ML19312C148: Difference between revisions

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| number = ML19312C148
| number = ML19312C148
| issue date = 07/26/1976
| issue date = 07/26/1976
| title = Supplies Revised Figures to 760319 Ltr to NRC Re Effects of Postulated Spent Fuel Cask Drop Accident
| title = Supplies Revised Figures to to NRC Re Effects of Postulated Spent Fuel Cask Drop Accident
| author name = Parker W
| author name = Parker W
| author affiliation = DUKE POWER CO.
| author affiliation = DUKE POWER CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 7912060716
| document report number = NUDOCS 7912060716
| title reference date = 03-19-1976
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
| page count = 1
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=Text=
=Text=
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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.
DUKE POWER COMPANY
V'CE PatsiOENT TELEPuoNE AmEA 704 p
    ,                                                    Powza Bun.Dtwo 422 Socra Cituacit Srazzi, Csunt.orTz N. C. asa4a w t LLI AM O. PA R M E R, J R.
f Tra Pacouct'en 373-4083
V'CE PatsiOENT                                                           p      ,          TELEPuoNE AmEA 704 f Tra Pacouct'en                                                                                         373-4083 July 26, 1976                                                /       dI,.h                 .
/
L] "aQ,k,%u.g ,6-gI    ,,6,                   .C]
dI,.h L] "aQ,k,%u.g,6-July 26, 1976 I
Mr. Benard C. Rusche                                                u.5+ N 15           M a
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E4WS       /
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Director of Nuclear Reactor Regulation                                            , A,j\.
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U. S. Nuclear Regulatory Commission                               v / /g j  g Washington, D. C. 20555 Attention:             Mr. A. Schwencer Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287
Mr. Benard C. Rusche E4WS
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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:==
==Dear Mr. Rusche:==
 
My {{letter dated|date=March 19, 1976|text=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.
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.
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.
This will raise the exclusion area boundary whole body dose to 8.5 Rem and the thyroid dose to 132.9 Rem.
V         truly yours, u-A William O. Parker, Jr.
As can be seen, the radiological consequences of this postulated accident remain well with the established limits of 10CFR100.
MST:vr                                       _
V truly yours, u-A William O. Parker, Jr.
                                                                      -                      7668 79120607/f                               g}}
MST:vr 7668 79120607/f g}}

Latest revision as of 01:26, 2 January 2025

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)
v • d • e


Text

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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

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