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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


==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


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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Latest revision as of 06:18, 22 October 2019

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.Training & Procedures revised.W/930825 Ltr
ML18011A119
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/23/1993
From: Robinson W, Verilli M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-930149, LER-93-007, LER-93-7, NUDOCS 9309010100
Download: ML18011A119 (9)
v • d • e


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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