ML17264A735
| ML17264A735 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/15/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-20, TAC-M74414, NUDOCS 9611220058 | |
| Download: ML17264A735 (5) | |
Text
.CATEGORY 1
REGULAT(
INFORMATION DISTRIBUTIONSTEM (RIDE)
I ACCESI'ON NBR:9611220058 DOC.DATE: 96/ll/15 NOTARIZED: NO DOCKET FACIE:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISS ING F G. S.
SUBJECT:
Notifies NRC that responses to request for addi info will be delayed until 970115,per GL 88-20.
DISTRIBUTION CODE: A011D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Generic Ltr 88-20 re Individual Plant Evaluations NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 T
E RECIPIENT ID CODE/NAME PD1-1 PD INTERNA 8USTO LE CENTER 0
DM'ECB RES/DST/IPEEE RGN 1
RGN 3
COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME VISSINGFG.
AEOD/SPD/RRAB NRR/DRPE/PD1-3 NRR/DSSA/SPSB RES/PRAB RGN 2
RGN 4
COPIES LTTR ENCL 0
EXTERNAL: LITCO-BRYCE,J.
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E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL
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AND ROCHES1ER GASANDEtECTRIC CORPORAT1ON
~ 89 EASTAVENUE, ROCHESTER, MY. 146d9-0001 AREA CODE716 5'-270O ROBERT C. MECREDY Vice President Nvcfeor operations November 15, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Generic Letter 88-20, Updated Response to Request for Additional Information (TACNo. M74414)
Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
(a)
Letter from A.R. Johnson, NRC, to R.C. Mecredy, RG&E,
Subject:
Ginna ProbabilislicRiskAssessnrent Project Report ofMarch 15, 1994, to the NRC in Response to Generic Letter No. 88-20; Request forAdditionalInformation (TACNo. M74414), dated February 23, 1996.
(b)
Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Generic Letter 88-20, Response to Request for Additional Information (TAC No.
M74414), dated April 19, 1996.
(c)
Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,
Subject:
Generic Letter 88-20, Updated Response to Request forAdditionalInformation (TAC No. M74414), dated July 31, 1996.
Dear Mr. Vissing,
By Reference (a), the NRC forwarded a request for additional information (RA1) related to the RG&E submittal ofa Level IIProbabilistic Safety Assessment (PSA) for Ginna Station per Generic Letter 88-20. The RAIasked for a written response to the NRC questions within 60 days ofreceipt ofthe letter. By Reference (b), RG&E indicated that the response to Enclosures 1 (Level 1) and 2 (Human Reliability Analysis) would be provided to the NRC by July 31, 1996 and the response to (Level 2) would be provided by November 15, 1996.
Subsequent to this, RG&E notified the NRC that responses to all three enclosures willbe delayed until November 15, 1996 (Ref. (c)).
pg(t 0
96ii220058, 96iii5 PDR ADQCK 05000244 P
PDR The purpose ofthis letter is to notify the NRC that responses to all three enclosures willbe delayed until January 15, 1997. As indicated in Reference (b), RG8cE has elected to re-perform the Level 2PSA ofGinna Station. RGB has made substantial progress has been made in re-performing the Level 1 evaluation and is in the final stages ofreleasing the study for internal review. An outside consultant has also been retained to review the document for completeness.
Following these reviews, RGB willsubmit a revised Level 1 PSA for Ginna Station which specifically addresses Enclosures 1 and 2 ofthe February 23, 1996 RAI. A response willalso be provided for the Level 2 questions (i.e., Enclosure 3) with a revised Level 2 evaluation to be submitted by May 1, 1997.
RG8'cE has made substantial changes to the previously submitted PSA in order to remove unnecessary conservatism, and to reflect conversion to 18 month fuel cycles and implementation ofimproved technical specifications which significantly affected surveillance testing intervals and allowed equipment outage times. In addition, all NRC comments provided in the RAI were specifically incorporated into the new analysis.
The implementation ofthese changes has proved to be more difficultthan originally forecasted.
Preliminary results indicate a much different risk profile due to these changes which has required additional verification in order to confirm. Itis also noted that a design flaw with respect to the PORVs and their DC electrical power supply was recently identified by the revised PSA and subsequently corrected during an unrelated forced outage.
RG8cE is confident that the revised PSA more accurately reflects the current risk profile of Ginna Station and willbe ofgreater use for other areas (e.g., support ofthe Maintenance Rule).
As such, RGkE willrespond to the February 23, 1996 RAI by January 15, 1996 with a revised Level 2 evaluation provided by May 1, 1997. Ifyou have any further questions or comments, please contact George Wrobel, Manager ofNuclear Safety and Licensing, at (716) 724-8070.
Very truly yours,
+Wc~-y Robert C. Mecredy MDF>885 xc:
U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector
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