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H. J. Pantva, Jr., Regulatory Technician 91119 415 171-12 111115 connetste one time son sacH cons.o.neset pastume oestmeco ese twee mesent nse apo],f,a Caute tv 8?tw C088Po4897
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On 01/10/85, a routino intnrnal record filn vnrification of the plant l
Survoillanco Tont Schmluling and Tracking System (STSTS) rovanlmi thn channni calibration and functional tant of thn Unit 2 main condonnor low vacuum Instrumentation had not bonn performmt within thn spncif tml monthly aurvuillanco intnrval for tha period of 12/09/84 through 12/16/84. Aftnr this I
dincovery, thn nubject tont, periodic tnut, PT A23, was antisfactority parformnd, vorifying opornbility of tho involvnd instrumentation.
l 2-D21-PTil N056A 1, B-1, C 1, and D 1.
Thonn instrumnnta enunn an automatic closurn of tha unit ranctor main atonm linn inolnLion vntvnn on low vacuum in thn unit main condannnr.
From 12/16/84 through 01/10/85 Unit 2 was in roactor shutdown, startup, and at pownr opnration at various rnnpoctive timen.
Thn minnm! pnrformancn of PT A23 ronutted f rom inndynrtent dnintion of tho PT rncord from thn STSTS computnr data bnno.
A dnfinitiva counn of thn dnlation was not datnrminmi.
A rnview of rmpitrmi rncord entrinn did not rnycal nntrinn which could havn rnnultml in thn daintien of PT A23 for Unit 2.
A comparinon of thn ST8TS data bann with tha procedurn to tho technical apncification crown rnfernnen showed no additional rncords havn bonn doloted which could rnnult in future noncomptinnen through lack of pnrformanco schnduling.
A program for daily comparison and logging of currnnt to thn previous day's numbor of HTHTH rncords wan institutod to hnip onnurn einlations and additions of STSTS rncords arn accountml for.
f.nhancomnnts to tha existing audit trail for indapandent chocks of accuracy in STST8 data nntrinn havn boon intLinted to allow morn offnctivo reviewn and a bottnr mnchaninm to parform ST3TS record number vartfications.
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On January 10, 1985, it was datormined required channel calibration and functional testing of the Unit 2 main condonsor low vacuu:n instrumentation had l
not bnen performed within the speciflod monthly survoillance interval for the period of December 9,1984, through December 16, 1984. This datormination was mado during a routino internal audit and record filo verification of the plant STSTS. Following this discovery, the subject test, periodic test, PT-A23, was satisfactorily performed, thereby verifying operability of the involved instrumentation, 2-D21-PTM-N056A-1, B-1, C-1, and D-1.
Those instrumonts causo automatic closura of the unit main steam lino isolation valvos on low vacuum in the unit's main condonsor. Unit 2 was in reactor shutdown, startup, and at pownr operation at various respectivo times from December 16, 1984, through January 10, 1985.
A review of required STSTS record entrios was porformed to datormina whether entrinn axisted which could havn resulted in the subject dolation of PT-A23.
In addition, a detailed ruview of tho involved computnr program was parformed to dotnrminn if a computer sof twaro failure may have boon involved with the deletion. Thema roviews failed to rovnal a dofinitivo couno for the dolution.
The invnstigation of this event concludod thn missed performanco of PT-A23 l
resulted from an inadvertent deletion of the PT record from the STSTS computer data bano.
A comparison of the STSTS data base with the proceduro to tho technical specification cross refornnce was performnd which showed additional rncords wara not dninted which could result in tuchnient specification noncomplianco i
duo to lack of pnrformanco scheduling.
A program for daily comparison and I
logging of currnnt to thn prnvious day's numbnr of STSTS rncords was institutod.
It in fnit this will holp onsuro STSTS record daintions and additions arn bettnr accounted for.
In addition, thn following changns havn bocn modo to improva the existing audit trail for indopnndent chocks of accuracy in STSTS nntrios and dotationn and to aid in monitoring plant nymtom paramotorn which may affect survoillanen nchnduling:
1.
Rncord Tally Thn curront rncord to total in the computar data bann is comparnd with tha total from thn prnvioun tally (plun all rncords addnd minun all rncords nrannd nincn thn previous tally).
