Pages that link to "05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System"
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The following pages link to 05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System:
Displayed 4 items.
- ML19120A333 (redirect page) (← links)
- 05000324/LER-2019-003, High Pressure Coolant Injection (HPCI) Inoperable (← links)
- 05000324/LER-2019-002, Manual Reactor Protection System Actuation and Specified System Actuation (← links)
- 05000324/LER-2019-001 (redirect page) (← links)
- 05000324/LER-2002-002 (← links)
- 05000324/LER-2001-001 (← links)
- IR 05000324/2019004 (← links)
- 05000324/LER-1982-048, Forwards Updated LER 82-048/03L-1 (← links)
- 05000324/LER-1982-077, Forwards LER 82-077/01T-0.Detailed Event Analysis Encl (← links)
- 05000324/LER-1982-080, Forwards LER 82-080/01T-0 (← links)
- 05000324/LER-1982-046, Forwards LER 82-046/03L-0 (← links)
- 05000324/LER-1982-045, Forwards LER 82-045/03L-0 (← links)
- 05000324/LER-1982-039, Forwards LER 82-039/03L-0 (← links)
- 05000324/LER-1982-028, Forwards LER 82-028/03L-0 (← links)
- 05000324/LER-1982-011, Forwards LER 82-011/01T-0 (← links)
- 05000324/LER-1982-023, Forwards LER 82-023/03L-0 (← links)
- 05000324/LER-1982-052, Forwards LER 82-052/03L-0 (← links)
- 05000324/LER-1982-047, Forwards LER 82-047/03L-0 (← links)
- 05000324/LER-1982-044, Forwards LER 82-044/03L-0 (← links)
- 05000324/LER-1982-059, Forwards LER 82-059/03L-0 (← links)
- 05000324/LER-1982-079, Forwards LER 82-079/03L-0 (← links)
- 05000324/LER-1982-043, Forwards LER 82-043/03L-0 (← links)
- 05000324/LER-1982-112, Forwards LER 82-112/03L-0 (← links)
- 05000324/LER-1983-006, Forwards LER 83-006/03L-0 (← links)
- 05000324/LER-1983-004, Forwards LER 83-004/03L-0 (← links)
- 05000324/LER-1982-137, Forwards LER 82-137/03L-0 (← links)
- 05000324/LER-1982-109, Forwards LER 82-109/03L-0 (← links)
- 05000324/LER-1981-032, Forwards LER 81-032/03L-0 (← links)
- 05000324/LER-1982-096, Forwards LER 82-096/03L-0 (← links)
- 05000324/LER-1982-104, Forwards LER 82-104/03L-0 (← links)
- 05000324/LER-1982-101, Forwards LER 82-101/03L-0 (← links)
- 05000324/LER-1982-091, Forwards LER 82-091/03L-0 (← links)
- 05000324/LER-1982-100, Forwards LER 82-100/03L-0 (← links)
- 05000324/LER-1982-097, Forwards LER 82-097/03L-0 (← links)
- 05000324/LER-1982-084, Forwards LER 82-084/01T-0 (← links)
- 05000324/LER-1982-093, Forwards LER 82-093/03L-0 (← links)
- 05000324/LER-1982-089, Forwards LER 82-089/03L-0 (← links)
- 05000324/LER-1982-082, Forwards LER 82-082/03L-0 (← links)
- 05000324/LER-1982-099, Forwards LER 82-099/01T-0 (← links)
- 05000324/LER-1982-086, Forwards LER 82-086/03L-0 (← links)
- 05000324/LER-1981-117, Forwards LER 81-117/03L-0 (← links)
- 05000324/LER-1981-123, Forwards LER 81-123/03L-0 (← links)
- 05000324/LER-1982-087, Forwards LER 82-087/03L-0 (← links)
- 05000324/LER-1980-119, Forwards LER 80-119/03L-0 (← links)
- 05000324/LER-1979-028, Forwards LER 79-028/03L-0 (← links)
- 05000324/LER-1982-090, Forwards LER 82-090/03L-0 (← links)
- 05000324/LER-1978-070, Forwards LER 78-070/03L-0 (← links)
- 05000324/LER-1978-073, Forwards LER 78-073/03L-0 (← links)
- 05000324/LER-1978-071, Forwards LER 78-071/03L-0 (← links)
- 05000324/LER-1978-069, Forwards LER 78-069/03L-0 (← links)
- 05000324/LER-1978-068, Forwards LER 78-068/03L-0 (← links)
- 05000324/LER-1982-092, Forwards LER 82-092/03L-0 (← links)
- 05000324/LER-1982-085, Forwards LER 82-085/01T-0 (← links)
- 05000324/LER-1983-012, Forwards LER 83-012/03L-0 (← links)
- 05000324/LER-1983-010, Forwards LER 83-010/03L-0 (← links)
- 05000324/LER-1983-013, Forwards LER 83-013/03L-0 (← links)
- 05000324/LER-1983-011, Forwards LER 83-011/03L-0 (← links)
- 05000324/LER-1983-008, Forwards LER 83-008/03L-0 (← links)
- 05000324/LER-1983-009, Forwards LER 83-009/03L-0 (← links)
- 05000324/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000324/LER-1983-003, Forwards LER 83-003/03L-0 (← links)
- 05000324/LER-1982-132, Forwards LER 82-132/03L-0 (← links)
- 05000324/LER-1982-124, Forwards LER 82-124/01T-0.Detailed Event Analysis Encl (← links)
- 05000324/LER-1982-128, Forwards LER 82-128/03L-0 (← links)
- 05000324/LER-1982-125, Forwards LER 82-125/03L-0 (← links)
- 05000324/LER-1982-126, Forwards LER 82-126/03L-0 (← links)
- 05000324/LER-1983-043, Forwards LER 83-043/01T-0 (← links)
- 05000324/LER-1982-106, Forwards LER 82-106/03L-0.Detailed Event Analysis Encl (← links)
- 05000324/LER-1983-031, Forwards LER 83-031/03L-0 (← links)
- 05000324/LER-1982-131, Supplemental LER 82-131/03L-1:on 821206,one-half Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam Line Radiation Monitor D, 2-D12-RM-K603D.Caused by Disconnection of Instrument Cable (← links)
- 05000324/LER-1983-021, Forwards LER 83-021/03L-0 (← links)
- 05000324/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000324/LER-1982-013, Forwards LER 82-013/03L-0 (← links)
- 05000324/LER-1982-020, Forwards LER 82-020/03L-0 (← links)
- 05000324/LER-1982-021, Forwards LER 82-021/03L-0 (← links)
- 05000324/LER-1983-014, Forwards LER 83-014/03L-0 (← links)
- 05000324/LER-1981-127, Forwards LER 81-127/03L-0 (← links)
- 05000324/LER-1983-025, Forwards LER 83-025/03L-0 (← links)
- 05000324/LER-1981-126, Forwards LER 81-126/03L-0 (← links)
- 05000324/LER-1983-027, Forwards LER 83-027/03L-0 (← links)
- 05000324/LER-1983-023, Forwards LER 83-023/03L-0 (← links)
- 05000324/LER-1982-129, Forwards LER 82-129/03L-0 (← links)
- 05000324/LER-1982-098, Forwards LER 82-098/03L-0 (← links)
- 05000324/LER-1982-116, Forwards LER 82-116/03L-0 (← links)
- 05000324/LER-1982-114, Forwards LER 82-114/03L-0 (← links)
- 05000324/LER-1982-120, Forwards LER 82-120/03L-0 (← links)
- 05000324/LER-1982-130, Forwards LER 82-130/01T-0 (← links)
- 05000324/LER-1982-119, Forwards LER 82-119/03L-0 (← links)
- 05000324/LER-1982-115, Forwards LER 82-115/03L-0 (← links)
- 05000324/LER-1982-122, Forwards LER 82-122/03L-0 (← links)
- 05000324/LER-1982-118, Forwards LER 82-118/03L-0 (← links)
- 05000324/LER-1982-105, Forwards LER 82-105/03L-0 (← links)
- 05000324/LER-1995-002, Forwards LER 95-002,fulfilling Requirement for Written Rept within Thirty Days of Reportable Occurrence Re HPCI Failure to Operate as Required During Performance of Periodic Tests (← links)
- 05000324/LER-1982-141, Forwards LER 82-141/03L-0 (← links)
- 05000324/LER-1982-135, Forwards LER 82-135/03L-0 (← links)
- 05000324/LER-1982-143, Forwards LER 82-143/03L-0 (← links)
- 05000324/LER-1982-140, Forwards LER 82-140/03L-0 (← links)
- 05000324/LER-1983-083, Updated LER 83-083/01T-1:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Discovered Shut.Caused by Operator Error.Valves Tagged for Identification.Auxiliary Operator Disciplined (← links)
- 05000324/LER-1983-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking (← links)
- 05000324/LER-1983-015, Forwards LER 83-015/03L-0 (← links)
- 05000324/LER-1983-007, Forwards LER 83-007/03L-0 (← links)
- 05000324/LER-1983-044, Forwards LER 83-044/03L-0 (← links)
- 05000324/LER-1983-046, Forwards LER 83-046/03L-0 (← links)
- 05000324/LER-1983-045, Forwards LER 83-045/03L-0 (← links)
- 05000324/LER-1983-037, Forwards LER 83-037/03L-0 (← links)
- 05000324/LER-1983-016, Forwards LER 83-016/03L-0 (← links)
- 05000324/LER-1983-024, Forwards LER 83-024/03L-0 (← links)
- 05000324/LER-1983-032, Forwards LER 83-032/03L-0 (← links)
- 05000324/LER-1983-030, Forwards LER 83-030/03L-0 (← links)
- 05000324/LER-1983-028, Forwards LER 83-028/03L-0 (← links)
- 05000324/LER-1983-033, Forwards LER 83-033/03L-0 (← links)
- 05000324/LER-1983-029, Forwards LER 83-029/03L-0 (← links)
- 05000324/LER-1982-064, Forwards Updated LER 82-064/03L-1 (← links)
- 05000324/LER-1983-017, Forwards LER 83-017/03L-0 (← links)
- 05000324/LER-1983-020, Forwards LER 83-020/03L-0 (← links)
- 05000324/LER-1982-095, Forwards LER 82-095/03L-0 (← links)
- 05000324/LER-1982-081, Forwards LER 82-081/03L-0 (← links)
- 05000324/LER-1982-022, Forwards LER 82-022/03L-0 (← links)
- 05000324/LER-1982-014, Forwards LER 82-014/03L-0 (← links)
- 05000324/LER-1982-017, Forwards LER 82-017/03L-0 (← links)
- 05000324/LER-1983-022, Forwards LER 83-022/03L-0 (← links)
- 05000324/LER-1983-018, Forwards LER 83-018/03L-0 (← links)
- 05000324/LER-1980-002, Forwards LER 80-002/03L-0 (← links)
- 05000324/LER-1979-057, Forwards LER 79-057/03L-0 (← links)
- 05000324/LER-1979-025, Forwards LER 79-025/03L-0 (← links)
- 05000324/LER-1981-022, Forwards Updated LER 81-022/03L-1 (← links)
- 05000324/LER-1983-042, Forwards LER 83-042/03L-0 (← links)
- 05000324/LER-1982-107, Forwards Updated LER 82-107/03L-1 (← links)
- 05000324/LER-1982-083, Forwards Updated LER 82-083/03L-1 (← links)
- 05000324/LER-1982-094, Forwards Updated LER 82-094/03L-1 (← links)
- 05000324/LER-1982-006, Forwards Updated LER 82-006/03L-1 (← links)
- 05000324/LER-1981-071, Forwards Updated LER 81-071/03L-1 (← links)
- 05000324/LER-1981-135, Forwarded Updated LER 81-135/03L-1 (← links)
- 05000324/LER-1981-133, Forwards Updated LER 81-133/03L-1 (← links)
- 05000324/LER-1998-002, Forwards LER 98-002-00,IAW 10CFR50.73.Commitments Made within Ltr,Encl (← links)
- 05000324/LER-1982-041, Forwards Updated LER 82-041/03L-1 (← links)
- 05000324/LER-2023-001, Two Main Steam Line Safety Relief Valves Inoperable (← links)
- 05000324/LER-2020-005, (Bsep), Unit 1 Re Condition Prohibited by Technical Specifications Due to Ventilation Charcoal Sample Lab Results (← links)
- 05000324/LER-1989-005-02, :on 890313,HPCI Removed from Svc Due to Limitorque Torque Switches Set Too High.Caused by Software Error Which Caused Indicated Output Torque to Read High. Setting Adjusted.Also Reported Per Part 21 (← links)
- 05000324/LER-1989-014-02, :on 890910,primary Containment Local Leak Rate Testing Revealed Leakage Which Degraded Primary Containment Safety Barrier.Cause Under Investigation for Root Cause Determination.Leak Rate Testing Continuing (← links)
- 05000324/LER-1989-012-02, :on 890830,emergency Bus E8 Temp high-480 Volt Ground Alarm Annunciation Occurred.Disassembly of Motor Revealed Failure of Windings.Root Cause for Failure Undetermined.Motor Rebuilt & Reinstalled (← links)
- 05000324/LER-1989-001-02, :on 890214,HPCI Initiation During Performance of Maint Surveillance Test on ECCS Trip Unit Occurred.Caused by Spurious Electrical Noise by Adjacent Trip Unit.Component Failures Tracked (← links)
- 05000324/LER-1989-011-02, :on 890703,RCIC Turbine Received Trip Signal & Inboard Steam Supply Isolation Valve E51-F007 Closed Due to False Primary Containment Div I Group 5 Isolation Signal. Caused by Personnel Error.Personnel Counseled (← links)
- 05000324/LER-1989-003-03, :on 890221,technician Lifted Lead on RWCU Temp Module,Resulting in RWCU Group III Isolation & Closing Inboard Isolation Valve.Caused by Personnel Error & Cabinet Design Deficiency.Modules in Panel Mapped (← links)
- 05000324/LER-1989-004, :on 890225,steam Leak Occurred on RCIC Outboard Steam Supply Isolation Valve in Vicinity of Steam Leak Detection Temp Switch.Caused by Actuation of Steam Supply Isolation Valve.Weld Seal Completed (← links)
- 05000324/LER-1989-006-03, :on 890424,HPCI High Steam Flow Isolation Instrument E41-PDT-N005 Failed in Upscale Tripped Position Causing HPCI Steam Supply Inboard Isolation Valve to Isolate.Caused by Failed Sensor Module (← links)
- 05000324/LER-1989-004-02, :on 890225,channel a of RCIC Sys Steam Leak Detection Instrumentation Received Isolation Signal & Inboard Isolation Valve Isolated.Caused by Steam Leak.Valve Body to Bonnet Joint Wrapped W/Blankets (← links)
- 05000324/LER-1997-004, :on 971003,results Identified That Five of Eleven Valves Were Found to Lift at Pressures Outside TS Limits.Caused by Oxide Accumulation on Pilot Disc Seat. Replaced SRV Pilot Valve Assemblies (← links)
- 05000324/LER-1988-011-01, :on 880725,RHR/primary Containment Isolation Inboard Isolation Valve E11-F009 Failed to Open.Caused by Failure of Electrical Contacts in Switch Number 1 to Close. Wiring Reconfigured to Utilize Spare Switch 2 (← links)
- 05000324/LER-1989-010-02, :on 890619,unit Received Group 1 Isolation While in Hot Shutdown W/Reactor Pressure at 150 Psig.Caused by High Steam Flow Isolation Signal.No Corrective Measures Considered Necessary (← links)
- 05000324/LER-1989-002-03, :on 890221,two Supports on HPCI Steam Supply Discovered W/Cracked Weld Indications Showing Rust.Caused by Poor Weld Quality.Welds Repaired (← links)
- 05000324/LER-1989-002, :on 890221,two Supports on HPCI Steam Supply Piping Had Cracked Weld Indications & HPCI Sys Declared Inoperable.Caused by Poor Weld Quality & Mild Transients During Operation.Weld Support Repaired (← links)
- 05000324/LER-1989-008-03, :on 890605,unplanned LOCA Initiation Signal Occurred During Routine Maint Testing of ECCS Resulting in Auto Starting of LPCI Core Spray & RHR Pumps.Caused by Spurious Trip of ECCS Trip Unit.Unit Replaced (← links)
- 05000324/LER-1989-007-03, :on 890603,unit Received Group III Isolation of RWCU Inboard & Outboard Isolation Valves During Calibr of RWCU Reject Flow Indicator.Caused by Lack of Specific Procedure.Calibr Procedures Will Be Written (← links)
- 05000324/LER-1988-001, :on 880102,manual Reactor Protection Sys Trip (Scram) Initiated Due to Decreasing Condenser Vacuum. Definite Root Cause Not Identified.Contractor Svcs Retained (← links)
- 05000324/LER-1987-008-04, :on 870727,loss of Reactor Protection Sys (RPS) Div 1 Bus Occurred.Caused by Low Voltage Conditions from Alternate Power Supply.Mod Developed to Prevent Voltage Decrease of Main Grid from Affecting RPS Bus (← links)
- 05000324/LER-1987-011-03, :on 871105,isolation of RCIC Sys Occurred Due to Spurious Actuation of RCIC Steam Leak Detection Instrumentation.Cause Unknown.Isolation Signal Reset & RCIC Sys Returned to Standby (← links)
- 05000324/LER-1987-010-03, :on 871104,inoperability of Reactor Bldg Fire Hose Station 2-RB-23 Occurred.Caused by Personnel Error Re Fire Drill.Procedural Revs to Ensure That Affected Sys Restored Following Drill Will Be Implemented (← links)
- 05000324/LER-1998-001-03, :on 980610,reactor Core Isolation Cooling Sys Isolation Instrumentation Setpoint Shift,Was Determined. Caused by Failure to Establish Comprehensive Actions. Affected Pressure Switch Setpoints Calibrated (← links)
- 05000324/LER-1987-007, :on 870504,Div 1 Group 5 Primary Containment Isolation of RCIC Sys Autoclosed.Caused by Valve Shifts of Involved Electronic Components Due to long-term Thermal Degradation.Faulty Part Replaced (← links)
- 05000324/LER-1989-001-03, :on 890214,momentary Initiation Signal Generated & HPCI Sys auto-started as Designed But Remained in Min Flow Mode & Did Not Inject Into Reactor Pressure Vessel.Caused by Spurious Closure Signal (← links)
- 05000324/LER-1987-009-02, :on 870817,Group 3 Isolation of Rcwu Sys Inlet Outboard Primary Containment Isolation Valve G31-F004 Occurred.Caused by Sticking read-set Temp Differential Switch.Replacement Switch Ordered (← links)
- 05000324/LER-1999-008-02, :on 990920,condenser Pressure Sensing Line Drain Activities Resulted in ESF & RPS Actuation.Caused by Inadequate Implementation of C/A to Previously Identified Condition.Procedures Were Revised.With (← links)
- 05000324/LER-1999-006-02, :on 990628,automatic Reactor SD Occurred.Caused by Condenser Low Vacuum Main Turbine Trip.Reviewed Operational Guidance & Development of Operational Strategy CWIP Trips.With (← links)
- 05000324/LER-1986-022-01, :on 861003,reactor Shut Down Due to Unsuccessful Restart of Motor Generator Set.Caused by Opened Fuses.Fuse 7 Transformer Replaced,Motor Generator Restarted & Loop Returned to Svc (← links)
- 05000324/LER-1986-021-01, :on 860919,reactor Protection Sys Bus a Inadvertently Deenergized Due to Personnel Error.Bus Output Breakers Opened Instead of Respective Unit 1 Breakers. Personnel Disciplined (← links)
- 05000324/LER-1986-025-01, :on 861120,determined That 861119 Surveillance of Reactor Jet Pump Missed.Caused by Personnel Error. Surveillance Performed Satisfactorily.Personnel Disciplined & Training Initiated (← links)
- 05000324/LER-1987-007-02, :on 870504,RCIC Sys Turbine Steam Supply Inboard Primary Containment Isolation Valve (PCIV) & Pump Suppression Pool Suction Supply Inboard PCIV Auto Closed on Group 5 Isolation.Caused by Instrument Drift (← links)
- 05000324/LER-1987-006-02, :on 870424,operability Testing of HPCI Sys Revealed HPCI Sys Pump Flow Controller Would Not Control in Automatic.Caused by Open Electrical Resistor R26.Resistor Replaced.Controller Dynamically Tuned (← links)
- 05000324/LER-1986-016-01, :on 860711,automatic Scram Signal Occurred Due to Reactor Low Level During Warmup Flush of Unit RHR Loop B. Caused by Failure to Terminate Warmup Flush Prior to Reactor Level Decreasing to lo-lo Setpoint (← links)
- 05000324/LER-1986-024-01, :on 861021,core Spray Subsys Pumps a & B Started & Injected 7,500-9,000 Gallons of Water from Torus Into Reactor.Caused by Personnel Error During Maint of Eccs. Personnel Disciplined & Inverters Relabeled (← links)
- 05000324/LER-1985-014, :on 851231 & 860101,discovered That Automatic Depressurization Sys a & B Logic Timing Relay K5A Out of Timing.Cause Undetermined.Relays Replaced (← links)
- 05000324/LER-1986-023-01, :on 861009,primary Containment Group 4 Isolation of HPCI Sys Occurred.Caused by Loss of Electrical Continuity at Terminal Connections of Thermocouple Leads. Thermocouple Lead Terminations Improved (← links)
- 05000324/LER-1987-003-02, :on 870202,discovered During Monthly Maint Surveillance Test That RCIC High Level Reactor Trip Function Inoperative.Caused by Disconnected Logic Lead to Function Actuation Relay E51-K52.Lead Reconnected (← links)
- 05000324/LER-1997-003-03, :on 970908,HPCI Declared Inoperable.Caused by Incorrect Evaluation of Procedure Requirements.Temporary Air Piping Removed & HPCI Sys Operability Restored (← links)
- 05000324/LER-1986-015, :on 860530,LPCI Subsystem Inoperable within 4 H of Initiating Maint on LPCI Sys Per Action Statements b.2 of Spec 3.5.3.1.Caused by Delay Due to Troubleshooting & Repair of Sensing Leg Isolation Valve (← links)
- 05000324/LER-1986-025, :on 861119,determined That Surveillance Testing for Reactor Jet Pump Not Performed.Caused by Personnel Error.Personnel Involved discplined.Real-time Training Completed (← links)
- 05000324/LER-1987-002-01, :on 870108,automatic Closure of RWCU Sys Inlet Primary Containment Isolation Valve G31-F004 Occurred Due to Reversed Thermocouple Leads.Caused by Personnel Error.Input Lead Reversal Corrected (← links)
- 05000324/LER-1997-002-03, :on 970724,core Spray Sys Minimum Bypass Flow MOV Declared Inoperable.Caused by non-conservative Calculated Motor Torque.Valve 2-E21-F031B & 2B Loop of CS Was Returned to Operability (← links)
- 05000324/LER-1999-007, :on 990714,noted That Overlapping of Safety Systems Outages Resulted in TS Prohibited Operation.Caused by Inadequate Training/Communications Re Implementation of Its.Training Will Be Provided to Operators.With (← links)
- 05000324/LER-1986-011, :on 860404,RWCU Sys Inlet Primary Containment Outboard Isolation Valve 2-G31-F004 Automatically Closed, Causing Isolation Trip Signal Initiation.Caused by Blown Fuse.Fuse Replaced (← links)
- 05000324/LER-1986-020-01, :on 860823,automatic Reactor Scram Occurred Due to Erroneous Reactor Low Level Signal.Caused by Personnel Error.Involved Technician Counseled.Appropriate Personnel Received Training (← links)
- 05000324/LER-1986-006-02, :on 860223,automatic Closure of Primary Containment Isolation Valves G16-F004 & F020 & Isolation of Reactor Bldg Ventilation Sys Occurred.Caused by Personnel Error.Plant Sys Returned to Svc (← links)
- 05000324/LER-1987-005-02, :on 870330,HPCI Sys Steam Supply Outboard Primary Containment Isolation Valve E41-F003 Declared Inoperable.Caused by Blown Control Power Fuse in Valve Operator Motor Breaker.Fuse & Coil Replaced (← links)
- 05000324/LER-1985-011-02, :on 851015,reactor Scrammed Following Closure of MSIV B21-FO22A.Caused by Dc Solenoid of three-way Valve Failing at Prior Indeterminate Time.Asco Valve Replaced (← links)
- 05000324/LER-1986-026-01, :on 861211,fire Watches Performed 15 Minutes Late.Caused by Restricted Access to Affected Fire Watch Areas Due to Radiological Spill Onto 50-ft Elevation Floor. Fire Watches Conducted & Personnel Disciplined (← links)
- 05000324/LER-1988-016-02, :on 880908,Div 2 Svc Water Vital Header Leak Resulted in Manual Isolation of Associated Header.Caused by Excessive Corrosion of 3/4-inch Blank Flange on Bypass Line. Flange Replaced & Vital Header Returned to Svc (← links)
- 05000324/LER-1987-004-02, :on 870311,reactor Scram on Low Level Due to Loss of Uninteruptible Power Supply & Subsequent Loss of Feedwater.Caused by Noncompliance W/Procedure to Transfer Power.Motor Replaced & Sys Returned to Normal (← links)
- 05000324/LER-1999-002-02, :on 990329,reactor Tripped.Caused by Failed Electrical Connections on Vibration Detector for Number 9 Main Turbine Bearing.Vibration Detectors for Main Turbine Number 9 Bearing Replaced.With (← links)
- 05000324/LER-1988-017-03, :on 881005,HPCI Vacuum Breaker Isolation Valve (2-E41-F079) Automatically Closed as Result of False Initiation Signal.Caused by Short Across High Drywell Pressure Relay.Equipment Tested Daily (← links)
- 05000324/LER-1999-001-02, :on 990317,RCIC Sys Declared Inoperable.Caused by Inadequate Packing Compression on live-load Packing.Valve 2-E51-F008 Repacked & Tested in Accordance with Plant Procedures.With (← links)
- 05000324/LER-1985-009-02, :on 850930,hi-hi Trip of Reactor Bldg Vent Exhaust Monitor D12-RM-N010B & Upward Spike of Redundant Monitor N010A Occurred.Caused by Crud Movement on Sys Line During Flush.Procedure to Be Revised (← links)
- 05000324/LER-1986-019-01, :on 860722,discovered That Reactor Transversing in-core Probe Sys Channel B,8 & 10 Tubing Pathways Interchanged at Channel Indexing Mechanism.Caused by Misidentification of Tubing (← links)
- 05000324/LER-1986-009, :on 860311,upscale Spike of Reactor Bldg Ventilation Exhaust Radiation Monitor Instrument Trip Unit Occurred.Cause Not Determined.Trip & Isolation Signals Reset & Sys Returned to Svc (← links)
- 05000324/LER-1986-007-01, :on 860309,high Radiation Alarm Trip of Reactor Bldg Ventilation Exhaust Radiation Monitor D12-RM-N010B Occurred,Resulting in Automatic Isolation of Bldg Ventilation Sys.Caused by Grounding (← links)
- 05000324/LER-1998-004-03, :on 981216,HPCI Sys Was Rendered Inoperable to Support Scheduled Maint Activity.Caused by Deficiencies in Scheduling & Planning of 2-E41-F079 Valve Work Activity. Personnel Have Been Briefed on Event.With (← links)
- 05000324/LER-1997-004-02, :on 971003,safety Relief Valves Exceeded TS Setpoint Limits,Was Identified.Caused by Formation of Oxide Bond Between Pilot Seat & Disc.Valves Will Be Disassembled & Inspected During First Quarter 1998 (← links)
- 05000324/LER-1998-005-02, :on 981123,chlorine Leak Results in CREVS & Suspended Fire Watches,Occurred.Caused by through-wall Perforation in Cast steel/neoprene-lined Piping T Section. Event Review Team Formed to Investigate.With (← links)
- 05000324/LER-1996-003-02, Forwards Supplemental LER 96-003-02 Re Operation of Unit in Excess of Max Power Level Specified in Operating License. List of Regulatory Commitments,Encl (← links)
- 05000324/LER-1986-014, :on 860429,automatic Trip of Reactor Protection Sys Logic Channels a & B Occurred.Caused by Upscale Trip of Reactor Power intermediate-range Monitor D. Channels Reset (← links)
- 05000324/LER-1986-013, :on 860423,upscale Trip of Reactor Power source-range Monitor a Occurred While Reactor Protection Sys Shorting Links Removed.Caused by Personnel Error. Technicians Counseled (← links)
- 05000324/LER-1986-012, :on 860414,RWCU Sys Suction Valve G31-F001 Automatically Isolated While Performing Wiring Check.Caused by Ambient Temp Isolation Instrument Loose Negative Terminal.Proper Termination Verified (← links)
- 05000324/LER-1986-001, :on 860107,discovered That 10 of 11 Safety Relief Valves Tested Exhibited Symptoms of higher-than- Allowed Setpoint Drift.Caused by Pilot disc-to-seat Sticking & High Friction.Maint Program Revised (← links)
- 05000324/LER-1999-003-02, :on 990418,inadequate Augmented Inservice Weld Insps Were Noted.Caused by Incorrect Assumptions by Personnel.Inspected Affected Weld During Current Unit 2 Ro. with (← links)
- 05000324/LER-1988-005-02, :on 880204,safety Relief Valves Setpoints Exceeded During Testing at Wyle Labs.Caused by Corrosion Induced Bonding of Pilot Valve Disc to Seat Surface.Valves Refurbished.Maint Personnel Counseled (← links)
- 05000324/LER-1999-005-02, :on 990511,determined That as-found Lift Settings for Two SRVs Exceeded TS Setpoint Limits.Cause Indeterminate.Srv Pilot Valve Assemblies Were Replaced with Certified Spares Prior to Startup of Plant.With (← links)
- 05000324/LER-1986-012-01, :on 860506,high Chlorine Alarm Condition Occurred.Caused by Failure to Close Chlorination Valve 2-CS-V34 Per Operating Procedures.Disciplinary Action Taken W/Personnel Involved (← links)
- 05000324/LER-1999-004-02, :on 990502,noted That Reactor Recirculation Sys Pump Discharge Bypass Valve 2-B32-F032B Was Inoperable. Caused by Valve Internal Component Tolerances & Missing Wedge Spring.Subject Valve Was Rebuilt.With (← links)
- 05000324/LER-1988-001-01, :on 880102,manual Reactor Protection Sys Trip Scram Initiated Due to Decreasing Condenser Vacuum.Caused by Leaks on Main Turbine.Surveillance Activity Initiated on Failure of Valves to Open (← links)
- 05000324/LER-1988-015, :on 880426,limiting Conditions of Tech Specs 3.5.3.2,3.6.1.1,3.6.1.2 & 3.6.1.3 Not Met While Performing Startup Testing to Meet Tech Specs.Caused by Not Recognizing Mode Change.Standing Instruction Issued (← links)
- 05000324/LER-1986-005-02, :on 860209,during Local Leak Rate Testing, Discovered Nonquantifiable Leakage Rate for Primary Containment Isolation Valve 2-RXS-PV-1222C.Caused by Leakage Past Valve Seat.Valves Being Replaced (← links)
- 05000324/LER-1988-010, :on 880420,RWCU Inlet Inboard Primary Containment Isolation Valve Automatically Closed.Caused by Momentary RWCU Sys Flow Perturbation.Plant Procedures Revised to Alert Operator to Problem (← links)
- 05000324/LER-1998-003-03, :on 980829,MSIV Closures Were Noted.Caused by Procedure Deficiency.Reviewed Lessons Learned from Occurrence with Operations Personnel & Revised Affected Operating Procedures (← links)
- 05000324/LER-1988-013-03, :on 880802,reactor Protection Sys Bus a Automatically Deenergized.Caused by Tripping of Electrical Protection Assemblies 5 & 6 & Reactor Protection Sys Logic a Scram Signal.Power to Bus Aligned to Normal (← links)
- 05000324/LER-1988-011-03, :on 880725,reactor RHR Shutdown Cooling Sys Primary Containment Isolation Sys Inboard Isolation Valve Would Not Open.Caused by Electrical Malfunction.Wiring of Instrument Reconfigured to Utilize Switch 2 (← links)
- 05000324/LER-1988-012, :on 880725,HPCI Declared Inoperable Due to Inability to Determine Environ Qualification of Electrical Termination/Splices of Auxiliary Oil Pump.Caused by Inadequate Workmanship When Splices Made (← links)
- 05000324/LER-1988-008-02, :on 880331,full Reactor Protection Sys Trip Occurred When Mode Switch of APRM Rotated Beyond Switch Mechanical Stop Position.Caused by Improperly Configured Switch.Switch Replaced (← links)
- 05000324/LER-1988-009-01, :on 880331,full Reactor Protection Sys Trip Occurred Due to Upscale Trip of Intermediate Range Monitor. Caused by Spurious Electronic Noise.Electronic Noise Suppressors Installed in Circuitry (← links)
- 05000324/LER-1985-014-02, :on 851231 & 860101,testing of Mod to Automatic Depressurization Sys Revealed That Sys Logic Timing Relays Out of Timing.Cause Not Determined.Relays Replaced.Setpoint Drift Will Be Evaluated in Future Testing (← links)
- 05000324/LER-1985-002, :on 850215,HPCI Sys & RHR LPCI Loop B Inoperable.Caused by Mispositioned HPCI Pump Discharge Valve E41-F006 & switch,E11-DPIS-N021B,outside Calibr Tolerances. DPIS-N021B Calibr & F006 Repositioned (← links)
- 05000324/LER-1986-001-01, :on 860107,testing of Safety Relief Valves Revealed That 10 Valves Exhibited Symptoms of Setpoint Drift.Caused by High Friction in Labyrinth Seal Area.Valves Refurbished & Recertified.Discs Replaced (← links)
- 05000324/LER-1988-007-01, :on 880319,visual & Liquid Penetrant Insps of Unit CRD Insert/Withdraw Lines Revealed Existence of Pinhole & Linear Indications in Lines.Caused by Chloride Contamination.Affected Lines Replaced (← links)
- 05000324/LER-1997-001-03, :on 970627,containment Atmospheric Control Monitor Was Inoperable Due to Thermoelectric Cooler Failure. Replaced Thermoelectric Coolers W/Improved Seal Design (← links)
- 05000324/LER-1987-012-03, :on 871207,unplanned Div I Primary Containment Group 5 Isolation of RCIC Sys Occurred.Caused by Personnel Error.Jumper Reinstalled & RCIC Sys Returned to Standby Readiness (← links)
- 05000324/LER-1988-006-02, :on 880308,control Rod 10-39 Unknowingly Withdrawn W/Reactor Protection Sys Shorting Links Installed. Caused by Personnel Error.Individuals Involved Counseled & Process of Software Mod to Be Reviewed (← links)
- 05000324/LER-1988-004-02, :on 880224,standby Gas Treatment Sys Trains 2A & 2B Autostarted & Reactor Bldg Ventilation Autoisolated. Caused by Blown Power Supply Fuse in Div I Trouble/Start Relay Logic Circuitry.Fuse Replaced (← links)
- 05000324/LER-1978-059-03, /03L-0 on 780904:RCIC Isolation Channel a Tripped Momentarily,Causing RCIC Sys to Be Inoper,Due to Defective RX-2 Relay (← links)
- 05000324/LER-1986-003-02, :on 860131,ultrasonic Exam of Reactor Shroud Head hold-down Bolts Revealed Existence of Crack Indications in 15 of Total 36 Bolts.Caused by Igscc.Addl Data Re Indication Phenomenon Will Be Acquired (← links)
- 05000324/LER-1985-011, :on 851015,reactor Pressure Spiked & Unit Auto Scrammed on High Power When MSIV B21-FO22a Auto Closed. Caused by Failure of three-way Solenoid Valve Assembly.Valve Assembly Replaced (← links)
- 05000324/LER-1986-010, :on 860317,primary Containment Group 6 Isolation Signal Occurred,Resulting in Automatic Isolation of Reactor Bldg Ventilation Sys.Caused by Electrical Shorting.Fuse Replaced & Signal Reset (← links)
- 05000324/LER-1986-004-02, :on 860303,primary Containment Group 6 Isolation,Automatic Isolation of Reactor Bldg Vent Sys & Automatic Start of Standby Gas Treatment Sys Occurred. Caused by Blown Fuse F-5.Fuse Replaced (← links)
- 05000324/LER-1986-008, :on 860310,emergency Ac 4160-volt Bus E-4 Automatically Deenergized.Caused by Auxiliary Operator Inadvertently Deenergizing Potential Transformer in Compartment Ako.Bus E-4 Reenergized (← links)
- 05000324/LER-1985-010-02, :on 851009,logic Sys Functional Test Did Not Verify Bypass of 40% Main Steam Isolation Function.Caused by Failure to Recognize Subj Testing Requirement.Function Verified on 851017.Review in Progress (← links)
- 05000324/LER-1985-012-02, :on 851122,unit Scrammed & Automatic Initiation of Primary Containment Groups 2 & 6 Isolation Valves Occurred on Low Level.Possibly Caused by Real or Sensed Flow Perturbation (← links)
- 05000324/LER-1996-003, :on 960317,units Declared Inoperable & Reactor Shutdown of Units Initiated.Caused by Corrosion Induced by Galvanic Coupling of Retainer Bolting.Corroded Bolting Replaced (← links)
- 05000324/LER-1985-013-02, :on 851205,RWCU Sys Inlet Outboard Isolation Valve 2-G31-F004 Automatically Closed.Caused by Circuitry Fuse F18 Blowing Due to Undetectable Current Surge.Fuse Replaced & RWCU Sys Returned to Svc (← links)
- 05000324/LER-1984-017-01, :on 841130,Group 3 Primary Isolation Occurred Due to Erroneous Reactor Water Cleanup Sys Area High Temp Signal.High Temp Signal Caused by Component Breakdown in Instrument Module N600F.Module Replaced (← links)
- 05000324/LER-1985-008-01, :on 850927,MSIVs F028A,F022C & F028C Did Not Fast Close During Surveillance Testing.Caused by disc-to- Seat Sticking of Valve Operator Double Solenoid Valves. Double Solenoid Valves Will Be Replaced (← links)
- 05000324/LER-1985-006-02, :on 850906,HPCI Rendered Inoperable Due to auto-closing of Sys Primary Containment Inboard Isolation Valve E41-F002.Caused by Alligator Clip from Test Equipment Leads Slipping Off Terminal Screw (← links)
- 05000324/LER-1985-005-03, :on 850904,reactor Scram Manually Initiated Due to Multiple Control Rod Drift Indications Resulting from Inadvertent Isolation of Air Supply to Control Rod Scram Air Header.Caused by Personnel Error (← links)
- 05000324/LER-1996-004-03, :on 960913,jet Pump Surveillance Was Not Performed Prior to Exceeding 25% Reactor Power.Caused by Human Performance Errors.Appropriate Disciplinary Action Taken W/Individuals Involved (← links)
- 05000324/LER-1996-003-03, :on 960828,MAPLHGR Thermal Limit as Specified in TS Was Exceeded During Unit 2 B2C11 Fuel Cycle,Due to Operation with PPC Error During Unit Coastdown.Feedwater Temperature Was Corrected on Unit 2 PPC (← links)
- 05000324/LER-1985-001, :on 850110,record File Verification of Plant Surveillance Test Scheduling & Tracking Sys Revealed Periodic Test Not Performed.Caused by Inadvertent Deletion from Data Base.Logging Program Instituted (← links)
- 05000324/LER-1992-009-03, :on 921030,continuous Fire Watch Not Established When DG Building Fire Door & Fire Detection Sys Were Inoperable.Personnel Did Not Comply W/Requirements. Review of Requirements Will Be Held by 930115 (← links)
- 05000324/LER-1992-004-03, :on 920730,RWCU Isolation Occurred During E7 Substation Deenergization of RWCU HX Outlet Temp Switch. Caused by Failure to Adequately Review Potential Effects of Activity.Procedures Revised (← links)
- 05000324/LER-1992-010-03, :on 921207,penetration Leakage Results Exceeded Allowable Limit During Local Leak Rate Testing,Due to Main Valve Disc Not Guiding Properly Into in-body Seat.Outboard MSIV Will Be Tested & Repaired (← links)
- 05000324/LER-1980-002-03, /03L-0:on 800102,during Normal Reactor Startup,Rod Sequence Control Sys Would Not Allow Rods to Be Pulled Until Rod 34-27 Was Bypassed full-in. Caused by Defective full- in Reed Switch.Switch Will Be Repaired or Replaced (← links)
- 05000324/LER-1979-057-03, /03L-0 on 790717:safety Relief Valve Lifted & Reset at 970 Lb for No Apparent Cause.Valve Solenoid & Operator Replaced.Supplemental Rept Will Be Issued When Results Received (← links)
- 05000324/LER-1992-006-03, :on 920819,pipe Support 2-BSEP-12-I Found Missing.On 920821,support 2-BSEP-12-G for SDV Instrument Vol Line Found Missing.Cause Not Determined.Walkdown Conducted, Missing Supports Replaced & Headers Inspected (← links)
- 05000324/LER-1985-007-02, :on 850409,reactor Water Cleanup Sys Inlet Primary Containment Inboard & Outboard Isolation Valves 2-G31-F001 & F004 Closed on Primary Containment Group 3 Isolation Signal (← links)
- 05000324/LER-1982-071-03, /03L-1:on 820701,primary Containment Penetrations & Isolation Valves Found to Have Leak Rate Greater than 0.60 L.Valves & Penetrations Repaired & Returned to Svc.No Further Action Planned (← links)
- 05000324/LER-1980-121-03, /03L-1:on 801229,following Reactor Scram,Reactor Level Instrument 2-B21-LI-R604A Did Not Track Properly to Decreasing Reactor Level.Caused by Instrument Level Transmitter 2-B21-LT-N026A Out of Calibr (← links)
- 05000324/LER-1992-005, :on 920528,MCC 2-2XB-2 Declared Inoperable Due to Seismic Support & Anchorage Deficiencies.Root Cause Analysis in Progress.Subj MCC Repaired & Engineering Evaluation Procedure ENP-12 Will Be Revised (← links)
- 05000324/LER-1992-003, :on 920413,observed That Foundation Bolts on Control Bldg Emergency Air Filtration Unit Appeared Not to Be in Full Contact W/Nuts.Caused by Missing Clip Angle Weld. Bolts Repaired & Welds Fabricated at Angle (← links)
- 05000324/LER-1985-002-02, :on 850215,HPCI Sys Declared Inoperable Following Testing Which Revealed HPCI Pump Discharge.Valve E41-F006 Would Not Open.Caused by Pump Valve Not Functioning within Calibr Tolerances (← links)
- 05000324/LER-1984-014-01, :on 841127,while Attempting to Establish Shutdown Cooling on 100pA of RHR Sys,Water Hammer Event Damaging Supports on Steam Condensing Line Occurred.Caused by Mispositioning of Output Jack (← links)
- 05000324/LER-1984-018, :on 841127,automatic Reactor Scram Occurred Due to Main Turbine Trip & Stop Valve Closure.Caused by Crud Accumulation in Instrument Internals of Level Switch 2-MD-LSH-MS-2.Instrument Internals Cleaned (← links)
- 05000324/LER-1984-011-01, :on 840924,automatic Trip of Channels a & B W/Primary Containment Isolation Sys Occurred Due to Reactor Low Water Level.Caused by Misoperation of RHR Sys.Operator Involved Counseled & Disciplined (← links)
- 05000324/LER-1996-001, :on 960202,planned Reactor Manual Scram Inserted to Support Start of Unit 2 B212R1 Refueling Outage. Caused by Accelerated Aging.New Assembilies Replaced & Increased Frequency of Monitoring Performance (← links)
- 05000324/LER-1984-001-02, :on 840330,local Leak Rate Testing of Primary Containment Isolation Valves Revealed Nonquantifiable Leak Rate for Reactor Feedwater Line B Penetration X-9B.Caused by Problems W/Seat discs,O-rings & Bellows (← links)
- 05000324/LER-1992-007-03, :on 920930,2A Train of SBGT Sys Initiated Due to Presence of Alpha Contamination Coincident W/Failure of RB Ventilation Sys.Technical Support Will Develop Inventory Program to Control Spent Fuel Pool Inventory (← links)
- 05000324/LER-1985-001-01, :on 850110,channel Calibr & Functional Test of Main Condenser Low Vacuum Instrumentation Discovered Not Performed within Specified Time.Caused by Deletion of Test from Data Base (← links)
- 05000324/LER-1992-005-03, :on 920528,MCC 2-2XB-2 Was Declared Inoperable Due to Inadequate Welding of MCC Floor Sill to Embedded Pad Channel.Replacement of 1/4 Inch Diameter Internal Mounting Bolt W/Carbon Steel Bolt (← links)
- 05000324/LER-1984-012-01, :on 841024,automatic Reactor Scram Occurred Due to High Reactor Pressure Resulting from Unit Primary Containment Group 1 Isolation.Caused by Main Steam Line High Flow Spike.Setpoints Reevaluated (← links)
- 05000324/LER-1984-016-01, :on 841115,reactor Water Cleanup Sys Primary Containment Isolation Valve 2-G31-F004 Would Not Close. Caused by Insufficient Spring Tension on Valve Motor Torque Switch Closing Contacts.Switches Replaced (← links)
- 05000324/LER-1996-002-02, :on 960306,SRVs Tested at Wyle Lab Exceeded TS Setpoint Limits Due to Setpoint Drift.Caused by Oxygen Induced Pilot disc-to-seat Bonding.Srv Pilot Valve Assemblies Replaced (← links)
- 05000324/LER-1992-013, :on 920430,unexpected Primary Containment Isolation Sys Group 6 Isolation Received & Standby Gas Trains Autostarted.Caused by Incomplete Clearance Instructions.Bus Load Lists Incorporated (← links)
- 05000324/LER-1996-001-02, :on 960202,CR Average 5% Insertion Time Exceeded TS Limits.Caused by Natural Aging of the CR HCU SSPV & Possible Pipe Threads Sealant Intrusion on Diagram. C/A Will Be Reported in Suppl (← links)
- 05000324/LER-1985-003-03, :on 850310,unexpected Primary Containment Group 1 Isolation Occurred During Response Time Testing of Main Turbine Stop Valves.Periodic Test PT-45.1.6-2 & Corresponding Response Time Test Revised (← links)
- 05000324/LER-1984-031, :on 841106,07,09 & 13,control Bldg Emergency Air Filtration Sys Initiated Due to Spurious Fire Alarms or Fire Detector Actuations.Caused by Actuations from Ventilation Testing & from Cigarette Smoke (← links)
- 05000324/LER-1984-013, :on 841112,while Performing Operability Test on HPCI Sys,Sys Auxiliary Oil Pump Tripped on Motor Circuit Breaker Thermal Overload & Would Not Restart.Cause Unknown. Devices Reset & Pump Returned to Svc (← links)
- 05000324/LER-1992-020, :on 920710,TS Surveillance CAC SBGTS Heater Indicated That Degraded Voltage Should Have Been Considered. Caused by Degraded Voltage at Mcc.Sbgt Heater Surveillance Will Be Revised to Compensate for Worst Case (← links)
- 05000324/LER-1984-010-01, :on 840827,during Refueling/Maint Outage, Automatic Trip of Both Reactor Protection Sys Channels a & B Occurred.Caused by Possible Welding or Mechanical Shock During Outage (← links)
- 05000324/LER-1984-009-01, :on 840810,spurious Instrument Upscale Spike of Reactor Power Intermediate Range Monitor D Occurred. Reactor Protection Sys Automatic & Manual Scram Trip Logic Relays Will Be Inspected (← links)
- 05000324/LER-1984-008-02, :on 840727,reactor Protection Sys Actuated Due to Electronic Noise Spike.Caused by Section of Fallen Grating Resulting from Snagged Technician Respirator Air Line.Grating Replaced (← links)
- 05000324/LER-1995-003-02, :on 951004,RHR Pump Was Inoperable Due to Inadequate 4KV Breaker Engagement.Counseled Involved Individual (← links)
- 05000324/LER-1991-020-02, :on 911214,HPCI Turbine Steam Supply Valve E41-F001 Would Not Open from Control Room During Second Overspeed Trip Test Due to Loose Limit Switch Assembly.Valve Limit Switch Assembly Tightened & Adjusted (← links)
- 05000324/LER-1991-021-02, :on 911217,voltmeter Internal Failure During Testing Resulted in Inadvertent HPCI Injection & Reactor Scram.Caused by Low Resistance Values at Input Terminals for Voltage Scales.Maint Policy Initiated (← links)
- 05000324/LER-1980-060-03, During Reactor Startup, Control Rod 38-27 Could Not Be Withdrawn Beyond Position 46. Caused by Control Rod Becoming Uncoupled from CRD Due to Dirty Filter.Crd Rebuilt & Filter Replaced (← links)
- 05000324/LER-1984-007, :on 840522,during Refueling/Maint Outage,Asme Testing Revealed Safety Relief Valve F013L Would Not Lift & F013E,J & K Lifted at Pressures Above Setpoint Tolerance. Caused by Friction in Labyrinth Seal Guides (← links)
- 05000324/LER-1982-121-03, Electrical Trip of Traverse in-core Probe (TIP) Drive Motor Occurred While TIP Detector Partially Inserted Into Core.Caused by Defective Tubing.Tubing Replaced (← links)
- 05000324/LER-1982-088-03, Suppression Pool Suction Supply Valve 2-E11-F004B Stem Spun Beyond Full Open Valve Position.Caused by IGSCC Due to Improper Heat Treating.New Valve Stem Installed (← links)
- 05000324/LER-1984-006, :on 840504,while Decreasing Reactor Level for Reactor Feedwater Sparger Repairs W/Reactor Defueled & Fuel Pool Gates Installed,Reactor Level Decreased to Low Level Setpoint.Procedure Revised (← links)
- 05000324/LER-1992-002-03, :on 920317,HPCI Sys Automatic Isolation Occurred,Resulting in Isolation Signal to HPCI B Logic. Caused by Personnel Error & Differences in Order in Which Temp Switches Heated.Switch Labels Replaced (← links)
- 05000324/LER-1983-089-03, /03L-0:on 831010,valve Solenoid Operator Power Supply Fuse FJ-1 Failed,Defeating Valve Capability to Automatically Close on Line Excess Flow.Caused by Water Splashover from Housekeeping Washing (← links)
- 05000324/LER-1982-069-03, Rod Overtravel Annunciation Received During Verification of Rod Drive Coupling for Rod 30-31.Caused by Loose Drive Unit Inner Filter.Inner Filter Replaced (← links)
- 05000324/LER-1992-001-03, :on 920129,annunicator for Low Electrohydraulic Fluid Pressure Received.On 920202,switch A1 Tripped & Full Scram Signal Received Causing Reactor Trip.Caused by Excessive Cycling.Reactor Power Reduced (← links)
- 05000324/LER-1984-004, :on 840222,while Testing Primary Containment Isolation Sys of Reactor Low Water Level,Logic Channel N0254A-1,MSIV B21-F028D Closed,Resulting in Reactor Scram. Caused by Ac & Dc Solenoid Valves Deenergized (← links)
- 05000324/LER-1984-003-01, :on 840214,normal Power Supply Feeder Emergency Bus E-4 Automatically Opened Due to Bus Undervoltage Condition Sensed by Bus Degraded Voltage Relay 27DV.Cause Unknown (← links)
- 05000324/LER-1991-011, :on 910824,light Bulb on Motor Control Ctr for RWCU Inlet Outboard Isolation Valve Burned Out & Bulb Broke Off in Socket,Causing Electrical Short.Caused by Blown Fuse. Light Bulb & Fuse Replaced (← links)
- 05000324/LER-1991-019-02, :on 911112,results of Testing Indicated MSIV Leakage on Main Steam Lines C & D,Exceeding TS Limit of 11.5 Scfh.Cause Unknown.Main Steam Lines C & D MSIV Repairs Completed (← links)
- 05000324/LER-1991-005-01, :on 910630,ESF Actuations Occurred When Floor Drain Isolation Valve Failed to Close on Group Ii/Div II Signal.Caused by Voltage Regulator Transient & Failure of solenoid-operated Valves.Solenoids Replaced (← links)
- 05000324/LER-1991-018-02, :on 911020,hydraulic Perturbation of Shared Ref Leg Occurred,Resulting in Isolation of RB Ventilation Sys & Automatic Start of 2A & 2B Sbgts.Caused by Lackof Attention to Detail.Technician Counseled (← links)
- 05000324/LER-1991-017-02, :on 911017,Wyle Labs Notified Util That safety- Relief Valves Exceeded Tech Spec Setpoint Drift.Caused by pilot-disc-to-seat Bonding Preventing Valves from Actuating.Ts Change Will Be Requested (← links)
- 05000324/LER-1991-016-02, :on 911005,severe Weather Induced Voltage Drop on off-site Distrubution Line,Resulting in Primary Containment Isolations.Caused by Electrical Storm.No Corrective Actions Required (← links)
- 05000324/LER-1991-015-02, :on 911002,unplanned ESF Actuation Occurred While Removing Reactor Low Level Instrumentation from Svc. Caused by Lack of Caution in Surveillance Procedure. Procedure Will Be Revised Re Analog Trip Unit (← links)
- 05000324/LER-1991-012-03, :on 910914,RWCU Sys Cleanup Leak hi-hi Alarm Annunicated in Main Control Room & Valve Group 3 Automatic Isolated Signal Received.Caused by Failure of Rosemount Transmitter.Transmitter Shipped to Vendor (← links)
- 05000324/LER-1991-013-03, :on 910914,RCS Structural Integrity Limit Exceeded When Operator Failed to Recognize Limiting Temp Condition.Rcs Temp Restored to 142 F & Standing Instruction Issued to Operator (← links)
- 05000324/LER-1984-005, :on 840228,Tech Spec 3.6.3a,re Inoperability of Primary Containment Isolation Valves,Not Met When Valve Packing on Reactor Water Cleanup Sys Inlet Outboard Isolation Valve 2-G31-F004 Adjusted (← links)
- 05000324/LER-1995-002-02, :on 950510,HPCI Sys Failed to Operate as Required During Performance of HPCI Periodic Test.Caused by End of Burnout.Verified Adequacy of Similar Resistors in Unit 1 & 2HPCI & RCIC Sys (← links)
- 05000324/LER-1982-141-03, /03L-0:on 821218,primary Containment Atmosphere Oxygen Analyzer 1-CAC-AT-1263-2 Showed Upscale Indication of Drywell Oxygen Concentration.Caused by 1263-2 Analyzer Zero Shift.Analyzer Calibr & Returned to Svc (← links)
- 05000324/LER-1982-135-03, /03L-0:on 821227,low Pressure Microswitch of Primary Containment Isolation Sys HPCI Steam Supply Pressure Instrument 2-E41-PSL-N001D Would Not Actuate During Test PT-02.1.2P.Caused by End of Component Life (← links)
- 05000324/LER-1982-143-03, /03L-0:on 821220,reactor Water Cleanup Differential Flow Indicator 2-G31-R615 Indicated Downscale During Routine Surveillance.Caused by Partially Plugged Low Side Sensing Line to FT-N041 & Out of Calibr Transmitters (← links)
- 05000324/LER-1982-140-03, /03L-0:on 821221,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1263-2 Showed Step Increase in Drywell Oxygen Concentration.Caused by Zero Shift Due to Analyzer Being Out of Calibr & by Small Piping Leak (← links)
- 05000324/LER-1981-143-03, While Performing Diesel Generator 4 Monthly Load Test,Model F5-1316-HS6 Would Not Assure Steady Load Greater than 1,000 Kw.Cause Undetermined.Diesel Generator Returned to Svc (← links)
- 05000324/LER-1983-097-01, /01T-0:on 831212,during IE Bulletin 83-02 Testing, Crack Indications Identified in 19 of 131 Welds.Caused by Intergranular Stress Corrosion Cracking.Eight Welds Repaired.Remaining Indications Acceptable (← links)
- 05000324/LER-1983-098-03, /03L-0:on 831118,determined Surveillance Procedures Did Not Provide for Individual Verification to Ensure Reactor Protection Sys (RPS) Instrument Channel Capable of Deenergizing RPS Scram Relay (← links)
- 05000324/LER-1991-011-03, :on 910824,primary Containment Penetration Discovered Not Completely Isolated Due to Potential Leakage Past RWCU Sys.Caused by Electrical Short During Light Bulb Replacement.Bulb & Fuse Replaced (← links)
- 05000324/LER-1991-006-03, :on 910821,temp Switch Incurred During Routine RWCU Surveillance Testing.Caused by Electrical Noise. Spurious Trips of Riley Model Temp Switches Identified in Rept (← links)
- 05000324/LER-1983-090-01, /01T-0:on 831111,drywell Equipment Drain Line, Floor Drain Line & Svc Air Header Determined Inadequate to Prevent Primary Containment Isolation During Seismic Event. Caused by Oversight During Design (← links)
- 05000324/LER-1983-094-03, /03L-0:on 831102,control Rod 38-23 Did Not Have RTGB Position Indication at 12 & Control Rod 30-39 Did Not Have RTGB Position Indication at 04.Caused by Problems on Indication Reed Switch of Each Rod (← links)
- 05000324/LER-1991-010-02, :on 910806,RWCU Sys Automatically Isolated on High Differential Flow While Being Restored to Svc.Caused by Inadequate Procedures.Rwcu Reject to Main Condenser Isolation Valve Replaced (← links)
- 05000324/LER-1983-091-03, /03L-0:on 831026,isolation Valve E51-F043C Would Not Reopen.Caused by Broken Bakelite Nipple in Valve Control Switch,Model EF4.Switch Module B47173 Replaced & Valve F043C Cycled & Returned to Svc (← links)
- 05000324/LER-1991-009-02, :on 910709,ESF Actuation Occurred Due to Voltage Spike During Routine Hpic Surveillance.Caused by de-energization of Relays.Movs Installed (← links)
- 05000324/LER-1991-008-03, :on 910709 & 24,RWCU Inlet Outboard Isolation Valve Received Nonregenerative Heat Exchanger Discharge High Temp Isolation Signal.Caused by Too Much Reactor Coolant. RWCU Returned to Svc (← links)
- 05000324/LER-1983-093-03, /03L-0:on 831024,control Room post-accident Monitoring Recorder/Indicator 2-CAC-AR-1263 Exhibited Erratic Indications of Drywell Oxygen Concentration.Caused by Excessive Buildup of Foreign Matl (← links)
- 05000324/LER-1983-095-01, /01T-0:on 831102,while Performing Visual Insp of Fire Barrier Penetrations,Some Penetrations Contained Link Seals Failing to Meet 3 H Fire Barrier Criteria.Cause Under Investigation (← links)
- 05000324/LER-1983-074-03, /03L-0:on 831006,reactor Recirculation Pump 2A Tripped Due to Motor Generator Set High Fluid Drive Temp. Caused by Slight Mechanical Shock of Motor Generator Set Fluid Drive High Temp Trip Device (← links)
- 05000324/LER-1983-085-03, /03L-0:on 830928,while Performing Diesel Generator 4 Monthly Load Test PT-12.2d,diesel Generator Would Not Develop Generator Output Current.Caused by Failed Solenoid Cell 9103B.Cell Replaced (← links)
- 05000324/LER-1983-081-03, /03L-0:on 830930,isolating Function of TIP C Guide Tube Primary Containment Isolation Ball Valve Found Inoperable When Machine Probe Would Not Fully Retract from Core.Investigation Will Be Performed (← links)
- 05000324/LER-1981-097-03, When Reactor Recirculation Pump 2A Tripped,No Annunciators Received. Caused by Intermittently Sticking Contacts of Logic Channels a & C.Switch Replaced (← links)
- 05000324/LER-1983-088-03, /03L-0:on 830927,RHR Subsystem HX Outlet Isolation Valve 2-E11-F003B Failed to Open Using Valve Motor Operator. Caused by Mechanically Stuck Circuitry Contactor.Auxiliary Contactor Replaced (← links)
- 05000324/LER-1983-087-03, /03L-0:on 830920,reactor Recirculation Pump 2A Tripped Due to Unintentional Actuation of Atws/Rpts Instrument B21-LTM-NO24A.Caused by Inadvertent Selection of Card File Location 3.Trip Condition Reset (← links)
- 05000324/LER-1983-070-03, /03L-0:on 830907,core Spray or RHR Pumps Running Annunciation Received W/No Abnormalities or Pumps Running. Caused by Microswitch NO20A Failure.Switch Replaced (← links)
- 05000324/LER-1983-080-03, /03L-0:on 830831,following Scram,While Utilizing HPCI Sys as Heat Sink for Reactor,Suppression Pool Water Level Exceeded Tech Specs.Caused by HPCI Pump Min Flow Valve Failing in Open Position.Valve Closed (← links)
- 05000324/LER-1983-082-03, /03L-0:on 830902,suppression Pool Level Exceeded Specs W/Value of -26.25 Inches.Caused by Failure of Operator to Adequately Monitor Level While Instrumentation Out of Svc Due to Plant Mod.Level Returned to Specs (← links)
- 05000324/LER-1983-084-03, /03L-0:on 830902,rod Worth Minimizer Went to Control Rod Group 4 While Last Two Control Rods of Group 3 Still Fully Inserted.Cause to Be Determined During Future Reactor Startup (← links)
- 05000324/LER-1983-073-03, /03L-0:on 830824,during Surveillance,Instrument Indication of Reactor Water Cleanup Sys Differential Flow Indicator 2-G31-R615,GE Model 180,indicated High.Caused by Entrapped Air in Transmitter Sensing Lines (← links)
- 05000324/LER-1983-059-03, /03L-0:on 830822,discovered Automatic Depressurization Sys Initiation Logic a Switch 2E11-PS-N016A Would Not Respond to Applied Test Signal.Caused by Corrosion of Switch Internals & Setpoint Drift (← links)
- 05000324/LER-1983-096-03, /03L-0:on 831226,augmented Offgas Bldg Fire Hose Stations 2-AOG57 to 62 Inoperable Due to Valve Body Crack Rupturing.Caused by Low Ambient Outside Air Temp & Lack of Heat Tracing.Valves V901 & V906 Replaced (← links)
- 05000324/LER-1983-061-03, /03L-0:on 830712,bus E-8 to Motor Control Ctr (MCC) 2XB Electrical Bus Feeder Breaker Tripped.Caused by MCC-powered Hydrolaser Shorting.Breaker Supplying Hydrolaser Opened/Feeder Breaker Closed to Reenergize MCC (← links)
- 05000324/LER-1983-051-03, /03L-0:on 830524,while Performing PT-03.1.2P,HPCI Sys Condensate Storage Tank Low Water Level Instrument 2-E41-LSL-N003 Did Not Respond to Applied Test Input.Caused by Deposit Blockage of Instrument Vent Line (← links)
- 05000324/LER-1983-015-03, /03L-0:on 830123,reactor Recirculation Pump 2A Tripped.Caused by ATWS Reactor Pressure Instrument 2-B21-PS-NO45C Actuation Below Tech Spec Limit.Instrument Replaced (← links)
- 05000324/LER-1983-007-03, /03L-0:on 830115,HPCI Sys Steam Line High Temp Primary Containment Isolation Sys Isolation Occurred, Rendering HPCI Sys Inoperable.Caused by Personnel Error Due to Instrument Mislabeling.Test Signal Removed (← links)
- 05000324/LER-1991-014-01, :on 910927,unplanned Reactor Protection Sys Actuation Occurred When Operators Realigned Scram Discharge Vol hi-hi Level Trip Bypass Switch.Caused by Failure to Follow Instructions.Operator Disciplined (← links)
- 05000324/LER-1983-092-03, /03L-0:on 831219,accumulator Leak Detection Instruments 2-C12-LS-129-42-11,46-35,50-19 & 18-03 Failed to Respond to Applied Test Input.Caused by Instrument Failure. Instrument Replaced (← links)
- 05000324/LER-1991-004-03, :on 910625,unplanned ESF Actuation Occurred. Caused by Component Failure in RWCU High Ambient Temp Switch Point Module.Temp Switch Point Module Replaced (← links)
- 05000324/LER-1983-054-03, Following High/Low Alarm Annunciation,Rtgb Suppression Pool Level Indicator 2-CAC-LI-2601-1,3 & 2-CAC-LI-3342 Levels Found Below Tech Spec Limit.Caused by Spraying Water (← links)
- 05000324/LER-1981-118-03, Five Secondary Containment Fire Seals Unable to Meet Test Acceptance Criteria & Declared Inoperable.Caused by Degradation Due to Cracking or Shrinking.Seals Repaired (← links)
- 05000324/LER-1995-001, :on 950105,discovered That Hydrogen/Oxygen Analyzer Sys Drain Valve Improperly Assembled During Sys Mod in 1987.Caused by Inadequate Mod Installation Instructions. Valve Reassembled & Bench Tested (← links)
- 05000324/LER-1983-083-01, /01T-0:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Found Shut. Auxiliary Operator Assigned to Hang Tag on 2-PWT-V5 Mistakenly Closed & Tagged 2-FP-V39 (← links)
- 05000324/LER-1983-077-03, /03L-0:on 830815,while Performing Loop Calibr of Remote Shutdown Panel Reactor Vessel Level Monitoring Instrumentation,Both Reactor Recirculation Pumps Tripped. Caused by Momentary Pressure Spike (← links)
- 05000324/LER-1991-007-03, :on 910407,determined That bus-to-bus Time on Emergency Diesel Generator 3 Resulted in Core Spray Sys 2A Response Time of 28.08 S.Caused by Slow Pressurization of Fuel Oil Header.Fuel Oil Pump Replaced (← links)
- 05000324/LER-1991-005-03, :on 910630,ESF Actuations Occurred.Caused by Voltage Regulator Transient W/Failure of Primary Containment Isolation Solenoid Operated Valves.Solenoids for 2-G16-F003 & 2-16-F004 Replaced (← links)
- 05000324/LER-1983-062-03, /03L-0:on 830707,performance of Primary Containment Volumetric Average Air Temp Test PT-1612 Revealed Temp Exceeded Tech Spec Limit of 135 F.Caused by Seasonal Ambient Temps & Plant Evolutions (← links)
- 05000324/LER-1983-057-03, /03L-0:on 830705,review of Documentation for ECCS-HPCI/CST Level Low Instruments Determined That Eight Tests Performed During 1979-82 Found One or Both Channels Operating Out of Tolerance & Left as Found (← links)
- 05000324/LER-1983-055-03, /03L-0:on 830704,while Performing ECCS Reactor Low Water Level Channel Calibr & Functional Test,Ads Relay 2-B21C-K24 Remained Energized When Test Signal Removed from N031A-3.Caused by Defective Slave Trip Unit (← links)
- 05000324/LER-1991-003-03, :on 910521,ESF Actuation Occurred.Caused by Erroneous Trip in RCIC Steam Line Break Isolation.Condition Cleared W/O Corrective Actions (← links)
- 05000324/LER-1983-060-03, /03L-0:on 830706,HPCI Sys Outboard PCIV E41-F003 Automatically Closed Following Steam Leak Detection Ambient Temp High & HPCI Isolation/Trip Signal a Initiated Annunciations.Caused by Spurious Actuation (← links)
- 05000324/LER-1983-053-03, /03L-0:on 830628,performance of High Steam Line Radiation Channel Function Test PT-1.1.12PC Revealed Monitor 2-D12-LRM-K603D Actuating Above Specified Limit.Caused by Instrument Drift.Monitor Recalibr (← links)
- 05000324/LER-1991-002-03, :on 910402,IRM D Spiked Upscale During Dc Ground Isolation Procedures Causing Full RPS Trip.Rps Trip Reset After Circuit Breaker Closed,Metal Oxide Varistors Installed & Adverse Condition Rept Issued (← links)
- 05000324/LER-1983-050-03, /03L-0:on 830809,instrument Isolation Valves to Signal Transmitters of RHR Sys Flow Indicator 2-E11-FI-3338 & RHR Head Spray Flow Indicator 2-E11-FI-3339 Inadvertently Closed.Caused by Personnel Error (← links)
- 05000324/LER-1983-079-03, /03L-0:on 830807,during Diesel Generator 1 Monthly Load Test PT-12.2a,generator Reverse Power Trip Occurred, Rendering Diesel Unavailable for Automatic Operation.Caused by Personnel Error.Personnel Counseled (← links)
- 05000324/LER-1983-076-03, /03L-0:on 830812,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1259-2,showed Drywell Oxygen Concentration Approx 1% Higher than Redundant Analyzer. Caused by Analyzers Out of Calibr (← links)
- 05000324/LER-1982-052-03, Surveillance Revealed Makeup Demineralized Water Tank Inventory Below Stds.Caused by Isolated Fire Protection Water Tank Makeup Supply Due to Planned Maint.Makeup to Tank Restored (← links)
- 05000324/LER-1983-071-03, /03L-0:on 830729,while Performing PT-09.2,average Temp of Suppression Pool Water Exceeded Specified Max Allowed Temp of 105 F W/Recorded Value of 106 F.Caused by High Seasonal Inlet Temp of RHR HX (← links)
- 05000324/LER-1983-049-03, /03L-0:on 830511,main Steam Line Channel Instrument 2-D12-RM-K603D Found Actuating Out of Specified Tolerances.Caused by Zener Diode VR5 Failure in Channel Instrument drawer.VR5 Replaced (← links)
- 05000324/LER-1983-034-01, /01T-0:on 830811,instrumentation Isolation Valves to Differential Pressure Sensing Switches 1-CAC-PDS-4222 & 4223 Found Closed.Caused by Inadequate Sys Valve Lineup. Valves Reopened (← links)
- 05000324/LER-1983-067-03, /03L-0:on 830724,while Performing Rpts,Reactor Low Water Recirculation Pump 2A Tripped When Temporary Electrical Jumper Removed.Caused by Removal of Wrong Jumper (← links)
- 05000324/LER-1983-068-03, /03L-0:on 830725,drywell Equipment Drain Sump Flow Square Root Signal Converter 2-G16-FY-K600 Found Functioning Out of Tolerances.Caused by Instrument Drift. Instrument Will Be Replaced (← links)
- 05000324/LER-1983-036-03, /03L-0:on 830424,routine Surveillance Revealed That Primary Containment multi-plant Temp Recorder Showed Temp Indications But Printed Erratically.Caused by Failed .5 Timing Relay Which Prevented Printing (← links)
- 05000324/LER-1982-131-03, 1/2 Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam/Line Radiation Monitor D,2-D12-RM-K603D. Caused by Loss of High Voltage Input to Relay (← links)
- 05000324/LER-1983-065-03, /03L-0:on 830714,HPCI Condensate Storage Tank Level Switches E41-LSL-N002 & N003 Found W/Float Setpoint Out of Calibr.Caused by Incorrectly Installed Level Switches.Level Switches Raised to Proper Level (← links)
- 05000324/LER-1983-044-03, /03L-0:on 830408 & 09,during Unit Startup & Power Operations,Control Rods 02-27(02),34-03(04),34-23(02) & 30-11(03) Had No Indications for Identified Positions.Caused by Failed Position Reed Switches.Reed Switches Replaced (← links)
- 05000324/LER-1983-046-03, /03L-0:on 830410,wires to Terminals 13 & 14 in Terminal Box for MSIV 2-B21-F028A Found Reversed.Cause Undetermined.Wires Reterminated to Proper Terminals (← links)
- 05000324/LER-1994-002, :on 940117,spurious Div 1 RCIC Isolation Signal Received,Closing Inboard Steamline Isolation Valve 2-E51-F007.Cause Unknown.Steam Leak Detection Sys Will Be Replaced During Refueling Outage (← links)
- 05000324/LER-1983-016-03, /03L-0:on 830323,reactor Bldg Exhaust Ventilation high-high Alarm Occurred Concurrent W/Group 6 Primary Containment Isolation Signal.Caused by Failure of Relay K2 in Indication & Trip Unit D12-K609A.Relay Replaced (← links)
- 05000324/LER-1983-024-03, /03L-0:on 830321,during Routine Channel Check, Discrepancies in Level Indication of Reactor Level Instrument 2-B21-LT-NO17D-1 & Redundant Instrument Found. Caused by Small Stem Packing Leak.Leak Repaired (← links)
- 05000324/LER-1983-032-03, /03L-0:on 830315,during PT-1.1.12PC,main Steam Line Radiation Monitor 2-D12-LRM-K603A Actuated Above Tech Spec Limit.Caused by Alignment & Alarm Setpoints Out of calibr.K603A Calibr & PT-1.1.12PC Completed (← links)
- 05000324/LER-1983-030-03, /03L-0:on 830314,both Recirculation Pumps Tripped. Caused by Slight Disturbance in Common Ref Leg.Trip Signal Reset (← links)
- 05000324/LER-1983-028-03, /03L-0:on 830314,during Test of post-accident Containment Pressure Monitoring instrumentation,PT-56.6PC Revealed Drywell Pressure Indicator/Recorder Did Not Respond to Signal.Caused by Button Misposition (← links)
- 05000324/LER-1983-056-03, /03L-0:on 830605,while Withdrawing Control Rods to Increase Reactor Power Level,Control Rod 26-19 Did Not Have RTGB Position Indication as Required.Caused by Faulty Position Indication Probe (← links)
- 05000324/LER-1983-026-03, /03L-0:on 830313,suppression Pool Level Indicator/ Recorder 2-CAC-LR-2602 Showed out-of-spec Low Level While Redundant Level Indicators Showed Normal Level.Caused by out-of-calibr Instrument Transmitter.Device Recalibr (← links)
- 05000324/LER-1983-033-03, /03L-0:on 830223,while Performing High Steam Line Radiation Channel Calibr & Functional Test,Main Steam Line Instrument Channels a & D Found Out of Calibr.Caused by Instrument Drift.Drawers Recalibr (← links)
- 05000324/LER-1983-058-03, /03L-0:on 830606,HPCI Sys Steamline Area Differential Temp High Logic a Isolation Signal Occurred, Causing Automatic Closure of HPCI Sys Steam Supply Outboard Valve PCIV 2-E41-F003 (← links)
- 05000324/LER-1983-029-03, /03L-0:on 830220,routine Surveillance During Plant Operation Revealed Audible Evidence of Airflow Through Both Doors of Reactor Bldg 50-ft Elevation.Caused by 1 1/2 Inch Diameter Hole in Outer Door.Hole in Door Sealed (← links)
- 05000324/LER-1983-041-03, /03L-0:on 830520,rad Drift Annunciation Received for Control Rod 38-35.Caused by Problem in Rod Position Indication Probe.Annunciator Cleared.Problem Will Be Resolved During Sept 1983 Outage (← links)
- 05000324/LER-1983-035-03, /03L-0:on 830520,reactor Water Cleanup Differential Flow Indicator 2-G31-R615 Indicated High. Caused by Low Output Signal from Flow Transmitter FT-N012. Transmitter Calibr & Returned to Svc (← links)
- 05000324/LER-1983-048-03, /03L-0:on 830520,surveillance Revealed Primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1259-2 Drywell Oxygen Concentration 1% Higher than Redundant Analyzer.Caused by Calibr Drift (← links)
- 05000324/LER-1982-064-03, While Performing Diesel Generator 3 Monthly Load test,PT-12.2C,diesel Tripped & Locked Out Due to Increase in Temp.Caused by Closed Diesel Jacket Water HX Inlet Valve.Valve Reopened (← links)
- 05000324/LER-1983-017-03, /03L-0:on 830126,during Standby Gas Treatment Sys Heater Check,One Heater Element in Treatment Sys a Found Inoperable.Caused by Damaged Power Supply Cable Terminal Lug Ring.Lugs Checked for Proper Tightness (← links)
- 05000324/LER-1983-019-01, /01T-0:on 830210,while Performing Drywell Insp, Instrument Air Tubing to Safety Relief & ADS Valve Accumulators Inadequately Supported.Caused by Inadequate Controls to Ensure Support Design Compliance (← links)
- 05000324/LER-1983-020-03, /03L-0:on 830129,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1263-2 Indicated 0.5% Step Decrease in Drywell Oxygen Concentration.Caused by Zero Shift in Instrument Magnetic Analyzer 1263-2.Analyzer Replaced (← links)
- 05000324/LER-1983-047-03, /03L-0:on 830513,during Supervisory Technical Review of Completed Test Procedure for Fire Suppression Water Sys Valve Operability Test,Two Sys Valves Not Covered. Test Procedure Temporarily Revised (← links)
- 05000324/LER-1982-095-03, /03L-0:on 820903,discovered That Most Recent ILRT Exceeded Specified Testing Interval.Caused by Improper Scheduling.Scheduling Program Revised to Reflect Correct Scheduling Criteria (← links)
- 05000324/LER-1983-040-03, /03L-0:on 830426,while Performing Operability Test of Remote Shutdown RHR Sys Flow Monitoring Instrumentation PT-55.8PC,determined RHR Sys Flow Transmitter 2-E11-FT-3338 Had No Output Response to Applied Test Signal (← links)
- 05000324/LER-1982-081-03, /03L-0:on 820621,rods 06-23 & 26-27 Did Not Have RTGB Indication at Certain Positions.Caused by Personnel Failure to Properly Reconnect Rod Position Indication Probe Connectors.Connectors Checked & Tightened (← links)
- 05000324/LER-1982-014-03, /03L-0:on 820117,primary Containment Atmospheric Oxygen analyzer,2-CAC-AT-1263-2,did Not Show Expected Trend in Drywell Concentration.Caused by Analyzer Components Heating Up Due to Stuck Thermostat Electrical Contacts (← links)
- 05000324/LER-1982-017-03, /03L-0:on 820118,remote Shutdown Panel Suppression Chamber Water Temp Recorder 2-CAC-TR-778 Did Not Record Temps.Caused by Print Head Actuation Linkage Separating from Solenoid Due to Lack of Spring Tension (← links)
- 05000324/LER-1982-024-01, /01T-0:on 820205,control Bldg Emergency Ventilation Sys Trains Would Not Isolate Upon Receipt of Chlorine Isolation Signal When Sys Control Switch Was in on Position.Cause Undetermined.Design Review Underway (← links)
- 05000324/LER-1983-022-03, /03L-0:on 830201,primary Containment Atmosphere Oxygen/Hydrogen Monitor 2-CAC-ATH-1259 Showed Erratic Indications of Drywell Concentrations.Caused by Water Accumulation in Sample Lines.Water Removed (← links)
- 05000324/LER-1983-012-03, /03L-0:on 830121,surveillance Revealed Control Air Pressure of Diesel Generator 3 Below Tech Spec Limit.Caused by Crud Accumulation in Diesel Control Air Moisture Drain Trap Filter.Filter Replaced (← links)
- 05000324/LER-1983-010-03, /03L-0:on 830119,during Plant Operation,Both Doors of Reactor Bldg 20-ft Elevation Personnel Air Lock Opened Simultaneously.Caused by Misalignment of Inner Door Due to Normal Wear Preventing Proper Bolt Engagement (← links)
- 05000324/LER-1983-013-03, /03L-0:on 830122,rod Block Monitor B Inoperable Annunciator Received When Control Rod 30-35 Selected. Caused by Three Defective Dual Operational Amplifier IC Chips on Fifth first-level Multiplexer Card.Card Replaced (← links)
- 05000324/LER-1983-011-03, /03L-0:on 830120,RHR Reactor Pressure Low Annunciation Received.Caused by Electrical Resistor & Relay Failure in Instrument NO21C.Instrument Replaced (← links)
- 05000324/LER-1983-008-03, /03L-0:on 830118,during Channel Calibr & Functional Test,Hpci Sys Condensate Storage Tank Low Level Instrument 2-E41-LSL-N003 Failed to Actuate within Required Tolerance.Caused by Debris in N003 Vent Line (← links)
- 05000324/LER-1983-009-03, /03L-0:on 830118,reactor Recirculation Pump 2A Tripped When Pump Motor Generator Set Drive Motor Tripped. Caused by Actuation of Motor Generator Set Drive Motor Field Overcurrent Relay Device 27.Trip Signal Reset (← links)
- 05000324/LER-1991-001-02, :on 910125,reactor Scram Occurred from 100% Power Due to Turbine Trip on High Reactor Water Level While Calibrating Feedwater Computer Point.Caused by Failure of Work Control Process.Calibrs Stopped (← links)
- 05000324/LER-1983-001-03, /03L-0:on 830102 & 05,RCIC Turbine Exhaust Diaphragm Pressure High Annunciator Alarmed.Caused by Instrument Drift on 830102 & Moisture Accumulation in Switch Housing on 830105 (← links)
- 05000324/LER-1983-003-03, /03L-0:on 830103,following Reactor Scram Due to Group 1 Isolation,Suppression Pool Level Found Out of Spec High at -26.5 Inches.Caused by Operation of HPCI & Safety Relief Valves for Level & Pressure Control During Event (← links)
