ASTM D5144-00
(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
SCOPE
1.1 This guide provides a common basis on which protective coatings for the surfaces of light water-moderated nuclear power generating facilities may be qualified and selected by reproducible evaluation tests. This standard 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 (PWR's) and Boiling Water Reactors (BWR's), 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 Preparation of Test Specimens 5 Radiation Resistance 6 Decontamination 7 Physical Properties 8 Chemical Resistance 9 Fire Evaluation 10 DBA Testing 11 Surface Preparation, Coating Application, and Inspection for 12 Shop and Field Work Quality Assurance 13 Keywords 14
1.2.1 In addition, this guide addresses technical topics within ANSI N5.12 and ANSI N101.2 that were covered by separate ASTM standards, for example, surface preparation, shop and field and coating application, and 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 This standard does not purport to address all of the safetyconcerns, 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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Designation:D5144–00
Standard Guide for
Use of Protective Coating Standards in Nuclear Power
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.
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, N101.2, and N101.4.
Responsibility for updating, rewriting, and issuing appropriateANSI replacement standards has been
transferredtoASTM,specificallyASTMCommitteeD-33,onProtectiveCoatingandLiningWorkfor
Power Generation Facilities.
The objective of this guide is to provide a common basis on which to define and specify the
performance requirements for the coatings that will be used in nuclear facilities. Quality assurance in
thenuclearindustryisamandatoryrequirementforallaspectsofsafety-relatednuclearcoatingswork.
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.
D5144–00
1. Scope D 4060 Test Method for Abrasion Resistance of Organic
Coatings by the Taber Abraser
1.1 This guide provides a common basis on which protec-
D 4082 Test Method for Effects of Radiation on Coatings
tive coatings for the surfaces of nuclear power generating
Used in Light-Water Nuclear Power Plants
facilities may be qualified and selected by reproducible evalu-
D 4227 PracticeforQualificationofCoatingApplicatorsfor
ation tests. This guide also provides guidance for application
Application of Coatings to Concrete Surfaces
and maintenance of protective coatings. Under the environ-
D 4228 PracticeforQualificationofCoatingApplicatorsfor
mental operating and accident conditions of nuclear power
Application of Coatings to Steel Surfaces
generation facilities, encompassing pressurized water reactors
D 4537 Guide for Establishing Procedures to Qualify and
(PWR’s) and boiling water reactors (BWR’s), coating perfor-
Certify Inspection Personnel for Coating Work in Nuclear
mance may be affected by exposure to any one, all, or a
Facilities
combination of the following conditions: ionizing radiation;
D 4538 Terminology Relating to Protective Coating and
contamination by radioactive nuclides and subsequent decon-
Lining Work for Power Generation Facilities
tamination processes; chemical and water sprays; high-
D 4541 Test Method for Pull-Off Strength of Coatings
temperature high-pressure steam; and abrasion or wear.
Using Portable Adhesion Testers
1.2 The content of this guide includes:
D 5139 Specification for Sample Preparation for Qualifica-
Section
tion Testing of Coatings to Be Used in Nuclear Power
Referenced Documents 2
Terminology 3
Plants
Significance and Use 4
E84 Test Method for Surface Burning Characteristics of
Coating Material Testing 5
Building Materials
Surface Preparation, Coating Application, and Inspection for 6
Shop and Field Work
E 1461 Test Method for Thermal Diffusivity of Solids by
Thermal Conductivity 7
the Flash Method
Quality Assurance 8
Keywords 9 E 1530 Test Method for Evaluating the Resistance to Ther-
mal Transmission of Materials by the Guarded Heat Flow
1.2.1 In addition, this guide addresses technical topics
Meter Technique
within ANSI N5.12 and ANSI N 101.2 that are covered by
2.2 Other Standards:
separate ASTM standards, for example, surface preparation,
ANSI N5.12 Protective Coatings (Paints) for the Nuclear
(shop and field) and coating application, (shop and field).
