Document: NRC Regulatory Guide
Document ID: 5810150e-ee20-4cd1-b72f-6e918a603f73
Document Type: regulatory_guide
Title: Applications for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1523/ML15233A056.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.206
CFR Part: 
CFR Title: 

Content:
or Component ......................... 15.7 ..................................................................................................................................................... 15.7.1 Gas Waste Management System Leak or Failure ......................................................... 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ................. 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure ................... 15.7.4 Fuel Handling Accident ............................................................................................ 15.7.5 Spent Fuel Cask Drop Accident ................................................................................. 15.7.6 Combined License Information................................................................................... 15.7.7 References ............................................................................................................... 15.8 Anticipated Transients Without Scram ....................................................................................... 15.8.1 General Background .................................................................................................. 15.8.2 Anticipated Transients Without Scram in the AP1000 .................................................. 15.8.3 Conclusion ............................................................................................................... 15.8.4 Combined License Information................................................................................... 15.8.5 References ................................................................................................................ Appendix A to DG-1325, Page A-23 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS 15A.1 Offsite Dose Calculation Models ...............................................................................................