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:
eveloped 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. Consequently, it may be necessary to adjust the guidance in this RG to apply to new reactor 1 The “ε1” symbol at the end of ASTM International, standard D 5144-08ε1 is used by ASTM International to identify an ASTM standard that was revised to correct an editorial error. The copyright date of the edited standard differs from the original publication date of the standard. DG-1331, Page 4 designs because these facilities might use design features that are different from the operating reactors that formed the basis for this RG. For example, a plant with passive containment cooling features might have different requirements for protective coatings on containment surfaces, or a plant might rely on the density of failed protective coating particles inside containment which would limit their transport to the emergency core cooling system (ECCS). Therefore, this RG provides guidance for new reactor designs with the recognition that the licensee or applicant may need to adjust some features based on the particular plant design. Nuclear power plants use protective coatings to protect the surfaces of facilities and equipment against corrosion and contamination from radionuclides and for wear protection during plant operation and maintenance activities. For plants with a design basis that includes a commitment to a previous revision of RG 1.54, the regulations cited above require that protective coatings be qualified and capable of surviving a design-basis event (DBE) without impairing the safety-related SSCs needed to mitigate the event. The NRC issued Rev. 0 of RG 1.54, “Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants,” (Ref. 8) to provide an acceptable method for complying with NRC QA requirements for protective