Pages that link to "05000287/LER-2008-001, Trip Due to Control Rod Drive System Processor Failure"
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The following pages link to 05000287/LER-2008-001, Trip Due to Control Rod Drive System Processor Failure:
Displayed 6 items.
- 10 CFR 50.73(a)(2)(iv), System Actuation (← links)
- 05000287/LER-2008-001 (redirect page) (← links)
- 05000287/LER-2015-001, Manual Reactor Trip Due to Unacceptable Main Feedwater Flow Control Valve Oscillations (← links)
- 05000287/LER-2005-002 (← links)
- 05000287/LER-2004-001 (← links)
- 05000287/LER-2002-001 (← links)
- 05000287/LER-2001-002 (← links)
- IR 05000269/2009002 (← links)
- 05000287/LER-1982-008, Forwards LER 82-008/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-010, Forwards LER 82-010/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-015, Forwards LER 82-015/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-005, Forwards LER 81-005/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-007, Forwards LER 82-007/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-012, Forwards LER 82-012/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1983-001, Forwards LER 83-001/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1983-005, Forwards LER 83-005/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1983-002, Forwards LER 83-002/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation (← links)
- 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications (← links)
- 05000287/LER-2023-001, Condition Prohibited by Technical Specifications Due to Isolation Valve Exceeding Inservice Testing Leakage Requirements (← links)
- 05000287/LER-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve (← links)
- 05000287/LER-2022-001, Response Actions Resulted in Brief Inoperability of Both Onsite and Offsite Emergency AC Power Paths (← links)
- 05000287/LER-1989-003-06, :on 890727,reactor Bldg Isolation Valve 3LWD-1 Returned to Svc W/O Being Leak Rate Tested Following Maint on Valve Operator.Caused by Deficient Communication Between Engineers.Leak Rate Test Performed (← links)
- 05000287/LER-1986-002-06, :on 860917,main Feedwater Pumps & Emergency Feedwater Sys Tripped & 3KI Essential Ac Power Lost During Reactor Trip Due to Pipe Rupture.Caused by Component Failure.Unit Brought to Hot Shutdown (← links)
- 05000287/LER-1986-003-01, :on 861028,radiation Indication Alarm Turbine Bldg Sump Monitor 3RIA-54 Discovered in Bypass Position. Caused by Defective Procedure Not Requiring Return to Normal Position After Placement in Bypass (← links)
- 05000287/LER-1985-001-02, :on 850723,unit Tripped on High RCS Pressure During Secondary Feedwater Transient.Caused by Erroneous Signal from Failed Integrated Control Sys Module.Failed Module Replaced (← links)
- 05000287/LER-1998-001-06, :on 981203,determined That LLRT Had Not Been Performed on Fittings.Caused by Inappropriate Action of Maint Field Planner & PMT Scheduler.Counseled Individuals Involved & Enhanced PMT Guidance.With (← links)
- 05000287/LER-2020-001, Manual Reactor Trip Due to Reaching Feedwater Heater Level Limit in Operating Procedure (← links)
- 05000287/LER-1986-001-04, :on 860131,reactor Tripped Due to High RCS Pressure.Caused by Instantaneous Failure of Amplifier in Feedwater Flow Transmitter A1.Unit Stabilized.Amplifier Replaced (← links)
- 05000287/LER-1985-005-05, :on 851024,anticipatory Reactor Trip Occurred on Loss of Main Feedwater Pump.Caused by Failure of Regulator Valve to Function Properly.Unit Stabilized at Hot Shutdown.Valve Positioner Will Be Installed (← links)
