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| Issue date | Title | Topic | |
|---|---|---|---|
| PNO-II-96-081, on 961112,Unit 2 Experienced Turbine Generator Trip from 100% Power.Investigation Into Cause of Turbine Generator Trip Revealed Ground Fault on Main Generator Stator Phase a Windings.Addl Followup Will Be Performed | 13 November 1996 | PNO-II-96-081:on 961112,Unit 2 Experienced Turbine Generator Trip from 100% Power.Investigation Into Cause of Turbine Generator Trip Revealed Ground Fault on Main Generator Stator Phase a Windings.Addl Followup Will Be Performed | |
| PNO-II-92-020, on 920327,hot Particle Was Detected on Forehead of Health Physics Technician When Exiting Radiation Control Area.No Erythema Was Oberved & Employee Scheduled to Visit Company Physician as Precaution | 30 March 1992 | PNO-II-92-020:on 920327,hot Particle Was Detected on Forehead of Health Physics Technician When Exiting Radiation Control Area.No Erythema Was Oberved & Employee Scheduled to Visit Company Physician as Precaution | |
| PNO-II-89-066A, updates Status of Hurricane Hugo for Nuclear Facilities in Southeast.Manning of Incident Response Ctr by Region II Continuing | 21 September 1989 | PNO-II-89-066A:updates Status of Hurricane Hugo for Nuclear Facilities in Southeast.Manning of Incident Response Ctr by Region II Continuing | |
| PNO-II-89-026, 80,000 1b Reactor Coolant Pump Motor Enroute to Cheswick,Pa Collapsed One Side of Low Boy Trailer Resulting in Small Brush Fire.Surveys at Site Confirmed No Contamination.Commonwealth of VA Health Dept Notified | 27 March 1989 | PNO-II-89-026:80,000 1b Reactor Coolant Pump Motor Enroute to Cheswick,Pa Collapsed One Side of Low Boy Trailer Resulting in Small Brush Fire.Surveys at Site Confirmed No Contamination.Commonwealth of VA Health Dept Notified | |
| PNO-II-89-015A, on 890225,primary to Secondary Steam Generator Tube Leak at Plant.Caused by Mechanical Failure. Eddy Current & Boroscopic Insps of Affected Tube Will Be Conducted Following Removal of Plug | 10 March 1989 | PNO-II-89-015A:on 890225,primary to Secondary Steam Generator Tube Leak at Plant.Caused by Mechanical Failure. Eddy Current & Boroscopic Insps of Affected Tube Will Be Conducted Following Removal of Plug | |
| PNO-II-89-015, on 890125,Unit 1 Tripped Due to Ruptured Air Line to Main Feedwater Regulating Valve.Subsequent to Trip, Radiation Monitor Indications & Increased Charging Flow Revealed primary-to-secondary Leak from C Steam Generator | 27 February 1989 | PNO-II-89-015:on 890125,Unit 1 Tripped Due to Ruptured Air Line to Main Feedwater Regulating Valve.Subsequent to Trip, Radiation Monitor Indications & Increased Charging Flow Revealed primary-to-secondary Leak from C Steam Generator | |
| PNO-II-88-022, on 880405,low Levels of Radioactive Matl Detected in Demineralizer Beds for Plant Makeup Water.Caused by Concentrating Effect of Radionuclides.Licensee Currently Storing Spent Demineralizer Beds Onsite Until NRC Approval | 6 April 1988 | PNO-II-88-022:on 880405,low Levels of Radioactive Matl Detected in Demineralizer Beds for Plant Makeup Water.Caused by Concentrating Effect of Radionuclides.Licensee Currently Storing Spent Demineralizer Beds Onsite Until NRC Approval | |
| PNO-II-88-004, on 880113,licensee Identified Resin Intrusion from Powdex Demineralizer Sys Into Secondary Side of Steam Generator.Resin Causes Formation of Sulphates,Believed to Be Prime Cause of Steam Generator Tube Failures | 14 January 1988 | PNO-II-88-004:on 880113,licensee Identified Resin Intrusion from Powdex Demineralizer Sys Into Secondary Side of Steam Generator.Resin Causes Formation of Sulphates,Believed to Be Prime Cause of Steam Generator Tube Failures | |
| PNO-II-87-079, on 871128,North Anna Unit 1 Was Taken Off Line Due to Excessive Seal Leakage on B Reactor Coolant Pump. Outage Planned for 10 Days to Replace Seal Package & Inspect Lower Radial Bearing on Pump.Commonwealth of VA Informed | 1 December 1987 | PNO-II-87-079:on 871128,North Anna Unit 1 Was Taken Off Line Due to Excessive Seal Leakage on B Reactor Coolant Pump. Outage Planned for 10 Days to Replace Seal Package & Inspect Lower Radial Bearing on Pump.Commonwealth of VA Informed | |
| PNO-II-87-070, on 871013,NRC Authorized Startup & Operation Limited to 50% Power for Facility,Down Since 870715 Following Steam Generator Tube Rupture.No Evidence of Steam Generator Tube Leakage Noted | 13 October 1987 | PNO-II-87-070:on 871013,NRC Authorized Startup & Operation Limited to 50% Power for Facility,Down Since 870715 Following Steam Generator Tube Rupture.No Evidence of Steam Generator Tube Leakage Noted | |
| PNO-II-87-060, on 870719,hot Particle Recovered from Skin of Left Shoulder Blade of Contract Health Physics Technician & Determined to Be 1.6 Uci of C-60.Investigation Continuing. Technician Restricted from Radiation Control Zone | 20 August 1987 | PNO-II-87-060:on 870719,hot Particle Recovered from Skin of Left Shoulder Blade of Contract Health Physics Technician & Determined to Be 1.6 Uci of C-60.Investigation Continuing. Technician Restricted from Radiation Control Zone | |
| PNO-II-87-053A, on 870730,State of Ny,Dept of Environ Conservation & Dept of Radiation Health Completed Survey of Miscellaneous Boxes & Equipment W/Markings from VEPCO Found in Abandoned Bldg in Springwater,Ny.No Problems Noted | 30 July 1987 | PNO-II-87-053A:on 870730,State of Ny,Dept of Environ Conservation & Dept of Radiation Health Completed Survey of Miscellaneous Boxes & Equipment W/Markings from VEPCO Found in Abandoned Bldg in Springwater,Ny.No Problems Noted | |
| PNO-II-87-053, on 870728,licensee Notified That Fireman Discovered Miscellaneous Boxes & Equipment in Abandoned Bldg Outside Springwater,Ny.Matl Might Be Clean Surplus Matl Disposed of After Cancellation of North Anna 3 | 29 July 1987 | PNO-II-87-053:on 870728,licensee Notified That Fireman Discovered Miscellaneous Boxes & Equipment in Abandoned Bldg Outside Springwater,Ny.Matl Might Be Clean Surplus Matl Disposed of After Cancellation of North Anna 3 | |
| PNO-II-87-049, on 870716,augmented Insp Team Formed After Licensee Calculated Possible Leak Rate of 600 Gpm.Util Will Visually Inspect Steam Generator for More Precise Reading on Occurrence & Reconstructing Circumstances of Event | 17 July 1987 | PNO-II-87-049:on 870716,augmented Insp Team Formed After Licensee Calculated Possible Leak Rate of 600 Gpm.Util Will Visually Inspect Steam Generator for More Precise Reading on Occurrence & Reconstructing Circumstances of Event | Safe Shutdown |
| PNO-II-87-048, on 870715,cold Shutdown Reached & Util Downgraded from Alert Status to Recovery Mode.Nrc Inspectors Will Remain Onsite to Follow Up on Licensee Actions & Assess Sequence of Events.Pno Updates PNO-II-87-047 | 15 July 1987 | PNO-II-87-048:on 870715,cold Shutdown Reached & Util Downgraded from Alert Status to Recovery Mode.Nrc Inspectors Will Remain Onsite to Follow Up on Licensee Actions & Assess Sequence of Events.Pno Updates PNO-II-87-047 | |
| PNO-II-87-047, on 870715,unit Experienced Steam Generator Tube Leak.Util Reported Estimated Release of Radioactive Matl to Atmosphere Less than 1.3% of Tech Spec Release Limit.Release Path Isolated | 15 July 1987 | PNO-II-87-047:on 870715,unit Experienced Steam Generator Tube Leak.Util Reported Estimated Release of Radioactive Matl to Atmosphere Less than 1.3% of Tech Spec Release Limit.Release Path Isolated | |
| PNO-II-87-043, on 870702,util Shutdown Facility for Longer than 48 Hs to Repair Manual Isolation Valve.Util Plans to Bring Plant to Hot Shutdown & Repair Valve.Svc Will Resume in Several Days | 2 July 1987 | PNO-II-87-043:on 870702,util Shutdown Facility for Longer than 48 Hs to Repair Manual Isolation Valve.Util Plans to Bring Plant to Hot Shutdown & Repair Valve.Svc Will Resume in Several Days | |
| PNO-II-86-074, on 861013,licensee Issued News Release Stating That Investigation of Alleged Offsite Drug Use Resulted in Dismissal or Voluntary Resignation of 13 Security Officers or Employees,Including Supervisor of Security at Surry | 14 October 1986 | PNO-II-86-074:on 861013,licensee Issued News Release Stating That Investigation of Alleged Offsite Drug Use Resulted in Dismissal or Voluntary Resignation of 13 Security Officers or Employees,Including Supervisor of Security at Surry | |
| PNO-II-86-061, on 860827,turbine & Reactor Manually Tripped Due to High Bearing Vibration on Main Turbine.Caused by Damage to Some Turbine Blades on Last Stage of Low Pressure Turbine.Corrective Action Being Evaluated | 29 August 1986 | PNO-II-86-061:on 860827,turbine & Reactor Manually Tripped Due to High Bearing Vibration on Main Turbine.Caused by Damage to Some Turbine Blades on Last Stage of Low Pressure Turbine.Corrective Action Being Evaluated | |
| PNO-II-86-056, on 860804,unidentified Leakage of 1.31 Gpm Noted.Power Reduced to Allow Containment Entry to Identify Leakage.Three Valves,Including Loop Stop Valve,Found Leaking.On 860805,reactor Shut Down to Repair Leak | 7 August 1986 | PNO-II-86-056:on 860804,unidentified Leakage of 1.31 Gpm Noted.Power Reduced to Allow Containment Entry to Identify Leakage.Three Valves,Including Loop Stop Valve,Found Leaking.On 860805,reactor Shut Down to Repair Leak | |
| PNO-II-86-051, media Interest Developed Re Denial of Plant Access to Eight Painting Contractor Employees Following Internal Licensee Investigation of Possible Illegal Drug Use.No Charges Filed | 17 July 1986 | PNO-II-86-051:media Interest Developed Re Denial of Plant Access to Eight Painting Contractor Employees Following Internal Licensee Investigation of Possible Illegal Drug Use.No Charges Filed | |
| PNO-II-86-029, on 860411,reactor Tripped While Unit Operating at 70%,due to Loss of Permanent Magnet Generator in Exciter Unit.Repairs Will Be Completed by 860415.During Shutdown, Cooldown Rate Higher than Expected | 14 April 1986 | PNO-II-86-029:on 860411,reactor Tripped While Unit Operating at 70%,due to Loss of Permanent Magnet Generator in Exciter Unit.Repairs Will Be Completed by 860415.During Shutdown, Cooldown Rate Higher than Expected | |
| PNO-II-86-023, on 860326,reactor Tripped from 100% Power Due to ESF Activation Which Occurred on High Steam Line Flow Coincident W/Low Steam Line Pressure.Caused by Closure of Loop B Main Steam Trip Valve.Investigation Underway | 26 March 1986 | PNO-II-86-023:on 860326,reactor Tripped from 100% Power Due to ESF Activation Which Occurred on High Steam Line Flow Coincident W/Low Steam Line Pressure.Caused by Closure of Loop B Main Steam Trip Valve.Investigation Underway | |
| PNO-II-86-020, on 851031,bushings Were Installed During Outage Following Engine Failure in Diesel Generator of Plant Unit 2 | 5 March 1986 | PNO-II-86-020:on 851031,bushings Were Installed During Outage Following Engine Failure in Diesel Generator of Plant Unit 2 | |
| PNO-II-86-002, on 851229,shutdown Initiated Due to RCS Leakage Exceeding Tech Spec Limits.Pressure Vessel Head Will Be Removed for Repair of Reactor Pressure Vessel Head Seals.Unit Will Be Out of Svc for Addl 16 Days | 7 January 1986 | PNO-II-86-002:on 851229,shutdown Initiated Due to RCS Leakage Exceeding Tech Spec Limits.Pressure Vessel Head Will Be Removed for Repair of Reactor Pressure Vessel Head Seals.Unit Will Be Out of Svc for Addl 16 Days | |
| PNO-II-85-122, on 851228,surveillance Test Determined That Unit 1 RCS Unidentified Leak Rate to Be Approx 0.28 Gpm in Excess of 1.0 Gpm TS Limit.Leakage Suspected to Be Coming from in-core Thermocouple Electrical Connection Seal | 30 December 1985 | PNO-II-85-122:on 851228,surveillance Test Determined That Unit 1 RCS Unidentified Leak Rate to Be Approx 0.28 Gpm in Excess of 1.0 Gpm TS Limit.Leakage Suspected to Be Coming from in-core Thermocouple Electrical Connection Seal | |
| PNO-II-85-100, on 851024,480-volt Circuit Breaker or Associated Components for One Battery Room Exhaust Ventilation Fan Failed,Causing Trip of Another Breaker. Plant Gradually Shut Down | 24 October 1985 | PNO-II-85-100:on 851024,480-volt Circuit Breaker or Associated Components for One Battery Room Exhaust Ventilation Fan Failed,Causing Trip of Another Breaker. Plant Gradually Shut Down | |
| PNO-II-85-095, on 851011,unit Shut Down Following Failure of One Emergency Diesel Generator to Pass Routine Checks While Down for Maint.Restart Procedures Underway.Pistons & Two Cylinders replaced.Post-repair Review & Testing Completed | 15 October 1985 | PNO-II-85-095:on 851011,unit Shut Down Following Failure of One Emergency Diesel Generator to Pass Routine Checks While Down for Maint.Restart Procedures Underway.Pistons & Two Cylinders replaced.Post-repair Review & Testing Completed | |
| PNO-II-85-089, on 850911,leak in Excess of Tech Specs Discovered in Reactor Coolant Loop Bypass Valve.Cause Not Stated.Valve Backseated & Leakage Reduced.Evaluation & Repairs Performed | 12 September 1985 | PNO-II-85-089:on 850911,leak in Excess of Tech Specs Discovered in Reactor Coolant Loop Bypass Valve.Cause Not Stated.Valve Backseated & Leakage Reduced.Evaluation & Repairs Performed | |
| PNO-II-85-075, on 850802,plant Shut Down Before Leakage in Steam Generator 14 Exceeded Tech Spec Limit of 500 Gallons Per Day in Single Steam Generator.Plant Remained Out of Svc for 14 Days to Repair Steam Generator Leaks | 5 August 1985 | PNO-II-85-075:on 850802,plant Shut Down Before Leakage in Steam Generator 14 Exceeded Tech Spec Limit of 500 Gallons Per Day in Single Steam Generator.Plant Remained Out of Svc for 14 Days to Repair Steam Generator Leaks | |
| PNO-II-85-061, on 850613,unplanned Release of Radioactive Gases Occurred.Caused by Relief Valves Lifting as Result of Water Filling Surge Drum That Removes Radioactive Gas from Primary Coolant.Offsite Doses Negligible | 14 June 1985 | PNO-II-85-061:on 850613,unplanned Release of Radioactive Gases Occurred.Caused by Relief Valves Lifting as Result of Water Filling Surge Drum That Removes Radioactive Gas from Primary Coolant.Offsite Doses Negligible | |
| PNO-II-84-042, on 840705,contractor Employee Sustained Back Injuries When Falling 10 Feet While Performing Decontamination Work.Employee Transported to Hosp.Evidence of Contamination,Cracked Rib & Back Injuries Identified | 5 July 1984 | PNO-II-84-042:on 840705,contractor Employee Sustained Back Injuries When Falling 10 Feet While Performing Decontamination Work.Employee Transported to Hosp.Evidence of Contamination,Cracked Rib & Back Injuries Identified | |
| PNO-II-82-078B, updating PNO-II-82-078A Re Status of Thermal Sleeves in RCS by Nondestructive Tests.Unit 2 to Remain Shut Down Approx 2 Wks to Remove Thermal Sleeves.Unit 1 Outage Extended to Sept to Replace Control Rod Guide Tube | 20 July 1982 | PNO-II-82-078B:updating PNO-II-82-078A Re Status of Thermal Sleeves in RCS by Nondestructive Tests.Unit 2 to Remain Shut Down Approx 2 Wks to Remove Thermal Sleeves.Unit 1 Outage Extended to Sept to Replace Control Rod Guide Tube | |
| ML20055B575 | 13 July 1982 | Updated PNO-II-82-078A:on 820707,insp of Steam Generator a Revealed That Recently Reinstalled Tube Lane Blocking Device on Secondary Side Was Loose Due to Improper Installation. Steam Generators B & C Devices Found Rigid | |
| PNO-II-82-078, on 820707,unit Shutdown to Investigate Low Level Noise.Noise Discovered to Be Vibration on Secondary Side of Steam Generator.No Corrective Actions Noted.Restart Rescheduled for 820712 | 8 July 1982 | PNO-II-82-078:on 820707,unit Shutdown to Investigate Low Level Noise.Noise Discovered to Be Vibration on Secondary Side of Steam Generator.No Corrective Actions Noted.Restart Rescheduled for 820712 | |
| PNO-II-82-064B, Westinghouse Has Completed Evaluation of Two Metal Objects Found in a & C Steam Generator Hot Leg Plenums.Both Objects Identified as Inconel Nuts from Control Guide Tube Hold Down Pins.Pins Replaced Prior to Startup | 1 July 1982 | PNO-II-82-064B:Westinghouse Has Completed Evaluation of Two Metal Objects Found in a & C Steam Generator Hot Leg Plenums.Both Objects Identified as Inconel Nuts from Control Guide Tube Hold Down Pins.Pins Replaced Prior to Startup | |
| PNO-II-82-064A, on 820609,tube End Damage Reported Below Tube Sheet on Hot Leg Side of Steam Generators a & C W/Peening Damage Over 75% of Sheet Area.Evaluation Continuing | 22 June 1982 | PNO-II-82-064A:on 820609,tube End Damage Reported Below Tube Sheet on Hot Leg Side of Steam Generators a & C W/Peening Damage Over 75% of Sheet Area.Evaluation Continuing | |
| PNO-II-82-064, on 820606,during Regular Inservice Insp Licensee Observed Peening Damage on Primary Side of Tube Ends in Steam Generators a & C.Damage Being Evaluated by Licensee & Westinghouse | 9 June 1982 | PNO-II-82-064:on 820606,during Regular Inservice Insp Licensee Observed Peening Damage on Primary Side of Tube Ends in Steam Generators a & C.Damage Being Evaluated by Licensee & Westinghouse | |
| PNO-II-80-034, on 800226,small Leak Observed from Reactor Water Storage Tank Cooling Sys.Estimated 270 Gallons of Water Contaminated Ground.Licensee Sampling of Storm Drain Sys Showed No Release.Contaminated Matl to Be Shipped | 27 February 1980 | PNO-II-80-034:on 800226,small Leak Observed from Reactor Water Storage Tank Cooling Sys.Estimated 270 Gallons of Water Contaminated Ground.Licensee Sampling of Storm Drain Sys Showed No Release.Contaminated Matl to Be Shipped | |
| PNO-II-80-030A, on 800220,util Issued Press Release on Reactor Trip.Westinghouse & Licensee Have Completed Initial Set of Noise Measurement Tests & Will Compare Results W/Normal Operation Testing to Locate Noise | 22 February 1980 | PNO-II-80-030A:on 800220,util Issued Press Release on Reactor Trip.Westinghouse & Licensee Have Completed Initial Set of Noise Measurement Tests & Will Compare Results W/Normal Operation Testing to Locate Noise | |
| PNO-II-80-030, on 800220,reactor Inadvertently Tripped When Input Breaker to nonsafety-related Rod Drive Motor/Generator Set 1-1 Opened.Caused by Custodial Personnel.Investigating Possible Loose Parts in Steam Generator C | 21 February 1980 | PNO-II-80-030:on 800220,reactor Inadvertently Tripped When Input Breaker to nonsafety-related Rod Drive Motor/Generator Set 1-1 Opened.Caused by Custodial Personnel.Investigating Possible Loose Parts in Steam Generator C | |
| PNO-II-79-001C, on 791005,completed Investigation Into Cause of Overpressurization of Vol Control Tank & Release of Radioactive Gases Into Bldg.Caused by High Influx of Water from Primary Sys | 10 October 1979 | PNO-II-79-001C:on 791005,completed Investigation Into Cause of Overpressurization of Vol Control Tank & Release of Radioactive Gases Into Bldg.Caused by High Influx of Water from Primary Sys | |
| ML20217A117 | 8 November 1978 | PNO-78-191:informs That Virginia Sunshine Alliance Plans Caravan Against VEPCO on 781111-12.VEPCO Notified State & Local Officials & Commonwealth of Virginia.Region II Received Notification of Event on 781108 | |
| ML20216K023 | 3 November 1978 | PNO-78-186:on 781102,unplanned Release of Radioactive Gases, Mostly Xe-133,occurred as Result of Spill of Three Gallons of Radioactive Liquid.Radioactive Release Activated Alarms & Workers Were Evacuated.Region II Notified on 781102 | |
| ML20216J753 | 26 October 1978 | PNO-78-182:on 781024,following Completion of Valve Maintenance & While Returning Charging Sys to Operation,Two Drain Valves Inadvertently Left Open.Thirteen Individuals Received Low Level Contamination & Decontaminated Onsite | |
| ML20249A661 | 1 August 1978 | PNS-78-037A:on 780731,newscast Indicated That Local Environ Group Planning Antinuclear Demonstration on 780805. Size of Group & Reason for Demonstration Not Indicated | |
| ML20248F146 | 26 May 1978 | PNO-78-116:on 780427,planned Surveys Conducted Inside Reactor Containment During Startup Testing Program Revealed Neutron & Gamma Radiation Levels in Excess of Those Predicted in FSAR | |
| ML20248K982 | 5 April 1978 | PNO-78-071:on 780405,initial Criticality Was Achieved.Region II Inspectors Reported That Actual Control Rod Configuration & Boron Concentration Were in Close Agreement W/Predicted Values.News Release Planned by Licensee | |
| ML20248L902 | 16 March 1978 | PNO-78-049:on 780315,letdown Valve Failed Closed W/Rcs in Solid Water,Cold Shutdown Condition & Average Temp of 158 Degrees F.Analysis Reveals No Excessive Stresses Were Incurred by Reactor Vessel or RCS Piping | |
| ML20248L121 | 6 March 1978 | PNO-78-040:on 780303,licensee Reported That Architect Engineer,Stone & Webster Engineering Corp,Used Incorrect Allowable Stresses When Designing Piping Support Lugs for safety-related Piping for Units 1 & 2 |