Pages that link to "05000249/LER-2006-001, Regarding Unit 3 Main Steam Safety Valves Exceed Surveillance Setpoint"
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The following pages link to 05000249/LER-2006-001, Regarding Unit 3 Main Steam Safety Valves Exceed Surveillance Setpoint:
Displayed 8 items.
- 05000249/LER-2006-001 (redirect page) (← links)
- 05000249/LER-2004-006 (← links)
- 05000249/LER-2004-005 (← links)
- 05000249/LER-2004-003 (← links)
- 05000249/LER-2004-002 (← links)
- 05000249/LER-2001-003 (← links)
- 05000249/LER-2001-002 (← links)
- 05000249/LER-2001-001 (← links)
- 05000249/LER-1982-027, Forwards LER 82-027/01T-0 (← links)
- 05000249/LER-1982-011, Forwards LER 82-011/03X-1 (← links)
- 05000249/LER-1982-022, Forwards LER 82-022/03L-0 (← links)
- 05000249/LER-1982-036, Forwards LER 82-036/03L-0 (← links)
- 05000249/LER-1982-035, Forwards LER 82-035/03L-0 (← links)
- 05000249/LER-1981-026, Forwards LER 81-026/03L-0 (← links)
- 05000249/LER-1982-034, Forwards LER 82-034/03L-0 (← links)
- 05000249/LER-1982-018, Forwards LER 82-018/03X-1 (← links)
- 05000249/LER-1982-033, Forwards LER 82-033/03L-0 (← links)
- 05000249/LER-1982-024, Forwards LER 82-024/03L-0 (← links)
- 05000249/LER-1982-025, Forwards LER 82-025/03L-0 (← links)
- 05000249/LER-1982-030, Forwards LER 82-030/03L-0 (← links)
- 05000249/LER-1982-031, Forwards LER 82-031/03L-0 (← links)
- 05000249/LER-1982-032, Forwards LER 82-032/03L-0 (← links)
- 05000249/LER-1983-004, Forwards LER 83-004/03L-0 (← links)
- 05000249/LER-1983-005, Forwards LER 83-005/01T-0 (← links)
- 05000249/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000249/LER-1983-003, Forwards LER 83-003/03L-0 (← links)
- 05000249/LER-1982-046, Forwards LER 82-046/03L-0 (← links)
- 05000249/LER-1982-044, Forwards LER 82-044/03L-0 (← links)
- 05000249/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl (← links)
- 05000249/LER-1982-043, Forwards LER 82-043/03L-0 (← links)
- 05000249/LER-1982-041, Forwards LER 82-041/03L-0 (← links)
- 05000249/LER-1982-039, Forwards LER 82-039/03L-0 (← links)
- 05000249/LER-1982-047, Forwards LER 82-047/03L-0 (← links)
- 05000249/LER-1983-015, Forwards LER 83-015/03L-0 (← links)
- 05000249/LER-1983-014, Forwards LER 83-014/03L-0 (← links)
- 05000249/LER-1983-010, Forwards LER 83-010/03L-0 (← links)
- 05000249/LER-1983-011, Forwards LER 83-011/01T-0 (← links)
- 05000249/LER-1983-008, Forwards LER 83-008/01T-0 (← links)
- 05000249/LER-1982-048, Forwards LER 82-048/03L-0 (← links)
- 05000249/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000249/LER-1982-008, Forwards Updated LER 82-008/03X-1 (← links)
- 05000249/LER-1983-013, Forwards LER 83-013/03L-0 (← links)
- 05000249/LER-1982-012, Forwards Updated LER 82-012/03X-1 (← links)
- 05000249/LER-1982-014, Forwards Updated LER 82-014/03X-1 (← links)
- 05000249/LER-1981-017, Forwards Updated LER 81-017/03X-1 (← links)
- 05000249/LER-1982-026, Forwards LER 82-026/03L-0 (← links)
- 05000249/LER-2021-001-01, Reactor Scram Due to Main Power Transformer Failure (← links)
- 05000249/LER-1984-019-02, :on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design (← links)
- 05000249/LER-1986-016-07, :on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure When Setscrews Holding Pinion Gear Vibrated Loose.Setscrew Tightened (← links)
- 05000249/LER-1986-015-07, :on 860924,determined That Quarterly Storage Battery Surveillance Not Performed During Required Interval. Caused by Personnel Error.Procedures Revised.Personnel Counseled (← links)
- 05000249/LER-1986-021-06, :on 861110,w/unit in Run Mode,Reactor Scram Occurred Due to Loss of Control Air to Msivs.Caused by Mechanic Inadvertently Removing Power Lead.Mechanic Reprimanded & Tailgate Conducted (← links)
- 05000249/LER-1986-014-07, :on 860826,during Operating Surveillance 2300-6, Monthly HPCI Sys Pump Test for Inservice Test Program, HPCI Gland Seal Leak Off Drain Failed to Adequately Drain HPCI Condenser Hotwell (← links)
- 05000249/LER-1986-013-07, :on 860827,unit Shutdown Due to Exceeding Limiting Conditions for Operations for Eccs.Caused by Failure of Valve 3-1402-4B.Valve Repaired.All ECCS Valve Operability Surveillances Will Be Performed (← links)
- 05000249/LER-1986-012-02, :on 860902,reactor Manually Scrammed Due to Excessive Number of Accumulator Alarms Received Due to CRD Pump Trip.Caused by Failed Charging Water Isolation Valve 3-305-113.Valve Repaired & Scram Testing Procedure Revised (← links)
- 05000249/LER-1986-012-01, Forwards Supplemental LER 86-012-01,correcting Error in Rept Re Procedure Number & Title Used for Surveillance (← links)
- 05000249/LER-1986-002-01, :on 860117,loss of Power to Radiation Monitors Occurred,Initiating Standby Gas Treatment Sys & Tripping Reactor Bldg Ventilation Sys.Caused by Procedural Inadequacy.Procedures Will Be Changed (← links)
- 05000249/LER-1986-017-07, :on 861014,Group I Isolated & Subsequent Reactor Scram Occurred.Caused When Contractor Inadvertently Jarred Msivs.Personnel Counseled (← links)
- 05000249/LER-1986-018-06, :on 861014,Group V (Isolation Condenser) Containment Isolation Signal Received.Corrective Actions Will Be Considered When Cause Determined (← links)
- 05000249/LER-1986-016, :on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure.Operability Restored. Valve Motors & Setscrews Inspected.Gears Safety Wired (← links)
- 05000249/LER-1986-016-01, Forwards Suppl to LER 86-016-01.Component Failure Info Provided & Typo Corrected (← links)
- 05000249/LER-1987-001-09, :on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established (← links)
- 05000249/LER-1986-024-05, :on 861205,unit Shutdown Commenced Due to Qualification Deficiency of Environmentally Qualified Cable Splices in Drywell Penetrations.Caused by Excessive Leakage Current.Qualified Tape Used to Repair Splices (← links)
- 05000249/LER-1986-009-07, :on 860708,diesel Generator 2/3 Automatically Started Following Inadvertent Initiation of Autostart Relay Circuitry.Caused by Personnel Error.Operating Foreman Counseled (← links)
- 05000249/LER-1986-023-05, :on 861201,Tech Spec Requirements for Reactor Coolant Sample Radioactivity Analysis Exceeded.Sample Not Analyzed Due to Miscommunication Between Radiation Chemistry Technician & Spectrometry Room Personnel (← links)
- 05000249/LER-1986-019-06, :on 861113,scram Occurred Due to Two Simultaneous,Unrelated half-scrams.First half-scram Caused by Personnel Error.Second half-scram Caused by Dirty Connection in Circuit.Connection Cleaned (← links)
- 05000249/LER-1986-020-05, :on 861113,isolation Condenser Containment Isolation Signal Received in Control Room.Cause Undetermined.Engineering Contacted,Test Instrumentation Installed & Analysis in Progress (← links)
- 05000249/LER-1986-005-09, :on 860519,emergency Diesel Generator Automatically Started & Closed 4-kV Bus 34-1 Due to Undervoltage Condition on Bus.Caused by Personnel Error. Individual Counseled (← links)
- 05000249/LER-1986-010-05, :on 860422,cribhouse Deluge Sys 2/3 Taken Out of Svc to Complete Portion of App R Mod Work.Testing Completed on 860503.Sys Placed in Svc on 860507 After Readjustment of Deluge Valve (← links)
- 05000249/LER-1986-026-03, :on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development (← links)
- 05000249/LER-1986-012-07, :on 860902,reactor Manually Scrammed Due to Large Number of Accumulator Alarms.Caused by Trip of CRD Pump 3B on Low Suction Pressure.Backup Pump Out of Svc for Repair.Procedure Dts 300-1 Changed (← links)
- 05000249/LER-1986-011-07, :on 860817,fuse Blew During Voltage Reading of Open Position Indicating Limit Switch for Air Operated Valve Tripping Reactor Bldg Ventilation,Drywell Purge Fans & Sump Pumps.Caused by Personnel Error (← links)
- 05000249/LER-1986-022-06, :on 861222,one of Two Fuel Pool Floor Radiation Monitors on Side of Refuel Floor of Reactor Bldg Spuriously Spiked Causing Automatic Start of Standby Gas Treatment Sys. Caused by Failed Radiation Monitor (← links)
- 05000249/LER-1986-025-05, :on 861211,reactor Scram Occurred During Cycle of Main Stop Valve (EIIS Code Ts).Caused by Closure of Three Main Stop Valves.Switch Replaced & Test Circuitry Operated as Required (← links)
- 05000249/LER-1986-008-08, :on 860618,Group II Primary Containment Isolation Received,Causing Isolation of Reactor Bldg Ventilation & Start of Standby Gas Treatment Sys.Caused by Personnel Error.Personnel Cautioned Re Maint (← links)
- 05000249/LER-1986-006-08, :on 860529,Group II & III Primary Containment Isolation Occurred While Work Performed on Analog Trip Sys. Caused by Personnel Inadvertently Grounding Live Wire. Personnel Reminded to Pay Attention to Details (← links)
- 05000249/LER-1987-003-06, :on 870227,shutdown Cooling HX Outlet Temp Found Greater than 212 F.Caused by Operator Failure to Adequately Monitor Reactor Water Temp on Proper Instrumentation.Water Temp Reduced (← links)
- 05000249/LER-1987-002-09, :on 870225,while Unit Operating at 87% Power, HPCI Sys Discovered Inoperable.Caused by Oil Pressure Regulation Valve Failure.Similar Event Occurred on 870313. Limits of PS4 Reset to 60 Psig Increasing (← links)
- 05000249/LER-1983-013-03, /03L-0:on 830322,while Performing Main Steam Line High Flow Surveillance,Switch 3-261-21 Tripped Beyond Tech Spec Limit.Caused by Particle on Switch Gear Movement.Switch Cleaned & Retested (← links)
- 05000249/LER-1986-003-08, :on 860403,power Lost to 4 Kv Emergency Bus 34-1 Resulting in Reactor Bldg Ventilation Sys Isolation. Caused by Personnel Leaving Relay Trip Check Open.Event Reviewed W/Responsible Individual (← links)
- 05000249/LER-1986-010-08, :on 860713,auto Blowdown Sys I Tripped During Instrument Surveillance Logic Test.Caused by Instrument Setpoint Drift.Relays Recalibr (← links)
- 05000249/LER-1986-007-08, :on 860612,standby Gas Treatment Sys Started Automatically & Reactor Bldg Ventilation Sys Isolated.Caused by Personnel Error Resulting in Use of Incorrect Procedures. Personnel Counseled (← links)
- 05000249/LER-1986-004-07, :on 860501,weekly Continuous Particulate Filter Sample from Ventilation Sampling Sys Found Broken.Possibly Caused by Personnel Error.Technicians Will Be Retrained Re Filter Handling & Gas Sampling (← links)
- 05000249/LER-1986-001-04, :on 860108,reactor Bldg Fuel Pool High Radiation Trip Signal Initiated Reactor Bldg Ventilation & Standby Gas Treatment Sys Autostart During Radiography on 613-ft Elevation.Caused by Personnel Error (← links)
- 05000249/LER-1985-025-06, :on 851231,Group II Primary Containment Isolation Occurred Due to Low Reactor Water Level Signal. Caused by Vibrated Level Indicator.No Corrective Action Necessary Due to Sensitivity of Instruments (← links)
- 05000249/LER-1978-033-03, /03L on 780821:during Survey,Dis 250-1,MSL Hi Flow Isolation Switch Psid 3-261-2C Tripped at 135.5 Psid.Caused by Bent Indicator Pointer Dragging Across Face Plate Prohibiting Proper Oper.(Encl to 7809220139) (← links)
- 05000249/LER-1978-035-03, /03L-0 on 780908:steam Leaking from Ventrom Vent Line.Caused by Cracked Weld.Repaired by Welding Externally. (Encl to 7809220138) (← links)
- 05000249/LER-1978-035, Forwards LER 78-035/03L-0 (← links)
- 05000249/LER-1978-032-03, /03L on 780817:room Cooler Fans Failed to Start When Pumps 3B & 3C started.4KV Switchgear 33 & 34 Auxiliary Contacts Were Found Dirty.(Encl to 7809220129) (← links)
- 05000249/LER-1978-032, Forwards LER 78-032/03L (← links)
- 05000249/LER-1978-009-01, /01X-1 on 780320:Cracks Found on end-to-pipe Weld on CRD Return Line.Caused by Intermittent to Low Cooling Water Flow Leaving the CRD Nozzle.Pipe Was Removed & Replaced. (Encl to 7809180035) (← links)
- 05000249/LER-1985-026-05, :on 850924,reactor Bldg Ventilation Sys Tripped & Isolated,Causing Initiation of Standby Gas Treatment Sys. Caused by Fuel Handlers Moving Discharged Local Power Range Monitor.Fuel Handling Dept Foreman Cautioned (← links)
- 05000249/LER-1985-024-06, :on 851120,reactor Scram Occurred Due to Loss of Power to Reactor Protection Sys Buses,Resulting in Ventilation Trip.Caused by Miscommunication Between Operation Foreman & Shifting Engineer (← links)
- 05000249/LER-1985-020-05, :on 850925,no Particulate Sample for Reactor Bldg Ventilation Sys Collected for Wk.Caused by Failure to Replace Screen in Filter Holder After Last Sample.Signs to Be Posted in Future (← links)
- 05000249/LER-1985-019-07, :on 850923,observed That Reactor Not Vented at Less than 149 F.Caused by Failure of Shutdown Procedure to Completely Outline Conditions to Vent Reactor.Reactor Head Vents Opened (← links)
- 05000249/LER-1985-022-07, :on 851115,spurious lo-lo Water Level Signal & Group I-III Isolations Occurred.Caused by Diver Mistakenly Hydrolazing Instrumentation Nozzle N-16B Rather than CRD Return Nozzle N-9.Proper Nozzle Hydrolazed (← links)
- 05000249/LER-1985-021-07, :on 851107,leakage in Nitrogen Makeup Isolation Valves Exceeded Tech Spec Limit for Type B & C Leak Testing. Caused by Dislodged Teflon Tape.Mechanics Informed Not to Use Teflon Tape as Sealant (← links)
- 05000249/LER-1985-023-05, :on 851017,reactor Tripped on Reactor Vessel Low Water Level Scram.Caused by Reactor Operator Error. Procedure Describing Operation & Balance of Feedwater Controllers Written (← links)
- 05000249/LER-1985-015-07, :on 850820,during Functional Test,Reactor Bldg Vent Sys Inadvertently Tripped & Isolated.Caused by Procedural Violation Due to Instrument Mechanic Error. Tailgate Presented.Mechanic Counseled (← links)
- 05000249/LER-1984-002-10, :on 840326,intermediate Range Monitors 14 & 16 Spiked hi-hi,causing Full Reactor Scram.Caused by Electronic Noise,Inducing Spurious Signals in Circuitry.Scram Signals Reset (← links)
- 05000249/LER-1985-005, :on 850216-17,caution Cards Inadvertently Hung on Unit 3 Diesel Generator Knife Switches Rather than Unit 2 Switches & Corresponding Unit 3 Switches Opened.Caused by Communications & Operator Error (← links)
- 05000249/LER-1984-005-03, :on 840716,during Unit Shutdown for Turbine Repair,Lpci Submarine Door Found Open.Caused by Personnel Error.Doors Secured W/Locking Bar to Prevent Handle Operation (← links)
- 05000249/LER-1985-017-06, :on 850905,fuel Pool Channel B High Radiation Trip Occurred,Causing Ventilation Sys Trip & Starting Gas Treatment Sys.Caused by Chips in water-filled Bucket Used for Cleanup.Bucket Immersed in Fuel Pool (← links)
- 05000249/LER-1985-016-07, :on 850826,equipment Attendant Observed HPCI Room Cooler Fan Breaker Emitting Smoke.Caused by Shorted Motor Contactor Coil.Coil & Auxiliary Contacts Replaced & Maint Procedure DMP 7300-5 Performed (← links)
- 05000249/LER-1985-010-01, :on 850427,full Reactor Scram Initiated from Low Water Level.Probably Caused by Vibration Near Sensor Rack Due to Improper Filling & Venting of Shutdown Cooling Sys.Equipment Attendants Retrained (← links)
- 05000249/LER-1985-011, :on 850416,high Radiation Signal from Refueling Floor Radiation Monitors Caused Reactor Bldg Ventilation Sys Trip & Isolation W/Standby Gas Treatment Sys B Automatically Starting (← links)
- 05000249/LER-1985-012-05, :on 850429,feedwater Check Valve 3-220-62A Observed to Leak 587.04 Scfh.W/Previous as Left Leakage, Total Leakage Exceeds Tech Spec Limit.Caused by Worn Pressure Seal Ring.Seal Ring Replaced (← links)
- 05000249/LER-1985-010-07, :on 850427,full Reactor Scram Initiated from Low Water Level W/Subsequent Group II & III Isolation.Cause Undetermined.Level Sensors 263-58 a & B to Be Replaced W/Analog Trip Units (← links)
- 05000249/LER-1984-007-02, :on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation.Caused by Failure of Servovalve Mechanism.Servovalve Replaced (← links)
- 05000249/LER-1985-014-07, :on 850520,delay Experienced in Returning Wet Pipe Sprinkler Sys to Svc Following Mod Initiated to Reroute Wet Pipe Sprinkler Sys Piping & Supply Header.Caused by Testing Delays (← links)
- 05000249/LER-1985-013-06, :on 850516,discovered That Both Channels of ARM 3-1705-16 Set to Trip at 120 Mr/H in Excess of Tech Spec Limit of 100 Mr/H.Caused by Personnel Error.Individual Instructed Re Usage of Dip 2100-9 (← links)
- 05000249/LER-1985-011-05, :on 850416,reactor Bldg Vent Trip & Isolation Occurred W/Standby Gas Treatment Sys B Automatically Started.Caused by Fuel Handlers Removing Machinery from Fuel Pool.Machinery Washed to Reduce Dose Levels (← links)
- 05000249/LER-1985-006, :on 850222,svc Water Leading to HPCI Room Cooler Discovered Valved Out,Causing Svc Water & HPCI Sys to Be Inoperable.Caused by Personnel Error.Valves Immediately Opened & Sys Restored (← links)
- 05000249/LER-1985-008-04, :on 850311,diesel Generator 2/3 Automatically Started W/No Actuation Signal Present.Caused by Vibration to Auto Start Relay During Mod.Following Auto Start,Engine Loaded & Operated for 88 Minutes (← links)
- 05000249/LER-1984-023-06, :on 841224,during HPCI Sys Pump Test,Main Pump Bearing Velocity Greater than Procedural Limit.Procedural Limit Found to Be Too Conservative.Inservice Testing Frequency Increased to Monthly (← links)
- 05000249/LER-1985-009-03, :on 850205,manual Isolation Valve 3-1699-15 to Torus Sight Glass Discovered Locked in Open Position.Caused by Personnel Error.Dos 1600-2 Changed to Include Second Signature Verifying Locked Closed Position (← links)
- 05000249/LER-1984-016-05, :on 841014,while Performing DOP 4400-8 Re Circulating Water Flow Reversal,Reactor Scrammed Due to Low Condenser Vacuum.Vacuum Breaker Opened to Prevent Turbine Damage (← links)
- 05000249/LER-1984-017-06, :on 841014,scram Discharge Vol High Level Bypass Circuit Accidentally Broken,Resulting in Full Reactor Scram.Jumpers Placed on Terminals DD8-DD11 Lost Contact as Removed & Scram Occurred (← links)
- 05000249/LER-1985-001-04, :on 850112,during Turbine Checks Surveillance, Reactor Scrammed from Turbine Trip.Caused by Oil Trip Solenoid Valve Malfunction.Solenoid Valve Replaced.Group I Isolation Caused by Switch Vibration (← links)
- 05000249/LER-1984-012, :on 840823,unit Scrammed Due to Operator Failure to Insert Intermediate Range Monitors Prior to APRMs Going Downscale.Caused by Operator Lack of Experience.Shift Mgt Reminded to Review Procedures (← links)
- 05000249/LER-1984-016, :on 841014,reactor Scram Occurred Due to Low Condenser Vacuum.Caused by Valve 3-4402-A Not Opening Completely.Stem for Valve Lubricated & Valve Cycled Six Times (← links)
- 05000249/LER-1984-022-04, :on 840317,reactor Scrammed While Adjusting Mode Switch in Attempt to Clear Rod Block.Caused by Operator Error When Mode Switch Inadvertently Moved to Shutdown Position.Operator Counseled (← links)
- 05000249/LER-1984-021-04, :on 840307,reactor Scrammed During Surveillance Testing.Caused by Bad Jumper Wire.Jumper Discarded & Personnel Reinstructed on Using Jumper Wire Const for Surveillance Test (← links)
- 05000249/LER-1984-018-03, :on 841020,reactor Scram Occurred Due to Low Feedwater Level.Caused by Bad Switch in Master Controller & Broken Valve.New stem-disc Assembly Installed (← links)
- 05000249/LER-1985-007-05, :on 850302,during Normal Operation,Two Normally Closed Torus Water Sample Valves Discovered Open W/Water Draining to Sump.Caused by Personnel Error.Valves Locked. Procedures Revised (← links)
- 05000249/LER-1985-006-05, :on 850222,HPCI Sys Inoperable Due to Valved Out Svc Water.Caused by Personnel Error.Valves Opened & Sys Operability Restored.All Svc Water Supply Valves to HPCI Locked Open to Prevent Recurrence (← links)
- 05000249/LER-1985-004-06, :on 850215,level Indicating Switch 3-263-58B Found to Trip at 116.5 Inches Water & Switch 3-263-57B Found to Trip at 127 Inches Water (Differential Pressure).Caused by Setpoint Drift.Switches Adjusted & Recalibr (← links)
- 05000249/LER-1985-005-05, :on 850216,undervoltage Protection on Bus 34-1 Lost.Caused by A-man Hanging Caution Cards on Wrong Knife Switches.Event Reviewed W/Operating Personnel.New Procedures for ECCS Undervoltage Test Created (← links)
- 05000249/LER-1984-020-05, :on 841026,MSIV Not Fully Opened Caused Reactor Scram Due to Group 1 Isolation.Caused by Bypass Valves Opening at Once Due to Faulty Voltage Comparator & Reactor Pressure Below Tech Spec Limits (← links)
- 05000249/LER-1985-003-07, :on 850206,HPCI Room Cooler Fan Belts Fell Off, Rendering Sys Inoperable.Cause Not Stated.Belts Replaced & Cooler Fans Ran Properly (← links)
- 05000249/LER-1984-018-05, :on 841020,reactor Scrammed on Low Water Level W/Feedwater Regulating Valve 3A in Auto.Caused by Bad Switch in Reset Circuitry of Controller.Master Controller Replaced (← links)
- 05000249/LER-1984-019-04, :on 841024,addl 49.3 Std Cubic Ft Per Hour Should Have Been Added to as Found Leakage Rate.Caused by Improper Calibr of Two Floor make-up Boxes.Flowmeter Calibr Pressure & Temp Verified (← links)
- 05000249/LER-1985-002-05, :on 850201,reactor Scrammed on Low Water Level W/O Cause.Caused by Vibration from Inservice Insp Std Which Inadvertently Hit Floor Near Instrument Rack 2203-6.Low Water Level Switches Replaced (← links)
