ML17265A266
| ML17265A266 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/05/1998 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9805150006 | |
| Download: ML17265A266 (3) | |
Text
CATEGORY 1 REUULA1%Y INFORMATION DISTRIBUTIOSSYSTEM (RIDS)
ACCESSION NBR: 9805150006 DOC.DATE: 98/05/05 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION HIECRE3Y,R.,C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Informs that util anticipate completion
& delivery of fire IPEEE assessment by 980630
& requesting delivery date for internal flood IPEEE assessment be changed to 981231.
DISTRIBUTION CODE:
A011D COPIES RECEIVED:LTR j ENCL 0 SIZE:
TITLE: Generic Ltr 88-20 re Individual Plant Evaluations DOCKET 05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: ACRS OUSTON,M ILE CE DRPM/PECB RES/DST/IPEEE RGN 1 RGN 3 COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING,G.
AEOD/SPD/RRAB NRR/DRPE/PD1-3 NRR/DSSA/SPSB RES/PRAB RGN 2 RGN 4 COPIES LTTR ENCL EXTERNAL: LITCO-BRYCE,J.
NRC PDR NOAC D
C N
NOTE TO ALL URIDSU RECIPIENTS:
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LTTR 19 ENCL Q5
WNn ROCHESTER GASANDEIECWICCORPORATION e 89 FASTAVENUE, ROCHESTER, N. Y Id&f9-II
'i ROBERT C. MECREDY Vice President Nuclear Operations ARFA CODE716 5'-2700 May 5, 1998 U.S. Nuclear Regulatory Commission Document Control Desk ATTN: Guy S.Vissing Project Directorate I-1 Washington, DC 20555
Subject:
Ginna Station Internal Flood IPEEE RE Ginna Nuclear Power Plant Docket No. 50-224 Ref.
(a):
Letter from RC Mecredy (RG&E) to GS Vissing (NRC),
nGinna Station IPE/IPEEE,n dated May 1, 1997.
(b):
Letter from RC Mecredy (RG&E) to GS Vissing (NRC), "Generic Letter 88-20, Level-1 Probabilistic Safety Assessment (PSA),n dated January 15, 1997.
(c):
Letter from AR Johnson (NRC) to RC Mecredy (RG&E), "Ginna Probabilistic Risk Assessment Project Report of March 15, 1994, to the NRC in Response to Generic Letter 88-20; Request for Additional Information (TAC No. M74414),n dated April 19, 1996.
Dear Mr. Vissing:
By Reference (a), RG&E submitted a request to extend the delivery date for the Fire and Internal Flood IPEEE assessments in connection with the updated Level-1 Ginna PSA [Reference (b), in response to Reference (c)] to June 30, 1998.
We anticipate completion and delivery of the Fire IPEEE assessment by J'une 30, 1998.
However, while performing the Fire IPEEE assessment, RG&E determined that the component location and cable routing database assembled for this assessment would be more appropriate for the Internal Flood IPEEE assessment'as well, rather than the database currently in use.
The major difference involves the mapping of component locations and cable routes to a more precise plant-spatial database (the division of areas into map grid spaces).
The affect ofemploying this new mapping process has been improved definition of components and cables affected by external event and spatial interaction scenarios.
9805i50006 980505 PDR ADOCK 05000244 P
PDR p()y 4
c
'G8cE anticipates that use ofthis newly compiled database willproduce an Internal Flood IPEEE assessment that can be integrated into our recently installed On-line Risk Monitor. As such, it would be more meaningful with respect to planning maintenance activities than a stand-alone study. Also, the performance ofthe Fire IPEEE assessment using this new database has improved the identification and modeling of inadvertent fire suppression system activation, which willbe important to the Internal Flood analysis.
The Core Damage Frequency (CDF) for internal flooding contributed about 6% ofthe total Level-1 PSA CDF in our original assessment (5 x 10 /yr out of 8 x 10 /yr). We expect the Internal Flooding CDF, using the updated PSA model and new database, to also approximate that level of contribution.
Based on our experience performing the Fire IPEEE assessment, RGB'nticipates that the reanalysis of the Internal Flood IPEEE can be completed by December 31, 1998. We request that the delivery date for the Internal Flood IPEEE assessment be changed to December 31, 1998.
Please contact George Wrobel, Manager of Nuclear Safety and Licensing, at (716) 771-3535 if you have any questions.
Very truly yours, Robert C. Mecredy XC:
Mr. Guy S. Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, DC 20555 US Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector