ML17325B430

Special Rept:On 900129,0202,08 & 15,four Fire Suppression Components Inoperable Longer than Allowed by Tech Spec 3.7.10.Fire Door 391 Declared Inoperable Due to Door Being Removed for Replacement.Fire Watch Maintained

ML17325B430
Person / Time
Site:	Cook
Issue date:	03/08/1990
From:	Blind A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Davis A NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003220062
Download: ML17325B430 (4)

Text

ACCELERATED DLUBUTION DEMO TION SYSTEM REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9003220062 DOC.DATE: 90/03/08 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald.C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Special rept:on 900129,0202,08 & 15,fire suppression components inoperable longer than allowed by TS 3.7.10.

DISTRIBUTXON CODE: IE22D 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 E CL ID CODE/NAME LTTR E CL PD3-1 LA 1 PD3-1 PD 1 GIITTER,J. 1 INTERNAL: ACNW AEOD/DOA AEOD/DSP/TPAB AEOD/ROAB/DSP DEDRO NRR/DET/ECMB 9H NRR/DET/EMEB9H3 NRR/DET/ESGB 8D NRR/DLPQ/LHFB11 NRR/DLPQ/LPEB10 NRR/DOEA/OEAB11 NRR/DREP/PRPB11 NRR/DST/SELB 8D NRR/DST/SICB 7E NR 8D1 NRR/DST/SRXB 8E R FWL RES/DSIR/EIB RGN3 FILE 01 EXTERNAL: EG&G WILLIAMS,S 4 L ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSIC MAYS,G 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASIH CONTACT THE.DOCUMENI'ONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 35 ENCL 35

Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458 Bridgman, Ml 49106 616 465 5901 INDIANA NICHIGAN POWM March 8, 1990 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 United States Nuclear Regulatory Commission Document Control One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Attn: A.B. Davis

Dear Mr. Davis:

This special report is being submitted in accordance with Technical Specification 3.7.10 action a, to inform you that the following four fire suppression components have been inoperable longer than allowed by Technical Specification 3.7.10 action a.

Fire detection in the Unit Two CD Emergency Diesel Generator Room was declared inoperable on January 29, 1990 due to a failed circuit board in the A.C.

inverter which supplies the detection circuit.

Replacement parts for the inverter are no longer available. A plant modification has been initiated to replace the old inverter with an available equivalent circuit. It is anticipated that the plant modification will be'ompleted and the detection restored to operability by April 24, 1990.

A fire watch, as required by Technical Specification 3.7.10 action a, will be maintained while the fire detection is inoperable.

lj) Fire Door 391 was declared inoperable on February 2, mU 1990 due to the door being removed for replacement.

(ci(QA

-OL Rc It was restored to operability on February 15, 1990. A fire watch, as required by Technical GG au~~

gwG Specification 3.7.10 action a, was maintained while the door was inoperable.

GQ GI-I Fire Dampers 1-HV-AC-FD-l, 1-HV-AC-FD-2, 1-HV-AC-FD-3, iNK 2-HV-AC-FD-1, 2-HV-AC-FD-2, and 2-HV-AC-FD-3,

('s located in the Unit One and Unit Two P-250 Computer GK op Rooms were declared inoperable on February 8, 1990 o.k0) when they failed to automatically close during 0

U.S. Nuclea gulatory Commission March 8, 199 Page 2 of 2 surveillance testing. An engineering evaluation is being performed to determine the reason for the failures and,the proper repairs or replacements, necessary. We will inform you via a follow up if report when the engineering evaluation is complete and the dampers have been restored to operability.

A fire watch, as required by Technical Specification 3.7.10 action a, is being maintained while the dampers are inoperable.

Fire Damper 1-HV-AQT-W2, located in the Unit One Reactor Cable Tunnel Quadrant 2 was declared inoperable on February 15, 1990 when it failed to fully close during a surveillance test. Repair activities on the damper have been temporarily suspended due to the inaccessability of the damper operating mechanism. A plant modification has been initiated to install a service port on the ventilation ductwork associated with the damper to allow repair activities to continue. We will inform you through a follow-up report when the plant modification is complete and the damper has been declared operable.

The damper will be maintained in a closed position until repair activities have been completed.

Sincerely, A.A. Blind Plant Manager AAB:clw Attachment CC: D.H. Williams, Jr.

A.B. Davis, Region M.P. Alexich III P.A. Barrett J.E. Borggren R.F. Kroeger NRC Resident Inspector J.G. Giitter, NRC R.C. Callen G. Charnoff, Esq.

Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau