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1、BRITISH STANDARD BS IEC 60780:1998 Nuclear power plants Electrical equipment of the safety system Qualification ICS 27.120.20 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 This British Standard, having been prepared under
2、 the direction of the Engineering Sector Committee, was published under the authority of the Standards Committee and comes into effect on 15 April 1999 BSI 03-2000 ISBN 0 580 32301 3 National foreword This British Standard reproduces verbatim IEC 60780:1998 and implements it as the UK national stand
3、ard. The UK participation in its preparation was entrusted to Technical Committee NCE/8, Reactor instrumentation, which has the responsibility to: aid enquirers to understand the text; present to the responsible international/European committee any enquiries on the interpretation, or proposals for c
4、hange, and keep the UK interests informed; monitor related international and European developments and promulgate them in the UK. A list of organizations represented on this committee can be obtained on request to its secretary. From 1 January 1997, all IEC publications have the number 60000 added t
5、o the old number. For instance, IEC 27-1 has been renumbered as IEC 60027-1. For a period of time during the change over from one numbering system to the other, publications may contain identifiers from both systems. Cross-references The British Standards which implement international or European pu
6、blications referred to in this document may be found in the BSI Standards Catalogue under the section entitled “International Standards Correspondence Index”, or by using the “Find” facility of the BSI Standards Electronic Catalogue. A British Standard does not purport to include all the necessary p
7、rovisions of a contract. Users of British Standards are responsible for their correct application. Compliance with a British Standard does not of itself confer immunity from legal obligations. Summary of pages This document comprises a front cover, an inside front cover, pages i and ii, the CEI IEC
8、title page, page ii, pages 1 to 19 and a back cover. This standard has been updated (see copyright date) and may have had amendments incorporated. This will be indicated in the amendment table on the inside front cover. Amendments issued since publication Amd. No.DateComments Licensed Copy: sheffiel
9、dun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 BSI 03-2000i Contents Page National forewordInside front cover Text of CEI IEC 607801 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI ii bl
10、ank Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 ii BSI 03-2000 Contents Page 1Scope and object1 2Normative refer
11、ences1 3Terms and definitions2 4General qualification process4 4.1Type testing5 4.2Operating experience5 4.3Qualification by analysis5 4.4Combined qualification5 4.5On-going qualification5 5Qualification procedures and methods6 5.1Identification of equipment of the safety system being qualified6 5.2
12、Equipment performance specifications6 5.3Type test procedures6 5.4Qualification by operating experience15 5.5Qualification by analysis16 5.6On-going qualification17 5.7Criteria of failure17 5.8Modifications17 5.9Planned maintenance18 6Documentation18 6.1General18 6.2Documentation files18 6.3Type tes
13、t data18 6.4Operating experience data18 6.5Analysis19 6.6Extrapolation19 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 BSI 03-20001 1 Scope and object This International Standard is applicable to electrical equipment of s
14、afety systems used in nuclear power plants, including components or equipment of any interface whose failure could adversely affect the performance of the safety system. It is also applicable to non-electrical interfaces associated with a safety function. This standard describes successively the gen
15、eral qualification process, the qualification procedures and methods to be used and the associated documentation. It is the primary role of qualification to ensure that, for each type of safety-related equipment, the design and the manufacturing processes are such that there is a high degree of conf
16、idence that future equipment of the same type will perform as required. This standard also gives preferential methods in various configurations, as well as severity levels to be used in the qualification sequence. These qualification requirements, when met, will provide adequate verification that th
17、e equipment of the safety systems is designed to perform its function. It should be taken into account that there exist different categories of qualification according to the task and the location of the equipment. Where qualification is required by other IEC standards or recommendations for nuclear
