ML22340A168

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

ML22340A168
Person / Time
Site:	Cook
Issue date:	11/30/2022
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22340A137	List: AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) ML22340A128 ML22340A129 ML22340A131 ML22340A132 ML22340A133 ML22340A134 ML22340A135 ML22340A136 ML22340A138 ML22340A139 ML22340A141 ML22340A142 ML22340A143 ML22340A144 ML22340A145 ML22340A146 ML22340A147 ML22340A148 ML22340A149 ML22340A150 ML22340A151 ML22340A152 ML22340A153 ML22340A154 ML22340A155 ML22340A156 ML22340A157 ML22340A158 ML22340A159 ML22340A160 ML22340A161 ML22340A162 ML22340A163 ML22340A164 ML22340A165 ML22340A166 ML22340A167 ML22340A168 ML22340A169 ML22340A170 ML22340A171 ML22340A172 ML22340A173 ML22340A174 ML22340A175 ML22340A176 ML22340A177 ML22340A178 ML22340A179 ... further results
References
AEP-NRC-2022-62
Download: ML22340A168 (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 31.0