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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] |
Text
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. . ; j Aruns,as Power & UpM Congany t.,, _j /ma mas twe:: Ox
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! December 1, 1989 l 2CAN128965 L
l U. S. Nuclear Regulatory Commission L- Document Control Desk {
Mail Station P1-137 Washington, D. C. 20555
SUBJECT:
Arkansas Nuclear One - 1. nit 2 Docket No. 50-368 License No. NPF-6 Licensee Event Report No. 50-368/89-005-01 Gentlemen:
In accordance with 10CFR50.73(c)(2)(1)(B), attached is the subject supplemental report concerning inadequate procedural guidance which resulted in voids in the sealant material of penetration fire barriers, rendering the barriers non-functional. Arkansas Power & Light Company previously committed to provide a supplemental report of additional discoveries of penetration fire barriers which did not meet the requirements of Technical Specifications upon completion of the inspections.
Very truly yours, a_.
E. C. wing General Manager, Technicti Support and Assessment ECE/DM/sgw Attachment i cc: Regional Administrator l Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 INPO Records Center 1500 Circle 75 Parkway ,
Atlanta, GA 30339-3064 pl 8912140118 891201 t I I PDR AI'OCK 05000368 S PDC.
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- I Form 1062.01 A i NRC Fore 366 U.S. Nuclear Regulatory Commission
-(9 83) Approved One No. 3150-0104 Expires: 8/31/85 LICEN5EE EVENT REPORT (LE R)
FACILITY NAME (1) Arkansas Nuclear One, Unit Two (DOCKET NUMBER (2) IPAGE (3) 10161010101 31 61 81)LQf,19J} i TITtt (4) Inadequate Procedural Guidance Resulted in Voids in sealant Material of i Penetration Fire Barriers Rendering the Barriers Non Functional IVENT DATE (5) LE R NUMBE R (6) i REPORT DATI (7) OTHER F ACILITIES INv0tvED (8) 1 l 15equentiell IRevisioni !
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I Month! Day lYear lYear l l Number l l Number Monthi Day lYear 1 Facility Names )ocket Number (s) l i i i i l )1 0 0101 1 ,1 , j I i i 1 I >
0! 51 11 81 81 91 Of 91--! 01 01 61--I Of 1 11 21 01 11 81 91 i)I ,
0 10101 I l_
OPERATING 1 ITH15 REPOR1 15 5UBMIT1ED PUR5uANT "O THE REQUIREMEN16 0F 10 CFR 5:
MDDI (9) i 11 (Check one or more of the followinn) (11)
POWERI l _ I 20.402(b) I,,_,1 20.405(c) l_ I 60.73(a)(2)(iv) 1.,,,1 7 3. 71(b) ,
LEVEll 1 ,,,1 20.405(a)(1)(1) 1.,,,1 60. 36(c)(1) l _ l 50.73(a)(2)(v) l_l 73.71(c)
(10) 1110101 1 20.40$(a)(1)(11) l_ l 50.36(c)(2) l _l 60.73(a)(2)(vii) l_ l Other (Specify in '
l _ l 20.405(a)(1)(111) 1 JI 60.73(a)(2)(1) I,,,,,1 60,73(a )(2)(v111)( A)1 Abstract below and I,,,1 20.40$(a)(1)(iv) l . ,,,1 50. 73(a)(2)( t i ) l_l 60.73(a)(2)(viti)(B)1 in Text, NRC Form I l 20.40$fa)(1)(v) I i 60.73:o)(2)(111) 1 I b0.73:o)(2)(x) 1 366A)
LIC iNSEL C0h1ACT FOR TH15 L :R (2) ,
home 1 Telephone Nweber lArea 1 ]
Dana Millar, Nuclear Safety and Licensing Specialist l Code l l
$10111916141 13111010 i COMPLETE ONI tlNE FOR EACH COMPONENT F AltVRE DESCRIBED IN THIS REPORT (J) l l l lReportablel l l l l lReportablel Causel5ystool Component IManufacturerl to NPRD5 I ICouselsysteel Comoonent (Manufacturer to NPRDS I l l 1 1 1 1 I i ,
I I I I I l l I I I I I i l I l I I I I i l I i l l l t i i i i l i , I I
I I l l l 1 l l 1 l i I I I I I I I I I I l I fiUPPLEMEN" REPORT EXPECTCD (la) l EXPECTEI) i Month Day Year
~
l $UBMISSION 1 l l Yes (If ves. conolete Exoected Subsission Date) III No I DATE (15) I i I i l l ABSTRACT (Limit to 1400 spaces, i.e. , approximately fif teen single space typewritten lines) (16) l in May 1989 AP&L initiated a plan to conduct non-routine inspections of penetration fire barriers l located in wall blockouts that contain silicone foam material with fire-retardant (damming) boards on both sides of the penetration as a result of NRC Information Notice 88*b6,
- Potential Problems with j Silicone foam Fire Barrier Penetration Seals". As a result of the inspections, twenty-four penetrations l l located in various fire barriers separating plant fire areas were identified with voids in the silicone i i foam material, rendering each penetration f f re barrier non-functional. As required by Technical
( 5pecifications, a fire watch was established within one hour of discovering the degradation in the seals.
i in each affected area fixed fite detection systems and fire suppression equipment are available to help ;
l prevent the spread of a fire, therefore, the safety significance is minimal. Additionally, trained fire brigade personnel are continuously available. Initial seal installation procedures used to install the '
l I silicone foes material were inadequate to ensure voids did not exist. Procedure revisions have been made to require removing of the damming boards on both sides of the barrier when performing repairs to previously sealed blockouts. Additional procedure revisions for new seal installations are in progress.
Repairs have been completed to restore each of the identified seals to the functional capability required by Technical Specifications. The ins. sections of the penetration fire barriers have been completed.
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. l Firm 1062.018
.NRC Foin 366A U.S. Nuclear Regulatory Commission (9 63) Approved OMB No. 3150 0104 LICEN5ft EVENT REPORT (LER) T[XT CONTINUATION FACILITY MAME (1) IDOCKCT NUMBER (2) l ttR NUMM R (6) l PAGE (3) l l l 15equentiell l Revision]
Arkansas Nuclear One, Unit Two i I Yearl I Number l l Number l 10151010I0I 31 61 et et 9f--t 01 01 bi--I of Il01210F10lb l TEXT (If more space is required, use additional NRC Form 3660 s) (17) l A. Plant Status At the time of discovery of the findings discussed in this report, Arkansas Nuclear One, Unit 2 l (AND-2) was in Operational Mode 1 (Power Operations). Reactor power level varied between 70 percent i and 100 percent full power. The seventh refueling outage on AND-2 began September 25, 1989 and ] !
ended November 22, 1989. I B. Event Description ]
In May 1989 special non-routine inspections of penetration fire barriers located in wall blockouts l I that contain fire-retardant (damming) boards on both sides of a penetration were initiated as a l j result of NRC Information Notice 88-56, " Potential Problems with 5tlicone foam Fire Barrier "
i Penetration Seals". The Information Notice discussed the potential that 60ew of the installed fire t'arrier penetration seals (PEN / SEA Q , specifically silicone foam, may not meet minimum requirements due to voids, gaps, splits or lack of fill material. Previous inspections of penetrat o fire barriers were those required by Technical Specifications, which require a visual inspection 91 the barriers at 1sast once per 18 months. While performing visual inspections, if a damming I coord is present, the integrity of the board is inspected, however, the inspection procedure does I I
not required the removal of the damming board and the inspection of the sealing material found i between the damming boards (e.g., st11 cone foam). Therefore, any degradation of a fite barrier.
due to the silicone foam material being inadequate, would not be identified during a routine visual inspection of a penetration tire barrier. A plan was established to inspect approximately )
twenty-five percent of the penetration fire barriers located in wall blockouts. 1 On May 18, 1989, when the damming board was removed from a penetration located in a well separating a corridor from an Engineered Safety Features switchgear room, a void was found in the silicone foam material. The penetration, containing a cable tray, is a twenty-two inch by ten inch opening ,
in a three-hour rated fire well, which is approximately twelve inches thick. The void in the !
silicone fome material was approximately seven inches in depth in a seal that contains ten inches j of silicone foam material, and apparently had existed since plant construction. Upon discovering i the void after the damming board was removed, the penetration fire barrier was comidered non-functional l i
and a fire watch was appropriately es i lished within one hout as required by Technical Specifications.
l On Nay 25, 1989, when the damming board was removed from e penetration located in a well separating a corridor from the turbine building, a void was found in the silicone foam material. The penetration, ;
containing a cable tray, is an opening thirty-six by eighteen inches located in a three-hour rated J fire wall approximately eighteen inches thick. The degradation consisted of a hole aproximately '
two inches in diameter and eight inches in depth in a seal that contains ten inches of silicone I i foam material. Plant modifications had been made in April 1985 which required the seal to be i repaired. At the time the void was identified, a fire watch was already established in the affected area.
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- On May 31, 1989, while continuing the inspections, two additional penetration seals were identified i l
with voids in the silicone fomm material. Both penetrations are located in a three-hour rated )
I fire wall, which is approximately twenty-four inches thick, that separates an electrical equipment 1 room from the cable spreading room. Each seal contained approximately ten incnes of silicone ;
l foam material. One penetration, containing a cable tray, is a forty-tvo by fourteen and one half j
inch opening, The void, located below the cable tray, was approximately four inches in diameter .
and nine inches deep. Plant modifications were made in October 1984 which breached the seal and required repair to the seal. The other penetration, containing a cable tray and conduit, is an opening approximately forty-two by seventeen inches. The void was approximately two inches in diameter and six inches deep. Although, plant modifications were made that required the seal to ,
be breached in a refueling outage in 1986, the location of the void would not have been af facted (
by the modification, therefore, the void apparently existed since plant construction. A fire watch was already established in the area when the voids were identified.
As the non-routine inspections of penetration fire barriers that contain fire retardant damming boards on both sides of a ponctration were continued, between July and September 1989, twenty additional fire barriers were identified as degraded. AP&L has inspected one hundred percent of 1 the penetration fire barriers located in wall blockouts that contain fire-retardant damming boards 1 on both sides of a penetration. See Table 1 for a listing of the penetrations, date identified, locations, void sizes and available fire detection and suppression equipment. The inspections and repairs of the identified barriers have been completed. When each penetration fire barrier was identified to be degraded, a fire watch was established as required by Technical Specifications.
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- I Form 1062.01B WRC Fore 366A U.$. Nuclear Regulatory Commission ,
-(9-83) Approved OMB No. 3150-0104 d Expires: 8/31/85 !
LIC[NSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY MAME (1) (DOCAET NUSER (2) l L(R NUMB [R (6) l PAGE (3) )
l l l lhequentiell IRevisionl i Arkansas Nuclear One, Unit Two l l Yearl i Number 1 1 Number.l j 10t$t010101 St 61 81 81 9t--I 01 Of St--I of Il01310F10lb i TEXT (If more space is required, use additional NRC Form 366A's) (17) l l
C. Safety significance i The effected plant fire eress and the adjacent areno (with the exception of the turbine building), i to each identified penetration which was ditcovered to have degraded silicone foam material, are l equipped with fixed fire detection systew (ionization type smoke detectors) with annunciation in I the AMO-2 Control Room. A protective wire fire detection cystem also existed in the cable spreading room. Each of these fire detection systems is required to be operable by Technical $pecifications.
Additionally, fire suppression equipment is located in each af fected area, in the form of fire i extinguishers or fire water hese reels. The cable spreading room, also, has a fixed automatic I suppression system that is required by Technical specifications. Fire Brigade personnel, specifically trained in fire fighting, are available at all times in the unlikely event a fire were to occur.
Also, the affected areas are easily accessible by personnel. Although the seals were degraced, considering the combination of the fixed detection, suppression equipment availability, and the response of the fire brigade personnel, significant protection against the spread of a fire existed. Therefore, the safety significance of the degraded seals is minimal.
D. Root Cause During initial plant construction, vendor procedures were used for the insteilation of silicone foam fire barrier sealant material and damming boards. The instructions included in the procedure did not specifically require an inspection of either side of the foam material after it was injected into the penetration. A plant specific procedure for seal installation was written and implemented in October 1985. Also, a training program was established to train personnel on j installation of seals. However, the procedure required that only one side of the foam seal be !
inspected for voids prior to the final damming board being installed. Inspection of only one side I of the seal was not adequate to identify a problem with voids in the material, j
[ach of the identified rsnetrations that was found degraded had silicone foam material installed I per the vendor procedure and therefore, post installation inspections were not required to be i performed. Without inspections any voids that may have been present in the silicone foam material j would not be identified.
E. Basis for Reportability Technical Specifications requiee that all penetration fire barriers protecting safety related I areas shall be functional at all times. If one or more of the required penetration fire barriers is non-functional, a continuous fire watch shall be estabitshed on at least one side of the affected penetration within one hour. When each of the barriers was identified as being non-functional, a fire watch was established within one hour as required by Technical Specifications. However, the barriers had been non-functional for greater than one hour, therefore, these events are reportable i per 10CFR$0.73(a)(2)(1)(B).
F. Corrective Actions Repairs have been completed to restore each identified penetration to the functional capability require.' by Technical Specifications. Procedure revisions have been made to require the removal i of the damming 1. cards on bu*at sides of the barrier when performing repairs to previously sealed l blockouts. To ensure both sides of the sealant material are inspected when performing new seal installations, an evaluation of the procedure is in progress and final revisions will be completed by December 31, 1989.
G. Additional Information There are no previously reported similar events related to degraded silicone foam material in penetration fire barriers.
