D33.04 - Quality Systems and Inspection

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.

SIGNIFICANCE AND USE
4.1 Establishment of an in-service coatings monitoring program permits planning and prioritization of coatings maintenance work as needed to maintain coating integrity and performance in nuclear CSL I coating systems. For additional information on nuclear maintenance coating work, refer to ASTM MNL8.4  
4.2 A coatings monitoring program enables early identification and detection of potential problems in coating systems. Some CSL I coating systems may be known in advance to be suspect, deficient, or unqualified. Monitoring coating performance will assist in developing follow-up procedures to resolve any significant deficiency relative to coating work.  
4.3 Degraded coatings may generate debris under design basis accident conditions that could adversely affect the performance of the post-accident safety systems. A coatings monitoring program may be required to fulfill safety analysis report and generic letter commitments for CSL I coating work in a nuclear power plant facility.
SCOPE
1.1 This standard covers procedures for establishing a monitoring program for condition assessment of Coating Service Level (CSL) I coating systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition and performance of the in-service coating systems.  
1.2 It is the intent of this standard to provide a recommended basis for establishing a coatings condition assessment program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this standard may be appropriate for each operating nuclear power plant depending on their licensing commitments.  
1.3 This requirements of ASME Section XI, In-Service Inspection Subsections IWE and IWL are beyond the scope of this 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.

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.

SIGNIFICANCE AND USE
4.1 This guide applies to personnel technically responsible for the safety-related coatings program.  
4.2 It is the responsibility of each nuclear facility or organization participating in a safety-related coatings program to ensure that only those personnel within their respective organizations who meet the requirements of this guide are designated as Nuclear Coatings Specialists.
SCOPE
1.1 This guide delineates recommendations for development of procedures and criteria for designation of an individual as a Nuclear Coatings Specialist involved in coating work in nuclear facilities. The Nuclear Coatings Specialist is responsible for the technical aspects of the safety-related coatings program in a nuclear facility or organization, which includes establishing processes and quality control requirements.  
1.2 This guide details the guidance provided in Guide D5144, and EPRI Report 1019157.  
1.3 It is the intent of this guide to provide several alternatives for designation of personnel as Nuclear Coatings Specialists.  
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.

SIGNIFICANCE AND USE
4.1 Establishment of an in-service linings monitoring program permits planning and prioritization of lining maintenance work as needed to maintain lining integrity and performance in nuclear Coating Service Level III systems. Refer to ASTM MNL-8, Manual on Maintenance Coatings for Nuclear Power Plants,7 and Guide D7230, which provides guidance for selecting lining materials for new construction or maintenance of safety-related lining systems.  
4.2 A linings monitoring program enables early identification and detection of potential problems in lining systems. Some Coating Service Level III lining systems may be known in advance to be suspect, deficient, or degraded. Monitoring lining performance will assist in developing follow-up procedures to resolve any significant deficiency relative to lining work.  
4.3 Degraded linings may generate debris under normal operation and testing or during upset conditions that could adversely affect the performance of safety-related systems. In most cases, the consequence of the debris generation is flow blockage, essential heat transfer reduction, or both; ultimately leading to degradation of equipment or system performance. A linings monitoring program may be required to fulfill licensing commitments for Coating Service Level III lining work.
SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level III lining (and coating) systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition of the in-service lining systems.  
1.2 Coating Service Level III lining systems subject to this guide are generally those applied to metal substrates comprising raw water, condensate-quality water, or fuel oil wetted (that is, full or intermittent immersion) surfaces in systems that may include:  
1.2.1 Service water piping upstream of safety-related components,  
1.2.2 Service water pump internals (draft tube, volutes, and diffusers),  
1.2.3 Service water heat exchangers including the channels, pass partitions, tubesheets, end bells, and covers  
1.2.4 Service water strainers,  
1.2.5 Reactor water storage tanks (RWSTs),  
1.2.6 Refuel cavity water storage tanks,  
1.2.7 Reactor makeup water system,  
1.2.8 Component cooling water system,  
1.2.9 Lube oil tanks for safety-related equipment, and  
1.2.10 Emergency diesel fuel oil system.  
1.3 It is the intent of this guide to provide a recommended basis for establishing a linings 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 any given operating nuclear power plant depending on its licensing commitments. Similar guidelines may be applicable for certain Coating Service Level II applications such as fluid immersion systems.  
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.

