L-2015-034, Response to Requests for Additional Information (Rais) Regarding License Amendment Request to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c (MF4631 and MF4632)
L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6
W3F1-2019-0054, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)
W3F1-2019-0062, License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
L-03-151, Original Issuance of the Pressure and Temperature Limits Report
05000528/LER-1986-063, Suppl to LER 86-063-00:on 850912,reactor Tripped Due to Core Protection Calculators Sensing Imminent Loss of Forced Coolant Circulation.Ref Leg of Vol Control Tank Level Indicator Monitored on Daily Basis
2CAN108704, Application for Amend to License NPF-6,changing Tech Spec to Decrease Boron Concentration Required in Boric Acid Makeup Tank.Review & Approval of Encl Matl in Order to Issue Amend Prior to Next Refueling Outage on 880212 Requested.Fee Pai
B16447, Application for Amend to License NPF-49,revising Shutdown Margin Requirements & Shutdown Margin Monitor Operability for Modes 3,4 & 5
B12733, Application for Amend to License DPR-65,revising Tech Specs to Allow Reduction of Concentration of Boric Acid in Boric Acid Storage Tanks & Piping to Level Where Heat Tracing No Longer Required to Prevent Boron Precipitation.Fee Paid
ST-HL-AE-2090, Forwards Annotated Section 2.4.1.2 from Amend 5 of Fire Hazard Analysis Rept Providing Addl Substantiation for Util Position on Tech Spec 3.1.2.2 Re Gravity Flow from Boric Acid Tanks to Charging Pumps
TMI-22-015, Submittal of Changes to Technical Specifications Bases
B14296, Responds to NRC 921117 Request for Addl Info Re 921112 Application for Amend to License NPF-49,changing TS on Temporary Heating Source - Operability of Charging Pump.Temp Alarms Located in Ventilation Panel in Control Room
TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases
B14559, Application for Amend to License DPR-65,revising TS to Provide Consistency W/Proposed Changes to GL 90-06 Re Resolution of Generic Issues 70 & 94
W3P86-3326, Supplemental Application for Amend to License NPF-38, Modifying 860820 Amend Request to Remove Refueling Water Storage Pool as Creditable Boration Flow Path in Tech Spec 3.1.2.2.Original Safety Analysis Remains Valid
W3F1-2019-0056, Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
05000400/LER-2022-004, Both Trains of High Head Safety Injection Inoperable
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
05000328/LER-1988-005, :on 880212,smoke Discovered Coming from Speed Increaser Unit for Centrifugal Charging Pump 2A-A.Caused by Bolts Backing Out Due to Lack of Periodic Adjustments.Speed Increaser Lube Oil Pump 2A-A CCP Replaced
05000312/LER-1985-019, :on 851002,reactor Trip Occurred & RCS Temp Decreased to Approx 70 F.Caused by Excessive Steam Loads Due to Two Open Relief Valves on Feedwater Heater 4A.HPI Flow Manually Initiated to Maintain Pressure
05000528/LER-1985-051, :on 851023,charging to RCS Lost.Caused by Maint Personnel Inadvertently Opening Unisolated Reactor Coolant Pump Injection Filter.Flow Reestablished Per Tech Spec 3.0.3.Personnel Involved Counseled
05000368/LER-1991-018-01, :on 911230,service Water Loop Inoperable Resulting in Entry Into TS 3.0.3.Cause Has Not Been Determined.Valve Replaced in Shut Position Under Operations Administrative Controls
05000369/LER-1984-003-01, :on 840220,during Normal Rotation of Equipment, Centrifugal Charging Pump 1A Would Not Start.Pump Breaker Not in Fully Connect Position Due to Personnel Error in Restoring Breaker After Routine Oil Sample
05000334/LER-1983-028-03, /03L-0:on 830926,charging Isolation Valve MOV-CH-310 Would Not Reopen After Being Stroked Shut. Caused by Dislodged Contactor Drive Pin Resulting in Misalignment.Pin Realigned
05000318/LER-1991-007, :on 910711,B Train Failure Occurred for Number 22 Bast Heater Circuit While Number 12 EDG Was Out of Svc. Caused by Component Failure.Replaced Fuses & Verified Integrity & Function of Control Power Circuit
05000369/LER-1983-098-03, /03L-0:on 831006,three Locked Open Valves Found Open & Unlocked.Caused by Personnel Failure to Use Operating Procedures.Personnel Counseled.Addl Actions Specified in RO-370/83-53
05000328/LER-1994-002, :on 940105,CCP Motor 2B-B Tripped on Timed Overcurrent.Pump Declared Inoperable & Removed from Svc.On 940108,facility Placed in Mode 4 (Hot Shutdown).Ccp 2B-B Disassembled & Rotating Element Replaced
05000302/LER-1978-057-03, /03L-0:on 781030,during Routine Plant Insp,Both Concentrated Boric Acid Storage Tank Discharge Valves CAV-38 & 43 Were Closed.Caused by Improper Valve Alignment During Restoration of Sys from Recirculation to Normal Modes
05000302/LER-1982-018-03, /03L-0:on 820308,following Recirculation of Boric Acid Sys Tanks,Both Tanks Were Isolated.Cause Attributed to Procedural Deficiency.Procedure OP-403 Revised
05000302/LER-1981-084-03, /03L-0:on 811228,chemical Addition Pump 1-B Would Not Pump.Cause Being Investigated.Until Cause Known,Util Is Running Chemical Addition Pumps on Daily Basis to Reduce Possibility of Recurrence
05000346/LER-1978-103-03, /03L-0:on 781009,during Surveillance Testing,Point R216 on Heat Trace Found One Degree Below 105 F Per Tech Spec 4.1.2.2.Caused by Blown Fuse in Temp Controller in Circuit 109.Fuse Replaced & Circuit Rechecked
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000302/LER-1979-106-03, /03L-0:on 791108,during Daily Operating Surveillance,Concentrated Boric Acid Flow Path Heat Trace Recorder HTRT-5 Failed.Caused by Broken Recorder Drive Cord.Drive Cord & Balance Motor Replaced
05000346/LER-1979-094-03, /03L-0:on 790924,boron Injection Flowpath Test Had Not Been Performed to Meet Surveillance Requirement. Caused by Personnel Error.Test Was Successfully Performed on 790925
05000302/LER-1979-017-03, /03L-0 on 790223:heat Trace Recorder for Concentrated Boric Acid Flowpath Was Malfunctioning & Rendered Inoperable.Caused by Failed Recorder Drive Wheel. Drive Wheel Replaced & Heat Trace Recorder Returned to Svc
05000346/LER-1979-099-03, /03L-0:on 791008,during Boron Injection Heat Trace Test,Unit Failed to Achieve 105 F Temp at One Point on Sys Heat Trace Line.Caused by Sys Design Deficiencies.Test ST 5011.01 Performed Successfully on 791009
05000316/LER-2075-061, Re Four Times of Inoperable Flow Path
05000316/LER-2075-021, Requesting Removal of LER 1975-021-00 from Records Due to Incorrectly Reported
05000400/LER-1996-020, :on 960906,inadvertent RWST Boron Dilution Event Occurred.Caused by Personnel Error.Operating Procedure Was Revised to Reflect locked-closed Designation for RWST Fill Valve 1DW-5
HNP-96-200, Responds to NRC Re Violations Noted in Insp Rept 50-400/96-09.Corrective Actions:Co Responsible for Inadvertent Filling & Resultant Dilution of Rwst,Was Counseled on Use of Error Prevention Techniques
05000400/LER-1996-013, :on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
HNP-94-028, Responds to NRC Re Violations Noted in Insp Rept 50-400/94-05.Corrective Actions:Procedures Containing Backflush Evolutions Revised to Give Radwaste Control Operator Single Point Accountability
05000315/LER-1992-004-01, :on 920420,7-day Test to Prove Operability of Boration Flow Paths from Refueling Water Storage & Boric Acid Storage Tanks Not Performed as Scheduled.Caused by Personnel Error.Test Successfully Performed
05000529/LER-1995-002-01, :on 950519,TS LCO 3.1.2.2 & LCO 3.1.2.4 Action Statements Not Met.Caused by an Unsatisfactory Swagelok Compression at Union of Flexible Tubing & Rigid Tubing. Pressure Transmitter Sensing Line Repaired
05000335/LER-2005-006, Equipment Failure Led to Inadvertent Mode Change During Cooldown
05000346/LER-1998-002-01, Regarding Plant Trip Due to High Pressurizer Level as a Result of Loss of Letdown Capability
05000346/LER-2003-006, From Davis-Besse Unit 1 Regarding Potential Errors in Analysis of Block Walls Regarding HELB Differential Pressure & Seismic Events
05000334/LER-1999-008, :on 990423,missed IST Program Surveillance Attribute,Was Identified.Caused by Inappropriate Exclusion of Testing Two Valves in Closed Direction within Original IST Program.Ist Program Revised.With
05000327/LER-1991-003, :on 910218,centrifugal Charging Pump Declared Inoperable & Removed from Svc Due to Pump Degradation.Caused by Heavy Wear on Impeller Shoulders in Wear Ring Area.Pump Rotating Element Replaced
W3F1-2005-0062, Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005
05000334/LER-1983-030-03, /03L-0:on 831003,charging Header Isolation Valve MOV-CH-289 Failed to Reopen After Being Stroked Closed for Dst 1.11.10.Caused by Binding of Mechanical Interlock on Valve Line Starter.Coil Replaced