| | | Reporting criterion |
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| 05000278/LER-1986-001-02, :on 860203,primary Containment Isolation Sys Group Ii/Iii Outboard Isolation Occurred.Caused by Starting Large Pump Motor While Motor Generator Set Out of Svc. Alternate Feed Changed to Static Inverter |
- on 860203,primary Containment Isolation Sys Group Ii/Iii Outboard Isolation Occurred.Caused by Starting Large Pump Motor While Motor Generator Set Out of Svc. Alternate Feed Changed to Static Inverter
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-001, :on 860203,Group III Outboard Isolation Occurred & half-scram Signal Generated.Caused by Lowered Voltage When Recirculation Pump 2B Started.Alternate Feed to New Static Inverter May Be Changed |
- on 860203,Group III Outboard Isolation Occurred & half-scram Signal Generated.Caused by Lowered Voltage When Recirculation Pump 2B Started.Alternate Feed to New Static Inverter May Be Changed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-001, :on 860101,reactor Protection Sys Initiated Full Reactor Scram.Caused by Incorrect Adjustment to Moisture Separator Drain Tank B Dump Valve Level Controller & Broken Air Supply Line to Tank Valve |
- on 860101,reactor Protection Sys Initiated Full Reactor Scram.Caused by Incorrect Adjustment to Moisture Separator Drain Tank B Dump Valve Level Controller & Broken Air Supply Line to Tank Valve
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-002-02, :on 860217,RWCU Sys Isolated While Unit in Shutdown Mode.Caused by Deenergization of RWCU Sys Nonregenerative HX Outlet Temp Switch by Technicians.Design Change Being Considered |
- on 860217,RWCU Sys Isolated While Unit in Shutdown Mode.Caused by Deenergization of RWCU Sys Nonregenerative HX Outlet Temp Switch by Technicians.Design Change Being Considered
| |
| 05000277/LER-1986-002-01, :on 851224,continuous Fire Watch in M-G Set Lube Oil Room Not Established When Smoke Detectors Bypassed on 851223 Due to Spurious Signals.Continuous Watch Established on 860107 |
- on 851224,continuous Fire Watch in M-G Set Lube Oil Room Not Established When Smoke Detectors Bypassed on 851223 Due to Spurious Signals.Continuous Watch Established on 860107
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1986-003, :on 860219,partial Containment Isolation Occurred When Plant Operator Removed Wrong Fuse While Applying Blocking Permit.Caused by Loose Fuse Label Strip. Label Secured W/Adhesive |
- on 860219,partial Containment Isolation Occurred When Plant Operator Removed Wrong Fuse While Applying Blocking Permit.Caused by Loose Fuse Label Strip. Label Secured W/Adhesive
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-003-02, :on 860219,partial Containment Isolation Occurred When Operator Removed Wrong Fuse While Applying Blocking Permit.Caused by Misleading Fuse Label & Lack of Adequate Operator Attention.Fuse Label Secured |
- on 860219,partial Containment Isolation Occurred When Operator Removed Wrong Fuse While Applying Blocking Permit.Caused by Misleading Fuse Label & Lack of Adequate Operator Attention.Fuse Label Secured
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-003-01, :on 860124,full Reactor Scram Initiated Due to Failure of Diesel Generator E-2.Caused by Failure of Dc Solenoids for MSIVs AO-86B & AO-86D.Solenoids Replaced |
- on 860124,full Reactor Scram Initiated Due to Failure of Diesel Generator E-2.Caused by Failure of Dc Solenoids for MSIVs AO-86B & AO-86D.Solenoids Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-004-01, :on 860124,full Scram Occurred When Recirculation Pump 2A Started.Caused by Voltage Transient. Mod Being Pursued to Change Alternate Feed from E-124-R-C to New Static Inverter |
- on 860124,full Scram Occurred When Recirculation Pump 2A Started.Caused by Voltage Transient. Mod Being Pursued to Change Alternate Feed from E-124-R-C to New Static Inverter
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-004-02, :on 860228,RHR Pump 3D Started Unexpectedly.On 860324,sequence of Events Occurred Again.Caused by Two Grounded Wires Inside Pump Breaker Compartment.Ground Wires Repaired |
- on 860228,RHR Pump 3D Started Unexpectedly.On 860324,sequence of Events Occurred Again.Caused by Two Grounded Wires Inside Pump Breaker Compartment.Ground Wires Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-005-02, :on 860306,low Level Scram & Group II & III Isolations Occurred as Reactor Pressure & Level Adjusted. Caused by Decrease in Main Condenser Vacuum Due to Maint Performed on Pump Drive Shaft |
- on 860306,low Level Scram & Group II & III Isolations Occurred as Reactor Pressure & Level Adjusted. Caused by Decrease in Main Condenser Vacuum Due to Maint Performed on Pump Drive Shaft
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-005-01, :on 860125,during Unit Shutdown,Shutdown Cooling & Head Spray Isolations Occurred While Fuse 16A-F16 in Panel 20C42 Repositioned.Caused by Deenergization of Relay Fed by Fuse.Shutdown Cooling Restored |
- on 860125,during Unit Shutdown,Shutdown Cooling & Head Spray Isolations Occurred While Fuse 16A-F16 in Panel 20C42 Repositioned.Caused by Deenergization of Relay Fed by Fuse.Shutdown Cooling Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-006-02, :on 860304,control Room Annunciator Core Spray Sys I Logic Power Failure Alarmed.Caused by Blown Fuses on Core a Spray Logic Due to Grounded Wires.Fuses Replaced |
- on 860304,control Room Annunciator Core Spray Sys I Logic Power Failure Alarmed.Caused by Blown Fuses on Core a Spray Logic Due to Grounded Wires.Fuses Replaced
| |
| 05000277/LER-1986-006, :on 860201,primary Containment Isolation Sys Group III Outboard Isolation Occurred & Reactor Protection Sys Generated half-scram Signal.Caused by Starting Large Pump Motor While motor-generator Out of Svc |
- on 860201,primary Containment Isolation Sys Group III Outboard Isolation Occurred & Reactor Protection Sys Generated half-scram Signal.Caused by Starting Large Pump Motor While motor-generator Out of Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-006-01, :on 860201,primary Containment Isolation Sys Group Ii/Iii Outboard Isolation Occurred.Caused by Starting Large Pump Motor While Motor Generator Set Out of Svc. Alternate Feed Changed to Static Inverter |
- on 860201,primary Containment Isolation Sys Group Ii/Iii Outboard Isolation Occurred.Caused by Starting Large Pump Motor While Motor Generator Set Out of Svc. Alternate Feed Changed to Static Inverter
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-007-02, :on 860305,during Performance of Routine Test RT 5.31, Crossaround Relief Valve Setpoint Check, Rod Sequence Control Sys Bypassed W/Reactor at Less than 21% Power.Caused by Procedure Inadequacy |
- on 860305,during Performance of Routine Test RT 5.31, Crossaround Relief Valve Setpoint Check, Rod Sequence Control Sys Bypassed W/Reactor at Less than 21% Power.Caused by Procedure Inadequacy
| |
| 05000277/LER-1986-007-01, :on 860203,Group II & III Outboard Isolation Occurred & half-scram Signal Generated During Shutdown. Caused by Erratic Voltage Control by Rheostat.Trips Reset & Motor Generator Returned to Svc |
- on 860203,Group II & III Outboard Isolation Occurred & half-scram Signal Generated During Shutdown. Caused by Erratic Voltage Control by Rheostat.Trips Reset & Motor Generator Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-007, :on 860203,Group III Outboard Isolation Occurred & half-scram Signal Generated While Unit 2 Shut Down.Caused by Erratic Voltage Control from Rheostat Usage. Surveillance Test Procedure Revised |
- on 860203,Group III Outboard Isolation Occurred & half-scram Signal Generated While Unit 2 Shut Down.Caused by Erratic Voltage Control from Rheostat Usage. Surveillance Test Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-008-02, :on 860304,HPCI Sys Steam Supply Valve MO-3-23-14 Failed to Open During Test.Caused by Disloged Movable Contact on Culter-Hammer Device 538 Relay.Contact Repositioned |
- on 860304,HPCI Sys Steam Supply Valve MO-3-23-14 Failed to Open During Test.Caused by Disloged Movable Contact on Culter-Hammer Device 538 Relay.Contact Repositioned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000277/LER-1986-008-01, :on 860227,Group II & III Outboard Isolation Occurred & half-scram Signal Generated While Unit at 100% Power.Caused by Erratic Voltage Control Associated W/Use of Rheostat for Adjustment |
- on 860227,Group II & III Outboard Isolation Occurred & half-scram Signal Generated While Unit at 100% Power.Caused by Erratic Voltage Control Associated W/Use of Rheostat for Adjustment
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-008, :on 860227,Group III Outboard Isolation Occurred & half-scram Signal Generated.Caused by Reactor Protection Sys B M-G Set Output Voltage Found Lower than Desired.Maint Request Form Issued |
- on 860227,Group III Outboard Isolation Occurred & half-scram Signal Generated.Caused by Reactor Protection Sys B M-G Set Output Voltage Found Lower than Desired.Maint Request Form Issued
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000000/LER-1986-009, Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised | Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised | |
| 05000278/LER-1986-009-02, :on 860318,manual Scram Occurred.Caused by Series of Personnel Errors Involving Failure to Withdraw Correct Control Rod & Verify Proper Position of Control Rod. Personnel Counseled & Procedures Revised |
- on 860318,manual Scram Occurred.Caused by Series of Personnel Errors Involving Failure to Withdraw Correct Control Rod & Verify Proper Position of Control Rod. Personnel Counseled & Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-009-01, :on 860318,reactor Protection Sys Initiated Full Scram Signal While Reactor in Shutdown Mode at 0% Power.Caused by de-energization of Scram Discharge Vol High Water Level Bypass Relays |
- on 860318,reactor Protection Sys Initiated Full Scram Signal While Reactor in Shutdown Mode at 0% Power.Caused by de-energization of Scram Discharge Vol High Water Level Bypass Relays
| |
| 05000277/LER-1986-010-02, :on 860413,containment Isolations Occurred When Startup Source 3 Deenergized.Caused by Transformer 1 Failure,Rupture & Subsequent Fire.Fire Extinguished.Startup Source Restored.Transformer Repaired |
- on 860413,containment Isolations Occurred When Startup Source 3 Deenergized.Caused by Transformer 1 Failure,Rupture & Subsequent Fire.Fire Extinguished.Startup Source Restored.Transformer Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-010-01, :on 860411,automatic Actuation of Reactor Protection Sys & Group 2 & 3 Isolations Occurred.Caused by Feedpump Min Flow Bypass Valves (AO-3139A,B & C) Failure Creating Low Reactor Water Level.Valves Fixed |
- on 860411,automatic Actuation of Reactor Protection Sys & Group 2 & 3 Isolations Occurred.Caused by Feedpump Min Flow Bypass Valves (AO-3139A,B & C) Failure Creating Low Reactor Water Level.Valves Fixed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-011-01, :on 860326,inboard Suction Valve of RWCU Sys Received Unexpected Isolation Signal.Caused by Technicians Testing Wrong Indicating Switch During Surveillance Testing. Instrument Technicians Counseled |
- on 860326,inboard Suction Valve of RWCU Sys Received Unexpected Isolation Signal.Caused by Technicians Testing Wrong Indicating Switch During Surveillance Testing. Instrument Technicians Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-011-02, :on 860425,partial Group III Isolation Occurred Due to Blown Fuse in Primary Containment Isolation Sys.Cause Unknown.Fuse 16A-F20 Replaced |
- on 860425,partial Group III Isolation Occurred Due to Blown Fuse in Primary Containment Isolation Sys.Cause Unknown.Fuse 16A-F20 Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-012-02, :on 860426,full Scram Occurred While Testing 500-kV Line Fault Detection Circuit.Caused by Personnel Error.Personnel Instructed to Exercise More Caution in Performance of Tests |
- on 860426,full Scram Occurred While Testing 500-kV Line Fault Detection Circuit.Caused by Personnel Error.Personnel Instructed to Exercise More Caution in Performance of Tests
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-012-01, :on 860413,partial Group I & II Isolations Occurred Due to Loss of Power to E-22 & E-23 4 Kv Emergency Busses.Caused by Failed Speed Switch Device on E-2 Diesel. Switch Replaced |
- on 860413,partial Group I & II Isolations Occurred Due to Loss of Power to E-22 & E-23 4 Kv Emergency Busses.Caused by Failed Speed Switch Device on E-2 Diesel. Switch Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-013-01, :on 860423,main Turbine Control Valve Fast Closure Scram Occurred During Routine Test.Caused by Trapped Air in Turbine Hydraulic Control Line.Fast Acting Solenoid Valves Replaced |
