BS IEC 60951-1-2009 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - General requirements《核电站 重要安全性仪器仪表.pdf

1、raising standards worldwideNO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAWBSI British StandardsWB9423_BSI_StandardColCov_noK_AW:BSI FRONT COVERS 5/9/08 12:55 Page 1Nuclear power plantsInstrumentation importantto safety Radiation monitoring for accident and post-accident condit

2、ions Part 1: General requirementsBS IEC 60951-1:2009National forewordThis British Standard is the UK implementation of IEC 60951-1:2009.The UK participation in its preparation was entrusted to Technical CommitteeNCE/8, Reactor instrumentation.A list of organizations represented on this committee can

3、 be obtained onrequest to its secretary.This publication does not purport to include all the necessary provisions of acontract. Users are responsible for its correct application. BSI 2009ISBN 978 0 580 68956 7ICS 13.280; 17.240; 27.120.20Compliance with a British Standard cannot confer immunity from

4、legal obligations.This British Standard was published under the authority of the StandardsPolicy and Strategy Committee on 30 September 2009Amendments issued since publicationAmd. No. Date Text affectedBRITISH STANDARDBS IEC 60951-1:2009IEC 60951-1Edition 2.0 2009-06INTERNATIONAL STANDARD NORME INTE

5、RNATIONALENuclear power plants Instrumentation important to safety Radiation monitoring for accident and post-accident conditions Part 1: General requirements Centrales nuclaires de puissance Instrumentation importante pour la sret Surveillance des rayonnements pour les conditions accidentelles et p

6、ost-accidentelles Partie 1: Exigences gnrales INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE XICS 27.120.20 PRICE CODECODE PRIXISBN 2-8318-1046-1 Registered trademark of the International Electrotechnical Commission Marque dpose de la Commission Electrotechnique

7、 Internationale BS IEC 60951-1:2009 2 60951-1 IEC:2009 CONTENTS FOREWORD.4 INTRODUCTION.6 1 Scope.8 2 Normative references .8 3 Terms and definitions .9 4 Design principles14 4.1 Basic requirements related to functions.14 4.2 Measurement range 16 4.3 Energy response .16 4.4 Minimum detectable activi

8、ty (or limit of detection)16 4.5 Precision (or repeatability).16 4.6 Accuracy (or relative error)17 4.7 Measurement time.17 4.8 Response time 17 4.9 Overload performance.18 4.10 Ambient background shielding or compensation devices .18 4.11 Requirements related to accident conditions .18 4.12 Reliabi

9、lity 19 4.13 User interface19 4.13.1 General .19 4.13.2 Display of measured value.19 4.13.3 Alarms.19 4.13.4 Status indication20 4.13.5 Local indications20 4.14 System testing, maintenance facilities and ease of decontamination .21 4.14.1 System testing.21 4.14.2 Maintenance facilities 21 4.14.3 Eas

10、e of decontamination .21 4.15 Electromagnetic interference .21 4.16 Power supplies22 4.17 Interfaces 22 4.18 Sampling assembly .22 4.19 Quality 23 4.20 Type test report and certificate 24 5 Functional testing .25 5.1 General .25 5.2 General test procedures 25 5.2.1 General .25 5.2.2 Tests performed

11、under standard test conditions 25 5.2.3 Tests performed with variation of influence quantities25 5.2.4 Calculations and/or numerical simulations .26 5.2.5 Reference sources 26 5.2.6 Statistical fluctuations28 5.3 Performance characteristics 28 5.3.1 Reference response 28 5.3.2 Sensitivity and relati

12、ve response for solid sources.28 BS IEC 60951-1:200960951-1 IEC:2009 3 5.3.3 Accuracy (relative error) 29 5.3.4 Response to other artificial radionuclides 30 5.3.5 Response to background radiation.30 5.3.6 Precision (or repeatability).31 5.3.7 Stability of the indication .31 5.3.8 Response time 31 5

13、.3.9 Overload test.32 5.4 Electrical performance tests 33 5.4.1 Alarm trip range.33 5.4.2 Alarm trip stability33 5.4.3 Fault alarm 33 5.4.4 Status indication and fault alarm tests .34 5.4.5 Warm-up time Detection and measuring assembly 34 5.4.6 Influence of supply variations 34 5.4.7 Short circuit w

14、ithstand tests.35 5.5 Environmental performance test 35 5.5.1 Stability of performance after storage 35 5.5.2 Mechanical tests36 5.5.3 Stability of performance with variation of temperature and humidity.37 5.5.4 Electromagnetic compatibility 39 Bibliography44 Table 1 Overview of the standards coveri

15、ng the domain of radiation monitoring.6 Table 2 Reference conditions and standard test conditions41 Table 3 Tests performed under standard test conditions 42 Table 4 Tests performed with variation of influence quantities43 BS IEC 60951-1:2009 4 60951-1 IEC:2009 INTERNATIONAL ELECTROTECHNICAL COMMISS

16、ION _ NUCLEAR POWER PLANTS INSTRUMENTATION IMPORTANT TO SAFETY RADIATION MONITORING FOR ACCIDENT AND POST-ACCIDENT CONDITIONS Part 1: General requirements FOREWORD 1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising all national electrote

17、chnical 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 Specificatio

18、ns, Technical 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,

19、governmental 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 decisi

20、ons or 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 interna

21、tional 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 orde

22、r to promote 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 clea

23、rly indicated in the latter. 5) IEC provides no marking procedure to indicate its approval and cannot be rendered responsible for any equipment declared to be in conformity with an IEC Publication. 6) All users should ensure that they have the latest edition of this publication. 7) No liability shal

24、l 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 damage or other damage of any nature whatsoever, whether direct or indirect, or for costs (including lega

25、l 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 publication. Use of the referenced publications is indispensable for the correct application of this publ

26、ication. 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 such patent rights. International Standard IEC 60951-1 has been prepared by subcommittee 45A: Instrume

27、ntation and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation. This second edition cancels and replaces the first edition published in 1988. This edition constitutes a technical revision. The main technical changes with regard to the previous edition are as follow

28、s. To clarify the definitions. To up-date the references to new standards published since the first issue. To update the units of radiation. BS IEC 60951-1:200960951-1 IEC:2009 5 The text of this standard is based on the following documents: FDIS Report on voting 45A/734/FDIS 45A/756/RVDFull informa

29、tion on the voting for the approval of this 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. A list of all parts of IEC 60951 series, under the general title Nuclear power plants Instrumen

30、tation important to safety Radiation monitoring for accident and post-accident conditions, can be found on the IEC website. The committee has decided that the contents of this publication will remain unchanged until the maintenance result date indicated on the IEC web site under “http:/webstore.iec.

31、ch“ in the data related to the specific publication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition, or amended. BS IEC 60951-1:2009 6 60951-1 IEC:2009 INTRODUCTION a) Technical background, main issues and organisation of the standard This IEC standard sp

32、ecifically focuses on radiation monitoring systems used for accident and post-accident operations. This standard is intended for use by purchasers in developing specifications for their plant-specific radiation monitoring systems and by manufacturers to identify needed product characteristics when d

33、eveloping systems for accident monitoring conditions. Some specific instrument characteristics such as measurement range, required energy response, and ambient environment requirements will depend upon the specific application. In such cases, guidance is provided on determining the specific requirem

34、ents, but specific requirements themselves are not stated. This standard is one in a series of standards covering post-accident radiation monitors important to safety. The full series is comprised of the following standards. IEC 60951-1 General requirements IEC 60951-2 Equipment for continuous off-l

35、ine monitoring of radioactivity in gaseous effluents and ventilation air IEC 60951-3 Equipment for continuous high range area gamma monitoring IEC 60951-4 Equipment for continuous in-line or on-line monitoring of radioactivity in process streams b) Situation of the current standard in the structure

36、of the IEC SC 45A standard series The IEC 60951 series of standards are at the third level in the hierarchy of SC 45A standards. They provide guidance on the design and testing of radiation monitoring equipment used for accident and post-accident conditions. Other standards developed by SC 45A and S

37、C 45B provide guidance on instruments used for monitoring radiation as part of normal operations. The IEC 60761 series provides requirements for equipment for continuous off-line monitoring of radioactivity in gaseous effluents in normal conditions. IEC 60861 provides requirements for equipment for

38、continuous off-line monitoring of radioactivity in liquid effluents in normal conditions. IEC 60768 provides requirements for equipment for continuous in-line and on-line monitoring of radioactivity in process streams in normal and incident conditions. Finally, ISO 2889 gives guidance on gas and par

39、ticulate sampling. The relationship between these various radiation monitoring standards is given in Table 1. Table 1 Overview of the standards covering the domain of radiation monitoring Developer ISO SC 45A Process and safety monitoring Scope Sampling circuits and methods Accident and post-acciden

40、t conditions Normal and incident conditions SC 45B Radiation protection and effluents monitoring Gas, particulate and iodine with sampling (OFF LINE) ISO 2889 IEC 60951-1 and IEC 60951-2 IEC 60761 series and IEC 62302 (noble gases only) Liquid with sampling (OFF LINE) N/A N/A IEC 60861 Process strea

41、ms (gaseous effluents, steam or liquid) without sampling (ON or IN-LINE) N/A IEC 60951-1 and IEC 60951-4 IEC 60768 N/A Area monitoring N/A IEC 60951-1 and IEC 60951-3 IEC 60532 BS IEC 60951-1:200960951-1 IEC:2009 7 Developer ISO SC 45A Process and safety monitoring Scope Sampling circuits and method

42、s Accident and post-accident conditions Normal and incident conditions SC 45B Radiation protection and effluents monitoring Central system N/A IEC 61504 IEC 61559 series For more details on the structure of the IEC SC 45A standard series, see the item d) of this introduction. c) Recommendations and

43、limitations regarding the application of this standard It is important to note that this Standard establishes no additional functional requirements for safety systems. d) Description of the structure of the IEC SC 45A standard series and relationships with other IEC documents and other bodies docume

44、nts (IAEA, ISO) The top-level document of the IEC SC 45A standard series is IEC 61513. It provides general requirements for I it shall be specified by the plant designer. The manufacturer shall specify the minimum detectable activity (or limit of detection) for nuclides of interest, taking into acco

45、unt the check sources or provisions incorporated to provide an on-scale indication on the monitor, as well as all useful data needed to specify the beginning of the effective range of measurement, even in transient operating conditions. The influence quantities, their range of values and the variati

46、on they cause on the minimum detectable activity (or limit of detection) shall be specified. 4.5 Precision (or repeatability) Precision (or repeatability) is a measure of the dispersion of the estimations around their average value. It shall be given by the manufacturer in the effective range of mea

47、surement in % of the signal value for a given confidence interval (or probability of error). Assuming that the estimations follow a Gaussian distribution, this probability should be expressed in terms of a number of standard deviations. NOTE For example, the precision could be 20 % of the signal val

48、ue within a part of the effective range of measurement with a probability of 95 % (meaning that all the estimations are within 2, with the standard deviation), and 30 % within another part of the effective range of measurement with another probability. BS IEC 60951-1:200960951-1 IEC:2009 17 Precisio

49、n shall be consistent with accident analysis assumptions, operator needs, and requirements imposed by other systems that use the radiation monitoring signals. Moreover, they shall be characterized for signal values below the beginning of the effective range of measurement. The influence quantities, their range of values and the variation they cause on precision shall be specified by the manufacturer. Typically, the precision should be w