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1、| | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | BRITISH STANDARD BS IEC 62118:2000 ICS 27.
2、120.10 NO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAW Nuclear reactor instrumentation Pressurized water reactor (PWR) of VVER design Monitoring adequate cooling within the core during cold shutdown Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006
3、, Uncontrolled Copy, (c) BSI This British Standard, having been prepared under the direction of the Engineering Sector Committee, was published under the authority of the Standards Committee and comes into effect on 15 April 2001 BSI 04-2001 ISBN 0 580 36881 5 BS IEC 62118:2000 Amendments issued sin
4、ce publication Amd. No.DateComments National foreword This British Standard reproduces verbatim IEC 62118:2000 and implements it as the UK national standard. The UK participation in its preparation was entrusted to Technical Committee NCE/8, Reactor instrumentation, which has the responsibility to:
5、aid enquirers to understand the text; present to the responsible international/European committee any enquiries on the interpretation, or proposals for change, and keep the UK interests informed; monitor related international and European developments and promulgate them in the UK. A list of organiz
6、ations represented on this committee can be obtained on request to its secretary. From 1 January 1997, all IEC publications have the number 60000 added to 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
7、to the other, publications may contain identifiers from both systems. Cross-references The British Standards which implement international or European publications referred to in this document may be found in the BSI Standards Catalogue under the section entitled International Standards Corresponden
8、ce Index, or by using the Find facility of the BSI Standards Electronic Catalogue. A British Standard does not purport to include all the necessary provisions of a contract. Users of British Standards are responsible for their correct application. Compliance with a British Standard does not of itsel
9、f confer immunity from legal obligations. Summary of pages This document comprises a front cover, an inside front cover, the IEC title page, pages 2 to 28, an inside back cover and a back cover. The BSI copyright notice displayed in this document indicates when the document was last issued. Licensed
10、 Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI NORME INTERNATIONALE CEI IEC INTERNATIONAL STANDARD 62118 Premire dition First edition 2000-11 Instrumentation des racteurs nuclaires Racteurs eau pressurise (REP) de type VVER Surveillance du refroidi
11、ssement correct du coeur pendant les tats darrt Nuclear reactor instrumentation Pressurized water reactor (PWR) of VVER design Monitoring adequate cooling within the core during shutdown Commission Electrotechnique Internationale International Electrotechnical Commission BS IEC 62118:2000 Licensed C
12、opy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 CONTENTS Page FOREWORD 4 INTRODUCTION 5 Clause 1Scope and object. 6 2Normative references. 6 3Definitions and abbreviations. 7 4Operating conditions 9 4.1General 9 4.2Normal power operation.1
13、0 4.3Hot shutdown operations .10 4.4Abnormal and accident conditions .10 4.5Cold shutdown operations11 5Measurement methods11 5.1General .11 5.2RPV water level measuring devices.12 5.2.1Differential pressure measurement 12 5.2.2Heated sensor measurement .13 5.3RPV inlet/outlet pipe water level measu
14、ring devices (systems as shown in figure 2).13 5.3.1Differential pressure measurement 13 5.3.2Ultrasonic liquid level monitoring14 5.4Core exit temperature sensing devices 14 5.4.1Core exit thermocouples 14 5.4.2RPV outlet pipe temperature14 5.4.3RHRS temperature (systems as shown in figure 2) 14 6I
15、nstrumentation requirements14 6.1General .14 6.1.1Safety classification.15 6.1.2Accuracy and response time 15 6.1.3Reliability.15 6.1.4Single failure considerations 15 6.2Differential pressure measurement 16 6.2.1Differential pressure transmitters .16 6.2.2Reference columns 16 6.2.3Differential pres
16、sure tap locations16 6.2.4Hydraulic instrument line installations 17 6.2.5Hydraulic instrument line temperature18 6.2.6Type and quality of the fluid in the instrument lines18 6.3Heated sensor measurement .18 6.4Ultrasonic liquid level measurement.18 6.4.1Application.18 6.4.2Accuracy and time respons
17、e 18 6.4.3Installation considerations19 6.4.4Special human machine interface considerations.19 6.5Temperature sensing devices 19 BS IEC 62118:2000 2 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 ClausePage 7 Data processing19 8
18、 Presentation of information.19 9 Verification and calibration20 10In-service testing and maintenance.20 11Qualification .20 12Documentation20 Annex A (informative) Events with potential core cooling degradation at VVERs 26 Annex B (informative) Plant operating states27 Figure 1 PWR configuration: (
19、VVER-440) Horizontal steam generators 21 Figure 2 PWR configuration: (VVER-1000) Horizontal steam generators 22 Figure 3 Water level measurement by differential pressure method for VVER 1000. 23 Figure 4 Thermal-hydraulic considerations affecting water level measurements (VVER-1000 systems) at reduc
20、ed inventory and reverse flow. 24 Figure 5 Water level measurement by direct acting transmitter (VVER-1000 systems) at reduced inventory and reverse flow 25 BS IEC 62118:2000 3 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 INTE
21、RNATIONAL ELECTROTECHNICAL COMMISSION _ NUCLEAR REACTOR INSTRUMENTATION PRESSURIZED WATER REACTOR (PWR) OF VVER DESIGN MONITORING ADEQUATE COOLING WITHIN THE CORE DURING SHUTDOWN FOREWORD 1)The IEC (International Electrotechnical Commission) is a worldwide organization for standardization comprising
22、 all national electrotechnical committees (IEC National Committees). The object of the 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, the IEC publishes International St
23、andards. 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 preparation. The IE
24、C 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 the IEC on technical matters express, as nearly as possible, an international consensus of
25、 opinion on the relevant subjects since each technical committee has representation from all interested National Committees. 3)The documents produced have the form of recommendations for international use and are published in the form of standards, technical specifications, technical reports or guid
26、es and they are accepted by the National Committees in that sense. 4) In order to promote international unification, IEC National Committees undertake to apply IEC International Standards transparently to the maximum extent possible in their national and regional standards. Any divergence between th
27、e IEC Standard and the corresponding national or regional standard shall be clearly indicated in the latter. 5) The IEC provides no marking procedure to indicate its approval and cannot be rendered responsible for any equipment declared to be in conformity with one of its standards. 6) Attention is
28、drawn to the possibility that some of the elements of this International Standard may be the subject of patent rights. The IEC shall not be held responsible for identifying any or all such patent rights. International Standard IEC 62118 has been prepared by subcommittee 45A: Reactor instrumentation,
29、 of IEC technical committee 45: Nuclear instrumentation. The text of this standard is based on the following documents: FDISReport on voting 45A/400A/FDIS45A/403/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. Th
30、is publication should be read in conjunction with IEC 60911. This publication has been drafted in accordance with the ISO/IEC Directives, Part 3. Annexes A and B are for information only. The committee has decided that the contents of this publication will remain unchanged until 2006. At this date,
31、the publication will be reconfirmed; withdrawn; replaced by a revised edition, or amended. BS IEC 62118:2000 4 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 INTRODUCTION Adequate core cooling can be achieved only by providing s
32、ufficient coolant flow to the core to remove the heat. During normal power operations, core cooling is adequately controlled and monitored by reactor control and protection systems, and cooling is maintained by forced circulation with the pumps of the Reactor Coolant System (RCS). During hot or cold
33、 shutdown operations, core cooling can be provided by different means such as forced circulation with the RCS pumps, natural circulation of the coolant or by the Residual Heat Removal System (RHRS). During certain abnormal conditions cooling must even rely on stationary boiling of the coolant. It is
34、 important that plant operators have reliable information concerning the coolant conditions and inventory in the Reactor Pressure Vessel (RPV). This information is usually related to the core, expressed specifically as the coolant temperature, pressure, flow and water level relative to the top of th
35、e core. It is also important that plant operators have reliable information concerning subcooling of the coolant and its time history to assess abnormal conditions. The information must be available for all conditions, including cold shutdown since core cooling interruptions have occurred at several
36、 VVERs. Annex A, which lists some of these events, identifies conditions which should be considered in the design of core cooling monitoring instrumentation. BS IEC 62118:2000 5 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 NUC
37、LEAR REACTOR INSTRUMENTATION PRESSURIZED WATER REACTOR (PWR) OF VVER DESIGN MONITORING ADEQUATE COOLING WITHIN THE CORE DURING SHUTDOWN 1 Scope and object This International Standard applies to pressurized water reactors (PWRs) of VVER design with configurations similar to those shown in figures 1 a
38、nd 2, and presents the requirements for monitoring adequate cooling within the core during hot and cold shutdown conditions. Annex B provides more information on VVER operating states. Good international practices to be used when designing new or upgrading existing core cooling monitors for VVER sys
39、tems are summarized in this standard. This standard does not consider the design details of the different VVER technological systems designs, except to the extent that the design affects the monitoring of core cooling. Requirements are given for core cooling monitoring instrumentation to ensure the
40、safe operation of VVERs during abnormal operation and during and after design basis accidents (DBA). Requirements for core cooling monitoring during conditions beyond a DBA, which could be a specific national requirement or consideration, are not covered here. The core cooling monitoring instrumenta
41、tion has to function under widely different conditions. The circumstances under which this instrumentation needs to function are described. Descriptions of diverse measuring principles and suitable devices are given along with requirements for the following: ? operational conditions; ? installation;
42、 ? operator displays; ? testing, calibration and maintenance; ? equipment qualification; ? documentation; ? redundancy. 2 Normative references The following normative documents contain provisions which, through reference in this text, constitute provisions of this International Standard. For dated r
43、eferences, subsequent amendments to, or revisions of, any of these publications do not apply. However, parties to agreements based on this International Standard are encouraged to investigate the possibility of applying the most recent editions of the normative documents indicated below. For undated
44、 references, the latest edition of the normative document referred to applies. Members of IEC and ISO maintain registers of currently valid International Standards IEC 60050(393):1996, International Electrotechnical Vocabulary (IEV) Chapter 393: Nuclear Instrumentation Physical phenomena and basic c
45、oncepts IEC 60737:1982, In-core temperature or primary envelope temperature measurements in nuclear power reactors Characteristics and test methods BS IEC 62118:2000 6 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:25 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BSI 04-2001 IEC 60770-1:1
46、999, Transmitters for use in industrial-process control systems Part 1: Methods for performance evaluation IEC 60780:1998, Nuclear power plants Electrical equipment of the safety system Qualification IEC 60880:1986, Software for computers in the safety systems of nuclear power stations IEC 60911:198
47、7, Measurements for monitoring adequate cooling within the core of pressurized light water reactors IEC 60964:1989, Design for control rooms of nuclear power plants IEC 60980:1989, Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating sta
48、tions IEC 60987:1989, Programmed digital computers important to safety for nuclear power stations IEC 61225:1993, Nuclear power plants Instrumentation and control systems important for safety Requirements for electrical supplies IEC 61226:1993, Nuclear power plants Instrumentation and control system
49、s important for safety Classification IEC 61227:1993, Nuclear power plants Control rooms Operator controls IEC 61343:1996, Nuclear reactor instrumentation Boiling light water reactors (BWR) Measurements in the reactor vessel for monitoring adequate cooling within the core IAEA Safety Guide 50-SG-D8:1984, Safety related instrumentation and control systems for nuclear power plants 3 Definitions and abbreviations For the purpose of this International Standard, the following definitions