Third Interim Rept Concerning Improper Anchor Bolt Matl. Caused by Failure of Const Quality Procedures to Require QC Personnel to Verify Correctness of Info on Matl Requisitions.Stop Work Order Issued to Change ProceduresML19262C622 |
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South Texas |
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12/31/1979 |
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HOUSTON LIGHTING & POWER CO. |
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ML19262C620 |
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NUDOCS 8002140734 |
Download: ML19262C622 (9) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum 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 ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML20078C2591994-10-19019 October 1994 Part 21 Rept Re Valtek Valves Addressed in NRC Part 21 Log Number 93-325,installed at South Texas Project.Valtek re-designed Trim to Meet All Requirements & Built Parts to Retrofit in Valves 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 ML20106E1951992-11-0202 November 1992 Part 21 Rept Re Cracked Fuel Nozzle Tips Purchased from Bendic.Initially Reported on 910405.Addl Testing of Tips Performed Completed,Reviewed & Recommendation to Prevent Failures Made ST-HL-AE-3903, Suppl to Special Rept:On 901126,fuel Oil Leak Noted at Injection Pump 1L of Standby Diesel 23.Caused by Crack on Threaded Portion of Delivery Valve Holder.Injection Pump Delivery Valve & Valve Holder Replaced on 9011271991-11-0404 November 1991 Suppl to Special Rept:On 901126,fuel Oil Leak Noted at Injection Pump 1L of Standby Diesel 23.Caused by Crack on Threaded Portion of Delivery Valve Holder.Injection Pump Delivery Valve & Valve Holder Replaced on 901127 ML20086P1591991-10-31031 October 1991 Part 21 Rept Re Microscopic Cracks in Fuel Nozzle Tip from Mfg Lot D87001.Cracks Perpendicular to Axis of Nozzle & Extend Through Case Hardening & Stop at Core.Interim/Final Report Will Be Forwarded as Further Development Occurs ML20083D7711991-09-20020 September 1991 Interim Part 21 Rept Re Failure of Fuel Injector Nozzle Tips.Initially Reported on 910723.Each Util Will Continue to Monitor Exhaust Gas Temps During Monthly Runs & Will Sample Lube Oil on Quarterly Basis for Contamination ML20072S9501991-04-0505 April 1991 Interim Part 21 Rept Re Failure of Standby Diesel Generator Fuel Nozzle Tips Mfg by Bendix.Initially Reported on 910327. on 910327 Memo Issued Requesting Recall of Affected Parts. Technical Evaluation Underway by Util ML20072T3081991-04-0404 April 1991 Advises That Ongoing Investigation Into Emergency Diesel Generator Failure Raised Questions Re Fuel Nozzle Tips Furnished by Cooper Energy Svc.Records Indicate Tips Supplied to Company ST-HL-AE-3655, Deficiency Rept & Part 21 Rept Re Change in Commitment to Procure Class 1E Battery Cables from Gould Nuclear Batteries Inc.Gould Discontinued Implementation of QA Program & Removed from Util Approved Vendor List1991-01-0303 January 1991 Deficiency Rept & Part 21 Rept Re Change in Commitment to Procure Class 1E Battery Cables from Gould Nuclear Batteries Inc.Gould Discontinued Implementation of QA Program & Removed from Util Approved Vendor List ST-HL-AE-3568, Revised Part 21 Rept Re Failure of Feedwater Isolation Valve Due to Thermal Incompatibility of Hydraulic Fluid1990-10-15015 October 1990 Revised Part 21 Rept Re Failure of Feedwater Isolation Valve Due to Thermal Incompatibility of Hydraulic Fluid ML20012C1351990-03-0808 March 1990 Part 21 Rept Re Failure of Connecting Rod in Standby Diesel Generator 22.Initially Reported on 891208.On 891128,master Connecting Rod Failed.Caused by over-drilling of Oil Holes. Final Rept, Finite Element Analysis of KSV-4-2A... Encl ML20011D1971989-12-0808 December 1989 Part 21 Rept Re 891128 Failure of Master Connecting Rod 4 & Ejection of Rod & Broken Pieces Through Right Ctr Door Frame Opening.Caused by High Cycle Fatigue to Transverse Oil Passage.Repairs to Crankshaft & Engine