1、IEEE Std 382-2006(Revision of IEEE Std 382-1996) IEEE Standard for Qualification of Safety-Related Actuators for NuclearPower Generating StationsI E E E3 Park Avenue New York, NY 10016-5997, USA15 March 2007IEEE Power Engineering SocietySponsored by theNuclear Power Engineering CommitteeIEEE Std 382
2、-2006(Revision ofIEEE Std 382-1996)IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of theIEEE Power Engineering SocietyApproved 6 December 2006IEEE-SA Standards BoardThe Institute of Electrical and Electron
3、ics Engineers, Inc.3 Park Avenue, New York, NY 10016-5997, USACopyright 2007 by the Institute of Electrical and Electronics Engineers, Inc.All rights reserved. Published 15 March 2007. Printed in the United States of America.IEEE is a registered trademark in the U.S. Patent +1 978 750 8400. Permissi
4、on to photocopy portions of any indi-vidual standard for educational classroom use can also be obtained through the Copyright Clearance Center.iv Copyright 2007 IEEE. All rights reserved.IntroductionIEEE Std 382-2006, a revision of IEEE Std 382-1996, is based on a review of IEEE Std 382-1996, presen
5、tpractices in equipment qualification, as well as, recent updates to mother standards IEEE Std 323-2003and IEEE Std 344-2004.aThe following issues were clarified or changed in this revision:a) Removed “Qualification cases” and Annex B. The environmental parameters provided conflictedwith IEEE Std 32
6、3-2003, which eliminated double peaks and values for environmental conditions.Moreover, the values provided were not relevant for new plant construction.b) Removed Annex C “Rational for normal thermal aging.” The methodology presented in Annex C isnot unique to actuators and is covered by IEEE Std 3
7、23-2003, IEEE Std 1205-2000, and IEEE Std101-1987. c) Revised Clause 2 “References.” Updated the references to reflect current revisions of IEEE Std 323-2003 and IEEE Std 344-2004, and added IEEE Std 1205-2000 and IEEE Std 101-1987 tocompensate for the removal of Annex C from IEEE Std 382.d) Revised
8、 6.3.2 “Test sequence and requirements.” Eliminated the requirement that the test sequencebe performed in the sequence presented and clarified that the purpose of the test sequence is to placethe actuator in its worst case end-of-life condition prior to the design basis event. Addedintermediate insp
9、ections between each step in the test sequence to reflect current practices andprovide data for condition monitoring. Added cycle aging to the test sequence whereas they wereimplicitly in the “Qualification cases” Part II of IEEE Std 382-1996.e) Added new clause entitled “Cycle aging test” to Part I
10、I “Tests” section of this standard to provideguidance as to the purpose and test requirements for the cycle aging test. Added flexibility for thenumber of cycles performed with the main requirement being that the number of cycles berepresentative for the application. Added guidance for how to incorp
11、orate manufacturersrecommended maintenance intervals into the qualification process.f) Moved definitions that are shared with IEEE Std 323-2003 and IEEE Std 344-2004 to the Glossaryin Annex D.g) Revised Clause 1 and Clause 4 of this standard to use the same wording and methods as presented inthe mot
12、her standard IEEE Std 323-2003.h) Revised 6.1 “Type test parameter values” to reflect the fact that the environmental parameters havebeen removed from this standard (i.e., Part II “Qualification cases,” and Annex B of IEEE Std 382-1996 were deleted). This section is now better aligned with IEEE Std
13、323-2003.aInformation on references can be found in Part I, Clause 2.This introduction is not part of IEEE Std 382-2006, IEEE Standard for Qualification of Safety-Related Actuatorsfor Nuclear Power Generating Stations.Copyright 2007 IEEE. All rights reserved. vNotice to usersErrataErrata, if any, fo
14、r this and all other standards can be accessed at the following URL: http:/standards.ieee.org/reading/ieee/updates/errata/index.html. Users are encouraged to check this URL forerrata periodically.InterpretationsCurrent interpretations can be accessed at the following URL: http:/standards.ieee.org/re
15、ading/ieee/interp/index.html.PatentsAttention is called to the possibility that implementation of this standard may require use of subject mattercovered by patent rights. By publication of this standard, no position is taken with respect to the existence orvalidity of any patent rights in connection
16、 therewith. The IEEE shall not be responsible for identifyingpatents or patent applications for which a license may be required to implement an IEEE standard or forconducting inquiries into the legal validity or scope of those patents that are brought to its attention.ParticipantsAt the time this st
17、andard was completed, the Working Group on Qualification of Actuators (SC 2.3) had thefollowing membership: William F. Sadowski, ChairPat G. McQuillian, Past ChairThe Subcommittee on Qualification (SC2) of Nuclear Power Engineering Committee that recommendedapproval of this standard had the followin
18、g membership:Satish K. Aggarwal, ChairThomas R. Hencey III, SecretaryChris AbernathySatish K. AggarwalNissen M. BursteinJerry DanielsJames F. GleasonEdward MohtashemiTed NeckowiczChad SmithToni WittamoreBohumil BartonicekPaul D. BaughmanAnup K. BeheraSteven D. BensonBrij BharteeyThomas BrewingtonNis
19、sen M. BursteinSteve CasadevallSuresh ChannarasappaGarry V. ChapmanJavier A. ChicoteSun Yeong ChoiChoon-Hoon ChungJames M. DeanLiviu Nicolae DelceaDennis E. DellingerPhilip DiBenedettoMichael DoughertyQuang H. DuongFrank DrummYasutaka EguchiWalter EmersonArtur J. FayaWells D. FargoRobert FrancisJame
20、s F. GleasonWilliam L. HadovskiHideo HaradaPeter HelanderJerrell C. HenleyDirk C. HoppDavid A. HorvathYao-Tung HsuIn-Koo HwangCraig S. IrishSerena A. JagtianiFrank W. KloerSushant KapurMohsin KhanHenry LeungBruce M. LoryPat G. McQuillanDaniel R. MikowTodd MittonAsif MohiuddinEdward MohtashemiCarole
21、Monchy-Leroyvi Copyright 2007 IEEE. All rights reserved.At the time this standard was approved, the Nuclear Power Engineering Committee (NPEC) had thefollowing membership:John Disosway, ChairJohn MacDonald, SecretaryThe following members of the individual balloting committee voted on this standard.
22、Balloters may havevoted for approval, disapproval, or abstention. Bill Newell James ParelloJanez PavsekJan S. PirrongDaniel J. PomereningRobert QueenanEdward L. QuinnJohn M. RichardsFred RoySteve SandbergGlen E SchinzelRoderick SimmsKjell SpangRichard G. StarckHirotsugu SuzukiMarek TenglerMarco Van
23、UffelenLaszlo VargaCarl WeberJohn WhelessJohn WhiteToni WittamoreRichard T. WoodToshio YamamotoSatish K. AggarwalIjaz AhmadGeorge AttarianGeorge BallassiFarouk D. BaxterBrij M. BharteeyWesley W. BowersDaniel F. BrosnanNissen M. BursteinRobert C. CarruthJohn P. CarterStephen A. FlegerRobert J. Fletch
24、erRobert FuldJames GleasonDale T. GoodneyBritton P. GrimWilliam L. HadovskiDavid A. HorvathPaul R. JohnsonHarvey C. LeakeJ. Scott MalcolmAlexander MarionMichael H. MillerGerald L. NicelyRoger D. ParkerJames ParelloGlen E. SchinzelNeil P. SmithJames E. StonerJames E. ThomasJohn WacloJohn WhitePaul L.
25、 YanosyDavid J. ZapraznySatish K. AggarwalGary E. ArntsonMunnu BajpaiWilliam G. BloetheWesley W. BowersThomas N. BrewingtonDaniel F. BrosnanNissen M. BursteinRobert C. CarruthNorbert N. CarteSuresh ChannarasappaGarry V. ChapmanDanila ChernetsovTommy P. CooperJohn DisoswayGary R. EngmannWells D. Farg
26、oStephen A. FlegerJames F. GleasonL. GradinRandall C. GrovesAjit K. GwalKuljit S. HaraWolfgang B. HaverkampHamidreza HeidarisafaDavid A. HorvathDennis HorwitzPaul R. Johnson Jr. James H. JonesJoseph L. KoepfingerG. L. LuriJohn D. MacDonaldOmar S. MazzoniJohn E. Merando, Jr. Gary L. MichelArthur S. N
27、eubauerMichael S. Newman Charles Kamithi NgetheJames ParelloMichael A. Roberts Fredrick L. Roy Bartien SayogoJohn H. Taylor James E. Thomas Mark A. Tillinghast James W. Wilson, Jr. David J. Zaprazny Copyright 2007 IEEE. All rights reserved. viiWhen the IEEE-SA Standards Board approved this standard
28、on 6 December 2006, it had the followingmembership:Steve M. Mills, ChairRichard H. Hulett, Vice ChairDon Wright, Past ChairJudith Gorman, Secretary*Member EmeritusAlso included are the following nonvoting IEEE-SA Standards Board liaisons:Satish K. Aggarwal, NRC RepresentativeRichard DeBlasio, DOE Re
29、presentativeAlan H. Cookson, NIST RepresentativeCatherine BergerIEEE Standards EditorMatthew CegliaIEEE Standards Program Manager, Technical Program DevelopmentMark D. BowmanDennis B. BrophyWilliam R. GoldbachArnold M. GreenspanRobert M. GrowJoanna N. GueninJulian Forster*Mark S. HalpinKenneth S. Ha
30、nusWilliam B. HopfJoseph L. Koepfinger*David J. LawDaleep C. MohlaT. W. OlsenGlenn ParsonsRonald C. PetersenTom A. PrevostGreg RattaRobby RobsonAnne-Marie SahazizianVirginia C. SulzbergerMalcolm V. ThadenRichard L. TownsendWalter WeigelHowad L. Wolfmanviii Copyright 2007 IEEE. All rights reserved.Co
31、ntents1. Overview 11.1 Scope 11.2 Purpose. 12. Normative references. 13. Definitions . 24. Introduction 24.1 General. 24.2 Requirements . 35. Identification of the generic actuator group. 35.1 Generic actuator group identification 35.2 Selection of actuator units for type testing 46. Qualification t
32、esting of selected actuators in generic actuator group 46.1 Type test parameter values 46.2 Type test plan. 56.3 Type test procedure 66.4 Inspection. 66.5 Acceptance criteria 76.6 Generic actuator group design modification 77. Qualification of actuator for specific application 87.1 General. 87.2 Act
33、uator specification 87.3 Relationship to generic actuator group 87.4 Relationship to specification 98. Documentation. 98.1 General. 98.2 Documentation for qualification of generic actuator group. 108.3 Documentation for qualification for a specific application . 109. Baseline functional test 109.1 S
34、cope 119.2 Test setup requirements . 119.3 Test conduct. 1110. Normal thermal aging test 1210.1 Scope 1210.2 Test setup requirements . 12Copyright 2007 IEEE. All rights reserved. ix10.3 Test conduct. 1211. Normal radiation aging test 1211.1 Scope 1211.2 Test setup requirements . 1211.3 Test conduct.
35、 1312. Cycle aging test 1312.1 Scope 1312.2 Test setup requirements . 1312.3 Test conduct. 1313. Normal pressurization cycle test 1413.1 Scope 1413.2 Test setup requirements . 1413.3 Test conduct. 1414. Vibration aging test 1414.1 Scope 1414.2 Test setup requirements . 1414.3 Test conduct. 1515. Sei
36、smic simulation test 1515.1 Scope 1515.2 Test setup requirements . 1515.3 Test conduct. 1516. DBE radiation exposure test 1916.1 Scope 1916.2 Test setup requirements . 1916.3 Test conduct. 1917. DBE environment test 1917.1 Scope 1917.2 Test setup requirements . 1917.3 Test conduct. 19Annex A (inform
37、ative) Method of selection of representative actuator(s) for type testing. 21Annex B (informative) Rationale for vibration and seismic test methods 25Annex C (informative) Performance verification test . 27Annex D (informative) Glossary . 28Annex E (informative) Bibliography. 30Copyright 2007 IEEE.
38、All rights reserved. 1IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating StationsPart IProcess1. Overview1.1 ScopeThis standard establishes criteria for qualification of safety-related actuators, and actuator components, inNuclear Power Generating Stations in or
39、der to demonstrate their ability to perform their intended safetyfunctions. 1.2 PurposeThe purpose of this standard is to provide direction for the implementation of the requirements of IEEE Std323-2003 as they apply to the specific features of safety-related actuator qualification.2. Normative refe
40、rencesThe following referenced documents are indispensable for the application of this document. For datedreferences, only the edition cited applies. For undated references, the latest edition of the referenceddocument (including any amendments or corrigenda) applies.Code of Federal Regulations, Tit
41、le 10, Energy-Nuclear Regulatory Commission, Part 100, Jan. 1996.11CFR publications are available from the Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washing-ton, DC 20013-7082, USA (http:/www.gpoa.gov/).IEEEStd 382-2006 IEEE STANDARD FOR QUALIFICATION OF SAFETY-RE
42、LATED2 Copyright 2007 IEEE. All rights reserved.IEEE Std 323-2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power GeneratingStations.2, 3IEEE Std 344-2004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment forNuclear Power Generating Stations 2IEEE Std 101-
43、1987 (Reaff 2004), IEEE Guide for the Statistical Analysis of Thermal Life Test Data. IEEE Std 1205-2000, IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1EEquipment Used in Nuclear Power Generating Stations.3. DefinitionsFor the purposes of this document, the following t
44、erms and definitions apply. The Authoritative Dictionaryof IEEE Standard Terms B34should be referenced for terms not defined in this clause.3.1 actuator: An electric, pneumatic, hydraulic, or electrohydraulic power-driven mechanism forpositioning two-position or modulating valves, and dampers. Inclu
45、ded are those components required tocontrol valve action and to provide valve position output signals, as defined in the actuator specification.3.2 generic actuator group: The actuator or family of actuators within a range of sizes with similar designprinciples, materials, manufacturing processes, l
46、imiting stresses, operating principles and design margins.3.3 motive power: The electric, fluid, air, nitrogen, or mechanical energy required to operate the actuator.3.4 ratio set: A set of performance parameter values described by a range of numerical values whoseboundaries have been established by
47、 doubling and halving the numerical mean value of a selected physicalperformance parameter.3.5 test operating cycle: The movement of an actuator through its required operations travel under specifiedloading conditions, terminating with a return to the starting position.3.6 type test: Tests made on o
48、ne or more sample actuators to verify adequacy of design and themanufacturing processes.4. Introduction4.1 GeneralThe primary objective of qualification is to demonstrate with reasonable assurance that safety-relatedactuators for which a qualified life or condition has been established can perform t
49、heir safety function(s)without experiencing common-cause failures before, during, and after applicable design basis events.Safety-related actuators, with their interfaces, must meet or exceed the equipment specificationrequirements. This continued capability is ensured through a program that includes, but is not limited to,design control, quality control, qualification, installation, maintenance, periodic testing, and surveillance.The focus of this standard is on qualification, although it affects the other parts of the program.2IEEE publications are availabl
