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| {{#Wiki_filter:PCCELERATQD DOCUMENT DIST RUTION SYSTEM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS)ACCESSION NBR:9309010100 DOC.DATE: 93/08/23 NOTARIZED: | | {{#Wiki_filter:PCCELERATQD DOCUMENT DIST RUTION SYSTEM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS) |
| NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit l, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION VERILLI,M. | | ACCESSION NBR:9309010100 DOC.DATE: 93/08/23 NOTARIZED: NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit AUTHOR AFFILIATION l, Carolina 05000400 AUTH. NAME VERILLI,M. Carolina Power & Light Co. |
| Carolina Power&Light Co.ROBINSON,W.R. | | ROBINSON,W.R. Carolina Power & Light Co. |
| Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 93-007-01:on 930523,unplanned ESF actuation occurred due to improper alignment of MOC switch.Performed insp to other 6.9 KV breakers.W/930825 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.D/05000400 RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL EG&G BRYCE g J~H NRC PDR NSZC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB RR~SSAQSPLB REG FZL~02 FILE 01 L ST LOBBY WARD NSIC MURPHYFG.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"Rl DS" RECIPIENTS: | | LER 93-007-01:on 930523,unplanned ESF actuation occurred due to improper alignment of MOC switch. Performed insp to other 6.9 KV breakers.W/930825 ltr. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| PLEASE HELP US TO REDUCE WASTE!CON TACf THE DOCUMENT CONTROL DESK, ROOM Pl-31 (r XT.504-206)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON"f NEED!D D S FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 I | | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| C~R Carolina power 8 Ught Company HARRIS NUCLEAR PLANT P.O.Box 165 New Hill, North Carolina 27562 AUG 2 5 isa Letter Number: HO-930149 UPS.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 93-007-01 Gentlemen:
| | / |
| In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
| | NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 LE,N 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 RR~SSAQSPLB 1 1 NRR/DSSA/SRXB 1 1 REG FZL~ 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL EG&G BRYCE g J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYFG.A 1 1 NSZC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D |
| The original report fulfilled the requirement for a written report within thirty (30)days of a reportable occurrence.
| | D NOTE TO ALL "Rl DS" RECIPIENTS: |
| This supplement is being submitted to provide additional information related to the unplanned Engineered Safety Feature actuation described in the original report.This report is in accordance with the format set forth in NUREG-1022, September 1983.Very truly yours, W.R.Robinson General Manager Harris Nuclear Plant MV:smh Enclosure c: Mr.S.D.Ebneter (NRC-RII)Mr.N.B.Le (NRC-PM/NRR)Mr.J.E.Tedrow (NRC-SHNPP)MEM/LER93-007.1/1/OS1 9309010100 930823 PDR ADOCK 05000400 S PDR
| | S CONTROL DESK, PLEASE HELP US TO REDUCE WASTE! CON TACf THE DOCUMENT YOUR NAME FROM DISTRIBUTION ROOM Pl-31 (r XT. 504-206 ) TO ELIMINATE LISTS FOR DOCUMENTS YOU DON"f NEED! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 |
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| NRC FORH,368 (5-92)U.S.NUCLEAR REGUUITDRY COMMISSION APPROVED BY OMB ND.3160.0104 EXPIRES 6)31)86 LICENSEE EVENT REPORT (LER)(See reverse for required naker of digits/characters for each block)ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS IHFORMATION COLLECTIOH REQUEST: 50.0 HRS.FORWARD COMHENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MAHAGEHENT BRANCH (HNBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON
| | I C~R Carolina power 8 Ught Company HARRIS NUCLEAR PLANT P.O. Box 165 New Hill, North Carolina 27562 AUG 2 5 isa Letter Number: HO-930149 UPS. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 93-007-01 Gentlemen: |
| ~DC 20555 0001~AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503-FACILITYNAMEII)
| | In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within thirty (30) days of a reportable occurrence. This supplement is being submitted to provide additional information related to the unplanned Engineered Safety Feature actuation described in the original report. This report is in accordance with the format set forth in NUREG-1022, September 1983. |
| Shearon Harris Nuclear Plant-Unit
| | Very truly yours, W. R. Robinson General Manager Harris Nuclear Plant MV:smh Enclosure c: Mr. S. D. Ebneter (NRC - RII) |
