IEEE 1082-1997 - IEEE Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations.pdf

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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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.Introduction(This introduction is not part of IEEE Std 1082-1997, IEEE Guide for Inco

22、rporating 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 application of a probabilistic risk assessment(

23、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 reliability analysis (HRA), systematically incorpo

24、rated 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 reliability in the mid-1970s was vividly demonst

25、rated 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 by TMI. This conference has become a series,

26、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 interface of incorporating and performing an

27、 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 of HRA has occurred. Most PRAs performHRA in

28、 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 necessary to include human reliability in risk as

29、sessments. 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 information. Since human error has been found to be an

30、 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-cially true regarding the quantification of Hum

31、an 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 technology they work.ParticipantsDuring the initial d

32、evelopment 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 SC7 and assumed acting chairmanshipof WG7.4. D

33、uring balloting and final editing, R. J. Christensen chaired SC7 and continued with the activi-Copyright 1997 IEEE. All rights reserved. iiities performed by WG7.4. The following list represents the membership of SC7 that attended the meetingsand contributed to the effort:Raymond J. Christensen, Cha

34、irOther 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, Chair Richard J. Holleman, Vice ChairAndrew G. S

35、alem, 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. HallB. HallbertL. HanesW. HannamanW. KleinW. Liv

36、ingstonC. 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. CarfagnoRobert C. CarruthRaymond J. ChristensenRo

37、bert 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 KasturiJames T. KeiperAlex MarionJohn R. Mat

38、rasR. 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 IsaakBen C. JohnsonLowell JohnsonRobert KennellyE.

39、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. Wolfmaniv Copyright 1997 IEEE. All rights reserved.Contents1. Overview 11.1

40、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 Screen human interactions . 94.5 Characterize h

41、uman 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) Bibliography 17Copyright 1997 IEEE. All rights reserv

42、ed. vCopyright 1997 IEEE. All rights reserved. viIEEE 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 interactions into probabi-listic risk assessments (

43、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 (HRA) framework is developed from standard pr

44、actices 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 clause.2.1 cognitive process: An internal hu

45、man 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 assessment of the state of the system.2.4 eve

46、nt: (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 occur.Copyright 1997 IEEE. All rights rese

47、rved. 1IEEEStd 1082-1997 IEEE GUIDE FOR INCORPORATING HUMAN ACTION RELIABILITY ANALYSIS2.6 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 evaluated to determine how the undesirable sys

48、temfailure 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 actions that affects equipment, response of sys

49、tems, 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.2.14 skill: A cognitive and/or physical control