05000272/LER-1993-006, :on 930221,station Power Transformers 12 & 22 Deenergized Due to Tripping of Common 13 Kv Ring Bus Section 4 Breakers & 500 Kv Section 1 Breakers.Caused by Inadequate Communication.Caution Tags Hung on Breakers
IA-92-382, Package Consisting of General Records Schedule 23,NRC Manual Chapter Bulletin 0231-30,NRC Manual Chapter 0231, Maint & Disposition of NRC Official Files & Records & Mgt Directive 3.53, NRC Records Mgt Program
ST-HL-AE-5481, Forwards Response to GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks, Per 10CFR50.54(f)
05000260/LER-1994-010, :on 941005,loss of ECCS Division II Instrumentation Resulting from Blown Fuse in Atu Inverter. Caused by a Failed Capacitor.Blown DC Input Fuse Was Replaced
05000331/LER-1998-003, :on 980410,invalid Esfas of Group III PCIS Was Noted.Caused by Procedure Deficiencies & Loss of Instrument AC Control Power.Revised Procedures & Reviewed Electrical Panel Labels & Associated Operating Procedures
05000245/LER-1989-003-02, :on 890323,design Deficiencies Identified on Reactor Bldg Closed Cooling Water Sys.Caused by Original Analyses Considering Closed Cooling Water Sys Piping as closed-loop Sys.Design Change Initiated
05000313/LER-1988-013, :on 880924,wire Discovered Terminated Incorrectly in 4,160-volt Ac Vital Power Supply Breaker Which Affected Automatic Starting Circuitry for HPI Pump. Cause Unknown.Wiring Error Corrected
05000266/LER-1996-016, :on 961030,discovered as-found Lift Pressure for Unit 2 Pressurizer Safety Valve 2RC-434 Exceeded Max Lift Pressure Allowed by ASME Code.Caused by Use of Ambient Temp in Test Lab.Set Valve at More Appropriate Ambient Temp
05000498/LER-1999-008, :on 990912,unit Tripped During Performance of Main Turbine Emergency Trip Test Procedures.Caused by Failure in Turbine Trip Test Circuitry.Main Control Boards Were Cleaned & Other Panels Were Inspected
05000423/LER-1998-006, Forwards LER 98-006-00,documenting Condition Determined Reportable at Unit 3 on 980115.Util Commitments in Response to Event Contained within Attachment 1 to Ltr
05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
05000336/LER-1997-037-02, :on 971126,reduced Flow to Heat Exchangers Due to Svc Water Piping Liner Matl Lodged in Strainer for Edg. Will Perform Svc Water Piping Internal Inspections to Locate Source of Piping Liner Matl & Will Perform Repairs on Lin
05000458/LER-1999-008, :on 990418,uplanned Automatic Closure of Div III DG Output Breaker Was Noted Due to Loss of Normal Power to Div III Switchgear During Testing.Caused by Personnel Error.Returned Electrical Lineup to Normal.With
05000354/LER-1999-006-01, :on 990518,unexpected Actuation of B Channel PCIS Occurred.Caused by Personnel Error.Addl Training Will Be Provided to Operations Personnel to Preclude Addl Unexpected ESF Actuations
05000409/LER-1985-019, :on 851026,partial Reactor Scram Occurred Due to Momentary Short in CRD Gas Pressure Circuit.Caused by Worn Mechanical Seal Allowing More Seal Water to Flow Through than Normal.Seal Leakage Reduced
05000245/LER-1996-058, :on 961106,discovered Postulated Tornado Missile Damage to CST Could Cause Transfer Pump House Flooding.Caused by Sys Design Oversight.Ventilation Opening to Be Secured or Modified
05000423/LER-1996-002, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual
05000361/LER-1985-022, :on 850330,during Monthly Surveillance on Pressurizer Pressure Low,Technician Removed Bypass from Channels A,C & D.Caused by Personnel Error.Technician Disciplined
05000298/LER-1995-018, :on 951121,recognized Design Bases of Steam Tunnel Blowout Panels Not Well Documented.Cause Cannot Be Established.Bulk of Fiberglass Removed from Blowout Panels
05000315/LER-1985-007-01, :on 850222,controlled Shutdown Initiated. Caused by Inoperable Control Room Emergency Ventilation Sys. Analysis of Potential Radiological Consequences of Operation at Higher Flow Rates Performed.Room Balanced
05000219/LER-1995-009, :on 960103,two APRM Were Inoperable Due to Lack of Complete Understanding of Circuitry.Addl Training on APRM Sys Provided & Quarterly Surveillance Test & Vendors Manual Revised
05000333/LER-1984-009, :on 840322,reactor Scram Occurred as Result of Low Reactor Vessel Operation.Caused by Failure of Operating Feed Pump Bearing.Plant Placed in Cold Shutdown While Repairs to Feed Pumps Completed
05000333/LER-1993-022, :on 931029,wires Between RPS Scram Contractor Were Not Installed Inside Protective Conduits.Caused by Inadequate Design & Design Review.Corrective Action:Eight Resistors Were Relocated
05000313/LER-1993-007, :on 931122,discovered Radwaste Area Effluent Flowpath Not Continuously Monitored During Release Due to Separated Sample Line Connection Resulting from Inadequate Procedural Guidance.Procedures Revised
05000333/LER-1993-014, :on 930529,discoverd Incomplete Logic Sys Functional Testing.Caused by Test Procedure Deficiencies. Surveillance Test Program Improved Plan Incorporated Into Improvement Program
05000361/LER-1982-075-03, /03L-0:on 820727,during Mode 2 Operation,Channel a Local Power Density Margin Monitor 2J1-0003-1 Failed Channel Check.Caused by Burnout of Bar Graph Display Unit within Monitor.Unit Replaced
05000263/LER-1991-016, :on 910405,discovered Failure of non-safety Isolation Valve Could Block Flow of Emergency Svc Water Through Unit Condensers.Caused by Design Inadequacy.C/A: Valve Secured in Open Position
05000282/LER-1993-009, :on 930715,receipt of Annunciator Charging Pump 12 Overload Trip Observed by CR Operators,Resulting in Unplanned Closure of Containment Isolation Valve.Standby Charging Pump Started Immediately
05000219/LER-1993-004-01, :on 930602,discovered Potential Torus Condition Outside Design Basis.Caused by Inadequate Design Info. Documentation Procedures Revised.Torus Calculations to Include Peak Pressure Info
05000499/LER-1993-010-01, :on 930526,discovered That Screen Drive Coupling on Essential Cooling Water Traveling Screen 2A Damaged.Caused by Aging of Elastomeric Element.Couplings Replaced & Preventive Maint Initiated
05000333/LER-1993-013-01, :on 930525,automatic Reactor Scram Occurred When APRM E Spiked While Indicated Water Level Approx 6%. Possibly Caused by Spiking of LPRM Input of APRM E. Radiation Sources Replaced W/Stronger Sources
05000293/LER-1993-002, :on 930225,RCIC Sys Declared Inoperable During Surveillance Testing.Caused by Galling of Valves Stem & Bonnet Chamber.Valve Stem & Bonnet Chamber Will Be Replaced & Parts Will Be Purchased Following Design
05000259/LER-1981-064-03, /03L-0:on 811027,switch 1 of Recirculation Discharge Valve Closure & Switch 2 of Cs/Rhr Valve Opening Permissive Were Outside Tech Spec Limits.Caused by Setpoint Drift.Switches Reset.Design Change Request Initiated
05000324/LER-1991-001-03, :on 910125,reactor Scram Occurred During Calibr of Feedwater Computer Point.Caused by Incorrect Procedure in Summary Sheet.Maint Procedures Reviewed & Revised
05000302/LER-1982-056-03, /03L-0:on 820827,during Normal Operation,Primary Containment Average Air Temp Exceeded 130 F Tech Spec Limit. Caused by Failure of Pneumatic Control Line for Industrial Coolers.Control Line Replaced & Coolers Returned to Svc
05000346/LER-1978-021-03, /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors
05000333/LER-1981-005-04, /04L-0:on 810112,annual Test of Offgas Automatic Isolation Not Performed as Required by Ets.Caused by Missed Surveillance Due to Conflict Between ETS & Operating Tech Specs.Surveillance Test Revised to Reflect ETS Requiremen
05000338/LER-1979-033-03, /03L-0 on 790321: C Steam Generator Narrow Range Level Indicator LI-1496 Gave Readings w/20% Disagreement W/Two Other Channels.Caused by Steam Leak in One Sensing Line Isolation Valve
05000333/LER-1978-097-01, /01X-1 on 781215:during Instrument Surveillance Procedure F-ISP 10,the 8 Temp Switches Associated W/ Isolation of HPCI Sys Steam Line Were Set Above Tech Spec Limits.Caused by Use of Wrong Conversion Table
05000312/LER-1979-015-03, /03L-0:on 791031,A/E Informed Util That as-built Configuration of Line 47360-10 Inch,When Seismically Reanalyzed,May Result in Pipe Support Overstress.Caused by Nonconformance of Const Drawings.New Support Installed
05000280/LER-1992-006-02, :on 920424,determined That Three Snubbers Did Not Satisfy One Acceptance Criteria of TS 4.17.E.1a. Caused by Personnel Error.No Immediate Action Necessary
05000280/LER-1991-006-01, :on 910419,AFW Pump 2-FW-P-3B Rendered Inoperable Due to Drawing Error.Pump Suction Line Plug Removed from Ecst,Satisfactorily Tested & Returned to Svc
05000280/LER-1990-006-01, :on 900701,station Svc Transformer Tripped Due to Actuation of Sudden Pressure Relay.Caused by Grounded Terminal in Sudden Pressure Relay Connector.Emergency & Abnormal Procedures Implemented
05000280/LER-1989-039, :on 891114,steam Generator a Header to Line Differential Pressure Input to Safety Injection Inoperable. Caused by Malfunctioning Relay Contact.Leads Removed from Contacts & Placed on Spare Contacts on Relay
05000280/LER-1989-027, :on 890815,containment Gaseous Radiation Monitor Momentarily Increased Above Alarm Setpoint,Resulting in Closure of Containment Instrument Air Compressor Valves. Caused by Increase in Airborne Concentration
05000281/LER-1993-006-03, :on 931115,Unit 2 Experienced Automatic Reactor Trip.Caused by Electrical Circuit Failure.Electrical Failure Traced to Defective Circuit Breaker & Replaced
05000272/LER-1979-066-03, /03L-0:on 791003,during Refueling Outage,Readings Showed Meteorological Instruments Inoperable.Apparently Caused by Lightning Strike Resulting in Induced Current in Rain Gauge Sensor,Removing Power from Sensors
05000255/LER-1988-008, :on 880512,containment Penetration Declared Inoperable Due to Failure to Complete Required Local Leak Rate Test within Prescribed Time Limitation.Caused by Data Entry Error.Test Schedule Verified
05000260/LER-1991-012, :on 910519,unplanned ESF Actuation Occurred Following Reactor Protection Sys Bus Deenergization.Caused by Random Equipment Failure.Failed RPS MG Set Motor Removed & Replaced
05000260/LER-1978-023-03, /03L-0 on 781211:reactor High Pressure Switches Ps-3-204A&B Exceeded Tech Spec Limits When Static-O-Ring 9N-AA45-(x9)-TT Pressure Switch Drifted Out of Tolerance
05000315/LER-1978-062-03, /03L-0:on 781107,Unit 1 AB Diesel Declared Inoperable Following Inadvertent Removal of Circuit Board Card from Diesel Voltage Regulator Circuitry.Removal Caused by Technician Snagging the Board on Clothing
05000528/LER-1990-010, :on 901012,ESF Actuation Caused by Calibr Step Omission in Work Document
05000397/LER-1991-013, :on 910507,non-compliances W/Tech Specs Identified as Part of Program of Surveillance Procedure Verification.Further Evaluation Performed.Quality Action Team to Be Chartered to Evaluate Program
05000397/LER-1988-016, :on 880518,reactor Protection Sys Actuation Ocurred.Caused by Error in Plant Design.Event Discussed in Mechanics Shop Meeting & Article Describing Event to Be Included in Prefuelling Outage Bulletin
05000397/LER-1988-013-01, :on 880512 & 13,loss of Power Occurred on Reactor Protection Sys (Rps).Caused by phase-to-ground Faults Due to Lightning.Rps Alternate Supply Electrical Protection Assembly Breaker & Logic Reset
05000335/LER-1996-009, :on 960710,operation Prohibited by Tss.Caused by Procedural Inadequacy & Personnel Error.C/As:Rev of Maint Procedures to Include Verification That Plant Conditions IAW TS Requirements Prior to Installation
05000529/LER-2005-006, Regarding Condition Prohibited by Technical Specifications Due to Partial Fouling of B Diesel Generator (EDG) Fuel Oil Strainer
05000250/LER-2005-005, Manual Reactor Trip Due to Decrease in the 3C Steam Generator Level
05000305/LER-2004-005, Regarding Safety Injection Accumulator Isolation Valve Position During Heatup Violated Technical Specifications - Procedure Deficiency
05000251/LER-2004-003, Regarding Bearing Oil Leak Causes High Head Safety Injection Pump to Be Inoperable Longer than Allowed by Technical Specifications
05000443/LER-2004-003, Regarding Fire Scenario Results in Unanalyzed Condition-Potential Loss of Charging
05000318/LER-2004-001, Regarding Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip
05000382/LER-2003-002, Regarding Failure of Emergency Diesel Generator a Fuel Oil Line
05000250/LER-2003-002-01, Manual Reactor Trip Due to Low Steam Generator Level
05000483/LER-2003-004, For Callaway Plant Unit 1 Regarding Boron Dilution Mitigation System Blocked in Mode 3 Which Not Consistent with FSAR Accident Analysis
05000346/LER-2003-003, From Davis-Besse Unit 1, Regarding Potential Inadequate HPI Pump Minimum Recirculation Flow Following SBLOCA
05000354/LER-2002-006, Operation with Offgas Rad Monitors Inoperable
05000397/LER-2002-001, Re Completion of Technical Specification Required Shutdown Fo Comply with Technical Specification LCO 3.8.1 Required Actions of Condition F
05000213/LER-1998-004, :on 980507,discovered Design Deficiency in Stack Radiation Monitor RMS-14B Isokinetic Sampling.Caused by Failure to Account for Spent Fuel Bldg Ventilation Flow. Will Develop CAP for RMS-14B
05000271/LER-1992-015, :on 920424,RCIC Sys Declared Inoperable When Sys Flow Controller Meter Indicated Approx 30 Gpm Flow W/ RCIC Not Operating.Caused by Setpoint Drift.Work Orders Initiated to Correct Meter Indication
05000458/LER-1998-004-03, :on 980514,noted That Surveillance Test Had Not Been Completed for Primary Containment Leakage Rate Testing Program.Caused by Lack of Proper Emphasis on Procedure Step Re Summation.Revised Pertinent Surveillance Procedures
05000245/LER-1996-052, :on 960920,motor Operated Valves Unable to Close within Stroke Time Limits.Caused by Inadequate Design Margin.Performed Modifications to Ensure IC-2 Will Close & Installed Break Detection Sys Re CU-3
05000458/LER-1995-004-01, :on 950419,auxiliary Bldg Door Was Determined Inoperable Due to Failure of Latching Mechanism.Immediately Restored Secondary Containment Door to Acceptable Configuration