ML17331B418

LER 94-002-00:on 940430,fire Watch Tour Was Omitted Due to Personnel Error.Revised Policy for Implementing Fire Watch tour.W/940531 Ltr

ML17331B418
Person / Time
Site:	Cook
Issue date:	05/31/1994
From:	Blind A, Hodge W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-002-01, LER-94-2-1, NUDOCS 9406100001
Download: ML17331B418 (5)

Text

DOCUMENT DISTRIBUTION SYSTEM Cc ACCELERATE REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9406100001 DOC.DATE: 94/05/31 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION HODGE,W.M. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION D

SUBJECT:

LER 94-002-00:on 940430,fire watch tour was omitted due to personnel error. Revised policy for implementing fire watch tour.W/940531 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 D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HICKMAN,J 1 1 D

INTERNAL: AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 NRR/J3SSA/SPLB 1 1 NRR/DSSA/SRXB 1 1

~'EG FILE 02 1 1 RES/DSIR/EIB 1 1 RGN ILE 01 1 1 EXTERNAL EGGG BRYCE i J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 NSIC MURPHY,G.A 1 1 NSIC POOREiW 1 1 NUDOCS FULL TXT 1 1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

Indiana Michigan Power Gontpany

~

Cook Nuclear Plant One Cook Place Bridgrnan, Mi 49106 616 465 5901 May 31, 1994 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-74 Docket No. 50-316 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort S stem the following report is being submitted:

94-002-00 Sincerely,

.'. Blind Plant Manager

/sb c'.

Attachment B. Martin, Region E. E. Fitzpatrick P. A. Barrett III R. F. Kroeger M. A. Bailey - Ft. Wayne NRC Resident Inspector J. B. Hickman NRC J. R. Padgett G. Charnoff, Esq.

D. Hahn INPO S. J. Brewer 9406100001 940531 PDR ADOCK 05000316 S PDR

NRC FORM 366 .S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 (5.92) EXPIRES 5/31/95 I ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENTBRANCH (MNBB 77I4), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555400 I, AND TO THE PAPERWORK REDUCTlON PROJECT (3(504)104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACIUTY NAME (I) DOCKET NUMBER (2) PAGE (3)

D. C. COOK NUCLEAR PLANT UNIT 2 05000 316 1 OF 3 TITLE (4)

FIRE WATCH TOUR OMITTED DUE TO PERSONNEL ERROR EVENT DATE 5 LER NUMBER 6 REPORT NUMBER 7 OTHER FACILITIES INVOLVED 8 FACIUTY NAME DOCKET NUMBER SEOUENTIAL REVISION MONTH DAY YEAR MONTH OAY NUMBER NUMBER '05000 FACIUTYNAME DOCKET NUMBER 04 30 94 94 002 00 05 31 94 05000 OPERATING THIS REPORT IS SUBMITTED PURSUA NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or m ore 11 MODE (9) 20.402(b) 20.405(c) 50.73(a) (2) (iv) 73.71(b)

POWER 20.405(a) (1) (i) 50.36(c) (1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 063 20.405(a) (1) (ii) 50.36(c) (2) 50.73(a)(2)(vii) OTHER 20.405(a) (1) (iii) 50.73(a) (2) (i) 50.73(a) (2) (viii)(A) (Speci ty in Abetract below and in Text, NRC 20.405(a) (1) (iv) 50.73(a) (2) (ii) 50.73(a) (2) (viii)(B) Form 366A) 20.405(a) (1) (v) 50.73(a) (2) (iii) 50.73(a) (2) (x)

LICENSEE CONTACT FOR THIS LER 12 NAME TELEPHONE NUMBER Bndude Area Code)

W. M. HODGE PLANT PROTECTION SUPERINTENDENT 616-465-5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE REPORfABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS To NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXP FCTE0 MONTH DAY YEAR YES SUBMISSION (tt yea, complete EXPECTED SUBMISSION DATE) DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single. spaced typewritten lines) (16)

On 01<<21-94 at 1015,.Fire Door 2-DR-AUX344 for the 609'levation (elev.) of the Turbine (Tur.) Building (Bldg.) was declared inoperable (which rendered the CO, suppression system for Fire Zones 46A, 46B 46C and 46D inoperable).

Technical Specifications (TS) 3.7.9.3 and 3.7.10 required Action items were established. On 04-29>>94 at 2308 an hourly FW toured the above described area. A shift turnover occurred at 2315 in which the tour point was omitted from the newly created tour sheet. The TS (3.7.9.3 and 3.7.10) required tour di.d not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30-94 at 0030. The FW Supervisor recognized that the TS 3.7.9.3 and 3.7.10 action statements were not being met and contacted FW personnel and had the tour point added to the tour. A tour of the area was conducted on 04-30-94 at 0037. The U-2 4Kv CO2 system for Fire Zones (FZ) 46Ae 46Be 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minutes.

The poli.cy for implementing fire watch tour sheets has been revised to require a review and then an independent review prior to use. This event was discussed and reviewed with the personnel involved.

