ML21125A505

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

ML21125A505
Person / Time
Site:	Cook
Issue date:	04/19/2021
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21126A238	List: AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21125A456 ML21125A457 ML21125A472 ML21125A473 ML21125A475 ML21125A482 ML21125A486 ML21125A487 ML21125A488 ML21125A493 ML21125A498 ML21125A499 ML21125A500 ML21125A501 ML21125A502 ML21125A503 ML21125A505 ML21125A508 ML21125A509 ML21125A510 ML21125A512 ML21125A514 ML21125A517 ML21125A518 ML21125A520 ML21125A521 ML21125A522 ML21125A524 ML21125A525 ML21125A526 ML21125A527 ML21125A529 ML21125A533 ML21125A534 ML21125A535 ML21125A537 ML21125A538 ML21125A539 ML21125A540 ML21125A542 ML21125A543 ML21125A545 ML21125A546 ML21125A547 ML21125A548 ML21125A550 ML21125A554 ML21125A557 ML21125A558 ... further results
References
AEP-NRC-2021-19
Download: ML21125A505 (1)

Text

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revision: 18.1 D. C. COOK NUCLEAR PLANT Table: 14.0-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 OCCURRENCES EVALUATED FOR VANTAGE 5 FUEL Fault Conditions Evaluated Accident FSAR Section 14.1.7 Startup of an Inactive Reactor Coolant Loop Fault Conditions Analyzed Accident FSAR Section Uncontrolled Rod Cluster Control Assembly Bank 14.1.1 Withdrawal From a Subcritical Condition Uncontrolled Rod Cluster Control Assembly Bank 14.1.2 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 Loss of Reactor Coolant Flow (including Locked 14.1.6 Rotor Analysis)1 14.1.8 Loss of External Electric Load or Turbine Trip(1) ,2 ,

14.1.9 Loss of Normal Feedwater3 ,4 Excessive Heat Removal due to Feedwater System 14.1.10 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 Rupture of a Control Rod Drive Mechanism Housing 14.2.6 (RCCA Ejection) 14.2.8 Major Rupture of a Main Feedwater Pipe (3) , (4) 14.3.1 Major Reactor Coolant Pipe Ruptures Loss of Reactor Coolant From Small Ruptured Pipes 14.3.2 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%.

UNIT 2