SIGNIFICANCE AND USE
4.1 The requirements of this guide apply to personnel who perform coating and lining work inspection during (1) fabrication, (2) receipt of items at the construction site, (3) construction, (4) pre-operational and startup testing, and (5) operational phases of nuclear facilities.  
4.2 It is the responsibility of each organization participating in the project to ensure that only those personnel within their respective organizations who meet the requirements of this guide are permitted to perform coating and lining work inspection activities covered by this guide.  
4.3 The organization(s) responsible for establishing the applicable requirements for activities covered by this guide shall be identified, and the scope of their responsibility shall be documented. Delegation of this responsibility to other qualified organizations is permitted and shall be documented.  
4.4 It is the responsibility of the organization performing these activities to specify the detailed methods and procedures for meeting the requirements of this guide, unless those methods and procedures are otherwise specified in the contract documents.  
4.5 In the event of conflict, users of this guide must recognize that the licensee’s plant-specific quality assurance program and licensing commitments shall prevail with respect to the process of qualifying personnel performing inspection of coating and lining work.
SCOPE
1.1 This guide delineates the requirements for development of procedures for the qualification and certification of personnel who perform inspection of coating and lining work. Establishment of qualification requirements to verify conformance to specified requirements for nuclear facility coating and lining work is necessary to assure satisfactory performance of the inspections and to avoid compromising safety-related coating systems.  
1.2 The intent of this guide is to provide a uniform interpretation of the requirements in ANSI/ASME N45.2.6 or ANSI/ASME NQA-1 as applicable, for the inspection of coating and lining work in nuclear facilities.  
1.3 It is the intent of this guide to provide a recommended basis for qualification and certification, not to mandate a singular basis for all qualifications. Variations or simplifications of the qualifications described in this guide may be appropriate for special coating and lining work other than safety-related coating and lining systems. Similarly, the qualification and certification process might be abbreviated for work of minor scope such as touch-up.  
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.

SIGNIFICANCE AND USE
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.  
4.2 This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating and lining work inspection.  
4.3 Certification/qualification of personnel performing coating and lining work inspection is addressed in Guide D4537.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating and lining inspection work for nuclear facilities.  
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its specific needs.  
1.3 Users of this guide must ensure that coating and lining work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.  
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.

SIGNIFICANCE AND USE
4.1 Establishment of an in-service coatings monitoring program permits planning and prioritization of coatings maintenance work as needed to maintain coating integrity and performance in nuclear CSL I coating systems. For additional information on nuclear maintenance coating work, refer to ASTM MNL8.4  
4.2 A coatings monitoring program enables early identification and detection of potential problems in coating systems. Some CSL I coating systems may be known in advance to be suspect, deficient, or unqualified. Monitoring coating performance will assist in developing follow-up procedures to resolve any significant deficiency relative to coating work.  
4.3 Degraded coatings may generate debris under design basis accident conditions that could adversely affect the performance of the post-accident safety systems. A coatings monitoring program may be required to fulfill safety analysis report and generic letter commitments for CSL I coating work in a nuclear power plant facility.
SCOPE
1.1 This standard covers procedures for establishing a monitoring program for condition assessment of Coating Service Level (CSL) I coating systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition and performance of the in-service coating systems.  
1.2 It is the intent of this standard to provide a recommended basis for establishing a coatings condition assessment program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this standard may be appropriate for each operating nuclear power plant depending on their licensing commitments.  
1.3 This requirements of ASME Section XI, In-Service Inspection Subsections IWE and IWL are beyond the scope of this 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 and health practices and determine the applicability of regulatory limitations prior to use.

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 and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 This guide applies to personnel technically responsible for the safety-related coatings program.  
4.2 It is the responsibility of each nuclear facility or organization participating in a safety-related coatings program to ensure that only those personnel within their respective organizations who meet the requirements of this guide are designated as Nuclear Coatings Specialists.
SCOPE
1.1 This guide delineates recommendations for development of procedures and criteria for designation of an individual as a Nuclear Coatings Specialist involved in coating work in nuclear facilities. The Nuclear Coatings Specialist is responsible for the technical aspects of the safety-related coatings program in a nuclear facility or organization, which includes establishing processes and quality control requirements.  
1.2 This guide details the guidance provided in Guide D5144, and EPRI Report 1019157.  
1.3 It is the intent of this guide to provide several alternatives for designation of personnel as Nuclear Coatings Specialists.  
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 and health practices and determine the applicability of regulatory requirements prior to use.

