LER#78-004/03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be StudiedML20064B745 |
Person / Time |
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Site: |
Surry ![Dominion icon.png](/w/images/b/b0/Dominion_icon.png) |
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Issue date: |
10/03/1978 |
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From: |
Baucom T VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
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To: |
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Shared Package |
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ML18113A547 |
List: |
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References |
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LER-78-004-03X, LER-78-4-3X, NUDOCS 7810100079 |
Download: ML20064B745 (3) |
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Similar Documents at Surry |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000281/LER-1992-001, Corrected Page 3 to LER 92-001-00 Re 920130 Mechanical Failure Due to Oil Leak from Charging Pump a Bearing & Damper Remaining Closed on Charging Pump B1992-03-26026 March 1992 Corrected Page 3 to LER 92-001-00 Re 920130 Mechanical Failure Due to Oil Leak from Charging Pump a Bearing & Damper Remaining Closed on Charging Pump B ML20245G9341989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed ML20078N5121983-10-14014 October 1983 LER83-043/03L-0:on 830914,following Reactor Trip,Flow Control Valve (FCV) Failed to Close Upon Receipt of Feedwater Isolation Signal.Caused by Malfunctioning Solenoid Valve & FCV-1488 Restricted by Antirotation Device 05000280/LER-1982-126, Updated LER 82-126/03X-1:on 821223,rod Position Indication for Control Rod F-4 Indicated Erratically & Fluctuated Greater than 12 Steps.Cause Unknown.Erroneous Signal Suspected of Being Inside Containment.Testing Underway1983-02-0808 February 1983 Updated LER 82-126/03X-1:on 821223,rod Position Indication for Control Rod F-4 Indicated Erratically & Fluctuated Greater than 12 Steps.Cause Unknown.Erroneous Signal Suspected of Being Inside Containment.Testing Underway 05000281/LER-1981-052, Updated LER 81-052/03X-1:on 810815,valve MOV-SW-202A Failed to Close Due to Grounded Motor.Grounding Caused by Flooding in Sump.Motor Replaced1983-01-31031 January 1983 Updated LER 81-052/03X-1:on 810815,valve MOV-SW-202A Failed to Close Due to Grounded Motor.Grounding Caused by Flooding in Sump.Motor Replaced 05000281/LER-1981-074, Updated LER 81-074/03X-1:on 811120,higher than Normal Activity Detected in Storm Drain Sys.Caused by Leaks from Stripper Feed Steam Heater Due to Failure of Heater Drain Receiver & Pumps to Prevent Overflow.Tubes Plugged1983-01-31031 January 1983 Updated LER 81-074/03X-1:on 811120,higher than Normal Activity Detected in Storm Drain Sys.Caused by Leaks from Stripper Feed Steam Heater Due to Failure of Heater Drain Receiver & Pumps to Prevent Overflow.Tubes Plugged 05000280/LER-1982-084, Updated LER 82-084/01X-1:on 820808,venting of a Charging Pump Resulted in Max Instantaneous Release Rate Being Exceeded.Caused by Failure to Change Radiation Monitor Setpoint Alarms to Reflect New Vent Sys Flow Rates1982-09-27027 September 1982 Updated LER 82-084/01X-1:on 820808,venting of a Charging Pump Resulted in Max Instantaneous Release Rate Being Exceeded.Caused by Failure to Change Radiation Monitor Setpoint Alarms to Reflect New Vent Sys Flow Rates 05000281/LER-1980-010, Updated LER 80-010/01X-1:on 800721,containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design1982-08-13013 August 1982 Updated LER 80-010/01X-1:on 800721,containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design Change 05000280/LER-1981-047, Updated LER 81-047/03X-1:on 810910,following Reactor Trip & While Returning to Power,Specific Activity of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit. Caused by Fuel Element Defect in Reactor Core1982-08-0303 August 1982 Updated LER 81-047/03X-1:on 810910,following Reactor Trip & While Returning to Power,Specific Activity of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit. Caused by Fuel Element Defect in Reactor Core 05000280/LER-1982-049, Updated LER 82-049/03X-1:on 820419,at 100% Power,Charging Pump Svc Water Pump 1-SW-P 10B Found W/Zero Discharge Pressure.Caused by Loss of Suction to Pumps Due to Increased Use of Svc Water by Chillers.Pump Operation Restored1982-08-0303 August 1982 Updated LER 82-049/03X-1:on 820419,at 100% Power,Charging Pump Svc Water Pump 1-SW-P 10B Found W/Zero Discharge Pressure.Caused by Loss of Suction to Pumps Due to Increased Use of Svc Water by Chillers.Pump Operation Restored 05000280/LER-1982-0731982-07-16016 July 1982 LER 82-073/03L-0:on 820622,charging Pump Svc Water Pump 1-SW-P-10B Failed to Develop Adequate Discharge Pressure. Caused by Insufficient Npsh.Svc Water to Chillers Throttled to Provide Sufficient NPSH 05000280/LER-1982-0711982-07-16016 July 1982 LER 82-071/03L-0:on 820618,motor Operated valve-1536 Pressure Power Operated Relief Block Valve Was Cycled Open But Failed to Close Fully,Remotely or Manually.Cause Undetermined.Valve Closed Electrically 05000280/LER-1979-045, Updated LER 79-045/01X-1:on 791228,air Would Not Flow Through Filters If Consequence Limiting Safeguards hi-hi Signal Removed from Control Circuit of Safeguards Area Exhaust Ventilation Dampers.Caused by Design Deficiency1982-07-15015 July 1982 Updated LER 79-045/01X-1:on 791228,air Would Not Flow Through Filters If Consequence Limiting Safeguards hi-hi Signal Removed from Control Circuit of Safeguards Area Exhaust Ventilation Dampers.Caused by Design Deficiency 05000280/LER-1980-059, Updated LER 80-059/01X-1:on 801016,util Informed of Potential for Loss of Auxiliary Feedwater Flow Following Steamline Rupture.Caused by Original Design Allowing Pump Runout & Subsequent Tripping of Sys Pump Motors1982-07-15015 July 1982 Updated LER 80-059/01X-1:on 801016,util Informed of Potential for Loss of Auxiliary Feedwater Flow Following Steamline Rupture.Caused by Original Design Allowing Pump Runout & Subsequent Tripping of Sys Pump Motors 05000280/LER-1982-0681982-07-14014 July 1982 LER 82-068/03L-0:on 820614,fire Detection Sys Discovered to Have Lost Program,Rendering Sys Inoperable.Probably Caused by Voltage Spike in Sys Resulting in Loss of Program.Sys Reprogrammed & Verified Operational 05000280/LER-1982-0261982-07-0909 July 1982 LER 82-026/03L-0:on 820618,electrical Penetration Found Improperly Sealed.Caused by Personnel Failure to Restore Penetration to Original State Following Cable Installation. Penetration Sealed 05000280/LER-1982-0741982-07-0909 July 1982 LER 82-074/03L-0:on 820618,following Check of Svc Water Piping,Pump 1-SW-P-10B Failed to Auto Start.Caused by Drift of Low Pressure Setpoint of Pressure Switch PS-SW-105.Switch Replaced 05000280/LER-1982-0361982-07-0909 July 1982 LER 82-036/03L-0:on 820611,motor Operated Valve