- on 860423,main Turbine Control Valve Fast Closure Scram Occurred During Routine Test.Caused by Trapped Air in Turbine Hydraulic Control Line.Fast Acting Solenoid Valves Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-013-02, :on 860426,neutron Monitoring Scram Occurred. Caused by Personnel Error While Performing Functional & Calibr Check of intermediate-range Monitors.Operator Disciplined |
- on 860426,neutron Monitoring Scram Occurred. Caused by Personnel Error While Performing Functional & Calibr Check of intermediate-range Monitors.Operator Disciplined
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-014-01, :on 860426,w/unit Shut Down,Scram Discharge Vol High Level Scram Occurred.Caused by Personnel Error.Operator Disciplined |
- on 860426,w/unit Shut Down,Scram Discharge Vol High Level Scram Occurred.Caused by Personnel Error.Operator Disciplined
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-014-02, :on 860618,shutdown Initiated Due to Potential Loss of Emergency Svc Water (Esw).Caused by Need to Repair ESW Pipe Leak Occurring in Inlet to RHR Room Cooler 2A.Pipe Temporarily Repaired & Ultrasonically Tested |
- on 860618,shutdown Initiated Due to Potential Loss of Emergency Svc Water (Esw).Caused by Need to Repair ESW Pipe Leak Occurring in Inlet to RHR Room Cooler 2A.Pipe Temporarily Repaired & Ultrasonically Tested
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1986-015-02, :on 860624,w/unit at 100% Power,Rwcu Sys Automatically Isolated.Caused by Wiring Error Resulting in Blown Fuse in RWCU Sys Electrical Circuit.Fuse Replaced.Mod Initiated to Correct Wiring Deficiency |
- on 860624,w/unit at 100% Power,Rwcu Sys Automatically Isolated.Caused by Wiring Error Resulting in Blown Fuse in RWCU Sys Electrical Circuit.Fuse Replaced.Mod Initiated to Correct Wiring Deficiency
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-015-01, :on 860620,w/unit in Cold Shutdown,Total Combined Leakage of Penetrations & Valves Subj to Type B & C Tests Exceeded Allowable Leak Rate Limit.Caused by Normal Valve Degradation.Valve Packing Replaced |
- on 860620,w/unit in Cold Shutdown,Total Combined Leakage of Penetrations & Valves Subj to Type B & C Tests Exceeded Allowable Leak Rate Limit.Caused by Normal Valve Degradation.Valve Packing Replaced
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1986-016-01, :on 860709,HPCI Sys Declared Inoperable Due to Turbine Control Valve Not Opening Beyond 75%.Caused by Ground in EG-M Control Box.Box Replaced & Sys Returned to Svc |
- on 860709,HPCI Sys Declared Inoperable Due to Turbine Control Valve Not Opening Beyond 75%.Caused by Ground in EG-M Control Box.Box Replaced & Sys Returned to Svc
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000277/LER-1986-016, :on 860709,HPCI Sys Declared Inoperable Due to Turbine Control Valve Not Opening Beyond 75%.Caused by Ground in electro-hydraulic Controls.Control Box Replaced. Failed Box Returned to Mfg for Repairs |
- on 860709,HPCI Sys Declared Inoperable Due to Turbine Control Valve Not Opening Beyond 75%.Caused by Ground in electro-hydraulic Controls.Control Box Replaced. Failed Box Returned to Mfg for Repairs
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000278/LER-1986-016-02, :on 860719,Group II & III Isolations Occurred Due to High Neutron Flux Scram When Startup Source 3 Lost. Caused by Switchyard Fault & Abnormal Configuration of Fault Detection Circuit |
- on 860719,Group II & III Isolations Occurred Due to High Neutron Flux Scram When Startup Source 3 Lost. Caused by Switchyard Fault & Abnormal Configuration of Fault Detection Circuit
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-017-01, :on 860704,both Channels of Rod Block Monitor Bypassed.Caused by Failed Relay Associated W/Control Rod 58-43.Defective Relay Replaced to Return Rod Block Monitor to Svc |
- on 860704,both Channels of Rod Block Monitor Bypassed.Caused by Failed Relay Associated W/Control Rod 58-43.Defective Relay Replaced to Return Rod Block Monitor to Svc
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1986-017-02, :on 860807 & 08,hourly Fire Watches Not Performed in Several Areas.Caused by Personnel Error. Security Personnel Counseled |