- 05000249/LER-1984-011-05, :on 840822,during Rod Worth Minimizer Prestartup Surveillance,Reactor Scrammed Due to Series of Events.Caused by Lack of Operator Caution While Verifying Mode Switch Position (← links)
- 05000249/LER-1984-010-06, :on 840821,feedwater Regulating Valve a Operator Vibrated Loose from Valve Steam Coupling,Causing Valve Disc to Fail in Closed Direction,Resulting in Reactor Scram Operator & Valve Stem Reconnected (← links)
- 05000249/LER-1984-012-05, :on 840823,unit Scrammed on Intermediate Range Monitor (IRM) hi-hi W/Companion APRM Downscale When IRMs Inserted.Caused by Personnel Error.Causes & Corrective Actions Investigated (← links)
- 05000249/LER-1984-009-07, :on 840808,operator Received Alarm Indicating High O2 Concentration in Torus.Caused by Failure of Torus to Reactor Bldg Vacuum Breaker 3-1601-20B Due to Shearing of Flathead Mounting Bolts (← links)
- 05000249/LER-1983-035-03, /03X-1:on 831004,during Drywell Insp,Water Observed Leaking from Recirculation Pump Bowl Drain A. Probably Caused by Socket Weld Joint Bottoming Out.Affected Piping Replaced During Outage (← links)
- 05000249/LER-1984-008-06, :on 840804,while Opening Valve 1601-58,drywell to Torus Differential Pressure Fell Below Tech Spec Level. Caused by Closed Pressure Control Valve 8599-538.Personnel Counseled (← links)
- 05000249/LER-1984-007-07, :on 840722,turbine Bypass Valve 1 Operated Erratically,Causing Group 1 Isolation on Main Steam Low Pressure.Caused by Failure of Servovalve (Model 450-1880) Mechanism for Opening & Closing Valve (← links)
- 05000249/LER-1984-005-07, :on 840716,east LPCI Corner Room Submarine Door Found Open.Caused by Stationmen Working in Area.Door Closed & Tech Specs Requiring Door to Be Closed Emphasized. Annunciators Will Be Installed (← links)
- 05000249/LER-1984-001, :on 840323,reactor Water Level Decreased to Low Level Alarm Point.Coolant Loss Compounded by Two Open Bypass Valves.Procedures Revised to Remind Operators to Close Turbine Valves (← links)
- 05000249/LER-1984-006-06, :on 840711,reactor Vessel Found Not Vented at Less than 149 F.Caused by Inadvertent Procedure Violation. Reactor Metal Temp Increased.Personnel Reminded of Venting Requirement (← links)
- 05000249/LER-1984-015-06, :on 840925,during Planned Unit Shutdown,Reactor Scrammed on Low Condenser Vacuum Caused by Air in-leakage Through Damaged Bellows on Seal Steam Relief Valve Discharge Line.Bellows Replaced (← links)
- 05000249/LER-1983-029-03, /03X-1:on 830726,Reactor Water Level Surveillance Dis 1500-3 & Reactor Water Level Sensor Lits 3-263-73 a Required Initial Dp Loading of 260 Inches of Water to Move Indicator.Caused by Worn Diaphragm Switch (← links)
- 05000249/LER-1984-014-05, :on 840904,ECCS Surveillances Not Completed Prior to Rendering Loop a Inoperable.Caused by Personnel Error While Taking LPCI Component Cooling Svc Water HX Delta P Valve Out of Svc (← links)
- 05000249/LER-1984-013-05, :on 840830,reactor Operation Continued While Primary Containment Purge Sys Butterfly Valve 3-1601-63 Out of Svc for Air Leak Repair.Caused by Personnel Error. Outage Cleared & Valve Cycled (← links)
- 05000249/LER-1984-004-07, :on 840425,reactor Scram Occurred on Protection Sys Channel A.Caused by Misaligned Styrofoam Block Allowing Contact Separation in Relay 590-112B.Relay Contacts Will Be Jumped (← links)
- 05000249/LER-1983-035-01, /01T-0:on 831004,during Drywell Insp,Water Observed Leaking from Recirculation Pump Bowl Drain A. Caused by 2-inch Crack on Tee.Affected Piping Will Be Cut Out.Isolation Valves & Tee Will Be Replaced (← links)
- 05000249/LER-1976-030, :on 761026,during Refueling Outage Local Leak Rate Testing Tip Purge Check Valve Exhibited Leakage Rate Above Tech Spec Limit.Caused by Dirt on Ball or Seating Area of Valve.Valve Cleaned (← links)
- 05000249/LER-1975-024, AO 50-249/75-24:on 750426,during Routine Calibr of HPCI Area Temp Sensors,Setpoints on 12 of 16 Temp Sensors Found Above Tech Spec Limit.Caused by Unsuitable Existing Temp Sensors for First Operation Surveillance Type Operation (← links)
- 05000249/LER-1975-025, :on 750428,during Routine Insp,Two Hydraulic Piping Restraints Inoperable.Cause Unknown.Inoperable Snubbers Will Be Replaced Before End of Outage (← links)
- 05000249/LER-1976-001-01, During Weekly Turbine Surveillance Testing,Closure of Control Valve 2 Failed to Initiate Reactor Half Scram.Caused by Malfunctioning Solenoid Valve.Solenoid Replaced (← links)
- 05000249/LER-1975-026, AO 50-249/75-26:on 780509,during Discharge test,24/48 Volt Dc Batteries Failed to Deliver Rated ampere-hour Capacity. Caused by Six Bad Cells in One Battery & Four Bad Cells in Other.Deteriorated Cells Will Be Replaced (← links)
- 05000249/LER-1975-027, :on 750515,cracks Observed on Five of Eight Header Pipe & One of Four Thermal Sleeve to Junction Box Welds.Caused by Design of Spargers Susceptible to Flow Induced Vibration.Spargers Will Be Replaced (← links)
- 05000249/LER-1976-006, :on 760324,drain Valve 2-4999-74 Found Blocked Open Mechanically & Electrically Inoperable.Caused by Valves Not Functionally Tested After Mods (← links)
- 05000249/LER-1976-007, :on 760428,following Removal of Rechar Sys from Svc,Explosion Occurred in 3B Offgas Sys.Cause Unknown. Investigation Initiated (← links)
- 05000249/LER-1975-028, AO 50-249/75-28:on 750522,main Steam Line Area Temp Sensors 261-16B,261-17 A-D & 261-18D Found W/Setpoints Above Tech Spec Limit.Caused by Misapplied Switches.Switches Reset within Tech Spec Limit (← links)
- 05000249/LER-1976-008, :on 760430,during Surveillance Testing,Component Cooling Svc Water Pump Vault Penetrations Found to Leak When Pressurized.Caused by Improper Application of Silicone Sealant (← links)
- 05000249/LER-1976-010, :on 760618,during Routine Insp,Reactor Water Found Leaking from Cleanup non-regenerative HX 3B-1204B. Caused by Lack of Fusion in Weld,Grinding,Rewelding & Testing.Cracks Ground Out (← links)
- 05000249/LER-1976-011, :on 760622,during Routine Instrument Surveillance Testing,Sustained High Reactor Pressure Switch 3-263-53A Found to Actuate Above Tech Spec Limit.Caused by Setpoint Drift.Switch Will Be Checked monthly.W/760720 (← links)
- 05000249/LER-1976-012, :on 760503,during Quarterly MSIV Timing Surveillance Testing,Msiv 3-203-1A Closed Above Tech Spec Limit.Caused by Dried Valve Packing.Valve Timing Adjusted (← links)
- 05000249/LER-1976-013, :on 760713,during steady-state Unit Operation, Circuit Breaker for Diesel Generator Cooling Water Pump Found in Tripped Position.Caused by Worn Pump Bearings. Mod Initiated (← links)
- 05000249/LER-1976-014, :on 760902,during Startup Operations,Control Room Indication Showed MSIV 3-203-2B Failed to Fully Close.Caused by Slippage of Actuator Arm of position-indicating Limit Switch on Shaft (← links)
- 05000249/LER-1976-015, :on 760912,during Routine Plant Insp,Steam Leak Found in Elbow on Moisture Separator Drain Tank Line B to D Feedwater Heaters.Caused by Failure of Support Bolt Due to Surge in Process Stream.Crack Ground & Welded (← links)
- 05000249/LER-1976-016, :on 760918,during Local Leak Rate Testing of Drywell & Torus Vent Isolation Valves,Valve 3-1601-23 Exhibited Leak Rate Above Tech Spec Limit.Caused by Packing Failures.Packing Bolts Tightened (← links)
- 05000249/LER-1976-017, :on 760918,during de-inerting of Drywell,Oxygen Concentration Exceeded 4%.Facility Not Shut Down within 24 H Period in Order to Satisfy Min Sys Load Requirements (← links)
- 05000249/LER-1976-018, :on 760921,during Refueling Outage Local Leak Rate Testing,Feedwater Check Valves 3-220-58A & 62A Exhibited Leak Rates Above Tech Spec Limit.Caused by Dirt in Seating Area & Worn Disc Assembly Pins (← links)
- 05000249/LER-1976-019, :on 760921,diesel Generator Not Shutdown Following Return to Svc of Bus 34-1 & Engine High Temp Alarm Received. Caused by Partially Clogged Strainer in Lube Oil Circulating Pump.Strainer Cleaned (← links)
- 05000249/LER-1976-020-01, Vol Bounded by Steam Line Drain Valves 3-220-1 & 2 Exhibited Leakage Above Tech Spec Limits.Caused by Deteriorated body-to-bonnet Pressure Seal Ring & Dirt in Seating Area (← links)
- 05000249/LER-1976-020, :on 760922,during Refueling Outage Local Leak Rate Testing,Vol Bounded by Main Steam Line Drain Valves 3-220-1 & 2 Exhibited Leak Above Tech Specs Limit.Probably Caused by Deteriorated Pressure Seal Ring (← links)
- 05000249/LER-1976-021, :on 760924,during Routine Insp of Drywell Snubbers,Snubbers 24 & 30 Appeared to Be Inoperable Due to Loss of Fluid.Caused by Leakage Through Grease Fittings. Grease Fittings Replaced (← links)
- 05000249/LER-1976-022, :on 760929,during Prerequisite Testing for Refueling Outage LPCI Logic Surveillance,Dpis 261-34A Failed to Trip.Caused by Roller Cam Being Jammed by Microswitch Actuating Arm.Switch Repaired (← links)
- 05000249/LER-1976-023, :on 761007,during Refueling Outage Local Leak Rate Testing,Lpci Primary Isolation Check Valve 3-1501-25B Exhibited Leak Rate Above Tech Spec Limit.Caused by Dirt & Scratches on Valve Seat.Valve Cleaned (← links)
- 05000249/LER-1976-024-01, :on 761009,following Refueling Outage Surveillance Test of Diesel Generator,Engine Speed Could Not Be Regulated from Control Room.Caused by Loose Wire on Diesel Governor Control Circuit.Wire Tightened (← links)
- 05000249/LER-1976-024, Following Refueling Outage Surveillance Testing of Diesel Generator,Engine Speed Could Not Be Adjusted from Control Room.Caused by Loose Wire on Diesel Governor Control Circuit (← links)
- 05000249/LER-1976-025, :on 761007,during Refueling Outage Local Leak Rate Testing,Feedwater Check Valves 3-820-58B & 62B Exhibited Leakage Rates Above Tech Spec Limit.Caused by Dirt in Seating Area.Valve Cleaned & Retested (← links)
- 05000249/LER-1976-026, :on 761012,during Valve Operability Testing of Drywell Spray Sys,Motor Operated Valve 3-1501-27A Failed to Open.Caused by Loose Terminal in Valve Control Circuitry. Terminals Tightened (← links)
- 05000249/LER-1976-027, :on 761009,during Routine Surveillance Testing,Six Component Cooling Svc Water Pump Vault Penetrations Exhibited Detectable Leakage When Pressurized.Caused by Operational Vibration.Penetrations Resealed (← links)
- 05000249/LER-1976-028, :on 761018,after Preliminary Testing & Subsequent Insp by vendor,250 Volt Battery Found in Degraded Condition. Caused by Prior Battery Charger Problems.Battery Replaced W/Larger Capacity Unit (← links)
- 05000249/LER-1976-029, :on 761028,during Refueling Outage Surveillance Testing,Control Rod Drive Return Line Primary Isolation Check Valve 3-0301-98 Exceeded Tech Spec Leak Rate Limit. Caused by Normal Wear of Seating Area (← links)
- 05000249/LER-1976-031, :on 761101,during Refueling Outage Local Leak Rate Testing,Isolation Check Valve 3-205-2-7 Exhibited Leak Rate Above Tech Spec Limit.Caused by Dirt in Seating Area & on Disc Pivot Pin (← links)
- 05000249/LER-1976-032, :on 761105,while Diesel Generator Being Operated to Perform 4 Kv Breaker Switching,Engine Speed Could Be Decreased But Not Increased.Caused by Mechanical Malfunction.Mod Request Submitted (← links)
- 05000249/LER-1976-033, :on 761108,during Routine Operator Insp,Threaded Connection Between Valve & Instrument Piping Found Leaking on Isolation Condenser Steam Line Flow Sensor.Caused by Cross Threading During Outage Maint (← links)
- 05000249/LER-1976-034, :on 761119,HPCI Logic Design Wiring Problem Was Identified as Result of HPCI Injection Valve 2301-8 Stem Failure.Valve Was Racked Out of Svc in Open Position.Mod Request Submitted (← links)
- 05000249/LER-1976-035, :on 761126,during Routine Monthly Surveillance Testing of torus-to-drywell Vacuum Breakers,One of Two Position Alarms Did Not Annunciate.Caused by Dirty Contacts in Relay 1601-DA.Contacts Cleaned (← links)
- 05000249/LER-1975-045, :on 751203,during Weekly Surveillance,Irm 12 Tripped Above Tech Spec Limit.Probably Caused by Instrument Setpoint Drift (← links)
- 05000249/LER-1975-046, :on 751207,during Reactor Shutdown for Maint, Snubber 25 Found Inoperable Due to Insufficient Amount of Hydraulic Fluid.Caused by Deteriorated Seals.Snubber Zirc Fitting Replaced (← links)
- 05000249/LER-1975-047, :on 751211,during Surveillance Testing,Unit 3 Diesel Generator Would Not Accept Load Above 100 Kw.Caused by Loose Locknut on Shutdown Solenoid.Locknut Tightened. Diesel 6 Month Insp Procedure Revised (← links)
- 05000249/LER-1975-048, :on 751222,during Instrument Surveillance,Hpci Flow Switch DPIS 3-2353 Tripped Above Tech Spec Limit.Caused by Misapplication of Switch.Program to Modify Instruments in Progress (← links)
- 05000249/LER-1975-049, :on 751223,during steady-state Operation,Channel a Refueling Floor Radiation Monitor Failed Downscale.Caused by Cable Connector Failure.Connector Replaced (← links)
- 05000249/LER-1976-001, :on 760104,during Weekly Surveillance Test,Closure of Control Valve 2 Failed to Initiate Reactor Half Scram. Caused by Malfunctioning Fast Acting Solenoid Valve.Work Request Issued to Replace & Test Solenoid (← links)
- 05000249/LER-1976-002, :on 760107,during Routine Insp,Eccs Fill Jockey Pump Found Inoperable.Caused by Insufficient Lubrication. ECCS Jockey Pump Coupling Will Be Added to Lubrication Program (← links)
- 05000249/LER-1976-003, :on 760110,during Weekly Turbine Check,Closure of Control Valve 2 Failed to Initiate Reactor Half Scram.Cause Unknown.Fast Acting Solenoid Will Be Inspected (← links)
- 05000249/LER-1976-004, :on 760303,during Surveillance Testing, Diesel Generator Could Not Be Loaded from Control Room Due to Loose Governor Control Wire.Apparently Caused by Vibration.Event Under Review (← links)
- 05000249/LER-1976-009, :on 760510,during Surveillance Test on Core Spray Valves,Valve Mo 3-1402-25B Tripped on Thermal Overload. Caused by Undersized Overload Heater.Mod Initiated to Replace Overload Heaters (← links)
- 05000249/LER-1984-003-07, :on 840405,health Physicist Became Separated from Group During Drywell Entry.Primary Containment Integrity Broken for Five Minutes.Caused by Procedural Deficiency.Dap 7-11 Revised (← links)
- 05000249/LER-1984-001-06, :on 840323,during Reactor Startup,Reactor Water Level Decreased to Low Level Alarm Point,Causing High Neutron Flux Reactor Scram.Cause Not Stated.Bypass Steam Flow Will Be Minimized in Future (← links)
- 05000249/LER-1983-041-03, /03L-0:on 831108,while Performing Auto Blowdown Logic Test Dis 250-4,time Delay Relay 287-105A Tripped at 127.6 s, Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Relay Adjusted (← links)
- 05000249/LER-1983-040-03, /03L-0:on 831028,diesel Generator Did Not Close Onto 4-kV Bus 34-1 & Feed Breaker Remained Tripped.Caused by Dirt Buildup on Contact 52H on Bus.Contact Burnished (← links)
- 05000249/LER-1983-038-03, /03L-0:on 831020,during Refueling Surveillances, HPCI Temp Switches TS3-23371A Tripped at 203.9 F.Caused by Setpoint Drift.Setpoint Adjusted.Repeatability Verified (← links)
- 05000249/LER-1983-039-01, /01T-0:on 831101,during Inservice Insp,Ultrasonic Test Showed Three Rejectable Indications in Weld 8-K46 on Cleanup Line 1201-8 & Three Axial Indications on safe-end to Elbow Weld 28-1 in Recirculation Sys (← links)
- 05000249/LER-1983-037-03, 83-037/03L-0:on 831005,during Daily Battery Surveillance, 250-volt Battery Charger Float Voltage Indicated Improper Float Voltage.Caused by Defective Amplifier Board.Defective Board Replaced (← links)
- 05000249/LER-1983-033-03, /03L-0:on 830926,reactor Bldg Ventilation Inlet Isolation Valve AO 3A-5741 Would Not Close on Auto or Manual Signal.Caused by Accumulated Dirt in Valve Internals. Solenoid Valve & Coil Replaced (← links)
- 05000249/LER-1983-032-03, /03L-0:on 830921,valve LPCI 1501-11B Closed During Installation of Terminal Jumper.Caused by Technician Inadvertently Placing Terminal Jumper on 903-3 Panel Instead of 903-10 Panel (← links)
- 05000249/LER-1983-034-03, /03L-0:on 830923,during Normal Operation,Mobile Crane Hit Wet Pipe Sprinkler Drain Valve,Breaking Valve & Spraying Water on Trackway.Caused by Personnel Error.Valve Repaired.Personnel Counseled (← links)
- 05000249/LER-1983-028-03, /03L-0:on 830723,differential Pressure Switch Ps 1349A Actuated Above Tech Spec Limit of 32.0 Inches of Water.Caused by Inadvertent Adjustment of High Differential Pressure Isolation Potentiometer (← links)
- 05000249/LER-1982-049-03, Diesel Generator D-3 Failed to Start Twice Following Semiannual Insp.Caused by Worn Out Cylinder & Accumulation of Dust Inside Air Starter. Ingersoll-Rand Air Starter Replaced (← links)
- 05000249/LER-1982-048-03, During Normal Operation, Oxygen Analyzer Unit Failed W/High Oxygen Alarm Up in Control Room.Caused by Failed Light Bulb,Tripping Photo Electric Cell.Bulb Replaced (← links)
- 05000249/LER-1982-047-03, /03L-0:on 821117,during Normal Operation,W/Reactor Vessel Low Water Level ECCS Initiation in Progress,Lis 263-72-C Found Set at 111.0 Inches Delta P.Caused by Defective Procedure.Lis 263-72-C Reset (← links)
- 05000249/LER-1983-031-01, /01T-0:on 830905,quarterly Valve Timing Surveillance DOS 250-2 performed.MSIV-1B & 1C Exceeded Tech Spec Closure Time.Caused by Timing Mechanism Being Out of Adjustment.Msivs Adjusted (← links)
- 05000249/LER-1982-042-01, Excessive Amount of Water Discovered Leaking from Recirculating Seal Cavity 3B.Caused by Failure Due to Excessive Heat of Recirculation Pump 3B Rotating Hardface Seal (EPN24610) (← links)
- 05000249/LER-1983-018-03, Torus Water Level Lowered Via LPCI Sys.Lpci Core Spray Pump Pressure Alarm Annunciated & Cleared After Close Signal.Valve Indicating Lights & Breaker Tripped.Caused by Procedure Inadequacy (← links)
- 05000249/LER-1983-025-03, /03L-0:on 830623 & 24,3D Main Steam Line Radiation Monitor Found Reading Low.Caused by Weak Electrometer Tubes. Monitor Repaired & Calibr (← links)
- 05000249/LER-1983-024-03, /03L-0:on 830615,while Performing Component Cooling Svc Water Pump Test,Pressure Regulating Valve Mo 3-1501-3B Could Not Be Opened Past 50% Using Differential Pressure Controller.Caused by High Resistance (← links)
- 05000249/LER-1983-026-03, /03L-0:on 830708,relay 287-112A Failed to Energize.Probably Caused by Pinched Eye Terminal Lug. Terminal Screw Loosened & Pinched Lug Dislodged (← links)
- 05000249/LER-1983-027-03, /03L-0:on 830714,rod Block Monitor Channel 7 Downscale Trip Level Setting Determined to Be 4.6/125 Full Scale & Below Tech Spec Limit.Caused by Electronic Drift of Channel 7.Setpoint Adjusted (← links)
- 05000249/LER-1983-015-03, /03L-0:on 830406,during Normal Operation W/Dis 287-1 in Progress,Pressure Switch Ps 3-1554 F Would Not Operate at Required Pressure.Caused by Plugged Instrument Snubber.Snubber Cleaned & Switch Replaced (← links)
- 05000249/LER-1983-014-03, /03L-0:on 830405,main Steam Line Log Radiation Monitor 3A Experienced Loss of High Voltage Power Causing Monitor to Go Downscale.Caused by Burned Out Resistor on High Voltage Power Supply.Monitor 3A Replaced (← links)
- 05000249/LER-1983-010-03, /03L-0:on 830312 & 18,during Normal Operation, Drywell & Torus Oxygen Indication Slowly Drifted Up on All Points.Caused by Faulty Oven Temp Switch in Oxygen Analyzer. Switch Replaced (← links)
- 05000249/LER-1983-011-01, /01T-0:on 830314,LPCI Pump Suction Valve MO3-1501-5A Failed to Close.Caused by Mechanical Overload Which Broke Manual Operator Housing.Cause of Overload Undetermined.Valve Motor & Manual Operator Housing Replaced (← links)
- 05000249/LER-1983-020-03, /03L-0:on 830521,when Control Rod Drive (CRD) G-6 Pulled from Core After Scram & Addl Withdrawal Signal Applied,Overtraval Alarm Came Up & Position Indication Lost. Caused by Detached CRD Inner Filter (← links)
- 05000249/LER-1983-008-01, /01T-0:on 830212,during Normal Operations,Core Spray Pump 1401-3A Failed to Start During Test.Caused by Circuit Breaker Recharging Motor Toggle Switch Inadvertently Left in Off Position.Switch Changed to on Position (← links)
- 05000249/LER-1983-017-03, /03L-0:on 830504,after Actuation of HPCI Deluge Sys,Weight Releasing Lever of Deluge Valve Tripped.Probably Caused by Misaligned Trip Linkage.Solenoid & Valve Linkage Disassembled/Assembled W/No Anomalies Noted (← links)
- 05000249/LER-1983-021-01, /01T-0:on 830523,differential Pressure Switches Ps 1349A & B Actuated Above Tech Spec Limit.Caused by Instrument Drift.Switches Reset.Trip Point Repeatability Verified (← links)
- 05000249/LER-1981-033-01, Unit 2/3 Diesel Generator (D/G) Tripped Due to High Cooling Water Temp & Unit 3 D/G Manually Tripped During Testing.Caused by Failure of Cooling Water Pump Discharge Valve (← links)
- 05000249/LER-1982-015-03, /03L-0:on 820323,during Routine Auto Blowdown Logic test,one-time Delay Relay Did Not Trip within Tech Spec Limit.Caused by Instrument Setpoint Drift.Time Relays Recalibr (← links)
- 05000249/LER-1983-016-01, /01T-0:on 830504,station Notified That Hydraulic Snubber 16,replaced in Feb 1983,attached on One End Only. Caused by Insufficient Personnel Interface.Work Package Procedures Revised (← links)
- 05000249/LER-1983-006-03, /03L-0:on 830208,while Performing DOS 1500-1 (LPCI Valve Operability Test),Torus Spray Isolation Valve MO3-1501-18A Failed in Open Position.Caused by Auxiliary Contact in Control Circuitry of Valve.Contact Replaced (← links)
- 05000249/LER-1983-004-03, /03L-0:on 830204,while Disc Operations Sys 1600-1 Valve Timing Test in progress,MO-3-1301-3 Failed to Open. Caused by Valve Disc Wedged Too Tightly Against Seat.Valve Cycled from Control & Successfully Timed (← links)
- 05000249/LER-1983-006-01, /01T-0:on 830208,LPCI Pump Suction Valve M03-1501-5D Failed Open.Caused by Auxiliary Contact CR 105X Failure in Control Circuitry of Valve.Contact Replaced (← links)
- 05000249/LER-1983-005-01, /01T-0:on 830208,diesel Generator Failed to Start. Caused by Failure of Air Starter Motor Vanes to Engage. Ingersoll-Rand Air Starter Motors,Air Filter & Air Regulating Valve Replaced (← links)
- 05000249/LER-1983-001-03, /03L-0:on 830104,source Range Monitor 24 High Rod Block Found in Excess of Tech Spec.Caused by Setpoint Drift. Monitor Readjusted & Returned to Svc (← links)
- 05000249/LER-1982-046-03, /03L-0:on 821112,water Discovered Spraying from 1-inch Drain Line Off Bottom of Feedwater Regulator Isolation Valve 3A.Caused by Cracked Weld at 1-inch Chain Line Due to Stresses from Thermal Effects (← links)
- 05000249/LER-1982-008-03, While Performing Refuel Surveillance Dis 2300-7,calibr Testing Discovered HPCI Temp Switches 2371A,2372A,2370C & 2370D Above Tech Spec Limit. Caused by Vibration Loosening Set Screws (← links)
- 05000249/LER-1982-044-03, /03L-0:on 821102,during Routine Surveillance, DIS-700-3,high Trip (Rod Block) on Source Range Monitor 24 Found to Trip Above Allowable Limits.Caused by Setpoint Drift on Hi Alarm Potentiometer.Setpoint Reset (← links)
- 05000249/LER-1982-023-01, No Low Power Range Monitor Input to Rod Block Monitor (RBM) Noted During DOP 700-E3.Caused by Shorted Steering Diodes on Several RBM Cards.Defective Diodes Replaced (← links)
- 05000249/LER-1983-009-03, /03L-0:on 830307,steam Leak on Shell of 3C3 Low Pressure Feedwater Heater Found Near Extraction Steam Inlet Nozzle.Caused by Heater Shell Erosion by Deflected Extraction Steam.Eroded Area Cut Out & Replaced (← links)
- 05000249/LER-1982-043-03, /03L-0:on 821028,magnetrol Level Switches 82D & 82F Did Not Trip When Tested.Cause Unknown.Upper Switch Contact Mechanisms Installed on All Failed Switches (← links)
- 05000249/LER-1982-041-03, /03L-0:on 821021,discovered That Monthly Fire Protection Surveillances Dfpp 411-2 Were Partially Finished & Exceeded 31 Day Completion Requirement.Caused by Operating Shift Oversight (← links)
- 05000249/LER-1982-039-03, /03L-0:on 821015,during DOS 1500-3,component Cooling Svc Water (Ccsw) Pump Test,Submarine Door to Ccsw Pump Vault Found Open.Caused by Personnel Error.Door Closed. Personnel Reminded to Keep Door Closed (← links)
- 05000249/LER-1982-036-03, /03L-0:on 820912,during Startup at 45% Power, Annunciator 903-5-N-4 Indicated Turbine Pressure Operator Load Rejection & Turbine Stop Valve Scrams Bypassed on One Subchannel of Channel a Half Scram Circuitry (← links)
- 05000249/LER-1982-035-03, /03L-0:on 820905,during Testing of Control Rod Drive H-4 for Overtravel,Overtravel Alarm Came Up & Position Indication Lost,Indicating Uncoupling of Control Blade from Drive.Probably Caused by Inner Filter Becoming Detached (← links)
- 05000249/LER-1981-026-03, /03L-0:on 810915,while Shutting Down,Rod P-10 Showed Wrong Position on Rod Worth Minimizer.Caused by Several Diode Failures on Two Digital Output Printed Circuit Boards.Boards Removed,Repaired & Tested Satisfactorily (← links)
- 05000249/LER-1982-034-03, /03L-0:on 820901,investigation Revealed That Substandard Electromatic Relief Valve Main Valve Disc Guide Sleeve Utilized on ERV 3-203-3C.Caused by Personnel Error in Ordering Sleeve.Sleeve Will Be Replaced (← links)
- 05000249/LER-1982-012-03, During Local Leak Testing of Primary Containment Isolation Valves,Drywell & Torus Purge Sys Valve Was Found to Leak at Rate in Violation of Tech Spec Limit.Caused by Failure of Resilient Seating Matl (← links)
- 05000249/LER-1982-018-03, /03X-1:on 820414,during Refueling Outage Quarterly Valve Timing Per Procedure DOS 1600-1,nitrogen Inerting Stop Valve 3-1601-55 Closure Time Exceeded Tech Specs.Caused by Hardening of Internal Seals.Valve Actuator Replaced (← links)
- 05000249/LER-1982-033-03, /03L-0:on 820727,sporadic Group I Isolation Signals Occurred on One Channel & Relay 595-101B Dropped in & Out.Caused by Faulty Main Steamline Temp Switch 261-18B. Contacts Jumpered Until Next Shutdown.Insp Planned (← links)
- 05000249/LER-1982-024-03, /03L-0:on 820604,during Auto Blowdown Permissive Surveillance Dis 287-1,pressure Switch 155D Would Not Trip. Caused by Leaking Internal Diaphragm.Switch Replaced & Tested (← links)
- 05000249/LER-1981-017-03, 3B Motor Generator Set Undervoltage Relay Failed to Trip on Undervoltage Signal. Caused by Sticking Relay Tripping Device.Tripping Device Cleaned,Lubed & Placed Back in Svc (← links)
- 05000249/LER-1982-030-03, /03L-0:on 820716,transient in-core Probe Ball Valve 3A Failed to Reclose After Opening.Cause Will Be Resolved During Next Outage.Valve Will Be Replaced & Supplemental LER Submitted When Cause Determined (← links)
- 05000249/LER-1982-031-03, /03L-0:on 820718,several Spurious Trips of Main Steam Line High Flow Isolation Switch Occurred.Caused by Disconnection of Mechanical Linkage Between Torque Tube Mechanism & Electrical Switch.Linkage Replaced (← links)
- 05000249/LER-1982-032-03, /03L-0:on 820718,during Attempt to Open 3-1601-23 Valve,Valve Cycled from Open to Close W/O Operator Action. Caused by Leakage of Air from Weep Hole of Versa Valve,Due to Hardening of O-ring Seal.Versa Valve Replaced (← links)
- 05000249/LER-1982-026-03, /03L-0:on 820628,while Performing Dis 500-7, Pressure Switch Ps 504C Tripped at 402 Psig,Exceeding Tech Specs.Caused by Instrument Setpoint Drift.Switch Reset to Correct Setpoint (← links)
- 05000249/LER-1981-021-03, Pinhole Leak Found on Reactor Water Cleanup Line from Regenerative Heat Exchanger. Caused by Sensitization During Initial Welding.Other Internal Cracks Discovered.Heat Exchanger Loop Replaced (← links)
- 05000249/LER-1982-027-01, /01T-0:on 820629,isolation Valve for HPCI Pressure Switch 3-2389D Developed Leak Which Depressurized Sensing Line.Caused by Loose Packing on Isolation Valve to Pressure Switch.Packing Nut Tightened (← links)
- 05000249/LER-1982-023-03, /03L-0:on 820510,while Performing DOP 700-E3,power Range Neutron Monitoring Sys Check,No Local Power Range Monitor Inputs to Rod Block Monitor Noted for Certain Control Rods.Caused by Shorted Steering Diodes (← links)
- 05000249/LER-1982-022-03, /03L-0:on 820508,time Required for Scram Discharge Vol Vent & Drain Valves to Close Exceeded Tech Spec Limits. Probably Caused by Inaccurate Method of Monitoring Scram Discharge Vol Vent & Drain Valve Closure Time (← links)
- 05000249/LER-1982-021-03, /03L-0:on 820505,during Normal Operations W/Full Core Scram Testing in Progress,Control Rod Drive C-12 Overtravel Alarm Came Up & Rod Position Indication Lost. Caused by Detached Inner filter.C-12 Recoupled (← links)
- 05000249/LER-1982-020-03, /03L-0:on 820421,while Performing Surveillance Dis 1300-3,time Delay Relays 595-117A,B & D Timed Out Slightly Longer than 15-s.Caused by Failure of Surveillance Procedure to Agree W/Tech Specs.Relays Reset (← links)
- 05000249/LER-1982-020, Forwards LER 82-020/03L-0 (← links)
- 05000249/LER-1982-019-01, /01T-0:on 820417,while Conducting ASME Class I Hydrostatic Test During Shutdown,Water Discovered Leaking from LPCI Check Valve 3/4-inch Test Equalizing Line.Caused by Inadequate Piping Support (← links)
- 05000249/LER-1982-019, Forwards LER 82-019/01T-0 (← links)
- 05000249/LER-1982-017-03, /03L-0:on 820407,cracked Weld Discovered on Test Tap of Condensate Booster Recirculation Line.All Leakage Contained in Turbine Bldg Floor Sumps.Cause Not Stated.Tap Cut & Capped (← links)
- 05000249/LER-1982-017, Forwards LER 82-017/03L-0 (← links)
- 05000249/LER-1982-016-03, /03L-0:on 820329,during Refueling Outage Mechanical Snubber 23 on Reactor Water Cleanup Sys Found Inoperable.Caused by Overloading Snubber During One Time Event.Snubber Replaced W/Hydraulic Snubber HSSA-10 (← links)
- 05000249/LER-1982-016, Forwards LER 82-016/03L-0 (← links)
- 05000249/LER-1981-025-01, During Automatic Depressurization Sys Valve Operability Surveillance,B Electromatic Relief Valve Failed to Open at Rated Pressure. Caused by Excessive Leakage on Threads (← links)
- 05000249/LER-1981-025, Forwards Updated LER 81-025/01X-1 (← links)
- 05000249/LER-1982-013-03, /03L-0:on 820204,during Refueling Outage,Nitrogen Inerting Makeup Sys Supplying Nitrogen to Drywell Found to Leak at Rate of 80.39 Scfh.Caused by External Damage to Pressure Valve RV-3-8526.Valve Will Be Replaced (← links)
- 05000249/LER-1982-013, Forwards LER 82-013/03L-0 (← links)
- 05000249/LER-1982-006-03, /03L-0:on 820122,quarterly Storage Battery Surveillances Not Performed for Third Quarter 1981. Caused by Miscoordination Between Implementing New Battery Check Procedure & Revising Computer Program (← links)
- 05000249/LER-1982-006, Forwards LER 82-006/03L-0 (← links)
- 05000249/LER-1981-035-03, During Normal Operation, Reactor Bldg to Torus Vacuum Breaker Valve 1601-20B Failed to Open.Caused by Failure of Versa solenoid,YGS-4522 U-3BC-10F-31.Solenoid Replaced (← links)
- 05000249/LER-1981-035, Forwards Updated LER 81-035/03X-1 (← links)
- 05000249/LER-1982-004-03, /03L-0:on 820117,during Local Leak Rate Testing of Containment Ventline,Measured Leakage Was 5612 Scfh Exceeding Tech Specs.Caused by Deterioration of Seating Surface.Valve Replaced (← links)
- 05000249/LER-1982-004, Forwards LER 82-004/03L-0 (← links)
- 05000249/LER-1982-002-03, /03L-0:on 820107,while Local Leak Rate Testing During Refueling Outage,Determined That Outboard MSIVs 3-203-2B & 3-203-2D Were Leaking in Excess of Tech Spec. Caused by Valve Packing Leakage.Packing Tightened (← links)
- 05000249/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000249/LER-1982-003-03, /03L-0:on 820115,during Steam Line Area Temp Switch Calibr Surveillance During Refueling Outage,Switch 3-261-16C Exceeded Tech Specs Limit of Less than or Equal to 200 F.Caused by Defective Temp Sensing Bulb.Switch Replaced (← links)
- 05000249/LER-1982-003, Forwards LER 82-003/03L-0 (← links)
- 05000249/LER-1982-001-03, /03L-0:on 820103,outer Seal on Vacuum Breaker 3-1601-32B Found Leaking in Excess of Tech Spec Limit. Caused by Worn Rubber O-ring Seal.Seal Will Be Replaced & Valve Retested During Present Refueling Outage (← links)
- 05000249/LER-1982-001, Forwards LER 82-001/03L-0 (← links)
- 05000249/LER-1981-020, Is Canceled (← links)
- 05000249/LER-1981-036-03, /03L-0:on 811102,while Performing Surveillance Dis 287-1,pressure Switch PS3-1554E Failed to Operate at Required Pressure.Caused by Plugged Instrument Snubber. Snubber Cleaned (← links)
- 05000249/LER-1981-036, Forwards LER 81-036/03L-0 (← links)
- 05000249/LER-1981-037-03, /03L-0:on 811119,while Performing Diesel Generator Operability Surveillance,Diesel Generator Exhibited High Coolant Water Temp.Caused by Defective Discharge Check Valve on Diesel Generator Cooling Water Pump (← links)
- 05000249/LER-1981-037, Forwards LER 81-037/03L-0 (← links)
- 05000249/LER-1981-039-01, /01T-0:on 811130,HPCI Room Fire Sys Initiation Alarm Sounded & Fire Protection Deluge Sys Actuated.Caused by High Concentration of Humidity/Steam Vapor in HPCI Room. Sys to Be Reviewed to Improve Reliability (← links)
- 05000249/LER-1981-039, Forwards LER 81-039/01T-0 (← links)
- 05000249/LER-1981-038-01, /01T-0:on 811122,during Normal Operations,Hpci Inboard Steam Supply Isolation Valve M03-2301-4 Had No Open Position Indication.Caused by Valve Packing Leak.Valve Repacked & Motor Replaced (← links)
- 05000249/LER-1981-038, Forwards LER 81-038/01T-0 (← links)
- 05000249/LER-1981-034-03, /03L-0:on 811026,source Range Monitor Channels 21 & 22 Found to Trip at Level Exceeding Tech Spec Limit.Caused by Drift of High Alarm Setpoint Potentiometer.Setpoints Adjusted (← links)
- 05000249/LER-1981-034, Fowards LER 81-034/03L-0.Detailed Event Analysis Encl (← links)
- 05000249/LER-1981-032-03, /03L-0:on 811020,four of Average Power Range Monitor Gain Adjustment Factors Noted Greater than Tech Spec.Caused by Change in Flux Distribution & Number/Location of Low Power Range Monitor Inputs (← links)
- 05000249/LER-1981-032, Forwards LER 81-032/03L-0 (← links)
- 05000249/LER-1981-033, Forwards LER 81-033/01T-0 (← links)
- 05000249/LER-1981-030-03, /03L-0:on 811014,Unit 3 Diesel Generator Fuel Cutoff Valve Found in Cutoff Position.Cause Unknown. Operator Opened Valve & Verified Operability.Review of Valves Completed to Ensure Locked Valve List Appropriate (← links)
- 05000249/LER-1981-030, Forwards LER 81-030/03L-0 (← links)
- 05000249/LER-1981-029-03, /03L-0:on 811005,w/scram Discharge Vol East Bank/ West Transducer Bypassed,East Bank/East Transducer Trouble Alarm Sounded & East Bank UT Level Monitor Declared Inoperable.Caused by Setpoint Drift (← links)
- 05000249/LER-1981-029, Forwards LER 81-029/03L-0 (← links)
- 05000249/LER-1981-031-03, /03L-0:on 811020,while Performing Routine Source Range Monitor Block Calibr Check,High Trip on SRM 23 Did Not Function Per Tech Specs.Caused by Bad Capacitor on Integrator Card Z13.Card Repaired & Tested Satisfactorily (← links)
- 05000249/LER-1981-031, Forwards LER 81-031/03L-0 (← links)
- 05000249/LER-1981-028-03, /03L-0:on 810918,during MSIV Timing,Two Valves (3-203-1A & 2B) Closure Times Exceeded Limits.Caused by Mechanism Drift.Valves Adjusted (← links)
- 05000249/LER-1981-028, Forwards LER 81-028/03L-0 (← links)
- 05000249/LER-1981-027-03, /03L-0:on 810917,during Diesel Generator Monthly Surveillance,Unit 3 Diesel Generator Failed to Start.Caused by Seal Leak in Air Start Regulator Valve.Valve Replaced (← links)
- 05000249/LER-1981-027, Forwards LER 81-027/03L-0 (← links)
- 05000249/LER-1981-024-01, /01T-0:on 810914,ultrasonic Testing Revealed Water in Steam Supply Line to HPCI Turbine.Caused by Low Point in Horizontal Section of Pipe.Drain Line Installed in Low Point & Routed Back to Same Line at Lower Elevation (← links)
- 05000249/LER-1981-024, Forwards LER 81-024/01T-0 (← links)
- 05000249/LER-1981-055-03, /03L-0:on 810830,small Leak Detected in Floor Drain Discharge Line of Radwaste Basement.Caused by Butt Weld Failure on Line 2/3-2014 6-inch Carbon Steel Pipe, Weakened by Corrosive Solutions.Pipe Replaced (← links)
- 05000249/LER-1981-055, Forwards LER 81-055/03L-0 (← links)
- 05000249/LER-1981-019-03, /03L-0:on 810821,main Steam Line High Flow Switches Dpis 3-261-2 & 3-261-2D Found Above Tech Spec Limits.Caused by Torque Shaft Gears Binding on Linkage Gears from Normal Wear & Filings Buildup.Gears Cleaned (← links)
- 05000249/LER-1981-019, Forwards LER 81-019/03L-0 (← links)
- 05000249/LER-1983-002, Forwards LER 83-002/01T-0 (← links)
- 05000249/LER-1982-049, Forwards LER 82-049/03L-0 (← links)
- 05000249/LER-1982-045-01, /01T-0:on 821109,during Normal Operation,Diesel Generator D-3 Tripped on Low Cooling Water Pressure.Caused by Bad Low Cooling Water Pressure Switch.Switch Replaced (← links)
- 05000249/LER-1982-045, Forwards LER 82-045/01T-0 (← links)
- 05000249/LER-1982-040-03, /03L-0:on 821019,upscale Trip Point of Channel B Refuel Floor Area Radiation monitor,3-1705-8B,found at 130 Mrem/H.Caused by Instrument Set Point Drift.Monitor Reset to Trip at 90 Mrem/H (← links)
- 05000249/LER-1982-040, Forwards LER 82-040/03L-0 (← links)
- 05000249/LER-1982-042, Forwards LER 82-042/01T-0 (← links)
- 05000249/LER-1981-040-01, /01T-0:on 811201,when Rx Pressure Decreased to 32 Psig,Rod N-9 Notched from Position 02 to 04 & Then to Position 06.Cause Unknown.Work Request Issued to Check Single Notch Control Switch During Next Refueling Outage (← links)
- 05000249/LER-1981-040, Forwards LER 81-040/01T-0 (← links)
- 05000249/LER-1983-019-03, /03L-0:on 830521,MSIV 203-1B Found W/Closure Time of 2.7 Exceeding Tech Spec Limit of 3 to 5 S.Caused by Misadjustment to Timing Mechanism on MSIV-203-1B.MSIV Adjusted within Tech Spec Limits (← links)
- 05000249/LER-1981-021, Forwards LER 81-021/03L-0 (← links)
- 05000249/LER-1981-023-03, /03L-0:on 810904,while Conducting Quarterly Scram Discharge Vol Continuous Level Monitor Calibr Check,West & East Bank/East Transducer high-high Level Alarm Tripped. Caused by Setpoint Drift (← links)
- 05000249/LER-1981-023, Forwards LER 81-023/03L-0 (← links)
- 05000249/LER-1981-022-03, /03L-0:on 810902,vessel low-low Water Level Isolation Switch Had Setpoint of 116.8 Inches,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Setpoint Adjusted (← links)
- 05000249/LER-1981-022, Forwards LER 81-022/03L-0 (← links)
- 05000249/LER-1981-014-03, /03L-0:on 810616,during Scram Air Sys Header Pressure Switch Calibr,Pressure Switches 3-302-99A & B Actuated W/Setpoint Lower than Required.Caused by Instrument Setpoint Drift.Switches Reset (← links)
- 05000249/LER-1981-014, Forwards LER 81-014/03L-0 (← links)
- 05000249/LER-1981-018-03, /03L-0:on 810619,LIS 263-72B Found Tripping Above Tech Spec Limit During Monthly Water Level ECCS Instrument Surveillance.Caused by Instrument Setpoint Drift.Setpoint Adjusted.Deviation Rept Encl (← links)
- 05000249/LER-1981-018, Forwards LER 81-018/03L-0 (← links)
- 05000249/LER-1980-048-03, Shutdown Cooling Sys Inboard Isolation Valve Did Not Close During Shutdown,While Testing Group 2 & 3 Isolation Circuitry.Caused by Breaker Door Interlock Out of Adjustment.Interlock Adjusted (← links)
- 05000249/LER-1980-048, Forwards Updated LER 80-048/03X-1 (← links)
- 05000249/LER-1981-015-03, /03L-0:on 810618,switch Actuated at 32.8 Inches During Calibr of Isolation Condenser Steam/Condensate Line High Flow.Caused by Instrument Drift.Switch Reset (← links)
- 05000249/LER-1981-015, Forwards LER 81-015/03L-0 (← links)
- 05000249/LER-1981-016-03, /03L-0:on 810618,water Level Instrument Surveillance Found LIS 263-57A Tripping Above Tech Spec Levels for Low Level Scram & Low Water Level Isolation. Caused by Instrument Setpoint Drift.Setpoint Adjusted (← links)
- 05000249/LER-1981-016, Forwards LER 81-016/03L-0 (← links)
- 05000249/LER-1981-001, Has Been Cancelled (← links)
- 05000249/LER-1981-003-03, /03L-0:on 810120,Model 288 Differential Pressure Indicating switch,3-1349B,tripped Above Tech Spec Limit. Caused by Instrument Drift.Switch Readjusted & Repeatability Verified (← links)
- 05000249/LER-1980-045-03, /03L-0:on 801219,drywell Spray Header Outboard Isolation Valve Did Not Close from Control Room.Probably Caused by Stuck Plunger on Closing Coil of Valve Motor Breaker.Plunger Freed by Moving Closing Coil by Hand (← links)
- 05000249/LER-1980-038-03, /03L-0:on 801021,crack Was Found on Reactor Water Cleanup Heat Exchanger Equalizing Line (3-1292-2-A).Cause Unknown.Leak Was Temporarily Patched (← links)
- 05000249/LER-1980-037-03, /03L-0:on 801020,during Normal Operation W/Dis 500-2 in Progress,Level Switch LIS 263-57B Was Found to Trip at Differential Pressure Less than Tech Specs.Caused by Instrument Drift.Instrument Readjusted (← links)
- 05000249/LER-1980-039-03, /03L-0:on 801022,during Normal Operation,While Conducting Isolation Condenser Valve Operability Tests, Inboard Isolation Valve 3-1301-1 Became Inoperable When Breaker Tripped Upon Receiving Open Signal.Cause Unknown (← links)
- 05000249/LER-1980-033-03, /03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged (← links)
- 05000249/LER-1980-028-03, /03L-0:on 800718,during Setpoint Surveillance, Solenoid Valve for Torus to Reactor Bldg Vacuum Breaker 3-1601-20A Determined Inoperative,Preventing Valve from Opening.Caused by Mechanical Failure.Valve Replaced (← links)
- 05000249/LER-2019-001, Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications (← links)
- 05000249/LER-1980-019-03, /03L-0:on 800420,during Switch Calibr Surveillance,Target Rock Relief Valve Press Switch PS-3-203-3A Tripped Below Tech Specs Limit.Caused by Setpoint Drift.Switch Readjusted within Tech Specs Limit (← links)
- 05000249/LER-1980-008-03, /03L-0:on 800307,during Refueling Outage While Performing Temp Switch Calibr Surveillance,Three Temp Switches Failed to Trip Per Specs.Caused by Drift,Excessive Gap Between Actuator & Switch Plunger or Dirty Contacts (← links)
- 05000249/LER-1980-009-03, /03L-0:on 800306,during Refueling Outage,While Performing LPCI Logic Tests,Injection Valve Mo 3-1501-22A Failed to Open.Caused by Loose Wire on Terminal Block in MCC-38-7 Due to Stripped Brass Screw (← links)
- 05000249/LER-1980-021-01, /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch (← links)
- 05000249/LER-1980-006-03, /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins (← links)
- 05000249/LER-1980-007-03, /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats (← links)
- 05000249/LER-1980-005-01, /01T-0:on 800213,while in S/D Mode,Msiv Scram Limit Switches Were Checked & of 16 Limit Switches,Two Found to Have Setpoints Greater than 10%.Caused by Switch Out of Calibr.Limit Switches Readjusted (← links)
- 05000249/LER-1980-004-03, /03L-0:on 800202,while Increasing Load by 2 Mwe Per Hour,Alarms Received in Control Room Indicating Failed Jet Pump.Jet Pump 13 Failed.Cause & Corrective Action Will Be Described in Supplemental Rept (← links)
- 05000249/LER-1980-002, Forwards LER 80-002/03L-0 (← links)
- 05000249/LER-1979-027, Forwards LER 79-027/03L-0 (← links)
- 05000249/LER-1980-011-03, /03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested (← links)
- 05000249/LER-1979-030-03, During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment (← links)
- 05000249/LER-1979-023-03, /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified (← links)
- 05000249/LER-1979-021-03, /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly (← links)
- 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak (← links)
- 05000249/LER-1980-017, /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start (← links)
- 05000249/LER-1980-021, /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operabil (← links)
- 05000249/LER-1980-030, /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds (← links)
- 05000249/LER-1980-032, /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block (← links)
- 05000249/LER-1980-040, /01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open (← links)
- 05000249/LER-1979-035, /03L-0 for Dresden Unit 3 Regarding Discovery of Valve Mo 3-1501-3A Having No Position Indication (← links)
- 05000249/LER-1980-010, /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively (← links)
- 05000249/LER-1979-030, /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 (← links)
- 05000249/LER-1980-011, /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification (← links)
- 05000249/LER-1980-012, /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification (← links)
- 05000249/LER-1980-015, /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted (← links)
- 05000249/LER-1980-013, /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve (← links)
- 05000249/LER-1975-005, Regarding Reactor Feed Pump 3C Pump Casing Vent Line Weld Break (← links)
- 05000249/LER-1975-019, For Dresden Unit 3 Regarding a Broken Test Line on Penetration X-105 D (← links)
- 05000249/LER-1975-009, For Dresden, Unit 3, 2A MSIV Not Full Open Scram (← links)
- 05000249/LER-1975-004, For Dresden, Unit 3, Reactor Feed Pump Minimum Flow Line Leak (← links)
- 05000249/LER-1975-001, For Dresden, Unit 3, Hydraulic Piping Restraint Failure (← links)
- 05000249/LER-1975-007, For Dresden, Unit 3, Failure of Hydraulic Pipe Suppressor (← links)
- 05000249/LER-1975-016, For Dresden, Unit 3, Excessive Control Rod Scram Times (← links)
- 05000249/LER-1975-013, For Dresden, Unit 3, Excessive Control Rod Scram Times (← links)
- 05000249/LER-1975-014, For Dresden, Units 3, Diesel Generator Inoperable (← links)
- 05000249/LER-1978-023, /01T-0 for Dresden Unit 3 Regarding Source Range Monitors 24 and 21 Being Declared Inoperable on 05/20/1978 (← links)
- 05000249/LER-1978-022, /03L-0 for Dresden Unit 3 Regarding Discovery of High Flow Isolation Switches DPIS 261-2C, 261-2N, and 261-2S to Trip at Values Exceeding the Technical Specification Limit (← links)
- 05000249/LER-1974-037, Regarding the Torus Oxygen Containment Out of Limit (← links)
- 05000249/LER-1974-022, Regarding HPCI High Flow Setpoint DPIS 3-2352 of 283 Inches H20 Which Is Above Technical Specifications (← links)
- 05000249/LER-1978-024, /03L-0 for Dresden Unit 3 Regarding the Discovery of PS3-263-53A to Trip at 1178 PSI Which Is Above Technical Specifications (← links)
- 05000249/LER-1974-025, Regarding Failure of B TIP Machine Valve to Close (← links)
- 05000249/LER-1974-027, Regarding Loss of Core Spray 3A Discharge Pressure (← links)
- 05000249/LER-1974-054, For Dresden 3 Regarding Core Spray Valve 3-1402-38As Failure to Close (← links)
- 05000249/LER-1974-047, Regarding Failure of Pressure Switch Instrument Taps on 2/3 Radwaste Filter (← links)
- 05000249/LER-1974-031, For Dresden Unit 3 Regarding the 2/3 Core Height Water Level Sensors Lits 3-263-73 A&B Having Setpoints Above the Technical Specification Limit (← links)
- 05000249/LER-1978-028-03, Re While Performing Surv. Dis 250-1, MSL Hi Flow Isolation Sw. Dpis 3-261-2c Tripped at 117 Psid (← links)
- 05000249/LER-1978-020, /03L-0 for Dresden 3 Regarding Discovery of Ps 3-203-3C Tripped at 1148 PSI Rx Pressure Incr (← links)
- 05000249/LER-1978-012, /01T-0 for Dresden 3 Regarding Disclosure of One Apparent Crack-Like Indication on the 330 Degrees Feedwater Sparger Along with Several Indications on the CRD Nozzle Thermal Sleeve Retainer (← links)
- 05000249/LER-1978-010, /01T-0 for Dresden 3 Regarding Discovery of 6 Hydraulic Snubbers Nos. 18, 19, 20, and 33 in Unit 3 Drywell and Nos. 1 and 3 in Isolation Condenser Pipeway with Less than Required Amount of Fluid (← links)
- 05000249/LER-1978-014, /01T-0 for Dresden 3 Regarding 24/48 Vdc Battery Failure to Pass the Refueling Outage Discharge Test (← links)
- 05000249/LER-1978-013, /01T-0 for Dresden 3 Regarding Setpoints Being Set High by 10% During the Quarterly Scheduled Calibration Dis 1700-1 (← links)
- 05000249/LER-1978-015, /03L-0 for Dresden 3 Regarding Discovery of One Snubber in Drywell to Be Functionally Inoperable by Bench Test During Inspection to Check 10% of All Hydraulic Snubbers During Refueling (← links)
- 05000249/LER-1978-016, /03L-0 for Dresden 3 Regarding Leakage Through Standby Liquid Control Check Valve 3-1101-15 Exceeding the T.S.4.7.A Limit for Single Valve Leakage of 29.38 Scfh (← links)
- 05000249/LER-1978-017, /01T-0 for Dresden 3 Regarding an NRC Request That Immediate Action Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Va (← links)
- 05000249/LER-1978-019, /03L-0 for Dresden 3 Regarding the Discovery of Ps 504C and 504D Found to Trip at 403 PSI and 405 PSI Respectively (← links)
- 05000249/LER-1978-018, /03L-0 for Dresden 3 Regarding the Discovery of U3 Diesel Oil Storage Tank at 9000 Gal. Which Is Below the 10000 Gal. Limit Required by Technical Specification 3.9.c (← links)
- 05000249/LER-1977-048, /03L-0 for Dresden 3 Regarding Excessive Leakage Noted Into the Drywell Floor Drains and a Reactor Shutdown Began in Order to Prevent Exceeding the Tech Specification Limit (← links)
- 05000249/LER-1977-050, /03L-0 for Dresden 3 Regarding an Attempt to Switch Cleanup Pumps and Subsequent System Isolated on High Pressure, and Valve M03-1201-1 Lost All Indication (← links)
- 05000249/LER-1977-051, /03L-0 for Dresden 3 Regarding Dis 500-2 Setpoint for Reactor Level Switch LIS 3-263-58B Found at ll6.8 Water Dp Which Is Above the Technical Specification Limit (← links)
- 05000249/LER-1977-057, /03L-0 for Dresden 3 Regarding the Failure of the LPCI Heat Exchange Discharge Valve (M03-1501-3A) to Open (← links)
- 05000249/LER-1978-001, /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109% (← links)
- 05000249/LER-1978-002, /03L-0 for Dresden 3 Regarding the Failure of MO-3-1501-5C to Reopen While Performing DOS 1500-1. the Motor Oper. Suction Valve to C LPCI Pp. Closed But Could Not Be Reopened from Control Room (← links)
- 05000249/LER-1978-003, /01T-0 for Dresden 3 Regarding Discovery of Containment Valve Leakages in Excess of Technical Specification 4.7.A Limits (← links)
- 05000249/LER-1978-009, /01T-0 for Dresden 3 Regarding an Ultrasonic Inspection of the Safe End-To-Pipe Weld on the CRD Return Line Revealed Indications Which Suggested Cracking (← links)
- 05000249/LER-1978-007, /03L-0 for Dresden 3 Regarding Dis 2300-6 HPCI Area Temperature SW 2371 a Tripped at 284.3 Degrees Fahrenheit (← links)
- 05000249/LER-1978-011, /01T-0 for Dresden 3 Regarding Cracks Identified in Cladding of CRD Nozzle Inner Radius and Vessel Wall Beneath Nozzle (← links)
- 05000249/LER-1978-005, /03L-0 for Dresden 3 Regarding the Discovery of a Pin Hole Leak in Minimum Flow Line from 3B Reactor Feedwater Pump Line 3-3205B-6 (← links)
- 05000249/LER-1978-006, /03L-0 for Dresden 3 Regarding the Discovery of Vacuum Breaker 1601-32F Binding (← links)
- 05000249/LER-1977-034, Regarding an Interruption in the Feedwater Flow Signal to the Circulation System (← links)
- 05000249/LER-1977-033, Regarding an Occurrence Where APRM 4 Would Not Generate an Inop Until 13 LPRMs Were Bypassed (← links)
- 05000249/LER-1977-032, Regarding a Surveillance Interval Discrepancy for the LPCI and Core Spray Pump and Valve Operability (← links)
- 05000249/LER-1977-036, Regarding a Failure of Test Valve MO-3-1501-20B Located on the Torus Test Return Line to Open (← links)
- 05000249/LER-1977-037, For Dresden Unit 3 Regarding an Occurrence of Less than 50% LPRM Inputs in APRM 1 and 2 (← links)
- 05000249/LER-1977-038, Regarding a Discovery of the Breaker for the Diesel Generator Cooling Water Pump Tripped (← links)
- 05000249/LER-1977-041, /01T-0 for Dresden 3 Regarding Discovery of APRM Nos. 4 and 6 to Inop on 12 Instead of 11 LPRMs Bypassed as Required by Technical Specification Section 3.1, Table 3.1.1 (← links)
- 05000249/LER-1977-039, /03L-0 for Dresden 3 Regarding Setpoint for Reactor Level Switch LIS 3-263-57B Found to Be Above the Technical Specification Limit (← links)
- 05000249/LER-1977-040, /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position (← links)
- 05000249/LER-1977-043, /03L-0 for Dresden 3 Regarding B Main Steam Line Radiation Monitor Indication Doubling (← links)
- 05000249/LER-1977-052, /03L-0 for Dresden 3 Regarding Discovery of DPIS 3-1349A Tripping at a Level Exceeding the Technical Specification Limit (← links)
- 05000249/LER-1977-017, Regarding the Discovery of APRM 4 to Generate an Inop When 60% of the LPRM Inputs Were Bypassed (← links)
- 05000249/LER-1977-018, Regarding the Discovery of the Analysis Completion Date for the April 77 Dresden 3 Reactor Water Exceeded the Allowable Limit by 17 Hours (← links)
- 05000249/LER-1977-022, Regarding Water Observed at the 6 Pipe Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted (← links)
