Document: NRC Regulatory Guide
Document ID: b143ccef-ed08-482d-bc4b-b4e012328090
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:
e that Results in Decreasing Steam Flow ........................................................................................................................ 15.2.2 Loss of External Electrical Load ................................................................................ 15.2.3 Turbine Trip .............................................................................................................. 15.2.4 Inadvertent Closure of Main Steam Isolation Valves .................................................... 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in Turbine Trip ...................... 15.2.6 Loss of ac Power to the Plant Auxiliaries .................................................................... 15.2.7 Loss of Normal Feedwater Flow ................................................................................. 15.2.8 Feedwater System Pipe Break .................................................................................... 15.2.9 Combined License Information .................................................................................. 15.2.10 References15.3 Decrease in Reactor Coolant System Flow Rate .................................. 15.3 ..................................................................................................................................................... 15.3.1 Partial Loss of Forced Reactor Coolant Flow .............................................................. 15.3.2 Complete Loss of Forced Reactor Coolant Flow ......................................................... 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) .................................................. Appendix A to DG-1325, Page A-22 15.3.4 Reactor Coolant Pump Shaft Break ............................................................................ 15.3.5 Combined License Information................................................................................... 15.3.6 References