ML20217A117
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| ML20217A117 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 11/08/1978 |
| From: | Klingler G, Nolan F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| PNO-78-191, NUDOCS 9804220159 | |
| Download: ML20217A117 (1) | |
Similar Documents at Surry, North Anna | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-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 Performed1996-11-13013 November 1996
[Table view]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-93-062, on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations1993-11-16016 November 1993 PNO-II-93-062:on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations PNO-II-93-037, on 930820,unscheduled Shutdown in Excess of 72 H Occurred Due to Need to Repair Leak in Joint on SG B. RCS Temp Reduced Below 200 Degrees F.Licensee to Inspect Drain Valve Assemblies on Sg.State of VA Notified1993-08-23023 August 1993 PNO-II-93-037:on 930820,unscheduled Shutdown in Excess of 72 H Occurred Due to Need to Repair Leak in Joint on SG B. RCS Temp Reduced Below 200 Degrees F.Licensee to Inspect Drain Valve Assemblies on Sg.State of VA Notified 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 Precaution1992-03-30030 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-90-066, on 901023,util Made 1 H Rept Per 10CFR50.72 Re Entry Into Station Emergency Plan for Shutdown of Unit 2. Caused by Svc Water Flow,Less That Design Basis Required Flow.Licensee Currently Evaluating Situation1990-10-23023 October 1990 PNO-II-90-066:on 901023,util Made 1 H Rept Per 10CFR50.72 Re Entry Into Station Emergency Plan for Shutdown of Unit 2. Caused by Svc Water Flow,Less That Design Basis Required Flow.Licensee Currently Evaluating Situation PNO-II-89-066A, updates Status of Hurricane Hugo for Nuclear Facilities in Southeast.Manning of Incident Response Ctr by Region II Continuing1989-09-21021 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 Notified1989-03-27027 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 Plug1989-03-10010 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 Generator1989-02-27027 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 Approval1988-04-0606 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-88-011, on 880206,slight Positive Pressure Created in Primary Drain Tank Due to Large Vol of Water & Overhead Gas Compressor Inoperable,Causing Gaseous Leak in Auxiliary Bldg.Cause Not Stated1988-02-0808 February 1988 PNO-II-88-011:on 880206,slight Positive Pressure Created in Primary Drain Tank Due to Large Vol of Water & Overhead Gas Compressor Inoperable,Causing Gaseous Leak in Auxiliary Bldg.Cause Not Stated 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 Failures1988-01-14014 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 Informed1987-12-0101 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-87-078, on 871126,licensee Removed Unit 1 from Svc to Repair Leaking Manway Cover on Secondary Side of C Steam Generator.Unit Cooled Down & Manway Gasket Replaced. Commonwealth of Virginia Informed1987-11-30030 November 1987 PNO-II-87-078:on 871126,licensee Removed Unit 1 from Svc to Repair Leaking Manway Cover on Secondary Side of C Steam Generator.Unit Cooled Down & Manway Gasket Replaced. Commonwealth of Virginia 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 Noted1987-10-13013 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-87-061, on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset1987-09-21021 September 1987 PNO-II-87-061:on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset 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 Zone1987-08-20020 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 Noted1987-07-30030 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 31987-07-29029 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 Event1987-07-17017 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 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 Isolated1987-07-15015 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-87-048, 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-87-0471987-07-15015 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-87-043, 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 Days1987-07-0202 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-87-040, on 870623,unit Manually Shut Down Following Estimated 40 Gpm Leak in Rcs.Caused by Packing on Reactor Coolant Loop Stop Valve.Licensee Preparing Unit to Go to Mode 5 to Effect Repairs1987-06-23023 June 1987 PNO-II-87-040:on 870623,unit Manually Shut Down Following Estimated 40 Gpm Leak in Rcs.Caused by Packing on Reactor Coolant Loop Stop Valve.Licensee Preparing Unit to Go to Mode 5 to Effect Repairs PNO-II-87-037, on 870607,licensee Entered 24 H Limiting Condition for Operation When Outside Recirculation Spray Pump B Failed Periodic Surveillance Test Due to High Vibration & Low Discharge Pressure.Unit Shut Down1987-06-0909 June 1987 PNO-II-87-037:on 870607,licensee Entered 24 H Limiting Condition for Operation When Outside Recirculation Spray Pump B Failed Periodic Surveillance Test Due to High Vibration & Low Discharge Pressure.Unit Shut Down PNO-II-87-032, updates PNO-II-87-029.Util Determined That Partial Closure of Isolation Valve Which Brought About Reactor Scram on 870516 Caused by Shearing of Valve Stem Above Backseat.Metallurgist Evaluating Break1987-05-21021 May 1987 PNO-II-87-032:updates PNO-II-87-029.Util Determined That Partial Closure of Isolation Valve Which Brought About Reactor Scram on 870516 Caused by Shearing of Valve Stem Above Backseat.Metallurgist Evaluating Break PNO-II-87-029, on 870516,unit Tripped on Low Reactor Coolant Flow Rate in Loop A.Caused by Partial Closure of Hot Loop Isolation Valve.Outage of 12 Days Planned to Correct Problem.Resident Inspector Will Provide Followup1987-05-18018 May 1987 PNO-II-87-029:on 870516,unit Tripped on Low Reactor Coolant Flow Rate in Loop A.Caused by Partial Closure of Hot Loop Isolation Valve.Outage of 12 Days Planned to Correct Problem.Resident Inspector Will Provide Followup PNO-II-87-011A, on 870213,leak Discovered in Svc Water Line Below Floor of Unit 2 Turbine Bldg.Util Will Replace Defective Portion of Unit 2 Side of Svc Water Piping.Unit 1 Side of Same Sys Tested & Acceptable1987-02-18018 February 1987 PNO-II-87-011A:on 870213,leak Discovered in Svc Water Line Below Floor of Unit 2 Turbine Bldg.Util Will Replace Defective Portion of Unit 2 Side of Svc Water Piping.Unit 1 Side of Same Sys Tested & Acceptable PNO-II-87-011, heatup of Unit 1 Beginning in Preparation for Return to Svc.Restart of Unit 2 Scheduled 2 to 3 Wks Later.Licensee Informed of Region II Acceptance of Restart Plan in 870210 Augmented Insp Team Rept1987-02-12012 February 1987 PNO-II-87-011:heatup of Unit 1 Beginning in Preparation for Return to Svc.Restart of Unit 2 Scheduled 2 to 3 Wks Later.Licensee Informed of Region II Acceptance of Restart Plan in 870210 Augmented Insp Team Rept PNO-II-86-091D, licensee Repts Two Addl Deaths Occurred as Result of Injuries from 861209 Accident.Caused by Break of 18-inch Feedwater Sys Suction Line Scalding Eight Workers W/Hot Water & Steam.Number of Dead Now Four1986-12-16016 December 1986 PNO-II-86-091D:licensee Repts Two Addl Deaths Occurred as Result of Injuries from 861209 Accident.Caused by Break of 18-inch Feedwater Sys Suction Line Scalding Eight Workers W/Hot Water & Steam.Number of Dead Now Four PNO-II-86-091C, ultrasonic Testing of Unit 1 Piping Elbow Disclosed Min Pipe Wall Thickness of 0.16 Inch.Design Specs Require 0.36 Inch Min Thickness.Ultrasonic Testing Continuing1986-12-15015 December 1986 PNO-II-86-091C:ultrasonic Testing of Unit 1 Piping Elbow Disclosed Min Pipe Wall Thickness of 0.16 Inch.Design Specs Require 0.36 Inch Min Thickness.Ultrasonic Testing Continuing PNO-II-86-091B, tour Conducted for Reporters of Site of 861209 Pipe Break Event.On 861212,pump Discharge Check Valve Inspected,Revealing One Missing Hinge Pin & Unseated Valve Disc.Nrc Pipe Break Specialist Onsite1986-12-12012 December 1986 PNO-II-86-091B:tour Conducted for Reporters of Site of 861209 Pipe Break Event.On 861212,pump Discharge Check Valve Inspected,Revealing One Missing Hinge Pin & Unseated Valve Disc.Nrc Pipe Break Specialist Onsite PNO-II-86-091A, Unit 2 Feedwater Pipe Rupture Resulted in Two Deaths as of 861211,w/four Other Workers Hospitalized.Unit 1 Shutting Down.Extensive Erosion/Corrosion Found Inside Pipe. NRC Augmented Insp Team Onsite.Investigation Continuing1986-12-11011 December 1986 PNO-II-86-091A:Unit 2 Feedwater Pipe Rupture Resulted in Two Deaths as of 861211,w/four Other Workers Hospitalized.Unit 1 Shutting Down.Extensive Erosion/Corrosion Found Inside Pipe. NRC Augmented Insp Team Onsite.Investigation Continuing PNO-II-86-091, on 861209,reactor Trip Occurred & Feedwater Line Ruptured Upstream of Main Feedwater Pump 2-A,injuring 8 Personnel,Some Seriously.Caused by Break in Elbow on Mainfeed Pump Header.Unit Maintained Stable Condition1986-12-10010 December 1986 PNO-II-86-091:on 861209,reactor Trip Occurred & Feedwater Line Ruptured Upstream of Main Feedwater Pump 2-A,injuring 8 Personnel,Some Seriously.Caused by Break in Elbow on Mainfeed Pump Header.Unit Maintained Stable Condition 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 Surry1986-10-14014 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-86-067, on 860918 & 19,two Control Rods Dropped Into Core.Caused by Worker Bumping Electrical Connector Which Resulted in Loss of Electric Power to Control Rod.Operators Manually Tripped Reactor & Started Cold Shutdown1986-09-23023 September 1986 PNO-II-86-067:on 860918 & 19,two Control Rods Dropped Into Core.Caused by Worker Bumping Electrical Connector Which Resulted in Loss of Electric Power to Control Rod.Operators Manually Tripped Reactor & Started Cold Shutdown 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 Evaluated1986-08-29029 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 Leak1986-08-0707 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-86-054, on 860722,unscheduled Shutdown Longer than 48 H Occurred Due to Inoperable Recirculation Containment Spray Heat Exchanger.Unit Placed in Cold Shutdown for Component Repairs.Commonwealth of VA Informed1986-07-23023 July 1986 PNO-II-86-054:on 860722,unscheduled Shutdown Longer than 48 H Occurred Due to Inoperable Recirculation Containment Spray Heat Exchanger.Unit Placed in Cold Shutdown for Component Repairs.Commonwealth of VA Informed PNO-II-86-052, on 860719,licensee Declared Unusual Event Due to Anonymous Telephoned Bomb Threat to Plant Security Shift Supervisor.No Evacuation Conducted & Unusual Event Terminated.Commonwealth of Virginia Informed1986-07-21021 July 1986 PNO-II-86-052:on 860719,licensee Declared Unusual Event Due to Anonymous Telephoned Bomb Threat to Plant Security Shift Supervisor.No Evacuation Conducted & Unusual Event Terminated.Commonwealth of Virginia Informed 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 Filed1986-07-17017 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-86-042, on 860616,unit Taken Out of Svc for More than 48 H to Repair Leaking Expansion Joint on Recirculation Spray Subsystem HX Return Line1986-06-18018 June 1986 PNO-II-86-042:on 860616,unit Taken Out of Svc for More than 48 H to Repair Leaking Expansion Joint on Recirculation Spray Subsystem HX Return Line PNO-II-86-037, on 860527,inadvertent Release of 28.5 Ci Xe-133 Occurred,Exceeding Tech Spec Limit,As Two Steam Generators Purged W/Air in Preparation for Eddy Current Testing.Purge Stopped & Reading Returned to Normal1986-05-29029 May 1986 PNO-II-86-037:on 860527,inadvertent Release of 28.5 Ci Xe-133 Occurred,Exceeding Tech Spec Limit,As Two Steam Generators Purged W/Air in Preparation for Eddy Current Testing.Purge Stopped & Reading Returned to Normal PNO-II-86-035, on 860511,partial Loss of Power & Initiation of Train B Safety Injection Occurred When Station Battery 1-B Removed from Svc.Caused by Failure of Adjusted Battery Chargers to Pick Up Load.Power Restored1986-05-13013 May 1986 PNO-II-86-035:on 860511,partial Loss of Power & Initiation of Train B Safety Injection Occurred When Station Battery 1-B Removed from Svc.Caused by Failure of Adjusted Battery Chargers to Pick Up Load.Power Restored 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 Expected1986-04-14014 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 Underway1986-03-26026 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 21986-03-0505 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-86-013, on 860205,packaged,unloaded mini-14 Rifle, Being Returned to Security After Repairs,Passed Undetected Through X-ray Search.Region Will Send Security Inspector to Facility on 860210.Util Prepared to Respond to Media1986-02-0606 February 1986 PNO-II-86-013:on 860205,packaged,unloaded mini-14 Rifle, Being Returned to Security After Repairs,Passed Undetected Through X-ray Search.Region Will Send Security Inspector to Facility on 860210.Util Prepared to Respond to Media 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 Days1986-01-0707 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 Seal1985-12-30030 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 1996-11-13 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000280/19993021999-09-0808 September 1999
[Table view]NRC Operator Licensing Retake Exam Repts 50-280/99-302 & 50-281/99-302 for Retake Exam Tests Administered on 990824. Exam Results:One SRO Candidate Received Part B re-take Operating Exam & Passed IR 05000338/19990031999-07-0202 July 1999 Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000280/19993011999-05-14014 May 1999 NRC Operator Licensing Exam Repts 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15 IR 05000338/19990011999-04-12012 April 1999 Insp Repts 50-338/99-01 & 50-339/99-01 on 990131-0313. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.In Addition,Results of Insp by Region Based Fire Protection Specialist Encl IR 05000338/19980111999-03-0101 March 1999 Insp Repts 50-338/98-11 & 50-339/98-11 on 981220-990130.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000338/19980101999-01-14014 January 1999 Insp Repts 50-338/98-10 & 50-339/98-10 on 981108-1219.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196H4131998-11-0505 November 1998 Insp Repts 50-338/98-05 & 50-339/98-05 on 980713-31 & 0921- 25.Violation Noted.Major Areas Inspected:Review of Licensee Calculations,Analysis,Performance Test Procedures & Other Engineering Documents Used to Support Design & Performance ML20196H4081998-11-0505 November 1998 Notice of Violation from Insp on 980713-31 & 0921-25. Violation Noted:As of 980712,AFW Pipe Supports Were Not Constructed IAW Details Shown on Design Drawings as Listed ML20155B0671998-10-0202 October 1998 NRC Operator Licensing Exam Repts 50-338/98-301 & 50-339/98-301 (Including Completed & Graded Tests) for Tests Administered on 980817-21 & 31-0903 IR 05000338/19980071998-08-18018 August 1998 Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for North Anna Nuclear Station IR 05000280/19980051998-07-13013 July 1998 Insp Repts 50-280/98-05 & 50-281/98-05 on 980503-0613.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20216H6711998-04-0303 April 1998 Insp Repts 50-338/98-01,50-338/98-01 & 72-0016/98-01 on 980125-0307.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970111998-01-12012 January 1998 Insp Repts 50-338/97-11,50-339/97-11 & 72-0016/97-04 on 971102-1213.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000280/19970111997-10-0707 October 1997 Partially Withheld Insp Repts 50-280/97-11 & 50-281/97-11 on 970924 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specialist IR 05000338/19970101997-10-0707 October 1997 Partially Withheld Insp Repts 50-338/97-10 & 50-339/97-10 on 970922-23 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specalist ML20216B2581997-08-29029 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Licensee Failed to Monitor Performance & Establish Goals Commensurate W/Safety for Emergency Switch Gear Heating Ventilation IR 05000338/19970041997-07-21021 July 1997 Insp Repts 50-338/97-04 & 50-339/97-04 on 970518-0621.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19970051997-07-15015 July 1997 Insp Repts 50-338/97-05 & 50-339/97-05 on 970616-20.No Violations Noted.Major Areas Inspected:Plant Support ML20140F2651997-06-0606 June 1997 Insp Repts 50-338/97-03 & 50-339/97-03 on 970406-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000338/19970021997-05-0505 May 1997 Insp Repts 50-338/97-02 & 50-339/97-02 on 970223-0405.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20148B6541997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Operators Failed to Verify That Unit 1 & 2 RCPs 1 Seal Leakoffs & Unit 2 Nr 46 Nuclear Power Range Chart Recorders Were Operational ML20137F7661997-03-21021 March 1997 Insp Repts 50-338/97-01 & 50-339/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20137F7411997-03-21021 March 1997 Notice of Violation from Insp on 970112-0222.Violation Noted:As of 970213,radiation Monitors Installed in Fuel Handling & Storage Locations,Did Not Provide Full Coverage for Area Used for New Fuel Receipt IR 05000338/19970991997-02-21021 February 1997 SALP Repts 50-338/97-99 & 50-339/97-99 for 941225-970111 IR 05000338/19960131997-02-0707 February 1997 Insp Repts 50-338/96-13 & 50-339/96-13 on 961208-970111.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20133G8881997-01-0606 January 1997 Notice of Violation from Insp on 961103-1207.Violation Noted:Licensee Failed to Ensure That Safeguards Area Walls Met Design Basis for Containing Pump Seal Leakage Described in Updated Final Safety Analysis Rept Section 15.4.1.8 ML20133J1991997-01-0606 January 1997 Insp Repts 50-338/96-12 & 50-339/96-12 on 961102-1207. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20133C9491996-12-27027 December 1996 EN-96-098:order Prohibiting Involvement in NRC Licensed Activities Will Be Issued on or About 970102 to Unlicensed Individual Formerly Employed as Contract Millwright.State of VA Will Be Notified ML20149M5831996-12-0202 December 1996 Notice of Violation from Insp on 960922-1102.Violation Noted:Rce Had Not Been Completed for Several Pump 1-CH-P-1A Seal Failures Which Occurred Between 960211 & 0718 IR 05000338/19960101996-12-0202 December 1996 Insp Repts 50-338/96-10 & 50-339/96-10 on 960922-1102. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000338/19960111996-11-15015 November 1996 Insp Repts 50-338/96-11 & 50-339/96-11 on 961014-18.No Violations Noted.Major Areas Inspected:Plant Support 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 Performed1996-11-13013 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 ML20134G9071996-10-21021 October 1996 Insp Repts 50-338/96-09 & 50-339/96-09 on 960811-0921. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20134G7971996-10-21021 October 1996 Notice of Violation from Insp on 960811-0921.Violation Noted:Procedure for Irradiated Fuel Damage While Refueling, 0-AP-30 Inadequate ML20128K0591996-09-30030 September 1996 Insp Repts 50-338/96-08 & 50-339/96-08 on 960812-16.No Violations Noted.Major Areas Inspected:Cr Simulator,Tsc,Osc, EOF, & Joint Info Ctr IR 05000338/19960071996-09-0909 September 1996 Insp Repts 50-338/96-07 & 50-339/96-07 on 960810.Violations Noted.Major Areas Inspected:Licensee Operations,Engineers, Maint & Plant Support ML20134C6401996-09-0909 September 1996 Notice of Violation from Insp on 960810.Violation Noted: on 940802,inadequate Maint Procedure Was Used to Control Maint Activities Affecting Quality IR 05000338/19940291994-12-29029 December 1994 Partially Withheld Insp Repts 50-338/94-29 & 50-339/94-29 on 941128-1202 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors IR 05000338/19930291994-01-12012 January 1994 Insp Repts 50-338/93-29 & 50-339/93-29 on Stated Date.No Violations Noted.Major Areas Inspected:Plant Status,Ler Followup,Safety Verification,Maintenance Observation, Surveillance Observation & Cold Weather Preparations ML20059L0511994-01-0404 January 1994 EN-94-001:on 940107,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $15,000 Will Be Issued.Action Based on Two Previous Similar Severity Level IV Violations Issued on 901207 & 920515 ML20059B2521993-12-14014 December 1993 Corrected NOV from Insp on 931017-1120,including Response Instruction ML20059B2751993-12-14014 December 1993 Notice of Violation from Insp on 931017-1120.Violation Noted:On 931029,periodic Test Procedure 2-PT-82H Was Not Implemented Correctly & While Performing Step 6.4.5,operator Incorrectly Placed Control Switch Breaker in pull-to-lock ML20059B2881993-12-14014 December 1993 Insp Repts 50-338/93-27 & 50-339/93-27 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation & Surveillance Observation PNO-II-93-062, on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations1993-11-16016 November 1993 PNO-II-93-062:on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations IR 05000338/19930241993-11-15015 November 1993 Insp Repts 50-338/93-24 & 50-339/93-24 on 930919-1016.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation, Surveillance Observation & LER Followup IR 05000338/19933011993-11-12012 November 1993 Exam Rept 50-338/93-301 on 931008-15.Exam Results:Eight ROs & Six SROs Passed Written & Operating Exams.Exam for Both Units IR 05000338/19930281993-10-29029 October 1993 Insp Repts 50-338/93-28 & 50-339/93-28 on 931014-20. Violations Noted.Major Areas Inspected:Circumstances Surrounding Unit 2 High Head Safety Injection Subsystem Not Meeting TS Min Flow Requirement on 931014 IR 05000338/19930261993-10-27027 October 1993 Insp Repts 50-338/93-26 & 50-339/93-26 on 930927-1001.No Violations or Deviations Noted.Major Areas Inspected: Licensee Radiation Protection Program,Involving Review of HP Activities Primarily Associated W/Unit 2 Refueling Outage IR 05000280/19933001993-10-20020 October 1993 Exam Repts 50-280/93-300 & 50-281/93-300 on 930920-24.Exam Results:Three SROs Passed Exam & One Out of Four ROs Failed Exam IR 05000338/19930211993-10-20020 October 1993 Insp Repts 50-338/93-21 & 50-339/93-21 on 930920-24.No Violations Noted.Major Areas Inspected:Organization of Chemistry Dept & Units Responsible for Handling & Shipping of Radioactive Matl & Plant Water Chemistry 1999-09-08 |
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PRELIMINARY NOT?FICATION ^ O b /I
~
i l November 8, 1978 (J l PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-78-191
_This preliminary notification constitutes EARLY notice of an event of P_0SSIBLE safety or public interest significance. The information presented is as initially received without verification or evaluation
_a_nd is basically all that is known by IE staff on this date.
FACILITY: Virginia Electric and Power Company North Anna Units 1 and 2/Surry Units 1 and 2 l Docket Nos. 50-338, 50-339, 50-280, 50-281 Louisa County and Surry County, Virginia
SUBJECT:
WEEKEND DEMONSTRATION AGAINST VEPC0 l
The Virginia Sunshine Alliance plans' a caravan demonstration against l VEPC0 on November 11-12. The caravan will start Saturday at the Surry l station. A truck carrying a mockup of a radioactive waste container I will travel to Richmond, Virginia, where the group plans to stage a mock i l
" Transport Accident" at VEPC0 Headquarters Saturday afternoon. Sunday l l
the group will proceed to the North Anna station to arrive in the early -
afternoon. mj Media interest has occurred. VEPC0 has notified state and local officials.
A The Commonwealth of Virginia has been notified. A news release is not j
i planned by the licensee nor NRC. >
Region II (Atlanta) received notification of this occurrence by telephone from the Resident Inspector at 10:00 a.m. on November 8,1978. This information is current as of'10:00 a.m. on November 8,1978.
Conta'ct: GKlingler, IE x28019 FNolan, IE x28019 Distribution: Transmitted H St WO Mrs.
Chairman Heridrie Commissioner Bradford S. J. Chilk, SECY Commissioner Kennedy Commissioner Ahearne C. C. Kammerer, CA Commissioner Gilinsky (Ford.istribution)
Transmitted: MNBB 7/ von P Bldg 3' O P J. G. Davi IE L. V. Gossick, ED0 S. H. Hanauer, EDO H. R. Denton, NRR Region f l</ [
R. C. DeYoung, NRR J. J. Fouchard, PA R. J. Mattson, NRR N. M. Hakler, MPA V. Stello, NRR .
R. G. Ryan, OSP R. S. Boyd, NRR H. K. Shapar, ELD SS Bldg.f.'0 9 (MAIL)
C. V. Smith, NMSS 0. G. Abston, 0IA R. Minogue, SD 0/
PRELIMINARY NOTIFICATION
.D r. c 7) 9804220159 781100 l
PDR I&E l
PNO-78-191 PDR l
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