| | | Reporting criterion |
|---|
| 05000289/LER-1977-001, Forwards LER 77-001/01T.Provides Supplemental Info | Forwards LER 77-001/01T.Provides Supplemental Info | |
| 05000289/LER-1977-001-01, /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | |
| 05000289/LER-1977-002-04, /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | |
| 05000289/LER-1977-003-03, /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | |
| 05000289/LER-1977-003, Forwards LER 77-003/03L.Provides Supplemental Info | Forwards LER 77-003/03L.Provides Supplemental Info | |
| 05000289/LER-1977-004-01, /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | |
| 05000289/LER-1977-004, Forwards LER 77-004/01T.Provides Supplemental Info | Forwards LER 77-004/01T.Provides Supplemental Info | |
| 05000289/LER-1977-005, Forwards LER 77-005/04T.Provides Supplemental Info | Forwards LER 77-005/04T.Provides Supplemental Info | |
| 05000289/LER-1977-005-04, /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | |
| 05000289/LER-1977-006-01, /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | |
| 05000289/LER-1977-006, Forwards LER 77-006/01T-0 | Forwards LER 77-006/01T-0 | |
| 05000289/LER-1977-007, Forwards LER 77-007/01T.Provides Supplemental Info | Forwards LER 77-007/01T.Provides Supplemental Info | |
| 05000289/LER-1977-007-01, /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | |
| 05000289/LER-1977-008-03, /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | |
| 05000289/LER-1977-008, Forwards LER 77-008/03L.Provides Supplemental Info | Forwards LER 77-008/03L.Provides Supplemental Info | |
| 05000289/LER-1977-009-01, /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | |
| 05000289/LER-1977-009, Forwards LER 77-009/01T.Provides Supplemental Info | Forwards LER 77-009/01T.Provides Supplemental Info | |
| 05000289/LER-1977-010, Forwards LER 77-010/01T.Provides Supplemental Info | Forwards LER 77-010/01T.Provides Supplemental Info | |
| 05000289/LER-1977-011, Forwards LER 77-011/01T.Provides Supplemental Info | Forwards LER 77-011/01T.Provides Supplemental Info | |
| 05000289/LER-1977-011-01, T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | |
| 05000289/LER-1977-012, RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | |
| 05000289/LER-1977-012-03, /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | |
| 05000289/LER-1977-013-04, /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | |
| 05000289/LER-1977-014-03, /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | |
| 05000289/LER-1977-015, Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | |
| 05000289/LER-1977-015-03, /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | |
| 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | |
| 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | |
| 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | |
| 05000289/LER-1977-017-03, /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | |
| 05000289/LER-1977-018-03, /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | |
| 05000289/LER-1977-019-03, /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | |
| 05000289/LER-1977-020, Forwards LER 77-20/04T-0 | Forwards LER 77-20/04T-0 | |
| 05000289/LER-1977-020-04, /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | |
| 05000289/LER-1977-021-01, /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revi | /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revised | |
| 05000289/LER-1977-022-01, /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | |
| 05000289/LER-1977-023-01, /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | |
| 05000289/LER-1977-023, RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | |