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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
- ML20084U245 + (LER ER-77-009:on 770130,discharge Water Temp Rose Above 5 F Limit During Power Escalation.Caused by Either Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded)
- ML20084U244 + (LER ER-77-010:on 770131,ice Loading on 345-kV Bus Tie & Station Power Lines Greater than Expected Due to Cooling Tower Plume Passing Lines.Caused by Environ Conditions & Cooling Tower Operation)
- ML20084U243 + (LER ER-77-011:on 770130,secondary Water Chemistry Limits for Sodium Concentration,Ph & Conductivity Exceeded Tech Spec 3.18 Due to Leak in Main Condenser West Half.Cause Suspected to Be Tube Vibration.Tubes Plugged)
- ML20084U242 + (LER ER-77-012:on 770205,tank Heater H68A for Boric Acid Tank T-53A Found Leaking During Routine Insp of Chemical & Vol Control Sys.Cause Not Stated.Heater Replaced)
- ML20084U230 + (LER ER-77-014:on 770107,discharge Water Temp Exceeded 5 F Limit Twice.Cause Related to Stopping or Starting of Cooling Pump P-39B During Startup)
- ML20084U229 + (LER ER-77-015:on 760623,discharge Water Temp Rose Above 5 F Limit.Caused by Cooling Water Sys Design.Npdes Limits Not Exceeded)
- ML20084U228 + (LER ER-77-016:on 770210,two Events Caused Discharge Water Temp to Rise Above 5 F Limit.Cause Related to Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded)
- ML19210E846 + (LER Monthly Rept for Oct 1979)
- ML19329B635 + (LER NP-33-77-03:on 770511,accidental Removal of Source Range Power Detector Temporary Electrical Cord from Socket Caused Momentary Loss of Power & Audible Indication in Control Room.Caused by Personnel Error.Plug Reinserted)
- ML19274D939 + (LER NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing One of Two Reactor Coolant Pumps from Operation.Caused by Damage to Surge Capacitors Due to Insufficient Mounting Base)
- 05000304/LER-1985-028-01, LER Number 85-028 Used to Rept Loss of RHR Cooling Flow.Ltr Should Be Disregarded + (LER Number 85-028 Used to Rept Loss of RHR Cooling Flow.Ltr Should Be Disregarded)
- ML19352A360 + (LER Output on All Events During 1980)
- ML20052F306 + (LER Output on BWR Compressed Air Sys & Other Instrument Sys Not Required for Safety from 1969 to Present)
- ML20052C947 + (LER Output on Events Involving Injuries from 1969 to Present)
- ML19290B932 + (LER Output on Events Involving Releases from 1969-Present)
- ML19207A033 + (LER Output on Events at TMI-1 & TMI-2 from 1969 to Present)
- ML19308C954 + (LER Output on Events at TMI-2 from 1969 to Present. Sorted by Event Date)
- ML19224A775 + (LER Output on Events of TMI-2 from 1969 to Present Output Sorted by Facility & Event Date)
- ML19308C010 + (LER Output on Safety Relief Valves from 1969 to Present. Output Sorted by Facility & Event Date)
- ML103400085 + (LER Palo Verde, Unit 3 - Submittal of Special Report 3-SR-2010-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable)
- ML20052F259 + (LER Printout)
- ML20054D413 + (LER Printout on Facility Events Involving Radioactive Releases from 1976 to Present)
- ML20237F622 + (LER Quality Evaluation for Catawba Units 1 & 2 During Period from Oct 1986 - Jul 1987)
- ML20235L759 + (LER Quality Evaluation for Peach Bottom Units 2 & 3 During Feb 1986 - May 1987)
- ML20238A696 + (LER Quality Evaluation for Summer During Period Jan 1986 - Jul 1987)
- ML20052F417 + (LER Reporting Sys)
- L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation + (LER Special Report Regarding Accident Monitoring Instrumentation)
- ML20085F479 + (LER UE-1-75:on 750228,three Procedural Deficiencies Re Review of Design Changes & Documentation Detected During Mods to Sys Associated W/Postulated High Energy Line Breaks Outside Containment)
- ML20058L541 + (LER Update Rept M-RO-77-33.On 771031,number 15 Bus Auto Transfer Malfunctioned.Caused by Use of Incorrect Const Prints)
- 05000259/LER-1985-038, LER Will Not Be Prepared Under 50-259/85038.Info to Have Been Included in Rept Incorporated as Rev to BFRO-50-259/85036 R1 + (LER Will Not Be Prepared Under 50-259/85038.Info to Have Been Included in Rept Incorporated as Rev to BFRO-50-259/85036 R1)
- ML090700553 + (LER for Palo Verde, Units 1 and 3, Regarding Special Reports 1-SR-2009-001-00, 3-SR-2009-001-00 on Fuel Building Ventilation System High Range, Radioactive Gaseous Effluent Monitor Inoperable)
- L-2009-097, LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours + (LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours)
- ML100431305 + (LER from Us Dept. of Defense, Armed Forces Radiobiology Research Institute Occurred on 03/16/09)
- 05000237/LER-1976-032-03, LER on 760512:malfunction of Drive Brakes on Reactor Bldg Crane Special Slow Speed Hoist Caused Reactor Vessel Head to Slip.Caused by Undersized Brake Release Solenoid Which Prevented Full Engagement of Hoist Brakes + (LER on 760512:malfunction of Drive Brakes on Reactor Bldg Crane Special Slow Speed Hoist Caused Reactor Vessel Head to Slip.Caused by Undersized Brake Release Solenoid Which Prevented Full Engagement of Hoist Brakes)
- ML101130451 + (LER, Limerick, Units 1 and 2, Special Report - Seismic Monitoring Instrumentation Inoperability)
- ML100700556 + (LER, Oconee, Units 1, 2, & 3, Submittal of 30-Day Report Pursuant to Ground Water Protection Initiative and Ground Water Monitoring Wells GM-7R and GM-7DR)
- SBK-L-15183, LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days + (LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days)
- L-2010-139, LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B + (LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B)
- L-2010-061, LER, St. Lucie, Units 1 & 2, Submittal of Unusual Environmental Event Report on Turtle Mortality + (LER, St. Lucie, Units 1 & 2, Submittal of Unusual Environmental Event Report on Turtle Mortality)
- L-2010-235, LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable + (LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable)
- ML082100448 + (LER, Virgil C. Summer, Special Report 2008-004 on Inoperability of the Plant Vent High Range Radiation Monitor RMA00131 for Greater than 72 Hours)
- 05000318/LER-1982-021-03, LER-021/03L-0:on 820714,22B Safety Injection Tank Pressure Found Decreased to 197 Psig on 820427.Caused by Loop Isolator Failure.Isolator Replaced + (LER-021/03L-0:on 820714,22B Safety Injection Tank Pressure Found Decreased to 197 Psig on 820427.Caused by Loop Isolator Failure.Isolator Replaced)
- 05000304/LER-1978-022-03, LER-022/03X-1 on 780222:grab Samples Not Obtained from 4 Tech Spec Rad Monitors Which Were Inoperable.Caused by Personnel Error + (LER-022/03X-1 on 780222:grab Samples Not Obtained from 4 Tech Spec Rad Monitors Which Were Inoperable.Caused by Personnel Error)
- 05000366/LER-1979-039-01, LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent + (LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent)
- ML043450377 + (LER-04-S01-00 for Peach Bottom Atomic Power Station (PBAPS) Unit 2 and Unit 3, 60 Day Security Event Report 2-04-S01)
- 05000321/LER-1979-069-03, LER-069/03L-0:on 790822,during Spray/Sprinkler Valve Checks, Only One Fire Pump Was Operable.Caused by Inadequate Procedures.Procedures Revised + (LER-069/03L-0:on 790822,during Spray/Sprinkler Valve Checks, Only One Fire Pump Was Operable.Caused by Inadequate Procedures.Procedures Revised)
- 05000316/LER-1982-082-03, LER-082/03L-0:on 821007,during Test on Fire Protection Carbon Dioxide Sys,Weld Leak Developed on One Leg of 4-inch Tee Fitting.Caused by Defective Weld.Weld Repaired & Inspected + (LER-082/03L-0:on 821007,during Test on Fire Protection Carbon Dioxide Sys,Weld Leak Developed on One Leg of 4-inch Tee Fitting.Caused by Defective Weld.Weld Repaired & Inspected)
- 05000325/LER-1982-054-03, LER82-054/03L-0:on 820607,reactor Core Isolation Cooling Sys Turbine Automatically Started on Reactor Low Level,But Tripped Due to Closure of Control Valve 1-E51-V9.Caused by Lack of Turbine Speed Demand Signal Due to Govern + (LER82-054/03L-0:on 820607,reactor Core Isolation Cooling Sys Turbine Automatically Started on Reactor Low Level,But Tripped Due to Closure of Control Valve 1-E51-V9.Caused by Lack of Turbine Speed Demand Signal Due to Governor Failure)
- 05000280/LER-1983-043-03, LER83-043/03L-0:on 830914,following Reactor Trip,Flow Control Valve (FCV) Failed to Close Upon Receipt of Feedwater Isolation Signal.Caused by Malfunctioning Solenoid Valve & FCV-1488 Restricted by Antirotation Device + (LER83-043/03L-0:on 830914,following Reactor Trip,Flow Control Valve (FCV) Failed to Close Upon Receipt of Feedwater Isolation Signal.Caused by Malfunctioning Solenoid Valve & FCV-1488 Restricted by Antirotation Device)
- 05000260/LER-1980-042-03, LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested + (LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested)
- 05000263/LER-2002-001-01, LERs 02-001-01 & 02-002-01 for Monticello Nuclear Generating Plant Re Mechanical Pressure Regulator Failure Causes Reactor Scram & Application of Instrument Deviation Acceptance Criteria Allowed As-Found Settings to Be Outsi + (LERs 02-001-01 & 02-002-01 for Monticello Nuclear Generating Plant Re Mechanical Pressure Regulator Failure Causes Reactor Scram & Application of Instrument Deviation Acceptance Criteria Allowed As-Found Settings to Be Outside Tech Spec Val)