ML17264A871

Provides 30-day Response to GL-97-01, Degradation of Control Rod Drive Mechanism Nozzles & Other Vessel Closure Head Penetrations. W/Nei Memo Re Assistance for Response

ML17264A871
Person / Time
Site:	Ginna
Issue date:	05/01/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-01, GL-97-1, NUDOCS 9705070009
Download: ML17264A871 (6)

Text

CATEGORY REGULAT INFORMATION DISTRlBUTION ZSTEM (RIDS)

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ACCESSION,'BR:9705070009 DOC.DATE: 97/05/01 NOTARIZED: NO -DOCKET ¹ FACIE:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECR'-'DY,R.C. Rochester Gas & Electric Corp.

RECEP.NAME RECIPIENT AFFILIATiON VISSINGiG.

SUBJECT:

Provides 30-day response to GL-97-01, "Degradation of Control Rod Drive Mechanism Nozzles & Other Vessel Closure Head Penetrations." W/NEI memo re assistance for response.

DISTRIBUTION CODE: A075D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: GL-97-01 Degraduation of Control Rod Drive Mechanism & Other Vessel NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E

REClPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LA/DRPE/PDl-1 1 1 PD1-1 PD 1 1 PDl-1/HAROLDiJ 1 0 VISSING,G. 1 1 INTERNA CENTER Ol 1 1 NRR/DE/EMCB 3 3 RES EMMEB 1 1 RGN M 1 1 EXTERNAL: NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10

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Q.'r AND ROCHESTER GAS AND EIECTRIC CORPORATION ~ 89 FASTAVENUE, ROCHESTER, N.Y. IrIQ9-0001 ARFA CODE716 5'-2700 ROBERT C. MECREDY Vice President Nvciear Operations May 1, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

30-day Response to Generic Letter 97-01, "Degradation of Control Rod Drive Mechanism Nozzles and Other Vessel Closure Heat Penetrations" R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

The purpose of this letter is to provide the 30-day response to Generic Letter 97-01, "Degradation of Control Rod Drive Mechanism Nozzles and Other Vessel Closure Head Penetrations." As requested, RG&E does intend to respond, within 120 days, relative to items 1 and 2 of the "Requested Information" section of the subject generic letter. This response will incorporate recommendations of the Westinghouse Owner's Group and other cognizant technical organizations, and proposed actions will be coordinated within a broad industry effort by the Nuclear Energy Institute.

Very truly yours, Robert C. Mecred GJW/459 xc: Mr. 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 060128 llllllllllllllllllllllllllllllllllllllll 9705070009 97050i PDR ADQCK 05000244 P PDR

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'B~E~RRD~A~D P<E April21, 1997 TO: NN Administrative Points Of Contact 808 JECT: Generic Letter (GL} 97-0l, Degradation of Control Rod Drive Mechanism ¹~e and Other Vessel Closure Head Penetratiom:

his i foxxn tian is Lg Aires to the re uired on e. Ple a

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1997 res ense

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anb,'at an w'tb i x ate indivi8ua

-~da ar Our April 16, 1997, letter to the NEI Nuclear Strategic Issues Advisory Committee (NSIAC) recommended. that licensees ym'vide'a 30-day GL response that aHows for maximum Qexibility in the 120-day response. VFe suggested a short resyonse t,hat addresses the two questions required to be answered: (1} whether or not tho requested. information willbe provided, and. (2) whether or not the requested information wiH be subnut ted vrithia. the requested time period.

In a conference call last week with NBI, the PWR Ovrners Group Chairmen requested that we provide liccnseeN explicit wording for use in their QO-day responses. The foHowing wording is suggested:

"[The licensee nameldocket number] w9l submit a written rosponso to the NRC by July 30, L3S7, relative to Items 1 and, 2 of the Begnested Information sac{ion j

of Generic Le tter 97-01, Degradation o Control 2hd Briue Necltanism and Other Vessel Closes Head Penetrations."

¹ lc The NSIAC latter focUsed on 1{em I of the Requested Tnformation section, primary water stress corrosion of the head penetration~. philo iL only brieQy mentioned Item 2, rosin bead. intrusion, our efforts are intended. to develop a coordinated.

industry response for both Items 1 and 2.

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NEI Administrative Points of Contact Ap'iil 21, 1997 Page 2 Hyoid have questions concerning this recommendation, cease contact Kurt Cozens at {202) 739-80SFi or by e-mail at 3cocnei.org.

Sincerely, David, J. Modeen KOC/dp c: NEI Alloy 600 Task Force PIER Garners Group Chairmen

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