1、N290.4-11Requirements for reactor control systems of nuclear power plantsLegal Notice for StandardsCanadian Standards Association (CSA) standards are developed through a consensus standards development process approved by the Standards Council of Canada. This process brings together volunteers repre
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17、f 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.CSA Standards Update ServiceN290.4-11October 2011Title:Requirements for reactor control systems of nu
18、clear power plantsPagination:20 pages (viii preliminary and 12 text), each dated October 2011To register for e-mail notification about any updates to this publicationgo to www.ShopCSA.caclick on E-mail Services under MY ACCOUNTclick on CSA Standards Update ServiceThe List ID that you will need to re
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21、ards Association 2011All 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 and related publications, visit CSAs Online Store at www.ShopCSA.ca or call toll-free 1-800-463-6727 or 416-747-4044.
22、The Canadian Standards Association (CSA) prints its publications on Rolland Enviro100, which contains 100%recycled post-consumer fibre, is EcoLogo and Processed Chlorine Free certified, and was manufactured using biogas energy.October 2011 iiiContents Canadian Standards Association Requirements for
23、reactor control systems of nuclear power plantsTechnical Committee on Reactor Control Systems, Safety Systems, and Instrumentation of Nuclear Power Plants ivSubcommittee on Reactor Control Systems of Nuclear Power Plants viPreface vii1Scope12 Reference publications 23 Definitions 34 Functional requi
24、rements 44.1 Normal operation 44.2 Anticipated operational occurrences (AOOs) 54.3 Design basis accidents (DBAs) 55Requirements55.1 Operating experience 55.2 Separation and independence between the reactor control system and shutdown systems 55.3 Relationship of the reactor control system to other p
25、rocess systems 55.4 Reliability 65.5 Fail-safe design 65.6 Control devices 65.7 Reactor start-up 75.8 Response following a reactor trip 75.9 Reactor subcritical 75.10 Reactor power measurement 85.11 Human-system interface 85.12 Testing 95.13 Maintenance capability 95.14 Standards for pressure-retain
26、ing piping components 95.15 Standards for instrumentation and interconnections 105.16 Equipment qualification 105.16.1 General 105.16.2 Environmental qualification 105.16.3 Seismic qualification 105.16.4 Ageing management 105.17 Software design 115.18 Cyber security 115.19 Control stability 115.20 C
27、hemistry 116 Quality management 11AnnexesA(informative) Guidance on control logic implementation 12N290.4-11 Canadian Standards Associationiv October 2011Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation of Nuclear Power PlantsJ. Grava CANTECH Associates Ltd.,Owen S
28、ound, Ontario ChairR. Black RCM Technologies Canada Corp.,Pickering, OntarioVice-ChairB. Coulas Bruce Power Inc.,Tiverton, OntarioVice-ChairB. Babcock Ontario Power Generation Inc.,Pickering, OntarioAssociateQ.-B.J. Chou Canadian Power Utility Services Ltd.,Toronto, OntarioC. Daniel Ontario Power Ge
29、neration Inc.,Pickering, OntarioG. Davies RCM Technologies Canada Corp.,Pickering, OntarioAssociateM. Debly NB Power Nuclear Corporation,Lepreau, New BrunswickA. Faya Federal Authority for Nuclear Regulation,Abu Dhabi, UAEAssociateM. Gerard Ontario Power Generation Inc.,Pickering, OntarioAssociateM.
