1、ANSI/ANS-15.21-2012format and content for safety analysisreports for research reactorsANSI/ANS-15.21-2012ANSI/ANS-15.21-2012American National StandardFormat and Content forSafety Analysis Reports for Research ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards
2、 CommitteeWorking Group ANS-15.21Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved April 3, 2013by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests t
3、hatthe 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 the procedures of the Standards Commit-tee of the American Nuclear Society; thes
4、e procedures are accredited by theAmerican National Standards Institute, Inc., as meeting the criteria forAmer-ican National Standards. The consensus committee that approved the stan-dard was balanced to ensure that competent, concerned, and varied interestshave had an opportunity to participate.An
5、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 notpreclude anyone from manufacturing, marketing, purchasing, or using prod-uct
6、s, 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 content of this standard reflects acceptable practice at the time ofits
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8、e 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 or by any ad hoc group of individuals.Responses to inquiries about r
9、equirements, recommendations, and0or permis-sive statements i.e., “shall,” “should,” and “may,” respectively! should be sentto the Standards Department at Society Headquarters. Action will be taken toprovide appropriate response in accordance with established procedures thatensure consensus.Comments
10、 on this standard are encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2013 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should rea
11、d “Extracted fromAmerican National Standard ANSI0ANS-15.21-2012 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 AmericaInquiryRequest
12、sThe American Nuclear Society ANS! Standards Committee will provide re-sponses to inquiries about requirements, recommendations, and0or permissivestatementsi.e., “shall,” “should,” and “may,” respectively!in American NationalStandards that are developed and approved by ANS. Responses to inquiries wi
13、llbe provided according to the Policy Manual for the ANS Standards Committee.Nonrelevant inquiries or those concerning unrelated subjects will be returnedwith appropriate explanation. ANS does not develop case interpretations ofrequirements in a standard that are applicable to a specific design, ope
14、ration,facility, or other unique situation only and therefore is not intended for genericapplication.Responses to inquiries on standards are published in ANSs magazine, NuclearNews, and are available publicly on the ANS Web site or by contacting the ANSStandards Administrator.InquiryFormatInquiry re
15、quests must include the following:1! the name, company name if applicable, mailing address, and telephonenumber of the inquirer;2! reference to the applicable standard edition, section, paragraph, figure,and0or table;3! the purposes! of the inquiry;4! the inquiry stated in a clear, concise manner;5!
16、 a proposed reply, if the inquirer is in a position to offer one.Inquiries should be addressed toAmerican Nuclear SocietyATTN: Standards Administrator555 N. Kensington AvenueLa Grange Park, IL 60526or standardsans.orgForewordThis Foreword is not a part of American National Standard “Format and Conte
17、nt forSafety Analysis Reports for Research Reactors,” ANSI0ANS-15.21-2012.!The American Nuclear SocietyANS!Standards Committee established Subcom-mittee ANS-15 in the fall of 1970 with the task of preparing a standard for theoperation of research reactors. In January 1972, this charter was expanded
18、toinclude the task of preparing standards for all aspects of research reactor needs.To implement this enlarged responsibility, Subcommittee ANS-15 established anumber of working groups to develop standards for consideration and comple-mentary action. This standard addresses itself to the format and
19、content ofsafety analysis reports SARs! for research reactors.Working Group ANS-15.21 was formed in 1991 to develop ideas and conceptsleading to a standard for guidance on the format and content of a researchreactor SAR, taking into account available guidance and recognizing that manyresearch reacto
20、r SARs have successfully presented descriptive and analyticalinformation through the use of a simple format and limited content.This standard recognizes the merits of the historical guidanceRegulatory Guide1.70, “Standard Format and Content of Safety Analysis Reports for NuclearPower Plants”!, the w
21、ork by the U.S. Nuclear Regulatory Commission on guid-ance for nonpower reactors NUREG-1537, “Guidelines for Preparing and Re-viewing Applications for the Licensing of Non-Power Reactors”!, the work of theU.S. Department of Energy Order 5480.23, “Nuclear Safety Analysis Reports”!,and the Internation
22、al Atomic Energy Agency work that encompasses safetyanalysis documentation Safety Series 35!.It is recognized that a power station has huge and variable sources of storedenergy, dedication to highly reliable on-line power, massive containment andenergy control features, and extremely harsh equipment
23、 operating environ-ments. Research reactors, on the other hand, are small, noninvasive facilitieswith low fission product inventories, minimal stored energy, and simple equip-ment environments, resulting in small risk compared to nuclear power plants.This standard recognizes the considerably reduced
24、 risks, markedly simpler sys-tems, and unique mission of research reactors. A graded approach to content,level of description, and level of analysis is thus very important. It is recognizedthat it is neither necessary nor possible to apply the same degree of descriptionor analysis for all systems or
25、 events. Where this standard uses terms such as“appropriate” or “as necessary,” these are to be interpreted as meaning suchvariation in the degree of description and analysis.Nuclear critical assemblies facilities operating in the context of ANSI0ANS-1-2000 R2012!, “Conduct of Critical Experiments”!
