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1、BRITISH STANDARD BS IEC 61888:2002 Nuclear power plants Instrumentation important to safety Determination and maintenance of trip setpoints ICS 27.120.20 ? Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI BS IEC 61888:2002 This British Standa
2、rd was published under the authority of the Standards Policy and Strategy Committee on 13 March 2003 BSI 13 March 2003 ISBN 0 580 41387 X National foreword This British Standard reproduces verbatim IEC 61888:2002 and implements it as the UK national standard. The UK participation in its preparation
3、was entrusted to Technical Committee NCE/8, Reactor instrumentation, which has the responsibility to: A list of organizations represented on this committee can be obtained on request to its secretary. Cross-references The British Standards which implement international publications referred to in th
4、is document may be found in the BSI Catalogue under the section entitled “International Standards Correspondence Index”, or by using the “Search” facility of the BSI Electronic Catalogue or of British Standards Online. This publication does not purport to include all the necessary provisions of a co
5、ntract. Users are responsible for its correct application. Compliance with a British Standard does not of itself confer immunity from legal obligations. aid enquirers to understand the text; present to the responsible international/European committee any enquiries on the interpretation, or proposals
6、 for change, and keep the UK interests informed; monitor related international and European developments and promulgate them in the UK. Summary of pages This document comprises a front cover, an inside front cover, the IEC title page, pages 2 to 20, an inside back cover an a back cover. The BSI copy
7、right date displayed in this document indicates when the document was last issued. Amendments issued since publication Amd. No. DateComments Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI NORME INTERNATIONALE CEI IEC INTERNATIONAL STANDARD
8、61888 Premire dition First edition 2002-08 Centrales nuclaires de puissance Instrumentation importante pour la sret Dtermination et maintenance des points de consigne Nuclear power plants Instrumentation important to safety Determination and maintenance of trip setpoints Numro de rfrence Reference n
9、umber CEI/IEC 61888:2002 BS IEC 61888:2002 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 68818 ? IEC:0202 2 CONTENTS FOREWORD.3 INTRODUCTION.4 1Scope.5 2Normative references .5 3Definitions 5 4Abbreviations .8 5Determination of setpoints8
10、5.1Safety8 5.2Safety analysis8 5.3Limiting safety system setting (LSSS)9 5.3.1Channel uncertainty and trip setpoint.9 5.3.2Channel uncertainty determination.12 5.3.3Trip setpoint 12 5.3.4Allowable value .12 5.4Combination of uncertainties .13 5.4.1Square-root-sum-of-squares method (SRSS).13 5.4.2Alg
11、ebraic method.13 5.5Operational considerations13 5.6Instrument channel range13 6Documentation .13 7Maintenance of safety system setpoints .14 7.1Testing14 7.2Replacement .15 Annex A (informative) Example of setpoint determination.18 Bibliography20 Figure 1 Nuclear safety-related setpoint relationshi
12、ps16 Figure 2 Process and measurement instrument uncertainties.17 Figure A.1 High reactor pressure setpoint relationships .19 BS IEC 61888:2002 2 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 68818 ? IEC:0202 3 INTERNATIONAL ELECTROTECHNIC
13、AL COMMISSION _ NUCLEAR POWER PLANTS INSTRUMENTATION IMPORTANT TO SAFETY DETERMINATION AND MAINTENANCE OF TRIP SETPOINTS FOREWORD 1)The IEC (International Electrotechnical Commission) is a worldwide organization for standardization comprising all national electrotechnical committees (IEC National Co
14、mmittees). 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 Standards. Their preparation is entrusted to technical commi
15、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. The IEC collaborates closely with the International Organization
16、 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 opinion on the relevant subjects since each technical com
17、mittee 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 guides and they are accepted by the National Committees in tha
18、t 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 the IEC Standard and the corresponding national or regional
19、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 drawn to the possibility that some of the elements of this
20、 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 61888 has been prepared by subcommittee 45A: Reactor instrumentation, of IEC technical committee 45: Nuclear instrumentation. T
21、he text of this standard is based on the following documents: FDISReport on voting 45A/444/FDIS45A/464/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 publication has been drafted in accordance with the ISO/
22、IEC Directives, Part 3. Annex A is for information only. The committee has decided that the contents of this publication will remain unchanged until 2008. At this date, the publication will be reconfirmed; withdrawn; replaced by a revised edition, or amended. BS IEC 61888:2002 3 Licensed Copy: sheff
23、ieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 68818 ? IEC:0202 4 INTRODUCTION The purpose of this International Standard is to provide descriptions and recommendations on how to determine and maintain calculations for instrument setpoints associated with IEC
24、61513. This standard addresses known contributing errors in the channel from the process (including the primary element and sensor) through to and including the final setpoint device. This standard applies to the determination of setpoints used for automatic actions. The recommendations may also be
25、used to determine indicator uncertainties for testing or operator decisions. In general, IAEA NS-R-1 and member country government regulations require that, where an important setpoint is specified for a variable on which a safety limit has been placed, the setting is so chosen that automatic protec
26、tive action will correct the most severe abnormal situation anticipated before a safety limit is exceeded. Inappropriate selection of a setpoint that does not leave a sufficient margin to account for instrument accuracy, the expected environment, and minor calibration variations can result in failur
27、e to trip before a safety limit is exceeded. Protective instruments are provided with setpoints where specific actions are either initiated, terminated or prohibited. Setpoints must be maintained within prescribed limits as defined by the operating licenses through periodic checks of the ability of
28、the channel to perform its function. The single most prevalent reason for the drift of a setpoint out of compliance with a license requirement or technical specification has been the selection of a setpoint that does not allow a sufficient margin between the license or technical specification limit
29、and the actual setting to account for instrument accuracy, the expected environment and minor calibration variations. In some cases, the setpoint selected was numerically equal to the license or technical specification limit and stated as an absolute value, thus leaving no apparent margin for uncert
30、ainties. In other cases, the setpoint was so close to the upper or lower limit of the instruments range that instrument drift placed the setpoint beyond the instruments range, thus nullifying the trip function. Other causes for drift of a setpoint out of conformity with the license or technical spec
31、ifications have been instrument design inadequacies and questionable calibration procedures. BS IEC 61888:2002 4 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 68818 ? IEC:0202 5 NUCLEAR POWER PLANTS INSTRUMENTATION IMPORTANT TO SAFETY DETE
32、RMINATION AND MAINTENANCE OF TRIP SETPOINTS 1 Scope This standard defines the requirements for assuring that automatic setpoints for nuclear safety system instrumentation (as defined in clause 3), are established and maintained within specified limits in nuclear power plants and nuclear reactor faci
33、lities. 2 Normative references The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies. IEC 60050-394:1995
34、, International Electrotechnical Vocabulary (IEV) Chapter 394: Nuclear instrumentation: Instruments IEC 60671, Periodic testing and monitoring of the protective system of nuclear reactors IEC 61513:2001, Nuclear power plants Instrumentation and control for system important to safety General requirem
35、ents for systems IAEA NS-R-1: 2000, Safety of nuclear power plants: Design 3 Definitions For the purposes of this document, the following terms and definitions apply. NOTEAdditional definitions related to instrumentation terminology may be found in IEC 60050-394. 3.1 allowable value a limit value th
36、at the trip setpoint may have when tested periodically, beyond which appropriate action shall be taken 3.2 analytical limit (of setpoint) limit of a measured or calculated variable established by the safety analysis to ensure that a safety limit is not exceeded. The margin between the analytical lim
37、it (of the setpoint) and the safety limit allows to take into account: the response time of the instrument channel, the range of transients due to the considered accident. BS IEC 61888:2002 5 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 6
38、8818 ? IEC:0202 6 3.3 as found the condition in which a channel, or portion of a channel, is found after a period of operation and before recalibration (if necessary) 3.4 as left the condition in which a channel, or portion of a channel, is left after calibration or final setpoint device setpoint ve
39、rification 3.5 drift an undesired change in output over a period of time where change is unrelated to the input, environment, or load 3.6 error the algebraic difference between the indication and the ideal value of the measured signal 3.7 final setpoint device a component, or assembly of components,
40、 that provides input to the process voting logic for actuated equipment NOTEExamples of final setpoint devices are bistables, relays, pressure switches, and level switches. 3.8 foldover a device characteristic exhibited when a further change in the input produces an output signal that reverses its d
41、irection from the specified input-output relationship 3.9 independent uncertainty uncertainty components are independent of each other if their magnitudes or algebraic signs are not significantly correlated 3.10 instrument channel an arrangement of components and modules, including sensor(s), as req
42、uired to generate a single protective action signal when required by a plant condition 3.11 instrument channel range the region between the limits within which a quantity is measured, received, or transmitted. Is expressed by stating the lower and upper instrument channel range values. 3.12 limiting
43、 safety system setting (LSSS) limiting safety system settings for nuclear reactors are settings for automatic protective devices related to those variables having significant safety functions 3.13 nuclear safety system instrumentation electronic and electrical equipment or instruments for ensuring t
44、he proper control and monitoring of a nuclear reactor, including all control and safety system instrumentation BS IEC 61888:2002 6 Licensed Copy: sheffieldun sheffieldun, na, Sun Nov 26 11:45:50 GMT+00:00 2006, Uncontrolled Copy, (c) BSI 68818 ? IEC:0202 7 3.14 primary element the system element tha
45、t quantitatively converts the measured variable energy into a form suitable for measurement 3.15 random variable whose value at a particular future instant cannot be predicted exactly but can only be estimated by a probability distribution function 3.16 reference accuracy number or quantity that def
46、ines a limit that errors will not exceed when a device is used under specified operating conditions 3.17 safety limit a limit on an important process variable, ,necessary to reasonably protect the integrity of physical barriers that guard against the uncontrolled release of radioactivity 3.18 safety
47、 system system important to safety provided to ensure that 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 design basis accident conditions (see IEC 61513) 3.19 saturation device charact
48、eristic exhibited when a further change in the input signal produces no additional change, or progressively less change, in the output 3.20 sensor portion of a channel that responds to changes in a plant variable or condition and converts the measured process variable into a signal, for example, ele
49、ctric or pneumatic 3.21 test interval elapsed time between the initiation (or successful completion) of tests on the same sensor, channel, load group, safety group, safety system, or other specified system or device 3.22 trip setpoint predetermined value for actuation of the final setpoint device to initiate a protective action 3.23 channel uncertainty the amount to which an instrument channels output is in doubt (or the allowance made therefo