ML17264A710
| ML17264A710 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/29/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A711 | List: |
| References | |
| NUDOCS 9610310096 | |
| Download: ML17264A710 (4) | |
Text
T 05000244 NOTES:License Exp date. in accordance with 10CFR2,2.109(9/19/72).
CATEGORY. 1 REGULATZ INFORMATION DZSTRZBUTIOALSTEM (RIDE)
(,ACCESSION NBR:9610310096 DOC.DATE: 96/10/29 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards application for amends to licenses DPR-18, requesting change to required actions of inoperable channels associated with feedwater pump.
DISTRIBUTION CODE:
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E NOTE TO ALL MRIDSM RECIPIENTS:
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ANn ROCHESTER GASANDElECTRIC CORPORATlON ~ 89 FASTAVENUE, ROCHESTER, N. Y 1ddd9-0001 ARFA CODE 716 6-27M ROBERT C. MECREDY Vice President Nvcleor Operations October 29, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Application for Amendment to Facility Operating License, Change to Required Actions for Inoperable Channels Associated With Auxiliary Feedwater Pump Actuation on Steam Generator Level - LowLow Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant
'ocket No. 50-244
References:
(a)
Letter from A.R. Johnson, NRC, to R.C. Mecredy, RG&E, Issuance of Amendment No. 61 to IracililyOperating License No. DPR-18, R.lr. Ginna Nuclear Popover Plant, dated February 13, 1996.
Dear Mr. Vissing,
By Reference (a), the NRC issued the Improved Technical Specifications (ITS) for Ginna Station.
Following implementation of the ITS, RG&E discovered an error with respect to Table 3.3.2-1, Function 6.c which references the incorrect Required Actionfor inoperable channels ofthe auxiliary feedwater pump actuation on Steam Generator Level - Low Low logic. The current Required Action is to restore the inoperable channel within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or initiate a plant shutdown to Mode 4.
The correct Required Action is to place the inoperable channel in "trip"within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or initiate a plant shutdown to Mode 4. The inoperable channel can then remain in trip indefinitely. As such, the purpose ofthis license amendment request (LAR) is to revise the specified required actions to be consistent withNUREG-1431 (which was the basis for Amendment No. 61). RG&E requests that upon NRC approval, this LARshould be effective immediately and implemented within 30 days.
Ve truly yours, Robert C. Mecre MDF$883 Attachments 9hi03i009h 9bi029 PDR ADOCK 05000244 P
PDR 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 Mr. F. WilliamValentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253