Pages that link to "05000266/LER-2013-001, Loss of Offsite Power to Unit 1 Safeguards Buses"
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The following pages link to 05000266/LER-2013-001, Loss of Offsite Power to Unit 1 Safeguards Buses:
Displayed 3 items.
- 05000266/LER-2013-001 (redirect page) (← links)
- 05000266/LER-2015-001, Inadequately Sealed Pipe Penetrations Result in Unanalyzed Condition for Internal Flooding (← links)
- 05000266/LER-2012-001 (← links)
- 05000266/LER-2004-001 (← links)
- 05000266/LER-2007-002 (← links)
- 05000266/LER-2001-004 (← links)
- 05000266/LER-2001-003 (← links)
- 05000266/LER-2001-002 (← links)
- 05000266/LER-2001-001 (← links)
- 05000266/LER-1982-030, Forwards LER 82-030/03L-0 (← links)
- 05000266/LER-1978-012, Forwards LER 78-012/01X-0 (← links)
- 05000266/LER-1978-014, Forwards LER 78-014/01T-0 (← links)
- 05000266/LER-1982-078, Forwards LER 82-078/03L-0 (← links)
- 05000266/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000266/LER-1982-017, Forwards 821210 Rev to Licensee 821115 LER 82-017/01T-1 Containing Addl Info Re Eddy Current Indication on Inner Diameter of Sleeve.W/O Rev.Svc List Encl (← links)
- 05000266/LER-1982-021, Forwards LER 82-021/03L-0 (← links)
- 05000266/LER-1982-016, Forwards LER 82-016/01T-0 (← links)
- 05000266/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000266/LER-1982-019, Forwards LER 82-019/01T-0 (← links)
- 05000266/LER-1982-018, Forwards LER 82-018/01T-0 (← links)
- 05000266/LER-1982-009, Telecopy Message of LER 82-009/01T-0:on 821030,tubes in Steam Generators a & B Found W/More than 40% Degradation.On 821025,insp Revealed 5 Wet or Dripping Explosive Plugs.No Cause Stated.Tubes Plugged (← links)
- 05000266/LER-1995-003, Forwards LER 95-003 Re Inadvertent EDG Start (← links)
- 05000266/LER-1982-025, Forwards LER 82-025/03L-0 (← links)
- 05000266/LER-1982-024, Forwards LER 82-024/03L-0 (← links)
- 05000266/LER-1982-026, Forwards LER 82-026/01T-0 (← links)
- 05000266/LER-1982-012, Forwards LER 82-012/03L-0 (← links)
- 05000266/LER-1993-001, Revised LER 93-001-00:on 930107,all 4,160 Volt Degraded Grid Voltage Protection Channels Declared Inoperable Due to Discovery That Settings for Relays on Subj Channels Being Too Low.Plant Mods Will Be Made (← links)
- 05000266/LER-1997-039, Forwards LER 97-039-00 Re RHR Loop Inoperable,Due to Inoperable CCW Pump.New Commitments within Rept Indicated in Italics (← links)
- 05000266/LER-1988-008, Informs That Mod to LER 88-008-00 Would Provide Redundant Feedwater Termination in Event of Main Steam Line Break Inside Containment.If Mod Not Completed on Unit 2 During Fall Outage,Mod Will Be Delayed Until Fall 1990 Outage (← links)
- 05000266/LER-2007-033, Forwards LER 07-033-00,re Discovery That Redundant Power Cables in AFW Room Do Not Meet App R Separation Criteria & Have Not Been Provided Exemption from Requirement (← links)
- 05000266/LER-1950-266, Responds to NRC Re Violations Noted in Insp Repts 50-266/97-07 & 50-301/97-07.Corrective actions:30-day Security LER 50-266/97-S01-00,was Submitted to Commission on 970304 (← links)
- 05000266/LER-1992-002, Forwards Response to NRC 921116 Request for Info Re CCW Sys & Ccvs,Per LER 92-002-00 & GL 83-28.Info Covers Classification of Auxiliary Sys Necessary to Ensure Safe Plant Shutdown (← links)
- 05000266/LER-1982-007, Opposes Wi Environ Decade Re LER 82-007.Issues Advanced Re Decontamination Process & Removal of Mechanical Plugs Constitute ill-conceived Attempt to Raise New Issues Unrelated to Case (← links)
- 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip (← links)
- 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications (← links)
- 05000266/LER-1998-017, :on 980512,discovered Deficient Welds on B Loop Rrtd Piping Pipe Whip Restraint.Caused by Support Being Cut & Partially Removed During Plant Mod MR 84-284.Deficient Welds Were Repaired,Inspected & Confirmed to Perform (← links)
- 05000266/LER-1998-016, :on 980427,refueling Sys Interlock Testing Did Not Match That of FSAR Description.Caused by More Literal & Restrictive Interpretation of Description in Fsar.Revised ORT-15 to Include Items Discussed in FSAR Section 9.5 (← links)
- 05000266/LER-1989-006, :on 890505,automatic Actuation of motor-driven Auxiliary Feedwater Pumps Occurred.Caused by Cognitive Personnel Error Concerning Projected Plant Conditions.Sys Response Evaluated (← links)
- 05000266/LER-1989-005, :on 890503,inoperability of Low Temp Overpressure Protection Sys Using Nitrogen Gas Discovered. Caused by Inadequate post-mod Testing.Nitrogen Regulators Moved to Location Near PORVs (← links)
- 05000266/LER-1998-014, :on 980417,ESF Actuation Automatic Start of Swp Occurred.Caused by Inadequate Procedure That Failed to Provide Info on Expected Start of Swps P32A & P32B.Revised Procedure Iwp 95-048-02 to Provide Necessary Info (← links)
- 05000266/LER-1998-013, :on 980416,discovered That Discharge Pressure Indicator Root Valves for Containment Spray Pumps Were Not Shut as Required.Caused by Failure to Maintain Adequate Configuration Control.Shut Subject Root Valves (← links)
- 05000266/LER-1989-007, :on 890625, Loss of Feedwater Turbine Trip Blocked Status Light Illuminated on Control Board 1-C03. Cause unknown.P-20 Bistable Alarm Module Replaced (← links)
- 05000266/LER-1989-004, :on 890421,discovered Nonconservative Analysis of Transfer to Containment Sump Recirculation Mode.Caused by Inadequate Analysis of Interruption of ECCS Flow During Large Break LOCA Scenario.Night Order Issued (← links)
- 05000266/LER-1989-002-01, :on 890412,during Type C Containment Leak Rate Testing,Charging Sys Check Valve 1-370 Discovered Leaking in Excess of Tech Spec Limits.Caused by Bent Dowel Pin in Valve Disc.Valve Repaired & Restored (← links)
- 05000266/LER-1998-012, :on 980330,discovered That twenty-seven Containment Penetration Pressure Tests Had Not Been Performed.Caused by Inadequate Program Monitoring & Mgt. Submitted Relief Request & Initiated Root Cause Evaluation (← links)
- 05000266/LER-1989-003, :on 890601,injection of High Artificial High Radiation Signal Failed to Close Containment Isolation Valve.Defective Solenoid Valve Controlling Air to Isolation Valve Air Operator Replaced (← links)
- 05000266/LER-1989-001-01, :on 890322,emergency Diesel Generator & Both Trains of Containment Spray Sys Inoperable During Power Operation of Both Reactors.Caused by Personnel Error. Containment Spray Sys Restored to Operation (← links)
- 05000266/LER-1998-025, :on 980731,determined That Operation of CR Smoke Exhaust fan,W-13C,could Prevent Maintaining Positive Pressure in Cr.Caused by Oversight in Initial Mod Project. Administrative Controls Implemented for Operation of Fan (← links)
- 05000266/LER-1987-005-01, :on 871121,reactor Coolant Pressure Decreased Resulting in Reactor Trip Due to Low Pressurizer Pressure. Caused by Spray Valve Failure.Broken Solder Connection Repaired & Pilot Valve Steam Replaced (← links)
- 05000266/LER-1998-024, :on 980721,inadvertent EDG Start Was Noted. Caused by Installation of Electrical Jumper Wire.Removed Temporary Jumper Wire & Revised Operating Procedure (← links)
- 05000266/LER-1998-023, :on 980718,circulating Water Pumphouse Roof Was Not IAW Plant Design Basis.Caused by Inadequate Consideration of Structural Requirements.Operability Determination to Evaluate Effect of Condition Was Completed (← links)
- 05000266/LER-1998-022, :on 980714,TS LCOs for Safety Injection & RHR Operation Occurred.Caused by Unplanned Equipment Inoperability.Duty & Call Superintendent Handbook Procedure Has Been Approved to Provide Operators Guidance (← links)
- 05000266/LER-1998-010, :on 980213,inadequate TS Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Verify Switch Position.Bistable Switch Continuity Was Verified within 24 H of Determining Testing Was Inadequate (← links)
- 05000266/LER-1998-010-01, Forwards LER 98-010-01,re Containment Spray Channel Functional Testing.Commitments Made within Ltr,Encl (← links)
- 05000266/LER-1998-021, :on 980702,discovered That ASME Section XI Inservice Stroke Tests Were Not Performed on Four Valves within Required Time Frame.Caused by Personnel Error.All 4 Valves Were Subsequently Tested & Found to Be Satisfactory (← links)
- 05000266/LER-1998-020, :on 980701,identified Group of Cables in Cable Spreading Room Which May Not Meet Licensee Fire Protection Commitments.Caused by Failure to Fully Implement Certain Requirements.Fire Watch Established Twice Per Shift (← links)
- 05000266/LER-1998-015-01, Forwards LER 98-015-01 Re Containment Fan Cooler Test Results Outside Acceptance Criteria.Addl Info Re Corrective Actions Taken,Provided.No New Commitments,Made (← links)
- 05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating (← links)
- 05000266/LER-1998-018, :on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified (← links)
- 05000266/LER-1998-008, :on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified (← links)
- 05000266/LER-1998-009, :on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed (← links)
- 05000266/LER-1997-038, :on 970926,determined That Inoperability of Standby Emergency Power Placed Unit 2 in 7-day Lco.Caused by Failure That Occurred When EDG G-03 Was Shutdown.Repaired Governor & Returned EDG G-03 to Service (← links)
- 05000266/LER-1996-016, :on 961030,discovered as-found Lift Pressure for Unit 2 Pressurizer Safety Valve 2RC-434 Exceeded Max Lift Pressure Allowed by ASME Code.Caused by Use of Ambient Temp in Test Lab.Set Valve at More Appropriate Ambient Temp (← links)
- 05000266/LER-1998-011, :on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed (← links)
- 05000266/LER-1997-043-01, Forwards LER 97-043-01,re Discovery That TS Surveillance of Reactor Trip Sys Interlocks Were Not Adequate. Supplemental Info Is Provided at End of Rept.Previous Commitments Made within Rept Also Encl (← links)
