ML20214G171

Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1985

ML20214G171
Person / Time
Site:	Seabrook, 05000000
Issue date:	02/28/1985
From:	BROOKHAVEN NATIONAL LABORATORY
To:	NRC
Shared Package
ML20213E815	List: ML20213E811 ML20214F446 ML20214F510 ML20214F578 ML20214F595 ML20214F603 ML20214F654 ML20214F699 ML20214F736 ML20214F755 ML20214F766 ML20214F817 ML20214G041 ML20214G057 ML20214G062 ML20214G065 ML20214G068 ML20214G079 ML20214G123 ML20214G128 ML20214G148 ML20214G171 ML20214G179 ML20214G181 ML20214G188 ML20214G192 ML20214G204
References
CON-FIN-A-3778, FOIA-87-6 NUDOCS 8705260444
Download: ML20214G171 (4)

Text

_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

\

l

', . I  ;

%) l w

l MONTHLY HIGHLIGHTS FOR FEBRUARY 1985 i

" Review of the Probabilistic Risk Assessment for the Seabrook Nuclear Power Plant" (FIN A-3778)

(Page 1 of 2)

BNL 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. Scope /

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 wil' perform a critical review of ';he plant design and PRA methods supplemented by audit calculations of selec-ted accident sequences to confirm the validity of the methods and results.

2. Work Performed During Period:

Containment response classes were defined in accordance with common char-acteristics between the plant damage states. Response class frequencies were also calculated based upon the applicant's values for determination of the various source term frequencies for both internal 6nd external events. Accident source term characteristics were also adjusted and re-fined for use by the NRC staff in their site consequence analysis. A re-port describing these source term characteristics was submitted to the NRC Project Manager.

3. Problems /Dela,vs :

None.

4. Summary of Progress to Date/ Milestones:

See Item 2.

l 8705260444 870515 PDR FOIA SHOLLYB7-6 PDR .

Y _ . _-

i I

" Review of the Probabilistic Risk Assessment for the Seabrook Nuclear Power Plant" (Page 2 of 2)

5. Next Reporting Period:

The results of the NRC site consequence analysis are expected to be com-pleted and sent to BNL to estimate severe accident risk.

A number of questions related to the frequency of the plant damage states for Seabrook need to be resolved through consultation with RRAB, RSB, and LLNL.

s

- - _ . , . . . . . - . _ . . . , . . . . . _ _ _ _ __ n , y- -

i

. F i .. L 1-a-L 6 i s. 'l L d i

,j F C P

• I ,6 t Icsc e ACCOLAl T T T L F HEC FTL 00 41 1 'J  % r v T t 's rF Fr. fra S F a A .i C U k t- P F A-377F SUFERVibrw : wa e* I P C T E A L ltvFSTICATCC

• PHAli k.

TEnh1 hat 10t DATE : 06/do/P5 Cllh AEF T YEAR P OP' l H TC PATE uTIFCT $1aFF EFr uGI :

(S3F SlAFF >< U h I F h ) 70 7.10 UlbrCT SalAR1Fs : 3,4"4 25,701.

FAlFdIAL K StrVICr3 9. 9.

ADF bl1PF OR T : 4 4 bijt C G A T C 4 CTS : O. C.

TPAVEl. EXPEASF5 : 9. O.

INCIFFCT EA PTOSES : 1,470 13,4?C.

GFhFnAL 6 AOF Tid. : 2,16d. 21,$63.

TOTAL CCdTS : 7,105, 71,207.

FENCENTA6F Cf AVAIL FLLCS SPEMT : 9et (FY 64 CARRYUbtR + FY e t F U t. 0 S NECEIVEC TO DATE)

)

Flin01hG ST ATUS :

FY 1924 Fy 19.j c cgpapcypp py go o 5 Fuht,$ FY I S P S F t r.D ING CARdVCVEk FuhJ18.C LtVLL GtC*n TC UAIF dAL. PEFUED (1 k1 (: Al f4 h) (! K1

40. 34  ? <s . O.

o

• • . )

l FEE RECOVERY COST STATUS FIh8 A-3778 TITLE: REVIEh 0F PRA FOR SEABHOOK NPP PEH100: FEBRUARY 1985 3 $ FY85 TASK /PLAhi PERICD CUMULATIVE

-A SEABROOK 00CKET 50-443 7,107. 71,209 TOTALS : 7,107. 71,209 4

- ~ . . , ,. , , - , , . - - -- - , - .