Industry
1.2.2 Applicable sections of this guide and specific accep-
ANSI N 101.2 Protective Coatings (Paints) for Light Water
tance criteria may be incorporated into specifications and other
Nuclear Reactor Containment Facilities
documents where appropriate.
ANSI N101.4 Quality Assurance for Protective Coatings
1.3 This standard does not purport to address all of the
Applied to Nuclear Facilities
safety concerns, if any, associated with its use. It is the
ASME Boiler and Pressure Vessel Code (BPVC), Section
responsibility of the user of this standard to establish appro-
XI, “Rules for Inservice Inspection of Nuclear Power
priate safety and health practices and determine the applica-
Plant Components,”Subsection IWE “Requirements for
bility of regulatory limitations prior to use.
ClassMCandMetallicLinersofClassCCComponentsof
Light-Water Cooled Power Plants”
2. Referenced Documents
EPRI TR-109937 (1998) Guideline on Nuclear Safety-
2.1 ASTM Standards:
Related Coatings
C 177 Test Method for Steady-State Heat Flux Measure-
10CFR50. Appendix B: Title 10, Chapter 1, Energy, Part
ments and Thermal Transmission Properties by Means of
50, Domestic Licensing of Production and Utilization
the Guarded-Hot-Plate Apparatus
Facilities, Appendix B, Quality Assurance Criteria for
D 3843 Practice for Quality Assurance for Protective Coat-
Nuclear Power Plants and Fuel Reprocessing Plants
ings Applied to Nuclear Facilities
10CFR50.65 Requirements for Monitoring the Effective-
D 3911 TestMethodforEvaluatingCoatingsUsedinLight-
ness of Maintenance at Nuclear Power Plants
Water Nuclear Power Plants at Simulated Design Basis
Guide 1.54 Regulatory/(1973) Quality Assurance Require-
Accident (DBA) Conditions
ments for Protective Coatings Applied to Water-Cooled
D 3912 Test Method for Chemical Resistance of Coatings
Nuclear Power Plants
Used in Light-Water Nuclear Power Plants
USNRC Review Plan 6.1.2 Protective Coating Systems
This guide is under the jurisdiction of ASTM Committee D-33 on Protective
Coating and Lining Work for Power Generation Facilities and is the direct Annual Book of ASTM Standards, Vol 06.01.
responsibility of Subcommittee D33.02 on Service and Material Parameters. Annual Book of ASTM Standards, Vol 04.07.
Current edition approved May 10, 2000. Published July 2000. Originally Annual Book of ASTM Standards, Vol 14.02.
published as D 5144 – 91. Last previous edition D 5144 – 97. Available from American National Standards Institute, 11 W. 42nd St., 13th
CertainASTM standards are available in compilation form (which includes this Floor, New York, NY 10036.
guide), as Compilation of ASTM Standards for Use of Protective Coating Standards Available from American Society of Mechanical Engineers, Three Park Ave.,
in Nuclear Power Plants for expedient reference and usage by personnel involved New York, NY 10016-5990.
in nuclear coating work. AvailablefromEPRIDistributionCenter,207CogginsDrive,P.O.Box23205,
Annual Book of ASTM Standards, Vol 04.06. Pleasant Hills, CA 94523 (510) 934-4212.
4 11
Annual Book of ASTM Standards, Vol 06.02. Available from the U.S. Government Printing Office, Washington, DC 20402.
D5144–00
(Paints) Organic Materials 3.2.9.1 Discussion—Note that ultimately a decision must be
made as to whether or not an indeterminate coating system is
10CFR20.1(C) Standards for Protection Against Radiation;
acceptable.
Purpose
USNRC Regulatory Guide 8.8 Information Relevant to
4. Significance and Use
Ensuring that Occupational Radiation Exposures At
4.1 This guide addresses the concerns of Regulation Guide
Nuclear Power StationsWill BeAs LowAs Is Reasonably
1.54 and Standard Review Plan 6.1.2, and the replacement of
Achievable
ANSI Standards N5.12, N101.2, and N101.4. This guide
covers coating work on previously coated surfaces as well as
3. Terminology
bare substrates. This guide applies to all coating work in
3.1 Definitions—Definitions for use with this guide are
Service Level I and III areas (that is, safety-related coating
shown in Terminology D 4538 or other applicable standards.
work). Applicable sections of this guide may also be used to
3.2 Definitions of Terms Specific to This Standard: evaluate and select protective coatings for Service Level II
areas where deemed appropriate by the licensee.
3.2.1 ALARA—the concept of reducing radiation exposure
4.2 The testing referenced in this guide is particularly
to personnel to levels “as low as is reasonably achievable,” as
appropriate for safety-related coatings inside the reactor-
defined in the USNRC Regulation Guide 8.8, and
containment. Other test methods may be used for assessing the
10CFR20.1(C).
suitability for service of safety-related coatings outside the
3.2.2 Coating Service Level I—Termsusedtodescribeareas
reactor-containment. Criteria for evaluation and selection of
inside the reactor-containment where coating failure could
Service Level III coatings shall be addressed in job specifica-
adversely affect the operation of post-accident fluid systems
tions. Guidance for selecting safety-related and other coatings
and, thereby, impair safe shutdown.
located outside the reactor-containment is provided in Sections
3.2.3 Coating Service Level II—Terms used to describe
4.4 and 4.5 of EPRI TR-109937 (1998).
areas outside the reactor-containment where coating failure
4.3 Users of this guide must ensure that coatings work
could impair, but not prevent, normal operating performance.
complies not only with this guide, but also with the licensee’s
The function of Coating Service Level II coatings is to provide
plant-specific quality assurance program and licensing com-
corrosion protection and decontaminability in those areas
mitments.
outside the reactor-containment subject to radiation exposure
4.4 Safety-Related Coatings:
and radionuclide contamination. Service Level II coatings are
4.4.1 The qualification of coatings for Service Levels I and
not safety-related.
III are different even though they are both safety-related. This
3.2.4 Coatings Service Level III—Terms used to describe
standard guide provides the minimum requirements for quali-
areas outside the reactor-containment where coating failure
fying Service Level I coatings and also provides guidance for
could adversely affect the safety function of a safety-related
additional qualification tests that may be used to evaluate
structure, system or component (SSC).
Service Level I coatings. This standard guide does not provide
3.2.5 Safety-Related Coating System—A coating system
minimum requirements for qualifying Service Level III coat-
used inside or outside of the reactor-containment, the detach-
ings but does provide guidance for qualification tests that may
ment of which could adversely affect the safety function of a
be applicable for use in evaluating Service Level III coatings.
safety-related structure, system or component (SSC).
4.4.2 Service Level I Coatings:
3.2.6 DBA Qualified Coating System—A coating system
4.4.2.1 All Service Level I coatings must be resistant to the
used inside reactor-containment that can be attested to having
effects of radiation and must be DBA qualified. The test
passedtherequiredlaboratorytesting,includingirradiationand
specimens shall be prepared, irradiated and DBA tested and
simulated Design Basis Accident (DBA), and has adequate
evaluated in accordance with the requirements of:
quality documentation to support its use as DBA qualified.
(a) Test Method D 3911 or plant specific requirements as
3.2.7 DBA Unqualified Coating System—A coating system
applicable,
used inside reactor-containment that cannot be attested to
(b) Test Method D 4082, and
having passed the required laboratory testing, including irra-
(c) Specification D 5139.
diation and simulated Design Basis Accident (DBA), or has
4.4.2.2 In addition to the requirements of 4.4.2.1, Service
inadequate quality documentation, or both, to support its use as
Level I coatings may be evaluated for additional qualities or
DBA qualified.
may require application controls when deemed applicable by
3.2.8 Acceptable Coating or Lining System—A safety-
the job specifications or licensing commitments.The following
related coating or lining system for which a suitability for
documents provide guidance for application, possible addi-
application review which meets the plant licensing require-
tional testing or for the further evaluation of Service Level I
ments has been completed and there is reasonable assurance
coatings when applicable:
that, when properly applied and maintained, the coating or
(a) Test Meth
...
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