Underway 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 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 ST-HL-AE-2868, Part 21 & Final Deficiency Rept Re ESF Diesel Generator Galling Damage.Initially Reported on 881026.Damaged Parts on Diesel Generator 21 Replaced.Deficiency Is Solely Attributable to Cooper-Bessemer Maint Activities1988-11-23023 November 1988 Part 21 & Final Deficiency Rept Re ESF Diesel Generator Galling Damage.Initially Reported on 881026.Damaged Parts on Diesel Generator 21 Replaced.Deficiency Is Solely Attributable to Cooper-Bessemer Maint Activities ST-HL-AE-2843, First Interim Part 21 & Deficiency Rept Re Elastomer Diaphragms Contained in Comsip Delphi Containment Hydrogen Analyzers.Initially Reported on 881012.Unit 1 Regulator Replaced.Next Rept Will Be Submitted by 8812161988-11-14014 November 1988 First Interim Part 21 & Deficiency Rept Re Elastomer Diaphragms Contained in Comsip Delphi Containment Hydrogen Analyzers.Initially Reported on 881012.Unit 1 Regulator Replaced.Next Rept Will Be Submitted by 881216 ST-HL-AE-2840, First Interim Deficiency & Part 21 Rept Re Class 1E Battery Cables.Initially Reported on 881012.Jumper Cables Will Be Replaced W/Qualified Cables Prior to Fuel Load.Next Rept Will Be Submitted by 8812301988-11-0909 November 1988 First Interim Deficiency & Part 21 Rept Re Class 1E Battery Cables.Initially Reported on 881012.Jumper Cables Will Be Replaced W/Qualified Cables Prior to Fuel Load.Next Rept Will Be Submitted by 881230 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ST-HL-AE-2767, Final Deficiency Rept Re Cracking of ESF Diesel Generator Heads.Initially Reported on 880801.Precautions Added to ESF Diesel Generator Instruction Manual to Ensure Engine Timing Checked Out Prior to Operation Following Maint1988-08-30030 August 1988 Final Deficiency Rept Re Cracking of ESF Diesel Generator Heads.Initially Reported on 880801.Precautions Added to ESF Diesel Generator Instruction Manual to Ensure Engine Timing Checked Out Prior to Operation Following Maint ST-HL-AE-2698, Final Deficiency Rept Re Veritrak Transmitters.Initially Reported on 860801.Reactor Protection Setpoints Currently in Use Considered Conservative & No Hardware Changes Required1988-06-29029 June 1988 Final Deficiency Rept Re Veritrak Transmitters.Initially Reported on 860801.Reactor Protection Setpoints Currently in Use Considered Conservative & No Hardware Changes Required ST-HL-AE-2696, Part 21 & Deficiency Rept Re Defects in Westinghouse Circuit Breakers.Initially Reported on 880520.Item Reportable Under 10CFR50.55(e) for Unit 2 & 10CFR21 for Units 1 & 2.Remaining Unit 2 Insps Will Be Completed Prior to Fuel Load1988-06-15015 June 1988 Part 21 & Deficiency Rept Re Defects in Westinghouse Circuit Breakers.Initially Reported on 880520.Item Reportable Under 10CFR50.55(e) for Unit 2 & 10CFR21 for Units 1 & 2.Remaining Unit 2 Insps Will Be Completed Prior to Fuel Load ST-HL-AE-2688, Final Deficiency Rept Re Leakage of aluminum-bronze Essential Cooling Water Sys.Initially Reported on 880512. No Safety Concerns Exist If Left Uncorrected Based Upon Detailed Technical Evaluations Previously Submitted1988-06-0909 June 1988 Final Deficiency Rept Re Leakage of aluminum-bronze Essential Cooling Water Sys.Initially Reported on 880512. No Safety Concerns Exist If Left Uncorrected Based Upon Detailed Technical Evaluations Previously Submitted ML20154M6061988-04-18018 April 1988 Provides Further Info Re Seal Matl Incompatibility Issue at Plant,Per 880415 Discussion.Recommends Enhanced Surveillance Program for Suspected Operators to Monitor for Excessive Leakage.Part 21 Related ST-HL-AE-2559, Seventh Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 860801.Westinghouse Presently Compiling Data from Tests on Transmitter Capsules & Amplifiers.Next Rept Will Be Submitted by 8806301988-03-25025 March 1988 Seventh Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 860801.Westinghouse Presently Compiling Data from Tests on Transmitter