TSTF-08-12, Submittal of Technical Specification Branch Positions Inconsistent with the Improved Standard Technical Specifications
TSTF-04-10, TSTF-476, Revision 0, Improved BPWS Control Rod Insertion Process (NEDO-33091)
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
TSTF-04-11, TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems
TSTF-04-05, TSTF-468, Revision 0, Declare Systems Inoperable Due to an Inoperable MCC or Distribution Panel in Lieu of ITS 3.8.9
TSTF-04-03, TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers
CPSES-199901700, Forwards Rev 15 to CPSES Fire Protection Rept & Description of Changes
05000445/LER-1990-035, :on 901011,potential common-mode Failure of HPSI Pumps Discovered Due to Incorrect Suction Vent Valve Application
05000445/LER-1992-024, :on 921022,determined That Surveillance for Containment post-accident Water Level Instrumentation Did Not Include Check of Level Sensors.Caused by Personnel Error.Vendor Manual Will Be Amended
05000445/LER-1992-023, :on 921021,security Officer Appeared to Be Unconscious & Exhibited Abrasions Indicative of an Assault. Caused by Personal Relationships Among Security Personnel. Investigation Still in Progress
05000445/LER-1996-005, :on 960310,entry Into TS 3.0.3 Occurred Due to Cracked Weld in SI Sys Piping.Removed & Replaced Cracked Weldment W/New Weld
05000445/LER-1992-025, :on 921023,equipment Failure Resulted in Drop of Four Control Bank B Group 1 Control Rods & Manual Reactor Trip.Caused by Inadequate Interior Cooling of Affected Rod Control Cabinet
05000445/LER-1992-002-01, :on 921012,manual Reactor Trip Due to Feedwater Flow Control Valve Failure.Pressure Regulators in Other Three Unit 1 FCVs & Four Unit 2 FCVs Were Verified to Be 0-125 Psig Regulators,As Required
05000445/LER-1992-021, :on 920516,electric Low Vacuum Trip Device Did Not Respond During Turbine Overspeed Surveillance Test & Several Faults Annunicated at Automatic Turbine Tester. Caused by Loose Wire.Wire Tightened
05000445/LER-1992-019, :on 920720,loss of Main Feedwater Resulted in Manual Reactor Trip Due to Rapidly Lowering SG Levels.Cause Unknown.Temporary Mod Installed to Bypass anti-water Hammer Interlock Circuits in Ssps
05000445/LER-1992-017, :on 920626,main Steam Supply Valves to AFW Turbine Not Quarterly Close stroke-time Tested.Caused by Procedure Error.Review of Inservice Test Valve Data Will Be Conducted
05000445/LER-1992-018, :on 920713,Westinghouse Informed Util of Significant Change in Evaluation Model,Resulting in Calculated Performance Outide Peak Temp Cladding Criteria. Licensing Document Change Initiated
05000445/LER-1992-016, :on 920623,phase B Line Between Unit 1 Station Transformer (1ST) & 1ST MOD Switch Broke Causing ESF Actuation.Caused by Design Deficiency in Lines Between 1ST & 1ST MOD switch.1ST Phase B Connector Repaired
05000445/LER-1992-015, :on 920610,time Delay Relay Associated W/ Blackout Sequencing Circuit Inoperable.Caused by Faulty Design to Allow Plant to Transfer Offsite Electrical Power to Alternate Source.Mod Process Revised
05000445/LER-1992-014, :on 920611,loss of Main Feedwater Resulted in Manual Reactor Trip Due to Rapidly Lowering Steam Generator Levels.Replaced Circuit Cards Were Sent to Ssps Vendor for Further Testing
05000445/LER-1992-011, :on 920618,failure of thermo-lag Fire Barrier Endurance Tests Results in Some Raceways Declared Inoperable.Caused by Inadequate Vendor Installation Specs. Fire Watch Routes Adjusted
05000445/LER-1992-013, :on 920511,loss of Cooling Water Flow to Fuel Pool Heat Exchanger Occurred After Realignment.Caused by Personnel Error.Personnel Retrained & Reevaluated & Heat Exchanger X-02 Has Restricted Use
05000445/LER-1992-012, :on 920603,reactor Shutdown Initiated Per Procedure.Caused by Less than Adequate Procedure Control of Oil Return Valve.Repositioned Valve,Procedure Change Stating Required Position of Valve & Controls Applied
05000445/LER-1992-005, :on 920218,operator Misinterpreted Procedure Step & Inadvertently Unblocked Actuation Signal Causing ESF Actuation.Caused by Personnel Error.Event Reviewed.Personnel Trained
05000445/LER-1992-020, :on 920720,output of motor-driven Auxiliary Feedwater Pump 1-02 Was Higher than Combined Flow to SG 03 & 04.Caused by Design Not Permitting Operator to Verify That Valve Closed.Procedures to Be Revised
05000445/LER-1992-009, :on 920508,reactor Tripped.Caused by Personnel Error During Testing.Appropriate Level of Positive Discipline Program Implemented for Individuals Involved & Cabinet Locking Scheme Modified
05000445/LER-1992-010, :on 920509,analog Channel Operational Test Not Performed Prior to Startup to Verify power-range Neutron Flux Low Setpoint.Caused by Personnel Error.Task Team Formed to Review Surveillance Test Process
05000445/LER-1992-008, :on 920406,control Room Heating Ventilation & Air Conditioning (HVAC) Sys Realigned to Emergency Recirculation Mode.Caused by Personnel Error.Electrical Control Building AO Has Been Counselled
05000445/LER-1992-007, :on 920401,train B Diesel Generator Declared Inoperable to Perform Scheduled Preventive Maint.Caused by Personnel Error.Individual Counseled,Procedure Enhanced & Standardized Tracking Device Developed
05000445/LER-1992-002, :on 920115,discovered That Surveillance Requirement for Area Temp Monitoring Not Performed in TS Required Interval of Once Per 12 H.Caused by Personnel Error.Control Over Assignment Improved
05000445/LER-1992-001, :on 920108,reactor Tripped Due to High Primary Water Temp.Caused by Personnel Error While Taking Manual Control of Generator Primary Water Sys.Intensive Training Conducted for Crew Involved
05000445/LER-1991-032, :on 911206,incomplete Calibr of Four Channels & Nonconserative Indication of Reactor Power Noted.Caused by Error in Wording of Work Order Instructions.Steps Have Been Revised in Surveillance Database
05000445/LER-1992-006, :on 920311,discovered That Two Surveillance Work Orders Failed to Include Calibr Instructions for P-9 Interlock,Channels N41 & N43.Caused by Personnel Error. Event Reviewed by All Maint Personnel
05000445/LER-1991-026, :on 911030,discovered That Pressurizer Safety Valves Inoperable.On 911028,valves Found to Have Setpoints 1% to 4% Less than TS Setpoint Tolerance.Caused by Inadequate Methodology.Valves Reset
05000445/LER-1992-004, :on 920206,discovered That 920130 Surveillance of Class 1E Battery Performed W/Battery in Equalize Rather than Float.Caused by Personnel Error.Personnel Involved Was Counseled.Battery Declared Operable
05000445/LER-1992-003, :on 920203,QA Surveillance Identified Invalid Boron Dilution Event Analyses.Caused by Inadequate Inputs & Methodology by Vendor.Design Basis of Boron Dilution Sys to Be Revised & Deficiencies Addressed
05000445/LER-1991-031, :on 911206,containment Ventilation Isolation Automatically Occurred Due to Overconservative Radiation Monitor Setpoint.Alarm Setpoint Recalculated & Procedure for Radioactive Effluent Releases Will Be Reviewed
05000445/LER-1991-029, :on 911204,handswitch Positions for Steam Supply Valves Left in pull-to-lock After Entering Mode 3, Defeating Automatic Function of Valves,Per TS 3.0.4.Caused by Personnel Error.Personnel Counselled
05000445/LER-1991-027, :on 911107,source-range Flux Doubling Signal Initiated,Actuating Inadvertent Boron Dilution Mitigation Function.Caused by Circuit Response to Power Supply Switchover.Procedure Changed
05000445/LER-1991-028, :on 911112,load Test Was Not Performed on Refueling Machine Auxiliary Monorail Hoist.Caused by Personnel Error.Personnel Involved Counseled on Need to Pay Attention to Detail
05000445/LER-1991-020, :on 910713,reactor Trip Resulting from Erratic Operation of Main Turbine Electrohydraulic Controller Occurred Due Turbine Trip Initiated by Hi-Hi Levels of SGs 1 & 2.Testing & Design Mods Performed
05000445/LER-1991-021, :on 910728,ESF Actuation Occurred.Caused by Lightning Strike.Design Mod to Switchyard to Enhance Reliability of Offsite Power Sources Partially Completed
05000445/LER-1991-024, :on 911004,main Steam Safety Valves Had Lift Setpoints Less than Setpoint Tolerance Allowed by Ts.Caused by Inadequate Procedure.Setpoint Verification Procedure Revised
05000445/LER-1991-023, :on 911003,reactor Tripped Due to Erratic Operation of Main Turbine Electrohydraulic Controller.On 910713,reactor Tripped Due to Seal Problem on Hydraulic Fluid Pumps.Design Mod Initiated
05000445/LER-1990-032, :on 900919,proper Identification of Design Bases Resulted in Operation/Testing of Containment Personnel Airlock Hydraulic Sys Inconsistent W/Existing Design.W/
05000445/LER-1990-033, :on 900926,personnel Error Lead to Momentary Loss of Containment Integrity
05000445/LER-1990-034, :on 900928,surveillance Missed for Channel Response Time Due to Personnel Error
TSTF-04-15, TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a
TSTF-04-08, TSTF-425, Revision 0, Relocate Surveillance Frequencies to Licensee Control
TSTF-04-16, TSTF-446, Revision 1, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791)
TSTF-04-17, Comment (1) of Dennis Buschbaum Re Technical Specification Task Force Response to 11/24/2004 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement to Modify Requirements Re Addition of
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
TSTF-04-04, TSTF-467, Revision 0, Add Restriction for Lowest Loop T(Ave) During Mode 2 Physics Testing
TSTF-04-13, TSTF-449, Revision 2, Steam Generator Tube Integrity