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:
......................................................................... F-1 APPENDIX G: Assumptions for Evaluating the Radiological Consequences of a Pressurized-Water Reactor Locked Rotor Accident ...................................................................................... G-1 APPENDIX H: Assumptions for Evaluating the Radiological Consequences of a Pressurized-Water Reactor Control Rod Ejection Accident ......................................................................... H-1 APPENDIX I: Analysis Decision Flowchart ............................................................................................I-1 APPENDIX J: Analytical Technique for Calculating Fuel-Design-Specific Non-Loss-of-Coolant-Accident Fission Product Release Fractions ................................ J-1 APPENDIX K: Acronyms ........................................................................................................................ K-1 DG-1389, Page 5 B. DISCUSSION Reason for Revision This revision of the guide (Revision 1) addresses new issues identified since the guide was originally issued. These include (1) using the term maximum hypothetical accident (MHA)1 loss-of-coolant accident (LOCA) to define the accident described in the applicable regulations in Section A above, with a clear delineation between source term assumptions and plant response,2 (2) adding transient release fractions from empirical data from in-pile, prompt power pulse test programs and analyses from several international publications of fuel rod performance under prompt power excursion conditions, (3) revising steady-state release fractions for accidents other than the LOCA based on a revision to the American National Standards Institute/American Nuclear Society (ANSI/ANS) Standard 5.4, “Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel” (Ref. 6), (4) adding information to acknowledge the proposed RG may provide useful information for satisfying