- 05000249/LER-1977-021, Regarding the Discovery of a Pin Hole Leak in the Minimum Flow Line from the 3A Reactor Feedwater Pump During a Reactor Shutdown (← links)
- 05000249/LER-1977-025, LERs 77-025-00, 77-026-00, 77-027-00 for Dresden Unit 3 Regarding Electromagnetic Relief Valves 3-203-3C and 3D, the Failure of 3D Electromatic Relief Valve, and the Failure of Electromatics 203-3D and 3E (← links)
- 05000249/LER-1977-011, Regarding Reactor Building Vacuum Breaker A03-1601-20A Not Opening as Required During a Routine Surveillance (← links)
- 05000249/LER-1977-012-01, Regarding a Failure of the Responsible Radman to Collect the Required 4 Hour Reactor Water Sample During the Start-Up (← links)
- 05000249/LER-1977-012, Regarding a Reactor Water Sampling Interval Violation on April 29, 1977 (← links)
- 05000249/LER-1977-014, Regarding an Occurrence of the Differential Pressure (D/P) Across the Off Gas High Efficiency Particulate After Filters (HEPA) Increasing to Approximately 13-Inches of Water (← links)
- 05000249/LER-1977-015, Regarding a Pressure Switch 3-1349B Setting Greater than the Tech Specification Limit of Less than or Equal to 32 W.C.D.P (← links)
- 05000249/LER-1977-019, Regarding CRD H-9 Being Determined to Exhibit a 90% Insertion Scram Time in Excess of 7.0 Seconds (← links)
- 05000249/LER-1977-016, For Dresden Unit 3 Regarding an Occurrence Where the APRM Flow Bias Off-Normal Alarm Annunciated During Normal Operation (← links)
- 05000249/LER-1977-001, For Dresden Unit 3 Regarding During Normal Operation, Differential Pressure Indicating Switch 3-1349A Failed in the Opening Position (← links)
- 05000249/LER-1977-003, For Dresden Unit 3 During Normal Operation, APRM 6 Indication Appeared to Be Registering Power Level Fluctuations of 6 - 10% (← links)
- 05000249/LER-1976-036, For Dresden Unit 3 a Routine Monthly Surveillance Audit Revealed That Three Unit-3 Surveillance Intervals Had Been Inadvertently Exceeded (← links)
- 05000249/LER-1975-044, Letter Submitting Correction to Abnormal Occurrence Report Entitled, Off-Gas Increase on Unit 3 (Report 50-249/75/44) (← links)
- 05000249/LER-1974-029, Letter Submitting Follow-Up Report to Letter Dated 10/02/1974, Entitled: Through-Wall Crack on Torus/Drywell Purge Line, Unit 3 (← links)
- 05000249/LER-1975-042, Regarding Failure of LPCI Valve 3-1501-5D Motor Trip (← links)
- 05000249/LER-1975-035, Regarding Failure of Circuit Breaker 152-3403 to Open During a Breaker Trip Event (← links)
- 05000249/LER-1988-009-03, :on 880505,Groups II & III Primary Containment Isolation Occurred During Shutdown for Scheduled Refueling Outage.Caused by Mgt Deficiency for Failure to Implement Corrective Actions from Previous Event (← links)
- 05000249/LER-1988-010-01, :on 880424,main Steam Safety Valve 3-203-4D Opened at Pressure in Excess of Tech Spec 4.6.E Required Setpoint.Caused by Setpoint Drift.Valve Overhauling,Setting & Retesting Prior to Installation Planned (← links)
- 05000249/LER-1988-007-04, :on 880413,standby Liquid Control Relief Valves Failed to Open During Performance.Caused by Blockage as Result of Sodium Pentaborate Solution.Procedure Will Be Revised to Indicate Testing of Relief Valves (← links)
- 05000249/LER-1988-011, :on 880412,Group II Primary Containment Isolation Occurred.Caused by Procedural Inadequacy.Power Restored to Monitors & Isolation Reset.Procedural Change Being Investigated (← links)
- 05000249/LER-1988-004-07, :on 880404,atmosphere Containment & Dilution Purge Check Valve Leaked Exceeding Tech Spec Limit.Cause of Leakage Undetermined.Cause Will Be Determined & Valve Will Be Repaired & Retested (← links)
- 05000249/LER-1988-003-06, :on 880323,flued Head Anchor (FHA) Supports Found in Excess of FSAR Design Criteria.Caused by Design & Const Deficiencies.Repairs to FHA to Be Performed Under Mod M12-3-88-20 (← links)
- 05000249/LER-1988-005-03, :on 880326,HPCI Sys Made Inoperable to Facilitate Preplanned Preventive Maint Testing.Caused by Mgt Decision to Perform Preventive Maint Testing of HPCI Turbine Overspeed Trip Sys.Hpci Tripped on 5,015 Rpm (← links)
- 05000249/LER-1988-002-01, :on 880113,emergency Diesel Generator Automatically Started W/No Initiation Conditions Indicated in Control Room.Caused by Mgt Deficiency Re Work Activity on Inservice Equipment.Station Policy Issued (← links)
- 05000249/LER-1988-001, :on 880105,discovered That 41 Individual Type B & C Local Leak Rate Tests Performed During Previous Refueling Outage Had Individual Testing Intervals Exceeding 24 Months.Review Conducted (← links)
- 05000249/LER-1983-002-01, /01T-0:on 830105,leakage from RWCU Test Tap Valve 3-1299-13 Occurred.Caused by Seat Damage of Valve.Valve Replaced During 1983 Refueling Outage (← links)
- 05000249/LER-1986-018-01, :on 861014,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented (← links)
- 05000249/LER-1986-020, :on 861113,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented (← links)
- 05000249/LER-1987-005, :on 870316,primary Containment Drywell Structural Steel Failed FSAR Design Requirements.Caused by Inadequate Verification of as-built Condition W/Design Prints During Const.Repair & Insp Planned (← links)
- 05000249/LER-1987-008, :on 870321,reactor Scrammed on Low Reactor Water Level.Caused by Procedural Inadequacy in Conjunction W/Component Failure.Procedure Revised to Add Provision for Opening Feedwater Pump Discharge Valves (← links)
- 05000249/LER-1981-003, Forwards LER 81-003/03L-0 (← links)
- 05000249/LER-1980-045, Forwards LER 80-045/03L-0 (← links)
- 05000249/LER-1980-037, Forwards LER 80-037/03L-0 (← links)
- 05000249/LER-1980-039, Forwards LER 80-039/03L-0 (← links)
- 05000249/LER-1980-038, Forwards LER 80-038/03L-0 (← links)
- 05000249/LER-1980-033, Forwards LER 80-033/03L-0 (← links)
- 05000249/LER-1980-028, Forwards LER 80-028/03L-0 (← links)
- 05000249/LER-1980-019, Forwards LER 80-019/03L-0 (← links)
- 05000249/LER-1980-007, Forwards LER 80-007/03L-0 (← links)
- 05000249/LER-1980-006, Forwards LER 80-006/03L-0 (← links)
- 05000249/LER-1980-004, Forwards LER 80-004/03L-0 (← links)
- 05000249/LER-1980-005, Forwards LER 80-005/01T-0 (← links)
- 05000249/LER-1980-002-03, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause (← links)
- 05000249/LER-1992-004-02, :on 920122,calculations Indicated Min Required 4 Kv Safety Bus Voltages for Buses 33-1 & 34-1 to Be 3832 Volts & 3792 Volts,Respectively.Caused by Inadequate Design Control.Mods Designed & Installed (← links)
- 05000249/LER-1980-008, Forwards LER 80-008/03L-0 (← links)
- 05000249/LER-1980-009, Forwards LER 80-009/03L-0 (← links)
- 05000249/LER-1980-001-03, /03L-0:on 800116,loss of Sampling Point Automatic Advance for Drywell Oxygen Analyzer Noted During Normal Operation.Caused by Electrical Failure of Stepping Switch Motor Part 808376.Motor Replaced & Advance Restored (← links)
- 05000249/LER-1979-027-03, /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found (← links)
- 05000249/LER-2016-001, Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire (← links)
- 05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value (← links)
- 05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing (← links)
- 05000249/LER-2013-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously (← links)
- 05000249/LER-2012-001, Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure (← links)
- 05000249/LER-2011-001, Regarding Control Rod Block Instrumentation Failure (← links)
- 05000249/LER-2010-003, For Dresden, Unit 3, Regarding Steam Leak Results in HPCI Inoperability (← links)
- 05000249/LER-2010-002, MSIV Leakage Exceeds Technical Specifications Allowable Limits (← links)
- 05000249/LER-2010-001, For Dresden, Unit 3, OPRM Power Supply Failure During Maintenance Results in Unit 3 Automatic Reactor Scram (← links)
- 05000249/LER-2009-001, Re Group I Isolation and Automatic Reactor Scram (← links)
- 05000249/LER-2008-003, Regarding Unplanned Control Rod Withdrawals (← links)
- 05000249/LER-2008-002, From Dresden, Unit 3 Regarding Unit 3 Primary Containment Isolation Valve Declared Inoperable (← links)
- 05000249/LER-2008-001, Regarding Unit 3 Drywell Floor Drain Sump Monitoring System Declared Inoperable (← links)
- 05000249/LER-2007-002-01, Transmittal of LER 07-002-01 for Dresden Nuclear Power Station Unit 3, Special Nuclear Material Accountability Discrepancy (← links)
- 05000249/LER-2007-002, Transmittal of LER 07-002-00 for Dresden, Unit 3, Regarding Special Nuclear Material Accountability Discrepancy (← links)
- 05000249/LER-2007-001, Regarding High Pressure Coolant Injection System Declared Inoperable (← links)
- 05000249/LER-2006-001, Regarding Unit 3 Main Steam Safety Valves Exceed Surveillance Setpoint (← links)
- 05000249/LER-2004-001, Hearing - Entergy Exhibit 14, LER 2004-001-00, Dresden, Unit 3 Automatic Scram During Testing of the Main Turbine Master Trip Solenoid Valves (← links)
- 05000249/LER-2004-004, Re Unit 3, Shutdown Due to Inoperable Source Range Monitor (← links)
- 05000249/LER-2003-001, Regarding Drywell Radiation Monitor Detector Not Fully Inserted (← links)
- 05000249/LER-2002-006, Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure (← links)
- 05000249/LER-2002-004, Regarding Main Steam Safety Valves Failed TS as Found Lift Setpoint (← links)
- 05000249/LER-2002-003, Reactor Recirculation Loop a Sensing Line Socket Weld Vibration Fatigue Failure (← links)
- 05000249/LER-2002-005, High Pressure Coolant Injection System Inoperable Due to Water Hammer Event (← links)
- ML070220017 (redirect page) (← links)
- 05000249/LER-2006-001-01, Regarding Unit 3 Main Steam Safety Valves Exceed Surveillance Setpoint (redirect page) (← links)
- ML071070318 (redirect page) (← links)
- 05000249/LER-2006-001-01 (redirect page) (← links)
- 05000237/LER-2006-005, Regarding Control Room Emergency Ventilation Air Conditioning System Inoperable Due to Leaking Fittings (← links)
- 05000237/LER-2006-004, Re Unit 2 Reactor Scram Due to Main Steam Isolation Valve Closure (← links)
- 05000237/LER-2006-003, Re Plant Reactor Steam Dome Pressure-Low Permissive Switch Determined to Have Been Historically Inoperable (← links)
- 05000237/LER-2006-002, Regarding Unit 2 High Pressure Coolant Injection System Declared Inoperable (← links)
- 05000237/LER-2006-001, Re Isolation Condenser Declared Inoperable Due to Inadequate Backfilling of Instrument Sensing Lines (← links)