ANSI ANS 15.4-2016 Selection and training of personnel for research reactors.pdf

1、An American National StandardPublished by the American Nuclear Society 555 N. Kensington AveLa Grange Park, IL 60526ANSI/ANS-15.4-2016Selection and Training of Personnel for Research ReactorsANSI/ANS-15.4-2016ANSI/ANS-15.4-2016 American National Standard Selection and Training of Personnel for Resea

2、rch Reactors Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-15.4 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Approved April 19, 2016 by the American National Standards In

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18、ional Standard ANSI/ANS-15.4-2016 American National Standard ANSI/ANS-15.4-2016 i Foreword (This foreword is not part of American National Standard “Selection and Training of Personnel for Research Reactors,” ANSI/ANS-15.4-2016.) The standard “Selection and Training of Personnel for Research Reactor

19、s,” ANS-15.4, was first published in 1977. It was revised in 2007 to incorporate requirements for requalification and medical competence of licensed or certified operations personnel. It is again being revised, to address changes in regulatory requirements and attitudes and changes to medical techni

20、ques. The standard is designed to be easily adopted by the wide range of research reactors in operation in the United States and abroad. Administrative and organizational requirements and structures, including reviews and audits, are found in companion standard ANSI/ANS-15.1-2007 (R2013), “The Devel

21、opment of Technical Specifications for Research Reactors.” Critical facilities and fast pulse reactors should rely on existing standards ANSI/ANS-1-2000 (R2012), “Conduct of Critical Experiments,” and ANSI/ANS-14.1-2004 (R2014), “Operation of Fast Pulse Reactors,” and should use ANS-15.4 to suppleme

22、nt these standards to the extent applicable. This standard might reference documents and other standards that have been superseded or withdrawn at the time the standard is applied. A statement has been included in the reference section that provides guidance on the use of the references. This standa

23、rd does not incorporate the concepts of generating risk-informed insights, performance-based requirements, or a graded approach to quality assurance. The user is advised that one or more of these techniques could enhance the application of this standard. The family of research reactor standards that

24、 would be helpful for operators, users, and regulators of these facilities are the following: ANSI/ANS-15.1-2007 (R2013), “The Development of Technical Specifications for Research Reactors”; ANSI/ANS-15.2-1999 (R2016), “Quality Control for Plate-Type Uranium-Aluminum Fuel Elements”; ANSI/ANS-15.8-19

25、95 (R2013), “Quality Assurance Program Requirements for Research Reactors”; ANSI/ANS-15.11-2009, “Radiation Protection at Research Reactor Facilities”; ANSI/ANS-15.15-1978 (R1986), “Criteria for the Reactor Safety Systems of Re-search Reactors” (withdrawn); ANSI/ANS-15.16-2015, “Emergency Planning f

26、or Research Reactors”; ANSI/ANS-15.21-2012, “Format and Content for Safety Analysis Reports for Research Reactors.” The ANS-15.4 Working Group that developed the standard under the auspices of the Operation of Research Reactors Subcommittee was composed of the following members: T. J. Myers (Chair),

27、 Individualretired from National Institute of Standards and Technology L. M. Bobek, University of Massachusetts-Lowell C. J. Heysel, McMaster University D. E. Hughes, National Institute of Standards and Technology M. G. Krause, University of Texas at Austin S. Miller, Armed Forces Radiobiology Resea

28、rch Institute P. T. Young, U.S. Nuclear Regulatory Commission American National Standard ANSI/ANS-15.4-2016 ii The Operation of Research Reactors Subcommittee had the following membership at the time of approval of this standard: T. H. Newton (Vice Chair), National Institute of Standards and Technol

29、ogy A. Adams, Jr., U.S. Nuclear Regulatory Commission M. J. Burger, Sandia National Laboratories D. Cronin, University of Florida at Gainesville L. P. Foyto, University of MissouriColumbia S. Miller, Armed Forces Radiobiology Research Institute M. K. Morrison, Idaho National Laboratory T. J. Myers,

30、Individual D. S. OKelly, Idaho National Laboratory D. M. Pinkston, Oak Ridge National Laboratory S. R. Reese, Oregon State University T. R. Schmidt, Individual R. Strader, National Institute of Standards and Technology The Research and Advanced Reactors Consensus Committee had the following membersh

31、ip at the time it reviewed and approved the standard: G. F. Flanagan (Chair), Oak Ridge National Laboratory B. Bevard (Vice Chair), Oak Ridge National Laboratory T. H. Newton (Vice Chair), National Institute of Standards and Technology A. Adams, Jr., U.S. Nuclear Regulatory Commission A. Afzali, Sou

32、thern Nuclear Operating Company J. K. August, Southern Nuclear Operating Company E. D. Blandford, University of New Mexico R. E. Carter, Individual L. P. Foyto, University of MissouriColumbia T. Grenci, Chicago Bridge the word “should” is used to denote a recommendation; and the word “may” is used t

33、o denote permission, neither a requirement nor a recommendation. 2.2 Definitions The following special definitions will be useful in understanding this and companion or reference standards. academic training: Academic training is successfully completed job-related college-level work. certificate or

34、charter: See “license.” certification: See “licensing.” certified: See “licensed.” Class A reactor operator: See “senior reactor operator.” Class B reactor operator: See “reactor operator.” controls: When used with respect to a nuclear reactor means apparatus and mechanisms the manipulation of which

35、 directly affects the reactivity or power level of the reactor. designated medical examiner: A licensed medical practitioner, either a Doctor of Medicine or a Doctor of Osteopathy, familiar with the medical provisions of this standard and the general responsibilities and work environment of the exam

36、inee. disqualifying or disqualifying conditions: Something that precludes unconditional medical approval for research reactor operator licensing. license: The written authorization, by the responsible authority, for an individual to carry out the duties and responsibilities associated with a positio

37、n requiring licensing. licensed: See “licensee.” licensee: An individual or organization holding a license. licensing: The confirmation by the responsible authority of the experience, education, medical condition, training, and testing pertinent to a specific job assignment. American National Standa

38、rd ANSI/ANS-15.4-2016 2 nonpower reactor: See “research reactor.” nuclear experience: Experience acquired in reactor facility start-up activities or operation. Experience in design, construction, maintenance, or related technical services that are job-related may also be considered. On-the-job train

39、ing at the reactor facility may qualify as equivalent nuclear experience on a one-for-onetime basis. Appropriate research or teaching or both may be includable as nuclear experience. on-the-job training: A systematic, structured method using a qualified person to provide the required job-related kno

40、wledge and skills to a trainee, usually in the actual workplace, with proficiency documented. owner or operator: See “licensee.” permanent medical condition: A change in the medical status of a licensed operator of probable duration greater than 90 days and for which the activities of the licensed o

41、perator may be restricted by the Level 2 person. Notification of this change shall be made to the responsible authority within 30 days of defining the condition as permanent. permit: See “license.” performance-based training: The type of training that continues or is repeated until established resul

42、ts are achieved. reactor operator: An individual who is licensed to manipulate the controls of a reactor. research reactor: A research reactor is defined as a device that is designed to support a self-sustaining neutron chain reaction for research, developmental, educational, training, or experiment

43、al purposes and that may have provisions for the production of radioisotopes. research reactor facility: Includes all areas within which the owner or operator directs authorized activities associated with the reactor. responsible authority: A governmental or other entity with the authority to issue

44、licenses, charters, permits, or certificates. safety-related systems: Those systems, structures, and components that perform functions necessary to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment. senior reactor operator: An

45、individual who is licensed to direct the activities of reactor operators. Such an individual is also a reactor operator. supervisory reactor operator: See “senior reactor operator.” solo operation: Operation of the controls, including monitoring of instrumentation, during reactor operation with no o

46、ther person at the facility. technical support personnel: Unlicensed personnel principally involved in the calibration, maintenance, repair, and radiation protection activities or performance of other craft and technical activities at the facility. Examples are laboratory technicians, instrument tec

47、hnicians, and health physics personnel. temporary medical condition: A change in the medical status of a licensed operator of duration of no more than 90 days and for which the activities of a licensed operator may be restricted by the Level 2 person. This change does not require a notification to t

48、he responsible authority. test reactor: See “research reactor.” American National Standard ANSI/ANS-15.4-2016 3 3 Functional levels and assignments of responsibility 3.1 General The establishment of functional levels and assignments of responsibility is the prerogative of the organization authorized

49、 to operate the research reactor. The functional levels and titles used below are not intended to define a specific organization or to completely define the responsibilities of each level of an organization. Responsibilities for various levels of an organization are typically described in the administrative section of facility technical specifications, as in ANSI/ANS-15.1-2007 (R2013) 11). It is recognized that for some research reactor facilities, the operating organization may include members of the design, experimental, or management staff. For purposes of this stan