Document: NRC Regulatory Guide
Document ID: a85f80f8-a5b4-4f0a-84fd-1eb04d49dd57
Document Type: regulatory_guide
Title: Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants + HISTORY - HISTORY 08/2016 – DG-1331 , Proposed Revision 3 10/2015 – Periodic Review of Revision 2 – Revise 10/2010 – Periodic Review of Revision 1 – No issues identified 04/2010 – DG-1242 , Proposed Revision 2 03/1999 – DG-1076 , Proposed Revision 1 (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1609/ML16097A448.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.54
CFR Part: 
CFR Title: 

Content:
Regulatory Commission (NRC) considers acceptable for the selection, application, qualification, inspection, and maintenance of protective coatings applied to nuclear power plants (NPPs). Applicability This RG applies to applicants and licensees subject to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, “Domestic Licensing of Production and Utilization Facilities” (10 CFR Part 50), Appendix A, “General Design Criteria for Nuclear Power Plants,” (Ref. 1), all applicants and licensees for a power reactor combined license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2) and all applicants and licensees for a renewed operating license under 10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants” (Ref. 3). Applicable Regulations • 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records,” requires, in part, that structures, systems, and components (SSCs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. GDC 1 also requires licensees to establish and implement a quality assurance (QA) program to provide adequate assurance that these SSCs will satisfactorily perform their safety functions. DG-1331, Page 2 • 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases,” requires, in part, that SSCs important to safety be designed for compatibility with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. • 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” establishes QA program requirements for the design, fabrication, construction, and testing of safety-related SSCs in NPPs. • 10 CFR 50.65, “Requirements for Monitoring