Pages that link to "05000338/LER-2024-001, Automatic Reactor Trip Due to PRNI High Negative Rate"
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The following pages link to 05000338/LER-2024-001, Automatic Reactor Trip Due to PRNI High Negative Rate:
Displayed 45 items.
- 10 CFR 50.73(a)(2)(iv)(A), System Actuation (← links)
- ML101380270 (← links)
- ML021610316 (← links)
- ML021550423 (← links)
- ML021350374 (← links)
- ML021340006 (← links)
- ML021330155 (← links)
- ML020990380 (← links)
- ML020870707 (← links)
- ML020870369 (← links)
- ML020870322 (← links)
- ML020870280 (← links)
- ML020840253 (← links)
- ML020800771 (← links)
- ML020800601 (← links)
- ML020710713 (← links)
- ML020710697 (← links)
- ML020700231 (← links)
- ML020650715 (← links)
- ML020650032 (← links)
- ML020640021 (← links)
- ML020600152 (← links)
- ML020580398 (← links)
- ML020510089 (← links)
- ML020500701 (← links)
- ML020420523 (← links)
- ML020390535 (← links)
- ML020380123 (← links)
- ML020330139 (← links)
- ML020290177 (← links)
- ML020280221 (← links)
- ML020160165 (← links)
- ML020090089 (← links)
- ML20087G307 (← links)
- ML20101H294 (← links)
- ML24211A003 (redirect page) (← links)
- 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate (redirect page) (← links)
- 05000338/LER-2024-001 (redirect page) (← links)
- 05000338/LER-2001-001 (← links)
- 05000338/LER-1982-047, Forwards LER 82-047/03L-0 (← links)
- 05000338/LER-1982-044, Forwards LER 82-044/03L-0 (← links)
- 05000338/LER-1982-043, Forwards LER 82-043/03L-0 (← links)
- 05000338/LER-1982-034, Forwards LER 82-034/03L-0 (← links)
- 05000338/LER-1982-042, Forwards LER 82-042/03L-0 (← links)
- 05000338/LER-1982-045, Forwards LER 82-045/03L-0 (← links)
- 05000338/LER-1982-046, Forwards LER 82-046/03L-0 (← links)
- 05000338/LER-1982-038, Forwards LER 82-038/03L-0 (← links)
- 05000338/LER-1982-033, Forwards LER 82-033/03L-0 (← links)
- 05000338/LER-1982-035, Forwards LER 82-035/03L-0 (← links)
- 05000338/LER-1982-040, Forwards LER 82-040/03L-0 (← links)
- 05000338/LER-1982-039, Forwards LER 82-039/03L-0 (← links)
- 05000338/LER-1982-037, Forwards LER 82-037/03L-0 (← links)
- 05000338/LER-1982-036, Forwards LER 82-036/03L-0 (← links)
- 05000338/LER-1982-032, Forwards LER 82-032/03L-0 (← links)
- 05000338/LER-1982-010, /03L-0:on 820505,valves MOV-FW-154A,B & C & TV-1884A,B & C Found W/Identical Control Circuits as Reported in LER 82-010 for Unit 2.Design Permits Operator to Open Valves W/O Resetting Phase a Isolation Signal (← links)
- 05000338/LER-1982-030, Forwards LER 82-030/03L-0 (← links)
- 05000338/LER-1982-029, Forwards LER 82-029/03L-0 (← links)
- 05000338/LER-1982-028, Forwards LER 82-028/03L-0 (← links)
- 05000338/LER-1982-031, Forwards LER 82-031/03L-0 (← links)
- 05000338/LER-1982-020, Forwards LER 82-020/03L-0 (← links)
- 05000338/LER-1982-065, Forwards LER 82-065/03L-0 (← links)
- 05000338/LER-1982-063, Forwards LER 82-063/03L-0 (← links)
- 05000338/LER-1982-057, Forwards LER 82-057/03L-0 (← links)
- 05000338/LER-1982-050, Forwards LER 82-050/03L-0 (← links)
- 05000338/LER-1982-059, Forwards LER 82-059/03L-0 (← links)
- 05000338/LER-1982-058, Forwards LER 82-058/03L-0 (← links)
- 05000338/LER-1979-070, Forwards LER 79-070/03L-0 (← links)
- 05000338/LER-1982-076, Forwards LER 82-076/03L-0 (← links)
- 05000338/LER-1982-085, Forwards LER 82-085/03L-0 (← links)
- 05000338/LER-1982-088, Forwards LER 82-088/03L-0 (← links)
- 05000338/LER-1978-111, Forwards LER 78-111/01T (← links)
- 05000338/LER-1978-107, Forwards LER 78-107/03L-0,LER 78-108/03L-0 & LER 78-109/03L-0 (← links)
- 05000338/LER-1978-091, Forwards LER 78-091/03L-0,LER 78-092/03L-0,LER 78-094/03L-0, LER 78-095/03L-0,LER 78-096/03L-0,LER 78-097/03L-0, LER 78-099/03L-0 & LER 78-103/03L-0 (← links)
- 05000338/LER-1978-090, Forwards LER 78-090/03L-0 (← links)
- 05000338/LER-1978-098, Forwards LER 78-098/01T-0 (← links)
- 05000338/LER-1982-055, Forwards LER 82-055/03L-0 (← links)
- 05000338/LER-1982-048, Forwards LER 82-048/03L-0 (← links)
- 05000338/LER-1982-053, Forwards LER 82-053/03L-0 (← links)
- 05000338/LER-1981-050, Forwards LER 81-050/03L-0 (← links)
- 05000338/LER-1982-049, Forwards LER 82-049/03L-0 (← links)
- 05000338/LER-1982-054, Forwards LER 82-054/03L-0 (← links)
- 05000338/LER-1982-052, Forwards LER 82-052/03L-0 (← links)
- 05000338/LER-1982-051, Forwards LER 82-051/03L-0 (← links)
- 05000338/LER-1983-004, Forwards LER 83-004/03L-0 (← links)
- 05000338/LER-1983-002, Forwards LER 83-002/03L-0 (← links)
- 05000338/LER-1982-090, Forwards LER 82-090/03L-0 (← links)
- 05000338/LER-1982-091, Forwards LER 82-091/03L-0 (← links)
- 05000338/LER-1982-087, Forwards LER 82-087/03L-0 (← links)
- 05000338/LER-1982-084, Forwards LER 82-084/03L-0 (← links)
- 05000338/LER-1982-082, Forwards LER 82-082/01T-0 (← links)
- 05000338/LER-1982-081, Forwards LER 82-081/03L-0 (← links)
- 05000338/LER-1982-080, Forwards LER 82-080/03L-0 (← links)
- 05000338/LER-1982-070, Forwards LER 82-070/03L-0 (← links)
- 05000338/LER-1982-079, Forwards LER 82-079/03L-0 (← links)
- 05000338/LER-1982-078, Forwards LER 82-078/03L-0 (← links)
- 05000338/LER-1982-077, Forwards LER 82-077/03L-0 (← links)
- 05000338/LER-1982-073, Forwards LER 82-073/03L-0 (← links)
- 05000338/LER-1982-069, Forwards LER 82-069/03L-0 (← links)
- 05000338/LER-1982-075, Forwards LER 82-075/03L-0 (← links)
- 05000338/LER-1982-074, Forwards LER 82-074/03L-0 (← links)
- 05000338/LER-1982-071, Forwards LER 82-071/03L-0 (← links)
- 05000338/LER-1982-068, Forwards LER 82-068/03L-0 (← links)
- 05000338/LER-1982-072, Forwards LER 82-072/03L-0 (← links)
- 05000338/LER-1983-016, Forwards LER 83-016/03L-0 (← links)
- 05000338/LER-1982-061, Forwards LER 82-061/03L-0 (← links)
- 05000338/LER-1982-062, Forwards LER 82-062/03L-0 (← links)
- 05000338/LER-1983-009, Forwards LER 83-009/03L-0 (← links)
- 05000338/LER-1981-076, Forwards LER 81-076/03L-0 (← links)
- 05000338/LER-1979-001, Forwards LER 79-001/01T-0 (← links)
- 05000338/LER-1983-077, Errata to LER 83-077/03L-0,forwarding Page 2,inadvertently Omitted from Original Distribution (← links)
- 05000338/LER-1983-006, Forwards LER 83-006/03L-0 (← links)
- 05000338/LER-1983-020, Forwards LER 83-020/03L-0 (← links)
- 05000338/LER-1983-019, Forwards LER 83-019/03L-0 (← links)
- 05000338/LER-1983-013, Forwards LER 83-013/03L-0 (← links)
- 05000338/LER-1983-018, Forwards LER 83-018/03L-0 (← links)
- 05000338/LER-1983-005, Forwards LER 83-005/03L-0 (← links)
- 05000338/LER-1984-015, Advises That LER 84-015-00 Will Not Be Used (← links)
- 05000338/LER-1983-010, Forwards LER 83-010/03L-0 (← links)
- 05000338/LER-1983-011, Forwards LER 83-011/03L-0 (← links)
- 05000338/LER-1983-012, Forwards LER 83-012/03L-0 (← links)
- 05000338/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000338/LER-1983-007, Forwards LER 83-007/03L-0 (← links)
- 05000338/LER-1950-338, Forwards LER 50-338/97-005-00.No Commitments Made (← links)
- 05000338/LER-1979-148, Forwards LER 79-148/01T-0 (← links)
- 05000338/LER-1997-002, Forwards LER 97-002-00.Commitment Made:Evaluation Will Be Performed to Review Preventive Maint Frequency for MSSV & Psv Disassembly,Insp & Retesting (← links)
- 05000338/LER-1985-026, Cancelled LER 85-026/00 (← links)
- 05000338/LER-1998-006, Forwards LER 98-006-00,per 10CFR50.73.Commitment Re Completion of Root Cause Evaluation,Listed (← links)
- 05000338/LER-1986-019, Forwards Response to NRC Re Three Findings Noted in Control Room Habitability Survey,Per NRC .Flow Data Reviewed,Tech Spec Violation Described in LER 86-019 & Testing Performed.Addl Findings Will Be Addressed by 870708 (← links)
- 05000338/LER-1985-020, Forwards Proprietary & Nonproprietary Westinghouse WCAP-11310, North Anna Unit 1 Steam Generator Tube Integrity Rept, Per 851216 LER 85-020-00 Commitment.W/O Repts (← links)
- 05000338/LER-1982-041, Forwards Updated LER 82-041/01X-1 (← links)
- 05000338/LER-2022-001-01, Automatic Reactor Trip During Control Rod Operability Testing (← links)
- 05000338/LER-2022-001, Automatic Reactor Trip During Control Rod Operability Testing (← links)
- 05000338/LER-2021-002, Unanalyzed Condition Due to App R Concerns with Cable Separation (← links)
- 05000338/LER-2024-001-01, Automatic Reactor Trip Due to PRNI High Negative Rate (← links)
- 05000338/LER-2024-001, Automatic Reactor Trip Due to PRNI High Negative Rate (← links)
- 05000338/LER-2021-001, Manual Reactor Trip on Degrading Condenser Vacuum Due to Piping Failure (← links)
- 05000338/LER-1988-027, :on 881117,discovered That Requirements of Tech Spec 3.3.2.1 Do Not Refer to Testing of ESF Final Actuated Devices.Caused by Interpretation of Requirements. Justification for Continued Operation Written (← links)
- 05000338/LER-1989-013-01, :on 890626,incore Flux Mapping Frame Assemble Found Unrestrained.Caused by Inadequate Installation. Engineering Work Request & 10CFR50.59 Safety Evaluation Written & Approved (← links)
- 05000338/LER-1989-016-01, :on 890826,recirculation Spray HX Svc Water a Supply Header Isolation Motor Operated Valves Deenergized in Closed Position.Caused by Miscommunication Between Shift Supervisor & Other Personnel.Power Reinstated (← links)
- 05000338/LER-1989-015-01, :on 890808,input Error in LBLOCA Analysis for 18% Steam Generator Tube Plugging Licensing Case Discovered. Caused by PCT Above Limit Specified in 10CFR50.46.Reanalysis Performed to Determine Impact (← links)
- 05000338/LER-1989-004-01, :on 890405,determined That One Steam Generator Tube of Initial Sample Group Was Defective During 1989 Refueling Outage.Caused by Primary Water Stress Corrosion Cracking.Tubes Susceptible to Failure Plugged (← links)
- 05000338/LER-1989-012-01, :on 890626,emergency Diesel Generator Inadvertently Started During Performance of Reactor Protection & ESF Response Time Testing.Caused by Personnel Error.Personnel Counseled (← links)
- 05000338/LER-1989-010-01, :on 890416,normal Power Supply to 4,160-volt Emergency Buses 1H & 2J Lost When Lifted Wire Inadvertently Grounded During Removal for Switchyard Mods.Caused by Personnel Error.Rhr Pump B Restored (← links)
- 05000338/LER-1989-005-01, :on 890225,unit Tripped from 76% Power When Initiating Signal for Reactor Trip Was Greater than Feedwater Flow Mismatch Coincident W/Low Steam Generator Level.Caused by Closure of Regulating Valve (← links)
- 05000338/LER-1989-008-01, :on 890414,determined That Less than Design Svc Water Sys Flow Available to Recirculational Spray Hxs.Caused by Inadequate Maint Procedures,Resulting in Missetting of Mechanical Stops.Stops & Limit Switches Reset (← links)
- 05000338/LER-1988-022, :on 881013,determined That Various Pipes in Safety Injection Sys & Chemical Vol & Control Sys Collected or Trapped Gas Which Might Affect Functions of Sys.Caused by Not Completely Venting Sys After Refill (← links)
- 05000338/LER-1989-008, :on 890414,determined That Water Flow to Recirculation Spray HXs Less than Design.Caused by Inadequate Maint Procedures Necessary to Achieve Throttled Valve Position.Valves Repositioned (← links)
- 05000338/LER-1989-014-01, :on 890719,unit Experienced Automatic Reactor Trip from 90% Power Due to Loss of Electro Hydraulic Control Sys Pressure.Caused by Failed O-ring on Turbine Trip Solenoid Operated Valve.Evaluation Initiated (← links)
- 05000338/LER-1988-021-02, :on 881007,error Discovered in Control Room Habitability Design Basis Calculation.Caused by Error in Design Basis by Use of Erroneous Assumption in S&W Calculation Number.Procedures Revised (← links)
- 05000338/LER-1989-007-01, :on 890328,local Leak Rate Limit Exceeded. Initial Evaluation Attributed Cause of Type C Test Failures to Misadjustment.Work Request Initiated & Valve Leakage & Maintenance History Monitored (← links)
- 05000338/LER-1989-066, :on 890323,1H Emergency Bus Inadvertently Deenergized for Approx 10 S.Caused by Personnel Error. Appropriate Emergency Diesel Generator Periodic Tests Will Be Revised to Prevent Testing at Abnormal Time (← links)
- 05000338/LER-1989-011-01, :on 881123,discrepancy Identified Between Operation of Control Room Air Conditioning Sys & Operational Requirements of Tech Spec 3.7.7.1 & Design Basis.Caused by Misinterpretation of Tech Specs (← links)
- 05000338/LER-1989-009-01, :on 890515,main Steam Line Code Safety Valves as Found Set Pressures Found to Be Outside Lift Set Pressure Tolerance.Cause of Event Not Determined.Valves Refurbished & Retested by Wyle Labs (← links)
- 05000338/LER-1989-007, :on 890328,combined as Found Leakage Exceeded Allowable Limit for Previous Operating Cycle.Caused by Misadjustment.Station Work Request Initiated to Inspect & Adjust Valves as Necessary (← links)
- 05000338/LER-1987-016-01, :on 870814,determined That Redundant Butterfly Valves in Turbine Overspeed Protection Sys Would Not Have Properly Isolated Steam Between 870629-870710.Caused by Inadequate Maint Procedures.Procedures Revised (← links)
- 05000338/LER-1987-017, :on 870715,unit Manually Tripped.Caused by Indications of Steam Generator Tube Rupture in Steam Generator C.Cooldown & Depressurization of RCS Conducted Per Station Emergency Operating Procedures (← links)
- 05000338/LER-1987-014-01, :on 870617,problem Developed W/Reactor Coolant Pump (RCP) Motor Requiring Replacement.On 870618,RCP Motor Uncoupled,Resulting in Small Leak in Pump Shaft.Corrective Actions Identified to Address Inadequacies (← links)
- 05000338/LER-1998-003-02, :on 980804,noted That Ten Svc Water Pipe Supports Had Been Inspected During First ISI Interval.Caused by Personnel Error.Completed Changes to Insp Isometric Drawings & Changes to ISI Program (← links)
- 05000338/LER-1987-024, :on 871204,Kaman Vent Stack B high-range Radiation Monitor Declared Inoperable Due to Failed Microprocessor.Caused by Faulty Programmable Read Only Memory (Prom).Prom Replaced (← links)
- 05000338/LER-1987-020-01, :on 871123,reactor Trip Generated Due to Feedwater Heater 5A hi-hi Level Signal.Caused by Fatigue Failure of Spring Inside Microswitch.Level Switch Replaced & Switches Inspected W/Satisfactory Results (← links)
- 05000338/LER-1987-023-01, :on 871124,Kaman Process Vent Normal Range Radiation monitor,RI-GW-178-1,declared Inoperable.Caused by Loose Connection Between Central Processing Unit Card & Sys. Central Processing Unit Card Replaced (← links)
- 05000338/LER-1987-022-01, :on 871010,pressurizer PORV Opened Due to Actuation of Overpressure Protection Sys.Caused by Reduction in Primary Sys Temp During Inservice Insp Test.Insp Procedure Will Be Revised (← links)
- 05000338/LER-1987-015, :on 870629,reactor Tripped Due to hi-hi Level in 5A Feedwater Heater.Caused by Improper Valve line-up Due to Failure to Follow Administrative Controls for Hanging & Removing Danger Tags.Procedures Revised (← links)
- 05000338/LER-1985-003-01, :on 850319,review of Facility Main Dam & Hydro Structures Revealed Previous Studies Failed to Identify Units 3 & 4 Const Area as Potential Flood Path to Units 1 & 2 Turbine Bldg.Concrete Wall Constructed (← links)
- 05000338/LER-1987-018, :on 870819,Limitorque Motor on Valve Found to Lack Environ Qualification Documentation.Caused by Inadequate Training & Procedural Controls.Motor Replaced & Adequate Training & Controls Established (← links)
- 05000338/LER-1987-013, :on 870614,loss of Normal Power Supply to Emergency Bus Occurred During Testing.Caused by Failure to Follow Procedures.Electrical Maint Procedure Will Be Revised & Personnel Will Be Instructed (← links)
- 05000338/LER-1987-009, :on 870508,main Steam Safety Valve Setpoints Discovered Below Tech Spec Limits.Cause Unknown.Setpoints Readjusted (← links)
- 05000338/LER-1987-012, :on 870604,partial Automatic Solid State Protection Sys Actuation Occurred.Caused by Procedure Inadequacy.Procedure for Periodic Test 36.5 Will Be Revised (← links)
- 05000338/LER-1987-018-01, :on 870819,Limitorque Motor Determined to Lack Environ Qualification Documentation.Caused by Inadequate Training & Procedural Controls on Environ Qualification Requirements.Motor Replaced (← links)
- 05000338/LER-1999-006-01, :on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With (← links)
- 05000338/LER-1998-002-01, :on 980312,missed Surveillance on Charging Pump Undervoltage Relay Occurred.Caused by Inadequate Revisions to Periodic Test Procedures.Review of Potentially Applicable Periodic Test Was Performed (← links)
- 05000338/LER-1987-007-01, :on 870422,during Mode 5,RHR Sys Temporarily Lost When Power Lost on 120-volt Ac Vital Bus 1-III.Caused by Blown Fuse Resulting in Inverter Failure.Tech Spec Will Be Changed to Eliminate RHR Interlock (← links)
- 05000338/LER-1986-018-01, :on 860915,w/unit in Hot Shutdown,Reactor Trip Breakers Opened When Individual Rod Position Indicators Determined Inoperable.Caused by Failed Transformer on Firing Card.Firing Card Replaced (← links)
- 05000338/LER-1987-011, :on 870515,core Alterations Initiated W/O Operable Charging Pump & on 870516,charging Pump C Discovered Inoperable.Caused by Personnel Error.Root Cause & Corrective Actions Under Evaluation (← links)
- 05000338/LER-1986-017-01, :on 860910,single Train ECCS Actuation from lo- Lo Pressurizer Pressure Signal Occurred.Caused by Personnel Error During Performance of Solid State Protection Sys Test. Evaluation Continuing (← links)
- 05000338/LER-1986-015-01, :on 860827,manual Turbine/Reactor Trip Initiated Due to High Turbine/Generator Vibration.Caused by Turbine Blade Failure,Resulting from Excessive Stress. Turbine Operating Procedures Revised (← links)
- 05000338/LER-1987-008-01, :on 870506,one of Three Pressurizer Code Safety Valves as Found Lift Pressure Setpoints Found to Be Higher than Max Lift Setting Allowed by Tech Specs.Safety Valve Lift Determined within Limits After Adjustment (← links)
- 05000338/LER-1987-006-01, :on 870430, as Found Dropout Voltages for Undervoltage Relay Found Below Min Allowable Value Stated in Periodic Test & Immediately Recalibr.Caused by Setpoint Drift.Periodic Test Revised (← links)
- 05000338/LER-1987-005-01, :on 870419,primary Coolant I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G Limit Set by Tech Spec 3.4.8.a Following Reactor Trip.Caused by Minor Fuel Cladding Defects in Reactor Core (← links)
- 05000338/LER-1987-004-01, :on 870419,reactor Tripped from Approx 67% Power During Controlled Rampdown Into Refueling Outage. Caused by Nuclear Instrumentation Sys Power Range High Negative Flux Rate Due to Dropped Rod (← links)
- 05000338/LER-1986-008-02, :on 860520,reactor Trip Occurred Due to Closure of All Three Main Feedwater Regulating Valves.Caused by Spurious Actuation of Feedwater Isolation Relay for Feedwater Regulating Valves (← links)
- 05000338/LER-1987-001-01, :on 870127,7-day Period Allowed for Fire Pump to Be Out of Svc Exceeded.Caused by Inclement Weather & Further Repair Efforts.Pump Returned to Svc on 870213.W/ (← links)
- 05000338/LER-1987-002, :on 870213 & 16,cardreader Which Permits Access to Auxiliary Feedwater Pump House Malfunctioned & Created Potential for Unauthorized Entry to Vital Area.Cause Not Stated.Cardreader Repaired (← links)
- 05000338/LER-1997-007, :on 970818,NIS High Flux Trip Setpoint Errors Occurred.Caused by Inherent Inaccuracies Associated with Calorimetric Heat Balance at Low Power Levels.High Power Trip Setpoints Were Reduced (← links)
- 05000338/LER-1985-029, :on 851228,during Performance of RCS Leak Rate Test,Leak of 1.28 Gpm Noted.Caused by Reactor Vessel Seal Ring Leaks Chemical & Vol Control Sys Pipe Crack.Seal Rings & Pipe Replaced (← links)
- 05000338/LER-1986-014-01, :on 860814,while at 0% Power intermediate-range Reactor Trip Occurred.Caused by Faulty Electrical Jumper. Jumper Installed Per Instrument Dept Procedure IMP-C-NI-01 to Prevent High Level Flux Trip (← links)
- 05000338/LER-1986-013-01, :on 860813,while at 100% Power,Rcs Unidentified Leakage Found in Excess of Allowable Tech Spec Limits.Caused by Leak in Resistance Temp Detector Loop C Bypass Flow Element.Flow Element Isolated (← links)
- 05000338/LER-1999-005, :on 990616,potential for Continued Feed Flow to Faulted SG During MSLB Was Noted.Caused by Incorrect Assumptions.Station Deviation Rept Was Submitted (← links)
- 05000338/LER-1986-019-02, :on 861211 & 12,control Room Emergency Ventilation Sys Subsystem Flow Rates Exceeded Tech Spec 3.7.7 Limits.Caused by Lack of Procedure to Clean & Test Intake Filters.Procedure Will Be Written (← links)
- 05000338/LER-1998-006-01, :on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal (← links)
- 05000338/LER-1986-003, :on 860222,process & Ventilation Vents High Range Effluent Radiation Monitors Declared Inoperable.Caused by Inadequate Software.Software Replaced.On 860221,monitor Experienced Source Check Failure (← links)
- 05000338/LER-1999-004, :on 990413,position Switch for Suction Supply Dampers to CR Emergency Fan Was Discovered Out of Position. Cause Could Not Be Determined.Station Entered Action Statement for TS 3.7.7.1.With (← links)
- 05000338/LER-1986-007-03, :on 860729,diesel-driven Fire Pump Out of Svc Greater than 7 Days.Caused by Test Coordinating Error Which Produced Delay.Personnel Responsible Counseled to Prevent Recurrence (← links)
- 05000338/LER-1988-026-01, :on 881021,surveillance Requirement Not Performed as Required by Tech Spec 3/4.3.3.11.Caused by Inadequate Review of Amend 48.Procedure Deviation Written to 1-OP-23.2, Waste Gas Decay Tanks & Waste. (← links)
- 05000338/LER-1986-009-01, :on 860531,reactor Tripped from 100% Power. Caused by Loss of Power to 120-volt Ac Vital Bus (VB) 1-I Due to 480/120-volt Ac Transformer Failure.Power Restored. Transformers Replaced on 860606 (← links)
- 05000338/LER-1988-022-02, :on 881013,determined That Various Pipes of Safety Injection Sys & Chemical Vol & Control Sys Collected or Trapped Gas.Caused by Not Recognizing That Normally Solid Sys Would Offgas.Pump Discharge Piping Vented (← links)
- 05000338/LER-1999-003, :on 990331,potential Loss of HHSI Pumps, Occurred Due to Postulated Main CR Fire.Caused by Incomplete Understanding of Time Sensitivity of Actions Required to Avoid Potential Loss.Procedure Revised.With (← links)
- 05000338/LER-1985-003-02, :on 850319,discovered Previous Studies Did Not Identify Units 3 & 4 Const Area as Potential Flood Path. Caused by Only Partial Flooding Addressed in Updated Fsar. Corrective Actions Being Evaluated (← links)
- 05000338/LER-1986-011-01, :on 860613,semiannual Fish Sample Obtained on 840823 Exceeded Reporting Level Requirements for Cesium. Caused by Primary to Secondary Sys Leakage.Sampling Increased to Quarterly (← links)
- 05000338/LER-1986-010-01, :on 860603,diesel-driven Fire Pump Determined Inoperable During Performance of Weekly Surveillance Test. Caused by Failed Starter Motor.Replacement Starter Motor Installed (← links)
- 05000338/LER-1986-012-01, :on 860527,fire Detection Equipment for Svc Water & Fuel Oil Pumphouses Removed from Svc to Accommodate Cable Pull Associated W/Svc Water Mods & Not Returned to Svc by 860610.Hourly Fire Watch Implemented (← links)
- 05000338/LER-1998-001, :on 980108,determined That Potential to Miss Interlock Logic Surveillance Testing During Previous mid- Cycle Shutdowns Existed.Caused by Inadequate Test Design Supplied by Vendor.Info from Last Startup Reviewed (← links)
- 05000338/LER-1999-001-01, :on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with (← links)
- 05000338/LER-1985-005, :on 850503 & 05,during Full Power Operation, Semiannual Functional Test on Seismic Triaxial Response Spectrum Recorder Not Performed.Caused by Inaccessible Device.Tech Specs Changed to Delete Test (← links)
- 05000338/LER-1997-008, :on 971027,both EDGs Inoperable During Testing. Caused by TS Surveillance Requirement to Demonstrate Operability of Remaining EDG When One Inoperable.Required TS Actions Cleared Following 1J EDG Testing (← links)
- 05000338/LER-1997-006-01, :on 970731,TS 3.0.3 Was Entered When Two Individual RPIs in Same Group Were Inoperable.Caused by Inoperable Control Rod Indicators.Review of Plant Parameters to Determine Failure Was Limited to Irpi (← links)
- 05000338/LER-1985-015, :on 850930,unit Rampdown Commenced After RCS Leakages Found.Caused by Diaphragm Failure on leak-off Header Isolation Valve & Elevated Stem Temp on RHR Sys Inlet Isolation Valve.Diaphragm & RHR Valve Repaired (← links)
- 05000338/LER-1997-009-01, :on 971118,incomplete Surveillance on Solid State Protection Circuits Was Noted.Caused by Inadequate Design by Vendor.Controlling Tps Were Revised to Include Instructions to Test Affected Logic Circuits (← links)
- 05000338/LER-1978-106-03, /03L-0:on 781010,power-range Instrumentation Channel N-41 Taken Out of Svc to Facilitate Replacement of Faulty Gain Pot.Caused by Dirt in Potentiometer,Resulting in Erratic Gain (← links)
- 05000338/LER-1978-105-03, /03L-0:on 781010,axial Flux Difference Deviated Greater than 5%.Caused by Rapid Load Reduction Necessitated by Problems W/Condenser Circulating Water Valve (← links)
- 05000338/LER-1978-104-03, /03L-0:on 781009,during Mode 1,leak Detected in Steam Valve 1-MS-120 Valve Leads to Steam Generator Auxiliary Feedwater Pump 1-FW-P-2.Caused by Isolation of Steamline,Causing Pump Inoperability (← links)
- 05000338/LER-1978-093-03, /03L-0:on 781017,multiplier Divider Card Output Drifted So That steam-feedwater Flow Mismatch Would Not Trip Until Actual Value of 1,932,000 Lbs Per Hour Occurred.Caused by Electronic Drift in Card.Card Recalibr (← links)
- 05000338/LER-1988-005, :on 880113,turbine Trip,Reactor Trip & Main Feedwater Isolation Occurred.Caused by hi-hi Level in Steam Generator Which Resulted from Generator Level Oscillations. Main & Auxiliary Feedwater Secured & Restored (← links)
- 05000338/LER-1988-025-01, :on 881101,Tech Spec 3.6.2.2 Violated.Caused by One Recirculation Spray Subsystem W/One Casing Cooling Subsystem Inoperable.Functional Testing on Casing Cooling Tank Level Transmitters Stopped (← links)
- 05000338/LER-1998-007-01, :on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With (← links)
- 05000338/LER-1988-023-01, :on 881012,missed Surveillance on Penetration Fire Barriers.Caused by Failure to Adequately Review DCP 80-21.Fire Dampers Inspected & Determined to Be Fully Operable & 18 Month Fire Barriers Inspected (← links)
- 05000338/LER-1988-016, :on 880513,recirculation Spray HX Not Placed in Dry Layup as Stated in Ufsar.Reviews to Allow Wet Layup May Not Have Completely Accounted for Biological Fouling. Operations Standing Order Issued (← links)
- 05000338/LER-1986-004-01, :on 860222,main Steam Line Radiation Monitor a Experienced Failure.Caused by Low Voltage Power Supply. Monitor Low Voltage Power Supply Will Be Replaced When Parts Available (← links)
- 05000338/LER-1985-027, :on 851224,Loop B Delta T Protection Channel 11 Declared Inoperable W/Channel III in Tripped Condition. Caused by Change in Loop B Cold Leg Resistance Temp Detector.Spare Cold Leg Connected (← links)
- 05000338/LER-1998-005-01, :on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With (← links)
- 05000338/LER-1988-018, :on 880405,channel Check Surveillance for Containment post-accident Pressure Instruments Missed. Caused by Failure to Recognize That Tech Spec 3.3.3.6 Requirements Met.Tech Spec 3.3.3.6 Entered (← links)
- 05000338/LER-1998-004-01, :on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With (← links)
- 05000338/LER-1986-001-02, :on 860119,turbine/reactor Trip Occurred.Caused by Difficulties W/Positioning Turbine Overspeed Protection Controller Keyswitch.Key Replaced (← links)
- 05000338/LER-1985-024, :on 851118,setpoints for Containment Gas & Particulate Radiation Monitors Exceeded Tech Spec Limits. Caused by Procedural Errors & Inadequate Procedures.Health Physics Procedures Revised (← links)
- 05000338/LER-1998-003, :on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With (← links)
- 05000338/LER-1988-014, :on 880318,reactor Trip Signal Generated When Steam Generator C Narrow Range Level Decreased to 25%.Caused by Failure to Maintain Level Above 25% While Flow Mismatch Bistable Was in Trip.Level Restored (← links)
- 05000338/LER-1988-019-02, :on 880621,design Change Package Relocated Two Solenoid Operated Valves from Main Steam Valve House to Quench Spray Pump House.Training Will Be Provided to All Ae Performing Plant Mods (← links)
- 05000338/LER-1988-017, :on 880216,discovered That Emergency Equalizing Valves for Containment Isolation Inner Air Lock Escape Doors Had Not Been Adequately Leak Tested.Caused by Incorrect Procedure.Emergency Equalizing Valves Tested (← links)
- 05000338/LER-1988-015, :on 880322,discovered That RHR Pumps Not Tested During Steam Generator Tube Rupture Outage.Caused by Administrative Error.Station Deviation Rept Submitted to Responsible Dept to Reschedule Missed Test (← links)
- 05000338/LER-1988-013, :on 880319,turbine Trip/Reactor Trip Occurred. Caused by Electrohydraulic Fluid Control Sys Malfunction. Servo Control Valves for Four Governor Valves Replaced & Tested Satisfactorily (← links)
- 05000338/LER-1988-011, :on 880311,post-mod Testing Not Performed as Required by Two Tech Specs.Caused by Inadequacy of Original Engineering Work Request.Investigation Performed to Determine If Valves Been Stroke Time Tested (← links)
- 05000338/LER-1985-003, :on 850319,flooding Potential Not Previously Evaluated.Concrete Wall Will Be Constructed Adjacent to West Wall of Turbine Bldg.Wall Height Sufficient to Prevent Flooding Above still-water Max Flood Level (← links)
- 05000338/LER-1988-008, :on 880202,inadvertent PORV Actuation Occurred During Solid Water Operations.Caused by Pressure Transient Which Occurred When Second Reactor Coolant Pump Started. PCV-1145 Placed in Manual Position & Opened (← links)
- 05000338/LER-1987-022, :on 871010,pressurizer PORV Opened Due to Actuation of Overpressure Protection Sys.Caused by Brief Reduction in Primary Sys Temp During Performance of Inservice Insp Test of RHR Sys Valves (← links)
- 05000338/LER-1988-007, :on 880126 & 27,fire Barrier Breaches Noted. Caused by Inadequate Design/Const Controls.Fire Watches Posted in All Affected Areas & Breached Fire Penetrations Sealed (← links)
- 05000338/LER-1988-006, :on 880112,Kaman Vent Stack a Normal Range Monitor RI-VG-179-1 Declared Inoperable.Caused by Flow Inverter Board Failure.Board Will Be Replaced & Analysis Will Be Performed to Determine Root Cause (← links)
- 05000338/LER-1988-012, :on 880315,RHR Capability Lost Due to Failed solenoid-operated Valve.Caused by Failure of Containment Valve 1-CC-TV-103B to Stroke Close within the Required Time Limit.Valve Refurbished and Stroked (← links)
- 05000338/LER-1988-003, :on 880107,Tech Spec 3.3.3.1,Action Statement 35 Exceeded.Caused by Radiation Monitor 1A Being Inoperable for More than 72 H Due to Ion Chamber Problems.Grab Samples Taken & Ion Chamber & Tube Replaced (← links)
- 05000338/LER-1997-002-02, :on 970515,set Pressure for One MSSV Was Found Outside Setpoint Tolerance Due to Setpoint Variance.Mssv That Failed Was Disassembled,Inspected,Repaired,Reassembled & Tested Satisfactorily (← links)
- 05000338/LER-1988-001, :on 880103,vent Stack a Normal Range Radiation Monitor Declared Inoperable Due to High Indicated Radiation Levels.Caused by Scintillator Tube Shorting to Detector Housing.Scintillator Tube Replaced (← links)
- 05000338/LER-1987-023, :on 871124,Kaman Process Vent Normal Range Radiation Monitor Declared Inoperable.Caused by Intermittent Continuity on Central Processing Unit Card.Action Statement 35 of Tech Specs 3.3.3.1 Entered (← links)
- 05000338/LER-1988-003-03, :on 880216,emergency Equalizing Valves for Containment Isolation Inner Air Lock Escape Doors Discovered Not Adequately Tested.Caused by Incorrect Procedure in Vendor Manual.Test Satisfactorily Performed (← links)
- 05000338/LER-1988-004-01, :on 880113,discovered Resin Intrusion Into Secondary Side Water Sys.Caused by Equipment Problems in Condensate Polishing Sys.Condensate Polishing Sys Removed from Operation & Cleanup Procedure Performed (← links)
- 05000338/LER-1978-085-03, /03L-0 on 780830:Testing of Quench Spray Pump 1-QS-P-1B Showed Pressure Drop of Over 10psi on the Suction Line During Oper,Caused by Wooden Dam in Piping. (Encl to 7810030071) (← links)
- 05000338/LER-1985-013, :on 850827,dynamic Range Train a Channel of Reactor Vessel Level Indication Sys Declared Inoperable, Effective 850819.Caused by Personnel Error in Identifying Mistake.Appropriate Tech Spec Action Performed (← links)
- 05000338/LER-1985-030, :on 851231,firearm Discovered by Security Personnel on Top of Duffle Bag Under Jacket Belonging to Util Employee.Firearm Confiscated.Investigation Revealed Firearm W/Employee Belongings by Accident (← links)
- 05000338/LER-1985-023, :on 851216,during Cold Shutdown & Vented RCS, Safety Injection Accumulators a & B Partially Injected Into Rcs.Caused by Lack of Info Re Accumulator Discharge Valves. Danger Tag Placed on Valve Supply Breakers (← links)
- 05000338/LER-1985-025, :on 851219,during Mode 5 RCS Heatup,Rcs Pressure Exceeded Lift Setting of Pressurizer Porv.Cause Unstated.Licensed Operator Training Will Put Addl Emphasis on Solid Water Operation Pressure Transients (← links)
- 05000338/LER-1986-006-01, :on 860326,trip from 100% Power Occurred.Caused by Safety Injection Due to Closure of Main Steam Line Trip Valve B.Ruptured Diaphragms Replaced (← links)
- 05000338/LER-1997-004-01, :on 970524,found Hi-Hi Alarm Setpoint for 1-RM-RMS-160 Out of Tolerance Due to Personnel Error. Instrumentation & Control Supervisor Coached Dept Personnel on Importance of Self Check (← links)
- 05000338/LER-1997-005-01, :on 970519,determined That eddy-current Testing Results Did Not Match Signatures Reported During Preservice Baseline Testing,Due to Personnel Error.Verified Current Signatures on Duplicate eddy-current Testing (← links)
- 05000338/LER-1996-004, :on 960910,identified Seismic Concerns Re Containment Particulate & Gaseous Radiation Monitors.Caused by Personnel Error in Understanding Regulatory Requirements. Performed Review of Design Changes (← links)
- 05000338/LER-1997-003-01, :on 970516,positive Reactivity Addition During Refueling Was Determined.Caused by Personnel Error.Control Room Crews Were Coached on Positive Reactivity Effect of Filling Cavity from R ST When RCS Is Greater (← links)
- 05000338/LER-1984-024-01, :on 841206,QA Audit Identified Five Periodic Tests Not Performed within Required Surveillance Intervals. Caused by Communication Breakdown Between Depts.Process to Track Overdue Tests Being Reviewed (← links)
- 05000338/LER-1986-002-03, :on 860223,reactor/turbine Trip Occurred from 100% Power.Caused by Turbine Control Sys Malfunction.Exact Cause Undetermined.Sys Tested Satisfactory & Unit Restarted (← links)
- 05000338/LER-1985-022, :on 851205,firearm Discovered & Confiscated by Security Personnel in Access Area.Employee Retained, Searched,Questioned & Escorted Offsite.Firearm in Duffle Bag by Accident,Based on Polygraph Test (← links)
- 05000338/LER-1985-017, :on 850917,reactor/turbine Trip Manually Initiated Due to Control Rods Dropping Into Core.Caused by Intermittent Fault in Alarm Circuit Cards.Cards Replaced on 850918 (← links)
- 05000338/LER-1985-020-01, :on 851118,eddy Current Insps of Steam Generator C Identified More than 1% of Sampled Tubes as Defective.Cause Under Investigation by Westinghouse.Tubes Plugged (← links)
- 05000338/LER-1986-003-01, :on 860222,process Vent & Ventilation Vents a & B Noble Gas High Range Effluent Radiation Monitors Declared Inoperable.Caused by Inadequacy of Instrument Software. Long-term Corrective Actions Undetermined (← links)
- 05000338/LER-1997-001-03, :on 970312,auxiliary Svc Water Pump Bolts Exceeded Design Basis Allowable Due to Personnel Error. Asw Pumps Were Declared Inoperable (← links)
- 05000338/LER-1985-010-01, :on 850814,PORVs Momentarily Opened Twice, Limiting RCS Pressure Below Tech Specs.Caused by Adjustments Made to Stabilize RCS Pressure After Reactor Coolant Pump Start.Procedures Revised to Decrease PORV Lift (← links)
