ML17264A834: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:CATEGORY 1 REGULATO      INFORMATION DISTRIBUTION          TEM  (RIDS)
{{#Wiki_filter:CATEGORY 1
I ACCESSION NBR:9703250218          DOC.'DATE: 97/03/18      NOTARIZED: NO          DOCKET FACIAL:50-,244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester              G 05000244 AUTH. NAME          AUTHOR AFFILIATION MECREDY,R.C.        Rochester Gas    !'lectric    Corp.
RECIP.NAME          RECIPIENT AFFILIATION VISSING,G.


==SUBJECT:==
==SUBJECT:==
Informs of intention to change reactor coolant pump flywheel insp interval from current 3-yr interval to 10-yr interval, consistent   w/WCAP-14535A.
Informs of intention to change reactor coolant pump flywheel insp interval from current 3-yr interval to 10-yr interval, consistent w/WCAP-14535A.
DISTRIBUTION CODE: A001D TITLE:  OR COPIES RECEIVED:LTR Submittal: General Distribution i ENCL Q   SIZE:
DISTRIBUTION CODE:
T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).                 05000244 E RECIPIENT           COPIES            RECIPIENT           COP1ES ID CODE/NAME          LTTR ENCL        ID CODE/NAME         LTTR ENCL PD1-1 LA                             PDl-1 PD VISSING,G.
A001D COPIES RECEIVED:LTR i
INTERNAL          CENTE     0                     NRR/DE/ECGB/A NRR'E/EMCB                            NRR/DRCH/HICB NRR/DSSA/SPLB                        NRR/DSSA/SRXB NUDOCS-ABSTRACT                      OGC/HDS3 EXTERNAL: NOAC                         1   1     NRC PDR D
ENCL Q SIZE:
E NOTE TO ALL "RIDS" RECIPIENTS:
TITLE: OR Submittal:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
General Distribution T
TOTAL NUMBER OF COPIES REQUIRED: LTTR             13   ENCL
05000244 E
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
I ACCESSION NBR:9703250218 DOC.'DATE: 97/03/18 NOTARIZED:
NO DOCKET FACIAL:50-,244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas !'lectric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
INTERNAL RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
CENTE 0
NRR'E/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL RECIPIENT ID CODE/NAME PDl-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COP1ES LTTR ENCL EXTERNAL: NOAC 1
1 NRC PDR D
E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL


AND ROCHESTER GAS AND ELECTRIC CORK)RATION ~ 89 EASTAYENUE, ROCHESTER N. Y IdiW9-0001                     AREA CODE716 Sd6-2700 ROBERT C. MECREDY Vice President                               March 18, 1997 Nvdear Operations U.S. Nuclear Regulatory Commission Document     Control Desk Attn:           Guy Vissing Project Directorate I-1 Washington, D.C.           20555
AND ROCHESTER GASANDELECTRICCORK)RATION ~ 89 EASTAYENUE, ROCHESTER N. Y IdiW9-0001 AREA CODE716 Sd6-2700 ROBERT C. MECREDY Vice President Nvdear Operations March 18, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555


==Subject:==
==Subject:==
Reactor Coolant Pump Flywheel Inspection                                     Interval       Change R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.:           WCAP-14535A,       "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination," dated November, 1996
Reactor Coolant Pump Flywheel Inspection Interval Change R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.:
WCAP-14535A, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination," dated
: November, 1996


