ML19312C148

From kanterella
Jump to navigation Jump to search
Supplies Revised Figures to to NRC Re Effects of Postulated Spent Fuel Cask Drop Accident
ML19312C148
Person / Time
Site: Oconee  
Issue date: 07/26/1976
From: Parker W
DUKE POWER CO.
To: Rusche B
Office of Nuclear Reactor Regulation
References
NUDOCS 7912060716
Download: ML19312C148 (1)


Text

)

.\\

DUKE POWER COMPANY Powza Bun.Dtwo 422 Socra Cituacit Srazzi, Csunt.orTz N. C. asa4a w t LLI AM O. PA R M E R, J R.

V'CE PatsiOENT TELEPuoNE AmEA 704 p

f Tra Pacouct'en 373-4083

/

dI,.h L] "aQ,k,%u.g,6-July 26, 1976 I

,,6,

.C]

g u.5+ N 15 M

Mr. Benard C. Rusche E4WS

/

, A,j\\.

a Director of Nuclear Reactor Regulation v / /g j U. S. Nuclear Regulatory Commission g

Washington, D. C.

20555 Attention:

Mr. A. Schwencer Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287

Dear Mr. Rusche:

My letter dated March 19, 1976 provided information concerning the effects of a postulated spent fuel cask drop accident, including a description of the calculation performed to determine the maximum nunber of fuel assemblies affected and the corresponding dose at the exclusion area boundary.

A review of this calculation has indicated that the number of affected assemblies should be increased from 73 to 76 assemblies.

This will raise the exclusion area boundary whole body dose to 8.5 Rem and the thyroid dose to 132.9 Rem.

As can be seen, the radiological consequences of this postulated accident remain well with the established limits of 10CFR100.

V truly yours, u-A William O. Parker, Jr.

MST:vr 7668 79120607/f g