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ASTM D5498-94(1999)

(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

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

Replaced By
ASTM D5498-01 - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities
Effective Date
10-Jun-2001
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 D5498-94(1999) - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear FacilitiesASTM D5498-94(1999) - Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities
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ASTM D5498-94(1999) - 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NOTICE: This standard has either been superseded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
Designation: D 5498 – 94 (Reapproved 1999)
Standard Guide for
Developing a Training Program for Coating Work Inspectors
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 4212 Test Method for Viscosity by Dip-Type Viscosity
Cups
1.1 This guide is intended to assist those responsible for
D 4214 Test Method for Evaluating Degree of Chalking of
developing a program for the indoctrination and training of
Exterior Paint Films
inspection personnel for coating work in nuclear facilities.
D 4258 Practice for Surface Cleaning Concrete for Coating
1.2 It is recognized that organizations and job responsibili-
D 4259 Practice for Abrading Concrete
ties vary widely among utilities and also among various
D 4260 Practice for Acid Etching Concrete
support and service companies. Portions of the program may
D 4261 Practice for Surface Cleaning Concrete Unit Ma-
not be applicable in all cases. Therefore, it is the responsibility
sonry for Coating
of each company to identify the appropriate subject matter for
D 4262 Test Method for pH of Chemically Cleaned or
its organization and its site specific needs.
Etched Concrete Surfaces
2. Referenced Documents D 4263 Test Method for Indicating Moisture in Concrete by
the Plastic Sheet Method
2.1 ASTM Standards:
D 4285 Test Method for Indicating Oil or Water in Com-
D 16 Terminology for Paint, Related Coatings, Materials,
pressed Air
and Applications
D 4414 Practice for Measurement of Wet Film Thickness by
D 1005 Test Methods for Measurement of Dry-Film Thick-
Notched Gages
ness of Organic Coatings Using Micrometers
D 4417 Test Method for Field Measurement of Surface
D 1186 Test Methods for Nondestructive Measurement of
Profile of Blast Cleaned Steel
Dry Film Thickness of Nonmagnetic Coatings Applied to
D 4537 Guide for Establishing Procedures to Qualify and
a Ferrous Base
Certify Inspection Personnel for Coating Work in Nuclear
D 1400 Test Method for Nondestructive Measurement of
Facilities
Dry Film Thickness of Nonconductive Coatings Applied to
D 4538 Terminology Relating to Protective Coating and
a Nonferrous Metal Base
Lining Work for Power Generation Facilities
D 2092 Guide for Preparation of Zinc-Coated Galvanized
D 4541 Test Method for Pull-Off Strength of Coatings
Steel Surfaces for Paint
Using Portable Adhesion-Testers
D 2240 Test Method for Rubber Property—Durometer
D 4610 Guide for Determining the Presence of and Remov-
Hardness
ing Microbial (Fungal or Algal) Growth on Paint and
D 2583 Test Method for Indentation Hardness of Rigid
Related Coatings
Plastics by Means of a Barcol Impressor
D 4752 Test Method for Measuring MEK Resistance of
D 3276 Guide for Painting Inspectors (Metal Substrates)
Ethyl Silicate (Inorganic) Zinc-Rich Primers by Solvent
D 3359 Test Method for Measuring Adhesion by Tape Test
Rub
D 3363 Test Method for Film Hardness by Pencil Test
D 4787 Practice for Continuity Verification of Liquid or
D 3925 Practice for Sampling Liquid Paints and Related
Sheet Linings Applied to Concrete Substrates
Pigment Coatings
D 4940 Method for Conductimetric Analysis of Water
D 4138 Method for Measurement of Dry Film Thickness of
Soluble Ionic Contamination of Blasting Abrasives
Protective Coating Systems by Destructive Means
D 5162 Practice for Discontinuity (Holiday) Testing of
Nonconductive Protective Coating on Metallic Substrates
E 337 Test Method for Measuring Humidity with a Psy-
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
chrometer (the Measurement of Wet-Bulb and Dry-Bulb
responsibility of Subcommittee D33.04 on Inspection. 6
Temperatures)
