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List of results

• 05000316/LER-1950-316, Advises That Event Described in LER 50-316/86-25 Determined Not Reportable,Per Vendor Info & Engineering Evaluation. Raychron Replacement Timers Seismically Qualified for Use in Exide Battery Chargers.Ler Number Will Not Be Rei  + (1,950)
• 05000315/LER-1950-315, Retracts LER 50-315/85-70,per Generic Ltr 86-10 & Engineering Evaluation.Ler Number Will Not Be Reissued. Records Should Be Updated Accordingly  + (1,950)
• 05000369/LER-1950-369, Submits Addl Info Re LER 50-369/82-66 Re Failures of Ventilation Unit Condensate Drain Tank Flow Totalizer. Differential Pressure Transmitter Replaced W/Fischer & Porter Liquid Vortex Flowmeter.Totalizer Functions Properly  + (1,950)
• 05000255/LER-1950-255, FOIA Request for 851118 LER 50-255/85-23 on Possible Low Temp Overpressure Sys Setpoint Error to Be Placed in PDR  + (1,950)
• 05000338/LER-1950-338, Forwards LER 50-338/97-005-00.No Commitments Made  + (1,950)
• 05000266/LER-1950-266, Responds to NRC Re Violations Noted in Insp Repts 50-266/97-07 & 50-301/97-07.Corrective actions:30-day Security LER 50-266/97-S01-00,was Submitted to Commission on 970304  + (1,950)
• 05000413/LER-1950-412, Forwards Rept Summarizing Review Results of Interunit Electrical Interfaces,Which Was Part of Corrective Action for LER 50-412/85-51.Item Also Identified in Insp Repts 50-413/85-35 & 50-414/85-32  + (1,950)
• 05000482/LER-1950-482, FOIA Request for Documents Re Plant LER 50-482/88-028 W/All Revs & Suppls  + (1,950)
• 05000424/LER-1950-424, Forwards LER 50-424/1990-08S Re Unsecured Safeguards Info Due to Personnel Error  + (1,950)
• 05000237/LER-1950-237, Updated LER 50-237/75-048:on 751007,through-wall Crack Found in Drywell/Torus Nitrogen Purge Line 1604-18.Addl Mods, Including Temp Controlled Isolation Valve Installation, Delayed Until Proposal Review  + (1,950)
• 05000237/LER-1950-237-76, /76-001:on 760101,oscillograph Alarms Received on 138-kV Yard.Bus Section 1-2 Oil Circuit Breaker Bus 1 Disconnect Arced & Glowed.Caused by Loose Connector on Cable Between Ocb & Bus 1 Disconnect on C Phase  + (1,950)
• 05000266/LER-1950-266-75, /75-4:on 750226,primary to Secondary Tube Failure Occurred in Steam Generator B & Went from Initial Point Leak to Max of 125 Gallons Per Minute.Extent of Incident & Radioactivity Below Point to Initiate Evacuation  + (1,950)
• 05000000/LER-1950-237, Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis  + (1,950)
• 05000259/LER-1950-259-762, /762:on 760204,design Deficiency Found While Investigating LPCI Loop Selection Logic.Final Rept Will Be Submitted Per 10CFR50.55(e)  + (1,950)
• 05000260/LER-1950-260-763, /763W:on 760412,five Reed Relays Failed.Four Reed Relays Permit Sequential Selection & Withdrawal of Control Rods & One Permits Two Control Rod Simultaneous Withdrawal. Caused by CP Claire Reed Relay Contact Failure  + (1,950)
• 05000259/LER-1950-259-763, /763T:on 760213.Condition Determined Not to Be Ro  + (1,950)
• 05000247/LER-1950-247-01, /01L:on 750829,during Normal Operation,Two Charging Pumps Became Inoperable.Caused by Excessive Seal Leakage.Design Mods investigated.W/750926 Forwarding Ltr  + (1,950)
• 05000000/LER-1950-266-75, /75-18:on 751217,during Cycle 3-4 Refueling, Discovered Section of Fuel Rod Missing.Caused by Water Impingement Through Baffle Plate While Failed Assembly in Cycle 2 Position H-1.Investigation in Progress  + (1,950)
• 05000000/LER-1950-266-76, /76-12:on 761222,wall Cladding Defects Noted in One Rod of Fuel Assembly G07.Caused by Rod Vibrating Against Rod Retaining Grid Springs.Peening of Core Baffle Plate Joints,Completed in Nov 1976,should Prevent Recurrence  + (1,950)
• 05000285/LER-1950-285, Documents Deletion of Licensing Basis Commitment in LER 50-285/77-5 Re Failure of Reactor Protective Sys Trip Unit to Trip Prescribed Setpoint,Due to Improper Pretrip & Trip Indication Bulbs in Trip Unit Circuitry  + (1,950)
• 05000254/LER-1950-254, Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR  + (1,950)
• 05000298/LER-1950-298, Notifies That LER 50-298/79-31 Was Voided & Will Not Appear in NRC Files  + (1,950)
• 05000346/LER-1950-346, Corrected Transmittal Ltr for Revised LER 50-346/80-091.LER Originally Ref as 80-090  + (1,950)
• 05000029/LER-1950-029, Advises That LER 50-29/80-05 Was Not Used for 1980  + (1,950)
• 05000295/LER-1950-295, Informs That Info Necessary to Update LER 50-295/79-63 Not Available.Event Under Investigation.Updated LER Will Be Submitted as Soon as Possible  + (1,950)
• 05000280/LER-1950-280, Forwards LER 50-280/97-005 Which Has Been Reviewed by Station Nuclear Safety & Operating Committee & Will Be Forwarded to Mgt Safety Review Committee for Review. Commitments Made within Ltr,Listed  + (1,950)
• 05000260/LER-1950-260, Forwards Rev 1 to LER 50-260/96-01 Re Conditions Involving Noncompliance W/Requirements of 10CFR50 App R.Rev Provides Addition of Missing Text at Top of Page 6,inadvertently Deleted When Rev 0 Submitted on 960318  + (1,950)
• 05000296/LER-1950-296, Forwards LER 50-296/96-004 Which Provides Details Re Loss of Instrumentation Input Logic for Plants Division I Eccs. Broader Evaluation of Inverter Problems Being Conducted Due to Aggregate of Events  + (1,950)
• 05000316/LER-1950-315, Advises That Failure of Component Cooling Water Containment Isolation Valve 1-CCM-458 to Close Not Reportable Per 10CFR50.73.LER 50-315/89-05 Retracted & LER Number Will Not Be Reissued  + (1,950)
• 05000331/LER-1950-331, Withdrawal of LER 50-331/2012-001  + (1,950)
• 05000458/LER-1950-458, Fouling, Request to Provide ACRS with LER-50-458/99-016-00, Us Patent May 28, 2002, Us 6.396,892  + (1,950)
• 05000327/LER-1950-001, Re Automatic Reactor Trip Following Loss of Turbine Auto Stop Oil (ASO) Pressure  + (1,950)
• 05000263/LER-1950-004, Regarding Voluntary LER for Control Rod Drive Insert Line Leakage  + (1,950)

• 05000267/LER-1974-021, :on 741121,high Pressure in Gas Waste Vacuum Tank Ruptured Disc & Lifted Relief Valve Allowing Unexpected Release of 700 Scf Waste Gas.Caused by Loss of Flowpath. Valves Replaced W/O Handjack  + (1,974)
• 05000249/LER-1974-025, Regarding Failure of B TIP Machine Valve to Close  + (1,974)
• 05000237/LER-1974-028, Regarding TIP Machine Ball Valve Failure  + (1,974)
• 05000249/LER-1974-027, Regarding Loss of Core Spray 3A Discharge Pressure  + (1,974)
• 05000249/LER-1974-047, Regarding Failure of Pressure Switch Instrument Taps on 2/3 Radwaste Filter  + (1,974)
• 05000237/LER-1974-033, Regarding Discovery of a Pinhole Leak on the 3A Reactor Feed Pump Minimum Flow Line  + (1,974)
• 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  + (1,974)
• 05000237/LER-1974-034, Regarding Failure of a Air Ejector Rupture Disc  + (1,974)
• 05000237/LER-1974-036, Regarding Discovery of a Small Leak on Reactor Feed Pump 3A Minimum Flow Line 3-3205A  + (1,974)
• 05000249/LER-1974-054, For Dresden 3 Regarding Core Spray Valve 3-1402-38As Failure to Close  + (1,974)
• 05000237/LER-1974-029, For Dresden 3 Regarding a Through-Wall Crack on Torus/Drywell Purge Line  + (1,974)
• 05000249/LER-1974-037, Regarding the Torus Oxygen Containment Out of Limit  + (1,974)
• 05000249/LER-1974-022, Regarding HPCI High Flow Setpoint DPIS 3-2352 of 283 Inches H20 Which Is Above Technical Specifications  + (1,974)
• 05000237/LER-1974-035, For Dresden Units 2 and 3 Regarding Secondary Containment Blowout Panel Failure  + (1,974)
• 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  + (1,974)
• 05000237/LER-1974-032, Regarding High Pressure Coolant Injection High Flow Instrument Anomaly  + (1,974)

• 05000000/LER-1975-014, :on 750519,analysis of Reactor Bldg Vent & Main Stack Charcoal & Particulate Filters for Wk of 750513-20 Revealed Release Rates of Halogens & Particulates Exceeding Tech Spec Limits by 23%  + (1,975)
• 05000000/LER-1975-005, :on 750127,analysis of Reactor Bldg Vent & Main Stack Charcoal & Particulate Filters Revealed Release Rates of Halogens & Particulates w/half-lives Greater than 8 Days, Exceeding Tech Spec Limits by 24%  + (1,975)
• 05000263/LER-1975-018, :on 750914,snubber Located Inside Drywell on B Loop LPCI Line Discovered Low on Oil.Caused by Improperly Installed Seal.Affected Part Replaced  + (1,975)
• 05000263/LER-1975-019, :on 750921,count Rate of SRM Decreased Below 3 Cps.Fuel Reloaded Near Detector.Operational Limit Above 3 Cps Will Be Established to Prevent Recurrence  + (1,975)
• 05000220/LER-1975-007, :on 750412,during Quarterly Testing,Ec IV 11 (AC) Failed to Open.Caused by Loose Connection in Remote Manual Wiring Terminal Block.Connection Tightened  + (1,975)
• 05000220/LER-1975-003, :on 750212,during Plant Startup,Waste Evaporator Concentrator Failed,Resulting in Leakage.Caused by Sulfuric Acid Contamination  + (1,975)
• 05000220/LER-1975-001, :on 750109,level Control Valve to Emergency Condensers Failed,Resulting in High Water Level Alarm.Caused by Inability to Close Valve.Level Maintained W/Manual Valve. Spare Controller Installed  + (1,975)
• 05000220/LER-1975-008, :on 750414,during Normal Operation,Relay Coil in Reactor Protection Sys Relay 12K30 Shorted.Caused by Environ & High Usage.Coil Replaced  + (1,975)
• 05000220/LER-1975-019, :on 750722,surveillance Test on Torus Vacuum Relief to Atmosphere Switches Not Completed.Caused by Failure to Note Recent Changes to Tech Specs.Revised Tech Specs Noted  + (1,975)
• 05000220/LER-1975-023, :on 750826,iodine Detection Sensitivity Milk Sample Found Inadequate.Caused by Failure of Contractor to Fulfill Procedural Requirements.Contractor Reinstructed  + (1,975)
• 05000220/LER-1975-014, :on 750618,during Monthly Testing,Standby Liquid Control Sys Pump 11 Would Not Start.Caused by Unlatched Power Breaker Trigger.Breaker Reset  + (1,975)
• 05000220/LER-1975-021, :on 750802,during Routine Surveillance Test RV-30A,core Spray Sparger Tripped at 6.4 Psid Instead of Required 5 Psid.Caused by Setpoint Drift.Redundant Component Operable.Sparger Recalibr  + (1,975)
• 05000220/LER-1975-006, :on 750405,during Surveillance testing,RE-18A Reactor Level lo-lo-lo Found Actuating at 131 Rather than 128.5 Inches of Water.Caused by Instrument Drift.Instrument Recalibr  + (1,975)
• 05000220/LER-1975-018, :on 750704,during Routine Operation,Emergency Condenser Vent Radiation Monitor Went Upscale Isolating Sys as Designed.Caused by Failure of Monitor Component Due to High Temp Environ.Monitor Replaced  + (1,975)
• 05000220/LER-1975-022, :on 750814,during Routine Operations,Reactor Bldg Vent Monitor Spiked Resulting in Operation of Emergency Vent Sys.Caused by Failed Solenoid & Broken Spring Plunger Nylon Tip.Tip Replaced  + (1,975)
• 05000220/LER-1975-020, :on 750725,environ Milk Sample Found Not Analyzed for 9 Days Following Collection.Caused by Samples Being Sent to Lab Via Ground Transportation.Samples Will Be Sent by Air to Eberline Corp Labs  + (1,975)
• 05000220/LER-1975-009, :on 750414,during Function Test,Average Power Range Monitor 11 Failed to Provide High Alarm.Caused by Open Transistor in Dual Alarm Unit.Transistor Replaced  + (1,975)