Interim Deficiency Rept Re Damage to Reactor Auxiliary & Shield Bldgs from 790903 Derrick Collapse During Hurricane David.Forwards Six Drawings Detailing Storm Damage.Available in Central FilesML17207A498 |
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Saint Lucie ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
10/04/1979 |
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From: |
FLORIDA POWER & LIGHT CO. |
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Shared Package |
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ML17207A497 |
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NUDOCS 7910250378 |
Download: ML17207A498 (15) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length 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 ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML17229A2631997-03-12012 March 1997 Part 21 Rept Re Followup of 970307 Event Involving Potential Spring Problem in Bettis Actuator.Recommends That Util Include Two Actuator Replacements of Springs as Precautionary Measures in Next Refurbishment Cycle ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML17229A1631996-11-27027 November 1996 Part 21 Rept Re 2-1878 Globe Piston Check Valves.A/Dv Plans to Include Philosophy of Both Enhancement W/Smaller Piston Check Valves.A/Dv Evaluated Found Condition of Piston Check Valve,Stuck Open ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML17229A0571996-09-19019 September 1996 Part 21 Rept Re 2 1878 Piston Check Valve That Failed to Close.Caused by Fretting Wear Damage Between Piston (Disc) & Valvo Body Caused by Pressure Pulsations of Reciprocating Pump ML17229A0101996-07-25025 July 1996 Part 21 Rept Re 2 1878 Stainless Steel,Piston Check Valve Installed in Charging Sys Failed to Close W/Reverse Flow. Performing Evaluation to Determine Cause of Incident.Other Customers Will Be Notified ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl 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 ML17227A4351992-05-28028 May 1992 Part 21 Rept Re Deficient Matl Supplied by Tioga Pipe Supply.Root Cause Investigation Results Provided.Matl Tested Met Spec Requirements.Tests Revealed That Only 3 Inch 3000# SB564 N04400 Tees W/Heat Code Ma Were Defective ML17227A4071992-04-28028 April 1992 Part 21 Rept Re crack-like Indications Found in Monel 400 Socket Weld Tee Fittings Supplied by Tioga Pipe & Supply Co.Fabrication Suspended & Metallurgical Exams Conducted. Util Procurement Process Modified ML17227A4161992-04-0101 April 1992 Part 21 Rept Re crack-like Indications Found in Three Inch Monel 400 Tee Fitting Supplied by Tioga Pipe Supply Co,Inc. Fabrication Suspended & Metallurgical Exams Conducted.Six Addl Tees Returned to Matl Supplier.Actions Completed L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML17223A5941990-03-0909 March 1990 Errata to 900126 Part 21 Rept Re Anchor/Darling Actuators Incorporating Use of Teldyne-Republic four-way Valves.Lists Plants Inadvertently Left Out in Original Rept ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML17223A1991989-06-0808 June 1989 Part 21 Rept Re Radiator Fan Shaft Bearing Failure at Plant. Problem Currently Under Investigation.Addl Info Will Be Provided When Available ML17222A7861989-04-17017 April 1989 Part 21 Rept Re Transformers & Sensors Encapsulated in Epoxy Found to Be Softening or Reverting Back to Liquid.Initially Discovered in Aug 1988 at Plant.Items Encapsulated W/Epoxy Should Be Inspected at Approx 18-month Intervals ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing 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 ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming 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 ML20135E2271985-08-23023 August 1985 Part 21 & Deficiency Rept Re Potential Problems W/Natl Valve & Mfg Co Pipe Clamps.Initially Reported on 850613.Ltrs Sent to Purchasers of Pipe Clamps Encl for Perusal ML20125B1611985-06-0606 June 1985 Supplemental Part 21 Rept Re Addl Circuit Breakers,Furnished as Spares,W/Overcurrent Trip Devices That May Have Short Time Delay Band Lever.Items Require Insp & Replacement If Link Found Incorrect LD-84-063, Part 21 Rept Re Evaluation & Corrective Action for Excessive Setpoint Drift in Some Potentiometers in Auxiliary Feedwater Actuation Sys Cabinet at St Lucie Unit 2 & Plant Protection Sys Cabinets at Palo Verde1984-10-26026 October 1984 Part 21 Rept Re Evaluation & Corrective Action for Excessive Setpoint Drift in Some Potentiometers in Auxiliary Feedwater Actuation Sys Cabinet at St Lucie Unit 2 & Plant Protection Sys Cabinets at Palo Verde ML20087J6661984-03-0808 March 1984 Followup Part 21 Rept Re Nuclear Valve/Actuator Stroking Time Possibly Lengthened Beyond 15 When Using hydrocarbon-based Lubricants.Ltrs to Affected Utils Encl L-83-511, Suppl to Final Deficiency Rept 82-014 Re Malfunctioning Shutdown Cooling Sys HX Bypass Valves.Valves Will Be Replaced W/Conventional Limitorque Operators Prior to Startup from First Refueling1983-10-0606 October 1983 Suppl to Final Deficiency Rept 82-014 Re Malfunctioning Shutdown Cooling Sys HX Bypass Valves.Valves Will Be Replaced W/Conventional Limitorque Operators Prior to Startup from First Refueling LD-83-050, Part 21 Rept Supplementing 830506 Notification of Potential Significant Safety Hazard Re Matl Defects in Stainless Steel Tubing Pressure Boundary Component.Ultrasonic Exam Shows Assemblies Acceptable Per ASME Code,Section III1983-06-0707 June 1983 Part 21 Rept Supplementing 830506 Notification of Potential Significant Safety Hazard Re Matl Defects in Stainless Steel Tubing Pressure Boundary Component.Ultrasonic Exam Shows Assemblies Acceptable Per ASME Code,Section III L-83-311, Clarifies 830418 Final Deficiency Rept Re Diesel Generator Start Relay Defect.Addl Indication Provided to Indicate to Control Room When Master Control Switch,Located in Diesel Generator Bldg,Is in Stop Position1983-05-19019 May 1983 Clarifies 830418 Final Deficiency Rept Re Diesel Generator Start Relay Defect.Addl Indication Provided to Indicate to Control Room When Master Control Switch,Located in Diesel Generator Bldg,Is in Stop Position L-83-282, Final Deficiency Rept Re Premature Indication of Valve Closure of Westinghouse Gate Valves.Initially Reported on 830223.Configuration Represents Normal Design Condition. Condition Not Reportable Per 10CFR50.55(e)1983-05-11011 May 1983 Final Deficiency Rept Re Premature Indication of Valve Closure of Westinghouse Gate Valves.Initially Reported on 830223.Configuration Represents Normal Design Condition. Condition Not Reportable Per 10CFR50.55(e) ML20072J7041983-05-0909 May 1983 Part 21 Rept Re short-term Reliability Problem W/Position Indicating Mechanism in Solenoid Valve Used to Control PORV 3750010.Magnet Position Indicating Mechanism Replaced on 830507.Corrective Action in Progress ML20023C6621983-05-0606 May 1983 Deficiency Rept Re Potential Significant Safety Hazard Concerning Defect in Stainless Steel Tubing Pressure Boundary Component.Initially Reported on 830504.Selected Tubes Returned to C-E Tubes for Reinsp L-83-275, Interim Deficiency Rept Re Failure of Two safety-related Agastat Relays to Time Out Properly & Installation of Incorrect Agastat Relay on Diesel Generator.Initially Reported on 830330.Investigation Ongoing1983-04-29029 April 1983 Interim Deficiency Rept Re Failure of Two safety-related Agastat Relays to Time Out Properly & Installation of Incorrect Agastat Relay on Diesel Generator.Initially Reported on 830330.Investigation Ongoing L-83-274, Final Deficiency Rept Re Loss of Continuity on Mineral Insulated Cable Assemblies.Initially Reported on 830330. Twenty-three Cable Assemblies W/Defective Connectors Repaired.Deficiencies Not Reportable Per 10CFR50.55(e)1983-04-29029 April 1983 Final Deficiency Rept Re Loss of Continuity on Mineral Insulated Cable Assemblies.Initially Reported on 830330. Twenty-three Cable Assemblies W/Defective Connectors Repaired.Deficiencies Not Reportable Per 10CFR50.55(e) L-83-260, Interim Deficiency Rept Re Westinghouse Gate Valve Premature Indication of Valve Closure.Initially Reported on 830223.Util Evaluating Condition & Will Submit Final Rept by 8305041983-04-25025 April 1983 Interim Deficiency Rept Re Westinghouse Gate Valve Premature Indication of Valve Closure.Initially Reported on 830223.Util Evaluating Condition & Will Submit Final Rept by 830504 L-83-251, Final Deficiency Rept 83-009 Re Condensate Storage Tank Damage.Initially Reported on 830322.Caused by Condensation of Steam Creating Local Vacuum Conditions.Double Butt Welded Plates Installed,Cracks Sealed & Designs Improved1983-04-21021 April 1983 Final Deficiency Rept 83-009 Re Condensate Storage Tank Damage.Initially Reported on 830322.Caused by Condensation of Steam Creating Local Vacuum Conditions.Double Butt Welded Plates Installed,Cracks Sealed & Designs Improved L-83-244, Final Deficiency Rept 83-005 Re Diesel Generator Start Relay.Initially Reported on 830318.Safety-related Function of Second Diesel Generator Not Compromised.Item Not Reportable Per 10CFR50.55(e)1983-04-18018 April 1983 Final Deficiency Rept 83-005 Re Diesel Generator Start Relay.Initially Reported on 830318.Safety-related Function of Second Diesel Generator Not Compromised.Item Not Reportable Per 10CFR50.55(e) L-83-242, Final Deficiency Rept Re Ground Fault in Reactor Protection Sys.Initially Reported on 830310.Condition Not Reportable Under 10CFR50.55(e) & Part 21.No Adverse Effect Would Result If Occurrence Left Uncorrected & Cables Left in Place1983-04-18018 April 1983 Final Deficiency Rept Re Ground Fault in Reactor Protection Sys.Initially Reported on 830310.Condition Not Reportable Under 10CFR50.55(e) & Part 21.No Adverse Effect Would Result If Occurrence Left Uncorrected & Cables Left in Place ML20069L0771983-04-18018 April 1983 Final Deficiency Rept Re Potential Low Suction Pressure Due to Bam Sys Safety Injection Actuation Signal Pump Start Logic.Initially Reported on 830318.Control Logic Modified L-83-245, Final Deficiency Rept Re Defective Weld on Safety Injection Test Piping.Initially Reported on 830318.Weld,piping & Fitting Replaced & Hanger Reinstalled1983-04-18018 April 1983 Final Deficiency Rept Re Defective Weld on Safety Injection Test Piping.Initially Reported on 830318.Weld,piping & Fitting Replaced & Hanger Reinstalled 1998-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229B0461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr ML17229B0051999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17241A3581998-12-0909 December 1998 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209. ML17229A9421998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17241A4931998-11-0101 November 1998 Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project). ML17229A9051998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr ML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8721998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8611998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr 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 ML17229A8481998-08-0707 August 1998 Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr. ML17229A9461998-08-0707 August 1998 Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr. ML17229A8301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr ML17229A7701998-05-31031 May 1998 Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr 1999-09-30
[Table view] |
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Interim Construction Deficienc Re ort Dama e Resultin From Derrick Failure Durin Hurricane David Name, of Station: St. Lucie Plant - Unit 52 Owner: Florida Power 6 Light Company .
Architect/Engineer: Ebasco Services, Incorporated, Date of Deficiency: September 3, 1979 Interim Report Filed: October 4, 1979
I. SUMMATE On Monday morning, September 3, 1979, at approximately 10:45 a.m., the Chicago Bridge a Iron guyed derrick buckled, twisted, and collapsed during Hurricane David. The lower portion of the derrick (below elevation +192 feet) did not collapse and was leaning at a slight angle from the, vertical, remaining braced to the containment shield wall by virtue of the horizontal strut braces. The upper portion of the derrick became dismembered and four major sections came to rest in or on the Reactor Auxiliary Building. A portion of the boom remained suspended by guy wires from the top of the containment shield wall. The guy wires performed their intended function and did not fail.
Per the requirements of 10CFR50.55(e), the event is reportable because the derrick failure caused significant damage to safety related structures and, were they to have remained uncorrected, could adversely affect the safety of operations of the plant, and does require extensive evaluation and repair.
Notification of the incident was telephoned in to the NRC Inspection and Enforcement Office on September 4, 1979 (approximately ll:45 a.m.) by Mr. N. Weems, Florida Power a Light Company's Assistant Manager, QA Construction.
After numerous onsite inspections, engineering is in the process of developing and dispositioning corrective actions for the damaged areas. Subsequent to aforementioned inspections, onsite confixmatory destructive and non-destructive testing will be implemented and any additional corrective action will be issued by engineering if required.
An interim report is being submitted while investigation of the damaged areas is still ongoing and repair work is proceeding.
II ~ DESCRIPTION The concrete Shield Building and the Reactor Auxiliary Building were at the r
following stages of construction when the hurricane passed the jobsite: The concrete Shield Building cylinder had been completed to elevation +191.42 feet and the Reactor Auxiliary Building, being constructed in a staggered manner, had walls and columns completed to the underside of floor slabs at elevations
+43 feet, +62 feet and +82 feet.
I Il
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II. DESCRIPTION (continued)
Com leted Actions to Identif Dama e A storm damage team was assembled to determine and document the extent of damage resulting from the derrick failure. The team consisted of a construction civil engineer and two assistant civil engineers. In conjunction, the Architect/Engineer has'isited the jobsite, both before and after derrick removal and cleanup, to observe the damage, and to confirm the task force findings. Areas completely unaffected by the derrick failure have been released for continued planned construction. Investigations are ongoing to determine if and where destructive and non-destructive testing should be performed before releasing areas adjacent to areas damaged.
The damage to the containment shield wall was limited to bent and sheared dowels projecting from the top of the cylinder wall and a small surface gauge on the exterior wall. The mapping of this damaged area has not yet been completed.
The damage'ithin the Reactor Auxiliary Building was extensive and consisted of penetration of floor slabs, shattered floor beam; spalled concrete, and bent and sheared dowels for columns and walls. There is a possibility of some cracking of some floor beams and girders and one exterior wall section.
The location of derrick and boom'ection resting positions, and details of observed damage to the Reactor Auxiliary Building is presented on the enclosed sketches, SK-2998-FG 75.01 to 75.06. In addition to the noted. damage on the attached sketches, cracks were observed on the surface of a few elevation
+43 feet floor beams. These cracks were chipped back to determine depth and were observed to be only surface shrinkage cracks. h T
In addition to .the. above structural damage in the Reactor Auxiliary Building I II I
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the following is a listing of damaged equipment and supports:
1 - Conduit on elevation +43 feet 2 Cable tray restraint on elevations +43 feet and +62'eet 3 - 4.16 KV Switchgear 2A3-1, 2, 3, 4, 5, 6, 7, 8 - Y~~='~","
I 4 - Station Service Transformer 2A2 'g'CPh,'.,
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', 4'C ITh, 6 - Pressurizer heater 'buses 2A3 and 2B3
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II. DESCRIPTION (continued)
Planned Actions to Further Identif Dama e Architect/Engineer has directed Construction to proceed with two testing programs to confirm the extent of damage within the Reactor Auxiliary Building.
The first program requires testing of reinforcing steel samples removed from the damaged floor beams and slabs at elevation +62 feet. Test results will indicate if the reinforcing which extends into the surrounding sound concrete had been overstressed during missile impact. The second program requires non-destructive testing of concrete members, 1) adjacent to damaged floor slab areas at elevations +43 feet and +62 feet, including all the beams at elevation +43 feet which were observed to have only surface cracks, and 2) in an exterior wall along the north side of the building which had only five day concrete strength when a section of thy derrick hit the top of the wall.
The pulse echo method was selected and will be performed by Muenow and Associates of Charlotte, North Carolina. The attached Figures 1 and 2 show the concrete members to be investigated.
In addition, the damaged areas on the containment shield wall will be mapped and evaluated prior to any repair work being initiated.
III. CORRECTIVE ACTIONS Com leted Corrective Actions Florida Power 6 Light Company's Quality Control Department has the responsibility to prepare nonconformance reports (NCR's) where damage has occurred to complete construction activities (i.e., after concrete placement)or equipment. Table 1 is a list of dispositioned NCR's summarizing categories of structural members, I
types of damage and corrective action to be taken.
Table 2 is a list of currently dispositioned NCR's summarizing the equipment damage and corrective action to be taken,-'additional NCR's will be issued as required.
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Three additional NCR's (834C, 842C and 851C) have been issued for the damaged concrete and reinforcing within slabs and beams at elevations +43 feet.
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III. CORRECTIVE ACTIONS (continued)
Planned Corrective Actions'continued)
These NCR's will not be dispositioned until after the rebar and echo testing programs are completed and data has been evaluated for final determination of damaged area. An additional NCR will be issued to cover the damaged rebar in the containment shield. wall.
Architect/Engineer will issue a Design Change Notification (DCN) form if resulting NCR dispositions require redetailing of floor beam and slab reinforcing at elevations +43 feet and +62 feet. Mechanical splicing of reinforcing steel will be used where lap splicing is impractical.
Involvement The procedures utilized to identify damage, evaluate and disposition corrective action are the following:
1 - Site Quality Procedure SQP-21 "Corrective Actions" for the handling of NCR's.
2 Ebasco Company Procedure E-69 "Design Change Notification/
Field Change Report" - for handling DCN's.
The Florida Power 8 Light Company's Quality Control Department has independently reviewed the damaged areas and issued NCR's to identify damaged areas and equipment. They will then follow-up the correctiveaction dispositioned by Engineering and apply the normal testing and inspection requirements for final approval.
Any NCR's that require redetailing will be handled by Engineering via DCN's.
'55 In addition to the above normal QC inspection and approval process and documentation, the storm damage team has photographed and mapped the damaged areas to permit additional documentation on the extent of damage.
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IV. SAFETY IMPLICATIONS The Chicago Bridge 6 Iron derrick failure caused significant damage to the Reactor Auxiliary Building structure which requires extensive evaluation and repair to establish the adequacy of the structure to perform its intended safety function and meet the criteria and bases stated in the Preliminary Safety Analysis Report. If it were to have remained uncorrected,. the structural damage could have possibly affected the safety of operations of the plant.
An extensive investigation is being performed to identify the extent of damage. No repair work or new construction will proceed in the affected areas until each area has been specifically evaluated and, where necessary, repair measures approved by the Architect/Engineer. Adequate documentation
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is being maintained to allow analysis and evaluation of the deficiency and the corrective action taken and the completed documentation package will I
of be a part of the final report.
V. CONCLUSION Q
The Chicago Bridge 6 Iron derrick failure was determined to be a potentially reportable accident on September 4, 1979 and such notification was made to the NRC Inspection and Enforcement Office the same day. Prior to any repair work or new construction in the affected areas, each area is specially evaluated C
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for structural soundness and repair measures approved. Adequate documentation on the structural evaluation and repair work is maintained.,
Subsequent to completing the planned action of identifying damage and the planned corrective actions, a final report will be submitted to the NRC.
The report will include a description of the deficiency, an. analysis of
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the safety implications and the corrective actions ~ r taken. Su fficient information (e.g., updated drawings, test results, copi.es of NCR's and DCN's) will be provided wt to permit analysis and evaluation of the deficiency and of the corrective The final report will be submitted by February 1, 1980. r I
action.
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Table 1 Dis ositioned Concrete NCR's Issued NCR's Cate pries Covered b NCR 830C Interior wall and projecting Bent rebars Rebend rebars to original reinforcing positions 831C, Columns, walls and projecting Spalled concrete Chip concrete back 1'-6, 841C, 845C, reinforcing and bent rebars cut off damaged rebars 846C g 848C, in walls and and mechanically splice 850C columns rebars 8350 Wall and projecting reinforc- Cracked concrete Chip back 1 ft. into sound ing and bent rebars concrete and mechanically splice rebars 832C Columns and projecting rein- Bent rebars Chip concrete back to forcing specified elevation for full rebar lab splice and install new rebar 833C Columns and projecting rein- Cracked near Chip concrete column and forcing floor level replace damaged reinforcing
Table 2 Dis sitioned Electrical NRC's Issued HCR's E ui ent Covered b NCR Dis sition 839Et 840E Conduits on elevation +62 feet Remove damaged conduit and replace with new 837E Cable tray restraints on Two restraints are to be repaired elevations +43 feet and by Construction to within AISC
+62 feet tolerances. Balance to be scrapped.
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