Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20043B5711990-05-25025 May 1990 LER 90-008-00:on 900425,safety Features Actuation Sys Level 1 Actuation Occurred,Resulting in Trip of Containment Radiation Monitors.Caused by High Radiation Fields While Lifting Core Support Assembly.Mod initiated.W/900525 Ltr ML20042F2811990-05-0303 May 1990 LER 90-007-00:on 900403,inadvertent,inconsequential Safety Features Actuation Signal Occured While Defueled.Caused by Incidental Contact W/Monitor in Containment.Temporary Barriers Built Around monitors.W/900503 Ltr ML19324C2081989-11-10010 November 1989 LER 89-014-00:on 891011,plastic Sheeting Blocked Off Fire Detectors in Auxiliary Feedwater Pump 1-1 Room & High Voltage Switchgear Room B,Making Fire Detectors Inoperable. Caused by Personnel Oversight.Event reviewed.W/891110 Ltr ML20028D2291983-01-0707 January 1983 Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint ML20040F3581982-02-0101 February 1982 LER 82-002/03L-0:on 820103,radiation Detector RE2007 on Safety Features Actuation Sys Channel 4 Failed Low.Low Radiation Bistable Tripped & Alarmed.Caused by Fabrication Error in Attaching Shortened Cable Wire ML20039E5571981-12-29029 December 1981 LER 81-076/03L-0:on 811130 & 1201,Door 306 Was Found Open. Caused by Installation Error.Closing Mechanism Adjusted to Exert Larger Force on Door ML20039D3041981-12-15015 December 1981 LER 81-064/03X-2:on 811012 & 13,pump for post-accident Containment Radiation Monitor Re 5029 Found Not Running. Caused by Component Failure Due to Pump Vane Wear.Pump Replaced & Maint Work Order Revised to Check Flaws Weekly ML20049A8471981-09-22022 September 1981 LER 80-091/01X-14:on 801223,required Analysis Indicated That 26 Walls Would Be Overstressed During Seismic Event & 11 Others Would Be Overstressed by Compartment Pressurization. Caused by Change in Analytical Methodology ML20004E4851981-06-0505 June 1981 LER 81-024/03X-1:on 810418,bus J Was Rapidly Taken Out of Svc Which Resulted in Loss of Decay Heat Pump 1-1.Caused by Personnel & Procedural Error.Procedure Mod Written ML20003H9771981-05-0404 May 1981 LER 81-022/03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error ML20003H7541981-05-0101 May 1981 LER 81-021/03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 ML19347D9471981-04-10010 April 1981 LER 80-091/01X-3:on 801223,analysis of Concrete Walls Per IE Bulletin 80-11 Determined That Some Walls Would Be Overstressed During Seismic Event.Caused by Change in Analytical Methodology Since Walls Were Designed ML19345G5991981-03-31031 March 1981 LER 79-101/03X-1:on 791017,safety Features Actuation Sys Channel 2 Radiation Detector Re 2005 Spiked,Tripping Channel 2 Radiation Bistable.Caused by Defective Low Range & Auxiliary Boards in Detector.Detector Replaced ML20002E3871981-01-20020 January 1981 LER 81-001/01T-0:on 810107,analysis Determined That Reportable Condition Had Existed on 801204 When Several Pipe Supports or Fuel Lines to Emergency Diesel Generators Found Disassembled.Caused by Outside Contractor Personnel Error ML19345E0211980-12-15015 December 1980 LER 80-083/03L-0:on 801116,feedwater Swing Caused Steam Generator 1-1 Level to Exceed Tech Spec Limits.Caused by Bad Relay in Integrated Control Sys.Relay 86/MBV-B Replaced. Relay 33X Changed on 801206 ML19331B6591980-08-0808 August 1980 LER 80-055/03L-0:on 800709,position Indication for ECCS Room Ventilation Exhaust damper,HA5441,lost.Cause Unknown.Damper Manually Closed ML19331B6791980-08-0707 August 1980 LER 80-057/03L-0:on 800710,while de-energizing Sfas Channel 2 for Maint on Bus Y2,control Room Operator Received Decay Heat Loop 2 High Flow Alarm.Decay Heat Cooler 1-2 Discharge Control Valve DH14A Failed Open.Caused by Procedural Error ML19329F9661980-07-0303 July 1980 LER 80-045/03L-0:on 800609,while Preparing to Perform ST 5091.01,NI-2 Found Partially Disconnected from Equipment in Control Room.Apparently Caused by Personnel Error.Info Tags Hung on Coax Cables to Insure Proper Connection ML19323F3231980-05-21021 May 1980 LER 80-039/03L-0:on 800423,Tech Specs Requirement Late Date Passed for Offsite Ac Sources Lineup & Available Weekly Test ST 5080.01.Caused by Oversight of Shift Supervisor When Test Not Indicated on Computer Printout Test Schedule ML19309G3881980-05-0101 May 1980 LER 80-030/01T-0:on 800418,contrary to Tech Spec 3.4.1,decay Heat Pump 1-2 Stopped When RCS Water Level Decreased to 37 Inches Above Hot Leg Piping Centerline.Caused by Valve Operator Component Failure.Work Order Issued for Adjustment ML19309F1771980-04-24024 April 1980 LER 80-024/03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued ML19305D8261980-04-10010 April 1980 LER 80-021/03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful ML19344D3281980-03-0606 March 1980 LER 80-013/03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel ML19296D4501980-02-28028 February 1980 LER 80-011/03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 ML19332A5601980-02-28028 February 1980 LER 80-012/03L-1:on 800201,reactor Operator Noticed Control Room Position Indication Was Lost for Letdown Cooler Isolation Valve MU2A.Caused by Const Personnel Bumping Into Disconnect Switch Breaker.Switch Repositioned ML19260D5591980-02-0707 February 1980 LER 80-006/03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed ML19260D9961980-02-0606 February 1980 LER 80-005/03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup ML19260D0371980-02-0404 February 1980 LER 80-004/03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration ML19290C2651980-01-0505 January 1980 LER 79-123/03L-0:on 791207,svc Water Pump 3 Strainer Motor Burned Up.Caused by Single Phasing in Breaker BE1280 on Motor Control Ctr E12C.Breaker Repaired on 791212 & Returned to Svc ML19290C2561980-01-0505 January 1980 LER 79-126/03L-0:on 791209,diesel Generator DG 1-1 Experienced Load Swings & Electrician Racked Out Wrong Breaker Making DG 1-2 Inoperable.Possibly Caused by Electronic Governor or Voltage Regulator Problems ML19290C2351980-01-0505 January 1980 LER 79-127/03L-0:on 791210,IBM Sys 7 Contact Data Logger Failed Rendering Fire & Radiation Remote Monitoring Inoperable.Caused by Intermittent Equipment Problem of Unknown Origin.Computer Program Reloaded ML19211A2711979-12-11011 December 1979 LER 79-111/03L-0:on 791114,during Surveillance Testing, Accelerometer Tracer Could Not Be Discerned Due to Excessive Noise.Caused by Component Failure.Source of Noise Being Investigated,Possibly Caused by Battery Charger ML19210E0991979-11-23023 November 1979 LER 79-106/01T-0:on 791112,design of 11 Seismic Hangers Not as Conservative as Required.Caused by Design Error.Hangers Modified Before Unit Returned to Operation ML19210D6281979-11-21021 November 1979 LER 79-104/03L-0:on 791025,reactor Coolant Pump 2-2 Tripped While Pump 1-1 Shut Down.Caused by Blown Fuse in Pump Interlock Circuit Due to Double Grounding on Dc Buses.Maint Work Orders & Facility Change Requests Completed ML19210D6711979-11-20020 November 1979 LER 79-103/03L-0:on 791023,first & Third Seals in Reactor Coolant Pump 1-1-1 Were Not Staging.Caused by Thermal Shocking Which Occurred During Loss of Offsite Power on 791015.Seal Package Refurbished & Reinstalled ML19210D6521979-11-20020 November 1979 LER 79-102/03L-0:on 791022,during Feedwater Sys Monthly Surveillance Test,No Oil Level Visible in Oil Sight Glass on Inboard Bearing of Auxiliary Feedpump Turbine 1-1.Caused by Loose Sight Glass.Glass Tightened & Oil Replaced ML19210C4791979-11-0101 November 1979 LER 79-099/03L-0:on 791008,during Boron Injection Heat Trace Test,Unit Failed to Achieve 105 F Temp at One Point on Sys Heat Trace Line.Caused by Sys Design Deficiencies.Test ST 5011.01 Performed Successfully on 791009 ML19209D1561979-10-13013 October 1979 LER 79-005/03L-1:on 790106,borated Water Storage Tank Bistable Was Tripped & Decay Heat Valves DH9A Opened & DH7A Closed.Cause by Component Failure of Output Relay K51A in Safety Feature Actuation Sys Channel 4 ML19249E8001979-09-26026 September 1979 LER 79-091/03L-0:on 790901,steam Generator 2 Low Level Trip Occurred on Steam & Feedwater Rupture Control Sys Channel 3.Caused by Inoperable Optical Isolator in Faulty Input Buffer Card.Board Was Replaced & New Buffer Card Installed ML19209D1711979-08-21021 August 1979 LER 79-086/03L-1:on 790725,train 2 of Control Room Emergency Ventilation Sys Was Inoperable.Cause by One of Three Thermistors in Compressor Motor Winding Failing to Open Circuit.Compressor Repaired & New One Will Be Installed ML19207B1171979-08-17017 August 1979 LER 79-084/01T-0 on 790806:containment Air Coolers Svc Outlet Valves,Automatically Regulated by Inlet Air Temp, Failed to Meet Response Time.Caused by Design Error in Actuator Air Opening Size.Valves Will Be Redesigned ML19249A2461979-08-16016 August 1979 LER 79-083/03L-0 on 790720:while Verifying Relative Position Indication for Group 5,Rod 4,discovered That Rod 6 of Group 5 Showed 50% Withdrawn on Absolute Position Indication.Caused by Oxide Buildup on Tube Reed Switches ML19249A2491979-08-13013 August 1979 LER 79-081/03L-0 on 790717:post-accident Containment Radiation Monitor Re 5029 Out of Svc Due to Pump Failure. Caused by Loss of Lubrication to Pump Bearings.Improved Pump Bearings Will Be Installed ML19242D6071979-08-10010 August 1979 LER 79-080/03L-0 on 790716:safety Features Actuation Sys Containment Radiation Detector Re 2005 Spiked & Tripped Channel 2 Containment Radiation Bistable.Caused by Component Failure.Detector Will Be Relocated Outside Containment ML19242B9481979-08-0606 August 1979 LER 79-078/03L-0 on 790710:indication of Source Range Neutron Detector NI-1 Failed Low Twice.Cause Due to Undetermined Component Failure in Both Cases.Unit Tested to Verify Operability ML19242C4371979-08-0303 August 1979 LER 79-077/03L-0 on 790705:auxiliary Feedwater Pump Turbine I-1 Steam Inlet Valve M5-106 Would Not Close on Simulated Low Turbine Inlet Pressure Signal.Caused by Component Failure Components Replaced ML19242C4801979-08-0303 August 1979 LER 79-076/03L-0 on 790708:reading of Core Flood Tank Level Indicator Li-CF3B2 Did Not Appear to Read Same as Indicator LI-CF3B1.Caused by Faulty Amplifier in Level Transmitter LT-CF3B2.Amplifier Replaced & Transmitter Recalibr ML19242C5081979-08-0202 August 1979 LER 79-074/03L-0 on 790707:auxiliary Feedwater Pump 1-2 suction-before-strainer Pressure Switch PSL-4929B Actuated at Pressure Input Outside Allowable Tolerance.Caused by Component Failure Due to Misapplication.Switch Replaced ML19242A8281979-08-0202 August 1979 LER 79-075/03L-0 on 790708:no Visible Oil Level in Outboard Bearing Oil Reservoir Sight Glass on Containment Spray Pump 1-2.Caused by Component Failure.Oil Added to Reservoir & Fittings Tightened ML19242A8461979-08-0202 August 1979 LER 79-073/03L-0 on 790708:during Checkout of Valve Relay, Main Steam Inlet to Auxiliary Feed Pipe Turbine 1-1 Isolation Valve Torqued While Opening.Caused by Normal Valve Wear.Valve Was Readjusted & Returned to Svc 1990-05-03
[Table view] Category:RO)
MONTHYEARML20043B5711990-05-25025 May 1990 LER 90-008-00:on 900425,safety Features Actuation Sys Level 1 Actuation Occurred,Resulting in Trip of Containment Radiation Monitors.Caused by High Radiation Fields While Lifting Core Support Assembly.Mod initiated.W/900525 Ltr ML20042F2811990-05-0303 May 1990 LER 90-007-00:on 900403,inadvertent,inconsequential Safety Features Actuation Signal Occured While Defueled.Caused by Incidental Contact W/Monitor in Containment.Temporary Barriers Built Around monitors.W/900503 Ltr ML19324C2081989-11-10010 November 1989 LER 89-014-00:on 891011,plastic Sheeting Blocked Off Fire Detectors in Auxiliary Feedwater Pump 1-1 Room & High Voltage Switchgear Room B,Making Fire Detectors Inoperable. Caused by Personnel Oversight.Event reviewed.W/891110 Ltr ML20028D2291983-01-0707 January 1983 Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint ML20040F3581982-02-0101 February 1982 LER 82-002/03L-0:on 820103,radiation Detector RE2007 on Safety Features Actuation Sys Channel 4 Failed Low.Low Radiation Bistable Tripped & Alarmed.Caused by Fabrication Error in Attaching Shortened Cable Wire ML20039E5571981-12-29029 December 1981 LER 81-076/03L-0:on 811130 & 1201,Door 306 Was Found Open. Caused by Installation Error.Closing Mechanism Adjusted to Exert Larger Force on Door ML20039D3041981-12-15015 December 1981 LER 81-064/03X-2:on 811012 & 13,pump for post-accident Containment Radiation Monitor Re 5029 Found Not Running. Caused by Component Failure Due to Pump Vane Wear.Pump Replaced & Maint Work Order Revised to Check Flaws Weekly ML20049A8471981-09-22022 September 1981 LER 80-091/01X-14:on 801223,required Analysis Indicated That 26 Walls Would Be Overstressed During Seismic Event & 11 Others Would Be Overstressed by Compartment Pressurization. Caused by Change in Analytical Methodology ML20004E4851981-06-0505 June 1981 LER 81-024/03X-1:on 810418,bus J Was Rapidly Taken Out of Svc Which Resulted in Loss of Decay Heat Pump 1-1.Caused by Personnel & Procedural Error.Procedure Mod Written ML20003H9771981-05-0404 May 1981 LER 81-022/03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error ML20003H7541981-05-0101 May 1981 LER 81-021/03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 ML19347D9471981-04-10010 April 1981 LER 80-091/01X-3:on 801223,analysis of Concrete Walls Per IE Bulletin 80-11 Determined That Some Walls Would Be Overstressed During Seismic Event.Caused by Change in Analytical Methodology Since Walls Were Designed ML19345G5991981-03-31031 March 1981 LER 79-101/03X-1:on 791017,safety Features Actuation Sys Channel 2 Radiation Detector Re 2005 Spiked,Tripping Channel 2 Radiation Bistable.Caused by Defective Low Range & Auxiliary Boards in Detector.Detector Replaced ML20002E3871981-01-20020 January 1981 LER 81-001/01T-0:on 810107,analysis Determined That Reportable Condition Had Existed on 801204 When Several Pipe Supports or Fuel Lines to Emergency Diesel Generators Found Disassembled.Caused by Outside Contractor Personnel Error ML19345E0211980-12-15015 December 1980 LER 80-083/03L-0:on 801116,feedwater Swing Caused Steam Generator 1-1 Level to Exceed Tech Spec Limits.Caused by Bad Relay in Integrated Control Sys.Relay 86/MBV-B Replaced. Relay 33X Changed on 801206 ML19331B6591980-08-0808 August 1980 LER 80-055/03L-0:on 800709,position Indication for ECCS Room Ventilation Exhaust damper,HA5441,lost.Cause Unknown.Damper Manually Closed ML19331B6791980-08-0707 August 1980 LER 80-057/03L-0:on 800710,while de-energizing Sfas Channel 2 for Maint on Bus Y2,control Room Operator Received Decay Heat Loop 2 High Flow Alarm.Decay Heat Cooler 1-2 Discharge Control Valve DH14A Failed Open.Caused by Procedural Error ML19329F9661980-07-0303 July 1980 LER 80-045/03L-0:on 800609,while Preparing to Perform ST 5091.01,NI-2 Found Partially Disconnected from Equipment in Control Room.Apparently Caused by Personnel Error.Info Tags Hung on Coax Cables to Insure Proper Connection ML19323F3231980-05-21021 May 1980 LER 80-039/03L-0:on 800423,Tech Specs Requirement Late Date Passed for Offsite Ac Sources Lineup & Available Weekly Test ST 5080.01.Caused by Oversight of Shift Supervisor When Test Not Indicated on Computer Printout Test Schedule ML19309G3881980-05-0101 May 1980 LER 80-030/01T-0:on 800418,contrary to Tech Spec 3.4.1,decay Heat Pump 1-2 Stopped When RCS Water Level Decreased to 37 Inches Above Hot Leg Piping Centerline.Caused by Valve Operator Component Failure.Work Order Issued for Adjustment ML19309F1771980-04-24024 April 1980 LER 80-024/03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued ML19305D8261980-04-10010 April 1980 LER 80-021/03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful ML19344D3281980-03-0606 March 1980 LER 80-013/03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel ML19296D4501980-02-28028 February 1980 LER 80-011/03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 ML19332A5601980-02-28028 February 1980 LER 80-012/03L-1:on 800201,reactor Operator Noticed Control Room Position Indication Was Lost for Letdown Cooler Isolation Valve MU2A.Caused by Const Personnel Bumping Into Disconnect Switch Breaker.Switch Repositioned ML19260D5591980-02-0707 February 1980 LER 80-006/03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed ML19260D9961980-02-0606 February 1980 LER 80-005/03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup ML19260D0371980-02-0404 February 1980 LER 80-004/03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration ML19290C2651980-01-0505 January 1980 LER 79-123/03L-0:on 791207,svc Water Pump 3 Strainer Motor Burned Up.Caused by Single Phasing in Breaker BE1280 on Motor Control Ctr E12C.Breaker Repaired on 791212 & Returned to Svc ML19290C2561980-01-0505 January 1980 LER 79-126/03L-0:on 791209,diesel Generator DG 1-1 Experienced Load Swings & Electrician Racked Out Wrong Breaker Making DG 1-2 Inoperable.Possibly Caused by Electronic Governor or Voltage Regulator Problems ML19290C2351980-01-0505 January 1980 LER 79-127/03L-0:on 791210,IBM Sys 7 Contact Data Logger Failed Rendering Fire & Radiation Remote Monitoring Inoperable.Caused by Intermittent Equipment Problem of Unknown Origin.Computer Program Reloaded ML19211A2711979-12-11011 December 1979 LER 79-111/03L-0:on 791114,during Surveillance Testing, Accelerometer Tracer Could Not Be Discerned Due to Excessive Noise.Caused by Component Failure.Source of Noise Being Investigated,Possibly Caused by Battery Charger ML19210E0991979-11-23023 November 1979 LER 79-106/01T-0:on 791112,design of 11 Seismic Hangers Not as Conservative as Required.Caused by Design Error.Hangers Modified Before Unit Returned to Operation ML19210D6281979-11-21021 November 1979 LER 79-104/03L-0:on 791025,reactor Coolant Pump 2-2 Tripped While Pump 1-1 Shut Down.Caused by Blown Fuse in Pump Interlock Circuit Due to Double Grounding on Dc Buses.Maint Work Orders & Facility Change Requests Completed ML19210D6711979-11-20020 November 1979 LER 79-103/03L-0:on 791023,first & Third Seals in Reactor Coolant Pump 1-1-1 Were Not Staging.Caused by Thermal Shocking Which Occurred During Loss of Offsite Power on 791015.Seal Package Refurbished & Reinstalled ML19210D6521979-11-20020 November 1979 LER 79-102/03L-0:on 791022,during Feedwater Sys Monthly Surveillance Test,No Oil Level Visible in Oil Sight Glass on Inboard Bearing of Auxiliary Feedpump Turbine 1-1.Caused by Loose Sight Glass.Glass Tightened & Oil Replaced ML19210C4791979-11-0101 November 1979 LER 79-099/03L-0:on 791008,during Boron Injection Heat Trace Test,Unit Failed to Achieve 105 F Temp at One Point on Sys Heat Trace Line.Caused by Sys Design Deficiencies.Test ST 5011.01 Performed Successfully on 791009 ML19209D1561979-10-13013 October 1979 LER 79-005/03L-1:on 790106,borated Water Storage Tank Bistable Was Tripped & Decay Heat Valves DH9A Opened & DH7A Closed.Cause by Component Failure of Output Relay K51A in Safety Feature Actuation Sys Channel 4 ML19249E8001979-09-26026 September 1979 LER 79-091/03L-0:on 790901,steam Generator 2 Low Level Trip Occurred on Steam & Feedwater Rupture Control Sys Channel 3.Caused by Inoperable Optical Isolator in Faulty Input Buffer Card.Board Was Replaced & New Buffer Card Installed ML19209D1711979-08-21021 August 1979 LER 79-086/03L-1:on 790725,train 2 of Control Room Emergency Ventilation Sys Was Inoperable.Cause by One of Three Thermistors in Compressor Motor Winding Failing to Open Circuit.Compressor Repaired & New One Will Be Installed ML19207B1171979-08-17017 August 1979 LER 79-084/01T-0 on 790806:containment Air Coolers Svc Outlet Valves,Automatically Regulated by Inlet Air Temp, Failed to Meet Response Time.Caused by Design Error in Actuator Air Opening Size.Valves Will Be Redesigned ML19249A2461979-08-16016 August 1979 LER 79-083/03L-0 on 790720:while Verifying Relative Position Indication for Group 5,Rod 4,discovered That Rod 6 of Group 5 Showed 50% Withdrawn on Absolute Position Indication.Caused by Oxide Buildup on Tube Reed Switches ML19249A2491979-08-13013 August 1979 LER 79-081/03L-0 on 790717:post-accident Containment Radiation Monitor Re 5029 Out of Svc Due to Pump Failure. Caused by Loss of Lubrication to Pump Bearings.Improved Pump Bearings Will Be Installed ML19242D6071979-08-10010 August 1979 LER 79-080/03L-0 on 790716:safety Features Actuation Sys Containment Radiation Detector Re 2005 Spiked & Tripped Channel 2 Containment Radiation Bistable.Caused by Component Failure.Detector Will Be Relocated Outside Containment ML19242B9481979-08-0606 August 1979 LER 79-078/03L-0 on 790710:indication of Source Range Neutron Detector NI-1 Failed Low Twice.Cause Due to Undetermined Component Failure in Both Cases.Unit Tested to Verify Operability ML19242C4371979-08-0303 August 1979 LER 79-077/03L-0 on 790705:auxiliary Feedwater Pump Turbine I-1 Steam Inlet Valve M5-106 Would Not Close on Simulated Low Turbine Inlet Pressure Signal.Caused by Component Failure Components Replaced ML19242C4801979-08-0303 August 1979 LER 79-076/03L-0 on 790708:reading of Core Flood Tank Level Indicator Li-CF3B2 Did Not Appear to Read Same as Indicator LI-CF3B1.Caused by Faulty Amplifier in Level Transmitter LT-CF3B2.Amplifier Replaced & Transmitter Recalibr ML19242C5081979-08-0202 August 1979 LER 79-074/03L-0 on 790707:auxiliary Feedwater Pump 1-2 suction-before-strainer Pressure Switch PSL-4929B Actuated at Pressure Input Outside Allowable Tolerance.Caused by Component Failure Due to Misapplication.Switch Replaced ML19242A8281979-08-0202 August 1979 LER 79-075/03L-0 on 790708:no Visible Oil Level in Outboard Bearing Oil Reservoir Sight Glass on Containment Spray Pump 1-2.Caused by Component Failure.Oil Added to Reservoir & Fittings Tightened ML19242A8461979-08-0202 August 1979 LER 79-073/03L-0 on 790708:during Checkout of Valve Relay, Main Steam Inlet to Auxiliary Feed Pipe Turbine 1-1 Isolation Valve Torqued While Opening.Caused by Normal Valve Wear.Valve Was Readjusted & Returned to Svc 1990-05-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 1999-09-30
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