PNO-II-85-071A, broken Valve Stem Discovered Following Disassembly of Inboard Main Steam Line Isolation Valve. Caused by Metal Fatigue.Evaluation Continuing: Difference between revisions
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Latest revision as of 13:07, 21 August 2022
| ML20132E839 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/26/1985 |
| From: | Brownlee V, Panciera V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-II-85-071A, PNO-II-85-71A, NUDOCS 8508020120 | |
| Download: ML20132E839 (1) | |
Similar Documents at Hatch | |
|---|---|
Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-II-99-025, on 990615,CR Operators Manually Shutdown Unit 2 Reactor from 41% Power,Due to Decreasing Condenser Vacuum. Cause of Decreasing Vacuum Has Not Been Determined.All Rods Installed as Required & All Safety Sys Functioned Properly1999-06-17017 June 1999
[Table view]PNO-II-99-025:on 990615,CR Operators Manually Shutdown Unit 2 Reactor from 41% Power,Due to Decreasing Condenser Vacuum. Cause of Decreasing Vacuum Has Not Been Determined.All Rods Installed as Required & All Safety Sys Functioned Properly PNO-II-99-016, on 990505,Hatch Unit 2 Had Main Generator Trip Form 98% Power,Due to Electrical Fault.Licensee Continuing Investigation Has Been Hampered Due to Inclement Local Weather Conditions.Plant Being Depressurized1999-05-0707 May 1999 PNO-II-99-016:on 990505,Hatch Unit 2 Had Main Generator Trip Form 98% Power,Due to Electrical Fault.Licensee Continuing Investigation Has Been Hampered Due to Inclement Local Weather Conditions.Plant Being Depressurized PNO-II-98-040, on 980917,licensee Declared Notification of Unusual Event Based on Transport of Two Injured & Potentially Contaminated Individuals to Local Hospital.Two Individuals Found Not to Have Sustained Serious Injury1998-09-18018 September 1998 PNO-II-98-040:on 980917,licensee Declared Notification of Unusual Event Based on Transport of Two Injured & Potentially Contaminated Individuals to Local Hospital.Two Individuals Found Not to Have Sustained Serious Injury PNO-II-97-060, on 971120,plant Operators Manually Scrammed Reactor from 70% Power Due to Damage to Condensate Sys. Flexible Bellows on 2A Condensate Booster Pump Was Overpressurized.Licensee Initiate Controlled Shutdown1997-11-21021 November 1997 PNO-II-97-060:on 971120,plant Operators Manually Scrammed Reactor from 70% Power Due to Damage to Condensate Sys. Flexible Bellows on 2A Condensate Booster Pump Was Overpressurized.Licensee Initiate Controlled Shutdown PNO-II-97-017, on 970312,licensee Reported Employee Collapses Onsite.First Aid Administered Until Ambulance Arrived. Employee Transported to Appling County General Hosp in Baxley,Ga & Pronounced Dead.Autopsy Will Be Performed1997-03-13013 March 1997 PNO-II-97-017:on 970312,licensee Reported Employee Collapses Onsite.First Aid Administered Until Ambulance Arrived. Employee Transported to Appling County General Hosp in Baxley,Ga & Pronounced Dead.Autopsy Will Be Performed PNO-II-97-006A, on 970129,plant Shutdown Due to Primary Pressure Boundary Leakage Update.Licensee Continuing to Cold Shutdown Conditions to Perform Addl Corrective Maint Activities.Resident Inspectors Monitoring Repair Actions1997-01-30030 January 1997 PNO-II-97-006A:on 970129,plant Shutdown Due to Primary Pressure Boundary Leakage Update.Licensee Continuing to Cold Shutdown Conditions to Perform Addl Corrective Maint Activities.Resident Inspectors Monitoring Repair Actions PNO-II-97-006, on 970129,Unit 1 Declared Notice of Unusual Event for Reactor Coolant Pressure Boundary Leakage,As Defined in TS 3.4.4.Resident Inspectors on Site Monitoring Licensee Actions.State of Ga Notified1997-01-29029 January 1997 PNO-II-97-006:on 970129,Unit 1 Declared Notice of Unusual Event for Reactor Coolant Pressure Boundary Leakage,As Defined in TS 3.4.4.Resident Inspectors on Site Monitoring Licensee Actions.State of Ga Notified PNO-II-93-061, on 931107,Unit 2 Began Shutdown Due to Increase in Unidentified Drywell Leakage.Util in Process of Implementing Reactor Vessel Water Level Mods Per Bulletin 93-0031993-11-10010 November 1993 PNO-II-93-061:on 931107,Unit 2 Began Shutdown Due to Increase in Unidentified Drywell Leakage.Util in Process of Implementing Reactor Vessel Water Level Mods Per Bulletin 93-003 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-89-066, licensees Prepared for Adverse Weather Conditions Due to Hurricane.Briefings Held W/Key Managers on Responsibilities to Check All Trailers,Secure Crane Hooks & Increase Emergency Food Supplies1989-09-21021 September 1989 PNO-II-89-066:licensees Prepared for Adverse Weather Conditions Due to Hurricane.Briefings Held W/Key Managers on Responsibilities to Check All Trailers,Secure Crane Hooks & Increase Emergency Food Supplies PNO-II-88-026B, on 880518,Unit 1 Achieved Criticality Following 30-day Outage Period to Correct Problems Identified as Result of INPO Evaluation.On 880515,Unit 2 Remained at Zero Power for Completion of Repairs on Valve1988-05-19019 May 1988 PNO-II-88-026B:on 880518,Unit 1 Achieved Criticality Following 30-day Outage Period to Correct Problems Identified as Result of INPO Evaluation.On 880515,Unit 2 Remained at Zero Power for Completion of Repairs on Valve PNO-II-88-026, on 880419,plant Shutdown Will Begin for Evaluation & Correction of Problems Noted in INPO Evaluation Conducted During Wks of 880314 & 21.Restart Planned within 30 Days.Unit 2 Reactor Scram Occurred on 8804171988-04-19019 April 1988 PNO-II-88-026:on 880419,plant Shutdown Will Begin for Evaluation & Correction of Problems Noted in INPO Evaluation Conducted During Wks of 880314 & 21.Restart Planned within 30 Days.Unit 2 Reactor Scram Occurred on 880417 PNO-II-88-021, on 880404,licensee Commenced Controlled Shutdown.Caused by Unidentified Reactor Coolant Leakage Approaching Tech Spec Limit of 5 Gallons/Minute Over 24 H. Licensee Plans 7-day Outage to Correct Situation1988-04-0505 April 1988 PNO-II-88-021:on 880404,licensee Commenced Controlled Shutdown.Caused by Unidentified Reactor Coolant Leakage Approaching Tech Spec Limit of 5 Gallons/Minute Over 24 H. Licensee Plans 7-day Outage to Correct Situation PNO-II-86-090A, cleanup of Contaminated Plant Areas Essentially Complete Except for Nitrogen Storage Area,Where Estimated 25-35% of 0.37 Ci Released Still Remains.Water Sources from Plant to Swamp Area Diverted Away from Outfall1986-12-0505 December 1986 PNO-II-86-090A:cleanup of Contaminated Plant Areas Essentially Complete Except for Nitrogen Storage Area,Where Estimated 25-35% of 0.37 Ci Released Still Remains.Water Sources from Plant to Swamp Area Diverted Away from Outfall PNO-II-86-090, on 861203,leak of About 50,000 Gallons Water from Spent Fuel Pools Discovered.Leak Detection Annunciator Failed to Alarm & Spent Fuel Pool Levels Dropped About 5 Ft. Leak Caused by Loss of Air to Inflatable Seals1986-12-0404 December 1986 PNO-II-86-090:on 861203,leak of About 50,000 Gallons Water from Spent Fuel Pools Discovered.Leak Detection Annunciator Failed to Alarm & Spent Fuel Pool Levels Dropped About 5 Ft. Leak Caused by Loss of Air to Inflatable Seals PNO-II-86-031, on 860425,w/unit at 85% Power,Reducer Section of Extraction Steam Line Running to Feedwater Heater Ruptured,Leaving Opening in Pipe Over 18 Inches Long.Caused by Moisture in Excitation Sys1986-04-25025 April 1986 PNO-II-86-031:on 860425,w/unit at 85% Power,Reducer Section of Extraction Steam Line Running to Feedwater Heater Ruptured,Leaving Opening in Pipe Over 18 Inches Long.Caused by Moisture in Excitation Sys PNO-II-85-121, on 851221,safety Equipment in Southeast Diagonal Room of Reactor Bldg Flooded W/Torus Water.Caused by Open Flow Path Through Disassembled RHR Pump Suction Valve.Water Removed & Rooms Decontaminated1985-12-23023 December 1985 PNO-II-85-121:on 851221,safety Equipment in Southeast Diagonal Room of Reactor Bldg Flooded W/Torus Water.Caused by Open Flow Path Through Disassembled RHR Pump Suction Valve.Water Removed & Rooms Decontaminated PNO-II-85-083, on 850818,util Notified by State of Wa That One Drum of Solidified Waste Oil Arrived at Us Ecology Burial Site W/Puncture Near Lower Ring.No Leakage Occurred. Util Burial Permit Suspended1985-08-22022 August 1985 PNO-II-85-083:on 850818,util Notified by State of Wa That One Drum of Solidified Waste Oil Arrived at Us Ecology Burial Site W/Puncture Near Lower Ring.No Leakage Occurred. Util Burial Permit Suspended PNO-II-85-070B, monitoring of Tropical Storm Bob Terminated.Natl Weather Svc No Longer Issuing Special Repts on Storm1985-07-26026 July 1985 PNO-II-85-070B:monitoring of Tropical Storm Bob Terminated.Natl Weather Svc No Longer Issuing Special Repts on Storm PNO-II-85-071A, broken Valve Stem Discovered Following Disassembly of Inboard Main Steam Line Isolation Valve. Caused by Metal Fatigue.Evaluation Continuing1985-07-26026 July 1985 PNO-II-85-071A:broken Valve Stem Discovered Following Disassembly of Inboard Main Steam Line Isolation Valve. Caused by Metal Fatigue.Evaluation Continuing PNO-II-85-071, on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed1985-07-25025 July 1985 PNO-II-85-071:on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed PNO-II-85-070A, on 850724,tropical Storm Bob Near Latitude 29.5 North & Longitude 80.3 West,About 40 Miles east-southeast of Daytona Beach,Fl.Storm Will Continue in Direction for Next 24 H.Precautions Will Be Taken If Needed1985-07-24024 July 1985 PNO-II-85-070A:on 850724,tropical Storm Bob Near Latitude 29.5 North & Longitude 80.3 West,About 40 Miles east-southeast of Daytona Beach,Fl.Storm Will Continue in Direction for Next 24 H.Precautions Will Be Taken If Needed PNO-II-85-053, on 850515,GPC Manually Shut Down Hatch Unit 1, IAW Ts,As Result of Safety Relief Valve Which Had Stuck Open But Eventually Reclosed.State of Ga Informed1985-05-16016 May 1985 PNO-II-85-053:on 850515,GPC Manually Shut Down Hatch Unit 1, IAW Ts,As Result of Safety Relief Valve Which Had Stuck Open But Eventually Reclosed.State of Ga Informed PNO-II-84-069A, update to PNO-II-84-069,issued on 841010. Region II Continues to Monitor Hurricane Josephine,Centered Near Latitude 29.4 North & Longitude 72.5 West1984-10-11011 October 1984 PNO-II-84-069A:update to PNO-II-84-069,issued on 841010. Region II Continues to Monitor Hurricane Josephine,Centered Near Latitude 29.4 North & Longitude 72.5 West PNO-II-83-054, on 830714,licensee Began Gradual Shutdown After Main Condenser Low Vacuum Condition Developed Re Operational Problems W/Air Ejectors for Unit.State of Ga Informed1983-07-15015 July 1983 PNO-II-83-054:on 830714,licensee Began Gradual Shutdown After Main Condenser Low Vacuum Condition Developed Re Operational Problems W/Air Ejectors for Unit.State of Ga Informed PNO-II-82-089, on 820730,facility Shut Down When Repairs to Emergency Diesel Generator Not Completed within Required Time.Repairs to Be Completed by 8208051982-08-0202 August 1982 PNO-II-82-089:on 820730,facility Shut Down When Repairs to Emergency Diesel Generator Not Completed within Required Time.Repairs to Be Completed by 820805 PNO-II-82-082, on 820715,unit Scrammed Due to Low Water Signal.Caused by Inadvertent Feedwater Pump Trip on Low Suction Pressure.Contaminated Water Overflowed from Precoat Tank to Turbine Bldg Floor & Outside to Ground.Area Closed1982-07-15015 July 1982 PNO-II-82-082:on 820715,unit Scrammed Due to Low Water Signal.Caused by Inadvertent Feedwater Pump Trip on Low Suction Pressure.Contaminated Water Overflowed from Precoat Tank to Turbine Bldg Floor & Outside to Ground.Area Closed PNO-II-82-067, on 820612, Turbine & Radwaste Bldgs Flooded by River Water.Caused by Ruptured Seal on Condensate Sys Water Box Manway.Contaminated Water Processed Through Radwaste Process Sys1982-06-15015 June 1982 PNO-II-82-067:on 820612, Turbine & Radwaste Bldgs Flooded by River Water.Caused by Ruptured Seal on Condensate Sys Water Box Manway.Contaminated Water Processed Through Radwaste Process Sys ML20216K1311978-09-25025 September 1978 PNO-78-172:on 780923,following Insp in Drywell W/Reactor Operating at Low Power,Three Men Were Trapped in Containment for Approx One Hour & 20 Minutes Due to Door Interlock Malfunction ML20216J8581978-08-18018 August 1978 PNO-78-145:on 780817,unit 2 Has Been Undergoing Low Power Startup Testing.Licensee Plans to Shutdown Unit 2 on 780821 to Modify Drywell Ventilation Sys,Required to Reduce Concrete Temp at Top of Biological Shield ML20216K1661978-07-0505 July 1978 PNO-78-131:on 780704,unit 2 Achieved Initial Criticality ML20248H8491978-05-0909 May 1978 PNO-78-106:on 780507,leak in off-gas Sys,Which Caused Release of Airborne Radioactivity Into Turbine Bldg.Buried off-gas Piping Being Excavated to Permit Further Exam.State of Ga Informed ML20151X6341977-10-0707 October 1977 PNO-77-176:on 771006,safety Relief Valves Failed to Operate After Reactor Tripped from 90% Power as Result of Error by Instrument Technician.Reactor Placed in Cold Shutdown Condition to Remove & Retest Suspect Valves ML20249A8551977-03-0101 March 1977 PNS-77-004:on 770222,after Fight W/Util Employee,Const Employee Was Fired & Directed to Leave Property.Upon Leaving Const Worker Tried to Run Down Security Guard W/Vehicle. Guard Drew Gun & Fired.Car Was Not Hit.Guard Was Suspended ML20140F5931977-02-0404 February 1977 PNO-77-022:on 770204,reactor Scrammed When Torus Temp Increased to 110 F.Caused by Two Target Rock Safety/Relief Valves Opening W/O Reseating Until Pressure Decreased to 100 Psig.Reactor Placed in Cold Shutdown ML20236K9191977-02-0101 February 1977 PNO-77-018:on 770131,while Operating at 90% Power Target Rock safety-relief Valve Opened & Did Not Reseat Until Pressure Decreased to 87 Psig.Reactor Placed in Cold Shutdown & safety-relief Valve Will Be Replaced ML20236L0651977-01-10010 January 1977 PNO-77-007:on 770109,CST While Operating at 91% Power Target Rock safety-relief Valve Opened & Did Not Reseat Until Pressure Decreased to 124 Psig.Reactor Manually Scrammed When Torus Temp Reached 110 Degrees F ML20236W8651975-12-15015 December 1975 PN-75-150:on 751213,GPC Notified Region 2 by Phone Re 2 Apparent Cracks Identified in 4 Inch Diameter Bypass Loop Around Loop a Recirculation Pump Discharge Valve.Licensee Replaced Pipe Tee & 1 Ft of 4 Inch Pipe ML20236U4271975-07-30030 July 1975 PN-75-058:on 750728,util Notified Region II That Reactor Blowdown from (95% Power) About 1005 Psi to About 430 Psi Occurred When 7 ADS Relief Valves Opened Simultaneously. Licensee Will Inspect Torus Before Returning to Power ML20236U1671975-06-11011 June 1975 PN-75-034:on 750611,Region II Ofc Was Notified That Security Guard at Hatch Had Received Outside Call on 750610 from Female Stating That Bomb Would Go Off at Hatch Plant within 24 Hrs.No Bomb Located 1999-06-17 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000321/19990091999-10-0707 October 1999
[Table view]Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823- 27.One Violation Being Treated as Ncv.Major Areas Inspected: Maint & Engineering IR 05000321/19990051999-09-16016 September 1999 Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000321/19990041999-08-0404 August 1999 Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000321/19990101999-07-20020 July 1999 Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Occurred & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Maint,Problem Identification & Resolution & Corrective Actions IR 05000321/19990031999-06-25025 June 1999 Insp Repts 50-321/99-03 & 50-366/99-03 on 990418-0529.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support PNO-II-99-025, on 990615,CR Operators Manually Shutdown Unit 2 Reactor from 41% Power,Due to Decreasing Condenser Vacuum. Cause of Decreasing Vacuum Has Not Been Determined.All Rods Installed as Required & All Safety Sys Functioned Properly1999-06-17017 June 1999 PNO-II-99-025:on 990615,CR Operators Manually Shutdown Unit 2 Reactor from 41% Power,Due to Decreasing Condenser Vacuum. Cause of Decreasing Vacuum Has Not Been Determined.All Rods Installed as Required & All Safety Sys Functioned Properly PNO-II-99-016, on 990505,Hatch Unit 2 Had Main Generator Trip Form 98% Power,Due to Electrical Fault.Licensee Continuing Investigation Has Been Hampered Due to Inclement Local Weather Conditions.Plant Being Depressurized1999-05-0707 May 1999 PNO-II-99-016:on 990505,Hatch Unit 2 Had Main Generator Trip Form 98% Power,Due to Electrical Fault.Licensee Continuing Investigation Has Been Hampered Due to Inclement Local Weather Conditions.Plant Being Depressurized IR 05000321/19990021999-05-0606 May 1999 Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000321/19990011999-04-0202 April 1999 Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non- Cited Violations Identified.Major Areas Inspected:Maint, Operations & Plant Support IR 05000321/19980091999-02-24024 February 1999 Insp Repts 50-321/98-09 & 50-366/98-09 on 981213-990123.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Rept Covers Insp in Health Physics & Independent Spent Fuel Storage IR 05000321/19980071998-12-29029 December 1998 Insp Repts 50-321/98-07 & 50-366/98-07 on 981101-1212.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000321/19980061998-11-24024 November 1998 Insp Repts 50-321/98-06 & 50-366/98-06 on 980920-1031. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000321/19980051998-10-15015 October 1998 Insp Repts 50-321/98-05 & 50-366/98-05 on 980802-0919.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Insp Also Included Insps by Regional Maint & Emergency Preparedness PNO-II-98-040, on 980917,licensee Declared Notification of Unusual Event Based on Transport of Two Injured & Potentially Contaminated Individuals to Local Hospital.Two Individuals Found Not to Have Sustained Serious Injury1998-09-18018 September 1998 PNO-II-98-040:on 980917,licensee Declared Notification of Unusual Event Based on Transport of Two Injured & Potentially Contaminated Individuals to Local Hospital.Two Individuals Found Not to Have Sustained Serious Injury IR 05000321/19980041998-08-21021 August 1998 Insp Repts 50-321/98-04 & 50-366/98-04 on 980621-0801.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Rept Includes Results of Insp by Regional Engineering & Safeguard IR 05000321/19980031998-07-14014 July 1998 Insp Repts 50-321/98-03 & 50-366/98-03 on 980503-0620.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support,Including Fire Hazards Analysis Requirements IR 05000321/19980021998-06-0101 June 1998 Insp Repts 50-321/98-02 & 50-366/98-02 on 980322-0502.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20217N1311998-04-21021 April 1998 Insp Repts 50-321/98-01 & 50-366/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20217N1101998-04-21021 April 1998 Notice of Violation from Insp on 980208-0321.Violation Noted:Maint Personnel Did Not Follow Procedures & Conducted Work That Was Not Specified on Maint Work Order Which Was Outside Approved Personnel Protection Clearance Boundary ML20216E7931998-03-10010 March 1998 Notice of Violation from Insp on 971228-980207.Violation Noted:As of 980207,measures Not Correctly Implemented in That Proposed Vendor Manual Change for Sys Not Submitted to Reflect Lower Set Point Requirement for PCV 2T48-F466 ML20216E7981998-03-10010 March 1998 Insp Repts 50-321/97-12 & 50-366/97-12 on 971228-980207. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199F5061998-01-23023 January 1998 Notice of Violation from Insp on 971116-1227.Violation Noted:On 971118,4 H Reporting Requirement Was Not Met. Several Workers Involved in Unit 2 Outage Activities Signed Into RCA on Improper RWPs Between 970317-0411 ML20199F5411998-01-23023 January 1998 Insp Repts 50-321/97-11 & 50-366/97-11 on 971116-1227. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20197F3571997-12-15015 December 1997 Notice of Violation from Insp on 971005-1115.Violation Noted:Licensee Failed to Label Properly Eight Spent Vacuum Filters Having Max Contact Dose Rates Ranging from 4.7 to 7.5 Rem Per Hour Which Were Suspended from Unit 1 Catwalk ML20197F3931997-12-15015 December 1997 Insp Repts 50-321/97-10 & 50-366/97-10 on 971005-1115. Violations & Deviations Noted.Major Areas Inspected:Maint, Engineering,Plant Support & Operations Re Health Physics Concern ML20197F3711997-12-15015 December 1997 Notice of Deviation from Insp on 971005-1115.Deviation Noted:Unit 2 Was Restarted on 940428 Following Spring Refueling Outage Repairs/Replacement Work Performed Under Design Change Request 96-006 ML20199G9381997-12-0101 December 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:On 970320,L Tillman Engaged in Deliberate Misconduct Causing Licensee to Be in Violation of TS 5.4,by Failing to Rept That Work Was Mistakenly Performed on Valve 2E51-F102 PNO-II-97-060, on 971120,plant Operators Manually Scrammed Reactor from 70% Power Due to Damage to Condensate Sys. Flexible Bellows on 2A Condensate Booster Pump Was Overpressurized.Licensee Initiate Controlled Shutdown1997-11-21021 November 1997 PNO-II-97-060:on 971120,plant Operators Manually Scrammed Reactor from 70% Power Due to Damage to Condensate Sys. Flexible Bellows on 2A Condensate Booster Pump Was Overpressurized.Licensee Initiate Controlled Shutdown ML20199B8121997-11-0303 November 1997 Notice of Violation from Insp on 970817-1004.Violation Noted:Written Procedures Were Not Implemented on 970815 & Maintenance Work Was Completed Using Maintenance Work Order W/Inadequate Instructions ML20199B8221997-11-0303 November 1997 Insp Repts 50-321/97-09 & 50-366/97-09 on 970817-1004. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000321/19970081997-10-0303 October 1997 Insp Repts 50-321/97-08 & 50-366/97-08 on 970818-22.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant IR 05000321/19970071997-09-11011 September 1997 Insp Repts 50-321/97-07 & 50-366/97-07 on 970629-0816.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20196J7431997-07-25025 July 1997 Insp Repts 50-321/97-05 & 50-366/97-05 on 970518-0628. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196J7051997-07-25025 July 1997 Notice of Violation from Insp on 970518-0628.Violation Noted:On 970609,steps 8.4.5 & 8.5.2 of Administration Control Procedure 30AC-OPS-001-OS,rev 15 Were Not Correctly Implemented ML20149H6651997-07-17017 July 1997 Insp Repts 50-321/97-06 & 50-366/97-06 on 970609-13. Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Including Problem Resolution,Operating Experience Feedback Programs & self-assessment Activities ML20149H6581997-07-17017 July 1997 Notice of Violation from Insp on 970609-13.Violation Noted: Improperly Stored Matl,Which Had Potential to Impact Performance of Safety Related Equipment in Control Room, Was Identified ML20141F8841997-06-17017 June 1997 Insp Repts 50-321/97-03 & 50-366/97-03 on 970406-0517. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20141F8641997-06-17017 June 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:Listed Examples of Inadequate Testing Procedures Were Identified ML20140C2301997-05-30030 May 1997 Notice of Violation from Insp on 970428-0502.Violation Noted:Policies & Procedures Were Not Adequately Implemented in Employee Assistance Program Info & Released W/O Written Permission from Employee ML20140C2441997-05-30030 May 1997 Insp Repts 50-321/97-04 & 50-366/97-04 on 970428-0502. Violations Noted.Major Areas Inspected:Fitness for Duty, Access Authorization & Physical Security Program for Power Reactors ML20148B8191997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Sections 8.12,8.13,4.2.2,4.7.7 & 8.8.3 of Procedure 30AC-OPS-001-OS Were Not Correctly Implemented IR 05000321/19970021997-05-0505 May 1997 Insp Repts 50-321/97-02 & 50-366/97-02 on 970223-0405. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000321/19973001997-04-0404 April 1997 NRC Operator Licensing Exam Repts 50-321/97-300 & 50-366/97-300 on 970314-20.Exam Results:All Candidates Passed Exam IR 05000321/19970991997-04-0404 April 1997 SALP Repts 50-321/97-99 & 50-366/97-99 for 950528-970222 ML20137F6301997-03-24024 March 1997 Notice of Violation from Insp on 970119-0222.Violation Noted:Design Control Requirements Not Translated Into Specifications ML20137F6451997-03-24024 March 1997 Insp Repts 50-321/97-01 & 50-366/97-01 on 970119-0222. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support PNO-II-97-017, on 970312,licensee Reported Employee Collapses Onsite.First Aid Administered Until Ambulance Arrived. Employee Transported to Appling County General Hosp in Baxley,Ga & Pronounced Dead.Autopsy Will Be Performed1997-03-13013 March 1997 PNO-II-97-017:on 970312,licensee Reported Employee Collapses Onsite.First Aid Administered Until Ambulance Arrived. Employee Transported to Appling County General Hosp in Baxley,Ga & Pronounced Dead.Autopsy Will Be Performed ML20134L0771997-02-13013 February 1997 Notice of Violation from Insp on 961208-970118.Violation Noted:Written Procedures Were Not Implemented & Listed Examples of Failure to Implement Procedures for Radiation Control Activities Were Identified PNO-II-97-006A, on 970129,plant Shutdown Due to Primary Pressure Boundary Leakage Update.Licensee Continuing to Cold Shutdown Conditions to Perform Addl Corrective Maint Activities.Resident Inspectors Monitoring Repair Actions1997-01-30030 January 1997 PNO-II-97-006A:on 970129,plant Shutdown Due to Primary Pressure Boundary Leakage Update.Licensee Continuing to Cold Shutdown Conditions to Perform Addl Corrective Maint Activities.Resident Inspectors Monitoring Repair Actions PNO-II-97-006, on 970129,Unit 1 Declared Notice of Unusual Event for Reactor Coolant Pressure Boundary Leakage,As Defined in TS 3.4.4.Resident Inspectors on Site Monitoring Licensee Actions.State of Ga Notified1997-01-29029 January 1997 PNO-II-97-006:on 970129,Unit 1 Declared Notice of Unusual Event for Reactor Coolant Pressure Boundary Leakage,As Defined in TS 3.4.4.Resident Inspectors on Site Monitoring Licensee Actions.State of Ga Notified 1999-09-16 |
July 26, 1985 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN0-II-85-71A This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without veriff-cation or evaluation, and is basically all that is known by the Region II staff on this dat2.
FACILITY: Georgia Power Company Licensee Emergency Classification:
Hatch Unit 1 Notification of Unusual Event Docket No. 50-321 Alert Baxley, Georgia- Site Area Emergency General Emergency X Not Applicable
SUBJECT:
UNSCHEDULED SHUTDOWN GREATER THAN 48 HOURS - UPDATE This PN updates PNO-II-85-71, issued July 25, 1985.
Disassembly of the inboard main steam line isolation valve in main steam line "A" has revealed a broken valve stem in the vicinity of the stem's backseat portion.
It appears that the break may have been caused by a metal fatigue failure. The affected valve in Unit I was manufactured by Atwood Morrel, but main steam isolation valves in Hatch Unit 2--which is operating at 100 percent power--are from a different vendor. Georgia Power is continuing to evaluate the valve problem.
Georgia Power is prepared to respond to media inquiries.
The State of Georgia has been informed. )
This information is current as of 11 a.m. (EDT) today.
Contact:
V. Panciera, 242-5525 V. Brownlee, 242-5583 DISTRIBUTION:
H. Streettitcf MNBB/ J Willsted.0 ' MAIL:
Chairman Palladino TF.;t.tsPhillips/yaf/W NRR T F-NMSS XDRIDiB Comm. Roberts PA OIA RES D0T: Trans Only Comm. Asselstine MPA AE00 Applicable State Comm. Bernthal ELD Comm. Zech Air Rights Il INP0 //3 D SECY SP NSAC ACRS R Regions: J /1:1r % po gg #tL gM Licensee:u_f27ev a ftp (ReactorLicensees)
Applicable Resident Site [/f(,
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8508020120 850726 PDR IIE PNO-II-95-071 A PDR I