1、Designation: D 5144 00Standard Guide forUse of Protective Coating Standards in Nuclear PowerPlants1This standard is issued under the fixed designation D 5144; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revisio
2、n. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.INTRODUCTIONProtective coatings (paints) have been used extensively in the nuclear industry to protect thesurfaces of facilities and equipmen
3、t from corrosion and contamination by radioactive nuclides inaccordance with ALARA. In the absence of a standard method of selecting, testing, and evaluatingcoatings, many sites evaluated paints by empirical tests to determine which were useful in theirparticular operation. Understandably, the metho
4、ds of testing were not uniform throughout the industry.It has been very difficult, consequently, to compare the results obtained at one site with those obtainedat another. Standard tests whereby industrial (nuclear) users of paints systematically preparespecimens and subject them to selected evaluat
5、ions, thus permitting uniform comparisons, areadvantageous, internationally as well as domestically.The designer of light water-moderated nuclear reactor systems must consider the possibility of aDesign Basis Accident (DBA) and the subsequent events which might lead to the release or expulsionof a f
6、raction of the fission-product inventory of the core to the reactor containment facility. Engineeredsafety features, principally a reactor containment facility, are provided to prevent the release of fissionproducts to the biological environment during and after this improbable event. The design, fa
7、brication,quality assurance, and testing of these engineered safety features ensure reliable operation and safetyunder all anticipated conditions.Large areas of the reactor-containment facility are painted with safety-related coatings. If severedelamination, peeling, or flaking causes significant po
8、rtions of the coating to be discharged into thecommon water reservoir, the performance of the safety systems could be seriously compromised bythe plugging of strainers, flow lines, pumps, spray nozzles, and core coolant channels. Safety-relatedcoatings may also exist outside of the reactor-containme
9、nt.This guide is the result of a comprehensive examination of the experience and data that have beendeveloped on protective coatings in the nuclear industry over approximately 40 years. Standardspertaining to nuclear coatings have historically been covered by ANSI N5.12, N101.2, and N101.4.Responsib
10、ility for updating, rewriting, and issuing appropriate ANSI replacement standards has beentransferred to ASTM, specifically ASTM Committee D-33, on Protective Coating and Lining Work forPower Generation Facilities.The objective of this guide is to provide a common basis on which to define and specif
11、y theperformance requirements for the coatings that will be used in nuclear facilities. Quality assurance inthe nuclear industry is a mandatory requirement for all aspects of safety-related nuclear coatings work.Licensees of nuclear power plants are required to determine if coated surfaces are withi
12、n the scope of10CFR50.65,“ The Maintenance Rule”. Any coated surfaces found to be within the scope of10CFR50.65 must satisfy the requirements of 10CFR50.65. ASME Section XI, Subsection IWEcontains the requirements for periodic evaluation of the reactor-containment steel pressure boundary.1Copyright
13、ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.1. Scope1.1 This guide provides a common basis on which protec-tive coatings for the surfaces of nuclear power generatingfacilities may be qualified and selected by reproducible evalu-ation tests. This guide also provides g
14、uidance for applicationand maintenance of protective coatings. Under the environ-mental operating and accident conditions of nuclear powergeneration facilities, encompassing pressurized water reactors(PWRs) and boiling water reactors (BWRs), coating perfor-mance may be affected by exposure to any on
15、e, all, or acombination of the following conditions: ionizing radiation;contamination by radioactive nuclides and subsequent decon-tamination processes; chemical and water sprays; high-temperature high-pressure steam; and abrasion or wear.1.2 The content of this guide includes:SectionReferenced Docu
16、ments 2Terminology 3Significance and Use 4Coating Material Testing 5Surface Preparation, Coating Application, and Inspection forShop and Field Work6Thermal Conductivity 7Quality Assurance 8Keywords 91.2.1 In addition, this guide addresses technical topicswithin ANSI N5.12 and ANSI N101.2 that are co
17、vered byseparate ASTM standards, for example, surface preparation,(shop and field) and coating application, (shop and field).1.2.2 Applicable sections of this guide and specific accep-tance criteria may be incorporated into specifications and otherdocuments where appropriate.21.3 This standard does
18、not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standa
19、rds:C 177 Test Method for Steady-State Heat Flux Measure-ments and Thermal Transmission Properties by Means ofthe Guarded-Hot-Plate Apparatus3D 3843 Practice for Quality Assurance for Protective Coat-ings Applied to Nuclear Facilities4D 3911 Test Method for Evaluating Coatings Used in Light-Water Nu
20、clear Power Plants at Simulated Design BasisAccident (DBA) Conditions4D 3912 Test Method for Chemical Resistance of CoatingsUsed in Light-Water Nuclear Power Plants4D 4060 Test Method for Abrasion Resistance of OrganicCoatings by the Taber Abraser5D 4082 Test Method for Effects of Radiation on Coati
21、ngsUsed in Light-Water Nuclear Power Plants4D 4227 Practice for Qualification of Coating Applicators forApplication of Coatings to Concrete Surfaces4D 4228 Practice for Qualification of Coating Applicators forApplication of Coatings to Steel Surfaces4D 4537 Guide for Establishing Procedures to Quali
22、fy andCertify Inspection Personnel for Coating Work in NuclearFacilities4D 4538 Terminology Relating to Protective Coating andLining Work for Power Generation Facilities4D 4541 Test Method for Pull-Off Strength of CoatingsUsing Portable Adhesion Testers4D 5139 Specification for Sample Preparation fo
23、r Qualifica-tion Testing of Coatings to Be Used in Nuclear PowerPlants4E 84 Test Method for Surface Burning Characteristics ofBuilding Materials6E 1461 Test Method for Thermal Diffusivity of Solids bythe Flash Method7E 1530 Test Method for Evaluating the Resistance to Ther-mal Transmission of Materi
24、als by the Guarded Heat FlowMeter Technique72.2 Other Standards:ANSI N5.12 Protective Coatings (Paints) for the NuclearIndustry8ANSI N 101.2 Protective Coatings (Paints) for Light WaterNuclear Reactor Containment Facilities8ANSI N101.4 Quality Assurance for Protective CoatingsApplied to Nuclear Faci
25、lities8ASME Boiler and Pressure Vessel Code (BPVC), SectionXI, “Rules for Inservice Inspection of Nuclear PowerPlant Components,”Subsection IWE “Requirements forClass MC and Metallic Liners of Class CC Components ofLight-Water Cooled Power Plants”9EPRI TR-109937 (1998) Guideline on Nuclear Safety-Re
26、lated Coatings1010CFR50. Appendix B: Title 10, Chapter 1, Energy, Part50, Domestic Licensing of Production and UtilizationFacilities, Appendix B, Quality Assurance Criteria forNuclear Power Plants and Fuel Reprocessing Plants1110CFR50.65 Requirements for Monitoring the Effective-ness of Maintenance
27、at Nuclear Power Plants11Guide 1.54 Regulatory/(1973) Quality Assurance Require-ments for Protective Coatings Applied to Water-CooledNuclear Power Plants111This guide is under the jurisdiction of ASTM Committee D-33 on ProtectiveCoating and Lining Work for Power Generation Facilities and is the dire
28、ctresponsibility of Subcommittee D33.02 on Service and Material Parameters.Current edition approved May 10, 2000. Published July 2000. Originallypublished as D 5144 91. Last previous edition D 5144 97.2Certain ASTM standards are available in compilation form (which includes thisguide), as Compilatio
29、n of ASTM Standards for Use of Protective Coating Standardsin Nuclear Power Plants for expedient reference and usage by personnel involvedin nuclear coating work.3Annual Book of ASTM Standards, Vol 04.06.4Annual Book of ASTM Standards, Vol 06.02.5Annual Book of ASTM Standards, Vol 06.01.6Annual Book
30、 of ASTM Standards, Vol 04.07.7Annual Book of ASTM Standards, Vol 14.02.8Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.9Available from American Society of Mechanical Engineers, Three Park Ave.,New York, NY 10016-5990.10Available from EPRI Distrib
31、ution Center, 207 Coggins Drive, P.O. Box 23205,Pleasant Hills, CA 94523 (510) 934-4212.11Available from the U.S. Government Printing Office, Washington, DC 20402.D 51442USNRC Review Plan 6.1.2 Protective Coating Systems(Paints) Organic Materials1110CFR20.1(C) Standards for Protection Against Radiat
32、ion;Purpose11USNRC Regulatory Guide 8.8 Information Relevant toEnsuring that Occupational Radiation Exposures AtNuclear Power Stations Will Be As Low As Is ReasonablyAchievable113. Terminology3.1 DefinitionsDefinitions for use with this guide areshown in Terminology D 4538 or other applicable standa
33、rds.3.2 Definitions of Terms Specific to This Standard:3.2.1 ALARAthe concept of reducing radiation exposureto personnel to levels “as low as is reasonably achievable,” asdefined in the USNRC Regulation Guide 8.8, and10CFR20.1(C).3.2.2 Coating Service Level ITerms used to describe areasinside the re
34、actor-containment where coating failure couldadversely affect the operation of post-accident fluid systemsand, thereby, impair safe shutdown.3.2.3 Coating Service Level IITerms used to describeareas outside the reactor-containment where coating failurecould impair, but not prevent, normal operating
