BS IEC 62705-2014 Nuclear power plants Instrumentation and control important to safety Radiation monitoring systems (RMS) Characteristics and lifecycle《核电厂 具有安全重要性的仪表和控制 辐射监测系统 (RM.pdf

《BS IEC 62705-2014 Nuclear power plants Instrumentation and control important to safety Radiation monitoring systems (RMS) Characteristics and lifecycle《核电厂 具有安全重要性的仪表和控制 辐射监测系统 (RM.pdf》由会员分享，可在线阅读，更多相关《BS IEC 62705-2014 Nuclear power plants Instrumentation and control important to safety Radiation monitoring systems (RMS) Characteristics and lifecycle《核电厂 具有安全重要性的仪表和控制 辐射监测系统 (RM.pdf（26页珍藏版）》请在麦多课文档分享上搜索。

1、BSI Standards PublicationNuclear power plants Instrumentation and controlimportant to safety Radiationmonitoring systems (RMS):Characteristics and lifecycleBS IEC 62705:2014National forewordThis British Standard is the UK implementation of IEC 62705:2014.The UK participation in its preparation was e

2、ntrusted to TechnicalCommittee NCE/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 necessary provisions ofa contract. Users are responsible for its correct application. Th

3、e British Standards Institution 2014.Published by BSI Standards Limited 2014ISBN 978 0 580 75983 3ICS 27.120.20Compliance with a British Standard cannot confer immunity fromlegal obligations.This British Standard was published under the authority of theStandards Policy and Strategy Committee on 31 A

4、ugust 2014.Amendments/corrigenda issued since publicationDate Text affectedBRITISH STANDARDBS IEC 62705:2014IEC 62705 Edition 1.0 2014-07 INTERNATIONAL STANDARD NORME INTERNATIONALE Nuclear power plants Instrumentation and control important to safety Radiation monitoring systems (RMS): Characteristi

5、cs and lifecycle Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la sret Systmes de surveillance des rayonnements (SSR): Caractristiques et cycle de vie INTERNATIONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE S ICS 27.120.20 PRICE COD

6、E CODE PRIX ISBN 978-2-8322-1773-3 Registered trademark of the International Electrotechnical Commission Marque 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

7、obtenu cette publication via un distributeur agr. BS IEC 62705:2014 2 IEC 62705:2014 IEC 2014 CONTENTS FOREWORD . 4 INTRODUCTION . 6 1 Scope 9 2 Normative references 9 3 Terms and definitions 11 4 Abbreviations 13 5 RMS categorization and classification 13 5.1 Function categorization for RMS . 13 5.

8、2 System classification for RMS . 13 6 RMS detailed design and implementation 14 6.1 General . 14 6.2 Radioactive noble gas off-line monitoring 14 6.3 Radioactive aerosol off-line monitoring . 15 6.4 Radioactive iodine off-line monitoring . 15 6.5 Liquid off-line monitoring . 15 6.6 Tritium off-line

9、 monitoring . 15 6.7 On-line or in-line monitoring 16 6.8 Area monitoring 16 6.9 Centralized system . 16 6.10 Leak detection 16 7 RMS integration and validation 16 7.1 RMS integration 16 7.2 RMS validation 16 8 RMS installation 16 9 RMS design modification . 17 10 RMS qualification 17 10.1 General .

10、 17 10.2 Environmental qualification . 17 10.3 Seismic qualification . 17 10.4 Electromagnetic interference. 18 11 Calibration . 18 11.1 General . 18 11.2 Periodical calibration and functional check 18 11.2.1 General . 18 11.2.2 Calibration check after installation . 18 11.2.3 Functional check 18 11

11、.2.4 Countermeasures to loss of monitoring during calibration or functional check . 18 11.3 Radiation calibration . 18 11.4 Calibration for other quantity . 18 11.5 Traceability . 19 Annex A (informative) Example of safety classification for RMS important to safety . 20 Annex B (informative) Relatio

12、n between IEC 61513 system lifecycle and IEC 62705 requirements . 21 BS IEC 62705:2014IEC 62705:2014 IEC 2014 3 Table 1 Overview of the standards covering the domain of radiation monitoring in NPPs 7 Table A.1 Example of safety classification for RMS important to safety 20 Table B.1 Relation between

