ANSI ANS 15.4-2007 Selection and training of personnel for research reactors《反应堆研究人员的选择和培训》.pdf

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1、ANSI/ANS-15.4-2007selection and training ofpersonnel for research reactorsANSI/ANS-15.4-2007ANSI/ANS-15.4-2007American National StandardSelection and Trainingof Personnel forResearch ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group AN

2、S-15.4Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved August 17, 2007by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe principles of open

3、ness 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 procedures are accredited by

4、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 National Standard is in

5、tended 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, processes, or procedures not

6、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 and publication. Change

7、s, 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 It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures.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 cautioned to determine the val

8、idity 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 sent to the Standards De

9、partment 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 Nuclear Society555 North K

10、ensington 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-15.4-2007 with permission of the publisher,the American Nuclear Socie

11、ty.” Reproduction prohibited under copyright conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis Foreword is not part of American National Standard “Selection and Training ofPersonnel for Research Reactors,” ANSI0ANS-15.4

12、-2007.!The standard “Selection and Training of Personnel for Research Reactors,” ANS-15.4, was first published in 1977. It was revised in 1988 to incorporate require-ments for requalification and medical competence of licensed or certified operationspersonnel. It is again being revised to reflect th

13、e considerable experience gainedover the last decade and a half, to address changes in regulatory requirementsand attitudes, and more importantly to fully incorporate the concept of performance-based selection and training of personnel. The standard is designed to be easilyadopted by the wide range

14、of research reactors in operation in the United Statesand abroad.Administrative and organizational requirements and structures, including re-views and audits, are found in a companion standard, “The Development ofTechnical Specifications for Research Reactors,” ANSI0ANS-15.1-2007.Critical facilities

15、 and fast pulse reactors should rely on the existing standards“Conduct of Critical Experiments,” ANS-1, and “Operation of Fast Pulse Reac-tors,” ANS-14.1, and should use ANS-15.4 to supplement these standards to theextent applicable.The family of research reactor standards that would be helpful for

16、operators,users, and regulators of these facilities are the following:ANSI0ANS-15.1-2007, “The Development of Technical Specifications for Research Reactors”ANSI0ANS-15.2-1999, “Quality Control for Plate-Type Uranium-Aluminum Fuel Elements”ANSI0ANS-15.7-1977; R1986 W1996!, “Research Reactor Site Eva

17、luation” withdrawn!ANSI0ANS-15.8-1995 R2005!, “Quality Assurance Program Requirements for ResearchReactors”ANSI0ANS-15.10-1994 W2004!, “Decommissioning of Research Reactors” withdrawn!ANSI0ANS-15.11-1993 R2004!, “Radiation Protection at Research Reactor Facilities”ANSI0ANS-15.15-1978; R1986 W1996!,

18、“Criteria for the Reactor Safety Systems of Re-search Reactors” withdrawn!ANSI0ANS-15.16-1982; R1988; R2000, “Emergency Planning for Research Reactors”ANSI0ANS-15.17-1981; R1987; R2000, “Fire Protection Program Criteria for ResearchReactors”ANSI0ANS-15.19-1991W2001!, “Shipment and Receipt of Special

19、 Nuclear MaterialSNM!by Research Reactor Facilities” withdrawn!ANS-15.20-20xx, “Criteria for the Reactor Control of Safety Systems of Research Reac-tors” under development!ANSI0ANS-15.21-1996; R2006, “Format and Content for Safety Analysis Reports forResearch Reactors”The ANS-15.4 Working Group that

20、 developed the standard under the auspices ofSubcommittee ANS-15, Operation of Research Reactors, was composed ofT. J. Myers Chair!, National Institute of Standards and TechnologyT. M. Raby Past Chair!, National Institute of Standards and TechnologyE. Ehrlich, General Electric CompanyW. J. Eresian,

21、U.S. Nuclear Regulatory CommissionD. J. Feltz, ConsultantM. M. Mendonca, U.S. Nuclear Regulatory CommissionS. OKelly, University of TexasW. J. Richards, National Institute of Standards and TechnologyT. R. Schmidt, Sandia National LaboratoriesR. Seale, University of ArizonaE. G. Tourigny, U.S. Depart

