Pages that link to "05000260/LER-2004-001, Regarding Reactor Scram from Sensed Power Load Unbalance Condition"
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The following pages link to 05000260/LER-2004-001, Regarding Reactor Scram from Sensed Power Load Unbalance Condition:
Displayed 6 items.
- 05000260/LER-2004-001 (redirect page) (← links)
- 05000260/LER-2014-001 (← links)
- 05000296/LER-2004-002 (← links)
- 05000260/LER-2001-003 (← links)
- 05000260/LER-2001-002 (← links)
- 05000260/LER-2001-001 (← links)
- ML051170244 (← links)
- ML051170242 (← links)
- 05000260/LER-1982-019, Forwards LER 82-019/03L-0 (← links)
- 05000260/LER-1982-018, Forwards LER 82-018/03L-0 (← links)
- 05000260/LER-1982-016, Forwards LER 82-016/03L-0 (← links)
- 05000260/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000260/LER-1982-012, Forwards LER 82-012/03L-0 (← links)
- 05000260/LER-1982-029, Forwards LER 82-029/03L-0 (← links)
- 05000260/LER-1982-040, Forwards LER 82-040/01T-0 (← links)
- 05000260/LER-1982-024, Forwards LER 82-024/03L-0 (← links)
- 05000260/LER-1982-010, Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful (← links)
- 05000260/LER-1982-025, Forwards LER 82-025/03L-0 (← links)
- 05000260/LER-1982-022, Forwards LER 82-022/03L-0 (← links)
- 05000260/LER-1981-001, Forwards LER 81-001/01T-0 (← links)
- 05000260/LER-1982-023, Forwards LER 82-023/01T-0 (← links)
- 05000260/LER-1982-020, Forwards LER 82-020/03L-0 (← links)
- 05000260/LER-1983-004, Forwards LER 83-004/01T-0 (← links)
- 05000260/LER-1983-002, Forwards LER 83-002/01T-0 (← links)
- 05000260/LER-1982-038, Forwards LER 82-038/03L-0 (← links)
- 05000260/LER-1982-039, Forwards LER 82-039/01X-0 (← links)
- 05000260/LER-1982-036, Forwards LER 82-036/03L-0 (← links)
- 05000260/LER-1983-010, Forwards LER 83-010/03L-0 (← links)
- 05000260/LER-1983-013, Forwards LER 83-013/03L-0 (← links)
- 05000260/LER-1983-012, Forwards LER 83-012/03L-0 (← links)
- 05000260/LER-1983-005, Forwards LER 83-005/03L-0 (← links)
- 05000260/LER-1982-006, Forwards LER 82-006/03L-0 (← links)
- 05000260/LER-1983-003, Forwards LER 83-003/03L-0 (← links)
- 05000260/LER-1982-034, Forwards LER 82-034/03L-0 (← links)
- 05000260/LER-1982-033, Forwards LER 82-033/03L-0 (← links)
- 05000260/LER-1982-030, Forwards LER 82-030/03L-0 (← links)
- 05000260/LER-1982-032, Forwards LER 82-032/03L-0 (← links)
- 05000260/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000260/LER-1982-037, Forwards LER 82-037/03L-0 (← links)
- 05000260/LER-1983-017, Forwards LER 83-017/03L-0 (← links)
- 05000260/LER-1983-016, Forwards LER 83-016/03L-0 (← links)
- 05000260/LER-1983-015, Forwards LER 83-015/03L-0 (← links)
- 05000260/LER-1983-009, Forwards LER 83-009/03L-0 (← links)
- 05000260/LER-1983-011, Forwards LER 83-011/03L-0 (← links)
- 05000260/LER-1983-008, Forwards LER 83-008/03L-0 (← links)
- 05000260/LER-1981-050, Forwards Updated LER 81-050/03X-3 (← links)
- 05000260/LER-1982-050, Forwards Updated LER 82-050/03X-1 (← links)
- 05000260/LER-1982-007, Forwards LER 82-007/03L-0 (← links)
- 05000260/LER-1982-035, Forwards Updated LER 82-035/03X-1 (← links)
- 05000260/LER-1982-026, Forwards Updated LER 82-026/03X-2 (← links)
- 05000260/LER-1986-003, Corrected Page 2 to LER 86-003-00:on 860226,energized Isolation Logic Tripped.Caused by Personnel Error.Temporary Cover for Protection Against Accidental Bumping of Bus Transfer Switch Provided (← links)
- 05000260/LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing (← links)
- 05000260/LER-1983-014, Forwards LER 83-014/03L-0 (← links)
- 05000260/LER-1981-069, Forwards Updated LER 81-069/03X-1 (← links)
- 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation (← links)
- 05000260/LER-2024-001-01, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure (← links)
- 05000260/LER-2024-001, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure (← links)
- 05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure (← links)
- 05000260/LER-2023-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line (← links)
- 05000260/LER-2021-001-01, Inoperability of a TS-required Main Steam Isolation Valve (← links)
- 05000260/LER-2021-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000260/LER-2021-001, Inoperability of a TS-required Main Steam Isolation Valve (← links)
- 05000260/LER-1989-008, :on 890309,ESF Actuation Occurred Due to Electrical Fault on Unit Station Svc Transformer 2B.Caused by Personnel Not Taking Appropriate Actions.Power Supplies Realigned & Isolation & Actuations Reset (← links)
- 05000260/LER-1989-020, :on 890702,logic Circuit Deenergized During Replacement of Fuse Resulting in Isolation of Reactor Zone Ventilation.Caused by Electricians Incorrectly Jumpering Fuse Prior to Removal.Instruction Revised (← links)
- 05000260/LER-1989-015, :on 890523,absence of Air Flow in RHR Pump Room Cooler Fan Duct 2C Discovered.Fan Verified Rotating Backwards.Caused by Personnel Error.Repairs Made by Rolling Cables & Verifying Proper Direction (← links)
- 05000260/LER-1989-006-02, :on 890331,reactor Protection Sys Deenergized, Resulting in ESF Actuations & Standby Gas Treatment,Control Room Emergency Ventilation & Refuel Zone Isolations.Caused by Personnel Standing on Breaker Cabinet (← links)
- 05000260/LER-1989-019, :890623,loop II of RHR Sys Technically Inoperable When Operability Required by Tech Specs.Caused by Inadequate Tracking & Dispositioning of Test Deficiency. Signature Requirements Added to Test Packages (← links)
- 05000260/LER-1989-026, :on 890810,diesel Generator B Declared Inoperable When Min Air Start Sys Pressure Not Met Due to Air Leak on High Pressure Head of Compressor.Caused by Failure to Reassemble Head Correctly (← links)
- 05000260/LER-1989-004-02, :on 890222,discovered That Previous Week Surveillance of 240-volt Shutdown Boards a & B Batteries Not Performed.Caused by Inadequate Tracking & Personnel Error. Surveillance Tracking Program Will Be Modified (← links)
- 05000260/LER-1989-013, :on 890409,discovered That Manway Covers in RHR Svc Water Pump Rooms a & D Not Bolted Down.Caused by Inadequate Identification of Flood Barriers in Plant Procedures.Procedures Will Be Modified.W/Undated Ltr (← links)
- 05000260/LER-1989-009-01, :on 890411,unplanned Scram & Main Steam Line Isolation Due to Spurious Spikes on Main Steam Line Radiation Monitors.Signal Cables from Radiation Monitors Disconnected to Prevent Spurious Trips (← links)
- 05000260/LER-1989-006-01, :on 890331,unplanned ESF Actuations Occurred Due to Loss of Reactor Protection Sys Motor/Generator Output.Caused by Personnel Standing on Breaker Cabinet. Scaffold Const Procedure Revised (← links)
- 05000260/LER-1989-011, :on 890404,RHR Svc Water Pump Room A-1 Sump Pump Declared Inoperable Due to Problem W/Level Switch Controlling Pump Operation.Caused by Sys Outages in Progress.Rhr Loop II Declared Operable (← links)
- 05000260/LER-1989-012, :on 890405,discovered That RHR Pump Breaker Not Racked Out as Required.Caused by Written Special Requirements Not Being Transmitted to Shift Personnel Prior to Board Transfer (← links)
- 05000260/LER-1989-023, :on 890723,standby Gas Treatment Train C Became Inoperable Due to Diesel Generator 3D Becoming Inoperable. Caused by Equipment Failure.Root Cause of Relative Humidity Heater Circuit Breaker Tripping Undetermined (← links)
- 05000260/LER-1989-018, :on 890606,diesel Generator a Declared Inoperable Resulting in Inoperability of RHR 2A Pump & Failure to Comply W/Tech Specs.Caused by Failure to Detect Damage from Corrosion Debris (← links)
- 05000260/LER-1989-007-02, :on 890317,wiring in Unit Neutron Monitoring Sys Intermediate Range Monitor & Source Range Monitor Found to Be Brittle & Cracked.Caused by Use of Inappropriate Wire.Wiring Replaced (← links)
- 05000260/LER-1989-022, :on 890721,humidity Control Heater Indicating Lights for Standby Gas Treatment Sys Trains a & B Extinguished.Caused by Heater Breakers Placed in Closed Position.Breakers Replaced & Doors Removed (← links)
- 05000260/LER-1989-017, :on 890607,intermediate Range Monitors C,G & H of Neutron Monitoring Sys Received hi-hi Signal.Caused by Failure to Implement Action to Disable Tungsten Inert Gas Auto Start Function.Memo Issued to Managers (← links)
- 05000260/LER-1989-024, :on 890718,contract Engineer Entered High Radiation Area W/O Proper Dose Monitoring Equipment.Caused by Failure to Comply W/Radiation Work Permit.Health Physics Training & Protected Area Access Revoked (← links)
- 05000260/LER-1989-002-01, :on 890120,determined That Existing Support Design for Automatic Depressurization Sys Air Accumulator Pressure Switches Not Seismically Qualified.Design Practices Has Changed Since Const of Plant (← links)
- 05000260/LER-1989-016-01, :on 890530,determined That 480 Volt Shutdown Board 2A Not Maintained in Seismically Qualified Configuration.Caused by Personnel Error.Conduct of Operations Instruction Revised (← links)
- 05000260/LER-1989-016, :on 890530,480-volt Shutdown Board Discovered in Disconnect Position W/Breaker Compartment Open.Caused by Failure to Comply W/Administrative Control Requirements. Compartment Door Closed & Latched (← links)
- 05000260/LER-1989-009, :on 890411,spurious Spikes on Independent Main Steam Line Radiation Monitors Resulted in Full Scram.Cause for Spikes Undetermined.Welding & Grinding in Area Stopped & Scram & Isolation Logic Reset (← links)
- 05000260/LER-1989-015-01, :on 890523,discovered No Air Flow in RHR 2C Pump Room Cooler Fan Duct.Caused by Personnel Error.Proper Fan Rotation Established & Verified.Min Qualification for Personnel Performing Const Test Initiated (← links)
- 05000260/LER-1988-019-01, :on 881214 & 27,discovered That Neutron Source Movement Performed W/O Min Required Trains of stand-by Gas Treatment Sys.Caused by Failure to Track Status of Subj Sys Train Following Performance of Surveillance (← links)
- 05000260/LER-1989-021, :on 890710,determined That Tech Spec 4-h Limiting Condition for Operation Exceeded by 2 Minutes. Caused by Personnel Error.Writers Guides Will Be Reviewed & Revised as Necessary (← links)
- 05000260/LER-1989-010-01, :on 890323,radiation Monitor Experienced Downscale Spike Following Upscale Spike,Resulting in Unplanned ESF Actuations.Caused by Arcing from Exposed Conductors on Communication Line.Cord Taped (← links)
- 05000260/LER-1989-014-01, :on 890518,4 Kv Feeder Breaker Tripped from Indicated Time Overcurrent,Deenergizing 480 Volt Shutdown Board 2A & Associated Loads.Cause of Event Not Determined. Breaker Insp & Target Relays Reset (← links)
- 05000260/LER-2020-001, For Browns Ferry Nuclear Plant, Unit 2, Core Spray System Inoperable for Longer than Permitted by Technical Specifications (← links)
- 05000260/LER-1987-005-03, :on 870725,safety Relief Valve Setpoints Exceeded During Lab Testing.Cause Under Investigation. Relief Valves Tested Satisfactorily After Adjustment, Refurbished,Recertified & Replaced in Sys (← links)
- 05000260/LER-1987-011-02, :on 871101,failure of 2B Reactor Protection Sys Motor Generator Set Motor Initiated Esf.Cause Undetermined. Failed Motor Replaced & Investigation Continuing (← links)
- 05000260/LER-1987-007, :on 870831,restart Test Determined That Drywell Control Air Primary Containment Isolation Valve Actuator Failed to Close on Loss of Motive Air.Caused by Personnel Error.Solenoid Valves Replaced (← links)
- 05000260/LER-1987-010-02, :on 870924,w/unit Defueled & Grinding Work in Progress,Insp Team Discovered Fire Watch Asleep in Drywell. Fire Watch Immediately Awakened & Disciplinary Action Initiated.Personnel Will Be Apprised of Event (← links)
- 05000260/LER-1987-004-03, :on 870624,RWCU Isolated Unexpectedly.Caused by Spurious Signal from Temp Indicating Switch (Tis) Monitoring Water Temp at non-regenerative HX Outlet.Tis Recalibr.W/ (← links)
- 05000260/LER-1989-003-01, :on 890203,discovered That Scram Function for source-range Monitors Not Operational & Two Jumpers Installed in Reactor Protection Sys Logic Not Removed.Caused by Personnel Error.Jumpers Removed (← links)
- 05000260/LER-1987-009-02, :on 870911,while Pressure Switch in RWCU Being Recalibr,Lead from Test Equipment Slipped Out of Connection & Created Short Circuit Which Blew Fuse.Blown Fuse Replaced (← links)
- 05000260/LER-1987-007-03, :on 870831,inboard Isolation Valve for Drywell Control Air Sys Did Not Close on Loss of Motive Air.Caused by Personnel Error.Valves Replaced & Actuators Will Be Modified to Meet Design Requirements (← links)
- 05000260/LER-1986-010, :on 860702,crack Indications Found in 10 Recirculation Sys Reactor Vessel Inlet Nozzle Safe Ends Due to Sensitive Ultrasonic Exam.Caused by Crevice Region Design of Safe Ends.Ends Replaced (← links)
- 05000260/LER-1988-016-01, :on 881209,unplanned Manual Start of RHR Pump Occurred.Caused by Personnel Error.Labeling of RHR Local Controls Will Be Corrected & Licensed Personnel Will Review Event (← links)
- 05000260/LER-1988-050, :on 881214,neutron Source Movement Between Units Spent Fuel Pools Performed W/O Min Standby Gas Treatment Sys Train Technically Operable.Caused by Failure to Track Operability Status.Procedure Revised (← links)
- 05000260/LER-1987-006-03, :on 870821,discovered Fire Watch Asleep.On 870829,determined That Required Fire Watch Not Present for Grinding Activities.Caused by Area Temp & Poor Communication Between Fire Watch,Craft Personnel & Foreman (← links)
- 05000260/LER-1986-014-01, :on 861003,crack Detected & Sized in Reactor Water Cleanup Sys Piping.Caused by Intergranular Stress Corrosion of Sensitized Type 304 Stainless Steel.Weld Will Be Repaired & Further Insp to Be Conducted (← links)
- 05000260/LER-1987-003-03, :on 870503,analysis of Water Sample from Reactor Vessel Found Ph Outside of Tech Spec (TS) Limits.On 870505,conductivity Increased Beyond TS Limits.Rwcu Demineralizers Placed in Svc (← links)
- 05000260/LER-1986-010-02, :on 860702,sensitive Ultrasonic Exam Revealed Crack Indications in Recirculation Sys Reactor Vessel Inlet Nozzle Safe Ends.Corrective Action Proposals Await Development of Acceptance Criteria (← links)
- 05000260/LER-1986-012-02, :on 860918,480-volt Shutdown Board Inadvertently Deenergized When Operator Attempted to Transfer Power from Normal to Alternate.Caused by Loose Wire (← links)
- 05000260/LER-1986-004-02, :on 860421,ESF Actuation Occurred During Replacement of Relay Coil on Reactor motor-operated Valve Board 2B.Caused by Electrician Error.Power Restored to Board & Electrician Cautioned (← links)
- 05000260/LER-1987-001-01, :on 870106,discovered That HPCI Isolation Valve Had Worm Gear w/33:1 Worm Gear Ratio Instead of 60:1 Gear Ratio.Caused by Mfg Error.Correct Valve Installed Prior to Startup (← links)
- 05000260/LER-1986-003-03, :on 860226,electricians Inadvertently Bumped Reactor Protection Sys a Bus Transfer Switch & Caused Half Scram,Partial Primary & Secondary Containment Isolation. Caused by Personnel Error.Isolations Reset (← links)
- 05000260/LER-1978-014-03, HPCI Sys Sustained Damage to High Pressure Pump & Reduction Gear Set Which Drives Low Pressure Pump.Caused by Failure to Open Valve in Lubrication Oil Line.Instruction Revised (← links)
- 05000260/LER-1988-009-03, :on 880909 & 1002,reactor Protection Sys Bus Deenergized,Completing Initiation Logic for Listed Esfs. Caused by Lack of Preventive Maint on Breaker & Board Compartment.Maint Activities to Be Carried Out (← links)
- 05000260/LER-1986-015-02, :on 861209,Trains a & C of Standby Gas Treatment Sys & Train a of Control Room Emergency Ventilation Actuated.Caused by Failed Coil in Relay.Coil Replaced & Safety Sys Reset (← links)
- 05000260/LER-1986-011-02, :on 860718,reactor Protection Sys Tripped Due to Motor Generator (MG) Set Problem.Caused by Excessive Dust Buildup on Motor Intake & Exhaust Vents Precluding Proper Cooling.Mg Set Cleaned (← links)
- 05000260/LER-1986-007-02, :on 860519,Div II Primary Containment Isolation Sys Power Fuse Blew,Causing Inadvertent Secondary Isolation & Initiation of Control Room Emergency Ventilation Sys. Caused by Fuse Failure.Fuse Replaced (← links)
- 05000260/LER-1988-012-03, :on 881013,three Men Observed Firewatch in Drywell in Less than Fully Alert State.Caused by Mgt & Personnel Errors.Firewatches Placed in non-work Status When Mgt Made Aware of Reported Problem (← links)
- 05000260/LER-1988-013-03, :on 881012,unplanned ESF Actuations Occurred. Caused by Power Supply Failure.Power Supply Replaced & Downscale Alarms Cleared.Isolation Reset & Affected Sys Returned to Normal on 881016 (← links)
- 05000260/LER-1988-006-01, :on 880824,reactor Protection Sys (RPS) Circuit Protector 2C2 Tripped,Deenergizing RPS Bus.Cause Not Determined.Reactor Protection Circuit Protector Reset & Firing Board Replaced (← links)
- 05000260/LER-1988-010-03, :on 880915,unplanned ESF Actuation Occurred During Performance of Mod to Primary Containment Isolation Logic.Caused by Personnel Error.Procedure Will Be Written to Require Review of All Scheduled Work (← links)
- 05000260/LER-1987-002-03, :on 870218,drywell Structural Deficiencies Discovered.Caused by Const Differences Between as-built & Designed Drywell Platform.Platform to Be Inspected & Modified as Necessary (← links)
- 05000260/LER-1986-005-02, :on 860403,primary Containment Isolation Occurred.Caused by Insecure Jumper Connections Across Relay & Hampered Relay Access During Surveillance Instruction. Interim Measure Eliminates Jumper Placement (← links)
- 05000260/LER-1986-009-02, :on 860530,local Leak Rate Test on RHR Sys Valve 2-FOV-74-48 Improperly Performed.Caused by Inadequate Review of Sept 1984 Rev to Procedure Which Allowed Improper Valve Lineup.Procedure Revised (← links)
- 05000260/LER-1986-008-02, :on 860606,secondary Containment Isolation & Initiation of Control Emergency Ventilation Sys Occurred When Isolation Sys Power Fuse Blew.Caused by Exposed Wire on Junction Box.Fuse & Wire Repaired (← links)
- 05000260/LER-1986-013-02, :on 860927,unplanned ESF Actuations Occurred Due to Failed Relay in Refueling Zone Vent Exhaust Radiation Trip Logic.Caused by Burned Coil in GE Model CR120A Relay. Relay Replaced (← links)
- 05000260/LER-1988-002-02, :on 880526 & 27,trip of Reactor Protection Sys Bus 2B Feeder Breaker Initiated Esf.Cause Undetermined. Breaker 952 Replaced W/Molded Case Switch (← links)
- 05000260/LER-1988-003-03, :on 880527,rust Found in Lower Containment Spray Header Due to Leaking Isolation Valves.Performance of Hydrostatic Test Stopped,Sys Depressurize & Lower Containment Spray Header Drained (← links)
- 05000260/LER-1988-008-03, :on 880905,transfer to Deenergized Transformer Caused Loss of Power at 2B 480 Volt Shutdown Board & Subsequent Loss of Power at 2B Reactor Protection Sys Bus, Initiating ESF Actuation.Feeder Breaker Closed (← links)
- 05000260/LER-1988-007-03, :on 880904,start of Reactor Protection Sys (RPS) Generator Set 2A Resulted in Loss of Power to RPS Bus 2A.Caused by Personnel Error.Half Scram & Isolations Reset & Sys Returned to Normal (← links)
- 05000260/LER-1988-001-03, :on 880510,diesel Generator 3A Started Due to Inadvertent Start Signal.Caused by Movement of Relay Cycling Causing Boots to Fall Off Contact Arm.Experiments Conducted W/Identical Relays & Boot Matl (← links)
- 05000260/LER-1988-006-03, :on 880824,480-volt Shutdown Board Voltage Transient Initiated Esf.Caused by Voltage Drop on Shutdown Board 2B When LPCI MG Set Returned to Svc.Circuit Protector 2C2 Reset (← links)
- 05000260/LER-1988-005-03, :on 880803,unit Received Spurious Low Reactor Water Level Signals Which Completed Initiation Logic for Reactor Scram.Caused by Procedural Inadequacies.Workplan Procedure Will Be Revised (← links)
- 05000260/LER-1988-004-02, :on 880701,low Reactor Water Level Signal Received by Reactor Protection Sys Resulting in ESF Initiation.Caused by Personnel Error.Sensing Lines Capped, Isolations Reset & Personnel Counseled (← links)
- 05000260/LER-1985-019-03, :on 851213,craftsmen Accidentally Bumped Normal/Alternate Transfer Switch,Causing Momentary Loss of Reactor Protection Sys Bus B.Isolation Signals Reset. Craftsmen Counseled (← links)
- 05000260/LER-1984-005-04, :on 840525,RHR Pump 2C Started Inadvertently While Performing Surveillance Instruction 4.2.B.45A.Caused by Operator Error & Poorly Written Procedure.Procedure & Similar Instructions Will Be Revised (← links)
- 05000260/LER-1985-020-02, :on 851220,mgt Notified That Eight Local Reactor Protection Sys Panels Not Constructed Per Design Drawings.Caused by Failure to Properly Document Actual Constructed Configuration During Const (← links)
- 05000260/LER-1997-001-05, :on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance (← links)
- 05000260/LER-1985-017-03, :on 851120,during Handling of Spent Local Power Range Monitor in Fuel Pool,Instrument Tube Came Too Close to Water Surface,Setting Off Alarms.Radiological Caution Statements Added to Procedure (← links)
- 05000260/LER-1985-016-02, :on 850606,excessive Setpoint Drift Discovered During Bench Testing.On 850722,factory Testing by Automatic Switch Co Confirmed TVA Test Data.Four Switches Returned to Factory (← links)
- 05000260/LER-1985-013-03, :on 851002,during Performance of Plant Surveillance Instruction,Inadvertent Secondary Containment Isolation Occurred When Alternate Feeder Breaker to Shutdown Board Tripped.Caused by Binding Trip Button (← links)
