ML16344A357

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7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.3.2-1, Plant Input Parameters for Small Break Loss-Of-Coolant Accident, Page 1 of 1
ML16344A357
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/24/2016
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16336A263 List: ... further results
References
AEP-NRC-2016-42
Download: ML16344A357 (1)


Text

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 24.0 Table: 14.3.2-1 Page:

1 of 1 Unit 2 PLANT INPUT PARAMETERS FOR SMALL BREAK LOSS-OF-COOLANT ACCIDENT Core Rated Thermal Power - 100%, MWt 3600(1)

Peak Linear Power, kW / ft 12.822 Fuel Type 17 x 17 Vantage 5 Fuel Total Core Peaking Factor, FQ 2.32 Hot Channel Enthalpy Rise Factor, FH 1.62 Hot Assembly Average Power Factor, PHA 1.46 Thermal Design Flow, gpm / loop 88,500 Nominal Vessel Average Temperature, °F 578.2(2)

Nominal Pressurizer Pressure, psia 2250(3)

Minimum Auxiliary Feedwater Flow Rate, lbm / s per SG 25.78 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 120 Nominal Steam Pressure, psia 791.863 SI Flow Delay Time, seconds 54 HHSI Cross-Tie Valve Position Open RHR Cross-Tie Valve Position Open (Injection)

Closed (Recirculation)

(1) Calorimetric uncertainty of 1.0034 resulted in an analyzed core power of 3612 MWt.

(2) Analysis supports operation over the range of nominal full-power Tavg values of 547.6°F-578.1 °F with Tavg uncertainty range of +4.1 °F / -5.6°F.

(3) Analysis supports operation at nominal initial pressurizer pressure of 2100 psia and 2250 psia with +/-62.6 psi uncertainty.