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ASTM E1297-08

(Test Method)

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

SIGNIFICANCE AND USE
p>Refer to Practice E 261 for a general discussion of the determination of decay rates, reaction rates, and neutron fluence rates with threshold detectors (1-29). Refer to Practice E 1006, Practice E 185 and Guide E 1018 for the use and application of results obtained by this test method.(34-36)
The half-life of  93mNb is 5730 ± 220 days (30) and has a K X-ray emission probability of 0.1099 ± 0.0025 per decay (30). The Kα and Kβ X-rays of niobium are at 16.5213–16.152 and 18.618–18.953 keV, respectively. The recommended  93Nb (n,n′)93mNb cross section comes from the IRDF-90 cross section compendium (31), was drawn from the RRDF-98 cross section evaluations (37) and is shown in Fig. 1.
Chemical dissolution of the irradiated niobium to produce very low mass-per-unit area sources is an effective way to obtain consistent results. The direct counting of foils or wires can produce satisfactory results provided appropriate methods and interpretations are employed. It is possible to use liquid scintillation methods to measure the niobium activity provided the radioactive material can be kept uniformly in solution and appropriate corrections can be made for interfering activities.
The measured reaction rates can be used to correlate neutron exposures, provide comparison with calculated reaction rates, and determine neutron fluences. Reaction rates can be determined with greater accuracy than fluence rates because of the current uncertainty in the cross section versus energy shape.
The  93Nb(n,n′)93mNb reaction has the desirable properties of monitoring neutron exposures related to neutron damage of nuclear facility structural components. It has an energy response range corresponding to the damage function of steel and has a half-life sufficiently long to allow its use in very long exposures (up to about 40 years). Monitoring long exposures is useful in determining the long-term integrity of nuclear facility components.
SCOPE
1.1 This test method describes procedures for measuring reaction rates by the activation reaction  93Nb(n,n′)93mNb.
1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 30 years.
1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016cm−2. In the presence of high thermal-neutron fluence rates (>1012cm−2·s−1), the transmutation of  93mNb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93mNb by reactions such as (n,2n) may occur and should be investigated.
1.4 Procedures for other fast-neutron monitors are referenced in Practice E 261.
1.5 Fast-neutron fluence rates can be determined from the reaction rates provided that the appropriate cross section information is available to meet the accuracy requirements.
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.7 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
30-Jun-2008
ICS
27.120.01 - Nuclear energy in general
Technical Committee
E10 - Nuclear Technology and Applications
Drafting Committee
E10.05 - Nuclear Radiation Metrology
Current Stage
Ref Project

Relations

Replaces
ASTM E1297-02 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
Effective Date
01-Jul-2008
Replaced By
ASTM E1297-08(2013) - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
Effective Date
01-Jan-2013
Referred By
ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
Effective Date
01-Jul-2008
Referred By
ASTM E720-23 - Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
Effective Date
01-Jul-2008
Referred By
ASTM E721-22 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
Effective Date
01-Jul-2008
Referred By
ASTM E2005-21 - Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
Effective Date
01-Jul-2008

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ASTM E1297-08 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of NiobiumASTM E1297-08 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
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REDLINE ASTM E1297-08 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of NiobiumREDLINE ASTM E1297-08 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
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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: E1297 − 08
StandardTest Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Niobium
This standard is issued under the fixed designation E1297; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E170Terminology Relating to Radiation Measurements and
Dosimetry
1.1 This test method describes procedures for measuring
93 93m
E181Test Methods for Detector Calibration andAnalysis of
reaction rates by the activation reaction Nb(n,n') Nb.
Radionuclides
1.2 This activation reaction is useful for monitoring neu-
E185Practice for Design of Surveillance Programs for
trons with energies above approximately 0.5 MeV and for
Light-Water Moderated Nuclear Power Reactor Vessels
irradiation times up to about 30 years.
E261Practice for Determining Neutron Fluence, Fluence
1.3 With suitable techniques, fast-neutron reaction rates for
Rate, and Spectra by Radioactivation Techniques
neutrons with energy distribution similar to fission neutrons
E262Test Method for Determining Thermal Neutron Reac-
16
can be determined in fast-neutron fluences above about 10
tion Rates and Thermal Neutron Fluence Rates by Radio-
−2
cm . In the presence of high thermal-neutron fluence rates
activation Techniques
12 −2 −1 93m
(>10 cm ·s ), the transmutation of Nb due to neutron
E844Guide for Sensor Set Design and Irradiation for
capture should be investigated. In the presence of high-energy
Reactor Surveillance, E 706 (IIC)
neutron spectra such as are associated with fusion and spalla-
E944Guide for Application of Neutron Spectrum Adjust-
93m
tion sources, the transmutation of Nb by reactions such as
ment Methods in Reactor Surveillance, E 706 (IIA)
(n,2n) may occur and should be investigated.
E1005Test Method for Application and Analysis of Radio-
metric Monitors for Reactor Vessel Surveillance, E 706
1.4 Procedures for other fast-neutron monitors are refer-
(IIIA)
enced in Practice E261.
E1006Practice for Analysis and Interpretation of Physics
1.5 Fast-neutron fluence rates can be determined from the
Dosimetry Results for Test Reactors, E 706(II)
reaction rates provided that the appropriate cross section
E1018Guide for Application of ASTM Evaluated Cross
information is available to meet the accuracy requirements.
Section Data File, Matrix E706 (IIB)
1.6 The values stated in SI units are to be regarded as
3. Terminology
standard. No other units of measurement are included in this
standard.
3.1 Definitions—The definitions stated in Terminology
E170 are applicable to this test method.
1.7 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
4. Summary of Test Method
responsibility of the user of this standard to establish appro-
4.1 High purity niobium is irradiated in a neutron field
priate safety and health practices and determine the applica-
93m 93 93m
producing radioactive Nb from the Nb(n,n') Nb reac-
bility of regulatory limitations prior to use.
tion. The metastable state decays to the ground state by the
2. Referenced Documents
virtual emission of 30 keV gamma rays that are all internally
2
2.1 ASTM Standards: convertedgivingrisetotheactualemissionoforbitalelectrons
D1193Specification for Reagent Water followed by X rays.
4.2 SourcesoftheirradiatedniobiumarepreparedforXray
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE10onNuclear
or liquid scintillation counting.
Technology and Applicationsand is the direct responsibility of Subcommittee
93m
E10.05 on Nuclear Radiation Metrology.
4.3 TheXraysemittedasaresultofthedecayof Nbare
Current edition approved July 1, 2008. Published August 2008. Originally
counted, and the reaction rate, as defined in Practice E261,is
approved in 1989. Last previous edition approved in 2002 as E1297–02. DOI:
calculated from the decay rate and irradiation conditions.
10.1520/E1297-08.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
4.4 The neutron fluence rate may then be calculated from
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
the appropriate spectral-weighted neutron activation cross
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. section as defined by Practice E261.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1297 − 08
5. Significance and Use andhasahalf-lifesufficientlylongtoallowitsuseinverylong
exposures(uptoabout40years).Monitoringlongexposuresis
5.1 Refer to Practice E261 fo
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E1297–02 Designation: E 1297 – 08
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Niobium
This standard is issued under the fixed designation E1297; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
93 93m
1.1 This test method describes procedures for measuring reaction rates by the activation reaction Nb(n,n8) Nb.
1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation
times up to about 30 years.
1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be
16 −2 12 −2 −1
determined in fast-neutron fluences above about 10 cm . In the presence of high thermal-neutron fluence rates (>10 cm ·s
93m
), the transmutation of Nb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such
93m
as are associated with fusion and spallation sources, the transmutation of Nb by reactions such as (n,2n) may occur and should
be investigated.
1.4 Procedures for other fast-neutron monitors are referenced in Practice E261.
1.5 Fast-neutronfluenceratescanbedeterminedfromthereactionratesprovidedthattheappropriatecrosssectioninformation
is available to meet the accuracy requirements.
1.6The values stated in SI units are to be regarded as the standard.
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.7 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.
2. Referenced Documents
2
2.1 ASTM Standards:
D1193 Specification for Reagent Water
E170 Terminology Relating to Radiation Measurements and Dosimetry
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
E185 PracticeforConductingDesignofSurveillanceTestsProgramsforLight-WaterCooledModeratedNuclearPowerReactor
3
Vessels, E706 (IF) Vessels
E261 Practice for Determining Neutron Fluence, Fluence Rate, Fluence, and Spectra by Radioactivation Techniques
E262 Test Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
3
E944Practice for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance Guide for Application of
Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
3
E1006 Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E706 (II) E 706(II)
E1018Guide for Application of ASTM Evaluated Cross Section Data File (ENDF/A)—Cross Section and Uncertainty File,
3
E706 (IIB) Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
3. Terminology
3.1 Definitions— The definitions stated in Terminology E170 are applicable to this test method.
1
This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved June 10, 2002. Published September 2002. Originally published as E1297–89. Last previous edition E1297–96.
Current edition approved July 1, 2008. Published August 2008. Originally approved in 1989. Last previous edition approved in 2002 as E1297–02.
2
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,orcontactASTMCustomerServiceatservice@astm.org.For Annual Book of ASTM Standards
, Vol 11.01.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 ----------------------
E1297–08
4. Summary of Test Method
93m 93 93m
4.1 High purity niobium is irradiated in a neutron field producing radioactive Nb from the Nb(n,n8) Nb reaction. The
metastable state decays to the ground state by the virtual
...