30、 Kotb Rgie du btiment du Qubec,Montral, QubecU. Kukreti RCM Technologies Canada Corp.,Pickering, OntarioAssociateW. Lam Ministry of Energy,Toronto, OntarioP. Lee Atomic Energy of Canada Limited,Mississauga, Ontario Canadian Standards Association Requirements for reactor control systems of nuclear po
31、wer plantsOctober 2011 vH. Leung HCL Inc.,Toronto, OntarioAssociateR.P. Lindsay RCM Technologies Canada Corp.,Pickering, OntarioAssociateR. Lojk Canadian Nuclear Safety Commission,Ottawa, OntarioL. Luckhardt Dresser Flow Solutions,Burlington, OntarioS. MacDonald Manchester Consulting,Saint John, New
32、 Brunswick J. Pilgrim GE-Hitachi,Peterborough, OntarioG. Ridgway GE-Hitachi,Peterborough, OntarioAssociateB. Rolfe Rolfe and Associates,Mississauga, OntarioG. Waterhouse Nuclear Logistics Inc. (Canada),Bowmanville, OntarioB. Willemsen NB Power Nuclear Corporation,Lepreau, New BrunswickAssociateM. Ci
33、anchetti Canadian Standards Association,Mississauga, OntarioProject ManagerS. Oh Canadian Standards Association,Mississauga, OntarioProject ManagerN290.4-11 Canadian Standards Associationvi October 2011Subcommittee on Reactor Control Systems of Nuclear Power PlantsB. Babcock Ontario Power Generation
34、 Inc.,Pickering, OntarioChairM. Borairi Atomic Energy of Canada Limited,Mississauga, OntarioG. Chun Canadian Nuclear Safety Commission,Ottawa, OntarioA. Firla Canadian Power Utility Services Ltd.,Toronto, OntarioP. Gribbons Bruce Power Inc.,Tiverton, OntarioR. Nicholls Hydro-Qubec,Gentilly, QubecP.
35、Paquette Bruce Power Inc.,Tiverton, OntarioR. Prime NB Power Nuclear Corporation,Lepreau, New BrunswickM. Cianchetti Canadian Standards Association,Mississauga, OntarioProject ManagerS. Oh Canadian Standards Association,Mississauga, OntarioProject Manager Canadian Standards Association Requirements
36、for reactor control systems of nuclear power plantsOctober 2011 viiPrefaceThis is the second edition of CSA N290.4, Requirements for reactor control systems of nuclear power plants. It supersedes the previous edition published in 1982. The title has been changed to reflect a change of scope. The new
37、 edition not only addresses CANDU reactors but also addresses other types of water-cooled power reactors.The development of the original Standard was initiated by the Canadian Nuclear Association to help prospective owners of nuclear power plants, as well as designers, manufacturers, fabricators, an
38、d installers of nuclear power plant components, by compiling the various requirements of regulatory authorities. Major changes to this edition include(a)broadening of requirements to incorporate other water-cooled reactor technologies; (b) improved integration with associated standards; and (c) inco
39、rporation of current terminology and operating experience.The specific objective of this Standard is to establish the minimum requirements for the design, manufacture and fabrication, qualification, and installation of reactor control systems in nuclear power plants, in order to ensure that they wil
40、l operate as intended. The purpose of this Standard is not to limit improved system design but to provide a minimum base against which innovations and new techniques can be compared.The CSA N-Series of Standards provides an interlinked set of requirements for the management of nuclear facilities and
41、 activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does
42、 not duplicate the generic requirements of CSA N286; however, it may provide more specific direction for those requirements.Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the
43、 provisions of the Nuclear Safety and Control Act and its supporting Regulations.This Standard has been prepared by the Subcommittee on Reactor Control Systems of Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation o
44、f Nuclear Power Plants, and the Standards Steering Committee on Nuclear Standards.October 2011Notes: (1) Use of the singular does not exclude the plural (and vice versa) when the sense allows.(2) Although the intended primary application of this Standard is stated in its Scope, it is important to no
45、te 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 practice for standardization as “substantial agreement. Cons
46、ensus implies much more than a simple majority, but not necessarily unanimity”. It is consistent with this definition that a member may be included in the Technical Committee list and yet not be in full agreement with all clauses of this publication.(4) To submit a request for interpretation of CSA
47、Standards, please send the following information to inquiriescsa.ca and include “Request for interpretation” in the subject line:(a) define the problem, making reference to the specific clause, and, where appropriate, include an illustrative sketch;(b) provide an explanation of circumstances surroun
48、ding the actual field condition; and(c) where possible, phrase the request in such a way that a specific “yes” or “no” answer will address the issue.Committee interpretations are processed in accordance with the CSA Directives and guidelines governing standardization and are published in CSAs period
49、ical Info Update, which is available on the CSA website at http:/standardsactivities.csa.ca.(5) CSA Standards are subject to periodic review, and suggestions for their improvement will be referred to the appropriate committee. To submit a proposal for change to CSA Standards, please send the following information to inquiriescsa.ca and include “Proposal for change” in the subject line:(a) Standard designation (number);N290.4-11 Canadian Standards Associationviii October 2011(b) relevant clause, table, and/or figure number;(c) wording of the proposed chan
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