Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024A5401983-06-0202 June 1983 LER 83-021/03L-0:on 830504,containment Sump Alarms Declared Inoperable.Caused by Defective Alarm Card.Alarm Card Replaced.Annunciator Alarm Will Be Checked daily.W/830602 Ltr ML20028G4811983-01-31031 January 1983 LER 83-004/03L-0:on 830101,containment Sump Level Alarm Would Not Clear.Caused by Dirt & Debris Which Interfered W/Level Switch Operation.Level Switch Tube Flushed ML20028G3801983-01-27027 January 1983 Uptated LER 82-010/03X-1 on 820212,following Reactor Trip, Element Assembly 19 Discovered Stuck at 8-inch Withdrawn Position.Cause Undetermined.Control Element Assembly & Associated Bundle Inspected ML20028F4391983-01-21021 January 1983 LER 82-084/03L-0:on 821223,sequencer Initiated Alarm Failed to Clear When Diesel Generator 12 Shut Down.Caused by Failure of Breaker Lever to Operate Auxiliary Switch in Cubicle Due to Displaced Assembly.New Assembly Installed ML20052J0421982-05-14014 May 1982 LER 82-018/03L-0:on 820417,control Element Assembly 21 Dropped Into Core After Electricians Inadvertently Disconnected Power,Resulting in Pressurizer Level Deviation Exceeding Tech Spec Limit.Caused by Personnel Error ML20050D4691982-04-0202 April 1982 LER 82-014/03L-0:on 820304,water Observed in Emergency Diesel Generator Lube Oil Dry Tank.Caused by Filling Tank from Unsampled Barrel of Oil Which Had Significant Amount of Water.New Procedure Written ML20027D1261981-04-0303 April 1981 LER 81-013/03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt ML19347D5611981-03-13013 March 1981 LER 81-012/03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted ML20003C6001981-03-0101 March 1981 Updated LER 81-002/03L-1:on 810108 & 0227,diesel Generator 12 Started Automatically.Generator Was Stopped & Start Failure Alarm Received.Caused by Insufficient Contact Wipe by Local Break Glass Start Switch.Actuator Fitting Removed ML20003A3881981-01-27027 January 1981 LER 80-066 Has Been Cancelled ML19351F6391981-01-0909 January 1981 LER 80-055/03L-0:on 801209,emergency Diesel Generator 12 Developed Fuel Oil Leak.Caused by Leak at Flared Type Brass Compression Fitting.Line Replaced ML19345B8391980-11-26026 November 1980 LER 80-050/03L-0:on 801027,wide Range ex-core Nuclear Instrument Channel B Failed.Caused by Greater than or Equal to 15-volt Dc Power Supply Having Low Supply W/Ac Ripple. Power Supply Replaced ML20002A7811980-11-17017 November 1980 LER 80-060/03L-0:on 801018,surveillance Testing Found RC-200 & RC-201 Lift Setpoints to Be 70 Psi & 56 Psi,Respectively, Above Max Tech Spec.Cause Not Stated.Setpoints Adjusted ML19305E8201980-05-16016 May 1980 LER 80-023/03L-0:on 800416,while 21 Diesel Generator Was Being Taken Off 24 4 Kv Bus Following Test,Two 15 Vdc Power Supplies Had No Output.Caused by Tripped Overvoltage Protection Modules ML19323C4191980-05-13013 May 1980 LER 80-024/03L-0:on 800417,during Containment Entry ,Leak in Middle Seal Instrument Line Flexible Hose Discovered.Cause Unknown.Failed Part Is Inside Containment Bldg & Is Still Radiologically Contaminated ML19309G4451980-04-30030 April 1980 LER 80-022/03L-0:on 800412,charging Pump 23 Removed from Svc to Repair Weld on Suction Relief Valve.Leak Caused by Vibration Induced Metal Fatigue in Heat Affected Zone of Weld.Leak Repaired & Mods Approved for Charging Pumps ML19309F4691980-04-25025 April 1980 LER 80-022/01T-0:on 800415,util Informed of Possible Deficiency in FSAR Section 14.3,boron Dilution Incident,For Case When RCS Is Drained to Hot Leg w/1% Shutdown Margin. Cause Not Stated.Procedures Changed ML19309F4001980-04-25025 April 1980 Updated LER 79-003/01X-2:on 790120,reactor Coolant Pump 22A Lower Seal Temp Alarm Activated & 2 Gpm Increase in Leak Rate Noted.Reactor Manually Tripped.Caused by Cracked Weld on Seal Pressure Sensing Line.Seal Assembly Replaced ML19309F3841980-04-25025 April 1980 LER 80-016/03L-0:on 800325,during Surveillance Testing, Channel a Wide Range Nuclear Instrument Did Not Respond in Calibr Mode.Apparently Caused by Failure of Channel Preamplifier.Power Supply Replaced W/Spare ML19309E6641980-04-18018 April 1980 LER 80-021/03L-0:on 800318,during Performance of Surveillance Test 23,saltwater Pump Did Not Start Upon Receipt of Safety Actuation Signal.Caused by Faulty Pin. Pin Replaced ML19305D7591980-04-10010 April 1980 LER 80-017/03L-0:on 800316,saltwater Svc Water Heat Exchanger 22 Was Taken Out of Svc.Caused by Need to Repair Tube Leak.Tube Leak Found & Plugged ML19309A7961980-03-25025 March 1980 LER 80-001/03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error ML19290E2321980-02-29029 February 1980 LER 80-007/03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry ML19294B7451980-02-29029 February 1980 LER 80-009/03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basis ML19296C8291980-02-27027 February 1980 LER 80-009/03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment ML19296D1291980-02-22022 February 1980 LER 80-005/03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown ML19296D1171980-02-19019 February 1980 LER 80-004/03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads ML19296A7041980-02-0808 February 1980 LER 80-003/03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired ML19260D9751980-02-0707 February 1980 LER 80-002/03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced ML19211D1061980-01-10010 January 1980 LER 79-046/03L-0:on 791214,plant Computer Taken Out of Svc for Corrective Maint,Rendering Incore Detector Sys Inoperable.Caused by Computer Rapid Access Disc Counter Incrementing Improperly,Forcing Computer to Stop ML19290C2781980-01-0404 January 1980 LER 79-047/03L-0:on 791204,while Performing post-refueling Low Power Physics Test,Average Temp Dropped Below Tech Specs.Caused by Operator & Erratic Control of Turbine Bypass Valves ML19210C4241979-11-0505 November 1979 LER 79-037/03L-0:on 791005,analog Meter in Channel Zf Containment Pressure Bistable for SIAS Found Nonlinear in Response to Surveillance Test Input Signals.Caused by Aging of Meter Movement.Meter Replaced ML19209C6791979-10-12012 October 1979 LER 79-049/03L-0:on 790924,loop Isolation Valve SI-617 Failed to Operate When Motor Operator Received Open Signal. Caused by Contact Misalignment of Movable Contactor. Contactor Realigned & Tested ML19209C8051979-10-11011 October 1979 LER 79-051/03L-0:on 790926,hydraulic Snubber Was Removed from Operation to Repair Anchors Attaching Snubber to Wall. Anchors Were Replaced & Hanger Restored to Operation ML19209C8601979-10-0909 October 1979 LER 79-035/03L-0:on 790922,plant Computer Failed.Caused by Printed Circuit Board Failure Which Generated Rapid Access Data Storage Disc Stop Signal.Circuit Board Replaced ML19209C0301979-10-0808 October 1979 LER 79-033/03L-0:790907,high Power & Thermal Power Low Pressure pre-trip & Trip Alarms Received on Reactor Protection Sys.Causes Unknown.Possibly Due to Moist or Dirty Detector Cables ML19209C0091979-10-0404 October 1979 LER 79-032/03L-0:on 790905,channel D Nuclear Instrumentation Sys Linear Power Range Was Indicating Erratically High. Caused by Inadequate Chassis Ground.Signal Returned to Normal After Cleaning Drawer Rails ML19249F3241979-10-0404 October 1979 LER 79-048/03L-0:on 790914,during Surveillance Test, Containment Spray Pump 12 Tripped on Ground Overcurrent. Caused by Motor Stator Coils Chafing Against Incoming Phase Lead,Thus Developing Short Circuits at Coil End ML19209A2951979-10-0101 October 1979 LER 79-031/03L-0:on 790903,spurious Trips on Reactor Protection Sys Channel C High Power Trip Units Occured.Cause Not Stated.Temp Element 2-TE-122HC Replaced ML19209A3041979-09-28028 September 1979 LER 79-038/03L-0:on 790829,115-volt Power Supply to Hydrogen Analyzer O-AE 6527 Was Inoperative.Caused by Shorted Winding in Power Transformer T-1 ML19209A5571979-09-28028 September 1979 LER 79-045/03L-0:on 790831,valve Operator Became Disconnected from Valve Stem.Caused by Failure of Pivot Locking Plate,Which Disconnected Actuator from Valve Stem. New Plate Installed & Actuator Repaired & Replaced ML19209A1061979-09-27027 September 1979 LER 79-044/03L-0:on 790913,water Leak Discovered Coming from Cracked Weld on Reactor Coolant Charging Pump Discharge Relief Valve Flange.Caused by Pinhole Crack in heat-affected Zone of Socket Weld.Valve Replaced ML19249D8041979-09-14014 September 1979 LER 79-047/01X-0:on 790914,air Start Sys Hangers Found Not Meeting Seismic Requirement.New Hangers Will Be Installed Meeting Seismic Requirements in Approx 5 to 7 Days ML19208A8031979-09-13013 September 1979 LER 79-034/03L-0:on 790813,during Routine Surveillance Test, Control Element Assembly Deviation Exceeded 7.5 Inches Required to Initiate Assembly Motion Inhibit.Caused by Circuit Failing,W/High Conduction Affecting Other Failures ML19208A3091979-09-11011 September 1979 LER 79-036/03L-0 on 790812:during Surveillance Test,Wide Range Nuclear Instrument Channel D Would Not Indicate Properly While in Calibr Mode.Apparently Caused by Bad Connection in Test & Power Cables.Connector Replaced 1993-07-09
[Table view] Category:RO)
MONTHYEARML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024A5401983-06-0202 June 1983 LER 83-021/03L-0:on 830504,containment Sump Alarms Declared Inoperable.Caused by Defective Alarm Card.Alarm Card Replaced.Annunciator Alarm Will Be Checked daily.W/830602 Ltr ML20028G4811983-01-31031 January 1983 LER 83-004/03L-0:on 830101,containment Sump Level Alarm Would Not Clear.Caused by Dirt & Debris Which Interfered W/Level Switch Operation.Level Switch Tube Flushed ML20028G3801983-01-27027 January 1983 Uptated LER 82-010/03X-1 on 820212,following Reactor Trip, Element Assembly 19 Discovered Stuck at 8-inch Withdrawn Position.Cause Undetermined.Control Element Assembly & Associated Bundle Inspected ML20028F4391983-01-21021 January 1983 LER 82-084/03L-0:on 821223,sequencer Initiated Alarm Failed to Clear When Diesel Generator 12 Shut Down.Caused by Failure of Breaker Lever to Operate Auxiliary Switch in Cubicle Due to Displaced Assembly.New Assembly Installed ML20052J0421982-05-14014 May 1982 LER 82-018/03L-0:on 820417,control Element Assembly 21 Dropped Into Core After Electricians Inadvertently Disconnected Power,Resulting in Pressurizer Level Deviation Exceeding Tech Spec Limit.Caused by Personnel Error ML20050D4691982-04-0202 April 1982 LER 82-014/03L-0:on 820304,water Observed in Emergency Diesel Generator Lube Oil Dry Tank.Caused by Filling Tank from Unsampled Barrel of Oil Which Had Significant Amount of Water.New Procedure Written ML20027D1261981-04-0303 April 1981 LER 81-013/03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt ML19347D5611981-03-13013 March 1981 LER 81-012/03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted ML20003C6001981-03-0101 March 1981 Updated LER 81-002/03L-1:on 810108 & 0227,diesel Generator 12 Started Automatically.Generator Was Stopped & Start Failure Alarm Received.Caused by Insufficient Contact Wipe by Local Break Glass Start Switch.Actuator Fitting Removed ML20003A3881981-01-27027 January 1981 LER 80-066 Has Been Cancelled ML19351F6391981-01-0909 January 1981 LER 80-055/03L-0:on 801209,emergency Diesel Generator 12 Developed Fuel Oil Leak.Caused by Leak at Flared Type Brass Compression Fitting.Line Replaced ML19345B8391980-11-26026 November 1980 LER 80-050/03L-0:on 801027,wide Range ex-core Nuclear Instrument Channel B Failed.Caused by Greater than or Equal to 15-volt Dc Power Supply Having Low Supply W/Ac Ripple. Power Supply Replaced ML20002A7811980-11-17017 November 1980 LER 80-060/03L-0:on 801018,surveillance Testing Found RC-200 & RC-201 Lift Setpoints to Be 70 Psi & 56 Psi,Respectively, Above Max Tech Spec.Cause Not Stated.Setpoints Adjusted ML19305E8201980-05-16016 May 1980 LER 80-023/03L-0:on 800416,while 21 Diesel Generator Was Being Taken Off 24 4 Kv Bus Following Test,Two 15 Vdc Power Supplies Had No Output.Caused by Tripped Overvoltage Protection Modules ML19323C4191980-05-13013 May 1980 LER 80-024/03L-0:on 800417,during Containment Entry ,Leak in Middle Seal Instrument Line Flexible Hose Discovered.Cause Unknown.Failed Part Is Inside Containment Bldg & Is Still Radiologically Contaminated ML19309G4451980-04-30030 April 1980 LER 80-022/03L-0:on 800412,charging Pump 23 Removed from Svc to Repair Weld on Suction Relief Valve.Leak Caused by Vibration Induced Metal Fatigue in Heat Affected Zone of Weld.Leak Repaired & Mods Approved for Charging Pumps ML19309F4691980-04-25025 April 1980 LER 80-022/01T-0:on 800415,util Informed of Possible Deficiency in FSAR Section 14.3,boron Dilution Incident,For Case When RCS Is Drained to Hot Leg w/1% Shutdown Margin. Cause Not Stated.Procedures Changed ML19309F4001980-04-25025 April 1980 Updated LER 79-003/01X-2:on 790120,reactor Coolant Pump 22A Lower Seal Temp Alarm Activated & 2 Gpm Increase in Leak Rate Noted.Reactor Manually Tripped.Caused by Cracked Weld on Seal Pressure Sensing Line.Seal Assembly Replaced ML19309F3841980-04-25025 April 1980 LER 80-016/03L-0:on 800325,during Surveillance Testing, Channel a Wide Range Nuclear Instrument Did Not Respond in Calibr Mode.Apparently Caused by Failure of Channel Preamplifier.Power Supply Replaced W/Spare ML19309E6641980-04-18018 April 1980 LER 80-021/03L-0:on 800318,during Performance of Surveillance Test 23,saltwater Pump Did Not Start Upon Receipt of Safety Actuation Signal.Caused by Faulty Pin. Pin Replaced ML19305D7591980-04-10010 April 1980 LER 80-017/03L-0:on 800316,saltwater Svc Water Heat Exchanger 22 Was Taken Out of Svc.Caused by Need to Repair Tube Leak.Tube Leak Found & Plugged ML19309A7961980-03-25025 March 1980 LER 80-001/03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error ML19290E2321980-02-29029 February 1980 LER 80-007/03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry ML19294B7451980-02-29029 February 1980 LER 80-009/03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basis ML19296C8291980-02-27027 February 1980 LER 80-009/03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment ML19296D1291980-02-22022 February 1980 LER 80-005/03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown ML19296D1171980-02-19019 February 1980 LER 80-004/03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads ML19296A7041980-02-0808 February 1980 LER 80-003/03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired ML19260D9751980-02-0707 February 1980 LER 80-002/03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced ML19211D1061980-01-10010 January 1980 LER 79-046/03L-0:on 791214,plant Computer Taken Out of Svc for Corrective Maint,Rendering Incore Detector Sys Inoperable.Caused by Computer Rapid Access Disc Counter Incrementing Improperly,Forcing Computer to Stop ML19290C2781980-01-0404 January 1980 LER 79-047/03L-0:on 791204,while Performing post-refueling Low Power Physics Test,Average Temp Dropped Below Tech Specs.Caused by Operator & Erratic Control of Turbine Bypass Valves ML19210C4241979-11-0505 November 1979 LER 79-037/03L-0:on 791005,analog Meter in Channel Zf Containment Pressure Bistable for SIAS Found Nonlinear in Response to Surveillance Test Input Signals.Caused by Aging of Meter Movement.Meter Replaced ML19209C6791979-10-12012 October 1979 LER 79-049/03L-0:on 790924,loop Isolation Valve SI-617 Failed to Operate When Motor Operator Received Open Signal. Caused by Contact Misalignment of Movable Contactor. Contactor Realigned & Tested ML19209C8051979-10-11011 October 1979 LER 79-051/03L-0:on 790926,hydraulic Snubber Was Removed from Operation to Repair Anchors Attaching Snubber to Wall. Anchors Were Replaced & Hanger Restored to Operation ML19209C8601979-10-0909 October 1979 LER 79-035/03L-0:on 790922,plant Computer Failed.Caused by Printed Circuit Board Failure Which Generated Rapid Access Data Storage Disc Stop Signal.Circuit Board Replaced ML19209C0301979-10-0808 October 1979 LER 79-033/03L-0:790907,high Power & Thermal Power Low Pressure pre-trip & Trip Alarms Received on Reactor Protection Sys.Causes Unknown.Possibly Due to Moist or Dirty Detector Cables ML19209C0091979-10-0404 October 1979 LER 79-032/03L-0:on 790905,channel D Nuclear Instrumentation Sys Linear Power Range Was Indicating Erratically High. Caused by Inadequate Chassis Ground.Signal Returned to Normal After Cleaning Drawer Rails ML19249F3241979-10-0404 October 1979 LER 79-048/03L-0:on 790914,during Surveillance Test, Containment Spray Pump 12 Tripped on Ground Overcurrent. Caused by Motor Stator Coils Chafing Against Incoming Phase Lead,Thus Developing Short Circuits at Coil End ML19209A2951979-10-0101 October 1979 LER 79-031/03L-0:on 790903,spurious Trips on Reactor Protection Sys Channel C High Power Trip Units Occured.Cause Not Stated.Temp Element 2-TE-122HC Replaced ML19209A3041979-09-28028 September 1979 LER 79-038/03L-0:on 790829,115-volt Power Supply to Hydrogen Analyzer O-AE 6527 Was Inoperative.Caused by Shorted Winding in Power Transformer T-1 ML19209A5571979-09-28028 September 1979 LER 79-045/03L-0:on 790831,valve Operator Became Disconnected from Valve Stem.Caused by Failure of Pivot Locking Plate,Which Disconnected Actuator from Valve Stem. New Plate Installed & Actuator Repaired & Replaced ML19209A1061979-09-27027 September 1979 LER 79-044/03L-0:on 790913,water Leak Discovered Coming from Cracked Weld on Reactor Coolant Charging Pump Discharge Relief Valve Flange.Caused by Pinhole Crack in heat-affected Zone of Socket Weld.Valve Replaced ML19249D8041979-09-14014 September 1979 LER 79-047/01X-0:on 790914,air Start Sys Hangers Found Not Meeting Seismic Requirement.New Hangers Will Be Installed Meeting Seismic Requirements in Approx 5 to 7 Days ML19208A8031979-09-13013 September 1979 LER 79-034/03L-0:on 790813,during Routine Surveillance Test, Control Element Assembly Deviation Exceeded 7.5 Inches Required to Initiate Assembly Motion Inhibit.Caused by Circuit Failing,W/High Conduction Affecting Other Failures ML19208A3091979-09-11011 September 1979 LER 79-036/03L-0 on 790812:during Surveillance Test,Wide Range Nuclear Instrument Channel D Would Not Indicate Properly While in Calibr Mode.Apparently Caused by Bad Connection in Test & Power Cables.Connector Replaced 1993-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With1999-10-22022 October 1999
- on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With
ML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With 05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With1999-09-20020 September 1999
- on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With
ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20211J3531999-09-0101 September 1999 Safety Evaluation Supporting Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-005, :on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With1999-08-23023 August 1999
- on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With
05000317/LER-1999-004, :on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With1999-08-23023 August 1999
- on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With
ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-003, :on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With1999-07-30030 July 1999
- on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With
ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-039, Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified LD-99-035, Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-002, :on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With1999-05-25025 May 1999
- on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With
ML20206U7031999-05-18018 May 1999 Rev 1 to Ran 97-031, Main CR Fire Analysis for IPEEE Section 4-1 ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20205J8331999-04-0707 April 1999 Safety Evaluation Concluding That Security Lighting,Portable Lighting & Helmet Lights,As Described by Licensee Satisfies Underlying Purpose of 10CFR50,App R,Section Iii.J.Grants Licensee Request for Exemption ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20204B5961999-03-17017 March 1999 Corrected Page 7 to SER for Amend 205 for License DPR-69. Staff Deleted Word Not on Line One of Page 7 ML20207L2991999-03-0808 March 1999 Safety Evaluation Supporting Amend 205 to License DPR-69 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons 05000317/LER-1997-010, :on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With1999-01-29029 January 1999
- on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With
ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors 05000317/LER-1998-009, :on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With1999-01-0808 January 1999
- on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With
ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative 05000317/LER-1998-008, :on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With1998-11-11011 November 1998
- on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With
ML20195D4271998-11-0505 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-69 ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 1999-09-30
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