Document: NRC Regulatory Guide
Document ID: 0db9d11c-023a-474a-8976-8d7219dd4011
Document Type: regulatory_guide
Title: Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1908/ML19086A072.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.181
CFR Part: 
CFR Title: 

Content:
ing of aging management and time limited aging analyses information and included a redline markup of NEI 98-03, Draft Revision 2 that requested specific changes in several general areas including: • Updating outdated references; • Removing internally inconsistent guidance concerning historical information; - 2 - ENCLOSURE • Clarifying the treatment of commitments in the FSAR; • Providing recommendations on FSAR format for submittal of updates; • Adding guidance for considering the need to update the FSAR to reflect third-party information (e.g., Army Corps of Engineers’ Reports, National Geologic Survey, etc.); • Referencing guidance for updating the FSAR to reflect license renewal and decommissioning activities; and • Clarifying expectations regarding updating beyond-design-basis information. In response to NRC staff’s preliminary comments on the proposed revision, NEI submitted an updated revision of “NEI 98-03, Guidelines for Updating Final Safety Analysis Reports, Draft Revision 2,” (ADAMS Accession No. ML17249A097), in response to a select group of preliminary comments related to licensing activities under 10 CFR Part 52. This revised draft version may contain new draft guidance beneficial to current and future holders of combined licenses (COL) issued under Part 52. Revision of RG 1.181 would allow for appropriate update of guidance for operating reactors with licenses issued under 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” as well as new guidance for holders of COLs issued under 10 CFR Part 52. 2. What is the impact on internal and external stakeholders of not updating the RG for the known issues, in terms of anticipated numbers of licensing and inspection activities over the next several years? The endorsed guidance related to 10 CFR 50.71(e) is out of date which impacts the fleet of operating reactors. Proper implementation of 10 CFR 50.71(e) by the applicant/licensee is essential to the proper