- 05000287/LER-1985-004-05, :on 851017,hydrogen Concentration Sampling of Isolated Gaseous Waste Disposal Tank Not Performed.Caused by Personnel Error.Tank Sampled & Analyzed (← links)
- 05000287/LER-1985-003-04, :on 851015,attempt to Open Electric Motor Operated Valve 3LP-2 from Control Room Failed.Caused by Low Torque Switch Settings.Valve Opened from Valve Actuator Contractors by Overriding Limit Circuit (← links)
- 05000287/LER-1985-001-04, :on 850723,reactor Tripped Due to High RCS Pressure.Caused by Erroneous Signal from Failed Integrated Control Sys Module.Module Replaced (← links)
- 05000287/LER-1985-002-05, :on 850828,fault Pressure Relay on Startup Transformer CT-3 Actuated,Initiating Lockout & Resulting in Loss of Ac Power.Cause Undeterminable.Load Ctr Transformer Feeder Breakers Reset (← links)
- 05000287/LER-1984-006-03, :on 841106,offgas Monitors from Condensate Steam Air Injectors Showed Rapid Increase in Radiation Count Rate.Caused by primary-to-secondary Coolant Leak.Reactor Shutdown,Tests Run & Tubes Plugged (← links)
- 05000287/LER-1984-003-02, :on 840607,trip Initiated by Reactor Protection Sys on Erroneous Indicated Loss of Feedwater Pumps.Cause Unknown.Unit Immediately Stabilized at Hot Shutdown (← links)
- 05000287/LER-1984-005-03, :on 840814,trip Occurred When Instrument Air Line to Powdex Outlet Valves Accidentally Sheared.Caused by Attempt to Straighten Bend Which Resulted from Work on Pipe Above Instrument Air Line (← links)
- 05000287/LER-1984-004-02, :on 840607,w/unit at 20% Power,Turbine Generator/Reactor Anticipatory Trip Occurred.Unit Stabilized at Hot Shutdown Conditions.Cause Unknown.Unit Restarted & Reached 100% Power on 840609 (← links)
- 05000287/LER-1984-002-02, :on 840216,reactor Trip Initiated by Reactor Protection Sys When High RCS Pressure Setpoint Reached. Caused by Failure of Rc Loop a Flow Transmitter Due to Malfunctioning Amplifier Assembly (← links)
- 05000287/LER-1983-014-03, /03L-0:on 831226,discovered Channel B Reactor Protective Sys a Hot Leg Temp Instrument Indicating More than 3 F Lower than Other Channels.Caused by Deficiency. Resistance Temp Detector Bridge Calibr (← links)
- 05000287/LER-1983-012-03, /03L-0:on 831018,valve 3FDW-382 Discovered Partially Opened & Declared Inoperable.Caused by Component Failure.Valve Manually Opened (← links)
- 05000287/LER-1983-011-03, /03L-0:on 83l013,discovered No Low Pressure Svc Water Flowing Through Operating 3B Mdefdw Pump.Pump Declared Inoperable.Caused by Component Failure.Valve 3SV-203 replaced.w/831111 1tr (← links)
- 05000287/LER-1984-001, :on 840105,discovered 3TE Switchgear Load Shed Source B Fuse Block Not Installed.Cause Unknown.Fuse Block Reinstalled & Station Mod to Install Fuse Blocks & Add Computer Alarms Will Be Completed (← links)
- 05000287/LER-1983-010-01, /01T-0:on 830830,as Result of QA Review & Other Reanalysis,Determined Axial Power Shaping Rod Limits for U3 C7 After 385 EFPD Not Conservative.Caused by Design Error. Limits Reanalyzed Using More Iterations (← links)
- 05000287/LER-1983-008-03, /03L-0:on 830707,during Emergency Safeguards on- Line Test,Valve 3LPSW-565 Failed to Operate.Caused by Mechanical Interlock & Motor Starter Coil Bind.Motor Starter Repaired (← links)
- 05000287/LER-1983-009-03, /03L-0:on 830727,HPI Pump 3A Tripped When Manual Start Attempted.Cause Unknown.Pump Reset (← links)
