ML20248L902
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| ML20248L902 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/16/1978 |
| From: | Klingler G, Nolan F, Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-78-049, PNO-78-49, NUDOCS 9806120046 | |
| Download: ML20248L902 (1) | |
Similar Documents at 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-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-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-88-004, 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-87-070, 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-87-060, 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-87-048, 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-87-047, 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-87-043, 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-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-86-061, 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-86-051, 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-86-029, 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-86-002, 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 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 Down1985-10-24024 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 Completed1985-10-15015 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 Performed1985-09-12012 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 Leaks1985-08-0505 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 Negligible1985-06-14014 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 Identified1984-07-0505 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 Tube1982-07-20020 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 ML20055B5751982-07-13013 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 8207121982-07-0808 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 Startup1982-07-0101 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 Continuing1982-06-22022 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 & Westinghouse1982-06-0909 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 Shipped1980-02-27027 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 Noise1980-02-22022 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 C1980-02-21021 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 Sys1979-10-10010 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 ML20217A1171978-11-0808 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 ML20216K0231978-11-0303 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 ML20216J7531978-10-26026 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 ML20249A6611978-08-0101 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 ML20248F1461978-05-26026 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 ML20248K9821978-04-0505 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 ML20248L9021978-03-16016 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 ML20248L1211978-03-0606 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 1996-11-13 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000338/19990031999-07-0202 July 1999
[Table view]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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 05000338/19960071996-09-0909 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 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 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 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 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 05000338/19933001993-10-20020 October 1993 Exam Repts 50-338/93-300 & 50-339/93-300 on 930825-0910 & 930921-24.Exam Results:Six SROs & Five ROs Received Written & Operating Exams.All Operators Passed Exams 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 IR 05000338/19930231993-10-15015 October 1993 Insp Repts 50-338/93-23 & 50-339/93-23 on 930822-0918.No Violations Noted.Major Areas Inspected:Plant Status, Operational Verification,Maint Observation,Training & Action on Previous Insp Items IR 05000338/19930251993-10-13013 October 1993 Insp Repts 50-338/93-25 & 50-339/93-25 on 930914-17.No Violations Noted.Major Areas Inspected:Eddy Current Exam of Steam Generator Tubes IR 05000338/19930201993-09-17017 September 1993 Insp Repts 50-338/93-20 & 50-339/93-20 on 930718-0821.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maint Observation, Surveillance Observation & Action on Previous Insp Items ML20056E8521993-08-0505 August 1993 Notice of Violation from Insp on 930620-0717.Violation Noted:Operating Procedure 1-OP-6.5.A Not Implemented Properly,In That While Performing Step 5.3.4.e,operator Failed to Fully Open EDG Exhaust Muffler Bypass Valve ML20056E8651993-08-0404 August 1993 Insp Repts 50-338/93-19 & 50-339/93-19 on 930620-0717. Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint Observation,Plant Status & Surveillance Observation ML20056D1671993-07-13013 July 1993 Insp Repts 50-338/93-18 & 50-339/93-18 on 930509-0619. Violations Noted.Major Areas Inspected:Examinations of Procedures & Representative Records,Interviews W/Personnel & Observaton of Activities in Progress 1999-07-02 |
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PRELIMINARY NOTIFICATION d~
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March 16, 1978 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PN
_This preliminary notification constitutes EARLY notice of an event of POSSIBLE safety or public interest significance. The information presented is as initially received without verification or evaluation and is basically all that is known by IE staff as of this date.
FACILITY: Virginia Electric and Power Company
' North Anna, Unit No. 1 Docket No. 50-338 Louisa County, Virginia
SUBJECT:
OVERPRESSURIZATION OF REACTOR COOLANT SYSTEM On March 15, a letdown valve failed closed with the reactor coolant system (RCS) temperature of 158in adegrees solid water, F. cold shutdown condition and an average 570 psig over a period of about five minutes and reportedly remainedRCS pre :
above the Technical Specification limit of 460 psig for less than one minute. =
but a pressurizer power-operated relief valve failed to actuate at itsR C2
( ! set point of 410 psig due to an omis'sion in the setpoint calibration procedure.
incurred by the reactor vessel or RCS piping. Analysis by the licensee l reveal Media interest is anticipated due to current interest in the North Anna b facility.
A news release is not planned by the licensee nor NRC.
Commonwealth of Virginia has been notified, The g s t
Region II (Atlanta) received initial notification of this occurrence by telephone-from station management at 2:40 p.m. on March 15.
is current as of 8:10 a.m. on March 16. This information
Contact:
GKlingler, IE x28019 FNolan, IE x28019 JSniezek, IE x28019 Distribution: Transmitted H St /L ',2 7 Chairman Hendrie Commissioner Kennedy Comniissioner Bradford "
S. J. Chilk, SECY C. C. Kammerer, CA Commissioner Gilinsky (For Distribution)
Transmitt'ed: MNBB / M A P P Bldg lL F .
L. V. Gossick, ED0 E. Volgenau IE E. G. Case, NRR S. H. Hanauer, ED0 Region ( ,I 1 M J. J. Fouchard, PA SS Bldg I M N R. Hartfield, MIPC C. V. Smitn, NMSS (MAIL)
_ R. G. Ryan, OSP T. J. McTiernan, 01A H. K. Shapar, ELD R. Minogue, SD PRELIMINARY NOTIFICATION 9806120046 78031b PDR I&E PNO-78-049 PDR
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