Inspections of penetration fire berriers on Arkansas Nuclear One, Unit One have been initiated and no degraded seals have been identified to date. Only one barrier remains to be inspected and I it will be inspected by December 31, 1989 I Energy Industry Identification System (EII5) codes are identified in the text as (XX).
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. I Firm 1042.013 l NRC Fem 366A U.S. Nuclear Regulatory Coenlission +
j (9 83) Approved 006 No. 3150-0104 l
tapires: 8/31/85 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION l FACILITY NME (1) l DOCKET NVISER (2) l .ER WUDGER (6) l PAGE (3) l l I i i Lequentiali IRevisioni Arkansas Nuclear One. Unit Two I i Yearl i Number I i Number i ;
10151010101 31 61 81 8) J,j,- I Of 01 51--I 01 Il01410F1015 TEKT (If more space is required, use additional NRC Fore 366A's) (17) J l
Table 1 ]
Date Fire 8errier Location - Void Size Fire Detection / Fire l Note 3 Number Fire Zone Note 1 Suppression Eouipment q 1
7 10-89 2104-08-133 Diesel Generator Access Three Voids ionization Type Smoke i l
Corridor and Notor Control 1) 10x3x10 Detectors and Protectowire Center 372 Elevation 2) 2x2x3 with Control Room Auxiliary 8u11 ding (A8) 3) 2x2x2 Annunciation. Open head sprinkler system.
Note 2. ;
1 10-89 2104 07-0115 64x14x6 i 7 12-89 2104-02-0073 2x5x10 2104-02-0083 24x24x10 7-31 89 2104 07 0121 Two Voids
- 1) 4x8x6
- 2) 2x2x6 7 10-89 2098-04 0072 Cable Spreading Room 6x14x6 Protectowire and ionization 372 Elevation AB type smoke detectors with Control Room Annunciation.
Closed and open head sprirkler systems. Note G.
7 25-89 2098-07-0091 2x2x10 7-28 89 2098-06-0089 Unknown-2098-06 0093 Airflow between rooms 1 I
7-31 89 2111-05-0001 Lower South Electrical 3x1x10 lonization Type Smoke Penetration Room. Detectors with Control Roon 372 Elevation AB annunciation. Pre-action closed head sprinkler systes. ,
Note 2.
8-7 89 2111 07-0017 Two Veids
- 1) 4xbx10
- 2) 4x5x10 8-9-89 2076-02-0057 Electrical Equipment 4x4x10 lonization Type Smoke (Notor Generator Set) Detectors with Control Room Room. 354 Elevation annunciation. No fixed fire A8 suppression equipment. Note 2. ,
8-10-89 2073-05 0140 Access Corridor; Pump %x3x10 lonization Type Smoke Detectors 2073-05-0152 and Tank Area 1x20x10 with Control Room annunciation.
354 Elevation AB No fixed fire Suppression.
Note 2.
4-15-89 2073-05-0135 4x10x10
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. s Form 1062.018 NRC Forn 366A U.S. Nuclear Regulatory Commission (9-83) Approved 04 No. 3150-0104 Empires: 8/31/85 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY M4NE (1) 100CKET NUS ER (2) l '.ER NLSSER (6) l PAGE (3) l l l l3equentiell lRevisioni Arkansas Nuclear Otse. Unit Two l l Yearl Number i Number l 10151010101 31 61 el el 91-- 01 01 5 --t Ot it01510F1015 TEXT (If more space is required, use additional NRC Fors $66A's) (17)
Table 3 Date Fire terrier Location Void Site Fire Detection / Fire Note 3 Number Fire Zone Note 1 Suporession Eouisment 9*29 89 2081-04-0037 Upper North Pipin0 3x,20x9 fonfration Type Smoke Penetration Area. Detectors with Control 354 Elevation AB Room annunciation. No fixed fire suppression equipment. Note 2.
8 13-89 2017-05-0063 Access Corridor, Boron 4x24x10 Ionization Type Smoke Mana0ement System Detectors with Control Area (Fire Zone 2040) Room annunciation. No 335 Elevation AB fixed fire suppression equipment. Note 2.
9-13-89 2055-05-0049 Lower South Piping 3x13x9h Iontratien Type Smoke Penetration Room Detectors with Control 335 Elevation AB Room annunciation. No fixed fire suppression equipment. Note 2.
9 14 89 2055 02-0137 4x4x9 9-14 89 2055 07-0173 14x14x9%
NOTE 1: Each void site is listed in inches with the last dimension being depth. The approximate thickness of the silicone foam material in each penetration is ten inches.
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NOTE 2: Manual fire suppression equipment in the form of portable fire extinguishers and fire hose reels are available. The area is easily accessible by fire brigade personnel.
NOTE 3: The identified date is the date of discovery of the degraded fire barrier.
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