Similar Documents at Surry |
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18152B4411999-08-27027 August 1999 LER 99-005-00: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 ML18152B4421999-08-27027 August 1999 LER 99-006-00: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 990827 Ltr ML18152B3771999-08-13013 August 1999 LER 99-004-00: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 ML18152B4181999-05-18018 May 1999 LER 99-002-00: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 990518 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18153A2741999-03-29029 March 1999 LER 99-002-00: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 ML18153A2681999-03-19019 March 1999 LER 98-013-01: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 ML18152B7261999-01-21021 January 1999 LER 99-001-00: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 ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5781998-12-16016 December 1998 LER 98-014-00: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 ML18152B7041998-12-0101 December 1998 LER 98-012-00: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 981201 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B7811998-07-31031 July 1998 LER 98-010-00: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 ML18153A2581998-06-0303 June 1998 LER 98-009-00: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 ML18152B8241998-05-22022 May 1998 LER 98-008-00: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 ML18152B7951998-04-29029 April 1998 LER 98-007-00: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 ML18153A2521998-04-22022 April 1998 LER 98-005-01: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 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00: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 ML18153A2301998-03-0606 March 1998 LER 98-004-00: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 ML18153A2251998-03-0404 March 1998 LER 98-002-00: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 ML18153A2201998-02-0606 February 1998 LER 98-001-00: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.W/980206 Ltr ML18153A2071998-01-13013 January 1998 LER 97-012-01: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 ML18153A2101998-01-13013 January 1998 LER 97-009-01: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 ML18153A1911997-11-26026 November 1997 LER 97-011-00: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 ML18153A1971997-11-26026 November 1997 LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset ML18153A1921997-11-25025 November 1997 LER 97-010-00: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.W/971125 Ltr ML18153A1831997-11-12012 November 1997 LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause ML18153A1791997-11-0707 November 1997 LER 97-008-00: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 ML18153A1721997-10-30030 October 1997 LER 97-007-00: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 ML18153A1421997-06-10010 June 1997 LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr ML18153A1391997-05-28028 May 1997 LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled ML18153A1291997-04-18018 April 1997 LER 97-006-00: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.W/970418 Ltr ML18153A1281997-04-15015 April 1997 LER 97-004-00: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.W/970415 Ltr ML18153A1241997-04-0808 April 1997 LER 97-002-01: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.W/970408 Ltr ML18153A1191997-03-19019 March 1997 LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr ML18153A1201997-03-19019 March 1997 LER 97-003-00: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.W/970319 Ltr ML18153A1131997-02-20020 February 1997 LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr ML18153A1101997-02-13013 February 1997 LER 97-002-00: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.W/970214 Ltr ML18153A0951997-01-0202 January 1997 LER 97-002-00: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 ML18153A0931996-12-12012 December 1996 LER 96-008-00: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.W/961212 Ltr ML18153A0691996-09-19019 September 1996 LER 96-007-00: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.W/960920 Ltr ML18153A0481996-08-26026 August 1996 LER 96-005-00: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.W/960826 Ltr ML18153A0521996-08-20020 August 1996 LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr ML18153A0321996-07-30030 July 1996 LER 96-006-01: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.W/960730 Ltr ML18153A0281996-07-17017 July 1996 LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr ML18153A0141996-07-0202 July 1996 LER 96-004-00: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.W/960702 Ltr 1999-08-27
[Table view] Category:RO)
MONTHYEARML18152B4411999-08-27027 August 1999 LER 99-005-00: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 ML18152B4421999-08-27027 August 1999 LER 99-006-00: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 990827 Ltr ML18152B3771999-08-13013 August 1999 LER 99-004-00: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 ML18152B4181999-05-18018 May 1999 LER 99-002-00: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 990518 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18153A2741999-03-29029 March 1999 LER 99-002-00: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 ML18153A2681999-03-19019 March 1999 LER 98-013-01: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 ML18152B7261999-01-21021 January 1999 LER 99-001-00: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 ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5781998-12-16016 December 1998 LER 98-014-00: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 ML18152B7041998-12-0101 December 1998 LER 98-012-00: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 981201 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B7811998-07-31031 July 1998 LER 98-010-00: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 ML18153A2581998-06-0303 