ML17254A315
| ML17254A315 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/04/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8504090311 | |
| Download: ML17254A315 (4) | |
Text
REGULA'TORY FORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR 850009031 1
DOC ~ DATE ~ 85/04/04 NOTARIZED NO DOCKET ¹ FACIL:50"244 Robert Emmet Ginna Nuclear Planti Unit ii Rochester G.
05000244 AUTH'AME AUTHOR AFFILIATION KOBERE R N ~
Rochester Gas 8 Electric Corp'EC IP ~ NAME RECIPIENT AFFILIATION Z'LtllOLINSKIE J A
Operating Reactors Branch 5
SUBJECT:
Responds to request to address sensitivity studies on axial power profiles in Exxon Nuclear Co ECCS evaluation models for 10X10 fuel, Analysis of fuel will be performed w/models that conform to 10CFR50 L App K, DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR j ENCL SIZE: J TITLE:
OR Submittal:
General Distribution NOTEStNRR/DL/SEP
- 1cy, OL; 09/19/69 05000244 REC IP IENT ID CODE/NAME NRR ORB5 BC 01 INTERNAL; ACRS 09 ELD/HOSP NRR/DL D IR NRR/DL/TSRG NRR/DSI/RAB RGN1 EXTERNAL: EGSG BRUSKEES NRC PDR 02 NOTES:
COPIES LTTR ENCL 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB NRR/D TB LPDR NSIC 03 05 COPIES LTTR ENCL' 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 28 ENCL
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/$5FIE I E($II$IS La v oeiba AHD Eiggyg IIIIIII StAVe ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER VKE PRESIDENT ELECTRIC &STEAM PIVODVCTION Tel.EPHONE AREA CODE Tld 546-2700 April 4I 1985 Director of Nuclear Reactor Regulation Attention:
Nr. John A. Zwolinskii Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washingtoni D.C.
20555
Subject:
Loss of Coolant Accident Analysis R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Zwolinski:
This letter is in response to a request from the NRC staff to address sensitivity studies on axial power profiles in the Exxon Nuclear Company (ENC) emergency core cooling system evaluation models for the 14xl4 ENC fuel in Ginna.
It is our understanding that analyses performed by ENC on a foreign plant show that the calculated peak clad temperature (PCT) for ENC fuel is within +
50 F of that for similar Westinghouse fuel.
The PCT calculated by 0
Westinghouse for Westinghouse fuel in Ginna is 1854 FI as reported in our submittal of December 20I 1983.
Application of a 50 F
0 increment to this yields 1904 g.
This leaves substantial margins 0
to the 10 CFR 50 limit of 2200 F.
Thus>
any additional uncertainties are not critical to compliance with the 10 CFR 50 limit for continued operation at full power.
We commit to have performedi and to submit to you within six monthsi analyses for ENC fuel in Ginna which are performed with evaluation models which are wholly in conformance with 10 CFR 50 and Appendix K to 10 CFR 50.
Very truly yours>
Roger W. Kober 85p4p903li Bgpypp tI ADQCII 050000dd P
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