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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- 05000373/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000338/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000325/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000328/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000324/LER-1982-085, Forwards LER 82-085/01T-0 +
- 05000321/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000311/LER-1982-085, Forwards LER 82-085/03L-0.Detailed Event Analysis Encl +
- 05000272/LER-1982-085, Forwards LER 82-085/01T-0.Detailed Event Analysis Encl +
- 05000316/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000259/LER-1982-085, Forwards LER 82-085/03L-0 +
- 05000325/LER-1978-085, Forwards LER 78-085/03L-0 +
- 05000295/LER-1978-085, Forwards LER 78-085/03L-0 +
- 05000440/LER-1986-085, Forwards LERs 86-083,86-084 & 86-086.LER 86-085 Will Be Sent Under Separate Cover +
- 05000354/LER-1986-085, :on 861114,full Reactor Scram Resulted from Valid Reactor High Pressure Signal.Caused by Personnel Improperly Calculating Peak Reactor Pressure During Turbine Control Valve Testing.Procedure Revised +
- 05000295/LER-1978-085-03, /03L-0:on 780827,discovered Missing Belt on Containment Area post-sampler Blower.New Belt Installed +
- 05000528/LER-1985-085, :on 850112,Train B Plant Vent Sys high-range Noble Gas Activity Monitor RU-144 Declared Inoperable. Caused by Inadequate Surveillance Procedure.Procedure Revised to Include Channel Check +
- 05000338/LER-1978-085-03, /03L-0 on 780830:Testing of Quench Spray Pump 1-QS-P-1B Showed Pressure Drop of Over 10psi on the Suction Line During Oper,Caused by Wooden Dam in Piping. (Encl to 7810030071) +
- 05000352/LER-1985-085, :on 851023,main Control Room Ventilation Sys Isolated & Train B of Emergency Fresh Air Sys Actuated. Caused by Failure of Optic Bulb of Chlorine Analyzer D (AE-78-016D).Bulbs Replaced +
- 05000454/LER-1985-085, :on 850829,determined That Two ASME Code Class 2 Welds in Safety Injection Sys Not Examined Per ASME Requirements.Caused by Misidentification of Weld for Exam. Relief from Requirements Granted on 850903 +
- 05000374/LER-1984-085-01, :on 841214,reactor Scram & Turbine Trip Occurred.Caused by Vibration Trip Signal from Loose Circuit Board Connection in Turbine Supervisory Sys.Vibration Card Reinstalled +
- 05000373/LER-1984-085, :on 841129,rev to LOA-FW-01 (Loss of Feedwater Heater) Made Due to Determination That Present Limit of 150 F Temp Change Caused by Loss in Feedwater Heating Nonconservative W/Respect to GE Analysis +
- 05000397/LER-1984-085, :on 840811 & 17,surveillance Performed on Standby Diesel Generators 1 & 2,DG1A & DG1B W/O Prelube Warmup.Memo Issued Outlining Understanding & Providing Interim Relief from Tech Specs +
- 05000325/LER-1978-085-03, /03L-0 on 781227:failed to Perform Quarterly Transmitter & Recorder Calibr for Drywell Oxygen Monitor CAC-AT-1259-2 in Mar & Sept 1978 Due to Misunderstanding of Tech Specs.Periodic Test Schedule Will Be Written +
- 05000348/LER-1983-085-03, /03L-0:on 831204,Containment Spray Sys Valve Inservice Tests FNP-1-STP-16.7 Not Performed within Allowed Time.Sys Declared Inoperable.Caused by Personnel Error.No Cause Found Re Improper Valve Stroking +
- 05000324/LER-1983-085-03, /03L-0:on 830928,while Performing Diesel Generator 4 Monthly Load Test PT-12.2d,diesel Generator Would Not Develop Generator Output Current.Caused by Failed Solenoid Cell 9103B.Cell Replaced +
- 05000316/LER-1983-085-03, /03L-0:on 830902,during Startup at 20% Power,After Turbine Generator Paralleled W/Sys Grid,Generator Load Increased to Prevent Motoring,Resulting in Pressure Drop Below Tech Specs.Caused by Heater Breaker Trip +
- 05000366/LER-1983-085-03, /03L-0:on 830817,during Control Panel Walkdown in Main Control Room,Torus Water Level Found Below Required Limit.Caused by Personnel Error.Level Restored to Acceptable Limits.Personnel Counseled +
- 05000370/LER-1983-085-03, /03L-0:on 831208,makeup Frequency to Vol Control Tank Increased & Containment & Equipment Sump 2A Pumped Out Several Times,Indicating Leakage Problem.Caused by Component Malfunction.Sample Line Isolated +
- 05000338/LER-1983-085-03, /03L-0:on 831220,discovered Thermal Power Containment Pressure Channel IV Drifting & Causing Intermittent Alarms.Possibly Caused by Dirt in Feedback Coil.Transmitter Cleaned +
- 05000362/LER-1983-085-03, /03L-0:on 831007,low Pressure Turbine 1,intercept Valve 3UV2200L,failed Trip Solenoid a & B Tests During Monthly Surveillance Test S023-3-3.34.Caused by Failed Logic Card in Control Circuit.Logic Card Replaced +
- 05000369/LER-1983-085-01, /01T-0:on 830930,discovered That Equipment/Cable Interfaces Using Crouse-Hinds Conduit Coupling as Sealing Method May Be Susceptible to Moisture Seepage.Caused by Design Oversight in Failure to Test Connections +
- 05000315/LER-1983-085-03, /03L-0:on 830817,train a Lower Containment Airborne Monitor Declared Inoperable Due to Failure of Control Terminal.Caused by Central Processing Unit Being in Locked Up State.Unit Reset +
- 05000321/LER-1983-085-03, /03L-0:on 830802,drywell Equipment Drain Sump Isolation Valve 1G11-F020 Had Double Position Indication in Full Closed Position.Caused by Loose Set Screw in Valve Closed Limit Switch Actuator.Actuator Adjusted +
- 05000395/LER-1983-085-03, /03L-0:on 830721-24,ambient Temp in Svc Water Pump House Exceeded Tech Spec Limits.Caused by Outside Air Temp Above Average.Mod to Evaluate Need for Installing Cooling Coils Being Processed +
- 05000373/LER-1983-085-03, /03L-0:on 830718,cooldown Rate in Excess of 100 F/ H Observed When full-core Scram Occurred.Caused by Rapid depressurization,full-core Scram & HPCS & RCIC Injection. Parameters Returned to Normal +
- 05000416/LER-1983-085-03, /03L-0:on 830719,inadvertent LOCA Signal Received in Div II LOCA Logic & RHR Pump B Breaker Closed Repeatedly Following Isolation.Cause of LOCA Signal Due to Troubleshooting Investigation +
- 05000333/LER-1978-085-04, /04X-1 on 781006:3rd Quarter Release of Halogens & Particulates Greater than Tech Specs.Caused by Steam Leaks & Fuel Pin Clad Performance +
- 05000321/LER-1982-085-03, /03L-0:on 821103,walkdown of TIP Withdrawal LSFT Logic Relay Wiring Revealed Two Wires Installed Onto Wrong Relay.Caused by Incorrect Relay Connection Diagram.Wires Will Be Terminated to Correct Terminal Relays +
- 05000315/LER-1982-085-03, /03L-0:on 820927,during Hot Standby Following Refueling,Steam Generator 2 Stop Dump Valve MRV-221 Removed from Svc.Caused by Need to Correct Seat Leakage.Valve Disc, Seat & Stem Replaced +
- 05000311/LER-1982-085-03, /03L-0:on 820816,two Malfunctions of Reactor Coolant Channel Flow Indication 24 Experienced Due to Failure of Signal Isolation Amplifiers.No Common Cause for Isolation Amplifier Failure Determined.Amplifiers Replaced +
- 05000272/LER-1982-085-01, /01T-0:on 821113,due to Resulting Loss of F & G Group Buses,Automatic Starting Feature of 1 & 2 Diesel Fire Pumps Disabled.Caused by Planned Maint on Station Power Transformer 12.Maint Completed & Power Restored +
- 05000316/LER-1982-085-03, /03L-0:on 821021,two Styluses on Containment Sump Level & Flow Monitoring Recorder Inoperable.Caused by Binding of Recorder Mechanism Causing Styluses to Remain in Slightly Raised Position +
- 05000259/LER-1982-085-03, /03L-0:on 821010,smoke Detector XS-39-27A Alarmed & Would Not Clear.Probably Caused by Increased Detector Sensitivity.Detector Replaced & Tested Satisfactorily. Firewatch Established +
- 05000280/LER-1982-085-03, /03L-0:on 820824,RCS post-reactor Trip Specific Activity Samples Found Greater than Tech Spec Limits.Caused by Fuel Defects in Reactor Core.Acclerated Sampling Frequency Implemented Till RCS Activity Less than Tech Spec +
- 05000325/LER-1982-085-03, /03L-0:on 820806,discovered Plant Procedures Did Not Provide for Channel Functional Test of Both Unit Aprms for Fixed Neutron Flux High within 24-h of Reactor Starting. Caused by Personnel Oversight.Procedure Revised +
- 05000338/LER-1982-085-03, /03L-0:on 821205,ECCS Actuated from High Steam Line Flow Coincident w/lo-lo Temp Average.High Steam Flow Signal Caused by Channels Being in Trip for maint.Lo-lo Temp Average Signal Caused by Reactor Trip +
- 05000348/LER-1978-085-03, /03L-0 on 781120:train a River Water(Rw)Pump 9 Secured Due to Vibration.Tech Specs Req at Least 2 Independent RW Loops to Be Operable.Caused by Bearing Damage Due to Fouling of Lube/Cooling Piping +
- 05000348/LER-1978-085, Forwards LER 78-085/03L-0 +
- 05000361/LER-1982-085-03, /03L-0:on 820805,control Element Assembly 68 Slipped & Dropped in Excess of Tech Specs.Caused by Slow Operation of Grippers.Control Element Assembly Exercised, Oxide Deposits Removed W/Hydrazine & Circuits Modified +
- 05000328/LER-1982-085-03, /03L-0:on 820705 & 06,lower Compartment Average Air Temp Was Greater than 120 F.Caused by Air Discharging Through Lower Compartment Air Cooler Fan 2B-B Which Was Out of Svc,Reducing Air Flow.Flow Passage Blocked +