ML17251B065: Difference between revisions
StriderTol (talk | contribs) Created page by program invented by StriderTol |
StriderTol (talk | contribs) Created page by program invented by StriderTol |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:REQULATO" INFORMATION DISTRIBUTION | {{#Wiki_filter:REQULATO" INFORMATION DISTRIBUTION | ||
'STEM(RIDS)ACCESSION | 'STEM (RIDS)ACCESSION/BR 88050402b0 DOC.DATE: 88/04/26 NOTARIZED: | ||
/ | NO DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Plant.Unit ii Rochester G 05000244 AUTH.NAME.AUTHOR AFFILIATION SNOMi B.A.'ochester Gas 5 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION STAHLEe C.NRC-No Detailed*ffiliation Given | ||
==SUBJECT:== | ==SUBJECT:== | ||
Responds to 870820 SER re performance testing of plant safety h Y elief valves.Util agrees to develop 5 implement procedures def ining timing Sc extent of required insps i4~maint.per NUREQ-0737 Item II.D.1 requirements. | |||
DISTRIBUTION CODE: | DISTRIBUTION CODE: A047D COPIES RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal: | ||
Inservice inspection/Testing/Relief from ASME Code NOTES: License Exp date in accordance eith 10CFR2i 2.109(9/19/72). | |||
Inservice inspection/Testing/Relief | 05000244 REC IP IENT ID CODE/NAME PDi-3 L*STAHLE>C COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD COPIES LTTR ENCL INTERNAL:*EOD/DOA*RM/DAF/LFMB NRR/DEST/MTB 9H OGC 15-B-18 RES/DE/EIB 1 1 1*EOD/DSP/TPAB NRR/DEST/MEB 9H NRR P AS/ILRB12 01 EXTERNAL: EQhQ ROCKHOLD>H NL 007 HEMMING NSIC LPDR NRC PDR TOTAL NUMBER OF COP IES REQUIRED: LTTR 21 ENCL | ||
~r I iiiiiiiiiiiiii ruirZZ gill 0 If A%Iiiiii Ii ZSirs(ZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, M K 14649.0001 April 26, 1988 TELEPHONC ALLA cooL 7ie 546.2700 U.S.Nuclear Regulatory Commission Document, Control Desk Attn: Mr.Carl'Stahle PWR Project Directorate No.1 Nashington, D.C.20555 | |||
*EOD/DOA*RM/DAF/LFMB NRR/DEST/MTB | |||
~ | |||
==Subject:== | ==Subject:== | ||
.Inspection | .Inspection and Maintenance of Safety Valves R.E.Ginna Nuclear Power Plant Docket No.50-244 | ||
== | ==Dear Mr.Stahle:== | ||
This letter is in response to the NRC's August 20, 1987 SER from Carl Stahle to Roger Kober, concerning performance testing of the Ginna safety and relief valves.In that SER, the NRC requested, that RG&E.commit to perform inspection and maintenance, as required to ensure the subsequent reliable operation of the safety valves,-following a safety valve lift which involves a loop seal or water discharge. | |||
RGGE agrees to develop and implement procedures defining the timing and extent of the required inspections and maintenance. | |||
These procedures will be developed during 1988, and implemented following the 1989 refueling outage.Based on this commitment, the requirements of NUREG-0737 Item II.D.l can be considered fully implemented, and this issue can be closed.Very truly yours, asoso402+sooo24e eoo26 ma~oo" Foe P Bruce A.Snow Superintendent Nuclear Production | |||
~q(6 g n'I ot~lg}} | |||
~q( | |||
Revision as of 14:43, 7 July 2018
| ML17251B065 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/26/1988 |
| From: | SNOW B A ROCHESTER GAS & ELECTRIC CORP. |
| To: | STAHLE C NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8805040260 | |
| Download: ML17251B065 (4) | |
Text
REQULATO" INFORMATION DISTRIBUTION
'STEM (RIDS)ACCESSION/BR 88050402b0 DOC.DATE: 88/04/26 NOTARIZED:
NO DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Plant.Unit ii Rochester G 05000244 AUTH.NAME.AUTHOR AFFILIATION SNOMi B.A.'ochester Gas 5 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION STAHLEe C.NRC-No Detailed*ffiliation Given
SUBJECT:
Responds to 870820 SER re performance testing of plant safety h Y elief valves.Util agrees to develop 5 implement procedures def ining timing Sc extent of required insps i4~maint.per NUREQ-0737 Item II.D.1 requirements.
DISTRIBUTION CODE: A047D COPIES RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal:
Inservice inspection/Testing/Relief from ASME Code NOTES: License Exp date in accordance eith 10CFR2i 2.109(9/19/72).
05000244 REC IP IENT ID CODE/NAME PDi-3 L*STAHLE>C COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD COPIES LTTR ENCL INTERNAL:*EOD/DOA*RM/DAF/LFMB NRR/DEST/MTB 9H OGC 15-B-18 RES/DE/EIB 1 1 1*EOD/DSP/TPAB NRR/DEST/MEB 9H NRR P AS/ILRB12 01 EXTERNAL: EQhQ ROCKHOLD>H NL 007 HEMMING NSIC LPDR NRC PDR TOTAL NUMBER OF COP IES REQUIRED: LTTR 21 ENCL
~r I iiiiiiiiiiiiii ruirZZ gill 0 If A%Iiiiii Ii ZSirs(ZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, M K 14649.0001 April 26, 1988 TELEPHONC ALLA cooL 7ie 546.2700 U.S.Nuclear Regulatory Commission Document, Control Desk Attn: Mr.Carl'Stahle PWR Project Directorate No.1 Nashington, D.C.20555
Subject:
.Inspection and Maintenance of Safety Valves R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Stahle:
This letter is in response to the NRC's August 20, 1987 SER from Carl Stahle to Roger Kober, concerning performance testing of the Ginna safety and relief valves.In that SER, the NRC requested, that RG&E.commit to perform inspection and maintenance, as required to ensure the subsequent reliable operation of the safety valves,-following a safety valve lift which involves a loop seal or water discharge.
RGGE agrees to develop and implement procedures defining the timing and extent of the required inspections and maintenance.
These procedures will be developed during 1988, and implemented following the 1989 refueling outage.Based on this commitment, the requirements of NUREG-0737 Item II.D.l can be considered fully implemented, and this issue can be closed.Very truly yours, asoso402+sooo24e eoo26 ma~oo" Foe P Bruce A.Snow Superintendent Nuclear Production
~q(6 g n'I ot~lg