ELV-00365, Forwards Comments on Sser 8.Spent Fuel Storage Racks Will Have Boraflex on All Sides,Including Sides Adjacent to Fuel Pool Walls
ST-HL-AE-2847, Forwards FSAR Pages Supporting Request to Utilize Heatup & Cooldown Curves for Tech Specs Instead of Curves Previously Submitted.Changes Will Be Incorporated in Future FSAR Amend
ST-HL-AE-2810, Notifies That Unit 2 Bypass/Inoperable Monitoring Will Be Installed for Containment Purge Sample Isolation Valves Prior to Fuel Load
ST-HL-AE-2821, Forwards Revised Pages to 880810 Relief Request RR-ENG-07 Re Preservice Insp Program,Per 880908 Telcon
ST-HL-AE-2514, Forwards Rev 0 to 5UO36JS0002, Preservice Insp Exam of Component Supports for South Texas Project Electric Generating Station-Unit 2
ST-HL-AE-2882, Forwards Preservice Insp Summary Rept for Class 1,Class 2 & Class 3 Component Supports at South Texas Project Electric Generating Station Unit 2
ST-HL-AE-2693, Discusses 880602 Meeting W/Nrc Re Use of PRA Techniques to Justify Extending Allowed Outage Times for Certain safety- Related Sys.Followup Meeting Will Be Scheduled for Fall 1988.Viewgraphs Encl
ST-HL-AE-2683, Forwards Annotated Revs to FSAR Re Redesign of Unit Initial Core to Accomodate Revised Cycle Length of Approx 400 Efpds. Westinghouse Evaluation Concluded That LOCA Analysis Unaffected by Change
ST-HL-AE-2807, Forwards Preservice Insp Summary Rept for Class 1 & Class 2 Pressure Retaining Components at South Texas Project Generating Station-Unit 2, Vols I & II
ST-HL-AE-2780, Requests Meeting W/Region IV to Discuss Schedule for Lock Down Security Schedule of Facility.Meeting Tentatively Scheduled for 880908
ST-HL-AE-2781, Forwards Preservice Insp Summary Rept of Steam Generator Tubing
ST-HL-AE-2751, Forwards Addl Info in Response to NRC Questions Re Revised Core Design & Energy Requirements
ST-HL-AE-2627, Discusses Highlights from 880405 Meeting Re as-built Reconciliation Program.Adequate Info Provided for NRC to Confirm That Design & Const Program Incorporated Features Per IE Bulletin 79-14
ST-HL-AE-2605, Forwards Rev 0 to Unit 2 Pump & Valve Inservice Test Plan. Valve Stroke Time Criteria Will Be Incorporated Into Subsequent Revs as Baseline Data Obtained.Plant Mods Affecting Plan Will Be Provided in Subsequent Revs
ST-HL-AE-2720, Forwards Rev 1 to Preservice Insp Program Relief Request RR-ENG-02,deleting Application to Unit 2
ST-HL-AE-2719, Forwards Revised Annotated FSAR Revs Re Radiological Consequences of Locked Rotor Accident
05000482/LER-1989-018, :on 890828,inoperability of Both Exhaust Sys Resulted Due to Failure to Place Dampers in Safeguard Position.Lesson Plan Issued on Tagging of Ventilation Dampers to Personnel
05000482/LER-1989-017, :on 890830,control Room Ventilation Isolation Signal Initiated When Chlorine Monitor Indicated High Level. Caused by Spurious Spike.Recorder Connected to Chlorine Monitor GK-AITS-3 to Monitor Channel Behavior
05000482/LER-1989-010, :on 890616,discovered That Tech Spec Requirement 4.11.2.6 Re Quantity of Radioactive Matl Not Met.Caused by Inadequate Programmatic Controls.Procedures Re Gas Decay Tank Additions Revised
05000482/LER-1989-012, :on 890626,control Room Ventilation Isolation Signal Initiated When Control Room Air Intake Radiation Monitor GKRE-04 Experienced Loss of Power.Caused by Blown Fuse.Fuse Replaced
05000482/LER-1989-011, :on 890623,both Class 1E Air Conditioning Units SGK05A & SGK05B Were Inoperable.Caused by Loose Wire Disconnected from Lug on pump-down Switch.Wire Recrimped & Units Returned to Svc.Personnel Reinstructed
05000482/LER-1989-009, :on 890419,exams of Fire Protection Sys Piping Revealed Incomplete Penetration of Pipe Seam Welds Existed in Discharge Header for motor-driven Fire Pump.Cause Unknown.Evaluation of Piping Being Conducted
05000482/LER-1989-016, :on 890809,discovered That Surveillance Procedure for Train B Reactor Trip Breaker Trip Actuating Device Operational Test Not Performed by 890703.Caused by Personnel Error.Program Enhancement Made