- 05000287/LER-1983-005-01, /01T-0:on 830314,supply Valve on Reactor Bldg Cooling Train B Failed.Caused by Main Feeder Breaker Tripping on Overcurrent.Breaker Reset,Overcurrent Trip Setting Increased & Setting Procedures Will Be Evaluated (← links)
- 05000287/LER-1983-002-01, /01T-0:on 830225,engineering Evaluation of Reactor Protective Sys Pump Power Monitor Test Revealed Failure to Have One Channel Tripped When Three Channels Operable.Caused by Deficient Procedures.Procedures Revised (← links)
- 05000287/LER-1983-006-03, /03L-0:on 830513,during Attempt to Replace Cell in Battery 3PB,power Lost from Emergency Feedwater Pump Turbine Auxiliary Oil Pump.Caused by Personnel Failure to Follow Procedure.Personnel Counseled (← links)
- 05000287/LER-1982-012-01, /01T-0:on 821117,steam Generator Tube Leak of 0.5 Gpm Indicated by Condensate Steam Air Ejector Offgas Radiation Monitor.Caused by Cracks in Tubes 65-1,68-4,78-4, 78-8 & 83-5.Tubes Removed from Svc for Lab Analysis (← links)
- 05000287/LER-1983-001-01, /01T-0:on 830223,HPI Train 3A Made Inoperable When Control Power Fuses for 3HP-24 & 3HP-26 Found Blown.Caused by Component Failure & Design Deficiency.Power Reduced & Blown Fuses Replaced (← links)
- 05000287/LER-1982-010-01, /01T-0:on 821004,discovered That Weekly Boron Waste Storage Tank Boron Sample Not Taken as Scheduled, Contrary to Tech Spec 4.1.3.Caused by Personnel Not Having Access to Posted Schedule Board.Board Replaced (← links)
- 05000287/LER-1982-014-01, /01T-0:on 821211,steam Generator Tube Leak Indicated by Condensate Steam Air Ejector Offgas Radiation Monitor.Caused by Crack in Tube 77-9.Tube 77-9 & Tube 78-2 Removed from Svc (← links)
- 05000287/LER-1982-015-01, /01T-0:on 821212,manual Containment Isolation Valves 3IA 90 & 91 Found Open,Violating Containment Integrity.Caused by Personnel & Procedure Error.Personnel Counseled & Procedure Revised (← links)
- 05000287/LER-1981-005-03, /03L-0:on 810323,engineering Safeguard Valve 3CS-5 Failed to Operate.Caused by Operator Failure Since Valve Could Be Operated Manually.Valve Operator Will Be Inspected During Next Outage (← links)
- 05000287/LER-1982-007-01, /01T-0:on 820521,during Video Insp of Fuel Assemblies,Broken Holddown Springs Found on Fuel Assemblies NJ001MH & NJ001M9.Caused by Fatigue Induced Cracking at Existing Surface Flaw.Springs Will Be Replaced (← links)
- 05000287/LER-1982-008-01, /01T-0:on 820609,during Removal of Locking Clips on Thermal Shield bolts,19 of 27 Bolts Had Bolt Heads Broken Off.Upon Completion of Locking Clip removal,46 of 96 Had Heads Broken Off.Caused by Stress Cracking (← links)
- 05000287/LER-1982-005-01, /01T-0:on 820330,spent Fuel Pool Fans Found to Have Been Inoperable During 820323-29 Move of 10 Fuel Assemblies.Caused by Personnel Error in That White Tags for Fans Not Placed or Removed During Leak Rate Test Procedure (← links)
- 05000287/LER-1982-005, Forwards LER 82-005/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-004-01, /01T-0:on 820226,nondestructive Testing of HPI Nozzles Revealed 3A2 Thermal Sleeve Displaced & Cracks in Inside Diameter of Piping & Safe End.Caused by Thermal Fatigue Due to Loose Thermal Sleeve.Piping Replaced (← links)
- 05000287/LER-1982-004, Forwards LER 82-004/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-002-03, /03L-0:on 820210,reactor Protection Sys Channel B Hot Leg Temp Readings Were Lower than Those of Channels A,C & D.Caused by Failure of Liner Bridge in Input Circuitry for Channel B Indication.Bridge Replaced (← links)
- 05000287/LER-1982-002, Forwards LER 82-002/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-003-01, /01T-0:on 820211,steam Generator Tube Leak of Approx 0.01 Gpm Indicated by Condensate Steam Air Ejector Offgas Monitor.Caused by Erosion of Tube at Point 31 Inches Above Fifteenth Tube Support Plate.Tube Explosively Plugged (← links)
- 05000287/LER-1982-003, Forwards LER 82-003/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-001-03, /03L-0:on 820128,channel B Borated Water Storage Tank Level Indication Declared Inoperable Due to Erratic Indication.Caused by Dirt & Oil in Level Indicator Booster Relay & High Thermostat Settings on Sys Heat Trace (← links)
- 05000287/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-016-03, /03L-0:on 811202,channel C Pump Power Monitor Failed to Send Trip Signal During Online Testing.Caused by Failed 1C on Monitor Logic Board.Board Replaced & Monitor Tested Satisfactorily (← links)
- 05000287/LER-1981-016, Forwards LER 81-016/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-014-03, /03L-0:on 811125,channel B flux-imbalance Flow Bistable Found to Trip Outside Tech Spec Limit.Caused by non-linear Gain on Reactor Protection Sys Channel B Scaled delta-flux Amplifier.Amplifier Replaced (← links)
- 05000287/LER-1981-014, Forwards LER 81-014/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-007-03, /03L-0:on 810329,inner Door Seal of Reactor Bldg Personnel Lock Found to Leak at Rate Greater than That Allowed by Procedure.Caused by Faulty Installation of Strong Backs.Gasket Shinned & Strong Backs Reinstalled (← links)
- 05000287/LER-1981-007, Forwards LER 81-007/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-006-03, /03X-1:on 810324,reactor Protection Sys Channel a High Pressure Trip Found Out of Calibr.Caused by Transmitter Drift.Pressure Transmitter Recalibr (← links)
- 05000287/LER-1981-006, Forwards LER 81-006/03X-1.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-008-03, /03L-0:on 810422,during Seismic Block Wall Insp, Discovered Breach of Fire Barrier in Penetration 3-T-T-1. Caused by Pulling of Electrical Cables Through Barrier. Breach Repaired Using RTV Foam (← links)
- 05000287/LER-1981-008, Forwards LER 81-008/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-004-03, /03L-0:on 810312,valve 3FDW-105 Failed to Close Electrically After Chemical Sampling of Steam Generator B. No Apparent Cause Found.Valve Manually Closed & Circuit Breaker Opened,Disabling Valve (← links)
- 05000287/LER-1981-004, Forwards LER 81-004/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-011-03, /03L-0:on 821004,while Inspecting Snubber Installed on 821002,mechanic Found Snubber Inoperable.Caused by Misreading of Hanger Sketch.Snubber Removed,Tested & Reinstalled (← links)
- 05000287/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1982-009-01, /01T-0:on 820804,during Refueling Insp of Reactor Coolant Pump,Five Closure Studs Found Degraded in Size Below Tech Spec Min.Caused by Boric Acid Corrosion Due to Closure Gasket Leakage.Studs Replaced (← links)
- 05000287/LER-1982-009, Forwards LER 82-009/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-015-01, /01T-0:on 810720,while Attempting to Perform Engineered Safeguard Periodic Test,Low Pressure Injection Pump 3-B Failed to Start.Caused by Personnel Error.Pump Motor Bearings Replaced & Personnel Counseled (← links)
- 05000287/LER-1981-015, Forwards LER 81-015/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-012-03, /03L-0:on 810624,valve 3PR-8 Failed in Closed Position,Isolating Radiation Monitors 3 RIA-47,48 & 49. Caused by Ruptured Diaphragm in Air Operator on Valve. Diaphragm Replaced (← links)
