ML17261A830
| ML17261A830 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/23/1989 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 GL-88-11, NUDOCS 8902020286 | |
| Download: ML17261A830 (5) | |
Text
D1S1 8 UTION DEMONSTREl 4
SYH'EM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 8902020286 DOC. DATE: 89/01/23 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION STAHLE,C.
NRC No Detailed AffiliationGiven
SUBJECT:
Responds to Generic Ltr 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Matls...."
DISTRIBUTION CODE: A008D, COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: Reactor Vessel Material Surveillan e
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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05000244 Report 05000244~
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 January 23, 1989 TCLCpHONL Asc* coor. vis 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Response to Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant.Operations" R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
~
Generic Letter 88-11 required each licensee to submit the results of a
technical analysis relative to the implementation of Revision 2 to Regulatory Guide 1.99.
A technical analysis has been completed for R.ED Ginna by Westinghouse.
The results of the analysis for the most limiting material are presented on Table 1.
The Adjusted Reference Temperature (ART) is calculated for 11 EFPY and 20 EFPY using Revision 2 to Regulatory Guide 1.99.
The ART is compared to the total RT calculated using Revision 1 to Regulatory Guide 1.99 at 21 EFPY.
The total RT at 21 EFPY is the basis for the current heatup and cooldown pressure/temperature limits in the Ginna Technical Specifications.
The calculated ART for the most l'imiting material at the 1/4 T (wall thickness) and 3/4 T locations using Revision 2 to Regulatory Guide 1.99, would exceed the respective reference temperature values that were used to generate the current 21 EFPY heatup and cooldown P/T limits in Technical Specifications.
In
- addition, the calculated ART for this material at present life (13.8 EFPY) would also exceed the respective values that form the basis for the current P/T limits.
RGt'E is 'presently evaluating potential changes to operating procedures equipment setpoints, and hardware which would provide consistency with Regulatory Guide 1.99, Rev.
2.
The type and extent of changes at Ginna Station will be evaluated for feasibility and cost-effectiveness, and implemented. to the extent considered appropriate, within the three year time period suggested in the Regulatory Guide.
Very truly yours, 8902020286 890128 PDR ADOCK 05000244 PDt":
Robert C. Mecredy General Manager Nuclear Production
RWZ>013 Attachments xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
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TABLE 1 COMPARISON OF MOST LIMITINGART AND RT~
11 EFPY
~14 T
~34 T 20 EFPY
~14 T
~34 T Rev.
2 to Regulatory Guide 1.99 ART Rev.
1 to Regulatory Guide 1.99 RT 187 154.6 207.7 175 177c 132' The current Ginna heatup and cooldown pressure/temperature limits are based upon these RT, values for 21 EFPY.