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:
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 the Effectiveness of Maintenance at Nuclear Power Plants,” includes safety-related SSCs that are relied on to remain functional during and following design-basis events with respect to specified functions and nonsafety-related SSCs. To the extent that protective coatings meet these criteria, these coatings are within the scope of the maintenance rule. • 10 CFR 52.47, “Contents of Applications; Technical Information,” requires, in part, that applications for standard design certification rules under 10 CFR Part 52 to comply with the principal design criteria in Appendix A to 10 CFR Part 50. • 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” requires, in part, that applications for combined licenses under 10 CFR Part 52 to comply with the principal design criteria in Appendix A to 10 CFR Part 50. • 10 CFR 52.137, “Contents of applications; technical information,” requires, in part, that applications for standard design approvals for nuclear power plants under 10 CFR Part 52 comply with the principal design criteria in Appendix A to 10 CFR Part 50, to the extent they are applicable to the scope of the design approval. • 10 CFR 52.157 Contents of applications; technical information in final safety analysis report, requires that applications for manufacturing licenses for nuclear power plants under 10 CFR Part 52 comply with the principal design criteria in Appendix A to 10 CFR Part 50. • 10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants,” establish requirements for obtaining a renewed license for operation beyond its initial 40 year operating license. Related Guidance • RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,”