ML16336A534

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7 to Updated Final Safety Analysis Report, Chapter 3, Table 3.4.1-3
ML16336A534
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: ML16336A534 (1)


Text

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

16.1 Table:

3.4.1-3 Page:

1 of 1 SENSITIVITY ANALYSIS EFFECT OF VARYING THE POWER DISTRIBUTION Power Distribution Power

% of Rated Tin Pressure Statistical Number Of Fuel Rods Which May Experience DNB Design 112 536.3 2250 0.54 Best Estimate 112 536.3 2250 0.09 EFFECT OF VARYING POWER LEVELS Power Distribution Power

% of Rated Tin Pressure Statistical Number of Fuel Rods Which May Experience DNB Best Estimate 100 536.3 2250 0.01 Best Estimate 112 536.3 2250 0.09 EFFECT OF VARYING FLOW RATE AT 112% POWER Power Distribution Flow

% of Rated Tin Pressure Statistical Number of Fuel Rods Which May Experience DNB Best Estimate 100 536.3 2250 0.09 Best Estimate 95 536.3 2250 0.18 Best Estimate 90 536.3 2250 0.42 The statistical number of rods which could experience DNB takes into account the distribution of the experimental data from which the W-3 DNB correlation was developed and the distribution of the power in the core.