ML17256A955
| ML17256A955 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/20/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17256A956 | List: |
| References | |
| 81-022-01T-0, 81-22-1T, NUDOCS 8205250151 | |
| Download: ML17256A955 (4) | |
Text
REGULATORY
'FORMATION DISTRIBUTION SY M (RIDS)
AOCE'SSION NBR:8205250151 DOC ~ DATE: 82/05/20 NOTARIZED:
NO DOCKET FACIL:50-204 Robert Emmet Ginna Nuclear Planti Unit lE Rochester G
05000244
'AUTH BYNAME AUTHOR AFFILIATION MAIEREJ ~ E ~
Rochester Gas L Electric Corp'R EiC IP ~ NAME RECIPIENT AFFILIATION ORUTCHFIELDED ~
Oper ating Reactor s Branch 5.
SUBJECT:
For wards "RE Ginna Revised LOCA ECCS Analyses for Nominal 8
Reduced Temp 8 Pressure Operation
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A0300 COPIES RECEIVED ILTR 'NCL I'IZE:,
TITLE: Asymmetric LOCA Loads (USI A-2)
NOTES:NRR/DL/SEP icy'50002LIO REC IP IENT ID CODE/NAME ORB 05 BC 01 INTERVAL: ELD/HDSA 13 NRR/DL/ORAB 08 SB 09 REG F IL 04 COPIES LTTR ENCL 7
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1 1
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1 RECIPIENT ID CODE/NAME NRR SHEAEJ 12 NRR/DSI/CPB 12 NRR/DST/GIB 07 RGN1 COPIES LTTR ENCL 1
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1 EXTERNAL: ACRS 11 NRC PDR 02 NTIS NOTES'-
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1 LPDR NSIC 03 05
'TOTAL NUMBER OF COPIES REQUIRED:
L'TTR 30 ENCL 30
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I ZZetn IIIIIIIIIIII Sl I I(IIII/Sl'OCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 55S'I 5 JOHN E, MAIER Vice President ccccpHONc Anc+ cooc 7is 546-2700 May 20, 1982 t
Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief
,Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington,- D.CD 20555
Subject:
LER 81-022/OIT-O, Error Discovered in the Transient or Accident Analysis R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
LER 81-022 was transmitted to IEE by letter dated January 4,
1982 from John E. Maier to Ronald C. Haynes.
The LER stated that an analysis of the loss of coolant accident would be performed prior, to the start-up of cycle XII to determine the effect of the revised fan cooler capacity.
The analysis has been completed and 10 copies of the resulting report are enclosed.
The revised analysis was done for normal reactor coolant system temperature and pressure and reduced temperature and pressure.
The reduced temperature and pressure case will be the subject of a future submittal and should be disregarded by the Staff at this time.
The revised analysis at normal temperature and pressure demonstrates a small change in PCT as a result of the revised fan cooler capacity.
Very truly yours, J
n E. Maier 8205250151 820520
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