26、 often have flexible cores andgenerally do not have coolant systems, fission product inventories, radioactivewaste streams, or confinement systems. Therefore, many of the requirements ofthis standard are not appropriate for nuclear critical assembly facilities, and it isbeyond the scope of the worki
27、ng group to include alternative guidance.Since the standard provides guidance on how facility descriptive information ispresented and does not introduce new criteria for any aspect of design, construc-tion, or operation, a very limited definition section is included.SARs are used extensively by anal
28、ysts, operations staff, review groups, andlicensing and chartering agencies in support of the research reactors uniquemission. The SAR provides the central repository of information used for per-forming analysis, determining bounding conditions, and establishing the foun-dation of technical specific
29、ations.iIn this process of creating standards against the background of established andvaried practices in many operating facilities, it is important to consider thefollowing:1! It is not intended that the standard be used as a demand model forbackfitting purposes;2! The standard should be a vital a
30、id for the new owner-agency;3! The standard should be helpful for the facility undergoing change ormodification;4! Thoughtful use of the standard by the industry should ease the burden oflicensing and chartering agencies.It is affirmed further that the use of any standard of performance, conduct, or
31、excellence is volitional. The decision to use a standard is a management matter,presumably based on technical advisement.Guidance may be found in the following supplementaryAmerican National Stan-dards developed for research reactors:ANSI0ANS-15.1-2007, “The Development of Technical Specifications f
32、or Re-search Reactors”;ANSI0ANS-15.2-1999 R2009!, “Quality Control for Plate-Type Uranium-Aluminum Fuel Elements”;ANSI0ANS-15.4-2007, “Selection and Training of Personnel for Research Reactors”;ANSI0ANS-15.7-1977 R1986!withdrawn!, “Research Reactor Site Evaluation”;ANSI0ANS-15.8-1995 R2005!, “Qualit
33、y Assurance Program Requirements forResearch Reactors”;ANSI0ANS-15.10-1994 withdrawn!, “Decommissioning of Research Reactors”;ANSI0ANS-15.1l-2009, “Radiation Protection at Research Reactor Facilities”;ANSI0ANS-15.15-1978 R1986!withdrawn!, “Criteria for the Reactor SafetySystems of Research Reactors”
34、;ANSI0ANS-15.16-2008, “Emergency Planning for Research Reactors”;ANSI0ANS-15.17-1981 R2000!withdrawn!, “Fire Protection Program Criteriafor Research Reactors”;ANSI0ANS-15.19-1991 withdrawn!, “Shipment and Receipt of Special NuclearMaterial by Research Reactor Facilities.”This standard might referenc
35、e documents and other standards that have beensuperseded or withdrawn at the time the standard is applied. A statement hasbeen included in the references section that provides guidance on the use ofreferences.This standard does not incorporate the concepts of generating risk-informedinsights, perfor
36、mance-based requirements, or a graded approach to quality as-surance. The user is advised that one or more of these techniques could enhancethe application of this standard.The working group included a broad spectrum of expertise in research reactoroperations, experiment and reactor analysis, SARs,
37、and interactions with char-tering and licensing agencies. The members represent a wide variety of researchreactorsincluding those at universities, national laboratories, and governmentiifacilitiesand participation in international standards work. Working GroupANS-15.21 of the ANS Standards Committee
