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ASTM D5163-04a

(Guide)

Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant

Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant

SCOPE
1.1 This guide covers procedures for establishing a program to monitor Coating Service Level I coating systems in operating nuclear power plants. Monitoring is an on going process of evaluating the condition of the in-service coating systems.
1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings monitoring program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this guide may be appropriate for each operating nuclear power plant depending on their licensing commitments. Similar guidelines are applicable for Service Level III and other areas outside containment.
1.3 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.

General Information

Status
Historical
Publication Date
31-Jul-2004
ICS
27.120.20 - Nuclear power plants. Safety
Technical Committee
D33 - Protective Coating and Lining Work for Power Generation Facilities
Drafting Committee
D33.04 - Quality Systems and Inspection
Current Stage
Ref Project

Relations

Replaces
ASTM D5163-04 - Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant
Effective Date
01-Aug-2004
Referred By
ASTM D5498-12a(2018) - Standard Guide for Developing a Training Program for Personnel Performing Coating and Lining Work Inspection for Nuclear Facilities
Effective Date
01-Aug-2004
Referred By
ASTM D8157-19 - Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants
Effective Date
01-Aug-2004
Referred By
ASTM D5144-08(2021) - Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Effective Date
01-Aug-2004

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ASTM D5163-04a - Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power PlantASTM D5163-04a - Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant
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ASTM D5163-04a - Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:D5163–04a
Standard Guide for
Establishing Procedures to Monitor the Performance of
Coating Service Level I Coating Systems in an Operating
1
Nuclear Power Plant
This standard is issued under the fixed designation D 5163; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope D 4538 Terminology Relating to Protective Coating and
Lining Work for Power Generation Facilities
1.1 This guide covers procedures for establishing a program
D 4541 Test Method for Pull-Off Strength of Coatings
to monitor the performance of Coating Service Level I coating
2
Using Portable Adhesion Testers
systems in operating nuclear power plants. Monitoring is an on
D 5144 Guide for Use of Protective Coating Standards in
going process of evaluating the condition of the in-service
Nuclear Power Plants
coating systems.
D 6677 Test Method for Evaluating Adhesion by Knife
1.2 It is the intent of this guide to provide a recommended
F 1130 Practice for Inspecting the Coating System of a Ship
basis for establishing a coatings monitoring program, not to
2.2 ANSI Standard:
mandate a singular basis for all programs. Variations or
N45.2.6—Qualification of Inspection, Examination, and
simplifications of the program described in this guide may be
3
Testing Personnel for Nuclear Power Plants
appropriate for each operating nuclear power plant depending
on their licensing commitments. Similar guidelines are appli-
2.3 SSPC Standard:
cable for Coating Service Level III and other areas outside
SSPC-PA2—Measurement of Dry Paint Thickness With
containment.
4
Magnetic Gages
1.3 This standard does not purport to address all of the
SSPC VIS 2—Standard Method of Evaluating Degree of
safety concerns, if any, associated with its use. It is the
4
Rusting on Painted Steel Surfaces
responsibility of the user of this standard to establish appro-
2.4 USNRC NUREG:
priate safety and health practices and determine the applica-
NUREG 1801, Vol 2, April 2001 Generic Aging Lessons
bility of regulatory limitations prior to use.
Learned (GALL) Report, Section XI.S8 – Protective
5
2. Referenced Documents Coatings Monitoring and Maintenance Program
2
2.1 ASTM Standards:
3. Significance and Use
D 610 Test Method for Evaluating Degree of Rusting on
3.1 Establishment of an in-service coatings monitoring pro-
Painted Steel Surfaces
gram permits planning and prioritization of coatings mainte-
D 714 Test Method for Evaluating Degree of Blistering of
nance work as needed to maintain coating integrity and
Paints
performance in nuclear Service Level I coating systems. For
D 1186 Test Methods for Nondestructive Measurement of
additional information on nuclear maintenance coating work,
Dry Film Thickness of Nonmagnetic Coatings Applied to
refer to ASTM Manual on Maintenance Coatings for Nuclear
a Ferrous Base
6
Power Plants.
D 3359 Test Methods for MeasuringAdhesion byTapeTest
3.2 Acoatings monitoring program enables early identifica-
D 4537 Guide for Establishing Procedures to Qualify and
tion and detection of potential problems in coating systems.
Certify Personnel Performing Coating Work Inspection in
2
Some Service Level I coating systems may be known in
Nuclear Facilities
advance to be suspect, deficient, or unqualified. Monitoring
1
This guide is under the jurisdiction of ASTM Committee D33 on Protective
3
Coating and Lining Work for Power Generation Facilities and is the direct Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
responsibility of Subcommittee D33.04 on Quality Systems and Inspection. 4th Floor, New York, NY 10036.
4
Current edition approved Aug. 1, 2004. Published September 2004. Originally Available from SSPC: The Society for Protective Coatings, 40 24th St., 6th
approved in 1991. Last previous edition approved in 2004 as D 5163 – 04. Floor, Pittsburgh, PA 15222-4656.
2 5
For referenced ASTM standards, visit the ASTM website, www.astm.org, or Available from U.S. Nuclear Regulatory Commission (NRC), PDR, 01F13,
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Washington DC 20555.
6
Standards volume information, refer to the standard’s Document Summary page on Available from ASTM International Headquarters, 100 Barr Harbor Dr., West
the ASTM website. Conshohocken, PA 19428-2959.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
D5163–04a
coating performance will assist in developing follow-up pro- 6.2.1 Copies of coating specifications, manufacturer’s prod-
cedures to resolv
...

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Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination

ABSTRACT
This specification prescribes the performance criteria for non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and protect uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction, respirable fraction, radiation resistance) as well as the mechanical and chemical properties for permanent coatings that are intended to immobilize dispersible radioactive contamination deposited on buildings and equipment as might result from anticipated to unanticipated events to include normal operating conditions, decommissioning, and radiological release. The coating is intended to reduce: migration of the contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air; and the spread of contamination as a result of external forces such as pedestrian traffic. It shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be applicable to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the coating may include constituents that will physically or chemically bind and hold radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
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Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

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3.1 Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.3) and national standards groups (see 2.1 and 2.2) have promulgated regulations and standards to ensure safe operation of these vessels. The support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 3-6).2 The objective of this practice is to provide guidelines for determining the neutron radiation exposures experienced by individual vessel supports.  
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SCOPE
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:  
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1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and are to be regarded as standard. Any values in parentheses are for information only.  
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1.5 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. (For example, (2).)  
1.6 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.

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