1、 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations IEEE Power and Energy Society SNponsored by the uclear Power Engineering Committee IEEE 3 Park Avenue New York, NY 10016-5997 USA 10 November 2010IEEE Std 497-2010(Revision of IEEE Std 497-2002)IEEE
2、 Std 497-2010 (Revision of IEEE Std 497-2002) IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of the IEEE Power and Energy Society Approved 30 September 2010 IEEE-SA Standards Board Approved 7 June 2011
3、American National Standards Institute Abstract: Criteria are established in this standard for variable selection, performance, design, and qualification of accident monitoring instrumentation, and include requirements for display alternatives for accident monitoring instrumentation, documentation of
4、 design bases, and use of portable instrumentation. Keywords: accident monitoring, display criteria, selection criteria, type variables The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2010 by the Institute of Electrical and Electronic
5、s Engineers, Inc. All rights reserved. Published 10 November 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 obtained through the Co
6、pyright Clearance Center. iv Copyright 2010 IEEE. All rights reserved. Introduction This introduction is not part of IEEE Std 497-2010, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations. History This standard evolved from IEEE Std 497-2002 B5.aIt re
7、presents a continued effort by the IEEE to support the specification, design, and implementation of accident monitoring instrumentation of nuclear power generating stations. IEEE Std 497-2002 B5 was developed to provide criteria for advanced instrumentation system designs and design modifications ba
8、sed on modern digital technology. It marked a clear path forward for the application of new technology. Though still maintaining applicability to existing systems, IEEE Std 497-2002 B5 also marked a departure from other historically related standards and guidance. It was the working groups intention
9、 that the criteria of this standard address the variety of possible accident monitoring channel configurations that current technology affords. It was also the working groups intention to address the control room displays of information using computer generated displays and calculated values. The cr
10、iteria presented in this standard provide guidance in this area without limiting the types of displays that can be made available to the operator. Although written primarily for new plant designs, existing plants may also use the guidance and applicable criteria in this standard. The use of applicab
11、le plant procedures to determine the requirements of the accident monitoring instrumentation provides the necessary flexibility for useful design criteria. This standard can be used to address the necessary changes to the plant configuration that occur over the operating life of any plant. Applicati
12、on The working group was requested to consider expanding the scope of IEEE Std 497 to include “nuclear facilities.” The working group decided not to pursue this change for the following two primary reasons: 1) Such a change would potentially include a wide range of “nuclear facilities.” The working
13、group believes that it would be extremely difficult to accommodate the diverse licensing bases, accident analyses, operating procedures, etc., for those facilities and still have the standard pertinent to new and operating nuclear power generating stations. Some nuclear facilities, such as uranium e
14、nrichment facilities, require no accident monitoring system because criticality accidents are precluded. 2) The focus of accident monitoring standards including ANS 4.5 B2, IEEE Std 497-2002 B5, and Regulatory Guide (RG) 1.97 B8 has always been on nuclear power reactors. RG 1.97 Revision 4 is design
15、ed to work hand in hand with IEEE Std 497-2002 B5, with a minimal number of exceptions that are identified as regulatory positions. If the next revision of IEEE Std 497 was expanded to include all types of nuclear facilities, a corresponding revision of RG 1.97 would need to include numerous excepti
16、ons for the criteria related to “nuclear facilities” other than power generating stations. This approach was not considered desirable for the industry. aThe numbers in brackets correspond to those of the bibliography in Annex C. Revision summary Since IEEE Std 497 was approved in 2002 the working gr
17、oup has compiled a list of more than 40 issues from user feedback and other sources to be addressed in this revision to the standard. The working group has considered and incorporated appropriate changes related to the following significant items: Latest developments and industry initiatives in the
18、application of digital technology. The regulatory positions and lessons learned identified during the RG 1.97, Revision 4 endoresment of IEEE Std 497-2002 B5. Expansion of the standards applicability to include operating nuclear power generating stations desiring to perform design modifications, in
19、addition to new plant designs. Consistency with referenced IEEE standards and IEEE standard definitions. Terminology that is instrument and control technology neutral (e.g., changed “micro-processor” to “computer”). Terminology usage consistent with both Pressurized Water Reactors and Boiling Water
20、Reactors (e.g., “safety function” rather than “critical safety function” and revising the definition of contingency action). Human system interface terminology revised to include “spatially dedicated continuously visible” and “accessible on demand.” Contents of Corrigendum 1 to IEEE Std 497-2002 B5
21、and comments received during the 2008 standard reaffirmation ballot. Other minor editorial improvements throughout the standard were also incorporated. Future work As the use of digital technology in the nuclear plant is a dynamic area of design, the working group intends to keep this area as an ong
22、oing future task. Another area that the group believes should be considered in a future revision to the standard is how to adopt risk informed techniques into accident monitoring criteria. Notice to users Laws and regulations Users of these documents should consult all applicable laws and regulation
