ANSI ANS 10.4-2008 verification and validation of non-safety-related scientific and engineering computer programs for the nuclear industry《核工业科研和工程用计算机程序的验证和确认导则》.pdf

《ANSI ANS 10.4-2008 verification and validation of non-safety-related scientific and engineering computer programs for the nuclear industry《核工业科研和工程用计算机程序的验证和确认导则》.pdf》由会员分享，可在线阅读，更多相关《ANSI ANS 10.4-2008 verification and validation of non-safety-related scientific and engineering computer programs for the nuclear industry《核工业科研和工程用计算机程序的验证和确认导则》.pdf（38页珍藏版）》请在麦多课文档分享上搜索。

1、ANSI/ANS-10.4-2008verification and validation of non-safety-relatedscientific and engineering computer programsfor the nuclear industryANSI/ANS-10.4-2008REAFFIRMED September 26, 2016 ANSI/ANS-10.4-2008; R2016 This standard has been reviewed and reaffirmed with the recognition that it may reference o

2、ther standards and documents that may have been superseded or withdrawn. The requirements of this document will be met by using the version of the standards and documents referenced herein. It is the responsibility of the user to review each of the references and to determine whether the use of the

3、original references or more recent versions is appropriate for the facility. Variations from the standards and documents referenced in this standard should be evaluated and documented. This standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a grade

4、d approach to quality assurance. Users should consider the use of these industry initiatives in the application of this standard. ANSI/ANS-10.4-2008American National StandardVerification and Validation of Non-Safety-RelatedScientific and Engineering Computer Programsfor the Nuclear IndustrySecretari

5、atAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-10.4Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved October 28, 2008by theAmerican National Standards Institute, Inc.AmericanNationalSta

6、ndardDesignation of this document as an American National Standard 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 proc

7、edures of the Standards Committee ofthe American Nuclear Society; 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, conc

8、erned, and varied interests havehad an opportunity to participate.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 notpreclud

9、e anyone from manufacturing, marketing, purchasing, or using prod-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 con

10、tent of this standard reflects acceptable practice at the time ofits 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 tim

11、e in accordance with established procedures. Users of this standardare 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

12、 or by any ad hoc group of individuals.Requests for interpretation 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

13、 encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2008 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmer

14、ican National Standard ANSI0ANS-10.4-2008 with permission of the publisher,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

15、of American National Standard “Verification and Validationof Non-Safety-Related Scientific and Engineering Computer Programs for the NuclearIndustry,” ANSI0ANS-10.4-2008.!The purpose of this standard is to provide guidelines for the verification andvalidation VANSI0ANS-10.5-2006, “Accommodating User

16、 Needs in Scientific and Engineer-ing Computer Software Development”;ANSI0ANS-10.2-2000, “Portability of Scientific and Engineering Software.”In addition, an effort has been made to maintain consistency in terminology andconcepts with various software standards being developed under the sponsorshipo

17、f the Institute of Electrical and Electronics Engineers, Inc., and to identifyareas of disagreement.Compliance with this standard does not substitute for compliance with regula-tory requirements. For example, any analysis that requires a 10 CFR Part 50Appendix B quality assurance program would still

18、 require one whether or not itconforms with this standard.Charles R. Martin was the working group chair for much of the development ofthis standard. His contributions are gratefully acknowledged.This standard has been written by Working Group ANS-10.4 of the AmericanNuclear Societys Standards Commit

19、tee. The membership of this group duringthe preparation of the final drafts consisted of the following:A. O. Smetana Chair!, Savannah River National LaboratoryB. L. Kirk, Oak Ridge National LaboratoryJ. B. Manneschmidt, Oak Ridge National LaboratoryK. A. Morrell, Savannah River Nuclear Solutions, LL

20、CC. R. Martin, U.S. Defense Nuclear Facilities Safety BoardSubstantial contributions toward the development of the earlier drafts of thisstandard have also been received from the following:H. Hunter, Oak Ridge National LaboratoryT. M. Lloyd, BNG Fuel SolutionsY. Orechwa, U.S. Nuclear Regulatory Comm