22、ment of EnergyW. G. Vernetson, University of FloridaW. L. Whittemore, General AtomicsiSubcommittee ANS-15, Operation of Research Reactors, had the following mem-bership at the time of approval of this standard:W. J. Richards Chair!, National Institute of Standards and TechnologyA. Adams, Jr., U.S. N

23、uclear Regulatory CommissionL. M. Bobek, University of Massachusetts, LowellJ. W. Bryson, Sandia National LaboratoriesC. D. Cooper, Bechtel BWXTM. L. Gildner, Oak Ridge National LaboratoryM. Krause, University of TexasP. M. Madden, U.S. Nuclear Regulatory CommissionC. McKibben, University of Missour

24、iColumbiaS. Miller, Armed Forces Radiobiology Research InstituteT. J. Myers, National Institute of Standards and TechnologyR. Nelson, Research Reactor Safety Analysis ServicesD. S. OKelly, University of TexasP. B. Perez, Entergy Nuclear VermontT. M. Raby, National Institute of Standards and Technolo

25、gyT. R. Schmidt, Sandia National LaboratoriesC. F. Sears, The Pennsylvania State UniversityConsensus Committee N-17, Research Reactors, Reactor Physics, Radiation Shield-ing and Computational Methods, had the following membership at the time itreviewed and approved the standard:T. M. Raby Chair!, Na

26、tional Institute of Standards and TechnologyA. Weitzberg Vice Chair!, IndividualW. H. Bell, American Institute of Chemical Engineers Alt. R. D. Zimmerman, American Institute ofChemical Engineers!R. E. Carter, IndividualD. M. Cokinos, Brookhaven National LaboratoryB. Dodd, Health Physics SocietyB. K.

27、 Grimes, IndividualN. Hertel, Georgia Institute of TechnologyW. A. Holt, American Public Health AssociationW. C. Hopkins, IndividualM. A. Hutmaker, U.S. Department of EnergyL. I. Kopp, IndividualP. M. Madden, U.S. Nuclear Regulatory Commission Alt. A. Adams, U.S. Nuclear RegulatoryCommission!J. F. M

28、iller, Institute of Electrical and Electronics EngineersJ. E. Olhoeft, IndividualW. J. Richards, National Institute of Standards and TechnologyT. R. Schmidt, Sandia National LaboratoriesA. O. Smetana, Savannah River National LaboratoryR. Tsukimura, Aerotest OperationsS. H. Weiss, National Institute

29、of Standards and Technology Alt. T. J. Myers, National Institute ofStandards and Technology)A. R. Veca, General AtomicsiiContentsSection Page1 Scope . 12 Definitions 13 Functional levels and assignments of responsibility 23.1 General 23.2 Level1 . 23.3 Level2 . 23.4 Level3 . 23.5 Level4 . 33.6 Other

30、technicalpersonnel . 34 Qualification 34.1 General 34.2 Level1 . 34.3 Level2 . 34.4 Level3 . 34.5 Level4 . 34.6 Othertechnicalpersonnel . 35 Initialtrainingandlicensing . 35.1 General 35.2 Initial training . 45.3 Training methods . 45.3.1 General 45.3.2 Classroom methods . 45.3.3 Self-study methods

31、. 45.3.4 On-the-job training methods . 45.3.5 Other methods . 45.4 Examinations . 45.5 Examination administration and evaluation 55.6 Medicalexamination 55.7 Licensing . 55.8 Specialorlimitedlicense 55.9 Othertechnicalpersonnel . 56 Requalification and relicensing . 66.1 General 66.2 Requalification

32、 program . 66.2.1 Refresher training 66.2.2 Written examination 66.2.3 Medical examination 66.2.4 Reactivity control manipulations . 66.2.5 Operating test or evaluation 66.2.6 Document review . 66.3 Evaluation and retraining . 76.4 Relicensing . 76.5 Absencefromlicensedfunctions . 76.6 Exemptions .

33、7 iii 7 Medical certification and monitoring or licensed personnel 77.1 Health evaluation responsibility 77.1.1 General aspects . 77.1.2 Medical examination frequency . 77.2 Health requirements and disqualifying conditions 87.2.1 Basis of requirements 87.2.2 General requirements 87.2.3 Disqualifying

34、 conditions . 87.2.4 Specific minimum capacities required for medicalqualification 97.2.5 Additional examination 107.3 Waiverorlimitedapproval . 107.3.1 Applicationrequirementsandcriteria . 107.3.2 Limited approval 107.4 Medical examination documentation 108 Fitnessforduty 109 Documentation and reco

35、rds . 119.1 Documentation 119.2 Records . 1110 References . 11ivSelection and Training of Personnelfor Research Reactors1 ScopeThis standard provides criteria for the selec-tion and training of research reactor operatingpersonnel. It addresses their qualifications,training, initial licensing, requal

36、ification, andrelicensing.This standard is predicated on levels of respon-sibility rather than on a particular organiza-tional concept.2 DefinitionsThe following special definitions will be usefulin understanding this and companion or refer-ence standards.academic training: Academic training is suc-

37、cessfully completed job-related college-levelwork.certificate or charter: See license.certification: See licensing.certified: See licensed.Class A reactor operator: See senior reactoroperator.Class B reactor operator: See reactoroperator.controls: When used with respect to a nuclearreactor means app

38、aratus and mechanisms themanipulation of which directly affects the re-activity or power level of the reactor.designated medical examiner: A licensedmedical practitioner familiar with the medicalprovisions of this standard.disqualifying or disqualifying conditions:Something that precludes unconditio

39、nal medi-cal approval for research reactor operatorlicensing.license: The written authorization, by the re-sponsible authority, for an individual to carryout the duties and responsibilities associatedwith a position requiring licensing.licensed: See licensee.licensee: An individual or organization h

40、old-ing a license.licensing: The confirmation by the responsi-ble authority of the experience, education, med-ical condition, training, and testing pertinentto a specific job assignment.nonpower reactor: See research reactor.nuclear experience: Experience acquired inreactor facility start-up activit

41、ies or operation.Experience in design, construction, mainte-nance, or related technical services that is job-related may also be considered. On-the-jobtraining at the reactor facility may qualify asequivalent nuclear experience on a one-for-onetime basis. Appropriate research or teaching orboth may

42、be includable as nuclear experience.on-the-job training: A systematic, structuredmethod using a qualified person to provide therequired job-related knowledge and skills to atrainee, usually in the actual workplace, withproficiency documented.owner or operator: See licensee.permit: See license.perfor

43、mance-based training: The type oftraining that continues or is repeated until es-tablished results are achieved.reactor operator: An individual who is li-censed to manipulate the controls of a reactor.research reactor: A research reactor is de-fined as a device that is designed to support aself-sust

44、aining neutron chain reaction for re-search, developmental, educational, training, orexperimental purposes and that may have pro-visions for the production of radioisotopes.research reactor facility: Includes all areaswithin which the owner or operator directs au-thorized activities associated with

45、the reactor.responsible authority: A governmental orother entity with the authority to issue li-censes, charters, permits, or certificates.1safety-relatedsystems: Those systems, struc-tures, and components that perform functionsnecessary to shut down the reactor and main-tain it in a safe shutdown c

46、ondition, and to min-imize radioactive releases to the environment.senior reactor operator: An individual whois licensed to direct the activities of reactoroperators. Such an individual is also a reactoroperator.supervisory reactor operator: See senior re-actor operator.shall, should, and may: The w

47、ord “shall” isused to denote a requirement; the word “should”is used to denote a recommendation; and theword “may” is used to denote permission, nei-ther a requirement nor a recommendation.solo operation: Operation of the controls, in-cluding monitoring of instrumentation, duringreactor operation wi

48、th no other person at thefacility.technical support personnel: Unlicensed per-sonnel principally involved in the calibration,maintenance, repair, and radiation protectionactivities or performance of other craft andtechnical activities at the facility. Examplesare laboratory technicians, instrument t

49、echni-cians, and health physics personnel.test reactor: See research reactor.3 Functional levels andassignments of responsibility3.1 GeneralThe establishment of functional levels and as-signments of responsibility is the prerogativeof the organization authorized to operate theresearch reactor. The functional levels and titlesused below are not intended to define a spe-cific organization or to completely define theresponsibilities of each level of an organization.Responsibilities for various levels of an organi-zation are typically described in the adminis-trat