1、N290.6-09Requirements for monitoring and display of nuclear power plant safety functions in the event of an accidentLegal Notice for StandardsCanadian Standards Association (CSA) standards are developed through a consensus standards development process approved by the Standards Council of Canada. Th
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17、d or use this document or make any copies of the contents hereof, and if you do make such copies, you are required to destroy them immediately. Use of this document constitutes your acceptance of the terms and conditions of this Legal Notice.Standards Update ServiceN290.6-09March 2009Title: Requirem
18、ents for monitoring and display of nuclear power plant safety functions in the event of an accidentPagination: 19 pages (vii preliminary and 12 text), each dated March 2009To register for e-mail notification about any updates to this publicationgo to shop.csa.caclick on CSA Update ServiceThe List ID
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21、ons in the event of an accidentCSA Standard100%ISBN 978-1-55436-804-4Technical Editor: Mary Cianchetti Canadian Standards Association 2009All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.To purchase CSA Standards
22、and related publications, visit CSAs Online Store at www.ShopCSA.ca or call toll-free 1-800-463-6727 or 416-747-4044.The Canadian Standards Association (CSA) prints its publications on Rolland Enviro100, which contains 100% recycled post-consumer fibre, is EcoLogo and Processed Chlorine Free certifi
23、ed, and was manufactured using biogas energy.March 2009 iiiContents Canadian Standards AssociationRequirements for monitoring and display of nuclearpower plant safety functions in the event of an accidentTechnical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear
24、Power Plants ivSubcommittee on Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the Event of an Accident viPreface vii1Scope 12 Reference publications 13 Definitions 34Parameter selection 55 Design considerations 56 Design requirements 56.1 Range and accuracy 56.2 R
25、esponse times 66.3 Commonality between information chains and special safety systems 66.4 Commonality between information chains and process systems 66.5 Redundancy 76.6 Independence between information chains that monitor and display the same plant characteristic 76.7 Reliability 76.8 Verification
26、capability 86.9 Maintenance and calibration capability 86.10 Component qualification 96.10.1 General 96.10.2 Environmental qualification 96.10.3 Seismic qualification 96.11 Software design 96.12 Standards for pressure-retaining components and supports 96.13 Identification and location requirements 9
27、6.14 Monitoring of radioactivity 106.15 Human factors 107Documentation 108 Quality assurance program 11AnnexesA (informative) Severe accidents 12N290.6-09 Canadian Standards Associationiv March 2009Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear Power
28、PlantsJ. Grava Southampton, Ontario ChairR. Black Ontario Power Generation Inc.,Bowmanville, OntarioVice-ChairB. Babcock Ontario Power Generation Inc.,Pickering, OntarioAssociateQ.-B.J. Chou Canadian Power Utility Services Ltd.,Toronto, OntarioR. Colquhoun Roy Colquhoun Associates,Toronto, OntarioB.
