ML17250B145

Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed

ML17250B145
Person / Time
Site:	Ginna
Issue date:	04/06/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson Office of Nuclear Reactor Regulation
References
NUDOCS 9004230251
Download: ML17250B145 (5)

Text

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ACCESSION NBR:9004230251 DOC.DATE: 90/04/06 NOTARIZED: NO DOCKET N FACIL:50-24$ Robert Emmet Ginna Nuclear Plant, Unit I, Rocheeter G 05000244, AUTH. NAME MECREDY,B..C.

'UTHOR AFFILIATION Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3

SUBJECT:

Discusses impact of SER issuance for inservice insp &

inservice testing programs. R DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR i ENCL 0. SIZE: I TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code D

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 8

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f zi zi zzzrzzz ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N K 14649 0001 April 6, 1990 TELEPHONE AREA CODE Tld 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Impact of SER Issuance for Inservice Inspection and Inservice Testing Programs R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

RG&E and the NRC have been discussing several relief requests associated with our submittal of the 1990-1999 Inservice Inspection and Inservice Testing Program intervals. Our understanding is that the NRC's Safety Evaluation Reports on these submittals are scheduled for the latter portion of April 1990.

This timing will not affect RG&E's implementation plans for these programs, except in two instances, as explained below:

1. Pum and Valve (IST) Pro ram RG&E submitted relief requests VR-8 and VR-9. by letter dated February 15, 1990 in order to extend the time between disassembly inspections. Based on NRC/contractor reviews, has been determined that an extended interval is reasonable, it although the exact duration has not yet been agreed upon.

Therefore, RG&E will not perform any disassembly of check valves 842A and B, or 867 A and B, during the 1990 refueling outage.

2. Inservice Ins ection (ISI) Pro ram RG&E submitted relief request No. 4 regarding Reactor Coolant Pump volumetric and visual examinations. Conversations to date with the NRC and contractors has indicated substantial agreement with the alternative examination methods provided, in the relief request. These alternative methods will be implemented during the 1990 refueling outage.

Very truly yours, p~psp251 gp p500pp>+<

pppb'DOCK Robert C.

Division Me re Manager Nuclear Production I n/0.

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xc: Mr. Allen R. Johnson (Mail Stop 14Dl)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector