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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 ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils 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 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A 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 ML17353A6141996-02-28028 February 1996 Part 21 Rept 10CFR21-0073 Re Defect W/Voltage Adjust Potentiometer Mfg by Chicago Telephone Supply Used on NEI Peebles (Portec) Voltage Regulators at Plant.Util Updating Voltage Regulators W/Maury Instrument Corp Potentiometer ML17352B1391995-04-28028 April 1995 Part 21 Rept Re Mechanical Defect in Shaft Length of Some HEA63 Lockout Relays Mfg Between 1990-94.Defect Identified Could Possibly Result in Binding of Front Shaft.Suspect Relays Checked for Date Codes & Replacements Ordered ML17352A8951994-11-15015 November 1994 Part 21 Rept Re Unit 3A Sequencers at Turkey Point Plant. Unless Contacted by FP&L to Perform Programming Changes & Subsequent V&V to Sequencer Software,United Controls Plans No Other Evaluation of Defect for Listed Reason 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 ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 ML17348B4411992-03-23023 March 1992 Interim Part 21 Rept Re Westinghouse Reactor Vessel Head Adaptor Tube Cracking.Wog Approved Project Authorization on 920205 for Reactor Vessel Closure Head Penetration Alloy 600 Primary Water Stress Corrosion Cracking ML17348B3051991-12-12012 December 1991 Supplement to 910812 Part 21 Rept Re Potential Generic Defects in Abb Type RHMH2 Model RK223068-EA & 069-EA Relays. Caused by Tape Fold Back Condition.New Method for Installing Insulation Tape Initiated ML17348B0431991-08-16016 August 1991 Part 21 Rept Re Potential Generic Component Defect Found During Insp of Asea/Abb Type RXMH2,Model RK223068-EA & RK223069-EA Relays.Caused by Misplacement of Insulating Tape Installed on Coil Termination ML17348B2921991-08-12012 August 1991 Part 21 Rept Re Potential Generic Component Defect in Asea/Abb Type RXMH2 Relays.Relays Utilized in Emergency Diesel Generator Bus Load Sequences.Info Gathering Underway. Customers Will Be Notified as Soon as Possible 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 ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway 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 ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint 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 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves 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 ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 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 1998-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17241A4891999-10-0707 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 ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 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 ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 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 ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. 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 ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 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 ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 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 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. ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 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 ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 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 ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. 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 ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 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 ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 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 ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr 1999-09-30
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O O P.O. BOX 3100 #AIAtAl, FLORIDA 33101 r_ mr y
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J u c-mm FLORIDA POWER & UGHT COMPANY May 30, 1973 Mr. Frank E. Kruesi, Director Directorate of Regulatory Operations U. S. Atomic Energy Commission Washington, D. C. 20545
Dear Mr. Kruesi:
Re: St. Lucie Plant Unit No. 1 Docket No. 50-335 Reactor Coolant Piping Incident Report .
As required by 10 CFR 50.55(e), we are filing a femal report covering an abnormal occurrence that occurred during cons.truction of St. Lucie Unit No. 1. This report covers bending of three instrunent piping nozzles on a pipe spool of the reactor coolant piping. The occurrence was previously reported verbally at the site to members of the Directorate ci. Regulatory Operations.
ours very truly, i
j /
?).
- ames Coughlin YcePresident 4
JC:sd Attachment ec: Mr. Noman C. Moseley, AEC-Atlantit Mr. Jack R. Newman 1
l 1
8306020038 730629
{DRADOCK 05000251 PDR
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REACTOR COOLANT PIPING INSTRUMENT N0ZZLE REPLACEMENT I Summary on May 1, 1973 it was reported by site quality control that three instrument nozzles appeared to be bent on reactor coolant pipe spool 42" RC-503-01 (see attached Exhibit A). The nozzles were the RTD nozzle, 510-01, and two Flow Measurement nozzles, 507-13.
The spool was removed from the reactor containment building and shipped back to Combustion Engineering's shop at Chattanooga for repairs. s -
II Description of Incident l
The subject spool was received on December 31, 1971. The spool was shipped.in a clear poly wrapping and secured to a wooden skid.
The spool was received and handled in accordance with CEND-353,
" Field Handling, Maintenance, and Storage Requirements for Combustion Engineering Furnished Equipment". In accordance with CEND-353, a visual inspection of the spool was performed by site Ebasco Quality Compliance. No bent instrument nozzles were noted. The spool was then covered by an additional green poly wrapping and stored.
Further, Material Receiving Report No. 849 was prepared and filed by Ebasco Site quality Control Personnel. No bent instrument nozzles were noted.
I The subject spool was removed from storage on April 26, 1973. A P&H Motor Crane with nylon slings was used to lift the spool to a flatbed. The flatbed was transported to the vicinity of the RCB Construction hatch and off-loaded with a P&H Motor Crane with nylon slings. No handling difficulties were reported.
On April 30th the night shif t piping crew rigged and moved the pipe spool piece into the reactor containment building and supported it approximately in its final location.
On the morning of Tuesday, Iby 1,1973, Broaddus Garnett, Quality l Control Welding Specialist, reported observing three instrument nozzles on Reactor Coolant Pipe Spool 42" RC-503-01 bent. Following Mr. Garnett's report, the night shift Quality Control and Construction logs were reviewed. Both logs indicated the nozzles were bent prior to rigging the subject spool into the containment.
! Further investigation revealed that Ballard Scalf, night shift Quality l
Control representative, had been requested by Harold Howel, night l shift Piping Supervisor, to inspect the instrument nozzles. Mr. Scalf confirmed that the nozzles were bent prior to rigging the subject spool into the containment. The procedure for moving the spool into place was continued with the thought that repairs might be made with it in its final location.
It may be inferred from the accumulated data that the bending of the instrument nozzles occurred during rigging and or transportation of Gke O@ool t@ the _ gcactor__ containment area. This is credible since
2, _ .
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the spool was covered with an opaque green poly wrapping.
III Corrective Action A - Repairs Pipe spool 42" RC-503-01 was shipped .back to Combustion Engineering's thattanooga shop on May 3, 1973. .Tius three bent nozzles were removed from the spool and replacements were attached using the same material and procedures utilized in the initial fabrication.
NDT was also the same as for the initial fabrication (see Exhibit B ASIE Forn NPP-1) . The spool was returned to the site May 14, 1973.
B - Action to Prevent Re-occurrence Procedures are being prepared to delineate the requirements for removal of wrappings prior to rigging and protection of appurtenances of ' reactor coolant piping prior to transportation.
IV Safety Implications There are no effects on the safety op'erations of the,St. Lucie Plant -
Unit 1 due to this incident as repairs and testing were performed in accordance with original Combustion Engineering procedures.
The adherence to new procedures regarding handling of such items will.
reduce the change of a reoccurrence of an incident of this type.
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. . F0lul .NPI' I DAT.\ I.. . i 11. 011 FAltlilCITED NI'El.E \H l'. aC
- 9 Dat! ' '
( k Hem drtti hv :!w I'rm i-i.ms nf ihr \ A lE C mir I!ntr )
,,,,,,,,,,,,,, Combustion Eng.r., Inc., Chatta.. Tenn. o,,,,,, 744A7 -
then.e a res AJ.see s . ei t .5escatort
- 3, gy,,,,a ,,, CombtIs tion T-c__ UN A w _ (' e. , _ o,g., p , 103g7 Fm"..w. ., e .n. .wa,, . . ,
71orida Pnve r & L i < h t Co . t i....t,.n .r pian. un ey, m Tc3. : r" W rce, Florida 3,,,,,,, -
- 3. Pipins 9 .7tem Identar.e es..n Reactor Coolant Pine .
(tstset de.s rspteen .a anten3*J u.e. c.een wo&ene e tc.s
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u ce. ins w. - E-234-072 p,,,,e..,Corbustion E M - % Tnc-Q Q*Q* fg.*g; c-- *v'g g . r** -*v y -
( Pre . . ute j L & emp.3 ...
O r. m .ai e,iai. ee.i.n. c on.i,..t..n. .na -rwe.n.h.p ..m.i.e. with Asur coae se ii. crr. cia..
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ro.ii.n .Aaaene.o.,, h e er, 1%9 GM . Dea.e 3., @ AWT M1 Rem: ek e: M.nufacturer.' Data Record. ProperIF identaried and signed ter comrwi....n d In.pect.rs hae, been turni.hed t.r .
o, e u..in, it,m o< t h.. re,.m Data revised _.1q_ cover re-1=c m -r of - f i m.
- c. e . , e. . n - ...,%,e.. a n ... v ., ,r o e. . ~ ~r..t,..,. . u ,... .
m'asurenent nozzles (507-13) and en.2 RTD nn cle (510 f" T . %,
nozzles trere danaced in the field. Ra,1 c=-s-r -,dn i, c-F e k, , -
- s. sa.p ura -
.t.uc 7,., Mone , t. Hydrostatic test to be applied in the field.
- s. De v. ,ifu,n or c. pin in.p..ie, 5M-M: Moe G"m 2 3 VP W& cNu 4r t.D__,3 - o
., t.,n. .a e - m. ,. . ., .: e n .. . p e. . - n o,.,. ,,p e . .,e - .. n e.o i e ., i t..c>ne . . - s e o ch ._
41/8" thick c 35 degrees: 63" R: length 172 1/16" ..c
- uman . - n an a . . . e t c.* e c
. A516-70: Cled A240-3 nil: one surre no::le 12 3/'" on se A 1m ^10s-11 & .
A351 CFS'f: four flow neasurement nor les 3" Feh. 1AO. F166 A 11 M Ta 316: __
one shutdown cooline out, nozzle 12' 3/4"0D Sch. 160. A105-TT F '191 CFSM: ~
five R.T.D. nor:les 1" Sch. 160 B164 $
CM.NTM'U.UWFECGi".RC'X -c m **
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We eerufy that the .tatement. made an this report see correct. [ . .
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R. H. Felton December 31. 1074 cemruoe of Ainthemats.n E apere.
' .CERTil'ICATE OF 51101' INSPEC110N -
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. ih , t< na e,.i .n .. h.to.n ." . v .tia c omm.. ...n . ...d 3, ih e w ai ..e.i se a, at n a.i e, ana r ...e v. .. ei in.... ... .no/., -
ihe sta .e Pr.eante o, Ohio on ,,.,,,,, ,a ,,, H . S . B . T . & T . ,,Unrt.. Cnnn. ,
haes entpected the paping de.cribes in this data report .n 'N 10.2 ?}._ . me J . tate that to the b.et of my knowle4e es.$ bolsif. the gnaer.f actiare r he. con.tructed this pip:ng.in ac cordanc e with t*te appi.c able .ection. of AS'.Id C.d e. Seetesa III. .<
e .
..e Dy Elgal A4 " hag cettsfieste nea'her the Inser gene nee hsa employer melse ene weer.nty, espee..eJ er imp!seJ. Concernen t the n 34;enJ JFaceite d en ths. Jef e repset. Feari'iemote, neiehee the in.p.et.,e rio, he. e-stseer shall be liab!e in any menner f.* ear par:ene.t insure er p.aperty desia g e .e e lo.. of .any h nJ e.i.ang from se eennect es wnh the. a.,.pect6on. .
Rts 19 a .