ANSI ANS 15.1-2007 The development of technical specifications for research reactors《研究反应堆用技术规范的开发》.pdf

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1、ANSI/ANS-15.1-2007the development of technicalspecifications for research reactorsANSI/ANS-15.1-2007ANSI/ANS-15.1-2007American National StandardThe Development of TechnicalSpecifications for Research ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards Committe

2、eWorking Group ANS-15.1Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved April 20, 2007by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe pr

3、inciples 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 procedures ar

4、e 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 Nationa

5、l 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, processes, or

6、 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 and pub

7、lication. 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 It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures.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 cautioned to d

8、etermine 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 sent to

9、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 Nuclear So

10、ciety555 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-15.1-2007 with permission of the publisher,the Americ

11、an 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 “The Development of Tech-nical Specifications for Resea

12、rch Reactors,” ANSI0ANS-15.1-2007.!ANS-15.1, “The Development of Technical Specifications for Research Reactors,”is the principal standard developed under the direction of SubcommitteeANS-15,Operation of Research Reactors. This standard impacts research reactors ofevery type and size and has been wi

13、dely used by most of them. Certain segmentsof this standard may be useful to critical experiment facilities and fast pulsereactors; however, these facilities should continue to use American NationalStandard ANSI0ANS-1-2000, “Conduct of Critical Experiments,” and ANSI0ANS-14.1-2004, “Operation of Fas

14、t Pulse Reactors.”This standard uses the word “significant” throughout. This word must be de-fined on a case-by-case basis for each user of the standard based on that usersspecific facility and Safety Analysis Report.The membership of the ANS-15.1 working group at the time of the revision of thestan

15、dard was as follows:A. Adams, Jr. Cochair!, U.S. Nuclear Regulatory CommissionT. R. Schmidt Cochair!, Sandia National LaboratoriesT. M. Raby, National Institute of Standards and TechnologyW. J. Richards, National Institute of Standards and TechnologyIn the process of creating this standard with resp

16、ect to existing and variedpractices in many operating facilities, it is important to consider the following:1! It is not intended that the standard be used as a demand model forbackfitting purposes;2! Its provisions should be used only to the extent applicable to the individualfacility;3! It should

17、be a significant aid for an existing and new owner or operator, orboth;4! It should be helpful for the facility undergoing change or modification, orboth;5! Its considered use should assist in implementing regulatory requirements.This standard addresses itself to technical specifications for and adm

18、inistrativecontrol of research and test reactors. However, Sec. 6, “Administrative Controls,”in this standard includes a review and audit section that effectively provides forthe function of operational quality assurance at research reactors. Additionalstandards have been prepared addressing other a

19、reas of interest and concern tooperators of research reactors. Guidance may be found in the following supple-mentary American National Standards developed for research reactors:ANSI0ANS-15.2-1999, “Quality Control for Plate-Type Uranium-Aluminum FuelElements”ANSI0ANS-15.4-1988R1999!, “Selection and

20、Training of Personnel for ResearchReactors”ANSI0ANS-15.7-1977; R1986 W1996!, “Research Reactor Site Evaluation”withdrawn!ANSI0ANS-15.8-1995 R2005!, “Quality Assurance Program Requirements forResearch Reactors”iANSI0ANS-15.10-1994 W2004!, “Decommissioning of Research Reactors”withdrawn!ANSI0ANS-15.11

21、-1993 R2004!, “Radiation Protection at Research ReactorFacilities”ANSI0ANS-15.15-1978; R1986W1996!, “Criteria for the Reactor Safety Systemsof Research Reactors” withdrawn!ANSI0ANS-15.16-1982; R1988; R2000, “Emergency Planning for Research Reactors”ANSI0ANS-15.17-1981; R1987; R2000, “Fire Protection

