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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
iCCH-90-14129' PHILADELPIIIA ELECTRIC COMPANY W[In/ ) PIACil ll0FIUM KlUMIC POWl:R STATION '
R. D.1. Ilox 208 -
M,F Delta, IYnnsylvania 17314
- rsuai wrnmi-tue ros tat or e nctittsc t C17) 4547014 D. B. Millet. Jr.'
vice treent June 25,1990 Docket No. 50-277 Document Control-Desk.
.U; S. Nuclear Regulatory Commission
' Washington, DC 20555
SUBJECT:
Licensee Event Report Peach Bottom Atomic Power Station - Unit 2 This LER concerns the operability of the Standby Gas Treatment System as a result of circuitry containing relays which were not environmentally qualified. This revision supplements the root cause of this event and provides' planned corrective actions.
Reference:
Docket No. 50-277 Report Number: 2-89-028 Revision Number: 01 Event Date: 11/08/89 Report Date: 6/25/90 facility: Peach Bottom Atomic Power Station RD 1 Box 208, Delta, PA 17314
'This LER is being submitted pursuant to the requirements-of 10 CFR 50.73(a)(2)(v).
Sincerely, Vice President cc: J. J. Lyash, USNRC Senior . Resident Inspector
.T. T. Martin, USHRC, Region I 9007020040 900625 i gDR--ADOCK0500{z}7
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APPROYED O!b NO 31 2 7104 LICENSEE EVENT REPORT (LER)- 5 $ ma' $ ' '8'
F 2.CILif Y NAMS til DOCEl f NUMSS R (71 P AGE i38 Peach Bottom Atomic Power Station - Unit 2 0 ]5 l 0 l0 l o l2 l7 !7 1 loFl ol 3
"' Standby Cas Treatment System Heater Control Relays Installed Without Environmental cuallflention Due To Unknown Cause IVENT DAlt lll Lin NUMBER ISI REPORY DAf f (76 OTHE R F ACILITit S INVDLVf D ($1 MO81H4 DAV YEAR YEAR N h* ' N,"$ MONTH DAi v t ast . Acatif v hauts DOCAt1 NUMBt M Si ,
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NAMF TE LEPHONE NUMStR AHE A CODE A. A. Fulvio, Regulatory Engineer 711 17 41516 l-171 01114 COMPLitt ONE LING FOR 4 ACH COMPONINT F AILURE DESCRISED IN THl0 RSPORY (131 CAU$5 Sv8 TEM COMPONENT C- rip ' '
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l l l On November 8, 1989, following a review of safety related relay applications it was determined that the Standby Gas Treatment System (SBGT) heater control relays were
, not qualified for the analyzed post loss of Coolant Accident (LOCA) radiation environment. At.1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, the SBGT was declared inoperable and a Unit 2 plant shutdown was-initiated in accordance with Technical Specifications. By 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on November 9 temporary radiation shielding was installed around the relays, the I:~ l SBGT declared operable and Unit 2 restored to full power. The relays were l
l subsequently relocated to an area in which the calculated Post LOCA Radiation Levels l do not exceed their 2.0E5 rad rating. The root cause of this event was a lack of procedural guidance to control the Environmental Qualification aspects of the l modification design process (CIRCA 1980). An assessment of the Peach Bottom EQ l Program-will be performed to ensure that required components have been included. No l previous similar LERs were identified, u.C f orm 366 00D1
nc , . a v s. wuctimuutavony commession LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Am;ovto ous wo. mo-oios tress: arc raciuty waus on pocut wuussa m paan m ten avusen m Piach Bottom Atomic Power Station "*" "E'#nEl' "UsU r
. Unit 2 0 l6 l0 l0 l0 l 2l7 l7 8 l9 -
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Requirements for the Report This report is required per 10 CFR 50.73(a)(2)(v) due to a condition which could have prevented fulfillment of the safety function of the Standby Gas Treatment System (Ells:BD) (SBGT).
Unit Status at Time of Event Unit 2 was in the Run Mode at 100 percent power. Unit 3 was in the Refuel Mode.
Description of Event
- On November 8, 1989, following a review of safety related relay applications, a '
procurement engineer (contract non-licensed) determined that both the "A" and "B" ,
had been omitted from trainSBGTSystemheater(Ells:EHTR)controlrelays(Ells:RLY)ipmentQualification the Environmental Qualification Report. Evaluation by the Equ .
(EQ)Branchdeterminedthattimedelayrelays 62-5944and62-6023-(AgastatmodelETR)
-were not qualified for the analyzed post Loss of Coolant Accident (LOCA)-high 1 radiation environment in the SBGT fan and filter room. The relays are in the heater '
actuation circuit to provide a time delay to allow SBGT system flow to be established. At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, both trains of the SBGT System were declared inopei Ale and a Unit 2 plant shutdown initiated in accordance with 51chnical Specification 3.7.B.4. At 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> the "B" train SBGT neater relay es provided with temporary !
shielding-and declared operable and at 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br /> Unit 2 was restored to full power.
On November 9,.at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> the "A" train SBGT heater relay was provided with temporary shielding and declared operable.
l Cause of the Event The SBGT heater actuation time delay relays were installed in November 1980 as a modificationtotheheatercontrolsystem(Modification 648). At the time of this modification the PBAPS equipment environmental qualification program controls and criteria were under the early stages of development.
In June 1985 the. environmental qualification report for electrical equipment was completed. During implementation of the equipment environmental qualification program in accordance with IE Bulletin 79-018 " Environmental Qualification of Class
-1E Equipment", and 10 CFR50.49, these relays were excluded from the qualification list of equipment important to safety which has the potential to be subject to a i harsh environment.- '
l The root cause of this exclusion has been determined to have been a lack of 1 procedural guidance to control Environmental Qualification aspects of the i modification process.during the time modification 648 was being implemented. At the time this modification was being implemented Philadelphia Electric Company was in the process of developing its response to Bulletin 79-018. To accomplish this, an l Environmental Qualification task force was established by the Nuclear Engineering l Department (NED). The task force was separated from the main body of NED to allow l full dedication to Bulletin 79-018. Because there was no procedural requirement to
.l notify the EQ task force of modifications being installed, the task force was not l made aware of modification 648 and newly installed relays 6P-5944 and 62-6023.
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(l OshC-teem 3364. . U S NUCLEf.R ElIVL ATORY COMMIT 010N "2'
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION - m aovioouewo mo-om
. ExNRES: 8'31/06 FAcettiv hAME lu DOCOLE1 NUMDth (29 LER hUMGER 161 PA04 (3)
P;ach Bottom Atomic Power Station.
- IE***N Unit 2-0 16 l 0 0 l 0 l 217 l7 8l9 -
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oli ol 3 oF o l3 f tXT f# more apoco e regurest use scheepnet 44C Form JAE4 W (1h Consequently, an evaluation of the EQ requirements for these relays was not performed ,
thus leading to their exclusion from the list of environmentally qualified electrical i h equipment.
A procedural requirement to perform an Environmental Qualification review as part of the modification det,ign process was implemented approximately one year later (mid 1981).
Analysis of the Event No safety consequences occurred as a result of this event.
The heater control relays used in the SBGT fan and filter room were purchased as nuclear safety related equipment and could withstand the analyzed post LOCA heat and humidity conditions. They were also qualified to withstand an integrated dose of 2.0 E5 rads. However, the worst case analyzed radiation exposure to the relays is j approximately-3.7 E6 rads. i SBGT is comprised of two full flow trains which may be used by either-plant. The SBGT heaters reduce humidity of air entering the filters (EIIS:FLT) to less than 70 percent. This protects the filters from moisture which would reduce their efficiency. Reduced efficiency of the filters due to failure of the heater control relays during a design basis LOCA in either unit could have resulted in offsite doses in excess of that-analyzed.-
Corrective Actions i A Unit 2 plant s'hutdown was initiated until temporary radiation shielding was in place.
-l The relays were relocated on 5/1/90 to an area in which the calculated post LOCA ;
I radiation levels do not exceed their 2.0E5 rad rating. '
-l Philadelphia-Electric Company will perform an assessment of the Peach Bottom EQ l Program to provide additional assurance that required items are included.
,i Previous Similar Events
- io previous similar Licensee Event Reports were identified.
I PORM 364A. 'U.S. GPCs 1988*SJ0*S89,000fd
k ethC Poem attA .' U.S. MUCLE A7. 7.8 LUL(104Y C0484H00 TON I
UCENSEE EVENT REPORT (LER) TEXT C*eNTINUATION mnono ow no Sino-om
. ' EKPIRts. S/31C FACluTY 8s4444 tu DOCILET NUhlBLR (2) LER OdUhtetR (gl PAGE (3)
'Paach Bottom: Atomic Power Station "'" "NUl' "OnN Unit 2.
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o l2 oF ol3 o l1 TFXT M more apses 4 requesd, ens ashetenst 44C 7enn NKaJ (17)
Requirements for thi Report-This report is required per 10 CFR 50.73(a)(2)(v) due to a condition which-could have prevented fulfillment of the safety function of the Standby Gas Treatment System (Ells:BD) (SBGT).
Unit ~ Status at Time of Event Unit 2 was in the Run Mode at 100 percent power. Unit 3 was in tim Refuel Mode.
Description of Event On November 8, 1989, following a review of safety related relay applications, a- i procurement engineer (contract non-licensed) determined that both the "A" and "B" train SBGT System heater'(EIIS:EHTR) control relays (EIIS:RLY) had been'omitted from the Environmental Qualification Report. Evaluation by the Equipment Qualification
~ ,
(EQ) Branch determined that time delay relays 62-5944 and 62-6023-(Agastat model ETR)'
were not qualified for the analyzed post loss of Coolant Accident (LOCA) high radiation environment in the SBGT fan and filter room. 'The relays are in the heater actuation circuit to provide a time delay to allow SBGT system flow to be established. At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, both trains of the SBGT System were declared inoperable and.a Unit 2 plant shutdown initiated in accordance with Technical Specification 3.7.B.4. At 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> the "B" train SBGT heater relay was-provided with temporary shielding and declared operable and at 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br /> Unit 2 was restored to full power.
On November 9, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> the "A" train SBGT heater relay was provided with temporary shielding and declared operable.
Cause of the Event The'SBGT heater actuation time delay relays were installed-in November 1980 as a modificationtotheheatercontrolsystem(Modification 648). At the time of'this modification the PBAPS equipment environmental qualification program controls and criteria were under the early stages of development.
In June 1985 the environmental qualification report for electrical equipment was completed. During implementation of the equipment environmental cualification program in accordance with IE Bulletin 79-018, " Environmental Qualification of Class 1E Equipment", and 10 CFR50.49, these relays were excluded from the qualification list of. equipment important to safety which has the potential to be subject to a harsh environment.
l The root cause of this exclusion has been determined to have been a lack of procedural guidance to control Environmental Qualification aspects of the
- modification process during the time modification 648 was being implementeri. At the time this modification was being implemented, Philadelphia Electric Company was in l the process of developing its response to Bulletin 79-018. To accomplish this, an l-Environmental Qualification task force was established by the Nuclear Engineering ,
l-Department (NED). The task force was separated from the main body of NED to allow l full dedication to Bulletin 79-018. Because there was no procedural requirement to notify the EQ task force of modifications being installed, the task force was not made aware of modification 648 and newly installed relays 62-5944 and 62-6023.
,,,,, , _ .v...cm m.e s.+ -
, ' 19 $h l
r NftC Foret 304A U S NUCLEAM E tiULATORY COMM10SION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION amovio ove No aiso-em exmts: swas -
F ACIL TV NAME (1) DOCELT NUMBER (2) LER NUMetM (61 PAGt 131 Piach Bottom Atomic Powe Station "'" '
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.l Consequently, an evaluation of the EQ requirt.ments for these relays was not performed l
.lthusleadingtotheirexclusionfromthelistOfenvironmentallyqw11fiedelectrical~ )
I equipment. j A procedural requirement to perform an Environmental Quelitication review as part of
- the modification design process was implemented approximately one year later (mid
'1981).
Analysis of the Event No safety consequences occurred as'a result of this event.
The heater control relays used in the SBGT fan and filter room were purchased as !
nuclear sa.fety related equipment and-could withstand the analyzed post LOCA heat and humidity conditions. They were also qualified to withstand an integrated dose of'2.0 E5 rads. However, the worst case analyzed radiation exposure to the relays is approximately 3.7 E6 rads. -l SBGT is comprised of two full flow trains which may be uscd by either plant. . The SBGT heaters reduce humidity of air entering the filters (Ells:FLT) to less than 70 percent. This protects the filters from moisture which would reduce their efficiency. Reduced efficiency of the filters due to failure of the heater control !
relays during a design basis LOCA in either unit could have resulted in offsite doses j in excess of that analyzed.
Corrective Actions A Unit 2 plant shutdown was initiated until temporary radiation shielding was in place. 9 L ,
l The relays were relocated on 5/1/90 to an area in which the calculated post LOCA.
l radiation levels do not exceed their 2.0E5 rad rating, li l '
l Philadelphia Electric Company will perform an assessment of the Peach Bottom EQ l Program.to provide additional assurance that required items are included.'
i:
Previous Similar Events No' previous similar Licensee Event Reports were identified.
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