==Dear Mr.     Vissing:==
==Dear Mr. Vissing:==
 
The purpose of this letter is to inform the NRC that Rochester Gas and Electric (RG&E) intends to change our reactor coolant pump (RCP) flywheel inspection interval from the current 3-year interval to a
The purpose of this letter is to inform the NRC that Rochester Gas and Electric (RG&E) intends to change our reactor coolant pump (RCP) flywheel inspection interval from the current 3-year interval to a 10-year interval.                     This change is consistent with the rationale discussed in the referenced WCAP (and the included NRC Safety Evaluation Report) as being in accordance with the criteria of Regulatory Guide 1.14.                   The inspection will consist of an Ultrasonic (UT) examination over the volume from the inner bore to the circle of one-half the outer radius or a surface examination (UT/PT) of exposed             surfaces defined by the volume of the disassembled flywheel as determined at the time of inspection.
10-year interval.
Based upon current plant schedules, the >>A>> RCP flywheel will be inspected in the 2003 plant refueling outage and the >>B>> RCP flywheel will be inspected in the 2005 plant refueling outage.
This change is consistent with the rationale discussed in the referenced WCAP (and the included NRC Safety Evaluation Report) as being in accordance with the criteria of Regulatory Guide 1.14.
In support of this change, as requested in the NRC's SER, RG&E has verified, through correspondence with the NSS vendor, that the Ginna RCP flywheels are made of SA533B materials.
The inspection will consist of an Ultrasonic (UT) examination over the volume from the inner bore to the circle of one-half the outer radius or a surface examination (UT/PT) of exposed surfaces defined by the volume of the disassembled flywheel as determined at the time of inspection.
Very     truly           yours, Robert C. Mecredy REJ/451 97OSaSoaaS       97OSX87 PDR       ADQCK 05000244
Based upon current plant schedules, the
              '"          PDR I
>>A>>
RCP flywheel will be inspected in the 2003 plant refueling outage and the
>>B>>
RCP flywheel will be inspected in the 2005 plant refueling outage.
In support of this change, as requested in the NRC's
: SER, RG&E has
: verified, through correspondence with the NSS vendor, that the Ginna RCP flywheels are made of SA533B materials.
Very truly yours, Robert C. Mecredy REJ/451 97OSaSoaaS 97OSX87 PDR ADQCK 05000244 PDR I
Illllllll1llll[llllljIlllllllllfl1HIIHlllll
Illllllll1llll[llllljIlllllllllfl1HIIHlllll


xc.'r. Guy Vissing (Mail Stop Project Directorate I-1 14B2)
xc.'r.
Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA   19406 Ginna Senior Resident Inspector
Guy Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector


C iC y}}
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Latest revision as of 09:49, 8 January 2025

Informs of Intention to Change Reactor Coolant Pump Flywheel Insp Interval from Current 3-yr Interval to 10-yr Interval, Consistent w/WCAP-14535A
ML17264A834
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/18/1997
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703250218
Download: ML17264A834 (4)


Text

CATEGORY 1

SUBJECT:

Informs of intention to change reactor coolant pump flywheel insp interval from current 3-yr interval to 10-yr interval, consistent w/WCAP-14535A.

DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR i

ENCL Q SIZE:

TITLE: OR Submittal:

General Distribution T

05000244 E

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

REGULATO INFORMATION DISTRIBUTION TEM (RIDS)

I ACCESSION NBR:9703250218 DOC.'DATE: 97/03/18 NOTARIZED:

NO DOCKET FACIAL:50-,244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas !'lectric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.

INTERNAL RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.

CENTE 0

NRR'E/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL RECIPIENT ID CODE/NAME PDl-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COP1ES LTTR ENCL EXTERNAL: NOAC 1

1 NRC PDR D

E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!

CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)

TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 13 ENCL

AND ROCHESTER GASANDELECTRICCORK)RATION ~ 89 EASTAYENUE, ROCHESTER N. Y IdiW9-0001 AREA CODE716 Sd6-2700 ROBERT C. MECREDY Vice President Nvdear Operations March 18, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy Vissing Project Directorate I-1 Washington, D.C.

20555

Subject:

Reactor Coolant Pump Flywheel Inspection Interval Change R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref.:

WCAP-14535A, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination," dated

November, 1996

Dear Mr. Vissing:

The purpose of this letter is to inform the NRC that Rochester Gas and Electric (RG&E) intends to change our reactor coolant pump (RCP) flywheel inspection interval from the current 3-year interval to a

10-year interval.

This change is consistent with the rationale discussed in the referenced WCAP (and the included NRC Safety Evaluation Report) as being in accordance with the criteria of Regulatory Guide 1.14.

The inspection will consist of an Ultrasonic (UT) examination over the volume from the inner bore to the circle of one-half the outer radius or a surface examination (UT/PT) of exposed surfaces defined by the volume of the disassembled flywheel as determined at the time of inspection.

Based upon current plant schedules, the

>>A>>

RCP flywheel will be inspected in the 2003 plant refueling outage and the

>>B>>

RCP flywheel will be inspected in the 2005 plant refueling outage.

In support of this change, as requested in the NRC's

SER, RG&E has
verified, through correspondence with the NSS vendor, that the Ginna RCP flywheels are made of SA533B materials.

Very truly yours, Robert C. Mecredy REJ/451 97OSaSoaaS 97OSX87 PDR ADQCK 05000244 PDR I

Illllllll1llll[llllljIlllllllllfl1HIIHlllll

xc.'r.

Guy Vissing (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

C iC y