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| Issue date | Title | Topic | |
|---|---|---|---|
| 05000324/LER-1992-001, Supplemental LER 92-001-01:on 920202,unit Scrammed During Main Turbine Control Valve Testing.Caused by Excessive Cycling of Turbine Control Valves.Hydraulic Accumulators a & B Disassembled | 2 September 1993 | Supplemental LER 92-001-01:on 920202,unit Scrammed During Main Turbine Control Valve Testing.Caused by Excessive Cycling of Turbine Control Valves.Hydraulic Accumulators a & B Disassembled | |
| 05000324/LER-1993-008 | 13 August 1993 | LER 93-008-00:on 930714,core Rated Thermal Power Exceeded Allowable Amount Due to Feedwater Flow Inaccuracy.Cause Believed to Be Due to Erosion/Corrosion of FW Flow Elements. FW Instrumentation recalibr.W/930812 Ltr | |
| 05000324/LER-1992-010 | 12 August 1993 | LER 92-010-01:on 921207,penetration Leakage Exceeded TS Allowable Limit Due to actuator-to-valve Alignment & disk-to-seat Alignment Problems.Line Bored Valve to Achieve concentricity.W/930812 Ltr | Local Leak Rate Testing |
| 05000324/LER-1991-019 | 12 August 1993 | LER 91-019-01:on 911112,LLRT Failure of Two MSL Inboard & Outboard Isolation Valves Resulted in Condition Outside Design Basis.Root Cause Analysis in Process.Msls C & D Inboard & Outboard MSIVs Repairs complete.W/930812 Ltr | Local Leak Rate Testing Earthquake |
| 05000324/LER-1993-003 | 10 May 1993 | LER 93-003-00:on 930408,identified That Drywell Spray Outboard Isolation Valve Installed in Reverse Direction. Caused by Design & Installation Error.Appropriate Documents Will Be revised.W/930507 Ltr | |
| 05000324/LER-1988-001 | 1 August 1990 | LER 88-001-07:on 880102,manual Reactor Scram Occurred Due to Decreasing Main Condenser Vacuum.Reactor Power at 55% & Vacuum Decreased to 22 Inches Mercury.Caused by Leaks on Main Turbine Piping.Piping repaired.W/900801 Ltr | |
| 05000324/LER-1983-019, Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed | 12 July 1984 | Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed | |
| 05000325/LER-1982-108, Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced | 18 May 1984 | Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced | |
| 05000325/LER-1982-122, Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C | 9 April 1984 | Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C | |
| 05000325/LER-1981-053, Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr | 29 March 1984 | Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr | |
| 05000325/LER-1981-055, Updated LER 81-055/03L-1:on 820622,drywell Equipment Drain Flow Integrator 1-G16-FQ-K603 Continuously Indicated Dwed Sump Flow W/No Pumps Running.Caused by Water Being Introduced Into Pneumatic calibrator.W/840328 Ltr | 28 March 1984 | Updated LER 81-055/03L-1:on 820622,drywell Equipment Drain Flow Integrator 1-G16-FQ-K603 Continuously Indicated Dwed Sump Flow W/No Pumps Running.Caused by Water Being Introduced Into Pneumatic calibrator.W/840328 Ltr | |
| 05000325/LER-1983-063, Updated LER 83-063/03L-1:on 831203,reactor Water Cleanup Sys (Rwcs) Differential Flow Indicator 1-G31-R615 Showed Erroneous Indication.On 831207,spurious Rwcs Alarm Annunciated.Caused by Air in Sensing lines.W/840222 Ltr | 22 February 1984 | Updated LER 83-063/03L-1:on 831203,reactor Water Cleanup Sys (Rwcs) Differential Flow Indicator 1-G31-R615 Showed Erroneous Indication.On 831207,spurious Rwcs Alarm Annunciated.Caused by Air in Sensing lines.W/840222 Ltr | |
| 05000325/LER-1983-057, Updated LER 83-057/03L-1:on 831119,during Unit Power Performance,Temp Recorder TR-1258 Printed Erratically.Caused by Dirty Electrical Contacts in Control Board Timing Relay. Contacts Cleaned & Returned to svc.W/840222 Ltr | 22 February 1984 | Updated LER 83-057/03L-1:on 831119,during Unit Power Performance,Temp Recorder TR-1258 Printed Erratically.Caused by Dirty Electrical Contacts in Control Board Timing Relay. Contacts Cleaned & Returned to svc.W/840222 Ltr | |
