| | | Reporting criterion |
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| 05000277/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | |
| 05000277/LER-1979-001-01, /01T-0 on 790104:design Errors in Cable Designations Were Identified.Ten Cables Found to Be Designated Nonsafeguard.Caused by Improper Designation of Cables During Design Phase.New Cable Routing Completed | /01T-0 on 790104:design Errors in Cable Designations Were Identified.Ten Cables Found to Be Designated Nonsafeguard.Caused by Improper Designation of Cables During Design Phase.New Cable Routing Completed | |
| 05000278/LER-1979-001-03, /03L-0 on 790111:discovered That Recorded hi-hi Trip Valve for Steam Line Radiation Monitor Was 50 man-rem/h Greater than Tech Spec Limit & No Corrective Action Taken. Caused by Procedural Deficiency | /03L-0 on 790111:discovered That Recorded hi-hi Trip Valve for Steam Line Radiation Monitor Was 50 man-rem/h Greater than Tech Spec Limit & No Corrective Action Taken. Caused by Procedural Deficiency | |
| 05000277/LER-1979-002-01, /01T-0 on 790108:cable Spreading Room Cardox Sys Disabled W/O Firewatch Present.Absence Due to Failure of Personnel to Notify Shift Supervisor Upon Work Completion | /01T-0 on 790108:cable Spreading Room Cardox Sys Disabled W/O Firewatch Present.Absence Due to Failure of Personnel to Notify Shift Supervisor Upon Work Completion | |
| 05000277/LER-1979-002, Forwards LER 79-002/01T-0 | Forwards LER 79-002/01T-0 | |
| 05000278/LER-1979-002-01, /01T-0 on 790108:roof Vent Stack Instantaneous Gas Release Rate Above Tech Spec Limit Due to Valve Operator Failure,Causing Loss of Inservice RHR Loop,Rise in Coolant Temp & Gaseous Release Via Core Isolation Cooling Valves | /01T-0 on 790108:roof Vent Stack Instantaneous Gas Release Rate Above Tech Spec Limit Due to Valve Operator Failure,Causing Loss of Inservice RHR Loop,Rise in Coolant Temp & Gaseous Release Via Core Isolation Cooling Valves | |
| 05000278/LER-1979-002, Forwards LER 79-002/01T-0 | Forwards LER 79-002/01T-0 | |
| 05000277/LER-1979-003-03, /03L-0 on 790109:2A Offgas Radiation Monitor Failed Downscale.Dirt on Contacts of Trip Test/Zero Calibr Switch Caused Input Key to Remain Deenergized Upon Release of Switch.Contacts Were Cleaned & Monitor Returned to Svc | /03L-0 on 790109:2A Offgas Radiation Monitor Failed Downscale.Dirt on Contacts of Trip Test/Zero Calibr Switch Caused Input Key to Remain Deenergized Upon Release of Switch.Contacts Were Cleaned & Monitor Returned to Svc | |
| 05000278/LER-1979-003-03, /03L-0 on 790111:during Unit Shutdown for Maint an Instrument Shutoff Valve to Pressure Switch Found Closed Due to Personnel Error.Unit Operated 9 Days W/Instrument Out of Svc.Appropriate Disciplinary Action Taken | /03L-0 on 790111:during Unit Shutdown for Maint an Instrument Shutoff Valve to Pressure Switch Found Closed Due to Personnel Error.Unit Operated 9 Days W/Instrument Out of Svc.Appropriate Disciplinary Action Taken | |
| 05000277/LER-1979-004-03, /04L-0 on 790112:during Surveillance Test of Cable Spreading Room Smoke Detector,Annunciator Could Not Be Reset Because It Was Not Properly Reset Previously.Detector Lead Disconnected to Reset Annunciator | /04L-0 on 790112:during Surveillance Test of Cable Spreading Room Smoke Detector,Annunciator Could Not Be Reset Because It Was Not Properly Reset Previously.Detector Lead Disconnected to Reset Annunciator | |
| 05000278/LER-1979-004-03, /03L-0 on 790117:during Surveillance Test,Setpoint of PS-3-14-44D Found to Be Greater than Tech Spec Max.Caused by Setpoint Drift on static-o-ring Model 5N-AA3 Pressure Switch.Instrument Recalibrated | /03L-0 on 790117:during Surveillance Test,Setpoint of PS-3-14-44D Found to Be Greater than Tech Spec Max.Caused by Setpoint Drift on static-o-ring Model 5N-AA3 Pressure Switch.Instrument Recalibrated | |
| 05000277/LER-1979-005-03, /03L-0 on 790118:at Power,Routine Surveillance Test Revealed Setpoint of DPIS-2-14-43B Was Below Tech Spec Min.Caused by Instrument DPIS-2-14-43B Being Out of Calibr Due to Setpoint Drift | /03L-0 on 790118:at Power,Routine Surveillance Test Revealed Setpoint of DPIS-2-14-43B Was Below Tech Spec Min.Caused by Instrument DPIS-2-14-43B Being Out of Calibr Due to Setpoint Drift | |
| 05000278/LER-1979-005-03, /03L-0 on 790208:setpoint of Reactor Core Isolation Cooling Turbine Steam Supply Flow Sensor Was Above Tech Specs Max.Caused by Setpoint Drift on Barton Model 288 Differential Pressure Switch.Switch Recalibrated | /03L-0 on 790208:setpoint of Reactor Core Isolation Cooling Turbine Steam Supply Flow Sensor Was Above Tech Specs Max.Caused by Setpoint Drift on Barton Model 288 Differential Pressure Switch.Switch Recalibrated | |
| 05000277/LER-1979-006-01, /01T-0 on 790130:recirculation Motor Generator Set Room Fire Detection Sys (Smoke Detectors) Disabled for Mod Work & Not Restored When Work Completed.Caused by Personnel Error.Sys Restored to Svc Upon Discovery | /01T-0 on 790130:recirculation Motor Generator Set Room Fire Detection Sys (Smoke Detectors) Disabled for Mod Work & Not Restored When Work Completed.Caused by Personnel Error.Sys Restored to Svc Upon Discovery | |
| 05000277/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | |
| 05000278/LER-1979-006-03, /03L-1 on 790212:at Power & During Surveillance Test,Setpoint of B Core Spray Pump Start Timer Was Less than Tech Spec Min.Caused by Setpoint Drift on GE Model CR-2820 Time Delay Relay.Relay Readjusted & Tested | /03L-1 on 790212:at Power & During Surveillance Test,Setpoint of B Core Spray Pump Start Timer Was Less than Tech Spec Min.Caused by Setpoint Drift on GE Model CR-2820 Time Delay Relay.Relay Readjusted & Tested | |
| 05000278/LER-1979-007-03, /03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested | /03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested | |
| 05000277/LER-1979-008-03, /03L-0 on 790225:fuses Were Blown in Control Circuit of Main Steam Relief Valve RV-71L.Replacements Blew Immediately.Caused by Failed Solenoid & Short Circuit.Leads to Solenoid Lifted;Fuses & Solenoid Replaced | /03L-0 on 790225:fuses Were Blown in Control Circuit of Main Steam Relief Valve RV-71L.Replacements Blew Immediately.Caused by Failed Solenoid & Short Circuit.Leads to Solenoid Lifted;Fuses & Solenoid Replaced | |
| 05000277/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | |
| 05000277/LER-1979-008-01, /01T-0 on 790219:steady State Power Level Exceeded License Limit by Less than 2% for About 6-h.Caused by Error Calculating Scanned Feedwater Flow.Power Reduced to License Limit | /01T-0 on 790219:steady State Power Level Exceeded License Limit by Less than 2% for About 6-h.Caused by Error Calculating Scanned Feedwater Flow.Power Reduced to License Limit | |
| 05000277/LER-1979-009-03, /03L-0 on 790213:fire Alarm Sys Malfunctioned, Causing Audible Signal to Alarm W/O Coding.Caused by Mechanical Binding of Cam in Alarm Box.Binding Problem Corrected & Sys Returned to Svc | /03L-0 on 790213:fire Alarm Sys Malfunctioned, Causing Audible Signal to Alarm W/O Coding.Caused by Mechanical Binding of Cam in Alarm Box.Binding Problem Corrected & Sys Returned to Svc | |
| 05000278/LER-1979-009-03, /03L-0 on 790307:calculated Torus Water Level Did Not Provide Proper Torus Water Vol Per Tech Spec.Caused by Failure to See Pressure Differential Between Drywell & Torus Holds Level in Downcomers Was Below Torus Level | /03L-0 on 790307:calculated Torus Water Level Did Not Provide Proper Torus Water Vol Per Tech Spec.Caused by Failure to See Pressure Differential Between Drywell & Torus Holds Level in Downcomers Was Below Torus Level | |
| 05000277/LER-1979-010-01, /01T-0 on 790226:power & Control Cables Associated W/Recirculation Pump Discharge Valves & Bypass Valves Were Found Routed in non-safeguard Cable Trays.Caused by Improperly Designated Cables During Design Phase | /01T-0 on 790226:power & Control Cables Associated W/Recirculation Pump Discharge Valves & Bypass Valves Were Found Routed in non-safeguard Cable Trays.Caused by Improperly Designated Cables During Design Phase | |
| 05000277/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | |
| 05000278/LER-1979-011-01, /01T-0 on 790323:during Routine Insp of Drywell & Torus Ventilation Valves,Inflatable Disc Seals Were Found Depressurized.Caused by Procedural Deficiency Following Mod to Drywell & Torus Vent Valves.Procedures Revised | /01T-0 on 790323:during Routine Insp of Drywell & Torus Ventilation Valves,Inflatable Disc Seals Were Found Depressurized.Caused by Procedural Deficiency Following Mod to Drywell & Torus Vent Valves.Procedures Revised | |
| 05000278/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | |
| 05000277/LER-1979-011-01, /01T-0 on 790302:engineering Review Determined Certain Containment Isolation Valves Incapable of Closing Against LOCA Pressure.Caused by Design Oversight.Future Mod to Expand Valve Open Alarm to Include Seal Low Pressure | /01T-0 on 790302:engineering Review Determined Certain Containment Isolation Valves Incapable of Closing Against LOCA Pressure.Caused by Design Oversight.Future Mod to Expand Valve Open Alarm to Include Seal Low Pressure | |
| 05000277/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | |
| 05000278/LER-1979-013-01, /01T-0 on 790613:main Steam Relief Valve RV3-2-71L Lifted,Causing Torus Water Vol to Exceed Tech Spec Limit by 2.6%.Reactor Manually Scrammed.Valve Replaced & Sent to Wiley Lab to Determine Cause for Failure | /01T-0 on 790613:main Steam Relief Valve RV3-2-71L Lifted,Causing Torus Water Vol to Exceed Tech Spec Limit by 2.6%.Reactor Manually Scrammed.Valve Replaced & Sent to Wiley Lab to Determine Cause for Failure | |
| 05000278/LER-1979-013, Forwards LER 79-013/01T-0 | Forwards LER 79-013/01T-0 | |
| 05000278/LER-1979-014, /O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement | /O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement | |
| 05000277/LER-1979-014-03, /03L-0 on 790327:trip Setpoint Drift of Drywell High Pressure Switch Was Beyond Tech Spec Limit.Caused by Static-O-Ring Model 12N-AA4 Being Out of Calibr Due to Setpoint Drift.It Was Recalibrated & Returned to Svc | /03L-0 on 790327:trip Setpoint Drift of Drywell High Pressure Switch Was Beyond Tech Spec Limit.Caused by Static-O-Ring Model 12N-AA4 Being Out of Calibr Due to Setpoint Drift.It Was Recalibrated & Returned to Svc | |
| 05000278/LER-1979-015, /O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc | /O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc | |
| 05000278/LER-1979-016-03, /03L-0 on 790628:while at Power,Routine Surveillance Test Revealed Setpoint of Switch 2 Was Below Tech Spec Min.Caused by Barton Model 288 Instrument Out of Calibr from Drift.Instrument Recalibr | /03L-0 on 790628:while at Power,Routine Surveillance Test Revealed Setpoint of Switch 2 Was Below Tech Spec Min.Caused by Barton Model 288 Instrument Out of Calibr from Drift.Instrument Recalibr | |
| 05000278/LER-1979-017-31, /03L-0 on 790615:while Reactor Subcritical,D Main Steam Line Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts. Condition Corrected by Repeated Testing | /03L-0 on 790615:while Reactor Subcritical,D Main Steam Line Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts. Condition Corrected by Repeated Testing | |
| 05000278/LER-1979-017, Discusses LER 79-017/03L-0.While Reactor Subcritical & Less than 212 F,Main Steam Line D Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts.Repeated Testing Corrected Condition | Discusses LER 79-017/03L-0.While Reactor Subcritical & Less than 212 F,Main Steam Line D Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts.Repeated Testing Corrected Condition | |
| 05000278/LER-1979-018-03, /03L-0 on 790630:during Surveillance Testing, Reactor Water Sample Line Isolation Valve Failed to Close. Caused by Lack of Valve Operator Spring Tension.Valve Operator Spring Tension Was Increased | /03L-0 on 790630:during Surveillance Testing, Reactor Water Sample Line Isolation Valve Failed to Close. Caused by Lack of Valve Operator Spring Tension.Valve Operator Spring Tension Was Increased | |
