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| * , P.o. BOX 529100 MI AMI, F L 33152 MCIAgg0py g ,, . | | * , P.o. BOX 529100 MI AMI, F L 33152 MCIAgg0py g ,, . |
| FLORIDA POWER & LIGHT COMPANY July <^4,1981 L-81-316 W ' | | FLORIDA POWER & LIGHT COMPANY July <^4,1981 L-81-316 W ' |
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| I Summary Post installation inspection of local control stations identified a cer-tain deficiency in the control switches supplied by Gould Rundel which could affect the starting mechanism of certain pumps (including fuel pool pumps). Because of the deficiency the pump will turn on but may not remain on when the switch is released. | | I Summary Post installation inspection of local control stations identified a cer-tain deficiency in the control switches supplied by Gould Rundel which could affect the starting mechanism of certain pumps (including fuel pool pumps). Because of the deficiency the pump will turn on but may not remain on when the switch is released. |
| This deficiency involved the switch development schedule in the purchase specification and was considered reportable under 10CFR50.55(e). FP&L (W. Hayward) notified the NRC (H Dance) on June 25, 1981. This final report is submitted to advise the NRC of the description of the deficiency and the corrective actions '.htc will be taken. | | This deficiency involved the switch development schedule in the purchase specification and was considered reportable under 10CFR50.55(e). FP&L (W. Hayward) notified the NRC (H Dance) on June 25, 1981. This final report is submitted to advise the NRC of the description of the deficiency and the corrective actions '.htc will be taken. |
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| IV Safety Implications The affected pumps include the fuel pool cooling pumps 2A and 2B which are safety related. The safety of operation of the nuclear power plant | | IV Safety Implications The affected pumps include the fuel pool cooling pumps 2A and 2B which are safety related. The safety of operation of the nuclear power plant |
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| could have been adversely affected sometime throughout the expected life time of the plant, if the switches that include the cam protuberance were to have remained uncorrected. | | could have been adversely affected sometime throughout the expected life time of the plant, if the switches that include the cam protuberance were to have remained uncorrected. |
| V Conclusion Corrective action as indicated in Section III of this report will be undertaken. This closes out this item for St. Lucie Unit 2 as regards-to 10CFR50.55(e) requirements. | | V Conclusion Corrective action as indicated in Section III of this report will be undertaken. This closes out this item for St. Lucie Unit 2 as regards-to 10CFR50.55(e) requirements. |
Latest revision as of 11:11, 17 February 2020
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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
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.. _ _ _ - . - - - - _ _ . .
- , P.o. BOX 529100 MI AMI, F L 33152 MCIAgg0py g ,, .
FLORIDA POWER & LIGHT COMPANY July <^4,1981 L-81-316 W '
Mr. James P. O'Reilly, Director, Region II (N ~
Office of Inspection and Enforcement g (f y g U. S. Nuclear Regulatory Commission J lif., A tla ta, er a 5 53 WL 31198W [3
- u.s.wxun acwmas
Dear Mr. O'Reilly:
'( 9 Re: St. Lucie Unit 2 V'1 g Docket No. 50-389 m Local Control Station Switch Protuberance On June 25, 1981, Florida Power & Light Company (FPL) reported to the Region II Office of Inspection and Enforcement a potential 10 CFR 50.55(e) condition involving local control switches supplied by Gould Rundel. A final report is attached for your review.
,j Very truly yours, Robert E. Uhrig W, /
l 1 Vice President
- Advanced Systems & Technology REU/TCG/ah Attachment j cc
- Director of Inspection and Enforcement U.S. Nuclear elegulatory Commission Washington, J. C. 20555 (with attachment)
Harold F. Reia, Esquire (w/o attachment)
, II l 8100030273 810724 j gDRADOCK05000g reOPLE . . SERVING PEOPLE
FINAL DEFICIENCY REPORT LOCAL CONTROL STATION SWITCH PROTUBERANCE i
- Name of Station St. Lucie Plant - Unit 2 Owner Florida Power and Light Company Architect / Engineer Ebasco Services Incorporated
- Date NRC Notified June 24, 1981
- Final Report Filed July 24, 1981 t
)
1 i
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I Summary Post installation inspection of local control stations identified a cer-tain deficiency in the control switches supplied by Gould Rundel which could affect the starting mechanism of certain pumps (including fuel pool pumps). Because of the deficiency the pump will turn on but may not remain on when the switch is released.
This deficiency involved the switch development schedule in the purchase specification and was considered reportable under 10CFR50.55(e). FP&L (W. Hayward) notified the NRC (H Dance) on June 25, 1981. This final report is submitted to advise the NRC of the description of the deficiency and the corrective actions '.htc will be taken.
Il Description Gould Rundel supplied type SS4 and SS6 switches on local control stations were identified as having a deficiency whereby the pump will turn on but may not remain on when switch is released. Upon further investigation it has been determined that a protuberance on the cam portion of the switch momentarily opens up the start contact once the switch is released from start position. The contact relay is deenergized for a time long enough to stop the pump. Accordingly, a nonconformance report (NCR No.1842E) was written on this item.
The fuel pool pumps 2A and 28 are the only safety related components identified as containing these types of switches in their local control stations. An indication light is present if the pump is de-energized.
i ihe vendor was contacted and it was verified tha t the switches were
, supplied according to the purchase specification. However, the vendor interpretation of the purchase specification which includt.d a switch de-velopment schedule led to a situation whereby the actual pumps' control and operational requirements were not met.
III Corrective Action t The purchase specification is' being revised to specify contact main-tenance during position change and the vendor will be requested to provide additional switches as per the revised specification. However, as an interim measure, repair will be performed at the site whereby the cam pro-tuberance will be ground out. These repaired switches will be included j for system testing purposes only and not for plant operations. A list of i the affected switches is maintained and the switches are tagged to iden-l tify them. Once new switches are received, the repaired ones will be replaced with the new switches prior to the end of 1981 and according to a repair procedure.
IV Safety Implications The affected pumps include the fuel pool cooling pumps 2A and 2B which are safety related. The safety of operation of the nuclear power plant
could have been adversely affected sometime throughout the expected life time of the plant, if the switches that include the cam protuberance were to have remained uncorrected.
V Conclusion Corrective action as indicated in Section III of this report will be undertaken. This closes out this item for St. Lucie Unit 2 as regards-to 10CFR50.55(e) requirements.
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