CS-203C Failed to Close During Performance of PT-17.1.Caused by Loose Field Wiring Disconnect Device at Motor Control Ctr Cubicle.Plug Reinserted & Valve Returned to Svc 05000280/LER-1982-0611982-07-0202 July 1982 LER 82-061/03L-0:on 820606,w/unit at 100% Power,Core Cooling Monitor a Showed Erratic Indication & Was Removed from Svc. Caused by Failed Printed Circuit Board.Board Replaced 05000280/LER-1982-0351982-07-0202 July 1982 LER 82-035/03L-0:on 820607,w/unit at Full power,TV-IA-201A Would Not Remain Closed After High Radiation Test Signal Cleared.Caused by Incomplete Valve Contact Due to Loosened Limit Switch Mounting Plate.Plate Secured 05000280/LER-1982-0651982-07-0202 July 1982 LER 82-065/03L-0:on 820609,w/unit at 100% Power,Core Cooling Monitor Channel B Failed,Resulting in Spurious Alarms.Caused by Faulty Thermocouple Input.Input Replaced 05000280/LER-1982-0661982-06-28028 June 1982 LER 82-066/03L-0:on 820602,steam Driven Auxiliary Feed Pump Started Automatically Due to Failure of Time Delay Relay Coil.Caused by Open Circuit in Coil.Defective Relay Replaced 05000280/LER-1982-0701982-06-28028 June 1982 LER 82-070/03L-0:on 820604,containment Spray Pump 1-CS-P-1A Failed to Start During Performance Testing 17.1.Caused by Pump Motor Breaker.Breaker Replaced & Pump Tested Satisfactorily 05000280/LER-1982-0321982-06-28028 June 1982 LER 82-032/03L-0:on 820531,pressure in Nitrogen Bottle Supplying Emergency Air to PCV-MS-202A & B Found Below Tech Spec Limit.Caused by Fitting Leaks in Air Lines.Fittings Tightened & Pressurized Bottle Installed 05000280/LER-1982-0291982-06-14014 June 1982 LER 82-029/03L-0:on 820518,during Periodic Test 2-PT-39B-2 Snubbers 2-RC-HSS-162 & 163 Found to Have Empty Remote Reservoir.Caused by Damaged O Ring on Common Valve Block. O Ring Replaced 05000280/LER-1982-0621982-06-14014 June 1982 LER 82-062/03L-0:on 820520,PT-27 Revealed Low Ampere Readings for Circuit 7A in Panels 8 & 9,contrary to Tech Spec.Caused by Damaged Tapes.Tapes Replaced 05000280/LER-1982-0591982-06-14014 June 1982 LER 82-059/03L-0:on 820517,during Recorder Pen Check,Pen on FR-GW-100 (Process Vent) Did Not Correspond to Actual Process Vent Flow Per Tech Spec.Caused by Seized Recorder Motor Bearing Due to Lack of Lubrication.Bearing Replaced 05000280/LER-1982-0601982-06-11011 June 1982 LER 82-060/03L-0:on 820514,charging Pump Svc Water Pump 1-SW-P-10A Found to Have 0 Discharge Pressure Due to Loss of Suction.Caused by Increased Use of Svc Water by Chillers.One Control Room Chiller Secured 05000280/LER-1982-0281982-06-11011 June 1982 LER 82-028/03L-0:on 820513,both Charging Pump Svc Water pumps,2-SW-10A & 10B,lost Suction.Caused by Clogged Suction Line Strainer Due to Marine Growth & Increased Use of Svc Water by Chillers 05000280/LER-1982-0241982-06-0808 June 1982 LER 82-024/01T-0:on 820524,weld Leak on a Steam Generator Channel Head Drain Piping at 2-RC-159 Identified During RCS Integrity Test PT-11.Caused by Random Defect in Root Weld, Possibly Due to Split Pass 05000280/LER-1982-0271982-06-0808 June 1982 LER 82-027/03L-0:on 820513,performance of PT 27B Revealed Amp Readings for Heat Tracing Panels 8 & 9,circuit 21A,below Acceptance Criteria.Caused by Excessive Heat.Defective Heat Tracing Replaced 05000280/LER-1982-0571982-06-0808 June 1982 LER 82-057/03L-0:on 820515,review of I-131 Spike History Revealed That Deviation Repts Not Submitted for 820106 & 0325 post-reactor Trip Specific Activity Samples of RCS W/Dose Equivalent I-131 Higher than Tech Specs 05000280/LER-1982-0581982-06-0808 June 1982 LER 82-058/03L-0:on 820516,T-26.1 Revealed Component Cooling Sys Radiation Monitor RM-CC-105 Reading Above Alarm Setpoint But Not Alarming.Caused by Out of Calibr Alarm & Oscillator Cards.Cards Calibr 05000280/LER-1982-0631982-05-28028 May 1982 LER 82-063/03L:on 820330,circuit Breakers for Heat Tracing Panels 8 & 9,circuits 7,found Inoperable.Caused by Mechanical Failure in One Breaker.Defective Breaker Replaced & Other Circuit Breaker Reset 05000280/LER-1982-0251982-05-28028 May 1982 LER 82-025/03L:on 820509,control Room Operator Overfilled B Accumulator Beyond Upper Tech Spec Limit.Caused by Operator error.HCV-2852B Opened to Drain Accumulator Tank to Tech Spec Limits 05000280/LER-1982-0551982-05-28028 May 1982 LER 82-055/03L-0:on 820429,MDP 21.3 Revealed That Control Room Envelope Might Not Meet Tech Spec Requirements.Caused by Leak in Door Seals & Improper Exterior Ventilation Lineup.Seals Replaced & Lineup Corrected 05000280/LER-1981-081, /03L-0:on 820121,during Research for LER 81-081/03L-0,found That Original Vacuum Pumps Were Replaced W/Pumps That Failed to Meet Required Seismic Qualifications. Study of Present Pumps Completed.Assistance Request Issued1982-02-19019 February 1982 /03L-0:on 820121,during Research for LER 81-081/03L-0,found That Original Vacuum Pumps Were Replaced W/Pumps That Failed to Meet Required Seismic Qualifications. Study of Present Pumps Completed.Assistance Request Issued ML20064B8251978-10-0505 October 1978 /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled ML20064B7451978-10-0303 October 1978 /03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be Studied 05000281/LER-1976-015, Updated LER 76-15/03L:on 761006,leakage of Water Observed from Recirculation Spray HX a Piping.Caused by Cracking in Heat Affected Zones of Several Welds.Listed Piping Will Be Replaced1976-11-19019 November 1976 Updated LER 76-15/03L:on 761006,leakage of Water Observed from Recirculation Spray HX a Piping.Caused by Cracking in Heat Affected Zones of Several Welds.Listed Piping Will Be Replaced 05000281/LER-1976-003, Updated LER 76-03/01T:on 760521,routine Chemistry Analysis of Primary Coolant Boron Concentration Indicated Unplanned Dilution Occurred.Caused by Three Tubes Cut on Steam Generator 2A.Tubes Plugged1976-07-27027 July 1976 Updated LER 76-03/01T:on 760521,routine Chemistry Analysis of Primary Coolant Boron Concentration Indicated Unplanned Dilution Occurred.Caused by Three Tubes Cut on Steam Generator 2A.Tubes Plugged 05000000/LER-1950-237, Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis1976-07-13013 July 1976 Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis 05000280/LER-1976-002, Updated LER 76-02/01T:on 760313,determined Worst Break LOCA Core Thermal Transient Analysis Inaccurate Since Effects of Steam Generator Tube Plugging on LOCA Not Considered1976-05-17017 May 1976 Updated LER 76-02/01T:on 760313,determined Worst Break LOCA Core Thermal Transient Analysis Inaccurate Since Effects of Steam Generator Tube Plugging on LOCA Not Considered 05000280/LER-1976-002, Updated LER 76-02/01T:on 760313,determined Worst Break LOCA Core Thermal Transient Analysis Inaccurate Since Effects of Steam Generator Tube Plugging on LOCA Not Considered. W/760525 Ltr1976-05-17017 May 1976 Updated LER 76-02/01T:on 760313,determined Worst Break LOCA Core Thermal Transient Analysis Inaccurate Since Effects of Steam Generator Tube Plugging on LOCA Not Considered. W/760525 Ltr 05000280/LER-1975-016, Updated LER 75-16/010:on 750822 & 23,channel II Protection Drifted in Nonconservative Direction.Caused by Moisture Accumulation Between Senson Insulation & Copper Lead Wire. All RTDs Replaced W/Improved Versions1976-02-0202 February 1976 Updated LER 75-16/010:on 750822 & 23,channel II Protection Drifted in Nonconservative Direction.Caused by Moisture Accumulation Between Senson Insulation & Copper Lead Wire. All RTDs Replaced W/Improved Versions 05000281/LER-1975-012, Suppl to LER 75-12/01T:on 750706,reactor Trip Occurred. Caused by Sudden Closure of Trip Valve in Main Steam Line B Followed by Closure of Main Steam Line Valves a & C1976-01-20020 January 1976 Suppl to LER 75-12/01T:on 750706,reactor Trip Occurred. Caused by Sudden Closure of Trip Valve in Main Steam Line B Followed by Closure of Main Steam Line Valves a & C 05000280/LER-1975-015, Updated LER 75-15/01T:on 750803,leaking Fitting on Overhead Gas Compressor B Resulted in Unplanned Release of Radioctive Matl from Site.Caused by Loose Fitting.Leaking Fitting Repaired1975-09-0303 September 1975 Updated LER 75-15/01T:on 750803,leaking Fitting on Overhead Gas Compressor B Resulted in Unplanned Release of Radioctive Matl from Site.Caused by Loose Fitting.Leaking Fitting Repaired 05000280/LER-1975-011, Suppl to LER 75-11/01T:on 750416,pinhole Leak Developed in Recirculation Line on Charging Pump 2-CH-P-1C Causing Ventilation Vent Sampler RMS-VG-109 to Alarm.Leak Found & Isolated1975-07-10010 July 1975 Suppl to LER 75-11/01T:on 750416,pinhole Leak Developed in Recirculation Line on Charging Pump 2-CH-P-1C Causing Ventilation Vent Sampler RMS-VG-109 to Alarm.Leak Found & Isolated 05000280/LER-1975-008, Supplementary LER 75-08/01L on 750427.Previously Described Event Caused by Apparent Inadequate Implementation of Administrative Controls During Const & Preoperation. Administrative Control of Electrical Wire Changes Increased1975-07-0707 July 1975 Supplementary LER 75-08/01L on 750427.Previously Described Event Caused by Apparent Inadequate Implementation of Administrative Controls During Const & Preoperation. Administrative Control of Electrical Wire Changes Increased 05000281/LER-1975-005, Updated LER 75-05/010:on 750225,radial Trip of Max 2.5% Existed.Caused by Prolonged Recovery of Rod F-2.Control Room Alarm Did Not Function Due to Defective Circuit Card. Card Replaced & Staff Cautioned1975-04-0808 April 1975 Updated LER 75-05/010:on 750225,radial Trip of Max 2.5% Existed.Caused by Prolonged Recovery of Rod F-2.Control Room Alarm Did Not Function Due to Defective Circuit Card. Card Replaced & Staff Cautioned 1992-03-26
[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
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61 CCC4ET NUveER 64 69 EVENT OATE 74 75 RE*CRT QATE e3 EVENT CESCRIPTION AND PROBASLE CONSECUENCES h l 1 o i 2 I lWith unit in nornal operation. at rated power, charging pump intermediate seal cooler l
,, ,3, ,1-SW-E-13 was checked for service water flow. This check was prompted by an observed, j
,3,,, gno-flow condition on unit 2 "B" cooler. As on Unit 2, Unit 1 "B" cooler had no flow. ;
y n , , , ,This is contrary to T.S.-3.3. A.S.C. and is reportable per T.S. 6.6.2.b. (2) . The fully
, redundant "A" cooler was in operation so that there was no effect on the health and ,
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' l 011 l l safety of the public.
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,,,aj ps on Unit 2, the no flow condition was caused by a dropped disc in the cooler outlet j y , , , , [ isolation valve. The valve was disassembled and the disc removed. Subsequently, a ;
replacement for the corroded stem was fabricated. The old disc and a new stem uere I l
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I Virginia Electric and Powar Company Surry Power Station Docket No: 050-0280 LER 73-004/03X-1 Event Date 3-5-78 foss of Service Water Flow Through Charging Puop Intermediate Seal Cooler
- 1. Description of Event:
At about 1500, 3-5-78, with the unit at normal operation and at rated power, the charging pump intermediate seal cooler 1-SW-E-1B was found to have no service water flow. This check was prompted by the discovery of a similar condition found on Unit 2 at about 1300 on the same day (reported in Unit 2 LER-78-004/03L-0). This event is contrary to Technical Specification ~
3.3.A.8.C. and is reportable in accordance with Technical Specification 6.6.2.b.(2).
- 2. Probable Consequence of Event:
The loss of the charging pu=p intermediate seal cooler 1-SW-E-13 had no effect upon the health and safety of the general public because adequate cooling of the charging pump component cooling system was available via the "A" charging pump intermediate seal cooler, which is a full size cooler.
- 3. Cause of Event:
The loss of flow to the "B" intermediate seal cooler was due to the failure of the cooler's discharge gate valve. Corrosion of the stem permitted the disc to drop free and obstruct the service water flow path.
4 Immediate Corrective Action:
The ic=ediate action was to verify flow to seal cooler 1-SW-E-1A. Cooler "B" was then isolated, the suspected valve was opened and the disc removed. A new steu was fabricated from stainless steel. The new stem and old disc were re-installed and the valve raturned to service.
J Following repair of the "B" cooler discharge valve, the "B" cooler was placed in service. The "A" cooler was isolated to examine its discharge valve.
A similar condition of stem corrosion was found but had not advanced to the point of dropping the disc. A new stem was fabricated and installed in this valve.
- 5. Scheduled Corrective Action:
The initial report indicated that all of the 1 1/2" and 2" valves in the charging pump service water system would be inspected during the then forthecming rufueling outage. This inspection was performed and several of the ralves were found in various stages of deterioration. However, due to the availability of spare parts, only those valves required to provide flow to at least luo lube oil coolers and one intermediate seal cooler were repaired or replaced. The other lube oil cooler and seal cooler are operable but with valves in varying stages of deterioration. As parts become available, these valves will be repaired. If they should fail before this, flow can be established by removal of the disc.
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tal Virginia Electric and Powar Company Surry Power Station, Unit 1 Docket No: 050-0280 LER 78-004/03X-1 ;
Event Date 3-5-78 j i
Loss of Service Water Flow Throuch Charging Puno Intermediate Seal Cooler )
- 6. Action Taken to Prevent Recurrence:
An engineering study was instituted to identify possible long term corrective action. Also discussed in the study was the mode of corrosion.
From observation of the failed components, it was decided that the mode of corrosion was predominantly galvanic, due to the brass stem in contacc with the bronze disc. The brass, being the anode of this galvanic couple, would I be wasted as was observed.
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As far as long term corrective action is concerned, it was concluded that a suitable replacementa valve with a valve design that embodies less dissimilarity of materials and a " fail-as-is" principle, should be installed in place of the existing valves. Based on this conclusion, a design change has been initiated to implement this idea. Present indications are that the replacement will commence concurrent with the steam generator replacement (s).
- 7. Generic Imolications:
The event possesses generic implications in that the corrosion observed in the cooler outlet valves may also exist in other gate valves of the f charging pump service water system. Based on the inspection performed, it was found that this problem was generic in the Walworth 1 1/2" and 2" gate valves.
Whether this problem exists in other types of safety related service' water valves will be determined in a separate study.
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