ML24159A195

Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 14, Table 14.0-1 (Unit 2)

ML24159A195
Person / Time
Site:	Cook
Issue date:	05/30/2024
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML24159A261	List: AEP-NRC-2024-20, Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Reactor (Unit 2) ML24159A163 ML24159A164 ML24159A165 ML24159A166 ML24159A167 ML24159A168 ML24159A169 ML24159A170 ML24159A171 ML24159A172 ML24159A173 ML24159A174 ML24159A175 ML24159A176 ML24159A177 ML24159A178 ML24159A179 ML24159A180 ML24159A181 ML24159A182 ML24159A183 ML24159A184 ML24159A185 ML24159A186 ML24159A187 ML24159A188 ML24159A189 ML24159A190 ML24159A191 ML24159A192 ML24159A193 ML24159A194 ML24159A195 ML24159A196 ML24159A198 ML24159A199 ML24159A200 ML24159A201 ML24159A202 ML24159A203 ML24159A204 ML24159A205 ML24159A206 ML24159A207 ML24159A208 ML24159A209 ML24159A210 ML24159A211 ML24159A212 ... further results
References
AEP-NRC-2024-20
Download: ML24159A195 (1)

Text

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 18.1 Table:

14.0-1 Page:

1 of 1 UNIT 2 OCCURRENCES EVALUATED FOR VANTAGE 5 FUEL Fault Conditions Evaluated FSAR Section Accident 14.1.7 Startup of an Inactive Reactor Coolant Loop Fault Conditions Analyzed FSAR Section Accident 14.1.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal From a Subcritical Condition 14.1.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power 14.1.3 Rod Cluster Control Assembly Misalignment 14.1.4 Rod Cluster Control Assembly Drop 14.1.5 Uncontrolled Boron Dilution 14.1.6 Loss of Reactor Coolant Flow (including Locked Rotor Analysis)1 14.1.8 Loss of External Electric Load or Turbine Trip(1), 2,

14.1.9 Loss of Normal Feedwater3,4 14.1.10 Excessive Heat Removal due to Feedwater System Malfunctions 14.1.11 Escessive Load Increase Incident 14.1.12 Loss of Offsite Power to the Station Auxiliaries (3), (4) 14.2.4 Steam Generator Tube Rupture 14.2.5 Rupture of a Steam Line 14.2.6 Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection) 14.2.8 Major Rupture of a Main Feedwater Pipe (3), (4) 14.3.1 Major Reactor Coolant Pipe Ruptures 14.3.2 Loss of Reactor Coolant From Small Ruptured Pipes From Cracks in Large Pipes which Actuates the Emergency Core Coolant System 1 Reanalyzed to support PSV setpoint tolerance of +3%.

2 Reanalyzed to support MSSV setpoint tolerance of +3%.

3 Evaluated to support MSSV setpoint tolerance of +3%.

4 Evaluated to support PSV setpoint tolerance of +3%.

UFSAR Revision 32.0