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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to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr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 DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9405090121 DOC.DATE:
94/05/02NOTARIZED:
NODOCKETFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION ST.MARTIN,J.T.
Rochester Gas&ElectricCorp.MECREDY,R.C.
Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION RJOHNSONIAR~ProjectDirectorate I-3D-S.A0500024.4
.DNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
SUBJECT:
LER94-022-01:on 940202,determined thatContainment PressurechannelsP-947&P-948wereinoperable.
Causedbyobstruction ofcommonpressuresensingline.Corrective action:iron oxidescalewasremoved&channelsdeclaredoperable.W/940502 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR fENCLISIZETITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.RECIPIENT IDCODE/NAME PD1-3PDINTERNAL:
AEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL:
EG&GBRYCE,J.H NRCPDRNSICPOORE,W.COPIESLTTRENCL111122111111221111221111RECIPIENT IDCODE/NAME JOHNSON,A AEOD/DSP/TPABNRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEBNRR/DSSA/SPLB EGEIL~02GÃ1FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL1111111111111111111111111D'S."'R25'ets/0205DNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR27ENCL27 ROCHESTER GASANDELECTRICCORPORATION 489EASTAVENUE,ROCHESTER MY.14849-0001 uf8rosestartROBERTCAtECREDYVicePresident CinnaNuclearProduction TEl.EPHONE AREACOOE71d5462700May2,1994U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate 1-3Washington, DC20555
Subject:
LER94-022,Rev'isLor~f,::,
Containment PressureTransmitters Inoperable DuetoBlockageofSensingLinebyCorrosion
- Products, CausesaCondition Prohibited byTechnical Specifications RG&EGinnaNuclearPowerPlantDocketNo.50-244Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(B),whichrequiresareportof"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications",
theattachedLicenseeEventReportLER94-002,Revlstoit'::,::,'1::,
isherebysubmitted.
nis'ci',::!rn'oI'u'ds'd"rn'!titrs'"'reycIs'io'ri;::
ssYi&n~cvsrncv~:srasrtsssw Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytyyours,RobertC.Mecreyc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector 8rQzP7+w/wA~~94050'70121
'F405020~G0A0PDRADOCK05000244SPDR NRCFORM366(5-92).S.NUCLEARREGULATORY COIIIISSION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0MRS.FORWARDCOMMENTSREGARDIHG BURDEHESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714)eUS~NUCLEARRECUtATORYCOMMISSIOHe WASHINGTOH, DC20555.0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FAclLITYNAME(1)R.E~GinnaNuclearPowerPlantDOCKETNQGIER(2)05000244PAGE(3)1OFQTITLE(4)Containment PressureTransmitters Inoperable, DuetoBlockageofSensingLinebyCorrosion
- Products, CausesaCondition Prohibited byTechnical Specifications MONTHDAYYEARYEAREVEHTDATE5LERNINBER6SEQUENTIAL HUHBERREVISIOHNUMBERMONTHDAYYEARREPORTDATE7OTHERFACILITIES INVOLVED8DOCKETNUMBERFACILITYNAME02029494--002--FACILITYNAMEDOCKETNUMBEROPERATING IKXIE(9)POWERLEVEL(10)N09873.71(b)73.71(c)50.73(a)<2)(iv) 50.73(a)(2)(v) 20.405(c) 50.36{c)(1) 20.402(b) 20.4D5{a)(1)(i)20.405(a)(1)(ii) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(l)(v) 50.36<c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii)
LICENSEECONTACTFORTHISLER1250.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)
OTHER(SpecifyinAbstractbelowandinText,NRCForm366ATHISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormore11NAMEJohnT.St.Martin-Director, Operating Experience TELEPHONE NUMBER(IncludeAreaCode)(315)524-4446C(NPLETEONELINEFOREACHCNIPOHENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEHCOMPOHEHT MANUFACTURER REPORTABLE TOHPRDSCAUSESYSTEMCOMPOHENT MANUFACTURER REPORTABLE TOHPRDSSUPPLEMENTAL REPORTEXPECTED14YES(lfyes,completeEXPECTEDSUBMISSIOH DATE).XxoEXPECTEDSUBMISSION DATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnFebruary2,l994,atapproximately 1642EST,withthereactoratapproximately 984steadystatepower,ControlRoomoperators determined thatContainment PressurechannelsP-947andP-948wereinoperable.
Basedonpost-event reviewofcomputerdata,thiscondition wasinviolation ofTechnical Specification Table3.5-2ActionStatements.
Immediate corrective actionwastodefeat.theinoperable channelsbyplacingtheaffectedbistables inthetrippedcondition.
Theunderlying causeoftheeventwasanobstruction inthecommoncontainment pressuresensinglineforp-947andP-948~!pipiulti rigoiasat~ax':hiing jt:aprpjeid~n:aQa'mi.;il:p'oa"'nti!o&6~i'a,-!1>hei,::p.".;:.%hisyen FeriYiimano'eI'ndiaoeatoexi'-:e!p'ro'gr'a m""cpan'set'i'c'8ii'ioi!a'."4)8@!'
""Corrective actionwastakentocleartheobstruction fromtheaffectedtubing,leaktestthepenetration pipingandtransmitter tubing,andverifytheproperoperation ofP-947andP-948.Corrective actiontoprecluderepetition isoutlinedinSectionV(B).NRCFORM366(5-92)
NRCFORM366A(5-92)U.SNUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDB'YCNSNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0MRS.FORWARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEINFORMATION AHDRECORDSMANAGEMENT BRANCH(MHBB/l'14),U.S.NUCLEARREGULATORY COMMISSION, WASHIHGTOH, DC20555-0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT AHDBUDGETWASHIHGTOH DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNINBER205000244LERNUMBER6SEQUENTIAL REVISION94-002--PAGE32OF9'EXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)PRE-EVENT PLANTCONDITIONS Theplantwasatapproximately 989steadystatereactorpowerwithnomajoractivities inprogress.
Instrument andControl(I&C)Department personnel wereinvestigating Containment PressurechannelP-947.Thisinvestigation wasinitiated byaMaintenance WorkRequest/TroubleReport(MWR/TR)writtenJanuary20,1994byControlRoomoperators becausetheMainControlBoardpressureindication forP-947(PI-947)wasobservedtobereadingslightlylowerthantheindication forContainment PressurechannelsP-945andP-949(PI-945andPI-949),whicharealsoontheMainControlBoard.II.DESCRIPTION OFEVENTA.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES:
oJune24,1992,1500EDST:Containment (CNMT)pressurechannelP-947outputindication startstobecomeinconsistent withchannelsP-945andP-949,asmonitored onthePlantProcessComputerSystem(PPCS).(Thisisbasedonpost-event reviewofarchiveddataonthePPCS.)Eventdateandtime.oJanuary20,1994:ControlRoomoperators submitMWR/TRonPI-947MainControlBoardindication.
oFebruary2,1994,1642EST:Discovery dateandtime.oFebruary4,1994,0007EST:Containment PressurechannelP-947isrestoredtooperablestatus.oFebruary4,1994,1536EST:Containment PressurechannelP-948isrestoredtooperablestatus.NRCFORM366A(5.92)
NRCFORH366A(5-92)U.S.NUCLEARREGULATORY (XNIIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOHBNO.3150-0104 EXPIRES5/31/95ESTINATED BURDENPERRESPOHSETOCOHPLYWITHTHISIHFORHATIOH COLLECTIOH REOUEST:50.0HRS.FORWARDCOHHENTSREGARDING BURDENESTIHATETOTHEINFORHATION ANDRECORDSHANAGEHEHT BRANCH(NNBB7714),U.S.NUCLEARREGULATORY CONHISSIOH, WASHINGTON, DC20555-0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFNANAGENENT ANDBUDGETWASHINGTON DC20503.FACILITYNAKE1R.E.GinnaNuclearPowerPlantDOCKETNWBER205000244LERNIMBER6TEARSEQUENTIAL 94--002--REVISIONPAGE3013OF9':4TEXT(Ifmorespaceisrequired, useadditionat copiesofNRCForm366A)(17)B.EVENT:OnJanuary20,1994,ControlRoomoperators observedthatoneMainControlBoardindication forCNMTpressure, PI-947,wasreadingslightlylowerthantheothertwoindicators, PI-945an'dPI-949.Theyinitiated aMWR/TR,forI&Cpersonnel toinvestigate thedifference inreadings.
OnJanuary21,I&Cperformed theannualcalibration ofthechannel.Thechannel(P-947)responded properlytoboththeelectronic checksandtoactualpressuresignalsinsertedintothetransmitter (PT-947).
Afterreviewing post-calibration trendingdataandarchivedPPCScomputertracesofCNMTpressure, I&CnoticedthatchannelP-947wasstillnottrackingconsistent withchannelsP-945andP-949.Furtherinvestigation wasconducted onFebruary2,1994,toidentifyiftherecouldbeanypossiblemechanical and/orelectrical problemswithP-947.OnFebruary2,1994,atapproximately 1612EST,withthereactoratapproximately 989.steadystatereactorpower,ControlRoomoperators declaredchannelP-947inoperable.
Theaffectedbistables wereplacedinthetrippedcondition.
Toverifytheoperability oftheredundant CNMTpressurechannels, theoperators thencausedasmallchangeinCNMTpressurebydepressurizing CNMTperoperating procedure 0-11,"ControlofMiniPurgeExhaustValvesWhileDepressurizing Containment".
I&Cpersonnel monitored test,pointsforCNMTpressurechannelsP-945,P-947,P-948,andP-949withadigitalmultimeter.
Duringthisdepressurization, atapproximately 1642EST,twochannels(P-947andP-948)didnotshowanyresponsetothesmallchangeinCNMTpressure.
TheControlRoomoperators formallydeclaredP-948inoperable atapproximately 1658EST.Theaffectedbistables wereplacedinthetrippedcondition peremergency restoration procedure ER-INST.1, "ReactorProtection BistableDefeatAfterInstrumentation LoopFailure".
P-947andP-948senseCNMTpressureviaacommonline(CNMTPenetration 203A).ACNMTentrywasmadetoverifythatthissensinglineforPT-947andPT-948,(Pen.203A)wasnotmechanically blocked.Pen.203Awasvisuallyverifiednottobeexternally obstructed.
Thevalvelineupsforthepressuretransmitters (PT-947andPT-948)wereverifiedtobecorrect.HRCFORH366A(5-92)
NRCFORM366A(5.92)US.NUCLEARREGULATORY COHIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEINFORMATION AHDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGUI.ATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31/0.0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYlOWE1R.E.GinnaNuclearPowerPlantDOCKETNUMBER205000244LERNUMBER6YEARSEQUENTIAL 94-002REVISION01PAGE34OFm!4TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)OnFebruary3,1994,aworkpackagefortroubleshooting andrepairoftheCNMTpenetration linewasprepared.
ACNMTentrywasmadeandPen.203Awaspressurized tothirty(30)poundspersquareinchesaboveatmospheric pressure(PSIG),usingsurveillance testprocedure PTT-23.17B, "Containment Isolation ValveLeakRateTestingContainment PressureTransmitters PT-947andPT-948Pen203A".PT-947andPT-948didnotrespondtothispressure, whichindicated ablockageinthepipingforPen.203Aorinthecommoninstrument tubingline.Backflushing withone-hundred-twenty (120)PSIGairsupplytocleartheblockagewasunsuccessful.
Pen.203AwasisolatedinsideCNMTtoprovidedoublebarrierisolation forCNMTintegrity.
Theinstrument tubingwasdisconnected outsideCNMT.Theinstrument tubingwasfoundtocontainwater,butthiswaterwasnot'hesourceoftheblockage.
The1/2inchcarbonsteeltubingforPen.203Awasfoundtobemechanically blockedwithathicksludge.Theblockagewasremoved.Thetubingwasreassembled andpreparations weremadetotestthetubing.OnFebruary3,1994,atapproximately 2207EST,Pen.203Awasdeclaredinoperable toperformrequiredAppendixJtesting.TheLimitingCondition forOperation (LCO)forTechnical Specification (TS)3.6.3.1.wasentered.Pen.203Awastestedinaccordance withsurveillance testprocedure PTT-23.17B, "Containment Isolation ValveLeakRateTestingContainment PressureTransmitters PT-947andPT-948Pen203A".Itwasdocumented inPTT-23.17B thatPT-947andPT-948nowaccurately responded whenthepenetration waspressurized to60PSIG.PTT-23.17B wassuccessfully completed atapproximately 2336ESTandPen.203Awasdeclaredoperableatapproximately 2340EST.OnFebruary4,1994,atapproximately 0007EST,P-947wasdeclaredoperable.
Thetransmitter andrackcalibration procedure forchannelP-948wasperformed laterinthedayonFebruary4,andP-948wasdeclaredoperableatapproximately 1536ESTonFebruary4,1994.HRCFORM366A(5-92)
NRCFORM366A(5-92)US.NUCLEARREGULATORY CQOIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYQUINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FOR'WARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMAHAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001, ANDTOTHEPAPERWORK REDUCTION PROJECT(3150-0104),
OFFICEOFMANAGEMENT AHDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNUMBER205000244YEAR94-002--01LERNUMBER6SEQUENTIAL REVISIONPAGE3TEXT(Ifmorespaceisrequired, useadditionat copiesofHRCForm366A)(17)'AA'~L':::LnIHT.:::i:,.yz',as sana!::,::@hanna 1s,.'::.~flu hy'Pr()%i'III,~e'ly.',-.:.jD'7,;59.';-'::-EST,';
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"=:"'-,.~HRCFORM366A(5-92)
NRCFORH366A(5-92)U.S.NUCLEARREGULATORY C(NIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYQGINO.3150-0104 EXPIRES5/31/95ESTINATED BURDENPERRESPOHSETOCOHPLYWITHTHISIHFORMATIOH COLLECTION REQUEST:50.0HRS.FORWARDCOHHENTSREGARDING
'BURDENESTIHATETOTHEINFORHATIOH ANDRECORDSHANAGEHENT BRANCH(HNBB7714)aUSTNUCLEARREGULATORY COHHISSIOHa WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(3150-0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAHE1R.E.GinnaNuclearPowerPlantDOCKETNIMBER205000244LERNUMBER6YEARSEQUENTIAL 94-002--REVISIOH01PAGE3LR~:<MTEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)C.INOPERABLE STRUCTURES gCOMPONENTS gORSYSTEMSTHATCONTRIBUTEDTOTHEEVENT:NoneD~OTHERSYSTEMSORSECONDARY FUNCTIONS AFFECTED:
Engineered SafetyFeaturesthatrelyonCNMTpressureinputsareSafetyInjection Actuation (SI),SteamLineIsolation, andContainment SprayActuation (CNMTSpray).Noneofthesefeatureswasaffectedbytheinoperability ofP-947andP-948,becauseatnotime,fromJune24,1992,toFebruary4,1994,wasCNMTpressureatorneartheactuation setpoints (4PSIGforSI,18PSIGforSteamLineIsolation, and28PSIGforCNMTSpray).Duringthisperiod,theredundant channels(forP-947thechannelsareP-945andP-949;forP-948thechannelsareP-946andP-950)wereinserviceandwerenottakenoutofserviceunlesstheaffectedhistahles wereplacedinthetripped""'"i,::,:::::::i..":...:.',9,,
- ',:,.%,::.:i!:-.'.I'P,.::.',":,':.'.:,,:.:%:::::",:::::".:
'",:,ll<:::,:i!i~>','-'-
.".i'ecan>+<-".::!
><'i'"happ:.>'l' METHODOFDISCOVERY:
Thiseventwasfirstidentified duetotheastuteobservation ofaControlRoomoperatoronJanuary20,1994,whoquestioned aslightdifference inindications forCNMTpressure.
Thesmalldeviation betweenredundant channelswaswithinthetolerance ofMainControlBoardinstrumentation channelchecks.ThemonthlyChannelFunctional TestsandannualChannelCalibrations associated withthesechannels(asrequiredbyTSTable4.1-1forunitsf17andf25)didnotdetecttheobstructed tubinglineduetothelocationoftheobstruction.
ThesludgewaslocatedbetweenCNMTandtherootisolation valvesforPT-947andPT-948.Theserootisolation valvesareclosedduringperformance ofthenecessary testsandcalibrations, inordertopressurize thevolumebetweenthevalveandthepressuretransmitter.
Thismethodoftestingisconsistent withthedefinition ofChannelFunctional Testing,asdefinedinTS1.7e3~a.ThefactthatthiseventaffectedbothchannelsP-947andP-948wasidentified asaresultoftheinvestigations performed byI&Cpersonnel onFebruary2,1994.HRCFORH366A(592)
NRCFORM366A(592)U.SNUCLEARREGULATORY CQOIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYQIBNO.'150-0104 EXPIRES5/31/95ESTIMATED BURDEHPERRESPOHSETOCOMPLYMITHTHISINFORMATION COLLECTION REGUEST:50.0MRS.FORHARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRAHCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, NASHINGTOH, DC20555-0001 ANDTOTHEPAPERIIORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGETIlASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNINBER20500024494--002--01LERHINBER6YEARSEQUENTIAL REVISIGHPAGE3,:;O~P:"jX4TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)AmoredetailedreviewofthearchivedPPCSrecordsofCNMTpressureconcluded thatchannelP-947hadnotresponded tochangesinCNMTpressuresinceJune24,1992,beginning atapproximately 1500EDST.NotethatwhileCNMTpressurechannelP-947ismonitored bythePPCS,channelP-948isnot.Inaddition, PI-948(andalsoPI-946andPI-950)haveascaleof10to200PSIA(absolute pressure).
Bycomparison, PI-947(andalsoPI-945andPI-949)haveascaleof0to60PSIG.ItisassumedthatP-948hadnotresponded tochangesinCNMTpressureforthesameamountoftimeasP-947.F.OPERATORACTION:TheControlRoomoperators observedthatthePI-947readingwasinconsistent onJanuary20,1994,andinitiated aMWR/TR.AfterbothchannelsP-947andP-948werediscovered tobeinoperable, theControlRoomoperators performed emergency restoration procedure ER-INST.1 andplacedtheaffectedbistables inthetrippedcondition.
Subsequently, theControlRoomoperators ensuredthathighersupervision andtheNRCResidentInspector hadbeennotifiedofthisevent.G.SAFETYSYSTEMRESPONSES:
NoneIII.CAUSEOFEVENTA.IMMEDIATE CAUSE:Theimmediate causeoftheeventwasthefailureofP-947andP-948torespondtochangesinCNMTpressureduetoobstruction ofthecommonpressuresensingline.NRCFORM366A(5-92)
KRCFORM366A(5.92)U.S.NUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBY(HUINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISIHFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIHATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.STNUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001, AHDTOTHEPAPERWORK REDUCTION PROJECT(31500104),OFFICEOFMAHAGEMEHT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNWBER2YEAR05000244g4LERHINBER6SEQUENTIAL
--002--REVISION01PAGE3TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)B.INTERMEDIATE CAUSE:C.Theintermediate causeoftheobstruction ofthecommonpressuresensinglineatPen.203Awasabuildupofcorrosion productsinthisline,whichis1/2inchOD,0.065inchwallthickness, carbonsteeltubing.Thesecorrosion productswerevisuallyexaminedandfoundtobereddishbrown/black incolor,visuallyreSembling iranOXideSCale.ThiiS!h'in!idpe!~Cia:;:,":':,,:
Crctrrcwan caprdciiCtS"""""""."e"4'"'~'"""'i""'i"""ROOTCAUSE:Theunderlying causeofthemso,,~t:-:,"'ii}h:::",ii-:':::,I:::::
-ei'k!:configuration.
I&Cpersonnel havecali.'b'rated thesetransmitters withawater-filled deadweight testerformanyyears.Theconfiguration ofthetransmitter andsensinglinefi+r~'Pe'ri:".",y-,20)'A prevented thedrainageofallthewateraftercalibsraf:ion.
Afterthetransmitter wasunisolated aspartofthecalibration process,thetrappedwatertraveleddowntothelowportionofthesensinglineP!:.:;'::!w hereityataje'djunJ'i~1!,PV'aPorati g,",nr".:.,"::
P(ejrCmtjng fQC1HRCFORM366A(5-92)
NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYMSNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0HRS~FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSIONS WASHINGTOH, DC205550001ANDTOTHEPAPERWORK REDUCTION PROJECT(31800104),OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNINBER20500024494--002--01LERNUMBER6YEARSEQUENTIALREVISIONPAGE3/god!1'4'EXT (Ifmorespaceisrequired, useadditional copiesotNRCForm366A)(17)Stagnantwaterhaeremainedinthecarbonsteelsensinq~ee5"Ape".LCD~!Pj~T}..-:-.,:20gh" forasubstantial periodoftimee'fter'.,',":;::.:e'i'4~3-:i~bditi'OiP.
Unctereach~th'i'i'5 conditions, significant"corrosion ofthecarbonsteelmaterialoeeuiii'5.
,Thecorrosion product,hydratedironoxide(commonrust)isvoluminous, occupying manytimesthevolumeofthemateriallosttothecorrosion process.Sufficient corrosion productaccumulated toblockthesensinglinetubing,resulting intheinoperability ofP-947andP-948.IV.ANALYSISOFEVENTThiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(B),whichrequiresareportof,"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications".
CNMTpressurechannelsP-947andP-948wereinoperable foraconsiderable lengthoftime,contr'O'Vg 5~c))::,th'i".~~reqYi';x".ime~nt,
-ofTSTable3.5-2,unitsg1.b.,2.b.,and5".c.OperaTion intlii.scondition sinceJune24,1992isacondition prohibited byTS.Anassessment wasperformed considering boththesafetyconsequences andimplications ofthisevent.Theresultsofthisassessment arethattherewerenooperational orsafetyconsequences orimplications attributed totheinoperability ofP-947andP-948because:oAreviewofplanthistoryandpreventive maintenance historyfileshasshownthattheredundant CNMTpressurechannels(P-945,P-946,P-949,andP-950)havebeeneitheroperableorplacedintheconservative trippedstatefromtheEventdtetotheDiscovery date~@'exieptl:,'go~rgajproYYimate'3/<i,njn'e i(,,i)g':i,:i,oAreviewofPPCSdatahasshownthat.theredundant pressurechannelshaveresponded topressurization ofthesensinglinesandpressurechangesinCNMT.9gsg'a'1;:@Tl'SjiCti~()n8 hah~>8iiS'pe
'.04M'itothesamefailuremodeasP-947andP-948.~Wi"'""'"RvkN4K6M HRCFORM366A(5-92)
NRCFORH366A(5.92)U.S.NUCLEARREGULATORY CQOlISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBY(NBNO.3150-0104 EXPIRES5/31/95ESTIHATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOHMEHTSREGARDING BURDENESTIHATETOTHEINFORMATION AHDRECORDSHANAGEHEHT BRANCH(HHBB7714),U.S.NUCLEARREGULATORY COMMISSIONS WASHIHGTOH, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31/0.0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1DOCKETHINBER2LERHINBER6SEQUENTIAL REVISIONPAGE3R.E.GinnaNuclearPowerPlant0500024494--00200Al9843,4TEXT(lfmorespaceisrequired, useadditional copiesofHRCForm366A)(17)00The2outof3logic(2/3)requiredforactuation ofSIwasreducedtoa2/2logicwiththeinoperability ofP-947.ThusSIactuation fromh&phCNMTpressure(4PSIG)wouldhaveoccurredasassumedinthedesignbasis.Thediverseactuation circuitry forSIhasthreeadditional meansofactuation (steamgenerator lowsteampressure, pressurizer lowpressure, andManual).Noneofthesediversemeanswasaffectedbytheinoperability ofP-947.0The2/3logicrequiredforSteamLineIsolation actuation wasreducedtoa2/2logicwiththeinoperability ofP-948.pressure(18PSIG)wouldhaveoccurredasassumedinthedesignbasis.0Thediverseactuation circuitry forSteamLineIsolation hasthreeadditional meansofactuation (hi-histeamflowwithsafetyinjection, histeamflowand2/4lowTavgwithsafetyinjection, andManual).Noneofthesediversemeanswasaffectedbytheinoperability ofP-948.0The2/3plus2/3logicrequiredforCNMTSprayactuation wasreducedtoa2/2plus2/2logicwiththeinoperability ofp-947ahdp-948K~!"exaej%i:,:,:::,ga~Tapprpkiiaats1p~in'i'iie'-.::+9),"
secchdsIYe9hCHI4Tpressure(28PSIG)wouldhaveoccurredasassumedinthedesignbasis.0Thealternate actuation circuitry forCNMTSpray(Manual)wasnotaffectedbytheinoperability ofP-947andP-948.NRCFORM366A(592)
NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATZON APPROVEDBTQU!NO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPOHSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEINFORMATION AHDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNIHIBER205000244LERNUMBER6YEARSEQUENTIAL 94-002--REVISION01PAGE3TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)On::;:!OMT~iFi"-"'::(@i~="lI""i"">I.""8:i
"'i="='""
c:-"ss""'"bi"i'.;!N":ii.
n'<""'n'nexgxzneg'an'@OS:::;
- P-::,",94T'.:,,
~HRCFORM366A(5-92)
HRCFORM366A(5-92)U.S.NUCLEARREGULATORY COHISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYQQHO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYMITHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORNARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(HNBB7714),U.S.NUCLEARREGULATORY COMMISSIDH, MASHIHGTOH, DC20555-0001 AHDTOTHEPAPERNORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGETllASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHNBER205000244YEAR94LERNUMBER6SEQUENTIAL
--002REVISION-01PAGE3TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)'1c)88~@>>.0$'i'off'8Xt'e'.spowexv4c'oiNckldeAt@%73,"t'b~4h8'~lacctdi@nt
';ll!'i'-,!!i!Ill,,
!!!i!!...ii!,!!i,'::,.!
ll...!!P,,ilia!!'l'i
'i!ii!i'!,:tile~
>>!i!:"'asedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUSoTheironoxidescalewasremovedfromtheobstructed penetration sensinglineandP-947andP-948wererestoredtooperablestatus.oTheotherchannelsthatmonitorCNMTpressurewereverifiedtorespondtosmallchangesinCNMTpressure.
HRCFORH366A(5-92)
NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBY(HNINO;3150-0104 EXPIRES5/31/95ESTIMATED BURDEHPERRESPONSETOCOMPLYIIITHTHISINFORMATION COLLECTIOH REQUEST:50.0HRS.FORllARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEIHFORMATIOH ANDRECORDSMANAGEMENT BRANCH(MHBB7714)4USTNUCLEARREGULATORY COMMISSION?
llASHINGTON, DC20555-0001 ANDTOTHEPAPERNORK REDUCTION PROJECT(3110-0104),
OFFICEOFMANAGEMENT AHDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNIMBER20500024494--002--01LERNUMBER6'YEARSEQUENTIAL REVISIONPAGE3TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:
oPPCScomputerpointsforCNMTpressurewillbearchiveddailyuntilthe1994refueling outagetoverifychanneloperability.
pl?CSScoa?putana;:-":;rior'ntsi'::fur,C,H::,,:MTSpr'sss urrsiieere oThesensinglinesforallCNMTpressurechannelswillbeinspected andcleanedoutduringthe1994refueling outage.oThemethodofcalibration oftheCNMTpressuretransmitters hasbeenchangedtousegas(insteadofwater)asthetest...e?sas4?999??an?
~~i..."vmmu?m,.
znSSrr....",??4;49?S?'as.ye.
rate....,44rs"',y; 4'?w'ia4ssSSS<cc s'?9~'rRmedium.a.'ipse',~i',.e',vase'cIj',pros'cveau'r'ea",s',::.';
gPreVpht;i'TIE+'EiI'cui',.:renice;.:I oTestingthesecontainment penetrations hasbeenenhancedtoincludeformaldocumentation ofpressurechannelresponse.m HRCFORM366A(5-92)
NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQIIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYIHIBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYNITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORMARDCOMHEHTSREGARDING BURDENESTIMATETOTHEINFORMATIOH ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, llASHIHGTOH, DC20555-0001 AHDTOTHEPAPERIIORK REDUCTION PROJECT(31400104),OFFICEOFMANAGEMENT AHDBUDGETNASHIHGTOH DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHWBER2YEAR0500024494LERNUMBER6SEQUENTIAL
-002REVISION01PAGE3~~"~":"'~F~>"4 TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)VI.ADDITIONAL INFORMATION A.FAILEDCOMPONENTS:
Therewerenofailedcomponents.
Theobstructed sensinglineis1/2inchOD,0.065inchwallthickness, carbonsteeltubing.Information aboutthevendorandmanufacturer isnotrelevanttothisevent.B.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:LER92-003wasalsoaneventcausedbyanobstructed pressuresensingline.However,theobstruction wascausedbybuildupofsludgefromnormalimpurities intheprocessfluid(feedwater).
Theobstruction referredtoinLER94-002wascausedbycorrosion fromtheinteraction ofthetestmediumandthesensinglinematerials.
C.SPECIALCOMMENTS:
NoneHRCFORM366A(5-92)
