Document: NRC Regulatory Guide
Document ID: 5810150e-ee20-4cd1-b72f-6e918a603f73
Document Type: regulatory_guide
Title: Applications for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1523/ML15233A056.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.206
CFR Part: 
CFR Title: 

Content:
llowing issuance of an operating license are performed. Final Safety Analysis Report Information Commitment Included in a License Condition The regulations in 10 CFR 50.71(e) and the DCR appendices to 10 CFR Part 52 include requirements for COL holders to update their FSARs. Specifically, 10 CFR 50.71(e)(3)(iii) requires the COL holder to submit an updated FSAR to the NRC annually during the period from the docketing of a COLA until the Commission makes the finding under 10 CFR 52.103(g). In addition, 10 CFR 50.71(e)(4) requires subsequent FSAR revisions to be filed annually or 6 months after each refueling outage provided that the interval between successive updates does not exceed 2424 months. These revisions reflect all changes made to the FSAR up to a maximum of 6 months before the date of the filing. Although these requirements for FSAR updates currently exist, requiring the inclusion of FSAR information commitment items in a license condition ensures that specific information identified during the initial licensing review is included in the design bases for the facility. This includes the information that should be reviewed as part of the design bases for the facility when reviews and evaluations, such as those performed in accordance with 10 CFR 50.54(f); 10 CFR 50.59; and 10 CFR 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” are required. The license condition should also include a milestone schedule for ensuring that the specific FSAR information identified is included in an FSAR update, as required by DG-1325, Page-84 10 CFR 50.71(e). This license condition may include information such as the following: a. FSAR-level design information from completed digital I&C DAC; b. FSAR-level design information from as-built reconciliations of piping; c. design features installed as a result of the completed pipe break hazards analyses; d. an update to turbine missile generation analyses, as necessary, based on