Pages that link to "05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump"
Jump to navigation
Jump to search
The following pages link to 05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump:
Displayed 50 items.
- ML12334A443 (← links)
- ML12188A542 (← links)
- ML11117A304 (← links)
- RC-14-0084, Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days (← links)
- RC-14-0085, Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days (← links)
- RC-06-0051, Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours (← links)
- RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area (← links)
- ML032660507 (← links)
- ML030860512 (← links)
- 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System (← links)
- 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator (← links)
- ML23150A162 (redirect page) (← links)
- 05000395/LER-2023-001 (redirect page) (← links)
- 05000395/LER-2001-003 (← links)
- 05000395/LER-2001-002 (← links)
- 05000395/LER-2001-001 (← links)
- 05000395/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-006, Forwards LER 82-006/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1994-002, Forwards LER 94-002 in Response to NRC Insp Rept 50-395/94-07 (← links)
- 05000395/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000395/LER-1983-002, Forwards LER 83-002/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-055, Forwards LER 82-055/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-054, Forwards LER 82-054/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-052, Forwards LER 82-052/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-051, Forwards LER 82-051/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-001, Forwards LER 82-001/03L-0 (← links)
- 05000395/LER-1983-001, Updated LER 83-001/01T-1:on 830119,three Refueling Water Storage Tank Level Transmitters Failed High.Caused by Transmitter Base Freezing.Transmitters Thawed.Insulated Encls & Addl Permanent Heat Trace Will Be Installed (← links)
- 05000395/LER-1982-061, Forwards LER 82-061/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-044, Forwards LER 82-044/01T-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-045, Forwards LER 82-045/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-046, Forwards LER 82-046/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-047, Forwards LER 82-047/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-049, Forwards LER 82-049/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-043, Forwards LER 82-043/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-042, Forwards LER 82-042/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-039, Forwards LER 82-039/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-040, Forwards LER 82-040/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-038, Forwards LER 82-038/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-035, Forwards LER 82-035/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-034, Forwards LER 82-034/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-037, Forwards LER 82-037/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-028, Forwards LER 83-028/01T-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-029, Forwards LER 83-029/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-027, Forwards LER 83-027/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analyis Encl (← links)
- 05000395/LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-020, Forwards LER 82-020/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-014, Forwards LER 82-014/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1991-006, Forwards LER 91-006 Re Inadvertent ESF Actuation of DG in Response to Violation Noted in Insp Rept 50-395/91-17. Corrective Actions:Operations Staff Briefed on Necessity of Attention to Detail (← links)
- 05000395/LER-1982-064, Forwards LER 82-064/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-066, Forwards LER 82-066/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-063, Forwards LER 82-063/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-062, Forwards LER 82-062/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-060, /03L-0:on 831117,investigation Into Previously Submitted LER 83-060 Revealed Four Testable Components Not Tested on Quarterly Basis.Caused by Inadequate Procedure.Test Procedures Revised (← links)
- 05000395/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-038, Forwards LER 83-038/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-034, Forwards LER 83-034/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-031, Forwards LER 83-031/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-030, Forwards LER 83-030/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-025, Forwards LER 83-025/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-026, Forwards LER 83-026/03L-0 (← links)
- 05000395/LER-1983-021, Forwards LER 83-021/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-023, Forwards LER 83-023/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-022, Forwards LER 83-022/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-024, Forwards LER 83-024/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-020, Forwards LER 83-020/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1996-004, Responds to Telcon W/G Lippard Re LER 96-004 on Leakage Past Motor Driven EFW Flow Control Valves Discovered During Recently Completed Refueling Outage at Station (← links)
- 05000395/LER-1983-019, Forwards LER 83-019/01L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-017, Forwards LER 83-017/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-008, Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-003, Forwards LER 82-003/03L-0 (← links)
- 05000395/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1985-015, Notifies That Util Agrees W/Alleged Violation 01 in Insp Rept 50-395/85-28.Corrective Actions Documented in Encl LER 85-015,Rev 1.Supervisors Counseled Re Equipment Operability. Util in Full Compliance W/Corrective Action (← links)
- 05000395/LER-1985-010, Forwards LER 85-010-00 in Response to Violations Noted in Insp Rept 50-395/85-15 (← links)
- 05000395/LER-1988-006, Special Rept Spr 88-05:on 880512,safety Injection/Reactor Trip Occurred When MSIV a Shut During Testing.Details Described in Encl LER 88-06.Accumulative Usage Factor for Affected Safety Injection Nozzle Did Not Exceed 0.70 (← links)
- 05000395/LER-1987-018, Forwards 870827 LER 87-018-00 Which Responds to Violation Addressed in Encl 1,Item a of Insp Rept 50-395/87-24.LER Addresses Reason for Violation & Corrective Actions Taken to Prevent Recurrence (← links)
- 05000395/LER-1987-007, Forwards 870513 LER 87-007 in Response to Violation Noted in Insp Rept 50-395/87-07.Util Agrees W/Alleged Violation. Corrective Action Should Allow Full Compliance by 870630 When Change to Surveillance Test Procedure 404.901 Fi (← links)
- IR 05000395/2023004 (← links)
- 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System (← links)
- 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator (← links)
- 05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump (← links)
- 05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault (← links)
- 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator (← links)
- 05000395/LER-2022-001, (VCSNS) Unit 1 - Revised Expected Submission Date for Supplement to Licensee Event Report 2022-001-00 (← links)
- 05000395/LER-2022-002, (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 (← links)
- 05000395/LER-2021-001-01, Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-1998-005, :on 980430,inadequate ASME Code Relief Valve Surveillance Testing Was Determined.Caused by Failure to Upgrade IST Implementing Procedures to Address Addl Test Requirements.Initiated Review (← links)
- 05000395/LER-1989-013, :on 890808,design Deficiency in Svc Water Pump House Ventilation Sys Confirmed.Deficiency Could Cause Flooding & Result in Failure of safety-related Electrical Power Supplies.Incident Reportable Per Part 21 (← links)
- 05000395/LER-1989-014, :on 890823,identified Noncompliance W/Tech Spec 3.11.2.1, Gaseous Effluent in That Two Waste Gas Storage Tanks Release W/Lower Limit of Detection Values Greater than Allowed.Caused by Personnel Error (← links)
- 05000395/LER-1988-012, :on 881202,identified Design Deficiency W/Class 1E 125 Volt Dc Distribution Sys.Caused by Design Deficiency. Mods to Dc Sys Appear to Be Ultimate Resolution to Design Problem (← links)
- 05000395/LER-1989-004, :on 890302,component Cooling Water Pump Started as Result of Improper Maint Activity,Resulting in ESF Actuation.Caused by Personnel Error.Communication Re Properly Scheduling Maint Established (← links)
- 05000395/LER-1989-009, :on 890428,discrepancy Noted Re Vol of Stored Diesel Fuel Oil in Current Design Basis Calculation & Tech Spec Sections Re Ac Sources.Caused by Personnel Error.Tech Spec Fuel Oil Vol Increased to 47,100 Gallons (← links)
- 05000395/LER-1989-007, :on 890414,missing Jumper Prevented RHR Train a mini-flow Isolation Valve from auto-closing.Caused by Removing Contacts in Closed Circuitry & Leaving Circuit Open.Jumper Installed (← links)
- 05000395/LER-1989-003, :on 890217,isolation Relay Installed to Isolate Multiple Dc Grounds on Valve Solenoids Determined Improperly Designed & Valves Declared Inoperable.Caused by Design Deficiency.Circuit Designs Modified (← links)
- 05000395/LER-1989-006, :on 890401 & 0330,turbine Trip Occurred Due to High Moisture Separator Reheater Level.Caused by Various Secondary Equipment Malfunctions.Reactor Trip & Trip Recovery Procedures Implemented (← links)
- 05000395/LER-1989-010, :on 890527,discovered That Channel Check for Sodium Hydroxide Storage Tank Level Not Performed as Required by Tech Spec 3.3.3.6.Caused by Personnel Error. Procedure 135.001 Revised & Issued (← links)
- 05000395/LER-1989-012, :on 890711,turbine Trip/Reactor Trip Occurred. Caused by Inadvertent Shorting of Ac Power Leads to Temp Converter Causing Control Power Fuse to Blow.Generator Backup Relays Reset & Runback Relay Replaced (← links)
- 05000395/LER-1989-005, :on 890322,diesel Generator B auto-started During Surveillance Test of Fire Switch.Caused by Incorrect Test Procedure Due to Personnel Error.Test Group Developed to Review & Coordinate Surveillance Testing (← links)
- 05000395/LER-1987-013, :on 870526,RCS Pressure Boundary Leakage Occurred.Caused by Crack in Reactor Coolant Pump C Thermal Barrier Flange in Area of Seal Injection Inlet Nozzle Weld. Weld Ground Out & Repaired (← links)
- 05000395/LER-1989-008, :on 890505,control Room Ventilation Aligned to Recirculation Mode Following Signal Spike on Control Room Supply Air Radiation Monitor.Caused by Migration of Oil from Blower or Pump.Housing Cleaned (← links)
- 05000395/LER-1987-016, :on 870722,room Ventilation Alignment to Emergency Recirculation Mode of Operation Occurred When Health Physicist Tapped Meter Face.Caused by Spurious Signal.Training Will Be Provided to Personnel (← links)
- 05000395/LER-1987-018, :on 870729,integrated Fire & Security (If&S) Sys Failed Due to Severe Electrical Storms.On 870730, Identified Failure to Monitor Containment Temp.Caused by Personnel Error.Shifts to Be Briefed (← links)
- 05000395/LER-1998-003, :on 980319,inadequate Solid State Protection Sys Testing,Was Determined.Caused by Inadequate Test Design Supplied by vendor.STP-345.037 & STP-345.074 Revised.Page 5 of 5 of Incoming Submittal Not Included (← links)
- 05000395/LER-1998-007, :on 980707,discovered Potential Failure of W Fuel Rod Design Criteria.Caused by Inadequate Methods & Incorrect Assumption.New Corrosion Model Being Incorporated Into PAD (← links)
- 05000395/LER-1998-004-01, Forwards LER 98-004-01 Re Unanalyzed Condition for Equipment Qualification Beyond Ten Minutes Following High Energy Line Break Outside Containment,Per 10CFR50.73(a)(2)(ii).Suppl Provides Addl Corrective Actions (← links)
- 05000395/LER-1987-027, :on 871029,primary & Backup Power Supply Failure Occurred Resulting in Reactor Trip & Loss of Control Functions.Caused by Failed Capacitor in Process Rack Panel Xpn 7008.Design Change Being Investigated (← links)
- 05000395/LER-1987-028, :on 871030,reactor Tripped Due to Power Loss to Source Range Nuclear Instrumentation.Caused by Use of Wrong Bulbs for Instrument & Control Power Status Lights.Program to Address Problem Being Developed (← links)
- 05000395/LER-1987-025, :on 871014,evaluation of Environ Qualification of 600 Volt Taped Wiring Splices Concluded Problem May Exist at Facility.Caused by Installation of Splices Utilizing Kerite Taped Back to Back (← links)
- 05000395/LER-1998-006, :on 980611,missed Surveillance on Post Accident Monitoring Sys Neutron Flux Instrumentation Channel Check Occurred.Caused by Procedural Inadequacy.Proper Channel Check Performed (← links)
- 05000395/LER-1987-017, :on 870724,seismic Event Annunciator IYA-1780 Setpoints Determined Greater than Required by Design.Caused by Ae Misreading of Scale & Tabulating Acceleration Values Higher than Design.Procedures to Be Revised (← links)
- 05000395/LER-1987-019, :on 870730,discovered Design Deficiency in Instrument Air Sys,Possibly Causing Failure of Control Room Ventilation.Caused by Misapplication of Check Valves. Justification for Operation Approved Based on Temporary Mod (← links)
- 05000395/LER-1987-019-01, Forwards LER 87-019-01.Schedule for Completion of Mod Updated to 871127 Due to Late Arrival of Matl for Mod (← links)
- 05000395/LER-1989-011, :on 890528,manual Reactor Trip Initiated Following Pressurizer Safety Value Failure.Cause Under Investigation.Operators Monitored RCS Pressure & Prepared to Initiate Safety Injection (← links)
- 05000395/LER-1988-009, :on 880726,reactor Trip Occurred While Personnel Testing Train B Solid State Protection Sys Actuation Logic & Master Relay.Caused by Lack of Adherence to Procedures.Procedures Revised (← links)
- 05000395/LER-1988-007, :on 880601,reactor Trip Occurred While Personnel Testing Train a Solid State Protection Sys Actuation Logic & Master Relay.Caused by Inadequate Procedures.Label Placed on Breaker & Switch (← links)
- 05000395/LER-1987-024, :on 870924,negative Rate Reactor Trip Occurred When Technician Deenergized Two Rod Control Power Supplies. Caused by Personnel Error.Personnel Counseled in Proper Application of Logic/Schematic Diagrams (← links)
- 05000395/LER-1987-023, :on 870922 & 23,control Room Ventilations Aligned to Emergency Recirculation Mode as Result of Spurious High Radiation Signals.Caused by Dirty Card Edges. All Card Edges Cleaned (← links)
- 05000395/LER-1987-022, :on 870911,motor-driven Emergency Feedwater Pumps Autostarted Due to Tripping of All Three Pumps.Caused by Personnel Error.Personnel Reindoctrinated to Anticipate Responses to Changing Plant Conditions (← links)
- 05000395/LER-1987-021, :on 870902,reactor Tripped Due to Electrical Fault in Main Generator Stator Ground.Caused by Failed Main Generator Bushing.Failed Bushing Replaced.Interface W/Ge to Verify Root Cause Ongoing (← links)
- 05000395/LER-1989-002, :on 890115,discovered That Scaffolding & Shielding Installations in East & West Penetration Rooms May Have Adverse Impact on Operability of safety-related Sys During Seismic Event.Caused by Personnel Error (← links)
- 05000395/LER-1987-015, :on 870616,main Control Board Annunciators Alarmed.Caused by Failure of Capacitor in Inverter Xit 5904 Which Caused Output Fuse to Blow.Failed Pressurizer Pressure Control Card & All Inverter Xit 5904 Replaced (← links)
- 05000395/LER-1987-014, :on 870606,failure to Perform Setpoint Verification Occurred.Caused by Personnel Error.Event Discussed W/Supervisor & Ltr Documenting Event Forwarded to All Supervisors,Including Maint Supervisors (← links)
- 05000395/LER-1987-012, :on 870609,plant Operated W/Two Feedwater Isolation Valves Inoperable.Caused by Decrease in Local Area Temp & Defective Pressure Transducer.Hydraulic Pressure Restored & Valves Declared Operable (← links)
- 05000395/LER-1987-011, :on 870603,115 Kv Line Feeding Switchgear XSW-1DA Experienced Voltage Fluctuations.Caused by Grid Sys Loads.Sys Dispatchers Adjusted Unit Loads to Boost 115 Kv Line Voltage Back to Normal Range (← links)
- 05000395/LER-1987-020, :on 870821,voluntary Entry Made Into Tech Spec Section 3.0.3 to Test Charging/Safety Injection Pump (C/Sip).Caused by Decision to Minimize Time W/Only One Operable C/Sip & Design Interlock (← links)
- 05000395/LER-1987-026, :on 871103,weekly Fire Svc Diesel Battery Test Exceeded Grace Period Allowed by Tech Spec Section 4.0.2. Caused by Personnel Error.Test Performed & Event Discussed During Maint Weekly Safety Meeting (← links)
- 05000395/LER-1997-004, :on 971012,piping Analysis Exceeded Code Allowables & TS Noncompliance Occurred Due to Snubber Failure.Sys Walkdowns Were Performed to Check for Any Damage to Piping or Associated Components (← links)
- 05000395/LER-1998-001, :on 980102,plant Shutdown Was Initiated.Caused by Failed Mechanical Governor on a Edg.Complete & Comprehensive Troubleshooting Was Performed (← links)
- 05000395/LER-1998-004, :on 980320,unanalyzed Condition for Equipment Qualification During Secondary Sys Line Break Outside Containment Emergency Feedwater Sys Occurred.Caused by Engineering Oversight.Initiated Engineering Evaluation (← links)
- 05000395/LER-1998-003, :on 980319,inadequate Solid State Protection Sys Testing Was Noted.Caused by Inadequate Test Design Supplied by Vendor.Procedures Revised (← links)
- 05000395/LER-1997-003, :on 970817,plant Was Entered Into TS 3.0.3. Cause Due to Less than Minimum Two Channels of OTDT Operable.Procedures Requiring Rev Due to TS Amend 75 Were Verified & Completed (← links)
- 05000395/LER-1987-008, :on 870526,fire Damper XFD-175 Discovered Blocked in Open Position W/No Roving Fire Watch Established in Affected Area.Caused by Personnel Error.Procedures Will Be Revised (← links)
- 05000395/LER-1987-006, :on 870407,preliminary Results of Third Inservice Eddy Current Exam Led to Entry Into Tech Spec 3.4.5.More than 1% of Inspected Tubes Defective.Caused by Stress Induced by Improper Rolling of Tubes (← links)
- 05000395/LER-1986-015, :on 860908 & 25,hourly Fire Watch Patrols Not Performed in Various Areas in Time Required by Tech Specs. Caused by Personnel Error.Personnel Counseled (← links)
- 05000395/LER-1987-009, :on 870508,during Simulated Blackout Section of Diesel Generator Surveillance Test,Svc Water Booster Pump Tripped on Low Suction Pressure.Caused by Design Deficiency. Contacts from Trip Circuit of Pump Removed (← links)
- 05000395/LER-1987-010, :on 870512,svc Water Screen Pump Failed to Start During ESF Loading Sequencer (Esfls) Testing.Caused by Defective Lug Crimp on Internal Vendor Wiring in Esfls Panel.Internal Wiring of Esfls Panels Reworked (← links)
- 05000395/LER-1986-012, :on 860714 & 24,offsite Power to Train a ESF Bus Interrupted.Caused by Fault During Maint Activity & Lightning Strike,Respectively.Faulty Agastat Relay Delayed Restart.Power Restored & Relay Replaced (← links)
- 05000395/LER-1986-017, :on 861101,smoke Detectors Declared Inoperable. Hourly Fire Watch Established.On 861103,inoperable Fire Barrier Discovered.Caused by Personnel Error & Inadequate Review.Event Discussed at Weekly Staff Meeting (← links)
- 05000395/LER-1987-007, :on 870413,during Third Refueling Outage,Six Steam Generator Tubes Misplugged.Caused by Personnel Error. Future Steam Generator Plugs Will Be Verified by Remote Video &/Or Still Photography (← links)
- 05000395/LER-1986-016, :on 861007,reactor Shut Down Due to Inability to Verify That RCS Leakage Less than 1 Gpm.Caused by Unseating of Reactor Coolant Drain Tank Relief Valve During Leak Rate Test.Relief Valve Repaired (← links)
- 05000395/LER-1999-010, :on 990730,discovered That UHS Dependent Components Were Potentially Outside Design Basis of Plant. Caused Indeterminate.Blank Flanges Were Subsequently Not Reinstalled.With (← links)
- 05000395/LER-1986-006, :on 860402,turbine Generator Trip Caused Reactor Trip.Caused by Loss of Excitation to Main Generator Due to Worn Brushes on Outboard Collector Ring.Brushes Replaced & Slip Ring Buffed (← links)
- 05000395/LER-1987-005, :on 870331,all Three Pressurizer Safety Valve Setpoints Tested Outside of Psig Tech Spec Limit.Caused by Differences in Test Methods to Measure Setpoints.Setpoints Verified & in Situ Testing of Valves Performed (← links)
- 05000395/LER-1999-009, :on 990604,plant Experienced Reactor Trip Due to Spurious High Flux Trip Signal in Power Range Nuclear Instrument Drawer N43.Defective Meter Was Replaced & Plant Was Returned to Svc on 990606.With (← links)
- 05000395/LER-1987-001, :on 870216,shift Supervisor Observed That Pressurizer Relief Tank Had Been Vented to Shutdown Waste Gas Decay Tank Due to Valve Leakage in Tank.Cause Not Stated.Procedure Revs Initiated (← links)
- 05000395/LER-1986-011, :on 860629,reactor Tripped from 90% Power. Caused by Inadvertent Feedwater Isolation Valve Closure Due to Momentary Loss of Electrical Power to Normally Energized Solenoid Valve.Connector & Valve Replaced (← links)
- 05000395/LER-1987-004, :on 870316,source Range Neutron Flux Channels Identified as Inoperable from 870308-0313.Caused by Discrepancy Between Requirements in FSAR & Tech Specs. GTP-702 & Test Frequency for Procedure Revised (← links)
- 05000395/LER-1986-009, :on 860531,reactor Tripped During Testing of power-range Neutron Detector Channels.Caused by Technician Incorrectly Making Adjustments to Second Channel.Personnel Counseled (← links)
- 05000395/LER-1999-003, :on 990412,surveillance on Manipulator Crane Load Cell Was Missed.Caused by Lack of Familiarity with VCSNS TS Srs.Core Alterations Were Suspended.With (← links)
- 05000395/LER-1999-004, :on 990413,fuel Assembly Top Nozzle Holddown Spring Failure Was Noted.Caused by Failure of Holddown Spring Attaching Screws.Replaced Top Nozzles on 28 twice- Burned Fuel Assemblies.With (← links)
- 05000395/LER-1986-008, :on 860515,discovered That Station Battery Rooms a & B High Temp Setpoint Could Exceed Tech Spec Limit Prior to Alarm.Caused by Personnel Error During Transfer of Alarm Setpoints on 830323.Alarm Reset (← links)
- 05000395/LER-1987-003, :on 870310,weekly Surveillance Not Performed on Diesel Fire Pump Starting Battery as Required by Tech Spec 4.7.9.1.3.Caused by Personnel Error.Event Discussed & Emphasis Placed on Timely Completion of Tests (← links)
- 05000395/LER-1999-001, :on 990311,missed Surveillance Test for Electrical Equipment Protective Devices Was Noted.Caused by Inadequate Surveillance Tps.Fire Watches Were Posted Per TS 3.8.4.3 LCO Requirements.With (← links)
- 05000395/LER-1985-028, :on 851007,inadvertent Safety Injection Occurred During Surveillance Test Procedure 125.011.Caused by Personnel Failure to Insert Manual Blocks Associated W/ Signals.Procedures Will Be Revised (← links)
- 05000395/LER-1984-042, :on 840928,while Investigating Event Associated W/ Radiation Monitor RM-A4,discovered Plant Design May Not Satisfy Intent of Tech Spec 3.3.2, ESF Actuation Sys Instrumentation. Monitor Returned to Svc (← links)
- 05000395/LER-1987-002, :on 870225,roving Fire Watch Patrol Inadvertently Established in Room IB-412-04 in Lieu of Room IB-412-14.Caused by Personnel Error.Face to Face Communications Between Personnel Required (← links)
- 05000395/LER-1986-014, :on 860727,reactor Trip Occurred.Caused by Spurious Operation of One of Two Other Control Valve Pressure Switches Coincident W/Test of Control Valve 4 Which Completed Two Out of Three Logic (← links)
- 05000395/LER-1986-013, :on 860717,discovered That Several 1 H Fire Watch Patrols for Intermediate Bldg 12-02 Missed.Caused by Failure to Follow Established Procedures.Five Individuals Involved Terminated (← links)
- 05000395/LER-1998-002, :on 980109,electrical Govenor (EG-A) Failed on a Edg.Caused by Inadequate post-refurbishment Bench Testing by Vendor.Vendor,Engine Sys,Inc Was Notified. Repaired & Tested EG-A,per 10CFR21 (← links)
- 05000395/LER-1986-010, :on 860612,breaker Alignment of Train B Charging/Safety Injection Pumps Resulted in Disabling Pumps from Automatic Start Under Loss of Offsite Power Conditions. Caused by Personnel Error (← links)
- 05000395/LER-1997-005, :on 971024,failure to Perform ASME Section XI Code Surveillance Test at Increased Frequency Noted.Caused by Personnel Confusion.Review Was Performed to Determine If Procedural Guidance Was Clear Enough (← links)
- 05000395/LER-1998-001, :on 980102,plant Shutdown Due to Failed Mechanical Governor on a EDG Was Noted.Caused by Inability to Correct a EDG Speed within Time Required by Ts. Mechanical Speed Control Governor Was Replaced (← links)
- 05000395/LER-1997-004, :on 971012,plant Personnel Found Two Snubbers Which Were in Locked Position.Caused by Personnel Oversight Freedom of Motion Tests of Suspect Snubbers Not Verified,Per TS Surveillance 4.7.7.c.New Snubbers Replaced (← links)
- 05000395/LER-1986-007, :on 860422,reactor Bldg Space Spray Pump B Inadvertently Started.Cause Not Determined.Spray Pump Discharge Valve Remained Closed & No Flow Introduced Into Reactor Bldg (← links)
- 05000395/LER-1997-006, :on 971113,TS Breaker Alignment Surveillance Was Not Performed.Caused by Personnel Error.Operator Was Dispatched to Do Surveillance Following Identification That Surveillance Had Not Been Performed (← links)
- 05000395/LER-1988-007, :on 880601,reactor Trip Due to Undervoltage on Train a Reactor Protection Occurred.Caused by Interruption of 48-volt Undervoltage Signal to Train a Breaker & B Bypass Breaker.Breaker Testing Initiated (← links)
- 05000395/LER-1988-003, :on 880201,level Indication Errors Occurred & Caused Condensation in Sensing Lines.Pressurizer Level Channels Adjusted to Compensate for Errors Experienced in Lines to Prevent Operator Confusion (← links)
- 05000395/LER-1988-001, :on 880204,three Perimeter Cameras Lost Due to Circuit Breaker Trip.Caused by Electricians Crimping Electrical Lead While Replacing Distribution Panel Cover. Security Procedures Implemented (← links)
- 05000395/LER-1999-008, :on 990518,manual RT Initiated Due to Main Turbine High Vibration.Caused by Light Rubbing within New Monoblock Turbine Rotor.Reactor Power Was Reduced.With (← links)
- 05000395/LER-1988-011, :on 881026,eddy Current Exam Completed & Results Yielded Insp Category C-3 Determination Since More than 1% of Inspected Tubes Were Defective.Caused by Primary Water Stress Corrosion Cracking (← links)
- 05000395/LER-1999-007, :on 990511,missed Surveillance Re Tadot Was Noted.Caused by Conflict in Requirements Between Surveillance Frequency & Actual Mode Requirment for Tadot. Revised Procedure STP-142.005.With (← links)
- 05000395/LER-1998-009, :on 981006,discovered Unanalyzed Condition for Speed Controller on Tdefwp.Caused by Belief That Current to Pneumatic(I/P) Transducer Could Only Fail Due to Loss of Air or Power.Licensee Isolated I/P from Air Supply (← links)
- 05000395/LER-1988-006-02, :on 880512,safety Injection/Reactor Trip Occurred When MSIV Closed During Testing.Caused by Operation of Test Switch.Action Required by Appropriate Emergency Operating Procedure Initiated (← links)
- 05000395/LER-1988-010-08, :on 880830,failure to Perform Fire Watch Following Fire Sys Computer Malfunction Induced by Lightning Striking Meteorological Tower.Caused by Inadequate Training & Procedural Guidance.Event Reviewed (← links)
- 05000395/LER-1988-005, :on 880426,fire Watch Not Established for Relay Room After Isolation of CO2 Sys,Per Tech Spec 3.7.9.3.a. Caused by Inadequate Review of Paperwork Due to Personnel Error.Involved Personnel to Review Incident (← links)
- 05000395/LER-1998-008, :on 980824,missed Surveillance Test for ECCS Subsystems.Caused by Inadequate Surveillance Test Procedure. Revised Surveillance Procedure.With (← links)
- 05000395/LER-1986-001, :on 860214,substantial Safety Hazard Evaluation Determined That Potential Failure Existed for Seven Valves in Emergency Feedwater Sys.Caused by Mfg Failure to Apply Capture Tack Welds to Internal Components (← links)
- 05000395/LER-1988-009, :on 880726,reactor Trip Occurred While Personnel Testing Train B Solid State Protection Sys Actuation Logic & Master Relay.Caused by Personnel Error & Undervoltage on Train A.Procedures Revised (← links)
- 05000395/LER-1988-004, :on 810526,civil Maint Found 2 Unsealed 2-inch Core Drills During Maint Activity.Cause Unknown.Shift Supervisor Notified of Condition,Continous Fire Watch Established & Request for Repairs Initiated (← links)
- 05000395/LER-1987-031, :on 871229,detailed Review of Fire Watch Patrol Log Revealed That Four Rooms Not Listed.Caused by Inadequate Fire Svc Sys Operating Procedure SOP-509.Roving Patrols Established,Log Revised & Procedure Reviewed (← links)
- 05000395/LER-1987-030, :on 871229,fire Watch Not Established for Partially Open Fire Door.Caused by Personnel Error.Auxiliary Operator Involved Attended 880106 Mgt Review Board Meeting Re Incident & Will Brief Each Shift (← links)
- 05000395/LER-1997-002, :on 970426,turbine Trip & Feedwater Isolation Occurred.Caused by Hi-Hi Level in Steam Generator C Signal. Verified Sys Integrity & Proper Plant Response & Initiated Plant Restart (← links)
- 05000395/LER-1988-002, :on 880216,reactor Trip Occurred During Surveillance Testing W/Nuclear Instrumentation Sys Power Range Channel N-42 Inoperable.Design of Meter Test Board Susceptable to Mechanical Loosening (← links)
- 05000395/LER-1997-001, :on 970422,initiated Manual Reactor Trip.Caused by Leak on Main Turbine Electro-Hydraulic Control (EHC) Sys. Replaced Hydraulic O Ring in EHC Sys & Reviewed Outage Package (← links)
- 05000395/LER-1985-034, :on 851225,reactor Tripped on RCS Depressurization Due to Failure of Pressurizer Spray Valve 444D.Caused by Improper Assembly of Positioner Pilot Valve. Valve Properly Installed & Personnel Counseled (← links)
- 05000395/LER-1986-005, :on 860220,fire Watch for Zone AB-12-07 Inadvertently Omitted When Fire Barrier Removal Permit Initiated to Facilitate Core Drill & Conduit Seal in Auxiliary Bldg.Personnel Counseled (← links)
- 05000395/LER-1985-029, :on 851009,shutdown Margin Surveillance Test Interval Exceeded.Caused by Personnel Error.Surveillance Test Task Sheets for Tests of Specified Frequencies Will Be Issued Independently (← links)
- 05000395/LER-1985-032, :on 851217,24-volt Dc Motor Associated W/ Voltage Regulator for Emergency Diesel Generators Failed. Caused by Cracked Delron Pinion Gear in Motor Housing.Gear Matl & Lubricant May Be Incompatible (← links)
- 05000395/LER-1985-030, :on 851006,surveillance Testing of Main Steam Safety Valves Revealed Lift Setpoints Out of Tolerance Allowed by Tech Specs.Cause Not Stated.Setpoints Adjusted & Valves Tested Satisfactorily (← links)
- 05000395/LER-1985-027, :on 850920,reactor Tripped Due to Loss of Main Feedwater Pumps During Testing of Condensate Sys.Caused by Improper Valve Lineup.Personnel Instructed & Training Program Developed (← links)
- 05000395/LER-1986-004, :on 860129,missed Readings of Control Board Instrument Channel Operability Checks Discovered,Resulting in Exceeding Tech Spec Surveillance Interval.Caused by Operator Error.Personnel Counseled (← links)
- 05000395/LER-1986-003, :on 860203,Train B of Component Cooling Water Failed to Actuate Following Reactor Trip & Safety Injection. Caused by Operator Error Resulting in Improper Breaker Alignment.Special Instructions Issued (← links)
- 05000395/LER-1986-002, :on 860202,reactor Tripped.Caused by Use of Deficient Electrical Feeder List During Maint on Distribution Panel,Resulting in Isolation of Condensate Flow.List Revised (← links)
- 05000395/LER-1985-031, :on 851014,inservice Insp of Steam Generator B Identified 9 Out of 700 Tubes W/Greater than or Equal to 40% through-wall Indications in Area of Hot Leg Tube Sheet (← links)
- 05000395/LER-1984-027, :on 840505,controlled Shutdown Initiated.Caused by Adjustments Made to Vol Boosters Affecting Valve Stroke Time.Design Mod Implemented to Segregate Vol Boosters from Trip Close Portion of Control Air Sys (← links)
- 05000395/LER-1985-019, :on 850723,grab Samples Not Obtained While Turbine Bldg Sump Radiation Monitor Inoperable.Caused by Personnel Oversight.Addl Controls to Process Surveillance Test Task Sheets Established (← links)
- 05000395/LER-1985-033, :on 851211,during Evaluation of Nonconformance Notice Re Potential Seismic & Steam Density Compensation Errors W/Reactor Vessel Level Indication Sys,Sys Considered Inoperable.Cause Not Stated (← links)
- 05000395/LER-1985-024, :on 850820 & 24,reactor Trips Occurred from 100% & 10% Power,Respectively.Caused by Low RCS Flow & Conservative Intermediate Range Setpoints.Precautions Added to Maint Procedures (← links)
- 05000395/LER-1985-021, :on 850820,hourly Fire Watch Not Performed on Foam/Pressure Fire Barrier Between Control Bldg & Turbine Bldg.Caused by Personnel Error.New Fire Watch Log & Patrol Will Be Initiated (← links)
- 05000395/LER-1985-020, :on 850820,containment Isolation Valve XVK-1633B Restored to Svc W/O post-maint Testing.Caused by Personnel Error.Testing on 850820 Showed Satisfactory Results.Procedures to Be Revised (← links)
- 05000395/LER-1985-022, :on 850824,reactor Trip Occurred on Steam Generator a lo-lo Level.Caused by Requirement to Maintain Min Values of Feedwater Flow & Temp During Startup.Feedwater & Condensate Sys Evaluation Program Initiated (← links)
- 05000395/LER-1996-009, :on 961026,potential Condition Considered to Be Outside App R Safe Shutdown Analysis Was Identified.Caused by Personnel oversight.FEP-4.0 Revised on 961026 to Require Verification That XVG08885-SI Closed (← links)
- 05000395/LER-1984-028, :on 840629,steam Inlet Flow Control Valve IFV-2030-MS Failed to Open Resulting in Inadvertent Start of Turbine Driven Emergency Feedwater Pump.Caused by Leaking Diaphragm on Operator.Diaphragm Replaced (← links)
- 05000395/LER-1984-046, :on 841106,ESF Actuation Occurred Due to short- Circuit on Bus 1DA.Caused by Personnel Error.Licensee Reviewed Details of Event W/Electrical & Instrument Personnel (← links)
- 05000395/LER-1985-018, :on 850729,discovered That Circuit Breakers Associated W/Relay Room Fire Damper electro-thermal Links Danger Tagged Open.Caused by Inadequate Test Procedure & Failure to Follow Administrative Procedure (← links)
- 05000395/LER-1996-007, :on 960730,determined That Itt Barton Model 763 Pressure Transmitters Safety Hazard After Previous Failures. Caused by Loose Strain Gauge Lead.Devices Returned for Analytical Testing.Also Reportable Per Part 21 (← links)
- 05000395/LER-1985-026, :on 850908,at 100% Power,Turbine Driven Emergency Feedwater Pump Indicator Read 250 Rpm.Caused by Seat Leakage Past Steam Supply Control Valve.Valve Repaired & Reset (← links)
- 05000395/LER-1985-017, :on 850618,during Reevaluation of Compliance W/ 10CFR50,App R Re Fire Protection Program,Div a Vital Power Sys Tray Not Separated from Div B Trays Containing Cables. Roving Fire Watch Established (← links)
- 05000395/LER-1996-010, :on 961202,missed Surveillance on Slave Relay Occurred.Caused by Personnel Oversight in Not Individually Tasking Each Surveillance Contained in Stps.Review Will Be Completed by 970228 (← links)
- 05000395/LER-1985-016, :on 850717,potential Substantial Safety Hazard Determined to Have Existed as Discussed in 850318 & 0521 LERs Re Failure of Feedwater Isolation Valve XVG-1611A (← links)
- 05000395/LER-1985-025, :on 850828,nonconservative Response Identified for Overpower Delta Temp Setpoint Following 850824 Reactor Trip.Caused by Failure to Install Electrical Jumper on Channel Cards.Jumper Installed & Tested (← links)
- 05000395/LER-1985-023, :on 850823,plant Mode Change Made from Hot Shutdown to Hot Standby W/O Proper Alignment of RHR Sys. Caused by Personnel Error & Failure to Follow Procedures. Sys Returned to Proper Alignment (← links)
- 05000395/LER-1985-013, :on 850429,reactor Trip Occurred Due to lo-lo Steam Generator Water Level in Steam Generator B. Caused by Transients in Deaerator Tank Level & Main Feedwater Pump Discharge Pressure (← links)
- 05000395/LER-1985-001, :on 850216 & 27,due to Failure of Rod Control Sys,Reactor Shut Down,Per Tech Spec 3.1.3.Caused by Low Output from Pulser Oscillator Circuit & Erratic Output of Supervisory Buffer Memory Circuit,Respectively (← links)
- 05000395/LER-1993-001, :on 930112,reactor Tripped from 100% Power on Positive Flux Rate on All Four power-range Channels.Caused by Spurious Actuation of Generator Backup Auxiliary Time Delay Relay.Relay Calibr Checked (← links)
- 05000395/LER-1985-011, :on 850418,control Rods Powered by Rod Control Sys Cabinet 2AC Failed to Move.Caused by Defective Slave Cycler Counter Card.Card Replaced.Preventive Maint Program for Rod Control Sys Cabinet Established (← links)
- 05000395/LER-1985-012, :on 850417,health Physics Personnel Identified Error in Liquid Radwaste Monitoring Computer Program.Caused by Personnel Error.Correct Correlation Factor Entered Into Program (← links)
- 05000395/LER-1992-007, :on 921027,noncompliance W/Sr of TS 3.3.1, Reactor Trip Sys Instrumentation, Identified Due to Inadequate Procedural Guidance.Surveillance Procedure Will Be Revised Prior to Next Test (← links)
- 05000395/LER-1985-014, :on 850506,diesel Generator non-valid Test Failure,Esf Blackout Load Sequencer Actuation & Overpressure Protection Sys Challenge Occurred.Caused by Personnel Error. Bus Drawers Labeled W/Appropriate Warnings (← links)
- 05000395/LER-1992-008, :on 921114,ESF Actuation Occurred Following Partial Loss of Offsite Power Due to Fallen Tree.Offsite Power Restored to ESF Train B,Edg B Secured & Operability Test Peformed on EDG A,Per TS SR 4.8.1.1.2.a.3 (← links)
- 05000395/LER-1996-007-01, :on 960730,determined That Safety Hazard, Reportable Per 10CFR21,existed Re Potential Failure of Transmitters Used for Pressure Protection Per 10CFR21.Model 763 Transmitter Was Installed (← links)
- 05000395/LER-1996-008, :on 960805,plant Personnel Discovered That STP-501.001,had Been Performed on B Train Station Battery, While Battery Was on Equalize Charge.Caused by Procedural Inadequacy.Procedure Has Been Changed (← links)
- 05000395/LER-1985-009, :on 850325,external Consultant Identified Size Inadequacy of Containment Penetration Protection Devices for in-core Instrumentation Flux Mapping Space Heaters.Primary Protection Device Tagged Open Pending Mods (← links)
- 05000395/LER-1985-008, :on 850404,reactor Manually Tripped Due to Loss of Various Secondary Plant Indications.Trip Resulted in Unmonitored Release from Main Steam Sys Relief Valves.Caused by Failure of Primary & Secondary Fuses (← links)
- 05000395/LER-1996-006, :on 960711,failure of Abb/Ite 27N Relays Occurred.Caused by Defective Timer Integrated Circuit U5. Identified,Replaced & Tested Subject 27N Relays & Notified Vendor of Situation (← links)
- 05000395/LER-1985-004, :on 850322,noncompliance W/Reg Guide 1.108 Requirements Re Diesel Generator Testing Identified.Caused by Test Frequency Based on Per Diesel Generator Unit Basis. Procedure Revs Initiated (← links)
- 05000395/LER-1985-006, :on 850320,discovered Senior Reactor Operator License Number SOP-20001 Expired 850203 W/O Submitting Renewal Application.Caused by Personnel Oversight.Licensee Will Provide Better Administrative Control (← links)
- 05000395/LER-1985-005, :on 850317,reactor Trip Occurred from 100% Power Due to lo-lo Level in Steam Generator A.Caused by Burned Contact in MSIV Test Switch.Msiv Switch Replaced & All MSIVs Tested (← links)
- 05000395/LER-1985-007, :on 850321,determined Scaffolding Installed for Preventive Maint on Overhead Cranes Could Have Adverse Impact on Operability of Onsite Ac Sources.Caused by Personnel Error.Personnel Counseled (← links)
- 05000395/LER-1984-049, :on 841227,during Installation of Load Reduction Test Equipment,Reactor Tripped.Caused by Technician Imposing Test Signal on Output of N-44 Power Range Channel.Lesson Plan Being Developed (← links)
- 05000395/LER-1984-051, :on 841219,actuation of Reactor Protection Sys Occurred on High Neutron Flux.Caused by Deenergization of Nuclear Instrumentation Source N-32 & Intermediate N-36 Range Channels (← links)
- 05000395/LER-1984-048, :on 841217,w/plant in Mode 3,unmonitored Liquid Release Occurred.Caused by Improper Valve Lineup.Operations Procedure for Liquid Radwaste Discharge Being Revised to Clarify Valve & Switch Alignment (← links)
- 05000395/LER-1992-006, :on 911113,C FWIV Failed Post Mod Test Due to Failure of Poppet Valve Seal in Actuator Control Assembly. Seals in FWIVs Replaced W/Improved Design & Valves Returned to Svc (← links)
- 05000395/LER-1984-050, :on 841218,actuation of Reactor Protection Sys Occurred on Steam/Feedwater Flow Mismatch Coincident W/Steam Generator Low Level Trip Signal.Caused by Personnel Error. Details Placed in Required Reading Book (← links)
- 05000395/LER-1985-002, :on 850221,failure to Perform Tech Spec Surveillance Requirement 4.11.2.1.2 within 24 H of Plant 850218 Startup Identified.Caused by Failure to Obtain & Analyze Grab Sample of Main Plant Vent (← links)
- 05000395/LER-1996-005, :on 960517,ESFs Steam Line Isolation Signal Inadvertently Generated.Caused by Cognitive Personnel Error. Technician Verbally Counseled (← links)
- 05000395/LER-1984-042-01, :on 841026,while Investigating Event Associated W/Radiation Monitor RM-A4,determined That Plant Design May Not Satisfy Intent of Tech Spec 3.3.2 Re ESF Actuation Sys Instrumentation (← links)
- 05000395/LER-1996-003, :on 960206,identified Discrepancy in Test Methodologies Between TS Required Testing & Actual Testing Performed.Caused by Recognize Discrepancy in Test Methodologies.Emergency TS Change Requested (← links)
- 05000395/LER-1984-044, :on 841002,following Removal of Two Fuses from Solid State Protection Sys Cabinet XPN-7020,relay Activated, Causing Train a RHR Suction Isolation Valves XVG-8702 a & B to Close.Caused by Drawing Errors (← links)
- 05000395/LER-1984-041, :on 840928,reactor Tripped from Approx 10% Power & Intermediate Range High Flux Bistable Did Not Reset on Decreasing Power.Caused by Operator Error.Incident Reviewed W/Personnel (← links)
- 05000395/LER-1984-040, :on 840920,while Repairing Silicone Foam Fire Seal blockout,ELB-2037,trace 687 Adjacent Blockout Found W/ Foam Removed.Fire Barrier Declared Inoperable.Hourly Fire Watch Established.Barrier Repaired on 840921 (← links)
- 05000395/LER-1984-052, :on 841226,discovered Two Leads Associated W/ Turbine Trip Circuitry Lifted.Cause Unknown.Event Currently Under Review (← links)
- 05000395/LER-1992-004, :on 920521,reactor Tripped from 9% Power on low-low SG Water Level in C Sg.Caused by Condenser Steam Dump Valves Not Fully Opening on Demand.Transducers Were Replaced W/Lower Impedance Transducers (← links)
- 05000395/LER-1992-005, :on 920602,second Sample of Explosive Gases Was Not Taken within 24 Hour Period as Required.Caused by Personnel Error.Importance of Complying with TS Related Sampling Requirements Emphasized (← links)
- 05000395/LER-1992-003, :on 920520,reactor Trip Occurred During Repair of Nuclear Instrumentation Due to Personnel Error.Personnel Completed Repair Activity Which Initiated Trip & Verified Operability of NI-42 Before Plant Restart (← links)
- 05000395/LER-1984-047, :on 841109,radioactive Liquid Effluent Monitors Inoperable.Caused by Closed Inlet & Outlet Valves.Counseling Session for Operators Held (← links)
- 05000395/LER-1996-002, :on 960126,voluntary Entry Into TS 3.0.3 Made to Recover Train a Chillwater Due to Equipment Problem on Chiller a Which Was Supplying Train a ESF Equipment.No Specific Corrective Action for Event Warranted (← links)
- 05000395/LER-1996-001, :on 960119,discovered Condition Not Covered by Plant Operating Emergency Procedures.Caused by Personnel Error.Use of Charging/Si Pump C on ESF Train B Administratively Restricted (← links)
- 05000395/LER-1985-003, :on 850228,during Reactor Startup,Reactor Trip Occurred on High Flux Positive Rate Trip.Caused by Operator Failure to Adhere to Procedures.Operator Counseled. Procedures Revised (← links)
- 05000395/LER-1984-045, :on 841018,power Loss to 120-volt Ac Distribution Panel APN-5901 Deenergized Solid State Protection Sys Channel I.Caused by Personnel Error During Performance of Plant Mod (← links)
- 05000395/LER-1984-031, :on 840717,discovered Seven Electrical Circuits Penetrating Containment Not Included in Tech Specs.Cause Unknown.Plant Mod Being Processed to Install Overcurrent Protection (← links)
- 05000395/LER-1984-037, :on 840820,discrepancy Observed Between Steam Generator wide-range & narrow-range Level Indications at 100% Steam Generator Level.Caused by Cold Calibr of wide- Range Level Transmitter (← links)
- 05000395/LER-1984-036, :on 840808,during Unrelated post-maint QC Insp, Kaowool on Ventilation Ducts in Battery Ventilation Rooms IB-23-01 & IB-23-02 Discovered Degraded or Missing.Cause Unknown.Repairs Completed (← links)
- 05000395/LER-1984-035, :on 840815,spurious High Radiation Alarms Experienced by Reactor Bldg High Range Atmospheric Purge Monitor RM-A14.Degraded Components Replaced & Monitor Tested Satisfactorily (← links)
- 05000395/LER-1984-033, :on 840802,normally Bolted Closed Fire Barrier Assembly Found Closed But Not Bolted.Caused by Personnel Error.Fire Watch Established.Missing Bolts Installed (← links)
- 05000395/LER-1984-032, :on 840729,during Reactor Startup,Reactor Tripped from 60% Power Due to lo-lo Steam Generator B Level. Caused by Erratic Operation of Main Feedwater Control Valve IFV-488-FW Vol Booster Deadband Adjustment (← links)
- 05000395/LER-1984-034, :on 840724,discovered That Electrical Maint Procedure 300.012, Agastat Relay Replacement, Did Not Require Delay Time Calibr of Relays in Installed Position. Related Event on 840821.Procedure Revised (← links)
- 05000395/LER-1984-030, :on 840421,ESF Cooling Unit 1DB Found W/O Coil V-brace Structural Member.Coil V-brace Installed on 840418 (← links)
- 05000395/LER-1984-029, :on 840713,three Speed & Transfer Switch Hinge Stud Assemblies on Svc Water Pump Torqued to Recommended Valve Failed.Util Contacting Brown Boveri for Corrective Action (← links)
- 05000395/LER-1984-039, :on 840907,board M Horizontal Fire Barrier Located Above Svc Water Booster Pump a Declared Inoperable Upon Discovery of Hole.Cause Not Stated.Barrier Replaced (← links)
- 05000395/LER-1984-038, :on 840907,second Position Indication Channel for PORV Declared Inoperable.Caused by Procedural Inadequacies in Surveillance Test Procedures 135.001 & 506.010.Channel Calibr (← links)
- 05000395/LER-2019-003-01, (Vcsns), Completion of a Technical Specification Required for Plant Shutdown (← links)
- 05000395/LER-1984-025, :on 840425,reactor Tripped from 100% Indicated Power as Result of Main Turbine Trip.Caused by Personnel Error.Importance of Fully Understanding Job Emphasized (← links)
- 05000395/LER-1995-004, :on 950813,surveillance Was Missed Due to Personnel Error.Completed Permanent Change to STP (← links)
- 05000395/LER-1992-001, :on 920111,surveillance for Axial Flux Difference Missed.Caused by Personnel Error.Initiated Log to Monitor Parameters & LER Placed in Required Reading for Personnel (← links)
- 05000395/LER-1984-026, :on 840505,main Steam Isolation Occurred Due to High Steam Flow Signal Coincident w/low-low Reactor Coolant Sys Temp Average Signal.Caused by Tripped High Steam Flow Bistables to Perform Maint (← links)
- 05000395/LER-1991-002, :on 910413 & 16,authorized Release of Liquid Effluent from Turbine Bldg Sump to Waste Surge Basin W/ Radwaste Concentrations Exceeded 0.5 MPC Due to Inadequate Procedural Guidance.Procedure HPP-710 Revised (← links)
- 05000395/LER-1984-024, :on 840422 & 29,reactor Tripped Due to Main Turbine Trip.Caused by Conservative Switch Settings & Loss of Suction on Motor Suction Pump.Procedure Changed to Delete Head Correction (← links)
- 05000395/LER-1984-023, :on 840417,w/unit in Mode 5,inadvertent Undervoltage Signal Occurred on ESF Bus 1DA,actuating ESF Load Sequencer & Initiating Start Attempt on Diesel Generator a Tagged Out of Svc for Maint (← links)
- 05000395/LER-1992-002, :on 920128,discovered That Sample Return Line from Radiation Monitor Temporarily Opened & Containment Phase a Isolation Valve Would Not Close.Caused by Personnel Error.Valve Repaired & Returned to Svc (← links)
- 05000395/LER-1984-016, :on 840301,following Maint,Diesel Generator a Emergency Safety Feature Load Sequencer Started to Sequence.Caused by Faulty one-shot Multivibrator Electronic Card.Sequencer Repaired (← links)
- 05000395/LER-1984-011, :on 840210,reactor Tripped Due to Turbine Trip on Low Discharge Pressure of shaft-driven Oil Pump.Caused by Procedural Inadequacy in Not Verifying Motor Suction Pump Operation Prior to Restart (← links)
- 05000395/LER-1984-008, :on 840207,low-low Level in Steam Generator B Tripped Reactor.Caused by Electronic Card FCY-488 Control Circuitry Failure Partially Closing Main Feedwater Regulating valve.Post-trip Review Conducted (← links)
- 05000395/LER-1984-010, :on 840209,reactor Manully Tripped at 8% Power. Plant Experienced Problems W/Main Turbine Speed Control. Cause Unknown.Reactor Coolant Pumps Restarted.Operating Procedure Revised (← links)
- 05000395/LER-1995-003, :on 950421,vol in Na Hydroxide Storage Tank Was Above TS Limits Due to Inadequate Procedural Guidance. Operations Personnel Drained Approx 60 Gallons from Tank to Restore Level to Middle of Specified Range (← links)
- 05000395/LER-1984-007, :on 840227,potential Bomb Threat Received Via Telcon.Cause Unknown.Search of 412 Ft Elevation of Control Bldg Conducted W/Negative Results.Plant Returned to Security Condition Green (← links)
- 05000395/LER-1984-006, :on 840131,noted That Overcurrent Protection Devices for Plant Paging Sys Not Included in Tech Spec 3.8.4.Rev to Tech Spec Will Be Submitted Adding Acceptable Fuses (← links)
- 05000395/LER-1983-144-03, /03L-0:on 831223,during Normal Operation,Erratic Behavior from Power Range Nuclear Instrument NI-42 Necessitated Quadrant Power Tilt Ratio Measurement.Cause Unknown.Bistables Placed in Trip (← links)
- 05000395/LER-1991-010, :on 911106,extender Board on ESF Load Sequencer Failed,Resulting in Loss of Power to Circuit Board & Trip of 7.2 Kv Circuit Breaker.Caused by Test Equipment Failure.Offsite Power Restored (← links)
- 05000395/LER-1983-138-03, /03L-0:on 831205 & 09,w/plant in Mode 5,QC Personnel Identified One Frozen Snubber & Several Rotated Pipe Clamps During Hanger/Snubber Insp of Feedwater & Steam Generator Blowdown Sys (← links)
- 05000395/LER-1991-009, :on 911015,discovered That Chg/Safety Injection Pump Runoff Limit Outside Tech Spec Limit of 680 Gpm.Caused by Effect of Instrument Uncertainties & Suction Boost.Cold Leg Injection Alignment Rebalanced (← links)
- 05000395/LER-1991-008, :on 911019 Preliminary Results of Sixth Inservice Eddy Current Exam on 911004 Indicated 1% of Tubes Inspected Defective.Caused by Stress Corrosion Cracking in Hot Leg Tubesheet.Tubes Plugged or Repaired (← links)
- 05000395/LER-1983-100-03, /03L-0:on 830912,during Mode 1,RCS Tavg Exceeded Power Distribution Limits by 2-1/2 Degrees.Caused by Failure of Permanent Magnet Generator 22-volt Power Supply Condenser & Atmospheric Dump Valves (← links)
- 05000395/LER-1983-069-03, /03L-0:on 830620,snubber FWH-0265 Declared Inoperable Due to Misalignment & Bent Paddle Plate.Caused by Transient Loading During Startup.Snubber Replaced W/Unit Modified to Suit Dimensional Requirements (← links)
- 05000395/LER-1983-068-03, /03L-0:on 830620,snubber FWH-1109 (Feedwater Sys) Declared Inoperable Due to Bearing Offset.Caused by Maint Activity in Immediate Area.Bearing Centered,Restaked,Tested & Declared Operable on 830620 (← links)
- 05000395/LER-1984-022, :on 840412,w/RCS at Half Pipe,Discharge Valve for Charging Pump a Discovered Closed,Making Boration Flow Path Inoperable.Caused by Personnel Error.One Operable Boration Flow Path Verified in Modes 5 & 6 (← links)
- 05000395/LER-1984-021, :on 840409,degradation of Kaowool Fire Wrap Identified on Three Cable Trays & Four Conduits in Control Room Chase Area.Caused by Aging & Personnel Walking on Wrap. Degraded Wrap Repaired (← links)
- 05000395/LER-1984-019, :on 840408,pressurizer Safety Relief Valve XVR-8010-C Removed,Tested & Found Inoperable.Valves Adjusted within Tech Spec Tolerance & Reinstalled (← links)
- 05000395/LER-1984-020, :on 840407,procedure Failed to Clearly Identify & Document Calibr of Individual train-related Low Fluid Oil Pressure Switches.Procedure 302.035 Revised & Calibr Performed on Each Switch (← links)
- 05000395/LER-1984-018, :on 840323,during Snubber Insp of Steam Generator Blowdown sys,11 Supports Would Not Maintain Design Function & Nine of 11 Failed Functional Test.Caused by Sys Transients.Snubbers Repaired or Replaced (← links)
- 05000395/LER-1984-013-01, Revised LER 84-013-01:on 840309,mod to Plant Integrated Fire & Security Sys Disabled Control Room Operator Ability to Receive Alarm Upon Actuation of Smoke Detectors in Zones Fff & Mmm of Intermediate Bldg (← links)
- 05000395/LER-1984-017, :on 840329,diesel Generator a or Bus Undervoltage Started & Actuated Blackout Load Sequencer for Less That 10 S.Caused by Personnel Error.Warning Labels Installed on Circuits (← links)
- 05000395/LER-1982-064-03, /03L-0:on 821223,nuclear Sampling Sys Valves 9398A (B) Failed to Close within Required Isolation Time Identified in Surveillance Requirement 4.6.4.3.Caused by Crud Buildup on Valve Seats.Crud Buildup Dislodged (← links)
- 05000395/LER-1982-066-03, /03L-0:on 821226,during Mode 1 Operation,Reactor Bldg Sump Leakage Detection Sys Declared Inoperable When High Level Alarm Remained in Alarm State.Caused by Failure of Capacitance Level Detection Sys.Sys Recalibr (← links)
- 05000395/LER-1982-063-03, /03L-0:on 821220,isotopic Iodine Analysis Not Performed within 6 H After Plant Went from 5% to 21% Thermal Power within 1 H.Caused by Failure to Notify Chemistry Dept to Perform Analysis.Procedure Developed (← links)
- 05000395/LER-1982-062-03, /03L-0:on 821220,seismic Switch YM-1782 Found to Have out-of-tolerance Trip Point on Transverse Sensor. Caused by Setpoint Drift on Horizontal Transverse Sensor. Switch Calibr & Returned to Svc (← links)
- 05000395/LER-1984-015, :on 840325,four Air Supply Valves to 36-inch Reactor Bldg Purge Valves Found Open.Caused by Personnel Error.Special Training Session Will Be Conducted Re Valve Position Requirements (← links)
- 05000395/LER-1983-137-03, /03L-0:on 831212,boric Acid Tank Level Indicator Found Out of Calibr.Caused by Instrument Drift.Transmitter Calibr.No Addl Corrective Action Other than Preventive Maint & Testing Required (← links)
- 05000395/LER-1983-136-03, /03L-0:on 831112,vital Instrumentation Panel APN-5901 Transferred to Alternate Power to Accommodate Mods to Normal Power Source.W/Train a RHR Sys in Svc,Suction Valve Closed.Caused by Dead Bus Transfer (← links)
- 05000395/LER-1983-133-03, /03L-0:on 831123,boron Injection Tank (Bit) Inadvertently Diluted to 19,700 Ppm While Performing Surveillance Testing.Caused by Lifting of Relief Valve XVR-8925.Boron Concentration Restored (← links)
- 05000395/LER-1983-134-03, /03L-0:on 831124,inner Door of Personnel Hatch Declared Inoperable.Caused by Broken Cam Follower.Door Secured from Inside Containment & Subsequently Repaired (← links)
- 05000395/LER-1983-135-03, /03L-0:on 831201,supports RHH-134,135 & 137 in RHR Sys Declared Inoperable.Cause Under Investigation.Supports Repaired,Tested & Declared Operable (← links)
- 05000395/LER-1983-130-03, /03L-0:on 831124,containment Bldg Internal Pressure Was Negative 1.2 Psig.Caused by Personnel Error & Inadequate Procedure.Exhaust Fan Secured & Supply Fan Started.Operating Procedure Revised (← links)
- 05000395/LER-1983-131-03, /03L-0:on 831124,pressurizer Pressure Trip Bistable PB-455D Began Alternately Tripping & Resetting. Caused by Electronic Component Failure.Defective Circuit Board Replaced & Channel Returned to Svc (← links)
- 05000395/LER-1991-007, :on 910826,discovered That Allowed Interval for Testing Component Cooling Water Sys Isolation Valves Exceeded on 910824.Caused by Weaknesses in Surveillance & Tracking Program.Tracking Modified (← links)
- 05000395/LER-1983-129-03, /03L-0:on 831121,during Surveillance Testing,Four Fire Dampers for Relay Room Carbon Dioxide Sys Failed to Close.Caused by Electrical Thermal Link Wiring Terminator Problem & Debris on Damper Tracks (← links)
- 05000395/LER-1983-128-03, /03L-0:on 831107 & 17,damaged Fire Barriers Identified in Svc Water Pump House.Caused by Maint Activity in Area.Operability of Smoke Detectors Verified & Hourly Fire Watch Patrol Established (← links)
- 05000395/LER-1983-127-03, /03L-0:on 831103,w/plant in Mode 1,discrepancy of 10% Observed During Channel Check Between Main Control Board & Control Room Evacuation Panel Indication for Pressurizer Relief Tank Level.Caused by Zero Shift (← links)
- 05000395/LER-1983-126-03, /03L-0:on 831105,during Installation of Electrical Panel Cover,Power Lead Shorted Out,Causing Plus/Minus Rate Trip & Hi Flux Trip on N-44.Caused by Wiring Routed Near Front of Panel.Shorted Lead Repaired (← links)
- 05000395/LER-1991-005, :on 910624,surveillance Test Procedure Re Main Steam Valve Operability Test Missed.Caused by Personnel Error.Valves Retested & Frequency of Scheduled Test,Per Tech Spec 4.0.5,increased (← links)
- 05000395/LER-1983-124-03, /03L-0:on 831101,Kaowool Fire Barrier on Conduit SWC-87C in Svc Water Pumphouse Found Damaged.Caused by Maint Activity.Kaowool Repaired (← links)
- 05000395/LER-1983-123-03, /03L-0:on 831022,w/plant in Mode 1,inlet Damper to Auxiliary Bldg Charcoal Exhaust Filter Fan B Failed to Open.Caused by Linkage Binding.Linkage Cleaned & Lubricated (← links)
- 05000395/LER-1983-125-03, /03L-0:on 831021,grab Sample of Main Plant Vent Not Taken within 12 H of Reactor Trip.Caused by Personnel Error.Technician Counseled on Failure to Perform Surveillance (← links)
- 05000395/LER-1983-122-03, /03L-0:on 831014,iodine Channel of RM-A3 Declared Inoperable After Hi Voltage Removed to Allow for Changing Filters.Cause Unknown.No Corrective Action Other than Scheduled Maint & Testing Planned (← links)
- 05000395/LER-1983-121-03, /03L-0:on 831019,recently Installed Fire Door Near Floor Opening in Control Bldg at 448-inch Elevation Not Identified on Auxiliary Operator Log.Caused by Personnel Error.Door Added to Log (← links)
- 05000395/LER-1995-002, :on 950220,ESF Actuation Occurred.Caused by Personnel Error.Proper Operation of ESF Equipment Verified (← links)
- 05000395/LER-1983-119-03, /03L-0:on 830927,turbine Room Sump Liquid Radiation Monitor RM-L8 Had Insufficient Sample Flow.Caused by Clogged Strainer in Sensing Line.Strainer Cleaned.Mod in Process to Install Strainer W/Backflush (← links)
- 05000395/LER-1983-120-03, /03L-0:on 831014,alarm Received in Control Room Associated W/Smoke Detectors in Zone Jjj.Caused by Bad Smoke Detector Head.Unit Replaced,Surveillance Test Performed & Zone Declared Operable on 831014 (← links)
- 05000395/LER-1983-117-03, /03L-0:on 831010,smoke Detectors in Zone Pp Declared Inoperable & Riac Panel 12 Locked Into Alarm & Would Not Reset.Caused by Steam Leaks in Area of Detectors. Valves Verified Tripped & Leaks Repaired (← links)
- 05000395/LER-1983-115-03, /03L-0:on 830927,HI-RAD Alarm Circuit Shorted. Control Room Supply Atmosphere Particulate Gaseous Iodine Monitor RM-A1 Declared Inoperable.Caused by Personnel Error. Monitor Repaired & Personnel Counseled (← links)
- 05000395/LER-1983-116-03, /03L-0:on 831003,discrepancy of 5% Observed During Performance of Channel Check Between Main Control Board & Control Room Evacuation Panel Indication for Boric Acid Tank Level.Caused by Instrument Drift (← links)
- 05000395/LER-1983-109-03, /03L-0:on 830918,integrated Fire & Security Computer Failed,Causing Loss of Alarms from Fire Detection Instrumentation & Loss of Computer Controlled Access Vital Area Doors & Card Readers.Cause Not Stated (← links)
- 05000395/LER-1983-118-03, /03L-0:on 831003,pressurizer Relief Tank Level Discrepancy of 10% Observed.Caused by Tank Level Transmitter Instrument Drift.Transmitter Recalibr (← links)
- 05000395/LER-1983-113-03, /03L-0:on 830924,operator Found Personnel Escape Door Hatch Outer Door Hard to Operate & Unsecured.Caused by Sheared Right Angle Gear Drive Pin.Both Doors Locked & Seal Leak Tested Satisfactorily (← links)
- 05000395/LER-1983-114-03, /03L-0:on 831004,steam Generator C Pressure Indicator 494 Declared Inoperable Due to Spiking Causing Various Alarms & Bistable to Actuate.Caused by Faulty Electronic Loop Power Supply Card (← links)
- 05000395/LER-1984-012, :on 840214,leak Rate Test Not Performed on Reactor Bldg Emergency Escape Hatch within 72 H Following Closure.Caused by Personnel Error.Special Instruction Issued (← links)
- 05000395/LER-1983-112-03, /03L-0:on 830923,signal Comparator IPB-953B1 Associated W/Containment Pressure Transmitter IPT-953 Declared Inoperable When Bistable Tripped & Would Not Reset. Caused by Defective Bistable Electronic Card (← links)
- 05000395/LER-1984-009, :on 840208,unit Tripped on low-low Steam Generator Level in Steam Generator C.Caused by Low Feedwater Temp.Plans Made to Restart Reactor (← links)
- 05000395/LER-1995-001, :on 950210,potential Loss of Automatic Engineered Safety Features Actuation Due to High Energy Line Break in Turbine Bldg Occurred.Nonconformance Notice Was Written to Address Degraded Condition (← links)
- 05000395/LER-1983-106-03, /03L-0:on 830904,post-accident Hydrogen Analyzer Panel a (XPN-7215A) Declared Inoperable When Calibr Rotometer Ball Bearing Indicator Lodged in Pressure Regulator.Caused by Personnel Error (← links)
- 05000395/LER-1983-104-01, /01T-0:on 830914,discovered That Hourly Fire Watch Patrol Not Established on 830909 When Fire Barrier Surrounding HVAC Ducts in HVAC Chiller Rooms Removed for QA Insp.Caused by Personnel Error (← links)
- 05000395/LER-1983-107-03, /03L-0:on 830914,reactor Bldg Internal Pressure Dropped Below Tech Spec Min.Caused by Change of Ambient Temp.Reactor Bldg Minipurge Supply Activated to Return Pressure to within Limits (← links)
- 05000395/LER-1983-105-03, /03L-0:on 830902,w/unit in Mode 1,refueling Water Storage Tank Level Transmitter LT-991 Failed High,Declared Inoperable & Placed in Bypassed Condition.Caused by Water in Conduit Resulting in Electrical Short (← links)
- 05000395/LER-1984-004, :on 840117,two Cable Junction Boxes Found Not Wrapped W/Kaowool & One Cable Run Had Damaged Kaowool in Three Areas.Caused by Const & Maint Activities in Area. Discrepancies Repaired (← links)
- 05000395/LER-1984-005, :on 840117,steam Generator B Low Level Caused Feedwater Flow Low Reactor Trip.Caused by Personnel Error. Surveillance Test Procedures Under Rev (← links)
- 05000395/LER-1983-102-03, /03L-0:on 830823 & 26,while in Mode 1,turbine Room Sump Liquid Radiation Monitor RM-L8 Had Insufficient Sample Flow.Caused by Clogged Solenoid Valve on 830823 & Closed Suction Line on 830826 (← links)
- 05000395/LER-1983-101-03, /03L-0:on 830902,component Cooling Sys Snubber CCH-082 Exceeded Alignment Limit by 6 Degrees.Caused by Loose Clamp.Clamp Realigned (← links)
- 05000395/LER-1984-003, :on 840112,24% of Main Plant Vent Exhaust RM-A3 & 66% of Reactor Bldg Purge RM-A4 Quarterly Composite Samples Found Missing.Cause Attributed to Personnel Error. Procedures Revised (← links)
- 05000395/LER-1983-100-01, /01T-0:on 830831,PORV PCV-445A Declared Inoperable Due to Possible Inadvertent Opening of Valve Upon Loss of Power to Protection Cabinet Iv.Caused by Design Error. PCV-445A Closed & Deenergized Until Corrected (← links)
- 05000395/LER-1983-098-03, /03L-0:on 830816,auxiliary Bldg Charcoal Exhaust Filter Plenum B(XAA-0040B)deluge Valve Tripped Open.Caused by Pressure Surge When Electric Fire Pump Started.Charcoal HEPA & Roughing Filters Replaced (← links)
- 05000395/LER-1983-097-03, /03L-0:on 830818,during Mode 2 Operation, Indication for Refueling Water Storage Tank Level Transmitter LT-993 Drifted Low.Caused by Internal Component Failure.Transmitter Replaced (← links)
- 05000395/LER-1983-039-03, RMS Train B Lost Electrical Power.Caused by Blown Main Power Supply Fuse.Fuse Replaced & Addl Fuse Protection Will Be Added (← links)
- 05000395/LER-1984-002, :on 840111,hourly Roving Fire Watch Patrol for Auxiliary Bldg Not Performed During Previous 8 H Per Tech Spec.Caused by Personnel Error.Roving Fire Watches Now Verifying Required Checks W/Shift Supervisor (← links)
- 05000395/LER-1983-096-03, /03L-0:on 830828,control Room Normal Ventilation Train a Declared Inoperable.Caused by Failure of Position Indicator Linkage on Supply Damper.Linkage Repaired (← links)
- 05000395/LER-1983-095-03, /03L-0:on 830822,train Subcooling Monitor B Declared Inoperable Due to Erratic Readings.Caused by Failure of Electronic Board.Failed Board Replaced & Applicable Surveillance Tests Performed (← links)
- 05000395/LER-1983-086-03, /03L-0:on 830809,emergency Feedwater Supply Valve IFV-3536 to Steam Generator a Failed Closed.Caused by Failure of Output Transistor to Bistable Relay.Bistable Replaced (← links)
- 05000395/LER-1984-001, :on 831223-27 & 29,daily Grab Samples of Svc Effluent Not Taken.Caused by Personnel Error.Individual Disciplined.Separate List of Daily,Weekly & Monthly Tech Spec Requirements Being Generated (← links)
- 05000395/LER-1983-066-03, /03L-0:on 830616,fire Barrier Kaowool Wrap on Conduit SWC-87C in Svc Water Pump House Found Torn.Caused by High Traffic on Access Ladder.Damaged Area Expeditiously Repaired (← links)
- 05000395/LER-1983-063-03, /03L-0:on 830616 & 27,turbine Bldg Sump Radiation Liquid Effluent Monitor RML-8 Declared Inoperable Due to Low Sample Flow.Caused by Accumulation of Trash in Sample Monitor Inlet Isolation Valve.Valve Cleaned (← links)
- 05000395/LER-1983-045-01, /01T-0:on 830531,speed Control (SC-2034A) for Turbine Driven Emergency Feedwater Pump on Main Control Board Found in Slow Speed Position.Caused by Operator Error & Procedure Deficiencies (← links)
- 05000395/LER-1983-009-03, /03L-0:on 830203,main Control Board Indicator (PI-950) for Reactor Bldg Pressure Failed Low.Caused by Intermittent Pressure Transmitter Failure.Transmitter Output Returned to Normal (← links)
- 05000395/LER-1983-143-03, /03L-0:on 831224,while in Mode 1,indication for Condensate Storage Tank Level Transmitter LT-3621 Failed High Because of Frozen Instrument Lines.Caused by Abnormally Cold Temp.Heat Trace Setpoints Increased (← links)
- 05000395/LER-1983-139-03, /03L-0:on 831214,remote Info Acquisition Cabinet 12 Tripped,Causing Intermediate Bldg Sprinkler Sys to Go Into Alarm Mode.Caused by Water Entering Panel & Shorting Out Electronic Cards.Cards Replaced (← links)
- 05000395/LER-1983-142-03, /03L-0:on 831216,identified Leakage from RCS Determined to Be 10.4 Gpm,Exceeding Tech Spec Limit.Caused by Excessive Leakage from Seal 2 on Reactor Coolant Pump C & Packing Leaks (← links)
- 05000395/LER-1983-141-03, /03L-0:on 831215,while in Mode 2,snubbers MSH-324 & MSH-325 Declared Inoperable.Caused by Transient in 32-inch Main Steam Line Which Induced 850 Lb Load in 4-inch Line. Snubbers Replaced (← links)
- 05000395/LER-1983-140-01, /01T-0:on 831224,instrument Lines for Refueling Water Storage Tank Level Transmitters Froze. Caused by Abnormally Cold Temps.Heat Applied to Transmitters.Heat Trace Setpoint Mods to Be Completed by 840120 (← links)
- 05000395/LER-1983-108-03, /03L-0:on 830902,while in Mode 1,diesel Generator a Output Breaker Failed to Close During Performance of Surveillance Test.Cause Not Determined.Test Performed & Unit Returned to Operable Status (← links)
- 05000395/LER-1983-111-03, /03L-0:on 830911,while in Mode 1,reactor Trip Occurred Following Power Interruption on 115 Kv Offsite Power Source.Cause of Trip from Transient to Onsite Power Source Under Investigation (← links)
- 05000395/LER-1983-103-03, /03L-0:on 830910,w/unit in Mode 1,plant Went from 97% Power to 79% within 1 H.Required Isotopic Iodine Analysis Not Performed within 2 to 6 H.Caused by Personnel Error.Procedure Mods Implemented (← links)
- 05000395/LER-1994-006, :on 941205,pressure Boundary Leak in Reactor Coolant Sys Identified.Caused by Seal Injection Nozzle Weld Failed as Consequence of Possible Defects.Exams of Weld Performed & Extent of Weld Failure Identified (← links)
- 05000395/LER-1991-003, :on 910702,ESF Actuation of Diesel Generator Occurred Due to Perturbation on off-site Source.Caused by Fault During thunderstorm.De-energized Components Identified & Restored & Secured EDG (← links)
- 05000395/LER-1983-077-03, /03L-0:on 830705,train B Solid State Protection Sys Declared Inoperable.Caused by Defective Circuit Board in Logic Circuitry.Board Replaced & Appropriate Surveillance Test Satisfactorily Performed (← links)
- 05000395/LER-1983-073-03, /03L-0:on 830703,6% Discrepancy Observed Between Main Control Board & Control Room Evacuation Panel Indication for Boric Acid Tank Level.Caused by Instrument Drift on Transmitter LT-163A (← links)
- 05000395/LER-1983-071-03, /03L-0:on 830626,auxiliary Bldg Smoke Detector Zone Hh Discovered in Alarm & Inoperable Since 830624.Caused by Personnel Failing to Reset Zone Following Welding Activity.Zone Reset (← links)
- 05000395/LER-1983-070-03, /03L-0:on 830629,pressurizer Relief Tank Level Indicator Removed from Svc Due to High Indication.Caused by Zero Shift on Transmitter.Transmitter Calibr (← links)
- 05000395/LER-1983-067-03, /03L-0:from 830601 to 19,reactor Bldg Sump Inventory Not Performed,Contrary to Tech Spec Surveillance Requirement 4.4.6.2.1.b.Caused by Personnel Failure to Implement Alternative Inventory Method (← links)
- 05000395/LER-1983-064-03, /03L-0:on 830616,while in Mode 1,snubber MK-CCH-306 Declared Inoperable Due to Misalignment.Caused by Inappropriate Maint Activity.Info Re Snubber Handling & Care Provided to Personnel (← links)
- 05000395/LER-1983-065-03, /03L-0:on 830616,while in Mode 1,RHR Snubber RHH-0211 Declared Inoperable Due to Bearing Protruded from Paddle Plate.Caused by Vibrational Effects Induced by Sys Operation.Snubber Repaired (← links)
- 05000395/LER-1983-061-03, /03L-0:on 830610,identified Surveillance Requirements for 6-inch Containment Purge Supply & Exhaust Isolation Valves Not Fully Conducted.Caused by Procedural Inadequacy.Procedure Developed (← links)
- 05000395/LER-1983-060-03, /03L-0:on 830609,boron Injection Tank Boron Concentration Fell Below Tech Specs.Caused by Overpressurized Sys,Resulting in Relief Valve Actuation. Procedures Revised (← links)
- 05000395/LER-1983-059-03, /03L-0:on 830609 & 0702,refueling Water Storage Tank Level Transmitter Failed High.Caused by Intermittent Internal Component Breakdown When Transmitter Temp Exceeds 100 F.Transmitter Will Be Replaced (← links)
- 05000395/LER-1983-062-03, /03L-0:on 830611 & 12,reactor Bldg Purge Exhaust Radiation Monitor Sample Pump Overload Protector Tripped. Caused by Loose Motor Controller Electrical Connections & Defective Pump Bearing.Bearing Replaced (← links)
- 05000395/LER-1983-094-03, /03L-0:on 830821,ambient Temp in Svc Water Pump House Exceeded Tech Specs.Caused by Unusually High Outside Air Temp (← links)
- 05000395/LER-1983-088-03, /03L-0:on 830728,during Surveillance Testing, Smoke Detector IXA-4947X Damaged & Declared Inoperable. Caused by Damage to Sensor When Removed for Testing.Damaged Unit Replaced & Tested Satisfactorily (← links)
- 05000395/LER-1983-087-03, /03L-0:on 830803,diesel Generator a Failed Diesel Generator Operability Surveillance Test.Caused by Dirty Contacts on Maint Local/Remote Selector Switch. Contacts Cleaned (← links)
- 05000395/LER-1983-089-03, /03L-0:on 830815,while in Mode 1,temp Indicator Declared Inoperable Due to Erratic Indication Causing Loop B Overtemp Delta Temp to Alarm.Caused by Spiking Originating in Isolation Amplifier.Amplifier Replaced (← links)
- 05000395/LER-1983-085-03, /03L-0:on 830721-24,ambient Temp in Svc Water Pump House Exceeded Tech Spec Limits.Caused by Outside Air Temp Above Average.Mod to Evaluate Need for Installing Cooling Coils Being Processed (← links)
- 05000395/LER-1983-084-03, /03L-0:on 830722,licensee Notified NRC Inspector That Surveillance Test Procedure 115.001 Did Not Adequately Address Tech Spec.Caused by Inadequate Procedure.Revised Procedure to Be Issued 830820 (← links)
- 05000395/LER-1983-044-01, /01T-0:on 830523,steam Generator B Feedwater Flow Transmitter FT-486 Did Not Respond to Change in Feedwater Flow.Caused by Personnel Error in Not Properly Identifying Transmitter on Tagout Sheet (← links)
- 05000395/LER-1983-038-03, /03L-0:on 830415,pressurizer Pressure Transmitter IPT-457 Found Out of Tolerance.Caused by Zero & Span Shift of Test Instrument Used in Calibr of Transmitter.Transmitter Recalibr (← links)
- 05000395/LER-1983-083-03, /03L-0:on 830719,while Performing Fire Barrier Surveillance,Kaowool Blanket Found Removed from Two Conduits in Battery Ventilation Room.Caused by Previous Maint Activity in Area.Fire Barrier Repaired 830721 (← links)
- 05000395/LER-1983-079-03, /03L-0:on 830711,smoke Detector IXA-4962F,boric Acid Tank Room,Removed During Surveillance Testing.Caused by Detector Head Not Properly Mounted in Base.Detector Head Properly Mounted (← links)
- 05000395/LER-1983-082-03, /03L-0:on 830718,diesel Generator B Tripped After Running for 12 Minutes During Surveillance Test.Caused by Spurious Alarm on High Crankcase Pressure. Switch Calibr Verified & Diesel Inspected (← links)
- 05000395/LER-1983-080-03, /03L-0:during Steam Generator Mod Outage of Mar to May 1983,surveillance of Certain Fire Doors Not Performed. Caused by Personnel Error.Plant Logs Revised (← links)
- 05000395/LER-1983-081-03, /03L-0:on 830715,reactor Bldg Radiation Monitor RMA-2 Removed from Svc to Replace Filter.Caused by Thermal Overloads Tripping Due to Excessive Heat in Control Panel. Overloads Reset (← links)
- 05000395/LER-1983-034-03, /03L-0:on 830409,motor Junction Box Cover on RHR Pump B Found W/Burned Area.Caused by Electrical Short to Ground Resulting from Insulation Failure.Termination Retaped & Pump Returned to Operable Status (← links)
- 05000395/LER-1983-031-03, /03L-0:on 830325,ECCS Mechanical Water Chiller XHX-001B Tripped.Caused by Intermittently Failing Valve Control Switch.Switch Repaired (← links)
- 05000395/LER-1983-030-03, /03L-0:on 830324,reactor Bldg Fire Detection Zones Ooo & Ppp Declared Inoperable When Power Supply Breaker Opened.Caused by Faulty Power Supply Transformer in Smoke Detector IXA-4964E in Zone Ppp.Transformer Replaced (← links)
- 05000395/LER-1983-025-03, /03L-0:on 830313,containment Bulkhead Door Seal on Personnel Access Air Lock Found W/Excessive Seal Leakage. Caused by Dirt on Door Seal.Seal Cleaned.Air Lock Tested (← links)
- 05000395/LER-1983-026-03, /03L-0:on 830318,reactor Bldg Cooling Unit Svc Water Flow Indicators Failed Low & Accident Monitoring Instrumentation Channel 4496 Declared Inoperable.Caused by Internal Failure of Indicator FI-4496.Indicator Replaced (← links)
- 05000395/LER-1983-021-03, /03L-0:on 830307,steam Generator Blowdown Monitor RM-L3 Failed Low,Reducing Number of Operable Channels. Caused by Moisture in Monitor Detector Due to Overhead Sample Valve O-ring Rupture.Detector Replaced (← links)
- 05000395/LER-1983-023-03, /03L-0:on 830309,main Control Board Pressure Indicator for Reactor Bldg Pressure Channel 950 Failed Low. Caused by Intermittent Electronic Failure of Transmitter. Transmitter Replaced (← links)
- 05000395/LER-1983-022-03, /03L-0:on 830308,conduit Containing Smoke Detector Circuits Cut During Core Drilling for Plant Mod.Fire Watch Posted.Caused by Failure to See Conduit Embedded in Fireproofing Matl.Conduit & Cable Replaced (← links)
- 05000395/LER-1983-024-03, /03L-0:on 830311,main Steam Line C Radiation Monitor Experienced Spurious Alarms.Caused by Slack Detector Cable Allowing Signal Oscillations.Detector Cable Will Be More Adequately Secured by 830501 (← links)
- 05000395/LER-1983-020-03, /03L-0:on 830305,fire Detector Sys Control Room Alarm Capability Lost for Intermediate Bldg Zones Aa,Bb & CC & for Diesel Generator Bldg Zones DG (427) & DG (436).Caused by Blown Fuse.Fuse Replaced (← links)
- 05000395/LER-1983-019-01, /01L-0:on 830317,trains of RHR & High Head Safety Injection Train a Inoperable for Approx 45 Minutes.Caused by Switching Problems W/Starting Circuitry of Chiller Unit XHX0001C.Switch Apparatus Modified (← links)
- 05000395/LER-1983-017-03, /03L-0:on 830305,remote Info Acquisition Cabinet Experienced Electronic Problems Rendering Four Reactor Bldg Zone 3 Smoke Detectors Inoperable.Caused by Printed Circuit Card Failure.Card Replaced (← links)
- 05000395/LER-1983-018-03, /03L-0:on 830306,while in Mode 1,nuclear Sampling Sys Valves 9398 A,B & C Failed to Close During Initial Performance of Accelerated Test Program.Caused by Crud Buildup on Valve Seats.Crud Dislodged & Switch Repaired (← links)
- 05000395/LER-1983-052-03, /03L-0:on 830528,main Control Board Indication for Steam Generator B Steam Pressure Failed High.Caused by Broken Wires on Transmitter PT-486 Strain Gage Assembly. Assembly replaced.PT-486 Calibr (← links)
- 05000395/LER-1983-049-03, /03L-0:on 830606,svc Water Booster Pump a Discharge Check valve,XVC-3135A-SW Declared Inoperable Due to Failure to Close on Reverse Flow.Caused by Worn Linkage. Hinge & Key Replaced & Valve Disk Lapped (← links)
- 05000395/LER-1983-053-03, /03L-0:on 830528,reactor Vessel Upper Plenun Level Indicator ILI-1320 on Main Control Board Removed from Svc Due to High Reading.Caused by Instrument Drift.Programmable Function Generator Recalibr (← links)
- 05000395/LER-1983-048-03, /03L-0:on 830517,w/plant in Mode 4,Zone 4 of Fire Svc Sys Locked in Trouble Alarm Status.Caused by Water Damage to Two Modules Located in Preaction Sprinkler Panel XPN-091.Engineering Evaluation Requested (← links)
- 05000395/LER-1983-008-03, W/Plant in Mode 1,main Control Board Indication for Steam Generator B Steam Pressure Decreased Approx 100 Psig.Caused by Plugged Transmitter Sensing Line.Sensing Line Back Flushed (← links)
- 05000395/LER-1983-014-03, /03L-0:on 830217 & 0303,pressurizer PORV PCV-445B Found Leaking.Events Discovered by High Temp Indication in PORV Discharge Piping.Cause Unknown.Valve Will Remain Closed & Be Disassembled During 830317 Outage (← links)
- 05000395/LER-1983-016-03, /03L-0:on 830216,w/plant in Mode 1,discrepancy of 6% Observed Between Main Control Board Indicators for Sodium Hydroxide Storage Tank Level.Caused by Loose Fitting on High Side Sensing Line of Level Transmitter (← links)
- 05000395/LER-1983-015-03, /03L-0:on 830219,while in Mode 1,5% Discrepancy Observed Between Main Control Board & Control Room Evacuation Panel Indication for Pressurizer Relief Tank Level.Caused by Design Error.New Transmitter Installed (← links)
- 05000395/LER-1983-047-03, /03L-0:on 830517,w/plant in Mode 4,turbine Bldg Sump Radiation Monitor (RM-L8) Removed from Svc Because of Inadequate Sample Pump Flow.Caused by Sludge Buildup.Pump Disassembled & Cleaned (← links)
- 05000395/LER-1983-050-03, /03L-1:on 830520 & 22,sump Pump XPP-138 Lost Prime & Became Incapable of Pumping Water,Rendering Reactor Bldg Sump Leakage Detection Sys Inoperable.Caused by Vapor Lock. Pump Primed.Air Vent Valve Will Be Installed (← links)
- 05000395/LER-1983-046-03, /03L-0:on 830520,sampling Line from Pressurizer Valve XVX-9357-SS Indicated Intermediate Position.Caused by Out of Adjustment Limit Switches on Valve.Switches Adjusted (← links)
- 05000395/LER-1983-040-03, /03L-0:on 830506,control Room Emergency Ventilation Sys Trains a & B Inoperable for 26 H.Caused by Failure in Implementing Procedural Controls.Personnel Counseled (← links)
- 05000395/LER-1983-042-01, /01T-0:on 830519,steam Leak Activated Smoke Detector,Tripping Open Intermediate Bldg Preaction Sprinkler Sys Deluge Valve.Caused by Personnel Error & Lack of Sys Knowledge.Deluge Valve Reset (← links)
- 05000395/LER-1983-043-03, /03L-0:on 830506,while in Mode 5,operations Personnel Stepped Through Maronite Board Fire Barrier.Caused by Personnel Error.Fire Watch Established.Area Posted. Barrier Repaired (← links)
- 05000395/LER-1983-041-01, /01T-0:on 830520,plant Entered Mode 3 W/Train B of Heat Tracing Associated W/Boron Injection Tank Flow Path Deenergized.Caused by Personnel Error & Inadequate Procedure.Panel Energized (← links)
- 05000395/LER-1983-037-03, /03L-0:on 830503,emergency Feedwater Valve IFV-3556-EF Failed to Remain Closed for 3 H.Caused by Air Leak Around Valve Positioner Gasket.Positioner Cover Tightened Down & Valve Tested Satisfactorily (← links)
- 05000395/LER-1982-003-03, /03L-0:on 820820,isolation Valve in Fire Svc Sys Found Closed,Rendering Fire Suppression Sys Inoperable for Control Bldg Cable Spreading Rooms & Chases.Caused by Header Valve Being Tagged Prior to Entering Mode 6 (← links)
- 05000395/LER-1983-035-03, /03L-0:on 830420,horizontal Fire Barrier Above Svc Water Booster Pump a Found Damaged.Caused by Maint Activities in Immediate Area of Fire Barrier.Damaged Barrier Replaced (← links)
- 05000395/LER-1983-010-03, /03L-0:on 830206,only One Isotopic Iodine Analysis Performed During Power Reduction from 50% to 5%.Caused by Personnel Misinterpreting Power Changes.Chemistry Lab Policy Issued Re Need for Analysis (← links)
- 05000395/LER-1983-007-03, /03L-0:on 830124,9% Discrepancy Found Between Main Control Board & Control Room Evacuation Panel (Crep) Indication for Pressurized Relief Tank Level.Caused by Instrument Drift.Crep Calibr & Returned to Svc (← links)
- 05000395/LER-1983-007, Forwards LER 83-007/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1983-006-03, /03L-0:on 830113,while in Mode 1,post-accident Hydrogen Analyzer a Declared Inoperable.Caused by Excessive Heat Damage to Wiring & Detector Cell Failing to Adequately Insulate Cover.Cover,Detector Cell & Wiring Replaced (← links)
- 05000395/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-061-03, /03L-0:on 821218,diesel Generator B (XEG001B) Failed Monthly Operability Test by Tripping on Low Lube Oil Pressure.Cause Unknown.Diesel Generator B Satisfactorily Restarted within 30 Minutes (← links)
- 05000395/LER-1991-001, :on 910219,missed Surveillance for Axial Flux Difference.Caused by Personnel Error.Review Made of Two Computer Generated Alarms Required by Tech Spec & Software Changes Made to Eliminate Synchronization (← links)
- 05000395/LER-1982-044-01, /01T-0:on 821202,surveillance Test Performed on 821005 for RHR Pump a Signed Off Approved When Acceptance Criteria Not Met.Caused by Personnel Error Due to Lack of Experience (← links)
- 05000395/LER-1982-045-03, /03L-0:on 821116,plant Entered Mode 1 W/O Performing Surveillance Test Procedure 134.001 Re Shutdown Margin Calculation Per Tech Specs.Caused by Personnel Oversight.Tech Specs Reviewed.Surveillance Program Revised (← links)
- 05000395/LER-1982-046-03, /03L-0:on 821117,main Control Board Indication for Steam Generator Feedwater Flow Read Zero.Caused by Personnel Leaving Equalizing Valves on Transmitters Open.Valves Closed & Personnel Indoctrinated (← links)
- 05000395/LER-1982-048-03, /03L-0:on 821117,condensate Polisher Backwash Water Released to Site Settling Ponds W/O Sampling.Caused by Inadequate Procedures for Release Process.Station Order Generated to Address Group Interface Prior to Release (← links)
- 05000395/LER-1982-047-03, /03L-0:on 821118,operations Personnel Failed to Document Tavg on 30-minute Basis Greater than 551 Degrees w/Tavg-Tref Deviation Alarm Not Reset.Caused by Failure of Operator to Recognize Surveillance Requirements (← links)
- 05000395/LER-1982-049-03, /03L-0:on 821118,Surveillance Requirement 4.7.9.1.1(e) Not Performed on Fire Suppression Water Sys. Caused by Fire Protection Group Being Unaware of Mode 6 Restriction.Personnel Counseled & Tracking Program Updated (← links)
- 05000395/LER-1982-043-03, /03L-0:on 821113,nuclear Instrumentation Power Range Channel (N42) low-range Trip Setpoint Found Set at 50% Instead of 25% of Rated Thermal Power.Caused by Personnel error.Low-range Trip Setpoint Reset (← links)
- 05000395/LER-1982-042-03, /03L-0:on 821110,RCS Temp Average Decreased When Control Rods Inserted.Caused by Simultaneous Rod Insertion & Main Steam Dumping.Control Rods Withdrawn & Steam Dump Isolated to Recover Temp Average (← links)
- 05000395/LER-1982-041-03, /03L-0:on 821109,during Mode 2,radiation Monitor RM-A1 (Control Room Isolation) Failed Surveillance Test Procedure 360.032.Caused by Instrument Drift.Monitor Calibr & Returned to Svc (← links)
- 05000395/LER-1982-039-03, /03L-0:on 821108,steam Generator Steam Flow Transmitter (FT-476) Power Supply Found Defective.Caused by Failure on Transmitter Power Supply (FQY-476).Channel Placed in Tripped Condition.Circuit Board Replaced & Tested (← links)
- 05000395/LER-1982-040-03, /03L-0:on 821108,Tech Spec 3.3.2 Had Not Been Complied W/Due to Improper Interpretation.Caused by Personnel Error.Ltr Issued Delineating Correct Interpretation of Tech Spec (← links)
- 05000395/LER-1982-038-03, /03L-0:on 821114,main Control Board Indication for Steam Generator a Steam Flow (FT-474) Failed to Indicate Sys Flow.Caused by Indicator Needle Sticking to Lower Stop. Channel Calibr Performed (← links)
- 05000395/LER-1982-035-03, /03L-0:on 821103,plant Entered Mode 3 W/Boric Acid Tank B Level Instrument LI-163A Inoperable.Caused by Instrument Out of Calibr Due to Zero Shift on Transmitter. Instrument Recalibr (← links)
- 05000395/LER-1982-034-03, /03L-0:on 821103,during Mode 4,radiation Monitor RM-G19C (Main Steam Line C Monitor) Failed to High Radiation Alarm Setpoint.Caused by Moisture Penetration of Cable Connectors Between Detector & Preamp.Detector Replaced (← links)
- 05000395/LER-1982-037-03, /03L-0:on 821104,steam Generator Blowdown Radiation Monitor (RM-L3) & Steam Generator Blowdown Discharge Radiation Monitor (RM-L10) Taken Out of Svc.Caused by Insufficient Sample Flow.Sys Aligned for RM-L10 (← links)
- 05000395/LER-1982-036-03, /03L-0:on 821103,plant Entered Mode 3 W/Control Room Evacuation Panel Pressurizer Relief Tank Level Indicator LI-470A Inoperable.Caused by Level Transmitter Being Out of Calibr.Transmitter Calibr (← links)
- 05000395/LER-1983-028-01, /01T-0:on 830406,out-of-tolerance Measurement Found on Undervoltage (UV) Trip Device Between Moving Core & Rolling Bracket.Caused by Mfg Variation of UV Trip Devices. Devices Will Be Replaced (← links)
- 05000395/LER-1983-029-03, /03L-0:on 830320,w/reactor Bldg Purge Initiated, Radiation Monitor RM-A4 Read Higher than Normal Pump RM-A4 & Detector Secured to Change Filter,Leaving Purge Unmonitored for 5 Minutes.No Activity Released During Event (← links)
- 05000395/LER-1983-027-03, /03L-0:on 830318,main Control Board Temp Indication TE-413 for Reactor Coolant Outlet Temp Exhibited Erratic Indications.Caused by Varying Resistance Between Compensated Lead & Low Side Resistance Leg of TE-413 (← links)
- 05000395/LER-1983-011-03, /03L-0:on 830208 & 17,during Mode 1 Operation, Nuclear Sampling Sys Valves 9398 A,B & C Failed to Close. Caused by Limit Switch Failure on One Valve & Crud Buildup on Other Valve Seats.Crud Dislodged.Limit Switches Repaired (← links)
- 05000395/LER-1983-012-03, /03L-0:on 830210,flow Indicator for Steam Generator a Feedwater Flow FI-477 Failed Low.Caused by Failure of Power Supply FQY-477.Circuit Board Replaced (← links)
- 05000395/LER-1983-013-03, /03L-0:on 830113 & 19,condensate Storage Tank Level Transmitters LT-3631 & LT-3631A Failed Due to Frozen Instrument Lines.Caused by Temp Sensing Element Not Being Located Per Design Specs.Element Relocated (← links)
- 05000395/LER-1982-027-03, /03L-0:on 821022,plant Entered Mode 2 for Initial Criticality W/One of Two Containment Hydrogen Monitors Inoperable.Caused by Inoperable Detector Cell in Containment Hydrogen Monitor B.Cell Replaced (← links)
- 05000395/LER-1982-028-03, /03L-0:on 821022,Mode 2 Entered for Initial Criticality W/Loose Parts Monitoring Sys Inoperable.Caused by Mods Being Performed on Sys Before Applicable Surveillances Performed.Mods Completed (← links)
- 05000395/LER-1982-026-03, /03L-0:on 821019,operator Noticed Frequent Auto Reactor Coolant Makeup to Vol Control Tank of Chemical Vol & Control Sys.Caused by Cracked Safety Injection Filter B Vent Valve.Leak Test Performed W/Results of 12 Gpm (← links)
- 05000395/LER-1982-025-03, /03L-0:on 821020,during Performance of Surveillance Test Procedure,Porv PCV-445A Found Leaking. Caused by Degraded Seat/Disk Interface Due to Steam Impingement.Valves Will Be Repaired (← links)
- 05000395/LER-1982-020-03, /03L-0:on 821011,reactor Bldg Base Mat Seismic Monitoring Instrument IYA-1780 Tested Unsatisfactorily. Caused by Battery Charger Failure Resulting in Battery Discharge.Battery Replaced & Surveillance Performed (← links)
- 05000395/LER-1982-021-03, /03L-0:on 821011,steam Line Pressure Dropped Below Tech Spec Min.Caused by Safety Valve 2806P Inadvertently Lifting After Being Freed from stuck-closed Position.Valve & Power Range Neutron Flux High Setpoint Reset (← links)
- 05000395/LER-1982-017-03, /03L-0:on 821006,controlled Leakage Exceeded Tech Specs During Surveillance Test Procedure.Caused by Improperly Set Needle Valves Located in Reactor Coolant Pump Seal Injection Line.Valves Positioned Correctly (← links)
