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:
guides are not substitutes for regulations and compliance with them is not required. Methods and solutions that differ from those set forth in RGs will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission. Paperwork Reduction Act This RG contains and references information collections covered by 10 CFR Parts 50, 52, and Part 54 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.). These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011, 3150–0151, and 3150-0155 respectively. Public Protection Notification The NRC may not conduct nor sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. B. DISCUSSION Reason for Revision This revision (Revision 3) of RG 1.54 approves, with certain clarifications and exceptions, the use of American Society for Testing and Materials (ASTM International) Standard D 5144-08ε1, “Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants,” 1 (Ref. 7), and multiple sub-tier ASTM International standards as identified in Figure 1 and described below. ASTM International, standard D 5144-08ε1 was issued in 2008 to provide a common basis on which protective coatings for the surfaces of nuclear power generating facilities may be qualified and selected through reproducible evaluation tests. This revision also expands the scope of this RG to address aging management of internal coatings and linings on components within the scope of license renewal under 10 CFR Part 54. Background The NRC developed this RG using definitions and insights from operating reactors. New reactor designs might use design features that are different from the operating reactors that formed the basis for this RG.