18、 power plants other than those described in this standard, the use of the general guidance provided in this standard is recommended. The qualification methods described here should be used for the initial qualification of the equipment and for maintaining qualification preservation following modific
19、ations. Other qualification rules for specific electrical equipment or test methods may exist elsewhere and should be used to supplement this standard. The references and methods for determining equipment design life are not directly covered by this standard. The manufacturers and users of equipment
20、 for safety systems are required to provide evidence that such equipment will meet or exceed its performance requirements throughout its installed life. This requires the establishment of different quality assurance programmes at various levels: design, qualification, production quality control, ins
21、tallation, maintenance and periodic testing. This standard deals only with the qualification aspects. The other steps in the quality assurance programme require strict control to ensure that subsequent equipment of the same type matches that which was qualified, and that is suitably applied, install
22、ed, maintained and periodically tested. 2 Normative references The following normative documents contain provisions which, through reference in this text, constitute provisions of this International Standard. At the time of publication, the editions indicated were valid. All normative documents are
23、subject to revision, and parties to agreements based on this International Standard are encouraged to investigate the possibility of applying the most recent editions of the normative documents listed below. Members of IEC and ISO maintain registers of currently valid International Standards. IEC 60
24、068-1:1988, Environmental testing Part 1: General and guidance. IEC 60068-2 (all parts), Environmental testing Part 2: Tests. IEC 60068-2-1:1990, Environmental testing Part 2: Tests Tests A: Cold. IEC 60068-2-2:1974, Environmental testing Part 2: Tests Tests B: Dry heat. IEC 60068-2-3:1969, Environm
25、ental testing Part 2: Tests Test Ca: Damp heat, steady state. IEC 60068-2-6:1995, Environmental testing Part 2: Tests Test Fc: Vibration (sinusoidal). IEC 60068-2-11:1981, Environmental testing Part 2: Tests Test Ka: Salt mist. IEC 60068-2-14:1984, Environmental testing Part 2: Tests Test N: Change
26、of temperature. IEC 60068-2-18:1989, Environmental testing Part 2: Tests Test R and guidance: Water. IEC 60068-2-27:1987, Environmental testing Part 2: Tests Test Ea and guidance: Shock. IEC 60068-2-28:1990, Environmental testing Part 2: Tests Guidance for damp heat tests. Licensed Copy: sheffieldun
27、 sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 2 BSI 03-2000 IEC 60068-2-29:1987, Environmental testing Part 2: Tests Test Eb and guidance: Bump. IEC 60068-2-30:1980, Environmental testing Part 2: Tests Test Db and guidance: Damp heat, cyclic (12 +
28、 12-hour cycle). IEC 60068-2-31:1969, Environmental testing Part 2: Tests Test Ec: Drop and topple, primarily for equipment-type specimens. IEC 60068-2-32:1975, Environmental testing Part 2: Tests Test Ed: Free fall (Procedure 1). IEC 60068-2-34:1973, Environmental testing Part 2: Tests Test Fd: Ran
29、dom vibration wide band General requirements. IEC 60068-2-52:1996, Environmental testing Part 2: Tests Test Kb: Salt mist, cyclic (sodium chloride solution). IEC 60068-2-57:1989, Environmental testing Part 2: Tests Test Ff: Vibration Time history method. IEC 60068-2-75:1997, Environmental testing Pa
30、rt 2-75: Tests Test Eh: Hammer test. IEC 60068-3 (all parts), Environmental testing Part 3: Background information. IEC 60068-3-3:1991, Environmental testing Part 3: Guidance Seismic test methods for equipment. IEC 60068-5-1:1991, Environmental testing Part 5: Guide to drafting of test methods Gener
31、al principles. IEC 60085:1984, Thermal evaluation and classification of electrical insulation. IEC 60529:1989, Degrees of protection provided by enclosures (IP Code). IEC 60544-2:1991, Guide for determining the effects of ionizing radiation on insulating materials Part 2: Procedures for irradiation
32、and test. IEC 60557:1982, IEC terminology in the nuclear reactor field. IEC 60980:1989, Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations. IEC 61000-4 (all parts), Electromagnetic compatibility (EMC) Part 4: Testing and measu
33、rement techniques. IEC 61298-2:1995, Process measurement and control devices General methods and procedures for evaluating performance Part 2: Tests under reference conditions. 3 Terms and definitions For the purposes of this International Standard, the following terms and definitions apply. 3.1 age
