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| | issue date = 09/21/1990 | | | issue date = 09/21/1990 |
| | title = 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 | | | title = 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 |
| | author name = BLIND A A, BREWER S J | | | author name = Blind A, Brewer S |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM, Qj REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ESSION NBR:9010160022 DOC.DATE:" 90/09/21 NOTARIZED: | | {{#Wiki_filter:ACCELERATED SYSTEM, DISTRIBUTION DEMONSTRATION Qj REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION BREWER,S.J. | | 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 |
| Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A. | |
| Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION | |
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| ==SUBJECT:== | | ==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 ID CODE/NAME PD3-1 LA COLBURN,T. | | LER 90-010-00:on 900824,10CFR50 App R deficiencies due to potential loss of local shutdown indication panel function. |
| INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFBll NRR/DOEA/OEAB11 NRR/DST/SELB 8D RR/gg/S3?LBBD1 REG FIL~02 GN3 TILE 01 EXTERNAL EG&G BRYCE i J H NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DOA AEOD/ROAB/DS P NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTBTO ALL"RIDS" RECIPIENTS: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR 1 ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Tncident Rpt, etc. |
| PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR 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.50-315Document 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: | | NOTES: |
| 90-010-00 Sincerely, A.A.Blind Plant Manager AAB:clj Attachment A'O (r HCQ (ii, Q OO.GlA cc: D.H.Williams, Jr.A.B.Davis, Region III M.P.Alexich P.A.Barrett J.E.Borggren R.F.Kroeger B.Walters-Ft.Wayne NRC Resident Inspector 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.
| | 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 |
| Lauzau B.A.Svensson/gg$
| | 1 1 |
| NRC SORM 366 (669)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)LITY NAME (1)D.C.Cook Nuclear Plant, Unit 1 APPROVED 0M B NO.31504)104 EXPIRES: 4(30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 500 HAS.FOAWAAD 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 MANAGEMENT AND BUDGET.WASHINGTON, DC 20503.DOCKET NUMBER (21 PA E 3 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 g@SEOUENTIAL NUMBER'/we~tcevteloN.4oc NUMBER MONTH DAY YEAR PACILITY NAMES D.C.Cook, Unit 2 DOCKET NUMBER(SI 0 5 0 0 0 3 0 8 24 9090 010 0 0 09 2190 0 5 0 0 0 0 PE RATING MODE (9)POWER LEYEL 1 0 0 X~.n Pv.~v":,'p..ix cx.S.$@THIS REI'ORT IS SUBMITTED PURSUANT TO THE RLOUIREMENTS OF 10 cFR (): (Cneck one or more oi the follow(op) l111 50.73(e I (2)I le)50.73(e)(2)(r) 20.405(c)EOM(c1(11 50.36(cl)21 20.402(bl 20.406(e)()
| | 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: |
| l(l)20.40S(e I)1)I 4)20.405(el(1)(4l) 20.405(e)lllllr)20.405(c))1)(rl 50.73(el(2)(r4)60,73(e)12)(rl4)(Al 50,73(e)(2)lrBI)(61 50.73(e)(2)(xl 50.73(c)(2)ii)X 50.73(el(2)(4) 50.73(e)(2)I BI)LICENSEE CONTACT FOR THIS LER (12)73.71(bl 73.71(cl OTHER ISpeciry in Abttrect oeiowend/n Text IIRC Form 366AJ NAME S.J.Brewer, Nuclear Safety and Licensin Section Manager TELEPHONE NUMBER AREA CODE 614 223-2 20 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER CAUSE SYSTEM COMPONENT MANUFAC TUREA TO NPRDS 5%MD)i SVPPLEMENTAL REPORT EXPECTED (14)YES III yn, complete EXPECTED SIIOMISSIOII DATE)NO ABSTRACT (Limit to teOO tpecn, Ee., epproximetely Iiftnn tinpie tpece typewriven tinct)(16)EXPECTED SUBMISSION DATF.(151 MONTH DAY YEAR 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.
| | 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! |
| Therefore, the event should not have presented a significant hazard to the public health and safety.NRC Form 366 (64)9)
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
| NAC FOAM 388A (84)9)US.NUCLEAR REGULATOAY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED 0MB NO.31600104 EXPIRES;4/30/92 ESTIMATED BURDEN PER AESPONSE TO COMPLY WTH THIS INFORMATION COL(.ECTION AEQUESTI 504)HRS.FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.
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| DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104), OFFICE OF MANAGEMENT'AND BUDGET,WASHINGTON, DC 20503, FACILITY NAME (1)DOCKET NUMBER (2)LEA NUMBER (Si SEQUENTIAL NVMSER REVISION NVMSER PAGE 13)D.C.Cook Nuclear Plant, Unit 1'tEXT///moro t/NCS/4 rtr/Ir/rtd, oto 4/f)foot/HRC Forrrr 3854'4/l(7)0 5 0 0 0 3 1 5 9 0 010 0 0 OF Conditions Prior to Occurrence Unit 1 in Mode 1 at 100 percent Rated Thermal~Unit 2 in Mode 6.Descri tion of Event On August 24, 1990, it was discovered that the routing of cables associated with the Unit One Local Shutdown Indication (LSI)panels was not in ccmpliance 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.
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| Unit 1 Fire Areas 40 (Zone 41), 48 (Zone 55), and 49 (Zone 56).The area analyses performed identified that a fire in any one of these fire areas could have eliminated both the Unit 1 and Unit 2~to the Local Shutdown Indication (LSI)panels.The discrepant cable in question was cable 1-29685G (EIIS/ED-CBL3) which runs between panels 1-LSI-6 and 1-LSI-6X.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 6, 1990, it was subsequently discovered that a similar condition existed 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.
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| 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).
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| 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).
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| 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)
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| NRC FORM 358A (589)US.NUCLEAR REGULATORY COlhMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.31500104 EXPIRESI 4130f92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST)50i)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (Ph)30), U.S.NUCLEAR REGULATORY COMMISSION.
| | Indiana Michigan Power Company |
| WASHINGTON.
| | ~ |
| DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104).
| | 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: |
| OFFICE OF MANAGEME'NT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LE R NUMB E R (5)YEAR@P SEQUENTIAL NUMBER REVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant, Unit 1 TEXT lit Irroro Eooco IS roerf)od.B44 oddi(ior>>I NRC form 36643)(Il)0 5 0 0 0 3]5 9 0 010 00 03 oF0 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.
| | In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted: |
| 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.
| | 90-010-00 Sincerely, A.A. Blind Plant Manager AAB:clj Attachment cc: D.H. Williams, Jr. |
| 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.
| | A.B. Davis, Region III M.P. Alexich P.A. Barrett A'O J.E. Borggren (r |
| 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.
| | R.F. Kroeger HCQ B. Walters Ft. Wayne (ii, Q OO NRC Resident Inspector |
| NRC Form 358A ($89)
| | . GlA J.G. Giitter, NRC J.G. Keppler M.R. Padgett G.'harnoff, Esq. |
| | Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau B.A. Svensson |
| | /gg$ |
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| NAC FORM 368A)689)U.S.NUCLEAR REGULATORY COI4MISSI ON LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPAOVEO OMB NO.31600'104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 600 HRS.FORWARD 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 MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME 11I DOCKET NUMBER 12)YEAR LER NUMBER)8)Sf DUE NTIAL NUMBER IIEVISION NUMSEII PAGE (3)D.C.Cook Nuclear Plant, Unit 1 TEXT/I/more epece/4 mr)II/red. | | 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. |
| Iree eddidone//VRC Farm 3664'4/117) 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 2-BLP-142 2MPP-210 2-MPP-240 2-N31 SG 1 Water Level (normal range)SG 4 Water Level (normal range)1 SG 1 Pressure SG 4 Pressure 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. | | 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) |
| This area is provided with adequate detection and suppression to substantially mitigate the impact on normal and LSI instrumentation. | | 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 |
| 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. | | ~v":, lllllr) |
| 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) | | 'p ..ix n X ~ |
| NRC FORM 366A (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3)504))04 EXPIRESI 4(30(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 502)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS 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 MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME O)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL NVMSSR REVISION NVMSER PAGE (3)D.C.Cook Nuclear Plant, Unit 1 TEXT ill mom spsso Is ssqoPsd.oss sddicionsl IYRC FomI 3664'sl (17)o s o o o 315 9 0 010 00 05 OF 0 5 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: | | . 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) |
| 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) l}} | | 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 |
| | ~ |
| | 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) |
| | |
| | l}} |
Similar Documents at Cook |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
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
~v":, lllllr)
'p ..ix n X ~
. 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
~
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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