ASTM D5144-08e1
(Guide)Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
SIGNIFICANCE AND USE
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.
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 D 7230 and D 7167 respectively, and Sections 4.4 and 4.5 of EPRI 1003102 (formerly TR-109937).
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.
Safety-Related Coatings:
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.
Coating Service Level I Coatings:
All Coating Service Level I coatings must be resistant to the effects of radiation and must be DBA qualified. The test specimens shall be prepared, irradiated and DBA tested...
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 Documents2 Terminology3 Significance and Use4 Coating Material Testing5 Thermal Conductivity5 Surface Preparation, Coating Application, and Inspection for
Shop and Field Work6 Quality Assurance7 Keywords8
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.
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 and health practices and determine the applicability of regulatory limitations prior to use.
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´1
Designation: D5144 − 08
StandardGuide for
Use of Protective Coating Standards in Nuclear Power
1
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.
1
´ NOTE—The title of Guide D5163 was corrected editorially in April 2009.
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 40 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
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D5144 − 08
1. Scope D3843 Practice for Quality Assurance for Protective Coat-
ings Applied to Nuclear Facilities
1.1 This guide provides a common basis on which protec-
D3911 Test Method for Evaluating Coatings Used in Light-
tive coatings for the surfaces of nuclear power generating
Water Nuclear Power Plants at Simulated Design Basis
facilities may be qualified and selected by reproducible evalu-
Accident (DBA) Conditions
ation tests. This guide also provides guidance for application
D3912 Test Method for Chemical Resistance of Coatings
and maintenance of protective coatings. Under the environ-
and Linings for Use in Nuclear Power Plants
mental operating and accident conditions of nuclear power
D4060 Test Method for Abrasion Resistance of Organic
generation facilities, encompassing pressurized water reactors
Coatings by the Taber Abraser
(PWRs) and boili
...
This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´1
Designation:D5144–00 Designation:D5144–08
Standard Guide for
Use of Protective Coating Standards in Nuclear Power
1
Plants
This standard is issued under the fixed designation D 5144; 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.
1
´ NOTE—The title of Guide D 5163 was corrected editorially in April 2009.
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 40 years. Standards
pertaining to nuclear coatings have historically been covered by ANSI N5.12, N101.2N5.12, 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 D-33,D33, on
Protective Coating and Lining Work for Power Generation Facilities.
The objective of this guide is to provide a common basis on which to define and specify protective
coatings for the performance requirements for the coatings that willsurfaces of nuclear power
generating facilities may be used in nuclear facilities. 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, “The Maintenance Rule”.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
1
This guide is under the jurisdiction ofASTM Committee D-33D33 on Protective Coating and LiningWork for Power Generation Facilities and is the direct responsibility
of Subcommittee D33.02 on Service and Material Parameters.
Current edition approved May 10, 2000. Published July 2000. Originally published as D5144–91. Last previous edition D5144–97.
Current edition approved Nov. 15, 2008. Published January 2009. Originally approved in 1991. Last previous edition approved in 2000 as D 5144 – 00.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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