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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000244/LER-1999-011, :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.With1999-09-22022 September 1999
- 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
05000244/LER-1999-004, :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-installed1999-08-24024 August 1999
- 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
05000244/LER-1999-007, :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 Technicians1999-07-23023 July 1999
- 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
05000244/LER-1998-003, :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 Restored1999-07-22022 July 1999
- 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to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 05000244/LER-1999-010, :on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm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.With1999-07-15015 July 1999
- 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
05000244/LER-1999-001, :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.With1999-06-21021 June 1999
- 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
05000244/LER-1999-009, :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.With1999-06-0202 June 1999
- 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
05000244/LER-1999-008, :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.With1999-05-27027 May 1999
- 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
05000244/LER-1999-006, :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.With1999-05-21021 May 1999
- 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
05000244/LER-1999-005, :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.With1999-05-13013 May 1999
- 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
05000244/LER-1999-003, :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.With1999-03-31031 March 1999
- 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
05000244/LER-1999-002, :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.With1999-03-29029 March 1999
- 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
05000244/LER-1998-005, :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.With1998-12-21021 December 1998
- 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
05000244/LER-1998-004, :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 Discovery1998-12-17017 December 1998
- 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
05000244/LER-1998-002, :on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R371998-07-14014 July 1998
- on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37
05000244/LER-1998-001, :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 Cells1998-03-11011 March 1998
- 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
05000244/LER-1997-007, :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 Identified1998-02-0606 February 1998
- 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
05000244/LER-1997-006, :on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status1998-02-0606 February 1998
- on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
05000244/LER-1997-005, :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 Reset1997-12-0101 December 1997
- 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
05000244/LER-1997-004, :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 Outage1997-11-24024 November 1997
- 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
05000244/LER-1997-003, :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 Configuration1997-09-29029 September 1997
- 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
05000244/LER-1997-002, :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 & 171997-08-19019 August 1997
- 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
05000244/LER-1996-009, :on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe1997-08-11011 August 1997
- on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
05000244/LER-1997-001, :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 F1997-03-0303 March 1997
- 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
05000244/LER-1996-015, :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 Line1997-01-22022 January 1997
- 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
05000244/LER-1996-013, :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-opened1996-11-27027 November 1996
- 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
05000244/LER-1996-012, :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 Replaced1996-09-19019 September 1996
- 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
05000244/LER-1996-011, :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 Secured1996-09-0505 September 1996
- 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
05000244/LER-1996-010, :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 Revised1996-09-0505 September 1996
- 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
05000244/LER-1996-008, :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 Level1996-08-0606 August 1996
- 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
05000244/LER-1996-007, :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 Replaced1996-07-12012 July 1996
- 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
