05000237/LER-1984-001, :on 840102,two of Four Redundant Main Steam Line Low Pressure Switches Tripped Below Tech Spec Limits. Caused by Instrument Setpoint Drift.Switches Recalibr |
- on 840102,two of Four Redundant Main Steam Line Low Pressure Switches Tripped Below Tech Spec Limits. Caused by Instrument Setpoint Drift.Switches Recalibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000249/LER-1984-001, :on 840323,reactor Water Level Decreased to Low Level Alarm Point.Coolant Loss Compounded by Two Open Bypass Valves.Procedures Revised to Remind Operators to Close Turbine Valves |
- on 840323,reactor Water Level Decreased to Low Level Alarm Point.Coolant Loss Compounded by Two Open Bypass Valves.Procedures Revised to Remind Operators to Close Turbine Valves
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-001-06, :on 840323,during Reactor Startup,Reactor Water Level Decreased to Low Level Alarm Point,Causing High Neutron Flux Reactor Scram.Cause Not Stated.Bypass Steam Flow Will Be Minimized in Future |
- on 840323,during Reactor Startup,Reactor Water Level Decreased to Low Level Alarm Point,Causing High Neutron Flux Reactor Scram.Cause Not Stated.Bypass Steam Flow Will Be Minimized in Future
| |
05000249/LER-1984-002-10, :on 840326,intermediate Range Monitors 14 & 16 Spiked hi-hi,causing Full Reactor Scram.Caused by Electronic Noise,Inducing Spurious Signals in Circuitry.Scram Signals Reset |
- on 840326,intermediate Range Monitors 14 & 16 Spiked hi-hi,causing Full Reactor Scram.Caused by Electronic Noise,Inducing Spurious Signals in Circuitry.Scram Signals Reset
| |
05000237/LER-1984-002-04, :on 840117,standby Gas Treatment Train B Fan Discharge Damper 2/3-7507B Control Room Indication Found Inoperative.Caused by Tripped Breaker.Breaker Reset & Control Room Indication Restored |
- on 840117,standby Gas Treatment Train B Fan Discharge Damper 2/3-7507B Control Room Indication Found Inoperative.Caused by Tripped Breaker.Breaker Reset & Control Room Indication Restored
| |
05000237/LER-1984-003, :on 840221,during Normal Operation,Core Spray Valve MO-1402-25A Failed to Operate from Control Room.Caused by Mechanical Overload of Gear Housing.Valve Control Circuitry Mod Initiated |
- on 840221,during Normal Operation,Core Spray Valve MO-1402-25A Failed to Operate from Control Room.Caused by Mechanical Overload of Gear Housing.Valve Control Circuitry Mod Initiated
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-003-07, :on 840405,health Physicist Became Separated from Group During Drywell Entry.Primary Containment Integrity Broken for Five Minutes.Caused by Procedural Deficiency.Dap 7-11 Revised |
- on 840405,health Physicist Became Separated from Group During Drywell Entry.Primary Containment Integrity Broken for Five Minutes.Caused by Procedural Deficiency.Dap 7-11 Revised
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-003-05, :on 840221,core Spray Valve MO2-1402-25A Failed to Operate from Control Room.Caused by Cracked Bearing Race & Gear Housing.Work Requests Written to Modify Existing Circuitry |
- on 840221,core Spray Valve MO2-1402-25A Failed to Operate from Control Room.Caused by Cracked Bearing Race & Gear Housing.Work Requests Written to Modify Existing Circuitry
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-004-02, :on 840222,during Procedure DOS 1400-2, Core Spray Valve Operability Test, Core Spray Suction Valve MO-2-1402-3A Failed to Close from Control Room.Caused by Faulty Auxiliary Breaker Contact |
- on 840222,during Procedure DOS 1400-2, Core Spray Valve Operability Test, Core Spray Suction Valve MO-2-1402-3A Failed to Close from Control Room.Caused by Faulty Auxiliary Breaker Contact
| 10 CFR 50.73(a)(2)(i) |
05000249/LER-1984-004-07, :on 840425,reactor Scram Occurred on Protection Sys Channel A.Caused by Misaligned Styrofoam Block Allowing Contact Separation in Relay 590-112B.Relay Contacts Will Be Jumped |
- on 840425,reactor Scram Occurred on Protection Sys Channel A.Caused by Misaligned Styrofoam Block Allowing Contact Separation in Relay 590-112B.Relay Contacts Will Be Jumped
