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:
o quality standards commensurate with the safety function to be performed. The evaluation to establish the quality group classification of these other systems should consider the guidance provided for quality groups B, C, and D in Staff Regulatory Guidance, Sections 1, 2, and 3 of this guide. As additional background information, the following paragraphs provide summary information and references related to other systems of classification and treatment that are related to, but separate from, the information presented in this RG. The American Nuclear Society (ANS) has prepared ANSI/ANS-58.14-2011, “Safety and Pressure Integrity Classification Criteria for Light Water Reactors” (Ref. 9), to provide criteria for the safety classification of items in light water reactor nuclear power plants, and for the assignment of pressure integrity classes to pressure-retaining items. In ANSI/ANS-58.14, the categories with respect to safety classification are denoted by the terms “safety-related,” “non-safety-related with augmented requirements,” and “non-safety-related,” and by Classes C-1 through C-5 for pressure integrity classification. As indicated in footnote 39 in ANSI/ANS-58.14, ANS Classes C-1 through C-4 generally correspond to Quality Groups A through D, respectively, as defined in 10 CFR 50.55a and RG 1.26. As described below in Section D, use of this alternative classification approach instead of the approach presented in this guide may be deemed acceptable if an applicant or licensee provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with GDC 1 and 10 CFR 50.55a. RG 1.26, Rev. 5, Page 5 As mentioned above, the ASME OM Code is incorporated into the NRC’s requirements in 10 CFR 50.55a. The OM Code specifies that its scope includes: (a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe