BYRON 2016-0120, Submittal of Report of Changes, Tests and Experiments for Evaluations Implemented for the Time Period 01/01/2014 - 11/30/2016
SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
NL-15-1392, Enclosure 6 - Farley Justification Matrix
NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 6 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
RNP-RA/08-0006, Request for Technical Specifications Changes Related to Control Room Habitability - Supplement
RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability
LIC-05-0081, Transmittal of Revision 1 of Fort Calhoun Station, Unit, Pressure Temperature Limits Report (PTLR)
BSEP 02-0163, Revision of Request for License Amendment - Frequency of Performance-Based Leakage Rate Testing
IA-86-615, Package of Purchase Orders Re Health Care for Region III Employees
ST-HL-AE-5646, Forwards Facilities Preliminary Response to Questions Reflecting Discussions Between Personnel & NRC Staff Which Visited Site During Week of 970505
BVY-92-139, Forwards Amend to License DPR-28,consisting of Proposed Change Number 166,revising TS Section 3.5.H.1,by Allowing one-time Extension of Seven Day LCO to Fourteen Days During Current Operating Cycle 16 to Permit Extensive Maintenance
05000369/LER-1989-009-01, :on 890421,ESF Actuation Occurred During Realignment of turbine-driven Auxiliary Feedwater Pump, Causing Pump Suction Pressure to Drop & Opening Valves. Caused by Improper Tagout Removal Procedure
05000301/LER-1989-002, :on 890329,unit Experienced Main step-up Transformer Lockout Main Generator Breaker Trip & Concurrent Turbine & Reactor Trips.Caused by Wiring Error in Terminal Box 2-TB69.Repairs Completed
05000320/LER-1987-011-01, :on 871123,Halon Sys Remained Out of Svc Following Completion of Surveillance Per Tech Spec 3.7.10.3 W/O Continuance of Fire Watch.Caused by Personnel Error.Sys Returned to Svc & Personnel Counseled
05000440/LER-1987-059, :on 870821,RWCU Containment Isolation Occurred Due to Indicated High Differential Flow.Caused by Particulate Buildup in Flow Control Valve Positioner Air Flow Restriction Orifice
05000213/LER-1986-033, :on 860715,w/plant in Mode 4,RCS Low Temp Overpressurization Protection (Ltod) Sys Interlock Would Not Permit Opening One Train of LTOP Isolation Valves.Tech Spec Temp Limits Reduced
05000334/LER-1987-006, :on 870325,motor-driven Auxiliary Feedwater Pump Inadvertently Started.Caused by Short Circuit Due to Operator Error.Surveillance Test Procedure Revised to Eliminate Need to Disconnect Timer Contacts
05000369/LER-1988-024, :on 880912,unit Entered Tech Spec 3.0.3 When Train a of ECCS & Train B of Component Cooling Sys Were Inoperable.Component Cooling 1B HX Failed Performance Test Because of Seasonal Environ Factors
05000369/LER-1998-001-01, :on 980128,inadvertent Removal of Fwst Channel from Tripped Condition & Cpcs Channel from Start Permissive Condition.Caused by Inadequate Procedures.Procedures Were Placed on Hold Pending Evaluation for Improved Guidance
05000414/LER-1986-021-01, :on 860530,main Feedwater Isolation Occurred During Testing of Auxiliary Safeguards Relays.Cause Undetermined.Isolation Signal Reset & Control Valves Realigned
05000278/LER-1988-003-02, :on 880520 & 22,primary Containment Isolation Sys Inboard Isolation & Half Reactor Scram Occurred.Caused by Reactor Protection Sys (RPS) Being Lightly Loaded.Rps Alternate Feed Breakers Reclosed
05000250/LER-1986-006, :on 860211,safety Injection Sys Actuated & Subsequent Reactor Trip Occurred.Caused by Const Activities on Unit 4 & Inadequate Instructions for Investigating Event. Procedures Revised
