ANSI IEEE 1082-1997 Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations《核电站采纳人类行为可靠性分析的指南》.pdf

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1、The Institute of Electrical and Electronics Engineers, Inc.345 East 47th Street, New York, NY 10017-2394, USACopyright 1997 by the Institute of Electrical and Electronics Engineers, Inc.All rights reserved. Published 1997. Printed in the United States of America.ISBN 1-55937-957-XNo part of this pub

2、lication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written per-mission of the publisher.IEEE Std 1082-1997(R2010)IEEE Guide for Incorporating Human Action Reliability Analysis forNuclear Power Generating StationsSponsorNuclear Power Engineering

3、Committeeof theIEEE Power Engineering SocietyApproved 16 September 1997Reaffirmed 20 September 2010IEEE Standards BoardApproved 27 April 1998Reaffirmed 11 August 2011American National Standards InstituteAbstract: A structured framework for the incorporation of human/system interactions into probabil

4、istic riskassessments is provided.Keywords: human reliability analysis (HRA), probabilistic risk assessment (PRA)IEEE Standards documents are developed within the IEEE Societies and the Standards CoordinatingCommittees of the IEEE Standards Association (IEEE-SA) Standards Board. The IEEE develops it

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20、f any individual standard for internal or personal use is granted by the Insti-tute of Electrical and Electronics Engineers, Inc., provided that the appropriate fee is paid to Copyright ClearanceCenter. To arrange for payment of licensing fee, please contact Copyright Clearance Center, Customer Serv

21、ice,222 Rosewood Drive, Danvers, MA 01923 USA; +1 978 750 8400. Permission to photocopy portions of any indi-vidual standard for educational classroom use can also be obtained through the Copyright Clearance Center.Copyright 1997 IEEE. All rights reserved. iiiIntroduction(This introduction is not pa

22、rt of IEEE Std 1082-1997, IEEE Guide for Incorporating Human Action Reliability Analysisfor Nuclear Power Generating Stations.)Any process that requires manual control to minimize public risk will require a high level of human reliabil-ity. This reliability can be evaluated through the systematic ap

23、plication of a probabilistic risk assessment(PRA). However, such an assessment requires a detailed understanding of human factors to form a completereliability estimate.The initial risk assessment made in the nuclear power plant industry, WASH-1400, recognized the need for adiscipline of human relia

24、bility analysis (HRA), systematically incorporated within the PRA enterprise. Butthe methodologyboth of analyzing human failure events and identifying and incorporating them appropri-ately in the PRAwas new, incomplete, and in several ways inadequate.The limitations of the understanding of human rel

25、iability in the mid-1970s was vividly demonstrated by theaccident at Three Mile Island (TMI). Following TMI, the Nuclear Regulatory Commission (NRC), inconjunction with the Institute of Electrical and Electronics Engineers (IEEE), immediately called for aconference on the human factor issues raised

26、by TMI. This conference has become a series, the fifth ofwhich was held in Monterey, California, in 1992. Parallel to this activity, Subcommittee 7, Human Factorsand Control Facilities, of the Nuclear Power Engineering Committee, began discussing the standardizationof the HRA technology. The PRA/HRA

27、 interface of incorporating and performing an HRA in the context ofa PRA was recognized as the most mature of the efforts of HRA. A guide, the least mandating of the IEEEstandards documents, was approved as an IEEE standards project in 1984. In recent years, some convergence in the ideas and methods

28、 of HRA has occurred. Most PRAs performHRA in a standard way, even when using approaches as diverse as the Systematic Human Action ReliabilityProcedure of the Electric Power Research Institute (EPRI) and the Accident Sequence Evaluation ProgramHRA method of the NRC.This guide outlines the steps nece

29、ssary to include human reliability in risk assessments. It is not its intent todiscuss the details of HRA methods, since this technology is evolving and cannot be addressed in the neededdepth in this guide. The reader is urged to review bibliography entries B1, B2, B5, B12, and B22 forthis informati

30、on. Since human error has been found to be an important contributor to risk, this guide under-scores the systematic integration of the HRA at the earliest stages and throughout the PRA.It is anticipated that human reliability technology will not escape controversy in the near future. This is espe-ci

31、ally true regarding the quantification of Human Error Probabilities, which is not specifically addressed inthis guide. In one sense this is a blessing, since it may ensure that the industries do not become complacentto the contribution of people and their actions to the risk spectrum of the technolo

32、gy they work.ParticipantsDuring the initial development of this guide, R. E. Hall was chair of WG7.2 and D. Schurman was secretary.WG7.2 split into WG7.2 and WG7.4. E. M. Dougherty chaired WG7.4, which assumed responsibility forthis guide. During the final stages of development, R. E. Hall chaired S

33、C7 and assumed acting chairmanshipof WG7.4. During balloting and final editing, R. J. Christensen chaired SC7 and continued with the activi-iv Copyright 1997 IEEE. All rights reserved.ties performed by WG7.4. The following list represents the membership of SC7 that attended the meetingsand contribut

34、ed to the effort:Raymond J. Christensen, ChairOther individuals who have contributed review and comments are as follows:The following persons were on the balloting committee:When the IEEE Standards Board approved this guide on 16 September 1997, it had the followingmembership:Donald C. Loughry, Chai

