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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20029C7321994-04-22022 April 1994 LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr ML20046B4731993-07-30030 July 1993 LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr ML20046A4911993-07-22022 July 1993 LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr ML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20045G7281993-07-0808 July 1993 LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr ML20045G8661993-07-0808 July 1993 LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr ML20045E7361993-06-29029 June 1993 LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr ML20029B1261991-02-28028 February 1991 LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr ML20028H8011991-01-24024 January 1991 LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr ML20044A1861990-06-20020 June 1990 LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr ML20043G1071990-06-13013 June 1990 LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr ML20043F1221990-06-0404 June 1990 LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20043A3441990-05-14014 May 1990 LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr ML20043A3401990-05-14014 May 1990 LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr ML20042G4521990-05-0707 May 1990 LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr ML20042F5801990-05-0404 May 1990 LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr ML20012E9931990-03-29029 March 1990 LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr ML20012F0001990-03-28028 March 1990 LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr ML20012E9951990-03-28028 March 1990 LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr ML20012E0101990-03-26026 March 1990 LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr ML20012C4971990-03-15015 March 1990 LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr ML20012C4861990-03-12012 March 1990 LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr ML20012B8991990-03-12012 March 1990 LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr ML20012B4221990-03-0606 March 1990 LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr ML20011F2701990-02-27027 February 1990 LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr ML20011F2091990-02-27027 February 1990 LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr ML20006F8601990-02-22022 February 1990 LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr ML20006E0521990-02-0808 February 1990 LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr ML20006B4801990-01-26026 January 1990 LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr ML19354D8931990-01-17017 January 1990 LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr ML20005F1921990-01-10010 January 1990 LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr ML20005E3971989-12-28028 December 1989 LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr ML19351A4551989-12-13013 December 1989 LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML19325E8221989-11-0303 November 1989 LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr ML19324B2511989-10-27027 October 1989 LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr ML19325C3281989-10-10010 October 1989 LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr ML19325C3701989-10-0909 October 1989 LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr ML20024F3771983-08-25025 August 1983 LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr ML20024F5731983-08-25025 August 1983 LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr ML20024E6761983-08-0404 August 1983 Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024D0071983-07-0808 July 1983 LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr ML20024D0091983-07-0808 July 1983 LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr ML20024B8231983-06-23023 June 1983 LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr ML20024C0141983-06-22022 June 1983 Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr ML20024A8881983-06-16016 June 1983 LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr 1999-08-23
[Table view] Category:RO)
MONTHYEARML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20029C7321994-04-22022 April 1994 LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr ML20046B4731993-07-30030 July 1993 LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr ML20046A4911993-07-22022 July 1993 LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr ML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20045G7281993-07-0808 July 1993 LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr ML20045G8661993-07-0808 July 1993 LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr ML20045E7361993-06-29029 June 1993 LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr ML20029B1261991-02-28028 February 1991 LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr ML20028H8011991-01-24024 January 1991 LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr ML20044A1861990-06-20020 June 1990 LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr ML20043G1071990-06-13013 June 1990 LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr ML20043F1221990-06-0404 June 1990 LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr ML20043A7871990-05-21021 May 1990 LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr ML20043A3441990-05-14014 May 1990 LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr ML20043A3401990-05-14014 May 1990 LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr ML20042G4521990-05-0707 May 1990 LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr ML20042F5801990-05-0404 May 1990 LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr ML20012E9931990-03-29029 March 1990 LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr ML20012F0001990-03-28028 March 1990 LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr ML20012E9951990-03-28028 March 1990 LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr ML20012E0101990-03-26026 March 1990 LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr ML20012C4971990-03-15015 March 1990 LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr ML20012C4861990-03-12012 March 1990 LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr ML20012B8991990-03-12012 March 1990 LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr ML20012B4221990-03-0606 March 1990 LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr ML20011F2701990-02-27027 February 1990 LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr ML20011F2091990-02-27027 February 1990 LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr ML20006F8601990-02-22022 February 1990 LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr ML20006E0521990-02-0808 February 1990 LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr ML20006B4801990-01-26026 January 1990 LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr ML19354D8931990-01-17017 January 1990 LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr ML20005F1921990-01-10010 January 1990 LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr ML20005E3971989-12-28028 December 1989 LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr ML19351A4551989-12-13013 December 1989 LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML19325F3951989-11-10010 November 1989 LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr ML19325E8221989-11-0303 November 1989 LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr ML19324B2511989-10-27027 October 1989 LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr ML19325C3281989-10-10010 October 1989 LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr ML19325C3701989-10-0909 October 1989 LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr ML20024F3771983-08-25025 August 1983 LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr ML20024F5731983-08-25025 August 1983 LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr ML20024E6761983-08-0404 August 1983 Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20024D0071983-07-0808 July 1983 LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr ML20024D0091983-07-0808 July 1983 LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr ML20024B8231983-06-23023 June 1983 LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr ML20024C0141983-06-22022 June 1983 Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr ML20024A8881983-06-16016 June 1983 LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr 1999-08-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
[Table view] |
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CHARLES CENTER e P.O. BOX 1475 e BALTIMORE. MARYLAND 21203 1475 l totytet Clif ts butttaa P9mm PLANT MPAnimWT ;
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l October 27, 1989 i i
U. ',S Nuclear Regulatory Commission Docket No. 50 317 -
Document Control Desk License No. DPR 53 ;
Vashington, D. C. 20555 f
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Dear Sirs:
t The attached IIR 89 012, Revision 1, is being sent to you as required under 10 CFR 50.73 guidelines, t
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Should you have any questions regarding this report, we would be pleased to l discuss them with you. ;
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[ Very truly yours, &
c f M i
L. B. Russell Manager Calvert Cliffs Nuclear Power Plant Department i
LBR:CI.B:sdw i
cc: William T. Russell .
Director, Office of Management Information i and Program Control ,
Messrs: G. C. Creel i C. H. Cruse l l
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At approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on July 20, 1989, with Unit 1 shutdown, a technicien discovered a master solenoid to the Switchgear Room Halon System to be disconnected.
Upon discovery, the llalon System was immediately declared inoperable and an hourly fire watch was established. The solenoid was reconnected and the solenoid was verified OPERABLE by a functional test.
Further investigation indicates that the solenoid was last taken out of service on June 29, 1989 and then inadvertently lef t disconnected. The root cause of this event is personnel error resulting from the lack of a written procedure for performing this task. Contributing causes include an inadequate procedure for addressing fire system impairments and the failure to apply temporary modifications and Safety Tagging procedures to this task.
Corrective actions include: revising a procedure to apply temporary modifications and Safety Tagging to fire systems; revising a Surveillance Test Procedure for verifying placement of solenoids; installing identification tags on solenoids; installing warning signs on llalon Systems; conducting a Quality Assurance Surveillance on applicability cnd working knowledge of procedures; establishing a written procedure for disabling colenoids; and conducting training.
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1, DESCRIPTION OF EVENT At approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on July 20, 1989, with Unit 1 shutdown (MODE 5 Cold Shutdown), a Fire and Safety Technician (FAST) (utility, non licensed) discovered that a master solenoid (1.ERV.2) to the Unit 1 Switchgear Room Halon System was disconnected. This solenoid actuates the discharge of Halon from three of nine Halon cylinders located on the west vall of the 45 foot elevation Switchgear room (See Figure 1). This disconnected solenoid was discovered during the routine performance of Surveillance Test Procedure (STP) M 291 0, *Halon System Valve Position Verification." However, the Halon System Master Solenoids are not checked as part of this STP and, therefore, the performance of the STP did not directly contribute to the discovery of this event.
Upon discovery of the disconnected solenoid, the Shift Supervisor was informed and the Halon System was immediately declared inoperable. The ACTION STATEMENT for Technical Specification 3.7,11.3, *Halon Systems," was entered and an hourly fire watch was established. The solenoid was inspected for damage and returned to its normal position, however, the ACTION STATEMENT remained in effect until an OPERABILITY determination could be made.
Even though there was no indication of damage to the solenoid or associated equipment, a functional test was performed to verify OPERABILITY, A maintenance order (MO No. 209 201 573A) was initiated and OPERABILITY of the solenoid was verified by performing Section VII of FTP.M 699 1, " Functional Test of 27' and 45' Switchgear Rooms Automatic Halon Release Solenoid Circuit." Upon satisfactory completion of the te:s t , the Halon System was declared OPERABLE wad the ACTION STATEMLNT was exited at approximately 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on July 20, 1989.
Further investigation into the event showed that the solenoid was last documented I to be out of service between approximately 0830 and 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on June 29, 1989.
! A FAST had performed a fire system impairment tagout at this time in accordance I with Calvert Cliffs Instruction C01 133, "Calvert Cliffs Fire Protection Plan".
The Halon System for the 27. foot and 45. foot Switchgear rooms was disabled by disconnecting each of the three master solenoids from its ass ociated Halon cylinder bank. This is the standard procedure for disabling a Halon System when work being performed in a room might cause an inadvertent actuation of the Halon System. In this instance, maintenance technicians wanted to heat a motor generator cot.pling on the 27. foot level Switchgear room.
The FAST who performed the tagout on June 29, 1989 believes that it was unlikely I that he lef t one master solenoid disconnecced. However, CCI.133 did not require independent verification of the fire system impatraent tagout. Therefore, there was no independent verification by any other personnel that all three master l solenoids were actually reconnected on June 29. During the investir,ation, it was also reported that the master solenoids were observed to be in place on July 14, 1989. This observation occurred during an informal walkdown of the Halon System I which was being conducted for the purposes of procedure development. However, this observation was not documented. No maintenance or other activities were identified during the period between June 29 and July 20 which would require the
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Room. Consequently, since it cannot be determined beyond a reasonable doubt that l the master solenoid was reconnected on June 29, we conclude from the documented evidence that the solenot.d was inadvertently left disconnected. !
- 11. CAUSE OF EVENT ,
The root cause of this event was determined to be personnel error resulting from the lack of an approved, written procedure for rendering the Halon System inoperable by disabling the three master solenofds. Activities which modify fire protection systems described in the Technical Specifications are required to be prescribed and accomplished in accordance with documented instructions, procedures, and drawinga. This task was incorrectly considered to be within the skills normally possessed by qualified personnel of the craft and, therefore, the FAST was unaware that a procedure was required. Contributing causes to this event are as follows.
CCI.133, 'Calvert Cliffs Fire Protection Plan" did not adequately address the method for taking fire detection or suppression systems out of service. C01 133 did not reference CCI 117 " Temporary Modification Control." The purpose of CCI.117 is to ensure that the disabling, bypassing, or changing of systems, sub systems, or components by some form of temporary modification will be properly reviewed for safety consequences, documented, and controlled. The task of disconnecting the solenoids was not recognized as a temporary modification to the plant. The use of CCI.117 would have required an independent verification to ensure that all of the master solenoids had been returned to service before declaring the Halon System OPERABLE.
In addition, CCI-133 did not adequately address when Safety Tagging is required or its relationship to Fire System Impairment Tagging. CCI.112. " Safety Tagging" was not referenced by CCI.133. The purpose of CCI.112 is to establish procedures for the tagging of equipment to ensure the safety of personnel and to ensure no adverse effect on operating equipment. . Fire System Impairment Tags were placed on fire detection and suppression equipment whenever they were taken out of service for maintenance. Due to the ambiguity of these instructions, a Safety Tag was considered not to be required for this task.
The investigation also revealed that the Halon System master solenoids did not have identification tags. Also STPs M 2910 and M 6991 did not have distinct verification and sign offs for each Halon System station.
III &HALYSIS OF EVFNr Total floodf.ng Halon 1301 Automatic Fire Suppression Systems are provided for the l
- 45. foot elevation and the 27 foot elevation Switchgear rooms. The Halon storage and distribution system is designed such that the same banks of bottles can supply Halon to either room depending on which room has the fire. There are three banks of bottles: one bank contains four bottles and only discharges to the 45 foot
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, olevation; the two bottle bank and three bottle bank have selector valves to allow l Halon flow to either Switchgear room. Therefore, a total of nine bottles would
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discharge in the event of a fire in the 45 foot elevation Switchgear room. The ,
master solenoid for the three bottle bank was disconnected, which would have prevented this bank from discharging for a fire in either Switchgear room.
Halon 1301 (Bromotrifluoromethane CBrF3 ) is theorized to extinguish fires by !
inhibiting the chemical chain reaction of the combustion process. As a result, Halon performs its function in very small concentrations as compared to other gaseous extinguishing agents such as carbon dioxide, which depends on oxygen displacement. NFPA 12A, the standard for Halon 1301 fire extinguishing systems, considers a 5% concentration sufficient for the types of fires anticipated in the Switchgear rooms. In fact, the appendix section of this code indicates that the flaming phase of combustion will be extinguished with even lower concentrations.
This is based on tests performed by the telephone industry on wired telephone distribution frames which consistently achieved complete extinguishment with less !
than 5% Halon concentration.
An evaluation of Halon concentration with the three bottle bank unavailable was performed. An initial calculated concentration of approxiwately 6% was available l for the 45. foot elevation Switchgear room and approximately 3.45% for the 27 foot Switchgear room. It can be concluded that the Halon system, even with the three bottle bank inoperable, would have prevented fire spreading within the room as well as outside the room. Our bases for this conclusion are provided below:
. In the 45. foot Switchgear room the initial discharge concentration of 6%
is above the recommended extinguishing concentration of 5% for this type of room.
. In the 27 foot Switchgear room the initial discharge concentration of 3.45%, while below the recommended extinguishing concentration, would have stopped flaming combustion and thereby prevented a fire from spreading.
. The detection systems which actuate the Halon systems were functional.
These systems provide an alarm indication to the Control Room. In addition, these systems utilize smoke detectors which respond much faster to fire conditions than heat detectors. Therefore any fire leading to discharge of the Halon System would still have been in an incipient stage.
. The plant fire brigade would respond to a fire in time to provide !
extinguishment of glowing combustion still remaining after the Halon discharge.
Therefore, there is reasonable assurance that the safety of the plant and the public was not significantly compromised by the event.
At approximately 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on July 20, 1989, a Determination of Reportability (CCI 118, Event No. 3425) was initiated to evaluate the event. NRC Region I was informed of the event at approximately 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> in accordance with 10 CFR 50.72 (b)(2)(1).
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of I 015 0F oli i mw . , w e.,. = v mi This event is reportable under 10 CTR 50.73 (a)(2)(1)(B) as a condition prohibited by the plant's Technical Gpecifications. Technical Specification 3.7.11.3 requires that an hourly fire watch be established in those areas protected by an inoperabje Halon System. This requirement was not met on June 29, 1989, when the Halon System for the Unit 1 Switchgear rooms was returned to service and the fire watch was discontinued with the solenoid still disconnected. Technical Specification 3.7.11.3 also requires that a Special Report be sent to the Commission within 30 days of the Halon System being inoperable for over 14 days.
This requirement was not met as a result of changing the event date from the date of discovery, July 20, 1989, to June 29, 1989. Therefore, the event occurred from approximately 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on June 29, 1989, to 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on July 20, 1989, a duration of approximately 21 days. Written procedures are required by Technical Specificatien 6.8.1 and Regulatory Guide 1.33, Rev. 2, ' Quality Assurance Program Requirements . Operation" to be established, implemented and maintained for the Fire Protection Program. This requirement was not met as a result of not having a procedure for disabling the Halon solenoid. The reportability date of the original LER was determined to be 30 days from the discovery date. There were no other inoperable or failed components, structures or systems which contributed to this event. No other plant system or components failures resulted from this event.
IV. CORRECTIVE ACTIONS A. Immediate Corrective Actions The following corrective actions were taken on July 20, 1989:
. Upon discovery of the event, the Halon System was declared inoperable and an hourly fire watch was established in accordance with Technical Specification 3.7.11.3.
. Af ter inspecting the solenoid for any noticeable damage, the solenoid was connected back to its Halon bank. Therefore, though remaining ,
inoperable by Technical Specifications, the Wlon System was functional.
. The solenoid was functionally tested satisfactorily and declared OPERABLE.
B. Short term Corrective Actions i
The following corrective actions were taken on July 22, 1989:
. Safety and Fire Protection Unit personnel were instructed that work performed in accordance with CCI.133 requires independent verification .
. The Manager Calvert Cliffs Nuclear Power Plant Department issued a roemo to ensure that the control and tagging of impaired firo protection equipment meet the requirements of CCI 112 as well as CCI.133.
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of 1 al6 0F 017 no n . , w o ,,ami.vnn C. Long term Corrective Actions The following corrective actions have been taken as a result of this event:
. CCI.133 has been revised to discontinue the use of fire system
, impairment tags and, instead, will reference CCI.112 Safety Tagging requirements. CCI.133 will ali.o require the use of C for teal.orary modifications to fire detection and suppression sys,CI tems. 117
. STP.M 291 0 has been revised to require verification that llalon actuator solenoids are in place. The STP has also been revised to have distinct verification and sign. offs for each Halon System station.
. STP.M 699 1 has been revised to have distinct vertiication and sign. offs for each llalon System station.
. Identification tags have been installed on llalon master solenoids.
. Warning signs, have been pinced near llalon cylinder banks which state,
' EIRE SUPPRESSION SYSTD( DO NOT DISTURB VIT110VT PERMISSION, CALL FIRE PROTECTION UNIT: X.4755/4931."
The following corrective actions will be taken as a result of this event:
. A Quality Assurance Eurveillance will be conduct.ed to: (1) evaluate if CCI 112 and 117 are applicable to any other plant activities not currently being applied co these CCIs and (2) determine if plant p9rsonnel (sample selected from cognizant disciplines) have an adequate working knowledge of CCIs 112, 117, and 133.
. Fire and Safety petsonnel will receive training on the revised requirements of CCI 133 and CCI.117.
. A written procedure will be established for disabling and restoring the Halon System master solenoids.
V. ADDITIONAL INFDRMATION l
Four previous events affecting the llalon System have occurred at Calvert Cliffs.
Details of these events may be found in LERs 7814, 7818, c.nd 78 41 for Unit I and 78 40 for Unit 2.
Identification of components referred to in the LER are:
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