Final Deficiency Rept Re Concrete Voids in Eighth Lift of Unit 1 Reactor Bldg Exterior Wall.Concrete Voids Repaired & Full Implementation of Recurrence Control Is CompleteML19296C601 |
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South Texas |
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02/18/1980 |
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HOUSTON LIGHTING & POWER CO. |
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Shared Package |
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ML19296C597 |
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NUDOCS 8002260693 |
Download: ML19296C601 (10) |
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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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FINAL REPORT INVESTIGATION AND REPAIR OF THE CONCRETE VOIDS IN THE EXTERIOR SHELL WALL OF THE STPEGS REACTOR CONTAINMENT BUILDINGS 1 AND 2 I.
SUMMARY
On July 16, 1979, pursuant to 10CFR50.55(e), Houston Lighting & Power Company submitted to the Nuclear Regulatory Commission (NRC), Region IV, an interim report on the detection of concrete voids in the 8th lift of the Unit 1 Reactor Containment Building (RCB). On August 15, 1979. Houston Lighting & Power Company (HL&P) submitted a Second Interim Report on the Reportable Deficiency. At the time of this Second Interim Report, a significant amount of investigation was complete and recomen-dations for corrective action had been proposed. The repair work and full implementation of the recurrence control, however, had not been completed. At this time, the investigation and repair of the defi-ciencies for both Unit 1 (Lift 1 through 17) and Unit 2 (Lift 1 through 6) have been completed except for an area in Unit 2 as described below. The investigation and repair work on the fifteenth lift of the Uni' 1 RCS had previously been completed and reported on June 5,1979.
The concrete voids described herein were found to have occurred in areas beneath shell penetrations and/or beneath the 8 inch channel and plate stiffeners where additional reinforcing steel are located. The repairs to restore the concrete shell to its original structural integrity have been completed, except for an approximately 10 foot by 14 foot area in the Unit 2 RCB where the liner was inadvertently deformed. The repair methods used were thoroughly tested and analyzed prior to their use; and were, to a great extent, based upon the investigation and ropair of the fifteenth lift in the Unit 1 Reactor Containment Building.
Subsequent to the discovery of the voids in Lift 8 of Unit 1, a Stop Work Notice was issued on all concrete pours. An investigation was conducted to determine the cause of the voids and as a result, a list of corrective action was defined that would preclude recurrence. This list was de-scribed in the Second Interim Report. Actions were taken to integrate these corrections into construction and inspection procedures; therefore, the Stop Work Notice was lifted.
During the investigation and analysis, it was detennined that if left uncorrected, these voids could have compromised the structural integrity of the Containment shell in that the as-built configuration would not have met its design load and shielding criteria.
II. DESCRIPTION OF THE INCIDENT
- a. Identification During the investigation of the Lift 15 voids on the Unit 1 Containment Building, infonnation was obtained from Site personnel which lead to the concern that voids might exist in Lift 8 of that same building.
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Final Report Page 2 Soundings were begun and it was detemined by drilling that voids did indeed exist. A program was established to identify all sig-nificant voids in the RCB exterior shell wall for both Units 1 and 2.
- b. Extent During the investigation of the extent of these voids, it was deter-mined that where such voids did exist, they were located beneath penetrations and/or the 8 inch channel or plate stiffeners where additional steel was located. One special area in Unit 1 was in-vestigated where a construction block-out had been located. The top of the block-out was suspected to have trapped voids during tne placement because of the horizontal nature of the joint. One void at each top corner was found and repaired using the same procedures as the others.
Larger voids were found in areas of larger penetrations where con-crete placement was more difficult due to the added congestion of reinforcing steel. Figures A and B represent the location and approximate volume of grout pumped into the voids for Units 1 and 2 respectively. Of the total number of holes drilled during this investigation in both Units, including all additional holes added for venting purposed, over 70". indicated that no void existed.
Unit 1: The largest void in tems of volume was located above the equipment hatch below an 8 inch plate stiffener. This void, however, did not extend through the shell wall . Voids were de-termined to have extended through the shell wall directly be-neath the four main steam lines and two 58 inch diameter HVAC penetrations. These voids did not extend beyond 12 inches from the bottom of the penetration sleeve, with the majority not ex-tending beyond 2 inches.
Unit 2: In general, voids determined in Unit 2 were not as large or deep as those found in Unit 1. One isolated area did vent to the outside of the Containment and was located below an electrical 0
penetration near Azimuth 335 and Elev. 45'. All remaining voids were located at random positions beneath other pencations and/or the 8 inch channel and plate stiffeners.
- c. Means of Obtaining Infonnation For tracking purposes, the investigation was divided into the following phases:
o Phase 1 - Previous investigation and repair of Lift 15, Unit 1.
o Phase 2 - Lift 8, Unit 1.
o Phase 3 - Equipment Hatch, Personnel Hatch, and Mair Steam and Feedwater Lines, Unit 1.
Final Report Page 3 o Phase 4 - Remaining Areas of Unit I where potential voids could exist.
o Phase 5 - Unit 2 (Areas similar to Unit 1)
Phase 2 was dispositioned separately to permit closecut of the existing nonconformance report identified for Lift 8 and also to assist the construction schedule at this elevation. Phase 2 has been identified on a nonconformance report submitted on 9-12-79 with closecut including repair and verification on 11-13-79.
Phase 3, 4 and 5 have been identified on a nonconformance report submitted on 1-8-80 with final closecut including repair and veri-fication on 2-7-80 with the exception of the areas at the liner deformation.
The work on these phases was identified in the nonconformance reporting system.
- d. Status of Construction At the time of the stop work order on June 22, 1979, concrete ex-terior wall placements had progressed through Lift 17 (Elev. +150')
on Unit I and through Lift 6 (Elev. +47') on Unit 2.
- e. procedures in Effect to Avoid the Incident Operating procedures were in effect that provided for preplacement planning and design engineering involvement in developing particular concreting methods to assist the placement. However, sufficient preplacement planning was not exercised and the procedures were determined to be inadequate.
III. CORRECTIVE ACTION
- a. Investioation Following completion of the investigation, as previously discussed in the Second Interim Report, the investigation was expanded to other areas of Unit 1 and similar areas in Unit 2.
The area identified in Phase 2 thru 5 were physically sounded by tapping to determine suspected voids behind the 3/8 inch liner mem-brane. A gap behind the 3/8 inch plate of as little as 0.001 inch to 0.002 inch will yield a hollow sound when the plate is tapped.
Such spaces are caused by thermal shrinkage of the liner plate, concrete shrinkage and settlement, the attachment of temporary weld-ments, etc. and are not structurally significant. The presence of voids requiring grout (groutable voids) was then confirmed by drilling through the liner plate in places where potential voids could be ex-pected such as under stiffeners and beneath penetrations where concentrated reinforcement was located. Other areas which sounded
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- Final Report Page 4 hollow, but where the lack of interferences made the occurrence of voids unlikely were also drilled. All such areas verified the absence of groutable voids.
Where the soundirg method was uncertain, such as through the thickened collars and plates around the penetrations, holes were drilled through the plate beneath the 8 inch stiffeners and between the bottom gusset stiffeners of the penetration sleeve. Where any showed a void, succes-sive holes were drilled to adequately define the void snd until no void was found.
A similar pattern of holes were drilled through external collar plates around penetrations on the exterior of the containmc-t ehell to locate voids that might exist there and to provide vents ft .y voids that might extend from inside to outside. All such hola ,cated in the area beneath penetrations were extended either e- interference occurred or until they intersected a void on thc pposite wall face.
All voids were pressure tested with water at controlled pressures to determine which holes were interconnected by voids behind the liner plate and also to see which vented to the outside. Interconnections were marked on the face of the liner and the optimum hole of an inter-connected group was selected for the eventual grout injection point.
This procedure, executed a day or so prior to grout, assured that the concrete would be saturated. It also served as a training or re-training program for personnel involved in the grouting operation in that the water was pumped through the same grout pump, grout hose and instrument skid (with pressure gauge) as was used for grouting.
Headphone communication teetween the injection area and the pump was also used. On completion of testing in each area, the valves were opened to drain off the water and in some instances, the air line was connected to the top-most hole and remaining water was forced out the lowest hole by air pressure.
Water pressure behind the liner plate was held to 10 to 20 psi by limiting the pressure at the skid to 30 to 40 psi while the water was moving, the difference being pressure loss in the 20 to 30 feet of 3/4 inch hose due to elevation differences and connections be-tween the skid and the liner. Whenever gauge pressures approached these values, water was shut off and the rate of pressure drop noted.
If the drop was rapid, water was turned on again to determine inter-connections or leaks to the outside. If the drop was slow, the test was terminated and the connection changed to another group of holes.
During testing of the Unit 2 RCB for void formations, inadvertent overpressurization occurred. This resulted in the " bulging" of a section of the steel liner. After relief of the overpressure, some residual defonnation remained. This matter is being handled as a separate non-confennance.
Final Report Page 5
- b. Material Qualifications The material selected to fill the voids behind the liner and beneath penetrations is Master Builders Masterflow 814 Prepackaged Commercial High Strength, Highly Fluid, Non-Shrink Portland Cement based grout which satisfies the requirements of CRD C588-76, Corps of Engineers Specification for Non-Shrink Grout. This grout does not bleed when mixed to a high fluidity with a flow cone reading as low as 15 sec-ond.e (flow cone, CRD C79) at as-mixed temperatures as low as 35 F, pro.ided the mix-water content is not in excess of that at which it was qualified at normal temperatures (the vicinity of 700F). High fluidity at the time of injection results in maximum penetration into '.he surface voids for bond and into honeycombed areas for con-solidation. Absence of bleeding means that bleedwater will not collect at the top of the voids or at the undarsides of the steel stiffeners and reinforcing steel to destroy contad and bond. The grout expands slightly after hardening to ensure permanent, tight contact with all surrounding concrete and steel surface.
Laboratory and field tests were performed previously for the lift 15, Unit 1 RCB repair to verify the compressive strength, modulus of elasticity, flow and bond characteristics, and bond / shear characteristics of the concrete / grout interface. All tests have confirmed the suitability of this grout for the intended use.