| 05000277/LER-1979-019-03, /03L-0 on 790501:during Surveillance Testing of Normally Open Primary Containment Isolation Valves,Four Oxygen Analyzer Sys Isolation Valves Failed to Close.Caused by Binding of Pistons in Valve Bodies.Valve Parts Rebuilt | /03L-0 on 790501:during Surveillance Testing of Normally Open Primary Containment Isolation Valves,Four Oxygen Analyzer Sys Isolation Valves Failed to Close.Caused by Binding of Pistons in Valve Bodies.Valve Parts Rebuilt | |
| 05000278/LER-1979-019-01, /01T-0 on 790621:during Seismic Support Insp Program, Reactor Core Isolation Cooling Piping Anchor Discovered to Have Two Bolts That Could Not Be Torqued. Caused by Improper Installation of Bolt Shells | /01T-0 on 790621:during Seismic Support Insp Program, Reactor Core Isolation Cooling Piping Anchor Discovered to Have Two Bolts That Could Not Be Torqued. Caused by Improper Installation of Bolt Shells | |
| 05000278/LER-1979-019, Forwards LER 79-019/01T-0 | Forwards LER 79-019/01T-0 | |
| 05000277/LER-1979-020-03, /03L-0 on 790503:solution Temp in Standby Liquid Control Sys Found to Be 2 F Less than Tech Spec Requirement for Existing Boron Concentration.Caused by Incorrect Acceptable Temp Controller Setpoint Range | /03L-0 on 790503:solution Temp in Standby Liquid Control Sys Found to Be 2 F Less than Tech Spec Requirement for Existing Boron Concentration.Caused by Incorrect Acceptable Temp Controller Setpoint Range | |
| 05000278/LER-1979-020-01, /01T-0 on 790621:radioactive Release Rate at Main Stack During Plant Startup Exceeded Tech Specs.Caused by Deficiency in Procedure for Depressurization Following Shutdown.Investigation Underway to Improve Procedure | /01T-0 on 790621:radioactive Release Rate at Main Stack During Plant Startup Exceeded Tech Specs.Caused by Deficiency in Procedure for Depressurization Following Shutdown.Investigation Underway to Improve Procedure | |
| 05000278/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | |
| 05000278/LER-1979-021-03, /03X-1:on 790630,during Surveillance Testing,Main Steam Sample Line Inboard Isolation Valve Failed to Close. Probably Caused by Valve Packing Binding or Solenoid Valve Sticking While Valve Was at High Temp | /03X-1:on 790630,during Surveillance Testing,Main Steam Sample Line Inboard Isolation Valve Failed to Close. Probably Caused by Valve Packing Binding or Solenoid Valve Sticking While Valve Was at High Temp | |
| 05000277/LER-1979-022-03, /03L-0 on 790513:fire Hose Nozzles Were Missing from Two Hose Stations in Turbine Bldg.Cause Not Noted. Nozzles Replaced & Wrench Tightened to Inhibit Removal | /03L-0 on 790513:fire Hose Nozzles Were Missing from Two Hose Stations in Turbine Bldg.Cause Not Noted. Nozzles Replaced & Wrench Tightened to Inhibit Removal | |
| 05000278/LER-1979-022-03, /03L-0 on 790719:annunciator Sys II Drywell Pressure Permits Containment Spray Alarmed During Routine Startup.Caused by Failure of Diaphragm on PS-3-10-119D. Switch Repaired,Tested & Returned to Svc within Five Days | /03L-0 on 790719:annunciator Sys II Drywell Pressure Permits Containment Spray Alarmed During Routine Startup.Caused by Failure of Diaphragm on PS-3-10-119D. Switch Repaired,Tested & Returned to Svc within Five Days | |
| 05000277/LER-1979-023-01, /01T-0 on 790724:insp Program Performed in Response to IE Bulletin 79-02 Identified Two Anchors in One Support Which Failed to Torque Test Properly.Caused by Improper Installation.Anchors Replaced | /01T-0 on 790724:insp Program Performed in Response to IE Bulletin 79-02 Identified Two Anchors in One Support Which Failed to Torque Test Properly.Caused by Improper Installation.Anchors Replaced | |
| 05000277/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | |
| 05000277/LER-1979-023-04, /04T-0 on 790515:routine Ph Analysis of Sewage Plant Effluent Identified Ph of 5.8 Which Exceeded Tech Specs.Caused by Air Blower Failure Which Allowed Dissolved Oxygen to Drop to 0 & Aeration Tank to Become Anaerobic | /04T-0 on 790515:routine Ph Analysis of Sewage Plant Effluent Identified Ph of 5.8 Which Exceeded Tech Specs.Caused by Air Blower Failure Which Allowed Dissolved Oxygen to Drop to 0 & Aeration Tank to Become Anaerobic | |
| 05000277/LER-1979-024, Forwards LER 79-024/01T-0 | Forwards LER 79-024/01T-0 | |