22、 Program Criteria forResearch Reactors”ANSI0ANS-15.19-1991 W2001!, “Shipment and Receipt of Special Nuclear Ma-terial SNM! by Research Reactor Facilities” withdrawn!ANSI0ANS-15.20-200x, “Criteria for the Reactor Control of Safety Systems ofResearch Reactors” under development!ANSI0ANS-15.21-1996; R2

23、006, “Format and Content for Safety Analysis Reportsfor Research Reactors”The membership of Subcommittee ANS-15 at the time of the standard revisionwas as follows:W. J. Richards Chair!, National Institute of Standards and TechnologyA. Adams, Jr., U.S. Nuclear Regulatory CommissionL. M. Bobek, Univer

24、sity 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 Missouri-ColumbiaS. Miller, Armed Forces Radiobiology

25、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 TechnologyT. R. Schmidt, Sandia National LaboratoriesC

26、. F. Sears, The Pennsylvania State UniversityConsensus 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 TechnologyA

27、. Weitzberg Vice Chair! IndividualW. H. Bell, American Institute of Chemical EngineersAlt. R. D. Zimmerman, American Institute of Chemical Engineers!R. E. Carter, IndividualD. M. Cokinos, Brookhaven National LaboratoryB. Dodd, Health Physics SocietyB. K. Grimes, IndividualN. E. Hertel, Georgia Insti

28、tute of TechnologyW. A. Holt, American Public Health AssociationW. C. Hopkins, IndividualM. A. Hutmaker, Jr., U.S. Department of EnergyL. I. Kopp, IndividualP. M. Madden, U.S. Nuclear Regulatory CommissionAlt. A. Adams, Jr., U.S. Nuclear Regulatory Commission!J. F. Miller, Institute of Electrical an

29、d Electronics EngineersJ. E. Olhoeft, IndividualW. J. Richards, National Institute of Standards and TechnologyiiT. R. Schmidt, Sandia National LaboratoriesA. O. Smetana, Savannah River National LaboratoryR. Tsukimura, Aerotest OperationsS. H. Weiss, National Institute of Standards and TechnologyAlt.

30、 T. J. Myers, National Institute of Standards and Technology)A. R. Veca, General Atomics iii ivContentsSection Page1 Introduction . 11.1 Scope 11.2 Application . 11.3 Definitions . 22 Safety limits and limiting safety system settings . 42.1 Safetylimits . 42.2 Limitingsafetysystemsettings 43 Limitin

31、gconditionsforoperations 53.1 Reactor core parameters . 53.2 Reactor control and safety systems . 53.3 Coolantsystems 53.4 Containment or confinement . 53.5 Ventilation systems . 63.6 Emergencypower . 63.7 Radiation monitoring systems and effluents 63.8 Experiments 63.9 Facility-specific limiting co

32、nditions for operations . 74 Surveillance requirements 74.1 Reactor core parameters . 74.2 Reactor control and safety systems . 84.3 Coolantsystems 84.4 Containment or confinement . 84.5 Ventilation systems . 84.6 Emergencypower . 84.7 Radiation monitoring systems and effluents 84.8 Experiments 94.9

33、 Facility-specific surveillance requirements 95 Designfeatures . 95.1 Site and facility description . 95.2 Reactor coolant system 95.3 Reactor core and fuel . 95.4 Fissionable material storage . 96 Administrative controls 96.1 Organization . 96.2 Reviewandaudit . 116.3 Radiationsafety 126.4 Procedur

34、es . 126.5 Experiments review and approval 136.6 Required actions 136.7 Reports 136.8 Records 157 References 15FigureFigure 1 Organization chart 10vThe Development ofTechnical Specifications forResearch Reactors1 Introduction1.1 ScopeThis standard identifies and establishes thecontent of technical s

35、pecifications TS! for re-search and test reactors. Areas addressed aredefinitions, safety limits, limiting safety sys-tem settings, limiting conditions for operation,surveillance requirements, design features, andadministrative controls. Sufficient detail is in-corporated so that applicable specific