21、issionD. Peercy, Sandia National LaboratoriesH. S. Hopkins, Lawrence Livermore National LaboratoryK. OKula, Westinghouse Safety Management SolutionsC. A. Sparrow, Mississippi State UniversityR. G. Quirk, U.S. Defense Nuclear Facilities Safety BoardR. C. Singleterry, Jr., NASA Langley Research Center

22、J. Pardo, Savannah River Nuclear Solutions, LLCD. Sparkman, U.S. Department of EnergyT. Austin, Bechtel NationalD. D. Brayton, Safer ServicesG. Danielson, U.S. Department of EnergyiJ. R. Shultz, U.S. Department of EnergyS. S. Seth, U.S. Department of EnergyR. C. Schrotke, Jr., Battelle Northwest Nat

23、ional LaboratoryR. W. Stevens, Jr., U.S. Department of EnergySubcommittee ANS-10, Mathematics and Computation, had the following mem-bership at the time of its approval of this standard:A. O. Smetana Chair!, Savannah River National LaboratoryB. R. Frank, Westinghouse Electric Company, LLCJ. B. Manne

24、schmidt, Oak Ridge National LaboratoryB. L. Kirk, Oak Ridge National LaboratoryR. C. Singleterry, Jr., NASA Langley Research CenterC. R. Martin, U.S. Defense Nuclear Facilities Safety BoardP. P. H. Wilson, University of Wisconsin-MadisonY. Orechwa, U.S. Nuclear Regulatory CommissionC. A. Sparrow, Mi

25、ssissippi State UniversityE. L. Quinn, Longenecker and AssociatesThe American National Standards Committee N17, Research Reactors, ReactorPhysics, and Radiation Shielding, had the following membership at the time itreviewed and approved this standard:T. M. Raby Chair!, National Institute of Standard

26、s and TechnologyA. Weitzberg Vice Chair!, IndividualS. Anderson, Westinghouse Electric Company, LLCW. H. Bell, American Institute of Chemical EngineersAlt. R. D. Zimmerman, American Institute of Chemical Engineers!R. R. Brey, Health Physics SocietyR. E. Carter, IndividualD. M. Cokinos, Brookhaven Na

27、tional LaboratoryM. L. Corradini, National Council on Radiation Protection and MeasurementsE. Ehrlich, General ElectricB. K. Grimes, IndividualN. E. Hertel, Georgia Institute of TechnologyC. Heysel, McMaster UniversityW. A. Holt, IndividualW. C. Hopkins, IndividualM. A. Hutmaker, Jr., U.S. Departmen

28、t of EnergyA. C. Kadak, Massachusetts Institute of TechnologyL. I. Kopp, IndividualP. M. Madden, U.S. Nuclear Regulatory CommissionAlt. A. Adams, Jr., U.S. Nuclear Regulatory Commission!J. F. Miller, Institute of Electrical and Electronics EngineersJ. E. Olhoeft, IndividualR. E. Pevey, University of

29、 Tennessee-KnoxvilleW. J. Richards, National Institute of Standards and TechnologyC. T. Rombough, CTR Technical Services, Inc.T. R. Schmidt, Sandia National LaboratoriesS. H. Shepherd, IndividualA. O. Smetana, Savannah River National LaboratoryR. R. Tsukimura, Aerotest OperationsA. R. Veca, General

30、AtomicsS. H. Weiss, National Institute of Standards and TechnologyAlt. T. J. Myers, National Institute of Standards and Technology)iiContentsSection Page1 Scope and objective . 11.1 Scope . 11.2 Objective 11.3 Guidance for applying this standard 12 Definitions . 13 Introduction and overview 24 Overv

31、iew of V complexity;regulatory requirements; and American Na-tional Standards Institute0American NuclearSocietyANSI0ANS-10.5-2006, “AccommodatingUser Needs in Scientific and Engineering Com-puter Software Development,” intended use ofthe program.Application of this standard is expected to pro-vide m

32、aterial for use in a quality assuranceprogram. This standard does not recommend aparticular approach toward quality assurance.Questions about frequency of reviews or au-dits, resolution of discrepancies, or responsibil-ity for configuration control are not within thescope of this standard.2 Definiti

33、onsIn the context of this standard, the followingdefinitions apply.non-safety-related: Software whose failurewould not create a hazard to a facility, worker,or member of the general public.validation: a! The process of testing a com-puter program and evaluating the results toensure compliance with s