Capsules & Amplifiers.Next Rept Will Be Submitted by 880630 ST-HL-AE-2538, Supplemental Deficiency Rept on Electrical Splices Using Raychem Heat Shrink Insulation Matl.Initially Reported on 870219.Review of Cables & Terminations Listed as Not Having Splice Performed to Assure Proper Transmission of Info1988-03-0101 March 1988 Supplemental Deficiency Rept on Electrical Splices Using Raychem Heat Shrink Insulation Matl.Initially Reported on 870219.Review of Cables & Terminations Listed as Not Having Splice Performed to Assure Proper Transmission of Info ST-HL-AE-2526, Forwards Proprietary WCAP-11761, South Texas Unit 1 & 2 Reactor Vessel Tilt & Waviness Clarification Study, in Response to 880208 & 11 Requests for Addl Info Re Reporting Condition.Rept Withheld (Ref 10CFR2.790)1988-02-19019 February 1988 Forwards Proprietary WCAP-11761, South Texas Unit 1 & 2 Reactor Vessel Tilt & Waviness Clarification Study, in Response to 880208 & 11 Requests for Addl Info Re Reporting Condition.Rept Withheld (Ref 10CFR2.790) ST-HL-AE-2442, Final Deficiency Rept Re Class 1E Cable Splices.Initially Reported on 870918.Stop Work Order F-02 Issued on 871001, Stopping Installation of All Raychem Matl in Class 1E Electrical Cable Splices1987-12-16016 December 1987 Final Deficiency Rept Re Class 1E Cable Splices.Initially Reported on 870918.Stop Work Order F-02 Issued on 871001, Stopping Installation of All Raychem Matl in Class 1E Electrical Cable Splices ST-HL-AE-2439, Sixth Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 870801.Temp Compensation Shift on Transmitter Capsules No Longer Concern,Per Westinghouse Testing.Amplifier Being Tested.Next Rept by 8803311987-12-0909 December 1987 Sixth Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 870801.Temp Compensation Shift on Transmitter Capsules No Longer Concern,Per Westinghouse Testing.Amplifier Being Tested.Next Rept by 880331 ST-HL-AE-2434, First Interim Deficiency Rept Re RHR Sys Valve Installation. Initially Reported on 871106.Couplings on Pneumatic Operator for Valve B2RHHCV0865,corrected to Change Fail Position from Closed to Open.Next Rept Will Be Submitted by 8801291987-12-0303 December 1987 First Interim Deficiency Rept Re RHR Sys Valve Installation. Initially Reported on 871106.Couplings on Pneumatic Operator for Valve B2RHHCV0865,corrected to Change Fail Position from Closed to Open.Next Rept Will Be Submitted by 880129 ST-HL-AE-2419, Final Part 21 & Deficiency Rept Re Inadequate Cooling of High Voltage Cubicle Panels for Standby Diesel Generators. Initially Reported on 870729.Design Mod to Provide Addl Cooling Completed & Drip Shields Over Vents Removed1987-11-25025 November 1987 Final Part 21 & Deficiency Rept Re Inadequate Cooling of High Voltage Cubicle Panels for Standby Diesel Generators. Initially Reported on 870729.Design Mod to Provide Addl Cooling Completed & Drip Shields Over Vents Removed ST-HL-AE-2400, Final Part 21 & Deficiency Rept Re Failure of Tubes in Component Cooling Water Hxs.Initially Reported on 871006. Discussions W/Vendor,Struthers Wells-Gulfport,Inc Indicated That Shell Side Flow Induced Vibration Problem Existed1987-11-0505 November 1987 Final Part 21 & Deficiency Rept Re Failure of Tubes in Component Cooling Water Hxs.Initially Reported on 871006. Discussions W/Vendor,Struthers Wells-Gulfport,Inc Indicated That Shell Side Flow Induced Vibration Problem Existed ST-HL-AE-2405, Part 21 Rept Re Component Cooling Water Hxs.Initially Reported on 871029.Detailed Info Will Be Submitted in Deficiency Rept by 8711051987-11-0202 November 1987 Part 21 Rept Re Component Cooling Water Hxs.Initially Reported on 871029.Detailed Info Will Be Submitted in Deficiency Rept by 871105 ST-HL-AE-2388, Final Deficiency Rept Re Failure of Standby Diesel Generator Fuel Injection Nozzles.Initially Reported on 870728. Defective Spray Nozzle Tip,Fuel Oil Filters & Lubricating Oil Replaced.All Spray Nozzle Tips Examined for Cracks1987-10-23023 October 1987 Final Deficiency Rept Re Failure of Standby Diesel Generator Fuel Injection Nozzles.Initially Reported on 870728. Defective Spray Nozzle Tip,Fuel Oil Filters & Lubricating Oil Replaced.All Spray Nozzle Tips Examined for Cracks ST-HL-AE-2384, Interim Deficiency Rept Re Class 1E Cable Splices.Initially Reported on 870918.Installation Work Stopped & Installations Determined Not to Meet Raychem Criteria Documented & Evaluated.Next Rept Expected by 8712181987-10-15015 October 1987 Interim Deficiency Rept Re Class 1E Cable Splices.Initially Reported on 870918.Installation Work Stopped & Installations Determined Not to Meet Raychem Criteria Documented & Evaluated.Next Rept Expected by 871218 ST-HL-AE-2385, Final Part 21 & Deficiency Rept Re Actuator Motor shaft-to- Pinion Keys Which Sheared Due to Incorrect or Defective Matl.Initially Reported on 8709171987-10-15015 October 1987 Final Part 21 & Deficiency Rept Re Actuator Motor shaft-to- Pinion Keys Which Sheared Due to Incorrect or Defective Matl.Initially Reported on 870917 ST-HL-AE-2369, Second Interim Deficiency & Part 21 Rept Re Cooling of Unit 1 High Voltage Cubicle Panels for Standby Diesel Generators.Initially Reported on 870729.Util Completed Design Mod to Provide Addl Cooling.Next Rept by 8711301987-09-30030 September 1987 Second Interim Deficiency & Part 21 Rept Re Cooling of Unit 1 High Voltage Cubicle Panels for Standby Diesel Generators.Initially Reported on 870729.Util Completed Design Mod to Provide Addl Cooling.Next Rept by 871130 ST-HL-AE-2338, Fifth Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 860801.Westinghouse Test Program Continuing.Next Rept Will Be Submitted by 8712151987-09-10010 September 1987 Fifth Interim Deficiency Rept Re Veritrak Transmitters. Initially Reported on 860801.Westinghouse Test Program Continuing.Next Rept Will Be Submitted by 871215 ST-HL-AE-2334, Interim Deficiency Rept Re Cooling of Standby Diesel Generator High Voltage Cubicle Panel.Initially Reported on 870729.Design Mod to Increase Cooling of Panels Completed. Next Rept Will Be Submitted by 8709301987-08-31031 August 1987 Interim Deficiency Rept Re Cooling of Standby Diesel Generator High Voltage Cubicle Panel.Initially Reported on 870729.Design Mod to Increase Cooling of Panels Completed. Next Rept Will Be Submitted by 870930 ST-HL-AE-2331, First Interim Part 21 & Deficiency Rept Re Standby Diesel Generator Fuel Injection Nozzles.Initially Reported on 870728.Damaged Fuel Injector Assembly for Diesel Replaced. Recurrence Control Measures Established.Next Rept by 8710261987-08-26026 August 1987 First Interim Part 21 & Deficiency Rept Re Standby Diesel Generator Fuel Injection Nozzles.Initially Reported on 870728.Damaged Fuel Injector Assembly for Diesel Replaced. Recurrence Control Measures Established.Next Rept by 871026 ST-HL-AE-2329, Part 21 & Final Deficiency Rept Re ESF Loading Sequencing. Initially Reported on 870717.Standby Diesel Generator Output Breaker Control Circuit Modified to Delay Closure Signal Until 6-s Following Recognition of Loss of Offsite Power1987-08-21021 August 1987 Part 21 & Final Deficiency Rept Re ESF Loading Sequencing. Initially Reported on 870717.Standby Diesel Generator Output Breaker Control Circuit Modified to Delay Closure Signal Until 6-s Following Recognition of Loss of Offsite Power ST-HL-AE-2321, Final Deficiency Rept Re Fgp Series Agastat Relays.Initially Reported on 870714.Qualified Relays & Sockets in Unit 2 Equipment Will Be Installed in Control Panels Prior to Diesel Start Testing1987-08-12012 August 1987 Final Deficiency Rept Re Fgp Series Agastat Relays.Initially Reported on 870714.Qualified Relays & Sockets in Unit 2 Equipment Will Be Installed in Control Panels Prior to Diesel Start Testing ST-HL-AE-2326, Final Deficiency Rept Re Error in Stress Analysis Program ME101 Used by Bechtel for Class 1 Piping.Initially Reported on 870710.Program Revised to Correct Stiffness Model.No Hardware Mods Required1987-08-12012 August 1987 Final Deficiency Rept Re Error in Stress Analysis Program ME101 Used by Bechtel for Class 1 Piping.Initially Reported on 870710.Program Revised to Correct Stiffness Model.No Hardware Mods Required ST-HL-AE-2307, Part 21 & Deficiency Rept Re ESF Actuation Signal Reset. Initially Reported on 870708.Control Circuits for Components Receiving ESF Actuation Signal Reviewed for Conformance Criteria.Affected Circuits Modified1987-08-0404 August 1987 Part 21 & Deficiency Rept Re ESF Actuation Signal Reset. Initially Reported on 870708.Control Circuits for Components Receiving ESF Actuation Signal Reviewed for Conformance Criteria.Affected Circuits Modified 1999-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210D4821999-07-21021 July 1999 1RE08 ISI Summary Rept for Steam Generator Tubing of South Texas Project Electric Generating Station Unit 1 ML20210D4491999-07-21021 July 1999 Revised Chapters to Operations QA Plan, Including Rev 9 to Chapter 1.0, Organization & Rev 6 to Chapter 16.0, Independent Technical Review NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With1999-07-15015 July 1999 LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20216D7481999-07-0707 July 1999 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1 NOC-AE-000593, Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With1999-06-28028 June 1999 LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With ML20196G5821999-06-23023 June 1999 LER 99-S02-00:on 990601,failure to Maintain Positive Control of Vital Area Security Key Was Noted.Caused by Lack of Attention to Detail.Discussed Event with Operator Involved IAW Constructive Discipline Program ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20196A2391999-06-15015 June 1999 Change QA-042 to Rev 13 of Operations QAP, Reflecting Current Organizational Alignment for South Texas Project & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-000563, Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with ML20206U5411999-05-18018 May 1999 Non-proprietary Errata Pages for Rev 2,Addendum 1 to WCAP-13699, Laser Welded Sleeves for 3/4 Inch Diamete Tube Feedring Type & W Preheater SGs Generic Sleeving Rept ML20206A7721999-04-30030 April 1999 STP Electric Generating Station Unit 1 Cycle 9 Colr NOC-AE-000543, Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with ML20205H0321999-03-31031 March 1999 Change QA-040 to Rev 13 of Operations QA Plan NOC-AE-000507, Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with ML20205A3781999-03-22022 March 1999 STP Electric Generating Station Simulator Certification Four Yr Rept for Units 1 & 2 ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results NOC-AE-000468, Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With ML20207D1101999-02-24024 February 1999 Change QA-039 to Rev 13 of Operations QA Plan, for STP ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20202E8471999-01-31031 January 1999 2RE06 ISI Summary Rept for SG Tubing of STP Electric Generating Station,Unit 2 ML20216G2011999-01-31031 January 1999 City Public Svc of San Antonio Annual Rept 1998-1999 ML20199G5961999-01-31031 January 1999 Cycle 7 Voltage-Based Repair Criteria Rept for Jan 1999 ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20199H4981999-01-11011 January 1999 2RE06 ISI Summary Rept for Welds & Component Supports of Stp,Unit 2 ML20206Q3751999-01-0404 January 1999 2RE06 ISI Summary Rept for Sys Pressure Tests (Class 1 & 2) ML20206Q3721999-01-0404 January 1999 2RE06 ISI Summary Rept for Repairs & Replacements ML20216G2171998-12-31031 December 1998 Houston Industries 1998 Annual Rept. App a 1998 Financial Statements & Us Securities & Exchange Commission Form 10-K Encl NOC-AE-000403, Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With ML20216G1521998-12-31031 December 1998 Central & South West Corp 1998 Summary Annual Rept & Securities & Exchange Commission Form 10-K ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 1999-09-09
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FIELD FABRICATED ANCHOR BOLT IMPROPER MATERIAL DEFICIENCY It!TERIM REPORT I.