- c. Design Analysis A calculation was performed to thoroughly examine and evaluate the Containment shell design, including the areas around the large and small penetrations. Based upon previous tests performed for the equal to Lift 4,000 psi was established conservatively for the concrete grout
- 15. Unit 1 RCB repair, a compressive strength of fc /
interf ace. The adequacy of the steel anchorage system of the penetrations to transfer forces into the concrete section was checked for the new strength. The design of the concrete shell sections, including the areas of stress concentrations around the penetrations, were re-evaluated for the new strength. A complete re-evaluation of the design showed that the grout repair would be adequate and the shell sections would be reacting within the allow-able stresses under the design loads,
- d. Recair
- 1. Grout Repair: The basic grouting equipment was a Chem-Grout unit which consisted of two (2) vertical shaft mixers mounted on a progressive cavity pump. Water was batched by gravity from a 50 gallon reservoir tank into a 25 gallon (approx.)
batching tank located over the mixers. Grout hose, lh inch diameter, in 50 foot lengths as needed, transferred the grout
Final Report Page 6 to the point of injection. 4 the injection area, control was exercised by a ball valve ' allowed by a pressure gauge mounted on a skid that could be m;ved from area to area. A 10 foot (longer if required) leng h of 1 inch hose carried the grout from the skid to 3/4 inch i.d. inserts (with ball valves) screwed into couplings welded to the liner plate. This is the same equipment that was used successfully in the repair of Lift 15, Unit 1.
Grout was mixed and pumped in accordance with the following procedure:
- Mixing water was pre-cooled by floating ice in a 10,000 gallon tanker located at the base of the building and further cooled by shaved ice floating in both the reserve holding and batching tanks above the two mixers.
- Grout was mixed with the maximum water shown on certified material test reports from the manufacturer. Ice from 55 gallon drums was substituted for some of the mixing water (by weight) in order to achieve the lowest temperatures possible. The grout, as mixed, generally showed flow cone consistenciesingherangeof15to20secondsattempera-tures of 40 to 50 F. The normal batch was 10 bags of Master-flow 814 grout which produced approximately 6 cubic feet of fluid grout. Five bag batches were produced frequently for topping out and where flow was slow.
- The pump hopper and grout hose were drained of water during the preparation of the first batch of grout. Grout was then pumped into a waste drum located at the liner connection until all remaining water in thq lines had been discharged and undiluted grout appeared.
- Grout connection was then made to the lowest open insert, as detennined during the preceeding water pressure testing, and pumping started. As in the pressure testing, successively higher insert holes were shut off as full-consistency grout appeared, i.e., water-diluted grout and/or air bubbles were allowed to escape. As the area filled and the last inter-connected hole closed, grout pressure was allowed to build up to 20 to 30 psi. As long as a hole would accept a measurable amount of grout (pressure gauge drop of 5 psi in about 15 seconds and/or a noticeable vibration of the 1 inch hose at the liner insert), the hole was repressurized.
Most areas " refused" at two or three pressure cycles, but a few were continued for as long as 10 minutes as water dripped from an open hole, which indicated continuing grout penetration.
Final Report Page 7
- Grout was next applied to peripheral holes where grout return had been minimal.
- 2. Liner Repair: The investigation of the concrete behind the liner plate necessitated the drilling of nominal lh inch diameter holes. In addition to the holes drilled for investigative pur-poses, some holes had to be drilled to facilitate the injection and venting of grout into areas requiring recairs.
The holes drilled in the liner plate' have been repaired by using couplings made of approved ASTM materials. (ASME SA-105 ASME Section III, Division 2, Subsection CC for Couplings, Plugs and Fittings). These couplings have been machined to fit the holes and welded to the liner to meet the ASME require-ments for leak tightness.
A defomed liner section in the Unit 2 RCB is being repaired by removing the damaged section and replacing it with a new section. Grout repair in this area will then be perfonned using the same procedures mentioned above. The grout section will be keyed to the existing concrete. The repair will re-store the liner and concrete section to its intended design condition.
- e. Action to Prevent Recurrence As a result of investigations reft. red to in the Second Interim Re-port for Lift 8, Unit i voids (on August 15,1979), it was deter-mined that recurrence could be prevented by providing for better accessibility to those areas of congestion where additional in-spection and vibration is required, and by strengthening the con-struction and quality control procedures. Construction and in-spection procedures and necessary engineering design documents have been revised to reflect the recomendations contained in Table 1 of the referenced Second Interim Report for the Lift 8 voids.
IV. SAFETY ANALYSIS An analysis to determine the safety implications of this incident was conducted as follows:
- On June 18, 1979, the Incident Review Comittee met and HL&P noti-fied the NRC that the condition was reportable under the requirements of10CFR50.55(e).
- The Comittee detemined that, if left uncorrected, these voids could have compromised the structural integrity of the RC3 shell in that the as-built configuration would not have met its design load and shielding requirements.
Final Report Page 8
- Areas where voids extended through the shell wall were evaluated for shielding requirements. The shielding adequacy was not compromised due to the fact that the voids were filled.
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