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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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The Light mmPuy sees,ee <>s ,ies & ee.., s e.o. ee, ivoo sees,ee.1 x.,21ooi <2is> 22s.o2,i November 11, 1980 ST-HL-AE-574 SFN: V-0530 Mr. Karl Seyfrit '
Director, Region IV Nuclear Regulatory Comission -
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
Dear Mr. Seyfrit:
South Texas Project
~
2 '
Units 1&2 Docket Nos. STN 50-498, STN 50-499 Interim Report Concerning Reactor Cavity Ventilation Design Please find attached our interim report regarding reactor cavity ventilation des.ign which Houston Lighting & Power Company verbally report-ed to your office on October 17, 1980 as being potentially reportable pursuant to 10CFR50.55(e). The next interim report will be submittad to your office by January 27, 1981.
If there are any questions concerning this item, please contact Mr.
Michael E. Powell at (713) 676-8592.
Very t ygyours, s / '
7 ea
/ .
Execu 1ve V resident MEP/pjb Attachment pS/ 7 8 011 1 s cQ-> sif 1
l
~. .
l
. l Houston Lighting & Power Company November 11, 1980 ST-HL-AE-574 SFN: V-0530 Page 2 cc: J. H. Goldberg D. G. Barker Howard Pyle R. L. Waldrop H. R. Dean -
D. R. Beeth J. D. Parsons G. B. Painter L. K. English A. J. Granger R. A. Frazar H. S. Phillips (NRC)
.1. O. Read Read-Poland Inc.)
M. D. Schwarz Baker & Botts)
R. Gordon Gooch Baker & Botts)
J. R. Newman Lowenstein Newman, Reis, Axelrad & Toll)
Director, Office of Inspection & Enforcement Nuclear Regulatory Comission Washington, D. C. 20555
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Houston Lighting & Power Company November 11, 1980 ST-HL-AE-574 SFN: V-0530 Page 3 M. L. Borchelt Executive Vice President Central Power 6 Light Company P. O. Box 2121 Corpus Christi, Texas 78403 R. L. Range Central Power & Light Company P. O. Box 2121 Corpus Christi, Texas 78403 R. L. Hancock Director of Electrical Utilities City of Austin P. O. Box 1088 Austin, Texas 78767 T. H. Muehlenbeck City of Austin P. O. Box 1088 Austin, Texas 78767 J. B. Poston Assistant General Manager of Operations City Public Service Board P. O. Box 1771 San Antonio, Texas 78296 A. vonRosenberg City Public Service Board P. O. Box 1771 San Antonio, Texas 78296 i
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Houston Ughdng & Power Ckunpany November 11, 1980 ST-HL-AE-574 SFN: V-0530 ;
Charles Bechoefer, Esquire Page 4 i Chairman, Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. James C. Lamb, III 313 Woodhaven Road Chapel Hill, North Carolina 27514 Dr. Emmeth A. Luebke Atomic Safety & Licensing Commission U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Steven A. Sinkin, Esquire 116 Villita Street t San Antonio, Texas 78205 Citizens for Equitable Utilities c/o Ms. Peggy Buchorn Route 1 Box 432 Brazoria, Texas 77422 Pat Coy Citizens Concerned About Nuclear Power 5106 Casa Oro San Antonio, Texas 77422 Ricnard W. Lowerre, Esquire Assistant Attorney General for the State of Texas P. O. Box 12548 Capitol Station Austin, Texas 78711 Bernard M. Bardenick Hearing Attorney Office of the Executive Legal Director U. S. Nuclear Regulatory Connission Washington, D. C. 20555 f
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Interim Report j Concerning Reactor Cavity Ventilation Design November 11. 1980 On October 17 ,1980, pursuant to 10CFR50.55(e), Houston Lighting &
Power Company notified your office of a potentially reportable deficiency concerning the reactor cavity ventilation design for the South Texas Project Electric Generating Station, Units 1 and 2.
The design criteria requires that ventilation be provided to the reactor cavity, primary shield wall penetrations and inspection toroid volunes suffi -
cient to maintain primary shield wall concrete temperatures within specified limits during nomal plant operation. During a recent confimatory themal analysis perfomed by Brown & Root of the reactor coolant piping supports located in primary shield wall penetrations, it was detemined that the temperature of the primary shield wall concrete in the penetration and along the face exposed to the reactor vessel would exceed the specified limits.
The structural integrity of the shield wall in these areas could be reduced because of localized concrete failure resulting from these temperatures.
Brown & Root has investigated th Cause of this design defect and deter-mined that the original ventilation calculation did not account for flow
' resistance due to the reactor vessel nozzle configuration and the reactor cavity seal plate configuration. The seal plate is required to limit asymetric loads on the reactor vessel following a break at the vessel nozzle (ref. FSAR 6.2.1.2.2.1 and 6.2.1.2.3.2). In addition, the vent area at the top of the reactor cavity is inadequate. This vent area design was based on preliminary infomation.
Assuming adequate ventilation design, the reactor can be brought to a safe shutdown condition following loss of cavity cooling without exceeding shield wall concrete temperature limits.
The current status of design and construction in the areas of concern is as follows:
Unit 1 Primary shield wall concrete has been poured to El. 29'-4".
The reactor vessel is in place and primary coolant piping welded to the reactor vessel nozzles. Primary shield wall concrete above E1. 29'-4 is on hold. The reactor cavity seal plate design has not been issued for constn .'. tion. It will not be issued until all design problems noteo - this deficiency are resolved. The reactor cavity cooling fan unit is at the site and is awaiting installation. This fan is currently placed on hold.
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Unit 2 Primary shield wall conrete has been poured to El.19'-0".
All primary shield wall concrete above E1.19'-0" is on hold.
The reactor vessel is not in place. The reactor cavity seal plate. design is in the same status as the design for Unit 1.
It will not be released for construction until all design problems noted in this deficiency are resolved. The reactor cavity cooling fan unit is at the site and is awaiting install-tion. This fan is currtently placed on hold.
In order to satisfactorily correct the design deiact, alternatives are currently being evaluated, which include redesign of the reactor cavity seal plate and potential reactor cavity venting designs.
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