05000322/LER-1988-006, :on 880430,loss of Emergency Bus 101 Occurred W/Subsequent Start of Emergency Diesel Generator 101 & Numerous ESF Actuations.Caused by Personnel Error.Procedural Revs Implemented to Emphasize Impact of Steps
05000369/LER-1988-020-02, :on 880912,actuator Disconnected from Valve Stem at Actuator to Valve Stem Coupling.Caused by Mgt Deficiency Due to Poor Planning/Scheduling by Operations. Operations Personnel Manually Opened Valve
05000370/LER-1988-009-03, :on 880724,main Feedwater Isolation Occurred When Instrumentation & Electrical Personnel Failed to Open Valve During Repair Work.Signal Reset & Sys Flow Restored. Good Communication Stressed
05000413/LER-1986-001-01, :on 860106,discovered That Carbon Sample Not Taken from Control Room Pressurizing Filter A,Per Tech Spec Requirement.Cause Not Stated.Work Request Issued to Perform Carbon Sample Removal
05000344/LER-1988-024, :on 880722,both Trains of Control Room Emergency Ventilation Sys Inoperable for 28 Min Due to Inability of Sys to Maintain Required Positive Pressure. Caused by Inadequate Outside Air Damper
05000321/LER-1987-016-01, :on 871214,main Control Room Environ Control Sys Isolation Occurred Due to False Chlorine Signal.Caused by Surveillance Procedure Inadequacy.Procedure Revised & Chlorine Detector Replaced & Recalibr
05000322/LER-1986-007, :on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised
05000255/LER-1985-020, :on 851008,discovered That Scheduled Date for Main Steam & Feedwater Sys Hydrostatic Test Exceeded ASME Required Time Interval.Caused by Misinterpretation of Requirements.Review Performed
05000327/LER-1985-040, :on 851009,trains Became Inoperable Due to Air Injection Into Suction of Pumps During Swap Over from Train B to a Rhr.Caused by Procedure Inadequacy.Pumps Shutoff & Vented.Rcs Level Increased.Valves Verified
05000413/LER-1985-049-01, :on 850807,inadvertent Isolation of Both Discharge Headers of Fire Protection (Ry) Pumps Occurred. Caused by Personnel Error.Correct Ry Header Isolated. Procedure 2-18 Revised
05000373/LER-1985-058-01, :on 850817,pressure Transient in Instrument Ref Line Actuated.Caused by Valving in of Differential Pressure Switch Instrument Ref Line While at Reactor Pressure by Instrument mechanic.w/850830 Ltr
05000338/LER-1985-005-01, :on 850503,semiannual Functional Test on Seismic Triaxial response-spectrum Recorders Not Performed. Caused by Inaccessibility During Power Operation.Change in Surveillance Test Requirement Requested
05000237/LER-1984-013, :on 840722,reactor Scrammed Due to Opening of Electron Hydraulic Control Sys,Causing Turbine to Trip on Low Oil Pressure.Caused by Personnel Error.Changes Made to Training Program for Newly Hired Attendants
05000339/LER-1985-004-01, :on 850318,forced Unit Rampdown from 100% Power Occurred.Caused by Inoperable Emergency Diesel Generator 2J Which Tripped on High Crankcase Pressure & Removed from Svc.Emergency Generator Repaired
RBG-21545, Rev 2 to River Bend Station Offsite Dose Calculation Manual
05000333/LER-1984-018, :on 840918,while Shut Down for Scheduled Maint Outage,Two Inadvertent Reactor Scrams Occurred within 1 H. Caused by Craft Personnel Accidentally Bumping Scram Discharge Instrument Vol Switch
05000296/LER-1985-002-01, :on 850107,power Cable Accidentally Shorted to Ground,Tripping Breaker That Supplies Several Instrument Panels.Caused by Bad Card.Personnel Briefed on Cause of Event
05000413/LER-1985-018, :on 850307,Train a Diesel Generator & Turbine Driven Auxiliary Feedwater Pump Concurrently Inoperable. Caused by Personnel Error Placing Batteries on Equalize Charge.Batteries Returned to Svc
05000317/LER-1984-005, :on 840502,through-wall Hole Occurred During Removal of Graphite Layer on Component Cooling HX 22.Second Hole Created on 840503.All Units 1 & 2 Saltwater Pumps Inoperable on 840514.Cause Unknown
05000397/LER-1984-042, :on 840517,reactor Manually Shut Down Due to Loss of Control of Vessel Water.Caused by Malfunction of Mechanical Linkage from Servo Control Motor.Linkage Repositioned & Refastened
05000414/LER-1990-011, :on 900711,discovered That Tagout Record Sheet for Closure of Valve 2NC-61 Had Been Active.Caused by Design Deficiency Due to Lack of Documentation on Relief Paths. Valve 2NC-61 Reopened Prior to Mode 4
05000327/LER-1984-043, :on 840627,during Surveillance,Thermal Fire Detector Discovered Inoperable.Required 1 H Fire Watch Not Established.Shift Engineer Not Notified.Fire Detector Replaced & Returned to Svc
05000321/LER-1984-009, :on 840609,following Cold Shutdown,Reactor Mode Switch Placed in Startup Position.Operating Personnel Determined APRM 15% Flux Scram Test Not Performed within 24 H of Startup
05000416/LER-1984-020, :on 840423 & 24,during Startup,Four Reactor Water Cleanup Sys Isolations Occurred Due to Feedwater Flow Oscillations
05000325/LER-1991-023, :on 910822,preparations for Flushing Reactor Water Cleanup Sys Inboard Isolation Valve Seat Resulted in RWCU Isolation on High Temp.Caused by Voiding Piping Downstream of G31-F044.RWCU G31-F001 Repaired
05000000/LER-1950-266-75, /75-18:on 751217,during Cycle 3-4 Refueling, Discovered Section of Fuel Rod Missing.Caused by Water Impingement Through Baffle Plate While Failed Assembly in Cycle 2 Position H-1.Investigation in Progress
05000389/LER-1984-003-01, :on 840129,hi-hi Steam Generator Level Turbine Trip Occurred,Resulting in Reactor Trip.Caused by Leakage Through Main Feed Regulating Valve A.Reactor Started & Plant Returned to Svc
05000395/LER-1984-004, :on 840117,two Cable Junction Boxes Found Not Wrapped W/Kaowool & One Cable Run Had Damaged Kaowool in Three Areas.Caused by Const & Maint Activities in Area. Discrepancies Repaired
05000325/LER-1995-001-01, :on 950106,TS 3.0.3 Entered Due to Two HCUs Accumulators Being Out of Svc Simultaneously.Cause of Event Under investigation.C11-11 Valves for Two HCUs Replaced.W/
05000254/LER-1994-001-04, :on 940102,inadvertent Insertion of Control Rod H-1 from Position 48 to 14 Occurred During Instrument Maint Surveillance.Cause Not Determined.Crd H-1 Inserted Into Position 00 & HCU Rebuilt
05000325/LER-1993-012, :on 930928,Group 1 Isolation Signal Generated Due to Resetting Main Turbine for Testing.Caused by Defective Procedure.Operating Procedure 50 Will Be Revised
JAFP-94-0240, 1993 Radiological Environ Operating Rept Ja FitzPatrick Nuclear Power Plant
05000311/LER-1990-012, :on 900403,radiation Monitoring Sys Plant Vent Radioactive Noble Gas Monitor 2R41C Lost Power Resulting in Isolation in Containment purge/pressure-vacuum Relief Sys. Cause Not Determined
TXX-3314, Forwards Environ Qualification Review for Facilities & Certification Forms
DCL-15-007, Response to NRC Request for Additional Information Regarding License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision, 1.
BVY 14-063, Relief Request ISI-06 Inservice Inspection Limited Examinations for the Fourth Ten-Year Interval Vermont Yankee Nuclear Power Station
NL-17-0447, Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times
NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)
L-HU-07-021, Units 1 and 2, Request for Approval of a Combined Nuclear Management Company Emergency Plan
L-06-048, Discharge Monitoring Report (NPDES) Permit No. PA0025615
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
05000265/LER-1984-012-06, :on 841201,reactor Bldg Fuel Pool Channel B Area Radiation Monitor Tripped,Isolating Reactor Bldg Ventilation & Starting Standby Gas Treatment Sys.Caused by Setpoint Drift.Monitor Recalibr