- 05000287/LER-1981-012, Forwards LER 81-012/03L-0 (← links)
- 05000287/LER-1981-013-03, /03L-0:on 810528,1-inch Breach Discovered in 3-h Fire Barrier in Floor of Control Room Outside Shift Supervisor Ofc.Cause Undefined Due to Breach Being Covered Since Const of Control Room (← links)
- 05000287/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-003-01, /01T-0:on 810226,B Steam Generator Was Pressurized to 550 Psig.Caused by Procedural Deficiency. Once-through Steam Generator Pressure Lowered.Procedures for Opening Startup Block Valves Will Be Revised (← links)
- 05000287/LER-1981-003, Forwards LER 81-003/01T-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-010-03, /03L-0:on 810517,broken Airline to Valve 3LPSW-525 Was Discovered.Caused by Breakage of Brass Nipple Between Air Supply Isolation Valve & Accumulator Tank.Brass Nipple Replaced (← links)
- 05000287/LER-1981-010, Forwards LER 81-010/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-011-03, /03L-0:on 810518,safety-related Mechanical Snubber Was Discovered Inoperable During Visual Insp.Caused by Ball Screw Shaft of Snubber Being Slightly Scored,Prohibiting Ball Bearings from Running Smoothly.Snubber Replaced (← links)
- 05000287/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1981-009-03, /03L-0:on 810507,containment Isolation Valve 3CS-6 Was Discovered in Intermediate Position,Resulting in Loss of Containment Integrity.Cause Undetermined.Valve 3CS-6 Verified Operable (← links)
- 05000287/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Encl (← links)
- 05000287/LER-1980-016-03, /03L-1:on 801123,fire Detectors String B-2 Went Into Alarm Condition.Caused by Dust Buildup in Detector. Detector Cleaned & Verified Operable (← links)
- 05000287/LER-1980-016, Forwards LER 80-016/03L-1.Detailed Event Analysis Encl (← links)
- 05000287/LER-1978-009-03, /03L-0:on 780320,valve HP-24 Failed to Open When Manually Actuated During Performance Test.Caused Probably by Dirt on Operator Contacts.Contacts Cleaned & Valve Operated Properly (← links)
- 05000287/LER-1978-009, Forwards LER 78-009/03L-0 (← links)
- 05000287/LER-1978-010-03, /03L-0:on 780322,no Flow Found Through B LPIS Cooler During Performance Test.Caused by Broken Valve Position Indicator.Valve Opened & Indicator Repaired (← links)
- 05000287/LER-1978-001-03, /03L-0:on 780105,Valve FDW-108 Failed to Close After Sample Removal.Similar Valve Failures Occured Previously.Probably Caused by Inability to Withstand environ.FDW-1-6,108 Replaced W/Appropriately Designed Valve (← links)
- 05000287/LER-1978-001, Forwards LER 78-001/03L-0 (← links)
- 05000287/LER-1978-012-01, /01T-0:on 780804,weld Filler Wires Found Mixed W/Shipment of Mn-Mo-Ni Filler Wires.Nsss Vendor Supplied W/Wire Containing Atypical Matl Composition.Unit Operation Continues W/Restrictive pressure-temp Limits (← links)
- 05000287/LER-1978-012, Forwards LER 78-012/01T-0 (← links)
- 05000287/LER-1978-008-03, /03L-0:on 780305,power Range Detector Found Spiking.Reactor Protection Sys Channel a Bypassed,Preventing Spurious Trips.Cause Not Determined.Investigation to Resume Next Refueling or Next Spiking (← links)
- 05000287/LER-1978-004-03, /03L-0:on 780203,valve BS-3 Failed to Open During Operability Test.Caused by Torque Switch Electrical Failure. Switch Replaced & Valve Operability Verified (← links)
- 05000287/LER-1978-008, Forwards LER 78-008/03L-0 (← links)
