1、IEEE Std 649-2006(Revision of IEEE Std 649-1991)IEEE Standard for Qualifying Class 1EMotor Control Centers for NuclearPower Generating StationsI E E E3 Park Avenue New York, NY10016-5997, USA29 December 2006IEEE Power Engineering SocietySponsored by theNuclear Power Engineering CommitteeIEEE Std 649
2、-2006(R2011) (Revision of IEEE Std 649-1991) IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of the IEEE Power Engineering Society Approved 15 September 2006 Reaffirmed 16 June 2011 IEEE-SA Standards Board
3、Approved 1 February 2007 Reaffirmed 16 April 2012 American National Standards Institute Abstract: The basic principles, requirements, and methods for qualifying Class 1E motor control centers for both harsh and mild environment applications in nuclear power generating stations are described. In addi
4、tion to defining specific qualification requirements for Class 1E motor control centers and their components in accordance with the more general qualification requirements of IEEE Std 323-2003, this standard is intended to provide guidance in establishing a qualification program for demonstrating th
5、e adequacy of Class 1E motor control centers in nuclear power generating station applications. Keywords: aging, analysis, class 1E, environmental qualification, harsh environment, mcc, mild environment, motor control center, operating experience, operational aging, qualification, qualified life, sei
6、smic, test _ The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2006 by the Institute of Electrical and Electronics Engineers, Inc. All rights reserved. Published 29 December 2006. Printed in the United States of America. IEEE is a regis
7、tered 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. Introduction This introduction is not part of IEEE Std 649-2006, IEEE Standard for Qualifying Cla
8、ss 1E Motor Control Centers for Nuclear Power Generating Stations. The requirements for qualification of Class 1E equipment are included in the United States Code of Federal Regulations. Among them are the following: a) b) c) 10CFR Part 50, Appendix B, Quality Assurance Criteria, IIIDesign Control.
9、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 the performance of a suitable testing program. 10CFR Part 50, Appendix B, Quality Assurance Criteria, XITest Control
10、. This requires that a test program be established and that testing be performed under suitable environmental conditions. These requirements, at least in part, can be met by suitable qualification. 10CFR Part 50, Section 50.49, Environmental Qualification of Electric Equipment Important to Safety. T
11、his rule codifies the qualification requirements for certain equipment, located in a harsh environment, that is important to safety. Information pertinent to developing designs and their qualification requirements can be found in the above mentioned documents and in 10CFR Part 50, Appendix A, Genera
12、l Design Criteria 1, 2, 4, and 23. Other governing bodies in the international community also have similar documents relating to qualification of nuclear plant equipment and should be consulted for additional guidance, as deemed appropriate. IEEE Std 323-2003 provides general guidance for demonstrat
13、ing and documenting the adequacy of electric equipment used in Class 1E systems. IEEE Std 649-2006 has been revised to deal specifically with motor control center equipment, using IEEE Std 323-2003 as the parent document for guidance. Adherence to this standard may not assure public health and safet
14、y because it is the integrated performance of the structures, fluid systems, instrumentation systems, and electrical systems of the station that limits the consequence of accidents. Each user is responsible for assuring that this standard, if used, is pertinent to his or her application. Class 1E eq
15、uipment used in nuclear power generating stations must meet its safety functional requirements throughout its installed life. This is accomplished by a thorough program of quality assurance, design, qualification, production, transportation, storage, installation, maintenance, periodic testing, and
16、surveillance. This standard is for the qualification portion of the program. The user should note that while this standard covers Class 1E equipment qualification, other documents, such as IEEE Std 603-1998, also require system integrity. Therefore, attention needs to be given to equipment performan
17、ce specifications and interfaces to ensure their adequate performance in a system. The nuclear power generating station safety analysis, in part, considers the station and its safety system design in terms of postulated service conditions. Inherent to each such analysis are two presumptions that mus
18、t be evaluated. First, designs must be such that equipment can perform designated safety functions in postulated service environments. Second, in-service aging must not degrade Class 1E equipment to the point where it cannot perform designated safety functions when required. iv Copyright 2006 IEEE.
