ML17264A468
| ML17264A468 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 05/08/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A469 | List: |
| References | |
| NUDOCS 9605100236 | |
| Download: ML17264A468 (4) | |
Text
CATEGORY 1.
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!i, REGULA(I INFORMATION DISTRIBUTION SYSTEM (RIDE)
ACCESSION NBR:9605100236 DOC.DATE: 96/05/08 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 a Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
SUBJECT:
Forwards application for amend to license 6 TS,correcting tpposo DISTRIBUTION CODE:
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E NOTE TO ALL NRIDSH RECIPIENTS PLEASE HELP US TO REDUCE WASTE!
CONTACT TIE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
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O AND ROCHESTER GASANDEIECTRIC CORPORATION ~ 89 FASTAVENUE, ROCHESTER, N. Y I/6/9-0001 ARFA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvdeor Operations May 8, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C. 20555
'ubject:
Application for Amendment to Facility Operating License Correction ofTypographical Errors Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing,
On February 24, 1996, RG&E implemented the Improved Technical Specifications (ITS) at Ginna Station per Amendment No. 61. Since that time, several typographical errors have been discovered withinthe ITS. In general, these errors are minor and are readily apparent.
However, several errors could lead to confusion and a potential incorrect application of a requirement.
Therefore, the purpose ofthis license amendment request (LAR)is to correct these typographical errors.
Currently, Ginna Station is in a defueled condition while in the performance of a steam generator replacement project.
The most limitingerror which requires correction applies in MODES 1 and
- 2. Consequently, RG&E requests NRC consideration of this LARin order to support a planned entry into MODE 2 on June 2, 1996. Upon NRC approval, the LARshould be considered effective immediately and implemented within 7 days.
Very truly yours, Robert C. Mecredy MDF~t844 Attachments eeaeta023e e6aeae fi PDR ADOCK 05000244' PDRJI eh
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U.S. Nuclear Regulatory Commission Mr. Guy 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