SIGNIFICANCE AND USE
4.1 Establishment of an in-service linings monitoring program permits planning and prioritization of lining maintenance work as needed to maintain lining integrity and performance in nuclear Coating Service Level III systems. Refer to ASTM MNL-8, Manual on Maintenance Coatings for Nuclear Power Plants,7 and Guide D7230, which provides guidance for selecting lining materials for new construction or maintenance of safety-related lining systems.  
4.2 A linings monitoring program enables early identification and detection of potential problems in lining systems. Some Coating Service Level III lining systems may be known in advance to be suspect, deficient, or degraded. Monitoring lining performance will assist in developing follow-up procedures to resolve any significant deficiency relative to lining work.  
4.3 Degraded linings may generate debris under normal operation and testing or during upset conditions that could adversely affect the performance of safety-related systems. In most cases, the consequence of the debris generation is flow blockage, essential heat transfer reduction, or both; ultimately leading to degradation of equipment or system performance. A linings monitoring program may be required to fulfill licensing commitments for Coating Service Level III lining work.
SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level III lining (and coating) systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition of the in-service lining systems.  
1.2 Coating Service Level III lining systems subject to this guide are generally those applied to metal substrates comprising raw water, condensate-quality water, or fuel oil wetted (that is, full or intermittent immersion) surfaces in systems that may include:  
1.2.1 Service water piping upstream of safety-related components,  
1.2.2 Service water pump internals (draft tube, volutes, and diffusers),  
1.2.3 Service water heat exchangers including the channels, pass partitions, tubesheets, end bells, and covers  
1.2.4 Service water strainers,  
1.2.5 Reactor water storage tanks (RWSTs),  
1.2.6 Refuel cavity water storage tanks,  
1.2.7 Reactor makeup water system,  
1.2.8 Component cooling water system,  
1.2.9 Lube oil tanks for safety-related equipment, and  
1.2.10 Emergency diesel fuel oil system.  
1.3 It is the intent of this guide to provide a recommended basis for establishing a linings 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 any given operating nuclear power plant depending on its licensing commitments. Similar guidelines may be applicable for certain Coating Service Level II applications such as fluid immersion systems.  
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 and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
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.  
4.2 This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating and lining work inspection.  
4.3 Certification/qualification of personnel performing coating and lining work inspection is addressed in Guide D4537.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating and lining inspection work for nuclear facilities.  
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its specific needs.  
1.3 Users of this guide must ensure that coating and lining work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.

SIGNIFICANCE AND USE
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.
This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating and lining work inspection.
Certification/qualification of personnel performing coating and lining work inspection is addressed in Guide D4537.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating and lining inspection work for nuclear facilities.
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its specific needs.
1.3 Users of this guide must ensure that coating and lining work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.

SIGNIFICANCE AND USE
The requirements of this guide apply to personnel who perform coating and lining work inspection during (1) fabrication, (2) receipt of items at the construction site, (3) construction, (4) pre-operational and startup testing, and (5) operational phases of nuclear facilities.
It is the responsibility of each organization participating in the project to ensure that only those personnel within their respective organizations who meet the requirements of this guide are permitted to perform coating and lining work inspection activities covered by this guide.
The organization(s) responsible for establishing the applicable requirements for activities covered by this guide shall be identified, and the scope of their responsibility shall be documented. Delegation of this responsibility to other qualified organizations is permitted and shall be documented.
It is the responsibility of the organization performing these activities to specify the detailed methods and procedures for meeting the requirements of this guide, unless those methods and procedures are otherwise specified in the contract documents.
In the event of conflict, users of this guide must recognize that the licensee's plant-specific quality assurance program and licensing commitments shall prevail with respect to the process of qualifying personnel performing inspection of coating and lining work.
SCOPE
1.1 This guide delineates the requirements for development of procedures for the qualification and certification of personnel who perform inspection of coating and lining work. Establishment of qualification requirements to verify conformance to specified requirements for nuclear facility coating and lining work is necessary to assure satisfactory performance of the inspections and to avoid compromising safety-related coating systems.
1.2 The intent of this guide is to provide a uniform interpretation of the requirements in ANSI/ASME N45.2.6 or ANSI/ASME NQA-1 as applicable, for the inspection of coating and lining work in nuclear facilities.
1.3 It is the intent of this guide to provide a recommended basis for qualification and certification, not to mandate a singular basis for all qualifications. Variations or simplifications of the qualifications described in this guide may be appropriate for special coating and lining work other than safety-related coating and lining systems. Similarly, the qualification and certification process might be abbreviated for work of minor scope such as touch-up.
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 whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
Personnel trained for coating work inspection are required to perform examination/inspection tasks to verify conformance of coating work to written requirements.
This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating work inspection.
Certification/qualification of personnel performing coating work inspection is addressed in Guide D 4537.
SCOPE
1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating inspection work for nuclear facilities.
1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its 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.

SIGNIFICANCE AND USE
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 D 5144, will perform satisfactorily in service.
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 owner, 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 D 5144, shall be identified, quantified, and documented.
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 owner'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 practice 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 D 5144.
1.2  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.

SIGNIFICANCE AND USE
Establishment of an in-service coatings monitoring program permits planning and prioritization of coatings maintenance work as needed to maintain coating integrity and performance in nuclear Coating Service Level I coating systems. For additional information on nuclear maintenance coating work, refer to ASTM Manual on Maintenance Coatings for Nuclear Power Plants.  
A coatings monitoring program enables early identification and detection of potential problems in coating systems. Some Coating Service Level I coating systems may be known in advance to be suspect, deficient, or unqualified. Monitoring coating performance will assist in developing follow-up procedures to resolve any significant deficiency relative to coating work.
Degraded coatings may generate debris under design basis accident conditions that could adversely affect the performance of the post-accident safety systems. A coatings monitoring program may be required to fulfill safety analysis report and generic letter commitments for Coating Service Level I coating work in a nuclear power plant facility.
SCOPE
1.1 This standard covers procedures for establishing a monitoring program for condition assessment of Coating Service Level I coating systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition and performance of the in-service coating systems.
1.2 It is the intent of this standard to provide a recommended basis for establishing a coatings condition assessment program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this standard may be appropriate for each operating nuclear power plant depending on their licensing commitments. Similar guidelines are applicable for Coating Service Level III and other areas outside containment.
1.3 This standard does not address the requirements of ASME Section XI, In-Service Inspection Subsections IWE and IWL.
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 and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
This guide applies to personnel technically responsible for the safety-related coatings program.
It is the responsibility of each nuclear facility or organization participating in a safety-related coatings program to ensure that only those personnel within their respective organizations who meet the requirements of this guide are designated as Nuclear Coatings Specialists.
SCOPE
1.1 This guide delineates recommendations for development of procedures and criteria for designation of personnel as a Nuclear Coatings Specialist involved in work in nuclear facilities. The Nuclear Coatings Specialist is responsible for the technical aspects of the safety-related coatings program in a nuclear facility or organization.
1.2 This guide details the guidance provided in Guide D 5144, USNRC Regulatory Guide 1.54 Revision 1, and EPRI Report 1003102.
1.3 It is the intent of this guide to provide several alternatives for designation of personnel as Nuclear Coatings Specialists.
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 and health practices and determine the applicability of regulatory requirements prior to use.

SIGNIFICANCE AND USE
Establishment of an in-service linings monitoring program permits planning and prioritization of lining maintenance work as needed to maintain lining integrity and performance in nuclear Coating Service Level III lining systems. For additional information on nuclear maintenance coating work, refer to Manual on Maintenance Coatings for Nuclear Power Plants.7  
A linings monitoring program enables early identification and detection of potential problems in lining systems. Some Coating Service Level III lining systems may be known in advance to be suspect, deficient, or degraded. Monitoring lining performance will assist in developing follow-up procedures to resolve any significant deficiency relative to lining work.
Degraded linings may generate debris under normal operation and testing or during upset conditions that could adversely affect the performance of the safety-related systems. In most cases, the consequence of the debris generation is flow blockage, essential heat transfer reduction, or both; ultimately leading to degradation of equipment or system performance. A linings monitoring program may be required to fulfill licensing commitments for Coating Service Level III lining work.
SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of Coating Service Level III lining (and coating) systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition of the in-service lining systems.
1.2 Coating Service Level III lining systems subject to this guide are generally those applied to metal substrates comprising raw water or condensate-quality water wetted (that is, full or intermittent immersion) surfaces in systems that include:
1.2.1 Service water piping upstream of safety-related components,
1.2.2 Service water pump internals (draft tube, volutes, and diffusers),
1.2.3 Service water heat exchangers including the channels, pass partitions, tubesheets, end bells, and covers
1.2.4 Service water strainers, and
1.2.5 Reactor water storage tanks (RWSTs) and refuel cavity water storage tanks.
1.3 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 any given operating nuclear power plant depending on its licensing commitments. Similar guidelines may be applicable for certain Coating Service Level II applications such as fluid immersion systems.
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 and health practices and determine the applicability of regulatory limitations prior to use.

SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of 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 Coating 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.

