PNO-III-94-086, on 941103,near End of Operability Test for 2B Emergency Diesel Generator Master Rod in Diesel Failed Resulting in Significant Internal Damage to 1L & 1R Cylinders
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| ML20203G914 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/07/1994 |
| From: | Miller L, Walker A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| PNO-III-94-086, PNO-III-94-86, NUDOCS 9712180258 | |
| Download: ML20203G914 (1) | |
Similar Documents at Braidwood | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-III-98-013, on 980126,turbine Tripped Causing Subsequent Reactor Trip.Cause of Turbine Trip Remains Under Investigation.Appears Replacement Circuit Board Had Incorrect Electronic Configuration1998-01-29029 January 1998
[Table view]PNO-III-98-013:on 980126,turbine Tripped Causing Subsequent Reactor Trip.Cause of Turbine Trip Remains Under Investigation.Appears Replacement Circuit Board Had Incorrect Electronic Configuration PNO-III-97-071, on 970903,Comm Ed Announced Series of Mgt Changes & Restructuring of Nuclear Div Organization.New Site Vice Presidents at Braidwood & Quad Cities Former Plant Managers.State of Il Will Be Notified of Mgt Changes1997-09-0303 September 1997 PNO-III-97-071:on 970903,Comm Ed Announced Series of Mgt Changes & Restructuring of Nuclear Div Organization.New Site Vice Presidents at Braidwood & Quad Cities Former Plant Managers.State of Il Will Be Notified of Mgt Changes PNO-III-94-086, on 941103,near End of Operability Test for 2B Emergency Diesel Generator Master Rod in Diesel Failed Resulting in Significant Internal Damage to 1L & 1R Cylinders1994-11-0707 November 1994 PNO-III-94-086:on 941103,near End of Operability Test for 2B Emergency Diesel Generator Master Rod in Diesel Failed Resulting in Significant Internal Damage to 1L & 1R Cylinders PNO-III-94-013, on 940308,contract Worker Was Injured When He Fell Into Blowdown Demineralizer Vault.Worker Was Transported in Ambulance to Area Hosp in Serious Condition1994-03-0909 March 1994 PNO-III-94-013:on 940308,contract Worker Was Injured When He Fell Into Blowdown Demineralizer Vault.Worker Was Transported in Ambulance to Area Hosp in Serious Condition PNO-III-93-061, on 931023,licensee Commenced Shutdown of Unit 1 Due to Indications of Primary to Secondary Leak in SG 1C. Shutdown Completed on 931025.State of Il Notified1993-10-25025 October 1993 PNO-III-93-061:on 931023,licensee Commenced Shutdown of Unit 1 Due to Indications of Primary to Secondary Leak in SG 1C. Shutdown Completed on 931025.State of Il Notified PNO-III-93-057, on 931003,reactor Tripped Due to Low Steam Generator Level.Feedwater Regulating Valve for D Steam Generator Had Failed in Fully Closed Position Due to Failed Positioner.State of Il Notified1993-10-0404 October 1993 PNO-III-93-057:on 931003,reactor Tripped Due to Low Steam Generator Level.Feedwater Regulating Valve for D Steam Generator Had Failed in Fully Closed Position Due to Failed Positioner.State of Il Notified PNO-III-92-056, on 921015,licensee Reported Discovery of Evidence of Vandalism in Upper Cable Spreading Room,Shared by Both Units,Caused by Contractor Employee Who Performed Firewatch Duties.Employee Site Access Suspended1992-10-16016 October 1992 PNO-III-92-056:on 921015,licensee Reported Discovery of Evidence of Vandalism in Upper Cable Spreading Room,Shared by Both Units,Caused by Contractor Employee Who Performed Firewatch Duties.Employee Site Access Suspended PNO-III-90-055, on 900801,unit Shut Down to Repair Check Valve 1A Essential Svc Water Pump.Caused by Failure of Pump Discharge Check Valve to Seat.Check Valve Will Be Replaced1990-08-0808 August 1990 PNO-III-90-055:on 900801,unit Shut Down to Repair Check Valve 1A Essential Svc Water Pump.Caused by Failure of Pump Discharge Check Valve to Seat.Check Valve Will Be Replaced PNO-III-89-047, on 890718,rod Control Sys Lost Power,Dropping Control Rods Into Reactors.Caused by Lightning Strikes.Power Supplies Reset & Rod Control Sys Operating Normally.Licensee Plans to Restart Both Units on 8907191989-07-19019 July 1989 PNO-III-89-047:on 890718,rod Control Sys Lost Power,Dropping Control Rods Into Reactors.Caused by Lightning Strikes.Power Supplies Reset & Rod Control Sys Operating Normally.Licensee Plans to Restart Both Units on 890719 PNO-III-89-029A, on 890425,Augmented Insp Team Began Insp at Plant in Response to NRC Observations of Two Employees Appearing Inattentive to Duty.Licensee Reestablished Shift Overview Superintendent Position to Provide Mgt Visibility1989-04-28028 April 1989 PNO-III-89-029A:on 890425,Augmented Insp Team Began Insp at Plant in Response to NRC Observations of Two Employees Appearing Inattentive to Duty.Licensee Reestablished Shift Overview Superintendent Position to Provide Mgt Visibility PNO-III-89-031, on 890423,licensee Shutdown Reactor Because Instrument Power Supply Was Found to Be Inoperable on 970422.Caused by Faulty Capacitor & Inverter Repaired & Returned to Svc on 8904251989-04-25025 April 1989 PNO-III-89-031:on 890423,licensee Shutdown Reactor Because Instrument Power Supply Was Found to Be Inoperable on 970422.Caused by Faulty Capacitor & Inverter Repaired & Returned to Svc on 890425 PNO-III-89-029, on 890418,Region III Operator Licensing Examiner Observed Individual with Eyes Closed in Chair in Unit 1 Cr.On 890419,licensing Examiner Observed Radiation Control Technician Asleep at Desk by RCA at Building Exit1989-04-24024 April 1989 PNO-III-89-029:on 890418,Region III Operator Licensing Examiner Observed Individual with Eyes Closed in Chair in Unit 1 Cr.On 890419,licensing Examiner Observed Radiation Control Technician Asleep at Desk by RCA at Building Exit PNO-III-89-025, on 890411,main Turbine Tripped by Licensee. Reactor Shut Down for Repairs on Already Malfunctioning Main Turbine Governor Valve.Unit Expected to Return to Svc on 890416.State of Il to Be Notified1989-04-11011 April 1989 PNO-III-89-025:on 890411,main Turbine Tripped by Licensee. Reactor Shut Down for Repairs on Already Malfunctioning Main Turbine Governor Valve.Unit Expected to Return to Svc on 890416.State of Il to Be Notified PNO-III-88-094, on 881115,discovered Joint in 4-inch Instrument Air Line Damaged & Causing Loss of Pressure in Compressed Air Sys.Air Line Joint Probably Stepped on by Painter Working in Area1988-11-16016 November 1988 PNO-III-88-094:on 881115,discovered Joint in 4-inch Instrument Air Line Damaged & Causing Loss of Pressure in Compressed Air Sys.Air Line Joint Probably Stepped on by Painter Working in Area PNO-III-88-088, on 881025,unit Manually Tripped from 28% Power to Avoid Challenging Reactor Protection Sys.Caused by Low Steam Generator Water Levels.Unit Expected to Be Down from Five to Seven Days While Strainers Cleaned1988-10-26026 October 1988 PNO-III-88-088:on 881025,unit Manually Tripped from 28% Power to Avoid Challenging Reactor Protection Sys.Caused by Low Steam Generator Water Levels.Unit Expected to Be Down from Five to Seven Days While Strainers Cleaned PNO-III-88-086, on 881016,reactor Automatically Shut Down Following Loss of Offsite power.Diesel-driven Auxiliary Feedwater Pumps Maintained Steam Generator Level.Caused by Explosion & Fire in Substation & Carboard in Delay Relay1988-10-18018 October 1988 PNO-III-88-086:on 881016,reactor Automatically Shut Down Following Loss of Offsite power.Diesel-driven Auxiliary Feedwater Pumps Maintained Steam Generator Level.Caused by Explosion & Fire in Substation & Carboard in Delay Relay PNO-III-88-048, on 880520,full Power OL Issued.Currently at 8% Power,Licensee Engaged in Power Ascension Activities. NRR Region IV Will Provide Augmented Insp Coverage of Power Ascension1988-05-23023 May 1988 PNO-III-88-048:on 880520,full Power OL Issued.Currently at 8% Power,Licensee Engaged in Power Ascension Activities. NRR Region IV Will Provide Augmented Insp Coverage of Power Ascension PNO-III-88-026, on 880323,licensee Began Orderly Shutdown of Unit 1 Due to Identified Deficiencies in Lubricant Used in motor-operated Limitorque Valves.Deficiencies Apply to 263 safety-related Valves in Both Units 1 & 21988-03-24024 March 1988 PNO-III-88-026:on 880323,licensee Began Orderly Shutdown of Unit 1 Due to Identified Deficiencies in Lubricant Used in motor-operated Limitorque Valves.Deficiencies Apply to 263 safety-related Valves in Both Units 1 & 2 PNO-III-88-017, on 880308,unit Achieved Initial Criticality. Conditions at Criticality as Expected.Nrc Inspectors Monitored Preparation for Criticality.Ol Permitting Fuel Loading & Low Power Testing Issued on 8712181988-03-0808 March 1988 PNO-III-88-017:on 880308,unit Achieved Initial Criticality. Conditions at Criticality as Expected.Nrc Inspectors Monitored Preparation for Criticality.Ol Permitting Fuel Loading & Low Power Testing Issued on 871218 PNO-III-87-154, on 871218,OL Issued to Facility to Permit Fuel Loading & Operation Up to 5% Power.Fuel Loading Scheduled for 871221.Initial Criticality Planned for Feb 19881987-12-21021 December 1987 PNO-III-87-154:on 871218,OL Issued to Facility to Permit Fuel Loading & Operation Up to 5% Power.Fuel Loading Scheduled for 871221.Initial Criticality Planned for Feb 1988 PNO-III-87-155, on 871220,fire Damaged Const Warehouse Outside Protected Area.Cause Under Investigation.Fire Did Not Affect Plant Operations.Local Fire Depts Summoned1987-12-21021 December 1987 PNO-III-87-155:on 871220,fire Damaged Const Warehouse Outside Protected Area.Cause Under Investigation.Fire Did Not Affect Plant Operations.Local Fire Depts Summoned PNO-III-87-099, on 870717,licensee Declared Diesel Generator 1B Inoperable Following Monthly Surveillance Test.Licensee Unable to Maintain Min Load of 5,500 Kw Per Tech Specs Due to Output Swings.Unit Shut Down in Excess of 48 H1987-07-21021 July 1987 PNO-III-87-099:on 870717,licensee Declared Diesel Generator 1B Inoperable Following Monthly Surveillance Test.Licensee Unable to Maintain Min Load of 5,500 Kw Per Tech Specs Due to Output Swings.Unit Shut Down in Excess of 48 H PNO-III-87-092, on 870702,util Issued full-power Operating License for Unit 1.State of Il to Be Notified.Unit 2 Under Const & 97% Complete1987-07-0202 July 1987 PNO-III-87-092:on 870702,util Issued full-power Operating License for Unit 1.State of Il to Be Notified.Unit 2 Under Const & 97% Complete PNO-III-87-081, on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants1987-06-11011 June 1987 PNO-III-87-081:on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants PNO-III-87-080, on 870529,reactor Achieved Initial Criticality.Ol Issued on 861017,authorizing Fuel Load & Subcritical Testing.Preparation for & Achievement of Initial Criticality Monitored by Resident Inspectors1987-06-0101 June 1987 PNO-III-87-080:on 870529,reactor Achieved Initial Criticality.Ol Issued on 861017,authorizing Fuel Load & Subcritical Testing.Preparation for & Achievement of Initial Criticality Monitored by Resident Inspectors PNO-III-87-049, on 870408,handgun Found on Contract Employee During Walk Through Metal Detector at Entrance to Protected Area.Incident Under Investigation.Individual Has Access to All Vital Areas in Plant Except for Central Alarm Station1987-04-0808 April 1987 PNO-III-87-049:on 870408,handgun Found on Contract Employee During Walk Through Metal Detector at Entrance to Protected Area.Incident Under Investigation.Individual Has Access to All Vital Areas in Plant Except for Central Alarm Station PNO-III-87-047, on 870329,failure of Rocker Arm on Emergency Diesel Generator 2B Number 5 Right Cylinder Occurred. Concurrent Metallurgical Analyses Being Conducted to Determine Cause of Event1987-04-0202 April 1987 PNO-III-87-047:on 870329,failure of Rocker Arm on Emergency Diesel Generator 2B Number 5 Right Cylinder Occurred. Concurrent Metallurgical Analyses Being Conducted to Determine Cause of Event PNO-III-87-020, on 870204,lubricating Oil & Fuel Leaks Detected During 24 H Test Run of Emergency Diesel Generator. Caused by Interference Between Cross Head & Cross Head Guide.Steps to Ensure Correct Clearance Being Taken1987-02-0606 February 1987 PNO-III-87-020:on 870204,lubricating Oil & Fuel Leaks Detected During 24 H Test Run of Emergency Diesel Generator. Caused by Interference Between Cross Head & Cross Head Guide.Steps to Ensure Correct Clearance Being Taken PNO-III-87-010, on 870121,both Component Cooling Water Pumps Tripped in Succession Rendering Sys Inoperable.Initial Cause Due to Low Surge Tank Flow.Cause of Low Flow Under Investigation.Operability Restored by Restoring Flow Level,1987-01-22022 January 1987 PNO-III-87-010:on 870121,both Component Cooling Water Pumps Tripped in Succession Rendering Sys Inoperable.Initial Cause Due to Low Surge Tank Flow.Cause of Low Flow Under Investigation.Operability Restored by Restoring Flow Level, PNO-III-86-126, on 861101,anonymous Male Caller Telephoned Plant Security Ofc Claiming Bomb Had Been Planted in Auxiliary Bldg.Auxiliary Bldg Evacuated Except for Firewatch & Security Personnel & Search Conducted.No Bomb Found1986-11-0303 November 1986 PNO-III-86-126:on 861101,anonymous Male Caller Telephoned Plant Security Ofc Claiming Bomb Had Been Planted in Auxiliary Bldg.Auxiliary Bldg Evacuated Except for Firewatch & Security Personnel & Search Conducted.No Bomb Found PNO-III-86-117, on 861017,operating License Issued to Commonwealth Edison Co for Braidwood Nuclear Power Station, Unit 1.License Limited to Fuel Loading & Initial Testing Activities Leading to Criticality1986-10-17017 October 1986 PNO-III-86-117:on 861017,operating License Issued to Commonwealth Edison Co for Braidwood Nuclear Power Station, Unit 1.License Limited to Fuel Loading & Initial Testing Activities Leading to Criticality PNO-III-86-101, on 860918,ASLB Issued Memorandum & Order Authorizing NRR to Issue Limited License to Util for Fuel Loading & Precriticality Testing.Fuel Loading Expected on 8610151986-09-19019 September 1986 PNO-III-86-101:on 860918,ASLB Issued Memorandum & Order Authorizing NRR to Issue Limited License to Util for Fuel Loading & Precriticality Testing.Fuel Loading Expected on 861015 PNO-III-86-053, on 860604,pressurizer Relief Tank Overpressurized W/Pure Water Bursting Rupture Diaphragm. Caused by Incorrect Valve Lineup During Testing Leak Detection Sys.Contractor Employees Injured1986-06-0505 June 1986 PNO-III-86-053:on 860604,pressurizer Relief Tank Overpressurized W/Pure Water Bursting Rupture Diaphragm. Caused by Incorrect Valve Lineup During Testing Leak Detection Sys.Contractor Employees Injured PNO-III-86-030, on 860325,while Conducting Hft,Two Main Steam Line Pipe Supports in Steam Tunnel Failed as Result of Apparent Water Hammer.State of Il Notified1986-03-26026 March 1986 PNO-III-86-030:on 860325,while Conducting Hft,Two Main Steam Line Pipe Supports in Steam Tunnel Failed as Result of Apparent Water Hammer.State of Il Notified PNO-III-80-040, station Will Start Limited Const of safety- Related Activities During Wk of 800303-08.Staff Will Slowly Be Increased to High of 700 in June1980-02-29029 February 1980 PNO-III-80-040:station Will Start Limited Const of safety- Related Activities During Wk of 800303-08.Staff Will Slowly Be Increased to High of 700 in June ML20249A8851977-12-27027 December 1977 PNS-77-050:on 771223,telephone Call Was Received by Secretary for Piping Contractor for Braidwood Site Re Bomb Threat.No Mass Evacuation Was Made & No Suspicious Devices Were Found During Search ML20236E9121977-08-16016 August 1977 PNS-77-031:on 770815,anonymous Call Was Received by Supervisor,Stating That Three Sticks of Dynamite Had Been Placed in Unit 1 Containment.Immediate Search Was Conducted & No Explosives Were Found.Site Was Not Evacuated ML20151U9931977-05-12012 May 1977 PNO-77-081:on 770511,ironworkers from Kankakee,Il Went on Strike.Ironworkers Contract Expires 770420 & Strike Concerns Wages & Work Rules.No Press Release Made ML20249B6381976-05-25025 May 1976 PNO-76-091:on 760525,primary Coolant Target Rock Relief Valve Failed to Close Properly.Preliminary Info Indicates No safety-related Problems Resulted from Event.Inspector at Site to Review Corrective Action & Cause of Failure 1998-01-29 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000456/19990131999-09-17017 September 1999
[Table view]Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824. Violations Noted.Major Areas Inspected:C/As & Engineering Related Activities to Address Technical Concerns Identified During Design Insp Completed on 980424 IR 05000456/19990121999-09-0303 September 1999 Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000254/19990101999-08-20020 August 1999 Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Major Areas Inspected:Licensee C/A Approach & Implementation of Configuration Control Processes at Each Site IR 05000456/19990111999-07-29029 July 1999 Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000456/19990091999-07-20020 July 1999 Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Major Areas Inspected:Licensee Radiation Protection Program.Circumstances Surrounding 990428, Gatehouse Monitor Exiting Incident Were Also Reviewed IR 05000456/19990071999-06-18018 June 1999 Insp Repts 50-456/99-07 & 50-457/99-07 on 990414-0524.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000457/19990081999-06-14014 June 1999 Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted. Major Areas Inspected:Isi & SG Insp Program IR 05000456/19990051999-05-20020 May 1999 Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Non- Cited Violations Identified.Major Areas Inspected:Review of Engineering & Technical Support & Corrective Actions IR 05000456/19990061999-05-11011 May 1999 Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.One non-cited Violation Re Configuration Control Error Occurred. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000456/19990021999-03-23023 March 1999 Insp Repts 50-456/99-02 & 50-457/99-02 on 990120-0301.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000456/19990041999-03-23023 March 1999 Insp Repts 50-456/99-04 & 50-457/99-04 on 990222-24 & 0303 Onsite & 0309 & 11 Region 3 Ofc.No Violations Noted.Major Areas Inspected:Physical Security Program IR 05000456/19980161999-02-11011 February 1999 Insp Rept 50-456/98-16 on 980916-990121.No Violations Noted. Major Areas Inspected:Containment Access Opening & Replacement Activities,Removal & Replacement of Sgs,Welding of SG Piping & Review of Quality Control Activities IR 05000456/19980201998-12-30030 December 1998 Insp Repts 50-456/98-20 & 50-457/98-20 on 981020-1207.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000456/19980211998-12-10010 December 1998 Insp Repts 50-456/98-21 & 50-457/98-21 on 981110-24.No Violations Noted.Major Areas Inspected:Aspects of Corrective Actions & Engineering Involvement in Corrective Action Process IR 05000456/19980181998-12-0404 December 1998 Insp Rept 50-456/98-18 on 981015-23 & 1109-10.No Violations Noted.Major Areas Inspected:Four Areas Associated with Licensee SG Replacement Project IR 05000456/19980191998-11-25025 November 1998 Insp Repts 50-456/98-19 & 50-457/98-19 on 981027-30.No Violations Noted.Major Areas Inspected:Licensee Implementation of 10CFR50.65 Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants ML20195G3731998-11-17017 November 1998 Insp Repts 50-456/98-14 & 50-457/98-14 on 980909-1019. Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering ML20195G3681998-11-17017 November 1998 Notice of Violation from Insp on 980909-1019.Violation Noted:As of 980818,licensee Failed to Initiate Measures to Determine Cause or Take Action to Preclude Recurrence of Loose Bolts on Two EDG Lubricating Oil Heat Exchanger Bells ML20195G3031998-11-13013 November 1998 Notice of Violation from Insp on 980915-1022.Violation Noted:On 981022,two Individuals Working Under RWP 984014 Removed Outer Rubber Gloves While Replacing Insulation in Containment IR 05000456/19980151998-11-13013 November 1998 Insp Repts 50-456/98-15 & 50-457/98-15 on 980915-1022. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program Focusing on Radiological Controls for Unit 1 Outage Activities & SG Replacement Project IR 05000456/19980171998-11-10010 November 1998 Insp Repts 50-456/98-17 & 50-457/98-17 on 981013-19. Violations Noted.Major Areas Inspected:Security Measures Implemented to Support Steam Generator Replacement Project ML20196D9201998-11-10010 November 1998 Notice of Violation from Insp on 981013-19.Violation Noted: Licensee Security Staff Discovered That on Three Occasions Between 980826 & 1002,security Officers Were Found Asleep on Post IR 05000456/19983051998-11-0202 November 1998 Exam Repts 50-456/98-305 & 50-457/98-305 on 980914 with Telephoned Exam Results 981020.No Violations Noted.Exam Results:Applicant Passed Retake Exam & Was Issued Reactor Operator License IR 05000456/19980121998-10-0505 October 1998 Insp Repts 50-456/98-12 & 50-457/98-12 on 980728-0908.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000456/19980111998-09-25025 September 1998 Insp Rept 50-456/98-11 on 980707-09,15-16,0805-06,10-13 & 26-28.No Violations Noted.Major Areas Inspected:Review of SG Replacement Program.Insp Focused on Welding of SG Feedwater Piping & Preparation Activities for Replacing SGs IR 05000456/19980131998-08-28028 August 1998 Insp Repts 50-456/98-13 & 50-457/98-13 on 980810-14.No Violations Noted.Major Areas Inspected:Review of Chemistry & Radiation Protection Programs IR 05000456/19980091998-08-25025 August 1998 Insp Repts 50-456/98-09 & 50-457/98-09 on 980609-0727. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support ML20236N0911998-07-0606 July 1998 Notice of Violations from Insp on 980421-0608.Violations Noted:On 980424,licensee Failed to Implement Specific Fire Protection Program Requirements in That Welding Machine Was Left Unattended & Energized in Fuel Handling Bldg ML20236N0941998-07-0606 July 1998 Insp Repts 50-456/98-08 & 50-457/98-08 on 980421-0608. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000456/19980101998-07-0202 July 1998 Insp Repts 50-456/98-10 & 50-457/98-10 on 980615-19.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000456/19980071998-06-18018 June 1998 Insp Repts 50-456/98-07 & 50-457/98-07 on 980519-22.No Violations Noted.Major Areas Inspected:Licensee Performance During Plant Biennial Exercise of Emergency Plan IR 05000456/19982011998-06-0101 June 1998 Insp Rept 50-456/98-201 on 980316-20,0330-0410 & 0420-24. No Violations Noted.Major Areas Inspected.Team Selected & Reviewed Relevant Portions of Ufsar,Ts,Drawings, Calculations,Mod Packages & Procedures IR 05000456/19980051998-05-19019 May 1998 Insp Repts 50-456/98-05 & 50-457/98-05 on 980310-0420. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support ML20248D0821998-05-19019 May 1998 Notice of Violation from Insp on 980310-0420.Violation Noted:On 980303,licensee Failed to Implement Braidwood Administrative Procedure 2321-18T11,Step E.1,for Sf Pool Skimmer Strainer Level Control IR 05000456/19983041998-04-29029 April 1998 NRC Operator Licensing Exam Repts 50-456/98-304OL & 50-457/98-304OL (Including Completed & Graded Tests) Administered During Wk of 980413 ML20217F5281998-04-21021 April 1998 Notice of Violation from Insp on 980331-0407.Violation Noted:Licensee Failed to Check That SG Worker Dosimetry Was Present & Correctly Worn IR 05000456/19980061998-04-21021 April 1998 Insp Repts 50-456/98-06 & 50-457/98-06 on 980331-0407. Violations Noted.Major Areas Inspected:Announced Review Protection Program.Insp Focused on Liquid & Gaseous Effluent Radiation Monitoring Programs ML20216B0611998-04-0808 April 1998 Notice of Violation from Insp on 980127-0309.Violation Noted:On 971010,21,1219 & 980105,licensee Failed to Require Independent Verification of Proper Sys Alignment for safety-related Valves Repositioned in Steps F.1.4 & F.1.7 ML20216B0761998-04-0808 April 1998 Insp Repts 50-456/98-02 & 50-457/98-02 on 980127-0309. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000456/19980031998-03-16016 March 1998 Insp Repts 50-456/98-03 & 50-457/98-03 on 980128-30.No Violations Noted.Major Areas Inspected:Operations & Maint ML20203D9201998-02-20020 February 1998 Insp Repts 50-456/97-22 & 50-457/97-22 on 971216-980126. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20203D9151998-02-20020 February 1998 Notice of Violation from Insp on 971216-980126.Violation Noted:In Nov 1989,licensee Failed to Initiate Deviation Rept & Take Corrective Measures to Preclude Repetition of Mechanical Failure to All 4 Main Feedwater Check Valves ML20202F2321998-02-11011 February 1998 Notice of Violations from Insp on 971112-21 & 980115. Violations Noted:Licensee Failed to Follow NSWP-A-15 & Bwap 330-10 Requirements to Issue PIF for Tempering Line Snubber Considered Inoperable on 971110 IR 05000457/19970211998-02-11011 February 1998 Insp Rept 50-457/97-21 on 971112-21 & 980115.Violations Noted.Major Areas Inspected:Operations & Engineering PNO-III-98-013, on 980126,turbine Tripped Causing Subsequent Reactor Trip.Cause of Turbine Trip Remains Under Investigation.Appears Replacement Circuit Board Had Incorrect Electronic Configuration1998-01-29029 January 1998 PNO-III-98-013:on 980126,turbine Tripped Causing Subsequent Reactor Trip.Cause of Turbine Trip Remains Under Investigation.Appears Replacement Circuit Board Had Incorrect Electronic Configuration ML20198G1231998-01-0707 January 1998 Partially Withheld Insp Repts 50-456/97-20 & 50-457/97-20 on 971117-21 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support Performance Involving Evaluation of Effectiveness of Physical Protection Program ML20202F1951998-01-0202 January 1998 Insp Repts 50-456/97-19 & 50-457/97-19 on 971104-1215. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 07100104/20120151998-01-0202 January 1998 Notice of Violation from Insp on 971104-1215.Violation Noted:On 971102,inspectors Identified That Licensee Had Failed to Fasten Covers on Incore Neutron Detector Drive Mechanism IR 05000456/19973101997-12-29029 December 1997 NRC Operator Licensing Exam Repts 50-456/97-310OL & 50-457/97-310OL for Tests Administered on 971006-1107.Three Senior Reactor Operators & One Reactor Operator Passed Exam. One Senior Reactor & One Reactor Operator Failed ML20199A5681997-12-17017 December 1997 Notice of Violation from Insp on 970923-1103.Violation Noted:On 971014,licensee Instrument Technician Made Error When Changing Setpoints on Unit 2 Containment Area Radiation Monitor 2AR11J.Error Resulted in High Radiation Alarm 1999-09-03 |
/ )/( 6/Dt4y . d 8 Date: November 7, 1994-3ELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-III-94-86 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or' evaluation, and is bas cally all that is known by the Region III otaff on this date.
Eacility Licensee Emeraency Classification Commonwealth Edison Co. General Emergency Braidwood 2 Site Area Emergency Braceville, Illinois Alert Unusual Event Docket No. 50-457 X Not Applicable
Subject:
DAMAGE TO EMERGENCY DIESEL GENERATOR On November 3, 1994, near the end of an operability test for the 2B cmergency diesel generator, a master rod in the diesel failed, resulting in significant internal damage to the IL and 1R cylinders. Unit 2 has been chut down since October 8 for refueling and maintenance.
An examination of the broken rod revealed numerous hairline cracks which apparently caused the rod failure, according to the licensee and a representative of the diesel manufactuser, Cooper Bessemer. The Cooper Qpssemer representative indicated that the cracks were probably due to an inappropriate repair technique (iron plating) during manufacturing used on limitea number of rods produced before 1987. The manufacturer issued a O CFR 21 notification in 1987 after a master rod failure at the Palo Verde Nuclear Power Station. The company notified Commonwealth Edison that only one rod had been sent to the utility, and it was installed at Byron. That rod was subsequently replaced. The Cooper Bessemer review apparently missed the maater rod which failed in the Braidwood diesel.
A Region III (Chicago) inspector was dispatched to the Braidwood site to review the diesel damage on November 4-5, 1994. The Cooper Bessemer
- representative indicated to the inspector that che company would review its 10 CFR 21 report and search its records for any additional rod problems that had been missed at the time of the 1987 review.
Licensee personnel are currently repairing the damaged dieseln .The diesel will be tested following the repair, which is expected to befcompleted November 8, 1994. { g5 a ~= ~
The State of Illinois will be notified. The information in ghisi l' preliminary notification has been reviewed with licensee management!y!,
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Region III was notified of the diesel damage on November 3, I594[, Thls j information is current as of 9 a.m. on November 7, 1994. g ; CI CONTACT:
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' owls Miller 38/829-9629
, Al Walker g*1708/829-9728
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