| 05000324/LER-1983-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking | 24 January 1984 | Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking | Weld Overlay Stress corrosion cracking |
| 05000325/LER-1983-045, Updated LER 83-045/03L-2:on 830919 & 24,inboard PCIV Steam Supply Valve ES1-F007 to RCIC Sys Would Not Completely Reopen.Caused by Loose Limitorque Motor Operator Spring Pack | 24 January 1984 | Updated LER 83-045/03L-2:on 830919 & 24,inboard PCIV Steam Supply Valve ES1-F007 to RCIC Sys Would Not Completely Reopen.Caused by Loose Limitorque Motor Operator Spring Pack | |
| 05000324/LER-1982-024, Updated LER 82-024/01T-1:on 820205,determined That Control Bldg Emergency Ventilation Sys Trains Will Not Isolate Upon Receipt of Chlorine Isolation Signal If Control Switch in on Position Due to Design Deficiency | 14 November 1983 | Updated LER 82-024/01T-1:on 820205,determined That Control Bldg Emergency Ventilation Sys Trains Will Not Isolate Upon Receipt of Chlorine Isolation Signal If Control Switch in on Position Due to Design Deficiency | |
| 05000324/LER-1983-083, Updated LER 83-083/01T-1:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Discovered Shut.Caused by Operator Error.Valves Tagged for Identification.Auxiliary Operator Disciplined | 23 September 1983 | Updated LER 83-083/01T-1:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Discovered Shut.Caused by Operator Error.Valves Tagged for Identification.Auxiliary Operator Disciplined | |
| 05000325/LER-1983-034, Updated LER 83-034/01T-1:on 830811,following Extended Maint & Refueling Outage,Instrument Isolation Valves to 1CAC-PDS-4222 & 4223 Discovered Closed.Caused by Cancelation of Equipment Clearance.Valves Reopened | 12 September 1983 | Updated LER 83-034/01T-1:on 830811,following Extended Maint & Refueling Outage,Instrument Isolation Valves to 1CAC-PDS-4222 & 4223 Discovered Closed.Caused by Cancelation of Equipment Clearance.Valves Reopened | |
| 05000325/LER-1983-017, Updated LER 83-017/03L-1:on 830326-28 & 0402,listed Control Rods Had No Indications for Identified Positions.Caused by Loose Prototypic Inlet Piping Connectors Due to Undervessel Work.Connectors Will Be Properly Fastened | 19 July 1983 | Updated LER 83-017/03L-1:on 830326-28 & 0402,listed Control Rods Had No Indications for Identified Positions.Caused by Loose Prototypic Inlet Piping Connectors Due to Undervessel Work.Connectors Will Be Properly Fastened | |
| 05000324/LER-1982-131, Supplemental LER 82-131/03L-1:on 821206,one-half Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam Line Radiation Monitor D, 2-D12-RM-K603D.Caused by Disconnection of Instrument Cable | 11 March 1983 | Supplemental LER 82-131/03L-1:on 821206,one-half Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam Line Radiation Monitor D, 2-D12-RM-K603D.Caused by Disconnection of Instrument Cable | |
| 05000324/LER-1981-090, Updated LER 81-090/03L-3:on 810817 & 23,suppression Chamber Water Level Indicator 2-CAC-LI-2601-3 Indicated Lower Level & on 810820,indicated Higher Level than Other Indicator.Caused by Changes in Trickle Flow to Wet Ref Leg | 28 January 1983 | Updated LER 81-090/03L-3:on 810817 & 23,suppression Chamber Water Level Indicator 2-CAC-LI-2601-3 Indicated Lower Level & on 810820,indicated Higher Level than Other Indicator.Caused by Changes in Trickle Flow to Wet Ref Leg | |
| 05000325/LER-1982-127, Updated LER 82-127/01T-1:on 821103,quick Start Testing of Diesel Generators 2,3 & 4 Not Performed for 12 H Period Per Tech Spec.Caused by Failure to Enter Requirement Into Daily Surveillance Rept on 821102.Testing Performed | 23 December 1982 | Updated LER 82-127/01T-1:on 821103,quick Start Testing of Diesel Generators 2,3 & 4 Not Performed for 12 H Period Per Tech Spec.Caused by Failure to Enter Requirement Into Daily Surveillance Rept on 821102.Testing Performed | |
| 05000325/LER-1982-135, Supplemental LER 82-135/03L-1:on 821019,1.5-inch Discrepancy Noted Between Narrow & Wide Range Instruments.Caused by Inoperable RTGB Level Instruments.Plant Mod Package Developed to Increase Accuracy | 23 December 1982 | Supplemental LER 82-135/03L-1:on 821019,1.5-inch Discrepancy Noted Between Narrow & Wide Range Instruments.Caused by Inoperable RTGB Level Instruments.Plant Mod Package Developed to Increase Accuracy | |
| 05000325/LER-1982-024, Supplemental LER 82-024/03L-2:on 820214,during Periodic Test,Discovered That Open Position Indication for Drywell to Suppression Vacuum Breaker X18H Could Not Be Achieved.Caused by Failure of Vacuum Breaker to Fully Stroke Open | 13 October 1982 | Supplemental LER 82-024/03L-2:on 820214,during Periodic Test,Discovered That Open Position Indication for Drywell to Suppression Vacuum Breaker X18H Could Not Be Achieved.Caused by Failure of Vacuum Breaker to Fully Stroke Open | |
| ML20054L976 | 29 June 1982 | LER82-054/03L-0:on 820607,reactor Core Isolation Cooling Sys Turbine Automatically Started on Reactor Low Level,But Tripped Due to Closure of Control Valve 1-E51-V9.Caused by Lack of Turbine Speed Demand Signal Due to Governor Failure | |
| 05000325/LER-1982-053 | 29 June 1982 | LER 82-053/03L-0:on 820604,during startup,09 Position Found Superimposed on 00 RTGB Position Indication for Fully Inserted Control Rod 10-07.Caused by Defective Rod Position Reed Switch.Investigation Scheduled for 1982 Outage | |
| 05000325/LER-1981-092, Updated LER 81-092/01T-2:on 811226,action Statement 3.3.2b Not Entered When B21-LT-N017D-1 Instrument Failed Upscale. Caused by Failure of Operations Personnel to Recognize & Perform Required Action | 21 June 1982 | Updated LER 81-092/01T-2:on 811226,action Statement 3.3.2b Not Entered When B21-LT-N017D-1 Instrument Failed Upscale. Caused by Failure of Operations Personnel to Recognize & Perform Required Action | Half scram |
| 05000325/LER-1981-093, Updated LER 81-093/01T-2:on 811226,reactor Protection Sys Vessel Low Level Trip instrument,1-B21-LT-NO17D-1,was Indicating Upscale.Caused by Personnel Failure to Recognize & Perform Tech Specs.Personnel Counseled | 18 June 1982 | Updated LER 81-093/01T-2:on 811226,reactor Protection Sys Vessel Low Level Trip instrument,1-B21-LT-NO17D-1,was Indicating Upscale.Caused by Personnel Failure to Recognize & Perform Tech Specs.Personnel Counseled | Half scram |
| 05000325/LER-1982-038, Updated LER 82-038/03L-1:on 820419.Reactor Scrammed When Electrical Bus 1A-1 Dc de-energized.Caused by Operator Error in Opening 125-volt Dc Battery Charger Output Breaker for Battery 1A-1.Breaker Closed & Power Restored to Bus | 4 June 1982 | Updated LER 82-038/03L-1:on 820419.Reactor Scrammed When Electrical Bus 1A-1 Dc de-energized.Caused by Operator Error in Opening 125-volt Dc Battery Charger Output Breaker for Battery 1A-1.Breaker Closed & Power Restored to Bus | |
| ML20062G308 | 21 December 1978 | /03L-0 on 781122:HPCI & RCIC Component Tests Were Overlooked Because Rescheduling Technique Provided No Clear Indication of Test Due Dates.Responsible Technician Reinstructed & Admin Operating Instruction AOI-5 Rev | |
| ML20064H896 | 19 December 1978 | /03L-0 on 781120:Senior Control Operator Did Not Have Completed Hatch Leak Rate Test Before Beginning Reactor Startup Due to Misunderstanding.Test completed.GP-1 Revised to Require Leak Test Verification by Control Operators | |
| ML20064H618 | 14 December 1978 | /03L-0 on 781114:torus Level of the HPCI Turbine Control Sys Was Slightly Above the Allowed 27 Inches.Proper Torus Level Restored to Normal.Torus Level Indicator Will Be More Clearly Marked | |
| ML20064H597 | 14 December 1978 | /03L-0 on 781114:Fire Hoses of Radwaste Bldg 3 Elevation Fire Stations Were Found Missing Due to Use by Personnel for Routine Radwaste Washdown.New Firehoses Installed & Mod Re Alternate Water Supply Is in Progress | |
| ML20064H589 | 14 December 1978 | /03L-0 on 781114:during Periodic Test 9.3.a the HPCI Egr Actuator Failed to Oper Properly Due to Water in Hydraulic Fluid Corroding Egr Actuator.Steam Leaking Past Seat of Valve HPCI E41-F001 Allowed Water Into Fluid | |
| ML20062F678 | 13 December 1978 | /03L-0 on 781112:reactor Steam Dome High Pressure Switch B32-PS-N018B Did Not Reset & Would Not Allow RHR Valve E11-F008 to Open for Shutdown Cooling at Reactor Pressure of 102psig.Caused by Sticking micro-switch | |
| ML20062F668 | 13 December 1978 | /03L-0 on 781117:while Reactor Was in Hot Shutdown Torus Level Increased .2 Above Tech Specs.Caused by Demineralized make-up Water Leakage Through Valves from RHR Keep-fill System Causing Torus Level to Rise | |
| ML20064G930 | 11 December 1978 | /03L-0 on 781109:Reactor Vessel Chemistry Exceeded Tech Spec Limits for Conductivity & Concentration Due to Presence of Organic Compounds in Condensate Sys.Organic Filtration & High Concentration of Ion Resin Cleanup Begun | |
| ML20062E438 | 30 November 1978 | /03L-0 on 781101:rod Block Monitor(Rbm) Channel a Was Found Out of Calibr During Testing Due to Setpoint Drift.Calibr Frequency Will Be Increased from Once to Twice Per Year | |
| ML20064E800 | 15 November 1978 | /03L-0 on 781017:reactor Bldg Radiat Exhaust Monitor D12-RM-N010B Failed Safe Causing Reactor Bldg Vent to Isolate,Due to Defective Transistor 2N1711 on 24V Pwr Supply | |
| ML20064E458 | 14 November 1978 | /01T-0 on 781101:util Was Informed by NRR of Nonconformance w/10CFR50 Append a Gen Design Criteria 54 & 56.Two Reactor bldg-to-torus Vacuum Breaker Lines Have Never Had Design Review by Nrc.Tech Spec Change Effective 781108 | |
| ML20064E337 | 9 November 1978 | /03L-0 on 781014:RCIC Turbine Was Tripped on Manual Overspeed for Training Purposes & Turbine control- Stop Valve E51-V8 Would Not Reset.Caused by Improperly Worn Adjusted Reset Lever | Overspeed trip |
| ML20064E292 | 9 November 1978 | /03L-0 on 781011:torus Level Dropped Below Tech Spec Minimum While Water from Torus Was Being Pumped,Via Rgr to Radwaste in Efforts to Reduce Torus Water Level. Caused by Operator Being Distracted | |
| ML20064E354 | 7 November 1978 | /03L-0 on 781006:condensate Storage Tank Level Switch E41-LS-N003 Found Out of Calibration During Periodic Condensate Storage Tank Low Level Channel.Caused by Instru Drift | |
| ML20064E349 | 6 November 1978 | /03L-0 on 781105:Control Oper Received Control Rod Drift Alarm for Rod 10-31.When Rod Position Display Was Selected,A False 3 Was Superimposed on Actual Rod Position Due to Aground on the Rpls Probe | |
| ML20064D821 | 2 November 1978 | /03L-0 on 781004:pressure Switch E11-PS-NO16B Failed During Periods Plci Pump Discharges ADS Permissive Test,Due to Corrosion Buildup on Plunger of Switch | |
| ML20064C015 | 10 October 1978 | /03L-0 on 780911:during Monthly 1 Diesel Generator Load Test,It Was Found That 1 Cylinder Was Not Firing,Due to Faulty Fuel Pump | |
| ML20064C001 | 9 October 1978 | /03L-0 on 780911:Snubber SW-142SS164 Found Inoperable During Periodic Test.Caused by Seal Degradation & Resulting Loss of Fluid | |
| ML20147C914 | 4 October 1978 | /03L-0 on 780904:RCIC Isolation Channel a Tripped Momentarily,Causing RCIC Sys to Be Inoper,Due to Defective RX-2 Relay | |
| ML20062A069 | 3 October 1978 | /03L-0 on 780904:rod Block Monitor B Inoperative Trip Came on & Stayed on for 1/4 of the Control Rod Selection Matrix.Caused by Failed Integrated Circuit in Rod Block Monitor self-test Circuitry | |
| ML20064B723 | 3 October 1978 | /03L-0 on 780905:during Periodic Test,Radiat Monitor D12-RM-NO10B HI-HI Trip Point Drifted to Higher than Permitted Level.Monitor Recalibrated.Drift Appears to Be Isolated Incident;No Further Action Taken |