1、raising standards worldwideNO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAWBSI Standards PublicationNuclear power plants Instrumentation and control important to safety Management of ageing of electrical cabling systemsBS IEC 62465:2010National forewordThis British Standard is
2、the UK implementation of IEC 62465:2010.The UK participation in its preparation was entrusted to Technical CommitteeNCE/8, Reactor instrumentation.A list of organizations represented on this committee can be obtained onrequest to its secretary.This publication does not purport to include all the nec
3、essary provisions of acontract. Users are responsible for its correct application. BSI 2010ISBN 978 0 580 56687 5ICS 27.120.20Compliance with a British Standard cannot confer immunity fromlegal obligations.This British Standard was published under the authority of the StandardsPolicy and Strategy Co
4、mmittee on 31 July 2010.Amendments issued since publicationAmd. No. Date Text affectedBRITISH STANDARDBS IEC 62465:2010IEC 62465Edition 1.0 2010-05INTERNATIONAL STANDARD NORME INTERNATIONALENuclear power plants Instrumentation and control important to safety Management of ageing of electrical cablin
5、g systems Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la sret Gestion du vieillissement des systmes de cbles lectriques INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE VICS 27.120.20 PRICE CODECODE PRIXISBN 978-2-88910-915
6、9 Registered trademark of the International Electrotechnical Commission Marque dpose de la Commission Electrotechnique Internationale colourinsideBS IEC 62465:2010 2 62465 IEC:2010 CONTENTS FOREWORD.4 INTRODUCTION.6 1 Scope.8 2 Normative references .8 3 Terms and definitions .8 4 Technical backgrou
7、nd.11 4.1 General .11 4.2 Cable types .11 4.3 Reasons for cable ageing management.12 4.4 Cable stressors .12 4.5 Cable testing techniques .13 5 Cable testing requirements.13 5.1 General .13 5.2 Test methods 14 5.3 Application of cable testing requirements 14 5.4 Test interval 14 5.5 Test location .1
8、4 5.6 Calibration of cable testing equipment.14 5.7 Test results .14 5.8 Validation of test methods .14 5.9 Software and test tool validation15 5.10 Qualification of test personnel .15 6 Acceptable means for cable testing 15 7 Testing of end devices15 8 Relationship between initial qualification and
9、 cable ageing management16 9 Example of a nuclear power plant practice for cable ageing management.16 10 Cable testing for long-term operation16 Annex A (informative) Typical components of an electrical cable .17 Annex B (informative) Cable testing techniques .20 Annex C (informative) Description of
10、 TDR test .22 Annex D (informative) Electrical measurement of NIS cables and detectors .26 Annex E (informative) Example of a nuclear power plant practice for cable ageing management.28 Bibliography31 Figure A.1 Example of cables covered by this International Standard.18 Figure C.1 Principle of TDR
11、test of an open cable22 Figure C.2 Principle of TDR test of a short cable23 Figure C.3 Simplified TDR traces for a cable with a passive load .23 Figure C.4 TDR test setup .24 Figure C.5 RTD cabling and corresponding TDR signature 25 Figure D.1 I-V curve.27 BS IEC 62465:201062465 IEC:2010 3 Figure E.
12、1 Photo of baskets in which samples of 1E cables are deposited and placed in the plant for periodic removal and testing29 Figure E.2 Schematic of test interval for mechanical tests30 Table 1 Examples of stressors with potential to damage cables .13 BS IEC 62465:2010 4 62465 IEC:2010 INTERNATIONAL EL
13、ECTROTECHNICAL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY MANAGEMENT OF AGEING OF ELECTRICAL CABLING SYSTEMS FOREWORD 1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising all national electrotechnical
14、 committees (IEC National Committees). The object of IEC is to promote international co-operation on all questions concerning standardization in the electrical and electronic fields. To this end and in addition to other activities, IEC publishes International Standards, Technical Specifications, Tec
15、hnical Reports, Publicly Available Specifications (PAS) and Guides (hereafter referred to as “IEC Publication(s)”). Their preparation is entrusted to technical committees; any IEC National Committee interested in the subject dealt with may participate in this preparatory work. International, governm
16、ental and non-governmental organizations liaising with the IEC also participate in this preparation. IEC collaborates closely with the International Organization for Standardization (ISO) in accordance with conditions determined by agreement between the two organizations. 2) The formal decisions or
17、agreements of IEC on technical matters express, as nearly as possible, an international consensus of opinion on the relevant subjects since each technical committee has representation from all interested IEC National Committees. 3) IEC Publications have the form of recommendations for international
18、use and are accepted by IEC National Committees in that sense. While all reasonable efforts are made to ensure that the technical content of IEC Publications is accurate, IEC cannot be held responsible for the way in which they are used or for any misinterpretation by any end user. 4) In order to pr
19、omote international uniformity, IEC National Committees undertake to apply IEC Publications transparently to the maximum extent possible in their national and regional publications. Any divergence between any IEC Publication and the corresponding national or regional publication shall be clearly ind
20、icated in the latter. 5) IEC itself does not provide any attestation of conformity. Independent certification bodies provide conformity assessment services and, in some areas, access to IEC marks of conformity. IEC is not responsible for any services carried out by independent certification bodies.
