| | | Reporting criterion |
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| 05000366/LER-1984-001-02, Revised LER 84-001-02:on 840203,during Insp of Torus Interior,Fracture in 54-inch Vent Header Detected.Caused by Matl Being Subj to Temp Below Ndtt.Vent Header Repaired & Procedure Changes &/Or Sys Mods Made | Revised LER 84-001-02:on 840203,during Insp of Torus Interior,Fracture in 54-inch Vent Header Detected.Caused by Matl Being Subj to Temp Below Ndtt.Vent Header Repaired & Procedure Changes &/Or Sys Mods Made | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 05000366/LER-1984-001-01, Revised LER 84-001-01:on 840203,plant Personnel Detected Fracture in 66-inch Vent Header in Bay 5.Caused by Brittle Fracture of Vent Header Matl.Vent Header Will Be Repaired Prior to Startup | Revised LER 84-001-01:on 840203,plant Personnel Detected Fracture in 66-inch Vent Header in Bay 5.Caused by Brittle Fracture of Vent Header Matl.Vent Header Will Be Repaired Prior to Startup | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 05000366/LER-1984-001, :on 840203,personnel Detected Fracture in 66- Inch Vent Header in Bay 5.Caused by Brittle Facture of Vent Header Matl.Vent Header Will Be Repaired & Addl Changes or Sys Mod Will Be Made to Improve Sys |
- on 840203,personnel Detected Fracture in 66- Inch Vent Header in Bay 5.Caused by Brittle Facture of Vent Header Matl.Vent Header Will Be Repaired & Addl Changes or Sys Mod Will Be Made to Improve Sys
| 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2) |
| 05000321/LER-1984-001-01, :on 840211,reactor Scram Followed High Vibration Turbine Trip.Caused by Bucket & Finger Damage to Both 13th Stages of Low Pressure Turbine A.Stage 13 Will Be Replaced at Later Date |
- on 840211,reactor Scram Followed High Vibration Turbine Trip.Caused by Bucket & Finger Damage to Both 13th Stages of Low Pressure Turbine A.Stage 13 Will Be Replaced at Later Date
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-002-01, :on 840224,while Preparing to Close Out Design Change Request,Records for Previous Local Leak Rate Test on Loop a Core Spray Min Flow Valve 1E21-F031A Not Available. Leak Test Failed.Valve Replaced |
- on 840224,while Preparing to Close Out Design Change Request,Records for Previous Local Leak Rate Test on Loop a Core Spray Min Flow Valve 1E21-F031A Not Available. Leak Test Failed.Valve Replaced
| |
| 05000366/LER-1984-002, :on 840220,five Main Steam Safety Relief Valves Failed to Lift in 1% Tolerance Range Required by Tech Specs. Caused by Corrosion Buildup on Pilot Assembly.Safety Relief Valves Calibr |
- on 840220,five Main Steam Safety Relief Valves Failed to Lift in 1% Tolerance Range Required by Tech Specs. Caused by Corrosion Buildup on Pilot Assembly.Safety Relief Valves Calibr
| 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-003-01, :on 840508,fuel Rod F1 Determined to Be in bowed-to-contact Condition Outside Gap Criterion Calculate Design Mcpr.Caused by Crud Induced Localized Corrosion.Fuel Bundle Not Returned to Svc in Reactor |
- on 840508,fuel Rod F1 Determined to Be in bowed-to-contact Condition Outside Gap Criterion Calculate Design Mcpr.Caused by Crud Induced Localized Corrosion.Fuel Bundle Not Returned to Svc in Reactor
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000321/LER-1984-004-01, :on 840327,personnel Found That Scram Discharge Vol High Level Thermal Level Sensors 1C1L-N060 A-D Not Functionally Tested at Required Frequency.Caused by Lack of Procedure.Procedure Written & Implemented |
- on 840327,personnel Found That Scram Discharge Vol High Level Thermal Level Sensors 1C1L-N060 A-D Not Functionally Tested at Required Frequency.Caused by Lack of Procedure.Procedure Written & Implemented
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000321/LER-1984-005, :on 840720,personnel Discovered Numerous Cable Leads Lifted & Not Properly Tagged in Control Room.Caused by Personnel Error & Inadequate Administrative Controls. Procedures Revised |
- on 840720,personnel Discovered Numerous Cable Leads Lifted & Not Properly Tagged in Control Room.Caused by Personnel Error & Inadequate Administrative Controls. Procedures Revised
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000321/LER-1984-005-01, :on 840629,cable Leads Lifted & Improperly Tagged & Separated in Control Room.Caused by Personnel Error.Procedure HNP-6921 Re Cable & Cable Ways Installation Revised to Strengthen Administrative Control |
- on 840629,cable Leads Lifted & Improperly Tagged & Separated in Control Room.Caused by Personnel Error.Procedure HNP-6921 Re Cable & Cable Ways Installation Revised to Strengthen Administrative Control
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000366/LER-1984-005, :on 840525,standby Liquid Control Sys Prvs Lifted at Lower than Expected Pressure When Bench Tested. Design Change Initiated to Replace Existing Prvs W/Prvs of Different Model.One Prv Replaced Thus Far |
- on 840525,standby Liquid Control Sys Prvs Lifted at Lower than Expected Pressure When Bench Tested. Design Change Initiated to Replace Existing Prvs W/Prvs of Different Model.One Prv Replaced Thus Far
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor |
| 05000366/LER-1984-006-01, :on 840716,control Rod Hoist Operation Performed W/O Demonstration Operation of Hoist Interlock.All Hoist Use Suspended.Procedure Revised |
- on 840716,control Rod Hoist Operation Performed W/O Demonstration Operation of Hoist Interlock.All Hoist Use Suspended.Procedure Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-006, :on 840311,while Operating Personnel Were Reducing Reactor Power,Control Rod 50-31 Found to Be Three Position Notches Away from Control Rod 02-23.Reactor Manually Scrammed |
- on 840311,while Operating Personnel Were Reducing Reactor Power,Control Rod 50-31 Found to Be Three Position Notches Away from Control Rod 02-23.Reactor Manually Scrammed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-007, :on 840604,following Turbine Load Reduction, Turbine Stop Valve Fast Closure Reactor Scram Received. Caused by Disc Pump Not Completely Seating on Main Turbine 2.Instrumentation Recalibr |
- on 840604,following Turbine Load Reduction, Turbine Stop Valve Fast Closure Reactor Scram Received. Caused by Disc Pump Not Completely Seating on Main Turbine 2.Instrumentation Recalibr
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-007-01, :on 840908,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated Due to High Differential Temp in Pump Room.Caused by Inboard Seal Leak on Reactor Water Cleanup Pump 2A.Pump Repaired |
- on 840908,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated Due to High Differential Temp in Pump Room.Caused by Inboard Seal Leak on Reactor Water Cleanup Pump 2A.Pump Repaired
| 10 CFR 50.73(a)(2) |
| 05000321/LER-1984-008, :on 840430,surveillance Coordinator Informed of Apparent Anomaly Re Due Date on Standby Gas Treatment Sys Ventilation & Valve Operability Procedure HNP-2-3655.Caused by Computer Programming Error |
- on 840430,surveillance Coordinator Informed of Apparent Anomaly Re Due Date on Standby Gas Treatment Sys Ventilation & Valve Operability Procedure HNP-2-3655.Caused by Computer Programming Error
| |
| 05000366/LER-1984-009-01, :on 840711,unplanned Automatic Activation Logic of More than One ESF Occurred.Caused by Defective Rev to HNP-2-3191.Procedure Revised to Prevent Unplanned Logic Actuation |
- on 840711,unplanned Automatic Activation Logic of More than One ESF Occurred.Caused by Defective Rev to HNP-2-3191.Procedure Revised to Prevent Unplanned Logic Actuation
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-009, :on 840609,following Cold Shutdown,Reactor Mode Switch Placed in Startup Position.Operating Personnel Determined APRM 15% Flux Scram Test Not Performed within 24 H of Startup |
- on 840609,following Cold Shutdown,Reactor Mode Switch Placed in Startup Position.Operating Personnel Determined APRM 15% Flux Scram Test Not Performed within 24 H of Startup
| 10 CFR 50.73(a)(2)(1) |
| 05000366/LER-1984-010-01, :on 840908,reactor Water Cleanup Inboard & Outboard Isolation Valves Isolated by High Differential Flow Signal.Caused by Demineralizer Not Being Full When Valved. Sys Returned to Svc |
- on 840908,reactor Water Cleanup Inboard & Outboard Isolation Valves Isolated by High Differential Flow Signal.Caused by Demineralizer Not Being Full When Valved. Sys Returned to Svc
| 10 CFR 50.73(a)(2) |