- 05000324/LER-1982-132-03, /03L-0:on 821217,during Nitrogen Makeup to Primary Containment,Core Auxiliary Cooling Sys 1-inch Drywell Inlet PCIV 2-CAC-V48 Discovered Leaking by Closed Valve Seat. Cause Undetermined.Containment Integrity re-established (← links)
- 05000324/LER-1991-004, :on 910218,invalid First Interval Hydrostatic Test Boundary on Reactor Pressure Vessel Identified.Cause Unknown.Technical Support in-service Insp Personnel Revising PT-80.1 (← links)
- 05000324/LER-1990-017, :on 901023,half Trip Signal,Half PCIS Group 1 Isolation Signal & Group 6 Isolation Occurred.Caused by Failure of Kepco Power Supply in Numac Lvps to Radiation Monitor B.Numac Lvps Replaced (← links)
- 05000324/LER-1994-009-02, :on 940619,isolation Signal Was Verified to Be Invalid & Valve Was Left Closed to Bypass Elements Being Heated.Caused by Personnel Error.Disciplinary Action Has Been Taken W/Maintenance Personnel (← links)
- 05000324/LER-1994-004, :on 940329,results of LLRT Indicated That Leakage on MSL Exceeded TS Limits Due to Scratches & Pitting Identified in Sealing Area of in-body Seats & Discs.Actuator Guide Tube Assemblies Were Removed (← links)
- 05000324/LER-1982-124-01, /01T-0:on 821121,quick Start Testing of Diesel Generators 1,2 & 4 Not Performed within Required 2-h Period. Caused by Misinterpretation of Plant Standing Instructions. Quick Starts Performed.Instructions Revised (← links)
- 05000324/LER-1994-008-02, :on 940521,dispatcher Switching Evolution Resulted in Loss of Offsite Power.Instructions for Any Planned Switching Activity at Nuclear Power Plant Will Require Dual Verification (← links)
- 05000324/LER-1982-128-03, /03L-0:on 821025,instrument Recorder 2-CAC-AR-1263 Showed Downscale Indication of Primary Containment Atmosphere Hydrogen & Oxygen Concentration.Caused by Failed Recorder Print Drive Motor.Drive Motor Replaced (← links)
- 05000324/LER-1982-117-03, /03L-0:on 821026,fire Watch Patrol Not Posted During Removal of Five Fire Barrier Penetration Seals in Control Bldg.Caused by Unfamiliarity W/Limiting Conditions for Operation & Fire Watch Requirements (← links)
- 05000324/LER-1982-125-03, /03L-0:on 821024,during steady-state Plant Operation,Reactor Recirculation Pump 2A Tripped W/Receipt of ATWS High Reactor Pressure/Low Level Trip Annunciator.Caused by Setpoint Drift.Instrument Calibr & Returned to Svc (← links)
- 05000324/LER-1982-126-03, /03L-0:on 821024,standby Liquid Control Sys Piping Heat Tracing on Lines Between Sys Accumulators 2-C41-A003A & B & Common Discharge Line Found Inoperable.Caused by Electrical Failure.Tracing Section Model FP-10 Replaced (← links)
- 05000324/LER-1983-043-01, /01T-0:on 830405,discovered Continuous Fire Watches for Inoperable Fire Detectors in Augmented Offgas Bldg Not Established on 830213.Caused by Personnel Error. Continuous Fire Watches Established (← links)
- 05000324/LER-1982-106-03, /03L-0:on 820917,while Reviewing Surveillance Procedures,Determined That Emergency Bus Degraded Voltage Channel Function Test Not Sufficient to Verify Operability of Emergency Bus Degraded Voltage Relays.Test Revised (← links)
- 05000324/LER-1994-007-01, :on 940318,identified That Snubber Support Anchor Bolts Were Degraded & Required Repair.Caused by Personnel Error.Const Craft Personnel Briefed on Importance of Fully Identifying Changes (← links)
- 05000324/LER-1983-031-03, /03L-0:on 830223,performance of Suppression Pool Level Indicators Operability Test Revealed Indicator/Recover Level,Redundant Indicators & Local Level Indicator Levels Incompatible.Caused by Loss of Trickle Flow (← links)
- 05000324/LER-1983-021-03, /03L-0:on 830301,HPCI Sys Declared Inoperable When Instrument 2E41-dPIS-N005 Showed Negative Indication While Redundant Instrument 2E41-dPIS-N004 Indicated Zero.Caused by Instrument drift.N005 Calibr & Returned to Svc (← links)
- 05000324/LER-1981-022-03, Primary Containment Atmospheric Control Suppression Pool Level Indicator, 2-CAC-LI-2601-3,gave Erratic Indication Level.Caused by Blockage in Water Supply Throttle Valve (← links)
- 05000324/LER-1982-015-03, /03L-0:on 820117,intermediate Range Monitor (IRM) C Declared Inoperable Due to Erratic Indication & IRM E,When on Range 9,indicated Downscale.Caused by Tear in Detector Signal Cable in IRM E & Defective Detector in IRM C (← links)
- 05000324/LER-1982-013-03, /03L-0:on 820116,reactor Low Level Switch 2-B21-LIS-N07 D-1 Actuated Below Min Level.Caused by Loose Setscrew Allowing Instrument Mechanism to Slip & Prevent Accurate Instrument Response.Screw Tightened (← links)
- 05000324/LER-1982-020-03, /03L-0:on 820129,primary Containment Atmospheric Oxygen Analyzer 2-CAT-AT-1263-2 Found Indicating High. Caused by Moisture Buildup in Analyzer Sample Piping. Moisture Removed & Analyzer Recalibr (← links)
- 05000324/LER-1982-021-03, /03L-0:on 820129,routine Comparison of Suppression Chamber Water Level Indicators on RTGB Revealed 1.5 Inch Discrepancy Between Narrow & Wide Range Instruments.Caused by Inoperability of RTGB Level Instruments (← links)
- 05000324/LER-1983-014-03, /03L-0:on 830216,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1259-2 Showed Drywell Oxygen Concentration 1% Higher than Indicated by Redundant Analyzer.Caused by Instrument Drift.Analyzer Recalibr (← links)
- 05000324/LER-1981-127-03, /03L-0:on 811121,printing Mechanism of Primary Containment Atmospheric Monitoring Recorder 2-CAC-AR-1259 Drove Hard Downscale When Exhibiting Indication of Hydrogen Concentration in Drywell.Caused by Instrument Drift (← links)
- 05000324/LER-1983-025-03, /03L-0:on 830216,closed Position Indication for Drywell to Suppression Pool Vacuum Breaker X18C Could Not Be Achieved.Caused by Problem W/Vacuum Breaker Closed Position Limit Switch LB-240-794.Problem Will Be Investigated (← links)
- 05000324/LER-1981-126-03, /03L-0:on 811119,during Routine Surveillance, Control Room Chart recorder/indicator,2-CAC-AR-1263,model Mark Ii,Discovered Showing Downscale Trend in Drywell Oxygen Concentration.Caused by Failure to Perform Required Maint (← links)
- 05000324/LER-1994-006-02, :on 940421,testing Indicated That Valves Would Not Pressurize.Caused by Failure of RWCU Suction Line Isolation Valves.Corrective Action:Installed Both RWCU Suction Isolation Valves (← links)
- 05000324/LER-1983-027-03, /03L-0:on 830216,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1263-2 Indicated Erroneous Drywell Oxygen Concentration.Caused by Instrument Drift.Analyzer Recalibr (← links)
- 05000324/LER-1983-023-03, /03L-0:on 830203,during Reactor Shutdown, Intermediate Range Monitor (IRM) E Did Not Give Onscale Indication Until IRM Range Switch Was on Position 2.Caused by Failed Bearing & Binding in Detector Drive Mechanism (← links)
- 05000324/LER-1982-129-03, /03L-0:on 821028,while Verifying Rod Drive Coupling for Rod 18-07,rod Overtravel Annunciator Received. Cause Unknown.Rod Will Be Inspected for Irregularities During Next Scheduled Control Rod Drive Rebuilding Outage (← links)
- 05000324/LER-1982-098-03, /03L-0:on 821027,measured Vibration Reading of 2B RHR Svc Water Pump Exceeded 1.5 Mils Vibration.Caused by Failed Gasket at Pump Rear Bearing Housing Allowing Loss of Casing Oil,Resulting in Increased Operating Temp (← links)
- 05000324/LER-1982-116-03, /03L-0:on 821023,while Performing Control Rod Operability Check,Rod 18-43 Did Not Have RTGB Indication at Position 18.Probably Caused by Defective Rod Position Indication Reed Switch (← links)
- 05000324/LER-1982-114-03, /03L-0:on 821019,control Rod 38-39 Had Simultaneous Full in & Full Out Position Indication While Fully Withdrawn.Caused by Defective IC Chip on Rod Position Indication Probe Circuitry Buffer Card Input.Chip Replaced (← links)
- 05000324/LER-1990-020-02, :on 901226,while Returning HPCI Sys to Svc, Determined That Min Flow Valve Control Power Fuse Blown, Resulting in Inoperability of Valve.Caused by Short in Indicating Light Bulb.Bulb & Fuse Replaced (← links)
- 05000324/LER-1982-120-03, /03L-0:on 821016,suppression Chamber Water Temp Recorder 2-CAC-TR-778 Was Recording Temps Intermittently. Caused by Recorder Print Actuation Solenoid Linkage Being Out of Adjustment.Linkage Adjusted (← links)
- 05000324/LER-1982-130-01, /01T-0:on 821029,during Insp of drywell,through- Wall Linear Indication Discovered at Weld R-20,located on RHR Shutdown Cooling Suction Line Between Line Manual isolation,E11-F067 & Downstream Elbow.Caused by Flaw (← links)
- 05000324/LER-1982-119-03, /03L-0:on 821007,reactor Recirculation Pump 2A Tripped When Test Signal Applied to Atws/Rpt Instrument 2-B21-LT-N024A-1.Caused by Failure of Periodic Test to Provide for Shutting N024A-1 Instrument Manifold Valves (← links)
- 05000324/LER-1982-115-03, /03L-0:on 821004,primary Containment Atmosphere Oxygen analyzer,2-CAC-AT-1263-2,indicated Abrupt Upscale Change from 3-6% in Drywell Oxygen Concentration.Caused by Output Shift Due to Excessive Moisture (← links)
- 05000324/LER-1982-122-03, /03L-0:on 821009,RCIC Sys Automatically Isolated Twice Upon Receipt of Spurious Steam Line Ambient Temp High Signals.Cause Unknown.No Instrumentation Failures Detected. RCIC Sys Returned to Normal Standby Readiness (← links)
- 05000324/LER-1982-118-03, /03L-0:on 821006,surveillance Revealed Control Rod 18-23 Had 7 Digit Continuously Lit in Location 1 Regardless of Rod Position.Caused by Defective Rod Position Indication Probe Switch.No Design Mods Planned (← links)
- 05000324/LER-1982-105-03, /03L-0:on 821006,control Rods 18-23 & PT-14.2.1 Exceeded Required 7-s to Fully Insert.Caused by Failure of Rod Hyraulic Control Unit Scram Pilot Valves SV-117 & 118 to Bleed Off Noninterruptible Instrument Air (← links)
- 05000324/LER-1990-018-02, :on 901123,HPCI Steam Leak Detection Channel B Logic Blew & HPCI Sys Manually Isolated.Probably Caused by Blown Fuse & Loose Wire.Relay & Fuse Replaced (← links)
- 05000324/LER-1982-112-03, /03L-0:on 820929,suppression Chamber Water Temp Recorder 2-CAC-TR-778 Discovered Intermittently Recording Temps on Chart Recorder.Caused by Out of Adjustment Recorder Print Actuation Solenoid.Solenoid Adjusted (← links)
- 05000324/LER-1982-113-03, /03L-0:on 821003,during Reactor Startup Coolant Analysis,Reactor Coolant Conductivity Exceeded Tech Specs. Caused by Breakdown of Reactor Water Cleanup Sys Resins. Resins Allowed to Decompose & Reactor Conductivity Reduced (← links)
- 05000324/LER-1990-011, :on 900830,RWCU Sys Manually Isolated Following Receipt of RWCU Leak Hi & hi-hi Annunciators (← links)
- 05000324/LER-1990-014-01, :on 900908,discovered ESF Actuation - RWCU Isolation When Fuse Blew in Power Supply to Differential Flow Istrument (← links)
- 05000324/LER-1990-017-02, :on 901023,ESF Actuation Occurred Due to Blown Fuse in Main Steam Line B & Reactor Bldg Ventilation Radiation Monitoring Power Supply B (← links)
- 05000324/LER-1982-107-03, Review of Fire Protection Carbon Dioxide Sys Surveillance Procedures Indicated Storage Bottle Weighing Device Did Not Have Periodic Calibr.Caused by Failure to Recognize Need for Accuracy Restraints (← links)
- 05000324/LER-1990-016-02, :on 901012,reactor Scram Occurred on Turbine Stop Valve Fast Closure Caused by Reactor High Level When Fuse Failed in Feedwater Control Sys Circuitry (← links)
- 05000324/LER-1990-006-01, :on 900604,hydraulic Perturbation of Reactor Vessel Resulted in Isolation of RWCU Sys.Caused by Increased Differential Pressure.Operations Personnel Restored Affected Sys to Svc (← links)
- 05000324/LER-1982-083-03, Performance of PT-20.6 Revealed That Drywell to Torus Vacuum Breakers X18A,C & E Were Leaking Excessively.Caused by Accumulation of Dirt, Scale & Silicone Base Sealant on Valve Seating Surfaces (← links)
