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:
................... 29 5.2 Accident-Specific Assumptions ........................................................................................ 30 5.3 Atmospheric Dispersion Modeling and Meteorology Assumptions ................................. 30 D. IMPLEMENTATION ............................................................................................................................ 33 REFERENCES ........................................................................................................................................... 35 APPENDIX A: Assumptions for Evaluating the Radiological Consequences of Light-Water Reactor Maximum Hypothetical Loss-of-Coolant Accidents ...................................................... A-1 APPENDIX B: Assumptions for Evaluating the Radiological Consequences of a Fuel Handling Accident .......................................................................................................................... B-1 APPENDIX C: Assumptions for Evaluating the Radiological Consequences of a Boiling-Water Reactor Rod Drop Accident ......................................................................................................... C-1 APPENDIX D: Assumptions for Evaluating the Radiological Consequences of a Boiling-Water Reactor Main Steamline Break Accident ..................................................................................... D-1 APPENDIX E: Assumptions for Evaluating the Radiological Consequences of a Pressurized-Water Reactor Steam Generator Tube Rupture Accident .......................................................... E-1 APPENDIX F: Assumptions for Evaluating the Radiological Consequences of a Pressurized-Water Reactor Main Steamline Break Accident ......................................................................... F-1 APPENDIX G: Assumptions for Evaluating the Radiological Consequences of a Pressurized-Water Reactor Locked Rotor Accident