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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[Table view]
Category:RO)
MONTHYEARML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
ML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7471999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7341999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp.
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
[Table view] |
Text
ACCELERATED DIS~BUTION DEMONS+ATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9205280129 DOC.DATE:
92/05/20NOTARIZED:
NODOCKET.iz FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION BACKUS,W.H.
Rochester Gas&ElectricCorp.MECREDY,R.C.
Rochester Gas&'lectric Corp.RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER92-005-00:on 920420,annual maintenance examperformed onbothS/G"A"&"B."242tubesin"A"&216tubesin"B"S/GrequiredC/Aduetotubedegradation.
Causedbyrecurring IGA/SCC&PWSCC.S/G returntonormal.W/920520 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR l.ENCLQSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.DNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
05000244'ARECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
ACNWAEOD/DSP/TPABNRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8ERES/DSIR/EIB EXTERNAL:
EG&GBRYCE,J.H NRCPDRNSICPOOREiW~COPIESLTTRENCL1111221.111112211111.133111.1RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DSPNRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8DNRRDST/SPLB8D1 R&02RGN1FIE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11DDS,RDNOTETOALL"RIDS"RECIPIENTS:
ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOiv1P1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR30ENCL30 tI
'OCHESTER GASANDELECTRICCORPORATION ROBERTCMECREDYVicePresident CinnaNuclearPsoducRon i;coenaeaee~e9EASTAVENUE,ROCHESTER N.K14649-0001 aTECEPHOkE AREACODE7165462700May20,1992U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555
Subject:
LER92-005,SteamGenerator TubeDegradation DuetoIGA/SCC,CausesQ.A.ManualReportable LimitstobeReachedR.E.GinnaNuclearPower.PlantDocketNo.50-244Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(other),andtheGinnaStationQualityAssurance ManualAppendixB,whichrequiresthat,"Ifthenumberoftubesinagenerator fallingintocategories (a)or(b)belowexceedsthecriteria, thenresultsoftheinspection shallbeconsidered areportable eventpursuantto10CFR50.73,"theattachedLicenseeEventReportLER92-005'is herebysubmitted.
Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,RobertC.MeredXC'.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussiaPA19406GinnaUSNRCSeniorResidentInspector 9205280129 920520PDRADOCK050002448PDR~@PE,<7~E W/~gag'l<
l NACFORM368(64)9)LICENSEEEVENTREPORT(LERIAPPROVEDOMBNO.31504)104 EXPIRES:4(30(92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F630).V.S.NUCLEARREGULATORY COMMISSION, WASHINGTON.
DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(31500104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON.
DC20503.'ACILITYNAME(1IR.E.GinnaNuclearPowerPlantDOCKETNUMBER(2)PAE3050002441OF09
""""SteamGenerator TubeDegradation DueTo1GA/SCCCausesQ.A.ManualReportable LimitsToBeReachedEVENTDATEIS)LERNUMBER(6I>>REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTHDAYYEARYEARBEOUENTIAL ergNUMBERNUMBERREYIBONMONTHOAYYEARFACILITYNAMESDOCKETNUMBER(S) 05000042092920050005209205000OPERATING MODE(9)POWERLEVEL(10)@P)CP@&m(r
'.a)P20A02(B)20.405(sI(I)ill20.405(sIllI(III20.405(el(1llill) 20A05(sI(1)(lv)20.405(s)
(II(vl20A05(c)50.38(cl(1) 50.38(cl(2) 50.73(sIl2)(l)50.73(el(2)(li) 50.73(sl(2)BillLICENSEECONTACTFORTHISLER(12)50.73(s)(2)(irl50.73(sl(2)(vl 50,73(sl(2)(vill 50,73(sI(2I(riIII(Al50,73(s)(2)(rilll(B)50,73(sl(2)(sl THISREPORTISSUBMITTFO PURSUANTT0THERLQVIREMENTS OF10CFR()IICnec>>OneormoreolthelollowinPI (1173.71(BI73.7((clXOTHERISpecllyInAottrectBelowendlnTenet,HRCForm366A)NAMEWesleyH.Backus.Technical Assistant to-theOperations ManagerTELEPHONE NUMBERAREACODE315524-4446COMPLETEONELINEFOAEACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFAC.TUREREPORTABLE TONPRDSSYSTEMCOMPONENT MANUFACTUREREPORTABLE TONPRDSXABTBGH314IR4$e($BW@~NIINA!
r.k45%4:SUPPLEMENTAL REPORTEXPECTED(14)EXPECTEDSU6MISSIONDATE115)MONTHDAYYEARYESIIIyer,completeEXPECTEDS(IB4IISSION DATEINOABSTRACTILlmltto1400rpecsLi,e.,epproslmerely Irfteentinplespreetypewritten linn)(18)Duringthe1992AnnualRefueling andMaintenance Outage,subsequent totheEddyCurrentExamination performed onboththe'"A"and"B"Westinghouse Series44SteamGenerator (S/G).,242tubesinthe"A"S/Gand2'16tubesinthe"B"'S/Grequiredcorrective actionduetotubedegradation.
-Twoadditional tubesineachS/Gwerestabilized andpluggedaspreventive action,duetoanti-vibration bar(AVB)concerns.
Theimmediate causeoftheeventwasthatthe"A"and"B"S/Gtubedegradation wasinexcessoftheGinnaQualityAssurance ManualReportability Limits.Theunderlying causeofthetubedegradation isacommonS/G'roblem ofapartially rolledtubesheetcrevicewithrecurring intergranular attack/stress corrosion cracking(IGA/SCC) andPrimaryWater-StressCorrosion Cracking(PWSCC)attack.onS/Gtubing.Corrective actiontakenwastoeithersleeve'rplugtheaffectedtubeswithacceptedindustryrepairmethods.NRCForm366(64)9) tI NRCFORM38SA(589)tUS.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDOMBNO.3150010OEXPIRES:O/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUESTI50/)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK REDUCTION.
PROJECT(315041(H),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1IDOCKETNUMBERl2)LERNUMBER(5)PAGE(3)YEARg)SEQUENTIAL NUMBERREVISIONNUM854R.E.GinnaNuclearPowerPlantTEXT///II>>>><<>>cobJoqokaLUood/I/ooo/HRC FeIIR3SSAB/(17) osooo244920050002o"09PRE-EVENT PLANTCONDITIONS TheplantwasintheCold/Refueling Shutdowncondition fortheAnnualRefueling andMaintenance Outage.ReactorCoolantSystem(RCS)wasdepressurized andRCStemperature wasapproximately 65F.SteamGenerator (S/G)EddyCurrentInspection was'inprogress.
DESCRIPTION OREVENTA.DATESANDAPPROXIMATE TIMESORMAZOROCCURRENCES:
0April20,1992,1200EDST:EventDateandTime0April20,1992,1200EDST:Discovery DateandTime0April21,1992,1330EDST:OralNotification madetotheNRCOfficeofNuclearReactorRegulation (NRR)..0April26,1992,1742EDST:repairscompleted.
SteamGenerator 0May5,1992:Follow-up writtenreportsenttoNRCOfficeofNRR.B.EVENTDuringthe1992AnnualRefueling andMaintenance Outage,anEddyCurrentExamination wasperformed inboththe"A"and"B"Westinghouse Series44DesignRecirculating SteamGenerators.
ThepurposeoftheEddyCurrentExamination wastoassessanycorrosion ormechanical damagethatmayhaveoccurredduringthecyclesincethe1991examination.
Theexamination wasperformed bypersonnel fromRochester GasandElectric(RG&E)andAllenNuclearAssociates, Inc.(ANA).Allpersonnel weretrainedandqualified intheEddyCurrentExamination methodandhavebeencertified toaminimumofLevelIfordataacquisition andLevelIIfordataanalysis.
NRCForm355A(609)
I NRCFORM388A(IS$9)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION tAPPROVEDOMBNO.3)600104EXPIRES:4/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHIS.INFORMATION COLLECTION REQUEST:503)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(P4)30).U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK REDUCTION PROJECT(31504)104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)R.E.GinnaNuclearPowerPlantTEXT(ffmoreSoeoelerfo/reer/,
Iree/frfooo/HRC
%%drrrr36543/(12) 0s00o244YEAR$g92-SEDUENTIAL NUMBER005@>REVISION.x:NUMER-0003cF09TheinitialEddyCurrentExamination ofthe"AE(and"B"SteamGenerators wasperformed" utilizing theZetec3-CoilMotorized RotatingPancakeCoil(MRPC)probeandtheZetecMIZ-18DigitalDataAcquisition System.The'frequencies selectedwere400,300,100,and25KHZ.Additional EddyCurrentExaminations ofthe"A"'nd"B"SteamGenerators wereperformed utilizing the.standard0.740"or0.720"O.D.BobbinCoilProbe.Thefrequencies selectedwere400,200,100and25KHZ.TheInletorHotLegExamination ProgramPlanincludedtheexamination of100%ofeachopenunsleeved steamgenerator tube.from'thetubeendtothetopofthetubesheetwithMRPC.Twentypercentofthetubeswereselectedandexaminedfortheirfulllength(20%randomsampleasrecommended intheElectricPowerResearchInstitute (EPRI)guidelines) withabobbincoil.Inaddition, 204of.eachtypeofsleevewasexaminedandtheremainder (unsleeved portion)ofthetubewasexaminedfulllength.AllRow1andRow2U-bendregionsselectedaspartofthe204randomsamplewereexaminedwiththeMRPCbetweentheg6TubeSupportPlateHotSide(TSPH)andtheg6TubeSupportPlateColdSide(TSPC)fromtheColdLegSide.Resultsoftheaboveinspections indicated that244tubesinthe"A"SteamGenerator (i.e.226-newrepairs,plus16previously pluggedtubes,plus2tubesstabilized forAnti-Vibration Bar(AVB)concerns) and218tubesinthe"B"SteamGenerator (i.e.183newrepairs,plus3B&Wexplosive plugs,plus30previously pluggedtubes,plus2tubesstabilized forAVBconcerns) requiredaction.Corrective actionsweretherefore takenfor242tubesinthe"A"S/G,andfor216tubesinthe"B"S/G.Preventive actions(forAVBconcerns) weretakenfor2tubesineachS/G.NRCForm368A(689)
NRCFORM366A(669)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LERITEXTCONTINUATION eAPPAOVED0MBNO.3)500)OEEXPIRE5I4/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST.'00 HRS.FORWARDCOMMENTSAEGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARAEGULATOAY COMMISSION, WASHINGTON, OC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(3)500104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBERFSISEOVENTIAL NVMER@rREVISIONNVMERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT///momEPEEE/E/PEVked, IIEPJ/(/BRE/NRC
%%dnR35663)((7)06000244920050004QF09OnApril20,1992atapproximately 1200EDST,withtheRCSdepressurized andtemperature atapproximately 65F,finalreviewofthe1992S/GInspection EddyCurrentresultswascompleted.
Resultsofthisreviewindicated thatmorethan10percentofthetotaltubesinspected aredegraded(i.e.imperfections greaterthan20percentofthenominalwallthickness) andmorethanonepercentofthetotaltubesinspected aredegraded(i.e.imperfections greaterthantherepairlimit)..Becauseoftheabove,theresultsoftheinspection areconsidered areportable eventpursuantto10CFR50.73perAppendixB-oftheGinnaStationQualityAssurance Manual.OnApril21,1992atapproximately 1330EDST,oralnotification wasmadetotheNRCOfficeofNRRpursuanttoAppendixBoftheGinna,Station QualityAssurance Manual.OnMay5,1992afollow-up writtenreportoftheSteamGenerators Inspection andRepairswassenttotheNRCpursuantto'Appendix BoftheGinnaStationQualityAssurance Manual.C.rINOPERABLE STRUCTURES COMPONENTS, ORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:D.None.OTHERSYSTEMSORSECONDARY FUNCTIONS AFFECTEDNone.E.METHODOPDISCOVERY:
Theeventwasapparentafterthefinalreviewofthe"A"and"B"SteamGenerators EddyCurrentExamination results.NRCPARR366A(669)
NRCFORM366A(889)(LS.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION tAPPROVEDOMBNO.3(500)04EXPIRES:4(30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUESTI50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(P430),U.S.NUCLEARREGULATORY COMMISSION.
WASHINGTON.
DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(3150010E),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)YEARoyerSEQUENTIAL NUMSERREVISIONNUMBERR.EPGinnaNuclearPowerPlantTEXT(I/moreepeceJeeePJPPILIreeaB(ro'encl HRCFcnn36848)()7)0600024492-0050005QF09P.OPERATORACTION:ControlRoomoperators completed thenotifications andevaluations requiredbytheA-25.1(GinnaStationEventReport),submitted fortheeventbytheS/Gsupervision.
G.SAFETYSYSTEMRESPONSES.
None.IIICAUSEOPEVENTA.IMMEDIATE CAUSE:Theimmediate causeoftheeventwasthatthe"ALIand"BLISteamGenerator tubedegradation wasinexcessoftheGinnaStationQualityAssurance ManualReportable Limits.B.ROOTCAUSE:Theresultsoftheexamination indicatethatIntergranular Attack(IGA)andIntergranular StressCorrosion Cracking(IGSCC)continuetobeactivewithinthetubesheet creviceregionontheinletsideofeachsteamgenerator.
Asinthepast,IGA/SCCismuchmoreprevalent inthe"B"SteamGenerator with118newcreviceindications reported.
Inthe"A"SteamGenerator, 34newcreviceindications werereported.
Themajorityoftheinlettubesheet crevicecorrosion indications areIGA/SCCoftheMillAnnealedInconel600tubematerial.
Thisformofcorrosion's believedtobetheresultofanalkalineenvironment forminginthetubesheet crevices.
Thisenvironment hasdeveloped overtheyearsasdepositsandactivespeciessuchassodiumandphosphate, havereacted,changinganeutralorinhibited creviceintotheaggressive environment thatpresently exists.NRCForm366A(6J)9)
NRCFORM386A(BJIS)i(LS.NUCLEARAEGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION tAPPROVEDOMBNO.31500104EXPIRES'/30/$
2ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFOAMATION COLLECTION REQUEST:500HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(PJ)30),US.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1'HEPAPERWORK REDUCTION PROJECT(3)500104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(8)YEARPRSEQUENTIAL Sa~r..6%NUMER%oREVISIONNVMSERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT////Sore8/reoe/e/Fr/rer/,
Iree///0'ooe/HRC ForIII38//AS/(IT) 24492005000OFAlongwithIGA/SCCin'thecrevices, thereappearstohavebeenaslightincreasein"PrimaryWaterStressCorrosion Cracking(PWSCC)attherolltransition duringthelastoperating cycle.Thismechanism wasfirstaddressed in1989andthisyeartherewere63rolltransition PWSCCindications in"B"SteamGenerator and189rolltransition (PWSCC)indications in"A"SteamGenerator.
ThesenumbersincludetubesthatmayhavePWSCCincombination withIGAandSCCinthecrevice.XVANALYSISOPEVERTThiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportitem(other)andtheGinnaStationQualityAssurance ManualAppendixBwhichrequiresthat,."Ifthenumberoftubesinagenerator fallingintocategories (a)or(b)exceedsthecriteria, thenresultsoftheinspection shallbeconsidered areportable eventpursuantto10CFR50.73."Thetubedegradation inthe"AL)and"B"SteamGenerators exceededthecriterion of(a)whichstates,"morethan10percentofthetotaltubesinspected aredegraded(imperfections
,greaterthan20percentofthenominalwallthickness)",
andthecriterion of(b)whichstates,"morethan1percentofthetotaltubesinspected aredegraded(imperfections greaterthantherepairlimit).Thisrepairlimitisdefinedas,"SteamGenerator tubesthathaveimperfections greaterthan40percentthroughwall,asindicated byEddyCurrent,shallberepairedbypluggingorsleeving."
NRCForm386A(86$)
.J NRCFOAM366A(669)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION eAPPROVEDOMBNO.31500)04EXPIRES:6/30/92ESTIMATED BURDENPE4RESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:50A)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHE4ECORDSAND4EPOATSMANAGEMENT BRANCH(F430).U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK 4EDUCTION PROJECT(31500104).
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, OC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBER(6)SEOUENTIAL gPNUMBERREVISIONNUMBERPAGE(3)R.E..GinnaNuclearPowerPlantTEXT/I/more<<>>ce/enrFI/rer/
Beea///Noor>>l NRCForrrlJ(ISAB/((2) 0500024-4920050007OF09Anassessment wasperformed considering thesafety.consequences andimplications ofthiseventwiththefollowing resultsandconclusions:
Therewerenosafetyconsequences orimplications resulting fromtheSteamGenerator tubedegradation inexcessoftheQualityAssurance ManualReportable Limitsbecause:.
oThe.degradedtubeswereidentified andrepairedpriortoanysignificant leakageorSteamGenerator tuberuptureoccurring.
0Evenassumingacompleteseverance ofaSteamGenerator tubeatfullpower,asstatedintheR.E.GinnaNuclearPowerPlantUpdatedFinalSafetyAnalysisReport(Ginna/UFSAR) section15.6.3,(SteamGenerator TubeRupture),
thesequenceofrecoveryactionsensuresearlytermination
.ofprimarytosecondary leakagewithorwithoutoffsitepoweravailable thuslimitingoffsiteradiation dosestowithintheguidelines of10CFR100.~Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMS.TOPRE-EVENT NORMALSTATUS:o'fthe244tubesinthe"A"SteamGenerator, 36tubeswererepairedusingaCombustion Engineering 27"weldedsleeveintheHotLeg,plus194tubeswererepairedusingaBabcockandWilcoxexplosively weldedtubesheet sleeveintheHotLegandalloftheabovetubeswillremaininservice.Theremaining 14tubes=wereremovedfromservicebypluggingboththeHotandColdLegtubeends.Atotalof185tubesinthe"A"SteamGenerator arecurrently pluggedand555tubesaresleeved.NRCForm366A(689)
I NRCFORM3SSA(W)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION lAPPROVEOOMB NO.3I50010O iEXPIRES:O/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(PJ)30),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(31504104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACII.ITY NAME(1IDOCKETNUMBER(2)YEARLERNUMBER(SlSEOVENTIAL NVMERREVISIONNUMBERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT/I/moree/>>ce/or/q/rer/
Iree<<IChE/<<>>/
NRC%%de3SBAB/(IT)0S00024492005000OF0Ofthe218tubesinthe"B"SteamGenerator, 186tubeswererepairedusingaCombustion Engineering 27"weldedsleeveintheHotLeg,plus9tubeswererepairedusingaCombustion Engineering 30"weldedsleeveintheHotLegandalloftheabovetubeswillremaininservice.Theremaining 23tubeswereremovedfrom=servicebypluggingboththeHotandColdLegtubeends.Atotalof313tubes.inthe"BL(SteamGenerator arecurrently pluggedand1134tubesaresleeved.Alltheaboverepairsonthe"A"and"BL(SteamGenerators werecompleted onApril26,1992atapproximately 1742EDST.B.ACTIONTAKENORPLANNEDTOPRVTENTRECURRENCE:
-Theoccurrence/presence ofIGA,SCC,.andPWSCCisacommonPWRSteamGenerator problem.Utilities withsusceptible tubingandpartially rolledcrevicesmustdealwiththisrecurring attackonSteamGenerator tubing.R.E.GinnaNuclearPowerPlantwillcontinuecarefulmonitoring ofbothprimaryRCSand'econdary sidewaterchemistry parameters.
Thesewaterchemistry parameters willcontinuetobeevaluated againstacceptedindustryguidelines inordertominimizeharmfulprimaryand/orsecondary sideenvironments.
DegradedSteamGenerator tubesshallbesleevedorpluggedinaccordance withtheInservice Inspection ProgramandAcceptedIndustryRepairmethods.ADDITIONAL INFORMATION A.FAILEDCOMPONENTS:
Thedegradedcomponents are:InconelGrade600tubeshavinganoutsidediameterof0.875inchesanda.nominalwallthickness of0.050inches.Thesetubesweremanufactured byHuntington AlloyCompany.'NRCForm3SSA(589)
NRCFORM388A(669)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDOMBNO.3)504104EXPIRES:E/30/IQESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:505)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F830),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1)IEPAPERWORK REDUCTION PROJECT(3150010E).
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, OC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBER(6)S~SEQVENTIAL NVM@ERj>gjREVISION:i.'/NVMSERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT///IIRvoEPoooJIISA(RR/,vJo//I/ooo/NRC Form36643/(17)060002449005-0009"09B.PREVIOUSLERsOMSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthe.following results:Thecreviceindications aresimilartothosereportedinA0-74-02, AO-75-07, R0-75-013, andLERs76-008,77-008,78-003,79-006,79022/80003/81009/82003/82022/83013/89=-001,90-004,and91-005.CSPECIALCOMMEHTS:
Foramoreindepthreport,refertothe"1992SteamGenerator EddyCurrentInspection" SummaryExamination ReportsenttotheNRCMay5,1992.NRCForm368A(BJ)9)
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