- 05000324/LER-1983-006-03, /03L-0:on 830114,primary Containment Atmosphere Oxygen Analyzer 2-CAC-AT-1263-2 Indicated 0.5% Step Increase in Drywell Oxygen Concentration.Caused by Instrument Zero Shift.Monitors Replaced & Instrument Recalibr (← links)
- 05000324/LER-1983-004-03, /03L-0:on 830105,during Jumper Installation, Reactor Protection Sys Relay C72-K6C Found Melted Around Coil.Caused by Overheating of Relay.Relays to Be Inspected Monthly Until Replaced W/Improved Components (← links)
- 05000324/LER-1994-003, :on 940221,personnel Containment Monitor Panel Cover Fell Against Relay Causing Primary Containment Sys Isolation.Caused by Personnel Error.Personnel Contamination Monitors Repositioned (← links)
- 05000324/LER-1982-094-03, Review of Source Range Monitor Sys Channel Functional Test PT-01.2.1 Revealed That Weekly Surveillance During Fuel Handling Did Not Reflect Mode 5 Testing Frequency.Caused by Oversight (← links)
- 05000324/LER-1982-006-03, RTGB Instrument 2-CAC-LR-2602 Indicated Level Exceeding Specified Upper Limit.Caused by Loss of Wet Ref Leg to Transmitters 2-CAC-LT-2602 & LT-2601.Trickle Flow re-established (← links)
- 05000324/LER-1982-137-03, /03L-0:on 821206,during Operability Test of Remote Shutdown Panel,Rhrsw D/P Transmitter 2-E11-POT-N002BX Did Not Respond to Test Input Signal.Caused by Failed Transmitter Differential Pressure Unit.Transmitter Replaced (← links)
- 05000324/LER-1981-071-03, Primary Containment Atmospheric Control Suppression Chamber Water Level Range Recorder 2-CAC-LR-2602 Read High.Caused by Blockage in Transmitter.Blockage Removed & Transmitter Recalibr (← links)
- 05000324/LER-1981-135-03, RTGB Instruments 2-CAC-LR-2602 & 2-CAC-LI-2601-3 Indicated Water Level Exceeding Tech Specs.Caused by Change in Trickle Flow to Wet Ref Legs of Instrument Transmitters.Transmitters Calibr (← links)
- 05000324/LER-1982-109-03, /03L-0:on 821207,measured Liquid Nitrogen Inventory in Containment Atmosphere Dilution Tank Exceeded 4,350 Gallons.Caused by Lifting of Tank Pressure Relief Valves Due to Loss of Vacuum within Tank Insulation Jacket (← links)
- 05000324/LER-1981-133-03, Difference Noted Between RTGB instrument,2-CAC-LR-2602,indicated Level & Redundant instrument,2-CAC-LI-2601-3,actual Level.Caused by Loss of Trickle Flow to Wet Ref Leg Due to Dropped Valve Disc (← links)
- 05000324/LER-1978-079-03, /03L-0 on 781017:reactor Bldg Radiat Exhaust Monitor D12-RM-N010B Failed Safe Causing Reactor Bldg Vent to Isolate,Due to Defective Transistor 2N1711 on 24V Pwr Supply (← links)
- 05000324/LER-1994-001-01, :on 940131,hardened Wetwell Vent Line Isolation Valve CAC Did Not Have PCIS Group 6 Isolation Label & Logic Not Functionally Tested.Caused by Personnel Error.Temporary Revision to PT 4.1.1 Performed Satisfactorily (← links)
- 05000324/LER-1981-032-03, /03L-0:on 810223,while Performing Required Testing as Result of Diesel Generator 2 Being Out of Svc for Maint, Diesel Generator 3 Declared Inoperable Due to Low Control Air Pressure.Caused by Misaligned Valve Disc (← links)
- 05000324/LER-1982-096-03, /03L-0:on 820814,review of Primary Containment Isolation Logic Revealed Failure to Meet Requirement to Have Low Condenser Vacuum Switches B21-PS-N056 (A-D) in Svc When Vessel Pressure Was Greater than or Equal to 500 Psig (← links)
- 05000324/LER-1982-104-03, /03L-0:on 820811,determined That Required Verification of Indicated Power Availability for Specified Plant Dc/Ac Electrical Sys & offsite-onsite Class IE Electrical Sys Was Not Covered in Plant Procedures (← links)
- 05000324/LER-1982-101-03, /03L-0:on 820805,during Review of Surveillance Procedures,Required Surveillance of Div I & II Dc Electrical Sys Tie Breakers Discovered Missing from Plant Procedures. Caused by Personnel Oversight.Procedure to Be Revised (← links)
- 05000324/LER-1982-091-03, /03L-0:on 820727,several Relays in Logic Trains for Group 6 Isolation Valves Were Not Time Response Tested as Required.Caused by Personnel Error Due to Inadequate Review of Plant Mods in Jan 1980.Procedures Will Be Revised (← links)
- 05000324/LER-1982-100-03, /03L-0:on 820802,while Reviewing Plant Test Procedures,Portion of Logic for Core Spray & LPCI Initiation Not Time Response Tested.Caused by Failure to Recognize Requirement in Procedure.Procedures Revised (← links)
- 05000324/LER-1982-097-03, /03L-0:on 820727,review of Time Response Test Procedures for Reactor Water Cleanup Low Level 2 Isolation, Revealed Armature Travel Time for Last Relay in Logic Chain Not Timed.Caused by Improper Terminals.Procedures Revised (← links)
- 05000324/LER-1982-084-01, /01T-0:on 820810,two Control Bldg Ventilation Isolation Dampers Not Receiving Close Signal Upon Detection of Chlorine.Caused by Faulty Original Design.Design Modified & Will Be Installed Prior to Startup (← links)
- 05000324/LER-1982-089-03, /03L-0:on 820722,review of Plant Maint Procedure Revealed That post-maint Testing of Primary Containment Isolation Valves Per App J Was Not Established.Caused by Administrative Oversight.Procedure Revised (← links)
- 05000324/LER-1982-082-03, /03L-0:on 820722,surveillance Frequency Outlined in Test Procedure PT-01.10 Did Not Reflect Required Weekly Testing While in Operational Mode 5.Caused by Oversight in Development of Test.Periodic Test Revised (← links)
- 05000324/LER-1982-099-01, /01T-0:on 820731,pneumatic Supply to Cooler Air Operated Fan Exhaust Dampers Found Not to Be safety-grade Air Source,Resulting in Damper Failure During Interruptible Instrument Air Loss.Caused by Design Deficiency (← links)
- 05000324/LER-1982-086-03, /03L-0:on 820715,during Refueling Outage,Source Range Monitors C & D Indicated Erratic Upscale Count Rate. Caused by Guide Tube Sealing Gland Leak Allowing Moisture Intrusion Into Detector Cable Connectors.Leak Repaired (← links)
- 05000324/LER-1981-117-03, /03L-0:on 811115,primary Containment Atmospheric Monitor Oxygen Analyzer 1259 Indicated Higher Drywell Oxygen Concentration than Analyzer 1263.Caused by Decreased Flow Due to Moisture Buildup in Analyzer 1259 Torus Sample Li (← links)
- 05000324/LER-1981-123-03, /03L-0:on 811118,B Logic Reactor Protection Sys one-half Group 1 Isolation Signal Received.Caused by Electrically Grounded Relay Coil.Coil Replaced (← links)
- 05000324/LER-1993-012-02, :on 931204,discovered Temperature Switch Inoperable for PCIS MSL High Temperature Trip Due to Personnel Error.Operators Counseled & PT 2.1.22A/B Will Be Revised (← links)
- 05000324/LER-1982-087-03, /03L-0:on 820715,during Routine Plant Equipment Surveillance,Fuel Oil Inventory in Diesel Generator 4 Discovered Less than Required.Caused by Bent Guide Assembly Preventing Free Float Movement.Guide Tube Replaced (← links)
- 05000324/LER-1981-012-03, /03L-0:on 810320,wiring Deficiency Associated W/ Actuation Switch Discovered That Prevented Switch Operation. Caused by Improper Writing of Field Revision to Plant Mods Requiring Installation of Switches (← links)
- 05000324/LER-1993-011-02, :on 931122,emergency Bus Feeder Breaker Trip Resulted in Containment Isolation Signals.Cause Unknown.No Corrective Actions Necessary (← links)
- 05000324/LER-1980-119-03, /03L-0:on 801225,primary Containment Atmospheric Monitor 2-CAC-AT-1263 Hydrogen Analyzer Transmitter Had No Output Signal.Caused by Dirty Contacts on Monitor Local/ Remote Switch.Contacts Cleaned & Monitor Recalibr (← links)
- 05000324/LER-1980-093-03, /03L-0:on 801102,control Rod 30-11 Discovered Not to Have full-in Indication When Fully Inserted.Caused by Failure of Reed Switch in Rod Position Indicator Probe. Problem to Be Corrected During Next Outage (← links)
- 05000324/LER-1979-028-03, /03L-0 on 790510:south Torus Hatch Was Open During Reactor Startup for Physics Testing Following Refueling Outage.Caused by Operating Procedure Deficiency.Procedures to Be Revised to Require Visual Insp (← links)
- 05000324/LER-1978-075-03, /03L-0 on 781122:HPCI & RCIC Component Tests Were Overlooked Because Rescheduling Technique Provided No Clear Indication of Test Due Dates.Responsible Technician Reinstructed & Admin Operating Instruction AOI-5 Rev (← links)
- 05000324/LER-1978-075, Forwards LER 78-075/03L-0 (← links)
- 05000324/LER-1978-074-03, /03L-0 on 781112:reactor Steam Dome High Pressure Switch B32-PS-N018B Did Not Reset & Would Not Allow RHR Valve E11-F008 to Open for Shutdown Cooling at Reactor Pressure of 102psig.Caused by Sticking micro-switch (← links)
- 05000324/LER-1978-074, Forwards LER 78-074/03l-0 (← links)
- 05000324/LER-1978-082-03, /03L-0 on 781117:while Reactor Was in Hot Shutdown Torus Level Increased .2 Above Tech Specs.Caused by Demineralized make-up Water Leakage Through Valves from RHR Keep-fill System Causing Torus Level to Rise (← links)
- 05000324/LER-1978-082, Forwards LER 78-082/03L-0 (← links)
- 05000324/LER-1982-090-03, /03L-0:on 820704,trip Logic Associated W/Rod Groups 1 & 4 Automatically Reset.Caused by Loose Operator Set Screw in Reactor Scram Reset Switch.Switch Adjusted & Returned to Svc.After Similar 820723 Event,Switch Replaced (← links)
- 05000324/LER-1978-072-03, /03L-0 on 781101:rod Block Monitor(Rbm) Channel a Was Found Out of Calibr During Testing Due to Setpoint Drift.Calibr Frequency Will Be Increased from Once to Twice Per Year (← links)
- 05000324/LER-1978-072, Forwards LER 78-072/03L-0 (← links)
- 05000324/LER-1990-012, :on 900830,reactor Scram Occurred (← links)
- 05000324/LER-1978-070-03, /03L-0:on 780923,reactor Coolant Conductivity Exceeded Tech Spec Requirements.Caused by Restarting RWCU Filter Pump After Pump Tripped,Resulting in Resin Injected Into Reactor Coolant.Rwcu Procedure Will Be Revised (← links)
- 05000324/LER-1978-073-03, /03L-0:on 780927,condensate deep-bed Demineralizer Conductivity Recorder Found Inoperable During Shift Turnover Insp.Caused by Turning Off Transmitter Due to Mislabeling of on-off Switch Positions (← links)
- 05000324/LER-1978-071-03, /03L-0 on 780924:during RCIC Sys Component Test, Found Throttle Valve E51-v8 in Closed Position.Cause Known (← links)
- 05000324/LER-1978-069-03, /03L-0:on 780912,fire Alarms Received But Would Not Reset.Fire Detection Instrumentation Inoperable.Caused by Smoke & Dust Resulting from Welding & Operation of Jackhammer.Fire Detectors Cleaned & Repaired (← links)
- 05000324/LER-1978-068-03, /03L-0:on 780912,during LPCI Pump Discharge Pressure Interlock Channel Functional Test,Pressure Switches E11-PS-N016B & E11-PS-N020D Failed to Actuate at 115 Psig. Caused by Corrosion Buildup in Switch Plungers (← links)
- 05000324/LER-1978-059, Forwards LER 78-059/03L-0 (← links)
- 05000324/LER-1978-066-03, /03L-0 on 780904:rod Block Monitor B Inoperative Trip Came on & Stayed on for 1/4 of the Control Rod Selection Matrix.Caused by Failed Integrated Circuit in Rod Block Monitor self-test Circuitry (← links)
- 05000324/LER-1978-066, Forwards LER 78-066/03L-0 (← links)
- 05000324/LER-1990-013-02, :on 900906,HPCI Declared Inoperable Due to Erratic Performance During Periodic Testing.Caused by Deficient Needle Valve Position.Maint Will Revise Procedures to Enhance Controls for Egr Needle Valve Adjustments (← links)
- 05000324/LER-1993-009-03, :on 931016,ADS Relays Energized Due to Volt Ohm Meter Improperly Set During Performance of Maint Surveillance Test (← links)
- 05000324/LER-1990-010-02, :on 900822,reactor Protection Sys Bus a Deenergized During Cold Shutdown.Caused by Personnel Error. Operators Disciplined & Clearance Procedure Will Be Revised to Clarify Double/Independent Verification (← links)