05000482/LER-1989-014, :on 890718,control Room Ventilation Isolation Signal Initiated by Spike on Control Room Air Intake Radiation Monitor.Caused by Voltage Transient Associated W/ Lamp Burning Out.Monitor Restored
05000482/LER-1989-015, :on 890717,discovered That Violation of Sampling Requirements of Tech Spec 3.11.1.1 Occurred.On 890716,daily Grab Sample Not Obtained for Continuous Liquid Effluent Release.Caused by Personnel Error
05000482/LER-1988-030, :on 890524,discovered That Violation of Tech Spec 3.5.2 Occurred Resulting in Containment Insp Not Properly Documented Following Containment Entries on 880102 & 05.Cause Unknown.Schedule Revised
05000482/LER-1989-013, :on 890711,feedwater Isolation Signal Occurred When Water in Steam Generator a Increased to hi-hi Level Setpoint,Causing Main Turbine Trip Signal.Caused by Leakage Through Bypass Control Valves
05000482/LER-1987-033, :on 870813,tests of All Types B & C Valves Indicated Leakage in Excess of Tech Spec Limit.Caused by Cognitive Personnel Error.Ltr Issued Outlining Testing Requirements & Maint Activities
05000482/LER-1987-039, :on 870916,absence of Position Indication for Pressurizer PORV BB-PCV-456A Block Valve Bb HV-8000B Discovered.Probably Caused by Personnel Error.Discussions Held W/Involved Personnel & Supervisors
05000482/LER-1987-017, :on 870419,reactor Trips Occurred During Reduction Required by Tech Spec 3.1.3.1.Caused by Rod Control Sys Logic Cabinet Card Failures.Degraded Cards Supplied by Westinghouse Replaced
05000482/LER-1987-008, :on 870208,control Room Ventilation Isolation Signal Initiated.Caused by Spurious Spike on Control Room Air Intake Chlorine Monitor Gk AITS-3.No Root Cause Identified.Design Change Being Considered
05000482/LER-1986-070, :on 861222,auxiliary Feedwater Pumps Started Due to Main Turbine & Feedwater Pump Trip.Caused by Personnel Removing Circuit Card While Bringing Main Turbine Up to Rated Speed.Sys Will Be Reviewed
05000482/LER-1986-071, :on 861225,two Control Room Ventilation Isolation Signals Occurred Due to Monitor GK-AITS-2 Indicating High Chlorine Level.Caused by Circuit Bulb Failure.Bulb Replaced.Monitor Returned to Svc
05000482/LER-1987-005, :on 870117,ESF Actuations Occurred During Turbine Testing.Caused by High Vibrations Which Required Rapid Reduction in Speed of Main Turbine.Precaution Added to Sys Procedure
05000482/LER-1987-004, :on 870120,while at 100% Power,Reactor Trip Occurred.Caused by Turbine Vibration.Turbine High Vibration Trip Circuitry Modified to Provide Alarm Rather than Trip Function.Evaluation Continuing
05000482/LER-1987-002, :on 870108,low Steamline Pressure Signal Occurred During Calibr Testing & ESF Actuation Initiated. Caused by Personnel Error.Improved Instrument Identification Tags & Procedural Enhancements Made
05000482/LER-1986-069, :on 861222,main Turbine Trip & Feedwater Isolation Occurred Due to Steam Generator hi-hi Level, Followed by Reactor Trip Due to Steam Generator lo-lo Level. Caused by Equipment Failure.Equipment Replaced
05000482/LER-1992-011, :on 920626,discovered That Testing Frequency for EDG B Had Not Been Increased to at Least Once Per Seven Days,Per Tss.Caused by Personnel Error.Procedure Adm 01-0244 EDG Reliability... Will Be Revised
05000482/LER-1992-013, :on 920814,determined That Sp for Trip Actuating Device Operational Test Manual Reactor Trip Did Not Properly Test Rtb Actuation Function.Caused by Personnel Error.Sp Revised to Include Trip Blocking
05000482/LER-1992-006, On 920228,binding & Slippage Between Reactor Coolant Sys Crossover Leg Saddles & Thrust Block Caused Unusual Noise.Shims on Generator Crossover Legs Removed & Reworked
05000482/LER-1992-002, :on 920219,after Failure of Gating/Sequencing Card in Inverter Supplying 120 Volt Ac safety-related Bus, Reactor Trip Occurred in SG A.Cause Undetermined.Review of Procedure Ofn 00-021 Conducted
