ML20234F272

Advises That Div of Radiation Protection Stds Has No Comments on 640122 Amend 5 to License Application.Amend Deals Solely W/Geological & Seismological Characteristics of Bodega Site

ML20234F272
Person / Time
Site:	05000000, Bodega Bay
Issue date:	02/28/1964
From:	Western F US ATOMIC ENERGY COMMISSION (AEC)
To:	Case E US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20234A767	List: IA-85-665, Discusses Seismic Design of Nuclear Power Plants,Including Const of Nuclear Plants in Seismically Active Zones ML20234A761 ML20234A769 ML20234A792 ML20234A798 ML20234A803 ML20234A812 ML20234A816 ML20234A827 ML20234A830 ML20234A838 ML20234A841 ML20234A844 ML20234A847 ML20234A851 ML20234A855 ML20234A858 ML20234A861 ML20234A864 ML20234A868 ML20234A871 ML20234A874 ML20234A893 ML20234A896 ML20234A900 ML20234A911 ML20234A922 ML20234A929 ML20234A932 ML20234A937 ML20234A944 ML20234A956 ML20234A965 ML20234A968 ML20234A976 ML20234A984 ML20234A993 ML20234A996 ML20234A999 ML20234B005 ML20234B008 ML20234B023 ML20234B032 ML20234B035 ML20234B040 ML20234B062 ML20234B066 ML20234B076 ML20234B084 ML20234B098 ... further results
References
FOIA-85-665 NUDOCS 8709230075
Download: ML20234F272 (2)

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Edson G. Case, Assistant Director. FEB . 2 8 1964 for Facility Licensing, DLR g,; + ;! r H d by-Forrest Western, Director ferrest Westctn 1 Division of Radiation Protection Standards

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i CALIFORNIA PACIFIC GAS AND BIBCTRIC COMPAltY, BOIEGA BAY,64 DOCKET NO. 50-2 p0AENINurr #5, dated 1/22/

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We have no coussent o'n the subject doctament as the matters 1

discussed therein are not within the purview of our casspetence. ]

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l Fortn AEC.8tB (Rev.H3) e. s. eevesamsus marma'erroca le--enat-a ,

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' Background Notes on: . "Facific Gas and Electric Company, Bodega Bay, California - Docket No. 50-205 kendment f$. dated 1/22/6k"

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The doc 1 ment deals solely with the geological and seismological characteristics oi' the Bodega site. The authors' conclusions all amount to ibe same thing: With somquate structural engineering the probability of an earthquake - induced accident is extremely small within the lifetime of the reactor.

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