- 05000338/LER-1985-019-01, :on 851024,turbine Trip Initiated Due to Loss of Reactor Coolant Pump Motor Cooling Water Flow & Elevated Motor Bearing Temps.Caused by Fault in Battery Room 1-III Supply for Motor.Breaker Tested (← links)
- 05000338/LER-1985-021-01, :on 851122,health Physics Supervisor Realized Clarifier Demineralizer Out of Svc When Tech Spec 3.11.1.3 Required Sys to Be in Svc.Evaluation of Methods to Increase Cesium Removal Capabilities Initiated (← links)
- 05000338/LER-1985-009-02, :on 850813,three Alarms Failed to Actuate as Required by Containment Max Triaxial Response Spectrum Functional Test.On 850823,time-history Accelerograph Could Not Be Deciphered Due to Electrical Noise (← links)
- 05000338/LER-1985-014, :on 850909,station Employee W/Restricted Clearance Had Unauthorized Access to Station Vital Areas. Caused by Improperly Encoded Key Card.New Badge Number Issued to Employee.Key Cards Checked (← links)
- 05000338/LER-1984-012-03, :on 840925,Fuel Cycle 5 Moderator Temp Coefficient Determined More Positive than Tech Specs Allow. Interim Control Rod Withdrawal Limits Implemented (← links)
- 05000338/LER-1996-010, :on 961024,automatic RT Occurred Due to Failed Generator Negative Phase Sequence Relay.Shipped Sgc Relay & Test Results to Mfg for Further Evaluation (← links)
- 05000338/LER-1996-009, :on 961010,determined Missed Surveillance Occurred W/Reactor Trip Bypass.Caused by Inadequate Surveillance Test Procedures.Revised Procedure Controlling Reactor Trip Bypass Breaker (← links)
- 05000338/LER-1985-011-01, :on 850918,emergency Diesel Generator 1J Tripped on High Crankcase Pressure & Repairs Not Completed within 72 H,Causing Cold Shutdown on 850921.Caused by Cracked Cylinder Liner.Liner Replaced (← links)
- 05000338/LER-1985-018, :on 850917,expiration of Reactor Operator License Discovered.Caused by Administrative Error. Administrative Controls for License Expiration Date Tracking Sys Will Be Reviewed & Revised as Required (← links)
- 05000338/LER-1985-016, :on 850911,RCS Loop B Bypass Line motor- Operated Valve Leak Exceeded Tech Spec Limits.Cause Unstated.Maint Performed on 850913 Resulting in Acceptable Leak Rate (← links)
- 05000338/LER-1985-005-01, :on 850503,semiannual Functional Test on Seismic Triaxial response-spectrum Recorders Not Performed. Caused by Inaccessibility During Power Operation.Change in Surveillance Test Requirement Requested (← links)
- 05000338/LER-1985-001-03, :on 850613,motor Driven Fire Pump Removed from Svc as Result of Maint Activity for Greater than 7 Days.Pump Returned to Operable Status on 850628.Fire Suppression Sys Operable During Event (← links)
- 05000338/LER-1983-036-03, /03L-0:on 830528,29,31 & 0607,during Startup from Mode 3 to 100% power,22 Individual RPIs Deviated from Group Demand Position.Caused by Instrument Drift Due to Temp Variations.Rpis Recalibr (← links)
- 05000338/LER-1996-006-01, :on 961003,charging Pump Interlock Logic Renders Pumps Inoperable.Caused by Design Error.Action Statement Was Entered on Both Units to Prevent Susceptable Pump line-up (← links)
- 05000338/LER-1996-008, :on 960926,identified Component Cooling Water Surge Tank Not Seismically Qualified When Tank Level Full. Caused by Personnel Error.Issued Justification for Continued Operation & Completed Design Mods (← links)
- 05000338/LER-1985-005-02, :on 850503,surveillance Not Performed on Seismic Triaxial response-spectrum Recorder.Caused by Inaccessibility During Power Operations.Test Will Be Performed During Next Refueling Outage (← links)
- 05000338/LER-1996-007-01, :on 960924,discovered TS Surveillance Failed to Include Functional Test of High Oxygen Alarm Associated W/ Waste Gas Decay Tank Hydrogen/Oxygen Analyzer.Surveillance Test Revised (← links)
- 05000338/LER-1996-004-01, :on 960910,seismic Concerns Were Noted Re Containment Particulate & Gaseous Radiation Monitors.Caused by Personnel Error.Rms Were Declared Inoperable & RCS Leak Rate Calculations Were Initiated (← links)
- 05000338/LER-1993-001-01, :on 930117,equalization Valve for Personnel Hatch Outer Door Escape Lock Was Discovered Open During Core Alterations.Caused by Personnel Error.Operations Re Core Alterations Suspended & Valve Closed (← links)
- 05000338/LER-1993-003, :on 930122,three CRD Mechanism Cooling Fan Timers Drifted Outside Setpoint Tolerance Limits Specified in TS Table 4.8-1.Caused by Poor Repeat Accuracy of Agastat 2400/7000 Time Delays.Relays Reset (← links)
- 05000338/LER-1993-002, :on 930120,as-found Set Pressures for One Pressurizer Safety Valve & Two MSSVs Found Outside TS Setpoint Tolerances.Caused by Setpoint Drift.Valves Will Be Refurbished at Wyle Labs (← links)
- 05000338/LER-1985-007-01, :on 850528,pressure/fire Seal 1DH002PB1 Found Open.Fire Watch Established & Boundary Resealed After New Cable Pulled.Administrative Procedure Training for Const Personnel Upgraded (← links)
- 05000338/LER-1992-015-01, :on 921029,determined That SW Isolation Valves Servicing MCR & Emergency Switchgear Room Chiller Condenser Not Verified Per TS 4.7.4.1.(a),due to Personnel Error.Rev to Periodic Tests Will Be Performed (← links)
- 05000338/LER-1984-009, :on 840911,motor Driven Fire Pump Not Returned to Svc within 7 Days Allowed by Tech Spec 3.7.14.1.Caused by Failure of Isolation Butterfly Valve Disk.Valves to Be Replaced W/Stainless Steel Internals (← links)
- 05000338/LER-1992-016-01, :on 921203,two Conditions Outside of TS 3.3.1.1,Table 3.3-1 Action 2.(a) & 3.6.2.2 Occurred.Caused by Inadequate Initial Development of Test Procedures.Change to TS Initiated (← links)
- 05000338/LER-1985-006-02, :on 850528,diesel Driven Fire Pump Became Inoperable.Caused by Engine Coolant Hose Rupture During Performance of Weekly Surveillance Test.Pump Repaired & Returned to Svc (← links)
- 05000338/LER-1979-148-01, /01T-0:on 791218,stress on Pipe Hangers CC-450 & CC-37 Exceeded Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Calculations.Weights Changed. Hanger Will Be Modified (← links)
- 05000338/LER-2020-001-01, For North Anna Power Station, Unit 1, Degraded Upper Cylinder Piston Pin Bushing Discovered During Maintenance Activities on Emergency Diesel Generator (← links)
- 05000338/LER-2020-001, For North Anna Power Station, Unit 1, Degraded Upper Cylinder Piston Pin Bushing Discovered During Maintenance Activities on Emergency Diesel Generator (← links)
- 05000338/LER-1985-004, :on 850328,depth of Compacted Backfill Over Svc Water Sys Supply & Return Piping Between Svc Water Pumphouse & Safeguards Area Determined Less than 6 Ft Required for Tornado Missile Protection (← links)
- 05000338/LER-1985-004-02, :on 850328,determined That Compacted Backfill Depth Over Svc Water Sys Supply & Return Piping Did Not Meet 6-ft Min Limit Required for Tornado Missile Protection. Cause Not Stated.Depth Corrected on 850329 (← links)
- 05000338/LER-1992-013-01, :on 921021,determined That ESF Response Time Testing for AFW Pump Not Performed.Caused by Personnel Error,Resulting in Inadequate Surveillance Test Procedure. Testing Performed & Procedures Revised (← links)
- 05000338/LER-1992-012-01, :on 920925,determined That Two Ci Instrument Air Supply Trip Valves Not Tested Per TS 4.6.3.1.2.(a),due to Personnel Error.Changes to Periodic Test Procedure Will Be Made During Next Refueling Outage (← links)
- 05000338/LER-1984-026, :on 841231,reactor Trip/Turbine Trip Occurred from 100% Power.Caused by Failed Firing Card in Rod Control Sys That Allowed Four Control Rods to Drop Into Core.Failed Firing Card Replaced & Startup Commenced (← links)
- 05000338/LER-1984-010, :on 840728,insp Revealed Valves W/Torque Switch Settings Different from Specified Setpoints.Caused by Using Superseded Settings & Confusion of Torque Switch Design.Setpoint Document Revised (← links)
- 05000338/LER-1992-010-01, :on 920714,discovered That EDG Fuel Oil Transfer Lines Not Missile Protected.Caused by Inadequate Initial Design of Plant.Abnormal Procedure 0-AP-41 Revised, Requiring Roving Watch of Subj Transfer Lines (← links)
- 05000338/LER-1996-005-02, :on 960827,reactor Trip Experienced from 100% Power.Caused by Failure of CR Drive Sys.Operations Emergency Procedure E-O, Reactor Trip or Safety Injection Was Entered (← links)
- 05000338/LER-1984-024, :on 841206,five Periodic Tests (PT) Not Performed within Required Surveillance Intervals.Caused by Breakdown in Communications Between Depts.Enhancements to PT Tracking Sys Being Developed (← links)
- 05000338/LER-1984-023-01, Has Been Canceled (← links)
- 05000338/LER-1984-017-01, :on 841005,five Workers Remained in Posted High Radiation Area W/O Proper Health Physics Coverage Required by Radiation Work Permit.Caused by Personnel Error.Health Physics Technician Terminated (← links)
- 05000338/LER-1996-001-01, :on 960216,MS & Pressurizer SV Setpoints Out of Tolerance Due to Setpoint Drift.Adjusted Pressurizer SVs 01-RC-SV-1551A & 01-RC-SV-1551C (← links)
- 05000338/LER-1984-016-01, :on 841005,employee Exposed to More than 1.250 Rem During Third Quarter 1984 Failed to Complete Form NRC-4. Training Dept Instructed to Emphasize Importance of Info Disclosure.Proprietary Details Withheld (← links)
- 05000338/LER-1984-014-02, :on 840928,turbine trip-reactor Trip Occurred. Caused by Incomplete Closure of Main Feed Regulating Valve & Main Feed Line Motor Operated Block Valve.Power Supply Card Replaced & Range Flux Detectors Adjusted (← links)
- 05000338/LER-1984-009-02, :on 840911,motor Driven Fire Pump Removed from Svc Due to Low Discharge Pressure.Caused by Pump Runout Failure of Isolation Butterfly Valve Disk.Recirculation Valve Replaced & Pump Tested (← links)
- 05000338/LER-1984-022, :on 841127,fire Protection Sys Main Header Ruptured,Causing Sys to Be Inoperable.Caused by Pipe Crack Probably Occurring During Installation.Ruptured Section of Pipe Replaced (← links)
- 05000338/LER-1984-013, :from 840910-25,liquid Radwaste Discharged W/O Treatment W/Projected Doses to Unrestricted Areas in Excess of Limits Specified in Tech Spec 3.11.1.3.Caused by Inadequate Checking of Demineralizers (← links)
- 05000338/LER-1984-025-01, :on 841217,fire Detection Sys for Emergency Switchgear & Air Conditioning Rooms Did Not Meet Operability Requirements.Cause Not Stated.Fire Watch Established (← links)
- 05000338/LER-1984-019, :on 841114,trip from 100% Power Occurred Due to Vital Bus Inverter Failure.Inverter Was Supplying Power to 125-volt Ac Vital Bus 1-III.Caused by Deenergization of Bus & Associated Equipment (← links)
- 05000338/LER-1996-003, :on 960314,mode 3 Entry with Inoperable Redundant Heat Trace Circuit.Caused by Personnel Error.C/A: Redundant Heat Trace Replaced,Tested & Returned to Svc on 960315 (← links)
- 05000338/LER-1992-014, :on 920608,noted That EDG Response Time Test Procedures Did Not Include Circuit Between 27W Relay & EDG CO2 Trouble Alarm Due to Personnel Errors.Complex Instrumentation SRs Being Reviewed (← links)
- 05000338/LER-1984-021-01, :on 841125,reactor Trip/Turbine Trip Occurred from 100% Power.Caused by Low Level Coincident W/Steam Flow/Feed Flow Mismatch Due to Failure of Controller Power Supply Card.Card Replaced (← links)
- 05000338/LER-1996-002, :on 960303,containment Particulate & Gaseous Radiation Monitors Inoperable.Caused by Inadequate Review of Containment Gaseous & Particulate Radiation Monitor. Suppl & Exhaust MOVs Shut (← links)
- 05000338/LER-1984-020-01, :on 841118,reactor Trip Occurred.Caused by Performing Overspeed Protection Controller Test Outside Normally Prescribed Procedure Sequence.No Repairs or Replacements Required Prior to Restart (← links)
- 05000338/LER-1984-010-02, :on 840722,insp of Torque Switch Settings of Five Motor Operated Valves Revealed Three Valves Had Torque Switch Settings in Excess of Tech Spec Setpoint (← links)
- 05000338/LER-1984-019-01, :on 841114,loss of Power to Relay Which Senses Reactor Coolant Pump C Breaker Position Caused Reactor Trip. Caused by Vital Bus Inverter Failure Due to Damaged SCRs & Blown Fuse (← links)
