1、ANSI/ANS-8.26-2007criticality safety engineer trainingand qualification programANSI/ANS-8.26-2007REAFFIRMED May 31, 2012ANSI/ANS-8.26-2007 (R2012)December 15, 2016ANSI/ANS-8.26-2007 (R2016) This standard has been reviewed and reaffirmed with the recognition that it may reference other standards and
2、documents that may have been superseded or withdrawn.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 original references
3、 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 graded approach to quali
4、ty assurance. Users should consider the use of these industry initiatives in the application of this standard. ANSI/ANS-8.26-2007American National StandardCriticality Safety Engineer Trainingand Qualification ProgramSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards
5、CommitteeWorking Group ANS-8.26Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved June 20, 2007by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests tha
6、tthe 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; these proced
7、ures 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.An American
8、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-ucts, proces
9、ses, 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 ofits approval
10、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 standardare caution
11、ed 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 should be s
12、ent 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 byAmerican Nuc
13、lear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2007 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-8.26-2007 with permission of the publisher,the
14、 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 American National Standard, “Criticality Safety EngineerTraining and Qualif
15、ication Program,” ANSI0ANS-8.26-2007.!Appendix A of ANSI0ANS-8.1-1998 R2007! reminds us that the few criticalityaccidents that occurred worldwide resulted from a failure to anticipate theunexpected in fissionable material handling and processing operations. To be acriticality safety engineer, one mu
16、st not only be familiar with nuclear criticalityand the factors that influence it but also recognize that criticality safety is onlymeaningful within the context of fissionable material operations. Minimizing therisk of a criticality accident to an acceptable level within the scope of operationsis t
17、he basic function of every person who works in the field of criticality safety.This requires personnel who are thoroughly familiar with fissionable materialprocesses and who work in close cooperation with operations personnel andmanagement. The goal of the criticality safety engineer is to assist op
18、eratingpersonnel in the conduct of safe and efficient operations while maintaining anacceptably low risk of a criticality accident.The art and science of nuclear criticality safety are complex. In addition tonuclear physics, an effective criticality safety engineer develops a multidisciplin-ary unde
19、rstanding of electricalsoftware, hardware!, chemical, mechanicalstruc-tural, heat transfer!, material, industrial procedural, ergonomic!, humanperformance behavioral!, and economic issues related to fissionable materialprocess control.Key elements of an effective training program include an understa
20、nding of theimpact of controlled parameters on the reactivity of a defined system and anability to effectively predict the reactivity of a system or process. A careful reviewof lessons learned from previous criticality accidents and other site-specificnonconformances can also be considered.Training
21、to the program content elements in this standard can enable criticalitysafety engineers to become effective advocates to foster a nuclear safetyconscious workforce and sound nuclear safety practices in support of facilityoperations personnel. One key element of the training program is practicalexper
22、ience with the parameters that affect the neutron multiplication of fission-able material systems. This experience can be achieved through hands-on criti-cality safety courses, conduct of experiments in a research reactor environment,or participation in critical experiments.This standard provides gu
23、idance for the content of training programs for nuclearcriticality safety specialists who are responsible for developing the analyses,controls, and safety documentation required for the safe handling of fissionablematerials. This standard presents a matrix of training and qualification criteriabased
24、 on education and experience combined with individual job functions andprovides for qualification of experienced staff by documentation. This standardstresses the necessity to integrate standard training subjects with operationalexperience in order to qualify as a criticality safety engineer.This st
25、andard does not specify how to develop or execute these training andqualification programs; it provides only the elements that should be included inthe programs. It is not intended that these programs lead to any professionalengineer certification, only that they create a common basis for criticalit
26、y safetyengineer qualification across the diverse organizations that rely on these spe-cialists. Standard criteria for establishing scopes, functions, and levels of com-petence for safety professionals are available in ASSE0ANSI Z590.2-2003 andASSE0ANSI Z590.1-200X, published or in draft form by the
27、 American Society ofSafety Engineers.iThis standard was prepared by the ANS-8.26 Working Group, which had thefollowing membership at the time of publication:J. A. Morman Chair!, Argonne National LaboratoryW. A. Blyckert, Mohr and AssociatesK. J. Carroll, BWXT Y-12M. R. Crowell, IndividualJ. R. Felty
28、, Science Applications International CorporationA. S. Garcia, U.S. Department of EnergyC. M. Hopper, Oak Ridge National LaboratoryS. F. Kessler, Lawrence Livermore National LaboratoryR. A. Knief, XE CorporationB. L. Lee, BWXT Y-12J. N. McKamy, National Nuclear Security AdministrationL. E. Paulson, G
29、E/Global Nuclear FuelAmericasR. E. Pevey, University of TennesseeC. L. Pope, Idaho National LaboratoryT. D. Powell, U.S. Nuclear Regulatory CommissionC. E. Reed, BWX Technologies, Inc.K. H. Reynolds, BWXT Y-12B. J. Rumble, NISYS CorporationN. F. Schwers, Sandia National LaboratoriesJ. T. Stewart, De
