ML17256A541
| ML17256A541 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/04/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17256A542 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8303110316 | |
| Download: ML17256A541 (5) | |
Text
REGULATORY FORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR;8303110316 DOC,DATE: 83/03/04 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emme,t Ginna Nuclear Planti Unit 1r Rochester G
05000244
'AUTH,NAME AUTHOR AFFILIATION MAIERgJ,Ei
'Rochester Gas L Electric Corp.
RHC IP, NAME RECIPIENT AFF IL'IATION ORUTCHF IELDi D ~
Operating Reactor s Branch 5
SUBJECT:
Forwards,"Pl')R Safety 8 Relief Valve Adequacy Rept/,
,"Pressurizer Safety Relief Line Evaluation Summary Rept'"
-per 821202 commi.tment.Valves will operate under design operatin'g condition TMI Item II.D.i requirements complete.
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DISTRIBUTION ~CODE' A046S
>COPIES 'RECEIVED LTR,
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OR Submittal';
TMI Action Plan 'Rgmt NUREG 0737 8"NUREG 0660 NOTES:NRR/DL/SEP 1cy ~
05000244 RECIPIENT ID 'CODE/NAME NRR ORB5 "BC Ol
<<COPIES L,TTR ENCL 7
F7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNAL: ELD/HDS4 IE/DEP =EPDS NRR.PAWLSONzN ~
NRR/DL DIR 14 NRR/DL/ADSA 17 NRR/DSI/ADRS 27 NRR/DS I/AS8 NRR/DST DIR 30 RGN1 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 IE/DEP D IR 33 IE/DEP/EPLB NRR/DHFS/DEPY29 NRR/DL/ADL 16 NRR/DL/ORAB 18 NRR/DSI/AEB RAB REG FIL 04 1
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1
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1 1
1 3
1 1
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1 EXTERNAL: ACRS LPDR NSIC NOTES:
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1 05.
1 1
INPOiJ ~ STARNES NRC 'PDR 02 NTIS "TOTAL NUMBER OF COPIES REQUIRED'TTR 44 ENCL
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ e9 EAST AVENUE, ROCHESTER, N.Y. I4649 JOHN E. MAIER Vice President TCLCPHO>C AREA coDK Tie 546-2700 March 4, 1983 Director of Nu clear Reactor Regu lat ion Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Post-TMI Requirements, NUREG 07 37, ITEM II.D.1 R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
Our letter dated December 2,
1982 committed to provide evaluations to verify the operability of the Ginna press-urizer safety and relief valves under all design operating conditions.
This included the effects of the discharge p ip ing on the valves.
The two reports
- enclosed, "Pressu rizer Safety and Relief Valve Adequacy Report" and "Pressurizer Safety and Relief Line Evaluation Summary Report", provide the evaluations.
These reports should complete the action items required by NUREG 0737, Item II.D.l.
The reports conclude that the Ginna valves will operate under all design operating conditions.
One item, verifica-tion,of proper ring setting by the manufacturer, remains to be completed for the safety valves.
Also,'t should be noted that the piping report includes a section of pipe which does not effect operability of the valves.
Three supports on this section are being modified as part of a general program to upgrade p ip ing at Ginna.
Very truly yours, Joh E. Maier 8303ii03ib 830304; PDR ADOCK 05000244 P,....
PDR.
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