ML17333A610

LER 96-004-00:on 960922,Unit 1 Main Transformer Pressure Trip Signal Received.Caused by Confirmed Lighting Strike Occurred.Sudden Pressure Trip Relay Tested & Replaced. W/961022 Ltr

ML17333A610
Person / Time
Site:	Cook
Issue date:	10/22/1996
From:	Blind A, Finissi M AMERICAN ELECTRIC POWER CO., INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-004, LER-96-4, NUDOCS 9610280167
Download: ML17333A610 (5)

Text

~ CATEGORY REGULATORY INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION alBR:9610280167 DOC.DATE: 96/10/22 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION FINISSIIM. American Electric Power Co., Inc.

BLIND,A.A. American Electric Power Co., Inc.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 96-004-00:on 960922,main generator trip on main transformer sudden overpressure.Due to Lightning Strike causes reactor trip.SPT relay was tested & replaced.

W/961022 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 HICKMANiJ 1 1 INTERNAL: A SPA 2 2 AEOD/SPD/RRAB 2 2 CE E 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 D

EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEiJ H 1 1 NOAC MURPHYiG.A 1 1 NOAC POOREiW. 1 1 0 NRC PDR 1 1 NUDOCS FULL TXT 1 1 E

N 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 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25

American Electri rer Cook Nuclear Plant One Cook Place Bndgman. Ml 49106 616 465 5901 AMERICAN ELECTRIC POMfER October 22, 1996 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:

96-004-00 Sincerely, A. A. Blind Site Vice President Imbd Attachment A. B. Beach, Region III E. E. Fitzpatrick P. A. Barrett S. J. Brewer J. R. Padgett D. Hahn Records Center, INPO NRC Resident Inspector 9hi0280i67 9hi022 PDR ADQCK 050003i5 S PDR

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NRC FORM 366A S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THI INFORMATIOH COLLECTION REQUEST: 50.0 HRS. FORWAR LICENSEE EVENT CONTINUATION COMHENTS REGARDING BURDEN ESTIHATE TO TH IHFORMATION AND RECORDS HANAGEMENT BRAHCH (HNB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWOR REDUCTION PROJECT (3150 0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

YEAR SEQUENTIAL REVISION Cook Nuclear Plant - Unit 1 50415 3OF3 TEXT (lr vore space Is required, use addIrIonal NRc Form 366A'si (17)

This event is being reported in accordance with 10CFR50.73(a)(2)(iv), as any event or condition that results in a manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). The RPS signal was in response to a turbine trip signal, which originated with the Main Transformer Sudden Pressure Trip relay signal.

Normal offsite power was available, the CD Emergency Diesel Generator was in standby and the AB EDG was running unloaded. No safety equipment was out of service prior to the trip. After the reactor trip, all safety systems operated normally in response to the trip signal and all post reactor trip responses were normal. This event was evaluated and determined to have no actual or potential adverse effect on the health and safety of the public.

Corrective Actions The SPT relay was tested and replaced due to inconsistent performance. The balance of the SPT relay circuitry was tested and found to be satisfactory. Transformer oil sample analysis was performed and verified that the SPT signal was spurious.

Failed Com onen Identification Not Applicable revious Similar Events None