SUMMARY
A. Synopsis of the Incident On February 8,1979, HL&P notifed the NRC of a potentially report-able deficiency under 10CFR50.55(e). This deficiency concerned the installation of anchor bolts manufactured from improper materials.
Written reports were forwarded to the NRC on March 8,1979 and June 5,1979. This constitutes the third interim report of the improper material deficiency relative to the field-fabricated anchor bolts.
The discovery of the use of improper material was made during a pull test on a B&R manufactured anchor bolt. The purpose of this test was to confirm that the anchor bolt would fail prior to the plate attachment. The plate, however, failed before the bolt, but at a stress much higher than the yield strength of the ASTM A36 bolt material. A subsequent investigation of the bolt material re-vealed that a mix-up had occurred in the bar stock material used to fabricate some of the anchor bolts et the South Texas Project site. Some of the anchor bolts manufactured from improper rod stock material are installed in various safety related applications in the Reactor Containment Building, Mechanical-Electrical Auxi-11ary Building and the Fuel Handling Building.
B. Postulated Cause of Incident The deficiency was caused by the failure of Construction Quality Procedures to adequately require Quality Control personnel to verify the correctness of all information on material requisitions.
As a result, material other than specified was released for in-s tallation.
C. Synopsis of Corrective Action The immediate response by Quality Assurance to this incident was to issue a stop work notice to prevent further use of site manu-factured bolts until the deficiency could be corrected. The con-struction procedure governing storege of materials was revised to provide for additional marking of the received material. Also, all site manufactured bolts and rod material were subjected to a hardness test program to verify material type for all material received through September,1979. For material received since September,1979, the certified material test reports have been
_1 8 0 0214 0 /3</
verified and the material has been permanently marked. To assure these corrective action measures are properly implemented, a resi-dent lead Quality Assurance inspector has been assigned on a full-term basis to the fabrication shop to supervise all operations.
Finally, a training program has been instituted to instruct site personnel in the proper procedure for identification of storage and traceability of bulk materials received.
D. Synopsis of the Results of the Safety Evaluation As the result of the fielu test and inspection program, non-con-forming anchor bolts were found in safety-related applications.
In most cases, ASTM A-193 Gr B7 bolts were found installed in lieu of the specifiec ASTM A-36 Grade. Because the ASTM A193 Gr B7 bolts are of a higher strength than the A-36 bolts, substitution of the higher strength material is considered acceptable. In other locations, however, the installed bolts are of a lesser grade material than originally required. In one case, Reactor Coolant System (RCS) hot and cold leg pipe support brackets, anchor bolt torque requirements were re-evaluated by Westinghouse and the lesser grade bolts were found to be acceptable. The re-maining locations are currently being evaluated by Brown & Root Design Engineering. If the installed anchor bolts are not found to be acceptable, they will be replaced with ASTM A-193 Gr B7 bolts or additional design measures will be taken to meet the correct load requirements.
II. DESCRIPTION OF INCIDENT A. Component Identification A large quantity of anchor bolts were manufactured at the South Texas Site by Brown & Root to offset an inadequate supply of vendor manufactured anchor bolts. The primary function of these elements
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is to secure structural steel members or machinery bases to their concrete foundations. Anchor bolts classified as Type I, II, III, IV, and V conform to ASTM A36 material. Classification Type VI conforms to ASTM A193.Gr B7 material. A sketch of the Type I thru VI bolts is shown in Figures 1 through 3. The bolt config-uration is designed based upon the loading, tensile stress area, and the yield strength of the bolt. A design allowable strength of 22 ksi was used for ASTM A36 bolts and 48 ski was used for ASTM A193 Gr B7 bolts. These design allowable strengths contain a considerable safety margin since the minimum yield strengths are 36 ksi and 115 ksi for the A36 and A193 material, respectively.
B. Source of the Incident The incident was discovered during an anchor bolt pull test on a B&R manufactured anchor bolt. The purpose of this test was to confirm that the bolt would fail before the plate. The plate, however, failed before, but at a stress much higher than the yield strength of the ASTM A36 bolt material. Investigation revealed that the bolt material was ASTM A193 steel instead :,i the ASTM A36 material that was specified for the bolt. A subsequent in-vestigation revealed that a mix-up had occurred in the bar stock material that was used to manufacture the bolts.
C. Date and Means by Which Incident Information was Obtained -
On February 1,1979, Quality Assurance was notified of the results of the pull test which indicated that material had been mixed. On February 8,1979, HL&P notified the NRC of a reportable deficiency under 10CFR50.55(e).
D. Unusual Circumstances Fabrication of anchor bolts at the STP site was not anticipated or intended for the Project. Original plans called for all anchor bolts to be furnished by vendors contracted for furnishing fabri-cated iron and steel. Production delays at several fabricators' facilities resulted in an inadequate supply of anchor bolts being shipped to the job site. In order to maintain job schedules, it was decided that site fabrication was the only viable alternative in obtaining anchor bolts.
E. Status of Construction at Time of Incident At the time of the incident, approximately 7,000 anchor bolts of various sizes and configurations had been manufactured at the STP job site. Of these, approximately 50% were installed in concrete.
The remainder of the bolts were located in the storage yard.
F. Procedures in Effect to Avoid Incident at Time of Incident The procedures in effect at the time of the incident required material verification by heat number at the receipt of the ship-ment and the assignment of a heat code to the material. Material identification from that time fonvard was maintained through fabrication by the heat code assigned. The verification of issued equipment consisted of a verification of the heat code transfer to the requisition to provide traceability throughout fabrication.
III. CORRECTIVE ACTION A. Immediate Response by Quality Assurance to the Incident Site Quality Assurance issued a non-conformance report on February 1, 1979 to reflect the results of a documentation review concerning rod stock material used in the manufacture of anchor bolts. As a 3
result of further investigations, Site Quality Assurance issued a stop work notice on the fabrication of anchor bolts at the job site.
B, Description of All Imediate Actions Taken to Correct the Deficiency Quality Assurance requested and obtained a revision to the Con-struction Procedure governing storage of materials to provide for additional marking of the received material. This additional marking was in the form of color coding and permanent marking of all Category I material. In addition, the revision to the pro-cedure required Quality Control to verify the heat codes of the material to the certified material test report for all material received.
C. Long Range Actions Taken to Correct the Deficiency The initial extent of this deficiency was determined by a review of the documentation associated with the rod stock used for site manu-factured anchor balts. The material heat numbers were taken from the warehouse requisitions and compared with the certified material test reports to determine if a mix-up had occurred.
After discovering the inconsistencies in the identification of anchor bolt material, a decision was made that all installed and uninstalled site manufactured bolts would be subjected to surface hardness testing as a means of verifying material type. A three phase program was initiated which consisted of (1) identification of all work orders issued for site manufactured anchor bolts, (2) the location of the bolts and determination of material type using a telebrinnell portable hardness kit, and (3) reporting of the results for engineering design evaluation.
The basic points of the field testing program included (1) the testing and verification of all material using the portable tele-brinnell hardness testing kit, (2) the verification and QC wit-nessing of the measurements taken by Construction Engineering, (3) the verification of the material type against the requirements of the design drawings, and (4) the identification of non-con-forming conditions. Field measurements were taken and independ-ently verified by Site Quality Control. The data forms, following verification by Quality Control, were submitted for engineering evaluation. A sample data form is shown in Figure 4.
The initial step in the hardness testing program was to inspect and test those bolts which had been fabricated and not yet in-stalled (approximately 3500). All field fabricated anchor bolts located in the miscellaneous steel laydown area were tested and documented. Approximately 460 non-conforming anchor bolts were found and Nonconformance Reports were issued. All of the bolts identified on these nonconformance reports were scrapped with the exception of 103 bolts, which were A193 material used in lieu of A36 material for Type V anchor bolts. A decision was made to use these colts in their intended location as the A193 material provides i higher strength than the original design requirements.
Once the colts in the storage yard were checked and verified, field personnel proceeded to locate and test the remaining field fabri-cated bolts installed in concrete (approximately 3900). Top priority was given to bolts needed for concrete pours. These items were tested, reviewed, and accepted (or rejected) by Construction Engineering and Quality Control personnel prior to pouring of concrete. Inspection data sheets were submitted for engineering review and final dispositioning.
Approximately 150 non-conforming anchor bolts were found in the Reactor Containment Building, Mechanical-Electrical Auxiliary Build-ing and Fuel Handling Building. In the Mechanical-Electrical Auxi-liary Building, higher strength A193 material was used in lieu of A36 material. In the other locations, the material installed was of a lesser grade than that required by the design drawings. The use of A36 material in these locations is presently being analyzed by Brown & Root Engineering.
The remaining items to be verified at the job site consisted of bulk material rod stock that may be used in future fabrication of anchor bol ts . All rod stock received prior to October 1,1979 has been hardness tested, bterial received after the date has been veri-fied against certified material test reports, marked with heat codes by QC Receiving, color coded, and segregated by safety classi-fication and material type in the storage yard. All bulk material has been properly identified and is in compliance with specifica-tions and procedures. The inspection data sheets for all bulk rod material have been submitted for final engineering review and dis-positioning.
All rod stock material and fabricated anchor bolts have been tested at the job site with the exception of pieces that are inaccessible.
There are approximately 400 bolts, both safety and non-safety re-lated, which are inaccessible at this time due to equipment place-ment, form work, etc. Testing will be accomplished as each area is made accessible.
Approximately 12,000 pieces of material b' c t- been tested at the South Texas job site. These figures ic.# alt safety related and non-safety related rod stock anf rw w oolt material.
IV. RECURRENCE CONTROL In order to preclude recurrence of this deficiency, five actions have been taken. These actions are:
A. Inspection Quality Assurance has assigned a resident lead inspector to the fabrication shop for supervision of all operations.
B. Material Identification Procedures have been instituted to require permanently stanying of the heat code on all Category I materials.
C. Verification Quality Control is required by procedures to verify all material heat code numbers identified in the heat code log back to the certified material test reports contained in the Quality Assurance
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va u i ts .
D. Receiving Inspection Procedural revisions have been incorporated to provide a systematic program for the identification and marking of material upon receipt at the job site prior to releasing for storage or fabrication.
E. Training Program A training program has been initiated in which site personnel are instructed in the proper procedure for identification, storage, and traceability of bulk materials received at the job site.
V. SAFETY ANALYSIS A. Niture of the Incident Anchor bolts manufactured from improper bar stock material are in-stalled in various safety-related applications in the Reactor Con-tainment Building, Mechanical-Electrical Auxiliary Building, and the Fuel Handling Juilding. The failure of specific anchor bolts could, under certain conditions, create a safety hazard.
B. Results of Investigations In seven locations, material has been installed that is of a lesser grade than required by the design drawings. In all other non-con-forming conditions, ASTM A193 Gr B7 material was installed in lieu of the ASTM A36 material specified on the design drawings. The substitution of the higher strength A193 B7 material for the A36 material is considered satisfactory in all cases for Type V anchor bol ts . In two locat'ons, ASTM A193 B7 material was used to fab-ricate Type II anchor bolts and is n>t considered satisfactory.
An evaluation is underway by Brown & Root Design Engineering to determine the significance of the cases in which improper substi-tution has been made. If the rese'ts of this evaluation are un-acceptable, the anchor bolts will , <eplaced or additional design measures taken to meet or exceed existing load requirements.
An extensive safety analysis will not be accomplished. All installed anchor bolts have been tested and identified and meet or exceed the design requirements, with the exception of the locations previously identified and presently undergoing evaluation.
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