ML17263A923
| ML17263A923 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/31/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9502080252 | |
| Download: ML17263A923 (5) | |
Text
I RIC)RITY (ACCELERATED RIDS PROCESSIX~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9502080252 DOC.DATE: 95/01/31 NOTARIZED: NO DOCKET FACIL: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 JOHNSON,A.R.
Project Directorate I-3 (PDl-3)
(Post 941001)
P 0
05000244 R
SUBJECT:
Discusses 950117 meeting w/NRC re TS improvement program for plant. Consensus reached between RG&E
& NRC that improved TS LAR will be submitted by RG&E in May 1995.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE-TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: FILE CENTER 031
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1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 11 ENCL 10
AND ROCHESTER GASANDE'LECTRTC CORPORATTON
~ 89 EASTArrENUE, ROCHESTER, N.Y. 14649.0001 ARFA CODE716 5'-2700 ROBERT C. MECREDY Vice President NUcleor Opefotions January 31, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Technical Specification Improvement Program for Ginna Station R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
On January 17, 1995, several members of Rochester Gas and Electric (George
- Wrobel, Mark Flaherty, and Bob Mecredy) met with the Nuclear Regulatory Commission staff (Walt Butler, Chris Grimes, James
- Cutchin, and Al Johnson) concerning the Technical Specification Improvement Program (TSIP) for Ginna Station.
The purpose of this meeting was to provide the staff with a status of the TSIP and to discuss the schedule for NRC approval of, and RG&E implementation of, the Improved Technical Specifications (ITS).
RG&E and the NRC reached consensus that the ITS license amendment request (LAR) will be submitted by RG&E in May 1995.
The NRC agreed that. a final SER would be prepared in October 1995 with the LAR being approved by November.
This schedule is necessary for RG&E licensed personnel to begin training on the ITS in October to support an implementation date of February 1996.
This implementation date is directly tied to the acceptance of new fuel with higher enrichment limits that is being used to convert to 18 month cycles beginning in 1996.
The failure to meet this schedule will directly result in the generation of redundant LARs necessary to support continued economic operation of Ginna Station.
This will tax both RG&E and NRC resources.
RG&E also presented concerns related to the ability to meet the schedule due to NRC review of other ongoing large-scale programs at Ginna Station (i.e.,
conversion to 18 month cycles and steam generator replacement) and the delays associated with the previously submitted Administrative Controls LAR.
The staff assured RG&E that they would allocate the necessary resources to support our schedule and recognized the Administrative Control LAR delays.
However, the staff also noted that the most recent full conversions to ITS have been approved by the NRC after only 6
months of internal review.
In addition, if the schedule appears to be slipping, RG&E should enumerate their concerns to NRC management (e.g. Associate Director for Projects).
'st502080252 9'50i3i PDR ADOCK 05000244 p
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In order to support meeting the above defined schedule, the NRC requested that RG&E provide the following as soon as they become available:
a)
The new analysis supporting the storage of higher enriched fuel.
The supporting TS changes do not have to be submitted along with the analysis since any necessary changes can be addressed in the May 1995 LAR.
b)
Identify the items to be relocated to the Core Operating Limits Reports (COLR) and the Pressure Temperature Limits Report (PTLR) and the methodology that will be used for these relocated items.
The meeting concluded with a
request by Mr.
Grimes that the Westinghouse plants converting to ITS come forward as one group as soon as possible to discuss proposed changes to NUREG-1431.
Mr.
Grimes indicated that changes can still be requested by RGGE on a plant-specific basis; however, it is the best use of NRC and industry resources to address issues which are generic to Westinghouse plants at the same time.
Very truly yours, Robert C. Mecredy MDF/716 xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
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