All tally valunn arn dinplayed.
If thn tally volunn do not nurno, a warning monnagn in displaynd and thn audit program aborts, thornby returning to thn computar pnrformanen updato modulo mnnu.
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S_chedulo Flag Tally The number of computer records with a schedulo flag or a stop flag at the last tally is compared with the number of records in the curront data baso having those flags. All tally values are displayed.
If the tally values do not agren, a warning massage is displayed.
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The number of computer records that have a nonblack value in the field frequenr.y at the last tally is compared with the number of records in the current data base with a nonblank entry. All tally values are displayed.
If the tally values do not agroo, a warning message is issued.
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e Cp&L Carolina Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 July 12, 1985 FILE: B09-135100 SERIAL:
BSEP/85-0512 NRC Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 DOCKET NO 50-324 LICENSE NO. DPR 62 REVIS10N 1 TO LICENSEE EVENT REPORT 2-85-001 Gentlemon In accordance with Title 10 to the Codo of Federal Regulations, the enclosed l
revised Licennoo Event Report is submitted. The original report l
fulfilled the requiremont for a written report within thirty (30) days of a reportable occurrence and was submitted in accordance with the format sat forth in NUREG 1022 September 1983.
Very truly yours, I
C. R. blots Conoral Manager Brunswick Steam Electric Plant HJP/dg Enclonura cc: Dr. J. N. Grace i
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| 05000324/LER-1985-001, :on 850110,record File Verification of Plant Surveillance Test Scheduling & Tracking Sys Revealed Periodic Test Not Performed.Caused by Inadvertent Deletion from Data Base.Logging Program Instituted |
- on 850110,record File Verification of Plant Surveillance Test Scheduling & Tracking Sys Revealed Periodic Test Not Performed.Caused by Inadvertent Deletion from Data Base.Logging Program Instituted
| | | 05000325/LER-1985-001, :on 850103,calibr of Reactor Vessel Shroud Level Instruments 1(2)-B21-LTM-N036-1 & N037-1,did Not Meet Design Intent.Caused by Inconsistency in Data Sheets. Instruments Properly Calibr |
- on 850103,calibr of Reactor Vessel Shroud Level Instruments 1(2)-B21-LTM-N036-1 & N037-1,did Not Meet Design Intent.Caused by Inconsistency in Data Sheets. Instruments Properly Calibr
| | | 05000324/LER-1985-001-01, :on 850110,channel Calibr & Functional Test of Main Condenser Low Vacuum Instrumentation Discovered Not Performed within Specified Time.Caused by Deletion of Test from Data Base |
- on 850110,channel Calibr & Functional Test of Main Condenser Low Vacuum Instrumentation Discovered Not Performed within Specified Time.Caused by Deletion of Test from Data Base
| | | 05000324/LER-1985-002-02, :on 850215,HPCI Sys Declared Inoperable Following Testing Which Revealed HPCI Pump Discharge.Valve E41-F006 Would Not Open.Caused by Pump Valve Not Functioning within Calibr Tolerances |
- on 850215,HPCI Sys Declared Inoperable Following Testing Which Revealed HPCI Pump Discharge.Valve E41-F006 Would Not Open.Caused by Pump Valve Not Functioning within Calibr Tolerances
| | | 05000325/LER-1985-002-01, :on 850206,automatic Isolation of Common Control Bldg HVAC Sys Occurred.Caused by Spurious Actuation of Plenum Chlorine Detector 2X-AT-2977.Detector Returned to Svc After Functional Testing |
- on 850206,automatic Isolation of Common Control Bldg HVAC Sys Occurred.Caused by Spurious Actuation of Plenum Chlorine Detector 2X-AT-2977.Detector Returned to Svc After Functional Testing
| | | 05000324/LER-1985-002, :on 850215,HPCI Sys & RHR LPCI Loop B Inoperable.Caused by Mispositioned HPCI Pump Discharge Valve E41-F006 & switch,E11-DPIS-N021B,outside Calibr Tolerances. DPIS-N021B Calibr & F006 Repositioned |
- on 850215,HPCI Sys & RHR LPCI Loop B Inoperable.Caused by Mispositioned HPCI Pump Discharge Valve E41-F006 & switch,E11-DPIS-N021B,outside Calibr Tolerances. DPIS-N021B Calibr & F006 Repositioned
| | | 05000325/LER-1985-003-02, :on 850108,adequate Surveillance Testing Did Not Exist to Verify Operability of Degraded Voltage & Loss of Voltage Regulation Relay Circuitry.On 850110,master-slave Feeder Breakers to Bus Automatically Opened |
- on 850108,adequate Surveillance Testing Did Not Exist to Verify Operability of Degraded Voltage & Loss of Voltage Regulation Relay Circuitry.On 850110,master-slave Feeder Breakers to Bus Automatically Opened
| | | 05000325/LER-1985-003, :on 850108,lack of Adequate Surveillance Test Procedures Discovered for Degraded Voltage & Loss of Voltage Actuation Relay Circuitry.On 850110,groups 3 & 6 Isolations Occurred Due to Loss of Emergency Bus E-1.W/undated Ltr |
- on 850108,lack of Adequate Surveillance Test Procedures Discovered for Degraded Voltage & Loss of Voltage Actuation Relay Circuitry.On 850110,groups 3 & 6 Isolations Occurred Due to Loss of Emergency Bus E-1.W/undated Ltr
| | | 05000324/LER-1985-003-03, :on 850310,unexpected Primary Containment Group 1 Isolation Occurred During Response Time Testing of Main Turbine Stop Valves.Periodic Test PT-45.1.6-2 & Corresponding Response Time Test Revised |
- on 850310,unexpected Primary Containment Group 1 Isolation Occurred During Response Time Testing of Main Turbine Stop Valves.Periodic Test PT-45.1.6-2 & Corresponding Response Time Test Revised
| | | 05000325/LER-1985-004, :on 850110,reactor Water Cleanup Sys Inlet Primary Containment Inboard Isolation Valve 1-G31-F001 Automatically Closed Due to Group 3 Primary Containment Isolation a Subsystem Trip |
- on 850110,reactor Water Cleanup Sys Inlet Primary Containment Inboard Isolation Valve 1-G31-F001 Automatically Closed Due to Group 3 Primary Containment Isolation a Subsystem Trip
| | | 05000324/LER-1985-005-03, :on 850904,reactor Scram Manually Initiated Due to Multiple Control Rod Drift Indications Resulting from Inadvertent Isolation of Air Supply to Control Rod Scram Air Header.Caused by Personnel Error |
- on 850904,reactor Scram Manually Initiated Due to Multiple Control Rod Drift Indications Resulting from Inadvertent Isolation of Air Supply to Control Rod Scram Air Header.Caused by Personnel Error
| | | 05000325/LER-1985-005-01, :on 850212,required Channel Functional Testing of Rod Block Monitors (RBM) Found Inadequate.Caused by Inadequate Plant Procedures.Rev Made to RBM Periodic Test 01.5.1.RBM Downscale Trip Function Tested |
- on 850212,required Channel Functional Testing of Rod Block Monitors (RBM) Found Inadequate.Caused by Inadequate Plant Procedures.Rev Made to RBM Periodic Test 01.5.1.RBM Downscale Trip Function Tested
| | | 05000324/LER-1985-006-02, :on 850906,HPCI Rendered Inoperable Due to auto-closing of Sys Primary Containment Inboard Isolation Valve E41-F002.Caused by Alligator Clip from Test Equipment Leads Slipping Off Terminal Screw |
- on 850906,HPCI Rendered Inoperable Due to auto-closing of Sys Primary Containment Inboard Isolation Valve E41-F002.Caused by Alligator Clip from Test Equipment Leads Slipping Off Terminal Screw
| | | 05000325/LER-1985-006, :on 850111,automatic Isolation of Units 1 & 2 Common Control Bldg HVAC Sys Occurred.Caused by Increased Sensitivity of Detector 1X Due to Lack of Electrolyte. Detector Cleaned |
- on 850111,automatic Isolation of Units 1 & 2 Common Control Bldg HVAC Sys Occurred.Caused by Increased Sensitivity of Detector 1X Due to Lack of Electrolyte. Detector Cleaned
| | | 05000324/LER-1985-007-02, :on 850409,reactor Water Cleanup Sys Inlet Primary Containment Inboard & Outboard Isolation Valves 2-G31-F001 & F004 Closed on Primary Containment Group 3 Isolation Signal |
- on 850409,reactor Water Cleanup Sys Inlet Primary Containment Inboard & Outboard Isolation Valves 2-G31-F001 & F004 Closed on Primary Containment Group 3 Isolation Signal
| | | 05000324/LER-1985-008-01, :on 850927,MSIVs F028A,F022C & F028C Did Not Fast Close During Surveillance Testing.Caused by disc-to- Seat Sticking of Valve Operator Double Solenoid Valves. Double Solenoid Valves Will Be Replaced |
- on 850927,MSIVs F028A,F022C & F028C Did Not Fast Close During Surveillance Testing.Caused by disc-to- Seat Sticking of Valve Operator Double Solenoid Valves. Double Solenoid Valves Will Be Replaced
| | | 05000325/LER-1985-008, :on 850124,reactor Scram Automatically Occurred Due to Main Turbine Trip & Stop Valve Closure Resulting from Vacuum in Main Condenser.Caused by Demineralized Water in Offgas Filter |
- on 850124,reactor Scram Automatically Occurred Due to Main Turbine Trip & Stop Valve Closure Resulting from Vacuum in Main Condenser.Caused by Demineralized Water in Offgas Filter
| | | 05000325/LER-1985-009, :on 850215,monthly Channel Functional Testing of Reactor Bldg Roof Ventilation Monitor Revealed Annunciator Card for Monitor Control Room Alarm Not Installed.Cause Unknown |
- on 850215,monthly Channel Functional Testing of Reactor Bldg Roof Ventilation Monitor Revealed Annunciator Card for Monitor Control Room Alarm Not Installed.Cause Unknown
| | | 05000324/LER-1985-009-02, :on 850930,hi-hi Trip of Reactor Bldg Vent Exhaust Monitor D12-RM-N010B & Upward Spike of Redundant Monitor N010A Occurred.Caused by Crud Movement on Sys Line During Flush.Procedure to Be Revised |
- on 850930,hi-hi Trip of Reactor Bldg Vent Exhaust Monitor D12-RM-N010B & Upward Spike of Redundant Monitor N010A Occurred.Caused by Crud Movement on Sys Line During Flush.Procedure to Be Revised
| | | 05000325/LER-1985-010-01, :on 850318,ventilation Exhaust Radiation Monitors 1(2)-D12-RM-N010A & B Inoperable.Caused by Inherent Problem in Periodic Test-04.1.1.Test Being Revised |
- on 850318,ventilation Exhaust Radiation Monitors 1(2)-D12-RM-N010A & B Inoperable.Caused by Inherent Problem in Periodic Test-04.1.1.Test Being Revised
| | | 05000324/LER-1985-010-02, :on 851009,logic Sys Functional Test Did Not Verify Bypass of 40% Main Steam Isolation Function.Caused by Failure to Recognize Subj Testing Requirement.Function Verified on 851017.Review in Progress |
- on 851009,logic Sys Functional Test Did Not Verify Bypass of 40% Main Steam Isolation Function.Caused by Failure to Recognize Subj Testing Requirement.Function Verified on 851017.Review in Progress
| | | 05000325/LER-1985-011-01, :on 850330,reactor Protection Sys Actuated During Refueling/Maint Outage.Caused by Monitor Circuitry Sensitivity to Cross Talk,Signal Noise & Spiking from Nearby Work.Personnel Advised of Monitor Sensitivity |
- on 850330,reactor Protection Sys Actuated During Refueling/Maint Outage.Caused by Monitor Circuitry Sensitivity to Cross Talk,Signal Noise & Spiking from Nearby Work.Personnel Advised of Monitor Sensitivity
| | | 05000324/LER-1985-011, :on 851015,reactor Pressure Spiked & Unit Auto Scrammed on High Power When MSIV B21-FO22a Auto Closed. Caused by Failure of three-way Solenoid Valve Assembly.Valve Assembly Replaced |
- on 851015,reactor Pressure Spiked & Unit Auto Scrammed on High Power When MSIV B21-FO22a Auto Closed. Caused by Failure of three-way Solenoid Valve Assembly.Valve Assembly Replaced
| | | 05000324/LER-1985-011-02, :on 851015,reactor Scrammed Following Closure of MSIV B21-FO22A.Caused by Dc Solenoid of three-way Valve Failing at Prior Indeterminate Time.Asco Valve Replaced |
- on 851015,reactor Scrammed Following Closure of MSIV B21-FO22A.Caused by Dc Solenoid of three-way Valve Failing at Prior Indeterminate Time.Asco Valve Replaced
| | | 05000324/LER-1985-012-02, :on 851122,unit Scrammed & Automatic Initiation of Primary Containment Groups 2 & 6 Isolation Valves Occurred on Low Level.Possibly Caused by Real or Sensed Flow Perturbation |
- on 851122,unit Scrammed & Automatic Initiation of Primary Containment Groups 2 & 6 Isolation Valves Occurred on Low Level.Possibly Caused by Real or Sensed Flow Perturbation
| | | 05000325/LER-1985-012, :on 850305 & 11,control Bldg Emergency Air Filtration Sys Train 2B Automatically Initiated Due to Fire Alarms.Caused by Personnel Plugging Smoke Detector in Base & Tobacco Smoke,Respectively |
- on 850305 & 11,control Bldg Emergency Air Filtration Sys Train 2B Automatically Initiated Due to Fire Alarms.Caused by Personnel Plugging Smoke Detector in Base & Tobacco Smoke,Respectively
| | | 05000325/LER-1985-013, :on 850307 & 22,control Bldg HVAC Sys Manually Isolated Due to Receipt of High Chlorine Alarms at Chlorination Sys Storage Location.Cause Not Determined |
- on 850307 & 22,control Bldg HVAC Sys Manually Isolated Due to Receipt of High Chlorine Alarms at Chlorination Sys Storage Location.Cause Not Determined
| | | 05000324/LER-1985-013-02, :on 851205,RWCU Sys Inlet Outboard Isolation Valve 2-G31-F004 Automatically Closed.Caused by Circuitry Fuse F18 Blowing Due to Undetectable Current Surge.Fuse Replaced & RWCU Sys Returned to Svc |
- on 851205,RWCU Sys Inlet Outboard Isolation Valve 2-G31-F004 Automatically Closed.Caused by Circuitry Fuse F18 Blowing Due to Undetectable Current Surge.Fuse Replaced & RWCU Sys Returned to Svc
| | | 05000324/LER-1985-014-02, :on 851231 & 860101,testing of Mod to Automatic Depressurization Sys Revealed That Sys Logic Timing Relays Out of Timing.Cause Not Determined.Relays Replaced.Setpoint Drift Will Be Evaluated in Future Testing |
- on 851231 & 860101,testing of Mod to Automatic Depressurization Sys Revealed That Sys Logic Timing Relays Out of Timing.Cause Not Determined.Relays Replaced.Setpoint Drift Will Be Evaluated in Future Testing
| | | 05000324/LER-1985-014, :on 851231 & 860101,discovered That Automatic Depressurization Sys a & B Logic Timing Relay K5A Out of Timing.Cause Undetermined.Relays Replaced |
- on 851231 & 860101,discovered That Automatic Depressurization Sys a & B Logic Timing Relay K5A Out of Timing.Cause Undetermined.Relays Replaced
| | | 05000325/LER-1985-014, :on 850309,RCIC Sys Automatically Isolated Due to Actuation of RCIC Equipment Room Ventilation Differential High Temp Instrument 1-E51-DTS-N601A.Caused by Steam Leak on Valve 1-E51-V20.Valve Repaired |
- on 850309,RCIC Sys Automatically Isolated Due to Actuation of RCIC Equipment Room Ventilation Differential High Temp Instrument 1-E51-DTS-N601A.Caused by Steam Leak on Valve 1-E51-V20.Valve Repaired
| | | 05000325/LER-1985-015, :on 850403,05,09,10,11,17 & 30,six Automatic & Three Manual Isolations of Units 1 & 2 Common Control Bldg (Cb) HVAC Sys Occurred.Caused by Chlorination Bldg Chlorine Alarms.No Evidence of Chlorine Leaks Found |
- on 850403,05,09,10,11,17 & 30,six Automatic & Three Manual Isolations of Units 1 & 2 Common Control Bldg (Cb) HVAC Sys Occurred.Caused by Chlorination Bldg Chlorine Alarms.No Evidence of Chlorine Leaks Found
| | | 05000325/LER-1985-016-01, :on 850923,nonquantifiable Leakage Noted in Primary Containment Isolation Valves 6 1-E11-F020A,B, 1-E21-F001A,B & 1-E21-F031B.Caused by Faulty Seats,Jackings & Discs.Valves Repaired & Returned to Svc |
- on 850923,nonquantifiable Leakage Noted in Primary Containment Isolation Valves 6 1-E11-F020A,B, 1-E21-F001A,B & 1-E21-F031B.Caused by Faulty Seats,Jackings & Discs.Valves Repaired & Returned to Svc
| | | 05000325/LER-1985-018, :on 850420,containment Atmosphere Control Sys Isolation Occurred.On 850426,reactor Water Cleanup Sys Inboard Primary Containment Valve Isolation Occurred |
- on 850420,containment Atmosphere Control Sys Isolation Occurred.On 850426,reactor Water Cleanup Sys Inboard Primary Containment Valve Isolation Occurred
| | | 05000325/LER-1985-019, :on 850515,control Bldg Emergency Air Filtration Sys Train 2A Automatically Initiated.Caused by Accidental Shorting of Fire Detector by Auxiliary Operator. Work Request Initiated to Correct Detector |
- on 850515,control Bldg Emergency Air Filtration Sys Train 2A Automatically Initiated.Caused by Accidental Shorting of Fire Detector by Auxiliary Operator. Work Request Initiated to Correct Detector
| | | 05000325/LER-1985-020, :on 850503 & 0620,problems Identified W/Logic Response Time Testing of Isolation Logic of Main Steam Line Drain Primary Containment Isolation Valves BF21-F016 & F019. Caused by Procedural Overlap |
- on 850503 & 0620,problems Identified W/Logic Response Time Testing of Isolation Logic of Main Steam Line Drain Primary Containment Isolation Valves BF21-F016 & F019. Caused by Procedural Overlap
| 10 CFR 50.73(a)(2)(i) | | 05000325/LER-1985-021, :on 850501,02,10,14 & 16,automatic Isolations of Common Control Bldg HVAC Sys Occurred.Caused by Spurious Actuation of Sys Air Intake Detector.Reservoir Levels in Detectors Restored |
- on 850501,02,10,14 & 16,automatic Isolations of Common Control Bldg HVAC Sys Occurred.Caused by Spurious Actuation of Sys Air Intake Detector.Reservoir Levels in Detectors Restored
| | | 05000325/LER-1985-022, :on 850502,primary Containment Group 6 & Reactor Bldg Ventilation Sys Isolated Due to Trouble Start Control Relay CR-4 Catching Fire.Caused by Relay Coil Insulation Breakdown.Relays Inspected |
- on 850502,primary Containment Group 6 & Reactor Bldg Ventilation Sys Isolated Due to Trouble Start Control Relay CR-4 Catching Fire.Caused by Relay Coil Insulation Breakdown.Relays Inspected
| | | 05000325/LER-1985-023, :on 850502,primary Containment Group 8 Isolation of RHR Sys Shutdown Cooling Inboard Primary Containment Valve 1-E11-F009 Occurred.Caused by Spurious Interruption of Logic Circuitry |
- on 850502,primary Containment Group 8 Isolation of RHR Sys Shutdown Cooling Inboard Primary Containment Valve 1-E11-F009 Occurred.Caused by Spurious Interruption of Logic Circuitry
| | | 05000325/LER-1985-024, :on 850621,common Control Bldg HVAC Sys Manually Isolated.Caused by Spurious Chlorine Alarm W/O Contributory Problems.Sys Returned to Normal Svc |
- on 850621,common Control Bldg HVAC Sys Manually Isolated.Caused by Spurious Chlorine Alarm W/O Contributory Problems.Sys Returned to Normal Svc
| | | 05000325/LER-1985-025, :on 850510,routine Corporate QA Audit of Plant Periodic Test Performances Revealed That from 850128-0321, High Pressure CO2 Fire Extinguishing Sys of Units 1 & 2 Common Control Bldg Inoperable |