SCOPE
1.1 This guide covers procedures for establishing a program to monitor the performance of 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 Coating 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.

SIGNIFICANCE AND USE
The requirements of this guide apply to personnel who perform coating work inspection during (1) fabrication, (2) receipt of items at the construction site, (3) construction, (4) pre-operational and startup testing, and (5) operational phases of nuclear facilities.
It is the responsibility of each organization participating in the project to ensure that only those personnel within their respective organizations who meet the requirements of this guide are permitted to perform coating work inspection activities covered by this guide.
The organization(s) responsible for establishing the applicable requirements for activities covered by this guide shall be identified, and the scope of their responsibility shall be documented. Delegation of this responsibility to other qualified organizations is permitted and shall be documented.
It is the responsibility of the organization performing these activities to specify the detailed methods and procedures for meeting the requirements of this guide, unless they are otherwise specified in the contract documents.
In the event of conflict, users of this guide must recognize that the licensee’plant-specific quality assurance program and licensing commitments shall prevail with respect to the process of qualifying personnel performing inspection of coating work.
SCOPE
1.1 This guide delineates the requirements for development of procedures for the qualification of personnel who perform inspection of coating work. These activities are accomplished to verify conformance to specified requirements for nuclear facility coating work whose satisfactory performance is required in order not to compromise safety-related coating systems.
1.2 This guide provides a uniform interpretation of the intent of the requirements in ANSI/ASME N45.2.6 for the inspection of coating work in nuclear facilities.
1.3 This guide meets the intent of ANSI/ASME NQA-1.
1.4 It is the intent of this guide to provide a recommended basis for qualification, not to mandate a singular basis for all qualifications. Variations or simplifications of the qualifications described in this guide may be appropriate for special coating work other than safety-related coating systems. Similarly, the qualification and certification process might be abbreviated for work of minor scope such as touch-up.
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 whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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.

SCOPE
1.1 This guide is intended to aid the coating specification writer in selecting and specifying the appropriate inspection requirements. It indicates the inspection requirements that may be employed for each of four service environments including mild, moderate, severe, and immersion (see Table 1).
1.2 In order to aid the user in determining when to specify inspection requirements, a relationship between the consequence of failure and the suggested level of inspection is demonstrated (see Fig. 1).
1.3 It is not the intent of this guide to address the selection of protective coating systems, to specify surface preparation and application requirements, or to be a referenced document in a specification.

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.

SCOPE
1.1 This guide delineates the requirements for development of procedures for the qualification of personnel who perform inspection of coating work. These activities are accomplished to verify conformance to specified requirements for nuclear facility coating work whose satisfactory performance is required in order not to compromise safety-related coating systems.
1.2 This guide provides a uniform interpretation of the intent of the requirements in ANSI/ASME N45.2.6 for the inspection of coating work in nuclear facilities.
1.3 This guide meets the intent of ANSI/ASME NQA-1.
1.4 It is the intent of this guide to provide a recommended basis for qualification, not to mandate a singular basis for all qualifications. Variations or simplifications of the qualifications described in this guide may be appropriate for special coating work other than safety-related coating systems. Similarly, the qualification and certification process might be abbreviated for work of minor scope such as touch-up.
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 whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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.

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.

SIGNIFICANCE AND USE
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 D 5144, will perform satisfactorily in service.
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 owner, 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 D 5144,  shall be identified, quantified, and documented.
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 owner’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 practice 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 does not purport to address all of the safety problems, 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.

SCOPE
1.1 This guide is intended to aid the coating specification writer in selecting and specifying the appropriate inspection requirements. It indicates the inspection requirements that may be employed for each of four service environments including mild, moderate, severe, and immersion (see Table 1).
1.2 In order to aid the user in determining when to specify inspection requirements, a relationship between the consequence of failure and the suggested level of inspection is demonstrated (see Fig. 1).
1.3 It is not the intent of this guide to address the selection of protective coating systems, to specify surface preparation and application requirements, or to be a referenced document in a specification.
WITHDRAWN RATIONALE
This guide is intended to aid the coating specification writer in selecting and specifying the appropriate inspection criteria. It indicates the inspection requirements that may be employed for each of four service environments including mild, moderate, severe, and immersion.
Formerly under the jurisdiction of Committee D33 on Protective Coating and Lining Work for Power Generation Facilities, this guide was withdrawn in January 2013 in accordance with section 10.5.3.1 of the Regulations Governing ASTM Technical Committees, which requires that standards shall be updated by the end of the eighth year since the last approval date.