- 05000338/LER-1992-004, :on 920226,inadvertent RPS Trip Signal Resulted During Turbine Trip Response Time Test.Caused by Personnel Error & Unclear Procedure Language.Individual Counselled & More Precise Procedure Instruction Submitted (← links)
- 05000338/LER-1984-022-01, :on 841127,main Header Ruptured,Causing Inoperability of Fire Protection Sys.Cause Unknown.Fire Main Pipe Replaced (← links)
- 05000338/LER-1992-011-01, :on 920724,discovered That Test Procedures for ECCS Did Not Include Verifying Safety Injection Throttle Valves Tagged in Proper Position.Caused by Personnel Error. Throttle Valves Properly Tagged (← links)
- 05000338/LER-1984-018-01, :on 841012,turbine & Reactor Trip Occurred Due to Loss of Electro Hydraulic Control Sys Control Power. Caused by Technician Unfamiliarity W/Equipment.Technician Counseled (← links)
- 05000338/LER-1985-002-02, :on 850128,eight Check Valves in post-accident Hydrogen Removal Sys Discovered Not Tested as Required by Station Valve Inservice Testing Program.Caused by Loss of Administrative Control.Addl Resources Assigned (← links)
- 05000338/LER-1995-004-02, :on 950907,missed Surveillance of N-16 Monitors Occurred.Caused by Result of Being Unaware N-16s Inoperable. Selector Switch Operated to Both Ni Selector Positions & Proper Power Levels Obtained/Restored (← links)
- 05000338/LER-1992-009, :on 920402,surveillance on Containment Purge & Exhaust Isolation Sys Missed & PORV Alarm Actuated Due to Personnel Error During Procedure Development.Addl Review of Other Complex Instrumentation Being Performed (← links)
- 05000338/LER-1984-006-03, :on 840801,air Cooling & Purging Sys Galvanized Ductwork & Supports Improperly Coated to Mitigate Corrosion. Caused by Insufficient Controls Due to Ductwork Painting Designated nonsafety-related (← links)
- 05000338/LER-1984-007-01, :on 840802,17 Cycle 4 Fuel Assemblies Determined to Be Leaking Based on Sipping Exams.Possibly Caused by Primary Hydriding,Debris Induced Fretting,Weld & Stress Related Defects.Evaluation Incomplete (← links)
- 05000338/LER-1992-008, :on 920319,both Channels of Auxiliary Feedwater Pump Station Blackout Automatic Start Circuit Defeated.Caused by Executing Inadequate Procedure.Test Terminated & Relays Returned to Svc (← links)
- 05000338/LER-1992-006, :on 920305,manual Reactor Trip Initiated When Group 2 of Control Bank B Dropped Into Core from 80 Steps. Caused by Failure of CRD Mechanism Firing Card.Trip Breakers Manually Opened & Card Inspected (← links)
- 05000338/LER-1991-020, :on 911031,discovered Shared Svc Water Sys May Not Have Been Able to Provide Design Flow to Accident Unit Recirculation Spray Hxs.Caused by Personnel Error.Spray Valves Opened (← links)
- 05000338/LER-1990-012-01, :on 901204,discovered That Remote Potential Existed for Operation of Shared Svc Water Sys in Unanalyzed Condition.Caused by Personnel Error.Applicable Procedures Will Be Revised (← links)
- 05000338/LER-1984-013-02, :on 840910-25,liquid Radwaste Discharge to Unrestricted Areas in Excess of Tech Spec Limits & Clarifier Effluent Discharged W/O Treatment.Caused by Inadequate Controls (← links)
- 05000338/LER-1984-011-01, :on 840914,pressurizer PORV Automatically Opened Three Times During Pressure Transient.Caused by Overpressurization.Discussion of Event Will Be Included as Part of Licensed Operator Retraining (← links)
- 05000338/LER-1984-008-02, :on 840901,radial Flaws Discovered During Insp of HX Lap Rings.Caused by Cracking Due to Chloride Induced Stress Corrosion.Stainless Steel Installed at Point of Lap Ring (← links)
- 05000338/LER-1992-003, :on 920121,determined That RHR Sys Suction Relief Valve Discharge Piping Arrangement May Not Pass Design Flowrate.Caused by Design Deficiency.Ts Change Package Developed to Raise RHR Temp (← links)
- 05000338/LER-1992-005, :on 920113,timers Drifted Outside Setpoint Tolerance Listed,Per Tech Spec Table 4.8-1.Caused by Setpoint Drift.Timers Reset & Successfully Retested.W/ (← links)
- 05000338/LER-1992-001-01, :on 920110,during SG Tube Inspection Outage, Defective Tubes Identified.Caused by Primary Water Stress Corrosion & Stress Corrosion Cracking.Defective Tubes Replaced (← links)
- 05000338/LER-1992-002-01, :on 920110, as Found Set Pressure for a Pressurizer Safety Valve Found Outside Setpoint Tolerence Due to Setpoint Drift.Safetyvalves Will Be Repaired & Readjusted as Necessary (← links)
- 05000338/LER-1991-023, :on 911227,w/unit in Cold Shutdown,Pzr Level Increased from 60 to 82% Cold Calibr Level.Caused by Personnel Error Due to Failure to Maintain Configuration Control After Type C Test.Personnel Cautioned (← links)
- 05000338/LER-1984-005-02, :on 840202,QC Inspector Discovered Solenoid Valve Conduit Seals Had Been Improperly Installed on Containment Isolation Valves.Caused by Personnel Error. Valves Inspected & Resealed (← links)
- 05000338/LER-1991-022-01, :on 911223,unit Shutdown Initiated Due to Indeterminate Status of SGs as Result of Eddy Current re- Review.Comprehensive Eddy Current Insp Plan Developed.W/ (← links)
- 05000338/LER-1991-020-01, :on 911031,discovered That Shared Svc Water Sys May Not Have Been Able to Provide Design Flow to Accident Unit Recirculation Spray Hxs.Caused by Personnel Error.Svc Water Pump B Returned to Automatic Operation (← links)
- 05000338/LER-1984-004-01, :on 840501,preliminary Results of Fire Protection Program Indicated Inadequacies in Six Categories, Including Separation,Fire Dampers,Fire Doors,Fire Suppression & Emergency Lighting (← links)
- 05000338/LER-1992-007, :on 920306,determined That Reactor Coolant Pump Bus Monthly Undervoltage & Underfrequency Channel Functional Tests Not Performed Per Ts.Caused by Personnel Error.Channel Calibr Test Temporarily Changed (← links)
- 05000338/LER-1991-010, :on 910423,auto Start of Emergency Diesel Generator 1J Occurred.Caused by Loss of Power from RSST a & Subsequent Start Due to Inadvertent Bypass of Air Start of Sov.Procedures Revised (← links)
- 05000338/LER-1991-021-01, :on 911126,discovered That Emergency Diesel Generator Battery Had Individual Cell Voltage Less than TS Low Limits.Caused by Addition of Water to Cells W/Low Electrolyte Levels.Battery Charged (← links)
- 05000338/LER-1991-019-01, :on 910903,discharge Relief Valve Lifted & Did Not Reseat Until After Pump Was Secured.Caused by Inadequate Maint Procedure.Procedure Revised.Blow Down Ring on Relief Valves Set Properly.Valves Sucessfully Tested (← links)
- 05000338/LER-1983-059-03, /03L-0:on 830918,while at 100% Power,Inner Seal on Containment Personnel Hatch Failed to Pass Periodic Test Following Containment Entry.Caused by Dirt Buildup on Seal. Seal Cleaned,Relubricated & Tested (← links)
- 05000338/LER-1981-062-03, Util Notified That 15 Block Walls in Fuel Bldg Did Not Meet Design Requirements of IE Bulletin 80-11.Caused by Refinement in Masonry Wall Design.Block Walls to Be Replaced (← links)
- 05000338/LER-1983-045-03, /03L-0:on 830628,containment Average Temp Exceeded 105 F Twice for Less than 4 H.First Temp Spike Caused by Mechanical Chiller Tripping on High Lube Oil Temp & Second Caused by Loss of Bearing Cooling to Chiller (← links)
- 05000338/LER-1991-017, :on 910808,main Steam Trip Valve a Shut,Causing Safety Injection & Reactor Trip.Caused by Water Entering Control Relay Junction Box for Valve.Rupture Discs Replaced & Defective Gutter Properly Sealed (← links)
- 05000338/LER-1981-063-03, Reactor Trip Breaker B Failed to Open When High Pressurizer Pressure Signal Simulated.Caused by Failure of Metal Latch in Undervoltage Trip Attachment.Attachment Replaced (← links)
- 05000338/LER-1979-001-01, /01T-0 on 790115:non-conservatism Identified in Calculations Performed in Monitoring Axial Power Distribution Fj(Z).Caused by Omission of Sys & Procedures Used to Monitor Fj(Z) (← links)
- 05000338/LER-1983-084-03, /03L-0:on 831202,fire Door Between Clean Charge Room & Auxiliary Bldg Would Not Latch Automatically.Caused by Loose & Missing Screws on Door Hinges.Screws Tightened & Missing Screws Replaced (← links)
- 05000338/LER-1983-086-03, /03L-0:on 831209,w/unit at 100% Power,Open Penetration Discovered in Fire Wall Between Motor Driven Auxiliary Feedwater Pump Room & Steam Driven Auxiliary Feedwater Pump Room.Wall Not Included in Test (← links)
- 05000338/LER-1983-082-03, /03L-0:on 831121,outer Seal on Containment Personnel Hatch Failed to Pass Periodic Test Following Entry.Caused by Accumulation of Dirt on Seal.Seal Cleaned & Relubricated (← links)
- 05000338/LER-1983-081-03, /03L-0:on 831118,individual Rod Position Indication for Channels M-10,F-06 & L-11 Deviated from Group Demand Position by Greater than 12 Steps.On 831120,channel 1-03 Deviated.Caused by Instrument Drift (← links)
- 05000338/LER-1983-083-03, /03L-0:on 831122,open Penetration Hole Discovered Between Safeguards Bldg & Quench Spray Pump House.Caused by Personnel Error.Continuous Firewatch Posted Immediately. Opening Filled (← links)
- 05000338/LER-1983-080-03, /03L-0:on 831118,following Rampdown & trip,I-131 Dose Equivalent Specific Activity Exceeded Tech Spec Limits. Caused by Minor Fuel Element Defects in Reactor Core.No Corrective Action Required (← links)
- 05000338/LER-1991-018, :on 910814,determined That EDG Time Response Testing Performed on 74% Undervoltage Instead of 72% as Required by Tech Specs.Caused by Personnel Error.Time Response Test Procedures Revised (← links)
- 05000338/LER-1983-074-03, /03L-0:on 831106,steam Generator C Channel I Level Indication Drifted High Out of Specified Tolerance.Caused by body-to-bonnet Leakage of Ref Leg Root Valve.Valve Leak Stopped (← links)
- 05000338/LER-1983-076-03, /03L-0:on 831101,individual Rod Position Indication for Channel N-09 Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift.Channel Recalibr (← links)
- 05000338/LER-1995-003-01, :on 950327,pressurizer Cooldown & Heatup Temps Exceeded TS Limits Due to Transient.Energized Pressurizer Heaters to Heat Incoming Water to Pressurizer as Result of SI Functional Test (← links)
- 05000338/LER-1991-016, :on 910722,charging Pump Temporary Flow Meter Discovered Outside ASME XI Accuracy Requirements.Caused by Personnel Error.Charging Pump Ref Data Measured W/Miniflow Recirculation Line Isolated (← links)
- 05000338/LER-1983-079-03, /03l-0:on 831020,leakage Observed from body-to- Bonnet Region of Loop Isolation Valve 1-RC-87.Caused by Excessive Boric Acid Corrosion in Studs.Valve Reparied & RCS Pressure Reduced to 2,235 Psig (← links)
- 05000338/LER-1983-067-03, /03L-0:on 831017,both Level Indicators for ECCS Accumulator Tank B Improperly Calibr,Resulting in Indicated Level Reading Higher than Actual Level.Caused by Instrument Drift (← links)
- 05000338/LER-1983-077-03, /03L-0:on 831017,three Snubbers Failed Visual Insp Periodic Tests.Two Found W/Uncovered Hydraulic Fluid Ports & Third W/Low Oil Level.Snubbers Replaced (← links)
- 05000338/LER-1983-078-03, /03L-0:on 831019,w/unit in Mode 3,RCS Loop 3 Temp Narrow Range Indicated 10 F Lower than RCS Loops 1 & 2. Caused by Valve Leakage.Supervisor Reinstructed (← links)
- 05000338/LER-1983-073-03, /03L-0:on 831028,containment Average Temp Dropped Below 86 F.Caused by Component Cooling Water to Containment Cooling Coils Dropping 20 F.Large Heat Load Changing Procedure Will Be Revised (← links)
- 05000338/LER-1983-060-03, /03L-0:on 831011,carbon Dioxide for Fuel Oil Pump Room 1 Did Not Discharge Automatically When Temp Sensor Heated Above Setpoint During Periodic Test.Caused by Fouling of Pilot Control Valve.Valve Replaced (← links)
- 05000338/LER-1983-072-03, /03L-0:on 831011,during 18-month Valve Operability test,HCV-1200B (Containment Isolation Valve for RCS Letdown) Stroked Closed Longer than 10 Max Required Time.Caused by Dry Packing & Dirty Stem (← links)
- 05000338/LER-1983-022-03, Review of ASME XI Iwv Program Identified 126 Valves Exercised &/Or Stroke Timed at Incorrect Frequency.Caused by Implementation of Fragmented Program (← links)