13、 IEC 61513 system lifecycle and IEC 62705 requirements . 21 BS IEC 62705:2014 4 IEC 62705:2014 IEC 2014 INTERNATIONAL ELECTROTECHNICAL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY RADIATION MONITORING SYSTEMS (RMS): CHARACTERISTICS AND LIFECYCLE FOREWORD 1) The I

14、nternational 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-operation on all questions concerning standardization in the electrical and e

15、lectronic 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 “IEC Publication(s)”). Their preparation is entrusted to technical commi

16、ttees; 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 preparation. IEC collaborates closely with the International Organization for

17、 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 consensus of opinion on the relevant subjects since each technical committee

18、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 made to ensure that the technical content of IEC Publications is accu

19、rate, 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 transparently to the maximum extent possible in their national and region

20、al publications. Any divergence between any IEC Publication and the corresponding national or regional publication shall be clearly indicated in the latter. 5) IEC itself does not provide any attestation of conformity. Independent certification bodies provide conformity assessment services and, in s

21、ome areas, access to IEC marks of conformity. IEC is not responsible for any services carried out by independent certification bodies. 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

22、 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 legal fees) and expenses arising out of the publication, use of, or

23、 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 publication. 9) Attention is drawn to the possibility that some of

24、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 62705 has been prepared by subcommittee 45A: Instrumentation, control and electrical systems of nuclear facilities, of

25、 IEC technical committee 45: Nuclear instrumentation. The text of this standard is based on the following documents: FDIS Report on voting 45A/960/FDIS 45A/973/RVD Full information on the voting for the approval of this standard can be found in the report on voting indicated in the above table. This

26、 publication has been drafted in accordance with the ISO/IEC Directives, Part 2. BS IEC 62705:2014IEC 62705:2014 IEC 2014 5 The committee 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 th

27、e data related to the specific publication. At this date, the publication will be reconfirmed, withdrawn, replaced by a revised edition, or amended. BS IEC 62705:2014 6 IEC 62705:2014 IEC 2014 INTRODUCTION a) Technical background, main issues and organisation of the Standard This IEC standard sets o

28、ut the requirements for the lifecycle management of radiation monitoring system (RMS) installed in the nuclear power plants (NPPs). This standard is applicable to the equipment of RMS and intended to be used during normal operations and anticipated operational occurrences, as well as, for certain mo

29、nitors, in accident conditions. This standard may be applicable to other nuclear facilities (e.g. nuclear fuel storage and processing sites) by evaluating the differences from NPPs. It is intended that the Standard be used by operators of NPPs (utilities), systems evaluators and by licensors. b) Sit

30、uation of the current Standard in the structure of the IEC SC 45A standard series IEC 62705 is the third level in the hierarchy of SC 45A standards. This standard provides guidance on the application of existing IEC/ISO standards covering design and qualification of system and equipment for RMS. Thi

31、s standard is an application supplement of IEC 61513 as shown in Annex B, and it is not intended that this standard limits the application of other IEC 61513 requirements to RMS lifecycle. For general requirements and guidance, the following standards provide requirements and guidance for RMS. IEC 6

32、1513 is the first level standard of SC 45A standards, and provides general requirements for I to measure the volumetric activity in air or gas systems (control room ventilation, reactor leakage collection, drywell ventilation exhaust, fuel handling building ventilation exhaust, reactor building vent

33、ilation purge exhaust) and detect any significant increase of radioactivity. For RMS designed only for normal operation condition, the design and testing of RMS shall be performed in accordance with IEC 60761-1 and IEC 60761-3. Instead of the set of IEC 60761-1 and IEC 60761-3, IEC 62302 may be used

34、 alternatively. For RMS designed for accident conditions, the design and testing of RMS shall be performed in accordance with IEC 60951-1 and IEC 60951-2. Sampling assembly for RMS used for this monitoring shall be designed and tested in accordance with ISO 2889. BS IEC 62705:2014IEC 62705:2014 IEC