05000482/LER-1992-012, :on 920707,discovered That Sp to Demonstrate Operability of Containment Personnel Airlock & Containment Emergency Escape Airlock Not Performed by 920526 & 0321, Respectively.Caused by Computer Error
05000482/LER-1992-010, :on 920508,informed That Instrument Channel Associated W/Pressure Transmitter ALPT38 Never in Tripped Condition.Caused by Inadequate Procedural Guidance. Procedure Revised & Personnel Trained
05000482/LER-1992-008, :on 920328,discovered That 30-minute Monitoring & Logging of Indicated Axial Flux Difference for Excore Channel Not Performed Per Tech Specs.Caused by Inadequate Procedure.Procedures Revised
05000482/LER-1992-009, :on 920417,failure of Humidity Sensors Resulted in Inoperability of Both Trains of Crevs.Caused by Normal Wear of Sensors.Sensors Will Be Replaced Every 36 Months & Procedure Inc L-1000 Conducted Every 18 Months
05000482/LER-1991-024, :on 911028,discovered That Incorrect Spring Packs Installed in Actuators for Spray Additive Tank Outlet. Team Initiated to Examine All Safety Related MOV Testing Programs.Mgt Action Plan Also Initiated
05000482/LER-1991-026, :on 911212,CR Ventilation Isolation Received When Key for RM Gk RE-004 Was Not Placed Fully in Bypass Position.Discussion of LER Will Be Included in Licensed Operator Requalification Training by 920430
05000482/LER-1992-001, :on 920113,failure to Follow Procedures Could Have Caused Both Intermediate Range Channels to Be Inoperable During Physics Testing.Caused by Temp Procedure Changes.Procedure Revised
05000482/LER-1991-002-01, :on 911112,Tech Spec 4.8.1.1.2 Could Not Be Satisfied for Emergency Diesel Generator B.Caused by Only Load Description & Not Numercial Value of Load Put Into Surveillance Procedures.Change to TS Submitted
05000482/LER-1992-005, :on 920227,notified That Containment Penetration Vent & Drain Valves May Not Have Been Included in Surveillance Test Procedure STS GP-007 Due to Inadequate Attention to Detail.Subj Procedure Revised
05000482/LER-1992-004, :on 920229,ESF Actuations Involving Lifting of Lead to Logic Circuit Card Occurred.Caused by Inadequate Procedural Development.Procedures Revised to Direct Control Room Operators to Hold Reset Switch
05000482/LER-1992-003, :on 920213,failure to Maintain Proper CR Evs Resulted When Train a Operated in Lieu of Train B.Caused by Inattention to Detail.Standing Order for CR Operators & Sys Operating Procedure to Be Revised
05000416/LER-1982-179-03, /03L-0:on 821229,smoke Detectors Covered During Planned Maint to Prevent False Alarms &/Or Damage.Hourly Fire Watch Established.Detectors Uncovered & Returned to Svc
05000416/LER-1982-185-03, /03L-0:on 821229,smoke Detection Zone 2-17 (East Corridor of Auxiliary Bldg;Elevation 103 Ft) Alarmed & Would Not Reset.No Fumes or Smoke Present.Caused by Spurious Actuation.Zone Returned to Operation on 830112
05000416/LER-1983-130-03, Shutdown Cooling Sys Isolated Twice When Suction Valve Received Isolation Signals.First Isolation Caused by Personnel Error.Second Caused by Use of Alligator Clips
05000416/LER-1983-184-03, /03L-0:on 831122,Div I Diesel Generator Declared Inoperable Due to Inoperable Standby Svc Water Pump A.Caused by Low Cooling Water Flow,Due to Personnel Error.Personnel Admonished
05000416/LER-1983-186-03, /03L-0:on 831122,standby Svc Water Pump a Declared Inoperable Due to Low Cooling Water Flow Through Pump. Caused by Sediment in Supply/Return Line Restricting Cooling Flow Through Pump a
05000416/LER-1983-183-03, /03L-0:on 831123,control Room Standby Fresh Air Unit B Found W/Flow Rate in Excess of Tech Spec Limit.Caused by Inadequate Retest Following Maint Work.Damper Limit Switches Readjusted
05000482/LER-1991-010, :on 910509,containment Emergency Escape Air Lock Hatch Closed W/O Having Required Leak Rate Test Performed Due to Inadequate Administrative Controls.Required Leak Rate Test Performed Satisfactorily
05000482/LER-1991-019, :on 911011,broken Fuel Rod Discovered in Fuel Assembly F31 Located in Core Position L-9 During Fuel off-loading Operations.Caused by grid-to-rod Fretting.New Core Loading Design Pattern Developed
05000482/LER-1991-008, :on 910528,ESF Actuations Occurred When Radiation Monitor Erroneously Restored to Svc,Resulting in Containment Purge Isolation Signal.Caused by Operator Error.Ltr Issued to Operations Personnel
05000482/LER-1991-011, :on on 910718,determined That Quarterly CCW Inservice Valve Test Not Completely Performed on 910514. Caused by Status Sheet Incorrectly Initialed to Signify Test Completed.Individual Counseled
05000482/LER-1991-021, :on 911021,emergency Diesel Generator a Restored W/Incorrect post-welding Hydrostatic Test Pressure on Jacket Water & Lube Oil Hx.Caused by Personnel Error. Procedure Adm 08-217 Will Be Enhanced
05000482/LER-1990-027, :on 910730,discovered That STS ML-001 Had Not Been Performed within Required Time Frame During Refueling Iv.Caused by Lack of Administrative Controls.Data Base Review Conducted
05000482/LER-1991-012, :from 910730-31,4 H Comparison of Control Rod Demand Position to Digital Position Indication Not Performed.Caused by Personnel Overlooking Four Failed Pulse Counter Cards on 910718.Personnel Counseled
05000482/LER-1991-014, :on 910905,potential Failure of Main Steam Isolation Valves to Fully Close Under All Conditions Discovered.Caused by Incorrect Accumulator pre-charge Curve. Correct pre-charge Curve Being Developed
05000482/LER-1991-015, :on 910907 & 09,discovered That Dirty, Temporary Filter in Place on Intake to RHR Pump Room & Air Flow for Room Coolers Could Not Be Obtained.Caused by Procedural Inadequacy.Workers Counseled
05000482/LER-1991-013, :on 910821,inoperability of Certain Safety Related Equipment Occurred Due to Potential of Fault in non-safety Related Circuit Propragating.Cause Unknown.Addl Insp of Conduit & Cable Performed
05000482/LER-1991-006, :on 910512,auxiliary Feedwater Actuation & Control Room Ventilation Isolation Occurred When Power Supply in ESF Actuation Sys Failed.Caused by Faulty 15 Volt Power Supply.Power Supply Replaced
05000482/LER-1991-018, :on 911002,containment Purge Isolation & Control Room Ventilation Isolation Signals Generated by Signals from Gaseous Channels of Radiation Monitors.Caused by High Gaseous Activity.Operators Counseled
05000482/LER-1991-016, :on 910910,discovered That Five Control Bldg HVAC Sys Ductwork Damper Insp Covers Not Reinstalled Since Maint Activities on 910909.Caused by Inadequate Work Controls.Instructions Will Be Reviewed
05000482/LER-1991-009, :on 910613,discovered That Surveillance Testing for Main Steam Loop 1 Low Point Drain Valve Not Performed at Required Frequency.Caused by Personnel Error.Clearance Order Procedure Revised
05000416/LER-1983-007-03, /03L-0:on 830107,fire Door OC520 Temporarily Blocked Open to Facilitate Planned Maint Area.Doors Closed on 830112 at Completion of Work
05000482/LER-1991-003, :on 910201,visual Insp of ASME Code Class 2 Piping Not Performed Per Tech Specs.Caused by Personnel Error.Review of Surveillance Procedures Conducted
05000482/LER-1991-001, :on 910101,unplanned Release of Waste Gas Decay Tank W/O Prior Sampling Occurred Due to Leak in Rupture Disk.Caused by Misalignment Between Faces of Flange.Disc Replaced Annually as Directed by Vendor
05000482/LER-1991-005, :on 910208,setpoint for Containment Base Slab Triaxial Response Spectrum Recorder Incorrectly Set.Caused by Changed Design Specs.Setpoint Change Request Approved & Surveillance Test Procedure Revised
05000416/LER-1983-005-03, /03L-0:on 830111,fire Door OR106 Blocked Opened to Allow Transport of Resin.Fire Watch Established Per Tech Specs.Door Closed When Job Completed on 830112
05000416/LER-1983-006-03, /03L-0:on 830112,fire Doors OC714 & OCT10 Temporarily Blocked Open to Facilitate Planned Maint.Fire Watch Posted & Doors Closed at Completion of Work
05000482/LER-1990-022, :on 901004,Tech Spec Violation,Involving Unqualified Individual Assuming Fire Brigade Duties, Occurred
05000482/LER-1990-019, :on 900820,Tech Spec Violation Occurred Due to Late Performance of Surveillance of Offsite AC Power Sources.Caused by Personnel Error.Operators Will Be Counseled on Prioritizing Requirements
05000482/LER-1990-017, :on 900729,determined That Portion of Contents of Waste Gas Decay Tank 3 Discharged to Radwaste Bldg HVAC, Resulting in Tech Spec Violation.Caused by Procedural Inadequacy.Work Request Initiated
05000482/LER-1992-007-01, :on 920326,hot Particle Picked Up During RCS Shim Restraint Rework Insp Results in Exposure Exceeding 10CFR20.101 Requirements.Hot Particle Control Program & Policies Being Reviewed
05000482/LER-1990-012, :on 900517,reactor Trip,Main Turbine Trip & Auxiliary Feedwater Actuation Signals Occurred.Caused by Steam Generator C Atmospheric Dump Valve Stuck Open. Converter Positioner Circuitry Replaced
05000482/LER-1990-013, :on 900519,main Turbine Trip Occurred as Result of hi-hi Moisture Separator Reheater Level.Root Cause Investigation Not Conclusive.Cautions Added to General Operating Procedure Gen 00-004
05000482/LER-1990-006, :on 900416,containment Purge Isolation Signal & Control Room Ventilation Isolation Signal Occurred.Caused by Inadequate Procedures to Govern Deenergization of 120- Volt Ac Distribution Ctrs.Procedures Revised
05000482/LER-1990-005, :on 900410,control Bldg/Auxiliary Bldg Pressure Boundary Door Found Open W/O Continuous Watch Established. Caused by Inadequate Procedures.Fire Protection Impairment Control Procedure Revised
05000482/LER-1990-004, :on 900405,Tech Spec Surveillance Requirement Not Satisfied Because of Personnel Error in Scheduling Surveillance Test.Procedure Adm 02-300 Revised
05000482/LER-1990-002, :on 900314,determined That Halon Release in Either ESF Switchgear Room Would Trip Both Class 1E Electrical Equipment Air Conditioning Units.Caused by Lack of Design Criteria.Criteria Revised
05000482/LER-1989-020, :on 891117,determined That as-built Configuration of Housing for Both Trains of Containment Cooling Fan HXs Not Seismically Qualified to Withstand Sse. Addl Seismic Restraints Installed
05000482/LER-1990-003, :on 900320,containment Purge Isolation Signal & Control Room Ventilation Isolation Signal Generated After Initiation of Containment Vent.Caused by Localized Accumulation of Gaseous Activity
05000482/LER-1990-025, :on 901223,common Min Flow Path Return Line for SI Pumps to RWST Frozen.Caused by Faulty Ambient Temp Switch.Switches Calibr to Insure Heat Trace Circuits & Alarms Activated
05000482/LER-1991-002, :on 910128,essential Svc Water Flow to Containment Cooling Units Below TS 4.6.2.3 Requirements of 4,000 Gpm.Caused by Inaccurate Flow Readings Provided by Local Annubars.Surveillance Procedure Revised
05000482/LER-1990-020, :on 900827,portable Sump Pump Installed W/Pump Discharge Directed to Storm Drains,Bypassing Turbine Bldg Drain Monitor LE-RE-59.Caused by Lack of Communication Between Involved Groups
05000482/LER-1990-026, :on 901123,tech Spec Violation Occurred Re Safety Related Class IE Battery Bank Powered from Spare Battery Charger.Caused by Error in Safety Evaluation for Procedure Mce E051Q-01.Procedure Deleted
05000482/LER-1990-001, :on 900206,reactor Tripped as Result of Loop Low Flow Condition Following Trip of Reactor Coolant Pump a, Causing Feedwater Isolation & Auxiliary Feedwater Actuation Signals.Caused by High Differential Current
05000482/LER-1989-019, :on 890919,determined That No Procedural Problem Existed & Equipment Problem Caused 890915 Test Deficiency.Caused by Reaching Incorrect Conclusion.Train Restored to Svc After Replacement of Relay