1、g3g3g3IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations IEEE Power and Energy Society SPg3ponsored by the ower System Relaying Committee IEEE 3 Park Avenue New York, NY 10016-5997 USA 29 October 2010IEEE Std C37.105-2010 (Revision of IEEE S
2、td C37.105-1987) IEEE Std C37.105-2010 (Revision of IEEE Std C37.105-1987) IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations Sponsor Power System Relaying Committee of the IEEE Power and Energy Society Approved 30 September 2010 IEEE-SA Sta
3、ndards Board Approved 19 July 2011 American National Standards Institute Abstract: Basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries in nuclear power generating stations including digital and analog devices, but excluding devices located inside the
4、 primary containment, are covered. Keywords: aging, auxiliaries, Class 1E, margin, nuclear, power plants, qualifying, radiation, relays, seismic, tests, thermal The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2010 by the Institute of
5、Electrical and Electronics Engineers, Inc. All rights reserved. Published 29 October 2010. 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
6、 obtained through the Copyright Clearance Center. iv Copyright 2010 IEEE. All rights reserved. Introduction This introduction is not part of IEEE Std C37.105-2010, IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations. IEEE Std 323a provides ge
7、neral guidance for demonstrating and documenting the adequacy of electrical equipment used in all Class 1E and interface systems. This standard has been prepared to deal specifically with protective relays and auxiliary equipment, using IEEE Std 323 as the parent document for guidance. Relays and au
8、xiliary equipment shall meet the applicable requirements of IEEE Std C37.90, IEEE Std C37.90.1, IEEE Std C37.90.2, and IEEE Std C37.90.3. IEEE Std 7-4.3.2 shall be used to address the use of Digital computer software and firmware used in all safety systems for nuclear generating stations. Safety sys
9、tems equipment in nuclear power generating stations must meet or exceed its performance requirements throughout its installed life. This is accomplished by a program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for
10、the design qualification portion of the program only. The nuclear power generating station safety analysis, in part, considers the station and its safety system design in terms of a set of postulated service conditions. Inherent to each such analysis are two requirements that must be evaluated to as
11、sure overall technical validity. First, designs must be such that equipment is capable of actually performing designated safety functions in postulated service environments. Second, in service aging must not degrade safety systems equipment from its original design condition to the point where it ca
12、nnot perform designated safety functions, when required. The special environmental stresses associated with some postulated service conditions promote the possibility that production testing, normal service testing, and surveillance may not be able to determine whether the equipment is vulnerable to
13、 failure, either as a result of inadequate design or aging. Under these circumstances, simultaneous failure of redundant safety equipment might occur just at the time safety functions are required. It is the fundamental role of qualification to provide reasonable assurance that design and age relate
14、d common failure modes do not exist and that the equipment design is adequate to permit the equipment to perform its safety function during postulated service conditions. Adherence to this standard alone may not suffice for assuring public health and safety since it is the integrated performance of
15、the structures, fluid systems, instrumentation systems, and electric systems of the generating station that establishes safe operating conditions. The user has the responsibility to establish that this standard is pertinent to the particular requirements of the generating station of concern and that
16、 the integrated performance of the station is adequate. IEEE Std C37.105 was issued in 1987 and reaffirmed in December 1999. This revision incorporates current nuclear industry practices for qualification of protective relays and auxiliaries. Notice to users Laws and regulations Users of these docum
17、ents 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 standard are responsible for observing or referring to the applicable regulatory requirements. IEEE does n
18、ot, 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. aInformation on references can be found in Clause 2. Copyrights This document is copyrighted by the IEEE. It is made available for a wi
19、de 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 and methods. By making this document available for use and adoption by public authorities and pri
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22、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 information about the IEEE Standards Association or the IEEE standards development process, visi
23、t 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.html. Users are encouraged to check this URL for errata periodically. Interpretations Current i
24、nterpretations 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 require use of subject matter covered by patent rights. By publication of this standard, no position
25、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, for conducting inquiries into the legal validity or scope of Patents Claims or determining whether
26、 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 expressly advised that determination of the validity of any patent rights, and the risk of infri
27、ngement of such rights, is entirely their own responsibility. Further information may be obtained from the IEEE Standards Association. v Copyright 2010 IEEE. All rights reserved. vi Copyright 2010 IEEE. All rights reserved. Participants At the time this standard was submitted to the IEEE-SA Standard
28、s Board for approval, the I9 Working Group had the following membership: Roy Ball, Chair Sahib Usman, Vice Chair Mannu Bajpai Gustavo Brunello Jeff Burnworth James D. Huddleston Steve Kunsman Marie Nemier Mario M. Ranieri R. Vittal Rebbapragada The following members of the individual balloting commi
29、ttee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. William Ackerman Munnu Bajpai Michael Baldwin Roy Ball Farouk Baxter Robert Beresh Wesley Bowers Daniel Brosnan Gustavo Brunello Jeff Burnworth John W. Chadwick, Jr. Garry Chapman Mason Clark R. Daubert S
30、urin Dureja Matthew Davis Paul Drum Doug Edwards Gary Engmann Rabiz Foda Jay Forster Frank Gerleve Britton Grim Roger Hedding Jerry Hohn James D. Huddleston Jose Jarque Joseph L. Koepfinger Steve Kunsman Jason Lin Albert Livshitz Gregory Luri Jesus Martinez Subinoy Mazumdar Jeffrey McElray Mark McGr
31、anaghan John Merando Gary Michel Marie Nemier James Parello Mario M. Ranieri R. Vittal Rebbapragada Mohindar S. Sachdev Tarlochan Sidhu H. Jin Sim James Stoner Shanmugan Thamilarasan Eric Udren Sahib Usman James Wilson Murty Yalla Karl ZimmermanWhen the IEEE-SA Standards Board approved this amendmen
32、t on 30 September 2010, it had the following membership: Robert M. Grow, Chair Richard H. Hulett, 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 Kuli
33、ck 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 Emeritus Also included are the following nonvoting IEEE-SA Standards Board liaisons: Satish Aggarwal, NRC Representative Richard DeBlasio, D
34、OE Representative Michael Janezic, NIST Representative Catherine Berger IEEE Standards Project Editor Matthew Ceglia IEEE Standards Program Manager, Technical Program Development vi Copyright 2010 IEEE. All rights reserved. Contents 1. Overview 1133346899910101212121313131414141414151515151516161616
35、16161717171718181.1 Scope . 1.2 Purpose 2 2. Normative references 2 3. Definitions 4. Qualification requirements . 5. Principles of qualification. 5.1 Application to protective relays and auxiliaries. 5.1.1 Identification of equipment and its application 5.1.2 Qualification program 5.2 Alternative m
36、ethods. 6. Qualification procedure 6.1 Testing alternative and test sequence. 6.1.1 Inspection and baseline data measurement 9 6.1.2 Performance evaluation 6.1.3 Aging . 6.1.3.1 Radiation aging tests 6.1.3.2 Operational aging test. 6.1.3.3 Thermal aging tests 6.1.4 Seismic testing . 6.1.5 Final oper
37、ational test 6.2 Analysis alternative . 6.2.1 Performance evaluation analysis 6.2.2 Aging analysis 6.2.2.1 Radiation aging analysis. 6.2.2.2 Operational aging analysis . 6.2.2.3 Thermal aging analysis. 6.2.3 Seismic analysis. 6.3 Electromechanical relays. 6.4 Static relays . 6.5 Microprocessor-based
38、 relays . 6.6 Switches. 6.6.1 Not applicable to switches . 6.6.2 Applicable to switches . 6.7 Auxiliary devices. 6.8 Other events. 6.9 Determination of qualification. 6.9.1 Failure during qualification 7. Environmental conditions. 8. Margin 9. Modifications 9.1 Modifications during qualification 9.2
39、 Modifications after qualification . 10. Documentation . vii Copyright 2010 IEEE. All rights reserved. 10.1 General 181818181818191919192010.2 Equipment qualification data. 10.2.1 Service conditions 10.2.2 Specific feature(s) 10.2.3 Qualification plan. 10.2.4 Test report 10.3 Supporting documentatio
40、n. 10.3.1 Operating experience data 10.3.2 Analysis . 10.3.3 Extrapolation Annex A (informative) Bibliography . viii Copyright 2010 IEEE. All rights reserved. IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations IMPORTANT NOTICE: This standard
41、 is not intended to ensure safety, security, health, or environmental protection. Implementers of the standard are responsible for determining appropriate safety, security, environmental, and health practices or regulatory requirements. This IEEE document is made available for use subject to importa
42、nt 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 and Disclaimers Concerning IEEE Documents.” They can also be obtained on request from IEEE or viewed at http
43、:/standards.ieee.org/IPR/disclaimers.html. 1. Overview This standard describes the basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries for applications in nuclear power generating stations. When properly employed it can be used to demonstrate the des
44、ign adequacy of such equipment under normal, abnormal, design basis event (DBE), and post=design basis event (post-DBE) conditions in accordance with IEEE Std 323.1Static relays that utilize analog and digital electronic components require additional considerations and applicable requirements of IEE
45、E Std C37.90, IEEE Std C37.90.1, IEEE Std C37.90.2, and IEEE Std C37.90.3. Microprocessor-based relays may require additional consideration of software and firmware qualification to comply with the requirements of IEEE Std 7-4.3.2, IEEE Std 1012, and IEEE Std 1028. The qualification procedure presen
46、ted is generic in nature. Other methods may be used at the discretion of the qualifier, provided the basic precepts of IEEE Std 323 are satisfied. 1.1 Scope This standard covers qualification of Class 1E protective relays and auxiliaries to be used outside the primary containment in the nuclear powe
47、r generating stations. Protective relays and auxiliaries located inside the primary containment in a nuclear power generating station present special conditions beyond the scope of this document. 1Information on references can be found in Clause 2. 1 Copyright 2010 IEEE. All rights reserved. IEEE St
48、d C37.105-2010 IEEE Standard for Qualifying Class IE Protective Relays and Auxiliaries for Nuclear Power Generating Stations 1.2 Purpose The purpose of this standard is to a) Define specific qualification methods for Class 1E protective relays and auxiliaries in accordance with the more general qual
49、ification requirements of IEEE Std 323. b) Provide guidance in establishing a program for demonstrating the design adequacy of Class 1E protective relays and auxiliaries in nuclear power generating stations applications. 2. Normative references The following referenced documents are indispensable for the application of this document (i.e., they must be understood and used, so each referenced document is cited in text and its relationship to this document is explained). For dated references, only the edition cited applies. For undated references, th