35、r Richard J. Holleman, Vice ChairAndrew G. Salem, Secretary*Member EmeritusAlso included are the following nonvoting IEEE Standards Board liaisons:Satish K. AggarwalAlan H. CooksonValerie E. ZelentyIEEE Standards Project EditorB. BellR. ConsidineA. DykesB. DolanE. DoughertyS. FlegerJ. FragolaR. Hall

36、B. HallbertL. HanesW. HannamanW. KleinW. LivingstonC. ReillyT. RyanD. SchurmanA. SpurginR. StarkeyA. StaveT. VossR. WatersJ. WreathallJ. ZgliczynskiL. AveryW. BanksR. Fuld G. LapinskyL. SothSatish K. AggarwalVincent P. BacanskasFarouk D. BaxterWes W. BowersDan F. BrosnanNissen M. BursteinS. P. Carfa

37、gnoRobert C. CarruthRaymond J. ChristensenRobert L. CopyakJ. J. DisoswayGary L. DomanEdward F. DowlingRich E. DulskiSurinder DurejaJay ForsterJ. R. FragolaJohn M. GallagherWil C. GangloffLuis C. GonzalezLawrence P. GradinJ. K. GreeneBritton P. GrimRobert E. HallJoe T. HazeltineGregory K. HenrySonny

38、KasturiJames T. KeiperAlex MarionJohn R. MatrasR. B. MillerBurt NemroffNeil P. SmithPeter SzabadosJames E. ThomasRaymond WeronickG. O. Wilkins onDavid J. ZapraznyMark S. ZarClyde R. CampStephen L. DiamondHarold E. EpsteinDonald C. FleckensteinJay Forster*Thomas F. GarrityDonald N. HeirmanJim IsaakBe

39、n C. JohnsonLowell JohnsonRobert KennellyE. G. “Al” KienerJoseph L. Koepfinger*Stephen R. LambertLawrence V. McCallL. Bruce McClungMarco W. MigliaroLouis-Franois PauGerald H. PetersonJohn W. PopeJose R. RamosRonald H. ReimerIngo RschJohn S. RyanChee Kiow TanHoward L. WolfmanCopyright 1997 IEEE. All

40、rights reserved. vContents1. Overview 11.1 Scope 11.2 Purpose. 12. Definitions . 13. Overview of an integrated HRA 23.1 Overall evaluation issues . 23.2 HRA process 34. Details of the HRA process . 54.1 Select and train team 64.2 Familiarize team with plant . 84.3 Build initial plant model 84.4 Scre

41、en human interactions . 94.5 Characterize human interactions 104.6 Quantify human interactions 114.7 Evaluate additional recoverability . 114.8 Update plant model 124.9 Review results 125. Documentation. 13Annex A (informative) An example for documenting HRA data . 14Annex B (informative) Bibliograp

42、hy 17Copyright 1997 IEEE. All rights reserved. viCopyright 1997 IEEE. All rights reserved. 1IEEE Guide for Incorporating Human Action Reliability Analysis forNuclear Power Generating Stations1. Overview1.1 ScopeThis guide provides a structured framework for the incorporation of human/system interact

43、ions into probabi-listic risk assessments (PRAs).1.2 PurposeThe purpose of this guide is to enhance the analysis of human/system interactions in PRAs, to help ensurereproducible conclusions, and to standardize the documentation of such assessments. To do this, a specifichuman reliability analysis (H

44、RA) framework is developed from standard practices to serve as a benchmarkto assess alternative ways of incorporating HRA into PRA.2. DefinitionsSeveral terms used in this guide are important, yet are ambiguous in common usage or not used frequentlyenough to be well known. They are defined in this c

45、lause.2.1 cognitive process: An internal human activity that receives, manipulates, and stores knowledge or infor-mation, or that controls actions according to this knowledge.2.2 consequences: The result(s) of (i.e., events that follow and depend upon) a specified event.2.3 diagnosis: A cognitive as

46、sessment of the state of the system.2.4 event: (A) Any change in conditions or performance of interest. (B) An occurrence at a specific point intime.2.5 event tree: A graphical representation of the logical progression of the possible scenarios through amultiple series of events that may, or may not

47、 occur.IEEEStd 1082-1997 IEEE GUIDE FOR INCORPORATING HUMAN ACTION RELIABILITY ANALYSIS2 Copyright 1997 IEEE. All rights reserved.2.6 fault tree: A graphical representation of an analytical technique whereby an undesired state of a systemis specified and the patterns leading to that state can be eva

48、luated to determine how the undesirable systemfailure can occur.2.7 framework: A conceptual system of tasks or activities used in a specified type of analysis.2.8 human action: The observable result (often a bodily movement) of a persons intention.2.9 human interaction: A human action or set of acti

49、ons that affects equipment, response of systems, orother human actions.2.10 model: An analog representation, which may be conceptual, qualitative, or quantitative.2.11 recovery: A set of interactions intended to restore failed equipment or to find alternatives to achieve itsfunction.2.12 reliability unit: That portion of a system for which a single reliability model is valid, i.e., for whichthere is a single mechanism of failure.2.13 rule: (A) A series of steps or activities with a single known or anticipated result. (B) A guideline foracting or planning action.2.