05000244/LER-1996-006, :on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 21996-06-20020 June 1996
- on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2
05000244/LER-1996-005, :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 Revised1996-06-17017 June 1996
- 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
05000244/LER-1996-002, :on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed1996-04-0808 April 1996
- on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed
05000244/LER-1996-004, :on 960309,decrease in Steam Generator Level Occurred.Caused by Failed Open Atmospheric Relief Valves. Booster Relay Replaced1996-04-0808 April 1996
- on 960309,decrease in Steam Generator Level Occurred.Caused by Failed Open Atmospheric Relief Valves. Booster Relay Replaced
05000244/LER-1996-001, :on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled1996-03-18018 March 1996
- on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled
05000244/LER-1995-009, :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/1995-12-14014 December 1995
- 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/
05000244/LER-1995-008, :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 Levels1995-09-25025 September 1995
- 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
05000244/LER-1995-007, :on 950803,lost Power from 34.5 Kv Offsite Power Circuit 751 Due to Offsite Electrical Storm,Resulting in Automatic Start of EDG B.Offsite Power Restored,Edg B Stopped & Realigned & Circuit 751 Cleared1995-09-0101 September 1995
- on 950803,lost Power from 34.5 Kv Offsite Power Circuit 751 Due to Offsite Electrical Storm,Resulting in Automatic Start of EDG B.Offsite Power Restored,Edg B Stopped & Realigned & Circuit 751 Cleared
05000244/LER-1995-006, :on 950630,34.5 Kv Offsite Power Circuit 751 Was Lost Due to Offsite Lightning Strike & Resulted in Automatic Start of a Edg.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1 to Stabilize Plant1995-07-31031 July 1995
- on 950630,34.5 Kv Offsite Power Circuit 751 Was Lost Due to Offsite Lightning Strike & Resulted in Automatic Start of a Edg.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1 to Stabilize Plant
05000244/LER-1995-005, :on 950607,FW Isolation on High SG Level Occurred.Caused by Decrease in Instrument Air Pressure Due to an Air Leak in Containment.Fw Flow Switched to Manual Control1995-07-0707 July 1995
- on 950607,FW Isolation on High SG Level Occurred.Caused by Decrease in Instrument Air Pressure Due to an Air Leak in Containment.Fw Flow Switched to Manual Control
05000244/LER-1995-004, :on 950407,SG Tube Degradation Occurred Due to Iga/Scc That Caused QA Manual Reportable Limits to Be Reached.Sleeved or Plugged Affected Tubes W/Accepted Industry Repair Methods1995-05-0808 May 1995
- on 950407,SG Tube Degradation Occurred Due to Iga/Scc That Caused QA Manual Reportable Limits to Be Reached.Sleeved or Plugged Affected Tubes W/Accepted Industry Repair Methods
05000244/LER-1995-003, :on 950407,inadvertent Automatic SI Actuation Occurred When Technician Unblocked SIAS Due to Misleading Procedural Direction.Pressurizer Pressure Channel P-431 Bistable Proving Switch Reinstated1995-05-0808 May 1995
- on 950407,inadvertent Automatic SI Actuation Occurred When Technician Unblocked SIAS Due to Misleading Procedural Direction.Pressurizer Pressure Channel P-431 Bistable Proving Switch Reinstated
05000244/LER-1995-002, :on 950212,concurrent Indication of Individual CR Position Briefly Unavailable.Caused by Short Circuit. Repair of Short Circuit Completed1995-03-14014 March 1995
- on 950212,concurrent Indication of Individual CR Position Briefly Unavailable.Caused by Short Circuit. Repair of Short Circuit Completed
05000244/LER-1995-001, :on 950203,pressurizer Safety Valves Lift Settings Found Above TS Tolerance During post-svc Test,Due to Setpoint Shifts That Resulted in Independent Trains Being Considered Inoperable1995-03-0606 March 1995
- on 950203,pressurizer Safety Valves Lift Settings Found Above TS Tolerance During post-svc Test,Due to Setpoint Shifts That Resulted in Independent Trains Being Considered Inoperable
05000244/LER-1994-012, :on 940921,approx 1032 Edst W/Reactor at Approx 98% Steady State Power,Power from Circuit 751 Was Lost. Caused by Automatic Actuation of B Emergency D/G Was Due to Undervoltage.Safeguards Buses Were Restored1994-10-21021 October 1994
- on 940921,approx 1032 Edst W/Reactor at Approx 98% Steady State Power,Power from Circuit 751 Was Lost. Caused by Automatic Actuation of B Emergency D/G Was Due to Undervoltage.Safeguards Buses Were Restored
05000244/LER-1994-011, :on 940917,indicating Lamp on B Train Safeguards Initiation Cabinet Failed.Caused by Loss of 125 Vdc Control Power.Burned Out Indicating Lamp & Blown Fuse Replaced1994-10-17017 October 1994
- on 940917,indicating Lamp on B Train Safeguards Initiation Cabinet Failed.Caused by Loss of 125 Vdc Control Power.Burned Out Indicating Lamp & Blown Fuse Replaced
05000244/LER-1994-010, :on 940916,volt Bus 12B Inadvertenly Tripped. Caused by Defective Procedure.Normal Power Supplies Restored & B Emergency Diesel Generator Stopped & Aligned for Auto Standby1994-10-17017 October 1994
- on 940916,volt Bus 12B Inadvertenly Tripped. Caused by Defective Procedure.Normal Power Supplies Restored & B Emergency Diesel Generator Stopped & Aligned for Auto Standby
