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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045E9961993-07-0101 July 1993 LER 93-012-00:on 930607,discovered That Surveillance Test on Fire Protection Sys Missed on 930601.Caused by Insufficient Degree of Attention Applied by Nonlicensed Individual.Test Satisfactorily completed.W/930701 Ltr ML20045E8661993-06-25025 June 1993 LER 93-011-00:on 930528,TS Violation Occurred When New Fuel Was Added to EDG Fuel Oil Storage Tank Prior to Completion of Chemical Analysis.Caused by Personnel Error.Individual counselled.W/930625 Ltr ML20044E7351993-05-20020 May 1993 LER 93-010-00:on 930425,noticed That Wide Range Reactor Level Indications Associated w/2A Condensing Chamber Drifted High than Level Instruments Associated w/2B Condensing Chamber.Caused by Level Instrument leaking.W/930520 Ltr ML20044E7341993-05-20020 May 1993 LER 93-008-00:on 930409,Tech Spec Violation Occurred.Caused by Setpoint Drift of Pressure Switch in Conjunction W/Less than Adequate Communication.Event Discussed W/Involved individuals.W/930520 Ltr ML20044E7381993-05-20020 May 1993 LER 93-009-00:on 930422,discovered Containment Sump Pump Collection & Flow Data Not Recorded in Surveillance Test. Caused by Personnel Error.Event Discussed W/Involved individuals.W/930520 Ltr ML20024G7391991-04-24024 April 1991 LER 91-004-00:on 910324,reactor Operator Failed to Initial Surveillance Test 5.3, Inoperable Valve Position Daily Log. Caused by Personnel Error Due to Failure to Follow Procedure.Operator counselled.W/910424 Ltr ML20028H3461990-12-10010 December 1990 Corrected LER 90-033-00:on 901108,discovered TS Limiting Condition of Operation Not Entered for Inoperable Containment Isolation Valve Due to Procedural Deficiency ML20044A6741990-06-25025 June 1990 LER 89-028-01:on 891108,determined That Standby Gas Treatment Sys Heater Control Relays Installed W/O Environ Qualification.Caused by Lack of Procedural Guidance.Relays relocated.W/900625 Ltr ML20043G8761990-06-14014 June 1990 LER 90-012-00:on 890815,discovered Valves Left Closed After Removal of Blocking Permit & on 890813,emergency Cooling Water Pump & Emergency Diesel Generator Removed from Svc. Caused by Inadequate procedures.W/900614 Ltr ML20043G0821990-06-11011 June 1990 LER 90-006-00:on 900511,blown Fuse from Battery Charger 3B Resulted in Declaring HPCI Sys,Core Spray B Logic,Rhr B Logic,Core Spray Subsystem B,Rhr Subsystem B & E2 & E4 Emergency Diesel Generators inoperable.W/900611 Ltr ML20043D7291990-06-0505 June 1990 LER 90-005-00:on 900507,Group 2A Primary Containment Isolation Sys Isolation Occurred During Surveillance Test. Caused by Inadequate Worker Practices.Blown Fuse Replaced & Personnel counseled.W/900605 Ltr ML20043D7211990-06-0404 June 1990 LER 90-011-00:on 900503,discovered That Tech Spec 3.4.1 Not Performed on 6-wk Frequency as Required.Caused by Personnel Error.Tracking of Surveillance Activities Scheduled to Be Transferred to Improved Software package.W/900604 Ltr ML20043C5921990-05-31031 May 1990 LER 90-010-00:on 900502,three Control Room Emergency Ventilation Actuations Occurred.Caused by Poor Electrical Continuity as Result of Oxidation Between plug-in Circuit Boards & Mating Electrical connections.W/900531 Ltr ML20043C5781990-05-30030 May 1990 LER 90-004-00:on 900430,Tech Spec Violation Occurred When MSIV Closure Timing Testing Not Performed in Required Surveillance Interval.Caused by Ambiguous Test Procedure. Surveillance Test revised.W/900530 Ltr ML20043C5721990-05-30030 May 1990 LER 90-009-00:on 900430,discovered That Rod Block Monitor Not Been Proven Operable Prior to Exceeding 30% Power as Required by Tech Specs.Caused by Programmatic Deficiency. General Plant Procedures revised.W/900530 Ltr ML20043A4691990-05-16016 May 1990 LER 90-008-00:on 900417,discovered That Testing of LPCI Pumps & Core Spray Subsystems Not Performed When LPCI Pump D Declared Inoperable on 900414.Caused by Personnel Error. Procedures Declaring Pump Inoperable revised.W/900516 Ltr ML20043A7831990-05-14014 May 1990 LER 90-007-00:on 900412,evaluation Involving Seismic Qualification Performed Due to Postulated Failure of Condensate & Vacuum Pumps During Design Seismic Events. Caused by Design Oversight.Program updated.W/900514 Ltr ML20042F9581990-05-0707 May 1990 LER 90-001-01:on 900124,shift Surveillance Log Did Not Meet Requirements of Tech Specs.Caused by Deficient Procedure. Surveillance Log Revised to Include Daily Instrument Check. W/900507 Ltr ML20042F3211990-05-0202 May 1990 LER 90-006-00:on 900402,actuation of Emergency Diesel Generator Occurred.Caused by Personnel Miscommunication. Shift Mgt Will Be Reminded of Necessity to Control Activities in Control room.W/900502 Ltr ML20042E9811990-04-30030 April 1990 LER 90-002-01:on 900128,ESF Sys Actuations Occurred Due to Reactor Vessel Level Fluctuations After Manual Scram.Caused by Failure of O-ring on Fluid Inlet Port to Servo Valve for Hydraulically Operated Valve.Valve replaced.W/900430 Ltr ML20042E9101990-04-27027 April 1990 LER 90-005-00:on 900326,Tech Spec Surveillance Not Performed within Required Interval.Caused by Personnel Error.Personnel Counseled & Will Periodically Review Omitted Test Rept to Ensure Performance of Surveillance tests.W/900427 Ltr ML20042E6801990-04-23023 April 1990 LER 89-031-01:on 891206 & 900105,Agastat Relays Found Not Properly Secured by Seismic Support Straps.Caused by Inadequate Installation or Reinstallation of Seismic Straps. Straps Properly reconnected.W/900423 Ltr ML20042E6821990-04-19019 April 1990 LER 90-004-00:on 900321,discovered Potentially Inoperable Safety Sys Due to Inadequate Emergency Svc Water Cooling Flow Through Room Coolers.Caused by Gradual Buildup of Corrosion & Silt.Mod completed.W/900419 Ltr ML20012C4831990-03-12012 March 1990 LER 89-029-01:on 891117,primary Containment Isolation Sys Actuation Occurred During Performance of Refueling Floor Ventilation Exhaust Radiation Monitor Testing.Cause Unknown. Selector Switch & Relay Contacts cleaned.W/900312 Ltr ML20012C4821990-03-12012 March 1990 LER 89-024-01:on 891006,local Power Range Monitor Spike Caused Reactor Scram Signal While in Hot Shutdown.Caused by Design &/Or Mfg Process as Identified by Ge.Detector Placed in Bypass Position & Scram Signal reset.W/900312 Ltr ML20012A0171990-02-23023 February 1990 LER 90-002-00:on 900128,reactor Manually Scrammed Due to Leak of Electrohydraulic Control Sys Fluid.Caused by Lock Nut on Interlock Dump Valve Setting Adjustment Bolt Becoming Unsecured Due to Sys Vibration.Leak stopped.W/900223 Ltr ML20012A0021990-02-23023 February 1990 LER 90-001-00:on 900124,discovered That Daily Instrument Check of Main Stack Flow Rate Monitor Not Performed.Caused by Incomplete Procedure.Operating Shift Surveillance Log Revised to Include Daily Instrument check.W/900223 Ltr ML20012A0841990-02-0707 February 1990 LER 90-001-00:on 900108,HPCI Sys Declared Inoperable During Surveillance Testing When Start Time Exceeded 25 S.Caused by Inadequate Calibr Procedure Which Allowed Setting of 18 S. Ramp Generator & Signal Converter replaced.W/900207 Ltr ML20011F5791990-02-0707 February 1990 LER 89-007-01:on 890411,green Discoloration Discovered in Grease on Stabs of Several Control Fuses in 4 Kv Switchgear. Probably Caused by Incomplete Procedure.Maint Procedure M-054.004 Revised to Include Fuse insp.W/900207 Ltr ML20006A9621990-01-19019 January 1990 LER 89-033-00:on 891220,full Scram Signal Received When Technician Performed Surveillance on APRM D.Caused by Procedural Deficiencies & Inattention to Detail by Technician.Technician counseled.W/900119 Ltr ML19354E0121990-01-17017 January 1990 LER 89-032-00:on 891218,discovered That Weekly Surveillance Test Not Performed within Surveillance Interval.Caused by Inappropriate Action Based on Failure to Follow Procedure. Surveillance Test Coordinator counseled.W/900117 Ltr ML19354E0091990-01-16016 January 1990 LER 89-011-00:on 891213,discovered That Two Surveillance Tests of Turbine Stop & Control Valve Encl Not Performed Per Tech Specs.Caused by Incorrect Std Practice of Surveillance Testing.Programmatic Controls established.W/900116 Ltr ML19354E0101990-01-16016 January 1990 LER 89-015-01:on 890721,while Attempting to Remove Malfunctioning Reactor Pressure Vessel Regulator Set,Bypass & Control Valves Opened,Causing Steam Line Pressure to Increase to 480 Psig.Components replaced.W/900116 Ltr ML19354E0851990-01-11011 January 1990 LER 89-010-00:on 891211,monthly Surveillance Test ST 9.7 Not Performed within Surveillance Interval Established by Tech Spec Table 4.1.1.Caused by Combination of Programmatic Weaknesses.Review performed.W/900111 Ltr ML20005G2451990-01-11011 January 1990 LER 89-016-01:on 890720 & 22,LPRM Detector 4B-40-33 Spiked High,Resulting in Full Reactor Scram Signal While in Cold Shutdown.Caused by Design/Mfg Defect in GE Detector. Detector Placed in Bypass position.W/900111 Ltr ML20005G1901990-01-0808 January 1990 LER 89-009-00:on 891207,HPCI Sys Declared Inoperable When Sys Failed to Start During Pump,Valve & Flow Surveillance Test.Caused by Loose Lock Nut on HPCI Oil Sys Relief Valve. Lead Seal Wire to Be Placed on Valve caps.W/900108 Ltr ML20005F8711990-01-0505 January 1990 LER 89-031-00:on 891206,discovered That Four Agastat Relays Not Properly Secured by Seismic Support Straps.Root Cause Under Investigation & Will Be Reported in Rev to Ler.Support Straps Promptly reconnected.W/900105 Ltr ML20005E3911989-12-26026 December 1989 LER 89-030-00:0n 891126,steam Leak Discovered Coming from Packing on RCIC Injection Check Valve AO-22.Caused by Failure of Valve Stem Packing.Normal Reactor Level Restored & Mods of Valve Will Be pursued.W/891226 Ltr ML20011D2331989-12-18018 December 1989 LER 89-029-00:on 891117,Group III Primary Containment Isolation Sys Actuation Occurred During Refueling Floor Ventilation Exhaust Radiation Monitor Testing.Cause Unknown. Test Procedure to Be revised.W/891218 Ltr ML19332E7081989-12-0606 December 1989 LER 89-028-00:on 891108,review Determined That Standby Gas Treatment Sys Heater Control Relays Unqualified for post-LOCA Radiation Environ & Declared Inoperable.Cause Undetermined.Radiation Shielding installed.W/891206 Ltr ML19332E6331989-11-27027 November 1989 LER 89-007-00:on 891026,reactor Vessel Temp & Reactor Coolant Pressure Not Logged Every 15 Minutes as Required by Tech Spec 4.6.A.2 During Performance Integrated Leak Rate Testing.Caused by Procedure deficiency.W/891127 Ltr ML19332E7591989-11-27027 November 1989 LER 89-008-00:on 891027,primary Containment Isolation Sys Group II & III Isolations Occurred When Spurious Reactor Low Level Signal Sensed by Instruments.Possibly Caused by Air Bubble in Sensing Lines.Line backfilled.W/891127 Ltr ML19332D3401989-11-22022 November 1989 LER 89-006-00:on 891023,during Reactor Temp Adjustment, Reactor High Pressure Scram Occurred.Caused by Improper Planning & Coordination of Multiple Evolutions.Surveillance & Hydrostatic Test revised.W/891122 Ltr ML19332C4931989-11-20020 November 1989 LER 89-005-00:on 891020,reactor Protection Sys Actuation & Primary Containment Isolation Sys Actuation Occurred Due to False High Reactor Pressure Signal & lo-lo Reactor Vessel Level Signal,Respectively.Caused by spike.W/891120 Ltr ML19332C8191989-11-15015 November 1989 LER 89-027-00:on 891016,observation & Logging of Suppression Pool Temp as Required by Tech Spec 4.7.2 Not Met.Caused by Personnel Error.Operations Shift Team counseled.W/891115 Ltr ML19324C4361989-11-0808 November 1989 LER 89-026-00:on 891012,control Room Emergency Ventilation Sys Actuation Occurred Due to Momentary False High Radiation Signal from Control Room Radiation Monitor B.Caused by Sensitivity of Thumbwheel switch.W/891108 Ltr ML19324C1781989-11-0606 November 1989 LER 89-023-00:on 891005,outboard MSIV Ac Solenoid Pilot Valves de-energized,resulting in Expected Closure of Outboard MSIV D & Automatic Reactor Scram.Caused by Incomplete Guidance.Procedure revised.W/891106 Ltr ML19325F1801989-11-0606 November 1989 LER 89-024-00:on 891006,reactor Protection Sys Initiated Full Reactor Scram Signal.Caused by Output Signal for LPRM 40-33A Spiking High.Lprm Detector Placed in Bypass Position & Scram Signal reset.W/891106 Ltr ML19325F1811989-11-0202 November 1989 LER 89-022-00:on 891003,unterminated Lead in Circuit to HPCI Trip Solenoid Rendered HPCI Stop Valve Trip Functions Inoperable.Caused by Leads Loosely Hanging Inside Door Panel.Hanging Leads Secured & Panel inspected.W/891102 Ltr ML19325F1791989-11-0202 November 1989 LER 89-025-00:on 891007,determined That nonsafety-related Bellows Leak Detecting Pressure Switches Installed on Main Steam Relief Valves Could Prevent Opening During Design Basis Condition.Plant Alteration installed.W/891102 Ltr 1993-07-01
[Table view] Category:RO)
MONTHYEARML20045E9961993-07-0101 July 1993 LER 93-012-00:on 930607,discovered That Surveillance Test on Fire Protection Sys Missed on 930601.Caused by Insufficient Degree of Attention Applied by Nonlicensed Individual.Test Satisfactorily completed.W/930701 Ltr ML20045E8661993-06-25025 June 1993 LER 93-011-00:on 930528,TS Violation Occurred When New Fuel Was Added to EDG Fuel Oil Storage Tank Prior to Completion of Chemical Analysis.Caused by Personnel Error.Individual counselled.W/930625 Ltr ML20044E7351993-05-20020 May 1993 LER 93-010-00:on 930425,noticed That Wide Range Reactor Level Indications Associated w/2A Condensing Chamber Drifted High than Level Instruments Associated w/2B Condensing Chamber.Caused by Level Instrument leaking.W/930520 Ltr ML20044E7341993-05-20020 May 1993 LER 93-008-00:on 930409,Tech Spec Violation Occurred.Caused by Setpoint Drift of Pressure Switch in Conjunction W/Less than Adequate Communication.Event Discussed W/Involved individuals.W/930520 Ltr ML20044E7381993-05-20020 May 1993 LER 93-009-00:on 930422,discovered Containment Sump Pump Collection & Flow Data Not Recorded in Surveillance Test. Caused by Personnel Error.Event Discussed W/Involved individuals.W/930520 Ltr ML20024G7391991-04-24024 April 1991 LER 91-004-00:on 910324,reactor Operator Failed to Initial Surveillance Test 5.3, Inoperable Valve Position Daily Log. Caused by Personnel Error Due to Failure to Follow Procedure.Operator counselled.W/910424 Ltr ML20028H3461990-12-10010 December 1990 Corrected LER 90-033-00:on 901108,discovered TS Limiting Condition of Operation Not Entered for Inoperable Containment Isolation Valve Due to Procedural Deficiency ML20044A6741990-06-25025 June 1990 LER 89-028-01:on 891108,determined That Standby Gas Treatment Sys Heater Control Relays Installed W/O Environ Qualification.Caused by Lack of Procedural Guidance.Relays relocated.W/900625 Ltr ML20043G8761990-06-14014 June 1990 LER 90-012-00:on 890815,discovered Valves Left Closed After Removal of Blocking Permit & on 890813,emergency Cooling Water Pump & Emergency Diesel Generator Removed from Svc. Caused by Inadequate procedures.W/900614 Ltr ML20043G0821990-06-11011 June 1990 LER 90-006-00:on 900511,blown Fuse from Battery Charger 3B Resulted in Declaring HPCI Sys,Core Spray B Logic,Rhr B Logic,Core Spray Subsystem B,Rhr Subsystem B & E2 & E4 Emergency Diesel Generators inoperable.W/900611 Ltr ML20043D7291990-06-0505 June 1990 LER 90-005-00:on 900507,Group 2A Primary Containment Isolation Sys Isolation Occurred During Surveillance Test. Caused by Inadequate Worker Practices.Blown Fuse Replaced & Personnel counseled.W/900605 Ltr ML20043D7211990-06-0404 June 1990 LER 90-011-00:on 900503,discovered That Tech Spec 3.4.1 Not Performed on 6-wk Frequency as Required.Caused by Personnel Error.Tracking of Surveillance Activities Scheduled to Be Transferred to Improved Software package.W/900604 Ltr ML20043C5921990-05-31031 May 1990 LER 90-010-00:on 900502,three Control Room Emergency Ventilation Actuations Occurred.Caused by Poor Electrical Continuity as Result of Oxidation Between plug-in Circuit Boards & Mating Electrical connections.W/900531 Ltr ML20043C5781990-05-30030 May 1990 LER 90-004-00:on 900430,Tech Spec Violation Occurred When MSIV Closure Timing Testing Not Performed in Required Surveillance Interval.Caused by Ambiguous Test Procedure. Surveillance Test revised.W/900530 Ltr ML20043C5721990-05-30030 