35、2014 15 6.3 Radioactive aerosol off-line monitoring RMS for radioactive aerosol off-line monitoring is used for the following purposes: to measure the volumetric activity of radioactive aerosols in gaseous effluents at the discharge point and the variation of volumetric activity. The monitor may als

36、o be used for the determination of the total discharge of radioactive aerosol over a given period; to measure the volumetric activity in air or gas systems (control room ventilation, reactor leakage collection, drywell ventilation exhaust, fuel handling building ventilation exhaust, reactor building

37、 ventilation purge exhaust) and detect any significant increase of radioactivity. For RMS designed only for normal operation condition, the design and testing of RMS shall be performed in accordance with IEC 60761-1 and IEC 60761-2. For RMS designed for accident conditions, the design and testing of

38、 RMS shall be performed in accordance with IEC 60951-1 and IEC 60951-2. Sampling assembly for RMS used for this monitoring shall be designed and tested in accordance with ISO 2889. 6.4 Radioactive iodine off-line monitoring RMS for radioactive iodine off-line monitoring is used for the following pur

39、poses: to measure the volumetric activity of radioactive iodines in gaseous effluents at the discharge point and the variation of volumetric activity. The monitor may also be used for the determination of the total discharge of radioactive iodine over a given period; to measure the volumetric activi

40、ty in air or gas systems (control room ventilation, reactor leakage collection, drywell ventilation exhaust, fuel handling building ventilation exhaust, reactor building ventilation purge exhaust) and detect any significant increase of radioactivity. For RMS designed only for normal operation condit

41、ion, the design and testing of RMS shall be performed in accordance with IEC 60761-1 and IEC 60761-4. For RMS designed for accident conditions, the design and testing of RMS shall be performed in accordance with IEC 60951-1 and IEC 60951-2. Sampling assembly for RMS used for this monitoring shall be

42、 designed and be tested in accordance with ISO 2889. 6.5 Liquid off-line monitoring RMS for continuous liquid off-line monitoring is used for following purposes: to measure the volumetric activity in liquid at the discharge point or the surface water and the variation of volumetric activity. The mon

43、itor may also be used for the determination of the total discharge of radioactive materials in liquid over a given period. The design and testing of RMS shall be performed in accordance with IEC 60861. 6.6 Tritium off-line monitoring RMS for continuous radioactive tritium off-line monitoring is used

44、 for following purposes: to measure the volumetric activity of tritium in gaseous effluents at the discharge point and the variation of volumetric activity. The monitor may also be used for the determination of the total discharge of tritium over a given period. The design and testing of RMS shall b

45、e performed in accordance with IEC 60761-1 and IEC 60761-5. Instead of the set of IEC 60761-1 and IEC 60761-5, IEC 62303 can be used alternatively. BS IEC 62705:2014 16 IEC 62705:2014 IEC 2014 6.7 On-line or in-line monitoring RMS for on-line or in-line monitor is required to provide continuous meas

46、urement; this is normally achieved by positioning the detectors in the process stream (e.g. immersed in, or adjacent to the process stream, in a pipe or tank). For RMS designed only for normal operation condition, the design and testing of RMS shall be performed in accordance with IEC 60768. For RMS

47、 designed for accident conditions, the design and testing of RMS shall be performed in accordance with IEC 60951-1 and IEC 60951-4. 6.8 Area monitoring RMS for area monitoring is used to monitor levels of gamma radiation in NPP. For RMS designed only for normal operation condition, the design and te

48、sting of RMS shall be performed in accordance with IEC 61031 in conjunction with IEC 60532. For RMS designed for accident conditions, the design and testing of RMS shall be performed in accordance with IEC 60951-1 and IEC 60951-3. 6.9 Centralized system The centralized system receives data from plan

49、t-wide monitored radiation information. The centralized system provides the information to operations personnel and performs data recording, data validation, data display, and system control functions. The design and testing for centralized system shall be performed in accordance with IEC 61504 in conjunction with the IEC 61559 series which specify the requirements for centralized system. If the centralized system is a part of the safety parameter display system, the design sha