23、s. 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 not, by the publication of its standards, intend to urg
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25、and use in private self-regulation, standardization, and the promotion of engineering practices and methods. By making this v Copyright 2010 IEEE. All rights reserved. document available for use and adoption by public authorities and private users, the IEEE does not waive any rights in copyright to
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29、ta, 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 interpretations can be accessed at the following URL: http:/stan
30、dards.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 is taken with respect to the existence or validity of any paten
31、t 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 any licensing terms or conditions provided in connection with
32、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 infringement of such rights, is entirely their own responsibility. F
33、urther information may be obtained from the IEEE Standards Association. vi Copyright 2010 IEEE. All rights reserved. Participants At the time this standard was submitted to the IEEE-SA Standards Board for approval, the Accident Monitoring Instrumentation Working Group had the following membership: G
34、reg M Hostetter, Chair Daryl Harmon, Vice Chair Dave Horvath Alex Klemptner Barry Marcus Iffti Rana Stephen Wyman At the time this standard was submitted to the IEEE-SA Standards Board for approval, the Subcommittee 6 (Safety Related Systems) under the Nuclear Power Engineering Committee had the fol
35、lowing membership: Daryl Harmon, Chair Mark Santschi, Vice Chair Ijaz Ahmed Royce Beacom David Curbo John Disosway Patrick Grove Ron Greenthaler Dave Herrell Dave Horvath Greg Hostetter Randy Jamison Ron Jarrett Rick Kendall Alex Klemptner Paul Loeser Barry Marcus Mike Miller Warren Odess-Gillet Iff
36、ti Rana Mark Stofko David Theriault Masafumi Utsumi Mark Walsh Mike Waterman Stephen Wyman Paul Yanosy Dave Zaprazny Deanna Zhug At the time this standard was submitted to the IEEE-SA Standards Board for approval, the Nuclear Power Engineering Committee had the following membership: John MacDonald,
37、Chair Satish Aggarwal, Vice Chair George Ballassi, Secretary Ijaz Ahmad George Attarian Farouk Baxter Mark Bowman Daniel Brosnan Nissen Burstein Robert Carruth John Carter John Disosway Dennis Dellinger Stephen Fleger Robert Fletcher Robert Fuld James Gleason Dale Goodney Daryl Harmon Dirk Hopp Davi
38、d Horvath Paul Johnson Thomas Koshy Harvey Leake Scott Malcolm Alexander Marion Michael Miller James Parello Mansoor Sanwarwalla Glen Schinzel J. E. Stoner James Thomas Marek Tengler Paul Yanosy David Zaprazny The following members of the individual balloting committee voted on this standard. Ballot
39、ers may have voted for approval, disapproval, or abstention. William J. Ackerman Satish Aggarwal Stan Arnot George Ballassi H. Stephen Berger Wesley Bowers Daniel Brosnan Nissen Burstein Robert Carruth Suresh Channarasappa Mark Clark Tom Crawford Paul Croll John Disosway Michael Dougherty vii Copyri
40、ght 2010 IEEE. All rights reserved. viii Copyright 2010 IEEE. All rights reserved. Gary Engmann Wells Fargo Stephen Fleger Rabiz Foda James Gleason Ron Greenthaler Randall Groves John Harauz Daryl Harmon Wolfgang Haverkamp David Herrell Werner Hoelzl David Horvath Greg M. Hostetter Peter Hung Randy
41、Jamison Paul Johnson James Jones Jason Karns Piotr Karocki Joseph L. Koepfinger Robert Konnik G. Lang Charles Lennon G. Luri Omar Mazzoni Michael S. Newman Ted Riccio Bartien Sayogo Glen Schinzel Gil Shultz James Smith Rebecca Steinman Gary Stoedter S. Thamilarasan James Thompson Michael Tucker John
42、 Vergis Michael Waterman Yvonne Williams Paul Yanosy David Zaprazny When the IEEE-SA Standards Board approved this standard 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 V
43、ictor 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 Emeritus Also incl
44、uded are the following nonvoting IEEE-SA Standards Board liaisons: Satish Aggarwal, NRC Representative Richard DeBlasio, DOE Representative Michael Janezic, NIST Representative Catherine Berger IEEE Standards Project Editor Matthew J. Ceglia IEEE Standards Program Manager, Technical Program Developm
45、ent ix Copyright 2010 IEEE. All rights reserved. Contents 1. Overview 1 1.1 Scope . 1 1.2 Purpose 1 1.3 Application 1 2. Normative references 2 3. Definitions 3 4. Selection criteria. 5 4.1 Type A variables 5 4.2 Type B variables 6 4.3 Type C variables 6 4.4 Type D variables 6 4.5 Type E variables 7
46、 4.6 Documentation of selection criteria. 7 5. Performance criteria . 9 5.1 Range. 9 5.2 Accuracy 9 5.3 Response time 9 5.4 Required operating time 9 5.5 Reliability 10 5.6 Documentation of performance criteria. 10 6. Design criteria 10 6.1 Single failure 10 6.2 Common cause failure . 11 6.3 Indepen
47、dence and separation. 11 6.4 Isolation . 12 6.5 Information ambiguity. 12 6.6 Power supply . 12 6.7 Calibration . 13 6.8 Testability 13 6.9 Direct measurement. 13 6.10 Control of access . 14 6.11 Maintenance and repair 14 6.12 Minimizing measurements. 14 6.13 Auxiliary supporting features 14 6.14 Po
48、rtable instruments 14 6.15 Documentation of design criteria. 14 7. Qualification criteria. 15 7.1 Type A variables 15 7.2 Type B variables 15 7.3 Type C variables 15 7.4 Type D variables 15 7.5 Type E variables 16 7.6 Portable instruments 16 7.7 Operating time . 16 7.8 Documentation of qualification
49、 criteria. 16 x Copyright 2010 IEEE. All rights reserved. 8. Display criteria . 16 8.1 Display characteristics. 16 8.2 Trend or rate information. 17 8.3 Display identification 17 8.4 Type of monitoring channel display 17 8.5 Display location. 17 8.6 Information ambiguity. 18 8.7 Recording 18 8.8 Digital display signal validation 18 8.9 Documentation of display criteria 18 9. Quality assurance 18 Annex A (informative) Accident monitoring instrument channel accuracy. 19 A.1 Introduction 19 A.2 Accuracy requirement groupings according to