05000244/LER-1994-009, :on 940809,SI Pumps Declared Inoperable Due to Leak at Socket Weld in Common Recirculation Line for SI Pumps.Affected Weld Inspected & Removed & Maint Procedure for Overhaul of SI Pumps Will Be Upgraded1994-09-0808 September 1994
- on 940809,SI Pumps Declared Inoperable Due to Leak at Socket Weld in Common Recirculation Line for SI Pumps.Affected Weld Inspected & Removed & Maint Procedure for Overhaul of SI Pumps Will Be Upgraded
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 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 05000244/LER-1999-011, :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.With1999-09-22022 September 1999
- 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
ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 05000244/LER-1999-004, :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-installed1999-08-24024 August 1999
- 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
ML17265A7381999-08-16016 August 1999 SE Approving Licensee Requests for Relief 37,38,39,40 & 41 for Re Ginna Nuclear Power Plant for Third & Fourth 10-year Inservice Insp Interval ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 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 05000244/LER-1999-007, :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 Technicians1999-07-23023 July 1999
- 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
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 05000244/LER-1998-003, :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 Restored1999-07-22022 July 1999
- 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
ML17265A7121999-07-19019 July 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp 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 05000244/LER-1999-010, :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.With1999-07-15015 July 1999
- 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
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 ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 05000244/LER-1999-001, :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.With1999-06-21021 June 1999
- 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
ML17265A6831999-06-17017 June 1999 Safety Evaluation Re Response to Supplement 1 to GL 87-02 for Ginna Nuclear Power Plant on USI A-46 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 05000244/LER-1999-009, :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.With1999-06-0202 June 1999
- 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
ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 05000244/LER-1999-008, :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.With1999-05-27027 May 1999
- 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
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 05000244/LER-1999-006, :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.With1999-05-21021 May 1999
- 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
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 05000244/LER-1999-005, :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.With1999-05-13013 May 1999
- 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
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 ML17265A7251999-04-23023 April 1999 Rev 1 to Rept of Development of Rg&E Seismic Safe SD Equipment & Relay Review Lists for USI A-46 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 ML17265A6341999-04-23023 April 1999 Safety Evaluation Supporting Amend 74 to License DPR-18 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 ML17265A6221999-04-0808 April 1999 Safety Evaluation Approving Rg&E Proposed Alternative to Exam Requirement of ASME Code,Section Xi,For Circumferential Shell Welds of RPV for Third 10-year Insp Interval ML17265A6181999-04-0606 April 1999 Safety Evaluation Concluding Proposed Rev 26 to Rg&E QAP for Station Operation Incorporating Reductions in Stated Commitments Will Continue to Comply with QA Criteria of App B to 10CFR50 & Therefore,Acceptable ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp 05000244/LER-1999-003, :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.With1999-03-31031 March 1999
- 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
05000244/LER-1999-002, :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.With1999-03-29029 March 1999
- 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
ML17265A5941999-03-0808 March 1999 Safety Evaluation Accepting Request for Relief 34 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval ML17265A5621999-03-0303 March 1999 Safety Evaluation Supporting Amend 73 to License DPR-18 ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation ML17265A5581999-03-0101 March 1999 Rev 1 to Gnpp Internal Flooding Probabilistic Safety Assessment Final Rept ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With ML17265A5541999-02-25025 February 1999 Safety Evaluation Approving Request to Apply leak-before- Break Status to Portions of Plant Residual Heat Removal Sys Piping ML17265A5341999-02-0404 February 1999 Safety Evaluation Granting Request Relief 36 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)
ACCESSION NBR:9907260052 DOC.DATE: 99/07/19 NOTARIZED: NO DOCKET FACIL'50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION TEED,R.C.
Rochester Gas
& Electric Corp.
MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP. NAME RECIPIENT AFFXLIATXON VISSING,G.S.
SUBJECT:
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.
DISTRIBUTION CODE:
XE74T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Safeguards Phys Sec Event Pt.
73.71 (Public Avai able)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)
Q 05000244 0
RECIPIENT ID CODE/NAME VZSS G.
COPIES LTTR ENCL 1
0 RECXPZENT ID CODE/NAME COPIES LTTR ENCL INTERNAL FILE CENTER RGNl XT 01 1
1 1
1 1
1 NMSS/FCSS/FCOB RES/DRAA/OERAB 1
1 1
1 EXTERNAL: NRC PDR D
0 E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 FULL TEXT CONVERSXON REQUIRED TOTAL NUMBER OF COPIES REQUXRED:
LTTR 7
ENCL 6
ANO ROCHESTER GASANDELECTRIC CORPORATIOhf
~ 89EASTAVENLIE'OCHESTER, MV 1d649.AX'I ~
AREA CODE716 546.2797 ROBERT C. PAECREDY Y ee Pres!eeet Nvereor Ooerorioee July 19 1999 U. S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy ST Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
LER 1999-S01, Safeguards Event R.ED Ginna Nuclear Power Plant Docket No.
50-244
Dear Mr. Vissing:
The attached Licensee Event Report LER 1999-S01 is submitted in accordance with 10 CFR 73.71 and Section I(b) of Appendix G, Reportable Safeguards Events.
Very truly yours, C'
Robert C.
Mec edy xc:
Mr. Guy S. Vissing (Mail Stop SC2)
Project Directorate I-1 Division of Reactor Projects
- I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.
NRC Ginna Senior Resident Inspector 99072b0052 95000244 PDR ADQCK 0 8
NRC FORM 366 IS'l999)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block) fftNIl'ME M " 5.1'mgAK 'mEy
'fonnsbon coBecbon request 50 hrs.
Reported hssons learned are Incorporated hto the ricensing process and fed back to industry. Forward comments regarding burden estimate'to the Records Management Branch (TA F33), U.S. Nuchar Reguhtory Commission, Washington, DC 205554001. Bnd to the Paperwork Reduction Project (31500104). OIRce of Management and Budget, Washington, DC 20503.
Ifan hfonnstion coaction does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a FACILITYNAMEIll R. E. Ginna Nuclear Power Plant DOCKET NUMBER I2I 05000244 PAGE I3) 1 OF 3
Safeguards Event EVENT DATE (5)
I.ER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED(8)
MONTH OAY 06 17 1999 SEQUENTIAL REVSION NUMBER NUMBER 1999
S01
00 MONTH 07 OAY 19 1999 FACIUTYNAME FACILITYNAME DOCKET NUMBER 05000 DOCKET NUMBER 05000 OPERATING MODE (9)
POWER LEVEL (10) 100 THIS REPORT IS SUBMITTED P 20.2201(b) 20.2203(B) (1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a) l2)(iv)
URSUANTTO THE REQUIREMENTSOF 10 CFR 5: (Check 50.73(a)(2)(i)(B) 50.73(a)(2) (ii) 20.2203(al(2)(v) 20.2203(a) (3) (i) 20.2203(a)(3) (ii) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2) (iii) 50.73(a)(2)(iv) 50.73(a) l2)(v) 50.73(a)(2)(vii) one or more) l11) 50.73(a)(2)(viii) 50.73(a)(2)(x)
X 73.71 OTHER Specify in Abstract below or in NAC Form 36SA NAME LICENSEE CONTACT FOR THIS LER l12)
TELEPHONE NUMBER Bncarde Area Code)
Ronald C. Teed - Supervisor Nuclear Security (716) 771-3232 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX
9 S
CAUSE SYSTEM COMPONENT MANUTAC'TURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED 04)
YES (Ifyes, complete EXPECTED SUBMISSION DATE).
NO X
EXPECTED SUBMISSION DATE (15)
MONTH OAY ABSTRACT (Limitto 1400 spaces, i.o., approximately 15 single. spaced typewritten lines) (16)
On June 17, 1999, at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />, a nuclear access authorization event was identified and determined to be reportabie to the Nuclear Regulatory Commission in accordance with 10CFR73.71, Appendix G Section l(b). It was determined that temporary unescorted access had been granted to a contractor employee who would not have been granted access had complete information concerning the circumstances of his military separation been known.
NRC FORM 36BA (91998)
I LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITYNAME I1)
R.E. Ginna Nuclear Power Plant DOCKET (2) 05000244 LER NUMBER Ie) y~A SEOUENIIAL REVI9ION NUNREA NUMBER 1999 -
S01
00 PAGE I3) 2 OF 3
TEXT (ifmore spaceis required, use addidonal copies of NRC Form 366A/ I17)
Pre-Event Plant Conditions The unit was in Mode 1, at normal operations at approximately 100 lo steady-state reactor power.
Description of Event On April 29, 1999, the Ginna Station Access Authorization office received the requested military records for an individual who had been granted temporary unescorted access on February 18, 1999.
After review of this documentation, it was determined that the individual's trustworthiness and reliability could be called into question.
Unescorted access was suspended immediately (on April 29) pending completion of an investigation.
Upon completion of this investigation, unescorted access was revoked on June 17, 1999.
III.
Event Summary While reviewing the Department of Defense form DD-214 supplied by this individual during in-processing for unescorted access to Ginna Station in February 1999, it was noted that he had an honorable discharge from the U.S. Navy. The narrative reason for separation was "Personality Disorder". As part of the background investigation process the individual was required to have a clinical interview with the Rochester Gas and Electric (RG&E) staff psychologist.
During this interview the information regarding his Navy discharge was discussed, along with other personal information.
Based on the information obtained at the time, the psychologist recommended the individual for unescorted access.
The rest of the individual's background investigation did not reveal any other information that would indicate the individual to be untrustworthy or unreliable.
Per NRC Regulatory Guide 5.66, it is not required to do any additional investigation into a military discharge that is honorable.
Information was received from the National Personnel Records Center (NPRC) on April 29, 1999.
Attached to the DD-214 received on April 29 was additional information pertaining to the individual's psychological evaluation conducted while he was in the Navy. The RG&E staff psychologist was provided with this additional information.
His recommendation was to attempt to contact the Navy to obtain more detailed information.
The individual's access authorization was suspended (on April 29), pending receipt of this information. When RG&E was unable to obtain additional information from the Navy, the-psychologist recommended a complete independent psychological evaluation.
On June 3 and June 10, 1999, the individual was evaluated and tested by an independent psychologist.
This report was then forwarded to the RG&E staff psychologist.
Upon review of the report on June 17, 1999, it was recommended that the individual's unescorted access authorization be revoked.
NRC FORM 366A (B IBBBI LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITYNAME 11)
R.E. Ginna Nuclear Power Plant DOCKET (2I 05000244 LER NUMBER {6l
~R SEUUENTIAE REVIBION NUMBER NUMBER 1999 -
S01
00 PAGE I3) 3 OF 3
TEXT (lfmore space is required, use addi donal copies of PfRC Form 366Af 117)
IV.
Corrective Action Short Term Short term corrective action was accomplished by suspending the individual's unescorted access to Ginna Station immediately upon receipt of the military documentation on April 29, 1999, and revoking this access authorization on June 17, 1999.
~Lan Term The individual's supervisors were interviewed regarding the individual's activities during the period when he had been granted unescorted access.
No unusual behavior was noted.
All components of the process for granting the individual unescorted access were reviewed and determined to be in accordance with the requirements of 10CFR73.56 and NRC Regulatory Guide 5.66.