ANS 58 14-2011 Safety and Pressure Integrity Classification Criteria for Light Water Reactors《轻水反应堆的安全性和压力完整性的分类标准》.pdf

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1、ANSI/ANS-58.14-2011safety and pressure integrityclassification criteria forlight water reactorsANSI/ANS-58.14-2011ANSI/ANS-58.14-2011American National StandardSafety and Pressure IntegrityClassification Criteria forLight Water ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclea

2、r SocietyStandards CommitteeWorking Group ANS-58.14Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved April 22, 2011by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National

3、 Standard attests thatthe 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 procedures of the Standards Committee ofthe American Nuclear

4、Society; these procedures are 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 par

5、ticipate.An 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 us

6、ing prod-ucts, 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

7、 time ofits approval and publication. 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 It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures.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 thi

8、s standardare 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.Requests for inter

9、pretation should be sent to 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.Pub

10、lished byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2011 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-58.14-2011 with permissio

11、n 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 AmericaInquiryRequestsThe American Nuclear Society ANS! Standards Committee will provide re-sponses

12、 to inquiries about requirements, recommendations, and0or permissivestatements i.e., “shall,” “should,” and “may,” respectively! in American NationalStandards that are developed and approved by ANS. Responses to inquiries willbe provided according to the Policy Manual for the ANS Standards Committee

13、.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 only a specific design, oper-ation, facility, or other unique situation and therefore is not inten

14、ded 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 requests must include the following:1! the name, company name if applicable,

15、 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! a proposed reply, if the inquirer is in a position to offer one.Inquiries

16、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 “Safety and Pressure Integ-rity Classification Criteria for Light Water Reactors,” ANSI0ANS-

17、58.14-2011.!This standard revises and supersedes the safety and pressure integrity classifi-cation criteria provided in ANSI0ANS-51.1-1983 R1988!withdrawn!, “NuclearSafety Criteria for the Design of Stationary Pressurized Water Reactor Plants,”and ANSI0ANS-52.1-1983 R1988!withdrawn!, “Nuclear Safety

18、 Criteria for theDesign of Stationary Boiling Water Reactor Plants.”1!The criteria in this stan-dard are primarily objective; are applicable to all nuclear power plant functions,structures, systems, components, and parts including consumables!; and areapplicable to any light water reactor LWR! nucle

19、ar power plant design. Thecriteria in ANSI0ANS-51.1-1983 R1988!withdrawn! and ANSI0ANS-52.1-1983R1988!withdrawn! are primarily subjective, apply primarily to systems, andapply only to the new designs of pressurized water reactors and boiling waterreactors BWRs! available in the United States in 1983

20、.This standard uses separate sets of terms for safety classification criteria2!andpressure integrity classification criteria.3!ANSI0ANS-51.1-1983 R1988!with-drawn! and ANSI0ANS-52.1-1983 R1988!withdrawn! address both safety andpressure integrity classification criteria using a single set of termsSaf

21、ety Classes1, 2, and 3, and Non-Nuclear Safety!. The applicability of these two sets of criteriais not identical. The single set of terms used inANSI0ANS-51.1-1983R1998!with-drawn!andANSI0ANS-52.1-1983R1988!withdrawn!creates inconsistencies anda potential for misinterpretations. These limitations ar

22、e avoided in this standard.The safety classification criteria in this standard are based on NEDC-31509,“Safety Classification Methodology and Criteria for Structures, Systems, Com-ponents and Parts in BWR Nuclear Power Plants,” developed by the Parts SafetyClassification Committee of the BWR Owners

23、Group and GE Nuclear Energy,and on EPRI NP-6895, “Guidelines for the Safety Classification of Systems,Components and Parts Used in Nuclear Power Plant Applications NCIG-17!,”developed by the Nuclear Construction Issues Group, a utility group sponsoredby the Electric Power Research Institute.The appl

24、ication of many requirements to nuclear power plant structures, sys-tems, components, and parts is based upon their safety classification. The safetyclassification of an item is typically used to determine which design, procure-ment, manufacturing, construction, and operating requirements or control

25、s apply.The term “safety-related” is used to identify items that, because of their func-tional safety importance, must meet stringent design requirements such asSeismic Category I criteria; IEEE Class 1E criteria for electrical items; ASMEBoiler and Pressure Vessel Code, Sec. III, criteria for press

26、ure integrity items;and environmental qualification requirements of Code of Federal Regulations,Title 10, “Energy,” Part 50, “Domestic Licensing of Production and UtilizationFacilities,” Sec. 49, “Environmental Qualification of Electric Equipment Impor-tant to Safety for Nuclear Power Plants.”The sa

27、fety classification of an item might be also used to help establish theprocurement requirements for the item. Typically, there are three types of pro-curement classifications: safety-related, commercial grade, and non-safety-related.1!The remaining portions of ANSI0ANS-51.1-1983 R1988!withdrawn! and

28、 ANSI0ANS-52.1-1983 R1988!withdrawn! are not superseded by this standard.2!Safety-related Q!, non-safety-related with augmented quality assurance or augmentedA!#, and non-safety-related N!.3!Classes 1, 2, 3, 4, and 5.iA safety-related procurement refers to an item that is purchased subject to thepro

29、visions of Code of Federal Regulations, Title 10, “Energy,” Part 21, “Reportingof Defects and Noncompliance” 10 CFR 21!, and is intended for use in applica-tions that are functionally safety-related. Commercial-grade procurement refersto an item that is purchased without the provisions of 10 CFR 21

30、but is intendedto be dedicated after receipt for use in applications that are functionally safety-related. Once a commercial-grade item is dedicated, it becomes a safety-relateditem. Non-safety-related procurement refers to an item that is purchased with-out the provisions of 10 CFR 21 and is intend

31、ed for use in applications that arefunctionally non-safety-related.During construction, safety-related items are subject to specific material selec-tion, design, fabrication, examination, testing, inspection, certification, installa-tion, and quality assurance requirements.Operationally, safety-rela

32、ted items typically are subject to specified require-ments for in-service inspection, in-service testing, maintenance, surveillance,and quality assurance.The classification “non-safety-related with augmented requirements” is appliedto certain non-safety-related items during procurement, construction

33、, and oper-ations when the item is not safety-related but is relied upon during a specialevent or where licensing requirements exist.The focus of safety classification in this standard is on the accomplishment ofsafety-related functions that may be considered to provide design-basis-eventprevention,

34、 mitigation, or both, without emphasizing one over the other. Multipleredundant levels of defense provide a balance of defense-in-depth strategies suchthat no single element e.g., accident prevention! or barrier e.g., containment! isemphasized to the exclusion of others. An adequate balance of preve

35、ntion andmitigation as well as consideration of defense in depth is provided in the classi-fication process through the consideration of the three basic safety-related func-tions identified in Code of Federal Regulations, Title 10, “Energy,” Part 50,“Domestic Licensing of Production and Utilization

36、Facilities,” Sec. 2, “Definitions.”The pressure integrity classification criteria provided in Sec. 5 are similar tothose of ANSI0ANS-51.1-1983R1988!withdrawn!, ANSI0ANS-52.1-1983R1988!withdrawn!, and Regulatory Guide 1.26, “Quality Group Classifications andStandards for Water-, Steam-, and Radioacti

37、ve-Waste-Containing Components ofNuclear Power Plants,” but have been revised to be applicable to any LWRdesign particularly an advanced passive design!.The basic design requirements for items assigned to each safety classificationare summarized in Sec. 6.This standard has been written for prospecti

38、ve use, but the criteria are based oncurrent practices and requirements applicable to licensed LWR designs.This standard might reference documents and other standards that have beensuperseded or withdrawn at the time the standard is applied. A statement hasbeen included in the references section Sec

39、. 7! that provides guidance on the useof references.This standard does not incorporate the concepts of generating risk-informedinsights, performance-based requirements, or a graded approach to quality as-surance. The user is advised that one or more of these techniques could enhancethe application o

40、f this standard.Working Group ANS-58.14 of the Standards Committee of the American NuclearSociety had the following membership at the time it developed this standard:iiM. A. Linn Chair!, Oak Ridge National LaboratoryD. P. Blanchard, Applied Reliability Engineering, Inc.S. A. Highley, AREVA NP, Inc.R

41、. A. Hill, ERIN Engineering and Research, Inc.G. B. Locklear, Engineering 2! include provisions for ensuring that allitems required by the licensing design basisare appropriately classified;3! allow maximum compatibility with plant-specific designs, policies, and procedures;4! achieve consistency i.

42、e., minimize classi-fication differences among similar items inthe plant! among utilities, vendors, designs,and regulators, and with current industryand regulatory practices.1.3 ApplicabilityThis standard is applicable to LWR designs. Itis based upon current regulations, criteria, andexperience. Som

43、e of the criteria and guidanceprovided herein might differ from those usedas the bases for previously licensed designs.1!Numbers in brackets refer to corresponding numbers in Sec. 7, “References.”2!See the Foreword and Appendices A through D for additional discussion.3!The scope of pressure-retainin

44、g items with respect to this standard is discussed in Sec. 5.12 Acronyms and definitions2.1 List of acronymsA: non-safety-related with augmented require-mentsALWR: advanced light water reactorAST: alternate source termANS: American Nuclear SocietyANSI: American National Standards InstituteASME: Amer

45、ican Society of Mechanical Engi-neersATWS: anticipated transient without scramB items consumed or expended in maintain-ing the chemical control of system processfluids e.g., resins, additive chemicals andgases such as boron, pH buffer, bromophe-nol blue, and nitric acid!;or items consumed or expende

46、d during main-tenance, installation, and modification ac-tivities and that are generally usedthroughout the plant and might not be4!In passive advanced light water reactor ALWR! designs, passive engineered safety features ESFs! arethose that rely on passive means to provide their functions. Passive

47、means are natural forces e.g., gravity andnatural circulation!, stored energy e.g., batteries, rotating inertia, and compressed fluid!, energy inherent tothe system, and noncycling valves. Passive means do not rely on large, continuously rotating machinery;multiple acting valves; or alternating-curr

48、entpowered divisions of electrical power.American National Standard ANSI0ANS-58.14-20112included in the above e.g., solvents, layoutfluid, welding rods, leak-testing fluid, tape,and penetrant testing materials!.design basis event (DBE): An event that is acondition of normal operation, including anti

49、ci-pated operational occurrences, design basis ac-cidentsor transient!, external events, or naturalphenomena for which the plant must be de-signed to ensure the three basic safety-relatedfunctions are achieved. See the definition for“safety-related” for a description of the threebasic safety-related functions.design function: A principal function for whicha SSC was included in the plant design. De-sign functions, as they relate to safety-relateditems, support one or more of the three basicsafety-related functions. For example