Document: NRC Regulatory Guide
Document ID: 70415715-297f-4d60-841c-514b0372a131
Document Type: regulatory_guide
Title: 02/2017 (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1608/ML16082A501.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.26
CFR Part: 
CFR Title: 

Content:
ntaining water, steam, or radioactive material in light- water-cooled nuclear power plants. Applicability This RG applies to all holders of operating licenses for nuclear power reactors subject to the provisions of 10 CFR 50, Appendix A, including those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel and all holders of and applicants for a power reactor combined license, standard design approval, or manufacturing license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref 2). Applicable Rules and Regulations • 10 CFR 50, “Domestic Licensing of Production and Utilization Facilities.” o 10 CFR 50 Appendix A, GDC 1 requires 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. This RG provides guidance on the quality standards appropriate to various classes of SSCs. RG 1.26, Rev. 5, Page 2 o 10 CFR 50.55a, “Codes and Standards,” subsections 50.55a(c), 50.55a(d), and 50.55a(e) state that certain systems and components of boiling- and pressurized-water-cooled nuclear power reactors must be designed, fabricated, erected, and tested in accordance with the standards for Class 1, 2, and 31 components given in Section III, “Nuclear Power Plant Components,” of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (BPV Code) (Ref. 3) or equivalent quality standards. This is referenced in Footnote 7 to 10 CFR 50.55a as the guidance for quality group classifications which are to be included in safety analysis reports. In addition, ASME Operation and Maintenance of Nuclear Power Plants (OM Code), Division 1, “Section IST: Rules for Inservice Testing of Light-Water Reactor Power Plants” (Ref. 4), covers an equipment scope that is further described in Section B below.