- 05000260/LER-1985-018-03, :on 851106,potential Created to Violate Secondary Containment.Caused by Failure to Provide Positive Control of Containment During Mod of Carbon Steel Piping in Emergency Equipment Cooling Water Sys (← links)
- 05000260/LER-1986-002-02, :on 860205,discovered Momentary Loss of Secondary Containment Due to Personnel Airlock Failure. Caused by Normal Wear in Sticking Solenoid Plunger.Plunger Cleaned & Lubricated.Circuit Tested (← links)
- 05000260/LER-1986-001, :on 851118,spent Fuel Pool Storage Gates Removed While Lead Shielding Blankets in Use.Caused by Inadequate Procedural Controls to Ensure Maint of Safety Evaluation Requirements.Procedures Revised (← links)
- 05000260/LER-1985-004-02, :on 850611,pH Value Below Tech Spec Limits. Cause Unknown.Formal Procedures for Handling of Chemistry Deviations in Special Operating Instructions for Future Safe End Replacement Work Established (← links)
- 05000260/LER-1985-014-03, :on 851024,overcurrent Trip of Reactor Protection Sys Motor Generator Set & Inadvertent Partial Containment Isolation Occurred.Caused by Procedural Deficiency.Plant Maint Instruction Revised (← links)
- 05000260/LER-1985-012-03, :on 850812,during Routine Surveillance Instruction,Esf Actuations Occurred.Caused by Slight Maladjustment of Refuel Zone Exhaust Radiation Monitor RI-90-144 Bug Source Due to Normal Wear (← links)
- 05000260/LER-1985-011-02, :on 850716,reactor Water Cleanup Sys Isolation Occurred When Two Isolation Circuit Fuses Failed During Refueling Outage.Cause Undetermined.Fuses Replaced (← links)
- 05000260/LER-1985-008-04, :on 850711,primary Containment Isolation Sys Group 3 Isolation Occurred When Incorrect Output Breaker of Reactor Protection Sys Motor Generator Set Opened.Caused by Personnel Error (← links)
- 05000260/LER-1985-009-03, :on 850712,during Unit 2 Refuel Outage, Inadvertent Containment Isolation Occurred When 480-V Shutdown Board Transferred to Deenergized Bus.Caused by Personnel Error.Employee Retrained on 850718 (← links)
- 05000260/LER-1985-010-04, :on 850626,inadvertent Secondary Containment Isolation Occurred Due to Failure of Fuse in Panel 9-42. Cause Not Determined.Blown Fuse Replaced.Isolation Signal Reset.Failure Considered Random (← links)
- 05000260/LER-1985-007-03, :on 850627,alternate Feeder Breaker Failed to Close,Resulting in Secondary Containment Isolation & Loss of Reactor Protection Sys Motor Generator.Caused by Breaker Failure Due to Loosened Bolts.Bolts Tightened (← links)
- 05000260/LER-1985-006-04, :on 850620,secondary Containment Isolation Initiated Due to Spike in Refuel Zone Exhaust Channel B Radiation Detector.Cause of Spike Unknown.Detector Successfully surveillance-tested (← links)
- 05000260/LER-1985-004-04, :on 850610,low Ph Value Identified in Reactor Water Chemistry Sample.Caused by Inleakage Into Reactor Water Cleanup Sys.Impurity Removed by Sys Operation (← links)
- 05000260/LER-1985-005-04, :on 850611,reactor Water Cleanup Sys Isolated Due to Blown Fuse.Caused by Electrician Shorting Out Wires on Relay During Removal.Personnel Cautioned.Fuse Replaced. Sys Reset (← links)
- 05000260/LER-1984-007-02, :on 840922,excessive Leakage Occurred on Main Steam Line Isolation Valves B & C.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating & Acceptable Leakage (← links)
- 05000260/LER-1984-007-04, :on 840922,MSIVs B & C Had Excessive Leakage Above Tech Spec Limits.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating. Also Reportable Per Part 21 (← links)
- 05000260/LER-1983-074-03, /03X-3:on 831110,during HPCI Startup,Rupture Occurred in Turbine Exhaust Inner Rupture Diaphragm After Isolation,Due to Auto Initiation Signal.Cause Unknown.Addl Testing to Be Performed (← links)
- 05000260/LER-1984-008-04, :on 841129,IGSCC Indications Found in Recirculation Piping Reactor Water Cleanup Piping & Jet Pump Instrument Nozzles.Affected Welds Will Be Repaired Before Startup (← links)
- 05000260/LER-1985-002-04, :on 850307,during Refueling Outage Initial Test Results Received for Main Steam Relief Valves.Tech Spec Criteria Not Met by Eight Valves.Caused by Pilot Disc Sticking.Valve Setpoints Will Be Reset (← links)
- 05000260/LER-1985-003-04, :on 850227,automatic Scram Occurred When Fuses Removed from Reactor Protection Sys Circuitry During Mod. Caused by Deficient Work Plan.Plan Revised (← links)
- 05000260/LER-1985-001-03, :on 850221,removal of Thermocouple Revealed 1-inch Long Wall Crack at Weld Located at Junction of Recirculation Sys Header & Riser.Cause Unknown.Crack Will Be Repaired by Weld Overlay (← links)
- 05000260/LER-1984-006-03, :on 840616,reactor Scrammed When Main Turbine Tripped on False Main Turbine Oil Tank Low Level Signal. Caused by Inadvertent Actuation of Oil Tank Level Switch. Procedure OI-47 Revised (← links)
- 05000260/LER-1984-004-03, :on 840222,during Startup,Reactor Scrammed. Caused by High Flux Spike on Channels C & F of Intermediate Range Monitors.Plant Written Procedures & Nuclear Engineer Qualification Program Revised (← links)
- 05000260/LER-1984-003-04, :on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment (← links)
- 05000260/LER-1983-082-03, /03L-0:on 831223,during Normal Operation, Recirculation Pump 2A Tripped Due to Actuation of Relay 2A-K21A Neutral Overvoltage.Caused by Gouged Insulation on Phase C Conductor in Cable 2PP1005 (← links)
- 05000260/LER-1950-260-763, /763W:on 760412,five Reed Relays Failed.Four Reed Relays Permit Sequential Selection & Withdrawal of Control Rods & One Permits Two Control Rod Simultaneous Withdrawal. Caused by CP Claire Reed Relay Contact Failure (← links)
- 05000260/LER-1983-078-03, /03L-0:on 831207,while Isolating Valve 1-FCV-74-66 for Maint,Rhr Crosstie Connection Isolated.Caused by Maint Activities on RHR Sys on Units 1 & 3.Crosstie Connection Restored (← links)
- 05000260/LER-1983-063-01, Discovered 2-LT-85-45A (West Side SDIV Level Transmitter) Did Not Initiate Trip When SDIV Level Exceeded 50-gallon Setpoint.Caused by Small Puncture Holes in Module Diaphragm (← links)
- 05000260/LER-1983-077-03, /03L-0:on 831121,during SI 4.1.A-7,switch LIS-3-203A Exceeded Trip Level Setting.Caused by Level Indicating Switch Calibr Drift.Barton Model 288 Switch Recalibr & Returned to Svc (← links)
- 05000260/LER-1983-075-03, /03L-0:on 831116,during Startup,Following Reactor Scram,R Factor Found Below R Setpoint of 1.0.Caused by Xenon Transient Due to Reactor Scram & Pulling of Rods to Prescram Pattern.Rods Inserted (← links)
- 05000260/LER-1983-072-03, /03L-0:on 831108,during Performance of High Flow Steam Line Calibr Functional test,Pdis-1-36B,1-13B & 1-050B Experienced Setpoint Drift.Barton Model 278 Pressure Switches Also Experienced Setpoint Drift (← links)
- 05000260/LER-1983-073-03, /03L-0:on 831128,percent Power/Core Max Limiting Power Density Ratio Found Less than Tech Spec Limit.Caused by Xenon Transient Due to Reactor Scram & Pulling of Rods to Prescram Pattern.Rods Inserted (← links)
- 05000260/LER-1983-066-31, /03L-0:on 831031,operator Observed Low Flow Alarm in Hydrogen Monitor B (H2AN-76-104).Caused by Moisture Collecting in Sample Lines.Lines Blown Down (← links)
- 05000260/LER-1983-067-03, /03L-0:on 831029,operator Observed RHR Loop II Flow Instrumentation Reading Upscale.Caused by Short in GE Type 531 Recorder FR-74-64.Recorder Repaired (← links)
- 05000260/LER-1983-074-01, /01T-0:on 831110,HPCI Sys Initiated,But Immediately Became Inoperable.Caused by Blown Turbine Exhaust Rupture Disc,Fike Model 16-CPV-CBT.Disc Replaced (← links)
- 05000260/LER-1983-071-03, /03L-0:on 831104,while Performing Surveillance Insp 4.2.B-7,2-PS-3-74A Pressure Switch 1 Had as-found Setpoint of 214.43 Psig.Caused by Calibr Drift.Barksdale B 2T-M12SS Switch Recalibr (← links)
- 05000260/LER-1983-065-03, /03L-0:on 831013,reactor Protective Sys Channel a Manually Tripped W/O Performing Functional Test on Scram Discharge Instrument Vol Channel B.Caused by Personnel Oversight.Tech Spec Criteria Stressed (← links)
- 05000260/LER-1983-070-03, /03L-0:on 831103,downstream HEPA MSA Ask 1743-1217 Filters in Standby Gas Treatment Train C Measured 98% DOP Removal.Caused by Degradation & Wear of Filters Through Normal Use.Filters Replaced (← links)
- 05000260/LER-1983-068-03, /03L-0:on 831021,during Normal Operation,Rhr Loop II Flow Instrumentation Pegged Upscale.Caused by Short in GE Type 531 Recorder Which Drove FR-74-64 & FI-74-64 Upscale Causing Fuse to Blow.Fuse Replaced (← links)
- 05000260/LER-1983-064-03, /03L-0:on 831016,during Normal Operation,Operator Observed RHR Loop II Flow Instrumentation Pegged Upscale. Caused by Defective Slidewire in Recorder FR-74-64.Recorder Replaced (← links)
- 05000260/LER-1983-062-03, /03L-0:on 831004,while Performing Surveillance Instruction 4.9.A.1(a),second Starter on Diesel Generator C Engaged W/Diesel While Operating at 900 Rpm.Caused by Air Leak in Solenoid Valve.New Valve Installed (← links)
- 05000260/LER-1983-031-03, Drywell Air Sampling Sys Inoperable After Drywell Leak Detection Radiation Monitor RM-90-256 Sample Pump Tripped.Caused by Fuse Failure Due to Addl Load on Outlet.Use of Outlet Restricted (← links)
- 05000260/LER-1983-059-03, /03L-0:on 830929,drywell Equipment Drain Sump Pump Excessive Operation Annunciation Discovered Alarming Frequently.Caused by Failure of Cycl-flex 60-minute Timer. Timer Replaced & Calibr (← links)
- 05000260/LER-1983-060-03, /03L-0:on 830930,test Bypass Valve FCV-75-50 Exceeded Closure Limit.Caused by Close Tolerance of Valve Limit Switch & Tight Valve Packing.Switch Adjusted (← links)
- 05000260/LER-1983-056-03, /03L-0:on 830920,while Performing SI 4.2.B-57, Discovered That RHR Pump 2C Cooler Fan Would Not Operate. Caused by GE CR124CO28 Overload Relay Tripping.Overload Relay Replaced (← links)
- 05000260/LER-1983-058-03, /03L-0:on 830927,operator Observed Diesel Generator 1C Trouble Alarm.Caused by Failed Control Power Transformer for Immersion Water Heaters & Lube Oil Circulating Pump.Transformer Replaced (← links)
- 05000260/LER-1983-061-01, /01T-0:on 831004,hydrogen Analyzers a & B Removed from Svc to Replace Pump Assembly After Notification from Manufacturer That Assemblies Would Not Perform Per Tech Spec.Caused by Mfg Deficiency (← links)
- 05000260/LER-1983-057-03, /03L-0:on 830923,while Performing S.I.4.9.A.4.b, Undervoltage Start of Diesel Generator,Diesel Generator 1A Oversped & Tripped.Caused by Electronic Governor Inhibited by Logic Breaker Malfunction (← links)
- 05000260/LER-1983-054-03, /03L-0:on 830916,west Side Scram Discharge Vol High Water Level Switch LS-85-45C Would Not Reset Following Scram.Caused by Setpoint Drift.Switch Recalibr (← links)
- 05000260/LER-1983-052-03, /03L-0:on 830827,hydrogen Analyzer B H2AN-76-104 Found Inoperable Due to Loss of Flow.Caused by Residue Collection in Sensing Line,Causing Inboard Isolation Valve to Stick Closed.Line Blown (← links)
- 05000260/LER-1983-050-03, /03L-0:on 830823,while Performing SI4.2.B-57,RHR Pump 2C Cooler Fan Would Not Operate.Caused by Tripping of Overload Relay,Ge Model CR124C028.Overload Relay Reset & Surveillance Instruction Completed (← links)
- 05000260/LER-1984-002-01, :on 840121,during Surveillance Testing,Operator Did Not Ensure Channel B Primary Containment Isolation Sys Reset Before Testing Channel C.Caused by Operator Error. Operator Counseled (← links)
- 05000260/LER-1983-033-03, Following Rod Adjustment & Preconditioning,Linear Heat Generation Rate & MAPLHGR Greater than Tech Spec Limits.Caused by Xenon Transient.Core Flow Reduced (← links)
- 05000260/LER-1983-049-03, /03L-0:on 830725,while Performing Surveillance Instruction 4.2.B-60,core Spray Ne Room Cooler Fan Would Not Operate.Caused by Tripped Overload Relays in Full Voltage Nonreversing Magnetic Starter.Relays Replaced (← links)
- 05000260/LER-1983-047-03, /03L-0:on 830725,during Normal Operation,W/Hpci Removed from Svc to Calibr Tachometer,Hpci Rendered Inoperable.Caused by Wiring Error During Tachometer Calibr. Wires Reterminated.Procedure Revised (← links)
- 05000260/LER-1983-084-03, /03L-0:on 831229,strainer on Pump C3 Became Restricted by Debris & All Flow Lost to North Header.Caused by River Debris.Strainer Cleaned & Pump Returned to Operability (← links)
- 05000260/LER-1983-083-03, /03L-0:on 831229,during Normal Operation,Hydrogen Analyzer B Hydrogen Sample Inlet Pump Discovered Inoperable. Caused by Seized Bearing Due to Improper Bearing Clearance in Metal Bellows Corp Motor Pn 25626 (← links)
- 05000260/LER-1984-001, :on 840108,during RCIC Flow Testing,Rcic Failed to Reach Rated Flow in Required 30 S.Caused by Probable Setpoint Drift.Electronic Governor Control Sys Recalibr (← links)
- 05000260/LER-1983-001-03, /03L-0:on 830128,interlock Providing Rod Withdrawal Block Inoperable When Refuel Platform Moved Over Core.Caused by Failure of Limit Switch 2 Due to Stuck Plunger (← links)
- 05000260/LER-1982-037-03, /03L-0:on 821122,while Performing Local Leak Rate Tests During Refueling Outage,Total as-found Leakage from Primary Containment Found Greater than Allowable,Per Tech Spec 4.7.A.2.g.Caused by Deterioration of Valve Seating (← links)
- 05000260/LER-1983-079-03, /03L-0:on 831212,discovered That Surveillance Instruction 4.2.B-1, Instrumentation That Initiates or Controls Core Standby Cooling Sys,Reactor Low Water Level, Not Performed within Max Frequency Interval (← links)
- 05000260/LER-1983-053-03, /03L-0:on 830907,during Normal Operation,While Performing Whole Core Low Power Range Monitor calibr,P-1 Indicated R Factor Less than Required.Caused by Uncalibr Monitor Due to Changes in Reactor Shape (← links)
- 05000260/LER-1983-022-03, /03L-0:on 830503,scram Discharge Vol Scram Switch Failed to Operate.Reactor Protection Sys Logic Switch Tripped Upon Actuation.Caused by Magnetrol Model Switch Drift Outside Operating Band.Switch Adjusted (← links)
- 05000260/LER-1983-036-03, /03L-0:on 830704,alarm Signal Detected on Reactor Bldg Elevation 593 Fire Protection Panel 2-25-311,Zone 2B, Heat Detector TE-39-46B & Could Have Masked Signals from Other Detectors.Caused by Bent Heat Detector (← links)
- 05000260/LER-1983-037-03, /03L-0:on 830705,increased Vibration & Motor Noise Found Emanating from Rmov Board Motor Generator Set 2EA. Caused by Worn Inboard/Outboard Bearings on Drive Motor. Bearings Replaced & Greased (← links)
- 05000260/LER-1983-035-03, /03L-0:on 830621,during Local Power Range Monitor Calibr,Calculated R Factor,Maplhgr & Linear Heat Generation Rate Limits Exceeded.Caused by Uncalibr Range Monitor Distribution Due to Set Up of New Rod Pattern (← links)
- 05000260/LER-1983-034-03, /03L-0:on 830615,during Normal Operation,Hpci Sys Declared Inoperable.Caused by Blown Inverter Fuse F1. Fuse Replaced.Failure Considered Random (← links)
- 05000260/LER-1983-044-03, /03L-0:on 830712,during Performance of 4.2.B-26, Level Switches LS-73-56A & B Mfg by Robertshaw Failed to Operate Properly.Caused by Dirt in Mechanical Linkage. Switches Cleaned (← links)
- 05000260/LER-1983-043-03, /03L-0:on 830720,during Transient Operation, Following Control Rod Sequence Exchange,R Calculation Less than R Setpoint.Caused by Xenon Transient W/Operation Closer to Thermal Limits.Control Rods Repositioned (← links)
- 05000260/LER-1983-041-03, /03L-0:on 830721,following Preconditioning Operations,Tech Spec Limit for Linear Heat Generation Rate Exceeded in Four Nodes.Caused by Insufficient Communication Between Operators During Flow Increases (← links)
- 05000260/LER-1981-050-03, Containment Atmosphere Torus Hydrogen Analyzer 2-H2M-76-104 Removed from Svc for Corrective Maint.Caused by Water in Sensing Lines.Design Change Request P-2693 Evaluated (← links)
- 05000260/LER-1983-039-03, /03L-0:on 830716,during Transient Operation, Following Control Rod Sequence Exchange & Scram Testing, Program P1 Indicated R Calculated Less than R Setpoint. Caused by Failure of TIP Machine Indexer D (← links)
- 05000260/LER-1983-017-03, /03L-0:on 830409,hydrogen Analyzer B,H2AN-76-104 Declared Inoperable Due to Receipt of loss-of-flow Light 76-88.Caused by Moisture Collecting in Sample Lines.Lines Blown Down & Dried.Moisture Collection Devices to Be Added (← links)
- 05000260/LER-1983-016-03, /03L-0:on 830406,drywell Pressure Switches 2-PS-64-58D,SW 1 & 2 Found to Operate at Setting Exceeding Tech Spec Limit.Caused by Setpoint Drift.Static O-ring Switch 12N-AA4 Recalibr (← links)
- 05000260/LER-1983-015-03, /03L-0:on 830406,drywell Pressure Switch 2-PS-64-57A Found Operating Above Tech Spec Limit.Caused by Setpoint Drift.Static O-ring Switch,Model 12N-AA4,recalibr, Tested & Returned to Svc (← links)
- 05000260/LER-1983-009-03, /03L-0:on 830319,HPCI Turbine Failed Due to Erratic Flow Controller.Caused by Trapped Air in Hydraulic Oil Control Sys Due to Maint Work (← links)
- 05000260/LER-1983-011-03, /03L-0:on 830319,during Test for Containment Air Dilution Sys Valve Operability,Valve FSV-84-8A Failed to Operate.Caused by Metal Particles on Position Indicating Magnet in Valve Stem.Valve Cleaned (← links)
- 05000260/LER-1983-008-03, /03L-0:on 830319,during Startup,Reactor Water Level Indicator LI-3-46A Observed to Be Reading Erroneously High Compared to Other Indications & Declared Inoperable. Caused by Meter Face Being Pushed Against Indicating Needle (← links)
- 05000260/LER-1991-007, :on 910409,ESF Actuation Occurred When Group 1 Primary Containment Isolation Initiated.Caused by Leaking Packing on Check Valve Differential Pressure Transmitters. Trapped Air Vented & Line Backfilled (← links)
- 05000260/LER-1991-006, :on 910329,unplanned Reactor Protection Sys Actuation Occurred During Average Power Range Monitor B Drifted High & Exceeded Setpoint.Caused by Unexpected Failure.Affected Components Replaced (← links)
- 05000260/LER-1991-004-01, :on 910326,reactor Protection Sys Actuation Occurred During Testing.Cause Undetermined.Ground Fault in Intermediate Range Monitor Channel C Detector Cable Shield Removed (← links)
- 05000260/LER-1991-005-01, :on 910327,unplanned ESF Actuation Occurred. Caused by Unexpected Failure of Relay Coil.Replacing Relay Coil & Realigning Affected Sys,Work Requests Issued & Replacing GE Type Relays (← links)
- 05000260/LER-1983-028-03, /03L-0:on 830526,during Normal Operation,Hpci Sys Declared Inoperable Due to Blown Inverter Fuse.Fuse Replaced.Hpci Turbine Control Valve Failed to Open Due to Misadjusted Rod.Rod Adjusted (← links)
- 05000260/LER-1983-029-03, /03L-0:on 830528,during Normal Operation,Drywell Radiation Monitor RE-90-256 Sample Pump Tripped.Caused by Blown Fuse.Fuse Replaced & Drywell Air Sampling Sys Returned to Svc (← links)
- 05000260/LER-1983-026-03, /03L-0:on 830521,during Rod Sequence Exchange, Calculated R Factor Less than R Setpoint.Caused by R Factor Calculated Out During Power Shaping Rod Moves.Rod Pattern Adjusted & Verified (← links)
- 05000260/LER-1983-024-03, /03L-0:on 830515,recirculation Pump 2A Tripped After Isolation Valve 2-24-744 Failed Closed.Caused by Sheared Coupling Pins.Crane Model XP-3600 Valve Repaired & Pump Returned to Svc (← links)
- 05000260/LER-1983-025-03, /03L-0:on 830520,pressure Switch PS-3-22B as-found Setpoint Set Above Tech Spec Limits During Performance of SI 4.1.A-5.Caused by Calibr Drift.Barksdale B2T-A12SS Pressure Switch Recalibr (← links)
- 05000260/LER-1983-027-03, /03L-0:on 830520,differential Pressure Switch for Pressure Suppression chamber-reactor Bldg Vacuum Breakers Found Operating Above Tech Spec Limits.Caused by Switch Drift.Switch 2-PDIS-64-20 Recalibr (← links)
- 05000260/LER-1983-023-03, /03L-0:on 830602,while Performing ST 4.1,A-6 Drywell Pressure Switch Found Operating Above Tech Spec Trip Setting,Initiating Drywell High Pressure Half Scram. Caused by Setpoint Drift (← links)
- 05000260/LER-1982-007-03, /03L-0:on 820126,while Performing SI 4.2.A-3, Reactor low-water Level Switch Lis-3-56A Switch Number 2 Was Found 8% Out of Tolerance.Caused by Setpoint Drift.Yarway Model 4418c Switch Recalibr & Functionally Tested (← links)
- 05000260/LER-1983-021-03, /03L-0:on 830423,calculated R Factor Less than Flow Bias Tech Spec Setpoint.Caused by Pulling Group of Eight Rods Four Notches to Fully Withdrawn Position.Tech Spec Revs Submitted (← links)
- 05000260/LER-1983-004-01, /01T-0:on 830220,reactor Water Level Switch Setpoints Discovered out-of-tolerance.Caused by Setpoint Drift in Barton 288 Switches.Switches Recalibr & Will Be Replaced Per DCR 1398 (← links)
- 05000260/LER-1983-002-01, /01T-0:on 830208,during Preparation for Startup, Pressure Switches PS-68-96 Switch 1,PS-3-74A Switch 1 & PS-3-74B Switches 1 & 2 Operated at 199.7,208.43,208.43 & 471.43,psi,respectively.Caused by Instrument Drift (← links)
- 05000260/LER-1982-035-03, During Refueling Outage, While Performing Surveillance Insp 4.6.H-2,upper Mechanical Snubber on Main Steam Line D Found Inoperable.Snubber Replaced.Engineering Analysis Encl (← links)
- 05000260/LER-1991-003-01, :on 910223,unplanned Start of RHR Pump D3 Occurred.Cause Unknown.Rhr Svc Water Pump Returned to Standby Readiness & Evaluation of Breaker Performed to Determine Failure Mechanism (← links)
- 05000260/LER-1982-038-03, /03L-0:on 821124,while Performing ST 4.7.A-3 (Pressure Suppression Chamber Rx Bldg Vacuum Breakers), Pressure Switches PDIS-64-20 & 21 Had Setpoint Above Tech Spec Limit.Caused by Setpoint Drift.Switches Recalibr (← links)
