1、 IEC 60987 Edition 2.1 2013-02 INTERNATIONAL STANDARD NORME INTERNATIONALE Nuclear power plants Instrumentation and control important to safety Hardware design requirements for computer-based systems Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la sret Exigenc
2、es applicables la conception du matriel des systmes informatiss IEC60987:2007+A1:2013 colourinsideTHIS PUBLICATION IS COPYRIGHT PROTECTED Copyright 2013 IEC, Geneva, Switzerland All rights reserved. Unless otherwise specified, no part of this publication may be reproduced or utilized in any form or
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16、 des questions contactez-nous: csciec.ch. IEC 60987 Edition 2.1 2013-02 INTERNATIONAL STANDARD NORME INTERNATIONALE Nuclear power plants Instrumentation and control important to safety Hardware design requirements for computer-based systems Centrales nuclaires de puissance Instrumentation et contrle
17、-commande importants pour la sret Exigences applicables la conception du matriel des systmes informatiss INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE ICS 27.120.20 ISBN 978-2-8322-0674-4 Registered trademark of the International Electrotechnical Commission Mar
18、que dpose de la Commission Electrotechnique Internationale Warning! Make sure that you obtained this publication from an authorized distributor. Attention! Veuillez vous assurer que vous avez obtenu cette publication via un distributeur agr. colourinside 2 60987 IEC:2007+A1:2013 CONTENTS FOREWORD .
19、4 INTRODUCTION . 6 1 Scope . 8 1.1 General . 8 1.2 Use of this standard for pre-developed (for example, COTS) hardware assessment 8 1.3 Applicability of this standard to programmable logic devices development . 9 2 Normative references . 9 3 Terms and definitions . 10 4 Project structure . 12 4.1 Ge
20、neral . 12 4.2 Project subdivision 12 4.3 Quality assurance . 13 5 Hardware requirements 13 5.1 General . 13 5.2 Functional and performance requirements . 14 5.3 Reliability/Availability requirements . 15 5.4 Environmental withstand requirements 16 5.5 Documentation requirements . 17 6 Design and de
21、velopment 17 6.1 General . 17 6.2 Design activities 17 6.3 Reliability 18 6.4 Maintenance 19 6.5 Interfaces 19 6.6 Modification . 19 6.7 Power failure . 19 6.8 Component selection . 19 6.9 Design documentation . 19 7 Verification and validation 20 7.1 General . 20 7.2 Verification plan 20 7.3 Indepe
22、ndence of verification 21 7.4 Methods 21 7.5 Documentation 22 7.6 Discrepancies 22 7.7 Changes and modifications . 22 7.8 Installation verification . 22 7.9 Validation 22 7.10 Verification of pre-existing equipment platforms 22 8 Qualification . 23 9 Manufacturing 23 9.1 Quality assurance . 23 9.2 T
23、raining of personnel. 24 60987 IEC:2007+A1:2013 3 9.3 Planning and organisation of the manufacturing activities. . 24 9.4 Input data 25 9.5 Purchasing and procurement . 25 9.6 Production . 27 10 Installation and commissioning . 29 11 Maintenance . 30 11.1 Maintenance requirements 30 11.2 Failure dat
24、a . 31 11.3 Maintenance documentation 32 12 Modification 32 13 Operation . 32 Annex A (informative) Overview of system life cycle 33 Annex B (informative) Outline of qualification . 34 Annex C (informative) Example of maintenance procedure 35 Bibliography 36 4 60987 IEC:2007+A1:2013 INTERNATIONAL EL
25、ECTROTECHNICAL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY HARDWARE DESIGN REQUIREMENTS FOR COMPUTER-BASED SYSTEMS FOREWORD 1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising all national electrotech
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34、y damage or other damage of any nature whatsoever, whether direct or indirect, or for costs (including legal fees) and expenses arising out of the publication, use of, or reliance upon, this IEC Publication or any other IEC Publications. 8) Attention is drawn to the Normative references cited in thi
35、s publication. Use of the referenced publications is indispensable for the correct application of this publication. 9) Attention is drawn to the possibility that some of the elements of this IEC Publication may be the subject of patent rights. IEC shall not be held responsible for identifying any or
36、 all such patent rights. This consolidated version of IEC 60987 consists of the second edition (2007) documents 45A/662/FDIS and 45A/666/RVD and its amendment 1 (2013) documents 45A/897/FDIS and 45A/906/RVD. It bears the edition number 2.1. The technical content is therefore identical to the base ed
37、ition and its amendment and has been prepared for user convenience. A vertical line in the margin shows where the base publication has been modified by amendment 1. Additions and deletions are displayed in red, with deletions being struck through. 60987 IEC:2007+A1:2013 5 International Standard IEC
38、60987 has been prepared by subcommittee 45A: Instrumentation and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation. This edition includes the following significant technical changes with respect to the previous edition: account has been taken of the fact that comp
39、uter design engineering techniques have advanced significantly in the intervening years; update of the format to align with the current IEC/ISO directives on the style of standards; alignment of the standard with the new revisions of IAEA documents NS-R-1 and NS-G-1.3, which includes as far as possi
40、ble an adaptation of the definitions; replacement, as far as possible, of the requirements associated with standards published since the first edition, especially IEC 61513, IEC 60880, edition 2, and IEC 62138; review of the existing requirements and updating of the terminology and definitions. This
41、 publication has been drafted in accordance with the ISO/IEC Directives, Part 2. The committee has decided that the contents of the base publication and its amendments will remain unchanged until the stability date indicated on the IEC web site under “http:/webstore.iec.ch“ in the data related to th
42、e specific publication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition, or amended. IMPORTANT The “colour inside” logo on the cover page of this publication indicates that it contains colours which are considered to be useful for the correct understanding
43、 of its contents. Users should therefore print this publication using a colour printer. 6 60987 IEC:2007+A1:2013 INTRODUCTION a) Technical background, main issues and organization of the standard The basic principles for the design of nuclear instrumentation, as specifically applied to the safety sy
44、stems of nuclear power plants, were first interpreted in nuclear standards with reference to hardwired systems in IAEA Safety Guide 50-SG-D3 which has been superseded by IAEA Guide NS-G-1.3. IEC 60987 was first issued in 1989 to cover the hardware aspects of digital systems design for systems import
45、ant to safety, i.e. safety systems and safety-related systems. Although many of the requirements within the original issue continue to be relevant, there were significant factors which justified the development of this revised edition of IEC 60987, in particular: a new standard has been produced whi
46、ch addresses in detail the general requirements for nuclear systems important to safety (IEC 61513); the use of pre-developed system platforms, rather than bespoke developments, has increased significantly. b) Situation of the current standard in the structure of the IEC SC 45A standard series The f
47、irst-level IEC SC 45A standard for computer-based systems important to safety in nuclear power plants (NPPs) is IEC 61513. IEC 60987 is a second-level IEC SC 45A standard which addresses the generic issue of hardware design of computerized systems. IEC 60880 and IEC 62138 are second-level standards
48、which together cover the software aspects of computer-based systems used to perform functions important to safety in NPPs. IEC 60880 and IEC 62138 make direct reference to IEC 60987 for hardware design. The requirements of IEC 60780 for equipment qualification are referenced within IEC 60987. For mo
49、dules to be used in the design of a specific system important to safety, relevant and auditable operating experience from nuclear or other applications as described in IEC 60780, in combination with the application of rigorous quality assurance programmes, may be an acceptable method of qualification. For more details on the structure of the SC 45A standard series, see item d) of this introduction. c) Recommendatio