| 05000366/LER-1984-010, :on 840924,reactor Water Cleanup (RWCU) Inboard & Outboard Isolation valves,2G31-F001 & 2G31-F004, Respectively,Isolated Due to High Differential Flow Signal. Caused by RWCU Demineralizer Not Full |
- on 840924,reactor Water Cleanup (RWCU) Inboard & Outboard Isolation valves,2G31-F001 & 2G31-F004, Respectively,Isolated Due to High Differential Flow Signal. Caused by RWCU Demineralizer Not Full
| 10 CFR 50.73(a)(2) |
| 05000321/LER-1984-010, :on 840820 & 22,reactor Water Cleanup (RWCU) Inboard Isolation Valve G31-F001 Closed.Caused by High Ambient RWCU Temp Trip Signal.Room Temp Reduced.Valve Returned to Svc |
- on 840820 & 22,reactor Water Cleanup (RWCU) Inboard Isolation Valve G31-F001 Closed.Caused by High Ambient RWCU Temp Trip Signal.Room Temp Reduced.Valve Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-011, :on 840602,required Monthly Surveillance Not Performed on Fire Hose Station HC-30.Caused by Misinterpretation of Tech Spec Surveillance Program Procedure HNP-831.Procedure Revised |
- on 840602,required Monthly Surveillance Not Performed on Fire Hose Station HC-30.Caused by Misinterpretation of Tech Spec Surveillance Program Procedure HNP-831.Procedure Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-011-01, :on 840620,following Repair of Valve 1E41-F001, HPCI Turbine Isolated During Testing.Caused by Emulsification of HPCI Turbine Lubricating Oil & Broken Ball on Tappet.Hpci Repaired & Returned to Svc |
- on 840620,following Repair of Valve 1E41-F001, HPCI Turbine Isolated During Testing.Caused by Emulsification of HPCI Turbine Lubricating Oil & Broken Ball on Tappet.Hpci Repaired & Returned to Svc
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000366/LER-1984-012, :on 840809,trip Signal to Reactor Water Cleanup Isolation Valve 2G31-F004 Caused Valve to Close.Caused by Failure of Fenwal Type 56100 Temp Switch.Switch Repaired & Recalibr |
- on 840809,trip Signal to Reactor Water Cleanup Isolation Valve 2G31-F004 Caused Valve to Close.Caused by Failure of Fenwal Type 56100 Temp Switch.Switch Repaired & Recalibr
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-012-01, :on 841114 & 20,reactor Protective Sys Logic Actuations Occurred for No Apparent Reason.Further Investigation Revealed No Cause |
- on 841114 & 20,reactor Protective Sys Logic Actuations Occurred for No Apparent Reason.Further Investigation Revealed No Cause
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-012, :on 841114,20 & 1206,reactor Protection Sys Logic Actuation Occurred for No Apparent Reason.Caused by Blown Fuse & Lifted Wire.Fuse in Panel 1H11-P610 & Wire Replaced |
- on 841114,20 & 1206,reactor Protection Sys Logic Actuation Occurred for No Apparent Reason.Caused by Blown Fuse & Lifted Wire.Fuse in Panel 1H11-P610 & Wire Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-013, :on 840729,during Procedure HNP-1-3154,HPCI Malfunctioned & Injected Into Reactor.Caused by Short Circuit Across 1/2 of HPCI Automatic Injection Logic.Hpci Test Jack E41-J1 Inspected & Cleaned |
- on 840729,during Procedure HNP-1-3154,HPCI Malfunctioned & Injected Into Reactor.Caused by Short Circuit Across 1/2 of HPCI Automatic Injection Logic.Hpci Test Jack E41-J1 Inspected & Cleaned
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-013-01, :on 840812,reactor Water Sample Not Obtainable Nor Analyzable for Conductivity,Per Tech Specs,Due to Failed Valve in Sample Line.Caused by Component Failure. Valve Repaired |
- on 840812,reactor Water Sample Not Obtainable Nor Analyzable for Conductivity,Per Tech Specs,Due to Failed Valve in Sample Line.Caused by Component Failure. Valve Repaired
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000366/LER-1984-014, :on 840811,reactor Recirculation Pump Auto Trip Relays 2B21-K43 & 2B21-K43D Discovered Removed from Sockets & Placed in Bottom of Control Panel.Caused by Personnel Error.Relays Reinstalled in Sockets |
- on 840811,reactor Recirculation Pump Auto Trip Relays 2B21-K43 & 2B21-K43D Discovered Removed from Sockets & Placed in Bottom of Control Panel.Caused by Personnel Error.Relays Reinstalled in Sockets
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-014, :on 841011,cracking Found in RCS Pressure Boundary.Caused by IGSCC in 21 of 22 Welds.Five Welds Found Acceptable.Remaining 17 Welds Will Be Repaired Via Weld Overlay |