- on 850510,routine Corporate QA Audit of Plant Periodic Test Performances Revealed That from 850128-0321, High Pressure CO2 Fire Extinguishing Sys of Units 1 & 2 Common Control Bldg Inoperable
| | | 05000325/LER-1985-026, :on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable |
- on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable
| | | 05000325/LER-1985-027, :on 850513,emergency Diesel Generator 2 Automatically Started Due to Loss of Plant Emergency Ac Bus E-2.Caused by Actuation of Breaker Position Master Linkage. Plant Electricians Received Live Time Training |
- on 850513,emergency Diesel Generator 2 Automatically Started Due to Loss of Plant Emergency Ac Bus E-2.Caused by Actuation of Breaker Position Master Linkage. Plant Electricians Received Live Time Training
| | | 05000325/LER-1985-028, :on 850514,design Error Determined in Standby Gas Treatment Sys Which Would Prevent Automatic Initiation Following Loss of Offsite Power.Plant Mods Will Be Implemented by 850708 |
- on 850514,design Error Determined in Standby Gas Treatment Sys Which Would Prevent Automatic Initiation Following Loss of Offsite Power.Plant Mods Will Be Implemented by 850708
| | | 05000325/LER-1985-029, :on 850515,during Refueling Outage,Primary Containment Group 1 Isolation Occurred While MSIVs Closed. Caused by Shorting of Test Lead to Relay B21-K22,initiating Channel a Logic Trip Signal.Fuses Replaced |
- on 850515,during Refueling Outage,Primary Containment Group 1 Isolation Occurred While MSIVs Closed. Caused by Shorting of Test Lead to Relay B21-K22,initiating Channel a Logic Trip Signal.Fuses Replaced
| | | 05000325/LER-1985-030, :on 850519,Groups 2,6 & 8 Containment Isolation Received When Breaker CB5B in Reactor Protection Sys Power Distribution Panel Opened.Caused by Loss of Power to Components Supplied by Breaker.Labels Revised |
- on 850519,Groups 2,6 & 8 Containment Isolation Received When Breaker CB5B in Reactor Protection Sys Power Distribution Panel Opened.Caused by Loss of Power to Components Supplied by Breaker.Labels Revised
| | | 05000325/LER-1985-031, :on 850523,full Trip of Reactor Protection Sys Channels a & B Occurred.Caused by High Current in Induction Heat Stress Improvement (IHSI) Equipment.Trip Signal Reset. IHSI Cables Shielded & Relocated |
- on 850523,full Trip of Reactor Protection Sys Channels a & B Occurred.Caused by High Current in Induction Heat Stress Improvement (IHSI) Equipment.Trip Signal Reset. IHSI Cables Shielded & Relocated
| | | 05000325/LER-1985-032, :on 850602,during Refueling/Maint Outage,Full Scram Occurred.Caused by Inoperative Signal to Intermediate Power Range Monitor A.Work Request Initiated & Monitor Observed W/No Problems Found |
- on 850602,during Refueling/Maint Outage,Full Scram Occurred.Caused by Inoperative Signal to Intermediate Power Range Monitor A.Work Request Initiated & Monitor Observed W/No Problems Found
| | | 05000325/LER-1985-033, :on 850520,testing Revealed That 9 of 11 Safety Relief Valves Actuated at Higher than Allowed Setpoints. Caused by Friction in Valve Labyrinth Seal Guide Areas. Valves Refurbished,Recertified & Reinstalled |
- on 850520,testing Revealed That 9 of 11 Safety Relief Valves Actuated at Higher than Allowed Setpoints. Caused by Friction in Valve Labyrinth Seal Guide Areas. Valves Refurbished,Recertified & Reinstalled
| | | 05000325/LER-1985-034, :on 850605,primary Containment Isolation of RHR Sys Occurred.Caused by Accidental Bumping of Circuit Fuse F15.Fuse Reinstalled & Isolation Reset |
- on 850605,primary Containment Isolation of RHR Sys Occurred.Caused by Accidental Bumping of Circuit Fuse F15.Fuse Reinstalled & Isolation Reset
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