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ASTM D5498-01

(Guide)

Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities

Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities

SIGNIFICANCE AND USE
Inspection personnel trained for coating work are required to perform examination/inspection tasks to verify conformance of coating work to written instructions/specifications.
With the use of this guide, those responsible for indoctrination and training, should be able to develop an appropriate program for training inspection personnel involved in coating work.
It should be understood that mastery of the subject matter addressed in this guide will not by itself result in the certification of inspectors. Certification of inspection personnel for coating work can be obtained as outlined in Guide D 4537.
This guide may be modified for use in nonnuclear facilities.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of inspection personnel for coating work in nuclear facilities.
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. Portions of the program may not be applicable in all cases. Therefore, it is the responsibility of each company to identify the appropriate subject matter for its organization and its site specific needs.
1.3 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.

General Information

Status
Historical
Publication Date
09-Jun-2001
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 D5498-94(1999) - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities
Effective Date
10-Jun-2001
Replaced By
ASTM D5498-09 - Standard Guide for Developing a Training Program for Personnel Performing Coating Work Inspection for Nuclear Facilities
Effective Date
01-Jun-2009
Referred By
ASTM D5163-16(2021) - Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants
Effective Date
10-Jun-2001
Referred By
ASTM D4537-12(2018) - Standard Guide for Establishing Procedures to Qualify and Certify Personnel Performing Coating and Lining Work Inspection in Nuclear Facilities
Effective Date
10-Jun-2001

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ASTM D5498-01 - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear FacilitiesASTM D5498-01 - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities
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ASTM D5498-01 - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities
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Standards Content (Sample)

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: D 5498 – 01
Standard Guide for
Developing a Training Program for Coating Work Inspectors
1
in Nuclear Facilities
This standard is issued under the fixed designation D 5498; 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 3359 Test Methods for MeasuringAdhesion by Tape Test
D 3363 Test Method for Film Hardness by Pencil Test
1.1 This guide is intended to assist those responsible for
D 3925 Practice for Sampling Liquid Paints and Related
developing a program for the indoctrination and training of
Pigmented Coatings
inspection personnel for coating work in nuclear facilities.
D 4138 Test Methods for Measurement of Dry Film Thick-
1.2 It is recognized that organizations and job responsibili-
ness of Protective Coating Systems by Destructive Means
ties vary widely among utilities and also among various
D 4212 Test Method for Viscosity by Dip-Type Viscosity
support and service companies. Portions of the program may
Cups
not be applicable in all cases. Therefore, it is the responsibility
D 4214 Test Methods for Evaluating the Degree of Chalk-
of each company to identify the appropriate subject matter for
ing of Exterior Paint Films
its organization and its site specific needs.
D 4258 Practice for Surface Cleaning Concrete for Coating
1.3 Users of this guide must ensure that coatings work
D 4259 Practice for Abrading Concrete
complies not only with this guide, but also with the licensee’s
D 4260 Practice for Liquid and Gelled Acid Etching of
plant-specific quality assurance program and licensing com-
Concrete
mitments.
D 4261 Practice for Surface Cleaning Concrete Masonry
2. Referenced Documents Units for Coating
2
D 4262 Test Method for pH of Chemically Cleaned or
2.1 ASTM Standards:
Etched Concrete Surfaces
D16 Terminology for Paint, Related Coatings, Materials,
D 4263 Test Method for Indicating Moisture in Concrete by
and Applications
the Plastic Sheet Method
D 1005 Test Method for Measurement of Dry-Film Thick-
D 4285 Test Method for Indicating Oil or Water in Com-
ness of Organic Coatings Using Micrometers
pressed Air
D 1186 Test Methods for Nondestructive Measurement of
D 4414 PracticeforMeasurementofWetFilmThicknessby
Dry Film Thickness of Nonmagnetic Coatings Applied to
Notch Gages
a Ferrous Base
D 4417 Test Methods for Field Measurement of Surface
D 1400 Test Method for Nondestructive Measurement of
Profile of Blast Cleaned Steel
DryFilmThicknessofNonconductiveCoatingsAppliedto
D 4537 Guide for Establishing Procedures to Qualify and
a Nonferrous Metal Base
Certify Personnel Performing Coating Work Inspection in
D 2092 Guide for Preparation of Zinc-Coated (Galvanized)
Nuclear Facilities
Steel Surfaces for Painting
D 4538 Terminology Relating to Protective Coating and
D 2240 Test Method for Rubber Property—Durometer
Lining Work for Power Generation Facilities
Hardness
D 4541 Test Method for Pull-Off Strength of Coatings
D 2583 Test Method for Indentation Hardness of Rigid
Using Portable Adhesion Testers
Plastics by Means of a Barcol Impressor
D 4610 Guide for Determining the Presence of and Remov-
D 3276 Guide for Painting Inspectors (Metal Substrates)
ing Microbial (Fungal or Algal) Growth on Paint and
Related Coatings
1
This guide is under the jurisdiction of ASTM Committee D33 on Protective
D 4752 Test Method for Measuring MEK Resistance of
Coating and Lining Work for Power Generation Facilities and is the direct
Ethyl Silicate (Inorganic) Zinc-Rich Primers by Solvent
responsibility of Subcommittee D33.02 on Service and Material Parameters.
Rub
Current edition approved June 10, 2001. Published August 2001. Originally
published as D 5498 – 94. Last previous edition D 5498 – 94 (1999).
D 4787 Practice for Continuity Verification of Liquid or
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Sheet Linings Applied to Concrete Substrates
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
D5498–01
D 4940 Test Method for Conductimetric Analysis of Water corrosion cycle, the four items necessary for corrosion to
Soluble Ionic Contamination of Blasting Abrasives occur, energy flow, galvanic corrosion, and basic methods of
D 5162 Practice for Discontinuity (Holiday) Testing of corrosion control.
Nonconductive Protective Coating on Metallic Substrates
4.1.3 Coating Technol
...

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SCOPE
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4.1 Personnel trained for coating and lining work inspection are required to perform examination/inspection tasks to verify conformance of coating and lining work to written requirements.  
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3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life.  
3.1.1 To satisfy the first requirement of 3.1, the tasks to be carried out are straightforward. Each of the irradiation capsules that comprise the surveillance program may be treated as a separate experiment. The goal is to define and carry to completion a dosimetry program that will, a posteriori, describe the neutron field to which the material test specimens were exposed. The resultant information will then become part of a database applicable in a stricter sense to the specific plant from which the capsule was removed, but also in a broader sense to the industry as a whole.  
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3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to ...
SCOPE
1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures2 (1-74).3  
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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.  
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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:  
1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.  
1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.  
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.  
1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm2 or exceeds 3.0 × 10−4 dpa (1).2 (See Terminology E170.)  
1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2.  
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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