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ASTM E1297-18(Test Method)
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

SIGNIFICANCE AND USE
5.1 Refer to Practice E261 for a general discussion of the determination of decay rates, reaction rates, and neutron fluence rates with threshold detectors (1-29).3 Refer to Practice E1006, Practice E185 and Guide E1018 for the use and application of results obtained by this test method.(30-32)  
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FIG. 1 RRDF/IRDFF-1.05 Cross Section Versus Energy for the  93Nb(n,n′) 93mNb Reaction  
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FIG. 1 Quality Assurance of Analytical Laboratory Data  
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ASTM
ASTM D3843-16(2021)e1(Practice)
Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

SIGNIFICANCE AND USE
4.1 Quality assurance, as covered by this practice, comprises all those planned and systematic actions necessary to provide adequate confidence that safety-related coating work in nuclear facilities as defined in Guide D5144, will perform satisfactorily in service.  
4.2 It is not practical to impose all the requirements of this practice on certain specific items that require only a small quantity of coating material. The licensee, consistent with his formal Quality Assurance Program, may accept affidavits of compliance or certification attesting to the quality of a shop or field coating for such items. If required by licensing commitment; safety-related coatings that are not qualified or for which the quantification basis is indeterminate as defined in Guide D5144, shall be identified, quantified, and documented.  
4.3 This practice may be incorporated in a project specification by direct reference or may be used to provide guidelines for the quality assurance program for coatings, on the basis of the licensee’s requirements. Effective use of this practice may also require the incorporation of applicable sections in project specifications for coatings on concrete, steel, equipment, and other related items.
SCOPE
1.1 This standard replaces ANSI N101.4 and provides a common basis for, and specifically comprises quality assurance requirements applicable to, safety-related protective coating work in Coating Service Level I areas of nuclear facilities as defined in Guide D5144.  
1.2 This standard meets the requirements of ANSI N101.4 while also recognizing advancements in technology and industry practices since transfer to ASTM responsibility for updating, rewriting, and issuing replacement standards to ANSI N101.4.  
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.

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ASTM
ASTM E2216-02(2020)(Guide)
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
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.

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ASTM
ASTM E1034-95(2020)(Specification)
Standard Specification for Nuclear Facility Transient Worker Records

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification doesPresident Barack Obama eulogy at John Lewis funeral not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1: Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the 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 does not alter the required content of records needed for in-processing of nuclear facility transient workers.
Note 2: This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).  
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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ASTM
ASTM C992-20a(Specification)
Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
1.6 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.  
1.7 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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ASTM
ASTM D8157-19(Guide)
Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 This guide presents concise guidance and approach to developing a test document for qualifying a coating for CSLI service, whether a new or existing coating. Guidance for evaluating existing qualification test data for applicability is presented in Guide D8104.  
4.2 The requirements for qualification testing can be found in Quality Assurance Criteria III (Design Control), IX (Control of Special Processes), and XI (Test Control) of 10 CFR 50, Appendix B, as implemented, respectively, by Requirements III, IX, and XI of NQA-1. A test document developed per this guide is intended to be compliant with these requirements.  
4.3 This guide implements the guidance provided in Guide D5144 for qualification of coatings for use in CSLI service. Additional guidance is provided in Regulatory Guide 1.54, Revisions 0 through 3, as may be invoked by the licensee.  
4.4 For plants with a license basis that predates the requirements of ANSI N5.12 and N101.2, this guide also is applicable. For these plants, the coatings or coating systems may be designated as acceptable, rather than qualified.  
4.5 All qualification testing shall comply with the licensee’s approved quality assurance program.
SCOPE
1.1 This guide provides an approach to identifying the need for and development of a test document to qualify coatings for Coating Service Level I (CSLI) service in nuclear power plants.  
1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings qualification test document, not to mandate a singular basis for all test documents. Variations or simplifications of the process described in this guide may be appropriate for any given operating or new construction nuclear power plant depending on its licensing commitments.  
1.3 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.  
1.4 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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