ML17264A440

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Provides Clarification to Re Partial Response to NRC Bulletin 96-001, Control Rod Insertion Problems.:
ML17264A440
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/29/1996
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, NUDOCS 9604090082
Download: ML17264A440 (3)


Text

CATEGORY 1 4

REGULA'lY INPORNATION DI)TRIBUTION SYSTEN (RIDE) 5(CESSION NBR:9604090082 DOC.DAZE: 96/03/29 NOTARIZED: NO DOCKET FA(::L:50-244 Robert Emme" Ginna Nuclear Plant, Unit 1, Rochester G

05000244 A(tTH.NAME AUTHOR AFFIIIATION, MEQREDQ,R.C.

Rochester Gas s Electr ic Corp.

RECIP,NAME RECIPIENT AFFILiATION JOHNSON,A.R.

SUBJECT:

Provides clarification to 960328 ltr re partial response to NRC Bulletin 96-001, "Control Rod insertion Problems.:

DISTRIBUTION CODE:

IES7D COPIES RECEIVED:LTR L ENCL 6 SIZE:M TITL(: NpC Bulletin 96-01 Control Rod Insertion Problems NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

T 05000244 RECIPIENT ID CODE/NAME NRR/DRPW/PD4-2 PM/THOMAS,K INTERNAL: AEOD NRR/DSSA/SRXB EXTERNAL: NOAC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-1 PD I E CENTER 033 RES NRC PDR COPIES LTTR ENCL D

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TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED:

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4ND ROCHESTER GASANDElECTRIC CORPORATION

~ 89 EASTAYENUE, ROCHESTER, N. V Id6rI9-0001 AREA CODE716 54'6-2700 ROBERT C. MECREDY Vice President Nvctear Operations March 29,1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-1 Washington, D.C.

20555

Subject:

Response

to NRC Bulletin 96-01, "Control Rod Insertion Problems",

March 8, 1996 R.

E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

The purpose of this letter is to provide a clarification to our March 28, 1996 letter regarding our partial response to the subject Bulletin.

RG&E will not perform a reactor trip at the end of this operating cycle.

Ginna Station experienced a reactor trip on March 8,

1996.

Operator observation of the digital rod position indication system indicated that there were no control rod insertion problems during this trip.

Our operators were well aware of the issues at Wolf Creek and

South, Texas.

They had been notified of these events by a posting on the Plan of the Day as early as March 1, 1996.

We therefore do not consider that performing a reactor trip at the end of this fuel cycle will provide additional useful data.

Very truly yours, Robert C. Mecredy NRC55422

~ GAH xc:

Mr. Allen R. Johnson (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 US NRC Ginna Senior Resident Inspector J

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