Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
model. A-5.8 Reduction of the amount of released organic iodine (e.g., Brockman-Bixler model in RADTRAD (Ref. A-4)) should not be credited. A-5.9 In the absence of collection and treatment of releases by ESFs such as the MSIV leakage control system, or as described in Regulatory Position A-5.4 above, the MSIV leakage should be assumed to be released to the environment as an unprocessed, ground-level release. A-5.10 Holdup and dilution of MSIV leakage releases into the turbine building should not be assumed. A-6. Containment Purging The licensee should analyze the radiological consequences from post-LOCA primary containment purging as a combustible gas or pressure control measure. If the installed containment purging capabilities are maintained for purposes of severe accident management and are not credited in any design basis analysis, radiological consequences need not be evaluated. If the primary containment purging is required within 30 days of the LOCA, the results of this analysis should be combined with consequences postulated for other fission product release paths to determine the total calculated radiological consequences from the LOCA. The licensee may take into account the reduction in the amount of radioactive material released via ESF filter systems using the guidance in Regulatory Guide 1.52 (Ref. A-6). DG-1389, Appendix A, Page A-13 APPENDIX A REFERENCES A-1. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy” (10 CFR Part 50). A-2. U.S. Nuclear Regulatory Commission (NRC), “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” NUREG-0800.1 A-3. U.S. NRC, “A Simplified Model of Aerosol Removal by Natural Processes in Reactor Containments,” NUREG/CR-6189, July 1996 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100130305). A-4. U.S. NRC, “RADTRAD: A Simplified Model for