May 1990 LER 90-009-00:on 900430,discovered That Rod Block Monitor Not Been Proven Operable Prior to Exceeding 30% Power as Required by Tech Specs.Caused by Programmatic Deficiency. General Plant Procedures revised.W/900530 Ltr ML20043A4691990-05-16016 May 1990 LER 90-008-00:on 900417,discovered That Testing of LPCI Pumps & Core Spray Subsystems Not Performed When LPCI Pump D Declared Inoperable on 900414.Caused by Personnel Error. Procedures Declaring Pump Inoperable revised.W/900516 Ltr ML20043A7831990-05-14014 May 1990 LER 90-007-00:on 900412,evaluation Involving Seismic Qualification Performed Due to Postulated Failure of Condensate & Vacuum Pumps During Design Seismic Events. Caused by Design Oversight.Program updated.W/900514 Ltr ML20042F9581990-05-0707 May 1990 LER 90-001-01:on 900124,shift Surveillance Log Did Not Meet Requirements of Tech Specs.Caused by Deficient Procedure. Surveillance Log Revised to Include Daily Instrument Check. W/900507 Ltr ML20042F3211990-05-0202 May 1990 LER 90-006-00:on 900402,actuation of Emergency Diesel Generator Occurred.Caused by Personnel Miscommunication. Shift Mgt Will Be Reminded of Necessity to Control Activities in Control room.W/900502 Ltr ML20042E9811990-04-30030 April 1990 LER 90-002-01:on 900128,ESF Sys Actuations Occurred Due to Reactor Vessel Level Fluctuations After Manual Scram.Caused by Failure of O-ring on Fluid Inlet Port to Servo Valve for Hydraulically Operated Valve.Valve replaced.W/900430 Ltr ML20042E9101990-04-27027 April 1990 LER 90-005-00:on 900326,Tech Spec Surveillance Not Performed within Required Interval.Caused by Personnel Error.Personnel Counseled & Will Periodically Review Omitted Test Rept to Ensure Performance of Surveillance tests.W/900427 Ltr ML20042E6801990-04-23023 April 1990 LER 89-031-01:on 891206 & 900105,Agastat Relays Found Not Properly Secured by Seismic Support Straps.Caused by Inadequate Installation or Reinstallation of Seismic Straps. Straps Properly reconnected.W/900423 Ltr ML20042E6821990-04-19019 April 1990 LER 90-004-00:on 900321,discovered Potentially Inoperable Safety Sys Due to Inadequate Emergency Svc Water Cooling Flow Through Room Coolers.Caused by Gradual Buildup of Corrosion & Silt.Mod completed.W/900419 Ltr ML20012C4831990-03-12012 March 1990 LER 89-029-01:on 891117,primary Containment Isolation Sys Actuation Occurred During Performance of Refueling Floor Ventilation Exhaust Radiation Monitor Testing.Cause Unknown. Selector Switch & Relay Contacts cleaned.W/900312 Ltr ML20012C4821990-03-12012 March 1990 LER 89-024-01:on 891006,local Power Range Monitor Spike Caused Reactor Scram Signal While in Hot Shutdown.Caused by Design &/Or Mfg Process as Identified by Ge.Detector Placed in Bypass Position & Scram Signal reset.W/900312 Ltr ML20012A0171990-02-23023 February 1990 LER 90-002-00:on 900128,reactor Manually Scrammed Due to Leak of Electrohydraulic Control Sys Fluid.Caused by Lock Nut on Interlock Dump Valve Setting Adjustment Bolt Becoming Unsecured Due to Sys Vibration.Leak stopped.W/900223 Ltr ML20012A0021990-02-23023 February 1990 LER 90-001-00:on 900124,discovered That Daily Instrument Check of Main Stack Flow Rate Monitor Not Performed.Caused by Incomplete Procedure.Operating Shift Surveillance Log Revised to Include Daily Instrument check.W/900223 Ltr ML20012A0841990-02-0707 February 1990 LER 90-001-00:on 900108,HPCI Sys Declared Inoperable During Surveillance Testing When Start Time Exceeded 25 S.Caused by Inadequate Calibr Procedure Which Allowed Setting of 18 S. Ramp Generator & Signal Converter replaced.W/900207 Ltr ML20011F5791990-02-0707 February 1990 LER 89-007-01:on 890411,green Discoloration Discovered in Grease on Stabs of Several Control Fuses in 4 Kv Switchgear. Probably Caused by Incomplete Procedure.Maint Procedure M-054.004 Revised to Include Fuse insp.W/900207 Ltr ML20006A9621990-01-19019 January 1990 LER 89-033-00:on 891220,full Scram Signal Received When Technician Performed Surveillance on APRM D.Caused by Procedural Deficiencies & Inattention to Detail by Technician.Technician counseled.W/900119 Ltr ML19354E0121990-01-17017 January 1990 LER 89-032-00:on 891218,discovered That Weekly Surveillance Test Not Performed within Surveillance Interval.Caused by Inappropriate Action Based on Failure to Follow Procedure. Surveillance Test Coordinator counseled.W/900117 Ltr ML19354E0091990-01-16016 January 1990 LER 89-011-00:on 891213,discovered That Two Surveillance Tests of Turbine Stop & Control Valve Encl Not Performed Per Tech Specs.Caused by Incorrect Std Practice of Surveillance Testing.Programmatic Controls established.W/900116 Ltr ML19354E0101990-01-16016 January 1990 LER 89-015-01:on 890721,while Attempting to Remove Malfunctioning Reactor Pressure Vessel Regulator Set,Bypass & Control Valves Opened,Causing Steam Line Pressure to Increase to 480 Psig.Components replaced.W/900116 Ltr ML19354E0851990-01-11011 January 1990 LER 89-010-00:on 891211,monthly Surveillance Test ST 9.7 Not Performed within Surveillance Interval Established by Tech Spec Table 4.1.1.Caused by Combination of Programmatic Weaknesses.Review performed.W/900111 Ltr ML20005G2451990-01-11011 January 1990 LER 89-016-01:on 890720 & 22,LPRM Detector 4B-40-33 Spiked High,Resulting in Full Reactor Scram Signal While in Cold Shutdown.Caused by Design/Mfg Defect in GE Detector. Detector Placed in Bypass position.W/900111 Ltr ML20005G1901990-01-0808 January 1990 LER 89-009-00:on 891207,HPCI Sys Declared Inoperable When Sys Failed to Start During Pump,Valve & Flow Surveillance Test.Caused by Loose Lock Nut on HPCI Oil Sys Relief Valve. Lead Seal Wire to Be Placed on Valve caps.W/900108 Ltr ML20005F8711990-01-0505 January 1990 LER 89-031-00:on 891206,discovered That Four Agastat Relays Not Properly Secured by Seismic Support Straps.Root Cause Under Investigation & Will Be Reported in Rev to Ler.Support Straps Promptly reconnected.W/900105 Ltr ML20005E3911989-12-26026 December 1989 LER 89-030-00:0n 891126,steam Leak Discovered Coming from Packing on RCIC Injection Check Valve AO-22.Caused by Failure of Valve Stem Packing.Normal Reactor Level Restored & Mods of Valve Will Be pursued.W/891226 Ltr ML20011D2331989-12-18018 December 1989 LER 89-029-00:on 891117,Group III Primary Containment Isolation Sys Actuation Occurred During Refueling Floor Ventilation Exhaust Radiation Monitor Testing.Cause Unknown. Test Procedure to Be revised.W/891218 Ltr ML19332E7081989-12-0606 December 1989 LER 89-028-00:on 891108,review Determined That Standby Gas Treatment Sys Heater Control Relays Unqualified for post-LOCA Radiation Environ & Declared Inoperable.Cause Undetermined.Radiation Shielding installed.W/891206 Ltr ML19332E6331989-11-27027 November 1989 LER 89-007-00:on 891026,reactor Vessel Temp & Reactor Coolant Pressure Not Logged Every 15 Minutes as Required by Tech Spec 4.6.A.2 During Performance Integrated Leak Rate Testing.Caused by Procedure deficiency.W/891127 Ltr ML19332E7591989-11-27027 November 1989 LER 89-008-00:on 891027,primary Containment Isolation Sys Group II & III Isolations Occurred When Spurious Reactor Low Level Signal Sensed by Instruments.Possibly Caused by Air Bubble in Sensing Lines.Line backfilled.W/891127 Ltr ML19332D3401989-11-22022 November 1989 LER 89-006-00:on 891023,during Reactor Temp Adjustment, Reactor High Pressure Scram Occurred.Caused by Improper Planning & Coordination of Multiple Evolutions.Surveillance & Hydrostatic Test revised.W/891122 Ltr ML19332C4931989-11-20020 November 1989 LER 89-005-00:on 891020,reactor Protection Sys Actuation & Primary Containment Isolation Sys Actuation Occurred Due to False High Reactor Pressure Signal & lo-lo Reactor Vessel Level Signal,Respectively.Caused by spike.W/891120 Ltr ML19332C8191989-11-15015 November 1989 LER 89-027-00:on 891016,observation & Logging of Suppression Pool Temp as Required by Tech Spec 4.7.2 Not Met.Caused by Personnel Error.Operations Shift Team counseled.W/891115 Ltr ML19324C4361989-11-0808 November 1989 LER 89-026-00:on 891012,control Room Emergency Ventilation Sys Actuation Occurred Due to Momentary False High Radiation Signal from Control Room Radiation Monitor B.Caused by Sensitivity of Thumbwheel switch.W/891108 Ltr ML19324C1781989-11-0606 November 1989 LER 89-023-00:on 891005,outboard MSIV Ac Solenoid Pilot Valves de-energized,resulting in Expected Closure of Outboard MSIV D & Automatic Reactor Scram.Caused by Incomplete Guidance.Procedure revised.W/891106 Ltr ML19325F1801989-11-0606 November 1989 LER 89-024-00:on 891006,reactor Protection Sys Initiated Full Reactor Scram Signal.Caused by Output Signal for LPRM 40-33A Spiking High.Lprm Detector Placed in Bypass Position & Scram Signal reset.W/891106 Ltr ML19325F1811989-11-0202 November 1989 LER 89-022-00:on 891003,unterminated Lead in Circuit to HPCI Trip Solenoid Rendered HPCI Stop Valve Trip Functions Inoperable.Caused by Leads Loosely Hanging Inside Door Panel.Hanging Leads Secured & Panel inspected.W/891102 Ltr ML19325F1791989-11-0202 November 1989 LER 89-025-00:on 891007,determined That nonsafety-related Bellows Leak Detecting Pressure Switches Installed on Main Steam Relief Valves Could Prevent Opening During Design Basis Condition.Plant Alteration installed.W/891102 Ltr 1993-07-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
[Table view] |
Text
.,
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~CCN-90-14107 3' ' i 4 .
PHILADELPHIA ELECTRIC COMPANY PEACil BOTIOM ATOMIC POWER STATION R. D.1, Box 208
- Delta, Pent:sylvania 17314 enxu morna-ns: rowns os excentNor . (717) 456-7014 h
t May 30, 1990 Docket No. 50-277 -i 4
Document Control Desk U. S. Nuclear Regulatory Commission Washington .OC 20555 i
SUBJECT:
Licensee Event-Report Peach Bottom Atomic Power Station - Unit 2 This LER concerns an event-in which a surveillance was not performed as i
. required by Technical Specifications.
Reference:
Docket No. 50-277 !
Report Number: 2-90-009 -l Revision Number: 00 l Event Date: 04/30/90 :!
Report Date: 05/30/90 '!
Facility: Peach Bottom Atomic Power Station .i RD 1. Box 208, Delta, PA 17314 !
This LER is being submitted pursuant to the requirements of 10 CFR l 50.73(a)(2)(1)(B). f Sincerely, .
j
, Plant Manager cc: J. J. Lyash, USNRC Senior Resident inspector T. T. Martin, USNRC, Region 1 9006050343 900530 PDR ADOCK 05000277 i S PDC
4sRC form 386 U S. NUCLE 17. (.44ULATORY COMMt&SION MPIOYtD OMS CLO 2it00104 [
- . LICENSEE EVENT REPORT (LER) 8"ma's e 2i> s f ACILITY NAME Hi DOCElT NUMSIR (2) PAGEi34 Peach Bottom Atomic Power Station - Unit 2 0]5l0l0]Ol2]717 1 loFl ol 3 ,
TITLt (48
_ Surveillance Not Performed As Required By Technical Specification f VENT DATE (Si Lim NUMetM (el RtPORY DAf t (76 OTHER f ACILITits INVOLVED 18)
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On 4/30/90 at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> with Unit 2 at 38.3% power, it was discovered that the Rod Block Monitor (RBM) had not been proven operable prior to exceeding 30% power as required by Technical Specifications. The surveillance tests (S12N-60B-RBM-AlFM and S12N-608-RBM-B1FM), which are normally performed monthly to verify.RBM operability, had not been performed since 2/25/90 due to Unit 2 being in cold shutdown. S12N-60B-l RBM-AIFM and S12N-608-RBM-BlFM were completed satisfactorily on 4/30/90 at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />. The root cause of this event was a programmatic deficiency in that it was an incorrect standard practice of performing these surveillance tests after reaching 30%
rated power. The appropriate General Plant procedures will be revised to ensure that the RBM has been proven operable prior to reaching 30% power. S12N-60B-RBM-AlfM and SI2N-60B-RBM-BlFM will be revised to allow performance with the RBM bypassed. A-43 l " Surveillance Testing System", will be revised to strengthen the requirement that surveillances be performed prior to returning a system to an operable status. There was one previous similar event identified. An assessment of the corrective actions l
taken as a result of this previous event will be performed and additional corrective actions will be taken as required.
l "s"e'E *"" **
Mac e. asea . u.s. NUCLEAR 7.EIULATORY COMMMS80N T',. . ' UCENSEE EVENT REPORT (LER) TEXT CUNTINUATION ' Aarviovio ous No. aiso-oio6 L excitss: sisic q PAciLITY,NAME til DOCKli NUMStR (2) LER NUMSER (5) PAGE (31
- P2ach Bottom Atomic Power. Station vsaa -
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. Unit 2 0 l5 l0 j o l0 l2 l7 l7 9lo -
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010 ol2 oF ol 3 TEXT (# more space is segwest, see eeWoonat NAC Form 38EAW llh
, Requirements for the Report cThis report is required per 10 CFR 50.73(a)(2)(1)(B) due to a surveillance not being performed when required by Technical Specifications.
Unit Condition at Time of Discovery 4
. Unit 2 was in the RUN Mode at 38.3% power.
There were no systems, structures, or components that were inoperable that contributed to this event.
Description of Event On 4/30/90 at:1030 hours with Unit 2 at 38.3% power, it was discovered that the Rod f Block Monitor (RBM) (Ells: MON) had not been proven operable prior to exceeding 30%
power.as required by Technical Specification 3.2.C. Surveillance tests SI2N-60B-RBM-A1FM and Sl2N-608-RBM-A1FM, "RBM Functional Checks", which are performed monthly to prove operability of the RBM when the reactor-is in the RUN Mode-and at greater than *
~ 30% power, had not been performed'on Unit 2 since 2/25/90 due to the unit being in cold shutdown (the RBM is bypassed at less than 30% power). :These tests were
- scheduled -to be: performed during power ascension,- but could not be performed as written prior.to reaching 30% power.due to the RBM being bypassed as-designed, +
b At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on 4/30/90, S12N-60B-RBM-AIFM was completed satisfactorily to prove the '
'A'~ channel RBM operable. AT 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />.on 4/30/90, with Unit 2 at 38.3% power,.
SI2N-60B-RBM-B1FM was completed satisfactorily to prove the 'B' channel RBM operable.
' Analysis'of Event
.There were no actual-safety consequences as a result of this event. S12N-608-RBM-A1FM and SI2N-608-RBM-B1FM perform functional tests of the ability of the 'A' and 'B' channels of the RBM to provide a control rod withdrawal block signal and associated alarms (Ells: ANN) at greater than 30% reactor power due to various input signals.
Technical Specification 3.2.C requires the RBM be functional in the RUN Mode when the signals are not bypassed (i.e., above 30% rated thermal power). -
Satisfactory performance of SI2N-60B-RBM-AlFM and SI2N-608-RBM-81FM at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on
Cause of the Event The root cause of this event was a programmatic deficiency in that it was an
' incorrect standard practice of performing these tests after reaching 30% rated power.
~A' contributing factor to the cause of this event is station procedures do not clearly state that SI2N-608-R8M-A1FM and S12N-608-RBM-B1FM must be performed prior to reaching 30% power.
NR FORM 346A *U.$. CNa 1986- UC-580 000 M ;
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WItc Pd 3BSA U.S. NUCLEAM REIULAfoRY COneMISS40N I
' "'- . LICENSEE EVENT REPORT (LER) TEXT CONTINUATION mRovto out No siso4io4
,- EXPIRES: B?31/03 .r FActLITY NAME (1) DOCKti NUM$tR L2) LER NUMSER 18) PAGE (3) -
PJach Bottom-Atomic Power Station "'" '
" 0Na UMsN Unit 2 0'l5 l0 l0 l0 l2 l7 l7 910 -
ol0l9 -
ol0 0l3 oF ol3 ftXT t# snore esece is roupured. use sawtoner NRC Fonn 3NCs)(17)
Corrective Actions l
Appropriate General Plant procedure (s) will be revised to eisure that the RBM has been proven operable prior to reaching 30% power.
S12N-60B-RBM-A1FM and SI2N-60B-RBM-BlfM will be revised to allow performance while the.RBM is. bypassed.
A-43, Surveillance Testing System", will be revised to strengthen the requirement that surveillances omitted due to a system being inoperable, be performed prior to returning a system to an operable status.
Previous Similar Events One previous similar LER'was identified. LER 3-89-11 reported an event in which ST's. .
were not~ performed prior to reaching an operational milestone requiring equipment- '
operability. -The corrective actions taken in LER 3-89-11 should have been effective in' preventing this event. An' assessment of the effectiveness and completeness of the ;
corrective actions taken as a result of LER 3-89-11 will be performed and additional corrective actions will be taken as required.
1 3
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i '.________________________________________.________________.__.____._._____________________