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| 05000244/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | |
| 05000244/LER-1983-001-03, /03L-0:on 830104,valve 9626A Found Mispositioned in Closed Position.Possible Causes Include Human Error & Deliberate Tampering.No Positive Conclusion Reached Even After Exhaustive Investigation | /03L-0:on 830104,valve 9626A Found Mispositioned in Closed Position.Possible Causes Include Human Error & Deliberate Tampering.No Positive Conclusion Reached Even After Exhaustive Investigation | |
| 05000244/LER-1983-002-03, /03L-0:on 830105,during Performance of ISI-7, Main Steam Snubber 160 Identified as Inoperable.Caused by Piston Rod Detachment from Piston.Snubber Replaced | /03L-0:on 830105,during Performance of ISI-7, Main Steam Snubber 160 Identified as Inoperable.Caused by Piston Rod Detachment from Piston.Snubber Replaced | |
| 05000244/LER-1983-002, Forwards LER 83-002/03L-0 | Forwards LER 83-002/03L-0 | |
| 05000244/LER-1983-003, Forwards LER 83-003/03L-0 | Forwards LER 83-003/03L-0 | |
| 05000244/LER-1983-003-03, /03L-0:on 830108,containment Vessel Sump a Isolation Valve AOV-1728 Failed to Close on Command.Cause Unknown.Valve Diaphragm Replaced & Leak Tests PT-23.23 & PT-2.5 Performed Satisfactorily | /03L-0:on 830108,containment Vessel Sump a Isolation Valve AOV-1728 Failed to Close on Command.Cause Unknown.Valve Diaphragm Replaced & Leak Tests PT-23.23 & PT-2.5 Performed Satisfactorily | |
| 05000244/LER-1983-004, Forwards LER 83-004/03L-0 | Forwards LER 83-004/03L-0 | |
| 05000244/LER-1983-004-03, /03L-0:on 830114,check Valve 862B Declared Inoperable After Failing to Close Promptly During Test of Containment Spray Sys.Maint Performed on Valve.Valve Retested Satisfactorily.Revised Test Method Developed | /03L-0:on 830114,check Valve 862B Declared Inoperable After Failing to Close Promptly During Test of Containment Spray Sys.Maint Performed on Valve.Valve Retested Satisfactorily.Revised Test Method Developed | |
| 05000244/LER-1983-005, Forwards LER 83-005/03L-0 | Forwards LER 83-005/03L-0 | |
| 05000244/LER-1983-005-03, /03L-0:on 830117,I-131 Spike Occurred in RCS After Unit Tripped from 100% Power.Caused Not stated.I-131 Concentration Returned to Normal Levels by Normal Letdown | /03L-0:on 830117,I-131 Spike Occurred in RCS After Unit Tripped from 100% Power.Caused Not stated.I-131 Concentration Returned to Normal Levels by Normal Letdown | |
| 05000244/LER-1983-006, Forwards LER 83-006/01T-0 | Forwards LER 83-006/01T-0 | |
| 05000244/LER-1983-006-01, /01T-0:on 830120,screen House Suction Bay Water Level Dropped Below Suction of Motor Driven & Diesel Driven Fire Pumps,Rendering Fire Suppression Sys Inoperable.Caused by Frazil Ice in Circulating Water Pump Suction | /01T-0:on 830120,screen House Suction Bay Water Level Dropped Below Suction of Motor Driven & Diesel Driven Fire Pumps,Rendering Fire Suppression Sys Inoperable.Caused by Frazil Ice in Circulating Water Pump Suction | |
| 05000244/LER-1983-007-03, /03L-0:on 830117,water Level in Pressurizer Dropped Below 12% Level.Caused by RCS Cooldown Following Trip.Level Returned to 19.5% within 15 Minutes | /03L-0:on 830117,water Level in Pressurizer Dropped Below 12% Level.Caused by RCS Cooldown Following Trip.Level Returned to 19.5% within 15 Minutes | |
| 05000244/LER-1983-007, Forwards LER 83-007/03L-0 | Forwards LER 83-007/03L-0 | |
| 05000244/LER-1983-008-01, /01T-0:on 830125,emergency Diesel Generator 1A Start Relay Indicating lights,R-1 & R-2,found Off,Causing Loss of Permissive Start Relays.Caused by Personnel Failure to Follow Procedures.Shift Supervisors Addressed on Subj | /01T-0:on 830125,emergency Diesel Generator 1A Start Relay Indicating lights,R-1 & R-2,found Off,Causing Loss of Permissive Start Relays.Caused by Personnel Failure to Follow Procedures.Shift Supervisors Addressed on Subj | |
| 05000244/LER-1983-008, Forwards LER 83-008/01T-0 | Forwards LER 83-008/01T-0 | |
| 05000244/LER-1983-009, Forwards LER 83-009/03L-0 | Forwards LER 83-009/03L-0 | |
| 05000244/LER-1983-009-03, /03L-0:on 830119,boric Acid Transfer Pump B Tripped Immediately After Start.Caused by Failed Control Power Fuses.Fuses Replaced | /03L-0:on 830119,boric Acid Transfer Pump B Tripped Immediately After Start.Caused by Failed Control Power Fuses.Fuses Replaced | |
| 05000244/LER-1983-010-03, /03L-0:on 830224,rod Position Indicator for Control Rod Bank SD Group 1 Position C09 Deviated from Control Bank SD by 12 Steps.Caused by Signal Error for Rod Position Indicator.Signal Adjusted to Correct Drift | /03L-0:on 830224,rod Position Indicator for Control Rod Bank SD Group 1 Position C09 Deviated from Control Bank SD by 12 Steps.Caused by Signal Error for Rod Position Indicator.Signal Adjusted to Correct Drift | |
| 05000244/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | |
| 05000244/LER-1983-011, Forwards LER 83-011/03L-0 | Forwards LER 83-011/03L-0 | |
| 05000244/LER-1983-011-03, /03L-0:on 830311,battery Charger Breaker Found Open.Caused by QC Inspector Accidentally Bumping Breaker While Climbing Ladder to Inspect Penetrations.Breaker Closed.Qc Inspector Cautioned | /03L-0:on 830311,battery Charger Breaker Found Open.Caused by QC Inspector Accidentally Bumping Breaker While Climbing Ladder to Inspect Penetrations.Breaker Closed.Qc Inspector Cautioned | |
| 05000244/LER-1983-012, Forwards LER 83-012/03L-1 | Forwards LER 83-012/03L-1 | |
| 05000244/LER-1983-012-03, /03L-1:on 830323,individual Doors for Personnel Hatch Had Higher Leak Rate than Allowed.Caused by Incorrect Maint Procedure on 821007 Requiring Only Door Seal Leak Testing.Procedure Revised.Other Procedures Reviewed | /03L-1:on 830323,individual Doors for Personnel Hatch Had Higher Leak Rate than Allowed.Caused by Incorrect Maint Procedure on 821007 Requiring Only Door Seal Leak Testing.Procedure Revised.Other Procedures Reviewed | |
| 05000244/LER-1983-012-01, /01T-0:on 830323,during Scheduled Local Leak Testing of Containment Personnel Hatch,Audible Exterior Door Shaft Leak Found.Caused by Improper Testing of Packing Area Following Maint.Maint Procedure Revised | /01T-0:on 830323,during Scheduled Local Leak Testing of Containment Personnel Hatch,Audible Exterior Door Shaft Leak Found.Caused by Improper Testing of Packing Area Following Maint.Maint Procedure Revised | |
| 05000244/LER-1983-013-01, /01T-0:results of multi-frequency Eddy Current Exam of Steam Generator a Inlet & Outlet Revealed No Tubes W/Indications Above Plugging limit.Twenty-three Tubes W/ Intergranular Attack Indications Found in Generator B | /01T-0:results of multi-frequency Eddy Current Exam of Steam Generator a Inlet & Outlet Revealed No Tubes W/Indications Above Plugging limit.Twenty-three Tubes W/ Intergranular Attack Indications Found in Generator B | |
| 05000244/LER-1983-013, Forwards LER 83-013/01T-0 | Forwards LER 83-013/01T-0 | |
| 05000244/LER-1983-014, Forwards LER 83-014/03L-0 | Forwards LER 83-014/03L-0 | |
| 05000244/LER-1983-014-03, /03L-0:on 830329,during Refueling Calibr,Certain Steam Generator Level Transmitter Outputs Shifted Low by 2 to 2.5% of Span.Caused by Instrument Drift.Transmitters Recalibr | /03L-0:on 830329,during Refueling Calibr,Certain Steam Generator Level Transmitter Outputs Shifted Low by 2 to 2.5% of Span.Caused by Instrument Drift.Transmitters Recalibr | |
| 05000244/LER-1983-015, Forwards LER 83-015/03L-0 | Forwards LER 83-015/03L-0 | |
| 05000244/LER-1983-015-03, /03L-0:on 830412,RHR Pump Manually Tripped Following Loss of RHR on Hot Leg of Loop.Caused by Leak in Steam Generator a Temporary Cold Leg Nozzle Isolation Device,Allowing Air in RCS & RHR Suction Line | /03L-0:on 830412,RHR Pump Manually Tripped Following Loss of RHR on Hot Leg of Loop.Caused by Leak in Steam Generator a Temporary Cold Leg Nozzle Isolation Device,Allowing Air in RCS & RHR Suction Line | |
| 05000244/LER-1983-016-03, /03L-0:on 830418,during Maint,Pinhole Leak Discovered on Boric Acid Transfer Sys Branch Connection Off Boric Acid Filter Outlet.Caused by Intergranular Attack Due to Stress Corrosion Cracking.Piping Will Be Replaced | /03L-0:on 830418,during Maint,Pinhole Leak Discovered on Boric Acid Transfer Sys Branch Connection Off Boric Acid Filter Outlet.Caused by Intergranular Attack Due to Stress Corrosion Cracking.Piping Will Be Replaced | |
| 05000244/LER-1983-016, Forwards LER 83-016/03L-0 | Forwards LER 83-016/03L-0 | |
| 05000244/LER-1983-017-03, /03L-0:on 830501,RHR Pumps a & B Took Suction from Refueling Water Storage Tank (Rust) for Filling Reactor Refueling Cavity.Rhr Pump Stopped & Flow Dropped to Zero. Caused by Power Failure to MCC D Circuit | /03L-0:on 830501,RHR Pumps a & B Took Suction from Refueling Water Storage Tank (Rust) for Filling Reactor Refueling Cavity.Rhr Pump Stopped & Flow Dropped to Zero. Caused by Power Failure to MCC D Circuit | |
| 05000244/LER-1983-018-03, /03L-0:on 820126,RCS Average Temp Reduced to Less than 350 F & Both Reactor Coolant Pumps Inoperable.Caused by Personnel Failure to Incorporate Tech Specs | /03L-0:on 820126,RCS Average Temp Reduced to Less than 350 F & Both Reactor Coolant Pumps Inoperable.Caused by Personnel Failure to Incorporate Tech Specs | |
| 05000244/LER-1983-019-03, /03L-0:on 830613,while Changing from Cold to Hot Shutdown,Containment Spray Pumps Found in pull-stop Position at 207 F.Caused by Changes in Tech Spec Interpretation. Pumps Placed in Auto | /03L-0:on 830613,while Changing from Cold to Hot Shutdown,Containment Spray Pumps Found in pull-stop Position at 207 F.Caused by Changes in Tech Spec Interpretation. Pumps Placed in Auto | |
| 05000244/LER-1983-020-03, /03L-0:on 830613,during Startup from Refueling Outage,Rcs Chloride Concentration Exceeded 15 Ppm at Greater than 250 F.Caused by Increased Chloride Solubility Due to Increasing RCS Temp & Contamination | /03L-0:on 830613,during Startup from Refueling Outage,Rcs Chloride Concentration Exceeded 15 Ppm at Greater than 250 F.Caused by Increased Chloride Solubility Due to Increasing RCS Temp & Contamination | |
| 05000244/LER-1983-021-03, /03L-0:on 830618,pressurizer Water Level Dropped Below 12%.Caused by RCS Cooldown After Reactor Trips.Level Restored by Increasing Charging Flow | /03L-0:on 830618,pressurizer Water Level Dropped Below 12%.Caused by RCS Cooldown After Reactor Trips.Level Restored by Increasing Charging Flow | |
| 05000244/LER-1983-022-03, /03L-0:on 830725,while Performing Procedure S-16.2 Nitrogen Makeup to Accumulators,Containment Isolation Valve AOV-846 for Nitrogen Supply to Containment Seized in Mid Position.Caused by Galling Plug | /03L-0:on 830725,while Performing Procedure S-16.2 Nitrogen Makeup to Accumulators,Containment Isolation Valve AOV-846 for Nitrogen Supply to Containment Seized in Mid Position.Caused by Galling Plug | |
