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 Issue dateTitleTopic
PNO-II-99-017, on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground18 May 1999PNO-II-99-017:on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground
PNO-II-99-015, on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws5 May 1999PNO-II-99-015:on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws
PNO-II-98-037A, on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed28 August 1998PNO-II-98-037A:on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed
PNO-II-98-037, on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified10 August 1998PNO-II-98-037:on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified
PNO-II-98-025, on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed11 May 1998PNO-II-98-025:on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be DevelopedDownpower
PNO-II-97-066, on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc31 December 1997PNO-II-97-066:on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc
PNO-II-97-064, on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation29 December 1997PNO-II-97-064:on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation
PNO-II-96-083, on 961214,Unit 2 Shutdown Due to Small Amount of Backleakage Through Injection Sys Discharge Check Valve, Causing Gas Entrainment in B Train of RHR Sys.Nrc Resident Inspectors Observed Unit Shutdown & RHR Testing16 December 1996PNO-II-96-083:on 961214,Unit 2 Shutdown Due to Small Amount of Backleakage Through Injection Sys Discharge Check Valve, Causing Gas Entrainment in B Train of RHR Sys.Nrc Resident Inspectors Observed Unit Shutdown & RHR Testing
PNO-II-96-082, on 961206,Unit 1 Taken Off Line in Order to Investigate/Locate Source of Increase in Unidentified Leakage.Nrc Resident Inspectors Will Continue to Closely Monitor Licensee Recovery Activities6 December 1996PNO-II-96-082:on 961206,Unit 1 Taken Off Line in Order to Investigate/Locate Source of Increase in Unidentified Leakage.Nrc Resident Inspectors Will Continue to Closely Monitor Licensee Recovery ActivitiesUnidentified leakage
PNO-II-93-021, on 930503,NRC Duty Officer Notified of Suspension of Licensed Operator Who Admitted to Offsite Arrest for Possession of Cocaine.Region II Monitoring Licensee Ongoing Investigation4 May 1993PNO-II-93-021:on 930503,NRC Duty Officer Notified of Suspension of Licensed Operator Who Admitted to Offsite Arrest for Possession of Cocaine.Region II Monitoring Licensee Ongoing Investigation
PNO-II-93-014, on 930324,NRC Duty Officer Notified That Previous Random Screening for Drugs of Licensed Reactor Operator at Plant Had Been Confirmed Positive for Cocaine. State of Sc & Local Officials Have Been Notified26 March 1993PNO-II-93-014:on 930324,NRC Duty Officer Notified That Previous Random Screening for Drugs of Licensed Reactor Operator at Plant Had Been Confirmed Positive for Cocaine. State of Sc & Local Officials Have Been Notified
PNO-II-91-004, on 910227,facility Shutdown Exceeded 48 H. Caused by Leaking Exciter Cooling Water Sys.Sys Under Investigation28 February 1991PNO-II-91-004:on 910227,facility Shutdown Exceeded 48 H. Caused by Leaking Exciter Cooling Water Sys.Sys Under Investigation
PNO-II-89-012, on 890215,security Guard Claimed to Have Been Assaulted Onsite.Guard Treated & Released from Hosp.Guard Involved in Security Event on 890113 Re Inattentiveness on Post.Guard Claimed Inattentiveness Due to Illness16 February 1989PNO-II-89-012:on 890215,security Guard Claimed to Have Been Assaulted Onsite.Guard Treated & Released from Hosp.Guard Involved in Security Event on 890113 Re Inattentiveness on Post.Guard Claimed Inattentiveness Due to Illness
PNO-II-88-047, on 880805,unit Shut Down Due to Primary to Secondary Leak in D Steam Generator.Generator Found to Have Unretrievable Part in Secondary Side During Last Outage.Eddy Current Tests of Two Generators Planned8 August 1988PNO-II-88-047:on 880805,unit Shut Down Due to Primary to Secondary Leak in D Steam Generator.Generator Found to Have Unretrievable Part in Secondary Side During Last Outage.Eddy Current Tests of Two Generators PlannedEddy Current Testing
PNO-II-88-044, on 880716,reactor Shut Down for Repair of Failed Charging Pump 2A.Shutdown Exceeded 48 H.Cause of Failure Under Investigation.Disassembly & Replacement of Pump Rotating Element Necessary.Startup Expected on 88072118 July 1988PNO-II-88-044:on 880716,reactor Shut Down for Repair of Failed Charging Pump 2A.Shutdown Exceeded 48 H.Cause of Failure Under Investigation.Disassembly & Replacement of Pump Rotating Element Necessary.Startup Expected on 880721
PNO-II-88-018A, suppl to PNO-II-88-018A,issued on 880309. NRC Augmented Insp Team on 880309 Has Completed Onsite Segment of Intended Mission.Licensee Given Concurrence to Restart Unit 2 on 880318 Based on Review of Insp Results18 March 1988PNO-II-88-018A:suppl to PNO-II-88-018A,issued on 880309. NRC Augmented Insp Team on 880309 Has Completed Onsite Segment of Intended Mission.Licensee Given Concurrence to Restart Unit 2 on 880318 Based on Review of Insp Results
PNO-II-88-018, on 880309,unit Tripped from 21% Power Resulting in Feedwater Isolation Which Caused Steam Generator Levels to Decrease10 March 1988PNO-II-88-018:on 880309,unit Tripped from 21% Power Resulting in Feedwater Isolation Which Caused Steam Generator Levels to Decrease
PNO-II-88-016, approx Six Gallons of Hydrazine Was Discharged Into Lake Wylie from Waste Water Treatment Pond at Catawba Nuclear Station Near York,Sc,Between Hrs of 9:40 Monday Night & 9:20 Tuesday Morning3 March 1988PNO-II-88-016:approx Six Gallons of Hydrazine Was Discharged Into Lake Wylie from Waste Water Treatment Pond at Catawba Nuclear Station Near York,Sc,Between Hrs of 9:40 Monday Night & 9:20 Tuesday Morning
PNO-II-88-012, on 880208,small Unplanned Gas Released Into Auxiliary Bldg & Ventilated to Atmosphere.Release within Allowable Limits & Not Required to Be Reported to Nrc.States of Sc & Nc Informed9 February 1988PNO-II-88-012:on 880208,small Unplanned Gas Released Into Auxiliary Bldg & Ventilated to Atmosphere.Release within Allowable Limits & Not Required to Be Reported to Nrc.States of Sc & Nc Informed
PNO-II-87-033, on 870522,plant Taken Out of Svc to Repair Two Leaks in Resistance Temp Detector Loop on RCS Cold Leg. Shutdown of Greater than 48 H Estimated for Cleanup of Boric Acid & Repair.Unit Will Remain in Hot Standby22 May 1987PNO-II-87-033:on 870522,plant Taken Out of Svc to Repair Two Leaks in Resistance Temp Detector Loop on RCS Cold Leg. Shutdown of Greater than 48 H Estimated for Cleanup of Boric Acid & Repair.Unit Will Remain in Hot StandbyBoric Acid
PNO-II-87-015A, on 870305,two High Temp Bearing Trips Occurred.Caused by Failure of California Controls Eutectic Type Temp Sensors.No Damage,Unusual Wear or Excessive Temps Revealed.Diesel Generator 1-B Journal Bearing Refurbished11 March 1987PNO-II-87-015A:on 870305,two High Temp Bearing Trips Occurred.Caused by Failure of California Controls Eutectic Type Temp Sensors.No Damage,Unusual Wear or Excessive Temps Revealed.Diesel Generator 1-B Journal Bearing Refurbished
PNO-II-87-015, on 870305,unit out-of-svc Greater than 48 H. Caused by Damaged Journal Bearing in One Tdi Diesel Generator.Damaged Bearing Found During Routine Maint & Replaced6 March 1987PNO-II-87-015:on 870305,unit out-of-svc Greater than 48 H. Caused by Damaged Journal Bearing in One Tdi Diesel Generator.Damaged Bearing Found During Routine Maint & Replaced
PNO-II-86-063, on 860901,plant Shut Down Due to Main Generator Turbine Trip Resulting from phase-to-phase Fault. Investigation of Cause & Full Extent of Damage Continuing. Unit Will Be Out of Svc for at Least 3 Months4 September 1986PNO-II-86-063:on 860901,plant Shut Down Due to Main Generator Turbine Trip Resulting from phase-to-phase Fault. Investigation of Cause & Full Extent of Damage Continuing. Unit Will Be Out of Svc for at Least 3 Months
PNO-II-86-057, on 860809,while Unit in Hot Standby,Reactor Coolant Pumps Experienced Seal Failure.Leak Initially Estimated at 60 Gpm But Decreased to 30 Gpm After Affected Pump Tripped.Unit Shut Down to Repair Pump Seals12 August 1986PNO-II-86-057:on 860809,while Unit in Hot Standby,Reactor Coolant Pumps Experienced Seal Failure.Leak Initially Estimated at 60 Gpm But Decreased to 30 Gpm After Affected Pump Tripped.Unit Shut Down to Repair Pump Seals
PNO-II-86-045B, on 860628-0701,augmented Insp Team Sent to Plant.Corrective Action Documented in 860630 Confirmatory Action Ltr Being Monitored by NRC Resident Inspectors.Plant at 6% Power7 July 1986PNO-II-86-045B:on 860628-0701,augmented Insp Team Sent to Plant.Corrective Action Documented in 860630 Confirmatory Action Ltr Being Monitored by NRC Resident Inspectors.Plant at 6% Power
PNO-II-86-045A, primary Sys Temp Dropped from 550 F to 465 F in 6 Minutes.Reactor Coolant Pumps Operated Throughout Event.Poor Human Factor Design Features Caused Operators Not to Be in Control1 July 1986PNO-II-86-045A:primary Sys Temp Dropped from 550 F to 465 F in 6 Minutes.Reactor Coolant Pumps Operated Throughout Event.Poor Human Factor Design Features Caused Operators Not to Be in Control
PNO-II-86-045, on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated27 June 1986PNO-II-86-045:on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated
PNO-II-86-041, on 860613,25 Gpm Leak Discovered Inside Containment.Caused by 360-degree Crack in Socket Weld to Flange for Variable Orifice Control Valve Outlet Side.Weld Will Be Analyzed by Westinghouse for Metal Fatigue17 June 1986PNO-II-86-041:on 860613,25 Gpm Leak Discovered Inside Containment.Caused by 360-degree Crack in Socket Weld to Flange for Variable Orifice Control Valve Outlet Side.Weld Will Be Analyzed by Westinghouse for Metal Fatigue
PNO-II-86-033, on 860508,Unit 2 Achieved Initial Criticality. All Parameters Near Anticipated Levels.Region II Based & Resident Inspectors Witnessed Event.Util Issuing News Release9 May 1986PNO-II-86-033:on 860508,Unit 2 Achieved Initial Criticality. All Parameters Near Anticipated Levels.Region II Based & Resident Inspectors Witnessed Event.Util Issuing News Release
PNO-II-86-018, on 860225,facility Began Initial Fuel Loading25 February 1986PNO-II-86-018:on 860225,facility Began Initial Fuel Loading
PNO-II-85-123, on 851230,two Contractor Vehicles Used to Provide Svc to Cafeteria Were Allowed Escorted Entry Into Licensee Protected Area.One of Vehicle Drivers Produced .38 Caliber Revolver Upon Entering Protected Area30 December 1985PNO-II-85-123:on 851230,two Contractor Vehicles Used to Provide Svc to Cafeteria Were Allowed Escorted Entry Into Licensee Protected Area.One of Vehicle Drivers Produced .38 Caliber Revolver Upon Entering Protected Area
PNO-II-85-115, licensee Reported That Transamerica Delaval DG 2B Experienced Two Failures of Main Bearing Number 7 During Test Runs Following tear-down Inspection.Believed That First Failure Due to Inadequately Supported Bearing6 December 1985PNO-II-85-115:licensee Reported That Transamerica Delaval DG 2B Experienced Two Failures of Main Bearing Number 7 During Test Runs Following tear-down Inspection.Believed That First Failure Due to Inadequately Supported Bearing
PNO-II-85-096, on 851018,reactor Shut Down Due to Unidentified RCS Leak of 1.3 Gpm.Cause Under Investigation. Probably Caused by RHR Valve Packing Leak.Plant in Hot Standby for 72 H21 October 1985PNO-II-85-096:on 851018,reactor Shut Down Due to Unidentified RCS Leak of 1.3 Gpm.Cause Under Investigation. Probably Caused by RHR Valve Packing Leak.Plant in Hot Standby for 72 HPacking leak
PNO-II-85-057, on 850606,during Routine Patrol,Breach of Plant Vital Area Discovered.Security Panel in Vent Duct Adjacent to Fire Door Bent Back.Security Officer Posted at Barrier.No Abnormal Conditions Found in Vital Area7 June 1985PNO-II-85-057:on 850606,during Routine Patrol,Breach of Plant Vital Area Discovered.Security Panel in Vent Duct Adjacent to Fire Door Bent Back.Security Officer Posted at Barrier.No Abnormal Conditions Found in Vital Area
PNO-II-85-004, on 850107,initial Criticality Achieved.All Parameters within Predicted Ranges.Low Power Testing Proceeding According to Schedule8 January 1985PNO-II-85-004:on 850107,initial Criticality Achieved.All Parameters within Predicted Ranges.Low Power Testing Proceeding According to Schedule
PNO-II-82-070, on 820618,radiography Crew Experienced Disconnection of Radioactive Source While Source Outside Shield.Caused Not Stated.Source Safely Returned to Shield22 June 1982PNO-II-82-070:on 820618,radiography Crew Experienced Disconnection of Radioactive Source While Source Outside Shield.Caused Not Stated.Source Safely Returned to ShieldOverexposure
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