IEEE 497-2016 en Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations《核电站事故监测仪器装置标准》.pdf

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1、 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations Sponsored by the Nuclear Power Engineering Committee IEEE 3 Park Avenue New York, NY 10016-5997 USA IEEE Power and Energy Society IEEE Std 497-2016 (Revision of IEEE Std 497-2010) IEEE Std 497-2016

2、(Revision of IEEE Std 497-2010) 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 15 May 2016 IEEE-SA Standards Board Abstract: Established in this standard ar

3、e criteria for variable selection, performance, design, and qualification of accident monitoring instrumentation for anticipated operational, design basis events and severe accidents. Keywords: accident monitoring, design criteria, display criteria, IEEE 497, performance criteria, selection criteria

4、, severe accidents, type variables The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2016 by The Institute of Electrical and Electronics Engineers, Inc. All rights reserved. Published 29 July 2016. Printed in the United States of Americ

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33、of such rights, is entirely their own responsibility. Further information may be obtained from the IEEE Standards Association. 5 Participants At the time this IEEE standard was completed, the Accident Monitoring Instrumentation Working Group had the following membership: Greg M. Hostetter, Chair Dar

34、yl Harmon, Vice Chair Michiaki Akiyama Jeri Chadwick Alexander Duchac James Gleason Takeshi Ikeuchi Gary Johnson Jason Karns Alex Klemptner Wolfgang Koenig Ifti Rana Yumi Sato Deirdre Spaulding-Yeoman Steve Wyman The following members of the individual balloting committee voted on this standard. Bal

35、loters may have voted for approval, disapproval, or abstention. William Ackerman Satish Aggarwal George Ballassi Royce Beacom William Bloethe Thomas Brewington Daniel Brosnan Nissen Burstein Robert Carruth Suresh Channarasappa Weijen Chen Tom Crawford John Disosway Stephen Fleger James Gleason Randa

36、ll Groves Ajit Gwal Daryl Harmon Hamidreza Heidarisafa Raymond Herb David Herrell Werner Hoelzl David Horvath Greg M. Hostetter Gary Johnson Piotr Karocki Robert Konnik Thomas Koshy G. Lang Jang-Soo Lee William Lumpkins John Macdonald Phillip McClure Kirklyn Melson Michael Newman Warren Odess-Gillet

37、t Jan Pirrong Robert Queenan Ted Riccio Bartien Sayogo Deirdre Spaulding-Yeoman Rebecca Steinman John Stevens John Vergis John White Yvonne Williams Shuhui Zhang When the IEEE-SA Standards Board approved this standard on 15 May 2016, it had the following membership: Jean-Philippe Faure, Chair Ted Bu

38、rse, Vice Chair John Kulick, Past Chair Konstantinos Karachalios, Secretary Chuck Adams Masayuki Ariyoshi Stephen Dukes Jianbin Fan J. Travis Griffith Gary Hoffman Ronald W. Hotchkiss Michael Janezic Joseph L. Koepfinger* Hung Ling Kevin Lu Annette D. Reilly Gary Robinson Mehmet Ulema Yingli Wen Phi

39、lip Winston Howard Wolfman Don Wright Yu Yuan Daidi Zhong *Member Emeritus 6 Copyright 2016 IEEE. All rights reserved. Introduction This introduction is not part of IEEE Std 497-2016, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations. History This s

40、tandard evolved from IEEE Std 497-2010 B41. It represents a continued effort by IEEE to support the specification, design, and implementation of accident monitoring instrumentation of nuclear power generating stations. IEEE Std 497-2010 B4 was developed to provide criteria for advanced instrumentati

41、on system designs and design modifications based on modern digital technology. It marked a clear path forward for the application of new technology. Though still maintaining applicability to existing systems, this version of IEEE Std 497 provides more current guidance based on historically related s

42、tandards and guidance. It was the working groups intention 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 display of information using computer gene

43、rated displays and calculated values. The criteria presented in this standard provide guidance in this area without limiting the types of displays that can be made available to accident management personnel. Although written primarily for new plant designs, existing plants may also use the guidance

44、and applicable criteria in this standard. The use of applicable 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 help address the necessary changes to the plant config

45、uration that occur over the operating life of any plant. Historically the standard addressed accident monitoring instrumentation used for anticipated operating occurrences (AOOs) and design basis events (DBEs). To address lessons learned from various industry events, the scope of this standard has e

46、volved to now include severe accidents. This evolution was intended to provide a broader applicability to cover both preventative and mitigative phases of potential plant events. A broader applicability of the standard was also achieved by moving to a more international, technology neutral approach

47、to the standard. This approach was achieved by changing to International Atomic Energy Agency (IAEA) definitions of terms, where applicable; the removal, where appropriate, of U.S. specific references; and involvement in the working group of members of other standards organizations. Furthermore, the

48、 corresponding International Electrotechnical Commission (IEC) counterparts to the IEEE standards referenced were investigated and introduced as a second set of normative references. This opens the possibility to apply this standard in the IEC domain. The individual IEEE and IEC reference sets in wh

49、ole are individually appropriate for use in the application of the standard, but inclusion of the IEEE and IEC references does not imply equivalency between the individual references of the two sets. Intended use The standard applies to instrumentation intended for use during anticipated operational occurrences (AOO), design basis events (DBE), and design extension conditions (DEC) including severe accidents. This standard defines severe accidents as a subset of design extension conditions during which fuel damage has occurred. Operationally, severe accidents and design ex