Category:Licensee Event Report (LER)

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• 05000003/LER-2008-001, Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error
• 05000016/LER-2008-001, Enrico Fermi, Unit 1 Re Corrective Action Program
• 05000029/LER-2021-001, Compensatory Measure Not Established for a Momentary I/O Board Communication Loss
• 05000049/LER-2021-001, Reactor Scram Due to Main Power Transformer Failure
• 05000133/LER-2004-001-01, Three Missing Fuel Rod Segments
• 05000133/LER-2004-001-02, Re Three Missing Fuel Rod Segments
• 05000133/LER-2005-001, Regarding Missing In-core Detectors
• 05000133/LER-2005-001-01, Re Missing Incore Detectors
• 05000133/LER-2010-001, Regarding Lost Radioactive Calibration Standard
• 05000146/LER-2003-001, Failure to Verify Operability of the Containment Vessel Intrusion Alarm
• 05000146/LER-2003-002, Re Failure of the Decommissioning Support Facility Intrusion Alarm
• 05000155/LER-2023-001, Human Performance Error Resulted in Compensatory Measures Not Properly Employed
• 05000186/LER-1917-005, University of Missouri-Columbia Research Reactor Regarding a Deviation from Technical Specification 3.5.a.3 and Its Associated Note (1)
• 05000186/LER-1919-005, Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specifications 3.2.a and 3.2.f.8
• 05000186/LER-2003-001, Curators of University of Missouri Re Instrument Malfunction That Occurred on 05/18/03
• 05000186/LER-2004-001, The Missouri University Research Reactor Regarding a Valve Mis-Positioning Event Discovered on 01/16/04
• 05000186/LER-2005-001, University of Missouri - Columbia Regarding Airlock Door Malfunction That Occurred on 03/10/2005
• 05000186/LER-2005-002, Missouri University Research Reactor Regarding a Deviation from Technical Specification 3.6.e
• 05000186/LER-2007-001, The University of Missouri Research Reactor Regarding Failure of Regulating Blade to Be Operable During Reactor Operation Resulting in a Deviation from Technical Specifications 3.2.a and 3.4.c
• 05000186/LER-2007-002, University of Missouri - Columbia Research Reactor, Re Written Communication as Required by the University of Missouri Research Reactor Technical Specification 6.1.h (2) Regarding a Deviation from Technical Specification 3.10.a
• 05000186/LER-2008-001, University of Missouri Research Reactor a Deviation from Technical Specification 3.10.b on 01/24/2008
• 05000186/LER-2008-002, University of Missouri - Columbia Research Reactor Re Written Communication as Required by the University of Missouri Research Reactor Technical Specification 6.1.h (2) Regarding a Deviation from Technical Specification 3.5.a
• 05000186/LER-2012-002, Letter Written Communication as Required by the University of Missouri Research Reactor Technical Specification 6.1 .h(2) Regarding a Deviation from Technical Specification 3.10.b
• 05000186/LER-2013-003, University of Missouri-Columbia Research Reactor - Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.1.h(2) Regarding a Deviation from Technical Specifications 3.2.b
• 05000186/LER-2014-003, University of Missouri-Columbia Regarding a Deviation from Technical Specifications 3.2.a
• 05000186/LER-2019-001, For University of Missouri, Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.3.a(l)
• 05000186/LER-2019-002, Univ. of Missouri Research Reactor, Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.a
• 05000186/LER-2019-004, University of Missouri-Columbia Research Reactor - Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.4
• 05000186/LER-2019-006, For University of Missouri-Columbia Research Reactor, on 12/10/2019 with Reactor Operating at 10 MW in Automatic Control Mode, Channel 4, 5 or 6 Downscale Annunciation Was Received
• 05000186/LER-2019-007, For University of Missouri-Columbia Research Reactor, on 12/09/2019, with Reactor Operating at 10 MW in Automatic Control Mode, Channel 4, 5 or 6 Downscale Annunciation Was Received
• 05000186/LER-2020-001, For University of Missouri-Columbia Research Reactor, Deviation from MURR Technical Specifications 3.2.a and 3.2.f.8
• 05000186/LER-2020-002, Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.f.8
• 05000186/LER-2021-004, University of Missouri Research Reactor, Deviation from Technical Specification 3.2.g.10
• 05000186/LER-2023-003, University of Missouri - Columbia Research Reactor, Written Communication as Required Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.b
• 05000186/LER-2024-001, Written Communication as Required by by LER 2024-001-00 for University of Missouri Research Reactor Technical Specification 6.6.c(3) Re Deviation from Technical Specification 3.1 0.d
• 05000186/LER-2024-003, University of Missouri Research Reactor, Specification Deviation from Technical Specification 3.2.g.21
• 05000206/LER-2018-001, Independent Spent Fuel Storage Installation, Spent Nuclear Fuel Canister Temporarily Wedged in Dry Cask Storage Container
• 05000219/LER-1917-002, Regarding Manual Scram Due to Degraded Main Condenser Vacuum
• 05000219/LER-1917-003, Regarding Automatic Scram While Subcritical Due to Low Reactor Level
• 05000219/LER-1917-005, Regarding Failure of the Emergency Diesel Generator 2 During Surveillance Testing Due to a Broken Electrical Connector
• 05000219/LER-2001-001, Re Reactor Shutdown Completion Required by Technical Specifications
• 05000219/LER-2002-001, Plant Operations Outside of Technical Specifications Due to a Degraded System
• 05000219/LER-2002-002, Local Leak Rate Test Results in Excess of Technical Specification Limits
• 05000219/LER-2002-003, Re Insufficient Appendix R Separation Criteria Due to Sand Erosion
• 05000219/LER-2003-001, Regarding License Violation Due to Security Officers Inattentive to Duty
• 05000219/LER-2003-002, For Oyster Creek Unit 1 Regarding Completion of Reactor Shutdown Required by Tech Specs Due to a Cable Fault
• 05000219/LER-2003-003, Regarding Actuation of Reactor Protection System Due to Grid Transient
• 05000219/LER-2003-004, Actuation of Reactor Protection System Due to Instrument Malfunction
• 05000219/LER-2004-001, Re 1 EDG Inoperable Caused by Cooling Fan Bearing Bolts Not Torqued Properly Following Preventative Maintenance Activities
• 05000219/LER-2004-002, Regarding Change in Methodology Used by General Electric and Global Nuclear Fuels to Demonstrate Compliance with Emergency Core Cooling System Performance Requirements
• 05000219/LER-2004-003, Regarding Actuation of Reactor Protection System Due to Spurious HI-HI Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference
• 05000219/LER-2004-003-01, 1 Oyster Creek, Unit 1, Regarding Actuation of Reactor Protection System Due to Spurious Hi-Hi Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference
• 05000219/LER-2004-004, Regarding Operation in Excess of the Thermal Power Limit Due to Plant Computer Isolator Power Supply Degradation Affecting Input Values to the Heat Balance Calculation
• 05000219/LER-2004-005, Regarding Main Steam Isolation Valve Failure to Close During Partial Valve Closure Surveillance Due to Mechanical Binding
• 05000219/LER-2004-006, Regarding Local Leak Rate Test Results in Excess of Technical Specifications
• 05000219/LER-2004-007, Regarding Automatic Containment Isolation Bypassed During Reactor Startup Due to an Inadequate Procedure
• 05000219/LER-2005-001, Regarding a Control Rod Drive Pump Was Returned to Service Prior to Correcting the Cause of Failure Resulting in a Technical Specification Violation
• 05000219/LER-2005-002, Correction of Licensee Event Report Dates for LER 2005-002-00 and LER 2005-001-01
• 05000219/LER-2005-003, Re Technical Specification Violation Due to Missing Test Cap
• 05000219/LER-2005-004, Regarding Actuation of an Emergency Diesel Generator Due to Unexpected Breaker Opening
• 05000219/LER-2005-005, Re Technical Specification Violation Due to Main Steam Safety Valves Setpoints Discovered Out of Tolerance
• 05000219/LER-2006-001, Regarding Unplanned Manual Scram Inserted During Planned Reactor Shutdown to Expedite Plant Cooldown
• 05000219/LER-2006-002, Regarding Failure of MSIV Surveillance Due to Transcription Error
• 05000219/LER-2006-003, Re Local Leak Rate Test Results in Excess of Technical Specifications
• 05000219/LER-2006-004, Re Operation Exceeding Maximum Power Level
• 05000219/LER-2007-001, Automatic Reactor Scram Following Trip of Reactor Feed Pump
• 05000219/LER-2007-002, Re Intermediate Range Monitor 16 Inoperable During Startup
• 05000219/LER-2007-003, For Oyster Creek, Unit 1, Regarding Unplanned Manual Reactor Scram Following Trip of Reactor Feed Pump Due to Lowering Condenser Vacuum
• 05000219/LER-2008-001, Automatic Reactor Shutdown Caused by Main Transformer Failure
• 05000219/LER-2009-001, Automatic Reactor Shutdown Caused by Main Transformer Failure
• 05000219/LER-2009-002, Failure to Take the Appropriate Tech Spec Action When Primary Containment Isolation Valve Became Inoperable
• 05000219/LER-2009-003, Regarding Manual Reactor Shutdown Caused by Loss of Cooling to the Main Transformer
• 05000219/LER-2009-004, Regarding Establishment of Secondary Containment Boundary Contrary to Technical Specification Requirements
• 05000219/LER-2009-005, Regarding Reactor Scram Following a Transmission Line Lightning Strike
• 05000219/LER-2009-006, Regarding EDG 1 Inoperable Due to Failure of Its Output Breaker to Close
• 05000219/LER-2010-001, Regarding Automatic Start of Emergency Diesel Generator Due to Unexpected Trip of the Id Bus Normal Feed Beaker
• 05000219/LER-2010-002, For Oyster Creek, Regarding Automatic Reactor Scram During Startup Due to Low Main Condenser Vaccum
• 05000219/LER-2011-001, For Oyster Creek Nuclear, Unit 1, Regarding Changes and Errors in the Methodology Used by General Electric-Hitachi to Demonstrate Compliance with 10 CFR 50.46 Acceptance Criteria
• 05000219/LER-2012-001, Regarding Reactor Scram Following a Transmission Line Trip
• 05000219/LER-2012-001-01, Regarding Reactor Scram Following a Transmission Line Trip
• 05000219/LER-2012-002, Regarding Loss of Offsite Power During Hurricane Sandy
• 05000219/LER-2012-002-01, Regarding Loss of Offsite Power During Hurricane Sandy
• 05000219/LER-2012-003, Regarding Indications Identified in the Control Rod Drive Return Nozzle (N9)
• 05000219/LER-2012-003-01, Regarding Control Rod Drive Return Nozzle Weld NC-4-1A PT Indications at N9
• 05000219/LER-2012-004, Regarding MCR HVAC System Technical Specification Violation
• 05000219/LER-2013-001, Regarding Automatic Reactor Scram Due to an Invalid Intermediate Range Monitor (IRM) Scram Signal
• 05000219/LER-2013-002, Regarding Manual Scram Due to Lowering Vacuum
• 05000219/LER-2013-003, Regarding Secondary Containment Integrity Momentarily Declared Inoperable
• 05000219/LER-2013-004, Regarding Manual Scram Due to Rise in Reactor Pressure During Turbine Valve Testing
• 05000219/LER-2013-005, Regarding Reactor Protection System (RPS) Actuation with the Reactor in Hot Shutdown
• 05000219/LER-2014-001, Regarding Manual Scram Due to Lowering Vacuum
• 05000219/LER-2014-003, Regarding Technical Specification Prohibited Condition Caused by Emergency Diesel Generator Inoperable for Greater than Allowed Outage Time
• 05000219/LER-2014-004, Regarding Local Leak Rate Test Results in Excess of Technical Specifications
• 05000219/LER-2014-005, Regarding Secondary Containment Declared Inoperable
• 05000219/LER-2014-006-01, Regarding Reactor Scram Due to Decreasing Reactor Water Level
• 05000219/LER-2015-001, Regarding Reactor Scram Due to EPR Failure During MPR Troubleshooting
• 05000219/LER-2015-002, Regarding Reactor Scram Due to Digital Protective Relay System Lockout
• 05000219/LER-2015-003, Regarding Failure of the No. 1 Emergency Diesel Generator to Start During Surveillance Testing
• 05000219/LER-2016-001, Regarding Failure of the 1 Emergency Diesel Generator During Surveillance Testing Due to a Cooling Water System Leak
• 05000219/LER-2016-002, Regarding Control Rod Drive Cooling Water System Isolation Scram Time Testing Not Performed
• 05000219/LER-2016-003, Regarding Manual Scram Inserted Due to Leakage from the D Reactor Recirculation Pump Seal
• 05000219/LER-2016-004, Regarding Technical Specification Violation Due to Main Steam Safety Valve Setpoint Discovered Out of Tolerance
• 05000219/LER-2016-005, Regarding Technical Specification Prohibited Condition Caused by One Electromatic Relief Valve Inoperable for Greater than Allowed Outage Time
• 05000219/LER-2017-001, Regarding Automatic Scram Due to APRM High Flux During Turbine Value Testing
• 05000219/LER-2017-004-01, 1 for Oyster Creek Nuclear Generating Station Regarding Reactor Protection System Channel Disabled During Test Box Use
• 05000219/LER-2018-001, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings
• 05000219/LER-2022-001, Compensatory Measures Not Implemented Per Sites Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure
• 05000220/LER-1917-002, Regarding Manual Reactor Scram Due to Pressure Oscillations
• 05000220/LER-1917-003, Regarding Automatic Reactor Scram Due to Reactor Vessel Low Water Level
• 05000220/LER-1975-039, For Nine Mile Point Unit 1 Regarding Failure to Perform the Weekly Stack Cartridge Analysis for 11/23/1975 - 11/29/1975
• 05000220/LER-1977-012, And LER 77-012-00 for Nine Mile Point Unit 1 Regarding Discovery of Discharge Pressure Switch in 12 Feedwater Pump Discharge Failed in the Closed Position and Regarding Discovery of Contacts on Relay for MSIV Isolation
• 05000220/LER-1977-020, And LER 77-020-00 for Nine Mile Point Unit 1 Regarding Discovery of Two Containment Oxygen Sampling System Check Valves Indicating Leakage in Excess of Single Valve Technical Specifications
• 05000220/LER-1977-021, Regarding Discovery of Sodium Valve for Liquid Effluents Exceeded the Limit of 1.5 Pmm and LER 77-021-00 Relating to the Stack Sample Pump Being Out of Service for 9 Hours 20 Minutes Due to
• 05000220/LER-1977-022, For Nine Mile Point Unit 1 Regarding Discovery of Linear Indications on Three Collet Retainer Tubes in Drive Mechanisms Removed from the Reactor Vessel
• 05000220/LER-1977-027, For Nine Mile Point Unit 1 Regarding Discovery of an Unacceptable Linear PT Indication in the Pipe at the Safe End to Pipe Weld Joint
• 05000220/LER-1977-028, For Nine Mile Point Unit 1 Regarding Failure of a Reactor Low Water Level Instrument to Trip When Tested
• 05000220/LER-1977-029, 77-030-00, 77-031-00, 77-034-00, & 77-035-00 for Nine Mile Point Unit 1 Low-Low-Low Level Set Point Out of Specs on RE-18A, Vacuum Switch Trip & Reset Point on Torus Relief Valves Out of Specs, Weld Leak in Emergency Condenser
• 05000220/LER-1977-032, For Nine Mile Point Unit 1 Regarding a Water Phase Material Sample in the Reactor Vessel Inspection Lapse During Refueling
• 05000220/LER-1978-001, Submittal of Licensee Event Report LER 78-01 Concerning Delta Temperature of the Discharge Water Exceeded Environmental Tech. Spec
• 05000220/LER-1978-003, Regarding Drywell High Pressure Switch RE04A Setpoint Drift and LER 78-003-00
• 05000220/LER-1978-005, And LER 78-005-00 for Nine Mile Point, Unit 1 Re During Unit Shutdown, Reserve Power Breaker on Power Board II Failed to Close in After Loss of Normal Power and During Plant Outage While Marking Up Outside MSIV 01-03 Discovered
• 05000220/LER-1978-006, Re During Steady State Operation, Performance of Surveillance Test IC-75 Found a Trip Setpoint of 22.5 Inches Water on One Vacuum Switch in the Vacuum Relief System from the Pressure Suppression Chamber to the
• 05000220/LER-1978-009, And LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections
• 05000220/LER-1978-009-01, For Nine Mile Point Unit 1 Regarding Replacement of Explosive Charges in the TIP Shear Valves with New Charges and the Resulting Unsatisfactory Ohmmeter Continuity Test for Acceptable Electric Contact
• 05000220/LER-1978-013, And LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2
• 05000220/LER-1978-014, LERs 78-014,00, 78-016-00, and 78-016-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump on 102 D/G Would Not Fill the Day Tank, Discovery of RE18C with a Setpoint of 129 Inches Wc, and
• 05000220/LER-1978-015, And LER 78-015-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump in 102 D/G Would Not Fill the Day Tank and Discovery That 12 Control Room Air Treatment Fan Would Not Run
• 05000220/LER-1978-018, For Nine Mile Point Unit 1 Regarding Discovery of Main Steam High Flow Switch with a Setpoint of 106.2 PSI, Which Is Above the Technical Specification
• 05000220/LER-1978-019, For Nine Mile Point Unit 1 Regarding Discovery That Hydraulic Snubber 31-HS-1 Had Failed and Was Empty of Hydraulic Fluid and Disconnected from Its Anchor at the Feedwater Pipe
• 05000220/LER-1978-020, LERs 78-020-00, 78-021-00, 78-022-00, and 78-023-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE18A with a Setpoint of 135 Inches Wc, Discovery of RE04A and RE04B with a Setpoint of 3.65 PSIG, Discovery o
• 05000220/LER-1978-024, For Nine Mile Point Unit 1 Regarding Discovery That Test N1-St-Q2,4,5,7,8,9, and 10 Had Not Been Performed During a Review of Quarterly Surveillance Test Results
• 05000220/LER-1978-025, LERs 78-025-00, 78-026-00, and 78-027-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE04D with a Setpoint of 3.70 PSIG, Discovery of Numerous Small Leaks in Small Sample and Instrument Pipes, and Discovery
• 05000220/LER-1978-028, For Nine Mile Point Unit 1 Regarding Discovery of the Allowable Test Interval of TS 4.1.4c for the Core Spray Power-Operated Valves Had Been Exceeded
• 05000220/LER-1978-029, Regarding Discovery of High Drywell Pressure Switches RE04A, RE04B, and RE04C with Setpoints Less Conservative than the Technical Specifications
• 05000220/LER-1978-030, 78-031-00, and 78-032-00 for Nine Mile Point Unit 1 Regarding, Respectively, Unavailability of Feedwater Pump 29-03 While Its Pump Seals Were Replaced, Unavailability of Liquid Poison Pump NP02A While a Frozen Valve
• 05000220/LER-1978-034, Regarding an Environmental Contractor Obtaining 22 Hourly Fish Impingement Samples, and One Two-Hour Sample, Which Is Contrary to the Technical Specification Requiring 24 Hourly Samples
• 05000220/LER-2002-001, Kilovolt Offsite Power Inoperable Due to Low Voltage on Line 4 and Line 1 Out of Service
• 05000220/LER-2002-002, Re Loss of One Control Rod Drive Pump Train Due to Circuit Breaker Failure
• 05000220/LER-2002-003, Loss of Power to Reactor Protection System (RPS) Bus 12 While RPS Bus 11 Emergency Power Source Was Inoperable
• 05000220/LER-2003-001, From Nine Mile Point, Unit 1 Regarding TS Cooldown Rate Exceeded During Required Cooldown for a Failed Solenoid Actuated Pressure
• 05000220/LER-2003-002, Regarding Reactor Scram Due to Electric Grid Disturbance
• 05000220/LER-2003-003, Regarding Automatic Initiation of Emergency Diesel Generator 103 Due to Momentary Loss of Offsite Power
• 05000220/LER-2003-004, Regarding Unplanned Inoperability of Emergency Cooling System Caused by Inadequate Review of Clearance for Replacement of Instrumentation Relay
• 05000220/LER-2004-001, Re Manual Reactor Scram and Cooldown Rate Exceeding Technical Specification Limits Due to Electrometric Relief Valve Failure to Close
• 05000220/LER-2004-002, Regarding Changes and Errors in the Methodology Used by General Electric and Global Nuclear Fuel to Demonstrate Compliance with Emergency Core Cooling System Performance Requirements
• 05000220/LER-2004-003, Re Inadequate Environmental Qualification Barrier Considerations Resulting in an Unanalyzed Condition
• 05000220/LER-2004-004, Regarding Manual Reactor Scram Due to Failure of 13 Feedwater Flow Control Valve Positioner
• 05000220/LER-2005-001, Regarding Automatic Reactor Scram Due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch
• 05000220/LER-2005-002, Re Fuel Moved with an Inoperable Source Range Monitor Due to Human Error Resulting in a Technical Specification Violation
• 05000220/LER-2005-003, Regarding Automatic Reactor Scram During Surveillance Testing Due to Inadvertently De-energizing 4160 Vac Power Board 11
• 05000220/LER-2005-004, Re Operation Prohibited by Technical Specifications Due to Unrevealed Inoperability of One Off-Site Power Source
• 05000220/LER-2006-001, Re Technical Specification Required Shutdown Due to Increased Drywell Leakage
• 05000220/LER-2006-002, Re HPCI Logic Actuation Due to Turbine Trip
• 05000220/LER-2008-001, Loss of Offsite Power Due to an Equipment Malfunction
• 05000220/LER-2008-002, Manual Reactor Scram Due to Loss of Reactor Pressure Control
• 05000220/LER-2008-003, Power Supplies for Drywell Pressure Indication Not Qualified for Required Post-Accident Operating Duration
• 05000220/LER-2009-001, Failure to Implement Required Technical Specification Actions Associated with Failed Surveillance Test
• 05000220/LER-2009-002, High Pressure Coolant Injection System Initiation Following a Manual Turbine Trip Due to High Turbine Bearing Vibrations
• 05000220/LER-2009-003, Regarding Manual Scram and High Pressure Coolant Injection Following a Loss of Feedwater Level Control Due to Firmware Deficiency
• 05000220/LER-2010-001, Regarding Reactor Scram Due to Inadequate Post Maintenance Testing
• 05000220/LER-2011-001, For Nine Mile Point, Unit 1 Turbine Trip Due to Oil Pressure Fluctuations to the Turbine Master Trip Solenoid
• 05000220/LER-2011-002, For Nine Mile Point, Unit 1, Regarding Changes and Errors in the Methodology Used by GE Hitachi to Demonstrate Compliance with 10 CFR 50.46 Acceptance Criteria
• 05000220/LER-2012-001, Regarding Automatic Reactor Scram Due to Electronic Pressure Regulator Failure
• 05000220/LER-2012-002, Regarding Automatic Reactor Scram Due to Automatic Generator Protective Trip
• 05000220/LER-2012-003, Regarding Loss of Isolation Function on Shutdown Cooling System Suction Line Due to an Operating Procedure Deficiency
• 05000220/LER-2012-004, Regarding Automatic Reactor Scram Due to a Generator Load Reject
• 05000220/LER-2012-005, Regarding Feedwater Level Control Failure, HPCI Initiation and Reactor Scram
• 05000220/LER-2012-006, Technical Specification Required Shutdown Due to Containment Leakage
• 05000220/LER-2012-007, Regarding High Pressure Coolant Injection System Logic Actuation Following an Automatic Turbine Trip Signal Due to High Reactor Water Level
• 05000220/LER-2013-001, Emergency Condenser 11 High Steam Flow Isolation Instrumentation Loss During Plant Startup
• 05000220/LER-2013-002, Regarding Unanalyzed Condition Caused by Unfused Control Room DC Ammeters
• 05000220/LER-2014-001, Regarding Reportable Conditions Not Reported During the Previous 3 Years Involving Average Power Range Monitors Inoperability
• 05000220/LER-2014-002, Regarding Unanalyzed Condition Due to Unfused Motor Operated Valve Control Circuit
• 05000220/LER-2014-005, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
• 05000220/LER-2015-001, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
• 05000220/LER-2015-002, Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
• 05000220/LER-2015-003, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
• 05000220/LER-2015-004, Regarding Automatic Reactor Scram Due to Main Steam Isolation Valve Closure
• 05000220/LER-2016-001, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
• 05000220/LER-2016-002, Regarding Isolation of Both Emergency Condensers Due to Loss of UPS 1628
• 05000220/LER-2017-001, Manual Reactor Scram Due to High Turbine Vibration
• 05000220/LER-2019-001, Automatic Reactor Scram Due to High Reactor Pressure
• 05000220/LER-2019-001-01, Automatic Reactor Scram Due to High Reactor Pressure
• 05000220/LER-2019-002, Condition Prohibited by Technical Specification Due to Vacuum Breaker Not Locked Closed
• 05000220/LER-2019-003, Manual Reactor Scram Due to Pressure and Power Oscillations
• 05000220/LER-2019-003-01, Manual Reactor Scram Due to Pressure and-Power Oscillations
• 05000220/LER-2019-004, Average Power Range Monitors Declared Inoperable
• 05000220/LER-2020-001, Control Room Air Treatment System Inoperable
• 05000220/LER-2020-001-01, Control Room Air Treatment System Inoperable
• 05000220/LER-2021-002, Isolation of Both Emergency Condensers Due to Loss of UPS 162A
• 05000220/LER-2023-001, Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria
• 05000220/LER-2023-001-01, Supplement to NMP1 Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria
• 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
• 05000220/LER-2078-001, Re Delta Temperature of Discharge Water Exceeded Specification 2.1.5 of Environmental Tech Specs
• 05000220/LER-2078-003-03, Re Surveillance Test Found Main Steam High Flow Switch with Setpoint of 107.5 PSI
• 05000237/LER-1916-003, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria
• 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits
• 05000237/LER-1974-028, Regarding TIP Machine Ball Valve Failure
• 05000237/LER-1974-029, For Dresden 3 Regarding a Through-Wall Crack on Torus/Drywell Purge Line
• 05000237/LER-1974-032, Regarding High Pressure Coolant Injection High Flow Instrument Anomaly