- 05000266/LER-1997-036, :on 970826,potential Common Mode Failure in DC Power Supply Which Could Disable AFW Sys Was Noted.Caused by Inadequate Design & Design Review.Plant Mods Were Performed to Eliminate Potential Common Mode Failure (← links)
- 05000266/LER-1999-007, :on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier (← links)
- 05000266/LER-1987-002, :on 870409,as Found Containment Integrated Leak Rate Determined to Exceed Allowable Tech Spec Limit.Caused by Packing Failure of One Valve.Valve Replaced & Successfully Tested as Part of Leak Rate Test (← links)
- 05000266/LER-1987-001-01, :on 870404,unit Manually Tripped After 22 Control Rods Dropped.Reactor Engineer Incorrectly Connected Leads Shorting Out Test Instrument.Mods to Test Equipment to Prevent Hookup Errors Evaluated (← links)
- 05000266/LER-1986-005-01, :on 861117,reactor Tripped Due to Loss of Power on Red Instrument Bus.Caused by Failure of Control Circuit Diode in Bus Inverter.Diodes Replaced (← links)
- 05000266/LER-1987-003, :on 870424,check Valve for Nitrogen Inlet to Reactor Coolant Drain Tank Vent Header Leak Rate Exceeded Containment Leak Rate Allowed.Caused by Foreign Matl in Nitrogen Piping.Valve Will Be Removed from Svc (← links)
- 05000266/LER-1997-020-01, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected (← links)
- 05000266/LER-1999-004-01, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer P (← links)
- 05000266/LER-1997-037, :on 970903,potential Failure of EDG Load Sequence Occurred.Caused by Inadequate Design of EDG Load Sequencing Logic.Mod Restored Operability of EDG During Load Sequencing (← links)
- 05000266/LER-1999-006, :on 990720,discovered That Fire Could Be Postulated in Central Area of 26 Foot Elevation of Pab.No Specific Cause Identified.Hourly Fire Rounds Being Performed in 26 Foot Pab Central Area & Procedure AOP 10A Revised (← links)
- 05000266/LER-1997-035, :on 970516,discovered Inadequate Seismic Support for Reactor Coolant Pump Rotor Stand.Caused by Rotor Stand Being Stored Since Initial Plant Construction.Moved Rotor Stand & Verified as Seismically Adequate (← links)
- 05000266/LER-1986-006-01, :on 861128,while Unit Operating at 100% Power, 2.5 Turbine Runback to 95% Power Experienced.Caused by Momentary Loss of Power on White Instrument Bus While Normal Power Supply Inverter Transferred to Spare (← links)
- 05000266/LER-1998-028, :on 981113,surveillances Required by Section XI Pressure Test Program Were Missed.Caused by Failure to Take Timely Action on & Implement Corrective Actions for ASME Program Problems.Completed 40 Month Pressure Test (← links)
- 05000266/LER-1999-003, :on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With (← links)
- 05000266/LER-1986-002, :on 860417,during Type C Leak Rate Test,Reactor Coolant Pump Component Cooling Water Supply Line Check Valve Rate Exceeded Tech Spec Limits.Caused by Sticking Valve Disc.Valve Repaired & Retested Satisfactorily (← links)
- 05000266/LER-1999-001-01, Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italic (← links)
- 05000266/LER-1998-006, :on 980122,unanticipated Partial Svc Water Sys Isolation During Special Test Occurred.Caused by Inadequate Test Procedure.Procedure PBTP-77 Will Be Archived W/ Documentation of Deficiencies (← links)
- 05000266/LER-1998-007, :on 980123,determined That Relay Installed in 1P-29 turbine-driven Auxiliary Fdw Pump Low Suction Pressure Trip Circuitry Possessed Incomplete Solder Connection.Caused by Incomplete Solder Connection.Circuitry Replaced (← links)
- 05000266/LER-1998-005, :on 980121,discovered That Control Rod Exercise Test Required Tech Specs Had Not Been Performed as Required. Caused Data Entry Error Into Computerized Maint Planning. Maint Planning Sys Revised (← links)
- 05000266/LER-1997-042, :on 971030,discovered That Upper Containment Personnel Air Interlock Had Been Inoperable.Caused by Removal of Remote Operating Gear.Reinstalled Remote Operating Connector Gear (← links)
- 05000266/LER-1998-004, :on 980114,RCP LO Collection Sys Design Did Not Comply W/App R Section III.0.Caused by Design Mod Conducted in 1981-82 Did Not Rigorously Document Design Basis of Locs. Minor Maint & Matl Repairs Were Initiated & Are Complete (← links)
- 05000266/LER-1998-029, :on 981227,discovered That Automatic Start Feature for Train B Svc Water Pumps Was Not Functional. Caused by Failure to Recognize Full Significance of Deenergizing Safeguards Relay Racks.Equipment Reenergized (← links)
- 05000266/LER-1998-002, :on 980108,failure of High Voltage Station Auxiliary Transformer Occurred Due to Ground in Low Voltage Side Bus Duct.Operability of 1X03 Was Restored & Verified to Be in Operation by Infrared Scan (← links)
- 05000266/LER-1998-001, :on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements (← links)
- 05000266/LER-1997-041, :on 971023,potential Common Mode Failure in Afws Control Circuits Was Noted.Caused by AFW Control Circuits Installed by Plant Mods.Temporary Mods Will Restore Physical Separation for Cables (← links)
- 05000266/LER-1997-040-01, Forwards LER 97-040-01 Which Documents Event That Occurred at Point Beach Nuclear Plant,Unit 1.Commitments Made within Ltr,Encl (← links)
- 05000266/LER-1997-039-01, :on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored (← links)
- 05000266/LER-1997-044, :on 971216,use of Dedicated Operators During IST of Containment Spray Sys Constituted Operation Prohibited by Ts.Caused by Improper Consideration for Use of Dedicated Operators.Revised Procedures (← links)
- 05000266/LER-1998-030, :on 981124,determined That Safety Related Battery Charges Should Be Reclassified as Hot Shutdown Equipment.Caused by Incorrect Assumption.Mod Will Be Installed to Provide Manual Switches (← links)
- 05000266/LER-1997-034, :on 970707,discovered Unplanned Loss of Voltage on Train B Safeguards Buses.Caused by Inadequate Design & Design Review for Installation of New Train B Edgs.Incorrect Wiring Reworked (← links)
- 05000266/LER-1985-002-01, Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept (← links)
- 05000266/LER-1999-001-02, Forwards LER 99-001-02 Re SI Recirculation Flow Line to RWST Frozen,Providing Rev to Internal Flooding Evaluation Discussed Safety Assessment Section of Encl Rept (← links)
- 05000266/LER-1988-001, :on 880110,potential Single Failure Discovered in 4,160 Volt Safeguards Switchgear.Caused by Design Error. Temporary Mod for Cell Switch Installed.Permanent Mod to Eliminate Single Failure Mod Being Designed (← links)
- 05000266/LER-1999-005, :on 990514,steam Leak from Low Pressure FW Heater Was Noted.Caused by Rupture & Walls Thinnings Which Accelerated Corrosion.Repaired FW Heaters (← links)
- 05000266/LER-1998-027, :on 981013,inadequate TS Surveillance Testing of non-essential Svc Water Isolation Logic,Was Identified. Caused by Failure of Existing Test Procedure to Adequately Consider All Postulated Failure Modes.Procedures Changed (← links)
- 05000266/LER-1988-005, :on 880518,Tech Specs Violated.Caused by Exclusion of Placing Delta T Channels in Trip During Calibr of Power Range Nuclear Instrumentation Channel in Procedure. Procedures Revised (← links)
- 05000266/LER-1998-026, :on 980914,determined That Operation of Potential Dilution in Progress Alarm Was Not Controlled IAW Ts.Caused by Failure to Address Plant Heatup Procedures. Revised Procedure OP-1A, Cold Shutdown to Hot Shutdown (← links)
- 05000266/LER-1998-003-01, Forwards LER 98-003-01 Re Discovery That Flow Rates Were Outside Design Basis of Plant.Rept Revises Corrective Action Commitment Re Replacement of SW Piping to Unit 2 Fan Cooler Motor Heat Exchangers (← links)
- 05000266/LER-1988-007, :on 880819,suspected Safety Injection (SI) Block Circuitry Design Deficiency Revealed Potential SI Inoperability.Design Changed to Separate SI Block by Train & Installation Planned on Next Refueling Outage (← links)
- 05000266/LER-1988-004, :on 880415,two Valves Exceeded Leak Rate Allowed by Tech Specs 15.4.4.II.B & Iii.B.Caused by Rust Particles on Valve Seat.Valve 755A Failure Operational in Nature.Valve 755A Replaced.Valve 528 Cleaned (← links)
- 05000266/LER-1997-032, :on 970630,discovered Inadequately Rated Electrical Buses Could Disable Switchgear & Cause Secondary Fires.Caused by Characteristic of Original Design. Established twice-per-shift Fire Watches (← links)
- 05000266/LER-1997-031, :on 970619,discovered That Auxiliary Feedwater (AFW) Pump Low Suction Pressure Trip Setpoints May Not Ensure Adequate Suction Pressure Protection for AFW Pumps Following Tornado Event.Caused by Inadequate Design (← links)
- 05000266/LER-1997-027, :on 970521,non-environmentally Qualified Matl Existed in Containment Hatch Applications.Caused by Inadequate Design Review.Mods Will Be Performed to Remove Existing Teflon Material (← links)
- 05000266/LER-1997-025, :on 970520,pressurizer Level Was Controlled Higher than Assumed in Accident Analysis.Caused by Inappropriately Changing Procedures W/O Adequate Consideration.Listed Affected Procedures Will Be Revised (← links)
- 05000266/LER-1988-002, :on 880219,discovered That Electric Strikes Which Lock Fire Doors Fail Open Upon Loss of Power.Caused by Design Deficiency.Fire Watches Posted & Doors Modified to Fail in Latched Position Upon Failure of Power (← links)
- 05000266/LER-1997-017, :on 920508,containment Third Door Was Blocked Open During Refueling Operations.Caused by Interpretation That Movement of Core Components Per TS Definitions Rather than Literal Wording.Routine Maintenance Procedure Revised (← links)
- 05000266/LER-1997-019, :on 970404,RHR Not Aligned IAW TS Requirements. Caused by non-conservative Decision Making & Not Recognizing When TS Were Not Controlling Plant Operations.Pbnp Mgt Philosophy Re TS Interpretations Changed to Minimize Use (← links)
- 05000266/LER-1997-010, :on 970219,svc Water & Component Cooling Water TS Action Requirements Were Not Met.Caused Because Licensee Did Not Comply W/Cold Shutdown Requirements of TS 15.3.3.C.2 & 15.3.3.D.2.Evaluations Were Performed (← links)
- 05000266/LER-1997-009, :on 970214,potential for Safety Injection Failure During Filling of Safety Injection Accumulator Discovered.Caused by Situation Not Adequately Covered by Procedures.Procedure OI-100 Revised (← links)
- 05000266/LER-1978-073-03, /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures (← links)
- 05000266/LER-1997-026, :on 970521,discovered TS Violation of Operability Requirement of MSL Isolation.Caused by Inadequate Consideration for Operability of All Required Functions.Verified Low RCS Sys Average Temp (← links)
- 05000266/LER-1997-018, :on 970403,potential for RHR Overpressure During Accidents Was Discovered.Original Design Did Not Provide Overpressure Protection for Isolated Piping Section. Evaluation Was Performed to Determine Stress on Piping (← links)
- 05000266/LER-1997-024, :on 970501,determined Post Accident Sampling Sys Degradation.Caused by Inadequate Design Review.Will Upgrade Containment Atmosphere Sample Sys & Will Perform Mod to Reduce Dose within GDC 19 Dose Limits (← links)
- 05000266/LER-1997-022, :on 970507,discovered That Postulated Control Room Fire May Cause Electrical Hot Short That Disables Limit or Torque Switches for Certain Movs.Mods Initiated to Remedy Condition (← links)
- 05000266/LER-1997-023, :on 970508,discovered Noncompliant Emergency Lighting for Postulated App R Fires.Caused by Alternative Provisions Made in Original Safe Shutdown Analysis.Emergency Lights Will Be Installed (← links)
- 05000266/LER-1985-010, :on 851220,during Full power,20% Turbine Runback Experienced.Caused by Failure of Isolation Transformer of 1DY04 Yellow Instrument Bus,Channel 44.Bus Connected to Alternate Power Source (← links)
- 05000266/LER-1986-001, :on 860102,during Full power,20% Turbine Runback Experienced.Caused by Voltage Spike in Channel 44 of Power Range Instrumentation Sys Due to Faulty 25-volt Power Supply.Power Supply Replaced (← links)
- 05000266/LER-1997-011, :on 970305,containment Fan Cooler Accident Fans Were Not Tested in Accordance with Tss.Caused by non-conservative Interpretation of Literal Requirements of Tss.Unit 1 & 2 Accident Fans Were Tested (← links)
- 05000266/LER-1997-013, :on 970304,CCWS Found Not in Accordance W/ Plant Design Basis.Caused by Inoperable Valve Due to Overtorquing in Closed position.Cross-tie Will Be Resolved (← links)
- 05000266/LER-1997-013-01, Forwards Suppl LER 97-013-01,re Component Cooling Water Sys Not IAW Plant Design Basis.Rept Replaces LER 97-013-00 in Its Entirety & Includes Addl Similar Occurrence Not Previously Reported to NRC (← links)
- 05000266/LER-1997-021, :on 970430,determined That Spent Fuel Pool Cooling Sys Was Not in Accordance W/Plant Design Basis.Cause Indeterminate.Closed & re-tagged Valves SF-27 & SF-28 & Investigated Basis for Fsar,App a (← links)
- 05000266/LER-1985-009, :on 851009,turbine Runback Occurred Due to Rod Drop Signal on Power Range Nuclear Instrumentation Sys. Caused by Technician Introducing Signal During Calibr of Negative Rate Runback Setpoint (← links)
- 05000266/LER-1997-006, :on 970120,refueling Cavity Drain Failed During Loca.Caused by Inadequate Evaluation of Original Design.Design of Refueling Cavity Drains Was Revised with Respect Capability to Withstand an Earthquake (← links)
- 05000266/LER-1985-007, :on 850911,turbine Runback from 100 to 80% Power Noted.Caused by Momentary Interruption of Power to Instrumentation Bus Inverter.Unit Returned to 100% & Conduit Packing Process Stopped (← links)
- 05000266/LER-1997-015, :on 970324,control Room Ventilation Sys Declared Inoperable Due to Failures of Backdraft Damper & Vent Duct Access Door.Backdraft Damper,Replaced (← links)
- 05000266/LER-1997-016, :on 970325,SG Level Logic Was Not Tested IAW Ts.Caused by Nonconservative Interpretation of Tss.Ts Amends Proposed to Provide Consistency Between Test Requirements & LCO Associated W/Sg Tests (← links)
- 05000266/LER-1997-014, :on 970321,auxiliary Feedwater Sys Inoperability Due to Loss of Instrument Air.Design Mods Initiated,Providing Pneumatic Supply to Control Valves (← links)
- 05000266/LER-1997-012, :on 970304,diesel-drive Fire Pump Day Tank Not Sampled IAW TSs.Non-conservative Interpretation of TS Led to Failure.Day Tank T-30 Sample Was Drawn & Analyzed W/Satisfactory Results (← links)
- 05000266/LER-1997-008, :on 970131,non-seismic Ductwork Located Above safety-related Equipment in Containment Occurred.Caused by Incomplete Seismic Evaluation.Mods Will Be Completed During Current Unit 2 Refueling Outage (← links)
- 05000266/LER-1997-007, :on 970124,determined That Potential Existed for EDG Overload Condition.Caused by Failure to Recognize This Condition When Plants Initially Licensed W/Two Edgs. Implemented Procedure Changes (← links)
- 05000266/LER-1997-005, :on 970116,1SI-852A Was Not Tested IAW Inservice Test Program Required by Tss.Caused Because Condition Revealed That Valve 1SI-852A Had Not Been Completely Tested.Tests Will Be Reviewed (← links)
- 05000266/LER-1985-005, :on 850726,during QA Audit of Spent Fuel Pool Records,Three Spent Fuel Assemblies Subcritical for Less than 1 Yr Stored Next to East Spent Fuel Pool Wall.Gamma Heating Effects Calculations Performed (← links)
- 05000266/LER-1997-004, :on 970113,potential for Particular Common Mode Failure That Could Affect Opposite Trains of Unit 2 Safeguards Equipment Was Noted.Caused by Lack of Physical Separation.Replaced Subject Circuit Breakers (← links)
- 05000266/LER-1985-004, :on 850725,diesel Generators auto-started After Loss of Low Voltage Station Transformer 1X04.Caused by Power Failure Due to Lockout of Low Voltage Station Transformer 1X04.Transformer Returned to Svc (← links)
- 05000266/LER-1997-003, :on 970109,did Not Perform Leak Test on Spare Containment Penetrations Per Ts.Caused by Lack of Routine Testing.Tested Penetrations W/Satisfactory Results (← links)
- 05000266/LER-1997-002, :on 970109,potential to Overpressurize Piping Between Containment Isolation Valves Occurred.Caused by Original Design Not Providing Overpressure Protection for Piping.Review Completed (← links)
- 05000266/LER-1997-001, :on 970108,safety Injection Delay Times Exceeded Design Basis Values.Caused by Degraded Voltage Conditions.Licensee Engineers Will Prepare FSAR Change Requests to Reflect LBLOCA Evaluation (← links)
- 05000266/LER-1996-015, :on 961231,main Steam Safety Valve Lift Setpoints Exceeded Design Basis Values.Caused by Lack of Margin Provided in Original Analysis.Ist Safety & Relief Valves Will Be Reviewed (← links)
- 05000266/LER-1985-008, :on 851002,loss of Containment Integrity Occurred When Inner Hatch Door Opened While Outer Door of Upper Personnel Hatch Open.Caused by Bent Shafts Supporting Interlock Cams.Doors Chained & Locked (← links)
- 05000266/LER-1996-014, :on 961229,failed to Obtain SG Blowdown Sample. Caused by Personnel Error.Sampled & Analyzed SG Blowdown Filter on 961229 (← links)
- 05000266/LER-1996-013, :on 961212,potential Common Mode Failure in 120 Vac Instrument Power Supplies Occurred.Caused by Design of 1982 Mods Did Not Recognize Postulated Failure Mechanism. Supplies Will Be Converted to Permanent Mods (← links)
- 05000266/LER-1985-003, :on 850626,reactor Tripped from 88% Power Due to Failure of Inverter for White Instrument Bus.Caused by Failure of Integrated Circuit.Circuits Replaced (← links)
- 05000266/LER-1985-006, :on 850903,turbine Runback Occurred.Caused by Voltage Spike on Red Instrument Bus,Resulting in Momentary Downward Spike on Nuclear Instrumentation Sys.Red Inverter Inspected & Returned to Svc.All Sys Normal (← links)
- 05000266/LER-1996-012, :on 961205,failed to Perform EDG Fuel Oil Tests.Caused by non-conservative Interpretation of Tss. Successfully Tested Fuel Oil & Revised TS Tests TS-81,TS-82, TS-83 & TS-84 (← links)
- 05000266/LER-1996-011, :on 961121,Delta T Trip Setpoint Were Not Reduced in Accordance with Ts.Caused by Less than Adequate Plant Ts.Tscr Has Been Submitted to Correct This Discrepancy (← links)
- 05000266/LER-1996-010, :on 961112,EDG Governor Failure Was Noted. Caused by Dislodging of Spring Clip in Synchronizer Indicator Assembly.Spring Clip Was Replaced W/Spare & EDG & Governor Were Tested,Per RMP-110B & TS-81 (← links)
- 05000266/LER-1996-008, :on 960806,inner Doors of Unit 1 Containment Upper Hatch Failed an Airlock Door Seal Test.Caused by Failure to Comply with Procedures TS-10A & TS-10A,App B. Containment Upper Hatch Repair Completed (← links)
- 05000266/LER-1996-009, :on 960912,discovered CCW Sys Does Not Conform W/Currently Applicable Design Basis for Closed Sys.Caused by Inadequate Design/Design Review.Valves CC-732A,732D & 732F Closed to Isolate Portion of Sys (← links)
- 05000266/LER-1985-001, :on 850405,during Refueling Shutdown W/Plant Proceeding Toward Cold Shutdown,Pressure on Steam Line a Decreased Causing Actuation of Safety Injection.Caused by Inadequate Precautions in Procedure OP-3C (← links)
- 05000266/LER-1992-010, :on 921208,discovered That Inservice Tests IT-40 & IT-45 Re SI Valves (Quarterly) Could Lead to Isolation of All Available Flow Paths for SI Pumps.Pra Performed.Issue Also Reported Per Part 21 (← links)
- 05000266/LER-1983-005-03, /03L-0:on 830628,control Operator Discovered 1PORV-430 Had No Position Indication on Main Control Board Due to Open Molded Circuit Breaker.Cause Unknown.Breaker Closed & Indication to 1PORV-430 Restored (← links)
- 05000266/LER-1983-002-01, /01T-0:on 830308,emergency Diesel 3D Failed to Start During Testing.On 830309,diesel Declared out-of-svc, Then Successfully Started.Caused by Faulty Type UG8 Woodward Governor.Procedures Revised Pending Replacement (← links)
- 05000266/LER-1992-007, :on 920818,RPS Engineered Safeguards Sys & Process Instrumentation within Cabinets Declared Inoperable. Caused by Friction Clip Assemblies Loaded Beyond Yield Point.Cabinet Bolting Upgraded (← links)