34、pecified require-ments. b! The demonstration that the verifiedcomputer programand by inference the math-ematical model! are an adequate representa-tion of the physical phenomena.verification: The process of evaluating theproducts of a software development activity toprovide assurance that they meet

35、the require-ments defined for them.Verification and validation is abbreviatedthroughout the standard as Vmanagement plan;requirements specification;design specification;program documentationusers manual, tech-nical manual, etc.!;source code;integrated program;installation package;test plan;VV the de

36、sign specification isverified against the requirements specifica-tion; and the source code is examined to ensureconsistency with the design specification.The criteria presented in this document de-pend upon the availability of a document stat-ing the requirements that a computer programmust satisfy.

37、 Because of the research basis ofmost scientific program development, how-ever, it is often not possible to provide a prioria complete requirements specification. Whatconstitutes a valid answer or appropriate algo-rithm is often not known until after differentapproaches have been tried and their res

38、ultsevaluated. In such cases an iterative approachis recommended that allows the requirementsto be refined or respecified as results fromdifferent activities of program development be-come available. The final program documenta-tion and the final Vrequirements definition;design;coding;integration an

39、d testing;installation;operation and maintenance.Table 1 provides a summary of Vthe general Vthe level of effort applied to each activity;the assignment of testing responsibilities;the procedures for incorporating V description of inputs in the ap-plication shall be provided to allow for testplannin

40、g.The VVschedule of VVVsummary of Vdevelopment materials evaluated;Vtools and techniques used;Vsecurity and control procedures followed;deviations from the VAmerican National Standard ANSI0ANS-10.4-20085Vanalyst who detected the discrepancy;description of the discrepancy;severity rating high,medium,

41、orlow!;impact of the discrepancy;recommended resolution.5.2 Verification of requirementsThe requirements specification forms the foun-dation for program development. It identifiesthe functions to be performed; the inputs, out-puts, and interfaces required; the accuracy andtiming that must be achieve

42、d; the models tobe used; and the acceptance criteria for theprogram.The requirements specification also forms thefoundation for V2! Testing is performed by the software de-veloper. In addition, testing is performed byanother developer without reference to theoriginal developers test plan, test datab

43、ase,or test results;3! Testing is performed by the software de-veloper. In addition, an organizationally in-dependent Vapproach to conducting tests and evaluat-ing test resultsH18537 requirements to be tested,H18537 acceptance criteria for each requirement,H18537 methods to be used for conducting th

44、etests,H18537 methods to be used to evaluate test re-sults and determine compliance with eachrequirement;American National Standard ANSI0ANS-10.4-20086test problem descriptions;test case specifications test cases are sim-plified test problems set up in order to dem-onstrate a specific capability of

45、the program!H18537 description of each test caseH18537H18537 unique identification,H18537H18537 objectives of the test case features tobe tested!,H18537H18537 input data,H18537H18537 expected results,H18537H18537 evaluation criteria,H18537H18537 relation to other tests,H18537H18537 rationale for tes

46、t setup,H18537H18537 hardware and software environmentin which tests will be run;plan for test databaseH18537 building,H18537 updating,H18537 maintaining,H18537 recording test output in the test database;test proceduresH18537 step-by-step instructions for execution oftest cases, evaluation of test r

47、esults, anddisposition of test output;planned reporting formats and proceduresH18537 discrepancy reports,H18537 test case log,H18537test report.Note that much of the information specified inthe test plan is developed later during programdevelopment. The test plan is updated as infor-mation becomes a

48、vailable.5.4 Verification of preliminary testplansTest plans prepared during program definitiondescribe the tests to be used to validate thesoftware product. A preliminary test plan de-fines the scope, objectives, and testing ap-proach; provides an initial description of thetest problems, test cases

49、, and test proceduresthat will be used; and describes the plannedreporting formats and procedures.Verification of a preliminary test plan is per-formed to ensure the following:1! The testing approach is consistent withthe scope and objectives stated in the plan;2! The tests being considered will be ade-quate and sufficient for demonstrating thatthe program conforms with the requirementsspecification;3! The reporting formats and procedures areconsistent with the Vdetailed descriptions of each test case, in-cluding, as applicableH18537 identification of any progra