21、6) All users should ensure that they have the latest edition of this publication. 7) No liability shall attach to IEC or its directors, employees, servants or agents including individual experts and members of its technical committees and IEC National Committees for any personal injury, property dam
22、age 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 this pub
23、lication. 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 all
24、such patent rights. International Standard IEC 62465 has been prepared by subcommittee 45A: Instrumentation and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation. The text of this International Standard is based on the following documents: FDIS Report on voting 45
25、A/795/FDIS 45A/803/RVD Full information on the voting for the approval of this International Standard can be found in the report on voting indicated in the above table. This publication has been drafted in accordance with the ISO/IEC Directives, Part 2. BS IEC 62465:201062465 IEC:2010 5 The committe
26、e has decided that the contents of this publication will remain unchanged until the stability date indicated on the IEC web site under “http:/webstore.iec.ch“ in the data related to the specific publication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition,
27、 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 of its contents. Users should therefore print this document using a colour printer. BS IEC 62465:2010 6 62465 IEC:201
28、0 INTRODUCTION a) Technical background, main issues and organisation of the Standard With the majority of nuclear power plants over 20 years old, the management of ageing of instrumentation and associated electrical cabling systems is currently a relevant topic, especially for those plants that have
29、 extended their operating licenses or are considering this option. This International Standard is intended to be used by operators of nuclear power plants (utilities), systems evaluators, and by licensors. b) Situation of the current Standard in the structure of the IEC SC 45A standard series IEC 62
30、465 is the third level IEC SC 45A document tackling the specific issue of management of ageing of electrical cabling systems in nuclear power plants for Instrumentation and Control (I steps to be followed to establish cable testing requirements for an ageing management program for nuclear power plan
31、t electrical cabling systems; and relationship between on-going qualification analysis and ageing management programs with regards to electrical cabling systems. It is recognized that testing and monitoring techniques used to evaluate the ageing condition of nuclear power plants electrical cabling s
32、ystems are continuing to develop at a rapid pace and that it is not possible for a standard such as IEC 62465 to include references to all modern technologies and techniques. However, a number of techniques have been mentioned within this International Standard and are described in Annexes B, C and
33、D. To ensure that this International Standard will continue to be relevant in future years, the emphasis has been placed on issues of principle, rather than specific technologies. BS IEC 62465:201062465 IEC:2010 7 d) Description of the structure of the IEC SC 45A standard series and relationships wi
34、th other IEC documents and other bodies documents (IAEA, ISO) The top-level document of the IEC SC 45A standard series is IEC 61513. It provides general requirements for I&C systems and equipment that are used to perform functions important to safety in NPPs. IEC 61513 structures the IEC SC 45A stan
35、dard series. IEC 61513 refers directly to other IEC SC 45A standards for general topics related to categorization of functions and classification of systems, qualification, separation of systems, defence against common cause failure, software aspects of computer-based systems, hardware aspects of co
36、mputer-based systems, and control room design. The standards referenced directly at this second level should be considered together with IEC 61513 as a consistent document set. At a third level, IEC SC 45A standards not directly referenced by IEC 61513 are standards related to specific equipment, te
37、chnical methods, or specific activities. Usually these documents, which make reference to second-level documents for general topics, can be used on their own. A fourth level extending the IEC SC 45A standard series, corresponds to the Technical Reports which are not normative. IEC 61513 has adopted
38、a presentation format similar to the basic safety publication IEC 61508 with an overall safety life-cycle framework and a system life-cycle framework and provides an interpretation of the general requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for the nuclear application sector. Compliance
39、 with IEC 61513 will facilitate consistency with the requirements of IEC 61508 as they have been interpreted for the nuclear industry. In this framework IEC 60880 and IEC 62138 correspond to IEC 61508-3 for the nuclear application sector. IEC 61513 refers to ISO as well as to IAEA 50-C-QA (now repla
40、ced by IAEA GS-R-3) for topics related to quality assurance (QA). The IEC SC 45A standards series consistently implements and details the principles and basic safety aspects provided in the IAEA code on the safety of NPPs and in the IAEA safety series, in particular the Requirements NS-R-1, establis
41、hing safety requirements related to the design of Nuclear Power Plants, and the Safety Guide NS-G-1.3 dealing with instrumentation and control systems important to safety in Nuclear Power Plants. The terminology and definitions used by SC 45A standards are consistent with those used by the IAEA. BS
42、IEC 62465:2010 8 62465 IEC:2010 NUCLEAR POWER PLANTS INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY MANAGEMENT OF AGEING OF ELECTRICAL CABLING SYSTEMS 1 Scope This International Standard provides strategies, technical requirements, and recommended practices for the management of normal ageing of ca
43、bling systems that are important to safety in nuclear power plants. The main requirements are presented in the body of this International Standard followed by a number of informative annexes with examples of cable testing techniques, procedures, and equipment that are available for the nuclear indus
44、try to use to ensure that ageing degradation will not impact plant safety. This International Standard covers cables and their accessories (e.g., connectors) installed in nuclear power plants (inside and outside the containment). It provides requirements to perform cable testing for the purposes of
45、predictive maintenance, troubleshooting, ageing management, and assurance of plant safety. It is concerned with Instrumentation and Control (I&C) cables, signal cables, and power cables of voltages less than 1 kV. More specifically, this International Standard focuses on in-situ testing techniques t
46、hat have been established for determining problems in cable conductors (i.e., copper wire) and, to a lesser extent, on insulation material (i.e., polymer). It follows the IEC 62342 standard on “Management of Ageing” that was prepared to provide general guidelines for management of ageing of I&C comp
47、onents in nuclear power plants, including cables. It should be pointed out that cable testing technologies are evolving and new methods are becoming available that are not covered in this International Standard. More specifically, this International Standard covers typical cable testing methods that
48、 have been in use in the nuclear power industry over the last decade. It should also be pointed out that a single cable testing technique is unlikely to provide conclusive results, and a reliable diagnosis normally requires a combination of techniques. 2 Normative references The following referenced
49、 documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies. IEC 60780, Nuclear power plants Electrical equipment of the safety system Qualification IEC/TR 62096, Nuclear power plants Instrumentation and control important to safety Guidance for the decision on modernization IEC 62342, Nu
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