Document: NRC Regulatory Guide
Document ID: 67108c69-a593-46ac-bb19-b89d1041f393
Document Type: regulatory_guide
Title: Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors (Rev. 0)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1624/ML16244A739.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.195
CFR Part: 
CFR Title: 

Content:
Regulatory Guide Periodic Review Regulatory Guide Number: 1.195, Revision 0 Title: Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light- Water Nuclear Power Reactors Office/division/branch: NRR/DRA/ARCB Technical Lead: Elijah D. Dickson Staff Action Decided: Reviewed with no issues identified 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)? No technical or regulatory issues were identified. RG 1.195, Revision 0, “Methods and Assumptions for Evaluating Radiological Consequences of Design basis Accidents at Light-Water Nuclear Power Reactors,” published May 2003, provides an approach acceptable to the NRC staff for licensees of operating power reactors on acceptable methods and assumptions for performing evaluations of fission product releases and radiological consequences of several postulated light-water reactor design basis accidents. This guide provides guidance on methods acceptable to the staff for determining the radiological sources; the scope, nature, and documentation of associated analyses and evaluations; consideration of impacts on analyzed risk; and the content of submittals acceptable to the NRC staff. One editorial issue was identified. The next time regulatory guide 1.195 is revised the revision should include deleting the references to the following regulatory guides currently being withdrawn: • RG 1.3, Rev. 2, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors” dated June 1974; • RG 1.4, Rev. 2, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors” dated June 1974; • RG 1.5 (Safety Guide 5), “Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors” dated March 1971; • RG 1.25, “Assumptions