ML20214G041
| ML20214G041 | |
| Person / Time | |
|---|---|
| Site: | Seabrook, 05000000 |
| Issue date: | 12/17/1984 |
| From: | Kato W BROOKHAVEN NATIONAL LABORATORY |
| To: | Lyon W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20213E815 | List:
|
| References | |
| CON-FIN-A-3778, FOIA-87-6 NUDOCS 8705260390 | |
| Download: ML20214G041 (4) | |
Text
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BROOKHAVEN NATIONAL LABORATORY i
ASSOCIATED UNIVERSITIES. INC.
Upton Long isiond NewYork 11973 (516) 282.
2444 i
Depor me it of Nuclear Energy FIS 66S' 4
December 17, 1984 Mr. Warren Lyon Reactor Systems Branch j
Division of Systems Integration i
Office of Nuclear Reactor Regulation Mail Stop P-1132 U. S. Nuclear Regulatory Commission.
Washington, D. C.
20555
Dear Mr. Lyon:
Enclosed is the November monthly report for the activities sponsored by your Branch. Also included are the computerized budge
- sunsnaries and the fee recovery cost status for each program.
I would suggest that you and your staff review the reports to determine whether there are any discrepancies.
If there are, please notify the principal investigatir.
We hope this meets with your approval.
If there are any questions re-garding format, distribution, or budget reporting, please contact Mr. A. J.
Weiss, Administrative Technical Assistant, FTS 666-4473.
Sincerely yours, l
, = ?
l W1ter Y. Kato Deputy Chairman WYK/jw I
Enclosures cc:
R. Bari, BNL S. H. Boyd, NRC R. Hall, BNL W. Houston, NRC H.Kaltman,NRC(RCTH!S CCeY ** !
J. Rosenthal, N 4
B. Sheron, NRC i
A. J. Weiss, BNL BNL Technical Monitors I
8705260390 870515 PDR FOIA SHOLLYe7-6 PDR
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I MONTHLY HIGHLIGHTS FOR NOVEMBER 1984
" Review of the Probabilistic Risk Assessment for the Seahrook Nuclear Power Plant" l
(FINA-3778) d RNL Principal Investigators:
M. Khatib-Rahbar (FTS 666-2626)
W. T. Pratt (FTS 666-2630)
NRC Project Manager:
W. Lyon (FTS 492-9405), RS Branch 1.
Scoce/
Purpose:
This project is to provide technical support to the Reactor Systems Branch in reviewing the accuracy and completeness of the Seabrook Proba-bilistic Safety Study (SPSS).
BNL will perform a critical review of the plant design and PRA methods supplemented by audit calculations Jf seleC-s ted accident sequences to confi rm the validity of the methods and results.
2.
Work Performed During Period:
Work was continued on reviewing the containment failure model.
Si gni fi-cant changes in ESF have been made via Amendment 53 dated August 1984, which might impact the frequency calculations for some events.
1 Work was also initiated on a preliminary report describing our evaluation of the PRA to date.
3.
P roblems/ Delays :
None.
4.
Summary of Progress to Date/ Milestones:
See Item 2.
5.
Next Reporting Period:
The PRA review will continue, and the preliminary report will also be completed and submitted to the NRC Project Manager.
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