38、 had the following membership:A. Adams, Jr. Chair!, U.S. Nuclear Regulatory CommissionS. Miller, Armed Forces Radiobiology Research Institute, National Naval Medical CenterS. Reese, Oregon State UniversityC. Stanley, Idaho National LaboratoryThe membership of Subcommittee ANS-15, Operation of Resear
39、ch Reactors, atthe time of the approval of this standard, was the following:D. S. OKelly Chair!, National Institute of Standards and TechnologyA. Adams, Jr., U.S. Nuclear Regulatory CommissionL. Bobek, University of Massachusetts LowellJ. Bryson, Sandia National LaboratoriesC. D. Cooper, Idaho Natio
40、nal LaboratoryD. Clovis, Sandia National LaboratoriesL. Foyto, University of Missouri Research Reactor CenterM. Gildner, Oak Ridge National LaboratoryM. Krause, University of Texas at AustinC. McKibben, University of Missouri Research Reactor CenterS. Miller, Armed Forces Radiobiology Research Insti
41、tute, National Naval Medical CenterT. J. Myers, National Institute of Standards and TechnologyS. Reese, Oregon State UniversityT. R. Schmidt, Sandia National LaboratoriesW. Schuster, National Institute of Standards and TechnologyJ. Sease, Oak Ridge National LaboratoryC. Stanley, Idaho National Labor
42、atoryM. H. Voth, U.S. Nuclear Regulatory CommissionConsensus Committee N17, Research Reactors, Reactor Physics, Radiation Shield-ing, and Computational Methods, had the following membership at the time itreviewed and approved this standard:T. M. Raby Chair!, National Institute of Standards and Techn
43、ologyA. O. Smetana Interim Chair!, Savannah River National LaboratoryA. Weitzberg Vice Chair!, IndividualS. L. Anderson, WestinghouseW. H. Bell, American Institute of Chemical EngineersR. R. Brey, Health Physics SocietyR. E. Carter, IndividualD. M. Cokinos, Brookhaven National LaboratoryM. L. Corrad
44、ini, National Council on Radiation Protection and MeasurementB. K. Grimes, IndividualM. A. Hutmaker, Jr., U.S. Department 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 Commi
45、ssion!J. F. Miller, Institute of Electrical and Electronics EngineersT. J. Myers, National Institute of Standards and TechnologyD. S. OKelly, National Institute of Standards and TechnologyJ. E. Olhoeft, IndividualR. E. Pevey, University of TennesseeKnoxvilleC. T. Rombough, CTR Technical Services, In
46、c.C. E. Sanders, University of NevadaLas Vegas/Sanders EngineeringT. R. Schmidt, Sandia National LaboratoriesA. O. Smetana, Savannah River National LaboratoryR. Tsukimura, Aerotest OperationsA. R. Veca, General Atomics iii ivContentsSection Page1 Introduction . 11.1 Scope 11.2 Definitions . 11.3 App
47、lication . 11.3.1 Purpose . 11.3.2 Format . 11.3.3 Style . 11.3.4 International System of Units SI! 21.3.5 SARtableofcontents 21.3.6 SARappendices . 21.3.7 Significant figures 21.3.8 Abbreviations . 21.3.9 References 21.3.10 Security 21.3.11 Procedures 21.3.12 Organizations . 21.3.13 Relationship to
48、 governance documents 22 SARcontents 32.1 Chapter1.Introduction 32.2 Chapter2.SiteCharacteristics . 32.3 Chapter 3. General Design of Buildings and Structures 32.4 Chapter4.Reactor . 42.5 Chapter 5. Reactor Coolant System and Connected Systems 52.6 Chapter 6. Engineered Safety Features . 52.7 Chapte
49、r 7. Instrumentation and Controls 62.8 Chapter 8. Electric Power 62.9 Chapter9.AuxiliarySystems . 72.10 Chapter10.ExperimentFacilitiesandUtilization . 72.11 Chapter 11. Operational Radiological Safety . 72.12 Chapter 12. Conduct of Operations 82.13 Chapter 13. Accident Analysis 82.14 Chapter 14. Technical Specifications or Equivalent Document! . 102.15 Chapter 15. Quality Assurance Program . 102.16 Chapter 16. Decontamination and Decommissioning 103 References 10AppendicesAppendix A Table of Contents for a Research Reactor Safety Analy