| 05000244/LER-1983-023-03, /03L-0:on 830619,following Manual Turbine Trip Due to Loss of electro-hydraulic Turbine Control,Block Valve MOV 516 Closed Due to Indicated Leakage Through Pressurizer PORV-430.Caused by High Pressurizer Pressure | /03L-0:on 830619,following Manual Turbine Trip Due to Loss of electro-hydraulic Turbine Control,Block Valve MOV 516 Closed Due to Indicated Leakage Through Pressurizer PORV-430.Caused by High Pressurizer Pressure | |
| 05000244/LER-1983-024-03, /03L-0:on 830621,Foxboro Model N-E11DM Steam Generator Steam Flow Transmitter FT-464 Found Out of Tolerance.Caused by Pressure Static Shift.Transmitter Adjusted | /03L-0:on 830621,Foxboro Model N-E11DM Steam Generator Steam Flow Transmitter FT-464 Found Out of Tolerance.Caused by Pressure Static Shift.Transmitter Adjusted | |
| 05000244/LER-1983-025-03, /03L-0:on 830620,small Leak Found in 3/8-inch Diameter Swag Lock Compression Fitting Connection Upstream of Pressurizer Liquid Sample Manual Isolation Valve V-956E. Caused by Thermal Stress | /03L-0:on 830620,small Leak Found in 3/8-inch Diameter Swag Lock Compression Fitting Connection Upstream of Pressurizer Liquid Sample Manual Isolation Valve V-956E. Caused by Thermal Stress | |
| 05000244/LER-1983-026-01, /01T-0:on 830915,boric Acid Storage Tank Solution Concentration Less than Tech Spec Requirements.Caused by Leakage of Reactor Makeup Water Through Valve FCV-110A & Check Valve 355.Sampling Increased | /01T-0:on 830915,boric Acid Storage Tank Solution Concentration Less than Tech Spec Requirements.Caused by Leakage of Reactor Makeup Water Through Valve FCV-110A & Check Valve 355.Sampling Increased | |
| 05000244/LER-1983-027-03, /03L-0:on 830916,while Reducing Power,Trip Occurred from 17% Power Resulting in Violations of Tech Specs 3.1.1.1a & C.Caused by low-low Steam Generator Level in Loop B.Operator Counseled | /03L-0:on 830916,while Reducing Power,Trip Occurred from 17% Power Resulting in Violations of Tech Specs 3.1.1.1a & C.Caused by low-low Steam Generator Level in Loop B.Operator Counseled | |
| 05000244/LER-1983-028-03, /03L-0:on 830916,small Leak Discovered in Weld on Outlet Side of Boric Acid to FCV-110A Manual Shutoff Valve V-354.Caused by Lack of Fusion in Weld at Point Where Weld Pass Overlapped.Area Ground Out & Rewelded | /03L-0:on 830916,small Leak Discovered in Weld on Outlet Side of Boric Acid to FCV-110A Manual Shutoff Valve V-354.Caused by Lack of Fusion in Weld at Point Where Weld Pass Overlapped.Area Ground Out & Rewelded | |
| 05000244/LER-1983-029-03, /03L-0:on 831116,found Unreliable Feedwater Temp Data Used in Heat Balance Calorimetrics,Resulting in Nuclear Power Ranges Not Calibr Per Tech Specs.Caused by Omitting Resistance Temp Device Data Points from Scan | /03L-0:on 831116,found Unreliable Feedwater Temp Data Used in Heat Balance Calorimetrics,Resulting in Nuclear Power Ranges Not Calibr Per Tech Specs.Caused by Omitting Resistance Temp Device Data Points from Scan | |
| 05000244/LER-1983-030-03, /03L-0:on 831216,actual Setpoint for Permissive Circuit P-10 Found Low at 8% Rather than 10% Full Power. Caused by Conflicting Tech Spec Requirements.Rev Proposed | /03L-0:on 831216,actual Setpoint for Permissive Circuit P-10 Found Low at 8% Rather than 10% Full Power. Caused by Conflicting Tech Spec Requirements.Rev Proposed | |