|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046C3131993-07-28028 July 1993 LER 93-015-00:on 930630,HPCI Sys Declared Inoperable Due to Indicated Flow During Surveillance.Caused by Foreign Matl That Plugged Portion of Restricting Orifice.Restricting Orifice Removed,Cleaned & reinstalled.W/930728 Ltr ML20046B5241993-07-26026 July 1993 LER 93-007-01:on 930317,automatic Closing of RCIC Sys Turbine Steam Supply Isolation Valves Occurred Due to High Steam Flow Signal.Increased Frequency of Valve Testing from Monthly to weekly.W/930726 Ltr ML20045F8601993-06-30030 June 1993 LER 93-014-00:on 930531,automatic Scram Occurred,Resulting from Operation of Auxiliary Transformer Differential Relay During Power Ascension.Uat Phase B & C Differential Relays Left Interchanged as Investigative aid.W/930630 Ltr ML20045E2301993-06-25025 June 1993 LER 93-013-00:on 930530,RCIC Sys Declared Inoperable & 7 Day TS 3.5.D.2 LCO Entered Due to Speed Oscillations Which Occurred After Several Minutes of steady-state Operation. Caused by Actuator Failure.Actuator replaced.W/930625 Ltr ML20045E2251993-06-25025 June 1993 LER 93-012-00:on 930529,unplanned PCIS Group I Isolation Signal Occurred While Opening MSIV During Startup,Resulting in Automatic Closing of Related Valves.Caused by Licensed Operator Error.Group 1 Isolation reset.W/930625 Ltr ML20045D6941993-06-23023 June 1993 LER 93-011-00:on 930525,determined That Initial as-found Popping Pressures of Pilot Valves for Three Target Rock Main Steam Relief Valves Out of TS Tolerance.Caused by Setpoint Drift.Valves Reworked & Reassembled by Target Rock Corp ML20045D1861993-06-18018 June 1993 LER 93-010-00:on 930519,SUT Became de-energized During Planned Calibr of Turbine/Generator Relays Lockout Test While Shut Down.Caused by Personnel Error.Discussion Conducted W/Personnel Re Attention to detail.W/930618 Ltr ML20044H0441993-06-0202 June 1993 LER 93-009-00:on 930504,circuit Breaker Did Not Close During Planned Bus Transfer Due to Loose Control Circuit Wire.Lug Replaced & Reterminated on 930505 & Post Work Testing Completed W/Satisfactory results.W/930602 Ltr ML20024G7451991-04-24024 April 1991 LER 91-005-00:on 910325,diesel Generator Inoperable,Causing Loss of Ac Power to Train B Components of Safety Sys & Actuating Portions of Primary/Secondary Containment Sys. Caused by Voltage Regulator failure.W/910424 Ltr ML20029A6721991-02-25025 February 1991 LER 91-001-00:on 910125,automatic Primary Containment Isolation Control Sys Group 5 Actuation Occurred,Resulting in Closing of RCIC Turbine Steam Supply Isolation Valves. Caused by High Flow conditions.W/910225 Ltr ML20028G9731990-09-20020 September 1990 LER 89-036-01:on 891122,determined That HPCI Sys Inoperable Due to Inoperable Gland Seal Condenser Blower Motor.Caused by age-related Wear of Motor.Blower Motor Replaced & Blower Tested W/Satisfactory results.W/900920 Ltr ML20028G9121990-09-18018 September 1990 LER 89-037-01:on 891130,primary Containment/Traversing in-core Probe Ball Valve Discovered to Be Almost Full Open. Caused by Damage to Valve Stem Due to Manual Manipulation of Stem.Ball Valve & Solenoid Actuator replaced.W/900918 Ltr ML20043G3541990-06-12012 June 1990 LER 90-008-00:on 900513,automatic Scram Resulting from Load Rejection Occurred While at Full Power,Resulting in Trip of Generator Field Breakers.Caused by Fault on Offsite 345 Kv Transmission sys.Loss-of-field Relay replaced.W/900612 Ltr ML20043F8291990-06-0606 June 1990 LER 90-007-00:on 900507,discovered That Drywell to Suppression Chamber Vacuum Breaker Surveillance Not Performed Prior to Startup in 1988.Caused by Misunderstanding of requirements.W/900606 Ltr ML20042F5911990-04-30030 April 1990 LER 90-006-00:on 900330,determined That Position of Primary Containment Sys Isolation Valve Not Recorded Daily,Per Tech Specs.Review Performed to Determine If Other Problems Existed.Plant Shut Down & Review performed.W/900430 Ltr ML20012F5751990-04-0606 April 1990 LER 90-003-00:on 900311,automatic Actuation of Main Steam Sys Group 1 Portion of Primary Containment Isolation Control Sys Occurred.Caused by False High Reactor Vessel Water Level Signal.Procedure Developed Re backfill.W/900406 Ltr ML20012E9831990-03-30030 March 1990 LER 90-002-00:on 900228,determined That Max Fraction of Limiting Power Density Not Checked Daily During Reactor Power Operation,Per Tech Spec 4.1.B.On 900323,addl Tech Spec Issue Discovered.Tech Specs changed.W/900330 Ltr ML20012C4871990-03-12012 March 1990 LER 90-001-00:on 900209,24 H Limiting Condition for Operation Entered When Two RCS Instrumentation Excess Flow Check Valves Inappropriately Verified Operable During Testing.Cause Undetermined.Two Valves replaced.W/900312 Ltr ML20005G0981990-01-0808 January 1990 LER 89-038-00:on 891208,unplanned Automatic Reactor Protection Sys Scram Signal & Reactor Scram Occurred.Caused by False Low Reactor Vessel Water Level Signal.Local Level Indicators Satisfactorily calibr.W/900108 Ltr ML20005F8481990-01-0808 January 1990 LER 89-039-00:on 891209,automatic Actuation of RHR Sys Portion of Primary Containment Isolation Control Sys Occurred.Caused by Hydrodynamic Transient That Actuated Protective High Pressure switches.W/900108 Ltr ML20005E8551989-12-30030 December 1989 LER 89-037-00:on 891130,discovered That Traversing in-core Probe Ball Valve,Mfg by Consolidated Controls,Inc,Closed,In Violation of Tech Specs.Caused by Damage to Valve Stem.Ball Valve & Actuator replaced.W/891230 Ltr ML20011D1361989-12-11011 December 1989 LER 89-035-00:on 891111,inadvertent Actuation of Portion of Secondary Containment Sys During Surveillance Testing Occurred.Caused by Location of Radiation Isolation Control Sys Channel a Logic Relay.Procedure revised.W/891211 Ltr ML20005D7421989-12-0606 December 1989 LER 89-033-00:on 891106,automatic Actuation of Group 1 Portion of Primary Containment Isolation Control Sys (PCIS) Occurred.Caused by High Reactor Vessel Water Level.Manual Valve Closed & PCIS Logic Circuitry reset.W/891206 Ltr ML19351A4581989-12-0606 December 1989 LER 89-034-00:on 891108,determined That Reactor Pressure Exceeded 150 Psig on 891107 W/O Performing Surveillance Procedure 8.5.4.4, HPCI Valve Operability Test. Caused by Personnel Error.Procedure initiated.W/891206 Ltr ML19332D1421989-11-22022 November 1989 LER 89-031-00:on 891024,closing Times for Two in-series Primary Containment Isolation Valves Exceeded Acceptance Criteria During Shutdown Testing.Cause Undetermined.Closing Time Retested W/Satisfactory results.W/891122 Ltr ML19332D6231989-11-20020 November 1989 LER 89-032-00:on 891020,pneumatic Pressure Drop for Two of Four Automatic Depressurization Sys Accumulators Discovered Greater than Max Acceptable Value.Caused by Leakage from Seat of Supply Check Valves.Seat replaced.W/891120 Ltr ML19324C3181989-11-0909 November 1989 LER 88-002-01:on 880117,full Reactor Protection Sys Scram Trip Signal Occurred During Surveillance Test,Resulting in Incomplete Actuations.Caused by Procedure Inadequacy.Logic Relay Replaced & Procedure revised.W/891109 Ltr ML19324B1131989-10-21021 October 1989 LER 89-030-00:on 890926,control Room High Efficiency Air Filtration Sys Flowrate non-conservative Due to Procedure Error.Caused by Transcription Error.Procedure Revised & Test Reperformed Using Corrected procedure.W/891021 Ltr ML19325D4681989-10-16016 October 1989 LER 89-029-00:on 890914,locked High Radiation Area Door Found to Have Been Unsecured Contrary to Tech Spec 6.13.2. Caused by Failure to Adhere to Approved Procedures. Training on Access Requirements initiated.W/891016 Ltr ML19325D1861989-10-10010 October 1989 LER 89-028-00:on 890907,HPCI Sys Declared Inoperable Because Mechanical Overspeed Trip Occurred During Surveillance Test. Caused by Failure of Ramp Generator Signal Converter Module. Module Removed & Sent to Mfg for exam.W/891010 Ltr ML17277B8221984-07-20020 July 1984 LER 82-049/01X-1:on 821102,main Steam Line Safety Valve a Set W/Nitrogen at Steam Relief Setting.Caused by Personnel Error.Valve Removed & Replaced W/Properly Set Spare Valve. Procedure revised.W/840720 Ltr ML20024C3231983-06-24024 June 1983 Updated LER 82-038/03X-1:on 820817,RCIC Steam Line High Differential Pressure Alarm Received.Caused by Air in Sensing Lines to Pressure Switches.Cross Threaded Cap Found on in-line Snubber.Snubber replaced.W/830624 Ltr ML20024C2211983-06-24024 June 1983 Updated LER 80-053/03X-1:on 800814,0907 & 14,HPCI Turbine Exhaust Line Snubber 23-3-36 Determined Inoperable.Caused by Transient Hydrodynamic Shock During Startup & Shutdown. Snubbers upgraded.W/830624 Ltr ML20024B8451983-06-24024 June 1983 LER 83-031/03L-0:on 830528,HPCI Sys Made Inoperable to Repair Steam Leak on AO 2301-31.Caused by Leaking Stem Packing.Packing Replaced.Valve Tested Satisfactorily.Sys Returned to svc.W/830624 Ltr ML20024B8321983-06-24024 June 1983 LER 83-030/03L-0:on 830527,both HPCI Area Smoke Detection Sys Alarmed in Main Control Room.Caused by Valve A02301-31 Steam Leak Causing False Indications.Valve repaired.W/830624 Ltr ML20024C3101983-06-21021 June 1983 Updated LER 79-007/03X-1:on 790212,while Performing Test 8.7.4.3,valves AO-5033A,CV-5065-10,15,16 & 17 Failed to Give Proper Position Indication When Cycled & to Close within Specified Tolerance.Cause Not stated.W/830621 Ltr ML20024A8861983-06-16016 June 1983 LER 83-027/03L-0:on 830518,during Routine Insp,Folding Fire Door Found Inoperable.Caused by Operating Cable Becoming Detached from Pulley Due to Slack.Cable Reattached & Operating Mechanism adjusted.W/830616 Ltr ML20023D1691983-05-0909 May 1983 Updated LER 82-008/01X-1:on 820331,HPCI Injection Valve MO-2301-8 Failed to Open in Required Manner.Caused by Missing Wire Jumper Intended to Bypass Motor Operator Torque Switch.Jumper Installed & Valve Tested Satisfactorily ML20023D0671983-05-0909 May 1983 LER 83-021/03L-0:on 830411,during Surveillance Test 8.7.4.3, Primary Containment Isolation Valve AO-5033B Failed to Meet 10-s Closing Time Requirements.Caused by Lubricant Infiltrating Solenoid Valve Components.Components Replaced ML20023D0181983-05-0404 May 1983 LER 83-022/03L-0:on 830413,overload on Valve Motor 1301-17 Resulted in Loss of High Pressure Core Cooling Backup Capability.Caused by Oxidation in Motor End Bell & Motor Brushes,Due to Humidity Caused by Leaking Valve Packing ML20028G1591983-01-28028 January 1983 LER 83-002/01T-0:on 830116,flow Ref off-normal Alarm Received.Average Power Range Monitor Flux Scram Trip Settings Affected.Cause Under Investigation.Flow Inputs Monitored & Amplifier B Recalibr ML20028F4121983-01-17017 January 1983 LER 83-002/01X-0:on 830116,while Clearing off-normal Alarm for Flow Comparators,Average Power Range Monitor Flux Scram Trip Settings Found in Nonconservative Direction.Caused by Drifting Proportional Amplifiers.Settings Checked Daily ML20028B0421982-11-16016 November 1982 LER 82-049/01T-0:on 821102,main Steam Line Safety Valve a Set W/Nitrogen at Steam Relief Setting of 1240 Psig, Exceeding Tech Specs.Caused by Personnel Error.Set Valve Removed,Procedure Adherence Stressed & Procedure Revised ML20027C9801982-10-20020 October 1982 LER 82-039/03L-0:on 820920,timing Tests of Three Reactor Water Cleanup Isolation Valves 1201-2,-5 & -80 Not Completed within Allowed Time.Caused by Operational Constraints Requiring Testing at Reduced Power ML20027C9941982-10-20020 October 1982 LER 82-040/03L-0:on 820920,found Reactor Protection Sys Initiation Function of Turbine Stop Valve Completed 1 Day Late.Caused by Decision to Defer Test Due to MSIV D Line Isolation.Tracking Sys Implemented to Prevent Recurrences ML20052B9141982-04-23023 April 1982 LER 82-010/03L-0:on 820326,during Review of Testing Requirements,Surveillance Test 8.I.4 Standby Liquid Control Sys Found Not Verified.Caused by Breakdown in Multidiscipline Review of Results ML20052F2071982-04-14014 April 1982 Updated LER 81-060/03X-1:on 811020,determined Potential Exists to Reduce Number of Operable APRM & IRM Instrument Channels in Rod Block Trip Sys to Below Tech Spec Min ML20050A6321982-03-19019 March 1982 Updated LER 82-055/01T-1:on 810926,during Shutdown,Yarway Level Indicators Started Oscillating.Drywell Temp Was 240 F at 81-ft W/Elevation Coolant Temp 220 F.Caused by Ineffective Drywell Cooling.Ventilation Returned to Svc ML20050A4521982-03-19019 March 1982 LER 82-006/01T-0:on 820304,while Performing Maint Re SIL 352 on Pressure Adjustment Mechanism HPCI Stop Valve,Three Broken cap-screws Found.No Cause Determined.Screws Examined, Replaced & Sys Returned to Svc ML20050A4331982-03-19019 March 1982 Updated LER 81-062/01X-1:on 811116,Wyle Labs Informed Util That Two Target Rock Safety Relief Valves Had Not Passed Setpoint Tests.Caused by Setpoint Shift Due to Changes to Designed Differential Forces from Excessive Pilot Leakage 1993-07-28
[Table view] Category:RO)
MONTHYEARML20046C3131993-07-28028 July 1993 LER 93-015-00:on 930630,HPCI Sys Declared Inoperable Due to Indicated Flow During Surveillance.Caused by Foreign Matl That Plugged Portion of Restricting Orifice.Restricting Orifice Removed,Cleaned & reinstalled.W/930728 Ltr ML20046B5241993-07-26026 July 1993 LER 93-007-01:on 930317,automatic Closing of RCIC Sys Turbine Steam Supply Isolation Valves Occurred Due to High Steam Flow Signal.Increased Frequency of Valve Testing from Monthly to weekly.W/930726 Ltr ML20045F8601993-06-30030 June 1993 LER 93-014-00:on 930531,automatic Scram Occurred,Resulting from Operation of Auxiliary Transformer Differential Relay During Power Ascension.Uat Phase B & C Differential Relays Left Interchanged as Investigative aid.W/930630 Ltr ML20045E2301993-06-25025 June 1993 LER 93-013-00:on 930530,RCIC Sys Declared Inoperable & 7 Day TS 3.5.D.2 LCO Entered Due to Speed Oscillations Which Occurred After Several Minutes of steady-state Operation. Caused by Actuator Failure.Actuator replaced.W/930625 Ltr ML20045E2251993-06-25025 June 1993 LER 93-012-00:on 930529,unplanned PCIS Group I Isolation Signal Occurred While Opening MSIV During Startup,Resulting in Automatic Closing of Related Valves.Caused by Licensed Operator Error.Group 1 Isolation reset.W/930625 Ltr ML20045D6941993-06-23023 June 1993 LER 93-011-00:on 930525,determined That Initial as-found Popping Pressures of Pilot Valves for Three Target Rock Main Steam Relief Valves Out of TS Tolerance.Caused by Setpoint Drift.Valves Reworked & Reassembled by Target Rock Corp ML20045D1861993-06-18018 June 1993 LER 93-010-00:on 930519,SUT Became de-energized During Planned Calibr of Turbine/Generator Relays Lockout Test While Shut Down.Caused by Personnel Error.Discussion Conducted W/Personnel Re Attention to detail.W/930618 Ltr ML20044H0441993-06-0202 June 1993 LER 93-009-00:on 930504,circuit Breaker Did Not Close During Planned Bus Transfer Due to Loose Control Circuit Wire.Lug Replaced & Reterminated on 930505 & Post Work Testing Completed W/Satisfactory results.W/930602 Ltr ML20024G7451991-04-24024 April 1991 LER 91-005-00:on 910325,diesel Generator Inoperable,Causing Loss of Ac Power to Train B Components of Safety Sys & Actuating Portions of Primary/Secondary Containment Sys. Caused by Voltage Regulator failure.W/910424 Ltr ML20029A6721991-02-25025 February 1991 LER 91-001-00:on 910125,automatic Primary Containment Isolation Control Sys Group 5 Actuation Occurred,Resulting in Closing of RCIC Turbine Steam Supply Isolation Valves. Caused by High Flow conditions.W/910225 Ltr ML20028G9731990-09-20020 September 1990 LER 89-036-01:on 891122,determined That HPCI Sys Inoperable Due to Inoperable Gland Seal Condenser Blower Motor.Caused by age-related Wear of Motor.Blower Motor Replaced & Blower Tested W/Satisfactory results.W/900920 Ltr ML20028G9121990-09-18018 September 1990 LER 89-037-01:on 891130,primary Containment/Traversing in-core Probe Ball Valve Discovered to Be Almost Full Open. Caused by Damage to Valve Stem Due to Manual Manipulation of Stem.Ball Valve & Solenoid Actuator replaced.W/900918 Ltr ML20043G3541990-06-12012 June 1990 LER 90-008-00:on 900513,automatic Scram Resulting from Load Rejection Occurred While at Full Power,Resulting in Trip of Generator Field Breakers.Caused by Fault on Offsite 345 Kv Transmission sys.Loss-of-field Relay replaced.W/900612 Ltr ML20043F8291990-06-0606 June 1990 LER 90-007-00:on 900507,discovered That Drywell to Suppression Chamber Vacuum Breaker Surveillance Not Performed Prior to Startup in 1988.Caused by Misunderstanding of requirements.W/900606 Ltr ML20042F5911990-04-30030 April 1990 LER 90-006-00:on 900330,determined That Position of Primary Containment Sys Isolation Valve Not Recorded Daily,Per Tech Specs.Review Performed to Determine If Other Problems Existed.Plant Shut Down & Review performed.W/900430 Ltr ML20012F5751990-04-0606 April 1990 LER 90-003-00:on 900311,automatic Actuation of Main Steam Sys Group 1 Portion of Primary Containment Isolation Control Sys Occurred.Caused by False High Reactor Vessel Water Level Signal.Procedure Developed Re backfill.W/900406 Ltr ML20012E9831990-03-30030 March 1990 LER 90-002-00:on 900228,determined That Max Fraction of Limiting Power Density Not Checked Daily During Reactor Power Operation,Per Tech Spec 4.1.B.On 900323,addl Tech Spec Issue Discovered.Tech Specs changed.W/900330 Ltr ML20012C4871990-03-12012 March 1990 LER 90-001-00:on 900209,24 H Limiting Condition for Operation Entered When Two RCS Instrumentation Excess Flow Check Valves Inappropriately Verified Operable During Testing.Cause Undetermined.Two Valves replaced.W/900312 Ltr ML20005G0981990-01-0808 January 1990 LER 89-038-00:on 891208,unplanned Automatic Reactor Protection Sys Scram Signal & Reactor Scram Occurred.Caused by False Low Reactor Vessel Water Level Signal.Local Level Indicators Satisfactorily calibr.W/900108 Ltr ML20005F8481990-01-0808 January 1990 LER 89-039-00:on 891209,automatic Actuation of RHR Sys Portion of Primary Containment Isolation Control Sys Occurred.Caused by Hydrodynamic Transient That Actuated Protective High Pressure switches.W/900108 Ltr ML20005E8551989-12-30030 December 1989 LER 89-037-00:on 891130,discovered That Traversing in-core Probe Ball Valve,Mfg by Consolidated Controls,Inc,Closed,In Violation of Tech Specs.Caused by Damage to Valve Stem.Ball Valve & Actuator replaced.W/891230 Ltr ML20011D1361989-12-11011 December 1989 LER 89-035-00:on 891111,inadvertent Actuation of Portion of Secondary Containment Sys During Surveillance Testing Occurred.Caused by Location of Radiation Isolation Control Sys Channel a Logic Relay.Procedure revised.W/891211 Ltr ML20005D7421989-12-0606 December 1989 LER 89-033-00:on 891106,automatic Actuation of Group 1 Portion of Primary Containment Isolation Control Sys (PCIS) Occurred.Caused by High Reactor Vessel Water Level.Manual Valve Closed & PCIS Logic Circuitry reset.W/891206 Ltr ML19351A4581989-12-0606 December 1989 LER 89-034-00:on 891108,determined That Reactor Pressure Exceeded 150 Psig on 891107 W/O Performing Surveillance Procedure 8.5.4.4, HPCI Valve Operability Test. Caused by Personnel Error.Procedure initiated.W/891206 Ltr ML19332D1421989-11-22022 November 1989 LER 89-031-00:on 891024,closing Times for Two in-series Primary Containment Isolation Valves Exceeded Acceptance Criteria During Shutdown Testing.Cause Undetermined.Closing Time Retested W/Satisfactory results.W/891122 Ltr ML19332D6231989-11-20020 November 1989 LER 89-032-00:on 891020,pneumatic Pressure Drop for Two of Four Automatic Depressurization Sys Accumulators Discovered Greater than Max Acceptable Value.Caused by Leakage from Seat of Supply Check Valves.Seat replaced.W/891120 Ltr ML19324C3181989-11-0909 November 1989 LER 88-002-01:on 880117,full Reactor Protection Sys Scram Trip Signal Occurred During Surveillance Test,Resulting in Incomplete Actuations.Caused by Procedure Inadequacy.Logic Relay Replaced & Procedure revised.W/891109 Ltr ML19324B1131989-10-21021 October 1989 LER 89-030-00:on 890926,control Room High Efficiency Air Filtration Sys Flowrate non-conservative Due to Procedure Error.Caused by Transcription Error.Procedure Revised & Test Reperformed Using Corrected procedure.W/891021 Ltr ML19325D4681989-10-16016 October 1989 LER 89-029-00:on 890914,locked High Radiation Area Door Found to Have Been Unsecured Contrary to Tech Spec 6.13.2. Caused by Failure to Adhere to Approved Procedures. Training on Access Requirements initiated.W/891016 Ltr ML19325D1861989-10-10010 October 1989 LER 89-028-00:on 890907,HPCI Sys Declared Inoperable Because Mechanical Overspeed Trip Occurred During Surveillance Test. Caused by Failure of Ramp Generator Signal Converter Module. Module Removed & Sent to Mfg for exam.W/891010 Ltr ML17277B8221984-07-20020 July 1984 LER 82-049/01X-1:on 821102,main Steam Line Safety Valve a Set W/Nitrogen at Steam Relief Setting.Caused by Personnel Error.Valve Removed & Replaced W/Properly Set Spare Valve. Procedure revised.W/840720 Ltr ML20024C3231983-06-24024 June 1983 Updated LER 82-038/03X-1:on 820817,RCIC Steam Line High Differential Pressure Alarm Received.Caused by Air in Sensing Lines to Pressure Switches.Cross Threaded Cap Found on in-line Snubber.Snubber replaced.W/830624 Ltr ML20024C2211983-06-24024 June 1983 Updated LER 80-053/03X-1:on 800814,0907 & 14,HPCI Turbine Exhaust Line Snubber 23-3-36 Determined Inoperable.Caused by Transient Hydrodynamic Shock During Startup & Shutdown. Snubbers upgraded.W/830624 Ltr ML20024B8451983-06-24024 June 1983 LER 83-031/03L-0:on 830528,HPCI Sys Made Inoperable to Repair Steam Leak on AO 2301-31.Caused by Leaking Stem Packing.Packing Replaced.Valve Tested Satisfactorily.Sys Returned to svc.W/830624 Ltr ML20024B8321983-06-24024 June 1983 LER 83-030/03L-0:on 830527,both HPCI Area Smoke Detection Sys Alarmed in Main Control Room.Caused by Valve A02301-31 Steam Leak Causing False Indications.Valve repaired.W/830624 Ltr ML20024C3101983-06-21021 June 1983 Updated LER 79-007/03X-1:on 790212,while Performing Test 8.7.4.3,valves AO-5033A,CV-5065-10,15,16 & 17 Failed to Give Proper Position Indication When Cycled & to Close within Specified Tolerance.Cause Not stated.W/830621 Ltr ML20024A8861983-06-16016 June 1983 LER 83-027/03L-0:on 830518,during Routine Insp,Folding Fire Door Found Inoperable.Caused by Operating Cable Becoming Detached from Pulley Due to Slack.Cable Reattached & Operating Mechanism adjusted.W/830616 Ltr ML20023D1691983-05-0909 May 1983 Updated LER 82-008/01X-1:on 820331,HPCI Injection Valve MO-2301-8 Failed to Open in Required Manner.Caused by Missing Wire Jumper Intended to Bypass Motor Operator Torque Switch.Jumper Installed & Valve Tested Satisfactorily ML20023D0671983-05-0909 May 1983 LER 83-021/03L-0:on 830411,during Surveillance Test 8.7.4.3, Primary Containment Isolation Valve AO-5033B Failed to Meet 10-s Closing Time Requirements.Caused by Lubricant Infiltrating Solenoid Valve Components.Components Replaced ML20023D0181983-05-0404 May 1983 LER 83-022/03L-0:on 830413,overload on Valve Motor 1301-17 Resulted in Loss of High Pressure Core Cooling Backup Capability.Caused by Oxidation in Motor End Bell & Motor Brushes,Due to Humidity Caused by Leaking Valve Packing ML20028G1591983-01-28028 January 1983 LER 83-002/01T-0:on 830116,flow Ref off-normal Alarm Received.Average Power Range Monitor Flux Scram Trip Settings Affected.Cause Under Investigation.Flow Inputs Monitored & Amplifier B Recalibr ML20028F4121983-01-17017 January 1983 LER 83-002/01X-0:on 830116,while Clearing off-normal Alarm for Flow Comparators,Average Power Range Monitor Flux Scram Trip Settings Found in Nonconservative Direction.Caused by Drifting Proportional Amplifiers.Settings Checked Daily ML20028B0421982-11-16016 November 1982 LER 82-049/01T-0:on 821102,main Steam Line Safety Valve a Set W/Nitrogen at Steam Relief Setting of 1240 Psig, Exceeding Tech Specs.Caused by Personnel Error.Set Valve Removed,Procedure Adherence Stressed & Procedure Revised ML20027C9801982-10-20020 October 1982 LER 82-039/03L-0:on 820920,timing Tests of Three Reactor Water Cleanup Isolation Valves 1201-2,-5 & -80 Not Completed within Allowed Time.Caused by Operational Constraints Requiring Testing at Reduced Power ML20027C9941982-10-20020 October 1982 LER 82-040/03L-0:on 820920,found Reactor Protection Sys Initiation Function of Turbine Stop Valve Completed 1 Day Late.Caused by Decision to Defer Test Due to MSIV D Line Isolation.Tracking Sys Implemented to Prevent Recurrences ML20052B9141982-04-23023 April 1982 LER 82-010/03L-0:on 820326,during Review of Testing Requirements,Surveillance Test 8.I.4 Standby Liquid Control Sys Found Not Verified.Caused by Breakdown in Multidiscipline Review of Results ML20052F2071982-04-14014 April 1982 Updated LER 81-060/03X-1:on 811020,determined Potential Exists to Reduce Number of Operable APRM & IRM Instrument Channels in Rod Block Trip Sys to Below Tech Spec Min ML20050A6321982-03-19019 March 1982 Updated LER 82-055/01T-1:on 810926,during Shutdown,Yarway Level Indicators Started Oscillating.Drywell Temp Was 240 F at 81-ft W/Elevation Coolant Temp 220 F.Caused by Ineffective Drywell Cooling.Ventilation Returned to Svc ML20050A4521982-03-19019 March 1982 LER 82-006/01T-0:on 820304,while Performing Maint Re SIL 352 on Pressure Adjustment Mechanism HPCI Stop Valve,Three Broken cap-screws Found.No Cause Determined.Screws Examined, Replaced & Sys Returned to Svc ML20050A4331982-03-19019 March 1982 Updated LER 81-062/01X-1:on 811116,Wyle Labs Informed Util That Two Target Rock Safety Relief Valves Had Not Passed Setpoint Tests.Caused by Setpoint Shift Due to Changes to Designed Differential Forces from Excessive Pilot Leakage 1993-07-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
Text
"
' 1*f 10 CFR 50.73 sosn.-
Pilgnm Nuclear Pour station Rocky Hill Road Plymouth, Massachusetts 02360 Ralph G. Bird senior Vice President - Nuclear September 20, 1990 BECo Ltr.90-111 U.S. Nuclear Regulatory Commission Attn: Document Control Desk
'i4ashington, D.C. 20555 Docket No. 50-293 License No. DPR
Dear Sir:
The enclosed supplemental Licensee Event Report (LER) 89-036-01, "High Pressure Coolant Injection System Inoperable Due to Inoperable Gland Seal Condenser Blower Motor", is submitted in accordance with 10 CFR Part 50.73.
Please do not hesitate to contact me if there are any questions regarding this report.
,E M R. G. ird TM/bal
Enclosure:
LER 89-036-01 cc:. Mr. Thomas T. Martin Regional Administrator, Region I
'U.S. Nuclear Regulatory Commission 475 Allendale Rd.-
King of Prussia, PA 19406 Sr. NRC Resident Inspector - Pilgrim Station Standard BECo LER Distribution gibN 90100$bO21 900920 )h
{DR ADOCK0500g3 1522-
!)
esRC F.em act u $ NUCLEL3 6.t.utatomy COMMetteON f t PPRoytD OMB NO. 3100 tim LICENSEE EVENT REPORT (LER) ' " a"8 5 ' '8' '"
- ACILity hAut ni Docatt NUMeth (21 FADI G Pilgrim Nuclear Power Station 0l5l0l0lo1 2l 9 l3 1 loFl 0l 4 High Pressure Coolant Injection System Inoperable Due to Inoperable Gland Seal :
Condenser Blower Motor lytNT Datt (Si LE R NUMet h iti REPORT DAtt til 0?ME R F ACILitsts sNVOLVED tSi MONin DAY vlAR vlAR "$giU '" . 7,$ MONTH DAY DEAR Facite? v hawls DOCLt t NUM6thtSI N/A 015l0l0l0; g l 8 9 N/A 1l1 2l2 8l 9 0 l 3l6 0l 1 0l9 2 l0 9l0 0l5l0 toio l l
,,,,,,,,,, inis AtPont is suouiteto Pursuant to tut RioviReutNis of 10 CFR 6 rC=a eae ., .r es ,en .,i on MOOR m 70 402th) 20 4051e1 E73teH2 Hew) 73.?1ttl 70 406(sinHd to M(eHil
_ _ { D0.736sH2tle) (D) _
73.716sl
- ! =0 .o.i.in He mMi. uni noi
.On.H H m
_ gugg;.,Ag ma,
,0 0,H.in H.i un.Heii. .n.iu. .nAi 20 406teH1Hav) 80.73:e HtH.I 90.736eH2HrsalHBl 20 4066aH1Het 50.73taH2Hehl 50.731aH2ptal LICEN5it CDNtact FOR iMit LIR lif t Navt itLEPHONE NUM6tm Thomas F. McElhinney - Senior Compliance Engineer 5 7 4 7l- 84 i 6l 5 ;
COMPLlit ONE LINI FOR L Ach CC4ePONtNT FalLURt Ditchist0 IN THIS RtPont Ital C. REP ' ' C- R ORtA 5
$v$ttM f CAU$t COMPONt N T O PR 4 CAult Sv8 TEM COMP 0Nt NT "h kpp g X B;J g iMi o G,0 l8,0 Y , i i ; l , i l I I I I I I I I I I I I I SurettMENT AL REPORT EXPECitD (145 MONTH DAY vtAR t t $ I,9 y.e, s.*npwre t h9tCtf p gugstt$$10N DA tti kO l l l ---
A.m Act ,u-, , . . , . . . ~,.4 ,. ... -. ,,, ,,, , , n .,
On November 22, 1989 at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, the High Pressure Coolant Injection (HPCI)
System was declared inoperable and a seven day Technical Specification (3.5.C.2)
Limiting Condition for Operation (LCO) was entered at that time.
The system was declared inoperable because the HPCI System turbine gland seal condenser blower motor did not start when the blower's control switch was moved to the START position in accordance with procedure. The blower motor did not start because of worn motor brushes, which resulted from motor shaft play. The motor shaft play was due-to age-related wear of the motor. The blower motor, installed during original construction (circa 1970), was manufactured by the General Electric Company and is a 250-VDC motor, model number 5BCJ56EA58.
The blower motor was replaced and the blower Las subsequently tested with s6tisfactory results. The HPCI System was declared operable on November 26, 1989 at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br />. The preventive maintenance program has been modified to include periodic brush replacement for the HPCI blower motor and for other motors used in similar applications.
This event occurred during power operation with the reactor mode selector switch in the RUN position. The reactor power level was 94 percent. The Reactor Vessel (RV) pressure was 1024 psig with the RV water temperature at 547 degrees Fahrenheit.
This report is submitted in accordance with 10 CFR 50.73(a)(2)(v)(D) and this ev a t posed no threat to the public health and safety.
]$'T_" _ -
l
]
mace asoa y a scucttaz tatutittav cowuission UCENSEE EVENT REPORT (LER) TEXT CONTINUATION ee=ovlo owe wo 3m-oio.
(KPih15. S'3i W 94clLif t OsatAL fil DOCEST NutIDin (24 Llh NUM$lm 16) PAGE (Si
- iaa " 2 M." 74*.D 1 Pilgrim Nuclear Power Station 0 6 l0 l0 l0 h l9l 3 81 9 0 l3 l 6 -
011 Ol 2 UF 0 I 4.
REASON FOR SUPPLEMENT This supplement meets the previous commitment to identify the results of the investigation regarding the wear of the HPCI System turbine gland seal condenter blower motor brush. The investigation had not been completed when the initial report was submitted.
l EVENT DESCRIPTION On November 22, 1989 at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, the High Pressure Coolant Injection (HPCI) f System was declared inoperable and a seven day Technical Specification (3.5.C.2)
Limiting Condition for Operation (LCO) was entered. The HPCI System was declared inoperable because the HPCI System turbine gland seal condenser (GSC) blower did not start when its control switch was moved to the START position.
Prior to the event, the Control Room Panel C-903C alarm, "HPCI Turbine Exhaust Hi Drain Pot Level", annunciated. In accordance with Alarm Response Procedure ARP-903C (Rev. 2), the GSC blower (P-223) was to be started and run until the alarm cleared. However, the alarm did not clear after the blower's control switch was moved to the START position. Subsequent investigation revealed that the alarm did not clear because the condensate level in the GSC was not lowered. The HPCI System was conservatively declared inoperable in accorjance with the Administrative Limits of procedure 2.2.21 (Rev. 35), "(HPCI) System", for an inoperable GSC.
Failure and Halfunction Report 89-453 was written to document the event. The NRC Operations Center was notified as required by 10 CFR 50.72 on November 22, 1989 at 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br />.
This event occurred during power operation with the reactor mode selector switch in L the RUN position. The reactor power level was approximately 94 percent. The Reactor Vessel (RV) pressure was approximately 1024 psig with the RV water ]
temperature at approximately 547 degrees Fahrenheit.
CAUSE
- The GSC blower motor did not start when the blower's control switch was moved to the START position because of N rn motor brushes. Following replacement of the GSC.
blower motor, a visual inspect. a revealed that both of the motor brushes were worn with one brush worn considerably more than'the other brush. The wear exhibited by the brushes resulted from motor shaft play. The GSC motor was installed during l
original construction (circa 1970). The motor manufacturer was contacted regarding
'the as-found conditions, and indicated that the motor shaft play was due to ,
age-related wear of the motor. The GSC blower motor was manufactured by the !
L General Electric Company and is a 250 VDC motor, model number SBCJ56EA58. !
l l
l L
3"Z,' "* "" _ _ _ _ _ _-
es8tC 9ere atta y & ttVCLEa3 ELSULt. TORY COMMitel00s LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Aa*=ono owa no mo-em
. Ex>tRts t'3 Pas eacitetv haMt tu Docet,t ouvMe,R Lil Lth Nuutta it> tact tai vs*- " W P." "'A*.70 Pilgrito Nuclear Power Station o 16 l0 l0 lo l2 l 9l3 8l 9 -
0]3l6 -
0l1 0l3 or 0l4 tm . ., . ,, - c, - .,nn CORRECTIVE ACTION The HPCI System GSC blower (P-223) motor was replaced and the blower was tested with satisfactory results. For the blower motor replacement, the HPCI System turbine steam supply valve (MO-2301-3) was closed and de-energized, and the control switch for the auxiliary oil pump was placed in the pull-to-lock position. Post work testing of the GSC blower was completed with satisfactory results on November 26, 1989 at approximately 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br />. The HPCI System was restored to normal standby service and declared operable on November 26, 1989 at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> and the seven day LCO was terminated at that time.
The preventive mairitenance program was modified to include the HPCI System GSC blower (P-223) motor itnd condensate pump (P-220) motor, and the RCIC System barometric tondenser vacuum pump (P-222) motor and condensate pump (P-221) motor.
Initially, ti.e brushes for these motors will be replaced on a once-per-refueling outage frequency. The frequency may be changed in accordance with preventive maintenance prog.am procedure 3.M.1-1, " Preventive Maintenance".
An Engineering Service Request (ESR 89-881) was written to determine the nud to declare the HPCI System turbine GSC inoperable due to an inoperable GSC blower.
This item is under investigation.
During the period that the HPCI System was inoperabic, appropriate LC0 testing was conducted in accordance with Procedure 8.5.4.5 (Rev. 6), "HPCI System Inoperable".
The procedure includes operability testing of the Reactor Core Isolation Cooling
-(RCIC). System, Automatic Depressurization System (ADS), Core Spray System (CSS),
and the Low Pressure Coolant Injection (LPCI) mode of the Residual Heat Removal (RHR) System.
SAFETY CONSEOUENCES This event posed no threat to the public health and safety.
The HPCI System GSC blower (P-223) is controlled manually or automatically, and is normally in standby service with its control switch in the AUTOMATIC position.
Routine operability testing of the HPCI System is conducted in accordance with the surveillance program. The testing is performed in accordance with procedures that include procedure 8.5.4.1, "(HPCI) System Pump and Valve Monthly / Quarterly Operability". The procedure includes operating the GSC blower during the test.
The function and control of the Reactor Core Isolation Cooling (RCIC) System barometric condenser vacuum pump (P-222) is similar to the HPCI System GSC blower (P-223). Routine operability testing of the RCIC System is similar to the HPCI System and is performed in accordance with procedures that include procedure 8.5.5.1, "RCIC Pump Operability Flow Rate and Valve Test at 1000 PSIG". The procedure includes operating the barometric condenser vacuum pump (P-222) during toe test.
1 gn,cy.. .
~
ui =Uettaa mutaionv co .o.,
7,cja =**
. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION = =ovio ove no m o-cio.
l-
- ActLily namt tu pocag, ngugtm tai Pact tai Llh NUMelR tGI
"*a " Me" M*.t:
Pilgrim Nuclear Power Station 015 l0 lo l0 l2 l 9l3 8[ 9 -
0l3l 6 -
0l1 0l4 oF 0 l4 nnw m e.,.e m ucwmuerun The LCO testing performed while the HPCI System was inoperable included operability testing of the RCIC System, ADS, CSS, and the RHR System /LPCI mode. The RCIC System was capable of providing high pressure cooling water to the Reactor Vessel while the HPCI System was inoperable. In the unlikely event that a RCIC System failure were to occur when its operation was needed while the HPCI System was inoperable, an automatic (or manual) actuation of the ADS would reduce the Reactor Vessel pressure for low pressure cooling provided independently by the CSS and RHkS/LPCI mode.
This report is submitted in accordance with 10 CFR 50.73(a)(2)(v)(D) because the HPCI System was declared inoperable.
SIMILARITY TO PREVIOUS EVENTS A review was conducted of Pilgrim Station Licensee Event Reports (LERs) submitted since January 1984. The review focused on LERs submitted in accordance with 10 CFR 50.73(a)(2)(v) that involved the HPCI System turbine GSC blower or GSC condensate pump. The review identified a similar problem with the HPCI System turbine GSC blower motor brushes that was reported in LER 50-293/89-025-00.
For LER 89-025-00, the HPCI System was declared inoperable on August 5, 1989 while operating at 50 percent reactor power. The system was declared inoperable because the HPCI System turbine GSC blower did not start when the blower's control switch was moved to the START position in accordance with procedure. The cause was normal age-related wear of the GSC blower motor brushes. The motor brushes were replaced. In retrospect, the motor shaf t play identified in this LER may have been a contributing cause to the August 5, 1989 event.
ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) CODES The EIIS codes for this report are as follows:
COMPONENTS CODES Alarm, Level LA Blower (P-223) BLO Motor M0 Condenser (Gland Seal Condenser) COND SYSTEMS Core Spray System (CSS) BM High Pressure Coolant Injection (HPCI) System BJ Integrated Control System (ADS) JA Panels System (C-903) JL Reactor Core Isolation Cooling (RCIC) System BN Residual Heat Removal (RHR) System B0 gag.o . .
mm