- 05000260/LER-1982-039-01, /01X-0:on 821204,during Fuel Outage,Level Switches LS-73-57A & 57B Found Inoperable.Caused by Stuck Robert Shaw Model 82798-C3 Level Switch Floats.Floats Freed & Level Switches Recalibr (← links)
- 05000260/LER-1982-036-03, /03L-0:on 821113,during Refueling Outage,Reactor Bldg Continuous Air Monitor 2-90-250 Became Inoperable Due to Broken Drive Belt on Sample Pump.Caused by Normal Wear. Std v-belt for Switzer Model 325 Svc Air Pump Replaced (← links)
- 05000260/LER-1983-010-03, /03L-0:on 830322,CRD 10-39 Failed to Scram While Performing SI 4.3.C.Caused by Valve Stem Separating from Valve Seat in Valve 85-617 (← links)
- 05000260/LER-1983-013-03, /03L-0:on 830325,during Rod Pulls to Set Target Rod Pattern,Calculated R Factor Was Less than R Setpoint for 54 Minutes.Caused by Limitation of Power Rod Withdrawal by Condensate Demineralizer Problems.Rod Pattern Adjusted (← links)
- 05000260/LER-1983-012-03, /03L-0:on 830323,during Startup Testing at 50.4% Power,Discovered Process Computer Contained Nonconservative Kf Factor.Caused by Increased Recirculation Stops at End of Previous Cycle for Increased Flow Operation (← links)
- 05000260/LER-1982-006-03, /03L-0:on 820125,while Performing SI 4.1.A-7,low Water Level Switch LIS-3-203B,switch 1 Found 3% Out of Tolerance.Caused by Setpoint Drift.Switch Recalibr (← links)
- 05000260/LER-1982-034-03, /03L-0:on 821022,primary Containment Purge Sys Not Tested After 720-h of Operation.Caused by Incorrect Logging of Sys Run Time.Instruction Will Be Revised by 821231 (← links)
- 05000260/LER-1982-033-03, /03L-0:on 821015,surveillance Sample SI.4.7.F.4 Taken from Charcoal Filters in Primary Containment Purge Sys Revealed Methyl Iodine Removal Efficiency of 72.31% Below Limit of Plus/Minus 85%.Caused by Matls Absorbed on Filte (← links)
- 05000260/LER-1991-001-02, :on 910116,unplanned Actuations of Various ESFs Occurred Due to Blown Fuse in Primary Containment Isolation Sys Logic Circuitry.Caused by Failure of GE Type CR120 Relay Due to Faulted Coil.Coils Replaced (← links)
- 05000260/LER-1982-030-03, /03L-0:on 821006,small Pinhole Leak Discovered in 3-inch Fire Protection Line Which Supplies Water to Cable Tray Fixed Water Spray Sys.Caused by through-wall Pitting Corrosion attack.Through-wall Hole Welded & Tested (← links)
- 05000260/LER-1982-032-03, /03L-0:on 821006,MSIVs 1-14,1-15,1-26,1-27,1-37, 1-38 & 1-52 Exceeded Allowable Leak Rate of 11.5 Std Cubic Ft Per Hour.Caused by Atwood-Morrill Globe Valves Leaking Past Main Seat.Valves Will Be Repaired (← links)
- 05000260/LER-1982-029-03, /03L-0:on 820921,pinhole Leak Discovered in 3-inch Fire Protection Line Supplying Water to cable-tray Fixed Water Spray Sys.Caused by through-wall Pitting Corrosion Attack.Ultrasonic Testing to Be Done by 830201 (← links)
- 05000260/LER-1982-040-01, /01T-0:on 821230,during Refueling Outage,While Performing Exams Under IE Bulletin 82-03,indications of Cracking Found in Recirculating Piping on Welds KR2-36 & KR12-14.Caused by Fatigue.Analysis Will Be Performed (← links)
- 05000260/LER-1994-001-02, :on 940214,loss of Unit 2,Division II ECCS Instrumentation Due to Blown Fuse.Caused by Failure of Atu Inverter Control Card.Blown Fuse & Control Card in ECCS Division II Atu Inverter Replaced (← links)
- 05000260/LER-1978-019, Forwards LER 78-019/01T-0 (← links)
- 05000260/LER-1982-024-03, /03L-0:on 820730,computer Heat Balance Calculated Reactor Thermal Power Nonconservatively Due to Erroneous Feedwater Flow Signal During steady-state Operation at 63% Power.Caused by Leaking Instrument Sensing Line Root Valve (← links)
- 05000260/LER-1982-021-03, /03L-0:on 820720,hydrogen Analyzer B Became Inoperable.Caused by Valcor Engineering Corp Solenoid Operator P/N V52630-529-1 Failure.Solenoid Replaced But Failed Again.Valve Will Be Repaired During Refueling Outage (← links)
- 05000260/LER-1982-025-03, /03L-0:on 820719,during Startup,Relay Coil Failed, Resulting in Partial Primary Containment Isolation.Caused by Burned Out Coil Relay,Causing Relay to Fail in Safe Direction for Primary Containment Isolation (← links)
- 05000260/LER-1982-022-03, /03L-0:on 820721,calculated R Factor Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block.Caused by High Core Exposure & Reduced Core Reactivity.Tech Spec Changes Issued (← links)
- 05000260/LER-1981-004-01, /01T-0:on 810119,reactor Water Level Switches LIS-3-203A Switch 1 & LIS-3-A,B,C,D Switch 2 Found Outside Tech Specs.Caused by Drift Due to Air Impact Drilling Next to Switch Panel.Switches Recalibr (← links)
- 05000260/LER-1981-001-01, /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed (← links)
- 05000260/LER-1982-023-01, /01T-0:on 820723,equalizer Valve on Differential Pressure Switch 2-Pdis-73-1B three-valve Block Manifold Would Not Close,Rendering Switch Inoperable.Caused by Improperly Seated Valve Manifold Equalizer Valve (← links)
- 05000260/LER-1982-020-03, /03L-0:on 820711,while Performing Surveillance on Main Steam Tunnel High Temp Switched TS-1-29A Failed to Operate.Caused by Valve Leakage Onto Switch Junction Box. Leak Reduced & Junction Box Sealed (← links)
- 05000260/LER-1990-005-03, :on 901002,deenergization of Reactor Protection Sys Occurred Due to Motor Generator Set Operation (← links)
- 05000260/LER-1982-019-03, /03L-0:on 820618,while Performing SI-2 (Rod Notch Exercise),Flow Bias Comparator Trip Prevented Rod Withdrawal.Caused by Gemac 563-02 Proportional Amplifier (FQ-68-81) Drifting Upscale.Amplifier Replaced (← links)
- 05000260/LER-1981-069-03, While Performing Special Instruction 4.1.A-8,scram Discharge Level Switch 2-LS-85-45E Inoperable.Caused by Separation of Switch Float from Arm.Robertshaw Model SL-305-EI-X Level Switch Replaced (← links)
- 05000260/LER-1982-018-03, /03L-0:on 820602,while Calibr Pressure Switches That Bypass Control Valve Fast Closure/Stop Valve Scram, Pressure Switch PS-1-81B Operated at 156.9 Psig.Caused by Instrument Drift.Switch Recalibr & Tested (← links)
- 05000260/LER-1982-016-03, /03L-0:on 820519,HPCI Lubricating Oil Reservoir Found Almost Empty & Reservoir Drain Valve 1-1/2 Turns Open, Rendering HPCI Inoperable.Caused by Personnel Error. Reservoir Filled.Lighting Will Be Improved (← links)
- 05000260/LER-1982-013, Forwards Updated LER 82-013/03X-1 (← links)
- 05000260/LER-1982-014-03, /03L-0:on 820420,HPCI Sys Made Inoperable for Calibr of Speed Sensing & Control Circuits W/O Performing Surveillance Tests.Caused by Personnel Error in Failing to Determine Inoperability (← links)
- 05000260/LER-1982-014, Forwards LER 82-014/03L-0 (← links)
- 05000260/LER-1982-011-03, /03L-0:on 820215,during Operation,While Performing Chamber Water check,2-LI-64-66 Indicated Improper Torus & Level & Declared Inoperable.Caused by Instrument Drift & Possible Air in Ref Leg.Transmitter Calibr (← links)
- 05000260/LER-1982-011, Forwards LER 82-011/03L-0 (← links)
- 05000260/LER-1982-008-03, /03L-0:on 820127,after Calibr,Rod Block Monitor Channel B Failed to Pass Functional Test of SI 4.2.C-2. Caused by Electronic IC Failure Possibly Due to Voltage Spike During Calibr.Ge 136B1333G1 Gain Change Card Replaced (← links)
- 05000260/LER-1982-008, Forwards LER 82-008/03L-0 (← links)
- 05000260/LER-1982-010-03, /03L-0:on 820121,during Full Power Operation SI 4.1.B.2 (APRM Output Signal Calibr) Not Performed within Required Frequency During 811014-28.Caused by Personnel Error (← links)
- 05000260/LER-1990-003-04, :on 900502,unplanned ESF Actuation Occurred. Caused by Personnel Error.Fuse Replaced & ESF Actuation Terminated.Event Will Be Reviewed W/Operations Personnel. W/9 Ltr (← links)
- 05000260/LER-1982-003-03, /03L-0:on 820116,during Normal Operation,While Performing Surveillance test,PS-3-74A Switch 1 & PS-68-96 Switch 1,low Pressure Switches,Were Out of Tolerance by 4% & 6%.Caused by Instrument Drift.Switches Recalibr (← links)
- 05000260/LER-1982-003, Forwards LER 82-003/03L-0 (← links)
- 05000260/LER-1982-002-03, /03L-0:on 820116,during Reduced Load While Performing MSIV Closure Si,Scram Trip Logic Az Annunciation Failed to Alarm.Caused by Failure of Limit Switch 4 of FCV-1-52 to Open.Switch Will Be Replaced (← links)
- 05000260/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000260/LER-1982-001-01, /01T-0:on 820115,during Offsite Verification of Process Computer Programming Changes Involving Data in Tech Spec Tables 3.5.I-3 & 3.5.I-4,discovered Input Error.Caused by Personnel Error.Personnel Will Be Reinstructed (← links)
- 05000260/LER-1982-001, Forwards LER 82-001/01T-0 (← links)
- 05000260/LER-1981-068-03, /03L-0:on 811211,reactor Low Water Level Switch 2-LIS-3-203D Switch 1 Operated Below Limit.Caused by Switch Calibr Drift.Barton Model 288A Switch Calibr & Returned to Svc.Util Preparing Action Re Design Change (← links)
- 05000260/LER-1981-068, Forwards LER 81-068/03L-0 (← links)
- 05000260/LER-1981-065-03, /03L-0:on 811211,HPCI Suppression Chamber High Level Switches Discovered to Be Set 8 Inches Above Normal Level.Caused by Change to Tech Specs Not Being Reflected in Table 3.2.B.Switches Physically Lowered (← links)
- 05000260/LER-1981-065, Forwards LER 81-065/03L-0 (← links)
- 05000260/LER-1981-058-03, Dw/Torus Differential Pressure Found Less than Tech Spec Limit.No Cause Given. Alarm Setpoint at 1.26 Psi Per Design Instructions.Setpoint Raised to Alert Operator to Start Compressor Manually (← links)
- 05000260/LER-1981-058, Forwards Updated LER 81-058/03X-1 (← links)
- 05000260/LER-1981-063-03, /03L-0:on 811117,northwest Core Spray Room Cooler Found Inoperable.Caused by Trip of CR124 Overload Relays. Relays Reset & Stater Current Verified (← links)
- 05000260/LER-1981-063, Forwards LER 81-063/03L-0 (← links)
- 05000260/LER-1981-060-03, /03L-0:on 811103,while Performing Mmi 40, Connection from Pressure Gauge to Bladder in Accumulator 24 Broke,Rendering Pump a Inoperable.Caused by Connector Being Overtightened.Bladder Replaced (← links)
- 05000260/LER-1981-060, Forwards LER 81-060/03L-0 (← links)
- 05000260/LER-1981-061-03, /03L-0:on 811106,during Normal Operation,Nrc Inspector Observed That High Alarm on Drywell Air Sampler Was Set Above 3X Background.Setpoints Reset & Program Established to Determine Setpoint Values (← links)
- 05000260/LER-1981-061, Forwards LER 81-061/03L-0 (← links)
- 05000260/LER-1981-055-03, /03L-0:on 811020,reactor Water Level Switches LIS-3-203C & D6 Switches 1 & 2 Were Out,Of Tolerance.Caused by Setpoint Drift.Switches Recalibr.Switches to Be Replaced W/Analog Transmitters & Trip Units (← links)
- 05000260/LER-1981-055, Forwards LER 81-055/03L-0 (← links)
- 05000260/LER-1981-057-03, /03L-0:on 811022,during Normal Operation, dihydrogen-dioxide Analyzer B Removed from Svc for Corrective Maint on Noisy Sample Return Pump.Caused by Loose Cam Pump Motor Shaft Due to Loose Key.Pump Replaced (← links)
- 05000260/LER-1981-057, Forwards LER 81-057/03L-0 (← links)
- 05000260/LER-1981-056-03, /03L-0:on 811021,bearings on 2B Dihydrogen Dioxide Sample Return Pump Seized.Pump & Motor Replaced (← links)
- 05000260/LER-1981-056, Forwards LER 81-056/03L-0 (← links)
- 05000260/LER-1981-002-03, /03L-0:on 810102,scram Discharge Instrument Vol Rod Block Level Switch 2-LS-85-45E Found Set at 27 Gallons. Alarm Switch 2-LS-85-45F Found Inoperable.Caused by Drift of Robertshaw Model SL-305-EI-X.Switch Recalibr (← links)
- 05000260/LER-1990-002-04, :on 900329,full Actuation of Reactor Protection Sys Occurred During Testing of Scram Discharge Instrument Vol Level Switches.On 900328,east Control Rod Drive Alarm Received.Cause Not Determined.Test Stopped (← links)
- 05000260/LER-1990-001-04, :on 900320,radiation Monitor on Refuel Zone Ventilation Exhaust Received High Radiation Trip Signal, Resulting in ESF Actuations.Caused by Loose Connector Pin on Radiation Detector.Detector Replaced (← links)
- 05000260/LER-1981-059-01, /01T-0:on 811030,reactor Low Pressure Switch 1 of PS-3-74A & Switch 1 of PS-68-95 Found Out of Tech Spec. Caused by Setpoint Drift.Setpoints Reset.Design Change Request Initiated to Replace Switches W/Trip Switches (← links)
- 05000260/LER-1981-059, Forwards LER 81-059/01T-0 (← links)
- 05000260/LER-1981-052, Forwards LER 81-052/03L-0 (← links)
- 05000260/LER-1981-053-03, /03L-0:on 811010,during Instrument Checks & observations,2-PI-75-48 Indicated Less than Tech Specs Limit.Caused by Valve Left Closed After Test.Personnel Reinstructed on Procedures (← links)
- 05000260/LER-1981-053, Forwards LER 81-053/03L-0 (← links)
- 05000260/LER-1981-051-03, /03L-0:on 811005,torus Water Level Transmitters 2-LT-64-54 & 2-LT-64-66 Found to Be Out of Required Instrument Accuracy.Caused by Setpoint Drift.Transmitters Recalibr & Returned to Svc (← links)
- 05000260/LER-1981-051, Forwards LER 81-051/03L-0 (← links)
- 05000260/LER-1981-045-03, /03L-0:on 810916,during Scram,When Manually Initiated,Hpci Gland Seal Condenser Upper Head Gasket Began Leaking.Caused by Head Gasket Stretching Out of Place Due to Overpressurization.Gasket Replaced (← links)
- 05000260/LER-1981-045, Forwards LER 81-045/03L-0 (← links)
- 05000260/LER-1981-048-03, /03L-0:on 810921,during Normal Operation,Flow Totalizer FQ-68-5 Drifted High Causing Erroneous Flow Indication to Average Power Range Monitor Channels.Caused by Electronic Failure.Totalizer Replaced (← links)
- 05000260/LER-1981-048, Forwards LER 81-048/03L-0 (← links)
- 05000260/LER-1981-047-03, /03L-0:on 810915,instrumentation for Controlling Core Standby Cooling Sys Thermostat at Core Spray Coolers Found Inoperable.Cause Unknown.Overload Relays on Full Voltage non-reversing Magnetic Starter Tripped (← links)
- 05000260/LER-1981-047, Forwards LER 81-047/03L-0 (← links)
- 05000260/LER-1981-044-03, /03L-0:on 810913,during Normal operation,hydrogen- Dioxide Analyzer B Sample Return Pump Discovered Inoperable. Caused by Failure of Pump Motor.Motor Repaired & Reinstalled (← links)
- 05000260/LER-1981-044, Forwards LER 81-044/03L-0 (← links)
- 05000260/LER-1981-042-03, /03L-0:on 810803,suppression Chamber High Level Sensors LS-73-57A & LS-73-57B Operated Time Delay Relay 23AK51 at Correct Setpoint But Parameter Sensor Relay 23AK15 Did Not Operate.Probably Caused by Timing Circuitry Failure (← links)
- 05000260/LER-1981-042, Forwards LER 81-042/03L-0 (← links)
- 05000260/LER-1991-002-03, :on 910223,unplanned Engineered Safety Feature Actuation Due to Radiation Monitors Downscale.Caused by Degraded Radioactive Bug Source in Radiation Monitors.Bug Source Readjusted (← links)
- 05000260/LER-1982-031-03, /03L-0:on 821004,while Performing Source & Background Check of Reactor & Turbine Bldg Vent Monitor, Charcoal Filter Found Out of Place.Caused by Personnel Error.Filter Replaced.Incident Discussed W/Personnel (← links)
- 05000260/LER-1982-031, Forwards LER 82-031/03L-0 (← links)
- 05000260/LER-1991-008, :on 910411,primary Containment Isolation Sys Logic Relay Failed,Resulting in ESF Actuations.Caused by End of Life Failure of GE Type CR120 Relay.Faulty Coil Replaced (← links)
- 05000260/LER-1983-046-03, /03L-0:on 830801,HPCI Declared Inoperable.Caused by Inverter Transformer 2 Failure.Transformer Replaced & HPCI Tested Satisfactorily (← links)
- 05000260/LER-1983-030-03, /03L-0:on 830607,torus Exhaust Valve FCV-64-34 Bypass to Standby Gas Treatment Sys Failed to Operate within 5 Time Limit.Caused by Indicating Limit Switches Being Out of Adjustment.Switches Adjusted (← links)
- 05000260/LER-1983-018-03, /03L-0:on 830413,core Max Fraction of Critical Power Determined That Min Critical Power Ratio Exceeded. Caused by Withdrawal of Deep Control Rods.Control Rods Inserted to Reduce Core Max Fraction of Critical Power (← links)
- 05000260/LER-1983-018, Forwards LER 83-018/03L-0 (← links)
- 05000260/LER-1983-019-03, /03L-0:on 830413,w/unit at 72.9% Power Returning to Rated Power,Calculated R Factor Less than R Setpoint for 4 H 44 Minutes.Caused by Local Power Peaking.Setting Adjusted (← links)
- 05000260/LER-1983-019, Forwards LER 83-019/03L-0 (← links)
- 05000260/LER-1983-020-03, /03L-0:on 830410,during Power Maneuvers for Recirculation Sys Testing,Calculated R Factor Was Less than R Setpoint for 2 H 45 Minutes.Caused by Power Peaking Due to Xenon Transients from Previous Power Changes (← links)
- 05000260/LER-1983-020, Forwards LER 83-020/03L-0 (← links)
- 05000260/LER-1989-028, :on 891206,reactor Protection Sys (RPS) Actuation Occurred Due to RPS Signal Generated by Low Scram Pilot Air Header Pressure.Caused by Failure of Soldered Connection.Air Leaks Repaired (← links)
- 05000260/LER-1981-049-03, /03L-0:on 810927,containment Atmosphere Dihydrogen Analyzer Removed from Svc for Maint for Approx 3.5-h.Caused by Tripping of Sample Return Pump Due to Setpoint Drift on Vacuum Switch.Switches Calibr (← links)
- 05000260/LER-1981-049, Forwards LER 81-049/03L-0 (← links)
- 05000260/LER-1981-035-01, Scram Discharge Instrument Vol Tank Level Switch 2-LS-85-45F Failed to Operate Per IE Bulletin 80-14 During Maint Outage.Caused by Inoperable Level Switch SL-305-EI-X.Switch Replaced (← links)
- 05000260/LER-1981-035, Forwards Updated LER 81-035/01X-1,per IEB-80-14 (← links)
- 05000260/LER-1981-043-01, /01T-0:on 810815,4,160-volt Shutdown Board U-2 Was Made Critical from Cold Condition W/Start Bus Undervoltage Relays Out of Svc for Start Bus 1A.Caused by Personnel Error.Relays Were Reconnected (← links)
- 05000260/LER-1981-043, Forwards LER 81-043/01T-0 (← links)
- 05000260/LER-1981-040-03, /03L-0:on 810720,while Valving Reactor Water Level Switch LIS-3-56C Into Svc,Recirculation Pump Tripped & HPCI & Reactor Core Isolation Cooling Initiated.Caused by Open Yarway Valve 4418C.Valve Closed.Personnel Cautioned (← links)
- 05000260/LER-1981-040, Forwards LER 81-040/03L-0 (← links)
- 05000260/LER-1981-037-03, /03L-0:on 810708,value for R Factor Found Out of Limits.Caused by Extenuating Circumstances Delaying Actions Necessary to Maintain Compliance W/Limit.Personnel Briefed on Close Monitoring of R Factor During Startup (← links)
- 05000260/LER-1981-037, Forwards LER 81-037/03L-0 (← links)
- 05000260/LER-1981-039-03, /03L-0:on 810720,HPCI Gland Seal Condenser Upper Header Gasket Began Leaking.Caused by Overpressurization of Tube Side Which Caused Gasket to Stretch Out of Place. Discharge Check Valve to Be Replaced (← links)
- 05000260/LER-1981-039, Forwards LER 81-039/03L-0 (← links)
- 05000260/LER-1981-041-03, /03L-0:on 810709,unit Crossconnect Capability Between Units 2 & 3 Reduced to One RHR Pump When RHR Pump 3C Became Inoperable.Caused by Pump Motor Failure on Ground Overcurrent During Testing (← links)
- 05000260/LER-1981-041, Forwards LER 81-041/03L-0 (← links)
- 05000260/LER-1981-038-03, /03L-0:on 810706,while Moving Equipment Through Equipment Air Lock Door,Door 238 Not Latched Properly When Opposite Door Was Opened,Resulting in Momentary Breach of Secondary Containment.Caused by Personnel Error (← links)
- 05000260/LER-1981-038, Forwards LER 81-038/03L-0 (← links)
- 05000260/LER-1981-035-03, /03L-0:on 810708,while Performing Level Switch Testing,Scram Discharge Instrument Vol Tank Level Switch 2-LS-85-45F Failed to Operate.Caused by Inoperable Robertshaw Level Switch Model SL-305-EI-X.Switch Replaced (← links)
- 05000260/LER-1981-036-03, /03L-0:on 810707,alarm for Smoke Detectors in Relay Room Was Received & Would Not Clear.Probably Caused by Grounded Wire in Detector or Cable.Kidde Cpd 1201 Detector Replaced (← links)
- 05000260/LER-1981-036, Forwards LER 81-036/03L-0 (← links)
- 05000260/LER-1980-058-03, During Performance of SI 4.1.A-8,scram Discharge Instrument Vol Tank Level Switch 2-LS-85-45F Failed Per IE Bulletin 80-14.Caused by Robertshaw Level Switch Inoperability (← links)
- 05000260/LER-1980-058, Forwards Updated LER 80-058/03X-1 (← links)
- 05000260/LER-1981-032-03, /03L-0:on 810702,equipment Air Lock Door 238 Was Not Properly Latched Before Opposite Door Was Opened.Caused by Personnel Error.Personnel Instructed in Correct Operation of Doors (← links)
- 05000260/LER-1981-032, Forwards LER 81-032/03L-0 (← links)
- 05000260/LER-1981-027-03, /03L-0:on 810604,during Mod Outage,Switch 2-PdIS-75-56 Was Found Outside Tech Spec Limits.Caused by Setpoint Drift of Barton Model 288 D/P Switch.Switch Recalibr (← links)
- 05000260/LER-1981-027, Forwards LER 81-027/03L-0 (← links)
- 05000260/LER-1981-033-03, /03L-0:on 810702,reactor Low Pressure Permissive Switch for Recirculation Pump Discharge Valve Actuation Switch 1 Failed.Cause Unknown.Switch Freed & Exercised to Verify Operability.Considered Random Failure (← links)
- 05000260/LER-1981-033, Forwards LER 81-033/03L-0 (← links)
- 05000260/LER-1981-034-03, /03L-0:on 810630,RHR Svc Water Pumps B2,D-1 & D-2 Were Not in Svc.Caused by Removing B2 from Svc to Change Motor Oil & Tagging Closed Crosstie Valve to Unit 1, FCV-1-74-100.Oil Changed (← links)
- 05000260/LER-1981-031-03, /03L-0:on 810701,RHR Pump Room Cooler 3-A Developed Water Leak.Caused by Broken Silfos Joint on 1/4-inch Vent Line.Joint Resoldered (← links)
- 05000260/LER-1981-034, Forwards LER 81-034/03L-0 (← links)
- 05000260/LER-1981-031, Forwards LER 81-031/03L-0 (← links)
- 05000260/LER-1981-030-03, /03L-0:on 810629,while Performing Surveillance Insp 4.5.B.1.D,valve 2-FCV-2-74-57 Became Inoperable,Making RHR Loop I Inoperable.Caused by Geared Limit Finger Base Breaking Off of Operator.Finger Base Replaced (← links)
