ML17251B065: Difference between revisions

From kanterella
Jump to navigation Jump to search
Created page by program invented by StriderTol
StriderTol Bot change
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REQULATO"   INFORMATION DISTRIBUTION       'STEM (RIDS)
{{#Wiki_filter:REQULATO" INFORMATION DISTRIBUTION
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.
'STEM (RIDS)
RECIP. NAME
ACCESSION /BR 88050402b0 DOC. DATE: 88/04/26 NOTARIZED:
                  'ochester         Gas 5 Electric Corp.
NO DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Plant.
RECIPIENT AFFILIATION STAHLEe C.             NRC No Detailed *ffiliation Given
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 *ffiliationGiven


==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~
Responds to 870820 SER re performance testing of plant safety h
maint. per NUREQ-0737 Item     II. D. 1 requirements.
Y elief valves. Util agrees to develop 5 implement procedures def ining timing Sc extent of required insps i4~
DISTRIBUTION CODE: A047D         COPIES RECEIVED: LTR       ENCL     SIZE:
maint. per NUREQ-0737 Item II. D. 1 requirements.
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       COPIES            RECIPIENT          COPIES ID CODE/NAME         LTTR ENCL         ID CODE/NAME       LTTR ENCL PDi-3 L*                              PD1-3 PD STAHLE> C INTERNAL: *EOD/DOA                                 *EOD/DSP/TPAB
DISTRIBUTION CODE:
            *RM/DAF/LFMB               1          NRR/DEST/MEB 9H NRR/DEST/MTB 9H           1          NRR P  AS/ILRB12 OGC   15-B-18                                         01 RES/DE/EIB                 1 EXTERNAL: EQhQ ROCKHOLD> H                         LPDR NL 007 HEMMING                         NRC PDR NSIC TOTAL NUMBER OF COP IES REQUIRED: LTTR             21   ENCL
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
~ r I


iiiiiiiiiiiiii ruirZZ                                                                     gill 0 If A%
iiiiiiiiiiiiii ruirZZ gill 0 IfA%
Iiiiii   Ii   ZSirs(ZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, M K 14649.0001 TELEPHONC ALLA cooL 7ie 546.2700 April 26,  1988 U.S. Nuclear Regulatory Commission Document,                   Control Desk Attn: Mr. Carl'Stahle PWR Project Directorate       No. 1 Nashington, D.C.                         20555
Iiiiii Ii ZSirs(ZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, MK 14649.0001 April 26, 1988 TELEPHONC ALLAcooL 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:==
==Subject:==
                    .Inspection and Maintenance of Safety Valves R.E. Ginna Nuclear Power Plant Docket No. 50-244
.Inspection and Maintenance of Safety Valves R.E. Ginna Nuclear Power Plant Docket No. 50-244


==Dear Mr. Stahle:==
==Dear Mr. Stahle:==
 
This letter is in response to the NRC's August 20, 1987 SER from Carl Stahle to Roger
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 which involves a loop seal or water discharge.
: Kober, concerning performance testing of the Ginna safety and relief valves.
lift 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.
In that
Based on       this   commitment, the requirements of NUREG-0737 Item II.D.l can be considered                           fully implemented, and this issue can be closed.
: 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.
Very truly yours, Bruce A. Snow Superintendent                                 q(6 Nuclear Production                      n'I ~
RGGE agrees to develop and implement procedures defining the timing and extent of the required inspections and maintenance.
g ot~
These procedures will be developed during 1988, and implemented following the 1989 refueling outage.
asoso402+        eoo26                                    lg ma ~oo      "    sooo24e Foe P}}
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}}

Latest revision as of 11:37, 8 January 2025

Responds to 870820 SER Re Performance Testing of Plant Safety & Relief Valves.Util Agrees to Develop & Implement Procedures Defining Timing & Extent of Required Insps & Maint,Per NUREG-0737,Item II.D.1 Requirements
ML17251B065
Person / Time
Site: Ginna 
Issue date: 04/26/1988
From: Snow B
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 *ffiliationGiven

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 IfA%

Iiiiii Ii ZSirs(ZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, MK 14649.0001 April 26, 1988 TELEPHONC ALLAcooL 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