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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
05000280/LER-1998-009, :on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed1998-06-0303 June 1998
- on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
05000280/LER-1998-008, :on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed1998-05-22022 May 1998
- on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
05000280/LER-1998-007, :on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-61998-04-29029 April 1998
- on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
05000280/LER-1998-006, :on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced1998-04-22022 April 1998
- on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
05000280/LER-1998-005, :on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame1998-04-22022 April 1998
- on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
05000280/LER-1998-003, :on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition1998-03-0909 March 1998
- on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
05000280/LER-1998-004, :on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs1998-03-0606 March 1998
- on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
05000280/LER-1998-002, :on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket1998-03-0404 March 1998
- on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
05000280/LER-1998-001-01, :on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was Submitted1998-02-0606 February 1998
- on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was Submitted
05000280/LER-1997-009, :on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status1998-01-13013 January 1998
- on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
05000280/LER-1997-012, :on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors1998-01-13013 January 1998
- on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
05000281/LER-1997-004-02, :on 971202,invalid Mstv Indication Results in Manual Reactor Trip W/Esf Actuation Were Noted.Caused by Displaced Open Limit Switch Arms.Open Limit Switch for Mstv a Was Relocated Closer to Valve Position Bar1997-12-31031 December 1997
- on 971202,invalid Mstv Indication Results in Manual Reactor Trip W/Esf Actuation Were Noted.Caused by Displaced Open Limit Switch Arms.Open Limit Switch for Mstv a Was Relocated Closer to Valve Position Bar
05000281/LER-1997-002-01, :on 970713,main Steam High Range Radiation Monitor Was Declared Inoperable.Caused by Equipment Failure. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-61997-12-10010 December 1997
- on 970713,main Steam High Range Radiation Monitor Was Declared Inoperable.Caused by Equipment Failure. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
05000280/LER-1997-011, :on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised1997-11-26026 November 1997
- on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
05000280/LER-1997-010, :on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared Operable1997-11-25025 November 1997
- on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared Operable
05000281/LER-1997-003-02, :on 971014,Unit 2 MSSVs Revealed That Lift Setting for Two MSSVs Were Outside as Found Setpoint Tolerance.Caused by Minor Setpoint Drift.Repaired,Revised & Adjusted Safety Valves1997-11-13013 November 1997
- on 971014,Unit 2 MSSVs Revealed That Lift Setting for Two MSSVs Were Outside as Found Setpoint Tolerance.Caused by Minor Setpoint Drift.Repaired,Revised & Adjusted Safety Valves
05000280/LER-1997-008-01, :on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset1997-11-0707 November 1997
- on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
05000280/LER-1997-007-01, :on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage1997-10-30030 October 1997
- on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
05000281/LER-1997-002-03, :on 970713,CR annunciator,2-RMA-A-7 for Main Steam Line Effluent High Range Radiation Monitors Alarmed. Caused by Intermittent Component Failure.Preplanned Alternate Method of Monitoring Initiated1997-08-12012 August 1997
- on 970713,CR annunciator,2-RMA-A-7 for Main Steam Line Effluent High Range Radiation Monitors Alarmed. Caused by Intermittent Component Failure.Preplanned Alternate Method of Monitoring Initiated
05000280/LER-1997-001, :on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation Circuitry1997-06-10010 June 1997
- on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation Circuitry
05000280/LER-1997-005, :on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled1997-05-28028 May 1997
- on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
05000280/LER-1997-006, :on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B1997-04-18018 April 1997
- on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B
05000280/LER-1997-004, :on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions Performed1997-04-15015 April 1997
- on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions Performed
05000280/LER-1997-002, :on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust Linkage1997-04-0808 April 1997
- on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust Linkage
05000281/LER-1997-001-01, :on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was Replaced1997-03-19019 March 1997
- on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was Replaced
05000280/LER-1997-003, :on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified Open1997-03-19019 March 1997
- on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified Open
05000280/LER-1997-002-01, :on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 9701161997-02-13013 February 1997
- on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116
05000281/LER-1997-002, :on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown1997-01-0202 January 1997
- on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
05000280/LER-1996-008-01, :on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers Replaced1996-12-12012 December 1996
- on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers Replaced
05000280/LER-1996-007, :on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch Training1996-09-19019 September 1996
- on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch Training
05000281/LER-1996-005-01, :on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other Tubing1996-08-26026 August 1996
- on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other Tubing
05000280/LER-1996-006, :on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to Batteries1996-07-30030 July 1996
- on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to Batteries
05000281/LER-1996-004-02, :on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status Trees1996-07-0202 July 1996
- on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status Trees
05000280/LER-1996-004, :on 960510,noticed That Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies Due to Personnel Error.Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures Implemented1996-06-10010 June 1996
- on 960510,noticed That Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies Due to Personnel Error.Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures Implemented
05000281/LER-1996-003-01, :on 960512,Unit 2 Pressurizer Safety Valve as Found Lift Setting Out of Tolerance.Valve Was Reassembled & Lift Setting Was Established & Tested Satisfactorily1996-06-0707 June 1996
- on 960512,Unit 2 Pressurizer Safety Valve as Found Lift Setting Out of Tolerance.Valve Was Reassembled & Lift Setting Was Established & Tested Satisfactorily
1999-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619 05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations 05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements 05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively 05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
1999-09-30
[Table view] |
text
February 3, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Dear Sirs:
10CFR50.73 Virginia Electric and Power Company Surry Power Station P.O.Bo:x:315 Surry, Virginia 23883 Serial No.:
95-047 SPS:VAA Docket Nos.:
50-280 50-281 License Nos.: DPR-32 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.
REPORT NUMBER*
50-280/50-281/95-002"00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.
Very truly yours, D. A. Christian Station Manager Enclosure cc:
Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 M. W. Branch NRC Senior Resident Inspector Surry Power Station
~5~2130175 950203 S
ADOCK 05000280 PDR
=
. NRC FORM 366
. U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 (5*92)
EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS LICENSEE EVENT REPORT (LER)
INFORMATION COLLECTION REQUEST:
50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block)
MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Surry Power Station, Unit 1 05000 -
280 1 OF4 TITLE (4)
Missed Smoke Detector Surveillance Due to Administrative Process Error EVENT DATE (5)
LER NUMBER (6 REPORT NUMBER (7)
OTHER FACILITIES INVOLVED 8)
SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR Surry Unit 2 05000 -281 FACILITY NAME DOCKET NUMBER 01 10 95 95 002 00 02 03 95 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: (Check one or more (11)
MODE (9)
N 20.402(b) 20.405(c)
- 50. 73 (a)(2)(iv) 73.71(b)
I L:~E~~~ 0) I O I 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71 (c) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii)
OTHER 20.405(a)(1)(iii)
X 50. 73 (a)(2)(i)
- 50. 73 (a) (2) (viii) (A)
(Specify in Abstract 20.405(a)(1)(iv) 50.73(a)(2)(ii)
- 50. 73 (a)(2)(viii)(B) below and in Text, NRG Form 366A) 20.405 (a)(1 )(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER 12)
NAME TELEPHONE NUMBER (Include Area Code)
D, A. Christian, Station Manager (804) 357-3184 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR I
YES NO SUBMISSION (If yes, complete' EXPECTED SUBMISSION DATE)
X DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15. single-spaced typewritten lines) (16)
On January 10, 1995, with Unit 1 at Hot Shutdown and Unit 2 at 100% power, it was identified that procedure O-EPT-0904-04, Six Month Smoke Detector Test {Pyrotronics),
due by January 5, 1995, had not been performed. The smoke detectors {EIIS-IC-DET}
in both units' cable tray rooms and the low level intake structure fuel oil tank room had not been tested within the allowed six month interval between surveillance tests. This is contrary to Technical Specification {TS) 4.18.A.1 which requires that a channel functional test be performed on the smoke detectors at least every six months to demonstrate operability. Procedure O-EPT-0904-04 was satisfactorily completed on May 24, 1994. TS 4.0.2 allows a 25 percent accommodation to the test interval. Therefore, O-EPT-0904-04 was to be performed no later than January 5, 1995.
The smoke detectors were satisfactorily tested on January 10, 1995, five days outside of the allowed six month test window.
The satisfactory performance of O-EPT-0904-04 demonstrated that the smoke detectors were fully capable of performing their intended function during this time frame; therefore, the health and safety of the public were not affected. This event is being reported pursuant to 10 CFR 50.73 {a) (2) (I) (B).
NRG FORM 366 (5-92)
BLOCK NUMBER 1
2 3
4 5
I..
I 6
7 8
9 10 11 12 13 14 15 e
e REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK NUMBER OF DIGITS/CHARACTERS TITLE UP TO 46 FACILITY NAME 8 TOTAL 3 IN ADDITION TO 05000 DOCKET NUMBER VARIES PAGE NUMBER UP T076 TITLE 6 TOTAL 2 PER BLOCK EVENT DATE 7 TOTAL 2.FORYEAR 3 FOR SEQUENTIAL NUMBER LER NUMBER 2 FOR REVISION NUMBER 6 TOTAL 2 PER BLOCK REPORT DATE UP TO 18 - FACILITY NAME 8 TOTAL-DOCKET NUMBER OTHER FACILITIES INVOLVED 3 IN ADDITION TO 05000 1
OPERATING MODE 3
POWER LEVEL 1
CHECK BOX THAT APPLIES REQUIREMENTS OF 10 CFR UP TO 50 FOR NAME 14 FOR TELEPHONE LICENSEE CONTACT CAUSE VARIES.
2 FOR SYSTEM 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1
CHECK BOX THAT APPLIES SUPPLEMENTAL REPORT EXPECTED 6 TOTAL 2 PER BLOCK EXPECTED SUBMISSION DATE (5-92) e U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2) e APPROVED BY 0MB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION
. AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
YEAR LER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER PAGE (3)
_Surry Power Station, Unit 1 05000 -
280 2
OF 4 95 002 00 TEXT (II more space is required, use addWona/ copies of NRG Form 365"') (17) 1.0 DESCRIPTION OF THE EVENT 2.0 On January 10, 1995, with Unit 1 at Hot Shutdown and Unit 2 at 100% power, it was identified that procedure O-EPT-0904-04, Six Month Smoke Detector Test (Pyrotronics),
due by January 5, 1995, had not been performed.
The smoke detectors {~IIS-IC-DET} in both units' cable tray rooms and the low level intake structure fuel oil tank room had not been tested within the allowed six month interval between surveillance tests. This is contrary to Technical Specification (TS) 4.18.A.1 which requires that a channel functional test be performed on the smoke detectors at least every six months to demonstrate operability. Procedure O-EPT-0904-04 was satisfactorily completed on May 24, 1994.
TS 4.0.2 allows a 25 percent accommodation to the test interval. Therefore, O-EPT-0904-04 was to be performed no later than January 5, 1995. The smoke detectors were satisfactorily tested on January 10, 1995, five days outside of the allowed six month test window.
Engineering identified that the Periodic Test {PT) paperwork due by January 5, 1995, had not been submitted. The Electrical Maintenance Department believed that the PT had been completed, but the paperwork could not be located. During the investigation to locate the missing paperwork, the PT was performed simultaneously as a precautionary measure. When it was determined that O-EPT-0904-04 had not been performed on schedule, a Deviation Report was submitted. No Action Statement was entered due to O-EPT-0904-04 having been satisfactorily completed before determination that the PT had not been performed on schedule.
The satisfactory performance of O-EPT-0904-04 demonstrated that the smoke detectors were fully capable of performing their intended function during this time frame; therefore, the health and safety of the public were not affected. This event is being reported pursuant to 10 CFR 50.73 (a) (2) (I) (8).
SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS
Procedure O-EPT-0904-04 was satisfactorily completed on May 24, 1994. The overdue six month surveillance was performed satisfactorily on January 10, 1995, five days outside of the six month test window. The satisfactory performance of O-EPT-0904-04 demonstrated that the smoke detectors were fully capable of performing their intended function during this time frame; therefore, the health and safety of the public were not affected. (5-92) e U.S. NUCLEAR REGULATORY COMMISSION e APPROVED BY 0MB NO. 3150*0104 EXPIRES 5/31/95
- LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION
. AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
YEAR lER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER Surry Power Station, Unit 1 05000 -
280 95 002 00 TEXT /II more space is required, use additional copies of NRC Form 366'\\) (17) 3.0 4.0 5.0
CAUSE OF THE EVENT
As a result of this overdue surveillance, the El.ectrical Maintenance Department initiated an evaluation of their surveillance tracking controls.
The results of the evaluation identified programmatic weaknesses in the administrative process for verifying completion of PTs in the Electrical Maintenance Department.
IMMEDIATE CORRECTIVE ACTION(S)
Electrical Periodic Test O-EPT-0904-04, Six Month Smoke Detector Test {Pyrotronics),
was performed satisfactorily on January 10, 1995.
ADDITIONAL CORRECTIVE ACTION(S)
An evaluation was initiated by the Electrical Maintenance Department to determine the cause of the overdue surveillance. The results of the evaluation identified programmatic weaknesses in the administrative process for verifying completion of PTs in the Electrical Maintenance Department.
Specifically, Maintenance Department Administrative Guideline {MDAG)-3, Maintenance Department PT Schedule and Tracking {Electrical), did not assign specific responsibilities and guidelines for PT scheduling and tracking within Electrical Maintenance. In addition, any PT which was scheduled for a duration longer than one month was not carried from one month to the next on the internal Electrical Maintenance PT schedule.
6.0 ACTIONS TO PREVENT RECURRENCE MDAG-3 was revised to assign specific responsibilities and guidelines for PT scheduling and tracking within Electrical Maintenance. Additional controls were added to MDAG-3 to strengthen the PT completion responsibilities of the Electrical Maintenance Department Supervisors. A senior office associate was assigned responsibility to assist in the operation and maintenance of PT scheduling and tracking. In addition, PTs that are not completed will be carried over from one month to the next on the internal Electrical Maintenance PT schedule.
Quality Assurance will perform an assessment of the tracking process in various departments which perform surveillance testing.
Departmental internal administrative practices will be reviewed, and any appropriate actions needed will be taken to strengthen the controls over the scheduling and tracking of surveillance testing.
PAGE (3) 3 OF 4 (5-92) e U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2) e APPROVED BY 0MB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION
. AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
YEAR LER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER PAGE (3)
Surry Power Station, Unit 1 05000 -
280 4
OF 4
95 002 00 TEXT (II more space is required, use additional copies of NRC Form 366A) (17) 7.0
SIMILAR EVENTS
LER 1-94-010-00 Missed Emergency Diesel Generator Battery Surveillance Due to Personnel Error 8.0 LER 1-91-022-00 LER 1-91-001-00 LER 1-90-007-00:.
Exceeding 92 Day Interval Between Surveillance Tests High Energy Line Inspection Not Performed Within TS Required Interval Due to Administrative Inadequacies Fire Protection Dampers Surveillance Procedure Not Performed Within Technical Specification Required Interval Due to Administrative Oversight
ADDITIONAL INFORMATION
As a result of LER S1-94-010-00, a Root Cause Evaluation was completed on December 19, 1994 and corrective actions were assigned. This root cause evaluation determined that the missed weekly surveillance described in the LER was caused by personnel error.
The root cause evaluation also examined the Electrical Maintenance Department surveillance tracking process. Actions initiated as a result of the root cause evaluation are still being implemented and are being tracked by the corrective action system.
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05000281/LER-1995-001-02, :on 950204,pressurizer Heatup Exceeded TS Limit Due to Lack of Procedural Control.Cooldown Rate Reduced, Deviation Rept Submitted & Plant Data for Event Supplied to Westinghouse to Peform Technical Evaluation |
- on 950204,pressurizer Heatup Exceeded TS Limit Due to Lack of Procedural Control.Cooldown Rate Reduced, Deviation Rept Submitted & Plant Data for Event Supplied to Westinghouse to Peform Technical Evaluation
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000280/LER-1995-001, :on 950108,Unit 1 Automatic Reactor Trip Occurred Due to Coupling Failed on Main Feed Pump.Cr Operators Acted Promptly & Placed Plant in Safe Hot Shutdown Condition |
- on 950108,Unit 1 Automatic Reactor Trip Occurred Due to Coupling Failed on Main Feed Pump.Cr Operators Acted Promptly & Placed Plant in Safe Hot Shutdown Condition
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | 05000280/LER-1995-002, :on 950110,smoke Detector Surveillance Was Missed Due to Administrative Process Error.Electrical Periodic Test O-EPT-0904-04 Was Performed Satisfactorily on 950110 |
- on 950110,smoke Detector Surveillance Was Missed Due to Administrative Process Error.Electrical Periodic Test O-EPT-0904-04 Was Performed Satisfactorily on 950110
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000281/LER-1995-002-02, :on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted |
- on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted
| | 05000280/LER-1995-003-02, :on 950412,Unit 1 Operating at 45% Reactor Power Due to Dropped Rod & Out of Band Delta Flux.Caused by Failed Stationary Coil Conductor for CR J-7.Plant Placed in Safe,Hot Shutdown Condition |
- on 950412,Unit 1 Operating at 45% Reactor Power Due to Dropped Rod & Out of Band Delta Flux.Caused by Failed Stationary Coil Conductor for CR J-7.Plant Placed in Safe,Hot Shutdown Condition
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)(A) | 05000281/LER-1995-003, :on 950224, as Found Calibration Test Data for Three RPS Transmitters Not within Allowable Tolerance. Caused by Faulty Pressure Gauge Used in Calibration.Pressure Gauge Replaced & Repeated Calibration Check |
- on 950224, as Found Calibration Test Data for Three RPS Transmitters Not within Allowable Tolerance. Caused by Faulty Pressure Gauge Used in Calibration.Pressure Gauge Replaced & Repeated Calibration Check
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000281/LER-1995-004, :on 950511,rod Control Sys Urgent Failure Annunciator Alarmed in Cr.Caused by Installation of Damaged Stationary Gripper Coil Regulation Circuit Card.Manual Reactor Trip Initiated & Card Replaced |
- on 950511,rod Control Sys Urgent Failure Annunciator Alarmed in Cr.Caused by Installation of Damaged Stationary Gripper Coil Regulation Circuit Card.Manual Reactor Trip Initiated & Card Replaced
| | 05000280/LER-1995-004-01, :on 950523,identified That Electrical Periodic Test Had Not Been Completely Performed During Mar 1995. Caused by Cognitive Error.Individuals Involved Counseled.W/ |
- on 950523,identified That Electrical Periodic Test Had Not Been Completely Performed During Mar 1995. Caused by Cognitive Error.Individuals Involved Counseled.W/
| 10 CFR 50.73(a)(2)(i)(8) | 05000281/LER-1995-005, :on 950521,manual Reactor Trip Initiated.Cause Due to Loose Solder Connection on Circuit Card Which Caused CRs to Drop Into Core.Unit Placed in Safe Shutdown |
- on 950521,manual Reactor Trip Initiated.Cause Due to Loose Solder Connection on Circuit Card Which Caused CRs to Drop Into Core.Unit Placed in Safe Shutdown
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | 05000280/LER-1995-005-01, :on 950531,review Identified Min Value Speed Used in Periodic Test Procedures Incorrect.Caused by Cognitive Personnel Error.Cat Level Verified in Compliance W/Revised Calculated Min Level of 98.4% |
- on 950531,review Identified Min Value Speed Used in Periodic Test Procedures Incorrect.Caused by Cognitive Personnel Error.Cat Level Verified in Compliance W/Revised Calculated Min Level of 98.4%
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000280/LER-1995-006-01, :on 950822,emergency Swps 1-SW-P-1A & 1-SW-P-1C Inoperable Due to Marine Growth.Entered Limiting Condition for Operation W/Ts 3.14.B When Each Eswp Was Removed from Svc for Testing |
- on 950822,emergency Swps 1-SW-P-1A & 1-SW-P-1C Inoperable Due to Marine Growth.Entered Limiting Condition for Operation W/Ts 3.14.B When Each Eswp Was Removed from Svc for Testing
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000281/LER-1995-006, :on 950614,experienced Generator Trip,Followed by Turbine & Reactor Trips.Cause Believed to Be Due to Inadvertent Action During Maintenance But Not Confirmed.Unit Placed in Safe Shutdown |
- on 950614,experienced Generator Trip,Followed by Turbine & Reactor Trips.Cause Believed to Be Due to Inadvertent Action During Maintenance But Not Confirmed.Unit Placed in Safe Shutdown
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000280/LER-1995-007, :on 950912,boron Crystals & Corrosion Products Discovered Outside Diameter of Vessel.Caused by through-wall Leakage.Work Request Initiated,Engineering & Shift Supervisor Notified |
- on 950912,boron Crystals & Corrosion Products Discovered Outside Diameter of Vessel.Caused by through-wall Leakage.Work Request Initiated,Engineering & Shift Supervisor Notified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(viii)(B) | 05000281/LER-1995-007-01, :on 951107,RT Occurred Due to Failed Rc Pump Motor.Caused by Internal Motor Stator Windings Grounded. Shift Technical Advisor Monitored Critical Safety Function Status Trees to Verify Parameters Acceptable |
- on 951107,RT Occurred Due to Failed Rc Pump Motor.Caused by Internal Motor Stator Windings Grounded. Shift Technical Advisor Monitored Critical Safety Function Status Trees to Verify Parameters Acceptable
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000280/LER-1995-008, :on 950919,pressurizer Safety Valve Found Setpoint Out of Tolerance.Caused by Psvs Being Installed Prior to Start of Most Recent Operating Cycle |
- on 950919,pressurizer Safety Valve Found Setpoint Out of Tolerance.Caused by Psvs Being Installed Prior to Start of Most Recent Operating Cycle
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii)(B) | 05000280/LER-1995-009, :on 950929,4,160 Volt Station Svc Bus Breaker 15C1 Opened,Resulting in Loss of 4,160 Volt Transfer Bus & Start of EDGs Due to Personnel Error.Breaker 15C1 re-closed & Personnel Involved Counseled |
- on 950929,4,160 Volt Station Svc Bus Breaker 15C1 Opened,Resulting in Loss of 4,160 Volt Transfer Bus & Start of EDGs Due to Personnel Error.Breaker 15C1 re-closed & Personnel Involved Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii)(A) | 05000280/LER-1995-010, :on 951006,four Component Cooling Heat Exchangers Determined to Be Inoperable.Caused by Tubesheet Blockage by Hydroids.Component Cooling Heat Exchangers Removed from Svc & Cleaned |
- on 951006,four Component Cooling Heat Exchangers Determined to Be Inoperable.Caused by Tubesheet Blockage by Hydroids.Component Cooling Heat Exchangers Removed from Svc & Cleaned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)(B) | 05000280/LER-1995-011, :on 951018,both Source Range Nuclear Instruments de-energized Due to Personnel Error.Initiated Abnormal Procedure-40 |
- on 951018,both Source Range Nuclear Instruments de-energized Due to Personnel Error.Initiated Abnormal Procedure-40
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) |
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