1、ANSI/ANS-3.5-2009nuclear power plant simulators for usein operator training and examinationANSI/ANS-3.5-2009ANSI/ANS-3.5-2009American National StandardNuclear Power Plant Simulators for Usein Operator Training and ExaminationSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyS
2、tandards CommitteeWorking Group ANS-3.5Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved September 4, 2009by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard
3、 attests thatthe principles of openness and due process have been followed in the approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under procedures of the Standards Committee ofthe American Nuclear Society;
4、these procedures are accredited by the Amer-ican National Standards Institute, Inc., as meeting the criteria for AmericanNational Standards. The consensus committee that approved the standardwas balanced to ensure that competent, concerned, and varied interests havehad an opportunity to participate.
5、An American National Standard is intended to aid industry, consumers, gov-ernmental agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notpreclude anyone from manufacturing, marketing, purchasing, or using prod-
6、ucts, processes, or procedures not conforming to the standard.By publication of this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The content of this standard reflects acceptable practice at the time ofi
7、ts approval and publication. Changes, if any, occurring through developmentsin the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures. Users of this standar
8、dare cautioned to determine the validity of copies in their possession and toestablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individual or by any ad hoc group of individuals.Requests for interpretation
9、 should be sent to the Standards Department atSociety Headquarters. Action will be taken to provide appropriate response inaccordance with established procedures that ensure consensus on theinterpretation.Comments on this standard are encouraged and should be sent to SocietyHeadquarters.Published by
10、American Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2009 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-3.5-2009 with permission of the pu
11、blisher,the American Nuclear Society.” Reproduction prohibited under copyright conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis Foreword is not a part of the American National Standard “Nuclear Power PlantSimulators fo
12、r Use in Operator Training and Examination,” ANSI0ANS-3.5-2009.!The nuclear power industry is currently in a mature phase of operation withencouraging successes in operating license extensions. In addition to life exten-sion activity, there is renewed interest in new construction of nuclear powerpla
13、nts. This fifth revision of the 1979 original standard continues in the philos-ophy of further addressing issues related to maintaining simulators throughoutthe life of commercial nuclear power plants. This revision of the standard doesnot preclude applying the functional requirements and criteria o
14、f this standardto next-generation reactors.ThefirstANS-3.5standard,publishedinJanuary1979,providedessentialrequire-ments for the acquisition of full-scope simulators to support operator training pro-grams. The secondANS-3.5 standard, published inApril 1981, further delineatedspecification requiremen
15、ts. Improvements in testing methods and overall consis-tency were subsequently included in the thirdANS-3.5 standard, published in Oc-tober 1985. The fourth ANS-3.5 standard, published in March 1993, introduced anew testing methodology and processes that effectively integrated training pro-cesses wi
16、th simulator testing and configuration management processes. The fifthANS-3.5 standard, published inApril 1998, further refined the integration of thetraining scenario validation process with the simulator testing process.As the industry matures and performance improves, plants routinely remainonlin
17、e throughout a fuel cycle. This provides fewer operational experience oppor-tunities previously afforded to licensed operators. Excellent plant performancehas also resulted in a more vital role for the simulator in providing operatorswith experience previously obtained in the actual plant. As a resu
18、lt, the impor-tance of a thoroughly tested simulator in providing a high quality training toolcannot be overemphasized.As industry performance continues to improve, accredited operator training pro-grams become a valuable component of a comprehensive simulator test program.This standard recognizes t
19、he current synergy between the traditional simulatortesting processes and training processes that may be used to complement anoverall simulator test program. This revision also recognizes recent changes inU.S. Nuclear Regulatory Commission regulations that eliminated formal simu-lator certification
20、submittal requirements and allows applicants for an operatorlicense to meet experience eligibility requirements on the reference unit simula-tor. The advent of increased regulator and industry oversight group scrutiny ofsimulators also influences this revision. The working group provided formalinput
21、 to the regulatory process to facilitate consistent perspectives.In addition to enhanced readability accomplished by professional technical edi-tors, users of this revision will find improvements and clarifications in theperformance testing methodology, new sections addressing simulator core perfor-
22、mance testing and post-event simulator testing, and other important guidancerequired to ensure accurate simulation for operator training.When a simulator is used for operator training and examination, it is expected tomeet the requirements set forth in this standard.Acknowledgements:This review and
23、revision cycle was fortunate to receive substantial support from adiverse and dedicated group of nuclear simulator experienced professionals rep-resenting many utilities and interested parties. A wide range of utility, indepen-dent,andindustryoversightorganizationparticipation,includingindividualswi
24、thisignificant military and commercial reactor experience, was represented in thisworking group. Input to the development of the standard was received throughvarious means, such as numerous surveys with .95% industry participation aswell as feedback from training and simulator associations. Working
25、group meet-ings were also attended and supported regularly by nonmember participants. Allaspects of power reactor and simulator design, construction, and operation, in ad-dition to extensive operator training and evaluation experience, were availablethroughout this review cycle. The average individu
26、al experience represented ateachworkinggroupmeetingwasapproximately26yearsofdiversenuclearindus-try experience, including 20 years of simulation related experience, and approxi-mately75collectiveyearsofoperatortrainingexperience.Workinggroupcontinuitywas preserved by members with a range of 2 to 24
27、years of working group partici-pation experience. The significant experience available and dedicated participa-tion were effectively used to prioritize and address each important issue.This standard might reference documents and other standards that have beensuperseded or withdrawn at the time the s
28、tandard is applied. A statement hasbeen included in the references section that provides guidance on the use ofreferences.This standard does not incorporate the concepts of generating risk-informedinsights or a graded approach to quality assurance. The user is advised that oneor both of these techni
29、ques could enhance the application of this standard.This standard was prepared by Working Group 3.5 of the Standards Committeeof the American Nuclear Society, which had the following membership:T. Dennis Chair!, individualJ. B. Florence Vice Chair!, Nebraska Public Power District, CooperK. P. Welche
30、l Secretary!, Duke Energy, OconeeF. J. Colby Editor!, L-3 Communications MAPPS, Inc.W. M. Shelly Style Editor!, EntergyL. Vick Parliamentarian!, U.S. Nuclear Regulatory CommissionS. K. Chang, Dominion, MillstoneK. J. Cox, Exelon, DresdenR. A. Felker, Western Services CorporationO. H. Havens, Jr., PS
31、EG Power, LLC, Salem/Hope CreekJ. D. Koutouzis, Institute of Nuclear Power OperationsA. A. Kozak, Dominion, North AnnaG. S. McCullough, American Electric Power, D. C. CookJ. B. Neis, Constellation Energy, GinnaH. O. Paris, GSE Systems, Inc.F. A. Tarselli, PPL Corporation, Susquehanna, LLCCertain hig
32、hly technically qualified individuals provided additional expert as-sistance and advice to the working group during the development of this stan-dard. They were as follows:T. R. Byron, Institute of Nuclear Power OperationsJ. J. Cataudella ANS-3.5 Past Chair!, Dominion, MillstoneJ. F. Collins, U.S. N
33、uclear Regulatory CommissionM. Fedele, CAE, Inc., Aviation SimulationD. Noe, GSE Systems, Inc.B. Panfil, FirstEnergy, PerryD. C. Trimble, U.S. Nuclear Regulatory CommissionM. Wyatt, ExelonSubcommittee ANS-21, Maintenance, Operations, Testing and Training, had thefollowing membership during its revie
34、w of this standard:iiT. Dennis Chair!, IndividualC. H. Moseley, Jr. Vice Chair!, BWXT/Y12N. W. Brown, Lawrence Livermore National LaboratoryC. L. Eldridge, Pacific Gas and Electric CompanyJ. Glover, Graftel, Inc.R. P. Kassawara, Electric Power Research InstituteJ. D. Koutouzis, Institute of Nuclear
35、Power OperationsL. E. Kreider, Engineering Planning and Management, Inc.E. M. Lloyd, Exitech CorporationC. A. Mazzola, Shaw Environmental the common goals, however, areto ensure safety, equipment availability, andefficient operations. This standard provides flex-ibility in the design and use of nucl
36、ear powerplant simulators in meeting these common goals.It is intended that in meeting the criteria ofthis standard, the simulator will be suffi-ciently complete and accurate to meet thetraining needs of the industry as well as therequirements of the NRC, as described in Codeof Federal Regulations,
37、Title 10, “Energy,”Part 55, “Operators Licenses” 10CFR55!1#.2!These requirements provide guidance in deter-mining the content and setting for training andexamination purposes. This standard allows theuse of a training needs assessment in severalareas where the standard may require featuresin excess
38、of the requirements of 10CFR55 1#.The organization of the standard is such thatsimulator functional and physical require-ments described in Sec. 3 correspond to testingand validation requirements described in Sec. 4.The subnumbering of Secs. 3 and 4 is consis-tent so that corresponding section parag
39、raphsaddress the same subject matter from a require-ments and testing standpoint.2 Definitionsbacktrack: To reset the simulator to some priortime in its operation.best estimate: Predicted reference unit perfor-mance data derived from engineering evalua-tion or operational assessment by subject matte
40、rexperts for specific puted values: Parameters representingthe state of reference unit systems or compo-nents that the simulator mathematical modelscalculate.design database: The design documents, per-formance data, records, assumptions, simplifi-cations, derivations, and other definable datathat fo
41、rm the basis of the design of the simu-lator hardware and software.fast time: To increase the rate of simulationfor some or all computed values with respect toreal time.freeze: The controlled pause of simulation.initial condition: A set of data that repre-sents the status of the reference unit from
42、whichreal time simulation can begin.malfunctions: A simulator feature or capabil-ity that provides for instructor-controlled deg-radation of performance of simulated plantcomponents, equipment, or systems. Overridecapability is not considered a malfunction.1!Guidance is provided in Appendix D to ada
43、pt this standard to part-task and limited-scope simulators toensure fidelity appropriate to the intended use for operator training and examination.2!Numbers in brackets refer to corresponding numbers in Sec. 6, “References.”1negative training: Training on a simulatorwhose configuration or performanc
44、e leads theoperator to an incorrect response to or under-standing of the reference unit.noticeable difference: Any difference in thephysical attributes or dynamic response be-tween the simulator and the reference unit thatis distinguishable by an observer and con-firmed by a subject matter expert.op
45、erating procedures: Controlled copies ofprocedures, including normal, abnormal, off-normal, emergency, surveillance, and alarm re-sponse procedures of the reference unit.operator: A licensed operator, or a senior li-censed operator, or a person in training to be alicensed operator or senior licensed
46、 operator.override: To interrupt or modify the input0output I0O! data transfer between the sim-ulator mathematical models and the panelinstrumentation.passive failure: A failure of a component orsystem that does not become evident until theaffected component or system is called upon tofunction.perfo
47、rmance testing: Testing conducted to ver-ify a simulators performance as compared toactual or predicted reference unit performance.physical fidelity: The degree of similarity be-tween the simulator and the reference unit,such as physical location of panels, equipment,instruments, controls, labels, a
48、nd related formand function.real time: Simulation of dynamic performancein the same time base relationships, sequences,durations, rates, and accelerations as the dy-namic performance of the reference unit.reference unit: The specific nuclear powerplant unit, identified by a unique docket num-ber, fr
49、om which the simulator control room con-figuration, system control arrangement, andsimulator design database are derived.repeatability: The capability of the simulatorto have successive tests of its dynamic perfor-mance conducted in the same time base rela-tionships, sequences, durations, rates, andaccelerations that, in turn, produce the sameresults within the limits required by thisstandard.replay: The recording of a simulator trainingsession in such a way that all or a portion of asimulator training exercise can be played back.run: The controlled resumpti
