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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D0201994-04-25025 April 1994 LER 94-007-01:on 931014,high Head Safety Injection Flow Balance Testing Found to Be Below TS Requirement.Caused by Unaccounted for Uncertainties.Cold Leg Safety Injection Leg Throttle Valve adjusted.W/940425 Ltr ML20045G9391993-07-0808 July 1993 Lr 93-017-00:on 930616,containment Hydrogen Analyzer Heat Trace Channel Calibration Not Performed on Staggered Test Basis Due to Inadequate Implementation of TS Amend.Test Procedure Satisfactorily performed.W/930708 Ltr ML20044H1591993-05-27027 May 1993 LER 93-016-00:on 930509,discovered That Containment Hydrogen Analyzer Pressure Switch PS-3 Sensing Line Disconnected in Local Panel.Caused by Personnel Error. Pressure Switch Calibr & Line reconnected.W/930527 Ltr ML20044D5711993-05-14014 May 1993 LER 93-002-00:on 930416,automatic Reactor Trip Initiated from Turbine Trip Due to Over Excitation of Main Generator. Emergency Procedure 2-E-0 Entered & Individuals Involved in Event Received Remediated training.W/930514 Ltr ML20044D2281993-05-12012 May 1993 LER 93-003-00:on 930424,manual Reactor Trip Initiated Due to Erratic Feedwater Flow Indications to SG C & Excessive Main Feedwater Regulating Valve Oscillations.Caused by Design Instabilities.Secondary Sys secured.W/930512 Ltr ML20044C9541993-05-0707 May 1993 LER 93-015-00:on 930427,discovered That Portions of Containment Pressure Channels That Input to Containment Spray hi-hi Pressure Not Tested Monthly.Caused by Personnel Error.Test Procedures changed.W/930507 Ltr ML20044C9811993-05-0606 May 1993 LER 93-014-00:on 930411,as-found Speed Setting of Steam Driven AFW Pump 1-FW-P-2 Found Below Required TS Limit. Caused by Incorrect Speed Control Setting.Pump Speed Adjusted & Maint Personnel counseled.W/930506 Ltr ML20024G6841991-04-18018 April 1991 LER 91-006-00:on 910403,discovered That Ac Offsite Power Source Surveillance Not Performed Due to Personnel Error. Surveillance Initiated Immediately & Positive Discipline Administered to supervisor.W/910418 Ltr ML20029B5601991-03-0606 March 1991 LER 91-005-00:on 910209,containment Building Penetrations Breached.Caused by Inadequate Procedural Controls.Core Mapping & Cavity Pump Down Activities Secured,Air Hose Removed & Hydrolase Hose capped.W/910306 Ltr ML20029A6471991-02-22022 February 1991 LER 91-004-00:on 910206,sealed Radioactive Source in Storage Not Leak Tested Prior to Use.Caused by Inadequate Procedures for Verifying Leak Testing of Sources.Procedures Revised.W/ 910222 Ltr ML20028H6681991-01-18018 January 1991 LER 90-009-01:on 900719,discovered That Response Time Testing of Pressurizer High Level Reactor Trip Function Not Performed in Accordance W/Tech Spec 3.3.1.1,Table 3.3-2. Caused by Personnel Error.Procedures revised.W/910118 Ltr ML20043H8321990-06-22022 June 1990 LER 90-007-00:on 900523,discovered That Two Sets of Concrete Roof Blocks on Svc Water Pump House Not in Required Safety Position.Caused by Lack of Administrative Controls.Blocks Restored to Required locations.W/900622 Ltr ML20043D5801990-06-0404 June 1990 LER 90-006-00:on 900504,casing Cooling Pump Not Put Into Alert Status & Surveillance Missed.Caused by Personnel Error.Pump 1-RS-P-3B Placed in Alert status.W/900604 Ltr ML20012E3301990-03-27027 March 1990 LER 90-003-00:on 900228,52 Valves Identified Not Included in Tech Spec Required Monthly Containment Integrity Verification Surveillance Program.Caused by Personnel Error & Inadequate Procedure.Procedure revised.W/900327 Ltr ML20012B6441990-03-0808 March 1990 LER 90-001-00:on 900215,inadvertent Partial Train a ESF Actuation of Containment Depressurization Sys Occurred. Caused by Human Error.Evaluation to Be Performed to Determine If Test Points Can Be moved.W/900308 Ltr ML20006E2371990-02-0808 February 1990 LER 90-001-00:on 900123,reactor Trip Occurred on Steam Feedwater Flow Mismatch.Caused by Failed Circuit Driver Card on Feedwater Regulating Valve.Feedwater Regulating Valve Driver Card replaced.W/900208 Ltr ML20006E3771990-02-0505 February 1990 LER 90-002-00:on 900127,fuel Bldg Ventilation Sys Not Aligned to Discharge Through Auxiliary Bldg HEPA Filter & Charcoal Adsorber Assembly During Fuel Movement.Caused by Personnel Error.Disciplinary Action taken.W/900205 Ltr ML20006A8531990-01-19019 January 1990 LER 89-019-00:on 891228,discovered That Outer Door of Containment Equipment Escape Air Lock Was Drawing in Air & Inner Door Noted as Not Being in Fully Closed Position.Cause Undetermined.Sys Enhancements Being evaluated.W/900119 Ltr ML20005F8781990-01-11011 January 1990 LER 89-018-00:on 891219,determined That Three Pressurizer Pressure Safety Injection Instrumentation Channels May Not Have Adequate Margin Between Actuation Setpoint & Bottom of Instrument span.W/900111 Ltr ML19332D5471989-11-22022 November 1989 LER 85-003-03:on 890907,determined That Situation Could Arise Where Water Level Would Rise to 264 Ft Before Next Required Surveillance Interval.Cause Not Determined.Dike to Be constructed.W/891122 Ltr ML20024B7821983-07-0606 July 1983 LER 83-048/03L-0:on 830606 & 17,intermediate Range Channels N35 & N36 High Neutron Flux Reactor Trip Setpoints Exceeded Tech Spec Requirements.Caused by Administrative Error. Setpoints reduced.W/830706 Ltr ML20024C1361983-06-30030 June 1983 LER 83-031/03L-0:on 830614,w/unit at 100% Power,Fire Door S54/5 from Emergency Switchgear Room to Cable Vault Would Not Latch.Fire Watch Posted Immediately.Caused by Misaligned Strike.Door Repaired within 1 h.W/830630 Ltr ML20024C3721983-06-30030 June 1983 LER 83-042/03L-0:on 830606,vital Bus 1-I Momentarily Deenergized While Trying to Clear Inverter Trouble Alarm. Caused by Operator Error.Bus energized.W/830630 Ltr ML20024B9891983-06-28028 June 1983 LER 83-047/03L-0:on 830530,emergency Diesel Generator 2J Tripped on High Crankcase Pressure During Surveillance Testing.Cause Not Determined.Diesel Tested Satisfactorily. W/830628 Ltr ML20024C2941983-06-23023 June 1983 LER 83-044/03L-0:on 830526,during Mode 3,one Recirculation Valve on Each of Two Casing Cooling Pumps Found Open.Caused by Procedure Inadequacy.Valves Closed Immediately.Maint Procedure Will Be revised.W/830623 Ltr ML20024C3071983-06-22022 June 1983 LER 83-034/03L-0:on 830525,during Mode 1,one Header of Control Room Bottled Air Pressurized Sys Had Lower than Required Pressure.Probably Caused by Leak from B Bank of Air Bottles.Header repressurized.W/830622 Ltr ML20024C0971983-06-22022 June 1983 LER 83-045/03L-0:on 830614,Fire Door S71-18,between Emergency Diesel Generator Room 2H & Turbine Bldg,Would Not Latch & Lock.Caused by Stuck Latch.Latch Adjusted & Lubricated.Door Designs modified.W/830622 Ltr ML20023E0951983-06-0101 June 1983 LER 83-027/03L-0:on 830505,one Header (42 Bottles) of Control Room Bottled Air Pressurized Sys Found to Have Lower than Required Pressure (2,290 Vs 2,300 Psig).Probably Caused by Leakage When Compressor malfunctioned.W/830601 Ltr ML20023E0721983-05-26026 May 1983 LER 83-029/03L-0:on 830509,following Rapid Rampdown from 100% to 4% power,I-131 Dose Equivalent Exceeded 1.0 Uci/G. Caused by Unidentified Fuel Element Defect Worsened by post-rampdown Conditions.Sampling increased.W/830526 Ltr ML20023D5371983-05-13013 May 1983 LER 83-022/03L-0:on 830412,review of ASME XI Iwv Program Identified 192 Valves Not Exercised &/Or Stroke Timed.Caused by Fragmented Implementation of Testing Program.Programs Upgraded ML20023D2491983-05-11011 May 1983 LER 83-032/03L-0:on 830412,during Mode 5,visual Insp of Hydraulic Snubber 2-WGCB-HSS-3B Revealed Damaged Reservoir W/O Fluid.Caused by Personnel Working in Area.Snubber Replaced ML20023C5371983-05-10010 May 1983 LER 83-021/03L-0:on 830411,Fire Door S-71-7 Between Svc Bldg Health Physics Area & Auxiliary Bldg Would Not Self Close.Caused by Removal of Reclosure Device for Maint of Closure Coupling.Reclosure Device Reinstalled ML20023B5931983-04-27027 April 1983 LER 83-029/03L-0:on 830402,during Mode 4,automatic Actuation of ECCS Occurred.Caused by Maint Personnel Standing on Conduit Resulting in Loss of lo-lo Pressurizer Pressure Safety Injection Block.Maint Personnel Reinstructed ML20023B5701983-04-27027 April 1983 LER 83-008/03L-0:on 830410,review Revealed That Procedure Used to Restore Boron Injection Tank Concentration Introduced Potential Unanalyzed Injection Flow Diversions. Caused by Oversight.Emergency Procedures Revised ML20028G6541983-02-0909 February 1983 LER 83-003/03L-0:on 830122,during Mode 5,RHR Flow Was Lost for 4 Minutes.Caused by Failure of 15 Kv a Inverter to Ac Vital Bus 1-III,de-energizing Auxiliary Relay for Pressure Channel P-1403.Vital Bus 1-III & RHR Flow Restored ML20028G6311983-02-0909 February 1983 LER 83-016/03L-0:on 830115 & 16,both Open & Closed Containment Isolation Valves TV-SI-200 & TV-CC-204C,train a Position Indication Lights Found Lit.Caused by Leaking Steam Generator Chemical Feed Line Vent Valve ML20028G0781983-01-31031 January 1983 LER 83-001/03L-0:on 830112,primary Grade Water Isolation Valve to Blender 1-CH-217 Remained Open Longer than Tech Spec Requirements.Caused by Personnel Error.Responsible Operator Reinstructed ML20028G0381983-01-28028 January 1983 LER 83-002/03L-0:on 830104,two of Four 2H Emergency Diesel Generator Surveillance Tests Required by Tech Spec Missed During Nov-Dec 1982.Caused by Scheduling Error.Test Frequency Increased to Meet Tech Spec Requirements ML20028G0131983-01-28028 January 1983 LER 83-011/03L-0:on 821119,individual Rod Position Indication Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift.Indicator Channel for Rods B-09 & 02 & F-06 Recalibr ML20028F3501983-01-19019 January 1983 LER 83-008/03L-0:on 830107,during Mode 3,individual Rod Position Indication Deviated from Group Demand Position by Greater than 12 Steps While Withdrawing Shutdown Bank B. Caused by Instrument Drift.Rods Recalibr ML20028E0391983-01-11011 January 1983 Updated LER 82-079/03X-1:on 821126,flow Path from Boric Acid Tanks to RCS Found Inoperable.Caused by Ruptured Diaphragm of Boric Acid Transfer Pump Suction Header Isolation Valve 1-CH-80.Valve Diaphragm Replaced ML20028E0441983-01-11011 January 1983 LER 82-085/03L-0:on 821215,w/unit at Full Power,Emergency Diesel Generator 2J Removed from Svc for 7 H to Adjust Voltage Regulator Response Time.Caused by Voltage Regulator Drift.Procedures Will Be Revised ML20028E0201983-01-11011 January 1983 LER 82-084/03L-0:on 821216,during Full Power,Input from Range Nuclear Instrument N-42 to Comparator Drawer N-50 Was in Defeat.Caused by Failure to Take N-42 Out of Defeat After Deviation Alarm Determination.Operators to Be Reinstructed ML20028E0781983-01-11011 January 1983 LER 82-078/03X-1:on 821125,w/unit in Mode 3,120-volt Ac Vital Bus 1-IV Lost Voltage.Caused by Failure of Normal Power Supply Inverter 1-VB-I-04,due to Failed Oscillator Board,Transformer & Fuse.Components Replaced ML20028D1311983-01-0505 January 1983 LER 82-083/03L-0:on 821213,emergency Diesel Generator 2J Removed from Svc.Caused by Failure of 40X Unexcitation Alarm Relay Coil.Carbon Deposits & Arcing Damage of 40/76 Relay Contact Prevented Good Contact ML20028D1571983-01-0505 January 1983 Updated LER 81-071/03X-2:on 810911,hydraulic Snubber on Main Steam Line Discovered Inoperable Due to Loss of Oil from Reservoir.Caused by Leak Due to Scored Brass Bushing on Piston Shaft.Snubber Purged & Refilled.Reach Rod Retorqued ML20028C5191982-12-31031 December 1982 LER 82-083/03L-0:on 821204,while Operating at 17% Rated Thermal Power,Turbine Control Sys Malfunctioned Causing Sudden Increase in Load,Resulting in Reactor Trip.Caused by Malfunction of Analog Converter ML20028A8651982-11-16016 November 1982 LER 82-067/03L-0:on 821019,suction to RHR Sys Pumps a & B Lost for 36 Minutes.On 821020,pump Suction Lost for 33 Minutes.Caused by Ambiguous RCS Level Indication While Water Drained to Centerline of Nozzles.Water Added ML20028A8821982-11-16016 November 1982 LER 82-060/03L-0:on 821019,station Battery I-IV Failed 18- Month Discharge Surveillance Test.Caused by Natural End of Life.Battery Replaced ML20028A9781982-11-16016 November 1982 LER 82-071/03L-0:on 821027,control Power for B Casing Cooling Pump Found de-energized.Caused by Opened Circuit Breaker Unintentionally Disturbed by Workers.Circuit Breaker Closed & Power Verified 1994-04-25
[Table view] Category:RO)
MONTHYEARML20029D0201994-04-25025 April 1994 LER 94-007-01:on 931014,high Head Safety Injection Flow Balance Testing Found to Be Below TS Requirement.Caused by Unaccounted for Uncertainties.Cold Leg Safety Injection Leg Throttle Valve adjusted.W/940425 Ltr ML20045G9391993-07-0808 July 1993 Lr 93-017-00:on 930616,containment Hydrogen Analyzer Heat Trace Channel Calibration Not Performed on Staggered Test Basis Due to Inadequate Implementation of TS Amend.Test Procedure Satisfactorily performed.W/930708 Ltr ML20044H1591993-05-27027 May 1993 LER 93-016-00:on 930509,discovered That Containment Hydrogen Analyzer Pressure Switch PS-3 Sensing Line Disconnected in Local Panel.Caused by Personnel Error. Pressure Switch Calibr & Line reconnected.W/930527 Ltr ML20044D5711993-05-14014 May 1993 LER 93-002-00:on 930416,automatic Reactor Trip Initiated from Turbine Trip Due to Over Excitation of Main Generator. Emergency Procedure 2-E-0 Entered & Individuals Involved in Event Received Remediated training.W/930514 Ltr ML20044D2281993-05-12012 May 1993 LER 93-003-00:on 930424,manual Reactor Trip Initiated Due to Erratic Feedwater Flow Indications to SG C & Excessive Main Feedwater Regulating Valve Oscillations.Caused by Design Instabilities.Secondary Sys secured.W/930512 Ltr ML20044C9541993-05-0707 May 1993 LER 93-015-00:on 930427,discovered That Portions of Containment Pressure Channels That Input to Containment Spray hi-hi Pressure Not Tested Monthly.Caused by Personnel Error.Test Procedures changed.W/930507 Ltr ML20044C9811993-05-0606 May 1993 LER 93-014-00:on 930411,as-found Speed Setting of Steam Driven AFW Pump 1-FW-P-2 Found Below Required TS Limit. Caused by Incorrect Speed Control Setting.Pump Speed Adjusted & Maint Personnel counseled.W/930506 Ltr ML20024G6841991-04-18018 April 1991 LER 91-006-00:on 910403,discovered That Ac Offsite Power Source Surveillance Not Performed Due to Personnel Error. Surveillance Initiated Immediately & Positive Discipline Administered to supervisor.W/910418 Ltr ML20029B5601991-03-0606 March 1991 LER 91-005-00:on 910209,containment Building Penetrations Breached.Caused by Inadequate Procedural Controls.Core Mapping & Cavity Pump Down Activities Secured,Air Hose Removed & Hydrolase Hose capped.W/910306 Ltr ML20029A6471991-02-22022 February 1991 LER 91-004-00:on 910206,sealed Radioactive Source in Storage Not Leak Tested Prior to Use.Caused by Inadequate Procedures for Verifying Leak Testing of Sources.Procedures Revised.W/ 910222 Ltr ML20028H6681991-01-18018 January 1991 LER 90-009-01:on 900719,discovered That Response Time Testing of Pressurizer High Level Reactor Trip Function Not Performed in Accordance W/Tech Spec 3.3.1.1,Table 3.3-2. Caused by Personnel Error.Procedures revised.W/910118 Ltr ML20043H8321990-06-22022 June 1990 LER 90-007-00:on 900523,discovered That Two Sets of Concrete Roof Blocks on Svc Water Pump House Not in Required Safety Position.Caused by Lack of Administrative Controls.Blocks Restored to Required locations.W/900622 Ltr ML20043D5801990-06-0404 June 1990 LER 90-006-00:on 900504,casing Cooling Pump Not Put Into Alert Status & Surveillance Missed.Caused by Personnel Error.Pump 1-RS-P-3B Placed in Alert status.W/900604 Ltr ML20012E3301990-03-27027 March 1990 LER 90-003-00:on 900228,52 Valves Identified Not Included in Tech Spec Required Monthly Containment Integrity Verification Surveillance Program.Caused by Personnel Error & Inadequate Procedure.Procedure revised.W/900327 Ltr ML20012B6441990-03-0808 March 1990 LER 90-001-00:on 900215,inadvertent Partial Train a ESF Actuation of Containment Depressurization Sys Occurred. Caused by Human Error.Evaluation to Be Performed to Determine If Test Points Can Be moved.W/900308 Ltr ML20006E2371990-02-0808 February 1990 LER 90-001-00:on 900123,reactor Trip Occurred on Steam Feedwater Flow Mismatch.Caused by Failed Circuit Driver Card on Feedwater Regulating Valve.Feedwater Regulating Valve Driver Card replaced.W/900208 Ltr ML20006E3771990-02-0505 February 1990 LER 90-002-00:on 900127,fuel Bldg Ventilation Sys Not Aligned to Discharge Through Auxiliary Bldg HEPA Filter & Charcoal Adsorber Assembly During Fuel Movement.Caused by Personnel Error.Disciplinary Action taken.W/900205 Ltr ML20006A8531990-01-19019 January 1990 LER 89-019-00:on 891228,discovered That Outer Door of Containment Equipment Escape Air Lock Was Drawing in Air & Inner Door Noted as Not Being in Fully Closed Position.Cause Undetermined.Sys Enhancements Being evaluated.W/900119 Ltr ML20005F8781990-01-11011 January 1990 LER 89-018-00:on 891219,determined That Three Pressurizer Pressure Safety Injection Instrumentation Channels May Not Have Adequate Margin Between Actuation Setpoint & Bottom of Instrument span.W/900111 Ltr ML19332D5471989-11-22022 November 1989 LER 85-003-03:on 890907,determined That Situation Could Arise Where Water Level Would Rise to 264 Ft Before Next Required Surveillance Interval.Cause Not Determined.Dike to Be constructed.W/891122 Ltr ML20024B7821983-07-0606 July 1983 LER 83-048/03L-0:on 830606 & 17,intermediate Range Channels N35 & N36 High Neutron Flux Reactor Trip Setpoints Exceeded Tech Spec Requirements.Caused by Administrative Error. Setpoints reduced.W/830706 Ltr ML20024C1361983-06-30030 June 1983 LER 83-031/03L-0:on 830614,w/unit at 100% Power,Fire Door S54/5 from Emergency Switchgear Room to Cable Vault Would Not Latch.Fire Watch Posted Immediately.Caused by Misaligned Strike.Door Repaired within 1 h.W/830630 Ltr ML20024C3721983-06-30030 June 1983 LER 83-042/03L-0:on 830606,vital Bus 1-I Momentarily Deenergized While Trying to Clear Inverter Trouble Alarm. Caused by Operator Error.Bus energized.W/830630 Ltr ML20024B9891983-06-28028 June 1983 LER 83-047/03L-0:on 830530,emergency Diesel Generator 2J Tripped on High Crankcase Pressure During Surveillance Testing.Cause Not Determined.Diesel Tested Satisfactorily. W/830628 Ltr ML20024C2941983-06-23023 June 1983 LER 83-044/03L-0:on 830526,during Mode 3,one Recirculation Valve on Each of Two Casing Cooling Pumps Found Open.Caused by Procedure Inadequacy.Valves Closed Immediately.Maint Procedure Will Be revised.W/830623 Ltr ML20024C3071983-06-22022 June 1983 LER 83-034/03L-0:on 830525,during Mode 1,one Header of Control Room Bottled Air Pressurized Sys Had Lower than Required Pressure.Probably Caused by Leak from B Bank of Air Bottles.Header repressurized.W/830622 Ltr ML20024C0971983-06-22022 June 1983 LER 83-045/03L-0:on 830614,Fire Door S71-18,between Emergency Diesel Generator Room 2H & Turbine Bldg,Would Not Latch & Lock.Caused by Stuck Latch.Latch Adjusted & Lubricated.Door Designs modified.W/830622 Ltr ML20023E0951983-06-0101 June 1983 LER 83-027/03L-0:on 830505,one Header (42 Bottles) of Control Room Bottled Air Pressurized Sys Found to Have Lower than Required Pressure (2,290 Vs 2,300 Psig).Probably Caused by Leakage When Compressor malfunctioned.W/830601 Ltr ML20023E0721983-05-26026 May 1983 LER 83-029/03L-0:on 830509,following Rapid Rampdown from 100% to 4% power,I-131 Dose Equivalent Exceeded 1.0 Uci/G. Caused by Unidentified Fuel Element Defect Worsened by post-rampdown Conditions.Sampling increased.W/830526 Ltr ML20023D5371983-05-13013 May 1983 LER 83-022/03L-0:on 830412,review of ASME XI Iwv Program Identified 192 Valves Not Exercised &/Or Stroke Timed.Caused by Fragmented Implementation of Testing Program.Programs Upgraded ML20023D2491983-05-11011 May 1983 LER 83-032/03L-0:on 830412,during Mode 5,visual Insp of Hydraulic Snubber 2-WGCB-HSS-3B Revealed Damaged Reservoir W/O Fluid.Caused by Personnel Working in Area.Snubber Replaced ML20023C5371983-05-10010 May 1983 LER 83-021/03L-0:on 830411,Fire Door S-71-7 Between Svc Bldg Health Physics Area & Auxiliary Bldg Would Not Self Close.Caused by Removal of Reclosure Device for Maint of Closure Coupling.Reclosure Device Reinstalled ML20023B5931983-04-27027 April 1983 LER 83-029/03L-0:on 830402,during Mode 4,automatic Actuation of ECCS Occurred.Caused by Maint Personnel Standing on Conduit Resulting in Loss of lo-lo Pressurizer Pressure Safety Injection Block.Maint Personnel Reinstructed ML20023B5701983-04-27027 April 1983 LER 83-008/03L-0:on 830410,review Revealed That Procedure Used to Restore Boron Injection Tank Concentration Introduced Potential Unanalyzed Injection Flow Diversions. Caused by Oversight.Emergency Procedures Revised ML20028G6541983-02-0909 February 1983 LER 83-003/03L-0:on 830122,during Mode 5,RHR Flow Was Lost for 4 Minutes.Caused by Failure of 15 Kv a Inverter to Ac Vital Bus 1-III,de-energizing Auxiliary Relay for Pressure Channel P-1403.Vital Bus 1-III & RHR Flow Restored ML20028G6311983-02-0909 February 1983 LER 83-016/03L-0:on 830115 & 16,both Open & Closed Containment Isolation Valves TV-SI-200 & TV-CC-204C,train a Position Indication Lights Found Lit.Caused by Leaking Steam Generator Chemical Feed Line Vent Valve ML20028G0781983-01-31031 January 1983 LER 83-001/03L-0:on 830112,primary Grade Water Isolation Valve to Blender 1-CH-217 Remained Open Longer than Tech Spec Requirements.Caused by Personnel Error.Responsible Operator Reinstructed ML20028G0381983-01-28028 January 1983 LER 83-002/03L-0:on 830104,two of Four 2H Emergency Diesel Generator Surveillance Tests Required by Tech Spec Missed During Nov-Dec 1982.Caused by Scheduling Error.Test Frequency Increased to Meet Tech Spec Requirements ML20028G0131983-01-28028 January 1983 LER 83-011/03L-0:on 821119,individual Rod Position Indication Deviated from Group Demand Position by Greater than 12 Steps.Caused by Instrument Drift.Indicator Channel for Rods B-09 & 02 & F-06 Recalibr ML20028F3501983-01-19019 January 1983 LER 83-008/03L-0:on 830107,during Mode 3,individual Rod Position Indication Deviated from Group Demand Position by Greater than 12 Steps While Withdrawing Shutdown Bank B. Caused by Instrument Drift.Rods Recalibr ML20028E0391983-01-11011 January 1983 Updated LER 82-079/03X-1:on 821126,flow Path from Boric Acid Tanks to RCS Found Inoperable.Caused by Ruptured Diaphragm of Boric Acid Transfer Pump Suction Header Isolation Valve 1-CH-80.Valve Diaphragm Replaced ML20028E0441983-01-11011 January 1983 LER 82-085/03L-0:on 821215,w/unit at Full Power,Emergency Diesel Generator 2J Removed from Svc for 7 H to Adjust Voltage Regulator Response Time.Caused by Voltage Regulator Drift.Procedures Will Be Revised ML20028E0201983-01-11011 January 1983 LER 82-084/03L-0:on 821216,during Full Power,Input from Range Nuclear Instrument N-42 to Comparator Drawer N-50 Was in Defeat.Caused by Failure to Take N-42 Out of Defeat After Deviation Alarm Determination.Operators to Be Reinstructed ML20028E0781983-01-11011 January 1983 LER 82-078/03X-1:on 821125,w/unit in Mode 3,120-volt Ac Vital Bus 1-IV Lost Voltage.Caused by Failure of Normal Power Supply Inverter 1-VB-I-04,due to Failed Oscillator Board,Transformer & Fuse.Components Replaced ML20028D1311983-01-0505 January 1983 LER 82-083/03L-0:on 821213,emergency Diesel Generator 2J Removed from Svc.Caused by Failure of 40X Unexcitation Alarm Relay Coil.Carbon Deposits & Arcing Damage of 40/76 Relay Contact Prevented Good Contact ML20028D1571983-01-0505 January 1983 Updated LER 81-071/03X-2:on 810911,hydraulic Snubber on Main Steam Line Discovered Inoperable Due to Loss of Oil from Reservoir.Caused by Leak Due to Scored Brass Bushing on Piston Shaft.Snubber Purged & Refilled.Reach Rod Retorqued ML20028C5191982-12-31031 December 1982 LER 82-083/03L-0:on 821204,while Operating at 17% Rated Thermal Power,Turbine Control Sys Malfunctioned Causing Sudden Increase in Load,Resulting in Reactor Trip.Caused by Malfunction of Analog Converter ML20028A8651982-11-16016 November 1982 LER 82-067/03L-0:on 821019,suction to RHR Sys Pumps a & B Lost for 36 Minutes.On 821020,pump Suction Lost for 33 Minutes.Caused by Ambiguous RCS Level Indication While Water Drained to Centerline of Nozzles.Water Added ML20028A8821982-11-16016 November 1982 LER 82-060/03L-0:on 821019,station Battery I-IV Failed 18- Month Discharge Surveillance Test.Caused by Natural End of Life.Battery Replaced ML20028A9781982-11-16016 November 1982 LER 82-071/03L-0:on 821027,control Power for B Casing Cooling Pump Found de-energized.Caused by Opened Circuit Breaker Unintentionally Disturbed by Workers.Circuit Breaker Closed & Power Verified 1994-04-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
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Attachment:
Page 1 of 3 Docket No. 50-338 Report No. LER 80-47/01T-0 l
Description of Event At 0146 on May 23, 1980, a Safety Injection occurred due to high steam line flow signal coincident with lo-lo T . This event resulted from the loss of Vital Bus I-III. At 0146, oniy* Train A of Safety Injection was actuated because the loss of Vital Bus 1-III deenergized the Solid State Protection System output cabinet for Train B. When power was restored to Vital Bus 1-III at 0148, Train B of Safety Injection was actuated. There was no release of radioactivity j during the transient.
As a result of the Safety Injection, the contents of the Boron Injection Tank (BIT) were flushed to the Reactor Coolant System which caused the concentration of the BIT to fall below the Tech. Spec, limit of 20,000 PPM borated water. Although the Tech. Spec. Limiting Condition for Operation was not met following the event, the BIT did perform its intended function.
As a result of the Safety Injection, the Refueling Water Storage Tank (RWST) level dropped below the 478,058 gallon limit required by T.S. 3.1.2.8.b.1 because the safety injection pumps draw suction from this tank to provide for the cold leg injection. Therefore, the RWST performed its function as intended.
As a result of the Safety Injection, the level in the Emergency Condensate Storage Tank (ECST) went below the value given in T.S. 3.7.1.3.
This is an expected occurrence following an ECCS actuation since the i auxiliary feedwater pumps take suction from this tank and start on a SI
) Signal to feed water to the steam generators. The ECST performed its j design function.
i During the Safety Injection the following unexpected events occurred i
which are contrary to Technical Specifications.
Upon receiving the Safety Injection Signal, emergency diesel generator 1H automatically started as designed; however, it tripped shortly thereafter on overspeed. The trip was reset and the diesel was
- successfully restarted to verify operability. This is a second occurance of diesel overspeed following a Safety Injection. The periodic test on IJ diesel generator was in progress at the time of the Safety Injection following preventative maintenance on the IJ diesel. The required one hour run on the IJ diesel had been completed and the diesel was paralleling the normal power supply to the emergency bus.
Also, fcllowing the Safety Injection a hi-hi containment pressure alarm was locked in due to a failed compstator card due to blown fuses.
The card fails in the safe (tripped) mode. The card was replaced and recalibrated.
The ECCS actuation is reportable per T.S. 3.5.2 and 6.9.2. However, Regulatory Guide 1.16 states that ECCS actuations are reportable under Unit 1 T.S. 6.9.1.8.i which requires a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notice and written follow up. This report is intended to meet the additional requirements of the 90 day report for T.S. 6.9.2.
The other events included in this discussion are reportable as 30 day items by T.S. 6.9.1.9.b.
This is the sixth actuation of the Emergency Core Cooling System reportable under T.S. 6.9.2.
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Attachment 2 of 3 Probable Consequences of Occurence The purpose of the Emergency Core Cooling System is to ensure adequate cooling of the reactor in the event of a loss of coolant accident. Although the safety injection system performed its intended function to inject borated water into the Reactor Coolant System, an actual accident condition did not exist and therefore the SI was not required. As a result, the health and safety of the general public were not affected.
Cause of Event The cause of the Safety Injection was the loss of Vital Bus I-III which removes power from feedwater flow / steam flow comparators for all three steam generators producing a high steam line flow signal. The loss of Vital Bus 1-III also cuts off supply of cooling water to the Reactor Coolant Pumps. The loss of coolant flow requires the operator to trip the Reactor Coolant Pumps which was done at 0141 stopping flow thru the RTD bypass lines. Due to ambient losses, the temperature in these lines dropped to the lo-lo T setpoint which together with the high steam line flow signal produc$3'the Safety Injection Signal.
The loss of Vital Bus 1-III was caused as a result of starting "A" Reactor Coolant Pump. The start of "A" RCP on Unit I at 0136 on 05-23-80 with the other two RCP's on Unit I and all three RCP's on Unit 2 running caused a reduction in voltage on "A" Reserve Station Service to which "1J" emergency bus is connected. At this time "1J" diesel was tied to this bus and it picked up load. The normal feeder breaker, 15J11, was tripped by directional overload relays. This caused a load rejection fror "1J" diesel. It is postulated that this load rejection caused a surge in voltage which was transmitted thru the battery charger and the batteries to 1-III inverter which blew two fuses, cau ing a loss of Vital Bus I-III.
The low levels in the RWST and ECST, and the loss of boric acid from the BIT, are all normal results of a Safety Injection and are expected to occur.
, The IH diesel generator tripped on overspeed following its automatic start because the governor failed to operate properly. Possible sticking or worn parts caused the governor to operate sluggishly.
The fuses in the comparator card for hi-hi containment pressure were apparently blown when Vital Bus 1-III was restored.
Immediate Corrective Action The Safety Injection Signal was reset at 0149 and Safety Injection was terminated by the control room operators in accordance with the applicable Emergency Procedure at 0151 when Reactor Coolant System letdown was established and cold leg injection flow was secured.
The operators refilled the RWST and ECST and reborated the BIT to their proper limits as required by the appropriate Technical Specification ACTION statements.
The governor on diesel generator 1H was replaced with a rebuilt govtrnor and several adjustments were made by the vendor representative.
The diesel generator was retested by special testing and determined to be operable.
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Attachment:
Page 3 of 3 The comparator card for hi-hi containment pressure was replaced.
The Vital Bus 1-III was restored by switching the power supply from the inverter to the voltage regulating transformer which was done at 0148 on 05-23-80. The blown fuses in the inverter were later replaced and the inverter put back in service.
Scheduled Corrective Action Operating procedures will be changed to caution against starting a Reactor Coolant Pump or other large loads if an Emergency Diesel Generator is tied to the same Reserve Station Service Bus as the Reactor Coolant Pump. Also, procedures will be changed to caution against adding large loads above prescribed Reserve Station Service loads.
The governor from "1H" Emergency Diesel Generator will be sent to the manufacturer for inspection. Diesel governors are scheduled to be replaced with rebuilt governors on a rotating basis for both Unit 1 and 2.
Fuses on all four inverters will be replaced.
Actions Taken to Prevent Recurrence A standing order was issued to avoid starting a Reactor Coolant Pump if an Emergency Diesel Generator is tied to the same Reserve Station Service Bus as the Reactor Coolant Pump.
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