Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 This guide addresses the concerns of Regulation Guide 1.54 and USNRC Standard Review Plan 6.1.2, and the replacement of ANSI Standards N5.12, N101.2, and N101.4. This guide covers coating work on previously coated surfaces as well as bare substrates. This guide applies to all coating work in Coating Service Level I and III areas (that is, safety-related coating work). Applicable sections of this guide may also be used to evaluate and select protective coatings for Coating Service Level II areas where deemed appropriate by the licensee.  
4.2 The testing referenced in this guide is particularly appropriate for safety-related coatings inside the reactor-containment. Other test methods may be used for assessing the suitability for service of safety-related coatings outside the reactor-containment. Criteria for qualification and performance monitoring of Coating Service Level III coatings shall be addressed in job specifications. Guidance for selecting and performance monitoring of Coating Service Level III coatings is provided Guides D7230 and D7167 respectively, and Sections 4.4 and 4.5 of EPRI 1019157 (formerly TR-109937 and 1003102.).  
4.3 Users of this guide must ensure that coatings work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.  
4.4 Safety-Related Coatings:  
4.4.1 The qualification of coatings for Coating Service Levels I and III are different even though they are both safety-related. This guide provides the minimum requirements for qualifying Coating Service Level I coatings and also provides guidance for additional qualification tests that may be used to evaluate Coating Service Level I coatings. This guide also provides guidance concerning selection of Coating Service Level III coatings.  
4.4.2 Coating Service Level I Coatings:  
4.4.2.1 All Coating Service Level I coatings must be resistant to the effects of radiation and must be DBA qualified. The test sp...
SCOPE
1.1 This guide provides a common basis on which protective coatings for the surfaces of nuclear power generating facilities may be qualified and selected by reproducible evaluation tests. This guide also provides guidance for application and maintenance of protective coatings. Under the environmental operating and accident conditions of nuclear power generation facilities, encompassing pressurized water reactors (PWRs) and boiling water reactors (BWRs), coating performance may be affected by exposure to any one, all, or a combination of the following conditions: ionizing radiation; contamination by radioactive nuclides and subsequent decontamination processes; chemical and water sprays; high-temperature high-pressure steam; and abrasion or wear.  
1.2 The content of this guide includes:    
Section  
Referenced Documents  
2  
Terminology  
3  
Significance and Use  
4  
Coating Material Testing  
5  
Thermal Conductivity  
5  
Surface Preparation, Coating Application, and Inspection for
Shop and Field Work  
6  
Quality Assurance  
7  
Keywords  
8  
1.2.1 In addition, this guide addresses technical topics within ANSI N5.12 and ANSI N101.2 that are covered by separate 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 acceptance criteria may be incorporated into specifications and other documents where appropriate.2  
1.3 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This internatio...

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This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: D5144 − 08 (Reapproved 2021)
Standard Guide for
Use of Protective Coating Standards in Nuclear Power
Plants
This standard is issued under the fixed designation D5144; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
Protective coatings (paints) have been used extensively in the nuclear industry to protect the
surfaces of facilities and equipment from corrosion and contamination by radioactive nuclides in
accordance with ALARA. In the absence of a standard method of selecting, testing, and evaluating
coatings, many sites evaluated paints by empirical tests to determine which were useful in their
particularoperation.Understandably,themethodsoftestingwerenotuniformthroughouttheindustry.
It has been very difficult, consequently, to compare the results obtained at one site with those obtained
at another. Standard tests whereby industrial (nuclear) users of paints systematically prepare
specimens and subject them to selected evaluations, thus permitting uniform comparisons, are
advantageous, internationally as well as domestically.
The designer of light water-moderated nuclear reactor systems must consider the possibility of a
Design BasisAccident (DBA) and the subsequent events which might lead to the release or expulsion
ofafractionofthefission-productinventoryofthecoretothereactorcontainmentfacility.Engineered
safety features, principally a reactor containment facility, are provided to prevent the release of fission
productstothebiologicalenvironmentduringandafterthisimprobableevent.Thedesign,fabrication,
quality assurance, and testing of these engineered safety features ensure reliable operation and safety
under all anticipated conditions.
Large areas of the reactor-containment facility are painted with safety-related coatings. If severe
delamination, peeling, or flaking causes significant portions of the coating to be discharged into the
common water reservoir, the performance of the safety systems could be seriously compromised by
the plugging of strainers, flow lines, pumps, spray nozzles, and core coolant channels. Safety-related
coatings may also exist outside of the reactor-containment.
This guide is the result of a comprehensive examination of the experience and data that have been
developed on protective coatings in the nuclear industry over approximately 50 years. Standards
pertaining to nuclear coatings have historically been covered by ANSI N5.12, ANSI N101.2, and
ANSI N101.4. Responsibility for updating, rewriting, and issuing appropriate ANSI replacement
standards has been transferred to ASTM, specifically ASTM Committee D33, on Protective Coating
and Lining Work for Power Generation Facilities.
The objective of this guide is to provide a common basis on which protective coatings for the
surfaces of nuclear power generating facilities may be qualified and selected by reproducible
evaluation tests. This guide also provides guidance for application and maintenance of protective
coatings. Quality assurance in the 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 within the scope of 10CFR50.65, “The Maintenance Rule.” Any coated surfaces
found to be within the scope of 10CFR50.65 must satisfy the requirements of 10CFR50.65. ASME
Section XI, Subsection IWE contains the requirements for periodic evaluation of the reactor-
containment steel pressure boundary.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
D5144 − 08 (2021)
1. Scope 2. Referenced Documents
1.1 This guide provides a common basis on which protec- 2.1 ASTM Standards:
tive coatings for the surfaces of nuclear power generating C177 Test Method for Steady-State Heat Flux Measure-
facilities may be qualified and selected by reproducible evalu- ments and Thermal Transmission Properties by Means of
ation tests. This guide also provides guidance for application the Guarded-Hot-Plate Apparatus
and maintenance of protective coatings. Under the environ- D3843 Practice for Quality Assurance for Protective Coat-
mental operating and accident conditions of nuclear power ings Applied to Nuclear Facilities
generation facilities, encompassing pressurized water reactors D3911 Test Method for Evaluating Coatings Used in Light-
(PWRs) and boiling water reactors (BWRs), coating perfor- Water Nuclear Power Plants at Simulated Design Basis
mance may be affected by exposure to any one, all, or a Accident (DBA) Conditions
combination of the following conditions: ionizing radiation; D3912 Test Method for Chemical Resistance of Coatings
contamination by radioactive nuclides and subsequent decon- and Linings for Use in Nuclear Power Plants
tamination processes; chemical and water sprays; high- D4060 Test Method for Abrasion Resistance of Organic
temperature high-pressure steam; and abrasion or wear. Coatings by the Taber Abraser
D4082 Test Method for Effects of Gamma Radiation on
1.2 The content of this guide includes:
Coatings for Use in Nuclear Power Plants
Section
D4227 Practice for Qualification of Coating Applicators for
Referenced Documents 2
Application of Coatings to Concrete Surfaces
Terminology 3
Significance and Use 4
D4228 Practice for Qualification of Coating Applicators for
Coating Material Testing 5
Application of Coatings to Steel Surfaces
Thermal Conductivity 5
Surface Preparation, Coating Application, and Inspection for 6 D4537 Guide for Establishing Procedures to Qualify and
Shop and Field Work
Certify Personnel Performing Coating and Lining Work
Quality Assurance 7
Inspection in Nuclear Facilities
Keywords 8
D4538 Terminology Relating to Protective Coating and
1.2.1 In addition, this guide addresses technical topics
Lining Work for Power Generation Facilities
within ANSI N5.12 and ANSI N101.2 that are covered by
D4541 Test Method for Pull-Off Strength of Coatings Using
separate ASTM standards, for example, surface preparation,
Portable Adhesion Testers
(shop and field) and coating application, (shop and field).
D5139 Specification for Sample Preparation for Qualifica-
1.2.2 Applicable sections of this guide and specific accep-
tion Testing of Coatings to be Used in Nuclear Power
tance criteria may be incorporated into specifications and other
Plants
documents where appropriate.
D5163 Guide for Establishing a Program for Condition
1.3 The values stated in inch-pound units are to be regarded
Assessment of Coating Service Level I Coating Systems
as standard. No other units of measurement are included in this
in Nuclear Power Plants
standard.
D7167 Guide for Establishing Procedures to Monitor the
Performance of Safety-Related Coating Service Level III
1.4 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the Lining Systems in an Operating Nuclear Power Plant
D7230 Guide for Evaluating Polymeric Lining Systems for
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter- Water Immersion in Coating Service Level III Safety-
Related Applications on Metal Substrates
mine the applicability of regulatory limitations prior to use.
1.5 This international standard was developed in accor- D7234 Test Method for Pull-OffAdhesion Strength of Coat-
ings on Concrete Using Portable Pull-Off Adhesion Tes-
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the ters
D7491 GuideforManagementofNon-ConformingCoatings
Development of International Standards, Guides and Recom-
mendations issued by the World Trade Organization Technical in Coating Service Level IAreas of Nuclear Power Plants
E84 Test Method for Surface Burning Characteristics of
Barriers to Trade (TBT) Committee.
Building Materials
E648 Test Method for Critical Radiant Flux of Floor-
This guide is under the jurisdiction of ASTM Committee D33 on Protective
Covering Systems Using a Radiant Heat Energy Source
Coating and Lining Work for Power Generation Facilities and is the direct
E1461 Test Method for Thermal Diffusivity by the Flash
responsibility of Subcommittee D33.02 on Service and Material Parameters.
Current edition approved Feb. 1, 2021. Published February 2021. Originally Method
approved in 1991. Last previous edition approved in 2016 as D5144 – 08 (2016).
DOI: 10.1520/D5144-08R21.
2 3
CertainASTM standards are available in compilation form (which includes this For referenced ASTM standards, visit the ASTM website, www.astm.org, or
guide), as Compilation of ASTM Standards for Use of Protective Coating Standards contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
in Nuclear Power Plants for expedient reference and usage by personnel involved Standards volume information, refer to the standard’s Document Summary page on
in nuclear coating work. the ASTM website.
D5144 − 08 (2021)
E1530 Test Method for Evaluating the Resistance to Ther- 4.2 The testing referenced in this guide is particularly
mal Transmission by the Guarded Heat Flow Meter appropriate for safety-related coatings inside the reactor-
Technique containment. Other test methods may be used for assessing the
2.2 Other Standards: suitability for service of safety-related coatings outside the
ANSI N5.12 Protective Coatings (Paints) for the Nuclear reactor-containment. Criteria for qualification and performance
Industry monitoring of Coating Service Level III coatings shall be
ANSI N101.2 Protective Coatings (Paints) for Light Water addressed in job specifications. Guidance for selecting and
Nuclear Reactor Containment Facilities performance monitoring of Coating Service Level III coatings
ANSI N101.4 Quality Assurance for Protective Coatings is provided Guides D7230 and D7167 respectively, and Sec-
Applied to Nuclear Facilities tions 4.4 and 4.5 of EPRI 1019157 (formerly TR-109937 and
ASMEBoilerandPressureVesselCode(BPVC) SectionXI, 1003102.).
Rules for Inservice Inspection of Nuclear Power Plant
4.3 Users of this guide must ensure that coatings work
Components, Subsection IWE Requirements for Class
complies not only with this guide, but also with the licensee’s
MC and Metallic Liners of Class CC Components of
plant-specific quality assurance program and licensing com-
Light-Water Cooled Power Plants
mitments.
EPRI 1019157 Plant Support Engineering: Guideline on
4.4 Safety-Related Coatings:
Nuclear Safety-Related Coatings Revision 2 (formerly
4.4.1 The qualification of coatings for Coating Service
TR-109937 and 1003102)
Levels I and III are different even though they are both
10CFR50 Appendix B:Title 10, Chapter 1, Energy, Part 50,
safety-related. This guide provides the minimum requirements
Domestic Licensing of Production and Utilization
for qualifying Coating Service Level I coatings and also
Facilities, Appendix B, Quality Assurance Criteria for
provides guidance for additional qualification tests that may be
Nuclear Power Plants and Fuel Reprocessing Plants
used to evaluate Coating Service Level I coatings. This guide
10CFR50.65 Requirements for Monitoring the Effectiveness
alsoprovidesguidanceconcerningselectionofCoatingService
of Maintenance at Nuclear Power Plants
Level III coatings.
USNRC Standard Review Plan 6.1.2 Protective Coating
4.4.2 Coating Service Level I Coatings:
Systems (Paints) Organic Materials
4.4.2.1 All Coating Service Level I coatings must be resis-
USNRC Regulatory Guide 1.54 Regulatory/(1973) Quality
tant to the effects of radiation and must be DBAqualified. The
Assurance Requirements for Protective Coatings Applied
test specimens shall be prepared, irradiated and DBA tested
to Water-Cooled Nuclear Power Plants, Revisions 0, 1,
and evaluated in accordance with the requirements of:
and 2
(a) Test Method D3911 or plant specific requirements as
USNRC Regulatory Guide 8.8 Information Relevant to En-
applicable,
suring that Occupational Radiation Exposures At Nuclear
(b) Test Method D4082, and
Power StationsWill BeAs LowAs Is ReasonablyAchiev-
(c) Specification D5139.
able
4.4.2.2 In addition to the requirements of 4.4.2.1, Coating
3. Terminology
Service Level I coatings may be evaluated for additional
qualities or may require application controls when deemed
3.1 Definitions—Definitions for use with this guide are
applicable by the job specifications or licensing commitments.
shown in Terminology D4538 or other applicable standards.
The following documents provide guidance for application,
4. Significance and Use
possible additional testing or for the further evaluation of
4.1 This guide addresses the concerns of Regulation Guide Coating Service Level I coatings when applicable:
1.54andUSNRCStandardReviewPlan6.1.2,andthereplace-
(a) Test Method C177,
ment of ANSI Standards N5.12, N101.2, and N101.4. This (b) Practice D3843,
guide covers coating work on previously coated surfaces as
(c) Test Method D3912,
well as bare substrates. This guide applies to all coating work (d) Test Method D4060,
in Coating Service Level I and III areas (that is, safety-related
(e) Practice D4227,
coating work). Applicable sections of this guide may also be (f) Practice D4228,
used to evaluate and select protective coatings for Coating
(g) Guide D4537,
Service Level II areas where deemed appropriate by the (h) Test Method D4541,
licensee. (i) Test Method E84,
(j) Test Method E648,
Available from IHS, 321 Inverness Drive South, Englewood, CO 80112, (k) Test Method E1461, and
http://www.ihs.com.
(l) Test Method E1530.
Available from American Society of Mechanical Engineers (ASME), ASME
4.4.2.3 Condition assessment and management of Coating
International Headquarters, Three Park Ave., New York, NY 10016-5990, http://
Service Level I coatings is also required by the licensee to
www.asme.org.
Available from EPRI Distribution Center, 207 Coggins Drive, P.O. Box 23205,
maintain the coatings following the initial application and
Pleasant Hills, CA 94523, http://www.epri.com.
subsequentrepairs.Thefollowingdocumentsprovideguidance
Available from U.S. Government Printing Office, Superintendent of
for the monitoring and management of the Coating Service
Documents, 732 N. Capitol St., NW, Washington, DC 20401-0001, http://
www.access.gpo.gov.
...

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