- on 841011,cracking Found in RCS Pressure Boundary.Caused by IGSCC in 21 of 22 Welds.Five Welds Found Acceptable.Remaining 17 Welds Will Be Repaired Via Weld Overlay
| 10 CFR 50.73(a)(2) |
| 05000321/LER-1984-014-01, :on 841011,unit Shut Down Due to IGSCC of Recirculation Piping & Rhr.Caused by Possible Fabrication &/Or Const Inadequacies.Engineering & Safety Consequence Being Assessed |
- on 841011,unit Shut Down Due to IGSCC of Recirculation Piping & Rhr.Caused by Possible Fabrication &/Or Const Inadequacies.Engineering & Safety Consequence Being Assessed
| 10 CFR 50.73(a)(2) |
| 05000366/LER-1984-015-01, :on 840814,surveillance Required by Tech Spec Section 4.7.8.6 Not Performed within Applicable Time Constraints.Caused by Personnel Error.Personnel Instructed |
- on 840814,surveillance Required by Tech Spec Section 4.7.8.6 Not Performed within Applicable Time Constraints.Caused by Personnel Error.Personnel Instructed
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(c)(2)(1) |
| 05000321/LER-1984-015, :on 840803,reactor Scram Received on Turbine Control Valve Fast Closure Subsequent to Generator Load Rejection.Caused by Component Failure.Safety Relief Valve a Top Works Will Be Replaced |
- on 840803,reactor Scram Received on Turbine Control Valve Fast Closure Subsequent to Generator Load Rejection.Caused by Component Failure.Safety Relief Valve a Top Works Will Be Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-016, :on 840815,spurious LOCA Signal Initiated Four RHR Pumps,Two Core Spray Pumps,Three Diesel Generators & HPCI & Rcic.Caused by Personnel Error in Completing Procedure Data Package |
- on 840815,spurious LOCA Signal Initiated Four RHR Pumps,Two Core Spray Pumps,Three Diesel Generators & HPCI & Rcic.Caused by Personnel Error in Completing Procedure Data Package
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-016-01, :on 840929,reactor Protection Sys Logic Actuation Occurred from Erratic Reactor Water Level a Instruments 1B21-N017A & B.Caused by Air Trapped in Instrument Lines.Variable Leg Backfilled |
- on 840929,reactor Protection Sys Logic Actuation Occurred from Erratic Reactor Water Level a Instruments 1B21-N017A & B.Caused by Air Trapped in Instrument Lines.Variable Leg Backfilled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-017-01, :on 841008,primary Containment Valves & Penetration Discovered Leaking in Excess of Specified Limits.Cause Undetermined.Valves Will Be Repaired Prior to Startup |
- on 841008,primary Containment Valves & Penetration Discovered Leaking in Excess of Specified Limits.Cause Undetermined.Valves Will Be Repaired Prior to Startup
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000321/LER-1984-017, :on 841008,during Performance of Procedure HNP-1-3952,numerous Primary Containment Isolation Valves Exceeded Tech Spec Limits.Caused by Equipment Wear.Valves Repaired,Tested & Returned to Svc |
- on 841008,during Performance of Procedure HNP-1-3952,numerous Primary Containment Isolation Valves Exceeded Tech Spec Limits.Caused by Equipment Wear.Valves Repaired,Tested & Returned to Svc
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000366/LER-1984-017, :on 840918,diesel Generator 2R43-S001A Failed to Start Properly.Caused by Failure to Increase Frequency of Start Tests & Blown Fuse in Field Flashing Circuit.Fuse Replaced & Personnel Counseled |
- on 840918,diesel Generator 2R43-S001A Failed to Start Properly.Caused by Failure to Increase Frequency of Start Tests & Blown Fuse in Field Flashing Circuit.Fuse Replaced & Personnel Counseled
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-018-01, :on 840824,contract Engineering Personnel Noted That Numerous Fire Barrier Penetration Seals Not Functional. Caused by Deficient Penetration Seals.Installation & Repair of Fire Seals Implemented |
- on 840824,contract Engineering Personnel Noted That Numerous Fire Barrier Penetration Seals Not Functional. Caused by Deficient Penetration Seals.Installation & Repair of Fire Seals Implemented
| 10 CFR 50.73(a)(2)(1) |
| 05000366/LER-1984-018-01, :on 841002,util Informed That Johnston Pump Co Standby Svc Water Pump 2P41-C002 Might Not Withstand DBE Because of Incorrect Assumption in Calculation Stress Analysis.Split Ring Removed |
- on 841002,util Informed That Johnston Pump Co Standby Svc Water Pump 2P41-C002 Might Not Withstand DBE Because of Incorrect Assumption in Calculation Stress Analysis.Split Ring Removed
| 10 CFR 50.73(a)(2) |
| 05000366/LER-1984-018, :on 841002,Johnston Pump Co Informed Util That Standby Svc Water Pump 2P41-C002 Might Not Withstand Dbe. Caused by Seismic Analysis Calculation Error.Approved Design Change Request Implemented & Tested |
- on 841002,Johnston Pump Co Informed Util That Standby Svc Water Pump 2P41-C002 Might Not Withstand Dbe. Caused by Seismic Analysis Calculation Error.Approved Design Change Request Implemented & Tested
| 10 CFR 50.73(a)(2) |
| 05000321/LER-1984-019, :on 841011,outer Clamp Missing on Seismic Restraint for RHR Svc Water Pump B (E11-COO1B).Caused by Inadequate Const/Installation.Outer Clamp Replaced During Pump Reassembly |
- on 841011,outer Clamp Missing on Seismic Restraint for RHR Svc Water Pump B (E11-COO1B).Caused by Inadequate Const/Installation.Outer Clamp Replaced During Pump Reassembly
| 10 CFR 50.73(a)(2)(1) |
| 05000321/LER-1984-019-01, :on 841011,outer Clamp on Seismic Restraint for RHR Svc Water Pump E11-C001B Discovered Missing.Caused by Inadequate Const/Installation.Clamp Will Be Replaced During Pump Reassembly |
- on 841011,outer Clamp on Seismic Restraint for RHR Svc Water Pump E11-C001B Discovered Missing.Caused by Inadequate Const/Installation.Clamp Will Be Replaced During Pump Reassembly
| 10 CFR 50.73(a)(2)(1) |
| 05000366/LER-1984-019, :on 840924,outboard Reactor Water Cleanup Sys (RWCU) Primary Containment Isolation Valve 2G31-F004 Closed & RWCU Pump 2G31-C001A Tripped.Caused by Failure of Two ATTS Master Trip Units.New Units Installed |
- on 840924,outboard Reactor Water Cleanup Sys (RWCU) Primary Containment Isolation Valve 2G31-F004 Closed & RWCU Pump 2G31-C001A Tripped.Caused by Failure of Two ATTS Master Trip Units.New Units Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-020-01, :on 841216,Group 2 Isolation Occurred for No Apparent Reason.Two Other Group 2 Isolations Occurred on 841219 & 28.Caused by Normal Grid Voltage Swings |
- on 841216,Group 2 Isolation Occurred for No Apparent Reason.Two Other Group 2 Isolations Occurred on 841219 & 28.Caused by Normal Grid Voltage Swings
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-020, :on 840821,unplanned Full Reactor Protection Sys Actuation Occurred.Caused by Opening Links When Turbine Off Line.Procedure Being Revised |
- on 840821,unplanned Full Reactor Protection Sys Actuation Occurred.Caused by Opening Links When Turbine Off Line.Procedure Being Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-021-01, :on 841019,half Scram Occurred in Channel a Due to Wire Shorted to Live Circuit in Panel H11-P609.Caused by Personnel Error.Scram Condition Cleared.Personnel Counseled to Use Caution While Working |
- on 841019,half Scram Occurred in Channel a Due to Wire Shorted to Live Circuit in Panel H11-P609.Caused by Personnel Error.Scram Condition Cleared.Personnel Counseled to Use Caution While Working
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-021, :on 840921,unit Received Reactor Scram Due to Incomplete Opening of Msiv.Caused by Nitrogen Leak on Pneumatic Sys Solenoid Valve for Inboard MSIV 2B21-F022D. Blown Gasket Replaced |
- on 840921,unit Received Reactor Scram Due to Incomplete Opening of Msiv.Caused by Nitrogen Leak on Pneumatic Sys Solenoid Valve for Inboard MSIV 2B21-F022D. Blown Gasket Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000321/LER-1984-022-01, :on 841112,contract Personnel Accidently Shorted Ground Wires for Contacts 5 & 6 of Initial Fuel Load Trip Relay C71-K13B,causing Fuses C71-F15A & B to Open.Personnel Counseled |
- on 841112,contract Personnel Accidently Shorted Ground Wires for Contacts 5 & 6 of Initial Fuel Load Trip Relay C71-K13B,causing Fuses C71-F15A & B to Open.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000366/LER-1984-022, :on 841006,motor Leads Disconnected to RHR Svc Water Pumps 1E11-COO1B & 1E11-COO1D.Caused by Personnel Error.Personnel Counseled |
- on 841006,motor Leads Disconnected to RHR Svc Water Pumps 1E11-COO1B & 1E11-COO1D.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |