ML17264A834
| ML17264A834 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| 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.
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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
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1 NRC PDR D
E NOTE TO ALL "RIDS" RECIPIENTS:
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CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
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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
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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
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