and the risk of infringement of such rights, is entirely their own responsibility. Further information may be obtained from the IEEE Standards Association. vi Copyright 2010 IEEE. All rights reserved. vii Copyright 2010 IEEE.

39、 All rights reserved. Participants At the time this standard was submitted to the IEEE-SA Standards Board for approval, the 2.10 Working Group had the following membership: David A. Horvath, Chair Suresh Channarasappa, Vice Chair Rebecca L. Steinman, Secretary Christopher D. Abernathy Steven Benson

40、Nissen Burstein Philip DiBenedetto Walter Emerson Douglas E. Hart Hamidreza Heidarisafa Peter Kang Frank Kloer James Parello Robert Queenan John M. Richards Thomas Ruggiero Michael Schaepkens Glen Schinzel At the time this guide was balloted, Subcommittee 2 on Qualification had the following members

41、hip: Nissen Burstein, Chair James Parello, Vice Chair James Gleason, Secretary Christopher D. Abernathy Saleem Akhtar Steven Benson Thomas Brewington Steve Casadevall Suresh Channarasappa Choon-Hoon Chung James Dean Dennis Dellinger Mike Dougherty Frank Drumm Walter Emerson Wells Fargo Artur Faya Ro

42、bert Francis Patrick Gove William Hadovski Tom Hencey III Dirk Hopp David A. Horvath Serena Krause Thomas Koshy Bruce Lory Asif Mohiuddin Edward Mohtashemi Charles Mohr Bill Newell Janez Pavsek Jan Pirrong Robert Queenan Fred Roy Steve Sandberg Glen Schinzel Kjell Spng Marek Tengler Marco Van Uffele

43、n Carl Weber John Wheless John White Richard Wood Toshio Yamamoto At the time this guide was balloted, the Nuclear Power Engineering Committee had the following membership: Scott Malcolm, Chair John D. MacDonald, Vice Chair Satish K. Aggarwal, SecretaryIjaz Ahmad George Attarian George Ballassi Faro

44、uk Baxter Mark Bowman Daniel Brosnan Nissen Burstein Robert Carruth John Carter John Disosway Stephen Fleger Robert Fletcher Robert Fuld Jim Gleason Dale Goodney William Hadovski David A. Horvath Paul Johnson Thomas Koshy Harvey Leake Alexander Marion Michael Miller James Parello Mansoor Sanwarwalla

45、 Glen Schinzel J.E. Stoner James Thomas Paul Yanosy David Zaprazny The following members of the individual balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. William J. Ackerman Satish K. Aggarwal Stan Arnot George Ballassi Farouk Baxter Ro

46、yce Beacom Robert Beavers Wesley Bowers Thomas Brewington Daniel Brosnan Nissen Burstein Robert Carruth Suresh Channarasappa Keith Chow Alireza Daneshpooy Roger Daugherty Dennis Dellinger John Disosway Michael Dougherty Richard Doyle Gary Engmann Wells Fargo Stephen Fleger James Gleason Dale Goodney

47、 Randall Groves Ajit Gwal Daryl Harmon Hamidreza Heidarisafa Lee Herron Werner Hoelzl David A. Horvath Greg Hostetter Peter Hung Randy Jamison Paul Johnson James Jones Piotr Karocki Rameshchandra Ketharaju Tanuj Khandelwal Chad Kiger Joseph L. Koepfinger Robert Konnik G. Lang John MacDonald Omar Maz

48、zoni John Merando Kimberly Mosley Michael S. Newman James Parello Iulian Profir Robert Queenan Ted Riccio Fredrick Roy Stephen Sandberg Bartien Sayogo Glen Schinzel Sara Seamans Gil Shultz James E. Smith Robert Stark Rebecca L. Steinman S. Thamilarasan James Thompson Michael Tucker John Vergis James

49、 Wilson Thomas Worrell Larry YonceWhen the IEEE-SA Standards Board approved this standard on 25 March 2010, it had the following membership: Robert M. Grow, Chair Richard H. Hullet, Vice chair Steve M. Mills, Past Chair Judith Gorman, Secretary Karen Bartleson Victor Berman Ted Burse Clint Chaplin Andy Drozd Alexander Gelman Jim Hughes Young Kyun Kim Joseph L. Koepfinger* John Kulick David J. Law Hung Ling Oleg Logvinov Ted Olsen Ronald C. Petersen Thomas Prevost Jon Walter Rosdahl Sam Sciacca Mike Seavey Curtis Siller Don Wright *Member Emeritu