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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 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted 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 ML20056E9751993-08-19019 August 1993 Provides Insp Results & Safety Analysis Re Operational Amplifiers Discussed in 920917 & 23 Ltrs as Potential Safety Issue.Concludes That There Are No Safety Concerns W/Respect to Buffer Amplier Module.Ltr Not 10CFR21 Notification ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 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 ML20118B2191992-09-23023 September 1992 Suppl to Part 21 Rept Re Potential Deviation in Some Bailey Controls Co 88 Series Modules,Transmitted Via .One Module Found Incapable of Reaching 100% Output at Max Rated Load.Recommends That Circuit Board Assemblies Be Inspected 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 ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl 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 ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 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 ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced 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 ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking 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 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 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 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 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 NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List 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 ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint 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 ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted 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 ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20129G4401985-05-29029 May 1985 Part 21 Rept Re Failure of Inner Polar Connector Between Damper Bar Circuit on Generator Main Field.Cause of Failure Not Defined.Further Investigation Necessary 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 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 ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With 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 ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With 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 ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca 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 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 ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With 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 ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island 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 ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 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 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. 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 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 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With 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 ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With 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 ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits 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 ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl 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 1999-09-30
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t.o. BOX 529100 MIAMI.F L 33152
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FLORIDA POVIER 5 LIGHT COMPANY October 31, 1980 L-80-365 N. James p. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission .
101 Harietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Hr. O'Reilly:
Re: St. Lucie.Unit 2 Docket No. 50-389 Dam er Actuators !
American Marming 5 Ventilating, Inc. (AWV) has.previously notified the HRC of deficiencies in their damper/louver actuators. On Harch 25, 1980 (L-80-103)
Florida Power 8 Light Company {FPL) submitted an interim deficiency report, pursuant to 10 CFR 50.55{e) requirements, advising the NRC ef the impact of those deficiencies on St. Lucie Unit 2 damper/'louver actuators. Additional information was provide'd to you in a June 30, 1980 letter {L-80-208) .which also stated that a final deficiency report would be submitted by October 31, 1980. Accordingly, a final report is attached for your review.
In a letter to the Director of Reactor Construction. Office of Inspection and Enforcement, in response to IE Bulletin 80-09 (Hydramotor Actuator Deficien-cies), FPL reported the existence of 47 .damper/louver actuators that could have contained the deficiencies reported by .AMV. During the preparation of the final report, it was determined that the correct nImIber of damper/louver actuators is 45, as initially reported to you on torch 25. 1980.
Very truly yours,
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Vice President Advanced Systems c Technology REU/TCG/ah
'ttachments cc: Harold F. Reis. Esquire of Inspection and Enforcemebt
'irector U. S. Nuclear Regulatory Commission Mas ington, 'D. C. 20555
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FINAL DEFICIENCY REPORT DAMPER'CTUATORS Name of Station: St. Lucie P1ant - Unit 2 Owner:, Rorida Power 8 Light Company Architect/Engineer: Ebasco Services, Incorporated Date BRC Notified: February 21, 1980 Interim Report Filed: Harch 25, 1980 Final Report Fi1ed: October 31, 1980
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SUMMARY
American Razming t'* Ventilating, Znc. (A%V) has notified the NRC, pu suant to 10CFR 21, of potential de"ects in some hydromotor actuatoxs fox dampers and louvexs, puxchased by AWV from XTT General Controls of Glendale, California. These potential defects involved incorrect material in' certain spring used in some actuators and the selection nomographs used for sizing certain actuators, which could be interpreted incorrectly.
The interim report (L-80-103, dated March 25, 1980) identified 45 dampezs .
and louvers as heing affected. Please note that L-80-241, dated July 28; 1980, incorrectly quantified the number affected as 47. The 19 dampers identified in the interim report as being placed on hold in the vendor's shop,, have been retestect and reworked as necessary by XTT and subsequent-ly shipped to the site for installation. AHV has evaluated the remaining 26 dampers and Iouvers (24 dampezs and 2 louvers) shipped to St Lucie site before -the deficiency was detected, using statistical data provided by XTT. Out of 26 dampers and louvers four dampers require spring re-..
placement; five dampexs require a spring adjustment, 15 dampers have been evaluated as meeting the torque requirements and corrective actions he perfoxmed on the two louvezs.
vill Per the requirements of 2.0CPR50.55(e) the events are deemed reportable.
By telephone PPL notified the NRC on Pebruaxy 21, 1980, and an interim
-report was submitt d on Haxch 25, 1980. This final report is submitted, to advise the NRC of the do'scription of the deficiency and the correct-ive actions that vill I
be taken.
. XX. DES CRZPTZON ZTT General Controls of Glendale, Califorziia, a subcontractor supplying nctuators to Amexican Haaaing & Ventilating Xnc., notified American
$ Tarnmg of the existence of a'material deviation in a certain spring in "ome hy'dramotor actuatozs. One spring, XTT Part No. 17443A, used in some NH91, 92, 95, 96 and 98 milliampere hydzamotor actuators has been discovered (in December, 1979) to be manufactured from an incorrect material. Zt does not possess the designed strength -and will, upon ac-tuation of a greater than three inch stroke, take a permanent set. This r sul'ts in a decreased force'utput of approximately 160 lbs. at all com-pressed positions. Nhen these aforementioned actuators are subjected elecuical input control signal of zero,. the actuatox output does not to'n develop the published. force when the output shaft is moved to its full position (i.e., fully closed or fully opened)'.
The dampers (D) impacted by the above spring material deviation are as follows:
Shi oed to Site before Deficiency was Detected D-14 D-30 D-16 D-31 D-29 D-32 Placed on Hold D-8A D-9A D-15 D-34 D-36 D-8B D-9B , D-33 D-35
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On February .5, 1960 American Narming received a letter from XTT General Controls stating that American Rarming purchased ITT General series or NH90 series hydramotor actuators which may have been se-Controls'H90 lected or sized by using the "Selection Nomographs" on XTT's application form 0608.1067.2. This "Selection Nomographs" problem was discovered, by XTT General Controls in the course" of their investigation concerning the spring material deviation problem. XTT General Controls advised American arming that the subject nomographs could be interpreted incorrectly.
The forces that are derived from the chart represent the actual spring or hydraulic forces only, i.e., the effects of friction or residual forces axe not included. These actuators could have about, 100 lbs.
hydrau-'9.c of friction and an additional 40 lbs. of residual hydraulic pressure.
. This means that the e was a possibility that, the XTT General series actuators supplied with. American Warming dampers and louvers Controls'K90 auld not meet the specified safety factors with respect to thrust deli-vered to ths damper assembly.
The dampers (D) and louvers {L) impacted by the above nomograph problem Mclude the 15 dampers listed above plus the fol3.owing 30 additional.
ed to Site before Deficien 1'hia was Detected D-7A D-18 D-27 D-73 D-19 D-28 D-12A D-20 D-39 D-12B D-21 D-40 D-13 D-22 D-17A D-23 D-.173 D-24 2L-7A $ Mote: These louvers were incorrectly 2L-7B 'I labled 2L-8 and 2L-ll in lette I-80-103 Placed on Hold D-1 D-6A D-2 D-1IA D-6B'-3 D-4 -. D-llB D-5A D-SB
.All the above dampers and louvers are safety related.
XXX COR~~CTXVE ACTION The 19 dampers identified as "placed on hold" have been reworked and.
retested by XTT General Controls and now meet all performance recpxire-ments.
The XTT General Controls has performed an actual test program with a large number of actuators (normal voltage, single phase) to determine thei minimum output forces. Actuators produced prior to December 1979 were included in the samples.
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Their Engineering Report no. 721.80.118 "AH/HH 90 Series Actuatoxs>>
Net Output Forces" dated July 15, 1980 is bossed on a statistical analysis of these test data. A copy of the. report was sent to the.
HRC's Office of Inspection and Enforcement by American Harming &
'Ventilating, Inc. The actuator farce data contained in this report included the lover force produced by the incorrect material'number
. 1 spring. Based on this statistical approach the report concluded that at an 808 confidence level, 98% of the units would have output forces at, or in excess of a statistical minimum..'This statistical minimum of the output forces was compared to each recpxired actuator l'-7A output force including .safety factors.
'ased on the At& has concluded that, E l
- 1) The following 15 dampers with'ITT actuators meet the specified
,.minimum torque xecpzixements:
D 18 D-24 D-73 D-14 D-16 D 19 D-20 D-21
- '-40.
D-39 D-17A D-22 D-17B D-23
- 2) The following 5 dampers recruire -a spring adjustment that could be performed without removing the actuator from damper. Access to these dazpers would. be available for later spring adjustment woxkf h W D-13 D-29 D-30 D-31 D-32
- 3) The fa9.l"return springs of the following 4 damper actuators have to be replaced to provide the required torque. Access to these dampers would also be available so that recpxixed work may be perfoxmed by
.A%V.
D-12A D-123 '-27 D-28
- 4) The following two louver actuators have to be either reworked or
-replaced to ensure the required output forces.
2L-7A~ 2L-7B Xn preparation for implementation of these. changes, St Lucie Unxt 2
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Site construction has been notified of the re~ired work on the dampexs and louvers
,Note that the above listed dampexs and louvers were already shipped to the site before the deficiency was detected.
As part of the plant's preoperational testing program, all the safety x lated dampexs and louvars will be test d prior to fuel load. to assuxe proper system operation.
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TV SAZETY Z~IPLZCATIONS The safety of operation of the nuclear power plant could have been adversely affected sometime throughout the expected lifetime of the
.plant, if the damper actuators that require spring adjustment or
-replacement were to have remained uncorrected.
V CONCLUSION Corrective action as indicated in Section XZZ of this report will be underta3cen by the vendor {AHV) at the St Lucie site. This closes out this item for St Lucie Unit 2 as regards both 10CFR50.55(e) and ZZ Bulletin 80-09.