ML17328A473

LER 90-010-00:on 900824,discovered That Routing of Cable Associated W/Local Shutdown Indication Panels Not in Compliance w/10CFR50,App R.Caused by Insufficient Scoping for Design Changes.Program revised.W/901016 Ltr

ML17328A473
Person / Time
Site:	Cook
Issue date:	09/21/1990
From:	Blind A, Brewer S INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-010, LER-90-10, NUDOCS 9010160022
Download: ML17328A473 (10)

Text

ACCELERATED SYSTEM, DISTRIBUTION DEMONSTRATION Qj REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ESSION NBR:9010160022 DOC.DATE:" 90/09/21 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 AUTH. NAME AUTHOR AFFILIATION BREWER,S.J. 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 90-010-00:on 900824,10CFR50 App R deficiencies due to potential loss of local shutdown indication panel function.

DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR 1 ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Tncident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 COLBURN,T. 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFBll 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 RR/gg/S3?LBBD1 1 1 NRR/DST/SRXB 8E 1 1 REG GN3 FIL~TILE 01 02 1 1

1 1

RES/DSIR/EIB 1 1 EXTERNAL EG&G BRYCE i 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 NOTBTO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! 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 P.O. Box 458 Bridgman. I'Jll 49106 616 465 590t INDIANA NICHIGiAN POWER September 21, 1990 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 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:

90-010-00 Sincerely, A.A. Blind Plant Manager AAB:clj Attachment cc: D.H. Williams, Jr.

A.B. Davis, Region III M.P. Alexich P.A. Barrett A'O J.E. Borggren (r

R.F. Kroeger HCQ B. Walters Ft. Wayne (ii, Q OO NRC Resident Inspector

. GlA J.G. Giitter, NRC J.G. Keppler M.R. Padgett G.'harnoff, Esq.

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

/gg$

NRC SORM 366 U.S. NUCLEAR REGULATORY COMMISSION (669) APPROVED 0M B NO. 31504)104 EXPIRES: 4(30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 500 HAS. FOAWAAD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, DC 20503.

LITY NAME (1) DOCKET NUMBER (21 PA E 3 D.C. Cook Nuclear Plant, Unit 1 0 5 o o o3 15 icF05 10CFR50 Appendix R Deficiencies Resulting in Potential Loss of Local Shutdown Indication Panel Function i EVENT DATE (51 LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

MONTH DAY YEAR YEAR SEOUENTIAL '/we~ tcevteloN DAY PACILITY NAMES DOCKET NUMBER(SI g@ NUMBER .4oc NUMBER MONTH YEAR D.C. Cook, Unit 2 0 5 0 0 0 3 0 8 24 9090 010 0 0 09 2190 0 5 0 0 0 THIS REI'ORT IS SUBMITTED PURSUANT TO THE RLOUIREMENTS OF 10 cFR (): (Cneck one or more oi the follow(op) l111 0 PE RATING MODE (9) 20.402(bl 20.405(c) 50.73(e I (2) I le ) 73.71(bl POWER 20.406(e)() l(l) EOM(c1(11 50.73(e)(2)(r) 73.71(cl LEYEL 1 0 0 20.40S(e I )1) I 4) 50.36(cl)21 50.73(el(2) (r4) OTHER ISpeciry in Abttrect oeiowend/n Text IIRC Form 20.405(el(1)(4l) 50.73(c) (2) ii) 60,73(e) 12)(rl4) (Al 366AJ

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. Pv. 20.405(e) 20.405(c) )1) (rl X 50.73(el(2)(4) 50,73(e) (2) lrBI)(61 cx.S . $@ 50.73(e) (2) I BI) 50.73(e) (2) (xl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE S.J. Brewer, Nuclear Safety and Licensin Section Manager 614 223 -2 20 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC. MANUFAC TURER CAUSE SYSTEM COMPONENT TUREA TO NPRDS 5%MD)i SVPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATF. (151 YES IIIyn, complete EXPECTED SIIOMISSIOII DATE) NO ABSTRACT (Limit to teOO tpecn, Ee., epproximetely Iiftnn tinpie tpece typewriven tinct) (16)

On August 24, 1990 with Unit One operating at 100 percent power and Unit Two in Node Six, it was discovered that the routing of cable associated with the Unit One Local Shutdown Indication (LSI) panels was not in ax)pliance with 10CFR50 Appendix R. On September 6, 1990, it was subsequently discovered that a similar condition existed for the Unit Two LSI panels.

The imnediate corrective action taken was initiation of plant aedifications to bring the subject plant cabling into canpliance with 10CFR50 Appendix R.

All identified areas are provided with adequate fire detection and suppression to substantially mitigate the impact of a fire on normal and LSI instrumentation. Therefore, the event should not have presented a significant hazard to the public health and safety.

NRC Form 366 (64)9)

NAC FOAM 388A US. NUCLEAR REGULATOAY COMMISSION (84) 9) APPROVED 0MB NO. 31600104 EXPIRES; 4/30/92 ESTIMATED BURDEN PER AESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COL(.ECTION AEQUESTI 504) HRS. FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P4)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104), OFFICE OF MANAGEMENT'ANDBUDGET,WASHINGTON, DC 20503, FACILITY NAME (1) DOCKET NUMBER (2) LEA NUMBER (Si PAGE 13)

SEQUENTIAL REVISION NVMSER NVMSER D.C. Cook Nuclear Plant, Unit

'tEXT ///moro t/NCS /4 rtr/Ir/rtd, oto 4 /f)foot/HRC Forrrr 3854'4/ l(7) 1 0 5 0 0 0 3 1 5 9 0 010 0 0 OF Conditions Prior to Occurrence Unit Unit 1

2 in Mode in Mode 1

6.

at 100 percent Rated Thermal ~

Descri tion of Event On August 24, 1990, it was discovered that the routing of cables associated Unit One Local Shutdown Indication (LSI) panels was not in ccmpliance with the with 10CFR50 Appendix R requirements., A postulated fire in any of three Unit One fire areas could have resulted in an inability to maintain power to the LSI panels. The following describes the analysis performed.

Unit 1 Fire Areas 40 (Zone 41), 48 (Zone 55), and 49 (Zone 56).

The area analyses performed areas could have eliminated both the Unit 1 and Unit 2 Shutdown Indication (LSI) panels.

identified that The cable 1-29685G (EIIS/ED-CBL3) which runs between panels 1-LSI-6 and 1-LSI-6X.

a discrepant fire in cable

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any one in of these to the Local question was fire A fault of this cable due to a fire would have eliminated the Unit 2 Alternate feed to the Unit 1 LSI panels. The Unit 1 normal power feed to the LSI panels was already assumed lost for a fire in 'any of these areas because various cables associated with the availability of MCC 1-ABC-B would have been lost.

On September condition existed 6, 1990, it was subsequently discovered that a similar for the Unit, Two LSI panels. A postulated fire in one of the Unit Two fire areas-could have resulted in an inability to maintain power to the LSI panels. The following describes the analysis performed.

Unit 2 Fire Area 29 (Zones 24, 25).

The area analyses performed identified that a fire in fire zone 24 would have faulted both the Unit 1 and Unit 2 power to the LSI panels. The discrepant cable in question was cable 1-1936R (EIIS/ED-CBL3). This Unit 1 alternate power source to the Unit 2 LSI panels runs in fire zone 24 which also contains the Unit 2 normal source cable 2-12467 (EIIS/ED-CBL3). Although 2-12467 also runs in zone 25, 1-1936R does not. Fire zones 24 and 25 are separated by a three-hour fire-rated wall.

NRC Form 388A (84)9)

NRC FORM 358A US. NUCLEAR REGULATORY COlhMISSION (589) APPROVED OMB NO. 31500104 EXPIRESI 4130f92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST) 50i) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (Ph)30), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEME'NTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME (1) DOCKET NUMBER (2) LE R NUMBE R (5) PAGE (3)

YEAR SEQUENTIAL REVISION

@P NUMBER NUMBER D.C. Cook Nuclear Plant, Unit TEXT litIrroro Eooco IS roerf)od. B44 oddi(ior>>I NRC form 36643) 1 0 5 0 0 0 3 ] 5 9 0 010 00 03 oF0 (Il)

Cause of Event The condition was the result of insufficient scoping for 10CFR50 Appendix R design changes. Insufficient controls were in place to ensure that new cables added to the plant cm)plied with 10CFR50 Appendix R requirements.

Anal sis of Event This event is being reported in accordance with 10CFR50.73 (a) (2) (ii) (B) and 10CFR50.73 (a) (2) (ii) (C) in that the condition was outside the design basis and not covered by the plant's operating and emergency procedures respectively.

