05000334/LER-1993-011, :on 930619,ESF Actuation Letdown Isolation Occurred While Synchronizing Main Unit Generator.Caused by Cooldown of RCS Due to Steam Demand.Plant Stabilized within Three Minutes & Pressurizer Level Restored
05000312/LER-1986-014, Updates Re Correction of Degraded DHR Capability Reported in LERs 86-02 & 86-14.Decay Heat Sys a Pump Casing Drain Lines Replaced Per Design Mod Package ECN R-0498. LER 86-14 Will Be Revised by 861208 to Reflect Mod
L-86-491, Forwards Comments on Exam Administered on 861117.Attachment Suppls & Replaces Comments Provided at 861120 Exam Exit Meeting & Contained in Util
B13911, Provides Response Re Issue 2 of RI-91-A-0103
05000312/LER-1987-015, :on 870207,numerous Cardox Zones Observed Deactivated When No Safety Concern for Personnel Noted. Caused by Personnel Not Reactivating Zone After Concern Resolved.Hourly Verification Initiated & Procedure Revised
05000312/LER-1986-024, :on 861115,during Fuse Replacement Activity in Bus Inverter S1A,power Momentarily Interrupted & DHR Train a Tripped.Caused by Design Not Allowing for Testability Using Substitute Power Source
05000312/LER-1986-012, :on 860606 & 09,while in Cold Shutdown,Two Snubbers Removed from Operating Decay Heat Sys.Caused by Personnel Error.Snubbers Reinstalled & Planned Work on Snubbers Delayed Until Decay Heat Sys Outage
05000312/LER-1986-030, :on 861208,decay Heat Sys Isolation Occurred During Transfer of Source Transformer.Caused by Personnel Error & Inadequate Procedure.Personnel Counseled & Procedures Revised
05000312/LER-1986-001, :on 860121,diesel Generator G-886B Declared Inoperable Due to Fuel Inlet Pressure Above Limits Specified in Process Stds.Safety Functions Performed.New Spare Parts Ordered for Generator
05000244/LER-1985-014, :on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs
05000244/LER-1985-009, :on 850408,during Secondary Sys Pressure Transient,Condensate Bypass Valve Automatically Opened Causing Turbine to Trip.Caused by Condensate Bypass Valve Switch in Automatic Position
05000244/LER-1985-008, :on 850407,reactor Tripped on Low Steam Generator Level.Caused by Operations Personnel Inability to Maintain Steam Generator Levels Above Trip Setpoints While Transferring Level Control
05000334/LER-1990-008, :on 900401,RCS Letdown Isolation/Esf Actuation Occurred.Erratic Automatic Response of Condenser Steam Valve PCV-MS-106A Caused RCS Temp to Decrease Below Tech Spec Min. Operators Took Manual Control & Shut Valve
05000334/LER-1980-096-03, /03L-0:on 801121,control Problem W/Bypass & Main Feed Regulating Valves Caused Transient in RCS That Could Not Be Controlled within Limits.Caused by Improperly Tuned Control Mod for Feed Bypass Valves
05000316/LER-2077-013, Re 7.5 Gallons of Boric Acid Being Injected Into RCS, Which Resulted in Tavg Decreasing 2.5 Degrees F
05000335/LER-2078-019, For St. Lucie Unit 1, on 05/30/78 Concerning During Special Low Pier Feedwater Control System Test a 15% Feedwater Bypass Control Valve Inadvertently Opened Fully Causing Excessive Cooling of 1A Steam Generator
05000315/LER-1980-018-03, /03L-0:on 800806,during post-refueling Startup,Rcs Average Temp Fell Below 541 F Contrary to Tech Spec 3.1.1.5. Caused by Unbalance Between Turbine Load & Reactor Power. Turbine Load Reduced
05000244/LER-1993-006, :on 931110,feedwater Transient Occurred,Due to Loss of Ability to Control Feedwater Regulating Valve.Caused by low-low SG Level Reactor Trip.New Screw & Nut Installed in Linkage Arm
05000244/LER-1990-013, :on 901211,turbine Trip W/Subsequent Reactor Trip Occurred.Caused by Inadvertent ATWS Mitigation Sys Actuation Circuitry (AMSAC) Actuation.Jumper,Omitted in AMSAC Circuit Design,Installed
05000244/LER-1994-007, :on 940427,feedwater Transient Occurred Due to Loss of Ability to Control Feedwater Regulating Valve, Causing Lo Lo SG Level Reactor Trip.Caused by Improperly Secured Stroke Adjust Set Screw
2CAN090504, Arkansas, Unit 2 - License Amendment Request to Modify Technical Specification 3.1.1.5, Minimum Temperature for Criticality