NRC FORM 366 (5.92)

NRC FORM 36SA U.S. NUCLEAR REGULATORY CON(MISSION (669) APPROVED 0MB NO. 3)50010E EXPIRES: 4/30)92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50A) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTIN UATION AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3(504(04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACIMTY NAME ()) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVNION NUM ER NUM ER D. C. COOK NUCLEAR PLANT UNIT 2 p p p p p3 16 94 0 0 2 0 002 OF 0 3 TEXT lllnord PlMcr llPNFdmd. N)P Addi5oeel llRC Fdm) JSSA'sl (I7) escri t o of Event On 01-21-94 at 1015, Fire Door 2-DR<<AUX344 (EIIS/NM-DR) for the 609'levation (elev.) of the Turbine (Tur.) Building (Bldg.) was declared inoperable(this door was inoperable because the area's ventilation system has made impossible for the door to completely close). This door also made the CO2 system for the lower elev. of the 4Kv room inoperable (FZs 46A, 46B, 46C and 46D). The CO2 system was not designed to allow for perimeter leakage of this magnitude 12'~ 120sq ft.) to effectively extinguish the, fire. A roving fire watch (10'y (FW) patrol was established to tour the affected fire zones and Fire Door 2-DR-AUX344 as required by Technical Specifications (TS) 3.7.9.3 and 3.7.10 (U-

2) ~

On 04-29-94 at 2308 a FW toured the above described area. A shift turnover occurred in which the tour point was omitted from the newly created tour sheet. The TS (3.7.9.3 and 3.7.10) required tour did not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30>>94 at 0030. The FW Supervisor recognized that the TS action statements were not being met and contacted FW personnel and had the tour point added to the tour.

A tour of the area was conducted on 04-30-94 at 0037.

Cause of Event The cause of this event was personnel error. The involved FW Supervisor failed to review the FW tour sheets upon completion, prior to the tours being conducted. This review would have identified all tour points were not incorporated onto the tour sheets for the shift.

Anal sis of Event The TS 3.7.9.3 action statement for an inoperable required CO2 system requires that "...within 1 hour: 1) verify at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.8, and establish a fire watch patrol to inspect the affected area once per hour, or 2) Establish a continuous fire watch to patrol the affected area."

The TS 3.7.10 action statement for an inoperable fire rated assembly requires that "... within 1 hour: 1) verify that the fire detectors and/or fire suppression system on at least one side of the inoperable assembly are OPERABLE and establish an hourly fire watch patrol, or 2) establish a continuous fire watch patrol on one side of the penetration...".

Failure to maintain an hourly FW patrol was .a violation of TS 3.7.9.3 and 3.7.10 and is reportable under 10 CFR 50.73(a)(2)(i)(B).

NRC Fotm 366A (669)

NRC FORM355A US. NUCLEAR REGULATORY COMMISSION 0 .

APPROVED OMS NO, 31500104

)589)

ESTIMATED 8URDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDLNG 8URDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT 8RANCH IP.530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 30555, AND TO THE PAPERWORK REDUCTION PROJECT )31500104). OFFICE OF MANAGEMENTANO 8UDGET, WASHINGTON, DC 30503.

FACILITYNAME I'l DOCKET NUMSER ll) LER NUMEER LEI ~ AGE 131 YEAR ,'OYI; 55QUENTIAL:,YS +EV~S~ON HUM ER 7>> HUM PA D. C. COOK NUCLEAR PLANT o s o o o 3 1 6 94 00 2 0 0 0 3 OF 0 3 TEXT Ill)tuup Forcp*)FFuuyd, u>> aAse'cd l JYAC Ann 35848) )3) na sis of Eve t co 'd The U-2 4Kv CO3 system for FZs 46A, 46B, 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW patrol for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minutes. The analysis of this event concludes that in the unlikely event of a fire, personnel would have been promptly aware of its presence and would have extinguished the fire without significant spreading of the fire or equipment damage. This conclusion is based on the following:

The detection for FZs 46A, 46B, 46C and 46D were in an operable state, in the event of a fire, the detectors would have alarmed in the U-2 Control Room, which is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, this alarming condition would have been investigated and the appropriate Fire Brigade resources would have been'ispatched to mitigate the fire.

Although an hourly FW patrol was not conducted for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minute period, it is concluded that the alarms/detection associated with affected fire zones would have allowed timely identification of a fire. Therefore, this event is not considered'o have created a significant safety concern, nor did it create a significant hazard to the health and safety of the general public.

Corrective Actions When the FW Supervisor was made aware of the omission of the tour point, the tour point was added and the affected area/equipment immediately toured for compliance with TS 3.7.9.3 and 3.7.10.

2 ~ This event was discussed with the involved personnel. The personnel are fully aware of the TS 3.7.9.3 and 3.7.10 requirements of an hourly FW patrol for an inoperable CO3 system and fire rated assembly, respectively.

3. Prior issuing Fire Watch tours sheets for implementation, they are now reviewed and independently reviewed to ensure accuracy.'revious Similar Events None NRC F one 355A (589)