- on 860807 & 08,hourly Fire Watches Not Performed in Several Areas.Caused by Personnel Error. Security Personnel Counseled
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1986-018-02, :on 860826,reactor Water Level Transmitter Found Out of Svc.Caused by Personnel Failure to Return Instrument Rack Isolation Valves to Proper post-test Position.Transmitter Valved Into Svc |
- on 860826,reactor Water Level Transmitter Found Out of Svc.Caused by Personnel Failure to Return Instrument Rack Isolation Valves to Proper post-test Position.Transmitter Valved Into Svc
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1986-018-01, :on 860811,reactor Protection Sys Initiated Full Scram on Low Water Level Condition.Caused by Electrical Fault in Circuit Breaker Compartment Due to Abraded Insulation of Cable.Circuit Breaker Replaced |
- on 860811,reactor Protection Sys Initiated Full Scram on Low Water Level Condition.Caused by Electrical Fault in Circuit Breaker Compartment Due to Abraded Insulation of Cable.Circuit Breaker Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1986-019-02, :on 860914,reactor Manually Scrammed Due to High Main Steam Line Radiation.Caused by Resin Injection When Pilter Demineralizer H Placed in Svc.Rwcu Sys Operated to Remove Impurities |
- on 860914,reactor Manually Scrammed Due to High Main Steam Line Radiation.Caused by Resin Injection When Pilter Demineralizer H Placed in Svc.Rwcu Sys Operated to Remove Impurities
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1986-019-01, :on 860808,combined Containment Leak Rate of Penetrations & Valves Subj to Type B & C Tests Determined in Excess of Allowable Limit.Caused by Normal Valve Degradation.Valves Repaired & Retested |
- on 860808,combined Containment Leak Rate of Penetrations & Valves Subj to Type B & C Tests Determined in Excess of Allowable Limit.Caused by Normal Valve Degradation.Valves Repaired & Retested
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1986-020-01, :on 860817,failure to Maintain Cold Shutdown Conditions & Exceeding Torus Vol Limit Discovered.Caused by Poor Planning of Proposed Operation by Station Supervision. GP-12 Revised |
- on 860817,failure to Maintain Cold Shutdown Conditions & Exceeding Torus Vol Limit Discovered.Caused by Poor Planning of Proposed Operation by Station Supervision. GP-12 Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1986-020-02, :on 861007,erroneous Signal in Feedwater Control Sys Generated Feedwater Transient Resulting in Reactor Low Water Level Scram.Caused by Poor Electrical Connection in Temp Element |
- on 861007,erroneous Signal in Feedwater Control Sys Generated Feedwater Transient Resulting in Reactor Low Water Level Scram.Caused by Poor Electrical Connection in Temp Element
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1986-021-01, :on 860813,discovered That Insp & Wire Replacements Performed on Core Spray Sys Min Flow Valve Operators W/O Authorization & Safety Blocking.Caused by Supervisor Error.Supervisor Counseled |
- on 860813,discovered That Insp & Wire Replacements Performed on Core Spray Sys Min Flow Valve Operators W/O Authorization & Safety Blocking.Caused by Supervisor Error.Supervisor Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000278/LER-1986-021-02, :on 861021,water Vol in Suppression Chamber Exceeded Max Tech Spec Limit.Caused by Delay in Performance of HPCI Surveillance Test.Procedure Will Be Revised to Record Water Level During Test |
- on 861021,water Vol in Suppression Chamber Exceeded Max Tech Spec Limit.Caused by Delay in Performance of HPCI Surveillance Test.Procedure Will Be Revised to Record Water Level During Test
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1986-022-01, :on 861013,low Condenser Vacuum Scram Occurred. Caused by Loose Startup Screen Matl Stuck in Valve Seat. Screen Matl Removed.Condensate Pump Suction Lines for Units 2 & 3 Will Be Inspected for Screen Matl |
- on 861013,low Condenser Vacuum Scram Occurred. Caused by Loose Startup Screen Matl Stuck in Valve Seat. Screen Matl Removed.Condensate Pump Suction Lines for Units 2 & 3 Will Be Inspected for Screen Matl
| 10 CFR 50.73(a)(2)(iv), System Actuation |