Document: NRC Regulatory Guide
Document ID: 74c49394-8dbf-46e7-b62a-b85de93b47d8
Document Type: regulatory_guide
Title: Initial Test Programs for Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 11/2012 – DG-1259 , Proposed Revision 4 11/2006 – DG-1166 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.68
CFR Part: 
CFR Title: 

Content:
of accidents during the testing period. Under 10 CFR 52.137(b), an application for approval of a SD, which differs significantly from the light-water reactor designs of plants that have been licensed and in commercial operation before April 18, 1989, or uses simplified, inherent, passive, or other innovative means to accomplish its safety functions, must meet the requirements of 10 CFR 50.43(e). Thus, the regulations in 10 CFR 50.43(e) may also apply to SD, DC, ML and COL applications submitted under 10 CFR 52.47(a)(2)(iii), 52.47(c)(2), 52.79(a)(2)(iii), 52.79(a)(24), 52.79(a)(28) and 52.137(b). Under 10 CFR 52.47(a)(2)(iii), applications for the certification of a nuclear power reactor design must contain in the FSAR a description of the facility that presents the design bases and the limits on its operations and presents a safety analysis of the SSCs and of the facility as a whole, including the unique, unusual or enhanced safety features having a significant bearing on the probability or consequences of accidental release of radioactive materials. To the extent that the DC is not incorporated by reference, 10 CFR 52.79(a)(2)(iii) requires that the COL FSAR include such unique, unusual or enhanced safety features. Furthermore, 10 CFR 52.79(a)(24), requires, in part, that if the COL application uses simplified, inherent, passive or other innovative means to accomplish the safety function, the application must describe how the design meets the requirements in 10 CFR 50.43(e). The regulations in 10 CFR 52.79(a)(28) require a COL application to describe plans for preoperational testing and initial operations, which includes testing to verify that unique, unusual or enhanced safety features systems will meet their design and test acceptance criteria. Under 10 CFR 52.47(c)(2), applicants for certification of a nuclear power plant design that differs significantly from a light-water reactor design licensed and in commercial operation before April 18, 1989, or using