19、All rights reserved. Production testing, normal service testing, and surveillance may not be able to determine whether the equipment is vulnerable to failure, either as a result of inadequate design or in-service time and environment, because of the special environmental stresses associated with som
20、e postulated service conditions included in the station safety analysis. Under these circumstances, common mode failure of redundant Class 1E equipment might occur at the time its safety function(s) is required. It is the fundamental role of qualification to provide reasonable assurance, with due re
21、cognition given to the established technology, that common mode failures due to design, manufacture, and age do not exist, and that the design and manufacture are adequate to permit the equipment to perform its safety function(s) during postulated service conditions. Synergistic effects and ionizing
22、 radiation dose-rate effects have become a concern within the industry and remain the subject of continuing research programs. Preliminary results indicate that synergistic effects can be either positive or negative. Such effects should be considered in developing a qualification program. The effect
23、s may be significant due to the inclusion of solid-state electronic components into motor control centers control schemes. Detrimental affects on the electronics may occur at radiation levels that have historically been considered a mild environment. Motor control centers qualified in accordance wit
24、h this standard will meet the requirements of IEEE Std 323-2003, which provide the basic principles for design qualification for all safety systems equipment for use in nuclear power generating stations. This revision to IEEE Std 649-1991 was made to update the standard to address industry concerns
25、with solid-state electronics and to update references and requirements of other IEEE standards. This standard defines requirements to qualify motor control centers and their components located in all areas of the nuclear power generating station, including harsh and mild environmental areas. At this
26、 time, it appears that the seismic event is the only design basis event with potential for common mode failure in mild environments; however, other environmental service conditions may also be contributors. Particular attention should be paid to the effects of radiation on solid-state electronics an
27、d the affects of EMI/RFI fields on the equipment. 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/updates/errata/index.html. Users are encouraged to check this URL for errata periodically. Interpreta
28、tions 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 require use of subject matter covered by patent rights. By publication of this standar
29、d, 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 which a license may be required to implement an IEEE standard or for conducting inquiries into the lega
30、l validity or scope of those patents that are brought to its attention. v Copyright 2006 IEEE. All rights reserved. Participants At the time this standard was completed, the Working Group on Motor Control Centers (SC2.14) had the following membership: Robert L. Francis, Chair Satish K. Aggarwal Anup
31、 K. Behera Thomas N. Brewington James M. Dean Quang H. Duong Sushant Kapur Daniel R. Mikow James Parello Randy Reynolds The Subcommittee on Qualification (SC2) of the Nuclear Power Engineering Committee that recommended approval of this standard had the following membership: Satish K. Aggarwal, Chai
32、r Patrick Gove, Secretary Bohumil Bartonicek Paul D. Baughman Anup K. Behera Steven D. Benson Brij Bharteey Thomas N. Brewington Nissen M. Burstein Steve Casadevall Suresh Channarasappa Garry V. Chapman Javier A. Chicote Sun Yeong Choi Choon-Hoon Chung James M. Dean Liviu Nicolae Delcea Dennis E. De
33、llinger Philip DiBenedetto Michael Dougherty Quang H. Duong Frank Drumm Yasutaka Eguchi Walter Emerson Wells D. Fargo Artur J. Faya Robert L. Francis James F. Gleason William L. Hadovski Hideo Harada Peter Helander Thomas R. Hencey III Jerrell C. Henley Dirk C. Hopp David A. Horvath Yao-Tung Hsu In-
34、Koo Hwang Craig S. Irish Serena A. Jagtiani Sushant Kapur Mohsin Khan Frank W. Kloer Henry Leung Bruce M. Lory P. G. McQuillan Daniel R. Mikow Todd Mitton Asif Mohiuddin Edward Mohtashemi Carole Monchy-Leroy Bill Newell James Parello Janez Pavsek Jan S. Pirrong Daniel J. Pomerening Robert Queenan Ed
35、ward L. Quinn John M. Richards Frederick L. Roy Steve Sandberg Glen E. Schinzel Roderick Simms Kjell Spang Richard G. Stark Hirotsugu Suzuki Marek Tengler Marco Van Uffelen Laszlo Varga Carl Weber John Wheless John White Toni Wittamore Richard T. Wood Toshio Yamamoto vi Copyright 2006 IEEE. All righ
36、ts reserved. At the time this standard was approved, the Nuclear Power Engineering Committee (NPEC) had the following membership: John Disosway, Chair John D. MacDonald, Secretary Satish K. Aggarwal Ijaz Ahmad George Attarian George A. Ballassi Farouk D. Baxter Brij M. Bharteey Wesley W. Bowers Dani
37、el F. Brosnan Nissen M. Burstein Robert C. Carruth John P. Carter Stephen Fleger Robert J. Fletcher Robert Fuld James F. Gleason Dale T. Goodney Britton P. Grim William L. Hadovski David A. Horvath Paul R. Johnson, Jr. Harvey C. Leake J. Scott Malcolm Alexander Marion Michael H. Miller Gerald L. Nic
38、ely Roger D. Parker James Parello Glen E. Schinzel Neil P. Smith James E. Stoner James E. Thomas John Waclo John White Paul L. Yanosy David J. Zaprazny The following members of the balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. Satish K
39、. Aggarwal Munnu Bajpai George A. Ballassi William G. Bloethe Wesley W. Bowers Thomas N. Brewington Daniel F. Brosnan Nissen M. Burstein Robert C. Carruth John P. Carter Suresh Channarasappa Weijen Chen Mark S. Clark Tommy P. Cooper Dennis E. Dellinger John Disosway Gary R. Engmann Wells D. Fargo Ro
40、bert L. Francis James F. Gleason L. Gradin Ron K. Greenthaler Randall C. Groves Ajit K. Gwal Hamidreza Heidarisafa Gary A. Heuston David A. Horvath Dennis Horwitz Paul R. Johnson, Jr. James H. Jones J. L. Koepfinger Robert L. Konnik G. L. Luri John D. MacDonald John E. Merando, Jr. Gary L. Michel Ki
41、mberly Y. Mosley Michael S. Newman James Parello Ted Riccio Michael A. Roberts Frederick L. Roy Bartien Sayogo David R. Smith John H. Taylor S. Thamilarasan James E. Thomas James W. Wilson, Jr. vii Copyright 2006 IEEE. All rights reserved. When the IEEE-SA Standards Board approved this standard on 1
42、5 September 2006, it had the following membership: Steve M. Mills, Chair Richard H. Hulett, Vice Chair Judith Gorman, Secretary Mark D. Bowman Dennis B. Brophy Joseph Bruder Richard Cox Bob Davis Julian Forster* Joanna N. Guenin Mark S. Halpin Raymond Hapeman William B. Hopf Lowell G. Johnson Herman
43、 Koch Joseph L. Koepfinger* David J. Law Daleep C. Mohla Paul Nikolich T. W. Olsen Glenn Parsons Ronald C. Petersen Gary S. Robinson Frank Stone Malcolm V. Thaden Richard L. Townsend Joe D. Watson Howard L. Wolfman *Member Emeritus Also included are the following nonvoting IEEE-SA Standards Board li
44、aisons: Satish K. Aggarwal, NRC Representative Richard DeBlasio, DOE Representative Alan H. Cookson, NIST Representative Jennie Steinhagen IEEE Standards Project Editor Matthew Ceglia IEEE Standards Program Manager, Technical Program Development viii Copyright 2006 IEEE. All rights reserved. Content
45、s 1. Overview 1 1.1 Scope . 1 1.2 Purpose 1 2. Normative references 1 3. Definitions 2 4. Other information . 2 4.1 General 2 5. Principles of qualification. 3 5.1 General 3 5.2 Specific application to MCCs 4 6. Environmental conditions. 7 6.1 General 7 7. Margin 7 7.1 General 7 8. Equipment specifi
46、cation . 8 8.1 General 8 9. Qualification procedures 12 9.1 General 12 9.2 Inspection 13 9.3 Baseline data measurement 13 9.4 Aging . 13 9.5 Seismic qualification . 18 9.6 Harsh environment events . 22 9.7 Final functional tests and inspection 23 9.8 Determination of qualification. 23 9.9 Extension
47、of qualified life . 24 10. Modifications 24 10.1 Modifications during qualification 24 10.2 Modifications after qualification . 24 ix Copyright 2006 IEEE. All rights reserved. 11. Documentation . 24 11.1 General 24 11.2 Equipment qualification data. 25 11.3 Supporting documentation. 26 Annex A (info
48、rmative) Use of experience data in seismic qualification of motor control centers. 27 Annex B (informative) Glossary 28 Annex C (informative) Typical functions of motor control centers . 30 x Copyright 2006 IEEE. All rights reserved. IEEE Standard for Qualifying Class 1E Motor Control Centers for Nu
49、clear Power Generating Stations 1. 1.11.2a) b) 2. Overview Scope This standard describes the basic principles, requirements, and methods for qualifying Class 1E motor control centers for both harsh and mild environment applications in nuclear power generating stations. Purpose The purpose of this standard is to: Define specific qualification requirements for Class 1E motor control centers and their components in accordance with the more general qualification requirements of IEEE Std 323-20031, 2and IEEE Std 344-2004. Provide guidance in establi
