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
3、stitute, Inc. American National Standard ANSI/ANS-15.4-2016 American National Standard Designation of this document as an American National Standard attests that the principles of openness and due process have been followed in the approval procedure and that a consensus of those directly and materia
4、lly affected by the standard has been achieved. This standard was developed under the procedures of the Standards Committee of the American Nuclear Society; these procedures are accredited by the American National Standards Institute, Inc., as meeting the criteria for American National Standards. Th
5、e consensus committee that approved the standard was balanced to ensure that competent, concerned, and varied interests have had an opportunity to participate. An American National Standard is intended to aid industry, consumers, governmental agencies, and general interest groups. Its use is entirel
6、y voluntary. The existence of an American National Standard, in and of itself, does not preclude anyone from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standard. By publication of this standard, the American Nuclear Society does not insure
7、 anyone utilizing the standard against liability allegedly arising from or after its use. The content of this standard reflects acceptable practice at the time of its approval and publication. Changes, if any, occurring through developments in the state of the art, may be considered at the time that
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9、can Nuclear Society accepts no responsibility for interpretations of this standard made by any individual or by any ad hoc group of individuals. Inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and “may,” respectively) should be sent to the Scient
10、ific Publications and Standards Department at Society Headquarters. Action will be taken to provide appropriate response in accordance with established procedures that ensure consensus. Comments on this standard are encouraged and should be sent to Society Headquarters. Published by American Nuclear
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13、rican Nuclear Society (ANS) Standards Committee will provide responses to inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and “may,” respectively) in American National Standards that are developed and approved by ANS. Responses to inquiries will
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15、eration, facility, or other unique situation only and therefore is not intended for generic application. Responses to inquiries on standards are published in ANSs magazine, Nuclear News, and are available publicly on the ANS Web site or by contacting the Scientific Publications and Standards Departm
16、ent. Inquiry Format Inquiry requests shall include the following: (1) the name, company name if applicable, mailing address, and telephone number of the inquirer; (2) reference to the applicable standard edition, section, paragraph, figure, and/or table; (3) the purpose(s) of the inquiry; (4) the in
17、quiry stated in a clear, concise manner; (5) a proposed reply, if the inquirer is in a position to offer one. Inquiries should be addressed to: American Nuclear Society Scientific Publications and Standards Department 555 N. Kensington Avenue La Grange Park, IL 60526 or standardsans.org American Nat
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
