| | | Reporting criterion |
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| 05000530/LER-1988-001-02, :on 880204,discovered Isolation Valve in Containment Pressure Transmitter Sensing Line Shut.Cause Not Determined.Pressure Transmitter Properly Aligned & Returned to Svc |
- on 880204,discovered Isolation Valve in Containment Pressure Transmitter Sensing Line Shut.Cause Not Determined.Pressure Transmitter Properly Aligned & Returned to Svc
| 10 CFR 50.73(e)(2) |
| 05000528/LER-1988-001-01, :on 880104,special Rept Not Submitted as Required by Tech Spec 3.3.3.3.Special Rept Required to Rept Seismic Monitoring Sys Inoperable Longer than 30 Days. Caused by Personnel Error.Cause Under Review |
- on 880104,special Rept Not Submitted as Required by Tech Spec 3.3.3.3.Special Rept Required to Rept Seismic Monitoring Sys Inoperable Longer than 30 Days. Caused by Personnel Error.Cause Under Review
| |
| 05000530/LER-1988-002, :on 880109,ASME Surveillance Interval Exceeded for Containment Isolation Valve.Caused by Personnel Error. Individual Will Receive Appropriate Counseling &/Or Disciplinary Action |
- on 880109,ASME Surveillance Interval Exceeded for Containment Isolation Valve.Caused by Personnel Error. Individual Will Receive Appropriate Counseling &/Or Disciplinary Action
| 10 CFR 50.73(e)(2)(v) |
| 05000529/LER-1988-002, :on 880118,ASME Section XI Surveillance Test Interval Exceeded.Caused by Inadequate Administrative Controls Established for Tracking of Partially Completed Surveillance Tests.Controls Established |
- on 880118,ASME Section XI Surveillance Test Interval Exceeded.Caused by Inadequate Administrative Controls Established for Tracking of Partially Completed Surveillance Tests.Controls Established
| |
| 05000528/LER-1988-002-01, :on 880122,calculations Indicate That High Log Trip Setpoints Were Set Contrary to Allowable Setpoint. Caused by Inadequate Programmatic Controls to Review Design Changes from Core Reload.Setpoints Reset |
- on 880122,calculations Indicate That High Log Trip Setpoints Were Set Contrary to Allowable Setpoint. Caused by Inadequate Programmatic Controls to Review Design Changes from Core Reload.Setpoints Reset
| 10 CFR 50.73(e)(2) |
| 05000529/LER-1988-003-01, :on 880120,operability of Ac Offsite Sources Not Verified within 1 H After Declaring Diesel Generator Operable Following Preventative Maint.Caused by Personnel Error.Disciplinary Action Administered |
- on 880120,operability of Ac Offsite Sources Not Verified within 1 H After Declaring Diesel Generator Operable Following Preventative Maint.Caused by Personnel Error.Disciplinary Action Administered
| |
| 05000529/LER-1988-004, :on 880210,identified That Discharge Valve of Auxiliary Feedwater Pump Mispositioned in Closed Position. Caused by Personnel Errors.Event Will Be Reviewed by Operating Crews in All Three Units |
- on 880210,identified That Discharge Valve of Auxiliary Feedwater Pump Mispositioned in Closed Position. Caused by Personnel Errors.Event Will Be Reviewed by Operating Crews in All Three Units
| |
| 05000530/LER-1988-004-02, :on 880406,loss of Power Event Occurred Which Resulted in Train B ESF Load Sequencer Sys Actuation.Caused by Error in Work Document Being Utilized to Replace Current Transformer.Maint Testing Stopped |
- on 880406,loss of Power Event Occurred Which Resulted in Train B ESF Load Sequencer Sys Actuation.Caused by Error in Work Document Being Utilized to Replace Current Transformer.Maint Testing Stopped
| 10 CFR 50.73(e)(2) 10 CFR 50.73(r)(2) |
| 05000528/LER-1988-004-01, :on 880229,Mode 4 Entered W/Hpsi Injection Pumps Inoperable.Caused by Procedural Inadequacy.Procedure Revised to Include Steps to Ensure That HPSI Pumps Returned to Operable Status Prior to Entering Mode 4 |
- on 880229,Mode 4 Entered W/Hpsi Injection Pumps Inoperable.Caused by Procedural Inadequacy.Procedure Revised to Include Steps to Ensure That HPSI Pumps Returned to Operable Status Prior to Entering Mode 4
| 10 CFR 50.73(c)(2) |
| 05000529/LER-1988-005-01, :on 880221,inadvertent Safety Injection from Safety Injection Tanks (Bp)(Acc) Occurred.Caused by Personnel Error.Appropriate Disciplinary Measures Will Be Taken.Malfunctioning Fuse Replaced |
- on 880221,inadvertent Safety Injection from Safety Injection Tanks (Bp)(Acc) Occurred.Caused by Personnel Error.Appropriate Disciplinary Measures Will Be Taken.Malfunctioning Fuse Replaced
| 10 CFR 50.73(s)(2) 10 CFR 50.73(s)(1) 10 CFR 50.73(s)(1)(4) |
| 05000528/LER-1988-005, :on 880123,backhoe Operator Inadvertently Damaged Post Indication Valve (Piv)(Kp)(Isv) & Caused Fire Suppression Water to Discharge Into Protected Area.Caused by Inadequate Procedure.Procedures Implemented |
- on 880123,backhoe Operator Inadvertently Damaged Post Indication Valve (Piv)(Kp)(Isv) & Caused Fire Suppression Water to Discharge Into Protected Area.Caused by Inadequate Procedure.Procedures Implemented
| |
| 05000530/LER-1988-005-01, :on 880908,technician Entered Locked High Radiation Area W/O Prior Approval of Radiation Protection Personnel.Caused by Personnel Error.Technician Denied Access to Controlled Area Pending Further Training |
- on 880908,technician Entered Locked High Radiation Area W/O Prior Approval of Radiation Protection Personnel.Caused by Personnel Error.Technician Denied Access to Controlled Area Pending Further Training
| |
| 05000530/LER-1988-005-02, :on 880908,maint Dept Technician Reported Unauthorized Entry Into Locked High Radiation Area on 880912.Caused by Personnel Error.Technician Counseled, Disciplined & Provided W/Addl Training |
- on 880908,maint Dept Technician Reported Unauthorized Entry Into Locked High Radiation Area on 880912.Caused by Personnel Error.Technician Counseled, Disciplined & Provided W/Addl Training
| |
| 05000529/LER-1988-006-01, :on 880726,B Train Loss of Power ESF Actuation Occurred.Caused by Inadequate Plant Design & Installation of Temporary Ventilation Trunk.Ventilation Trunk Removed from Transformer Leads W/O Incident |
- on 880726,B Train Loss of Power ESF Actuation Occurred.Caused by Inadequate Plant Design & Installation of Temporary Ventilation Trunk.Ventilation Trunk Removed from Transformer Leads W/O Incident
| |
| 05000528/LER-1988-006, :on 880321,determined That Allowable Surveillance Test Interval Had Been Exceeded for Incore Detector Sys.Caused by Personnel Error & Inadequate Programmatic Controls.Personnel Counseled |
- on 880321,determined That Allowable Surveillance Test Interval Had Been Exceeded for Incore Detector Sys.Caused by Personnel Error & Inadequate Programmatic Controls.Personnel Counseled
| 10 CFR 50.73(c)(2) 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(v) |
| 05000528/LER-1988-008, :on 880212,RCS Leakage Monitor Declared Inoperable Due to Notification of Particulate change-out Excess.Caused by Personnel error.Change-out Periodicity Revised to Once Per 24 H |
- on 880212,RCS Leakage Monitor Declared Inoperable Due to Notification of Particulate change-out Excess.Caused by Personnel error.Change-out Periodicity Revised to Once Per 24 H
| |
| 05000530/LER-1988-008-02, :on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulted in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Temporary Heat Trace Installed |
- on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulted in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Temporary Heat Trace Installed
| 10 CFR 50.73(e)(2) 10 CFR 50.73(s)(2) 10 CFR 50.73(s)(2)(iii) |
| 05000530/LER-1988-008, :on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulting in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Resistance Heating Installed |
- on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulting in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Resistance Heating Installed
| |
| 05000529/LER-1988-010, :on 880415,allowable Surveillance Test (ST) Interval for Plant Vent Sys Monitors (Pvsm) Exceeded.Caused by Personnel Error.Appropriate ST on Pvsm Completed & Terminology in ST 75ST-9ZZ07 Changed |
- on 880415,allowable Surveillance Test (ST) Interval for Plant Vent Sys Monitors (Pvsm) Exceeded.Caused by Personnel Error.Appropriate ST on Pvsm Completed & Terminology in ST 75ST-9ZZ07 Changed
| |
| 05000528/LER-1988-010-01, :on 880706,ground Fault in 13.8 Kv Bus Caused Fire in Unit Auxiliary Transformer & Reactor Trip.Caused by Bullet Hole Point Faults in Phase Bus B Adjacent to Support Bar.Fire Extinguished & Bus Reenergized |
- on 880706,ground Fault in 13.8 Kv Bus Caused Fire in Unit Auxiliary Transformer & Reactor Trip.Caused by Bullet Hole Point Faults in Phase Bus B Adjacent to Support Bar.Fire Extinguished & Bus Reenergized
| |
| 05000529/LER-1988-011-01, :on 880522,decontamination Worker Received 2.607 Rem Whole Body Dose to Right Leg Resulting in Cumulative Whole Body Exposure for Quarter of 3.209 Rem. Caused by Incomplete Decontamination |
- on 880522,decontamination Worker Received 2.607 Rem Whole Body Dose to Right Leg Resulting in Cumulative Whole Body Exposure for Quarter of 3.209 Rem. Caused by Incomplete Decontamination
| |
| 05000529/LER-1988-012-01, :on 880615,Channel D Linear Power Inoperable Due to Improper Landing of Leads to Plant Protection Sys Drawer.Caused by Personnel Error.Plant Protection Sys Channel D Linear Power Density Tripped |
- on 880615,Channel D Linear Power Inoperable Due to Improper Landing of Leads to Plant Protection Sys Drawer.Caused by Personnel Error.Plant Protection Sys Channel D Linear Power Density Tripped
| 10 CFR 50.73(s)(2) |
| 05000528/LER-1988-013, :on 880325,essential Motor Driven Auxiliary Feedwater Pump Failed to Achieve Rated Pressure.Caused by Stress Corrosion Cracking/Hydrogen Embrittlement.Matl Changes Initiated.Part 21 Related |
- on 880325,essential Motor Driven Auxiliary Feedwater Pump Failed to Achieve Rated Pressure.Caused by Stress Corrosion Cracking/Hydrogen Embrittlement.Matl Changes Initiated.Part 21 Related
| 10 CFR 21.21(b)(3) 10 CFR 50.73(o)(2) |
| 05000529/LER-1988-014-01, :on 881116,reactor Trip Occurred as Result of Low Steam Generator Water Level.Caused by Inadequate Feedwater Flow Due to Leakage of Packing.Procedural Changes Implemented & Evaluation Being Performed |
- on 881116,reactor Trip Occurred as Result of Low Steam Generator Water Level.Caused by Inadequate Feedwater Flow Due to Leakage of Packing.Procedural Changes Implemented & Evaluation Being Performed
| |
| 05000528/LER-1988-014, Discusses Reportability Determination of LER-88-014-00 Re Inoperability of Unit 2 Main Steam Safety Valves,Per 10CFR50.73.Util Believes Event Caused by Misinterpretation of Guidance Provided in 10CFR50.73 & NUREG-1022 | Discusses Reportability Determination of LER-88-014-00 Re Inoperability of Unit 2 Main Steam Safety Valves,Per 10CFR50.73.Util Believes Event Caused by Misinterpretation of Guidance Provided in 10CFR50.73 & NUREG-1022 | |
| 05000528/LER-1988-015, :on 880512,automatic Actuation of Reactor Protection Sys Occurred.Power Supply Found to Be Varying in Amplitude Intermittently Which Could Cause Varying Removal & Reinstatement of Buck & Boost Voltage |
- on 880512,automatic Actuation of Reactor Protection Sys Occurred.Power Supply Found to Be Varying in Amplitude Intermittently Which Could Cause Varying Removal & Reinstatement of Buck & Boost Voltage
| 10 CFR 50.73(s)(2)(ii) 10 CFR 50.73(s)(2) |
| 05000529/LER-1988-015-01, :on 881203,new Fuel Area Radiation Monitor RU-19 Discovered Inoperable.Caused by Malfunction in Clock in Computer Internals to Monitor.Area Survey Conducted W/Negative Results & Night Order Issued |
- on 881203,new Fuel Area Radiation Monitor RU-19 Discovered Inoperable.Caused by Malfunction in Clock in Computer Internals to Monitor.Area Survey Conducted W/Negative Results & Night Order Issued
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(iv) 10 CFR 50.73(e)(2)(v) |
| 05000529/LER-1988-015, :on 881203,chemistry Technician Discovered That New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Malfunction of Clock in Computer Internal to Monitor. Monitor Reset & Operated Properly |
- on 881203,chemistry Technician Discovered That New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Malfunction of Clock in Computer Internal to Monitor. Monitor Reset & Operated Properly
| 10 CFR 50.73(s)(2) |
| 05000528/LER-1988-016, :on 880514,reactor Trip Occurred.Caused by Nonconservative Operator Performance During Reactor Startup. Info Utilized for Estimated Critical Condition Will Be Corrected |
- on 880514,reactor Trip Occurred.Caused by Nonconservative Operator Performance During Reactor Startup. Info Utilized for Estimated Critical Condition Will Be Corrected
| 10 CFR 50.73(e)(2) |
| 05000529/LER-1988-016-01, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | |
| 05000528/LER-1988-017, :on 880529,Trains a & B Essential Chillers Discovered Inoperable Due to Shut Root Isolation Valves for Transmitter.Caused by Personnel Errors While Affixing Warning Labels Near Valves |
- on 880529,Trains a & B Essential Chillers Discovered Inoperable Due to Shut Root Isolation Valves for Transmitter.Caused by Personnel Errors While Affixing Warning Labels Near Valves
| 10 CFR 50.73(e)(2) |
| 05000528/LER-1988-018, :on 880729,NSSS ESF Actuation Sys Cabinet Potter & Brumfield Relay Failure Discovered.Caused by Inadequate Design by Cabinet Engineer.Relays Replaced & Design Changes Implemented |
- on 880729,NSSS ESF Actuation Sys Cabinet Potter & Brumfield Relay Failure Discovered.Caused by Inadequate Design by Cabinet Engineer.Relays Replaced & Design Changes Implemented
| 10 CFR 21.21(b)(3) 10 CFR 21.21(b)(2) |
| 05000528/LER-1988-020, :on 881210,control Element Assemblies Slipped. Caused by Apparent Ground on Lower Lift Coil & Design Defect in Control Element Drive Mechanism Control Sys.Part 21 Related |
- on 881210,control Element Assemblies Slipped. Caused by Apparent Ground on Lower Lift Coil & Design Defect in Control Element Drive Mechanism Control Sys.Part 21 Related
| 10 CFR 21.21(b)(3) 10 CFR 21.21(b)(2) |
| 05000528/LER-1988-021, :on 880821,reactor Trip Occurred Due to High Pressurizer Pressure.Caused by Failure of Microswitch in Stator Coolant Flow Trip Circuit.Microswitch Replaced.W/ |
- on 880821,reactor Trip Occurred Due to High Pressurizer Pressure.Caused by Failure of Microswitch in Stator Coolant Flow Trip Circuit.Microswitch Replaced.W/
| 10 CFR 50.73(c)(2) |
| 05000528/LER-1988-022, :on 880319,bolting Which Secures Gasket Retainer Plate Fractured.Caused by Bolts Not Meeting Spec Requirements.Changes Being Implemented to Replace Matl.W/ |
- on 880319,bolting Which Secures Gasket Retainer Plate Fractured.Caused by Bolts Not Meeting Spec Requirements.Changes Being Implemented to Replace Matl.W/
| 10 CFR 21.21(b)(3) 10 CFR 21.21(b)(2) 10 CFR 50.73(o)(2) |
| 05000528/LER-1988-025, :on 881201,discovered Surveillance Procedure Not Completed within Tech Specs Required Frequency.Caused by Inadequate Review of Amend.Surveillance Interval Revised to Be Consistent W/Amend |
- on 881201,discovered Surveillance Procedure Not Completed within Tech Specs Required Frequency.Caused by Inadequate Review of Amend.Surveillance Interval Revised to Be Consistent W/Amend
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(iv) 10 CFR 50.73(e)(2)(viii)(A) 10 CFR 50.73(e)(2)(iii) |