ML17251A236
| ML17251A236 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/19/1988 |
| From: | Rich Smith ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17251A237 | List: |
| References | |
| NUDOCS 8809010061 | |
| Download: ML17251A236 (2) | |
Text
ACCESSION NBR:8809010061 DOC.DATE: 88/08/19 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION SMITHiR. E.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION 6'TAHLE,CD PWR Project Directorate 1
SUBJECT:
Forwards revised rept re steam generator hydraulic snubber replacement program.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR i ENCL
/
SIZE:
g TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 8
RECIPIENT ID CODE/NAME PD1-3 LA STAHLEiC INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NUDOCS-ABSTRACT 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL "5
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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N. Y. 14649-0001 ROBERT E, SMITH Vice President Production and Eng1neering August 19, 1988 TELEPHONE AitEACQQEvte 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Steam Generator Snubber Replacement R.E.
Ginna Nuclear Power Plant Docket No. 50-244
References:
- 1. Meeting Summary, dated July 29, 1988 from Carl Stahle (USNRC)
- 2. Application for Amendment attached to a letter dated May 13, 1988 from B.A. Snow (RG&E)
Dear Mr. Stahle:
Reference 1
summarized the results of a
meeting held July 20, 1988 to discuss Rochester Gas Electric Corporation's Application in Reference 2 concerning the steam generator snubber replacement program.
Although technical understanding of the program was achieved at the
- meeting, RG&E was requested to document additional information discussed at that meeting.
Enclosed is a revised
- report, Steam Generator Hydraulic Snubber Replacement
- Program, Revision 3,
which contains the additional information concerning the two analysis cases performed for 'the reactor coolant loop in the hot condition and the analysis performed for the cold condition.
Very truly you bert E.
mith'nclosure xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Prr0
~
88090i006i 8808i9 PDR ADOCN, 05000244, P
PNU