36、ations canbe derived or extracted.1.2 Application1.2.1 PurposeIt is recognized that because of the special na-tureandwiderangeofresearchreactors,nogen-eralstandardcanbeappliedwithoutthoughtfulinterpretationandthatnotallrequirementsareapplicabletoeveryfacility.Accordingly,incorpo-ration of various re

37、quirements of this standardintotechnicalspecificationsmayrangefromde-tailed application to unqualified inapplicability.Technical specifications may also be referred toas technical safety requirements TSR!.The technical specifications represent an agree-ment between the owner or operator, or both,and

38、 the responsible authority on administra-tive controls, equipment availability, and oper-ational parameters.Specific limitations and equipment require-ments for safe reactor operation and for deal-ing with abnormal situations, typically derivedfrom the Safety Analysis Report SAR!, arecalled specific

39、ations. These specifications rep-resent a comprehensive envelope of safe oper-ation. Only those operational parameters andequipment requirements directly related to ver-ifying and preserving that safe envelope shallbe listed. Procedures to meet the requirementsof these technical specifications shall

40、 not bepart of the technical specifications.1.2.2 FormatIn order to ensure that all items that may berelevant for inclusion in the technical specifi-cations have been considered, the require-ments of this standard include the heading andnumbering format of major sections “1 Intro-duction,” “2 Safety

41、 limits and limiting safetysystem settings,” “3 Limiting conditions for op-eration,” “4 Surveillance requirements,” “5 De-sign features,” and “6Administrative controls”!and the first level of subheadings2.x, 3.x, etc.!.Beginning with Sec. 2, each heading and thefirst level of subheading shall be add

42、ressed ifapplicable. All headings and numbering at thenext level and beyond 2.x.x, 3.x.x, etc.! shallbe addressed if applicable, altered as neces-sary, or omitted if not applicable.Individual specifications in Secs. 2, 3, and 4shall include the following related informationin the format shown:Applic

43、ability: This is a statement that indi-cates which components are involved and whenthey are involved;Objective: This is a statement that indicatesthe purpose of the specifications!;Specifications!: This statement provides spe-cific data, conditions, or limitations that bounda system or operation. Th

44、is statement is themost important statement in the technical spec-ifications agreement;Basis: The basis is a statement that providesthe background or reason for the choice of spec-ifications!, or references a particular portionof the Safety Analysis Report that does.Although each of the preceding st

45、atements pro-vides important information, only the “Specifi-cations!”and“Applicability”statementsgovern.Section5,“Designfeatures,”andSec.6,“Admin-istrative controls,” should state the specifica-tionswithouttherelatedinformation.Section1,“Introduction,”mayincludedefinitionsthatwouldclarify the usage

46、of terms.11.3 DefinitionsThe following definitions are listed to provideuniform interpretation of terms and phrasesused in this and associated standards.certificate or charter: See license.certified: See licensed.Class A reactor operator: See senior reactoroperator.Class B reactor operator: See reac

47、toroperator.channel: A channel is the combination of sen-sor, line, amplifier, and output devices that areconnected for the purpose of measuring the valueof a parameter.channel calibration: A channel calibration isan adjustment of the channel such that its out-put corresponds with acceptable accurac

48、y toknown values of the parameter that the chan-nel measures. Calibration shall encompass theentire channel, including equipment actuation,alarm, or trip, and shall be deemed to include achannel test.channel check: A channel check is a qualita-tive verification of acceptable performance byobservatio

49、n of channel behavior, or by compar-ison of the channel with other independent chan-nels or systems measuring the same parameter.channel test: A channel test is the introduc-tion of a signal into the channel for verificationthat it is operable.confinement: Confinement is an enclosure ofthe overall facility that is designed to limit therelease of effluents between the enclosure andits external environment through controlled ordefined pathways.containment: Containment is an enclosure ofthe facility designed to 1! be at a negativeinternal pressu