ML16341C475

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7 to Updated Final Safety Analysis Report, Chapter 9, Table 9.7-6
ML16341C475
Person / Time
Site: Cook  
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: ML16341C475 (1)


Text

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

19.1 Table:

9.7-6 Page:

1 of 1

SUMMARY

OF CRITICALITY SAFETY ANALYSES NORMAL STORAGE CONFIGURATION Design Basis burnups at 4.95% +/-0.05% initial enrichment 0 in Region 1 50 in Region 2 38 in Region 3 Temperature for analysis 20°C (68°F)

Reference K (KENO-5a) 0.9160 Calculational bias, k 0.0090 Axial burnup effect 0.0037 UNCERTAINTIES Bias statistics (95%/95%)

+/-0.0021 KENO-5a statistics (95%/95%)

+/-0.0012 Manufacturing tolerances

+/-0.0064 Water-gap

+/-0.0045 Fuel enrichment

+/-0.0034 Fuel density

+/-0.0035 Burnup (38 MWD/KgU)

+/-0.0019 Burnup (50 MWD/KgU)

+/-0.0047 Eccentricity in position

+/-0.0019 Statistical combination of uncertainties1

+/-0.0110 TOTAL 0.9287 +/-0.0110 Maximum reactivity (k) 0.940 1 Square root of sum of squares.