Unit 1 Fire Areas 40, 48, and 49 Analysis.

a. Fire Area 40:

Our Safe Shutdown System Analysis (SSSA) shows that for a fire in area 40 control room indications equivalent to those found on the LSI cabinet would be lost. Due to cable misrouting, the LSI panel indications would also have been lost.

Further investigation revealed the reason that the control roan indication would have been lost is because one of the alternate sources to the CRID panels, the isolixreters, is located in this area. What the SSSA does not shcFAT is that the preferred source to the CRID panels would have been available. The inverters are located in fire area 41 (fire zone 42C). Therefore, normal control room indication of process rmnitoring would have been available for fire in Area 40.

b. Fire Areas 48 and 49:

Under conservative assumptions of loss of function for an area fire, the SSSA shows that for a fire in areas 48 and 49 both the control room and the LSI panel indications would, have been lost.

However, fire areas 48 and 49 are provided with adequate suppression and detection to substantially mitigate the impact on normal and LSI instrumentation.

NRC Form 358A ($89)

NAC FORM 368A U.S. NUCLEAR REGULATORY COI4MISSION

)689) APPAOVEO OMB NO. 31600'104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LER) ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 600 HRS. FORWARD TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IF@30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 131504104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME 11I DOCKET NUMBER 12) LER NUMBER )8) PAGE (3)

YEAR Sf DUE NTIAL IIEVISION NUMBER NUMSEII D.C. Cook Nuclear Plant, Unit TEXT /I/ more epece /4 mr)II/red. Iree eddidone//VRC Farm 3664'4/117) 1 o 5 o o o 3 1590 0 1 0 000 4 oF 05 Anal sis of Event Unit 2 Fire Area 29 (Zones 24 and 25) Analysis:

According to our Safe Shutdown Systems Analysis, a fire in area'9 would not have eliminated process nanitoring indication in the control room for steam generators 1 and 4. The following indication would have been available in the Unit 2 control room:

2-BLP-112 SG 1 Water Level (normal range) 2-BLP-142 SG 4 Water Level (normal range) 1 2MPP-210 SG 1 Pressure 2-MPP-240 SG 4 Pressure 2-N31 Source Range Ronitoring Channel 1 2-NLP-151 or 2-NLP-153 Pressurizer Water Level 2-NPS-121 RCS Pressure (wide range)

These indications could provide an indirect means of determine RCS temperature. This area is provided with adequate detection and suppression to substantially mitigate the impact on normal and LSI instrumentation.

Conclusion In conclusion, the condition did not adversely impact the health and safety of the public due to the fact that areas 40, 48, and 49 of Unit 1 and Area 29 of Unit 2 are provided with suppression and detection to substantially mitigate the impact on normal and LSI instrumentation. Also, a large portion of the station normal instrumentation would remain functional since fires propagate at a finite rate rather than causing an instantaneous loss of function for an entire area.

NRC Form 388A (689)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVED OMB NO. 3)504))04 EXPIRESI 4(30(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 502) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P4)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK RFDUCTION PROJECT (3)504)104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME O) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION NVMSSR NVMSER D.C. Cook Nuclear Plant, Unit 1 o s o o o 315 9 0 010 00 05 OF 0 5 TEXT illmom spsso Is ssqoPsd. oss sddicionsl IYRC FomI 3664'sl (17)

Corrective Actions Unit One A plant Temporary Modification was initiated which installed a 1 ampere fuse in 1-LSI-6 on the load side of the 1-29685G cable. This way a fire in the fire areas of concern would not eliminate the ability of providing Unit 2 power to the LSI panels.

Unit Two A plant Minor Modification was initiated to provide a one-hour fire enclosure around the conduit 2-12467 that exists in fire zone 24. There is suppression and detection in the area. Conduit 2-12467 was in 10CFR50 Appendix R compliance on 9/20/90.

General Our program for ensuring continued 10CFR50 Appendix R compliance will be revised. It is anticipated that this revision will be in place by March 1, 1991.

FB1 led nent Identification None.

Previous Similar Events 050-315/90-008: 10CFR50 Appendix R deficiencies resulting in potential loss of auto-start of service water pumps due to incorrect implementation of design change.

NR C Form 366A (64)9)

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