29、 Coulas Bruce Power Inc.,Tiverton, OntarioG. Davies RCM Technologies Canada Corp.,Pickering, OntarioM. Debly NB Power Nuclear Corporation,Lepreau, New BrunswickS. Desaulniers Hydro-Qubec,Gentilly, QubecA. Faya Pebble Bed Modular Reactor (Pty) Ltd.,Centurion, South AfricaAssociateM. Kotb Rgie du btim
30、ent du Qubec,Montral, QubecU. Kukreti RCM Technologies Canada Corp.,Pickering, OntarioAssociateW. Lam Ministry of Energy,Toronto, OntarioP. Lee Atomic Energy of Canada Limited,Mississauga, OntarioH. Leung HCL Inc.,Toronto, OntarioAssociate Canadian Standards AssociationRequirements for monitoring an
31、d display of nuclearpower plant safety functions in the event of an accidentMarch 2009 vR.P. Lindsay RCM Technologies Canada Corp.,Pickering, OntarioAssociateR. Lojk Canadian Nuclear Safety Commission,Ottawa, OntarioL. Luckhardt Dresser Flow Solutions,Burlington, OntarioJ. Pilgrim GE-Hitachi,Peterbo
32、rough, OntarioG. Ridgway GE-Hitachi,Peterborough, OntarioAssociateB. Rolfe Rolfe and Associates,Mississauga, OntarioG. Waterhouse Nuclear Logistics Inc. (Canada),Bowmanville, OntarioM. Cianchetti Canadian Standards Association,Mississauga, OntarioProject ManagerI. Hipsz Canadian Standards Associatio
33、n,Mississauga, OntarioProject ManagerN290.6-09 Canadian Standards Associationvi March 2009Subcommittee on Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the Event of an AccidentB. Babcock Ontario Power Generation Inc.,Pickering, OntarioChairD. Boulay Hydro-Qubec,C
34、entrale nuclaire Gentilly-2Bcancour, QubecR. Colquhoun Roy Colquhoun Associates,Toronto, OntarioJ.-Y. Fiset Canadian Nuclear Safety Commission,Ottawa, OntarioD. Gillard Ontario Power Generation Inc.,Darlington Nuclear Generating Station,Bowmanville, OntarioP. Lee Atomic Energy of Canada Limited,Miss
35、issauga, OntarioK. Locke Bruce Power,Tiverton, OntarioS. MacDonald Manchester Consulting,Saint John, New BrunswickR. Prime NB Power Nuclear Corporation,Lepreau, New BrunswickJ. Vinnai Atomic Energy of Canada Limited,Mississauga, OntarioM. Cianchetti Canadian Standards Association,Mississauga, Ontari
36、oProject ManagerA. Kwong Canadian Standards Association,Mississauga, OntarioProject Manager Canadian Standards AssociationRequirements for monitoring and display of nuclearpower plant safety functions in the event of an accidentMarch 2009 viiPrefaceThis is the second edition of CSA N290.6, Requireme
37、nts for monitoring and display of nuclear power plant safety functions in the event of an accident. It supersedes the previous edition, published in 1982 under the title Requirements for Monitoring and Display of CANDU Nuclear Power Plant Status in the Event of an Accident.Major changes to this edit
38、ion include(a) harmonization with CSA N285.0 and CSA N286;(b) the addition of an informative annex on severe accidents; and(c) the addition of information to aid in the selection of parameters to be monitored.This Standard provides requirements and recommendations for the design, manufacture, instal
39、lation, and qualification of those components specifically involved in the monitoring and display of post-accident information for a nuclear reactor. The monitoring and display of nuclear power plant variables following an accident are important safety functions; appropriate operator actions followi
40、ng such an event rely on the availability of adequate information.Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its
41、supporting Regulations.This Standard has been prepared by the Subcommittee on Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the Event of an Accident, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation
42、 for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.March 2009Notes: (1) Use of the singular does not exclude the plural (and vice versa) when the sense allows.(2) Although the intended primary application of
43、this Standard is stated in its Scope, it is important to note that it remains the responsibility of the users of the Standard to judge its suitability for their particular purpose.(3) This publication was developed by consensus, which is defined by CSA Policy governing standardization Code of good p
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47、sed where possible to permit a specific “yes” or “no” answer.Committee interpretations are processed in accordance with the CSA Directives and guidelines governing standardization and are published in CSAs periodical Info Update, which is available on the CSA Web site at www.csa.ca. Canadian Standar
48、ds AssociationRequirements for monitoring and display of nuclearpower plant safety functions in the event of an accidentMarch 2009 1N290.6-09Requirements for monitoring and display of nuclear power plant safety functions in the event of an accident1Scope1.1This Standard provides requirements for the
49、 design, testing, installation, and qualification of equipment for the display of nuclear power plant safety functions in the event of an accident.1.2This Standard applies to existing plants, life extensions, and new builds. 1.3This Standard applies to equipment that enables the operator to(a) monitor the plant safety functions post-accident, both short- and long-term; andNote: Monitoring assists the operator in selecting a strategy to restore or maintain the safety functions (control, cool, and contain).(b) determine when conditions are developing that wa
