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ASTM E3105-17(2023)

(Specification)

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

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.  
1.4 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.

General Information

Status
Published
Publication Date
31-May-2023
ICS
27.120.20 - Nuclear power plants. Safety
Technical Committee
E10 - Nuclear Technology and Applications
Drafting Committee
E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components
Current Stage
Ref Project

Relations

Refers
ASTM D4060-10 - Standard Test Method for Abrasion Resistance of Organic Coatings by the Taber Abraser
Effective Date
01-Feb-2010
Refers
ASTM D4541-09 - Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers
Effective Date
01-Feb-2009
Refers
ASTM D4060-07 - Standard Test Method for Abrasion Resistance of Organic Coatings by the Taber Abraser
Effective Date
01-Jun-2007
Refers
ASTM D4541-95e1 - Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers
Effective Date
10-Feb-2002
Refers
ASTM D4541-02 - Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers
Effective Date
10-Feb-2002
Refers
ASTM D4060-95 - Standard Test Method for Abrasion Resistance of Organic Coatings by the Taber Abraser
Effective Date
10-Dec-2001
Refers
ASTM D4060-01 - Standard Test Method for Abrasion Resistance of Organic Coatings by the Taber Abraser
Effective Date
10-Dec-2001

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ASTM E3105-17(2023) - Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive ContaminationASTM E3105-17(2023) - Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination
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ASTM E3105-17(2023) - Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination
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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.
Designation: E3105 − 17 (Reapproved 2023)
Standard Specification for
Permanent Coatings Used to Mitigate Spread of Radioactive
Contamination
This standard is issued under the fixed designation E3105; 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. Scope 3.1.1 contamination, n—radioactive material in an un-
wanted location.
1.1 This specification is intended to provide a basis for
identification of non-removable permanent coatings and fixa-
3.1.2 environmental conditions, n—external factors that
tives as a long-term measure used to immobilize radioactive
may contribute to the performance of the coating, including,
contamination, minimize worker exposure, and to protect but not limited to, temperature, humidity, and ventilation.
uncontaminated areas against the spread of radioactive con-
3.1.3 long-term measure, n—greater than six months.
tamination.
3.1.4 lower flammability limit (LFL), n—the lower end of
1.2 The values stated in inch-pound units are to be regarded
the concentration range over which a flammable mixture of gas
as standard. The values given in parentheses are mathematical
or vapor in air can be ignited at a given temperature and
conversions to SI units that are provided for information only
pressure.
and are not considered standard.
3.1.5 permanent coating, n—a non-removable, durable
1.3 This standard does not purport to address all of the
film-forming product used to physically or chemically hold or
safety concerns, if any, associated with its use. It is the
bind radioactive particulate.
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter- 3.1.6 waste acceptance criteria (WAC), n—the criteria that a
mine the applicability of regulatory limitations prior to use.
material must meet for acceptance in a waste disposal site;
1.4 This international standard was developed in accor- these criteria may vary per disposal site.
dance with internationally recognized principles on standard-
3.1.7 working time, n—the time period between the opening
ization established in the Decision on Principles for the
of the material storage container or mixing of components until
Development of International Standards, Guides and Recom-
the prepared material can no longer be successfully applied to
mendations issued by the World Trade Organization Technical
a surface.
Barriers to Trade (TBT) Committee.
4. Significance and Use
2. Referenced Documents
2.1 ASTM Standards: 4.1 Some of these specifications may prove difficult to meet.
D4060 Test Method for Abrasion Resistance of Organic A product that meets some, but not all, of the performance
Coatings by the Taber Abraser specifications herein may have value, and this specification
D4541 Test Method for Pull-Off Strength of Coatings Using may be used as a guide by which to evaluate such products.
Portable Adhesion Testers
4.2 This specification establishes performance specifica-
tions for permanent coatings that are intended to immobilize
3. Terminology
dispersible radioactive contamination deposited on buildings
3.1 Definitions:
and equipment as might result from anticipated to unantici-
pated events to include normal operating conditions,
This specification is under the jurisdiction of ASTM Committee E10 on
decommissioning, and radiological release.
Nuclear Technology and Applications and is the direct responsibility of Subcom-
mittee E10.03 on Radiological Protection for Decontamination and Decommission-
4.3 The coating is intended to be a permanent, non-
ing of Nuclear Facilities and Components.
removable, long-term material used for decommissioning and
Current edition approved June 1, 2023. Published June 2023. Originally
operations. It is intended to reduce: (1) migration of the
approved in 2017. Last previous edition approved in 2017 as E3105 – 17. DOI:
10.1520/E3105-17R23.
contamination into or along buildings, equipment, and other
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
surfaces; (2) resuspension of contamination into the air; and (3)
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
the spread of contamination as a result of external forces such
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. as pedestrian traffic.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E3105 − 17 (2023)
4.4 The permanent coating is intended to reduce the air- 6.8 The permanent coating should not attract or be a
borne intake hazards of the radioactive contamination. foodstuff for animals, insects, pests, or undesirable bacteria.
6.9 The permanent coating shall be chemically nonhazard-
4.5 The permanent coating shall be applicable to both
vertical and horizontal surfaces. ous after curing as defined by the U.S. Environmental Protec-
tion Agency (EPA).
4.6 The permanent coating should be able to work within a
range of environmental and radiological conditions.
7. Performance Requirements
4.7 The permanent coating should be applicable to both
7.1 Shelf Life—The permanent coating shall have a shelf life
porous and nonporous materials such as concrete, wood, metal,
in accordance with 8.1.
ceramics, and plastics.
7.2 Working Time—The permanent coating shall exhibit a
4.8 The permanent coating may include constituents that
working time sufficient to meet a realistic application rate.
will physically or chemically bind and hold radioactive con-
Working time is heavily dependent on the method of applica-
tamination.
tion. The application method is purposely left unconstrained
and is up to the manufacturer to prescribe.
5. Mechanical Properties
7.3 Cure Time—The permanent coating shall exhibit a
5.1 The permanent coating shall be compatible with at least
curing time sufficient to meet realistic operational and envi-
one of the following application systems: conventional or
ronmental conditions (that is, <24 h). The permanent coating
remote spray, foam, brush, fog, or roll.
shall form a film that meets the physical, mechanical, and other
requirements listed in Sections 4 – 8 of this specification.
5.2 The
...

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1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) (1, 5, 13, 48, 49).2 In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units.  
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.  
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This specification prescribes the performance criteria for strippable/removable coatings used in immobilizing radioactive contamination, minimizing worker exposure, and facilitating subsequent decontamination or protecting uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, tensile strength, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction) as well as the mechanical and chemical properties for strippable/removable coatings. The strippable/removable coating is intended to reduce: migration of the radioactive contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air and the airborne intake hazards of the contamination; and the spread of contamination as a result of external forces such as pedestrian traffic. The strippable/removable coating shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be readily applied to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the strippable/removable coating may include constituents that will physically or chemically bind and immobilize radioactive contamination.
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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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3.1 Temperature monitors are used in surveillance capsules in accordance with Practice E2215 to estimate the maximum value of the surveillance specimen irradiation temperature. Temperature monitors are needed to give evidence of overheating of surveillance specimens beyond the expected temperature. Because overheating causes a reduction in the amount of neutron radiation damage to the surveillance specimens, this overheating could result in a change in the measured properties of the surveillance specimens that would lead to an unconservative prediction of damage to the reactor vessel material.  
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1.1 Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E944 and Practice E853 define appropriate computational procedures.  
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5.1 Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed.  
5.2 Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.
SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.  
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4.1.1 This document provides guidance for performing S&M in a way that will ensure worker and public safety, while also addressing stakeholder requirements.  
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4.2 Use of this guide helps ensure that the S&M plan addresses the significant activities and actions necessary to maintain these facilities in a safe and stable condition until they can be decommissioned.
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1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D).  
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Standard Guide for Nuclear Facility Decommissioning Plans

SIGNIFICANCE AND USE
4.1 The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed.  
4.2 In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1757 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.6  
4.3 This decommissioning plan will be developed to serve as the executive document that describes the objectives of the decommissioning program and identifies and defines the elements necessary to accomplish the program.  
4.4 A detailed implementation plan describing how the objectives of the decommissioning plan will be met should be prepared. Some of the documents or implementation plans that may be required to support the overall decommissioning program include an engineering plan; a cost, schedule, and financing plan (10 CFR 140 and 170); a field implementation plan; a health and safety plan (29 CFR 1910.120, Guide E1167); a quality assurance plan (10 CFR 50.59 and 10 CFR 830.120); an emergency plan; an environmental monitoring plan (Guide E1819); a radiological protection plan (10 CFR 20, 10 CFR 835, Guide E1167); and a physical security plan (10 CFR 73). These implementation plans shall be separate from and consistent with the decommissioning plan.
SCOPE
1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC), Agreement State license, under Department of Energy (DOE) orders, or whose operation was overseen by another federal, state, or local agency.  
1.2 The guide applies to the preparation and content of the decommissioning plan document itself.  
1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide.  
Note 1: Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 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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