34、ing (natural) change with the passage of time of physical, chemical or electrical properties of a component or equipment under design range operating conditions, which may result in degradation of significant performance characteristics 3.2 accelerated ageing accelerated process designed to simulate
35、 an advanced life condition in a short period of time. It is the process of subjecting an equipment or a component to stress conditions in accordance with known measurable physical or chemical laws of degradation in order to render its physical and electrical properties similar to those it would hav
36、e at an advanced age operating under expected operational conditions 3.3 auditable data technical information which is documented and organized in a readily understandable and traceable manner that permits independent auditing of the inferences or conclusions based on the information 3.4 components
37、items from which the equipment is assembled (for example resistors, capacitors, wires, connectors, transistors, tubes, switches, springs, etc.) Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 BSI 03-20003 3.5 containment po
38、rtion of the engineered safety features designed to act as the barrier, after the reactor primary envelope, to prevent the release, even under reactor accident conditions, of unacceptable quantities of radioactive material beyond a controlled zone 3.6 postulated initiating events events (or their cr
39、edible combinations) such as equipment failures, operator errors, earthquakes and their consequences which are postulated as part of the design basis and which could lead to anticipated operational occurrences or accident conditions 3.7 design life time during which satisfactory performance based on
40、 full design consideration can be demonstrated for a specified set of operating conditions 3.8 equipment qualification demonstration by means of analyses, type tests or operating experience, that the equipment is able to function within its required accuracy and performance requirements in all requi
41、red operational and environmental conditions 3.9 qualification margin difference between the most severe specified functional and environmental conditions of the plant and the conditions used through the whole qualification process 3.10 installed life time interval from installation to removal, duri
42、ng which the equipment or components thereof may be subjected to design operational conditions NOTEEquipment may have an installed life of 40 years with certain components changed periodically; thus the installed life of the components would be less than 40 years. 3.11 interface between safety syste
43、m and other systems junction or junctions between equipment of the safety system and other equipment or devices (Examples: connection boxes, splices, terminal boards, electrical connections, grommets, gaskets, cables, conduits, enclosures, etc.) 3.12 operating experience accumulation of verifiable o
44、perational data for conditions equivalent to those for which particular equipment is to be qualified 3.13 qualified life period of time for which satisfactory performance can be verified for a specified set of operational conditions NOTEThe qualified life of a particular equipment item may be change
45、d during its installed life where justified. 3.14 safety system all those systems important to safety provided to ensure, in any condition, the safe shutdown of the reactor and the heat removal from the core and/or to limit the consequences of anticipated operational occurrences and accident conditi
46、ons (see IEC 60557) NOTEThe safety system consists of the protection system, the safety actuation system, and the safety system support features. Equipment of the safety system may be provided solely to perform safety functions or may perform safety functions in some plant operating states and non-s
47、afety functions in other plant operational states. Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:42:24 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 60780:1998 4 BSI 03-2000 3.15 safety function specific purpose of the safety system or other items important to safety, for example, to
48、 shut down the reactor or to remove residual heat. Each postulated initiating event may require that one or more safety functions be accomplished NOTEA list of safety functions is given in IAEA Safety Guide 50-SG-D1 on Safety functions and equipment classification for BWR, PWR and PTR. 3.16 sample e
49、quipment production equipment tested to obtain data that are valid over a range of specific ratings NOTEIt is often necessary to carry out type tests on several samples of the same equipment. 3.17 operational conditions influence quantities expected as a result of normal operating requirements, expected extremes in normal operating requirements and postulated conditions appropriate for the postulated initiating events of the station 3.18 type tests tests that are made on sample