ML17264A452
| ML17264A452 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/19/1996 |
| From: | Mercredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-20, TAC-M74414, NUDOCS 9604250104 | |
| Download: ML17264A452 (5) | |
Text
CATEGORY j.
REGULATO INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR!9604250104 DOC.DATE: 96/04/19 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MERCREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Document Control Branch (Document Control Desk)
SUBJECT:
Responds to request for addi info re GL 88-20:level 2
probabilistic risk assessment.
DISTRIBUTION CODE:
A011D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Generic Ltr 88-20 re Individual Plant Evaluations A
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
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0 TOTAL NUMBER OF COPIEB REQUIRED:
LTTR 25 ENCL
AND ROCHESTER GASANDELECIICCORPORATION ~ 89 EASTAYENUE, ROCHESTER, N. Y Id6d9 000I AREA CODE7I6 5'-2700 ROBERT C. MECREOY Vice President Nuclear Operations April 19, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C. 20555
Subject:
Generic Letter 88-20, Response to Request for Additional Information (TAC No.
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 Probabilistic RiskAssessment 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:
Level 2 Probabilisti c Risk Assessment, dated March 10, 1995.
Dear Mr. Johnson,
By Reference (a), the NRC forwarded a request for additional information (RAI) related to the RG&E submittal ofa Level IIProbabilistic Safety Assessment (PSA) for Ginna Station per Generic Letter 88-20. The RAI asked for a written response to the NRC questions within 60 days ofreceipt ofthe letter. This letter provides RG&E's response to the RAI.
Since the submittal ofthe Ginna Station PSA in 1994, RG&;E has made, and is making, significant changes to the plant, particularly during the 1996 Refueling Outage.
These changes include steam generator replacement, conversion to improved standard technical specifications (including the associated surveillance testing interval changes), reduction in Tand a change from an 12 month to 18 month fuel cycle. RG&E has also developed additional insights into the PSA via a detailed review and evaluation as aresultof adding additional members to the PSA staff (see Ref. (b)). This has resulted in the development of several improvements to the PSA models in addition to the physical plant changes discussed above.
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P As such, the PSA re-evaluation ofGinna Station has been delayed beyond our original projections.
AllPSA efforts are now being directed towards supporting implementation ofthe Maintenance Rule as required by July 10, 1996. Attempting to respond to the RAI at this time would be detrimental to providing this necessary support. In addition, attempting to quantify the impact of several issues as requested by the staff in Reference (a) would not be in the best interest of the NRC or RGkE since the fault tree models have undergone significant revision since the 1994 submittal. Therefore, RGB'roposes the followingwith respect to responding to the RAI:
a.
Asummary report ofthe new Level I PSA for Ginna Station willbe submitted to the NRC by July 31, 1996. This report willaddress those questions contained in Enclosures 1 (Level
- 1) and 2 (Human Reliability Analysis) to Reference (a).
b.
Asummary report ofthe new Level 11 PSA for Ginna Station willbe submitted to the NRC by November 15, 1996. This report willaddress those questions contained in Enclosure 3 (Level 2) to Reference (a).
Ifyou have any further questions or comments, please contact George Wrobel, Manager ofNuclear Safety and Licensing, at (716) 724-8070.
Very truly yours, Robert C. Mecredy xc:
U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)
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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