ML16343A141

7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.3.2-1, Plant Input Parameters for Small Break Loss-of-Coolant Accident

ML16343A141
Person / Time
Site:	Cook
Issue date:	10/24/2016
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16336A263	List: AEP-NRC-2016-42, Fire Protection Program Change Summary ML16336A225 ML16336A228 ML16336A238 ML16336A291 ML16336A292 ML16336A294 ML16336A295 ML16336A297 ML16336A298 ML16336A299 ML16336A300 ML16336A301 ML16336A302 ML16336A303 ML16336A304 ML16336A305 ML16336A306 ML16336A308 ML16336A309 ML16336A310 ML16336A311 ML16336A312 ML16336A313 ML16336A314 ML16336A315 ML16336A316 ML16336A317 ML16336A318 ML16336A319 ML16336A320 ML16336A322 ML16336A323 ML16336A324 ML16336A325 ML16336A327 ML16336A328 ML16336A329 ML16336A330 ML16336A332 ML16336A333 ML16336A334 ML16336A336 ML16336A337 ML16336A338 ML16336A339 ML16336A340 ML16336A341 ML16336A342 ML16336A345 ... further results
References
AEP-NRC-2016-42
Download: ML16343A141 (2)

Text

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Table: 14.3.2-1 Sheet:

1 of 2 Unit 1 Last Revised: Revision 25.0 Plant Input Parameters for Small Break Loss-of-Coolant Accident Core Rated Thermal Power-100% (MWt) 3304 Peak Linear Power, kW/ft 15.171 Fuel Type 15x15 Upgrade Fuel Total Core Peaking Factor, FQ 2.32 Hot Channel Enthalpy Rise Factor, FH 1.55 Hot Assembly Average Power Factor, PHA 1.38 Thermal Design Flow, gpm/loop 83,200 Nominal Vessel Average Temperature, °F 577.4(1)

Nominal Pressurizer Pressure, psia 2250(2)

Pressurizer Pressure Uncertainty (psia)

+/-67 Minimum Auxiliary Feedwater Flow Rate, lbm/s per SG 14.68 Steam Generator Tube Plugging (Maximum), %

10 Initial Accumulator Water Volume, ft3 946 Accumulator Tank Volume, ft3/tank 1350 Accumulator Water Temperature, °F 130 Minimum Accumulator Cover Gas Pressure (minus uncertainties), psia 600 Refueling Water Storage Tank Temperature, °F 105 Nominal Steam Pressure, psia 848.32

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Table: 14.3.2-1 Sheet:

2 of 2 Unit 1 Last Revised: Revision 25.0 Plant Input Parameters for Small Break Loss-of-Coolant Accident SI Flow Delay Time, seconds 54 HHSI Cross-Tie Valve Position Open (Injection & Cold Leg Recirculation)(3)

RHR Cross-Tie Valve Position Open (Injection)

Closed (Cold Leg Recirculation)

(1) Analysis supports operation over the range of nominal full-power Tavg values of 553.7°F - 575.4°F.

(2) Analysis supports operation at nominal initial pressurizer pressure (without uncertainties) of 2100 psia and 2250 psia.

(3) Conservatively modeled HHSI cross-tie valves closed in injection phase.