- 05000266/LER-1996-004, :on 960731,operation of Svc Water Sys Was Outside Design Basis.Caused by Deficient Original SW Sys Analysis.Operating Restrictions Were Established to Ensure Adequate SW Pump Availability (← links)
- 05000266/LER-1996-007, :on 960814,discovered Several Instances Where Physical Separation of Redundant SR Circuits Inside Mcb Not Provided.Caused by Lack of Written Criteria for Separation of Wiring.Circuit Breakers Were Replaced (← links)
- 05000266/LER-1996-006, :on 960813,emergency Power Out of Service Coincident with Opposite Train SW Pump.Root Cause Evaluation Being Performed.C/As Will Be Determined as Necessary from Results of Root Cause Evaluation (← links)
- 05000266/LER-1996-002, :on 960422,determined That steam-driven AFW Valves Were Shut.Caused by Poor Communication.Crew Discussion Re Valve Misoperation Occurred & Test Procedures Reviewed (← links)
- 05000266/LER-1996-005, :on 960801,determined Containment Fan Coolers Susceptible to SW Flashing.Caused by Original Design Not Analyzed for Transient Conditions Described.Util to Submit Formal Evaluation Re Plan for Mods to SW Sys (← links)
- 05000266/LER-1992-009, :on 921012,identified That CCW Sys Surge Tank Vent Valves 1&2cc-00017 Did Not Meet Design Basis.Caused by Oversight During Original Design of CCW Sys.Design Will Be Evaluated & Modified If Necessary (← links)
- 05000266/LER-1992-004, :on 920515,improper Sequencing of Emergency Safety Features Occurred.Caused by Faulty Relay for 1-W1B1.Time Delay Relay Replaced & Adjusted to within Acceptance Criteria (← links)
- 05000266/LER-1992-004-01, :on 920515,discovered Improper Sequencing of Esf.Caused by Failure to Identify Need for Acceptance Criteria for Shared Components.Test Procedure ORT-3 Revised (← links)
- 05000266/LER-1996-003, :on 960621,discovered Plant Operation Outside of Design Basis.Caused by Inadequate Analysis Re Determination of Original TS Parameters.Revised Procedure OP-3C & OP-1A Re Cold Shutdowns (← links)
- 05000266/LER-1992-006, :on 920531,SG a MSIV IMS-2018 Failed to Fully Close During Initial Test.Caused by Galling on Both Ends of Valve Shaft Due to Mispositioning of Gaskets.Msiv Instructions Will Be Updated & Revised (← links)
- 05000266/LER-1992-005, :on 920527,during Performance of Refueling Procedure Temp cool-down Limit Was Exeeded Per Ts.Caused by Personnel Error.Need to Perform SG Crevice Flushing in Future Will Be Assessed (← links)
- 05000266/LER-1996-001, :on 960405,inadvertent ESF Actuation in Train B Due to DC Sys Ground Occurred.Caused by Inadequate Ground Search Technique.Site Engineering Personnel Will Be Involved in Ground Detection Needed on DC Sys (← links)
- 05000266/LER-1992-008-01, :on 921005,automatic Turbine Trip & Reactor Trip Occurred.Caused by B Train Solenoid Vent Valve Being Open.Thorough Review of PC-11,Part 2 Performed.Vent Valve Replaced & Retested Satisfactorily (← links)
- 05000266/LER-1984-005, :on 840831,during Review of Reload Transition Rept,Engineer Noted Subcritical Uncontrolled Rod Cluster Control Assembly Withdrawal Accident Assumed Operation of One Reactor Coolant Pump in Basis of Analysis (← links)
- 05000266/LER-1992-003-01, :on 920428,EDG G01 Automatically Started When Potential Transformer for Supplied Bus Deenergized.Caused by Personnel Error.Addl Loads on Bus 1B04 Secured & Isolated & Buses 1B03 & 1B04 Reenergized (← links)
- 05000266/LER-1984-003-01, :on 840721,high Neutron Flux Generated by Source Range Instrumentation Channel 32,activating Reactor Protection Sys.Caused by Detector Malfunction After Source Range Intruments Energized When Unblocked (← links)
- 05000266/LER-1984-004, :on 840721,inadvertent Actuation of Reactor Protection Sys Occurred on Low Pressurizer Pressure.Caused by Interlock Circuit P7 Deenergized Due to Maint Work.Maint Work Procedure Under Review (← links)
- 05000266/LER-1991-015, :on 911128, a SG Main Steam Isolation Bypass Valve Was Left Open.Caused by Procedural Inadequacy W/ Inservice Test IT-280.Valve Was Immediately Shut (← links)
- 05000266/LER-1992-001, :on 920120,automatic Runback of Unit 1 Turbine Occurred.Caused by Improper Installation of Interlock Jumper by Two Personnel Performing post-maint Testing.Electricians Counseled (← links)
- 05000266/LER-1991-014, :on 911103,20% Runback of Turbine Generator Occurred.Caused by Output Transient on power-range Nuclear Instrumentation Channel N44.On 911105,voltage Spike Occurred.Power Supply Replaced (← links)
- 05000266/LER-1990-002-02, :on 910419,degradation of Steam Generators Tubes Occurred.Cause Unknown.Util Will Monitor Tube Integrity in Each Steam Generator & Plug Tubes Which Exceed or Approach Plugging Limit in Tech Spec (← links)
- 05000266/LER-1991-002, :on 910419,degradation of Steam Generator Tubes Occurred After Inservice Exam.Caused by Defective Tube. Tube Integrity in Each Steam Generator Monitored & Tubes That Exceed TS Limits Plugged (← links)
- 05000266/LER-1984-002, :on 840228,licensee Notified by Swri That One Indication in Each Outlet Nozzle Weld Exceeded ASME Code Allowable Size.Caused by Entrapped Foreign Matl in Weld. Requirements of ASME Section XI Satisfied (← links)
- 05000266/LER-1984-001-01, :on 840225,visual Insp of Control Rod Guide Tube Split Pins Revealed Three Nuts Missing.Caused by Stress Corrosion Cracking Due to Heat Treatment Temp.Pins Will Be Replaced at Future Outage (← links)
- 05000266/LER-1950-266-75, /75-4:on 750226,primary to Secondary Tube Failure Occurred in Steam Generator B & Went from Initial Point Leak to Max of 125 Gallons Per Minute.Extent of Incident & Radioactivity Below Point to Initiate Evacuation (← links)
- 05000266/LER-1991-012, :on 910924,turbine Runback Experienced from 100% to 80% Power During Maint on Inverter Dyod,Resulting in Voltage Spike on Dc Supply Bus to Inverter.Caused by Blown Fuse.Maint Work Request Issued (← links)
- 05000266/LER-1991-013, :on 911003,nuclear Instrumentation Turbine Runback Occurred.Caused by Positive Voltage Spike on Output of Detectors a & B of Channel N44.Detectors Replaced.W/ (← links)
- 05000266/LER-1991-011, :on 910906,turbine Runback from 100% to 80% Power Experienced During Reactor Protection Sys Logic Testing of power-range High Setpoint.Caused by Spurious Output Voltage Transient.Procedure Changed (← links)
- 05000266/LER-1991-009, :on 910727,runback of Unit 1 Turbine Generator Discovered Initiated.Cause Unknown.Flux Maps Monitored for Quadrant Power Tilt & Core Flux Mapping Initiated (← links)
- 05000266/LER-1983-009-01, /01T-0:on 831001,Type B & C Leakage Tests Performed During Outage & Total as-found Leakage Exceeded Tech Spec Limits.Caused by Foreign Matl on Valve Seating Surfaces.Valves Cleaned & Retested (← links)
- 05000266/LER-1995-005, :on 950416,CR Personnel Initiated Manual Reactor Trip When CR E11 Dropped Part Way Into Core During Troubleshooting Activities.Caused by Failed Stationary Gripper Coil.Coil Fuse Replaced (← links)
- 05000266/LER-1991-010, :on 910816,determined That Four Hydrogen Monitor Channels,Powered from White Instrument Bus, Contained Default Calibr Parameters.On 910629,white Instrument Bus Lost.Mod Initiated (← links)
- 05000266/LER-1995-004, :on 950328,loss of Voltage Relays Not Calibr to TS Limits.Caused by Review of Setpoint Changes from Temporary Values to Permanent Was Less than Adequate.Ts 15.3.0 Was Entered at 0703 (← links)
- 05000266/LER-1995-003-01, :on 950325,inadvertent EDG Start.Caused by Error Made by Test Engineer.Edg Was Shutdown & Restored to Normal stand-by Mode (← links)
- 05000266/LER-1983-011-03, /03L-0:on 831027,w/unit in Cold Shutdown,Insp of 4,160-volt Ac Breaker for Safety Injection Pump 1P15B Revealed Loose Wire in Lockout Relay Circuit 86.W/circuit Open,Electrical Protection Disabled (← links)
- 05000266/LER-1995-002-01, :on 950313,undervoltage Relays Inadvertently Actuated During Mod Work Re Installation of Addl Edgs.Caused by Loose Wire Pulled Out of Wire Lug.Wire Relugged & Relanded (← links)
- 05000266/LER-1995-001, :on 950228,unusual Event Declared & Load Decrease Commenced as Loss of DC Control Power Occurred in Two Accident Fan Coolers.Caused by Short Circuit.Affected Bulb,Socket & Fuses Replaced (← links)
- 05000266/LER-1983-010-03, /03L-0:on 830929,acceptance Test of Fire Detection Sys Found Remote Alarm Function Disabled for Fire Detectors in Auxiliary Feedwater Pump,Vital Switchgear & Cable Spreading Rooms.Caused by Wiring Work (← links)
- 05000266/LER-1983-007-01, /01T-0:on 830802,containment Isolation Valve 1CV-3200C in Suction Line of Containment Radioactive Gas & Particulate Monitoring Sys Failed to Close.Caused by Failure of Solenoid Valve to Cycle (← links)
- 05000266/LER-1982-025-03, /03L-0:on 821117,while Reviewing Test Data,Two 480-volt Safeguards Undervoltage Relays Found Not Meeting 0 Volt Time Delay Spec.Relays Adjusted to within Spec & Returned to Svc (← links)
- 05000266/LER-1982-024-03, /03L-0:on 821116,during Review of Test Data,Steam Flow Transmitter FT-465 Discovered 0.177% Nonconservative. Caused by Nonconservative Static Zero Shift.Instrument Recalibr (← links)
- 05000266/LER-1991-008, :on 910629,automatic Reactor Trip Occurred on Unit 1.Caused by Loss of Power from 1-DY03 White Inverter. Corrective Action Includes Installation of Static Transfer Switches in the Event That Inverter Fails (← links)
- 05000266/LER-1991-007, :on 910626,fire Barrier Penetration Seal Discovered Inoperable.Caused by Personnel Error.Fire Watch Stationed & Maintained in Affected Area Until Both Barriers Restored (← links)
- 05000266/LER-1991-006, :on 910615,inadvertent Start of EDG Occurred. Caused When Operator Opening Generator Annunciator Panel. Tech Spec Test TS-1 Initiated Determining Operability of G01 (← links)
- 05000266/LER-1991-005, :on 910530,reactor Trip Occurred Due to Loss of Unit 1 Red Instrument Bus.Caused by Failure of Inverter. Maint Work Request Initiated to Investigate Inverter Failure (← links)
- 05000266/LER-1983-008-01, /01T-0:on 830830,containment Isolation Valve 1CV-3200C in Suction Line of Containment Radioactive Gas & Particulate Monitoring Sys Failed to Close.Caused by 3-way Solenoid Valve Failing to Cycle (← links)
- 05000266/LER-1983-004-03, /03L-0:on 830621,breaker Serving MOV-826B Found Open During Normal Operation & Redundant Valve MOV-826C Not Tested Prior to Disabling MOV-826B.Probably Caused by Personnel Accidentally Opening Breaker (← links)
- 05000266/LER-1991-001, :on 910405,loss of off-site Power to Both Units Resulted in Loss of Normal Feedwater.Cause Unknown. Operators Resolved Conditions Which Resulted in Design Inadequacy (← links)
- 05000266/LER-1994-011, :on 941004,discovered That on 940409 Redundant DHR Requirements Not Met During Refueling Outage Due to Inadequate Communication to Operators Re Interpretation of TS 15.3.1.A.3.b.Both RHR Pumps Secured (← links)
- 05000266/LER-1994-010, :on 940927,inadvertent EDGs Start,Loss of Two Station Battery Chargers & Unit 2 Loss of DHR Occurred When Control Operator Operating Gas Turbine Incorrectly Manipulated Controls.Subj Equipment Restored (← links)
- 05000266/LER-1983-006-03, /03L-0:on 830711,during Normal Operation,Min Frequency Requirements Dictating Measurement of Boron Concentration in Boric Acid & Refueling Water Storage Tanks Exceeded.Caused by Personnel Error (← links)
- 05000266/LER-1994-008, :on 940812,discovered That Containment Integrity Requirements Not Satisfied During Valve Testing. Root Cause Evaluation Initiated & Procedures IT-40,IT-40A, IT-45 & IT-45A Revised (← links)
- 05000266/LER-1994-007, :on 940713,discovered That Containment Integrity Requirements Not Satisfied During Low Head SI Suction Valves Testing Due to Procedural Deficiency. Applicable IST Procedures Will Be Revised (← links)
- 05000266/LER-1982-012-03, /03L-0:on 820621,during Annual Diesel Insp, Emergency Diesel Generator 3D Output Breaker Failed to Close.Caused by Broken Latch Check Switch.Switch Replaced (← links)
- 05000266/LER-1983-001-03, /03L-0:on 830104,during Normal Operation,Panel D-400 Became Inoperable.Caused by Failed Power Supply.Power Supply Replaced W/Upgraded Components (← links)
- 05000266/LER-1994-006, :on 940620,Halon Sys Declared Inoperable Due to Incorrect Operability Determination Following Spurious Halon Actuation on 940618.Caused by Nitrogen Leakage.Turbine Bldg Shift Log Will Be Revised (← links)
- 05000266/LER-1982-021-03, /03L-0:on 821102,during Installation of New Fire Protection Equipment,Fire Detectors Were de-energized.Caused by Misunderstanding Between Plant & Contractor Personnel.New Detectors Installed & Tested Satisfactorily (← links)
- 05000266/LER-1982-016-01, /01T-0:on 821002,containment Isolation Valve 1CV-3200C in Suction Line of Radioactive Gas & Particulate Monitoring Sys Failed to Close.Caused by Failure of 3-way Solenoid Valve to Cycle.Valve Closed & Repaired (← links)
- 05000266/LER-1982-015-03, /03L-0:on 820914,fluid Level in Gas Stripper Noted Decreasing Abnormally After Stripper Returned to Svc Following Maint.Caused by High Stress Low Cycle Failure of Lap Joint Flange Stub Piece.Lap Joint Flange Replaced (← links)
- 05000266/LER-1994-005, :on 940509,determined That Unit 1 Reactor Cavity Cooling Fans in Condition Potentially Outside Design Basis Due to Failure to Install Cooling Fan Assemblies. Assemblies Installed,Per Mod Request 94-032 (← links)
- 05000266/LER-1994-004, :on 940427,unexpected Automatic Trip of Reactor Occurred During Hot Control Rod Drop Testing Due to Inadequate Work Control.Human Performance Root Cause Evaluation 94-016 Being Conducted on Event (← links)
- 05000266/LER-1982-018-01, /01T-0:on 821015,while Attempting to Shift Yellow Instrument Bus to Alternate Supply,Bus de-energized & Turbine Runback Occurred.Caused by Shifting Wrong Bus Power Supply Due to Misunderstanding.Warning Signs Posted (← links)
- 05000266/LER-1994-003, :on 940217,reactor Coolant Sys Sample Line Declared Inoperable & Isolated.Caused by Failure of SC-955 as Result of Loss of Coolant Accident.Penetration P-28a on Units Isolated (← links)
- 05000266/LER-1994-002, :on 940208,both EDG G02 Train B EDG Voluntarily Removed from Svc for Annual Maint.Caused by Power Fluctuations.Damaged Bus Bar & Jumper Wire Replaced (← links)
- 05000266/LER-1982-030-03, /03L-0:on 821217,safety-related Snubber Located on Steam Generator A,Main Steam Line,Found Leaking Oil Past Shaft Seal.Caused by Damaged Shaft Seal O Ring.New Shaft Seal Kit Installed & Snubber Tested & Returned to Svc (← links)
- 05000266/LER-1994-001, :on 940208,automatic Actuation Feature of Halon Fire Suppression Sys for Afp Room & Vital Switch Room Disabled.Caused by Personnel Error.Hourly Fire Rounds Performed Until Halon Restored to Svc, (← links)
- 05000266/LER-1978-015-01, /01T-0 on 781009:snubber on Pressurizer Relief Line Was Found Inoperable.Grinnel Model HS-17,21/2 Inch X 5 Inch Bore & Stroke Snubber Failed for Undetermined Cause. Snubber Replaced & Surveillance Prog Expanded (← links)
- 05000266/LER-1978-015, Forwards LER 78-015/01T-0 (← links)
- 05000266/LER-1978-012-01, /01X-0:on 780627,during Visual Insp of Fire Barrier Penetration Seals,Horizontal Seals Found Constructed Differently than Specified.Caused by Change in Const Drawings (← links)
- 05000266/LER-1978-014-01, /01T-0:on 780920,primary-to-secondary Leakage Noted During Normal Operation.Caused by Two Leaking Tubes & One Leaking Plug on Inlet Side of Steam Generator A.Tubes Will Be Plugged & Plug Will Be Weld Repaired (← links)
- 05000266/LER-1990-008, :on 900720,discovered RCS Leakage of Approx 0.27 Gpm.Leakage Through Canopy Seal Weld on Control Rod Drive Mechanism I-3 & Upstream Weld on Steam Generator B. Leaks Repaired by Welding (← links)
- 05000266/LER-1993-009, :on 931202,EDG G02 Declared Inoperable Due to Relay Malfunction in One of Redundant Starting Circuits. Testing & Insp of STLO-2 Relay Ongoing to Improve Understanding of Root Cause of Failure (← links)
- 05000266/LER-1978-016-01, /01T-0 on 781106:turbine Runback Resulted from Safeguards Bus Tie Breaker Trip.Westinghouse Model CV-7 Undervoltage Relay on Tie Breaker Tripped Causing Breaker to Open.No Line Voltage Surges Detected (← links)
- 05000266/LER-1990-010, :on 900816,load Rejection Resulted in Axial Flux Differential Being Outside Prescribed Limits.Caused by Malfunction of Turbine electro-hydraulic Governor Control. Defective Circuit Boards Replaced (← links)
- 05000266/LER-1990-009, :on 900723,reactor Protection Sys Actuation Occurred.Caused by Fuse Failure.Failed Fuse & Fuse in Circuit Replaced (← links)
- 05000266/LER-1990-007, :on 900712,error Indicating Potential for Failure to Comply W/Peak Cladding Temp Acceptance Limit Noted.Caused by Human Error.Util Committed to Reduced Height Dependent Heat Flux Hot Channel Factor Limit (← links)
- 05000266/LER-1993-008, :on 930910,determined SW Valves Inoperable During Surveillance Testing Due to Instrument Air Tubing Improperly Connected to Associated Solenoid Valve.Returned Valve to Svc W/O post-maint Testing (← links)
- 05000266/LER-1990-012, :on 901012,potential Single Failure in B03-B01 & B04-B02 Control Circuits Occurred (← links)
- 05000266/LER-1993-007, :on 930726,inadvertent Emergency Diesel Start & Loss of Station Battery Charger Occurred Due to Blown Fuse During Calibr of 1A-06 Voltmeter.Blown Fuse Replaced & Instructions for Calibr Revised (← links)
- 05000266/LER-1990-006, :on 900619,nuclear Instrumentation Turbine Runback Occurred.Caused by Spurious Signal Believed to Have Been Negative Spike.Voltage Spike Considered Spurious (← links)
- 05000266/LER-1982-007-01, /01T-0:on 820329,during secondary-to-primary Leak Check,Two Leaking Tubes in a Steam Generator & 28 Defective Tubes in a & B Steam Generators Discovered.Caused by Caustic.All Defective & Leaking Tubes Plugged (← links)
- 05000266/LER-1982-010-03, /03L-0:on 820414,ICP 2.9 Found Not to Provide for Proper Unblocking of Source Range High Flux Reactor Trip Over Small Range of Instrument Readings.Caused by Failure to Identify Subtle Procedural Flow.Procedure to Be Revised (← links)
- 05000266/LER-1982-010, Forwards LER 82-010/03L-0 (← links)
- 05000266/LER-1982-011-03, /03L-0:on 820415,during Biweekly Calibr Check ICP 2.1 of Reactor Protective Sys Functions,Overpower Delta T Setpoint 2 for Channel 2 Found Less Conservative than Tech Spec Limit.Caused by Setpoint Drift in Impulse Summer Uni (← links)
- 05000266/LER-1982-011, Forwards LER 82-011/03L-0 (← links)
- 05000266/LER-1982-009-03, /03L-0:on 820408,4.16-kV Safeguards Undervoltage Relays Did Not Meet 0-volt Time Delay Spec.Caused by Manufacturer Characteristic Curves.Relays Not Capable of Less than 0.38-s.Tech Spec Change Requested on 820427 (← links)
- 05000266/LER-1982-008-03, /03L-0:on 820323,minor Installation Defects Noted on Four of Six Containment Pressure Transmitters Installed as TMI Response Mod.Caused by Backfit Contractor QC Program Breakdown (← links)
- 05000266/LER-1982-008, Forwards LER 82-008/03L-0 (← links)
- 05000266/LER-1982-006-01, /01T-0:on 820311,type B & C Valve Leakage Tests Exceeded Tech Spec Limits.Caused by Corrosion.Svc Air Check Valves Disc Replaced & Valve Cover Remachined (← links)
- 05000266/LER-1982-006, Forwards LER 82-006/01T-0 (← links)
- 05000266/LER-1992-003, Comments on Preliminary Draft of NUREG/CR-4674, Precursors to Potential Severe Core Damage Accidents:1992,Status Rept. Section B.14 of Draft NUREG Based on Unit 2 of LER 92-003 (← links)
- 05000266/LER-1993-006, :on 930416,discovered That Outside CIV Not Leak Tested,Per TS 15.4.4.III.D Requirements Due to Review on 840202,recommending That Valve Be Tested During RHR Hydrostatic Testing.Subj Valve Replaced (← links)
- 05000266/LER-1992-009-01, Forwards Suppl LER-92-009-01 Re Ccws Surge Tank Vent Valves Being Outside Design Basis.Rept Provided to Rept Final Corrective Actions to Resolve Condition (← links)
- 05000266/LER-1993-005, :on 930415,containment Accident Fan Time Delay Relay 1-TDR-26 (Turbine Bldg Cooler Svc Water Inlet Valve 1SW-2880) Unexpectedly Closed.Caused by Failure to Recognize Presence of Relay in Contact.Function Changed (← links)
- 05000266/LER-1993-004, :on 930408,employee Found Third Door to Unit 2 Containment Hatch Secured Open.Personnel Ignored Signs to Close Door While Refueling.Door Immediately Shut & Security Posted at Access.Fuel Procedures Modified (← links)
- 05000266/LER-1990-005, :on 900510,steam Generator lo-lo Level Reactor Trip Occurred During Cold Shutdown.Caused by Inadequate Warning Sign Posting.Nonconformance Rept Written to Document Event & Recommend Evaluation (← links)
- 05000266/LER-1990-004, :on 900404,single Failure Potential in Safeguards Switchgear B03/B04 Tie Breaker Discovered & Could Have Resulted in Failure of Diesel Generator.Control Power Fuses for Tie Breakers Removed (← links)
- 05000266/LER-1990-003, :on 900409,determined That Piping & Supports in Fuel Oil Pumphouse Could Not Be Demonstrated to Perform Support Functions.Caused by Design Base Not Sufficiently Documented.Mod Performed to Support Fuel Oil Piping (← links)
- 05000266/LER-1990-002, :on 900402,main Steam Safety Valve 1-MS-2013 Failed to Relieve Setpoint During Tech Spec Testing.Caused by Personnel Error During Setpoint Adjustment.Safety Valves 1-MS-2011,1-MS-2006 & 1-MS-2008 Restored (← links)
- 05000266/LER-1982-005-01, /01T-01:on 820222,poison Test Samples & Two Fuel Assemblies W/Less than 1-yr Cooling Period Found Placed Next to Divider Wall in Spent Fuel Pool.Caused by Tech Spec Misinterpretation (← links)
- 05000266/LER-1982-005, Forwards LER 82-005/01T-0 (← links)
- 05000266/LER-1982-003-01, /01T-0:on 820217,during Surveillance Testing, Emergency Diesel Generator 3D Failed to Operate.Caused by Sticking Shutdown Solenoid Plunger on Woodward Type UG8 Governor.Solenoid Cleaned,Checked & Generator Tested (← links)
- 05000266/LER-1982-003, Forwards LER 82-003/01T-0 (← links)
- 05000266/LER-1982-004-03, /03L-0:on 820206,during Inservice Testing, Differential Pressure Instrument 4007 for Auxiliary Feed Pump P38A Found Isolated.Probably Caused by Failure to Return Instrument to Svc Following Calibr (← links)
- 05000266/LER-1982-004, Forwards LER 82-004/03L-0 (← links)
- 05000266/LER-1982-001-03, /03L-0:on 820107,steam Generator Pressure Sensing Lines Discovered Frozen on a Steam Generator.Caused by Inadequate Freeze Protection & Extremely Cold Weather.Addl Heat Lamps Installed (← links)
- 05000266/LER-1982-001, Forwards LER 82-001/03L-0 (← links)
- 05000266/LER-1982-002-03, /03L-0:on 820112,during Hot shutdown,1PT-469 Steam Generator Pressure Transmitter Isolated by Maint Personnel Due to Leaking Coupling.Pressure Sensing Tubing Showed Signs of Steam Leak Due to Freezing (← links)
- 05000266/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000266/LER-1981-020-03, /03L-0:on 811219,frozen Sensing Line Caused High Indication of Steam Generator Pressure Instrument 1PT-482. Caused by Incomplete Insulation of Line & by Cold Weather. Instrument Placed in Tripped Position & Tubing Thawed (← links)
- 05000266/LER-1981-020, Forwards LER 81-020/03L-0 (← links)
- 05000266/LER-1981-019-01, /01T-0:on 811210,steam Flow Channels FC-464 & FC-465 Found to Be Indicating Zero Flow Following Rephasing. Caused by Improper Zero Setting on Transmitters.Channels Placed in Trip to Provide Safeguard Signals Pending Calibr (← links)
- 05000266/LER-1981-019, Forwards LER 81-019/01T-0 (← links)
- 05000266/LER-1981-014-01, /01T-1:on 811010,while Performing Refueling Leakage Tests of Containment Isolation valves,4-inch Check Valve in Svc Air Supply Found to Have Leakage Exceeding Tech Specs.Caused by Foreign Matl in Internals (← links)
- 05000266/LER-1981-014, Forwards LER 81-014/01T-1 (← links)
- 05000266/LER-1981-004-03, /03L-0:on 810425,during Inservice Testing of Containment Spray Valves (IT-50),Valve 1-860D Failed to Open.Caused by Maladjusted Closing Torque Switch.Switch Adjusted & Valve Retested & Returned to Svc (← links)
- 05000266/LER-1981-004, Forwards LER 81-004/03L-0 (← links)
- 05000266/LER-1981-003-03, /03L-0:on 810328,3D Diesel Generator Dc Power Failure Alarm Actuated.Caused by Failure of Field Failure Voltage (Ffv) Relay Coil.Ffv Relay Coil Replaced & Generator Returned to Svc (← links)
- 05000266/LER-1993-003, :on 930319,discovered That Setpoints for Low Temp Overpressure Sys Nonconservative.Caused by Failure to Recognize RCS Pressure Transmitters in Subj Sys Development Analysis.Operations Special Order Issued (← links)
- 05000266/LER-1993-002, :on 930218,both EDG Declared Inoperable Due to Blown Fuse.Blown Fuse in Metering Circuit Replaced & Operating Instruction OI-35, Electrical Equipment Operation Revised (← links)
- 05000266/LER-1990-001, :on 900402,containment Isolation Valve Leakage Found in Excess of Tech Spec Limits.Suspected That Two Intermediate Attempts May Have Partially Cycled Valve.Valve Reassembled & Tested Satisfactorily (← links)
- 05000266/LER-1989-008-01, Advises That Tech Spec Change Request to Clarify Table 15.3.5-3,Item 3.b Re ATWS Mitigating Actuation Circuitry Automatically Bypassed at Power Level Greater than 40% Power Level,Per LER 89-008-01 Will Be Submitted by 900412 (← links)
- 05000266/LER-1981-018-03, /03L-0:on 811016,while Connecting Wet Pipe Flow Switches Into Emergency Diesel Generator Area Smoke Detection Sys,Wiring Error Caused Sys Supply Fuses to Blow. Caused by Personnel Error (← links)
- 05000266/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl (← links)
- 05000266/LER-1981-017-01, /01T-0:on 811030,during refueling,10 Tubes in a Steam Generator & 7 Tubes in B Steam Generator Found to Exceed Tech Specs.Caused by Caustic.Crevice Flush Planned Before Startup & Defective Tubes Sleeved (← links)
- 05000266/LER-1981-017, Forwards LER 81-017/01T-0 (← links)
- 05000266/LER-1981-015, Updated LER 81-015/01T-1:on 811010,high & Low Head Safety Injection Check Valve Leakage Test Indicated Leakage in Excess of Acceptable Criteria for 1-853C.Cause Not Stated. Affected Line Flushed & 1-853C Retested (← links)
- 05000266/LER-1981-016-01, /01T-0:on 811016,vendor Notified of Unusually High Failure Rate of Westinghouse Nbfd Relays Upon de-energization.Caused by Voltage Spike.Gradual Replacement of Designed Relays or Coils Planned (← links)
- 05000266/LER-1981-016, Forwards LER 81-016/01T-0 (← links)
- 05000266/LER-1981-015-01, /01T-0:on 811010,during Refueling Outage,High & Low Head Safety Injection Check Valve Leakage Test Indicated Excessive Leakage.Cause Not Stated.Affected Line Flushed & Passed Retest (← links)
- 05000266/LER-1981-013-03, /03L-0:on 810921,records Revealed That Safeguards Bus Undervoltage Relays Were Not Tested within Required Time Frame.Caused by Earlier than Normal Testing During Annual Diesel Overhaul.Surveillance Callup Modified (← links)
- 05000266/LER-1981-013, Forwards LER 81-013/03L-0 (← links)
- 05000266/LER-1981-012-01, /01T-0:on 810828,control Room Critical Control Power Failure Alarm Annunciated.Caused by Breakers Accidentally Opened by Contractor Personnel Installing Fire Barriers in Control Room.Breakers Closed & Alarm Cleared (← links)
- 05000266/LER-1981-012, Forwards LER 81-012/01T-0 (← links)
- 05000266/LER-1981-011-03, /03L-0:on 810721,during Biweekly Safeguards Sys Logic Periodic Testing,Unit 1 Test Switch PC-950A Failed. Probably Caused by Dirty Contacts.New Rees Contact Block Installed (← links)
- 05000266/LER-1981-011, Forwards LER 81-011/03L-0 (← links)
- 05000266/LER-1990-011, :on 900829,low Net Positive Suction Head to Containment Spray Pumps W/Eccs in Recirculation Mode Occurred.Caused by Procedural Deficiency.Temporary Procedure Changes Initiated (← links)
- 05000266/LER-1982-029, Forwards LER 82-029/03L-0 (← links)
- 05000266/LER-1982-027-03, /03L-0:on 821211,operator Noted That Steam Generator Pressure Transmitter 1PT-469 Indicated Higher than Other Channels.Caused by Frozen Sensing Line Due to Inadequate Interim Piping Insulation (← links)
- 05000266/LER-1982-027, Forwards LER 82-027/03L-0 (← links)
- 05000266/LER-1982-028-03, /03L-0:on 821215,routine Test on Fire Detection Sys Found Panel D407 Which Monitors Unit 1 Rod Drive Room Inoperable.Caused by Blown Fuse.Fuse & Indication Lights Replaced on 821215.Detection Sys Undergoing Design Review (← links)
- 05000266/LER-1982-028, Forwards LER 82-028/03L-0 (← links)
- 05000266/LER-1982-020-01, While Performing Type B & C Leakage Tests of Containment Penetrations & Isolation Valves,One Valve Had Leakage Exceeding Limit.Cause Not Stated.Valve Clapper & Seat Lapped (← links)
- 05000266/LER-1982-020, Forwards Updated LER 82-020/01X-1 (← links)
- 05000266/LER-1982-017-01, /01T-0:on 821030,four Tubes in Steam Generator a & Three Tubes in Steam Generator B Indicated Degradation Greater than 40% Plugging Limit.Caused by Intergranular Attack.Tubes Mechanically Plugged (← links)
- 05000266/LER-1978-010-01, /01T-1 on 780528:Indication of primary-to- Secondary Leak of 145 Gpd in the a SG Was Noted on 780524. Source of Leak Due to Failure of Tube at Position R44C35. Tube Plugged & Unit Returned to Svc (← links)
- 05000266/LER-1994-009, :on 940909,EDG G-02 Inadvertently Started & Station Battery Charger D-08 Tripped Off Due to Blown Fuse. Caused by Inadequate Procedure.Blown Fuse Replaced & Electrical Distribution Sys Restored to Normal (← links)
- 05000266/LER-1991-003, :on 910429,charging Sys Check Valve 1-370 Discovered W/Leakage in Excess of Limits Due to Worn Disc Arm Bushing Steps.Worn Disc Arm Bushing Steps Cladded W/ E308 Weld Matl & Hand Filed to Design Contour (← links)
- 05000266/LER-1989-010, :on 891120,auxiliary Feedwater Flow Transmitters Inadvertently Isolated.Caused by Error in Approved Procedure & Personnel Cognitive Error.Unit 1 Transmitters Valved Back Into Svc Immediately (← links)
