RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
BVY 14-030, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 1
BVY 18-020, Submittal of 2017 Radioactive Effluent Release Report
BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves
05000281/LER-1996-003-01, :on 960512,Unit 2 Pressurizer Safety Valve as Found Lift Setting Out of Tolerance.Valve Was Reassembled & Lift Setting Was Established & Tested Satisfactorily
NL-03-058, Reply to Request for Additional Information Regarding Proposed License Amendment for 1.4% Measurement Uncertainty Recapture Power Uprate
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
NG-92-3686, Forwards Request for TS Change RTS-186A to License DPR-49, Revising TS Sections 3/4.1 & 3/4.2 (Instrumentation Requirements),Per NRC & BWROG Review of 911219 Request for TS Change 186
NG-94-1147, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-331/94-01.Corrective Actions:Upon Discovery of Missed TS Surveillance,Aprms Declared Inoperable & Plant Entered LCO Until Surveillance Complete
05000254/LER-1998-011-02, :on 980716,unqualified Circuit Card Was Installed in SD Instrument Vol Level Transmitter,Rendering It Inoperable.Caused by Personnel Error.Reviewed Event with Instrument Maint,Sys Engineering & Procurement Engineering
05000281/LER-1986-015-02, :on 861031,pressurizer Safety Valves Had Lift Setpoints Outside Allowable Limits During Refueling Surveillance Testing.Safety Valve Setpoints Reset.Vendor Failure Analysis Underway
05000281/LER-1986-015-01, :on 861031,pressurizer Safety Valve Setpoints Found Outside Allowable Limits.Caused by Failure to Compensate for Operating Temp & Valve Wear.Valves Replaced & Setpoints Reset
05000263/LER-1978-015-03, /03L-0:on 780805,one APRM Scram Trip Setting at Four to Five Percent Low.Caused by Large Power Shape Changes Resulting in LPRM Output Changes.Gain Setting Corrected.W/
05000286/LER-1982-004-01, /01T-0:on 820713,setpoints for Crosby Model Hb Pressurizer Safety Relief Valves PCV-466 & PCV-468 Discovered Below Tech Spec Limit During Cold Testing.Caused by Mechanical Valve Drift.Valves Reset
05000280/LER-1982-008-03, /03L-0:on 820121,instrument Malfunction Resulted in Loss of All Pressurized Heaters.Caused by Short in One Pressurized Level Comparator.Short Repaired & Pressurizer Control Sys Returned to Normal Condition
05000254/LER-1983-003-03, /03L-0:on 830118,during Reactor Water Level Calibr Procedure Qis 10-1,switch LIS-1-263-58A Tripped Below Tech Specs.Caused by Instrument Setpoint Drift.Level Switch Recalibr
05000331/LER-1994-001-01, :on 940107,determined That Test of Average Power Range Monitor High Flux Scram Trip Setpoint Inadequate.Caused by Unawareness of Test Requirement.Test Verified Clamping Function Set Properly
05000260/LER-1981-001-01, /01T-0:on 810102,scram Discharge Vol Level Switch 2-LS-85-45A Found Inoperable & -C & -D Found Offscale.Caused by One Robert Shaw Switch Model SL-305-EI-X Sticking & Setpoint Drift.Stuck Switches Float Chamber Back Flushed
05000282/LER-1991-005, :on 910516,pressurizer Safety Valve Lift Setpoint Found 2.5% Low During Test.Future Testing of Safety Valves Will Be Done Using Steam
05000219/LER-1982-006, Forwards LER 82-006/01T-0.Detailed Event Analysis Encl
05000219/LER-1981-036, Forwards LER 81-036/03L-0.Detailed Event Analysis Encl
05000306/LER-1989-004-02, :on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip Occurred
05000260/LER-1981-014-03, /03L-0:on 810313,mode a of Reactor Water Level Instrumentation Indicated Full Upscale Resulting in Turbine Trip.Caused by Loss of Ref Leg to 2-LITS-3-203A & B & 2-LIS-3-184 Due to Partially Open Equalizing Valve
05000271/LER-1980-010-03, /03L-0:on 800307,50-millisecond Value Used in GE Transient Analysis for Reactor Protection Sys Delay Time in Violation of Tech Specs.Tech Spec 3.1.A Will Be Revised
05000254/LER-1979-038-01, /01T-0:on 791128,scram & ECCS Initiation Setpoints Set Lower than Required by Tech Specs.Caused by Initial Instrument Ref Leg Calculations Based on Temp of 135 F. Indicating Switches Recalibr
05000281/LER-1991-003-02, :on 910424,pressurizer Safety Valves Found to Have Lift Setpoints Lower than Min Due to Minor Damage/Wear. Valves Refurbished,Reset & re-installed
05000281/LER-1991-001-02, :on 910307,block Valves Declared Inoperable Until Required Surveillance Testing Satisfactorily Complete. Caused by Personnel Error.Task Team Formed to Address Missed Surveillance & Other Recent Similiar Events
05000281/LER-1995-002-02, :on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted
05000280/LER-1995-008, :on 950919,pressurizer Safety Valve Found Setpoint Out of Tolerance.Caused by Psvs Being Installed Prior to Start of Most Recent Operating Cycle
05000260/LER-1993-008-01, :on 930616,turbine Stop Valve Limit Switch Malfunctioned & Failed to Deenergize Associated RPS Relays Due to Personnel Error.Work Order Initiated to Repair Limit Switch to Allow Reperformance of SI
05000237/LER-1977-026, Regarding the Discovery of Pressure Switch PS-263-51A to Activate at 614 PSI
BVY 17-004, Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool
05000280/LER-2011-001, Regarding Reactor Trip on Both Units Due to Loss of Offsite Power
L-MT-06-069, Submittal of Revision 2 to the Cycle 23 Core Operating Limits Report
05000280/LER-2006-001, Re Voluntary Report - Motor Driven AFW Pump High Flow Condition with Low Steam Generator Pressure
05000306/LER-1997-003-01, :on 970517,Unit 2 Was Brought to Planned Hot Shutdown Condition to Perform Valve Maint in 22 RCP Containment Vault.Caused by Inattention to Detail.Will Evaluate Revising Plant Operating Procedures
05000281/LER-1993-001-03, :on 930420,RHR Rendered Inoperable When CC Sys Flow Heat Exchanger Inadvertently Isolated.Caused by Cognitive Personnel Error.Evaluation of Decay Heat Removal Sys Configuration Will Be Performed
L-81-156, RO 335-B-81-05:on 810325,discovered Loss of Recording Thermograph Sys.Possibly Caused by Wave Action,Surges, Commercial Fishing or Vandalism.Corrective Action Not Necessary Due to Deletion of ETS 3.1.A.5
BVY 16-020, Transmittal of 2015 Radioactive Effluent Release Report
05000280/LER-1983-024-03, /03L-0:on 830517,RHR Pump B Removed from Svc, Rendering RHR Loops Inoperable.Caused by Pump Cavitation Due to Inaccurate Standpipe Level Indication.Rcs Level Increased.Rhr Pump Vented & Returned to Svc
05000281/LER-2008-001, Pressurizer Safety Valves Fail as Found Setpoint
05000331/LER-1994-008, :on 940517,determined That Testing Had Not Been Performed at Required Surveillance Frequency for Reactor High Pressure Scram Pressure Switch.Caused by Inadequate Tracking.Appropriate Half Scram Inserted