ML17328A970

LER 91-002-00:on 910220,discovered That Previous Procedure Rev Omitted Fire Damper from Insp List & Damper Not Included in Surveillance.Cause Not Conclusively Determined.Damper Visually & Functionally inspected.W/910322 Ltr

ML17328A970
Person / Time
Site:	Cook
Issue date:	03/22/1991
From:	Blind A, Carteaux P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-002-01, LER-91-2-1, NUDOCS 9103280137
Download: ML17328A970 (7)

Text

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ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM

~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9103280137 DOC.DATE: 91/03/22 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION CARTEAUX,P.'F. 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 91-002-00:on 910220,discovered that previous procedure rev omitted fire damper from insp list & damper not included D in surveillance. Cause not conclusively determined. Damper visually & functionally inspected.W/910322 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 2 ENCL TITLE: 50.73i50.9 Licensee Event Report (LER), Incident RPt, etc.

SIZE:

NOTES:

COPIES RECIPIENT COPIES D A'ECIPIENT ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' PD3-1 LA 1 1 PD3-1 PD 1 D COLBURN,T. 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DSTQ~ZLB8 D1 1 1 NRR/DST/SRXB 8E 1 1 R FISE~ ,1 1 RES/DSIR/EIB 1 1 RGN3 FIVE Ol 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 D

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

Indiana Michigan Power Company Cook Nuclear Plant~

One Cook Place Bridgman, Ml 4S106 616 465 5901 INDIANA NfCHIGAN POWM March 22, 1991 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 ortin S stem the following report is being submitted:

91-002-00 Sincerely, A.A. Blind Plant'Manager AAB sb Attachment c: D.H. Williams, Jr.

A.B. Davis, Region M.P. Alexich III P.A. Barrett B.F. Henderson R.F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector T. Colburn NRC J.G. Keppler M.R. Padgett G. Charnoff, Esq.

Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau B.A. Svensson 9103230i37 9i0322 PDR ADOCK 0500033.l~

PDR p/ 3 I

0 I

1t l

NRC FORM 366 U rL NUCLEAR REGULATORY COMMISSION (689) APPROVED OMB NO. 3150d104 EXPIRES: 4/30/92 IMATEO BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REGUESTt 500 HRS. FORWARD LICENSEE EVENT REPORT ILER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR AEGULATOAYCOMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150d104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME (1I DOCKET NUMBER (2) PA E 3 D. C. Cook

"'""'issed Nuclear Plant, Unit 2 Surveillance of a Single'Fire Damper Due to Inadvertent o 5 o o 0316ioF03 Omission of Damper from Procedure During Procedure Revision EVENT DATE (5) LE R NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

MONTH DAY YEAR YEAR sf ovENTIAL 'ct/2 RSVS~ MONTH DAY YEAR FACILITYNAMES DOCKET NUMBERIS)

NUMBER ko NUMBER 0 5 0 0 0 0 2 2 0 9 1 9 1 0 0 2 0 0 0 3 2 2 9 1 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF R (): /Chock ono or moro ol tho /ollOwinpl ('ill MODE (0) 20.402(It) 20.406(cl 50.73(sl(2)(irl 73.71(II)

POWER 20.405( ~ l(1)(i) 50.36(c) (1) 50.73(v))2) iv ) 73.71(c)

LEVEL (10) 1 p p 20.405( ~ ) (1)(ll) 50.36(c) (2) 60.73(sl(2)(villi(A) 50.73(s) (2)(rll) OTHER /Spoclly In Ahrtroct

.v<s v. "

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v. 20 406( ~ l(1)(ill) horow ond In Text, IIIIC Form X 50.73(sl(2)(II 36EA/

20.405(s) (1)(ivl 50.73(s)(2)(9) 50.73(s) (2)(vill)IB) c,co ., @; .j4. 20.406 (s I (1)(r) 50.734)(2)(III) 50.73( ~ ) (2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AAEA CODE P. F. Carteaux, Safety and Assessment Superintendent t7 1 6 4 6 5 5 9 p COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE MANUFAC. EPORTABLE TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER TO NPRDS QB

C~r yr .'N i.

SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SV 9 M I SS ION DATE (15l YES /I/ ym, comploto EXPECTED SIIBkrISSIOI/ DATE/ NO ABSTRACT /Llmlt tO /400 MwcoL is.. opprOxlmotoly /litton rlnplocpoto ryPowrirron linml (16)

On 2-20-91, while revising the inspection procedure for fire dampers protecting safety-related areas, procedure revision had inadvertently omitted a fire dan)per from the it was discovered that a previous inspection list. Due to the amission, subsequent surveillance performance using the procedure did not include the omitted damper.

%he Plant's Technical Specifications require the performance of a visual inspection of each fire (:hngper and its associated hardware at least once per 18 months. Prior to the omission, the dang~ was part of the procedure and had been properly surveilled.

At the time of discovery, the omitted danger was visually and ~ionally insp~ and accepted. 'lhe dang~ showed no adverse effects due to the extended time interval and remained within specification during the unsurveyed period. Current Administrative Controls governing procedure revision review requirements will reduce the probability of similar events.

NRC Form 366 (64)9)

NRC FORM358A UA NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 31500104 (SBS)

EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(500(BE). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503, F AC I LITY NAME (1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)

YEAR 2'EQUENTIAL,:$ g)I REVISION 43 NUMBER NUMBER D. C. Cook Nuclear Plant, Unit 2 p p p p p 3 1 6 9 1 0 0 2 0 0 02or-03 TEXT ///moro spooo/I roqrrirod, oro oddirr'orro/HRC form 3/ISAS/(12)

Condition Prior to Occurrence Unit Two in Mode One (power operation) at 100% pcarer.

Descri tion of Event While revising the inspection procedure for fire damgers (EIIS/VJ-DMP) protecting safety-related areas, it was discovered that a previous procecIure revision had inadvertently c(mitted fire damper 2-HV-SGPA-1.

2-HV-SGPA-1 is located in the switchgear cable spreading roam. Due to the canimion, subse(@sent surveillance performance using the prorcakure did not. include the omitted damper. 'Ihe Plant s Technical Specifications rectuire the perforrtance of a visual inspection of each fire damper and its associated harchrare at least once per 18 months. Prior to the omission, the damper was part of 'the procedure and had been properly surveilled.

At the time of discovery (2-20-91), the omitted dan)ger was outside the grace period of the surveillance cycle by 107 days. The dan)ger was im(nediately visually and functionally. inspected and accepted. The dan)ger sheared no adverse effects due to the extended time interval and remained within specification during the unsurveyed period.

Cause of Event The cause of the event was the inadvertent omission of the fire damper from the surveillance procedure during a procedure revision. At what stage in the procedure revision process or how the omission occurred is not conclusively known.

Anal sis of Event The event is being reported under 10 CFR 50.73(a) (2) (i) (B) as a cordition prohibited by the Plant s Technical Specifications. At the time of discovery (2-20-91), the unsurveyed fire damper was outside the grace period of the surveillance cycle by 107 days. The dang~ was immediately visually and functionally tested and accepted. 'Ihe damger showed no adverse effects due to the extended time interval and remained within specifications during this time frame. Based on the above, it has been concluded that the Event had no impact on public health and safety.

NRC Form 355A (SJ)9)

NRC FOAM 366A U.S. NUCLEAR AEGULATORYCOMMISSION APPROVED 0MB NO. 31500106 (6$ 9) EXPIRES: 6/30/92 ESTIMATED BURDEN PER RESPONSE TO COMP(.Y WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECOAOS TEXT CONTINUATION AND REPOATS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)500104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503, FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 46VISION YEAR 3@ SEOUENTIAL NUMBEII NUM664 D. C. Cook Nuclear Plant, Unit 2 o s o o o 316 9 l 0 0 2 0 0 0 3 OF 0 3 TEXT lllmrrm HMce /T mrlrr/md. II'ddrT/rrrM/HRC/rrrrm 36MB/ ()7)

Corrective Actions At the time of discovery (2-20-91), the amitted damper was immediately visually and funcitonally inspec~ and accept. 'Ihe amitted damper was also added to the inspection procedure to ensure dan)per in.~tion in the next surveillance period. Current Administrative Controls governing procedure revision review requirements (which identified this discrepancy) will reduce the probability of similar events in the future; thus, no further action will be taken.

Failed nent Identification None.

Previous Similar Events None.

NR C Form 366A (649)