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-004-05, :on 840222,during Core Spray Valve Operability Test DOS 1400-2,core Spray Suction Valve MO-2-1402-3A Failed to Close from Control Room.Caused by Faulty Auxiliary Breaker Contact.Contacts Replaced |
- on 840222,during Core Spray Valve Operability Test DOS 1400-2,core Spray Suction Valve MO-2-1402-3A Failed to Close from Control Room.Caused by Faulty Auxiliary Breaker Contact.Contacts Replaced
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-005-06, :on 840618,security Computer Taken Out Svc, & Fire Detection Alarms Could Not Be Indicated.Caused by Personnel Error.Procedure Will Be Revised to Establish Controls Following Computer Outage |
- on 840618,security Computer Taken Out Svc, & Fire Detection Alarms Could Not Be Indicated.Caused by Personnel Error.Procedure Will Be Revised to Establish Controls Following Computer Outage
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-005-03, :on 840716,during Unit Shutdown for Turbine Repair,Lpci Submarine Door Found Open.Caused by Personnel Error.Doors Secured W/Locking Bar to Prevent Handle Operation |
- on 840716,during Unit Shutdown for Turbine Repair,Lpci Submarine Door Found Open.Caused by Personnel Error.Doors Secured W/Locking Bar to Prevent Handle Operation
| |
05000249/LER-1984-005-07, :on 840716,east LPCI Corner Room Submarine Door Found Open.Caused by Stationmen Working in Area.Door Closed & Tech Specs Requiring Door to Be Closed Emphasized. Annunciators Will Be Installed |
- on 840716,east LPCI Corner Room Submarine Door Found Open.Caused by Stationmen Working in Area.Door Closed & Tech Specs Requiring Door to Be Closed Emphasized. Annunciators Will Be Installed
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-006-04, :on 840208,east LPCI Corner Room Submarine Door Found Open & Unattended.Caused by Personnel Error.Door Immediately Closed & Secured & Signs Hung Emphasizing Tech Spec Requirements |
- on 840208,east LPCI Corner Room Submarine Door Found Open & Unattended.Caused by Personnel Error.Door Immediately Closed & Secured & Signs Hung Emphasizing Tech Spec Requirements
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-006, :on 840208,east LPCI Corner Room Submarine Door to Torus Basement Open & Unattended.Caused by Personnel Error.Personnel Retrained |
- on 840208,east LPCI Corner Room Submarine Door to Torus Basement Open & Unattended.Caused by Personnel Error.Personnel Retrained
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-006-06, :on 840711,reactor Vessel Found Not Vented at Less than 149 F.Caused by Inadvertent Procedure Violation. Reactor Metal Temp Increased.Personnel Reminded of Venting Requirement |
- on 840711,reactor Vessel Found Not Vented at Less than 149 F.Caused by Inadvertent Procedure Violation. Reactor Metal Temp Increased.Personnel Reminded of Venting Requirement
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-007-02, :on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation.Caused by Failure of Servovalve Mechanism.Servovalve Replaced |
- on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation.Caused by Failure of Servovalve Mechanism.Servovalve Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-007-07, :on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation on Main Steam Low Pressure.Caused by Failure of Servovalve (Model 450-1880) Mechanism for Opening & Closing Valve |
- on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation on Main Steam Low Pressure.Caused by Failure of Servovalve (Model 450-1880) Mechanism for Opening & Closing Valve
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-007-06, :on 840628,during Hot Standby,Fuse 2330-702 Removed,Causing Loss of Automatic Control for Lpci/Component Cooling Water Sys HX Delta P.Caused by Wiring Sys Using Same Fuse Circuits |
- on 840628,during Hot Standby,Fuse 2330-702 Removed,Causing Loss of Automatic Control for Lpci/Component Cooling Water Sys HX Delta P.Caused by Wiring Sys Using Same Fuse Circuits
| 10 CFR 50.73(a)(2)(vi) |