- 05000260/LER-1981-030, Forwards LER 81-030/03L-0 (← links)
- 05000260/LER-1981-029-03, /03L-0:on 810621,flow Bias Loop a Drifted High, Affecting Average Power Range Monitors A,C & E & Rod Block Monitor A.Caused by Electronic Failure of GE Model 563-02 Flow Totalizer.Flow Totalizer Replaced (← links)
- 05000260/LER-1981-029, Forwards LER 81-029/03L-0 (← links)
- 05000260/LER-1989-029-01, :on 891221,required Number of RHR Svc Water Pumps Available Found Less than Required Due to Loss of Two Redundant Pumps.Caused by Failure of Level Switch Associated W/Sump Pump B1.Level Switch Calibr (← links)
- 05000260/LER-1989-028-01, :on 891206,reactor Protection Sys Actuation Occurred Due to Trip Signal Generated by Low Scram Pilot Air Header Pressure.Caused by Failure of Soldered Connection. Connection Repaired (← links)
- 05000260/LER-1981-028-01, /01T-0:on 810611,while Performing Routine Surveillance Test SI 4.2.B.8 During Maint Outage,Reactor High Pressure Switches Ps 68-93 Switch 2 & Ps 68-94 Switch 2 Were Above Tech Spec Limits.Caused by Setpoint Drift (← links)
- 05000260/LER-1981-028, Forwards LER 81-028/01T-0 (← links)
- 05000260/LER-1981-026-03, /03L-0:on 810520,inservice Insp Ultrasonic Exam Did Not Receive Required Evaluation.Caused by Effect of Reduced Recording Level Not Being Recognized Until Recent Questions Were Raised in Area.Procedures Clarified (← links)
- 05000260/LER-1981-026, Forwards LER 81-026/03L-0 (← links)
- 05000260/LER-1981-022-03, /03L-0:on 810512,during Performance of High Water Level in Scram,Scram Discharge Vol Level Switch Found Inoperable.Caused by Float Disconnected from Switch Arm. Robertshaw Model SL-305-EI-X Level Switch Replaced (← links)
- 05000260/LER-1981-022, Forwards LER 81-022/03L-0 (← links)
- 05000260/LER-1981-020-03, /03L-0:on 810505,during Core Standby Cooling Sys Suppression Chamber High Level Surveillance Instruction, Level Switches Operated at Correct Setpoint,But Annuciator & Relays Failed to Operate.Cause by Failure of Relay 23AK51 (← links)
- 05000260/LER-1981-020, Forwards LER 81-020/03L-0 (← links)
- 05000260/LER-1981-014-03, /03L-0:on 810313,mode a of Reactor Water Level Instrumentation Indicated Full Upscale Resulting in Turbine Trip.Caused by Loss of Ref Leg to 2-LITS-3-203A & B & 2-LIS-3-184 Due to Partially Open Equalizing Valve (← links)
- 05000260/LER-1981-014, Forwards LER 81-014/03L-0 (← links)
- 05000260/LER-1981-015-03, /03L-0:on 810325,HPCI Turbine Was Removed from Svc to Repair Defective Switch 2-LS-73-5.Caused by Steam Leak Which Prevented Repair While Turbine Was Operational.Switch Repaired (← links)
- 05000260/LER-1981-015, Forwards LER 81-015/03L-0 (← links)
- 05000260/LER-1981-012-03, /03L-0:on 810311,loop 1 FCV-75-22 Failed to Open While Performing SI 4.5.A.1.d on Core Spray Sys.Caused by Contact in Open Circuitry of FCV-75-22 Fvr Starter Failing to Make Up.Motor Contactors Disassembled & Inspected (← links)
- 05000260/LER-1981-012, Forwards LER 81-012/03L-0 (← links)
- 05000260/LER-1981-006-03, /03L-0:on 810121,core Max Fraction of Limiting Power Density Exceeded Limit.Caused by Power Increase in Conjunction W/Inoperable Process Computer.Power Reduced & Control Rod Pattern Adjustment Made on 810123 (← links)
- 05000260/LER-1981-006, Forwards LER 81-006/03L-0 (← links)
- 05000260/LER-1981-005-03, /03L-0:on 810119,core Max Fraction of Limiting Power Density Exceeded Limit for One Node in Core.Caused by Operation Close to Limit in Conjunction W/Minor (Normal) Perturbation in Monitored Parameters.Power Reduced Slightly (← links)
- 05000260/LER-1981-005, Forwards LER 81-005/03L-0 (← links)
- 05000260/LER-1981-003-03, /03L-0:on 810112,core Spray Pump Discharge Pressure Switch 2-PS-75-16 Found Outside Tech Spec Limits. Caused by Setpoint Drift.Switch Recalibr & Replaced (← links)
- 05000260/LER-1981-003, Forwards LER 81-003/03L-0 (← links)
- 05000260/LER-1981-002, Forwards LER 81-002/03L-0 (← links)
- 05000260/LER-1989-027-02, :on 891123,discovered There Were Less than Required RHR Svc Water Pumps Available to Supply Cooling Water to RHR HXs Due to Loss of Pump Room Sump Pumps.Caused by Lack of Attention to Detail (← links)
- 05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits (← links)
- 05000260/LER-1981-007-03, /03L-0:on 810129,during Power Increases,Tech Spec Limit of 13.33 Kw/Ft for Linear Heat Generation Rate Exceeded in One Node.Node Reached 13.77 Kw/Ft.Caused by Xenon Transient Resulting from Increased Core Power (← links)
- 05000260/LER-1981-007, Forwards LER 81-007/03L-0 (← links)
- 05000260/LER-1980-056-03, /03L-0:on 801215,reactor Water Level Switch LIS-3-56A Switch 2 Setpoint Found Outside of Tech Spec Limits.Caused by Yarway Model 4418c Setpoint Drift.Switch Recalibr & Functionally Tested for Repeatability (← links)
- 05000260/LER-1980-056, Forwards LER 80-056/03L-0 (← links)
- 05000260/LER-1981-025-03, /03L-0:on 810526,equipment Airlock Doors 235 & 236 Were Opened Simultaneously,Breaching Secondary Containment. Caused by Failed Electric Strike on Door 236.Electric Strike Solenoid Replaced (← links)
- 05000260/LER-1981-025, Forwards LER 81-025/03L-0 (← links)
- 05000260/LER-1981-024-03, /03L-0:on 810519,equipment Airlock Doors 237 & 238 Were Opened Simultaneously Resulting in Breach of Secondary Containment.Caused by Electric Strike Failure on Door 238 Due to Improperly Aligned Solenoid.Solenoid Realigned (← links)
- 05000260/LER-1981-024, Forwards LER 81-024/03L-0 (← links)
- 05000260/LER-1981-023-01, /01T-0:on 810527,pressure Switches PS-1-81A,B & PS-1-91A,B Were Found Above Tech Spec Limit.Caused by Setpoint Drift.Switches Reset.Design Change Requested to Replace Switches (← links)
- 05000260/LER-1981-023, Forwards LER 81-023/01T-0 (← links)
- 05000260/LER-1980-053-03, Discovered Leak on Heat Exchanger During Steady State Operation.Caused by Leaking Inner Head Gasket on RHR Heat Exchanger Due to Loose Flange Nuts.Gasket Replaced & New Nuts W/Locking Tabs Installed (← links)
- 05000260/LER-1981-018-03, /03L-0:on 810418,xenon Transient Observed Following Control Rod Sequence Exchange.Caused by Earlier Load Reduction in Conjunction W/New Control Rod Pattern. Control Rods Inserted & R Factor Brought within Limits (← links)
- 05000260/LER-1981-018, Forwards LER 81-018/03L-0 (← links)
- 05000260/LER-1980-026-03, Reactor Motor Operated Valve Board Lost Power to Normal Feeder Breaker Which Is Supplied from 3A Compartment of 2A Shutdown Board.Cause Unknown.Suspected Power Sensor Unit Tested Satisfactorily (← links)
- 05000260/LER-1980-026, Forwards Updated LER 80-026/03X-1 (← links)
- 05000260/LER-1980-053, Forwards Updated LER 80-053/03X-1 (← links)
- 05000260/LER-1981-011-03, /03L-0:on 810311,during Normal Operation,Core Spray Sys I Flow Indicator 2-FI-75-21 Failed to Indicate Flow.Caused by Failure of Transmitter Model 555111BDA3AAA. Transmitter Replaced & Required Testing Performed (← links)
- 05000260/LER-1981-011, Forwards LER 81-011/03L-0 (← links)
- 05000260/LER-1981-017-03, /03L-0:on 810409,unit 2 Reactor Zone Ventilation Sys Found Isolated.Caused by Temporary Alteration Which Bypassed Isolation During Relay Replacement.Controlled Shutdown Initiated (← links)
- 05000260/LER-1981-017, Forwards LER 81-017/03L-0 (← links)
- 05000260/LER-1981-019-01, /01T-0:on 810425,bypass Installed on Main Steam High Temp Isolation Relays to Control Unit Conditions for Maint on Ventilation Sys.Caused by Electrical Components Malfunction.Repairs Initiated & Ventilation Restored (← links)
- 05000260/LER-1981-019, Forwards LER 81-019/01T-0 (← links)
- 05000260/LER-1981-008-03, /03L-0:on 810220,reactor Core Isolation Cooler Turbine Trip & Throttle Valve Closed & Would Not Reopen. Caused by Overload Heater Relay.Relay Replaced (← links)
- 05000260/LER-1981-008, Forwards LER 81-008/03L-0 (← links)
- 05000260/LER-1981-021-03, /03L-0:on 810507,HPCI Gland Seal Condenser Upper Head Gasket Began Leaking During Automatic Reactor Shutdown Sys Initiation.Caused by Head Gasket Stretched Out of Place Due to Overpressurization of Condenser Tube Side (← links)
- 05000260/LER-1981-021, Forwards LER 81-021/03L-0 (← links)
- 05000260/LER-1981-016-03, /03L-0:on 810406,scram Discharge Tank Level Switch 2-LS-85-45A Setpoint Exceeded Tech Spec.Caused by Setpoint Drift.Switch Recalibr & Will Be Replaced (← links)
- 05000260/LER-1981-016, Forwards LER 81-016/03L-0 (← links)
- 05000260/LER-1981-009-03, /03L-0:on 810302,recirculation Motor Generator Sets 2B & 2A Tripped.Caused by Resistance Temp Detector Operating 2A-K45B Relay & Tripping 2B Set.Set 2A PT Fuse Compartment Door Jarred & Circuit Interrupted (← links)
- 05000260/LER-1981-009, Forwards LER 81-009/03L-0 (← links)
- 05000260/LER-1981-013-03, /03L-0:on 810111,surveillance Test on Jet Pumps SI 4.6.E.1,was Inadvertently Omitted.Caused by Personnel Error.Employee Who Handles Tracking Sys Has Been Cautioned Re Necessity to Perform SI as Scheduled (← links)
- 05000260/LER-1981-013, Forwards LER 81-013/03L-0 (← links)
- 05000260/LER-1980-059-03, /03L-0:on 801230,FR-77-16 Observed Downscale During Drywell Equipment Drain Sump Pump Operation.Caused by Shift in Model 555 GE Transmitter FT77-16 Zero Adjustment. Transmitter Recalibr,Tested & Returned to Svc (← links)
- 05000260/LER-1980-059, Forwards LER 80-059/03L-0 (← links)
- 05000260/LER-1980-057-03, /03L-0:on 801215,pressure Switches PS-1-76,PS-1-82 & PS-1-86,which Monitor Main Steam Line Low Pressure,Were Found Outside Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr (← links)
- 05000260/LER-1980-057, Forwards LER 80-057/03L-0 (← links)
- 05000260/LER-1980-055-03, /03L-0:on 801208,core Spray Discharge Pressure switch,2-PS-75-16,found Set Outside Tech Spec Limits.Caused by Mercroid Model DA-7004-804 Setpoint Drift.Switch Inspected & Calibr (← links)
- 05000260/LER-1980-055, Forwards LER 80-055/03L-0 (← links)
- 05000260/LER-1980-041-01, /01T-0:on 801005,during fuel-shuffling Operations, Fuel Was Placed in Cell 58-19 W/Adjacent Control Rod 54-19 Withdrawn.Caused by Deficient Procedure for Fuel Support Casting Replacement.Procedures Will Be Revised (← links)
- 05000260/LER-1980-041, Forwards LER 80-041/01T-0 (← links)
- 05000260/LER-2019-003, Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise (← links)
- 05000260/LER-1989-025-01, :on 890919,observed That Tech Spec Compensatory Measure Not in Place for Two Inoperable Hose Stations.Caused by Personnel Error.Fire Protection Procedures Will Be Enhanced to Require Periodic Verification (← links)
- 05000260/LER-1980-009-03, /03L-0:on 800213,during Normal Operation,Steam Line B Radiation Monitor 2-RM-90-138 Failed Downscale Resulting in Half Scram & Half Isolation.Caused by Loss of Power Output from Power Drawer.Power Drawer Replaced (← links)
- 05000260/LER-1980-010-03, /03L-0:on 800216,during Hot Shutdown,Crack Was Found in HPCI Turbine Coupling Bearing Support Pedestal. Probably Caused by Water Hammer While Warming HPCI from out- of-svc Condition.New Pedestal Installed (← links)
- 05000260/LER-1980-010, Forwards LER 80-010/03L-0 (← links)
- 05000260/LER-1980-009, Forwards LER 80-009/03L-0 (← links)
- 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation (← links)
- 05000260/LER-1983-032-03, /03L-0:on 830610,number of Offsite Power Sources Available Reduced to One When Main Transformer 2B Removed from Svc for Maint.Caused by Inadequate Brazing of Low Voltage Coil Connections.Connections Repaired (← links)
- 05000260/LER-1979-018, Forwards LER 79-018/03L-0 (← links)
- 05000260/LER-1982-015-03, /03L-0:on 820510,condensation Collected & Blocked Sample Flow to Containment Atmospheric Monitor of Turbine Bldg Exhaust for 52-h.Caused by Loose Temporary Support Allowing Low Point to Form in Sample Line (← links)
- 05000260/LER-2019-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000260/LER-2077-001, For Browns Ferry Nuclear Plant, Unit 2, False Alarm Would Not Clear That Was Received from Smoke Detector in Reactor Building, Elevation 565, During Normal Operation (← links)
- 05000260/LER-2077-004, For Browns Ferry Nuclear Plant, Unit 2, Two Heat Detectors in the Fire Protection System for the Recirculation MG Sets Which, Would Not Alarm (← links)
- 05000260/LER-2077-005, For Browns Ferry Nuclear Plant, Unit 2, Drywall Oxygen Sensor 02M-76-43 Became Erratic During Normal Operation & Read Erroneously High Because of Grounded Shields (← links)
- 05000260/LER-2077-006, For Browns Ferry Nuclear Plant, Unit 2, Unit Being Shut Down as Specified by Technical Specification 3.6.F.3 Due to the 2B Reactor Recirculation Motor-Generator Set Being Out of Service Greater than 24 Hours (← links)
- 05000260/LER-2077-008, For Browns Ferry Nuclear Plant, Unit 2, Random Failure of Two Isolation Valves in One Traversing Incore Probe (Txp) Tube Could Not Have Been Closed If Required Between 2045 Hours on 3/16/1977, & 0100 Hours on 3/17/1977 (← links)
- 05000260/LER-2077-007, For Browns Ferry Nuclear Plant, Unit 2, Limiting Critical Power Ratio-Ratio (Cprrat) Changed from .988 to 1.009 After Local Power Range Monitors (Lprms) Were Calibrated During Steady-State Operation at 97-Percent Power (← links)
- 05000260/LER-2077-009, For Browns Ferry Nuclear Plant, Unit 2, Notification by NSSS Vendor, Minimum Critical Power Ratio Limit, as Determined by Analysis of Turbine Trip Without Bypass, Should Be 1.29 for Power Operation with Core Average Exposure (← links)
- 05000260/LER-2077-010, For Browns Ferry Nuclear Plant, Unit 2, Drywell Oxygen Sensor 202M-76-43 Became Erratic During Normal Operation (← links)
- 05000260/LER-2077-012, For Browns Ferry Nuclear Plant, Unit 2, Two Hydraulic Snubbers Were Found Inoperable During the Performance of Surveillance Instruction 4.6.H (← links)
- 05000260/LER-2078-002, For Browns Ferry Nuclear Plant, Unit 2, Reactor Pressure Switch PS-68-95 Not Functioning as Required by Tech Spec Table 4.2.B During Normal Operation While Performing Surveillance Instruction ST 4.2.B-7 (← links)
- 05000260/LER-2078-001, Surveillance Samples Were Taken from Charcoal in Unit 2 Primary Containment Purge System Following Maintenance Outage (← links)
- 05000260/LER-2078-003, Relief Valve 2-1-41 Opened and Failed to Reseat During Steady State Operation (← links)
- 05000260/LER-2078-004, Relief Valve 2-1-5 Opened and Failed to Reseat During Steady State Operation (← links)
- 05000260/LER-2078-005, For Browns Ferry Nuclear Plant, Unit 2, Unidentified Coolant Leakage in Drywall Was Found to Be 9.5 Gpm & Exceeded 5 Gpm Limit of Technical Specification 3.6.C.1. During Normal Operation (← links)
- 05000260/LER-2078-009, For Browns Ferry Nuclear Plant, Unit 2, Local Leak Rate Tests of All Containment Isolation Valves Where Leak Rate Exceeded Allowable Leak Rate of 60 Percent of La Per 24 Hours or 707.1 Scfh (← links)
- 05000260/LER-2078-006, For Browns Ferry Nuclear Plant, Unit 2, Check Valve 2-73-603 in High-Pressure Coolant Injection System Was Found in Open Position During Maintenance Inspection After Failing Local Leak Rate Test (← links)
- 05000260/LER-2078-008, For Browns Ferry Nuclear Plant, Unit 2, Reactor Building Ventilation Radiation Monitoring Channel Failed During Refueling Outage (← links)
- 05000260/LER-2078-010, For Browns Ferry Nuclear Plant, Unit 2, Relief Valve on Standby Liquid Control Pump B Opened at 900 Psig (Which Is Lower than Designed Setting of 1425 +/- 75 Psig as Designated by Tech Spec 4.4.A.2.A) During Surveillance Testin (← links)
- 05000260/LER-1999-010, :on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily (← links)
- 05000260/LER-1999-009, :on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug (← links)
- 05000260/LER-1999-008, :on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions (← links)
- 05000260/LER-1999-007, :on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With (← links)
- 05000260/LER-1999-006, :on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With (← links)
- 05000260/LER-1999-005, :on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With (← links)
- 05000260/LER-1999-004-01, :on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset (← links)
- 05000260/LER-1999-004, Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF (← links)
- 05000260/LER-1999-003-02, :on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram (← links)
- 05000260/LER-1999-003, Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept (← links)
- 05000260/LER-1999-002-02, :on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With (← links)
- 05000260/LER-1999-001-05, :on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With (← links)
- 05000260/LER-1999-001-03, :on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable (← links)
- 05000260/LER-1999-001, Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments (← links)
- 05000260/LER-1998-004-03, :on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With (← links)
- 05000260/LER-1998-003-03, :on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve (← links)
- 05000260/LER-1998-003, Forwards LER 98-003-00 Re Automatic Reactor Scram on Unit 2 from 100% Power.Event Was Result of Valve Failure Which Caused Generator Stator Cooling Water to Exceed High Temp Setpoint for Tt Which Resulted in Automatic Reactor S (← links)
- 05000260/LER-1998-002-04, :on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls (← links)
- 05000260/LER-1998-002, Forwards LER 98-002-00 Re Condition in Which Control Rods Moved Without Required Channels of Rod Block Monitor Being Operable.Util Reporting Event Pursuant to 10CFR50.73(a)(2)(i)(B),as Any Operation (← links)
- 05000260/LER-1998-001-02, :on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source (← links)
- 05000260/LER-1998-001, Forwards LER 98-001-00,concerning Engineered Safety Feature Actuations That Occurred When 2B Reactor Protection Sys Bus Transferred to de-energized Source (← links)
- 05000260/LER-1997-008-02, :on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges (← links)
- 05000260/LER-1997-008, Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests (← links)
- 05000260/LER-1997-007-02, :on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced (← links)
- 05000260/LER-1997-007, Forwards LER 97-007-00 Re Reactor Scram from 70 Percent Power.Event Resulted from Pressure Perturbation in electro- Hydraulic Control Sys at Turbine Control Valves (← links)
- 05000260/LER-1997-006-02, :on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated (← links)
- 05000260/LER-1997-006, Forwards LER 97-006-00 Re Inoperable Unit 2 Hpcis Discovered During Power Ascension from Unit 2 Cycle 9 Refueling Outage. Rept Submitted in Accordance w/10CFR50.73(a)(2)(v) (← links)
- 05000260/LER-1997-005-03, :on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped (← links)
- 05000260/LER-1997-005, Forwards LER 97-005-00,providing Details Concerning auto- Start of Engineered Safety Features.Event Resulted from Inadequate Procedure in That Procedure for Developing Post Mod Tests Did Not Require Task Risk Review (← links)
- 05000260/LER-1997-004-03, :on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule (← links)
- 05000260/LER-1997-004, Forwards LER 97-004-00,providing Details Re Failure to Perform Required Surveillances During Refueling Outage Time Frames as Required by TS (← links)
- 05000260/LER-1997-003-03, :on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated (← links)
- 05000260/LER-1997-003, Forwards LER 97-003-00 Re Failure of HPCI Surveillance Instruction (← links)
- 05000260/LER-1997-002-04, :on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs (← links)
- 05000260/LER-1995-003, :on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified (← links)
- 05000260/LER-1995-003-02, Forwards LER 95-003-02 Re Unit 2 SRVs Exceeding TS Setpoint Limit During Tests Performed During Unit 2 Cycle 7 Refueling Outage (← links)
- 05000260/LER-1996-004-01, :on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified (← links)
- 05000260/LER-1996-008, :on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges Replaced (← links)
- 05000260/LER-1995-001, :on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers (← links)
- 05000260/LER-1996-008-02, :on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot Cartridges (← links)
- 05000260/LER-1996-007-02, :on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised (← links)
- 05000260/LER-1994-010, :on 941005,loss of ECCS Division II Instrumentation Resulting from Blown Fuse in Atu Inverter. Caused by a Failed Capacitor.Blown DC Input Fuse Was Replaced (← links)
- 05000260/LER-1994-010-01, Forwards LER 94-010-01,clarifying Analysis of Event Section Which Division I & Division II ECCS Equipment Remained Operable for Automatic Initiation (← links)
- ML042520218 (redirect page) (← links)
- 05000296/LER-2004-003, Regarding Main Steam Relief Valve Inoperability LCO Exceeded During Operating Cycles 10 and 11 Due to Setpoint Drift (← links)
- 05000260/LER-2004-003, Regarding Inoperability of Turbine Control Valve Fast Closure Pressure Switches Beyond TS Allowable Outage Time (← links)
- 05000260/LER-2004-002, Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2 (← links)
- 05000296/LER-2004-001, Regarding Inoperability of Diesel Generator 3D Beyond TS Allowable Outage Time (← links)