June 1998 LER 98-009-00: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 ML18152B8241998-05-22022 May 1998 LER 98-008-00: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 ML18152B7951998-04-29029 April 1998 LER 98-007-00: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 ML18153A2521998-04-22022 April 1998 LER 98-005-01: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 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00: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 ML18153A2301998-03-0606 March 1998 LER 98-004-00: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 ML18153A2251998-03-0404 March 1998 LER 98-002-00: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 ML18153A2201998-02-0606 February 1998 LER 98-001-00: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.W/980206 Ltr ML18153A2071998-01-13013 January 1998 LER 97-012-01: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 ML18153A2101998-01-13013 January 1998 LER 97-009-01: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 ML18153A1911997-11-26026 November 1997 LER 97-011-00: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 ML18153A1971997-11-26026 November 1997 LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset ML18153A1921997-11-25025 November 1997 LER 97-010-00: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.W/971125 Ltr ML18153A1831997-11-12012 November 1997 LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause ML18153A1791997-11-0707 November 1997 LER 97-008-00: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 ML18153A1721997-10-30030 October 1997 LER 97-007-00: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 ML18153A1421997-06-10010 June 1997 LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr ML18153A1391997-05-28028 May 1997 LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled ML18153A1291997-04-18018 April 1997 LER 97-006-00: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.W/970418 Ltr ML18153A1281997-04-15015 April 1997 LER 97-004-00: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.W/970415 Ltr ML18153A1241997-04-0808 April 1997 LER 97-002-01: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.W/970408 Ltr ML18153A1191997-03-19019 March 1997 LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr ML18153A1201997-03-19019 March 1997 LER 97-003-00: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.W/970319 Ltr ML18153A1131997-02-20020 February 1997 LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr ML18153A1101997-02-13013 February 1997 LER 97-002-00: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.W/970214 Ltr ML18153A0951997-01-0202 January 1997 LER 97-002-00: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 ML18153A0931996-12-12012 December 1996 LER 96-008-00: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.W/961212 Ltr ML18153A0691996-09-19019 September 1996 LER 96-007-00: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.W/960920 Ltr ML18153A0481996-08-26026 August 1996 LER 96-005-00: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.W/960826 Ltr ML18153A0521996-08-20020 August 1996 LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr ML18153A0321996-07-30030 July 1996 LER 96-006-01: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.W/960730 Ltr ML18153A0281996-07-17017 July 1996 LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr ML18153A0141996-07-0202 July 1996 LER 96-004-00: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.W/960702 Ltr 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. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00: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 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00: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 ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00: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 ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00: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 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00: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 ML18153A2681999-03-19019 March 1999 LER 98-013-01: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 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr 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. ML18152B7261999-01-21021 January 1999 LER 99-001-00: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 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00: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 ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.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 ML18152B7041998-12-0101 December 1998 LER 98-012-00: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 981201 Ltr 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 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00: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 ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00: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 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00: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 ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00: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 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01: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 ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00: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 ML18153A2301998-03-0606 March 1998 LER 98-004-00: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 ML18153A2251998-03-0404 March 1998 LER 98-002-00: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 1999-09-30
[Table view] |
Text
. \ .
- surry, Virginia 23883 January 29, 1993 U. S. Nuclear Regulatory Commission Serial No.: 93-047 Document Control Desk Docket No.: 50-280
. Washington, D. C. 20555 License No.: DPR-32 Gentlemen:
Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Unit 1.
REPORT NUMBER 50-280/93-001-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by the Corporate Management Safety Review Committee.
Very truly yours, Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station n o n r. .., "
9302100236 930129 PDR ADOCK 05000280 S PDR
.., NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 (6-89) EXPIRES: 4/30/92 ESTIMATED BURDEN 'PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN LICENSEE EVENT REPORT (LER) ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION .PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) PAGE 3 Surry Power Station Unit 1 0 5 0 0 0 2 8 0 OF O 7 TITLE (4 ) Reactor Trip and Safety Injection Due to Spurious High Consequence Limiting Safeguards Signal Caused by Malfunctioning Relay EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NAMES DOCKET NUMBER(S)
MONTH DAY YEAR YEAR ::11:1 MONTH DAY YEAR NUMBER NUMBER 0 0 0 0 1 089393 0 0 1 0 0 0 1 5 0 0 0 OPERATING N THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more of the following) (11)
MODE (9) 20.402(b) 20.405(c) 50.73(a(2)(w) 73.71(b) t - - - - - - - , - -.........-+---1 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 (Specify;, Ab"'act below and in Text NRC Form 366A) 20.405(a)(1}(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) 20.405(a)( 1}(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) 20.405(a)( 1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBE_R M. R. Kansler, Station Manager AREA CODE 804357 REPORTABLE CAUSE SYSTEM COMPONENT TO NPRDS X JERLY W 1 2 0 y X W 1 2 0 y EXPECTED MONTH DAY YEAR SUBMISSION YES (II yes, c001plete EXPECTED SUBMISSION DATE) DATE (15)
ABSTRACT (Lima lo 1400 spaces, i.e., approximately fifteen single-space lypewritten tines) ( 16)
On January 8, 1993 at 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br />, with Unit 1 operating at 100% power, a reactor trip *and safety injection occurred due to spurious initiation of ,the train "A" high consequence limiting safeguards (Hi-CLS). The spurious signal was generated during troubleshooting by either a l(_)Ose negative lead or an intermittently closing contact on relay 3/4-CLS-lA. On January 9, 1993 at 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br />, with Unit 1 at hot shutdown, a spurious initiation of train A safety injection occurred during testing after replacement of relay 3/4-CLS- lA. The spurious signal was caused by testing prior to removal of a temporary modification (electrical jumper). After both spurious actuations, operators used the appropriate procedures to stabilize the unit. Failed components were replaced and a root cause evaluation was conducted. An engineering evaluation will be performed to identify single point failures which can cause spurious actuations. Circuitry modifications and relay preventive maintenance will be evaluated. A drawing error will be corrected and the everit will be discussed in safety evaluation training. This report is required by 10 CFR 50.73(a)(2)(iv).
NRC Fam 366 (6*89)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 (6-89) EXPIRES: 4130/92 ESTIMATED BURDEN PER RESPONSE Tb COMPLY WITH THIS INFORMATION LICENSEE EVENT REPORT (LER) COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) .. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3)
SEQUENTIAL Jil~~t REVISION YEAR
- NUMBER -:-:-:-:-:-: NUMBER Surry Power Station Unit 1 oI s I o I o I o I 2 Is Io 9 I 3 - 0 I 0 I 1 - 0 I 0 oI 2 OF ol 7 TEXT (ltmao space I* required, u** additional NRC Fam 366A'*) (17) 1.0 - DESCRIPTION OF THE EVENT On January 8, 1993 at 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br />, with Unit 1 operating at 100% power, a reactor trip and safety injection occurred due to spurious initiation of the train "A" high consequence limiting safeguards
. (Hi-CLS) [EIIS: JE].
Prior to the spurious Hi-CLS signal, surveillance testing of the ~ain A Hi-CLS logic had been in progress in accordance with procedure l-PT-8.4, "Consequence Limiting Safeguards (Hi Train)". The channels I and II portions of this test !lad been completed satisfactorily. Following testing of channel III with a circuit te$t switch in the test position, the "test terminate" pushbutton was depressed but the logic did not return to the normal mode. At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, the eight hour action statement in effect for surveillance testing was exited and a twelve hour action statement was entered in accordance with Technical Specification (TS) 3.7.C, Action 14, due to the inoperable train A Hi-CLS logic.
Troubleshooting was initiated to determine if relay 3-CLS-lAM [EIIS: JE, RLY] was energizing as required to enable the train A Hi-CLS logic to return to normal (See Figure 1). The troubleshooting involved depressing and holding the test terminate pushbutton while checking the circuitry required to energize relay 3-CLS-lAM. When the "CLS reset" pushbutton was depressed simultaneously with the test terminate pushbutton and the logic did not return to normal, it was concluded that the test switch was not the cause of the malfunction. It was determined that the malfunction was in another part of the circuit, most likely in contact 9 of relay 3/4-CLS-lA [EIIS: JE, RLY]. Voltage readings taken across contact 9 indicated either no voltage was being supplied to the contact or that the contact was closed. The electricians removed their voltmeter probes from the contacts and exited the relay cabinet to evaluate their readings. Following this action, with the test terminate pushbutton still depressed, the spurious train A Hi~CLS signal occurred and train A safety injection actuated as designed.
Following the train A Hi-CLS signal and safety injection, the following safety systems automatically actuated as designed: train A and B reactor trip generated by the safety injection signal (all control rods inserted into the core), turbine trip, trip of both main feedwater pumps and feedwater isolation, phase 1 and 2 containment isolation, start of both motor driven auxiliary feed water pumps, start of the turbine-driven auxiliary feedwater pump on low-low steam generator water level, discharge of one bank of the main control room, air bottles, start of emergency filtered exhaust fan 1-VS-F-58A and associated ventilation damper alignment, start of emergency diesel- generator No. 1 (loading was not required), and AMSAC. In addition, operators manually initiated reactor trip, turbine trip, and safety injection in accordance with emergency operating procedure l-E-0, "Reactor Trip or Safety Injection".
This caused train B safety injection actuation and the following automatic safety system initiations:
start of emergency filtered exhaust fan l-VS-F-5813 and associated ventilation damper alignment, NRC Form 366A (6-89)
NRG FORM 366A US, NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO, 3150-0104 (6-89) EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY Wl)'H THIS INFORMATION LICENSEE EVENT REPORT (LEA) COLLECTION REQUEST: 50,0 HRS, FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530); U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503, FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
Surry Power Station Unit 1 YEAR tl{f SEQUENTIAL NUMBER
REVISION NUMBER oI s I ol o I 0 I 2 Is I 0 9 I3 - 0 I 0 I 1 - 0 I 0 ol 3 OF 017 TEXT (If mae space is required, use additional NRC Fam 366A's) (17) 1.0 - DESCRIPTION OF THE EVENT (CONT'D) discharge of the second bank of the main control room air bottles, and start of emergency diesel generator No. 3 (loading was not required)_ Safety systems functioned as designed except for source range neutron flux monitor N-31 [EIIS: IG, RI], which did not indicate as expected after its high voltage power supply re-energized followii:ig the reactor trip.
- On January 9, 1993 at 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br />, with Unit 1 at hot shutdown, a spurious initiation of train A safety injection occurred during testing after replacement of relay 3/4-CLS-lA. Following recovery from the January 8, 1993 reactor trip, troubleshooting of the Hi-CLS circuitry had continued. A temporary modJfication (TM), consisting of a jumper across contact 2 of safety injection actuation -relay CR-CLS-lAl, had been installed to maintain the train A safety injection signal in order to prevent additional spurious safety injection signals from occurring during troubleshooting. Relay 3/4-CLS-lA was replaced. Testing of the train A Hi-CLS was then performed with the jumper in place to prevent a spurious safety injection signal in the event relay 3/4-CLS-lA was not the only problem in the circuit.
After completion of testing, when the test terminate pushbutton was depressed, the train A safety injection signal occurred.
Following the safety injection signal, the following automatic actuations occurred as designed: train A safety injection, trip of the running main feedwater pump, start of both motor-driven auxiliary feedwater pumps, discharge of one bank of the main control room air bottles, start of emergency filtered exhaust fan l-VS-F-58A and associated ventilation damper alignment, and start of emergency diesel generator No. 1 (loading was not required). Safety injection was not manually initiated following the automatic initiation because the operators correctly diagnosed that the signal was-spurious.
This report is required by 10 CFR 50.73(a)(2)(iv), because automatic and manual engineered safety features actuations took place. -
2.0 - SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS The Hi-CLS signal is designed to actuate safety injection and other engineered safety features systems upon receipt of a high containment pressure signal indicative of a loss of primary or secondary coolant inside containment. Although the Hi CLS signal and the safety injection signal in this event were not caused by an actual high containment pre*ssure condition, plant systems functioned to place the plant in a safe and stable condition. Source range neutron flux monitor N-32 was operable and capable of
NRC FORM 366A (6-89)
- U.S. NUCLEAR REGULATORY COMMISSION
- APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION LICENSEE EVENT REPORT (LER) COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWOR_K REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. .
FACILITY NAME (1) DOCKET NUMBER 12) LEA NUMBER (6) PAGE(3)
IJ~~~~
SEQUENTIAL REVISION YEAR
- ttf NUMBER NUMBER Surry Power Station Unit 1 oI s I ol o I 0 1218 I 0 9 I3 - 0 I 0 I 1 - 0 I 0 014 OF ol 7 TEXT (II more space is required, use additional NRC Fam 366A's) {17) 2.0- SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS (CONT'D) performing its safety functions. There were, therefore, no adverse consequences to public health and safety.
3.0 - CAUSE OF THE EVENT A root cause evaluation determined that the January 8, 1993 Hi CLS initiation was caused by intermittent cycling of relay 3-CLS-lAM. This relay is normally energized and _de-energizes on a Hi-CLS signal. It is de-energized during logic testing and is re-energized at the conclusion of testing
. by depressing the test terminate pushbutton. During the troubleshooting steps, relay 3-CLS-lAM energized, resulting in the test switch returning to normal because the test terminate pushbutton was being held in. It then quickly de-energized, initiating the train A Hi-CLS and safety injection as designed. The root cause evaluation team identified two conditions which could have caused the spurious cycling.
First, the negative lead on relay 3/4-CLS- lA was found to be loose during relay replacement. The loose connection could have caused an intermittent cycling of relay 3-CLS-lAM, since ihe negative terminal of 3-CLS-lAM was wired to the negative terminal of 3/4-CLS- lA.
The second condition was high resistance across contact 9 on relay 3/4-CLS- lA, which could cause an intermittent cycling of relay 3-CLS-lAM. The high resistance was caused by oxidation and dust accumulation.
The failure of source range neutron detector N-31 to indicate was due to a short circuit condition across the center conductor and the inner shield of its signal cable. The short circuit was detennined to be internal to the detector and was the result of age-related degradation.
The January 9, 1993 safety injection initiation was caused by testing the Hi-CLS logic before removing the jumper instaUed to maintain the train A safety injection signal. Testing before removal of the jumper was the result of cognitive error.by licensee engineering personnel.
During preparation and review of the TM and associated safety evaluation, it was decided that testing should be performed with the protection of the jumper. This decision was based on the understanding that a failure of the test switch had possibly contributed to the spurious Hi-CLS actuation and that the jumper would prevent additional actuations. During the Hi-CLS actuation on January 8, 1993, personnel at the relay cabinet had not seen or heard relay 3-CLS- lAM cycle. This relay is required to
NRC FORM 366A (6-89)
- U.S. NUCLEAR REGULATORY COMMISSION
- APPROVED 0MB NO. 3150-0104 EXPIRES: 4130/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION LICENSEE EVENT REPORT (LER) COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3)
Surry Power Station Unit 1 YEAR rrir SEQUENTIAL NUMBER ttf REVISION NUMBER ol sl ol o I o I 2 Is Io 9 13 - 0 I 0 I 1 - 0 I 0 ols OF ol 7 TEXT (II mae space Is required, use addiional NAC Fam 366A's) (17}
3.0 - CAUSE OF THE EVENT (CONT'D) energize in order for the test switch to return to normal. Since the personnel at the cabinet did not detect any cycling of relay 3-CLS-lAM, their first indication of the Hi-CLS actuation was the sound of the iest switch unlatching and returning to normal. This led to the belief that the test switch may have returned to normal without the required relay actuation. The sequence of events recorder later showed that relay 3-CLS-lAM had actually cycled twice within a 0.3 second interval. Therefore, the relay actuation had occurred but was not detected.
The NSSS vendor elementary diagram for safety injection was reviewed to determine if testing before jumpei: removal would create any adverse effects. This drawing indicated that no spurious actuations would occur; however, the drawing did not show contact 2 of test switch TS-CLS-lA, which is in series with the jumpered contact. The test switch contact initiated the spurious safety injection signal when it was opened then re-closed, which de-energized then re-energized the safety injection output relay, during the testing sequence. The station elementary diagram for Hi-CLS correctly shows the two contacts in series.
4.0 - IMMEDIATE CORRECTIVE ACTIONS Following the Hi-CLS actuation and the safety injection actuation, operators used the appropriate emergency operating procedures to stabilize the plant. The shift technical advisor reviewed the critical safety function status trees to ensure plant parameters remained within safe bounds.
5.0 - ADDITIONAL CORRECTIVE ACTIONS A multi-discipline root cause evaluation team was formed to investigate the event.
Relay 3/4-CLS-lA and source range/ intermediate range detector assembly N-31/N-35 were replaced.
Evaluations of the causes of the component failures were conducted.
After completion of the required repairs, testing, and post-trip reviews, Unit 1 was restarted. The unit was critical at 0701 hours0.00811 days <br />0.195 hours <br />0.00116 weeks <br />2.667305e-4 months <br /> and ori line at 1507 hour~ on January 11, 1993.
6.0 - ACTIONS TO PREVENT RECURRENCE Single point relays (relays whose failure could cause spurious safety system actuations) will be identified. The feasibility of modifying circuitry to remove single point failures will be evaluated.
NRC FORM 366A
'(6-89)
- U.S. NUCLEAR REGULATORY COMMISSION
- APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION LICENSEE EVENT REPORT (LER) COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31~0-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3) ftt SEQUENTIAL REVISION YEAR
=~:::::::::: NUMBER t::.:::i NUMBER Surry Power Station Unit 1 ol sl ol o I 0 I 2 Is I 0 9 I3 - 0 I 0 I 1 - 0 I 0 ol 6 OF ol 7 TEXT (lfm<<e space is required, use additional NRC Fam 366A'6) (17) 6.0 - ACTIONS TO PREVENT RECURRENCE (CONT'D)
Preventive maintenance and/or periodic replacement ~f these relays will be evaluated.
The incomplete NSSS vendor elementary diagram will be updated.
The e\Tent will be discussed in training sessions for safety evaluation preparers and reviewers.
7.0- SIMILAR EVENTS Licensee Event Report 50-280/88-029: A reactor trip and safety injectio_n occurred due to spurious initiation of train A Hi-CLS during performance of a periodic test. The spurious Hi-CLS initiation was caused by failure of a contact in relay 3-CLS-lAM to close when the test terminate pushbutton was depressed. The relay was replaced.
8.0 - ADDITIONAL INFORMATION Failed Components:
- a. Westinghouse Model BFD44S relay
- b. Westinghouse Source and Intermediate Range Detector Assembly - Part No. WL 23823 NRC For~ 366A (6-89)
PN_R_C_F_O_R_M_366_A---*--------------U-(6-89)
- __R_EG_U_LA_T_O_RY_CO-M-M-ISS-ION-,,.....---------A-P_P_R_O_V_E_D_O_M_B_N_0___3_1S0-0--1-04---------,
EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION LICENSEE EVENT REPORT (LER) COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31S0-0104). OFFICE OF MANAGEMENT AND .
BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3)
YEAR f'% SEQUENTIAL NUMBER REVISION*
NUMBER Surry Power Station Unit 1 050002809 3 0 0 1 0 0 0 7 TEXT (II moro IP"C* lorequirod, ... addllonal NRC F<<m 366A'o) ( 17)
~XI 3 IS 3 ~SET IS 3 o..s PUSHlUTTON }- TEST TEANl,..TE I~
q IAII ltllllN CONTROL 80 Q.OSEII IN RESET 8 TS 12 3 l'IISKIUTTON CLS 0..S TS 6 IA Wt CLS a.osm CLS IA IN TEST II q
3/4 CI.S RESET PERMISSIVE o-------i----,
TEST
,...__STAYS IN -
FCII THIS TEST
. II . ITHIS IS A DIFFEIEIT 3 3-Q.S TS-Q.S*IA TEST IIIITCla CI.S
- IIM*X IOPEN IN TESn IOH*X 314 3 CR 3 TS 0..S IA 0..S WI a.s IAI .......
CLS CLS IA
~ CONTACT 2 TEST SWITCH
~
1 0..DSm 111£N AEUY CR zCI.Sl IAIHI 0..5 3:1LS :
TEST
- _ c::TIIC~NTEST IN ~~c'------------~---~------,--,
+-------T IS EIEAGIZED 6r-1 ~
-ro-sr----- ~ 1
,., ------~
l'IISIEJ - .
z CONT.CT Z
- CR O..S IAI ca.DSED 1111 tt a.s
. NIIAT!tlO Figure 1 Hi-CLS Simplified Logic Schematic NRC Form 366A (6-89)