35、performance.The function of Coating Service Level II coatings is to providecorrosion protection and decontaminability in those areasoutside the reactor-containment subject to radiation exposureand radionuclide contamination. Service Level II coatings arenot safety-related.3.2.4 Coatings Service Leve
36、l IIITerms used to describeareas outside the reactor-containment where coating failurecould adversely affect the safety function of a safety-relatedstructure, system or component (SSC).3.2.5 Safety-Related Coating SystemA coating systemused inside or outside of the reactor-containment, the detach-me
37、nt of which could adversely affect the safety function of asafety-related structure, system or component (SSC).3.2.6 DBA Qualified Coating SystemA coating systemused inside reactor-containment that can be attested to havingpassed the required laboratory testing, including irradiation andsimulated De
38、sign Basis Accident (DBA), and has adequatequality documentation to support its use as DBA qualified.3.2.7 DBA Unqualified Coating SystemA coating systemused inside reactor-containment that cannot be attested tohaving passed the required laboratory testing, including irra-diation and simulated Desig
39、n Basis Accident (DBA), or hasinadequate quality documentation, or both, to support its use asDBA qualified.3.2.8 Acceptable Coating or Lining SystemA safety-related coating or lining system for which a suitability forapplication review which meets the plant licensing require-ments has been complete
40、d and there is reasonable assurancethat, when properly applied and maintained, the coating orlining will not detach under normal or accident conditions.3.2.9 Indeterminate Coating or Lining SystemA safety-related coating or lining system for which there is insufficientevidence to demonstrate that it
41、 is suitable for its intended useand that it is acceptable.3.2.9.1 DiscussionNote that ultimately a decision must bemade as to whether or not an indeterminate coating system isacceptable.4. Significance and Use4.1 This guide addresses the concerns of Regulation Guide1.54 and Standard Review Plan 6.1
42、.2, and the replacement ofANSI Standards N5.12, N101.2, and N101.4. This guidecovers coating work on previously coated surfaces as well asbare substrates. This guide applies to all coating work inService Level I and III areas (that is, safety-related coatingwork). Applicable sections of this guide m
43、ay also be used toevaluate and select protective coatings for Service Level IIareas where deemed appropriate by the licensee.4.2 The testing referenced in this guide is particularlyappropriate for safety-related coatings inside the reactor-containment. Other test methods may be used for assessing th
44、esuitability for service of safety-related coatings outside thereactor-containment. Criteria for evaluation and selection ofService Level III coatings shall be addressed in job specifica-tions. Guidance for selecting safety-related and other coatingslocated outside the reactor-containment is provide
45、d in Sections4.4 and 4.5 of EPRI TR-109937(1998).4.3 Users of this guide must ensure that coatings workcomplies not only with this guide, but also with the licenseesplant-specific quality assurance program and licensing com-mitments.4.4 Safety-Related Coatings:4.4.1 The qualification of coatings for
46、 Service Levels I andIII are different even though they are both safety-related. Thisstandard guide provides the minimum requirements for quali-fying Service Level I coatings and also provides guidance foradditional qualification tests that may be used to evaluateService Level I coatings. This stand
47、ard guide does not provideminimum requirements for qualifying Service Level III coat-ings but does provide guidance for qualification tests that maybe applicable for use in evaluating Service Level III coatings.4.4.2 Service Level I Coatings:4.4.2.1 All Service Level I coatings must be resistant to
48、theeffects of radiation and must be DBA qualified. The testspecimens shall be prepared, irradiated and DBA tested andevaluated in accordance with the requirements of:(a) Test Method D 3911 or plant specific requirements asapplicable,(b) Test Method D 4082, and(c) Specification D 5139.4.4.2.2 In addi
49、tion to the requirements of 4.4.2.1, ServiceLevel I coatings may be evaluated for additional qualities ormay require application controls when deemed applicable bythe job specifications or licensing commitments. The followingdocuments provide guidance for application, possible addi-tional testing or for the further evaluation of Service Level Icoatings when applicable:(a) Test Method C 177,(b) Practice D 3843,(c) Test Method D 3912,(d) Test Method D 4060,(e) Practice D 4227,(f) Practice D 4228,(g) Guide D 4537,D 51443(h) Test Method D 4541,(i) Test Method E 84,(j) Test Me