30、partment for TransportUnited KingdomF. E. Trumble, Washington Safety Management Solutions, LLCR. E. Wilson, U.S. Department of EnergyThis standard was prepared under the guidance of Subcommittee 8, FissionableMaterials Outside Reactors, of the American Nuclear Society. Subcommittee 8had the followin
31、g membership at the time this standard was approved:T. P. McLaughlin Chair!, Los Alamos National LaboratoryJ. A. Schlesser Secretary!, Washington Safety Management Solutions, LLCF. M. Alcorn, IndividualH. D. Felsher, U.S. Nuclear Regulatory CommissionA. S. Garcia, U.S. Department of EnergyN. Harris,
32、 British Nuclear Fuels, PLCB. O. Kidd, BWXT Y-12R. A. Libby, Pacific Northwest National LaboratoryD. A. Reed, Oak Ridge National LaboratoryT. A. Reilly, IndividualH. Toffer, Fluor Federal ServicesG. E. Whitesides, IndividualConsensus Committee N16, Nuclear Criticality Safety, had the following mem-b
33、ership at the time of approval:C. M. Hopper Chair!, Oak Ridge National LaboratoryR. A. Knief Vice-Chair!, XE CorporationG. H. Bidinger, IndividualR. D. Busch, University of New MexicoR. S. Eby, American Institute of Chemical EngineersM. A. Galloway, U.S. Nuclear Regulatory CommissionC. D. Manning, A
34、REVA NPS. P. Murray, Health Physics SocietyR. E. Pevey, University of TennesseeR. L. Reed, Washington Safety Management Solutions, LLCB. M. Rothleder, U.S. Department of EnergyW. R. Shackelford, Nuclear Fuel Services, Inc.R. G. Taylor, IndividualR. M. Westfall, Oak Ridge National LaboratoryL. L. Wet
35、zel, BWX Technologies, Inc.R. E. Wilson, U.S. Department of EnergyiiContentsSection Page1 Introduction . 12 Scope . 13 Definitions 14 Management responsibilities . 15 Criticality safety engineer qualification levels . 26 Training and qualification program . 27 General training and qualification area
36、s 38 Documentation of the training and qualification program 49 References 4 iii Criticality Safety Engineer Trainingand Qualification Program1 IntroductionBoth ANSI0ANS-8.1-1998 R2007!1#1!andANSI0ANS-8.19-2005 2# require that manage-ment provide personnel who are skilled in theinterpretation of dat
37、a and analyses pertinentto nuclear criticality safety and who are famil-iar with operations to provide technical advice.This standard defines and presents guidelinesfor the content of a training and qualificationprogram for nuclear criticality safety engineers.This standard defines three categories
38、of crit-icality safety engineers and differentiates thecategories by experience and knowledge. Foreach of these categories, general guidance isprovided in the form of essential competenciesthat address the broad classes of functions typ-ically carried out by the nuclear criticality safetystaff. This
39、 standard presents only content ele-ments. It is left to management to create andimplement specific training programs to en-sure that the nuclear criticality safety staff isvested with the necessary knowledge and ex-perience for specific job tasks.2 ScopeThis standard presents the fundamental con-te
40、nt elements of a training and qualification pro-gram for individuals with responsibilities forperforming the various technical aspects of crit-icality safety engineering. The standard presentsa flexible array of competencies for use by man-agement to develop tailored training and quali-fication prog
41、rams applicable to site-specific jobfunctions, facilities, and operations.3 Definitions3.1 LimitationsThe definitions given below are of a restrictednature for the purpose of this standard. Otherspecialized terms are defined in Glossary ofTerms in Nuclear Science and Technology 3#.3.2 Shall, should,
42、 and mayThe word “shall” is used to denote a require-ment; the word “should” is used to denote a rec-ommendation; and the word “may” is used todenote permission, neither a requirement nor arecommendation.3.3 Glossary of termscriticality safety staff: The collection of crit-icality safety engineers,
43、senior criticality safetyengineers, criticality safety engineers in train-ing, and other criticality safety technical sup-port personnel.facility: This word is used throughout the stan-dard in a manner consistent with existing, op-erating facilities; however, it is also intendedto apply to facilitie
44、s that have ceased opera-tions i.e., in the decommissioning phase!,fa-cilities that have not yet been built i.e., in thedesign stage!, operations with fissionable ma-terials outside structurese.g., below-grade stor-age and disposal sites!, and the movement ofmaterials between on-site facilities.nucl
45、ear criticality safety: Protection againstthe consequences of a criticality accident, pref-erably by prevention of the accident.nuclear criticality safety evaluationNCSE!:A formal, technically reviewed analysis thatestablishes the technical bases, limits, and con-trols for the nuclear criticality sa
46、fety of a givenoperation.4 Management responsibilities4.1 Training and qualification programANSI0ANS-8.19-20052#requires managementto establish a training and qualification pro-gram for nuclear criticality safety staff. Theprogram shall include requirements for demon-1!Numbers in brackets refer to c
47、orresponding numbers in Sec. 9, “References.”1stration that competency in the content ele-ments listed in Sec. 7 has been achieved.At the discretion of management, certain re-quirements of Sec. 7 may be deferred until theresources required to meet those requirementsare available.2!In such cases, pro
48、visional qual-ification may be given to the criticality safetyengineer until the deferred training is com-pleted. Such deferrals shall be provided for inthe training program document and recordedin the criticality safety engineers trainingrecord.4.2 Program reviewThe effectiveness of the criticality
49、 safety engi-neer training and qualification program shallbe reviewed periodically. The interval betweenreviews shall not exceed three years. Manage-ment shall ensure that such reviews are con-ducted and documented.5 Criticality safety engineerqualification levelsThree levels of criticality safety engineer qual-ification are defined by this standard. Qualifi-cation to these levels shall be achieved byparticipation in a training and qualificationprogram that encompasses the content ele-ments given in Sec. 7 of this standard. Thefollowing sections summarize the q
