ML16343A028

7 to Updated Final Safety Analysis Report, Chapter 11, Table 11.2-6

ML16343A028
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: ML16343A028 (1)

Text

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

16.6 Table:

11.2-6 Page:

1 of 1 PRINCIPAL AUXILIARY SHIELDING Design parameters for the auxiliary shielding include:

Core thermal power 3391 MWt Fraction of fuel rods containing small clad defects 0.01 Reactor coolant liquid volume 12600 ft.3 1 Letdown flow (normal purification) 75 gpm Cesium purification flow (intermittent) 75 gpm Cut-in concentration deborating demineralizer 100 ppm Dose rate outside auxiliary building

<1 mrem/hr Dose rate in the building outside shield walls

<2.5 mrem/hr COMPONENT CONCRETE SHIELD THICKNESS Ft. - In.

Mixed Bed Demineralizers 4 - 0 Charging pumps 2 - 6 Liquid holdup tanks 2 - 8 Volume control tank 3 - 9 Reactor Coolant filter 2 - 6 Boric Acid Evaporator 2 - 4 Gas decay tanks 3 - 3 Waste Gas Compressors 2 - 8 Waste Evaporator 2 - 0 Liquid Waste Holdup Tank 2 - 0 Spent Resin Storage Tank 4 - 0 1 This value has been conservatively chosen for the purpose of shield design. Actual best-estimated reactor coolant systems volumes can be obtained from the current Westinghouse IMP databases.