- 05000266/LER-1981-010-01, /01T-0:on 810716,check Valves 1-853C & D Were Opened Up & Found Stuck in Full Open Position During Testing.Caused by Interference Between Disc Wire & Valve Body.Disc Wires Replaced W/Cotter Pins (← links)
- 05000266/LER-1981-010, Forwards LER 81-010/01T-0 (← links)
- 05000266/LER-1981-009-01, /01T-0:on 810714,per IE Bulletin 80-11 Analyses, Contractor Reported That Four Control Room & Two Battery Room Walls Did Not Meet Revised Criteria for Seismic Event. Caused by Reanalysis Per Revisions.Supports Installed (← links)
- 05000266/LER-1981-009, Forwards LER 81-009/01T-0 (← links)
- 05000266/LER-1981-008-01, /01T-0:on 810710,four Tubes in Steam Generators Were Verified to Have Degradation Greater than 40% Which Exceeds Plugging Limit of Tech Specs.Caused by Intergranular Attack Due to Caustic.Defective Tubes Plugged (← links)
- 05000266/LER-1981-008, Forwards LER 81-008/01T-0 (← links)
- 05000266/LER-1981-007-01, /01T-0:on 810626,during Normal Operation,Unit Tripped from Approx 80% Power Due to Loss of Instrument Bus. Caused by Performance of Backfitting Mods.Plant Contractors Reinstructed (← links)
- 05000266/LER-1981-007, Forwards LER 81-007/01T-0 (← links)
- 05000266/LER-1981-006-01, /01T-0:on 810621,spray Additive Isolation Valve 1-831A Found Shut.Caused by Failure of Operator to Position Valve Correctly After Surveillance Testing.Valve Repositioned & Locked Open (← links)
- 05000266/LER-1981-006, Forwards LER 81-006/01T-0 (← links)
- 05000266/LER-1981-003, Forwards LER 81-003/01T-0 (← links)
- 05000266/LER-1981-005, Forwards LER 81-005/03L-0 (← links)
- 05000266/LER-1981-005-03, /03L-0:on 810515,control Room Emergency Filtration Sys Fans,Common to Both Units,Found Operating Outside Design Flow Rates Per Tech Specs.Caused by Improperly Balanced Backdraft Damper at Fan Discharge.Dampers Readjusted (← links)
- 05000266/LER-1980-016-03, /03L-0:on 801217,during Testing,Emergency Diesel Generator 4D Failed to Close in on Bus.Caused by Slippage of Flexible Shaft Coupling on Speed Sensing Frequency Generator Drive Shaft.Coupling Secured (← links)
- 05000266/LER-1980-016, Forwards LER 80-016/03L-0 (← links)
- 05000266/LER-1981-001-01, /01T-0:on 810102,while Performing Monthly Ventilation Sys Test,Supply Breaker for Safeguards Motor Control Ctr 1B42 Tripped.Caused by Dust in Instantaneous Trip Valve on Breaker.Breaker Cleaned & Tested (← links)
- 05000266/LER-1981-001, Forwards LER 81-001/01T-0 (← links)
- 05000266/LER-1980-015-01, /01T-0:on 801210,during Refueling Outage Surveillance Testing of safety-related Shock Suppressors, Snubber 1-HS-14 Found to Be Inoperable.Caused by Low Level in Reservoir,Resulting from Piston Rod O-ring Seal Leakage (← links)
- 05000266/LER-1980-015, Forwards LER 80-015/01T-0 (← links)
- 05000266/LER-1980-011-03, /03L-0:on 800926,found That,Aug 1977-Sept 1980, Containment Spray Sys Spray Additive Valves Were Tested Per ASME Program Requirements Instead of Per Tech Specs.Caused by Administrative Error Re NRC (← links)
- 05000266/LER-1980-011, Forwards LER 80-011/03L-0 (← links)
- 05000266/LER-1980-013-01, /01T-0:on 801113,suction to 1P4B Boric Acid Transfer Pump Isolated,Rendering Pump Inoperable.Probably Caused by Personnel Error in Returning Valve Lineup to Normal Following Recirculation & Sampling (← links)
- 05000266/LER-1980-013, Forwards LER 80-013/01T-0 (← links)
- 05000266/LER-1980-009-01, /01T-0:on 800728 While in Cold Shutdown & During Hydrostatic Leak Test of Steam Generators,Two Dripping Explosive Plugs & Two Wet End Plugs Noted.Cause Not Stated. Dripping Plugs Weld Repaired (← links)
- 05000266/LER-1980-009, Forwards LER 80-009/01T-0 (← links)
- 05000266/LER-1980-014-01, /01T-0:on 801211,results of Ongoing Refueling Outage Steam Generator Eddy Current Insp Indicated Defective Tubes.Eight Tubes W/Crevice Defects Taken Out of Svc.Caused by Corrosion.Defects Plugged (← links)
- 05000266/LER-1980-014, Forwards LER 80-014/01T-0 (← links)
- 05000266/LER-1981-002-03, /03L-0:on 810113,post Acceptance Review of Annual Test Results from 04-80,for Control Room Emergency Filtration Sys,Showed 1980 Annual Test Incomplete.Caused by Personnel Failing to Determine Sys Velocity & Flow Info (← links)
- 05000266/LER-1981-002, Forwards LER 81-002/03L-0 (← links)
- 05000266/LER-1980-012-03, /03L-0:on 801005,logs Showed Decrease in Holdup Tank Pressure During 801002-05.Evaluation Showed Leak on Compression Fitting on Inlet to Valve IPCV-1022C.Caused by Improper Reinstallation of Valve After Cleaning (← links)
- 05000266/LER-1980-012, Forwards LER 80-012/03L-0 (← links)
- 05000266/LER-1980-010-03, /03L-0:on 800827,during Normal Operation,After Redundant Containment Spray Pump Recirculation Phase Suction Valve Maint,Operability Test Was Not Performed.Caused by Personnel Failure to Fully Comprehend Maint Procedures (← links)
- 05000266/LER-1980-010, Forwards LER 80-010/03L-0 (← links)
- 05000266/LER-1989-009, :on 891107,D05 & D06 Station Batteries Declared Inoperable.Caused by Original Design Deficiency.Mod Completed to Restore Battery D05 to Operable Status by Replacing Eight nonsafety-related Breakers (← links)
- 05000266/LER-1980-008-03, /03L-0:on 800606,during Normal Operation,Testing Revealed That Relay 1-247/AO2X in Train B Would Not Drop Out to Initiate Undervoltage Trip Function.Cause Not Determined. Relay Replaced & Tested Satisfactorily (← links)
- 05000266/LER-1980-008, Forwards LER 80-008/03L-0 (← links)
- 05000266/LER-1989-008, :on 890910,ATWS Mitigating Actuation Circuitry Automatically Bypassed at About 42% Reactor Power, Disenabling Sys.Caused by High Tech Spec Setpoint.Enable/ Disable Setpoint Reset to 30% (← links)
- 05000266/LER-1980-002-01, /01T-0:on 800311,during shutdown,800 Psi secondary-to-primary Hydrostatic Leak Test of B Steam Generator Revealed Tube R23C44 Leaking,Tube R8C37 Wet & Plug End R23C50 Wet.Tube Holes Will Be Weld Plugged (← links)
- 05000266/LER-1980-007-01, /01T-0:on 800611,blue Instrument Bus 1Y02 Was de-energized,resulting in de-energization of 3 Containment Pressure Channels.Caused by Personnel Error.Power Restored & Instrumentation Returned to Normal (← links)
- 05000266/LER-1980-007, Forwards LER 80-007/01T-0 (← links)
- 05000266/LER-1980-005-03, /03L-0:on 800417,during Normal Operation,Review of Security Logs Revealed That Designated Fire Brigade Was Below Min Supervision Requirements on Three Occasions.Caused by Operations Personnel Designation Error (← links)
- 05000266/LER-1980-005, Forwards LER 80-005/03L-0 (← links)
- 05000266/LER-1980-004-03, /03L-0:on 800409,w/plant at Normal Steady State, Emergency Diesel Generator Failed to Start During Routine Surveillance Test.Second Attempt Unsuccessful.Caused by Broken Vane in Starting Air Motor.Air Motor Replaced (← links)
- 05000266/LER-1980-004, Forwards LER 80-004/03L-0 (← links)
- 05000266/LER-1980-003-03, /03T-0:on 800318,during post-mod Testing of Containment Spray Sys,Relay 1CSB Would Not Latch.Caused by Latching Mechanism Misalignment.Latch Adjusted & Proper Operation Verified on 800318.Similar Relay Bench Tested (← links)
- 05000266/LER-1980-003, Forwards LER 80-003/03T-0 (← links)
- 05000266/LER-1980-002, Updated LER 80-002/01T-01:on 800311,during 800 Psi Secondary to Primary Hydrostatic Leak Test,Tubes R23C44 & R8C37 & Plug End R23C50 Found Leaking.Eddy Current Insp Performed.Tube Holes & Leaking Explosive Plugs Were Plug Welde (← links)
- 05000266/LER-1980-006-03, /03L-0:on 800417,during Analysis of as-built safety-related Piping Sys Per IE Bulletin 79-14,overstressed Condition Discovered in Cooling Sys Piping.Caused by Lack of Support Between Valves Upstream of Juncture (← links)
- 05000266/LER-1980-006, Forwards LER 80-006/03L-0 (← links)
- 05000266/LER-1978-017-01, /01T-0 on 781206:control Rod K-7 Control Bank D Became Misaligned More than 15 in & Caused Quadrant Flux Tilt of More than 2%.Caused by Personnel Error (← links)
- 05000266/LER-1978-017, Forwards LER 78-017/01T-0 (← links)
- 05000266/LER-1979-022-01, /01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown (← links)
- 05000266/LER-1979-022, Forwards LER 79-022/01T-0 (← links)
- 05000266/LER-1980-001-01, /01T-0:on 800202,during Routine Calibr of Pressure Transmitters for Motor Driven Auxiliary Feed Pumps, Transmitter Isolation Block Valves Discovered Closed.Caused by Inadvertent Closing of Isolation Valves.Snubbers Added (← links)
- 05000266/LER-1980-001, Forwards LER 80-001/01T-0 (← links)
- 05000266/LER-1979-001-01, /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed (← links)
- 05000266/LER-1979-001, Forwards LER 79-001/01T-0 (← links)
- 05000266/LER-1979-012-01, /01T-0 on 790805:primary to Secondary Leak Noted in Steam Generator A.Caused by Defective Tubes in Steam Generators a & B.Leaking & Defective Tubes Plugged (← links)
- 05000266/LER-1979-012, Forwards LER 79-012/01T-0 (← links)
- 05000266/LER-1979-008-01, /01T-0 on 790502:remote Possibility Exists for Simultaneous Safety Injection in Both Units,Which Could Result in Emergency Diesel Overloading.Pressurizer Logic & Power Supplies Changed (← links)
- 05000266/LER-1979-008, Forwards LER 79-008/01T-0 (← links)
- 05000266/LER-1979-009-01, /01T-0 on 790510:during Hydrostatic Test of Fire Water Sys,Compression Fitting Failed.Caused by Broken Flange.Flange Replaced (← links)
- 05000266/LER-1979-009, Forwards LER 79-009/01T-0 (← links)
- 05000266/LER-1979-017, Discusses 791105 & 20 Meetings W/Nrc Re Info & Data on Steam Generator Tube Problems,Presented in LER 79-017/01T-0 on 791116.Certificate of Svc (← links)
- 05000266/LER-1979-020-01, /01T-0:on 791115,during Refueling Shutdown,Anchor in Steam Generator a Auxiliary Feedwater Line Contained Const Deficiency.Caused by Improper Installation of Three Bolts in Anchor Support Plate.Anchor Permanently Modified (← links)
- 05000266/LER-1979-020, Forwards LER 79-020/01T-0 (← links)
- 05000266/LER-1979-019-01, /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle (← links)
- 05000266/LER-1979-019, Forwards LER 79-019/01T-0 (← links)
- 05000266/LER-1979-021-01, /01T-0:on 791211,during Normal Operation, Increasing Steam Generator Primary to Secondary Leakage Noted.Caused by Leaking Tube in Steam Generator B.Plugs Welded & Repaired (← links)
- 05000266/LER-1979-021, Forwards LER 79-021/01T-0 (← links)
- 05000266/LER-1978-018-01, /01T-0 on 781219:during Normal Power Operation, Power Range Channel 44 Failed,Causing 20% Turbine Runback. Failure of Power Designs,Inc,Model UPMP-X54W Power Supply Caused Instrument to Fail (← links)
- 05000266/LER-1978-018, Forwards LER 78-018/01T-0 (← links)
- 05000266/LER-1978-019-01, /01T-0 on 7901228:both Heat Tracing Circuits of Circuit 47 of the Boric Acid Sys Were Inoperable Due to Defective Potentiometers in the Thermon Model SCR Controller for Each Circuit (← links)
- 05000266/LER-1978-019, Forwards LER 78-019/01T-0 (← links)
- 05000266/LER-1979-016-03, /03L-0:on 791003,emergency Diesel Generator 3D Failed to Start for Monthly Tech Spec Test.Caused by Sticking of Woodward UG8 Dial Control Governor Load Limit Strap in Stop Position.Governor Replaced (← links)
- 05000266/LER-1979-016, Forwards LER 79-016/03L-0 (← links)
- 05000266/LER-1979-015-01, /01T-0:on 791002,during Normal Power Operation, Loose Tube Fitting Discovered on Common Line from containment-to-containment Pressure Transmitters.Cause Undetermined.Fitting Tightened (← links)
- 05000266/LER-1979-015, Forwards LER 79-015/01T-0 (← links)
- 05000266/LER-1979-010-01, /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed (← links)
- 05000266/LER-1979-018-01, /01T-0:on 791102,taping on Unit 2 Containment Motor Leads Did Not Meet Const Specs.Insp Showed Similar Situation W/Unit 2.Cause Not Stated.Unit 2 Motor Leads Retaped by 791109.Unit 1 Will Be Complete Prior to Startup (← links)
- 05000266/LER-1979-018, Forwards LER 79-018/01T-0 (← links)
- 05000266/LER-1979-017-01, /01T-0:on 791103,testing Revealed 131 Defective Tubes in a & B Steam Generators.Cause Under Investigation. Tubes Welded & Plugged (← links)
- 05000266/LER-1979-014-03, /03L-0:on 790912,charging Pump 1-P2B Found to Have Cylinder Block Crack.Caused by Pressure Spiking During Compression Stroke Following Hydrogen Separation During Suction Stroke.Cracked Block Replaced (← links)
- 05000266/LER-1979-014, Forwards LER 79-014/03L-0 (← links)
- 05000266/LER-1979-013-01, /01T-0:on 790830,Unit 1 Taken Off Line for Steam Generator primary-to-secondary Leakage Repair.Leakage Had Risen to 324 Gallons Per Day.Caused by 88% Defect Located Just Below Top of Tubeseheet.Tube Plugged (← links)
- 05000266/LER-1979-013, Forwards LER 79-013/01T-0 (← links)
- 05000266/LER-1979-011-01, /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open (← links)
- 05000266/LER-1979-011, Forwards LER 79-011/01T-0 (← links)
- 05000266/LER-2019-002, Operation Not Maintained within Pressure and Temperature Limit Report (PTLR) as Required by Technical Specification 3.4.3 (← links)
- 05000266/LER-2019-001, Loss of Main Condenser Cooling Results in Manual Reactor Trip (← links)
- 05000266/LER-2018-001, Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Conditions (← links)
- 05000266/LER-1987-004-01, Forwards LER 87-004-01 Detailing Loss of Red Instrument Bus During Replacement of Battery Cell.Encl Delayed Due to Depth of Investigation (← links)
- 05000266/LER-1986-003-01, :on 860603,reactor Trip Occurred Due to Loss of Power on White Instrument Bus.Caused by Trip of White Inverter Output Breaker.Procedures for Placing Inverter on Line Will Be Revised (← links)
- 05000266/LER-1917-003, Regarding Degraded Condition (← links)
- 05000266/LER-1917-002, Regarding Operation or Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-1917-001, Regarding Control Room Barrier Inadvertently Disabled (← links)
- 05000266/LER-2016-003, Regarding Operation or Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-2016-002, Regarding Operation or Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-2016-001, Regarding Degraded Condition (← links)
- 05000266/LER-2015-006-01, Regarding Automatic Reactor Trip - Revision (← links)
- 05000266/LER-2015-006, Regarding Automatic Reactor Trip (← links)
- 05000266/LER-2015-004, Regarding Emergency Diesel Generator Switchgear Room Exhaust Fan Removal from Service Results in Operation or Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-2015-003, Regarding D-107 Battery Charger Failure to Limit Current Results in Operation or Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-2015-002, Regarding Manual Reactor Trip (← links)
- 05000266/LER-2015-001, Regarding Inadequately Sealed Pipe Penetrations Result in Unanalyzed Condition for Internal Flooding (← links)
- 05000266/LER-2013-002, Regarding Condition Prohibited by Technical Specifications (← links)
- 05000266/LER-2013-001, Loss of Offsite Power to Unit 1 Safeguards Buses (← links)
- 05000266/LER-2012-005, Potential Operation Prohibited by Technical Specifications (← links)
- 05000266/LER-2012-004, Regarding Unit 1 Manual Reactor Trip (← links)
- 05000266/LER-2012-003, Regarding 2B-04 Safeguards 480V Bus De-Energized (← links)
- 05000266/LER-2012-002, Regarding Condition Prohibited by Technical Specification 3.7.5, Auxiliary Feedwater (← links)
- 05000266/LER-2011-001, Regarding Loss of Offsite Power to Unit 1 Safeguards Buses (← links)
- 05000266/LER-2010-005, For Point Beach Regarding Improper Administrative Controls for HELB Barriers (← links)
- 05000266/LER-2010-004, From Nextera Energy Point Beach Improper Controls for Breach of HELB Barrier (← links)
- 05000266/LER-2010-003, Regarding Potential for Residual Heat Removal Trains to Be Inoperable During Mode Change (← links)
- 05000266/LER-2010-002, Regarding Manual Reactor Trip Due to Lowering Condenser Vacuum (← links)
- 05000266/LER-2010-001, Regarding Engineered Safety Features Steam Line Pressure Dynamics Modules Discovered Outside of Technical Specification Values (← links)
- 05000266/LER-2009-001, Component Cooling Water Pump Inoperable in Excess of Technical Specification Allowed Completion Time (← links)
- 05000266/LER-2008-003, Regarding Appendix R Fire Scenario Resulting in Safe Shutdown Required Capability Not Maintained (← links)
- 05000266/LER-2008-002, Regarding One Service Water Pump Inoperable in Excess of Technical Specification Allowed Completion Time (← links)
- 05000266/LER-2008-001, Regarding Manual Reactor Shutdown Required by Technical Specification LCO 3.8.1 AC Sources-Operating Not Met (← links)
- 05000266/LER-2007-008, For Point Beach, Unit 1, Non-Conservative Low Temperature Overpressure Protection System Basis (← links)
- 05000266/LER-2007-006, Re Fire Inspection Analysis of Pressurizer Power-Operated Relief Valves and Block Valves (← links)
- 05000266/LER-2007-005, Regarding Manual Reactor Shutdown Required by Technical Specification; LCO 3.7.5 Auxiliary Feedwater Not Met (← links)
- 05000266/LER-2007-004, Regarding Manual Reactor Trip Due to Loss of Feedwater Regulating Valve Control (← links)
- 05000266/LER-2007-003, Regarding ESFAS Instrumentation, Lead/Lag Time Constants for Steam Line Pressure Outside Technical Specification Values (← links)
- 05000266/LER-2007-001, Re CREFS Inoperability, Both Control Room Charcoal Filter Fans Inoperable (← links)
- 05000266/LER-2006-002, Re Fuel Assemblies in Spent Fuel Pool Do Not Meet Technical Specification Requirements (← links)
- 05000266/LER-2006-001, Regarding Control Room Emergency Filtration System Inoperable (← links)
- 05000266/LER-2005-008, Re Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Circulating Water Pump Failure (← links)
- 05000266/LER-2005-006, Re Calculation Errors in Model for ECCS Long Term Cooling (← links)
- 05000266/LER-2005-007, Regarding Control Rod Movement with Refueling Cavity Water Level Below TS 3.9.6 Limit (← links)
- 05000266/LER-2005-005, Postulated Faults with Electrical Current in Excess of Maximum Interrupt Ratings and Nonconservative Technical Specification for Degraded Voltage Time Delay Relay Settings (← links)
- 05000266/LER-2005-003, Re Potentially Inoperable Safety Injection Pumps (← links)
- 05000266/LER-2005-004, Re Auxiliary Feedwater Recirculation Capability in Local Operating Mode (← links)
- 05000266/LER-2005-002, And LER 05-002-00 for Point Beach, Units 1 and 2 Re Unanalyzed Conditions Due to Inadvertent Omission of Safe Shutdown Equipment from Fire Organizational Plan (← links)
- 05000266/LER-2004-003, Re Reactor Shutdown Required by Containment Penetration Tsac 3.6.3.C (← links)
- 05000266/LER-2003-002, Regarding Reactor Trip Due to Rod Drive Motor-Generator Set Failure (← links)
- 05000266/LER-2003-001, Re as Found Condition of Degraded Grid Voltage Relays Not within Technical Specification Limits (← links)
- 05000266/LER-2001-005, Page 3 of LER 01-005-00 and 4 Pages of Information on Point Beach Procedures (← links)
- 05000266/LER-2002-003, Re Possible Common Mode Failure of AFW Due to Partial Clogging of Recirculation Orifices (← links)
- 05000266/LER-2002-002, A-Train Reactor Protection Cable Routed in B-Train Cable Trays (← links)
- 05000266/LER-2002-001, From Point Beach Nuclear Plant Unit 1 Regarding Steam Generator Blowdown Valve Analyzed as Not Able to Close Against Full Differential Pressure (← links)
- 05000266/LER-2001-006, Re Appendix R Requirements Not Satisfied for Unanalyzed Fire Induced Damage to Auxiliary Feedwater System (← links)
- 05000266/LER-1998-015, :on 980420,containments Fan Cooler Test Results Were Outside Acceptance Criteria.Cause Is Still Being Evaluated.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed (← links)
- 05000266/LER-1995-006, :on 950714,reactor Tripped Due to Loss of Generator Excitation as Result of Accumulation of Condensation.Unit 1 Generator Exciter Inspected & Repaired & Flow of CW to Unit 1 Exciter Cooler Reduced (← links)
- ML13095A183 (redirect page) (← links)
- ML25051A225 (← links)
- 05000266/LER-2013-002, Regarding Condition Prohibited by Technical Specifications (← links)