Current edition aproved January 15, 1994. Published March 1994.
Annual Book of ASTM Standards, Vol 06.01.
Annual Book of ASTM Standards, Vol 06.02.
Annual Book of ASTM Standards, Vol 09.01.
5 6
Annual Book of ASTM Standards, Vol 08.02. Annual Book of ASTM Standards, Vol 11.03.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
D 5498
2.2 Steel Structures Painting Council Standards: 4.1.5 Quality Assurance—Key points include philosophy,
SSPC-PA1 Shop, Field and Maintenance Painting 10 CFR 50 Appendix B, elements of quality assurance (QA)
SSPC-PA2 Measurement of Dry Paint Thickness with Mag- program, written procedures, organizational structure, audits
netic Gage and 10 CFR 21.
SSPC-SP1 Solvent Cleaning 4.1.6 Engineering Specifications—Key points include ele-
SSPC-SP2 Hand Tool Cleaning ments, purpose, and inspection role defined.
SSPC-SP3 Power Tool Cleaning 4.1.7 Coating Work Procedures—Key points include pur-
SSPC-SP5 White Metal Blast Cleaning pose and elements.
SSPC-SP6 Commercial Blast Cleaning 4.1.8 Nuclear Documents—Key points include regulations,
SSPC-SP7 Brush-Off Blast Cleaning ANSI, ASTM, material qualifications, personnel qualifications,
SSPC-SP8 Pickling and safety related versus non-safety related.
SSPC-SP10 Near-White Blast Cleaning 4.1.9 Pre-Job and Job Conferences—Key points include
SSPC-SP11 Power Tool Cleaning to Bare Metal purposes, participants, conflicts, specifications versus proce-
SSPC-VIS1–89 Visual Standard for Abrasive Blast Cleaned dures versus standards, material specifics, job specifics, exempt
Steel areas, inaccessible areas, and limited access areas.
2.3 Federal Standards: 4.1.10 Materials Receiving, Storage and Handling—Key
10 CFR 50 Appendix B, Quality Assurance Criteria for points include materials for surface preparation, cleaning,
Nuclear Power Plants and Fuel Reprocessing Plants coating, thinning, inspecting, labeling, controlled storage, shelf
10 CFR 21 Reporting of Defects and Noncompliance life, safety/fire, disposal, inventory control, and material safety
data sheets.
3. Significance and Use
4.1.11 Safety—Key points include health, fire, general and
3.1 Inspection personnel trained for coating work are re- job specific.
quired to perform examination/inspection tasks to verify con-
4.1.12 Pre-Surface Preparation Inspection— Key points
formance of coating work to written instructions/specifications. include how, and what to look for on concrete and steel.
3.2 With the use of this guide, those responsible for indoc-
4.1.13 Surface Preparation Methods/Equipment—Key
trination and training, should be able to develop an appropriate points include importance, methods for concrete/steel, equip-
program for training inspection personnel involved in coating
ment, compressed air cleanliness and standards.
work.
4.1.14 Surface Preparation Inspection— Key points include
3.3 It should be understood that mastery of the subject
contaminants, degree of cleanliness, profile/roughness, meth-
matter addressed in this guide will not by itself result in the
ods, equipment, and dust removal.
certification of inspectors. Certification of inspection personnel
4.1.15 Calibration and Proper Use of Inspection
for coating work can be obtained as outlined in Guide D 4537.
Instruments—Key points include use and calibration.
3.4 This guide may be modified for use in nonnuclear
4.1.16 Environmental Measurements—Key points include
facilities.
purpose, procedures, temperatures, relative humidity (RH),
dew point (DP), wind velocity, and weather.
4. General Requirements for Training for Level I
4.1.17 Mixing Methods/Equipment—Key points include
4.1 As a minimum, training shall include sufficient informa-
temperature, mixing, thinning, sweat-in or induction period,
tion to e
...

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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.  
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ASTM E3105-17(2023)(Specification)
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.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
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ASTM E1035-18(2023)(Practice)
Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

SIGNIFICANCE AND USE
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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