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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20045B3021993-06-11011 June 1993 LER 93-001-00:on 930513,discovered That One Channel of Rvlms Inoperable Since Probe Replaced in Oct 1992.On 930507, Discovered That Two Sensors in Rvlms Indicating Wet.Caused by Design Error.Wiring Polarity corrected.W/930611 Ltr ML20024H2281991-05-21021 May 1991 LER 91-003-00:on 910421,actuation of EFW Sys During Plant Heatup Occurred Due to Low Once Through Steam Generator Level.Caused by Leaking Feedwater Recirculation Valve.Plant Startup Procedure OP 1102.02 Will Be revised.W/910521 Ltr ML20024H0861991-05-10010 May 1991 LER 91-002-00:on 910410,inadvertent Actuations of Combined Control Emergency Ventilation Sys Occurred.Caused by Transient Noise Spike.Mod Will Be Completed by 910531 to Install Time Delay in Actuation circuitry.W/910510 Ltr ML20024G9781991-05-10010 May 1991 LER 90-004-01:on 900531,discovered Degraded Fire Barrier Penetration During Insp Per Generic Ltr 86-10.Caused by Failure to Identify Adequate Fire Barrier Seal During 1983 Plant Walkdown.Fire Watch posted.W/910510 Ltr ML20029C3771991-03-22022 March 1991 LER 91-006-00:on 910222,core Protection Calculator Reactor Coolant Sys Flow Channels Not Being Calibrated within Tech Spec.Caused by Personnel Error.Operations Manager Counseled Operators Involved in event.W/910322 Ltr ML20029B1331991-02-27027 February 1991 LER 91-004-00:on 910125,control Room Radiation Monitor Alarm/Trip Setpoint Greater than Normal.Caused by Personnel Error.Operations Manager Will Counsel Shift Supervisors & Night Order Will Be posted.W/910227 Ltr ML20028H6841991-01-21021 January 1991 LER 90-021-00:on 901222,potential RCS Leak Noted in Area of Pressurizer Upper Level Instrument Nozzle.Caused by Pure Water Stress Corrosion Cracking.New Nozzle Installed Into Penetration from Shell OD.W/910121 Ltr ML20043C6801990-05-31031 May 1990 LER 89-025-01:on 891221,identified That Portion of Wall Located in Auxiliary Bldg Had Not Been Previously Identified as Tech Spec Fire Barrier.Caused by Personnel Error.Wall Being Upgraded to Tech Spec status.W/900531 Ltr ML20043C3781990-05-30030 May 1990 LER 90-012-00:on 900430,18 Month Channel Calibr of Liquid Radwaste Effluent Line Flow Monitor Not Performed as Required.Caused by Inadequate Controls to Ensure Followup Actions Taken in Timely Manner.Amends revised.W/900530 Ltr ML20043C0361990-05-23023 May 1990 LER 90-003-01:on 900423,discovered That Incorrect Monitoring Instrumentation for Radiological Effluent Ventilation Sys Utilized to Comply W/Tech Specs.Caused by Mgt Oversight.Logs Process Monitors Will Not Be used.W/900523 Ltr ML20043A7411990-05-17017 May 1990 LER 90-004-01:on 900212,discovered That Backwater Valve in Floor Drain Pipe in Emergency Feedwater Pump Room Missing. Caused by Inadequate Configuration Control.Backwater Pumps Installed & Will Be Included in Maint program.W/900517 Ltr ML20042F7681990-05-0101 May 1990 LER 90-002-01:on 900131,errors Identified in Calculation Used to Establish Calibr Tables for Steam Generator Water Level Transmitters.Errors in Original Calculation Not Identified.Calibr Procedures revised.W/900501 Ltr ML20042F7751990-05-0101 May 1990 LER 90-010-00:on 900401,personnel Failed to Complete Control Element Assembly Position Log.Caused by Surveillance Program Deficiencies & Lack of Mgt Involvement.Shift Briefing Completed & Procedure Change incorporated.W/900501 Ltr ML20042E1981990-04-10010 April 1990 LER 90-008-00:on 900311,determined That Seal Leakage Test for Containment Personnel Air Lock Had Not Been Performed, Per Tech Specs.Caused by Personnel Error.Procedure Revs Initiated & Personnel counseled.W/900410 Ltr ML20012F5051990-04-0505 April 1990 LER 89-027-00:on 891005,determined That Leakage Rate for Containment Isolation Check Valve in Excess of Leakage Rate Allowed Per Tech Specs.Caused by Loose Weld Slag in Valve Seat Area.Valve Cleaned & reassembled.W/900405 Ltr ML20012F5031990-04-0505 April 1990 LER 90-007-00:on 900306,RCS Charging Line Rendered Inoperable Due to Deficient Piping Support Weld.Caused by Inadequate Work Controls & post-installation Insp Processes. Field Walkdowns & Weld Insps initiated.W/900405 Ltr ML20012F5741990-04-0404 April 1990 LER 90-006-00:on 900305,instrumentation Channels Declared Inoperable,Resulting in Manual Actuation of Reactor Protection Sys.Caused by Procedural Deficiencies.Functional Tests of Log Power Level Channels performed.W/900404 Ltr ML20012C7221990-03-14014 March 1990 LER 90-004-00:on 900212,identified That No Backwater Valve Located in Floor Drain Pipe in One of Emergency Feedwater Pump Rooms.Caused by Inadequate Configuration Control. Valves Installed on 900215.W/900314 Ltr ML20012C1821990-03-12012 March 1990 LER 85-029-00:on 850520,unusual Motor Vibrations Identified on Svc Water Pump 2PM4A.On 861028,high Vibrations Noted on Upper Motor Bearings of Pump 2PM4B.Caused by Improper Installation.New Bearings installed.W/900312 Ltr ML20012B7271990-03-0808 March 1990 LER 89-049-01:on 891220,discovered That Okonite T-95 Tape Not Used to Tape Internal Motor Lead Connections for Main Feedwater Containment Isolation Valves.Caused by Personnel Error.Valves Taped According to Design drawing.W/900308 Ltr ML20012B5701990-03-0505 March 1990 LER 90-003-00:on 900201,failure to Perform Monthly Source Check Surveillance on Three Radiation Process Monitors Occurred.Caused by Inadequate Procedure Change by Personnel. Source Check on Monthly Basis implemented.W/900305 Ltr ML20011F6741990-03-0202 March 1990 LER 90-002-00:on 900131,errors Identified in Calculation Used to Establish Calibr Tables for Steam Generator Water Level Transmitters.Caused by Incorrect Static Pressure Assumption.Trip Setpoint Bistable increased.W/900302 Ltr ML20011F6781990-03-0101 March 1990 LER 89-026-00:on 891112,gaps in Piping Supports on Supply & Return Piping for Containment Coolers Identified.Caused by Inadequate Design Technique Used in Original Support Design. Shims Added Before Restart from outage.W/900301 Ltr ML20011F5831990-02-27027 February 1990 LER 89-022-01:on 891114,normal Offsite Power Feeder Breaker to 4,160-volt Ac ESF Bus Opened,Resulting in Loss of Power to Bus 2A3.Caused by Inadequate post-maint Test Controls. Test Switch Opened & Job Order changed.W/900227 Ltr ML20011F7311990-02-23023 February 1990 LER 90-001-00:on 900126,identified That Required Visual Insps of Containment Bldg After Entry Made Not Documented as Being Performed.Caused by Inadequate Procedural Guidance. Administrative Controls to Be established.W/900226 Ltr ML20006D7391990-02-0606 February 1990 LER 89-034-01:on 891031,determined That Tech Spec 3.9.1 Had Likely Been Violated Re Independent Circuits of Control Room Emergency Air Conditioning Sys.Caused by Inadequate Guidance Re Equipment Svc Removal.Procedures revised.W/900206 Ltr ML20011E2371990-01-31031 January 1990 LER 89-012-01:on 890626,RCS Backleakage Through Safety Injection Sys Check Valve Occurred Three Times.Caused by Missing Rollpins Which Connect Valve Disc to Valve Disc Shaft.Rollpins Replaced & Valves reassembled.W/900131 Ltr ML20011E2291990-01-31031 January 1990 LER 89-039-01:on 891116,discovered That Door for Upper North Electrical Penetration Room Open & Latch Mechanism Missing. Caused by Abnormally High Differential Pressure Across Door. Ventilation Sys Flow Balance performed.W/900131 Ltr ML20011E1451990-01-30030 January 1990 LER 89-024-00:on 891231,loose Terminal in Feedwater Control Sys Cabinet Resulted in Reactor Trip.Caused by Loose Connection on Terminal.Loose Connection Reterminated properly.W/900130 Ltr ML20006C1451990-01-29029 January 1990 LER 89-048-00:on 891228,automatic Reactor Trip & ESF Actuation Occurred as Result of Loss of All Main Feedwater Flow Due to Inadvertent Tripping of Main Feedwater Pump. Caused by Personnel error.O-rings replaced.W/900129 Ltr ML19354E3331990-01-22022 January 1990 LER 89-025-00:on 891221,two Piping Penetrations Located in Barrier Not Surveilled as Required by Tech Specs.Caused by Personnel Error.Fire Watch Posted When Necessary Per Tech Spec.W/900122 Ltr ML20006A8661990-01-22022 January 1990 LER 89-041-00:on 891221,automatic Actuation of Emergency Feedwater Sys Initiated.Caused by Lack of Adequate Procedural Guidance.Valve Positioners CV-2623 & CV-2673 Adjusted & Guidance Procedures developed.W/900122 Ltr ML20006A8671990-01-22022 January 1990 LER 89-042-01:on 891209,inadvertent Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Keying of Hand Held Radio in Vicinity of Chlorine Monitors by Technician.Technician counseled.W/900122 Ltr ML20005F1551990-01-18018 January 1990 LER 89-023-01:on 891117,noted That Channel a Not Responding to Change in Power Level & Declared Inoperable.Caused by Defective Preamplifier.Evaluation of Sys Design & Channel Functional Test initiated.W/900108 Ltr ML20006B6461990-01-18018 January 1990 LER 89-047-00:on 891219,RCS Temp Increased Above 250 F W/ Oxygen Concentration Greater than Tech Specs Limit.Caused by Inadequate Procedural Guidance.Plant Startup Procedure Revised to Require Chemistry Dept signoff.W/900118 Ltr ML19354D8291990-01-15015 January 1990 LER 89-044-00:on 891214,incorrect Assumptions & Calculational Errors Identified for Low Pressure Injection & Reactor Bldg Spray Pumps When Aligned to Take Suction from Reactor Bldg sump.W/900115 Ltr ML20005G1681990-01-0909 January 1990 LER 89-045-00:on 891210,discovered That U-bolt Supports on Two Containment Isolation Valves in Containment Bldg Not Installed & Pressurizer Sample Lines & Valves Considered Inoperable.Missing U-bolts installed.W/900109 Ltr ML20005F1481990-01-0808 January 1990 LER 89-042-00:on 891209,inadvertent Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Keying of Hand Held Radio in Vicinity of Chlorine Monitors by Technician.Technician counseled.W/900108 Ltr ML20005F1571990-01-0808 January 1990 LER 89-043-00:on 891208,discovered That Approx 50% of One Nut Ring Half Beneath Reactor Vessel Nozzle Flange Corroded Away.Caused by Gradual Deterioration of Gasket Matl.Design Change implemented.W/900108 Ltr ML20005F2071990-01-0404 January 1990 LER 89-040-00:on 891205 & 06,automatic Actuations of Emergency Diesel Generator Occurred as Result of Loss of Power to 480-volt ESF Bus.Caused by Personnel Error During Bus Transfer.Mgt Briefings conducted.W/900104 Ltr ML20005F0471990-01-0303 January 1990 LER 89-046-00:on 891204,reactor Bldg Isolation Valves Rendered Inoperable Due to Deficient Welds on Piping Supports Which Were Installed During Initial Plant Const. Deficient Supports Repaired Prior to restart.W/900103 Ltr ML20011D2521989-12-18018 December 1989 LER 89-039-00:on 891116,discovered That Door for Upper North Electrical Penetration Room Open & Missing Latch Mechanism. Caused by Extensive Use During 56-day Refueling Outage.More Frequent Insps of Door Condition to Be done.W/891218 Ltr ML20011D2501989-12-18018 December 1989 LER 89-023-00:on 891117,approach to Criticality Commenced After Seventh Refueling Outage W/Logarithmic Power Level Channels Inoperable.Caused by Electrical Noise in Circuitry. Defective Preamplifier replaced.W/891218 Ltr ML19351A6731989-12-14014 December 1989 LER 89-022-00:on 891114,inadequate post-maint Test Controls Resulted in de-energizing 4,160 Volt Ac ESFs Electric Bus Uexpectedly.Caused by Inadequate post-maint Test Controls. Job Order Instructions changed.W/891214 Ltr ML19354D5521989-12-14014 December 1989 LER 89-038-00:on 891114,reactor Trip Occurred as Result of Inadvertent Closure of Main Feedwater Isolation Valve.Caused by Personnel Error.Disciplinary Action Taken Against Individual & Senior Mgt Personnel Put on shift.W/891214 Ltr ML19351A4651989-12-11011 December 1989 LER 89-021-00:on 891111,when Low Level Radwaste Water in Waste Condensate Tank Aligned to Be Released,Discovered That Radiation Monitor Inoperable for Duration of Release.Caused by Personnel Error.Procedure revised.W/891211 Ltr ML19332F6171989-12-11011 December 1989 LER 89-037-00:on 891110,reactor Trip Occurred as Result of Inadvertent Grounding of Reactor Protection Sys Power Supply During Surveillance Testing.Caused by Inadequate Procedure. Procedures revised.W/891211 Ltr ML20005D6821989-12-0101 December 1989 LER 89-005-01:on 890518 & 25,damping Board Removed from Penetration Containing Cable Tray.On 890531,voids Noted in Penetration Seals.Caused by Erroneous Vendor Procedures. Penetrations Restored & Procedures revised.W/891201 Ltr ML19332E8611989-11-30030 November 1989 LER 89-034-00:on 891031,control Room Emergency Air Conditioning Sys Rendered Inoperable Due to Removing Independent Circuits from Svc.Caused by Inadequate Guidance.Procedures Revised & Circuits flagged.W/891130 Ltr 1998-10-22
[Table view] Category:RO)
MONTHYEARML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20045B3021993-06-11011 June 1993 LER 93-001-00:on 930513,discovered That One Channel of Rvlms Inoperable Since Probe Replaced in Oct 1992.On 930507, Discovered That Two Sensors in Rvlms Indicating Wet.Caused by Design Error.Wiring Polarity corrected.W/930611 Ltr ML20024H2281991-05-21021 May 1991 LER 91-003-00:on 910421,actuation of EFW Sys During Plant Heatup Occurred Due to Low Once Through Steam Generator Level.Caused by Leaking Feedwater Recirculation Valve.Plant Startup Procedure OP 1102.02 Will Be revised.W/910521 Ltr ML20024H0861991-05-10010 May 1991 LER 91-002-00:on 910410,inadvertent Actuations of Combined Control Emergency Ventilation Sys Occurred.Caused by Transient Noise Spike.Mod Will Be Completed by 910531 to Install Time Delay in Actuation circuitry.W/910510 Ltr ML20024G9781991-05-10010 May 1991 LER 90-004-01:on 900531,discovered Degraded Fire Barrier Penetration During Insp Per Generic Ltr 86-10.Caused by Failure to Identify Adequate Fire Barrier Seal During 1983 Plant Walkdown.Fire Watch posted.W/910510 Ltr ML20029C3771991-03-22022 March 1991 LER 91-006-00:on 910222,core Protection Calculator Reactor Coolant Sys Flow Channels Not Being Calibrated within Tech Spec.Caused by Personnel Error.Operations Manager Counseled Operators Involved in event.W/910322 Ltr ML20029B1331991-02-27027 February 1991 LER 91-004-00:on 910125,control Room Radiation Monitor Alarm/Trip Setpoint Greater than Normal.Caused by Personnel Error.Operations Manager Will Counsel Shift Supervisors & Night Order Will Be posted.W/910227 Ltr ML20028H6841991-01-21021 January 1991 LER 90-021-00:on 901222,potential RCS Leak Noted in Area of Pressurizer Upper Level Instrument Nozzle.Caused by Pure Water Stress Corrosion Cracking.New Nozzle Installed Into Penetration from Shell OD.W/910121 Ltr ML20043C6801990-05-31031 May 1990 LER 89-025-01:on 891221,identified That Portion of Wall Located in Auxiliary Bldg Had Not Been Previously Identified as Tech Spec Fire Barrier.Caused by Personnel Error.Wall Being Upgraded to Tech Spec status.W/900531 Ltr ML20043C3781990-05-30030 May 1990 LER 90-012-00:on 900430,18 Month Channel Calibr of Liquid Radwaste Effluent Line Flow Monitor Not Performed as Required.Caused by Inadequate Controls to Ensure Followup Actions Taken in Timely Manner.Amends revised.W/900530 Ltr ML20043C0361990-05-23023 May 1990 LER 90-003-01:on 900423,discovered That Incorrect Monitoring Instrumentation for Radiological Effluent Ventilation Sys Utilized to Comply W/Tech Specs.Caused by Mgt Oversight.Logs Process Monitors Will Not Be used.W/900523 Ltr ML20043A7411990-05-17017 May 1990 LER 90-004-01:on 900212,discovered That Backwater Valve in Floor Drain Pipe in Emergency Feedwater Pump Room Missing. Caused by Inadequate Configuration Control.Backwater Pumps Installed & Will Be Included in Maint program.W/900517 Ltr ML20042F7681990-05-0101 May 1990 LER 90-002-01:on 900131,errors Identified in Calculation Used to Establish Calibr Tables for Steam Generator Water Level Transmitters.Errors in Original Calculation Not Identified.Calibr Procedures revised.W/900501 Ltr ML20042F7751990-05-0101 May 1990 LER 90-010-00:on 900401,personnel Failed to Complete Control Element Assembly Position Log.Caused by Surveillance Program Deficiencies & Lack of Mgt Involvement.Shift Briefing Completed & Procedure Change incorporated.W/900501 Ltr ML20042E1981990-04-10010 April 1990 LER 90-008-00:on 900311,determined That Seal Leakage Test for Containment Personnel Air Lock Had Not Been Performed, Per Tech Specs.Caused by Personnel Error.Procedure Revs Initiated & Personnel counseled.W/900410 Ltr ML20012F5051990-04-0505 April 1990 LER 89-027-00:on 891005,determined That Leakage Rate for Containment Isolation Check Valve in Excess of Leakage Rate Allowed Per Tech Specs.Caused by Loose Weld Slag in Valve Seat Area.Valve Cleaned & reassembled.W/900405 Ltr ML20012F5031990-04-0505 April 1990 LER 90-007-00:on 900306,RCS Charging Line Rendered Inoperable Due to Deficient Piping Support Weld.Caused by Inadequate Work Controls & post-installation Insp Processes. Field Walkdowns & Weld Insps initiated.W/900405 Ltr ML20012F5741990-04-0404 April 1990 LER 90-006-00:on 900305,instrumentation Channels Declared Inoperable,Resulting in Manual Actuation of Reactor Protection Sys.Caused by Procedural Deficiencies.Functional Tests of Log Power Level Channels performed.W/900404 Ltr ML20012C7221990-03-14014 March 1990 LER 90-004-00:on 900212,identified That No Backwater Valve Located in Floor Drain Pipe in One of Emergency Feedwater Pump Rooms.Caused by Inadequate Configuration Control. Valves Installed on 900215.W/900314 Ltr ML20012C1821990-03-12012 March 1990 LER 85-029-00:on 850520,unusual Motor Vibrations Identified on Svc Water Pump 2PM4A.On 861028,high Vibrations Noted on Upper Motor Bearings of Pump 2PM4B.Caused by Improper Installation.New Bearings installed.W/900312 Ltr ML20012B7271990-03-0808 March 1990 LER 89-049-01:on 891220,discovered That Okonite T-95 Tape Not Used to Tape Internal Motor Lead Connections for Main Feedwater Containment Isolation Valves.Caused by Personnel Error.Valves Taped According to Design drawing.W/900308 Ltr ML20012B5701990-03-0505 March 1990 LER 90-003-00:on 900201,failure to Perform Monthly Source Check Surveillance on Three Radiation Process Monitors Occurred.Caused by Inadequate Procedure Change by Personnel. Source Check on Monthly Basis implemented.W/900305 Ltr ML20011F6741990-03-0202 March 1990 LER 90-002-00:on 900131,errors Identified in Calculation Used to Establish Calibr Tables for Steam Generator Water Level Transmitters.Caused by Incorrect Static Pressure Assumption.Trip Setpoint Bistable increased.W/900302 Ltr ML20011F6781990-03-0101 March 1990 LER 89-026-00:on 891112,gaps in Piping Supports on Supply & Return Piping for Containment Coolers Identified.Caused by Inadequate Design Technique Used in Original Support Design. Shims Added Before Restart from outage.W/900301 Ltr ML20011F5831990-02-27027 February 1990 LER 89-022-01:on 891114,normal Offsite Power Feeder Breaker to 4,160-volt Ac ESF Bus Opened,Resulting in Loss of Power to Bus 2A3.Caused by Inadequate post-maint Test Controls. Test Switch Opened & Job Order changed.W/900227 Ltr ML20011F7311990-02-23023 February 1990 LER 90-001-00:on 900126,identified That Required Visual Insps of Containment Bldg After Entry Made Not Documented as Being Performed.Caused by Inadequate Procedural Guidance. Administrative Controls to Be established.W/900226 Ltr ML20006D7391990-02-0606 February 1990 LER 89-034-01:on 891031,determined That Tech Spec 3.9.1 Had Likely Been Violated Re Independent Circuits of Control Room Emergency Air Conditioning Sys.Caused by Inadequate Guidance Re Equipment Svc Removal.Procedures revised.W/900206 Ltr ML20011E2371990-01-31031 January 1990 LER 89-012-01:on 890626,RCS Backleakage Through Safety Injection Sys Check Valve Occurred Three Times.Caused by Missing Rollpins Which Connect Valve Disc to Valve Disc Shaft.Rollpins Replaced & Valves reassembled.W/900131 Ltr ML20011E2291990-01-31031 January 1990 LER 89-039-01:on 891116,discovered That Door for Upper North Electrical Penetration Room Open & Latch Mechanism Missing. Caused by Abnormally High Differential Pressure Across Door. Ventilation Sys Flow Balance performed.W/900131 Ltr ML20011E1451990-01-30030 January 1990 LER 89-024-00:on 891231,loose Terminal in Feedwater Control Sys Cabinet Resulted in Reactor Trip.Caused by Loose Connection on Terminal.Loose Connection Reterminated properly.W/900130 Ltr ML20006C1451990-01-29029 January 1990 LER 89-048-00:on 891228,automatic Reactor Trip & ESF Actuation Occurred as Result of Loss of All Main Feedwater Flow Due to Inadvertent Tripping of Main Feedwater Pump. Caused by Personnel error.O-rings replaced.W/900129 Ltr ML19354E3331990-01-22022 January 1990 LER 89-025-00:on 891221,two Piping Penetrations Located in Barrier Not Surveilled as Required by Tech Specs.Caused by Personnel Error.Fire Watch Posted When Necessary Per Tech Spec.W/900122 Ltr ML20006A8661990-01-22022 January 1990 LER 89-041-00:on 891221,automatic Actuation of Emergency Feedwater Sys Initiated.Caused by Lack of Adequate Procedural Guidance.Valve Positioners CV-2623 & CV-2673 Adjusted & Guidance Procedures developed.W/900122 Ltr ML20006A8671990-01-22022 January 1990 LER 89-042-01:on 891209,inadvertent Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Keying of Hand Held Radio in Vicinity of Chlorine Monitors by Technician.Technician counseled.W/900122 Ltr ML20005F1551990-01-18018 January 1990 LER 89-023-01:on 891117,noted That Channel a Not Responding to Change in Power Level & Declared Inoperable.Caused by Defective Preamplifier.Evaluation of Sys Design & Channel Functional Test initiated.W/900108 Ltr ML20006B6461990-01-18018 January 1990 LER 89-047-00:on 891219,RCS Temp Increased Above 250 F W/ Oxygen Concentration Greater than Tech Specs Limit.Caused by Inadequate Procedural Guidance.Plant Startup Procedure Revised to Require Chemistry Dept signoff.W/900118 Ltr ML19354D8291990-01-15015 January 1990 LER 89-044-00:on 891214,incorrect Assumptions & Calculational Errors Identified for Low Pressure Injection & Reactor Bldg Spray Pumps When Aligned to Take Suction from Reactor Bldg sump.W/900115 Ltr ML20005G1681990-01-0909 January 1990 LER 89-045-00:on 891210,discovered That U-bolt Supports on Two Containment Isolation Valves in Containment Bldg Not Installed & Pressurizer Sample Lines & Valves Considered Inoperable.Missing U-bolts installed.W/900109 Ltr ML20005F1481990-01-0808 January 1990 LER 89-042-00:on 891209,inadvertent Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Keying of Hand Held Radio in Vicinity of Chlorine Monitors by Technician.Technician counseled.W/900108 Ltr ML20005F1571990-01-0808 January 1990 LER 89-043-00:on 891208,discovered That Approx 50% of One Nut Ring Half Beneath Reactor Vessel Nozzle Flange Corroded Away.Caused by Gradual Deterioration of Gasket Matl.Design Change implemented.W/900108 Ltr ML20005F2071990-01-0404 January 1990 LER 89-040-00:on 891205 & 06,automatic Actuations of Emergency Diesel Generator Occurred as Result of Loss of Power to 480-volt ESF Bus.Caused by Personnel Error During Bus Transfer.Mgt Briefings conducted.W/900104 Ltr ML20005F0471990-01-0303 January 1990 LER 89-046-00:on 891204,reactor Bldg Isolation Valves Rendered Inoperable Due to Deficient Welds on Piping Supports Which Were Installed During Initial Plant Const. Deficient Supports Repaired Prior to restart.W/900103 Ltr ML20011D2521989-12-18018 December 1989 LER 89-039-00:on 891116,discovered That Door for Upper North Electrical Penetration Room Open & Missing Latch Mechanism. Caused by Extensive Use During 56-day Refueling Outage.More Frequent Insps of Door Condition to Be done.W/891218 Ltr ML20011D2501989-12-18018 December 1989 LER 89-023-00:on 891117,approach to Criticality Commenced After Seventh Refueling Outage W/Logarithmic Power Level Channels Inoperable.Caused by Electrical Noise in Circuitry. Defective Preamplifier replaced.W/891218 Ltr ML19351A6731989-12-14014 December 1989 LER 89-022-00:on 891114,inadequate post-maint Test Controls Resulted in de-energizing 4,160 Volt Ac ESFs Electric Bus Uexpectedly.Caused by Inadequate post-maint Test Controls. Job Order Instructions changed.W/891214 Ltr ML19354D5521989-12-14014 December 1989 LER 89-038-00:on 891114,reactor Trip Occurred as Result of Inadvertent Closure of Main Feedwater Isolation Valve.Caused by Personnel Error.Disciplinary Action Taken Against Individual & Senior Mgt Personnel Put on shift.W/891214 Ltr ML19351A4651989-12-11011 December 1989 LER 89-021-00:on 891111,when Low Level Radwaste Water in Waste Condensate Tank Aligned to Be Released,Discovered That Radiation Monitor Inoperable for Duration of Release.Caused by Personnel Error.Procedure revised.W/891211 Ltr ML19332F6171989-12-11011 December 1989 LER 89-037-00:on 891110,reactor Trip Occurred as Result of Inadvertent Grounding of Reactor Protection Sys Power Supply During Surveillance Testing.Caused by Inadequate Procedure. Procedures revised.W/891211 Ltr ML20005D6821989-12-0101 December 1989 LER 89-005-01:on 890518 & 25,damping Board Removed from Penetration Containing Cable Tray.On 890531,voids Noted in Penetration Seals.Caused by Erroneous Vendor Procedures. Penetrations Restored & Procedures revised.W/891201 Ltr ML19332E8611989-11-30030 November 1989 LER 89-034-00:on 891031,control Room Emergency Air Conditioning Sys Rendered Inoperable Due to Removing Independent Circuits from Svc.Caused by Inadequate Guidance.Procedures Revised & Circuits flagged.W/891130 Ltr 1998-10-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 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 ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
[Table view] |
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f Entcrgy r~n o-naaune-Operations .
tiny 10, 1991 1CAN059101 U. S. Nuclear Regulatory Conimisnion Document Control Desk Hail StatJon PI-137 Washington, D. C. 20555 SUllJECT: Arkansas Nuclear One - Unit 1 Docket No. 50-313 1icense No. DPR-51 1.icensee Event Report 50-313/90-004-01 Centlemen:
In accordance with 10CFR50.73(a)(2)(1)(B), attached is a supplemental report concerning a degraded ilte barrier penetration as the result of personnel oversight.
Very truly yours, e, ,.:)I+i.e w James J Fisicato i Director. Licensing JJF/TFS/mmg Attachment cc Regional Administrator
. Region IV U. S. Nuclear Regulat cory Commission !
611 Ryan Plaza Drive. Suitc 1000 Arlington, TX 76011 INPO Records Center Suite 1500 1100 Circle, 75 Parkway Atlanta, GA 30339-3064 l
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- Expires: 4/30/92 LICENSEE E V I; N T rep 0RT (L E R)
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Nam _Icic11nte Numler Arna lines F. Smtt, Nucimr Safety an! Licmsing Sgwrialist (ble Sj0l19[6j4l-j5j0]Ojo 0111EII: UE LINE RN IW31011RNINT FAlllHE IIRRIBII) IN 11 TIS 15R16 (13J Reportable Reportable Catwc SystmJILun)L tbtittfact. urn loEME Catne fysun Amun1L lilaufacturer to NIME L JJJ_ JlL ! L!I 1 !!
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On Hay 31, 1990 at 1330, while conducting a fire barrior penetration seal inspection as part of a comprehensivo inspection program initiated as part of a Generic Letter ,
86-10 cvaluation, a degraded ffre barrier was discovered by personnel within the fire protection group at Arkansas Nuclear one. Tho deficient. seal consisted of a 2 inch metal sleeve through a floor slab and a 1) inch conduit contained within the ,
sleeve. A review of past documentation revealed this condition has existed prior to a general fire barrier inspection walk down conducted in 1983. Since this condition was not identified during this walk down or subsequent Technical Specification surveillances, the root. cause of this condition has been determined to be personnel error and oversight regarding incorrect procedure identification of penetration-number 97-0038. Upon discovery of this condition, the corresponding firn detection system was verified operable, a fire watch was posted in accordance with Technical Specification requirements, the fire barrier was scaled, and the applicable fire print and penetration log updated. In addition, the fire barrier inspection l proceduro will be revised and a t raining program will bo implemented for firo l barrier inspectors. This supplemental report extends applicability to Unit 2 by documenting a similar event discovered as part of the samo inspection program.
}@C Fom 366A U. S. Nuclear R93ulatnty Caulssicu (6-89) Al ptwui (!!B Mo. 3150-01(A i Expires: 4/30/92 h10NSIT. IMNT RDWT (llR) 1 EXT QNTINUATI(N FACIhlTY N W. (1) IUK17 NLMIER (2) IIR NLMBER (6) p/GE (3)
Supential Revisim Arkansas Nuclear Om, Unit Om _hm Numler Nuniler 0]dOjd0}gjjj 3 9lJ r J_jjj 4 -
_0j 1 d2@jp[6 TEXT (If more space is tupiiral, use tuliticml NRC Form 366A s) (17)
A. plant Status At the timo this condition was discovered, Unit 1 (ANO-1) was in power operat ions at 80 percent. Reactor Coolant. System (RCS) [AB] temperature was 519 degrees Fahrenholt and reactor coolant system pressure was approximately 2155 psig.
At the time discovery of the second condition, Arkansas Nuclear One Unit 2 (ANO-2) was in startup conditions (Hodo 2) with RCS temperature at 545 degrees Fahrenheit, pressure at 2250 psia, and zero percent reactor power.
B. Event Description On May 31, 1990 at 1330, while conducting a fire barrier penetration seal inspection as part of a comprehensivo inspection program initiated to ensure installed snals are in accordance with tested configurations or have adequate basis for installation (l.c., Generic Letter 86-10 cvaluation), a degraded fire barrior was discovered by personnel within the fire protection group at Arkansas Nuclear One (AN0). The degraded fire barrier consisted of a 2 inch metal sleeve extending approximately 3 inches above the floor slab to approximately 22 inches below the floor slab between the cable spreading room and the solid waste filler storage room. A lj inch conduit passing through the 2 inch metal slenvo was surrounded by an open annulus which did not contain a fire retardant seal. The sloove appears to have been used as an equipment drain line, at ono time, with the portion of t.he drain line extending through the floor slab modified into a sleeve and subsequently utilized for the routing of conduit through the fire batrier. The slenvo and conduit pass through penetration number 97-0038 in room
- 97. The sleeve passing through the floor slab was surrounded by an adequate seal and was properly identified in the fire barrier inspection proceduro. The conduit within the sleeve was not surrounded by a seal nor was it identified in the inspection proceduro. Documentation portaining to installation of the conduit indicates that the conduit was routed prior to a major fire barrier walk down effort, conducted in 1983, which served to field verify the adequacy of penetration seals located in either an NRC required fire barrier or insurance required fire barrier. The results of the firo barrior walk down effort were used to supply baselino data for future inspections of fire barrier penetration seals.
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NRb Tom 3f4A U. S. Nuclear Regulatwy Omnissim (6-89) A;ptwul (im tb. 3150-0104 F.xp h es: 4/30/92 LIONSIT. ITINT RDRT (ITR) 'ilXT GriflNUATI(N FACibrIY NAME (1) IIIKl!r NltiHII (2) 11R NMR (6) FAT. (3)
S(quent la1 Revisim Arkansas Nuclear Or, Unit Om _Lm _ . Nirirr Nuset
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A second degraded fire barrier was discovered by ANO fire protectio! -
- on April 17, 1991 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> during a continuation of the comprr' inspect Jon program, fire barrier FB-2081-03 is located between tb penetration room and the heat exchanger equipment area at elevnt' Unit 2 Auxiliary Building [NF]. A small through void was discov, around piping at penetration 2081-03-0029. The through void was c a steady flow of air was dntected flowing into the penetration room On the same barrier air flow was detected at two conduits, penetratiot 2081-0033 and 0034, at t.he condulet covers. The condulet covers are approximately two inches from the barrier.
C. Root Cause Fire barrier penetration seals inspected during the walk down efforc of 1983, including penetration number 97-0038, were ett.her found containing a satisfactory fire barrier seal or were modified to conform with approved fire barrier scalant standards. Hist orical documentation of penetrat ion number 97-0038 indicates that no deficiencies were found with this fire barrier seal during the 1983 walk down. Since existing documentation indicates that the routing of conduit was performed prior to the 1983 walk down, the condition should have been identified during these inspections since inspectlon guidance was availabic to the inspector, llowever, the s leeve configuration was such that it could have misled the inspector to overlook the gap and accept the fire barrier penetration as satisfactory. Additionally, several Technical Specification surveillance procedures for fire barrier penetrations have boon performed since 1983 and also have failed to identify the deficient fire barrier penetration seal. Therefore, the root cause of this condition has been determined to be personnel error and oversight related to the failure to identify an inadequate fire barrier seal during the 1983 walk down effort. A contributing factor associated with this condition may be attributed to the fact that the sleeve through which penetration number 97-0038 passes was not correctly identified in the procedure used to perform Technical Specification inspections. Technical Specification surseillances were conduced by maintenance personnel; whereas, the current fire barrier penetration seal inspection program is being conducted by the ANO fire protection group.
Fire barrier FB-2081-03 was also inspected during the walk down effort of 1983 and documented to be satis factory. The condit ion is believed to have existed prior to the 1983 inspection and should have been identifled during these inspections since adequate guidance was available to the inspector.
Additionally, several Technical Specification surveillances of fIro barrier penetrations have been performed since 1983 and also have failed to identify the deficiencies. Therefore the root cause of this condition is personnel error related to the failure to idnntify an adequate fire barrier seal during the 1983 walk down effort.
Ni[CIbiu366A U. S. Nuclear Rg;ulatory Cuelsshu (6-W) A;pmvol (UB No. 3150-0104 f>pires: 4/30/92 1.lC17NT. IMNT KPJWF (IIR) 'l1XT QNflNDATilN fW:llJIY fWE (1) l lIIKl?f NtM10R (2) U2LtMREIA) pNE E S<rpot f al Revision Arkansas Nacimr Gie, Unit Om _hnt _ _N&r _Nmb.L 0l5l0j0[0l 3j 1[3 9Lo -
_o 1-ol_^
o11_ ol4lcFlol6 WXT (if nnin space is tnpiirni, use adlitia.ial NRC Form 36M's) (17)
D. Corrective Actions Upon discovery of this condition, the fire det ection system for the cable spreading room was verified operable and a fire watch was posted in accordanco with Technical Specification req'tirements. The fire barrier was scaled through a job request Jr.itiated to ensure the annulus between the sleeve and conduit was adequntely enclosed. In responsn to identifying the ftre barrier penetration for future inspections, the new fire barrier penetration designation for sloove (97-0127) has been listed on flic print 97-1 and entered in penetrat. ion 1.og fB-00-bl. This should be e f fect ive in providing a cue to inform the fire barrier inspector t bat. t his penet rat.f on exists and requires inspection during future inspactions.
Add i t ional ly , fire barrier inspection procedure (1405.016) will be revised to correctly identify the new designated fire barrier pennt. ration. This action will bn complet.ed by August 1, 1991. These actions are in addition to the current ftre barrier seal inspectton program which is part of the AND Busines;.
plan ( Act ion D.5.C) scheduled for complet ion pr ior to December 31, 1991. The objectives of thn assessment program are to verify the physical configuration of Technical Specification penetrat ion seals, per form evaluations of seal designs when deviations arn identified, develop a data base and procedures for seal configuration management, and the correction of identified deficiencies.
To providn addit on t guidance to the fire barrier penetration seal inspector on the correct methc 1 inspect ing firn barrier penetrations , a training program will be developed addressing the identification of defic ient conditions. The training program also will present a discussion of penetration scalant material and possibin conditionn rendering particular sealant materials deficient. This program is schedulod for Jovolopment by September 1, 1991.
Upon discovery of the second degraded fire tarrier, the firn detection system for the area wa= verified to be operable and a fire watch was posted in accordance with Technical SpecificnLion requirements. A job request was init iated t n repair the deficiencies.
E. Sa fety Signi ficance This condition has pot ential safety significance considering that the deficient firn barrier seal provides protect.fon for the cable spreading room. A fire spreading to the cable spreading room could result in degraded plant cont.rol due to possible conductor damage associated with Control Roam i ns t.rumen t a t ion . The degree of dnmage to Control Room instrumentation is dependent on the naturn and extent of the ftre within the cable spreading area. plant control in the event of a fire in the cable spreading room is addressed through abnormal operating procudure 1203.02.
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, a Nku Fonn 366A U. S. Nucinar Regulatory Comissico
. (6-89) A; pro mi O!B No. 3150-0104 i' . F.xpires: 4/30/92 1.10NSEF. IMNT ElWf (IIR) '11Xf QNf1NUAT][N FAC11,ITY NAME (1) IU KCf NtNBIR (2) 112 NUMIER (6) IW1E (3)
Supmntial Revisien Arkansas Nuclear O m, Unit O n Year Egler Numler l0{5j0l0}%3[lL3_9] O --
0 LQl 4 --
011 0l5}T{Q]6
- 11Xf (If more sincn is rapiiral, use ackliticnal Nhc lbnu 366A s) (17)
In nr.tuality, the firn proventativo measures currently available make the spread of fire in these areas only remotoly possible. Theso measures include a fixed fire detection system in the cable spreading room which provides alarm annunciation in the ANO-1 Control Room, fire suppression equipment in the form of firo extinguishers, fire water hose rnols, and an automatically actuated system. Fire Brigado personnel, specifically trained in fire fighting, are available at all times in the unlikely event a fire worn to occur. Although the seal was degradod, tho ava11ah111ty of detection instrumentation, suppression equipment, and Firo Brigado pnrsonnel prmido adequate protection against firo propagation. Thereforo, thoro la not a safety concern related to the degraded seal.
The second degraded fire barrior had less safety significanco because the areas on either side of the barrier did not contain as much potentially combustible material and a large number of cables associated with Instrumentation and control were not involved. Firo detection instrumentation and Fire Brigado personnel were also available if a fire worn to have occurred in the area of the second degraded barrior.
At the ANO sito there are approximately 8600 total penetrations through plant firo barriers. Approximately 5,000 penetrations have already boon reverified with only the two barriors addressed in this report being identified as deficient. Therefore, considering the small population of deficient penetrations which have been identified, the safety concerna as they relate to potentially existent conditions are relatively small for thu remaining number of seals.
F. Basis For Reportability Technical Specifications require that all penetration fire barriors protecting safety related areas shall be operable. With onn or more of the required penetration fire barriors inoperable, a continuous fire watch must be established in the affected area within one hour. Although the fire watch was established within one hour of discovering the deficient fire barrior, investigation of the cordition revealed that it had most likely existed for greater than one hour iithout a fire watch established. Therefore, this event is reportable pursuant to 10CFR50.73(a)(2)(1)(B) as a condition prohibited by-Technical Specifications.
I l
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hM: Pom 3(M U. S. Ntclear Rmilatory Osn(ssim
'(6-89) Al pttun! 01B No. 3150-0104
- Fxpirm: 4/30/92 LIQA97. IMNT IGMET (!JR) UXT QNflM1ATi(N FN:ll.rlY NRW: (1) IHM:f MH111R (2) 11R MMIFR (6) IWiE (3)
Snitusititil Revinlai Arkamas Nuclear Om, Unit Om Ynnt _&tmlet__ latgrt_
0}5}0j0j.0l3dj3_9l0-- 0 LOj 4 --
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UXf (1f mre spim is rulu.IrnI, use akiitlavil NRC l'orm 36(A,n) (17)
G. Additional information Condillons involving inadequate fire barrier seals in conjunction with personnel related nrror were previously reported in Licensen Event Reports 50-368/88-018, and-50-368/90-013.
A revision to this Licensco Event Report will be submitted by January 31, 1992 to document additionr.1 inadequate fire barrier seals identified as part. of thn current 11ro Larrict inspect ion J. rop, ram.
Energy Industry Identification System (Ells) codes are identified I. the text as (XX].
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