- 05000338/LER-1983-071-03, /03L-0:on 831009,w/unit in Mode 5,one Train of RCS Low Temp Overpressurization Protection Sys Taken Out of Svc. Caused by Vent Valve Malfunction in Liquid Nitrogen Plant, Making Train Unavailable for Nitrogen Makeup (← links)
- 05000338/LER-1983-075-03, /03L-0:on 831013,Fire Door S54/11,between Unit 1 Turbine Bldg & Unit 2 Emergency Switchgear Room,Failed to Latch.Caused by Misaligned Striker.Continuous Fire Watch Posted.Latch Repaired (← links)
- 05000338/LER-1983-070-03, /03L-0:on 831002,one of Two Inservice Control Room Bottled Air Banks Dropped Below Min 2,300 Psig Pressure. Caused by Open High Pressure Unloader Valve Check Valve Failing to Prevent Backflow.Valve Replaced (← links)
- 05000338/LER-1983-064-03, /03L-0:on 830928,steam Generator B Main Steam Trip Valve TV-MS-101B Required Greater than 2 Minutes to Close When Actuated from Control Room.Caused by Corrosion at Check Valve.Valve Cleaned (← links)
- 05000338/LER-1983-069-03, /03L-0:on 831002,Channel III of Steam Generator Level C Drifted High Erratically.Caused by Leaking Vent Valve.Valve Replaced During Scheduled Maint Outage (← links)
- 05000338/LER-1983-068-03, /03L-0:on 830930,while Attempting to Increase Turbine Speed,Rcs Temp Fell Rapidly to 538 F Which Manually Tripped Reactor.Caused by Excessive Steam Flow to Turbine Generator.Speed Sensor Replaced (← links)
- 05000338/LER-1983-062-03, /03L-0:on 830925,containment Sump Pump Discharge Isolation Valve TV-DA-100B Would Not Fully Close Either Automatically or Manually from Control Room.Caused by Mechanical Binding.Limit Switch Arm Realigned (← links)
- 05000338/LER-1983-065-03, /03L-0:on 830928,RCS Unidentified Leakage Exceeded 1 Gpm.Cause Not Stated.After Leakage Quantified & Verified Not to Be Pressure Boundary Leakage,Unidentified Leakage Decreased.Identified Leakage Increased (← links)
- 05000338/LER-1983-066-03, /03L-0:on 830929,during Startup,Six Individual Rod Position Indicators Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift. Indicator Channels Recalibr (← links)
- 05000338/LER-1983-063-03, /03L-0:on 830928,post-reactor Shutdown Specific Activity Samples of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit.Caused by post-trip Enhancing Release of Fission Fragments (← links)
- 05000338/LER-1984-003-02, :on 840208,turbine trip-reactor Trip Occurred Due to Spurious electro-hydraulic Control Fluid Reservoir Low Level Turbine Trip Signal.Caused by Pump Vibration Due to Unloader Malfunction.Unloaders Readjusted (← links)
- 05000338/LER-1983-057-03, /03L-0:on 830903 & 12,Fire Door S71-19 Between Emergency Diesel Room 1H & Turbine Bldg Would Not Latch. Caused by Faulty Latching Mechanism & Misalignment.Latch Repaired & Realigned (← links)
- 05000338/LER-1984-002, :on 840118,RCS Vented to Containment Atmosphere & Single Train Inadvertent ECCS Actuation Occurred at 110 F During Removal of Solid State Protection Sys Output Fuses. Caused by Lack of Procedural Guidance (← links)
- 05000338/LER-1995-001-01, :on 950127,ESF Actuated Due to Automatic RT on Low Flow in RCS B Loop.Emergency Procedure 1-E-0,RT & SI Was Entered (← links)
- 05000338/LER-1995-002-01, :on 950203,one Train of Ssps on Each Unit Declared Inoperable & Appropriate Action for TS 3.3.2.1 Entered.Caused by Original HELB Analysis Not Evaluating Potential Failure.Design Changes Implemented (← links)
- 05000338/LER-1984-001, :on 840109,plant Shut Down Due to High RCS Unidentified Leakage.Caused by Defective Tubes & Leaking Tube Plugs.Tubes Plugged & Leaking Plugs Repaired (← links)
- 05000338/LER-1983-038-03, /03L-0:on 830606 & 07,intermediate Range Channels N36 & N35 High Neutron Flux Reactor Trip Setpoints Found Higher than Tech Spec Limits.Caused by Administrative Error. Intermediate Range Setpoints Reduced (← links)
- 05000338/LER-1983-006-03, /03L-0:on 830125,triaxial Peak Accelegraphs on RHR HX & Safety Injection Pipe Found Inoperable from Corrosion Damage on Internal Parts.Caused by Moisture Entering Accelegraphs.Units Replaced (← links)
- 05000338/LER-1983-085-03, /03L-0:on 831220,discovered Thermal Power Containment Pressure Channel IV Drifting & Causing Intermittent Alarms.Possibly Caused by Dirt in Feedback Coil.Transmitter Cleaned (← links)
- 05000338/LER-1991-014, :on 910703,determined That ASME Section XI Surveillance Requirements Inadequately Performed for Four Boric Acid Transfer Pumps During Second Quarter 1991.Caused by Personnel Error.Generic Ltr 89-04 Reviewed (← links)
- 05000338/LER-1991-013, :on 910522,determined That Stroke Time Surveillance Requirements for Closed Direction Testing of 4 Quench Spray Pump Discharge MOVs Not Performed.Caused by Personnel Error.Valves Stroke Tested (← links)
- 05000338/LER-1991-012, :on 910520,auxiliary Feedwater Pump auto-start Signal Received.Caused by Personnel Error.Steam Generator Returned to Normal,Feedwater Isolation Reset & Breakers Closed to Restore Feed Capabilities (← links)
- 05000338/LER-1991-011, :on 910511,source of Leakage Identified Between B Cold Leg Loop Stop Valve & Isolation Valve for 3/4 Inch Upper Disc Pressurization Line.Caused by High Cycle Fatigue. Action Statement of Tech Spec 3.4.6.2 Entered (← links)
- 05000338/LER-1983-058-03, /03L-0:on 830808,incorrect Alignment of Charging High Head Safety Injection Pump Breakers & Control Switches Discovered.Caused by Inadequate Procedural Guidance. Alignment Corrected (← links)
- 05000338/LER-1983-056-03, /03L-0:on 830807,outside Containment Recirculation Spray Valve MOV-RS-155B Failed to Reopen.Caused by Housing Gaskets on Valve Operator Not Thick Enough to Provide Bevel Gear & Roller Bearing Play.Motor Replaced (← links)
- 05000338/LER-1991-015, :on 910714,exposed Control Bus Wire in Process Control Cabinet Shorted,Resulting in Induction of Voltage Spike on Vital Bus & Loss of Control Power to Low Pressure Relay.Caused by Personnel Error (← links)
- 05000338/LER-1994-008-02, :on 941215,inadequate Missile Protection Due to Incomplete Procurement/Design Review of Manhole Covers.Info Action Statement for AP-41,Severe Weather Conditions Was Entered at 1045 Hr on 941215 (← links)
- 05000338/LER-1983-049-03, /03L-0:on 830710,following Reactor Trip from 100% power,I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G.Caused by Minor Fuel Element Defects in Reactor Core.Sampling Frequency Accelerated (← links)
- 05000338/LER-1983-047-03, /03L-0:on 830706,w/unit at 100% Power & One High Head Safety Injection (Nhsi) Pump Undergoing Maint,Second HHSI Pump Removed from Svc Due to High Bearing Temp.First Pump Returned to Svc (← links)
- 05000338/LER-1983-039-03, /03L-0:on 830706,w/unit at 100% Power,Containment Inner Personnel Air Lock Had Detectable Seal Leakage.Caused by Improper Setting of Closed Limit Switch on Door.Switch Adjusted.Satisfactory Leak Test Performed (← links)
- 05000338/LER-1983-037-03, /03L-0:on 830626,conditioning Module TC-MM 100A-1 to Meteorological 33-ft Temp Chart Recorder Drifted by 1.15 F.Caused by Instrument Drift.Module Recalibr (← links)
- 05000338/LER-1983-043-03, /03L-0:on 830620,during steady-state Operation, Greater than 12 Step Disagreement Noted Between Individual Rod Position Indication for Rods J-13 & G-13.Caused by Instrument Drift.Rpi Channels Recalibr (← links)
- 05000338/LER-1991-001, :on 910224,discovered That Hot Leg Safety Injection Branch Flow Above Tech Spec Requirements of Less than or Equal to 650 Gpm.Caused by Errors in Flow Measurements.Throttle Valves Adjusted (← links)
- 05000338/LER-1983-054-03, /03L-0:on 830803,Fire Door S54-8 Failed to Automatically Reclose.Caused by Missing Retaining Ring on Sequencing Bar Pin.Pin Repositioned Correctly (← links)
- 05000338/LER-1983-024-03, /03L-0:on 830517,engineering Review of Steam Driven Auxiliary Feedwater Pump Periodic Tests Revealed Pump Bearing Temps Not Being Measured in Accordance W/Asme XI Iwp Requirements (← links)
- 05000338/LER-1983-055-03, /03L-0:on 830805,unacceptable Leak Rate Determined for Outer Personnel Hatch Door.Caused by Wear Due to Normal Use.Seal Replaced (← links)
- 05000338/LER-1983-051-03, /03L-0:on 830723,post-reactor Shutdown Specific Activity RCS Samples Indicated Dose Equivalent I-131 Level Above Tech Spec Limit.Caused by Fuel Element Defect in Reactor Core.Sampling Frequency Accelerated (← links)
- 05000338/LER-1983-050-03, /03L-0:on 830723,w/util Ramping Down & Reactor Power at 65%,axial Flux Difference Exceeded Target Band for 1 Minute.Caused by Tube Leak in Gland Steam Condenser.Axial Flux Returned to Required Band (← links)
- 05000338/LER-1983-053-03, /03L-0:on 830726,discharge Damper for 1-HV-F-40B Failed to Open While Running Associated Safeguards Exhaust Fan.Caused by Air Leak in Diaphragm of Actuating Mechanism for Damper AOD-HV-1301B.Damper Repaired (← links)
- 05000338/LER-1983-052-03, /03L-0:on 830729,individual Rod Position Indication for Rod J-13 Indicated 110 Steps Instead of Required 228.Caused by Bad Connection of Signal Conditioning Module.Connection Reseated (← links)
- 05000338/LER-1994-006-01, :on 940917,set Pressures for One Pressurizer Safety Valve Was Found to Be Outside Setpoint Tolerances Allowed by TS 3.4.3.Caused by Setpoint Drift.Pvs Were Refurbished & Retested (← links)
- 05000338/LER-1983-046-03, /03L-0:on 830711-26,13 Individual Rod Position Indicators Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift Due to Detector Temp Variations.Channel Recalibr (← links)
- 05000338/LER-1983-044-03, /03L-0:on 830711,during Startup Operation, Individual RPI Found Out of Calibr at Zero Position by 20 to 30 Steps Low.Caused by Fluctuation of Regulated 118-volt Ac Voltage (← links)
- 05000338/LER-1983-020-03, /03L-0:on 830407,during Surveillance Testing, Inside Containment Recirculation Spray Pump 1-RS-P-1B Tripped.Cause Unknown.Pump Satisfactorily Tested & Returned to Svc (← links)
- 05000338/LER-1983-019-03, /03L-0:on 830405,individual Rod Position Indication for Control Bank C,Rod D-12,deviated from Group Demand Position.Caused by Instrument Drift.Instrument Recalibr (← links)
- 05000338/LER-1983-013-03, /03L-0:on 830317,steam Generator a Steam Flow Channel IV Failed Low.Cause Unknown.Failed Channel Placed in Tripped Condition (← links)
- 05000338/LER-1991-009, :on 910411,18 & 0501,determined That Various Surveillance Tests for Main Steam Check Valves,Safety Injection Trip Valve & Seal Water Supply Valve Not Performed.Caused by Personnel Error (← links)
- 05000338/LER-1994-005-02, :on 940909,ESF Actuation Occurred When Main Feedwater Pumps Tripped Due to SG High High Level.Reheat Pressure Transmitter Repaired & Calibrated Satisfactorily & Returned to Svc (← links)
- 05000338/LER-1994-007-01, :on 940914,identified Missed Surveillance on Main Steam Trip Valve Snubber Due to Administrative Process Change Error.Visually Inspected & Replaced Snubber (← links)
- 05000338/LER-1983-018-03, /03L-0:on 830318,individual Rod Position Indication for Rod N-09 in Shutdown Bank a Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift.Problem Generic to Westinghouse Sys (← links)
- 05000338/LER-1983-005-03, /03L-0:on 830313,individual Rod Position Indication for Rod G-13 in Shutdown Bank a Deviated from Group Demand Position.Caused by Instrument Drift.Problem Generic to Westinghouse Analog Position Indication Sys (← links)
- 05000338/LER-1983-010-03, /03L-0:on 830304,while in Mod 3,fire Door S71-17 Between 1J Emergency Diesel Generator Room & Turbine Bldg Declared Inoperable.Caused by Warping Due to Closing Door During Diesel Operation.Closure Device Readjusted (← links)
- 05000338/LER-1983-011-03, /03L-0:on 830304,while in Mode 3,turbine Driven Auxiliary Feedwater Pump Tripped on Overspeed During Testing.Caused by Incorrect Setting of Turbine Governor on 830228.New Governor Installed & Pump Tested Satisfactorily (← links)
- 05000338/LER-1983-012-03, /03L-0:on 830304,individual Rod Position Indication for Rod D-04 in Control Bank C Indicated Zero Steps & Deviated from Group Demand Position.Caused by Faulty Signal Conditioning Module.Conditioning Module Replaced (← links)
- 05000338/LER-1983-035-03, /03L-0:on 830528,following Rapid Rampdown from 100% to 0% power,I-131 Dose Equivalent Exceeded Tech Spec Limit.Level Returned to Limit within 12 H.Caused by Fuel Element Defect in Reactor Core (← links)
- 05000338/LER-1983-033-03, /03L-0:on 830523,w/Unit 2 in Mode 5,pressurizer PORV PCV-2455c Lifted Three Times to Mitigate RCS Pressure Transient Caused by Inadvertent SI Actuation.Caused by Inadequate Instrumentation Procedures (← links)
- 05000338/LER-1983-032-03, /03L-0:on 830521,during Mode 1 Operation, Containment Temp Rose to Greater than 105 F for 30 Minutes. Caused by Malfunctioning Mechanical Chiller.Steam Jet Chiller Aligned to Containment Cooling Coils (← links)
- 05000338/LER-1983-041-03, /03L-0:on 830606,following Reactor Trip from 100% power,I-131 Dose Equivalent Exceeded 10 Mci/G.Caused by Fuel Element Defect in Reactor Core.Accelerated Sampling Frequency Implemented (← links)
- 05000338/LER-1983-040-03, /03L-0:on 830603,w/unit at 100% Power,Fire Door S71-19 Would Not Close W/O Assistance.Caused by Reclosure Mechanism Out of Adjustment.Mechanism Readjusted.Design Mods to Fire Door Being Investigated (← links)
- 05000338/LER-1983-030-03, /03L-0:on 830511,containment Personnel Hatch Inner Door Failed Leakage Surveillance Test.Caused by Dirt Accumulating on Inner Door Seal During Containment Entries Prior to Test (← links)
- 05000338/LER-1983-017-03, /03L-0:on 830516,while in Mode 1,individual Rod Position Indication for Control Bank B Rod D-10 Deviated from Group Demand Position.Caused by Detector & Signal Conditioning Card Drift (← links)
- 05000338/LER-1983-028-03, /03L-0:on 830507,inside Containment Recirculation Spray Pump 1-RS-P-1B Tripped During Surveillance Testing. Caused by Faulty B Phase Overcurrent Device in Breaker. Replacement Breaker Installed (← links)
- 05000338/LER-1983-026-03, /03L-0:on 830426,calibr Check of Delta T/Tavg Protection Channel 1 Revealed Erratic Tavg Lead Lag Derivative Card.Cause Undetermined.Card Replaced & Channel Calibr (← links)
- 05000338/LER-1982-002-03, /03L-0:on 820111,containment Particulate Activity detector,RM-159 & Containment Gaseous Activity Detector, RM-160,failed Low.Caused by Loose Electrical Connector on RM-159 & Drive Motor Failure on RM-160 (← links)
- 05000338/LER-1983-025-03, /03L-0:on 830429,while Conducting Surveillance Test,Conditioning Module TC-MM-100A to Meteorological 33-ft Temp Chart Recorder Drifted 1.6 F.Caused by Instrument Drift.Module Recalbr (← links)
- 05000338/LER-1983-023-03, /03L-0:on 830423,low Head Safety Injection Pump 1-SI-P-1B Suction Isolation Valve Failed to Open.Caused by Lack of Lubrication on Valve Stem to Operator Nut Area.Stem Lubricated & Stroked (← links)
- 05000338/LER-1983-007-03, /03L-0:on 830202,during Mode 5,high Head Safety Injection Throttle Valve Found Out of Alignment by 7/8 of Turn.Caused by Miscount of Valve Handle Turns During Type C 821109 Test or 821108 Valve Verification Procedure (← links)
- 05000338/LER-1983-004-03, /03L-0:on 830125,svc Water Supply Valves MOV-SW- 103B & C & Discharge Valve MOV-SW-104C to Recirculation Spray HXs Would Not Open.Caused by Problems in Valve Operators.Valves Removed & Cleaned (← links)
- 05000338/LER-1983-002-03, /03L-0:830104,meteorological Delta Temp Recorder Determined Out of Tolerance.Caused by Instrument Drift. Recorder Recalibr (← links)
- 05000338/LER-1991-008, :on 910309,containment Integrity Momentarily Lost When Inner Door Equalizing Valve Partially Opened. Caused by Faulty Limit Switch.Containment Integrity Verified by Performance of Inner & Outer Test (← links)
- 05000338/LER-1994-003-02, :on 940426,containment Hydrogen Analyzer Found Inoperable Due to Mechanical Failure of Fitting.Containment Analyzer Sample Fitting Tightened & Leak Stopped (← links)
- 05000338/LER-1991-007, :on 910305,waste Gas Decay Tank Maintained with Oxygen Concentration Greater than 2% W/Hydrogen Concentration Greater than 4% for More than 48 H.Caused by Personnel Error.Memo Provided to Clarify Event (← links)
- 05000338/LER-1982-090-03, /03L-0:on 821205,3A Auxiliary Feedwater Pump Removed from Svc to Determine Cause of Overcurrent Flag Drops on a & C Phase.Cause Not Determined.Flags Reset & Motor Bridged & Meggered W/O Discrepancies (← links)
- 05000338/LER-1982-091-03, /03L-0:on 821207,during Mode 4,pressure in Nitrogen Reservoir B for Pressurizer PORV (PCV-1455C) Dropped Below Min.Caused by Excessive Nitrogen Leakage Through Nitrogen Reservoir B Relief Valve.Valve Repaired (← links)
- 05000338/LER-1982-087-03, /03L-0:on 821205,during Mode 1,individual RPI for Rod H-02 in Control Bank D Deviated from Group Demand Position by Greater than 12 Steps W/No Rod Motion.Caused by Instrument Drift.Rpi Channel Recalibr & Returned to Svc (← links)
- 05000338/LER-1982-084-03, /03L-0:on 821205,at 20% Power,Channels FI-1475 & FI-1485 for Steam Generators a & B Steam Flow Showed Below Actual Flow.Caused by Transmitter for FI-1475 & Multiplier/ Divider/Square Root for FI-1485 Being Out of Calibr (← links)
- 05000338/LER-1982-082-01, /01T-0:on 821206,both Trains of Automatic Safety Injection Blocked for 22 H & 30 Minutes Following Inadvertent Safety Injection.Caused by Emergency Procedure Which Misled Operators.Procedure Revised (← links)
- 05000338/LER-1982-081-03, /03L-0:on 821203,svc Water Supply Header a to Units 1 & 2 Charging Pump Lube Oil Coolers & Air Compressors Isolated to Repair Pinhole Leak.Caused by Corrosion.Affected Piping Cut Out & Replaced (← links)
- 05000338/LER-1982-080-03, /03L-0:on 821128,while in Mode 3,containment Isolation Svc Air Valve Found Open & Unattended.Cause Unknown.Valve Closed & Locked.Investigation Underway (← links)
- 05000338/LER-1994-004-02, :on 940621,sixteen Individual Control Rod Position Analog Computer Points Were Discovered Off Scan. Caused by Computer Points Being Off Scan.Computer Points Were Returned to Scan & Operation (← links)
- 05000338/LER-1982-070-03, /03L-0:on 821116 & 28,head Tracing Circuits ET-117N & ET-116N Failed,Reducing Piping Temp Below 145 F. Cause of 821116 Event Not Stated.Failure on 821128 Caused by Loose Insulation.Failed Channel Replaced & Insulation Added (← links)
- 05000338/LER-1982-079-03, /03L-0:on 821126,in Mode 3,flow Path from Boric Acid Tanks to RCS Inoperable.Caused by Ruptured Diaphragm of Boric Acid Transfer Pump Suction Header Isolation Valve 1-CH-80.Valve Diaphragm Replaced (← links)
- 05000338/LER-1982-078-03, /03L-0:on 821125,in Mode 3,120-volt Ac Vital Bus 1-IV Lost Voltage.Caused by Failure of Normal Power Supply Inverter 1-VB-I-04 Due to Failed Oscillator Board, Transformer & Fuse.Parts Replaced & Inverter Tested (← links)
- 05000338/LER-1982-077-03, /03L-0:on 821119,MOV-1536 Could Not Be Opened After Period Test.Caused by Loose Control Cable Connection at Motor Operator.Loose Connection Tightened (← links)
- 05000338/LER-1982-073-03, /03L-0:on 821118,B Reactor Trip Breaker Failed to Auto Open on Simulated Reactor Signal.Caused by Stuck Undervoltage Tripping Mechanism.Device Removed,Cleaned, Lubricated & Reinstalled (← links)
- 05000338/LER-1982-069-03, /03L-0:on 821110,in Mode 5,pressurizer PORV Previously Blocked Open Found Closed.Caused by PORV Block Not Adequately Secured During Installation.Block Reinstalled (← links)
- 05000338/LER-1991-003, :on 910130,steam Generator Tube Defect Noted. Caused by Primary Water Stress Corrosion Cracking.Tubes That Look Degrading Will Be Removed from Svc (← links)
- 05000338/LER-1982-075-03, /03L-0:on 821119,individual Rod Position Indicator for Rods B-10 in Control Bank A,D-4 in Control Bank C & N-9 in Shutdown Bank A,Deviated from Group Demand Position W/No Rod Motion.Caused by Instrument Drift.Channels Recali (← links)
- 05000338/LER-1982-074-03, /03L-0:on 821119,protection Channel I Overtemp Delta T & Overpower Delta T Placed in Trip,Rendering Channel Inoperable.Caused by T-hot NRA Card (TM-412M) Failure. Channel Recalibr (← links)
- 05000338/LER-1982-071-03, /03L-0:on 821105,B Inside Recirculation Spray Pump (1-RS-P-1B) Did Not Operate within Required Time During Functional Testing.Caused by Drift in Actuation Timer Setting.Timer Readjusted & Retested (← links)
- 05000338/LER-1982-068-03, /03L-0:on 821102,charging Pumps & Boric Acid Flowpaths Rendered Inoperable.Caused by Maint on Charging Pump C Normal Suction Valve MOV-1270A Which Required Removal of Valve Bonnet.Valve Bonnet Replaced (← links)
- 05000338/LER-1982-072-03, /03L-0:on 821115,while Testing Heat Detectors, High Pressure Carbon Dioxide Sys Automatic Actuation Valves Failed to Operate.Caused by Pneumatic Actuation Devices Being Mechanically Bound.Devices Cleaned (← links)
- 05000338/LER-1983-016-03, /03L-0:on 830323,w/unit at 100% Power,Stiffener Support Not Added to Bus Svc Water Auxiliary Relay Panel J Per Design Change 80-S45I.Caused by Personnel Error. Stiffener Support Added (← links)
- 05000338/LER-1982-061-03, /03L-0:on 820917,during Chemistry Log Review, Specific Activity of Primary Coolant Exceeded Tech Specs. Caused by Migration of I-131 Through Pinhole Leaks in Fuel Cladding.Specific Activity Returned to Acceptable Limits (← links)
- 05000338/LER-1982-062-03, /03L-0:on 820917,cold Leg Injection Line Check Valve Found W/Five Corroded Bolts.Caused by Small Leak at Body to Bonnet Gasket.Studs & Bonnet Gasket Replaced (← links)
- 05000338/LER-1983-009-03, /03L-0:on 830218,control Room Operator Observed Indications of Cavitation on RHR Pumps a & B.Cause Unknown. Pumps Secured & Vented.No Air Observed While Venting Pumps (← links)
- 05000338/LER-1981-076-03, /03L-0:on 811117,two Valves on Train B Low Head Safety Injection Sys Found to Be Closed,Thereby Rendering Single ECCS Subsystem Inoperable.Caused by Operator Error. Valves Reopened (← links)
- 05000338/LER-1994-002-02, :on 940420,A Charging Pump Discharge Check Valve Failing to Seat Could Prevent Adequate HHSI Flow to Reactor Core Was Discovered.Cause Could Not Be Determined. Corrective Action:Valve Parts Were Replaced (← links)
- 05000338/LER-1991-002, :on 910125,two Pressurizer Safety Valves & 7 of 15 Main Steam Safety Valves Foud Outside Setpoint Tolerances Allowed by Tech Specs.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted (← links)
- 05000338/LER-1982-065-03, /03L-0:on 820919,routine Recalibr of Pressurizer Level Transmitter LT-1-461,revealed Transmitter Out of Calibr.Caused by Instrument Drift.Transmitter Replaced.New Transmitter Calibr Successfully (← links)
- 05000338/LER-1982-063-03, /03L-0:on 820924,ambient Temp Signal Conditioner & Control Room Delta Temp Recorder Responses Found to Exceed Calibr Procedure Acceptance Criteria.Caused by Instrument Drift.Instruments Recalibr (← links)
- 05000338/LER-1982-057-03, /03L-0:on 820910,setpoint for Turbine Impulse Pressure Comparator in Instrument Procedure Found Incorrect. Caused by Typographical Error During Procedure Revision. Procedure Corrected & Card Recalibr (← links)
- 05000338/LER-1982-050-03, /03L-0:on 820826,fire Doors A80-1 & A80-2 Between Units 1 & 2 Rod Control Rooms & Auxiliary Bldg & Fire Doors A59-1 & A59-2 Between Units 1 & 2 Cable Vault Rooms & Auxiliary Bldg Found Not in Periodic Testing Program (← links)
- 05000338/LER-1982-059-03, /03L-0:on 820827,ventilation Vent B Gaseous Radiation Detector Response Found to Exceed Calibr Test Acceptance Criteria.Caused by Gradual Deterioration of Photomultiplier Tube & Preamplifier.Parts Replaced (← links)
- 05000338/LER-1982-058-03, /03L-0:on 820826,manipulator Crane Area Monitor RM-RMS-162 Failed to Meet Acceptance Criteria of Periodic Calibr & Declared Inoperable.Caused by Instrument Drift Greater than 3% Response Requirement.Assembly Replaced (← links)
- 05000338/LER-1979-051-03, /03L-0 on 790416:RHR Isolation Valve MOV-1701 Failed to Close Automatically in Reponse to Trip Signal. Caused by Misaligned Limit Switch Contact in Valve Close Circuitry.Contact Realigned & Valve Retested Satisfactorily (← links)
- 05000338/LER-1979-034-03, /03L-0 on 790410:snubber 1-RC-HSS-85 Had Empty Reservoir & Declared Inoperable.Caused by Improperly Seated O Ring Resulting in Leak.Snubber Replaced (← links)
- 05000338/LER-1978-138-03, /03L-0 on 781228:during Operation Indication from Pressure Transmitter 1494,1 C Steam Generator Failed High,Caused by Faulty Power Supply.Associated Pressure Channel Taken Out of Svc & Faulty Card Replaced (← links)
- 05000338/LER-1982-076-03, /03L-0:on 821207,while in Mode 3,w/casing Cooling Pump 3A Removed from Svc to Perform Maint,Mode Change Made Due to Unscheduled Outage.Maint Completed in Mode 5 (← links)
- 05000338/LER-1978-127-03, /03L-0 on 781204:during Pwr Reduction,Axial Flux Difference Deviated Greater than 5%;during Return to Full Pwr Afd Deviated Greater than -5%.Caused by Load Reduction Caused by Unit Being on Load Following (← links)
- 05000338/LER-1978-127, Forwards LER 78-127/03L-0 (← links)
- 05000338/LER-1978-125-01, /01T-0 on 781130:noted That Emergency Diesel Generator Battery Racks Were Improperly Installed.Caused by Failure to Perform Requested Mods (← links)
- 05000338/LER-1978-125, Forwards LER 78-125/01T-0 (← links)
- 05000338/LER-1978-121-03, /03L-0 on 781111:during Pwr Reduction,Axial Flux Difference Deviated Greater than Tech Spec Limits.Deviation Caused by Rapid Load Reduction Caused by Failure of Turbine Governor Valve 4 to Open During Test (← links)
- 05000338/LER-1978-121, Forwards LER 78-121/03L-0 (← links)
- 05000338/LER-1978-123-03, /03L-0 on 781115:Detectors a & B of Incore Movable Detector Sys Stuck in Inserted Position Due to Fouled Incore Movable Detector Guide Thimbles (← links)
- 05000338/LER-1978-123, Forwards LER 78-123/03L-0 (← links)
- 05000338/LER-1978-108-03, /03X-1 on 781012:during Mode 1 Opers,At 100% Pwr, Feedwater Flow Transmitter FT-1496 on Feedwater Loop C Failed Low.Caused by Blown Fuse.Fuse Subsequently Replaced (← links)
- 05000338/LER-1978-108, Forwards LER 78-108/03X-1 (← links)
- 05000338/LER-1978-063-03, /03X-1 on 780728:particulate Filter & Charcoal Filter Were Clogged.Caused by Driving Mechanism of RM-RMS-159 Filter Being Jammed (← links)
- 05000338/LER-1978-063, Forwards LER 78-063/03X-1 (← links)
- 05000338/LER-1978-119-03, /03L-0 on 781110:during Critical Steady State Oper Alarms Showed High Steam Line Differential Pressure on Line B.Proper Bistables Tripped,Placing Plant in Safe Condition. Caused by Faulty Instru Loop Pwr Supply Card in Circu (← links)
- 05000338/LER-1978-119, Forwards LER 78-119/03L-0 (← links)
- 05000338/LER-1978-124-01, /01T-0 on 781116:Svc Water & Component Cooling Piping & Pipe Supports Not Analyzed for Thermal & Seismic Stresses.Design Personnel Utilized Wrong Svc Water Temps for Stress Analysis.Present Analysis Shows Adequate Support (← links)
- 05000338/LER-1978-124, Forwards LER 78-124/01T-0 (← links)
- 05000338/LER-1982-085-03, /03L-0:on 821205,ECCS Actuated from High Steam Line Flow Coincident w/lo-lo Temp Average.High Steam Flow Signal Caused by Channels Being in Trip for maint.Lo-lo Temp Average Signal Caused by Reactor Trip (← links)
- 05000338/LER-1982-088-03, /03L-0:on 821207,automatic Safety Injection Received Due to High Steam Flow Signal Coincident w/lo-lo Tavg Signal.Caused by Personnel Error.Safety Injection Secured & Individuals Made Aware of Actions (← links)
- 05000338/LER-1978-117-03, /03L-0 on 781101:main Steam Trip Valve 1-TV-MS-111A Was Detected Leaking Due to a Deteriorated Internal Gasket.Valve Was Isolated & Gasket Replaced (← links)
- 05000338/LER-1978-116-03, /03L-0 on 781102:during Pwr Escalation,Upper Flux Deviation Alarm Was Received & Traced to a High Quadrant Pwr Tilt Ratio.Believed Cause Was Nonlinear Detector Resonse at Lower Pwr (← links)
- 05000338/LER-1978-115-03, /03L-0 on 781107:during 1-pt-134 Periodic Test, MOV-QS102A Would Not Return to Normal Closed Position Because of Dirty Contacts on Valves Torgue Switch.Contacts Were Cleaned (← links)
- 05000338/LER-1978-114-03, /03L-0 on 781101:axial Flux Difference Deviated Greater than -5% from Target for One Minute.Caused by Pwr Reduction Necessitated by Problem with Cooling Fans on Main Station Transformer C (← links)
- 05000338/LER-1978-114, Forwards LER 78-114/03L-0,78-115/03L-0,78-116/03L-0 & 78-117/03L-0 (← links)
- 05000338/LER-1978-113-03, /03l-0 on 780927:after maint,TV-BD100A,B,D & F Were Tested But Not Timed Prior to Return to Svc,Due to Personnel Error.Personnel Have Reviewed the Requirements (← links)
- 05000338/LER-1978-110-03, /03l-0 on 781024:following a Reactor Trip,The Containment Bulk Avg Temp Exceeded 105 Degrees F Tech Spec Limit Due to Steam Loss to Chilled Water Sys Vacuum Refrigeration Unit (← links)
- 05000338/LER-1978-100-01, /01X-0 on 781108:a Field Mod Was Made to Vessel Lower Head Insulation & the Mod Was Not Seismically Analyzed IAW FSAR Due to Personnel Error.Subsequently Analyzed by Stone & Webster & by Westinghouse (← links)
- 05000338/LER-1978-100, Forwards LER 78-100/01X-0, 78-110/03L-0 & 78-113/03L-0 (← links)
- 05000338/LER-1978-120-01, /01T-0 on 781121:inspec of Station Battery Racks Revealed That Racks Had Been Improperly Assembled & Installed During Constr.Deficiencies Will Be Corrected (← links)
- 05000338/LER-1978-122-01, /01T-0 on 781113:during Steady State Oper,It Was Discovered That Only One Seal or Barrier Exists for Spare Pipe Penetrations in Conflict W/Fsar Due to Oversight of Design Personnel.Engineering Is Analyzing It for Solution (← links)
- 05000338/LER-1978-120, Forwards LER 78-120/01T-0 & LER 78-122/01T-0 (← links)
- 05000338/LER-1978-118, Forwards LER 78-118/99T-0 (← links)
- 05000338/LER-1978-112-03, /03L-0 on 781025:During Routine Startup Oper,Axial Flux Difference Deviated Greater than 5% from target.48 Penalty Min Accumulated.Caused by Xenon Transient Occurrence.Corrective Action:Boration by Reactor Operator (← links)
- 05000338/LER-1978-112, Forwards LER 78-112/03L-0 (← links)
- 05000338/LER-1978-089-03, /03X-1 on 780915:during Periodic Test,A Bistable (FC-1485 in Protec Channel Iv)Associated W/Hi Steamline Flow S.I.Actuation Failed to Trip,Due to Defective Bistable Card (← links)
- 05000338/LER-1978-026-99, /99X-1 on 780413:with All Rods Out at Beginning of Core Life,Hot Zero Pwr Moderator Temp Coefficient Revealed It Was More Positive than 0 Delta K/K/F in Tech Spec,Due to Positive Mtc for the all-rods-out Configuration (← links)
- 05000338/LER-1978-026, Forwards LER 78-026/99X-1 & 78-089/03X-1 (← links)
- 05000338/LER-1978-111-01, /01T-0:on 781025,nonseismically Qualified Instantaneous Contacts & Agastat Timers Used in Control Circuits for MOV-QS-102A & MOV-QS-102B.Control Circuit Will Be Modified by Design Change (← links)
- 05000338/LER-1978-109-03, /03L-0:on 781011,during Functional Test on Containment Hydrogen Recombiner 2-HC-HC-1,heater Gas Temp Failed to Reach Greater than 700 F.Caused by Operator Selecting Improper Control Settings (← links)
- 05000338/LER-1978-107-03, /03L-0:on 781005,during Full Power Operation, Containment Atmosphere & Gas Monitoring Sys Inoperable.On 781005,breaker to Containment Atmosphere Particulate & Gas Monitoring Pump Opened,Cutting Power to Sys (← links)
- 05000338/LER-1978-102-03, /03L-0:on 781002,during Mode 3 Operation,Channel 3 of Steam Generator Level Indicator LI-1496 Tripped.Caused by Leak on Manifold Gasket Below Level Transmitter Resulting in Low Reading (← links)
- 05000338/LER-1978-101-03, /03L-0:on 781002,during Mode 3 operation,power- Range Detector N-44 Placed in Trip Mode Until Detector Calibr.Caused by Detector Replacement (← links)
- 05000338/LER-1978-103-03, /03L-0:on 781004,during Heatup from Hot Shutdown to Hot Standby,Feedwater Line from Ecst 1-CN-TK-1 to Steam Generators A,B & C Via 1-FW-P-3B Auxiliary Feedwater Pumps Not Secured.Caused by Unavailability of Plant 2d (← links)
- 05000338/LER-1978-099-03, /03L-0:on 780926,during Mode 5 Operatio,Level Transmitter LT-1475 Did Not Activate hi-hi Level Turbine Trip & Feedwater Isolation Bistable Until Actual Level of 76.82 Reached.Caused by Transmitter Output Drift (← links)
- 05000338/LER-1978-097-03, /03L-0:on 780928,fluid Lost in Snubber 1-RC-HSS-873.Caused by Warping of Reservoir from Steam Generator Insulation on Blanket (← links)
- 05000338/LER-1978-096-03, /03L-0:on 780927,fluid Lost in Snubber 1-RC-HSS-861.Caused by Leak at Reservoir Seal (← links)
- 05000338/LER-1978-095-03, /03L-0:on 780928,during Routine Recalibr,High Pressure Reactor Trip Bistable Would Not Activate Until Actual Pressure of 2,396 Psig Reached.Caused by Transmitter Output Drift (← links)
- 05000338/LER-1978-094-03, /03L-0:on 780927,containment Isolation Valves TV- CC-102D & TV-CC-102F Failed to Close During Cycling.Caused by Blocked Solenoid Air Supply (← links)
- 05000338/LER-1978-092-03, /03L-0:on 780927,transmitter LT1486 Did Not Activate hi-hi Level Turbine Trip & Feedwater Isolation Until Level of 76.33% Reached in Violation of Tech Spec Limit.Caused by Drift in Transmitter Output (← links)
- 05000338/LER-1978-091-03, /03L-0:on 780927,nonconservative Low Flow Trip Setpoint Discerned During Routine Recalibr of Reactor Coolant Flow Loop Channel B.Caused by Procedural Error.Loop Calibr Corrected (← links)
- 05000338/LER-1978-090-03, /03L-0:on 780919,during Critical steady-state Operation,Axial Flux Difference Deviated Greater than -5% from Target.Caused by Rapid Load Reduction Necessitated by Clogging of Condensate Pump Strainer (← links)
- 05000338/LER-1978-098-01, /01T-0:on 781004,nonconservatism Noted in Calculations Performed on Axial Power Distribution Monitoring Sys.Caused by Data Value round-off (← links)
- 05000338/LER-1978-061-99, /99X-1 on 780712:the Area Temp Monitoring Log Erroneously Recorded Excessive Temps in Battery Rooms.Cause Is Unknown (← links)
- 05000338/LER-1978-061, Forwards LER 78-061/99X-1 & 78-089/03L-0 (← links)
- 05000338/LER-1982-055-03, /03L-0:on 820809,util Notified by Westinghouse That Potential Exists for Undetected Failure in Spss Resulting in No Safeguard Actuation from Affected Slave Relays.Surveillance Test Changed to Verify Closure (← links)
- 05000338/LER-1982-048-03, /03L-0:on 820805,fire Door S71-19 Would Not Latch. on 820806,fire Doors S54-2 & S54-13 Would Not Close Automatically.Caused by Maladjusted Latch on Door S71-19 & Faulty Reclosure Devices on Doors S54-2 & S54-13 (← links)
- 05000338/LER-1994-001-02, :on 940122,EDG Fuel Oil Transfer Pumps Declared Inoperable Due to Improper Greasing of Pump Motor Bearings.Fuel Oil Pump House Exhaust Fans Secured & Portable Heaters Installed (← links)
- 05000338/LER-1982-053-03, /03L-0:on 820726,Type C Tests Revealed Containment Isolation Valves W/Unacceptable Leak Rates.Cause Undetermined.Valves Will Be Repaired or Adjusted & Acceptable Level of Leakage Verified (← links)
- 05000338/LER-1981-050-03, /03L-0:on 810615,individual Rod Position Indication for Rod J13 in Shutdown Bank a Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift.Channel for Rod J13 Properly Recalibr (← links)
- 05000338/LER-1982-049-03, /03L-0:on 820723,w/unit Defueled,Defective/Failed Welds Found in Two Thermal Sleeves.Cause Unknown. Westinghouse Investigating Failure.Thermal Sleeves Will Be Removed During Present Outage (← links)
- 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.28 (← links)
- 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.28 (← links)
- 05000338/LER-2024-001-01, Automatic Reactor Trip Due to PRNI High Negative Rate (← links)
- 05000338/LER-2024-002, H EDG Failure to Achieve Rated Speed / Frequency During Surveillance Testing (← links)
- 05000338/LER-2024-003, Loss of Offsite Power Train a Relay Failure During Surveillance Testing (← links)
- 05000338/LER-2024-002-01, Ih EDG Failure to Achieve Rated Speed / Frequency During Surveillance Testing (← links)
- 05000338/LER-2024-003-01, Loss of Offsite Power Train a Relay Failure During Surveillance Testing (← links)