ML17332B000

LER 95-007-00:on 950912,required Hourly Firewatch Tour for Unit 2 4 Kv Switchgear Complex Not Completed.Caused by Personnel Error.Shift Security Supervisor Directed to Include Active Fire Watch tours.W/951025 Ltr

ML17332B000
Person / Time
Site:	Cook
Issue date:	10/25/1995
From:	Blind A, Hodge W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-95-007-01, LER-95-7-1, NUDOCS 9511010278
Download: ML17332B000 (5)

Text

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(ACCELERATED RZDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9511010278 . DOC.DATE: 95/10/25 NOTARIZED- NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 P AUTH. NAME AUTHOR AFFILIATION HODGE,W. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 95-007-00:on 950912,reguired hourly firewatch tour for Unit 2 4 kV switchqear complex not completed. Caused by 0 personnel error.She.ft security supervisor directed to 1nclude active fire watch tours.W/951025 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 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNA EOD/~W

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/ B 2 1

2 1

AEOD/SPD/RRAB NRR/DE/ECGB 1

1 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/SPSB/B 1 1 NRR/DSSA/SRXB 1 ~ 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHY,G.A 1 ~ 1 NOAC POORE,W. 1 1 NRC PDR 1. 1 NUDOCS FULL TXT 1 1 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED.'ULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 INDIANA NICHIGAN POWER October 25, 1995 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 the following report is being submitted:

95-007-00 Sincerely, A. A. Blind Plant Manager

/clc Attachment c: H. J. Miller, Region E. E. Fitzpatrick III P. A. Barrett R. F. Kroeger M. A. Bailey - Ft. Wayne S. J. Brewer M. R. Padgett G. Charnoff, Esq.

D. Hahn Records Center, INPO NRC Resident Inspector

~QGt".t B,i 95iiOi0278 'P5i025 PDR ADOCK 050003ib 8 PDR

NRC FORM 366 .S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5.92)

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH TH!S INFORMATION COLLECTION REOUEST: 50.0 HRS, LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEtt ESTIMATE TO THE INFORMATICN FORWARD AND RECORDS MANAGEMENT BRANCH (MiVBB 2214), U,S, NUCLEAR REGULATORY COMMISSION. WASHINGTON, Oc 205554XXII, AND TO THE PAPERWORK REDUCTION PROJECT (315(hot04), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAhlE (I) DOCKET NUMBER (2) PAGE (2)

Oonald C. Cook Nuclear Plant - Unit 2 05000 316 1 OF TITLE (4)

Firewatch Tour Not Conducted Due To Personnel Error EVENT DATE 5 LER NUMBER 6 REPORT NUMBER 7 OTHER FACILITIES INVOLVED 8 SEOUENTIAL REVISION FACIUTY NAME DOCKET NUMBER MoiVTH DAY YEAR YEAR MONTH DAY YEAR NuhIBER NUMBER Cook Unit 1 05000 315 FACIUTY NAME DOCKET NUMBER 09 12 95 95 007 00 10 25 95 05000 OPERATING THIS REPORT IS SUBMITTED PURSUA NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or more 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) 20.405(a) (I ) (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) isoeorty In AbelraCt below and In Text, NRC 20.405(a) (1) (iv) 50.73(a) (2) (ii) 50.73(a)(2) (viii)(8) 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 (Include Area Code)

W. Hodge, Plant Protection Superintendent 616/465-5901 x3370 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT REPORTABLE REPCRTABLE MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH Dr Y YEAR YES SUBMISSION tlt yea, comntete EXPECTED SUBMISSION DATE) No X DATE (15)

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

On September 12, 1995, with Unit 2 in Mode 1 at 7 percent rated thermal power, the required hourly firewatch tour for the Unit Two 4Kv Switchgear Complex was not completed. This tour had been established in support of equivalent shutdown capability for Appendix R on August 24, 1995. It was determined that from 0510 to 0713 hours0.00825 days <br />0.198 hours <br />0.00118 weeks <br />2.712965e-4 months <br /> no firewatch tour was conducted for the area. As this time period of 123 minutes is in excess of the required hourly tour, the Technical Specification Action Statement was not met. On September 27, 1995 this event was determined to be reportable in accordance with 10CFR50.73(a)(2) I(B), as operation prohibited by Technical Specifications.

This event is attributable to personnel error. A failure to communicate information needed to perform the required tour was identified. The Shift Security Supervisor was directed to include active fire watch tours in the pre-shift briefings. Previously tracked separately, Appendix R tours have been added to the normal fire watch tours and programmed into the hand carried electronic wand system used by firewatch personnel.

In the event of a fire in this area, the fire detection system in the complex, which was operable, would have alarmed in the Control Room. The switchgear complex is protected by a manually operated low pressure CO, fire suppression system and has low combustible loading. Based on this, it is concluded that this event did not constitute a significant hazard to the health and safety of the general public.

NRC FORM 366 15.921

NRC FORMSSEA US, NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO. 31500)04 (689)

ESTIMATED BURDEN PER RESPONSE TO COMPLY,WTH THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50,0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE To THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P.530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND To THE PAPERWORK REDUCTION PROJECT 1315041041, OFFICE OF MANAGEMENTAND BUDGET,WASHINGTON. OC 20503.

FACILITY NAME (1) DOCKET NUMBER 12) LER NUMBER (61 PAGE (3)

"EA" Rar SEQUENTIAL REVISION NUMBER NUMEER Donald C. Cook Nuclear Plant - Unit TEXT llfmoro JPEOO JJ rOOviiod, Pro oddrtioool HRC Form 36643) nT) 2 osooo316 9 5 0 0 7 0 0 0 2 OF 0 3 Conditions Prior to vent Unit 1 in Mode 6, defueled Unit 2 in Mode 1 at 7 percent rated thermal power esc 'ion 0 Eve On September 12, 1995, with Unit 2 in Mode 1 at 7 percent rated thermal power, the required hourly firewatch tour for the Unit Two 4Kv Switchgear Complex was not completed. This tour had been established in support of equivalent shutdown capability for Appendix R on August 24, 1995.

As required by Technical Specifications (TS) 3.1.2.3 and 3.7.1.2, equivalent shutdown capability had been established upon the planned removal from service of the support capability of Unit One Reactivity Control (CVCS) systems and AuxiliaiyFeedwater (AFW) systems, on August 24, 1995, and September 8, 1995, respectively. This shutdown capability requirement was accomplished by verifying the operability of the fire detectors in the affected Unit Two areas and establishing an hourly fire watch patrol.

The Unit Two 4Kv Switchgear Complex, as part ofthe Appendix R tour, was required to be toured on an hourly basis. It was determined that on September 12, 1995, from 0510 to 0713 hours0.00825 days <br />0.198 hours <br />0.00118 weeks <br />2.712965e-4 months <br /> no firewatch tour was conducted for the area. As this time period of 123 minutes is in excess of the required hourly tour, the Technical Specification Action Statement was not met.

Cause Of Ev This event is attributable to personnel error. A failure to communicate information needed to perform the required tour was identified. Contributing to this event was the practice of tracking Appendix R tours separately from other required tours.

This event is being reported in accordance with 10CFR50.73(a)(2)(B) as operation prohibited by the plant's Technical Specifications. Technical Specifications 3.1.2.3 and 3.7.1.2 action statements for loss of Unit 1 shutdown support capabilities for the Reactivity Control System/Charging Pumps (CVCS) and Auxiliary Feedwater Systems (AFW) requires equivalent shutdown capability be provided in Unit 2. Failure to conduct the hourly fire watch patrol in the Unit 24Kv Switchgear Complex was determined to be reportable under the provisions of 10CFR50.73 on September 27, 1995.

NRC Form 366A (689)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (669) APPROVED OMB No. 31500)OS ESTIMATED BURDEN PER RESPONSE To COMPLY WTH THIS LICENSEE EVENT REPORT ILERI INFORMATION COLLECTION REQUEST: 50A) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE To THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F430). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND To THE PAPERWORK REDUCTION PROJECT (3150410S). OFFICE OF MANAGEMENTANO BUDGE1',WASHINGTON. DC 20503.

FACILITY NAME (1) DOCKET NUMBER I2) PAGE (3)

LER NUMBER (61 YEAR  : SSOUSNTIAL S~ REVISION v@) NUMBER ~% NUMSSR Donald C. Cook Nuclear Plant - Unit 2 p 6 p p p 3 1 6 9 5 0 0 7 0 0 0 3oF 0 3 TEXT illmoss ssMSP is TSOoPaf, oss ssldio'oosl Ni(C Fosm 3664'sl ()2) nal sisof Event con'd The required fire watch tour of the Unit 2 4Kv Switchgear Complex was not performed for 123 minutes. In the event of a fire in this area, the fire detection system in the complex, which was operable, would have alarmed in the Control Room. Immediate action would have been implemented to mitigate the fire as required by Plant procedures. The switchgear complex is protected by a manually operated low pressure CO, fire suppression system and has low combustible loading. Based on this, it is concluded that this event did not constitute a significant hazard to the health and safety of the general public.

Co ective Aetio The Shift Security Supervisor was directed to include active fire watch tours in the pre-shiit briefings.

Previously tracked separately, Appendix R tours have been added to normal fire watch tours and programmed into the hand carried electronic wand system used by firewatch personnel.

Prey ous S'milar Events 315/95-009-00 316/94-002-00 316/94-009-00 315/93-003-00 315/91-001-00 NRC Fosm 366A (669)