BS IEC 60951-3-2009 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Equipment for continuous high rang.pdf

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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 plants Instrumentation important tosafety Radiation monitoringfor accident and post-accidentconditi

2、ons Part 3: Equipment for continuous high range areagamma monitoringBS IEC 60951-3:2009National forewordThis British Standard is the UK implementation of IEC 60951-3:2009.The UK participation in its preparation was entrusted to Technical CommitteeNCE/8, Reactor instrumentation.A list of organization

3、s represented on this committee can 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 68957 4ICS 13.280; 17.240; 27.120.20Compliance with a British S

4、tandard cannot confer immunity fromlegal 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 60951-3:2009IEC 60951-3Edition 2.0 2009-

5、06INTERNATIONAL STANDARD NORME INTERNATIONALENuclear power plants Instrumentation important to safety Radiation monitoring for accident and post-accident conditions Part 3: Equipment for continuous high range area gamma monitoring Centrales nuclaires de puissance Instrumentation importante pour la s

6、ret Surveillance des rayonnements pour les conditions accidentelles et post-accidentelles Partie 3: Ensemble de surveillance locale en continu des rayonnements gamma large gamme INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE MICS 27.120.20 PRICE CODECODE PRIXISB

7、N 2-8318-1046-3 Registered trademark of the International Electrotechnical Commission Marque dpose de la Commission Electrotechnique Internationale 2 60951-3 IEC:2009 CONTENTS FOREWORD.3 INTRODUCTION.5 1 Scope.7 2 Normative references .7 3 Terms and definitions .8 4 Design principles8 4.1 General .8

8、 4.2 Range of measurement .8 4.3 Accuracy (relative error) 8 4.4 Location of sensors .8 4.5 Detector radiation response characteristics .8 4.6 Requirements related to accident conditions .8 5 Functional testing .9 5.1 General .9 5.2 Reference sources 9 5.2.1 General .9 5.2.2 Gamma .9 5.2.3 Beta 9 5.

9、2.4 Neutron .9 5.3 Performance characteristics 10 5.3.1 Reference response 10 5.3.2 Sensitivity and relative response for solid sources.11 5.3.3 Variation of response with angle of incidence 11 Figure 1 Energy response10 Table 1 Overview of the standards covering the domain of radiation monitoring.5

10、 Table 2 Additional tests to complement the general tests required in IEC 60951-1.12 BS IEC 60951-3:200960951-3 IEC:2009 3 INTERNATIONAL ELECTROTECHNICAL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION IMPORTANT TO SAFETY RADIATION MONITORING FOR ACCIDENT AND POST-ACCIDENT CONDITIONS Part 3: Equip

11、ment for continuous high range area gamma monitoring FOREWORD 1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising all national electrotechnical committees (IEC National Committees). The object of IEC is to promote international co-operati

12、on 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, Technical Reports, Publicly Available Specifications (PAS) and Guides (hereafter referred to as “I

13、EC 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, governmental and non-governmental organizations liaising with the IEC also participate in this prepara

14、tion. 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 agreements of IEC on technical matters express, as nearly as possible, an international consens

15、us 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 use and are accepted by IEC National Committees in that sense. While all reasonable efforts are

16、 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 promote international uniformity, IEC National Committees undertake to apply IEC Publications tra

17、nsparently 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 indicated in the latter. 5) IEC provides no marking procedure to indicate its approval and cannot

18、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 shall attach to IEC or its directors, employees, servants or agents including individual experts and membe

19、rs 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 legal fees) and expenses arising out of the publication, use of, or reliance upon, this IEC Publication or

20、 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 publication. 9) Attention is drawn to the possibility that some of the elements of this IEC Publication ma

21、y be the subject of patent rights. IEC shall not be held responsible for identifying any or all such patent rights. International Standard IEC 60951-3 has been prepared by subcommittee 45A: Instrumentation and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation. Thi

22、s second edition cancels and replaces the first edition published in 1989. This edition constitutes a technical revision. The main technical changes with regard to the previous edition as are follows: To clarify the definitions. To update the references to new standards published since the first iss

23、ue. To update the units of radiation. This standard is to be read in conjunction with IEC 60951-1. BS IEC 60951-3:2009 4 60951-3 IEC:2009 The text of this standard is based on the following documents: FDIS Report on voting 45A/736/FDIS 45A/758/RVDFull information on the voting for the approval of th

24、is 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 Instrumentation important to safety Radiation moni

25、toring 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.ch“ in the data related to the specific p

26、ublication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition, or amended. BS IEC 60951-3:200960951-3 IEC:2009 5 INTRODUCTION a) Technical background, main issues and organisation of this standard This IEC standard specifically focuses on radiation monitorin

27、g 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 developing systems for accident monitoring

28、 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 requirements, but specific requirements themselves

29、 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-line monitoring of radioactivity in gaseous

30、 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 of the IEC SC 45A standard series IEC 6095

31、1 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 SC 45B provide guidance on instruments used for

32、 monitoring radiation as part of normal operations. IEC 60761 series provide requirements for equipment for continuous off-line monitoring of radioactivity in gaseous effluents in normal conditions. IEC 60861 provides requirements for equipment for continuous off-line monitoring of radioactivity in

33、liquid effluents in normal conditions. IEC 60768 provides requirement 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 particulate sampling. The relationship between these va

34、rious radiation monitoring standards is given in the Table 1 below. 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-accident conditions Normal and incident condition

35、s 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 streams (gaseous effluents, steam or liquid) wi

36、thout 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 60951-3:2009 6 60951-3 IEC:2009 Developer ISO SC 45A Process and safety monitoring Scope Sampling circuits and methods Accident and post-accident conditions N

37、ormal and incident conditions SC 45B Radiation protection and effluents monitoring Central system N/A IEC 61504 IEC 61559 For more details on the structure of the IEC SC 45A standard series, see item d) of this introduction. c) Recommendations and limitations regarding the application of the standar

38、d 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 documents (IAEA, ISO) The top-level document of the IEC SC

39、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 standard series. IEC 61513 refers directly to other IEC SC 45A standards for general topics related to

40、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 computer-based systems, and control room design. The standards referenced directly at this second lev

41、el 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, technical methods, or specific activities. Usually these documents, which make reference to second-le

42、vel 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 a presentation format similar to the basic safety publication IEC 61508 with an overall safety life

43、-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 with IEC 61513 will facilitate consistency with the requirements of IEC 61508 as they have been in

44、terpreted 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 standards as well as to IAEA 50-C-QA (now replaced by IAEA GS-R-3) for topics related to quality assurance (QA). The IEC SC 45A standard

45、s 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, establishing safety requirements related to the design of Nuclear Power Plants, and the Safety Gu

46、ide 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 IEC 60951-3:200960951-3 IEC:2009 7 NUCLEAR POWER PLANTS INSTRUMENTATION IMPORTANT TO SAFE

47、TY RADIATION MONITORING FOR ACCIDENT AND POST-ACCIDENT CONDITIONS Part 3: Equipment for continuous high range area gamma monitoring 1 Scope This part of IEC 60951 provides general guidance on the design principles and performance criteria for equipment for continuous high range area gamma monitoring

48、 in nuclear power plants for accident and post-accident conditions. General requirements for technical characteristics, test procedures, radiation characteristics, electrical, mechanical, and environmental characteristics are given in IEC 60951-1. These requirements are applicable in this part unles

49、s otherwise stated. This standard is applicable to installed dose rate meters that are used to monitor high levels of gamma radiation during and after an accident. It covers equipment intended to isotropically measure air kerma, ambient dose or other exposure quantities due to gamma radiation of energy between 80 keV and 7 MeV. The equipment is intended primarily for the purpose of nuclear plant safety. Portable instruments for emergency purpo