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
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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withdrawn!, “NuclearSafety Criteria for the Design of Stationary Pressurized Water Reactor Plants,”and ANSI0ANS-52.1-1983 R1988!withdrawn!, “Nuclear Safety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withdrawn!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withdrawn!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withdrawn!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