- 05000395/LER-1982-014-03, /03L-0:on 821002,air Pressure Equalizing Valves Would Not Cycle in Proper Sequence,Rendering Reactor Bldg Airlock Inoperable.Caused by Chain Drive Sprocket Shearing Key,Allowing Sprocket to Slip Into Associated Drive Shaft (← links)
- 05000395/LER-1982-010-03, /03L-0:on 821001,PORV Block Valve MVG-8000A Would Not Reopen at Conclusion of Reactor Vessel O-ring Leak Test. Caused by Wear in Valve Stem Packing Which Contributed to Overtorque Condition.Stem Packing Replaced (← links)
- 05000395/LER-1982-012-03, /03L-0:on 820928,reactor Bldg high-range Radiation Monitor RM-G7 Had Problems W/Spiking That Caused High Radiation Alarms.Spikes Caused by Electrical Interference in Detection Cable.Monitor Tested & Returned to Svc (← links)
- 05000395/LER-1982-011-03, /03L-0:on 820930,Mode 3 Entered W/Pressurizer Relief Tank Level Indication LI-470A Inoperable at Control Room Evacuation Panel.Caused by Transmitter Not Calibr Properly,Due to Defective Amplifier & Calibr Circuit Card (← links)
- 05000395/LER-1982-013-03, /03L-0:on 821001,differential Pressure Level Transmitter Accumulator Tank a Level Found Below Tech Specs by Approx 7% Following Recalibr.Caused by Transmitter Showing Incorrect Level Indication.Transmitter Recalibr (← links)
- 05000395/LER-1990-010, :on 901117,insp Revealed That Output Voltage Low & Slowly Degrading,Causing Trip of Breaker Supplying Protection Set I.Caused by Failure of Ferroresonant Transformer.Transformer Repaired (← links)
- 05000395/LER-1982-007-03, /03L-0:on 820925,diesel Generator Bldg Preaction Sprinkler Sys Heat Detectors Failed to Actuate Sprinkler Valve.Caused by Degraded Circuit Card in Sprinkler Sys Control Cabinet.Card Replaced (← links)
- 05000395/LER-1982-006-03, /03L-0:on 820922,several High Range Monitors Failed High.Caused by Moisture Accumulation in Detector Preamp Connections.Plant Completed Initial Fuel Load But Was Not Critical.Monitors Replaced Except RM-G19B (← links)
- 05000395/LER-1982-004-03, /03L-0:on 820915,test Signal Generated Causing B Train RHR Header Isolation Valve to Shut & Isolate Suction. Pump Manually Tripped.Surveillance Test Procedure Revised to Line Up Alternate RHR Train W/Valve Locked Out (← links)
- 05000395/LER-1982-005-03, /03L-0:on 820916,five Smoke Detectors at 400-ft & 412-ft Elevations of Control Bldg Disabled,Rendering Preaction Sprinkler Sys Automatic Actuation Capability Inoperable.Caused by Need to Perform Welding in 400-ft Area (← links)
- 05000395/LER-1994-002-01, :on 940128,pressure & Flow Data for Charging/ Safety Injection Pumps Identified Condition Outside of Design Basis.Caused by Personnel Error.Controls Established & Test Procedures Revised (← links)
- 05000395/LER-1982-002-03, /03L-0:on 820818,after Calibr Pressure Transmitter for RHR Train a Suction Isolation Valve,Valve Operator re-energized & Suction Isolation Valve Shut.Caused by Switch Being Left in Test Position.Personnel Reinstructed (← links)
- 05000395/LER-1983-003-03, /03L-0:on 830108 & 20,main Control Board Indication for Steam Generator a Feedwater Flow IFI-477 Failed Low.Caused by High Instrument Cabinet Temp.Power Supply Card Replaced & Recalibr (← links)
- 05000395/LER-1994-003, :on 940209,EDG Seismic Qualifications Not Verified for Level Switches Providing Automatic Control of Fuel Oil Tank Level.Caused by Failure of Supplier.Level Switch Replaced (← links)
- 05000395/LER-1983-004-03, /03L-0:on 830109,spurious Inadequate Core Cooling Alarms Received on Channel B of RCS Subcooling Margin Monitor.Cause Unknown.Channel & Sys re-energized on 830110 & Channel Returned to Svc on 830111 (← links)
- 05000395/LER-1982-055-03, /03L-0:on 821208,while in Mode 1,reactor Operators Noticed Frequent Auto Makeup to Rcs.Caused by Leaking Seal Injection Filter Drain Valve XVT-8386B.Second Isolation Valve in Series Installed in Drain Line (← links)
- 05000395/LER-1982-054-03, /03L-0:on 821208,loose Part Detection Sys Failed Daily Channel Check.Caused by Microprocessor Failure. Microprocessor Replaced (← links)
- 05000395/LER-1982-052-03, /03L-0:on 821204,during Mode 1,main Steam Line a Radiation Monitor RM-G19A Gave Spurious Alarms.Caused by Instrument Drift.Monitor Calibr & Returned to Svc (← links)
- 05000395/LER-1982-051-03, /03L-0:on 821202,Sys Test Procedure 145.002 Unsatisfactorily Performed on Waste Evaporator.Caused by Thermal Cut Out Switch Being Disconnected from Evaporator Distillate Pump Junction Box.Switch Replaced (← links)
- 05000395/LER-1982-050, Forwards Corrected LER 82-050/03L-0.Detailed Event Analysis Encl (← links)
- 05000395/LER-1982-001-03, /03L-0:on 820813,while Performing Test on Feeder Breaker for Control Room Train B Normal Ventilation Fan, Breaker Would Not Manually Reset.Caused by Random Failure of Square D Breaker (Fhl 36050-15M).Breaker Replaced (← links)
- 05000395/LER-1994-001, :on 940113,Appendix R Analysis Determined to Be Outside Design Basis Due to Analysis for Circuits Susceptible to Hot Shorts.Caused by Personnel Error.Fire Watch Patrols Established for Zones Effected (← links)
- 05000395/LER-1990-009, :on 901026,design Defect Discovered in Chilled Water Sys & Reported Per 10CFR21 by Gilbert/Commonwealth, Inc (← links)
- 05000395/LER-1993-005, :on 931203,partial Phase a Containment Isolation Actuation Occurred.Caused by Inaccurate Drawing for Ssps.Trouble Shooting Discontinued & Ssps Restored to Normal Alignment (← links)
- 05000395/LER-1993-004, :on 930629,identified Noncompliance W/Srs of TS 4.3.2.1,Table 3.3-3.8.b.Caused by Personnel Error.Retest Sucessfully Performed & Personnel Involved Have Taken Part in Discussion of Importance of Review Process (← links)
- 05000395/LER-1993-003, :on 930628,TS Violation Occurred Due to Personnel Error Re non-licensed Operator Performing Evolution W/O Consulting Governing Procedure.Reactor Bldg Purge Supply Valves Closed (← links)
- 05000395/LER-1990-008, :on 900505,energizing of Sequencer Initiated Undervoltage Sequence Causing ESF Bus a to Deenergize. Caused by Incorrectly Installed Undervoltage Circuit Agastat Relay.Relay Rewired (← links)
- 05000395/LER-1990-007, :on 900423,during Offsite Relay Testing,Oil Circuit Breaker Supplying Bus 3 Tripped Open,Resulting in Loss of Power to ESF Train B & Diesel Generator B Start. Caused by Deficient Procedure.Testing Stopped (← links)
- 05000395/LER-1990-006, :on 900412,unplanned ESF Actuation Occurred When Train B Emergency Diesel Generator Automatically Started.Caused by Personnel Error.Feeder Breaker from Battery Reopened (← links)
- 05000395/LER-1990-005, :on 900410,steam Generator Tube Eddy Current Exam Yielded Insp Category C-3 Results.Caused by Primary Water Stress Corrosion Cracking in Hot Leg Tubesheet Area. Defective Tubes Plugged or Repaired (← links)
- 05000395/LER-1990-004, :on 881114,investigation Determined That Two Leads for Cabinet XPN-6002 Had Been Previously Disconnected in 881114 Refueling Outage,Rendering Transmitter LT-1976 Inoperable.Caused by Personnel Error (← links)
- 05000395/LER-1990-003, :on 900406,computer Software Error Caused Nonconservative Radiation Monitor Setpoints.Caused by Software Developer Personnel Error.Setpoints Readjusted & Procedures/Software Evaluated (← links)
- 05000395/LER-1990-002, :on 900318,inadvertent ESF Actuation Occurred When Emergency Start Signal Reset.Caused by Procedure Inadequacy When Emergency Start Signal Still Present on Train B.Sys Operating Procedure Revised (← links)
- 05000395/LER-1993-002, :on 930318,identified That Category C-3 Applied Following SG Tube Eddy Current Exam.Caused by Primary Water Stress Corrosion Cracking.All Defective Tubes Plugged Per Tech Spec Requirements (← links)
- 05000395/LER-1983-001-01, /01T-0:on 830119,w/plant in Mode 1,three Refueling Water Storage Tank Level Transmitters Failed High. Caused by Frozen Instrument Lines.Transmitters Thawed. Insulated Encls Will Be Installed (← links)
- 05000395/LER-1982-065-03, /03L-0:on 821222,electrical Power Lost to Train a Radiation Monitoring Sys.During Investigation of Loss of Power,Maint Personnel Accidently Short Circuited Train B. Caused by Blown Power Fuses Due to Personnel Error (← links)
- 05000395/LER-1982-059-03, /03L-0:on 821215,w/plant in Mode 1,several Fire Doors Not Verified Closed.Caused by Doors Not Being Included in Auxiliary Operator Logs Rev & Therefore Not Checked.Log Being Revised to Ensure That Doors Checked (← links)
- 05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault (← links)
- 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator (← links)
- 05000395/LER-2022-002, (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 (← links)
- 05000395/LER-2021-001-01, Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-2019-003-01, (Vcsns), Completion of a Technical Specification Required for Plant Shutdown (← links)
- 05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 (← links)
- 05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.4 (← links)
- 05000395/LER-2019-001-01, Regarding Condition Prohibited by Technical Specification 3.4.6.1 (← links)
- 05000395/LER-2018-001-01, Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator (← links)
- 05000395/LER-2018-001, Valid Actuation of Emergency Diesel Generator (← links)
- 05000395/LER-1917-005, V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip (← links)
- 05000395/LER-1917-006, Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor (← links)
- 05000395/LER-1917-003, For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester on Main Transformer Causes Reactor Trip (← links)
- 05000395/LER-1917-002, Regarding Low Feedwater Flow to the B Steam Generator Causes Automatic Reactor Trip (← links)
- 05000395/LER-2016-004-01, Regarding Steam Propagation Barrier Degrade Due to Missing Orifices (← links)
- 05000395/LER-2016-006, Regarding Circuit 1 Hot Gas Bypass Valve Failure Renders A-Train Chiller Non-functional and A-Train Charging Pump Inoperable (← links)
- 05000395/LER-2016-005, Regarding Steam Propagation Barrier Degraded Due to Removal of Ventilation Duct Access Panel for Surveillance Activities (← links)
- 05000395/LER-2016-004, Steam Propagation Barrier Degraded Due to Missing Orifices (← links)
- 05000395/LER-2016-003, Regarding Steam Propagation Door Discovered Propped Open (← links)
- 05000395/LER-2016-001-01, Transmittal of Low Refrigerant Renders A-Chiller Non-Functional and A-Charging Pump Inoperable (← links)
- 05000395/LER-2016-002, Regarding Pressurizer Heater Inoperable Longer than Technical Specification Limiting Condition for Operation 3.4.3 (← links)
- 05000395/LER-2015-002, Regarding Low Oil Level Trip Renders Chillers Non-Functional and a Train of Charging System Inoperable (← links)
- 05000395/LER-2015-001, Regarding Reactor Building Spray Isolation Valve Failure Renders Train of Reactor Building Spray Inoperable (← links)
- 05000395/LER-2014-003, Regarding Component Cooling System Emergency Makeup a Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable (← links)
- 05000395/LER-2014-002, Regarding Reactor Vessel Head Penetration Weld Indications Attributed to Primary Water Stress Corrosion Cracking (← links)
- 05000395/LER-2013-006, Regarding Securing Control Room Ventilation Emergency Recirculation While Associated Radiation Monitor Was Out of Service (← links)
- 05000395/LER-2013-004, Regarding Spray System Relief Valve Failure to Lift at Required Setpoint Renders the Reactor Building Spray System Inoperable (← links)
- 05000395/LER-2013-003, Trip Setpoint Renders Chiller and Control Room Emergency Filtration Inoperable (← links)
- 05000395/LER-2013-002, V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open (← links)
- 05000395/LER-2013-001, V. C. Summer Nuclear Station, Unit 1, Regarding Grid Disturbance Results in an Engineered Safeguard Features Actuation of the a EDG (← links)
- 05000395/LER-2012-003, Regarding Reactor Vessel Head Penetrations Not Meeting Requirements of 10 CFR50.55(g)(6)(ii)(D) (← links)
- 05000395/LER-2012-002, Seismically Qualified Refueling Water Storage Tank Aligned to Non-Seismic Piping (← links)
- 05000395/LER-2012-001, Regarding Core Exit Thermocouples Inoperable Due to an Inadequate Maintenance Procedure (← links)
- 05000395/LER-2011-003, Regarding Inadvertent Safety Injection During Reactor Startup Due to Excessive Differential Steam Line Pressure (← links)
- 05000395/LER-2011-002, V. C. Summer Regarding Failure to Maintain One Train of Safe Shutdown Systems in Accordance with Appendix R Section III.G.a/III.G.3 (← links)
- 05000395/LER-2010-002-01, Regarding Unanalyzed Condition Due to Wiring Discrepancy in the B Emergency Diesel Generator Appendix R Isolation Circuitry (← links)