| ¹1 DOCKET NUMBER 12)05000 400 PAGE I3)1 OF 4 TITLE(4)Unplanned Engineered Safety Feature Actuation when"B" Emergency Diesel Generator started on loss of ower to the lB-SB Safet Bus.MONTH DAY YEAR YEAR EVENT DATE(5)I.ER NUMBER 16)SEQUENTIAL NUHBER REVISION NUMBER MOHTH DAY YEAR REPORT DATE IT)FACILITY HAME DOCKET NUMBER 05000 OTHER FACILITIES INVDI.VED IB)5 23 93 93 007 01 8 23 93 FACILITY NAHE DOCKET NUMBER 05000 OPERATING ,MODE 19)POWER LEVEL IID)15%20.402(b)20.405(a)(1)(i) 20.405(a)(1)(ii) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)('l)(v) 20.405(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50'3(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 0 THE REQUIREMENTS OF.10 CFR 6: (Check one or more)I1 THIS REPORT IS SUBMITTED PURSUANT T 73.71(b)73.71(c)OTHER (Specify in Abstract below and in Text, NRC Form 366A)NAME Michael Verrilli LICENSEE CONTACT FOR THIS LER ii2)TELEPHONE NUMBER (Include Area Code)(919)362-2303 CDMPI.ETE ONE LINE FOR EACH COMPONENT FA)LURE DESCRIBED IN THIS REPORT 113)CAUSE B SYSTEH CL B455 COMPONENT MANUFACTURER REPORTABLE TO NPRDS";MÃ%0Ã65 g)),.;3:c;)
| | Mr. N. B. Le (NRC - PM/NRR) |
| :%('.4.s CAUSE SYSTEH COMPONENT HANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 114)YES (If yes, complete EXPECTED SUBMISSION DATE).X ND EXPECTED SUBMISSIOH DATE 116)MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)116)On May 23, 1993 the Starts Transformer to Auxiliary Bus E supply breaker 121 failed to open automat3.cally when the corresponding Auxil3.ary Transformer supply breaker 122 was closed.This resulted in both transformers feed3.ng the same bus.After troubleshooting, recommendations were made and action taken to manually open breaker 121.Upon opening breaker 121, emergency bus B-SB supply breaker 125 opened on interlock resulting in deenergizing of the B-SB bus and automatic start and loading of the'B'mergency Diesel Generator (EDG).The Auxiliary Feedwater System turbine driven and"B" motor drive'n pumps started at this point, as rectuired and were subsequently secured to stabilize steam generator levels.A Containment Ventilation Isolation Signal also occurred during the transient due to the failure of a radiation monitor supply power fuse.Breaker 121 failed to automatically open due to a misally.gned Mechanism Operated Cell (MOC)switch in breaker 122, which defeated the auto-open interlock.
| | Mr. J. E. Tedrow (NRC - SHNPP) |
| The cause of this event was determined to be insufficient training and procedural controls to ensure that the MOC switch was properly aligned following maintenance. | | MEM/LER93-007.1/1/OS1 9309010100 930823 PDR ADOCK 05000400 S PDR |
| Corrective actions will include training, procedure revisions and enhancements to ensure proper MOC switch alignment in applicable breakers.This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned NRC FORM 366 NRC FOR)3BBA'(5-'92)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)t APPROVED BY OMB NO.3(600'(04 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPOHSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 KRS~FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (MHBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME (I)Shearon Harris Nuclear Plant Unit Nl DOCKET NUMBER (2)05000/400 93 007 LER NUMBER (B)YEAR.SEQUEHTIAL REVISION 01 PAGE (3)2 OF 4 TEXT If more s ace is re uired use add(tional co ies of NRC Form 366A (IT)EVENT DESCRIPTION:
| | |
| On May 23, 1993 during power ascension following a one day outage, Operators were swapping auxiliary loads from the Startup Transformers (SUTs)to Unit Auxiliary Transformers (UATs).At 1555 while attempting to swap the loads on Auxiliary Bus'E', the SUT to Bus'E'upply breaker 121 failed to open automatically when UAT supply to Bus'E'reaker 122 was closed.This resulted in Bus'E'eing supplied by both transformers.
| | NRC FORH,368 U.S. NUCLEAR REGUUITDRY COMMISSION APPROVED BY OMB ND. 3160.0104 EXPIRES 6)31)86 (5-92) |
| Maintenance and Technical Support personnel were contacted and research efforts to determine possible causes and appropriate corrective action were commenced.
| | ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH LICENSEE EVENT REPORT (LER) THIS IHFORMATION COLLECTIOH REQUEST: 50.0 HRS. |
| A concern was identified associated with circulating currents through both transformers due to the parallel operation, which could result in transformer failure.This concern provided a sense of urgency to take prompt action to open one of the breakers and eliminate the parallel supply line-up.Operators observed normal stable currents through both transformers as indicated on the main control board, and discussed which breaker they would open in the event of rapidly increasing transformer currents.It was concluded that the UAT supply breaker 122 would be opened if this were to occur.This was based on the assumption that the circuitry may not recognize that breaker 122 is actually closed.The control room staff's main focus of concern was the possibility of losing power to Aux Bus"E", which would result in a loss of Emergency Bus"B-SB".Following research and troubleshooting efforts by Operations, Maintenance, and Technical Support personnel, a conclusion was reached that breaker 121 should be manually opened.This was recommended to the control room staff and at 1732 breaker 121 was locally opened.Emergency Bus"B-SB" supply breaker 125 immediately tripped open on interlock, deenergizing the bus and resulting in an automatic start and loading of the B-SB Emergency Diesel Generator.
| | FORWARD COMHENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MAHAGEHENT BRANCH (See reverse for required naker of digits/characters for each block) (HNBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON~ DC 20555 0001 ~ AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503-FACILITYNAMEII) Shearon Harris Nuclear Plant-Unit ¹1 DOCKET NUMBER 12) PAGE I3) 05000 400 1 OF 4 TITLE(4) Unplanned Engineered Safety Feature Actuation when "B" Emergency Diesel Generator started on loss of ower to the lB-SB Safet Bus. |
| The Auxiliary Feedwater System turbine-driven and"B" motor-driven pumps then automatically started as required, and were subsequently secured to stabilize steam generator levels.In addition, a Containment Ventilation Isolation Signal occurred during the transient due to failure of a power supply fuse for Containment Leak Detection Radiation Monitor, RM-3502A.The fuse was replaced (per WRY g93-AFKQl) and after successful testing, the monitor was restored and the Containment Ventilation System returned to it's normal alignment.
| | EVENT DATE(5) I.ER NUMBER 16) REPORT DATE IT) OTHER FACILITIES INVDI.VED IB) |
| Upon subsequent inspection of breaker 122, Maintenance personnel discovered that the Mechanism Operated Cell (MOC)switch was in the"Breaker OPEN" position.This MOC switch is physically located on the inside wall of the breaker cabinet and during the breaker rack-in process engages with an attachment on the left outside corner of the breaker called an actuating NRC FORM 366A 5-92)
| | SEQUENTIAL REVISION FACILITY HAME DOCKET NUMBER MONTH DAY YEAR YEAR NUHBER NUMBER MOHTH DAY YEAR 05000 FACILITY NAHE DOCKET NUMBER 5 23 93 93 007 01 8 23 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF.10 CFR 6: (Check one or more) I1 |
| (IRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPROVED BY OMB NO.3160 0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MITM THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORMARD COMMENTS REGARDING BURDEH ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MNBB 7714)i U~S~NUCLEAR REGULATORY COMMISSIONi HASHINGTOH, DC 20555-0001, AND TO THE PAPERNORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET MASNINGTON DC 20503.FACILITY NAME I1)Shearon Harris Nuclear Plant.Unit¹1 DOCKET NUMBER I2)05000/400 YEAR 93 LER NUMBER (6)SEQUEHTIAL 007 REVISION 01 PAGE I3)3 OF 4 TEXT If more s ace is r uired use additional co ies of NRC Form 366A I)7)EVENT DESCRIPTION: (Cont.)When properly aligned and engaged this switch rotates electrical contacts when the breaker is opened or closed.The MOC switch was in the"Breaker OPEN" position due to these components being misaligned as a result of the last rack-out/rack-in evolution. | | ,MODE 19) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) |
| Therefore, when breaker 121 was locally opened, with the MOC switch in breaker 122 not properly engaged, both breakers erroneously appeared open to the interlock logic and breaker 125 tripped open automatically. | | POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) |
| Although misalignment was evident,.the MOC switch had to be engaged with the breaker, at leas up until auxiliary loads were swapped from the UATs to SUTs on May 21, 1993;otherwise, breaker 125 would have received a trip signal earlier.Based on this, the MOC switch most likely slipped off the MOC actuating angle either during the previous auxiliary load swap evolution or two days later during this event when breaker 122 was closed.A scar on the damaged MOC actuating angle indicates that the switch most likely slipped off the angle when breaker 122 was closed on May 23, 1993.CAUSE:-The cause of this event was the improper alignment of the MOC switch during the rack-in of breaker 122 that occurred on November 20, 1992 and subsequent contact"slip-off" on May 23, 1993.This condition created a false"breaker open" signal and resulted in the automatic trip of breaker 125 on interlock. | | LEVEL IID) 15% 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 50.73(a)(2)(viii)(B) Abstract below 20.405(a)(1)(iv) 50.73(a)(2)(ii) and in Text, 20.405(a)('l)(v) 50 '3(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A) |
| The following factors contributed to the improper switch alignment; lack of knowledge on the part of operators regarding the proper method for checking MOC alignment during breaker rack-in and inadequate maintenance procedures resulting in improper installation and position verification of the MOC switch and actuating angle.AFETY SIGNIFICANCE: | | LICENSEE CONTACT FOR THIS LER ii2) |
| There were no safety consequences as a result of this event.The"B" Emergency Diesel Generator started automatically upon the loss of power to the"B" Safety bus and was available for emergency loads.The"B" Essential Services Chilled Water Circulating Pump (P-4)did not automatically start as designed, but did start upon a manual start signal.This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned actuation'f an Engineered Safety Feature (ESF).Although similar misalignment problems with 6.9 KV breakers have occurred in the past, none have resulted in a reportable condition. | | TELEPHONE NUMBER (Include Area Code) |
| Operator training was conducted following an event that occurred in 1988, but was not incorporated into the initial or continuing training programs to ensure a knowledge of this condition was maintained. | | NAME Michael Verrilli (919) 362-2303 CDMPI.ETE ONE LINE FOR EACH COMPONENT FA)LURE DESCRIBED IN THIS REPORT 113) |
| | ";MÃ%0Ã65 REPORTABLE REPORTABLE CAUSE SYSTEH COMPONENT MANUFACTURER CAUSE SYSTEH COMPONENT HANUFACTURER TO NPRDS TO NPRDS g)),.;3:c;) |
| | '.4. s B CL B455 :%( |
| | SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR EXPECTED YES SUBMISSIOH (If yes, complete EXPECTED SUBMISSION DATE). X ND DATE 116) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 116) |
| | On May 23, 1993 the Starts Transformer to Auxiliary Bus E supply breaker 121 failed to open automat3.cally when the corresponding Auxil3.ary Transformer supply breaker 122 was closed. This resulted in both transformers feed3.ng the same bus. After troubleshooting, recommendations were made and action taken to manually open breaker 121. Upon opening breaker 121, emergency bus B- SB supply breaker 125 opened on interlock resulting in deenergizing of the B-SB bus and automatic start and loading of the 'B'mergency"B"Diesel Generator (EDG). The Auxiliary Feedwater System turbine driven and motor drive'n pumps started at this point, as rectuired and were subsequently secured to stabilize steam generator levels. |
| | A Containment Ventilation Isolation Signal also occurred during the transient due to the failure of a radiation monitor supply power fuse. |
| | Breaker 121 failed to automatically open due to a misally.gned Mechanism Operated Cell (MOC) switch in breaker 122, which defeated the auto-open interlock. The cause of this event was determined to be switch insufficient training and procedural controls to ensure that the MOC was properly aligned following maintenance. |
| | Corrective actions will include training, procedure revisions and breakers. |
| | enhancements to ensure proper MOC switch alignment in applicable This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned NRC FORM 366 |
| | |
| | NRC FOR) 3BBA |
| | '(5-'92) |
| | LICENSEE EVENT REPORT (LER) |
| | U.S. NUCLEAR REGULATORY COMMISSION t APPROVED BY OMB NO. |
| | EXPIRES 3(600'(04 5/31/95 ESTIMATED BURDEN PER RESPOHSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 KRS ~ |
| | FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (MHBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503. |
| | FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (B) PAGE (3) |
| | Shearon Harris Nuclear Plant YEAR. SEQUEHTIAL REVISION Unit Nl 05000/400 2 OF 4 93 007 01 TEXT If more s ace is re uired use add(tional co ies of NRC Form 366A (IT) |
| | EVENT DESCRIPTION: |
| | On May 23, 1993 during power ascension following a one day outage, Operators were swapping auxiliary loads from the Startup Transformers (SUTs) to Unit Auxiliary Transformers (UATs). At 1555 while attempting to swap the loads on Auxiliary Bus 'E', the SUT to Bus 'E'upply breaker 121 failed to open automatically when UAT supply to Bus 'E'reaker 122 was closed. This resulted in Bus 'E'eing supplied by both transformers. |
| | Maintenance and Technical Support personnel were contacted and research efforts to determine possible causes and appropriate corrective action were commenced. A concern was identified associated with circulating currents through both transformers due to the parallel operation, which could result in transformer failure. This concern provided a sense of urgency to take prompt action to open one of the breakers and eliminate the parallel supply line-up. Operators observed normal stable currents through both transformers as indicated on the main control board, and discussed which breaker they would open in the event of rapidly increasing transformer currents. It was concluded that the UAT supply breaker 122 would be opened if this were to occur. This was based on the assumption that the circuitry may not recognize that breaker 122 is actually closed. The control room staff's main focus of concern was the possibility of losing power to Aux Bus "E", which would result in a loss of Emergency Bus "B-SB". |
| | Following research and troubleshooting efforts by Operations, Maintenance, and Technical Support personnel, a conclusion was reached that breaker 121 should be manually opened. This was recommended to the control room staff and at 1732 breaker 121 was locally opened. Emergency Bus "B-SB" supply breaker 125 immediately tripped open on interlock, deenergizing the bus and resulting in an automatic start and loading of the B-SB Emergency Diesel Generator. |
| | The Auxiliary Feedwater System turbine-driven and "B" motor-driven pumps then automatically started as required, and were subsequently secured to stabilize steam generator levels. In addition, a Containment Ventilation Isolation Signal occurred during the transient due to failure of a power supply fuse for Containment Leak Detection Radiation Monitor, RM-3502A. |
| | The fuse was replaced (per WRY g93-AFKQl) and after successful testing, the monitor was restored and the Containment Ventilation System returned to it's normal alignment. |
| | Upon subsequent inspection of breaker 122, Maintenance personnel discovered that the Mechanism Operated Cell (MOC) switch was in the "Breaker OPEN" position. This MOC switch is physically located on the inside wall of the breaker cabinet and during the breaker rack-in process engages with an attachment on the left outside corner of the breaker called an actuating NRC FORM 366A 5-92) |
| | |
| | (IRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160 0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MITM THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. |
| | FORMARD COMMENTS REGARDING BURDEH ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MNBB 7714)i U ~ S ~ NUCLEAR REGULATORY COMMISSIONi HASHINGTOH, DC 20555-0001, AND TO THE PAPERNORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET MASNINGTON DC 20503. |
| | FACILITY NAME I1) DOCKET NUMBER I2) LER NUMBER (6) PAGE I3) |
| | Shearon Harris Nuclear Plant . |
| | YEAR SEQUEHTIAL REVISION Unit ¹1 05000/400 3 OF 4 93 007 01 TEXT If more s ace is r uired use additional co ies of NRC Form 366A I)7) |
| | EVENT DESCRIPTION: (Cont.) |
| | When properly aligned and engaged this switch rotates electrical contacts when the breaker is opened or closed. The MOC switch was in the "Breaker OPEN" position due to these components being misaligned as a result of the last rack-out / rack-in evolution. Therefore, when breaker 121 was locally opened, with the MOC switch in breaker 122 not properly engaged, both breakers erroneously appeared open to the interlock logic and breaker 125 tripped open automatically. Although misalignment was until evident,. the MOC switch had to be engaged with the breaker, at leas up auxiliary loads were swapped from the UATs to SUTs on May 21, 1993; otherwise, breaker 125 would have received a trip signal earlier. Based on this, the MOC switch most likely slipped off the MOC actuating angle either during the previous auxiliary load swap evolution or two days later during this event when breaker 122 was closed. A scar on the damaged MOC actuating angle indicates that the switch most likely slipped off the angle when breaker 122 was closed on May 23, 1993. |
| | CAUSE:- |
| | The cause of this event was the improper alignment of the MOC switch during the rack-in of breaker 122 that occurred on November 20, 1992 anda subsequent contact "slip-off" on May 23, 1993. This condition created false "breaker open" signal and resulted in the automatic trip of breaker 125 on interlock. The following factors contributed to the improper switch alignment; lack of knowledge on the part of operators regarding the proper method for checking MOC alignment during breaker rack-in and inadequate maintenance procedures resulting in improper installation and position verification of the MOC switch and actuating angle. |
| | AFETY SIGNIFICANCE: |
| | There were no safety consequences as a result of this event. The "B" Emergency Diesel Generator started automatically upon the loss of power to the "B" Safety bus and was available for emergency loads. The "B" Essential Services Chilled Water Circulating Pump (P-4) did not automatically start as designed, but did start upon a manual start signal. |
| | This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned actuation'f an Engineered Safety Feature (ESF). Although similar misalignment problems with 6.9 KV breakers have occurred in the past, none have resulted in a reportable condition. Operator training was conducted following an event that occurred in 1988, but was not incorporated into the initial or continuing training programs to ensure a knowledge of this condition was maintained. |
| NRC FORM 366A (5-92) | | NRC FORM 366A (5-92) |
| NRC F&M 366A (5-92)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)t APPROVED BY OMB NO.3160.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME III Shearon Harris Nuclear Plant Unit¹1 DOCKET NUMBER I2I 05000/400 93 007 LER NUMBER I6I YEAR.SEOUENTIAL REVISION 01 PAGE (3I 4 OF 4 CORRECTIVE ACTIONS: 2.3.An inspection of other 6.9 KV breakers was performed. | | |
| to ensure proper MOC switch alignment. | | NRC F&M 366A (5-92) |
| No other discrepancies were identified. | | U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) t APPROVED BY OMB NO. 3160.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS. |
| The problem with the Essential Services Chilled Water Circulating Pump (P-4)was corrected by Work Request and Authorization (WR&A)¹93-AFKP3, which replaced the supply breaker's closing coil.Training has been provided to operations personnel on proper methods to verify MOC switch alignment during 6.9 KV breaker rack-in evolutions. | | FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503. |
| 4~5.6.Initial and Continuing Training programs will be changed to incorporate the training required by corrective action¹3.Maintenance procedures will be developed and revised as necessary to include inspection of MOC switch and actuating angle condition and alignment. | | FACILITY NAME III DOCKET NUMBER I2I LER NUMBER I6I PAGE (3I Shearon Harris Nuclear Plant YEAR. SEOUENTIAL REVISION Unit ¹1 05000/400 4 OF 4 93 007 01 CORRECTIVE ACTIONS: |
| A placard will be installed inside 6.9 KV breakers to indicate the location for conducting MOC alignment verification. | | An inspection of other 6.9 KV breakers was performed. to ensure proper MOC switch alignment. No other discrepancies were identified. |
| EIIS INFORMATION4 ESCW P-4 Pump-KM HRC FORM 366A (5-92) 0~~(}} | | : 2. The problem with the Essential Services Chilled Water Circulating Pump (P-4) was corrected by Work Request and Authorization (WR&A) |
| | ¹93-AFKP3, which replaced the supply breaker's closing coil. |
| | : 3. Training has been provided to operations personnel on proper methods to verify MOC switch alignment during 6.9 KV breaker rack-in evolutions. |
| | 4 ~ Initial and Continuing Training programs will be changed to incorporate the training required by corrective action ¹3. |
| | : 5. Maintenance procedures will be developed and revised as necessary to include inspection of MOC switch and actuating angle condition and alignment. |
| | : 6. A placard will be installed inside 6.9 KV breakers to indicate the location for conducting MOC alignment verification. |
| | EIIS INFORMATION4 ESCW P-4 Pump - KM HRC FORM 366A (5-92) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30
[Table view] |
Text
PCCELERATQD DOCUMENT DIST RUTION SYSTEM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9309010100 DOC.DATE: 93/08/23 NOTARIZED: NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit AUTHOR AFFILIATION l, Carolina 05000400 AUTH. NAME VERILLI,M. Carolina Power & Light Co.
ROBINSON,W.R. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 93-007-01:on 930523,unplanned ESF actuation occurred due to improper alignment of MOC switch. Performed insp to other 6.9 KV breakers.W/930825 ltr. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
/
NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 LE,N 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 RR~SSAQSPLB 1 1 NRR/DSSA/SRXB 1 1 REG FZL~ 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL EG&G BRYCE g J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYFG.A 1 1 NSZC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D
D NOTE TO ALL "Rl DS" RECIPIENTS:
S CONTROL DESK, PLEASE HELP US TO REDUCE WASTE! CON TACf THE DOCUMENT YOUR NAME FROM DISTRIBUTION ROOM Pl-31 (r XT. 504-206 ) TO ELIMINATE LISTS FOR DOCUMENTS YOU DON"f NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32
I C~R Carolina power 8 Ught Company HARRIS NUCLEAR PLANT P.O. Box 165 New Hill, North Carolina 27562 AUG 2 5 isa Letter Number: HO-930149 UPS. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 93-007-01 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within thirty (30) days of a reportable occurrence. This supplement is being submitted to provide additional information related to the unplanned Engineered Safety Feature actuation described in the original report. This report is in accordance with the format set forth in NUREG-1022, September 1983.
Very truly yours, W. R. Robinson General Manager Harris Nuclear Plant MV:smh Enclosure c: Mr. S. D. Ebneter (NRC - RII)
Mr. N. B. Le (NRC - PM/NRR)
Mr. J. E. Tedrow (NRC - SHNPP)
MEM/LER93-007.1/1/OS1 9309010100 930823 PDR ADOCK 05000400 S PDR
NRC FORH,368 U.S. NUCLEAR REGUUITDRY COMMISSION APPROVED BY OMB ND. 3160.0104 EXPIRES 6)31)86 (5-92)
ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH LICENSEE EVENT REPORT (LER) THIS IHFORMATION COLLECTIOH REQUEST: 50.0 HRS.
FORWARD COMHENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MAHAGEHENT BRANCH (See reverse for required naker of digits/characters for each block) (HNBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON~ DC 20555 0001 ~ AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503-FACILITYNAMEII) Shearon Harris Nuclear Plant-Unit ¹1 DOCKET NUMBER 12) PAGE I3) 05000 400 1 OF 4 TITLE(4) Unplanned Engineered Safety Feature Actuation when "B" Emergency Diesel Generator started on loss of ower to the lB-SB Safet Bus.
EVENT DATE(5) I.ER NUMBER 16) REPORT DATE IT) OTHER FACILITIES INVDI.VED IB)
SEQUENTIAL REVISION FACILITY HAME DOCKET NUMBER MONTH DAY YEAR YEAR NUHBER NUMBER MOHTH DAY YEAR 05000 FACILITY NAHE DOCKET NUMBER 5 23 93 93 007 01 8 23 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF.10 CFR 6: (Check one or more) I1
,MODE 19) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL IID) 15% 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 50.73(a)(2)(viii)(B) Abstract below 20.405(a)(1)(iv) 50.73(a)(2)(ii) and in Text, 20.405(a)('l)(v) 50 '3(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)
LICENSEE CONTACT FOR THIS LER ii2)
TELEPHONE NUMBER (Include Area Code)
NAME Michael Verrilli (919) 362-2303 CDMPI.ETE ONE LINE FOR EACH COMPONENT FA)LURE DESCRIBED IN THIS REPORT 113)
";MÃ%0Ã65 REPORTABLE REPORTABLE CAUSE SYSTEH COMPONENT MANUFACTURER CAUSE SYSTEH COMPONENT HANUFACTURER TO NPRDS TO NPRDS g)),.;3:c;)
'.4. s B CL B455 :%(
SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR EXPECTED YES SUBMISSIOH (If yes, complete EXPECTED SUBMISSION DATE). X ND DATE 116)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 116)
On May 23, 1993 the Starts Transformer to Auxiliary Bus E supply breaker 121 failed to open automat3.cally when the corresponding Auxil3.ary Transformer supply breaker 122 was closed. This resulted in both transformers feed3.ng the same bus. After troubleshooting, recommendations were made and action taken to manually open breaker 121. Upon opening breaker 121, emergency bus B- SB supply breaker 125 opened on interlock resulting in deenergizing of the B-SB bus and automatic start and loading of the 'B'mergency"B"Diesel Generator (EDG). The Auxiliary Feedwater System turbine driven and motor drive'n pumps started at this point, as rectuired and were subsequently secured to stabilize steam generator levels.
A Containment Ventilation Isolation Signal also occurred during the transient due to the failure of a radiation monitor supply power fuse.
Breaker 121 failed to automatically open due to a misally.gned Mechanism Operated Cell (MOC) switch in breaker 122, which defeated the auto-open interlock. The cause of this event was determined to be switch insufficient training and procedural controls to ensure that the MOC was properly aligned following maintenance.
Corrective actions will include training, procedure revisions and breakers.
enhancements to ensure proper MOC switch alignment in applicable This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned NRC FORM 366
NRC FOR) 3BBA
'(5-'92)
LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION t APPROVED BY OMB NO.
EXPIRES 3(600'(04 5/31/95 ESTIMATED BURDEN PER RESPOHSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 KRS ~
FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (MHBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.
FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (B) PAGE (3)
Shearon Harris Nuclear Plant YEAR. SEQUEHTIAL REVISION Unit Nl 05000/400 2 OF 4 93 007 01 TEXT If more s ace is re uired use add(tional co ies of NRC Form 366A (IT)
EVENT DESCRIPTION:
On May 23, 1993 during power ascension following a one day outage, Operators were swapping auxiliary loads from the Startup Transformers (SUTs) to Unit Auxiliary Transformers (UATs). At 1555 while attempting to swap the loads on Auxiliary Bus 'E', the SUT to Bus 'E'upply breaker 121 failed to open automatically when UAT supply to Bus 'E'reaker 122 was closed. This resulted in Bus 'E'eing supplied by both transformers.
Maintenance and Technical Support personnel were contacted and research efforts to determine possible causes and appropriate corrective action were commenced. A concern was identified associated with circulating currents through both transformers due to the parallel operation, which could result in transformer failure. This concern provided a sense of urgency to take prompt action to open one of the breakers and eliminate the parallel supply line-up. Operators observed normal stable currents through both transformers as indicated on the main control board, and discussed which breaker they would open in the event of rapidly increasing transformer currents. It was concluded that the UAT supply breaker 122 would be opened if this were to occur. This was based on the assumption that the circuitry may not recognize that breaker 122 is actually closed. The control room staff's main focus of concern was the possibility of losing power to Aux Bus "E", which would result in a loss of Emergency Bus "B-SB".
Following research and troubleshooting efforts by Operations, Maintenance, and Technical Support personnel, a conclusion was reached that breaker 121 should be manually opened. This was recommended to the control room staff and at 1732 breaker 121 was locally opened. Emergency Bus "B-SB" supply breaker 125 immediately tripped open on interlock, deenergizing the bus and resulting in an automatic start and loading of the B-SB Emergency Diesel Generator.
The Auxiliary Feedwater System turbine-driven and "B" motor-driven pumps then automatically started as required, and were subsequently secured to stabilize steam generator levels. In addition, a Containment Ventilation Isolation Signal occurred during the transient due to failure of a power supply fuse for Containment Leak Detection Radiation Monitor, RM-3502A.
The fuse was replaced (per WRY g93-AFKQl) and after successful testing, the monitor was restored and the Containment Ventilation System returned to it's normal alignment.
Upon subsequent inspection of breaker 122, Maintenance personnel discovered that the Mechanism Operated Cell (MOC) switch was in the "Breaker OPEN" position. This MOC switch is physically located on the inside wall of the breaker cabinet and during the breaker rack-in process engages with an attachment on the left outside corner of the breaker called an actuating NRC FORM 366A 5-92)
(IRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160 0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MITM THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORMARD COMMENTS REGARDING BURDEH ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MNBB 7714)i U ~ S ~ NUCLEAR REGULATORY COMMISSIONi HASHINGTOH, DC 20555-0001, AND TO THE PAPERNORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET MASNINGTON DC 20503.
FACILITY NAME I1) DOCKET NUMBER I2) LER NUMBER (6) PAGE I3)
Shearon Harris Nuclear Plant .
YEAR SEQUEHTIAL REVISION Unit ¹1 05000/400 3 OF 4 93 007 01 TEXT If more s ace is r uired use additional co ies of NRC Form 366A I)7)
EVENT DESCRIPTION: (Cont.)
When properly aligned and engaged this switch rotates electrical contacts when the breaker is opened or closed. The MOC switch was in the "Breaker OPEN" position due to these components being misaligned as a result of the last rack-out / rack-in evolution. Therefore, when breaker 121 was locally opened, with the MOC switch in breaker 122 not properly engaged, both breakers erroneously appeared open to the interlock logic and breaker 125 tripped open automatically. Although misalignment was until evident,. the MOC switch had to be engaged with the breaker, at leas up auxiliary loads were swapped from the UATs to SUTs on May 21, 1993; otherwise, breaker 125 would have received a trip signal earlier. Based on this, the MOC switch most likely slipped off the MOC actuating angle either during the previous auxiliary load swap evolution or two days later during this event when breaker 122 was closed. A scar on the damaged MOC actuating angle indicates that the switch most likely slipped off the angle when breaker 122 was closed on May 23, 1993.
CAUSE:-
The cause of this event was the improper alignment of the MOC switch during the rack-in of breaker 122 that occurred on November 20, 1992 anda subsequent contact "slip-off" on May 23, 1993. This condition created false "breaker open" signal and resulted in the automatic trip of breaker 125 on interlock. The following factors contributed to the improper switch alignment; lack of knowledge on the part of operators regarding the proper method for checking MOC alignment during breaker rack-in and inadequate maintenance procedures resulting in improper installation and position verification of the MOC switch and actuating angle.
AFETY SIGNIFICANCE:
There were no safety consequences as a result of this event. The "B" Emergency Diesel Generator started automatically upon the loss of power to the "B" Safety bus and was available for emergency loads. The "B" Essential Services Chilled Water Circulating Pump (P-4) did not automatically start as designed, but did start upon a manual start signal.
This event is being reported per 10CFR50.72(a)(2)(iv) as an unplanned actuation'f an Engineered Safety Feature (ESF). Although similar misalignment problems with 6.9 KV breakers have occurred in the past, none have resulted in a reportable condition. Operator training was conducted following an event that occurred in 1988, but was not incorporated into the initial or continuing training programs to ensure a knowledge of this condition was maintained.
NRC FORM 366A (5-92)
NRC F&M 366A (5-92)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) t APPROVED BY OMB NO. 3160.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.
FACILITY NAME III DOCKET NUMBER I2I LER NUMBER I6I PAGE (3I Shearon Harris Nuclear Plant YEAR. SEOUENTIAL REVISION Unit ¹1 05000/400 4 OF 4 93 007 01 CORRECTIVE ACTIONS:
An inspection of other 6.9 KV breakers was performed. to ensure proper MOC switch alignment. No other discrepancies were identified.
- 2. The problem with the Essential Services Chilled Water Circulating Pump (P-4) was corrected by Work Request and Authorization (WR&A)
¹93-AFKP3, which replaced the supply breaker's closing coil.
- 3. Training has been provided to operations personnel on proper methods to verify MOC switch alignment during 6.9 KV breaker rack-in evolutions.
4 ~ Initial and Continuing Training programs will be changed to incorporate the training required by corrective action ¹3.
- 5. Maintenance procedures will be developed and revised as necessary to include inspection of MOC switch and actuating angle condition and alignment.
- 6. A placard will be installed inside 6.9 KV breakers to indicate the location for conducting MOC alignment verification.
EIIS INFORMATION4 ESCW P-4 Pump - KM HRC FORM 366A (5-92)
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