|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H SNRC-1423, Part 21 Rept Re Accdos (HP-85) & Rms Computer Codes. Initially Reported on 880126.Engineering Change Request Implemented Involving Rms Computer Code Software & Should Be Completed by Feb 19881988-01-29029 January 1988 Part 21 Rept Re Accdos (HP-85) & Rms Computer Codes. Initially Reported on 880126.Engineering Change Request Implemented Involving Rms Computer Code Software & Should Be Completed by Feb 1988 SNRC-1386, Part 21 Rept Re Forged Steel Fittings Mfg by Std Fittings Co & Inspected by X-Ray Insp,Inc.Investigation Still Going on & NRC Resident Inspector Will Be Informed of Util Findings & Remedial Action to Be Taken for Fittings Requiring Rework1987-12-21021 December 1987 Part 21 Rept Re Forged Steel Fittings Mfg by Std Fittings Co & Inspected by X-Ray Insp,Inc.Investigation Still Going on & NRC Resident Inspector Will Be Informed of Util Findings & Remedial Action to Be Taken for Fittings Requiring Rework SNRC-1388, Part 21 Rept Re Defects in GE Termination Lugs Used for Control Wiring in 4160 Volt Switchgear Equipment.Initially Reported on 871016.GE Advised That Wire Will Be Stripped W/ Stripping Tools Which Incorporate Stops to Control Length1987-10-19019 October 1987 Part 21 Rept Re Defects in GE Termination Lugs Used for Control Wiring in 4160 Volt Switchgear Equipment.Initially Reported on 871016.GE Advised That Wire Will Be Stripped W/ Stripping Tools Which Incorporate Stops to Control Length SNRC-1366, Part 21 Rept Re 2 Inch 90 Degree Elbow Forged Steel Fittings Mfg by Std Fittings Co & Inspected by X-Ray Insp Inc. Existing Plant Documents Will Be Reviewed in Attempt to Locate Listed Identified Fittings & Completed by 8709301987-08-14014 August 1987 Part 21 Rept Re 2 Inch 90 Degree Elbow Forged Steel Fittings Mfg by Std Fittings Co & Inspected by X-Ray Insp Inc. Existing Plant Documents Will Be Reviewed in Attempt to Locate Listed Identified Fittings & Completed by 870930 ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken ML20210S3351987-02-0404 February 1987 Part 21 Rept Re Cracking in O-ring on Latch Mechanism on Contactors in Nuclear Exciters.Initially Reported on 861216. Sprecher & Schuh Changed O-ring Matl to Viton E60C. Contactors Will Be Returned to Vendor & Rebuilt ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20141A1081986-03-31031 March 1986 Part 21 Rept 134 Re Potential Defect in K-1 Relay in Generator Voltage Regulator.Initially Reported on 860219. Corrective Action Must Take Into Account Equipment Operating Range of 100-137.5-volt Dc ML20154K3611986-03-0505 March 1986 Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328 ML20137X3891986-02-27027 February 1986 Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors Defective ML20153G1021986-02-19019 February 1986 Part 21 Rept Re Potential Defect in K-1 Relays of Dsr or Dsrv Standby Diesel Generators Mfg by Gould/Ite.Relays Have Incorrect Voltage Range.Dc Voltage Source or Voltage Regulator Circuitry Requires Mod ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20132D4141985-09-25025 September 1985 Part 21 Rept Re Defective Rochester Instrument PR-2035 Under Voltage Relays Exhibiting Tendency to Drift from Designated Setpoint &/Or Inability to Maintain Deadband Adjustment. Investigation Continuing.Final Rept by 851011 ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc SNRC-1197, Interim Deficiency & Part 21 Rept Re Procurement & Installation of Coils & Starters for Square D Co 480-volt Motor Control Ctrs.Initially Reported on 850719.Matls & Stock Numbers Revised1985-07-23023 July 1985 Interim Deficiency & Part 21 Rept Re Procurement & Installation of Coils & Starters for Square D Co 480-volt Motor Control Ctrs.Initially Reported on 850719.Matls & Stock Numbers Revised ML20128N4981985-07-22022 July 1985 Part 21 Rept Re Tendency of Rochester Instrument Sys Undervoltage Relays Installed in Emergency Switchgear for Degraded Voltage Protection to Drift from Calibr Setpoints. Defective Relays Replaced SNRC-1189, Forwards Summary Description of Util Resolution Re Tdi 10CFR21 Notifications Issued After 840401.Util Will Inform NRC of Actions Re Future Tdi Part 21 Notification Until Final SER Issued in Jul 19851985-06-28028 June 1985 Forwards Summary Description of Util Resolution Re Tdi 10CFR21 Notifications Issued After 840401.Util Will Inform NRC of Actions Re Future Tdi Part 21 Notification Until Final SER Issued in Jul 1985 ML20127H5411985-05-17017 May 1985 Part 21 Rept Re Potential Defect in Engine Generator Control Panels of Dsr or DSRV-16 Standby Diesel Generator.Review of Generator Control Panel Installation by Each Facility Recommended ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20112J7061985-04-0202 April 1985 Part 21 Rept Re Possible Defect in mineral-insulated Cable Assemblies.Design,Mfg & Qualification Testing of high-range Containment Area Monitoring Sys Completed.Design Qualification Rept Encl ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed ML20112A0701985-03-0606 March 1985 Part 21 Rept Re Cracked Weld in Coil Guards - Conical Baffle.Lilco Has Copy of Weld Procedure WPS-402-700510, Rev 0 & Will Arrange to Perform Repairs SNRC-1130, Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 8412081984-12-28028 December 1984 Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 841208 ML20101P9361984-12-20020 December 1984 Part 21 Rept Re Fatigue Cracks on Fuel Injection Pump Delivery Valve Holders of PC-2 & PC-2.3 Emergency Diesel Generators.All Valve Holders W/Improper Radius Will Be Replaced SNRC-1112, Deficiency Rept Re Apparent Accelerated Corrosion in Four Reactor Bldg Svc Water Strainers Mfg by RP Adams Co,Inc. Initially Reported on 841015.Two Strainer Welds Repaired Under ASME Section XI Article IWD-40001984-11-27027 November 1984 Deficiency Rept Re Apparent Accelerated Corrosion in Four Reactor Bldg Svc Water Strainers Mfg by RP Adams Co,Inc. Initially Reported on 841015.Two Strainer Welds Repaired Under ASME Section XI Article IWD-4000 ML20106D3831984-10-0808 October 1984 Part 21 Rept Re Adjustment of Low Voltage Shutoff & Turnon for GE Dedicated Inverters Improperly Set.Utils Notified to Check & Readjust as Necessary ML20084L1151984-05-0808 May 1984 Suppl 1 to Part 21 Rept Re United Electric Controls Fuel Oil Filter Differential Pressure Switches at Shoreham Plant. Switch Also Provided to Listed Plants.Corrective Actions Defined in 840328 Rept Will Be Applied ML20083P9801984-04-0909 April 1984 Part 21 Rept Re Broken Engine Driven Lube Oil Pump Discharge Nozzle Boss.Caused by Overtorquing of Tapered Thread Adapter.Adapter Changed to Straight Threads W/Undercut ML20087P8711984-03-28028 March 1984 Part 21 Rept Re Two Failed Fuel Oil Filter Differential Pressure Switches.Caused by Pressure Pulsation on Low Pressure Side of Switch.Switch Replaced ML20113C6001984-03-26026 March 1984 Discusses Bonney Forge Part 21 Rept.S&W Notified That Evaluation Required Re Matl Delivered to Shoreham Not Meeting Nca 3967.4(e)(2) Requirements SNRC-1018, Interim Deficiency Rept Re Failure of Turbocharger on Emergency Standby Diesel Generator.Temporary Bypass Valve Around Turbocharger Prelube Drip Line Orifice Installed. W/Certificate of Svc.Related Correspondence1984-03-0909 March 1984 Interim Deficiency Rept Re Failure of Turbocharger on Emergency Standby Diesel Generator.Temporary Bypass Valve Around Turbocharger Prelube Drip Line Orifice Installed. W/Certificate of Svc.Related Correspondence 1997-05-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02:on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired 05000322/LER-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1988-0151990-05-16016 May 1990 LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 05000322/LER-1986-0141990-05-16016 May 1990 LER 86-014-01:on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153 05000322/LER-1987-0121990-05-16016 May 1990 LER 87-012-01:on 870504,uplanned Actuation of ESF Occurred. Caused by Technician Loosing Footing & Accidently Hitting Outside Cover of Level Switch.Permanent Ladders & Platforms Installed at Head Tank Level Switches 05000322/LER-1988-0171990-05-16016 May 1990 LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned 1997-05-01
[Table view] |
Text
sownwoomooomacowro m o m w - wm
. b hne.i W er PART 21 IIERIFICATION NO. %-W-M CU PANY tW E_ M wuM b o-u DATE OF LETTER. nldeo D00(ET NO. I'$o-32L DATE DISTRIFlIED iddte 0 m-ORIGINALREPORT SUPPLEBRARY % I'
~
DISTRIBlHION: N EACTOR (R) g REL CYCE & SAEGil4RDS (3 j ~.
FATERIALS (FD-~
IE FILES IEF15!S s EES IE FILES AD/SGb ;
AD/ FREI AD/ROI EGIONS I,II,III,IV,V EGIONS I,II,III,IV,V EGIONS I,II,III,IV,V VS00R BR. R-IV ECOR BR. R-IV E00R BR. R-IV LOEB / FPA FIG 5715 NFSS / FCFS SS-395 NPWDOL AEOD DIB 7602 LOEB/FFA FIB 5715 IES / SG SS-881 NRP/ DOE AEOD 018 7602 LDEB / PPA FIG 5735 NRR/DSI. ASLBP E/W 450 AEOD FIG 7602 NMT -
3Aof3p p;g_7210A ASBP E/W 450 NRR/ DOL CENTPAL FILES 016 GERAL FILES 016 ASLBP E/W 450 CBERAL FILES CENTRAL FILES ( GRON) (GR0iG CSERALFILES 016 PDR CBURAL FILES SS-395 l C&JRAL FILES (GRDBD iPDR PDR PDR TEPA [PDR LPDR TERA b '
l ACTION:
l PRELIMINARY EVALUATION OF THE' ATTACHED REPORT ItOICATES EAD RESPONSIBILITY FOR FOLLO'dJP AS SH0hN BELOW:
IE
. { , NRR 2 IES 2 OlER EES PS', 8/1/80 8 01212 U (o(Y 8 An\so
_ __ _ _Mdio
n 2c. b ).- p D *~ K.. <w . . . . . . :
' C.
STONE & WEBSTER ENGil4EERING CORPORATION
. 245 SUMMEn STREET. B O ST C N. M ASSACHUScTTS g .
ADDR ESS ALL COR R E SPON DENCE TO P.O. B OX 2325. BOSTON. M A S$. 02107 W U TELEX 94 0001 s0570% 94-0977 D. S t.N C mm MIL L. N J. PO S
%~CY."o "'01'ri:."
" ='. 0.. m ..o M W.SMa G ON. O C.
Mr. Victor Stello December 2, 1980 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stella:
NOTIFICATION OF DEFECT, 10CFR21 SHOREHAM NUCLEAR POWER STATION - UNIT 1 LONG ISLAND LIGHTING COMPANY Stone & Webster Engineering Corporation (S&W), pursuant to the provisions of 10CFR21 hereby provides notification of a " defect" concerning the Shoreham Nuclea7 , Power Station, Unit 1, owned by Long Island Lighting Company (LILCO) and for which S&W provided both engineering and construction services.
In accordance with the requirements of Section 21.21(b)(3), the following information is submitted:
- 1. Name and address of the individual informing the Commission:
Mr. P. A. Wild Director of Engineering Stone & Webster Engineering Corporation Post Office Box 2325 Boston, MA 02107
- 2. Identification of the facility, or the basic component supplied for such facility, which contains a defect:
Shoreham Nuclear Power Station, Unit 1 General Electric Company (GE) 4 kV switch'g'6ar' circuit breaker - Limit Switches
- 3. Identification of firm constructing facility or supplying basic component which contains a defect:
Basic Component supplied by GE
VS 2 i
- 4. Nature of the defect and the safety hazard which could be created by such defect:
There exists a departure from the technical requirements of a procurement document in that breakers could have failed to operate as specified.
The defective circuit breaker limit switches are basic components in GE metal-clad switchgear (4 kV) and the switchgear has been delivered to a purchaser and installed in accordance with manufacturer's requirements.
Various limit switches on several breakers had become loose.
This enabled the limit switch to move away from its operating lever and permitted the switch contacts to return to their normally open position. The resulting loss of continuity in the breaker control circuit would result in the inability of the breaker to close.
The breakers are required under design basis events to assure the capability to shut down the reactor and maintain it in a safe shutdown condition. Degradation of such essential safety-related equipment represents a major reduction in the degree of protection provided to the public health and safety and results in a substantial safety hazard.
- 5. Date on which information of such defect was obtained:
December 2, 1980
- 6. In the case of a basic component which contains a defect, the number and location of all such components in use at, supplied for, or being supplied for facilities subject to the regulation:
Shoreham Nuclear Power Station l Our investigation to date has shown no defect exists on any other S&W plants. Should this information change, this report will be supplemented and appropriate advice given to purchasers or licensees.
l l 7. The corrective action which has been, is beingl'br-will be taken; I name of individual or organizaton responsible; and length of time I taken to complete the action:
l -
The limit switch screws will be tightened and lock-tite will i
be applied at Shoreham Nuclear Power Station. This work will be completed by December 1980. In addition, station breaker l
inspection procedures will be revised to require inspection and, as necessary, service of the limit switches.
. - - - . - ==
, --e - y
VS 3
- 8. Advice related to the defect that has been given to purchasers or licensees:
No other action apart from that specified under the previous section.
NRC has been previously informed of this problem by LILCO submittals SNRC-466 dated March 5, 1980, and SNRC-483 dated July 7, 1980, under 10CFR50.55(e). This problem concerns the same GE switchgear, whereby S&W submitted 10CFR21 reports to you dated July 23, 1980, concerning snap rings, fuse holders, and closing latches.
If you require an'; further information, please contact Mr. R. B. Bradbury at 617-973-0291.
Very truly yours, s h : N $N P. A. Wild Director of Engineering PAS:Imh
, 8..
1 l
I i
(
.4 -- . m_
e