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 Issue dateTitleTopic
0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With11 December 1998LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With
1CAN099401, LER 94-V01-00:on 940804,functional Test Procedure for Hydrogen Analyzer Was Not Adequate to Alert Plant Personnel.Caused by Personnel Oversight.Functional Test Procedure Has Been Revised7 September 1994LER 94-V01-00:on 940804,functional Test Procedure for Hydrogen Analyzer Was Not Adequate to Alert Plant Personnel.Caused by Personnel Oversight.Functional Test Procedure Has Been Revised
05000368/LER-1990-01530 July 1990LER 90-015-00:on 900628,channel Functional Tests for Logarithmic Power Level Nuclear Instrumentation Found to Be Inadequate.Caused by Personnel Error Re Plant Procedure Development.Plant Startup Procedure revised.W/900730 LtrTime of Discovery
Fuel cladding
05000368/LER-1990-01427 July 1990LER 90-014-00:on 900626,reactor Trip Occurred from Approx 30% Rated Thermal Power on Low Departure from Nucleate Boiling Ratio.Caused by Erroneous Indication Received by Control Element Assembly Calculator 1.W/900727 Ltr
05000313/LER-1990-0042 July 1990LER 90-004-00:on 900531,degraded Fire Barrier Penetration Seal Discovered in 2-inch Metal Sleeve Through Floor Slab & Conduit Contained within Sleeve.Caused by Personnel Oversight.Fire Barrier Sealed & Log updated.W/900702 LtrFire Barrier
Fire Watch
05000368/LER-1990-01329 June 1990LER 90-013-00:on 900530,degraded Fire Barrier Penetration Discovered During Routine Tour of Auxiliary Bldg.Caused by Improper Sealing of Penetration While in Breached Condition. Fire Barrier Sealed & Personnel counseled.W/900629 LtrFire Barrier
Fire Watch
05000368/LER-1990-01125 May 1990LER 90-011-00:on 900425,discovered That post-accident Hydrogen Analyzers Did Not Appear Independent Due to Sharing Common Nitrogen Bottle Supplies.Caused by Design Oversight. Plant Mod Re Nitrogen Supplies initiated.W/900525 LtrTime of Discovery
05000368/LER-1989-02225 May 1990LER 89-022-02:on 891114,4,160-volt Ac ESF Electric Bus Unexpectedly Deenergized During post-maint Testing on Auxiliary Relay.Caused by Inadequate Test Controls.Job Order Changed to Include Test switch.W/900525 Ltr
05000368/LER-1950-368, :on 860722,while Conducting Routine Plant Tour, Fire Watch Personnel Found Asleep at Fire Watch Stations. Fire Watch Personnel Replaced.Similar Event Reported in LER 50-368/83-04329 August 1986
on 860722,while Conducting Routine Plant Tour, Fire Watch Personnel Found Asleep at Fire Watch Stations. Fire Watch Personnel Replaced.Similar Event Reported in LER 50-368/83-043
Time of Discovery
Fire Barrier
Continuous fire watch
Fire Watch
05000368/LER-1986-006, Corrected LER 86-006-00:on 860421,reactor Protective Sys Actuated on Two of Four Core Protection Circulator Channels. Caused by Electrical Noise from Starting Reactor Coolant Pump.Channel C Circuit Card Replaced30 May 1986Corrected LER 86-006-00:on 860421,reactor Protective Sys Actuated on Two of Four Core Protection Circulator Channels. Caused by Electrical Noise from Starting Reactor Coolant Pump.Channel C Circuit Card Replaced
05000368/LER-1979-026, Oversize Updated LER 79-026/03X-1:on 790323,fire Dampers Not Installed Per Design Specs.Caused by Installation Qa.Fire Dampers Cited Installed as Required.Aperture Card Available in PDR7 June 1984Oversize Updated LER 79-026/03X-1:on 790323,fire Dampers Not Installed Per Design Specs.Caused by Installation Qa.Fire Dampers Cited Installed as Required.Aperture Card Available in PDRContinuous fire watch
05000313/LER-1983-023, Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being Developed20 December 1983Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being DevelopedBoric Acid
Fire Barrier
Fire Protection Program
Fire Watch
05000368/LER-1983-045, Revised LER 83-045/03X-4:on 830916-1123,fire Protection Deficiencies Identified.Cause & Corrective Actions Listed16 December 1983Revised LER 83-045/03X-4:on 830916-1123,fire Protection Deficiencies Identified.Cause & Corrective Actions ListedFire Barrier
Fire Protection Program
Fire Watch
05000368/LER-1983-020, Telecopy LER 83-020/01T-0:on 830519,fire Watch Posted in Wrong Location for Period Exceeding Tech Spec Limit.Further Details Will Be Provided19 May 1983Telecopy LER 83-020/01T-0:on 830519,fire Watch Posted in Wrong Location for Period Exceeding Tech Spec Limit.Further Details Will Be ProvidedFire Watch
05000313/LER-1983-007, Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure19 April 1983Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure
ML20064H92419 December 1978/03L-0 on 781129:Chilled Water Return Containment Isolation valve,2CV3850-2,was Taken Out of Svc to Repair Control Room Communication Breaker Contacts.Breaker Was Changed to Type AB Contacts
ML20147H44419 December 1978/03L-0:on 781121,borated Water Storage Tank Boron Concentration Fell Below Tech Specs Limit.Caused by Open Condensate Valve CS-38.Valve Closed Increasing Boron Concentration
ML20064H90719 December 1978/03L-0 on 781128:both Doors of the Personnel Hatch Doors Were Simultaneously Opened,Caused by a Sheared Mechanical Door Interrlock Gear Key.Mechanical Interlock Repairs Made & Containment Air Lock Declared Operable
ML20064J1747 December 1978/03L-0 on 781109:during Mode 3 Oper,Emergency Diesel Generator B Tripped from 100% Load.Caused by Damage to Rod & Main Bearings,Crankshaft & Pistons,Perhaps Due to Loose Baseplate Mounting Screw
ML20064E95820 November 1978/01T-0 on 781107:received Notice That Speed Switch Made by Dynalog Corp Had Design Problem That Could Cause Failure.Speed Switch Replaced
ML20064E95620 November 1978/03L-0 on 781107:during Post-Core Hot Functional Testing B Condensate Storage Tank Dropped Below Tech Spec Minimum.Caused by Inability of Makeup Plants to Produce High Demand for Condensate
ML20064E96120 November 1978/01T-0 on 781107:during Mode 3 Oper,Noted That First Cycle Plant Protec Sys Setpoint Changes Req by Rosemont Pressure Transmitter Substitution Were Less than Conservative.Caused by Failure to Change Setpoint
ML20064E97220 November 1978/01T-0 on 781108:technician Installed Replacement Speed Switch in B Emergency Diesel Generator W/O Having Job Order Approved by Shift Supervisor.Due to Forgetfulness of Instru Technician
ML20064F10216 November 1978/01T-0 on 781102:during Post-Core Hot Functional Test,Prior to Initial Criticality Mode 3 Oper,Lift Setpoints of Main Steam Line Code Safety Valves Were Nonconservative. Caused by Incorrect Identification of Simmer Point
ML20064E5473 November 1978/03L-0 on 781006:during Post-Core Hot Functional Test,Prior to Initial Criticality,Mode 3 Oper,Emergency Feedwater Valve 2CV-1025-1,hydraulic Pump Motor Failed. Motor Was Replaced & Tested Successfully
ML20064E5291 November 1978/03L-0 on 781005:During Post-Core Hot Functional Testing,Pressurizer Code Safety Valve Was Gagged to Eliminate Weepage.Weepage Occurred Following Corrective Maintenance.Valve Was Allowed to Cool & Proper Oper Proved
ML20204B4176 October 1978/01T-0:on 780925,during Surveillance Test,Control Rod Driveline Breaker a Failed to Trip on First Attempt. Caused by Trip Mechanism Mechanical Arm Being Out of Adjustment.Arm Adjustment Corrected