- 05000287/LER-1978-006-03, /03L-0:on 780210,Control Rod 3,Group 4,dropped Into Core During Breaker Test,Causing Power Runback to 55%. Caused by Stator Short Due to Excessive Moisture Entering Through Nonleakproof O-ring Seal.Stator Replaced (← links)
- 05000287/LER-1978-004, Forwards LER 78-004/03L-0 (← links)
- 05000287/LER-1978-006, Forwards LER 78-006/03L-0 (← links)
- 05000287/LER-1978-005-03, /03L-0:on 780207,valve BS-2 Failed in Intermediate Position During Operability Test.Caused by Valve Stem Failure & Partly by Faulty Torgue Switch.Stem & Switch Replaced.Stems Made by Walworth (← links)
- 05000287/LER-1978-007-03, /03L-0:on 780208,suction Valve 3LPSW-123 Observed Closed During 3B Pump Startup.Valve Closure Cause Unknown. Probably Caused by Erroneous Closing During Repairs on on Pervious Day.Valve Opened & Pump Checked for Damages (← links)
- 05000287/LER-1978-007, Forwards LER 78-007/03L-0 (← links)
- 05000287/LER-1978-005, Forwards LER 78-005/03L-0 (← links)
- 05000287/LER-2018-002-01, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 3 Main Feeder Buses (← links)
- 05000287/LER-2018-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 3 Main Feeder Buses (← links)
- 05000287/LER-1917-001, Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout (← links)
- 05000287/LER-2016-001, Regarding Reactor Building Cooling Unit Inoperability Exceeds Technical Specification Completion Time (← links)
- 05000287/LER-2015-002, Regarding Broken Electrical Conductor Supplying Start-up Transformer (← links)
- 05000287/LER-2015-001, Regarding Manual Reactor Trip Due to Unacceptable Main Feedwater Flow Control Valve Oscillations (← links)
- 05000287/LER-2013-001, Re Manual Reactor Trip Due to Main Feedwater Flow Oscillations (← links)
- 05000287/LER-2012-001, For Oconee, Unit 3, Regarding Three Main Steam Relief Valves (MSRV) Lift Pressure Exceeds + 1% Tolerance (← links)
- 05000287/LER-2009-002, For Oconee Nuclear Station Unit 3, Regarding Trip Due to Generator Phase Differential Lockout (← links)
- 05000287/LER-2009-001, For Oconee, Unit 3, Regarding Two Pals CIVs Inoperable Due to Use of Unqualified Seat Material (← links)
- 05000287/LER-2008-001, Trip Due to Control Rod Drive System Processor Failure (← links)
- 05000287/LER-2006-001, Re Actuation of Emergency Generator Due to Spurious Transformer Lockout (← links)
- 05000287/LER-2005-001, Regarding TS LCO Condition Allowed Outage Time and Required Action Completion Time Exceeded Due to Blockage of Lpi/Bs Pump Room Air Flow Path (← links)
- 05000287/LER-2001-001-01, Regarding Reactor Pressure Vessel Head Leakage Due to Stress Corrosion Cracks Found in Nine Control Rod Drive Nozzle Penetrations (← links)
- 05000287/LER-2004-004, Regarding Open Containment Penetration During Refueling Activities (← links)
- 05000287/LER-2003-001, From Oconee, Unit 3 Regarding Apparent Reactor Pressure Vessel Head Leakage from a Control Rod Drive Nozzle (← links)
- 05000287/LER-2001-003, Minor Reactor Pressure Vessel Head Leakage from Several Control Rod Drive Nozzle Penetrations Due to Primary Water Stress Corrosion Cracking (← links)
- ML090120436 (redirect page) (← links)
- 05000269/LER-2008-002, Regarding Main Steam Relief Valves Exceeded Lift Setpoint Acceptance Band (← links)
- 05000269/LER-2008-001, Gas Void Found in High Pressure Injection System Suction Piping (← links)
- 05000270/LER-2008-001, Regarding Unit 2 Reactor Trip Due to Indication of Loss of Vacuum During Calibration of a Condenser Pressure Transmitter (← links)