ML16343A024

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7 to Updated Final Safety Analysis Report, Chapter 11, Table 11.2-2
ML16343A024
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: ML16343A024 (1)


Text

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

16.1 Table:

11.2-2 Page:

1 of 1 PRIMARY SHIELD DESIGN PARAMETERS, NEUTRON AND GAMMA FLUXES DESIGN PARAMETERS Core thermal power 3391 MW Active core height 144 in.

Effective core diameter 132.7 in.

Baffle wall thickness 1.125 in.

Barrel wall thickness 2.25 in.

Thermal shield wall thickness 2.75 in.

Reactor vessel I.D.

173.0 in.

Reactor vessel wall thickness 8.625 in.

Reactor coolant cold leg temperature 536°F Reactor coolant hot leg temperature 600°F Maximum thermal neutron flux exiting primary concrete 8.4 x 103n/cm2sec.

Reactor shutdown dose exiting primary concrete

<15 mrem/hr CALCULATED NEUTRON FLUXES ENERGY GROUP INCIDENT FLUXES (n/cm2 - sec)

LEAKAGE FLUXES (n/cm2 - sec)

E 1 Mev 7.7 x 108 2.5 x 101 5.3 Kev < E < 1 Mev 1.3 x 1010 5.6 x 101

.625 ev < E < 5.3 Kev 7.8 x 109 9.5 x 101 E <.625 ev 2.0 x 109 8.4 x 103 CALCULATED GAMMA FLUXES ENERGY GROUP INCIDENT FLUXES

(/cm2 - sec)

LEAKAGE FLUXES

(/cm2 - sec)

E = 7.5 Mev 4.5 x 109 4.4 x 105 E = 4.0 Mev 1.2 x 109 3.1 x 105 E = 2.5 Mev 2.2 x 109 3.4 x 105 E = 0.8 Mev 7.6 x 108 2.8 x 104