05000237/LER-1984-008-04, :on 840530,Cardox Sys Master Valve Not Tested in Automatic Mode.Caused by Lack of Documentation to Verify That Cardox Sys electro-mechanical Master Pilot Valve Operable in Automatic Mode.Procedure Revised |
- on 840530,Cardox Sys Master Valve Not Tested in Automatic Mode.Caused by Lack of Documentation to Verify That Cardox Sys electro-mechanical Master Pilot Valve Operable in Automatic Mode.Procedure Revised
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-008-06, :on 840804,while Opening Valve 1601-58,drywell to Torus Differential Pressure Fell Below Tech Spec Level. Caused by Closed Pressure Control Valve 8599-538.Personnel Counseled |
- on 840804,while Opening Valve 1601-58,drywell to Torus Differential Pressure Fell Below Tech Spec Level. Caused by Closed Pressure Control Valve 8599-538.Personnel Counseled
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-008, :on 840530,during Fire Protection Tech Spec Audit,Lack of Cardox Sys Master Valve Test in Automatic Mode Noted.Surveillance Procedure Revised to Test Valve in Both Manual & Automatic Modes |
- on 840530,during Fire Protection Tech Spec Audit,Lack of Cardox Sys Master Valve Test in Automatic Mode Noted.Surveillance Procedure Revised to Test Valve in Both Manual & Automatic Modes
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-009-05, :on 840621,during Normal Operations,Feedwater Regulating Valve a Operator Vibrated Loose from Valve Stem Coupling.Caused by Vibration of Locknut.Two Sheet Metal Lock Taps Installed |
- on 840621,during Normal Operations,Feedwater Regulating Valve a Operator Vibrated Loose from Valve Stem Coupling.Caused by Vibration of Locknut.Two Sheet Metal Lock Taps Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-009-07, :on 840808,operator Received Alarm Indicating High O2 Concentration in Torus.Caused by Failure of Torus to Reactor Bldg Vacuum Breaker 3-1601-20B Due to Shearing of Flathead Mounting Bolts |
- on 840808,operator Received Alarm Indicating High O2 Concentration in Torus.Caused by Failure of Torus to Reactor Bldg Vacuum Breaker 3-1601-20B Due to Shearing of Flathead Mounting Bolts
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-010-05, :on 840626,during Startup,Feeder Breaker Position in Control Room Lost on Breaker at Bus 29 Which Feeds MCC 28-7 & 29-7.Breaker Inadvertently Tripped.Caused by Loose Wire.Operator Training Conducted |
- on 840626,during Startup,Feeder Breaker Position in Control Room Lost on Breaker at Bus 29 Which Feeds MCC 28-7 & 29-7.Breaker Inadvertently Tripped.Caused by Loose Wire.Operator Training Conducted
| |
05000249/LER-1984-010-06, :on 840821,feedwater Regulating Valve a Operator Vibrated Loose from Valve Steam Coupling,Causing Valve Disc to Fail in Closed Direction,Resulting in Reactor Scram Operator & Valve Stem Reconnected |
- on 840821,feedwater Regulating Valve a Operator Vibrated Loose from Valve Steam Coupling,Causing Valve Disc to Fail in Closed Direction,Resulting in Reactor Scram Operator & Valve Stem Reconnected
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-011-04, :on 840705,several Mechanical Penetrations Found Not Sealed.Fire Watch Established.Penetrations Sealed W/Cerafiber & Vimasco |
- on 840705,several Mechanical Penetrations Found Not Sealed.Fire Watch Established.Penetrations Sealed W/Cerafiber & Vimasco
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-011-05, :on 840822,during Rod Worth Minimizer Prestartup Surveillance,Reactor Scrammed Due to Series of Events.Caused by Lack of Operator Caution While Verifying Mode Switch Position |
- on 840822,during Rod Worth Minimizer Prestartup Surveillance,Reactor Scrammed Due to Series of Events.Caused by Lack of Operator Caution While Verifying Mode Switch Position
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-011, :on 840705,fire Watch Established Due to Discovery of Several Unsealed Mechanical Penetrations.All Penetrations Sealed W/Cerafiber & Vimasco |
- on 840705,fire Watch Established Due to Discovery of Several Unsealed Mechanical Penetrations.All Penetrations Sealed W/Cerafiber & Vimasco
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-012-05, :on 840823,unit Scrammed on Intermediate Range Monitor (IRM) hi-hi W/Companion APRM Downscale When IRMs Inserted.Caused by Personnel Error.Causes & Corrective Actions Investigated |
- on 840823,unit Scrammed on Intermediate Range Monitor (IRM) hi-hi W/Companion APRM Downscale When IRMs Inserted.Caused by Personnel Error.Causes & Corrective Actions Investigated
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-012-04, :on 840709,reactor Scrammed.Caused by Instrument Mechanic Mistakenly Turning Reactor Protective Sys Channel B Instead of Channel a Hydrogen Addition Switch to Off |
- on 840709,reactor Scrammed.Caused by Instrument Mechanic Mistakenly Turning Reactor Protective Sys Channel B Instead of Channel a Hydrogen Addition Switch to Off
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-012, :on 840823,unit Scrammed Due to Operator Failure to Insert Intermediate Range Monitors Prior to APRMs Going Downscale.Caused by Operator Lack of Experience.Shift Mgt Reminded to Review Procedures |
- on 840823,unit Scrammed Due to Operator Failure to Insert Intermediate Range Monitors Prior to APRMs Going Downscale.Caused by Operator Lack of Experience.Shift Mgt Reminded to Review Procedures
| |
05000237/LER-1984-013, :on 840722,reactor Scrammed Due to Opening of Electron Hydraulic Control Sys,Causing Turbine to Trip on Low Oil Pressure.Caused by Personnel Error.Changes Made to Training Program for Newly Hired Attendants |
- on 840722,reactor Scrammed Due to Opening of Electron Hydraulic Control Sys,Causing Turbine to Trip on Low Oil Pressure.Caused by Personnel Error.Changes Made to Training Program for Newly Hired Attendants
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-013-05, :on 840830,reactor Operation Continued While Primary Containment Purge Sys Butterfly Valve 3-1601-63 Out of Svc for Air Leak Repair.Caused by Personnel Error. Outage Cleared & Valve Cycled |
- on 840830,reactor Operation Continued While Primary Containment Purge Sys Butterfly Valve 3-1601-63 Out of Svc for Air Leak Repair.Caused by Personnel Error. Outage Cleared & Valve Cycled
| 10 CFR 50.73(a)(2)(1) |
05000237/LER-1984-013-03, :on 840722,flow Bypass Valve FV-1 of Electro Hydraulic Control Sys Opened Causing Turbine Trip & Reactor Scram.Caused by Personnel Error.Investigation Committee Convened to Review Event |
- on 840722,flow Bypass Valve FV-1 of Electro Hydraulic Control Sys Opened Causing Turbine Trip & Reactor Scram.Caused by Personnel Error.Investigation Committee Convened to Review Event
| |
05000249/LER-1984-014-05, :on 840904,ECCS Surveillances Not Completed Prior to Rendering Loop a Inoperable.Caused by Personnel Error While Taking LPCI Component Cooling Svc Water HX Delta P Valve Out of Svc |
- on 840904,ECCS Surveillances Not Completed Prior to Rendering Loop a Inoperable.Caused by Personnel Error While Taking LPCI Component Cooling Svc Water HX Delta P Valve Out of Svc
| |
05000237/LER-1984-014-03, :on 840109,during Normal Operations,Hpci Turbine Trip Low Pressure Surveillance Dis 2300-3 Performed Late.Caused by Personnel Error.Addl Training Provided |
- on 840109,during Normal Operations,Hpci Turbine Trip Low Pressure Surveillance Dis 2300-3 Performed Late.Caused by Personnel Error.Addl Training Provided
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-015-06, :on 840925,during Planned Unit Shutdown,Reactor Scrammed on Low Condenser Vacuum Caused by Air in-leakage Through Damaged Bellows on Seal Steam Relief Valve Discharge Line.Bellows Replaced |
- on 840925,during Planned Unit Shutdown,Reactor Scrammed on Low Condenser Vacuum Caused by Air in-leakage Through Damaged Bellows on Seal Steam Relief Valve Discharge Line.Bellows Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-015-03, :on 840627,during Startup Operation,Time Pumpdown of Drywell Equipment & Floor Drain Sumps Not Performed at Proper Time.Personnel Involved Given Addl Training |
- on 840627,during Startup Operation,Time Pumpdown of Drywell Equipment & Floor Drain Sumps Not Performed at Proper Time.Personnel Involved Given Addl Training
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-016-05, :on 841014,while Performing DOP 4400-8 Re Circulating Water Flow Reversal,Reactor Scrammed Due to Low Condenser Vacuum.Vacuum Breaker Opened to Prevent Turbine Damage |
- on 841014,while Performing DOP 4400-8 Re Circulating Water Flow Reversal,Reactor Scrammed Due to Low Condenser Vacuum.Vacuum Breaker Opened to Prevent Turbine Damage
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-016-03, :on 840803,2,420 Gallons of Contaminated Water Spilled from Floor Drain Surge Tank Room Sump to Ground. Caused by Overfilling of Tank.Prevention of Operators from Filling Tank Above 90% & Repairs Initiated |
- on 840803,2,420 Gallons of Contaminated Water Spilled from Floor Drain Surge Tank Room Sump to Ground. Caused by Overfilling of Tank.Prevention of Operators from Filling Tank Above 90% & Repairs Initiated
| |
05000249/LER-1984-016, :on 841014,reactor Scram Occurred Due to Low Condenser Vacuum.Caused by Valve 3-4402-A Not Opening Completely.Stem for Valve Lubricated & Valve Cycled Six Times |
- on 841014,reactor Scram Occurred Due to Low Condenser Vacuum.Caused by Valve 3-4402-A Not Opening Completely.Stem for Valve Lubricated & Valve Cycled Six Times
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-017-05, :on 840828,initial Fire Watch Not Completed within 1 H When Fire Detection Sys & Sprinkler Control Room Alarms Inoperable.Caused by Shift Unaware of Limitation. Shift Reviewing Fire Protection Tech Specs |
- on 840828,initial Fire Watch Not Completed within 1 H When Fire Detection Sys & Sprinkler Control Room Alarms Inoperable.Caused by Shift Unaware of Limitation. Shift Reviewing Fire Protection Tech Specs
| 10 CFR 50.73(a)(2)(1) |
05000249/LER-1984-017-06, :on 841014,scram Discharge Vol High Level Bypass Circuit Accidentally Broken,Resulting in Full Reactor Scram.Jumpers Placed on Terminals DD8-DD11 Lost Contact as Removed & Scram Occurred |
- on 841014,scram Discharge Vol High Level Bypass Circuit Accidentally Broken,Resulting in Full Reactor Scram.Jumpers Placed on Terminals DD8-DD11 Lost Contact as Removed & Scram Occurred
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000249/LER-1984-018-03, :on 841020,reactor Scram Occurred Due to Low Feedwater Level.Caused by Bad Switch in Master Controller & Broken Valve.New stem-disc Assembly Installed |
- on 841020,reactor Scram Occurred Due to Low Feedwater Level.Caused by Bad Switch in Master Controller & Broken Valve.New stem-disc Assembly Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-018-04, :on 841004,fire Equipment Monthly Insp Incomplete.Caused by Oversight of Five Missing Items.Five Items Inspected & Surveillance Completed on 841004 |
- on 841004,fire Equipment Monthly Insp Incomplete.Caused by Oversight of Five Missing Items.Five Items Inspected & Surveillance Completed on 841004
| |
05000249/LER-1984-018-05, :on 841020,reactor Scrammed on Low Water Level W/Feedwater Regulating Valve 3A in Auto.Caused by Bad Switch in Reset Circuitry of Controller.Master Controller Replaced |
- on 841020,reactor Scrammed on Low Water Level W/Feedwater Regulating Valve 3A in Auto.Caused by Bad Switch in Reset Circuitry of Controller.Master Controller Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
05000237/LER-1984-019-06, :on 841206,w/unit in Refuel & Inservice Insp in Progress,Welds Located in Reactor Water Cleanup Sys Identified as Having Rejectable Indications.Repairs Will Be Made by Weld Overlay &/Or Pipe Replacement |
- on 841206,w/unit in Refuel & Inservice Insp in Progress,Welds Located in Reactor Water Cleanup Sys Identified as Having Rejectable Indications.Repairs Will Be Made by Weld Overlay &/Or Pipe Replacement
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
05000237/LER-1984-019, :on 841206,w/unit in Refuel & Inservice Insp in Progress,Welds Located in Reactor Water Cleanup Sys Identified as Having Rejectable Indications.Welds Repaired by Weld Overlay or Pipe Replacement |
- on 841206,w/unit in Refuel & Inservice Insp in Progress,Welds Located in Reactor Water Cleanup Sys Identified as Having Rejectable Indications.Welds Repaired by Weld Overlay or Pipe Replacement
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |