BSEP 13-0107, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard (NFPA) 805 (NRC TAC Nos. ME9623 and ME9624)
L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps
NL-16-0169, Enclosures 15, 16, 17, 18 & 19: Vogtle (Units 3 & 4) - Justification Matrix, Evaluation of Proposed Changes LAR for Revision for Emergency Planning ITAAC, Rev to Units 3 & 4 COL Appendix C - Proposed Changes, and Off-Site Response Organiz
NL-15-1392, Enclosure 14 - Vogtle (Units 3 and 4) Standard Emergency Plan Annex & Enclosure 15- Vogtle (Units 3 and 4) Justification Matrix
NL-15-1392, Enclosure 12 - Vogtle (Units 1 and 2) Justification Matrix
NL-15-1392, Enclosure 6 - Farley Justification Matrix
NL-12-2268, Edwin I. Hatch, Unit 1, SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 11
05000321/LER-1989-013-02, :on 891003,RWCU Sys Valve 1G31-F020 Closed, Rendering Inservice Reactor Coolant Monitor Inoperable. Caused by Cognitive Personnel error.In-line Conductivity Surveillance Initiated & Personnel Counseled
NL-03-052, Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specification (ITS)
L-PI-03-007, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information
RA22-010, Cycle 20 Core Operating Limits Reports
B14236, Forwards Relief Request from ASME Boiler & Pressure Vessel Code Section XI Requirements,In Response to GL 90-05,to Make Interim Repairs to Leak in Piping as Alternative to IWA-7000 repair/IWA-7000 Replacement
LD-92-043, Forwards Response to Remaining Outstanding Request for Addl Info (RAI) 230.1 & Revs to Responses for RAIs 220.6 & 220.7, Providing Figure 3.7-2 & Expanding Description of How Average Power Spectral Density Calculated,Respectively
05000334/LER-1989-009-01, :on 890902,hi-hi Alarm Received on Train a Auxiliary Bldg Ventilation Radiation Monitor RM-VS-102A. Caused by Large Vol of Reactor Coolant in Sample Panel. Isolation Valve Will Be Repaired
05000324/LER-1989-010-02, :on 890619,unit Received Group 1 Isolation While in Hot Shutdown W/Reactor Pressure at 150 Psig.Caused by High Steam Flow Isolation Signal.No Corrective Measures Considered Necessary
05000346/LER-1988-029, :on 881218,control Rod Group 3 Safety Rods Dropped Into Core as Result of Troubleshooting in CRD Sys Causing Reactor to Go Subcritical.Caused by Personnel Error. Maint Personnel Trained
05000369/LER-1988-040, :on 881025,observed Air Leaking Through Penetration Into Containment Bldg.Caused by Defective Procedure Due to Mgt/Qa Deficiency & Inappropriate Action. Procedure PT/0/A-4700/48 Changed
05000458/LER-1989-009, :on 890316,noticed That Structural Ribs Reinforcing for 1 H Rated Thermo-Lag Covering on Div 2 Conduits,Cable Trays & Supports Removed.Caused by Deficiency in Vendor Installation & QC Program
05000333/LER-1989-007-01, :on 890509,surveillance of Fire Barrier Penetrations Missed Due to Misinterpretation of Barriers. Fire Watch Established & Required Surveillance Completed & Ref Manual Revised
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
05000461/LER-1987-043, :on 870724,reactor Scram Occurred as Result of Turbine Control Valve Fast Closure.Caused by Loose Connectors in Turbine Trip Vibration Detection Circuitry. Connectors Corrected Under GE Supervision
05000282/LER-1987-014, :on 870528,nuclear Instrumentation Sys Power Range Inaccuracies Shown During Startup Physics Testing. Caused by greater-than-predicted Change in Radial Leakage. License Amend Request Will Be Made
05000328/LER-1987-003-01, :on 870130,five Areas Identified That Did Not Receive ASME Section XI Pressure Test Insp During First Period of Program.Caused by Procedural Error.All ASME Section XI Procedures Revised
05000298/LER-1987-017, :on 870707,both Diesel Generators Automatically Started When Lightning Strike Resulted in Loss of 69 Kv Transmission Line.Damaged Arrestors Repaired
05000382/LER-1989-003, :on 890204,operators Inadvertently Allowed LPSI Pump B to Start During Testing.Caused by Personnel Error.Personnel Responsible Counseled to Be More Cautious & Thorough Approach When Following Procedures
05000366/LER-1987-011-02, :on 870902,surveillance Requirements for Main Control Room Environ Control Sys Missed,In Violation of Tech Specs.Caused by Personnel Error.Procedures Revised & Satisfactorily Performed & Personnel Counseled
05000219/LER-1987-032, :on 870824,augmented Offgas Sys H2 Analyzer Not Calibr,Per Tech Spec.Caused by Personnel Error.Ler Will Be Required Reading for All Involved Depts to Stress Importance of Thorough Review of Plant Procedures
05000029/LER-1986-011, :on 861003,surveillance Requirement for Containment Isolation Valves Not Performed.Caused by Failure to Properly Incorporate Requirement Into Procedure.Full Review of Surveillance Conducted
05000461/LER-1987-029, :on 870524,motor Driven Reactor Feed Pump Feedwater Regulating Valve 1FW004 Malfunctioned Causing High Water Level Transient.Caused by Failure of Regulating Valve. Mode Selector Switch Placed in Shutdown
05000298/LER-1986-028, :on 861021,58 Out of 88 Seismic Class Is Supports on Standby Gas Treatment Sys Suction Ductwork Found Structurally Inadequate.Caused by Undocumented Design Changes.Mods Immediately Initiated
05000250/LER-1987-005, :on 870119,w/unit in Mode 2,control Room Ventilation Isolated & Switched to Recirculation Mode & Containment Vent Isolated.Caused by Process Radiation Monitor Spike.Equipment Being Evaluated
05000328/LER-1987-002-01, :on 870121,discovered That Local Leak Rate Test Vent for Sampling Sys Containment Isolation Flow Control Valves Installed Incorrectly.Caused by Personnel Error.Work Request Initiated to Correct Configuration
05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed
05000413/LER-1988-047, :on 871221,reactor Trip Signal & Feedwater Isolation (Fi) Signal Occurred & on 871224,FI/turbine Trip Signal Actuated.Caused by Design Deficiency & Personnel Error,Respectively.Procedure Involved Revised
05000327/LER-1987-019, :on 870318,operator Observation Discovered That Four Emergency Diesel Generators Started.Caused by Inadequacy of Procedure to Isolate Degraded Voltage Timer Contacts for Functional Testing
05000341/LER-1986-014, :on 860516,while Refueling,Offsite Ac Power to Div 2 Interrupted,Causing half-scram.Caused by Personnel Procedural error.Half-scram Reset & Sys Restored
05000315/LER-1986-008-01, :on 860424,reactor Trip Function of Manual Safety Injection Circuitry Found Not Specifically Tested During Review to Ensure Compliance W/Tech Spec Surveillance & Bases Requirements
05000352/LER-1986-006-01, :on 860122,failure to Perform Tech Spec Surveillance Requirements Discovered.Caused by Inadequate Communication of Surveillance Test Due Dates.Administrative Guideline Implemented
05000213/LER-1988-011, :on 880408,required Test Interval for Surveillance Procedure Sur 5.2-9 Found Exceeded by 1 Wk in Violation of Tech Specs.Caused by Personnel Error.Test Performed on 880408 W/Satisfactory Results
05000369/LER-1988-006-02, :on 880328,nuclear Svc Water Sys Isolation Valve Not Tested Following Maint Per Tech Spec 4.0.5.Caused by Personnel Error.Signs Affixed to ESF Valves to Inform Personnel of Required Testing Following Maint
05000341/LER-1988-024, :on 880705,isolation of HPCI During Performance of Functional Test Occurred.Caused by Personnel Error. Surveillance Successfully Performed on Same Day & Accountability Meeting Held W/Individual
05000382/LER-1988-005, :on 880321,blown Undervoltage Circuit Fuse Replacement Results in Tech Spec 3.0.3 Entry.Caused by Inadvertent Shortening of Two Wire Connections.Change to Tech Spec Being Pursued to Correct Deficiency
05000320/LER-1986-003-01, :on 851117,fuel Handling Bldg Exhaust Monitors HPR-221A & HPR-221B Not Tested within Required Interval,Per Tech Spec 3.3.3.1.Caused by Personnel Error.Monitors Successfully Tested
05000416/LER-1986-009, :on 860319,supply Air Flow to Automatic Depressurization Sys Air Receivers Determined to Be Excessive.Caused by Sys Operating Pressure of 185 Psig Exceeding Design Valve Seat Leak Tightness
05000302/LER-1985-020, :on 851009,both MSIVs from Steam Generator B Automatically Closed Due to Spurious Emergency Feedwater Initiation & Control Actuation.Caused by Low Steam Generator Level Indication.Trip Module Replaced
05000338/LER-1985-020-01, :on 851118,eddy Current Insps of Steam Generator C Identified More than 1% of Sampled Tubes as Defective.Cause Under Investigation by Westinghouse.Tubes Plugged
05000397/LER-1985-059, :on 851113,scram Occurred Due to Failure of Power to Control Reactor Feedwater Sys Reactor Pressure Vessel Level Instrument Channel.Caused by Failed Critical Instrument Power Inverter.Study Underway
05000366/LER-1986-004, :on 860131,62-day Surveillance Requirement for Fire Detector Alarms Not Met.Caused by Personnel Oversight Resulting in Procedural Deficiency.Procedure 425V-SUV-015-25 Revised
05000281/LER-1984-015, :on 841029,during Breaker Testing,Load Shedding Initiated & Main Feedpump Tripped Leading to Low Steam Generator Level & Reactor Trip.Caused by Inadequate Procedures.Procedure Revised
05000316/LER-1985-040-01, :on 851205,ESF Actuation Signal Occurred After Alarm Received on Upper Containment normal-range Area Monitor Train B.Apparently Caused by Aging of DA-11 Gm Tubes in Monitor.Investigation Continuing
05000413/LER-1985-045, :on 850710,reactor Trip Occurred on lo-lo Steam Generator Level.Incorrect Main Steam Pressure Transmitter Isolated During Surveillance Calibrs.Caused by Personnel Error
05000344/LER-1985-008, :on 850630,while Performing Surveillance Testing on Reactor Protection Sys,Low Pressurizer Pressure Safety Injection Established.Caused by Partially Deficient Procedures.Safety Injection Reset
05000336/LER-1985-010, :on 850615,loss of Low Temp Overpressure Protection Due to Isolation & Venting of Pressurizer Pressure Transmitters.Caused by Procedure Inadequacy.Porvs Manually Opened & Procedure Revised
05000482/LER-1985-041, :on 850609 & 13,auxiliary Feedwater Actuation & Steam Generator Blowdown & Sample Isolation Occurred. Caused by Main Feedwater Pump a Trips
05000251/LER-1985-008-01, :on 850411,small Leak Discovered at Fitting on Test Connection Between Containment & Containment Isolation Valve.Caused by Test Connection Leakage & Malfunction of Valve CV-4-951
05000325/LER-1985-030, :on 850519,Groups 2,6 & 8 Containment Isolation Received When Breaker CB5B in Reactor Protection Sys Power Distribution Panel Opened.Caused by Loss of Power to Components Supplied by Breaker.Labels Revised
05000443/LER-1992-023, :on 921112 & 16,three safety-related Components,Within Scope of IST Program,Not Tested Prior to Entry Into Mode 4.Caused by Personnel & Procedure Error. Using Proper Documentation Will Be Stressed
05000528/LER-1985-016, :from 850323-0415,hourly Fire Patrols Not Conducted Per Tech Spec 3.7.12.Caused by Personnel Disregard for Responsibilities.Personnel Fired &/Or Replaced W/Station Staff & Logs & Monitoring Improved
05000498/LER-1992-008, :on 920731,CVI Actuation Occurred But Radiation Monitors Did Not Indicate Any High Radiation Conditions. Caused by Momentary Variance in Current to Remote Control Unit.Module Cabinets Will Be Repaired
05000325/LER-1984-032, :on 841116,automatic Isolations of Common Control Bldg Ventilation Sys Occurred Due to Respective Actuations of Sys Air Intake Plenum Chlorine Detector 2X-AT-2977.Cause Undetermined
05000322/LER-1985-006, :on 850204,valving in Reactor Pressure Transmitter for Remote Shutdown Panel Caused Transient in Ref Leg of Instrument.Technicians Cautioned Re Valve Manipulations on Reactor Pressure Vessel Leg
05000370/LER-1984-025, :on 840826 & 30,turbine Driven Auxiliary Feedwater Pump Experienced Reverse Rotation,Causing Overpressurization of Pump Suction Piping.Caused by Leaking Swing Check Valve.Leaking Valve Replaced
05000443/LER-1992-008, :on 920626,determined That 18-month Surveillance Test Program for EDG Inadequately Tested Undervoltage Circuitry,Per NRC Info Notice 92-040.Caused by Misinterpretation of Testing Requirements
05000334/LER-1984-011, :on 841012,eight Main Steam Safety Valve Lift Settings Found Outside Tech Spec Limits.Caused by Setpoint Drift.Valves Adjusted & Tested
05000366/LER-1985-007, :on 850210 & 24,reactor Water Cleanup Inboard Isolation Valve 2G31-F001 Isolated as Result of False Trip Signal.Caused by Bad Connection Where Trip Card 2G31-N661A Plugged Into Connector
05000374/LER-1984-032-01, :on 840626,reactor Water Cleanup Sys Isolated on Spurious High Differential Temp Div 1 Leak Detection (Jm) Trip.Caused Apparently by Induced Signal While Performing RCIC Functional Test.Isolation Reset
05000281/LER-1976-009-03, /03L:on 760615,valve Operator MOV-2862B Would Not Operate When Cycled by Console Control Switch.Caused by Actuation of Thermal Overloads in Breaker housing.Three- Point Adjustment Screws Loosened
05000327/LER-1995-006, :on 950606,determined That Wga (Which Monitors Hydrogen Concentrations) Being Operated Incorrectly.Caused by Design Limitations.Alarm Logic Will Be Reconfigured to Ensure TS Compliance
HL-4868, Forwards Response to NRC 950606 RAI Re Core Shroud Mod Installed at Facility,To Clarify Methodology in Suppl a to Rev 1 to GENE-771-34-0794.GE Proprietary Rept, Finite Element Analysis... Also Encl.Ge Proprietary Rept Withheld
05000331/LER-1983-010-03, /03L-0:on 830411,during Refueling Outage,One Snubber Found Inoperable,One Indeterminant,One Had Missing Bushing & One W/Bushing Disengaged.Caused by Procedure Error During Previous Maint
05000440/LER-1991-003, :on 910106,performance of Inadequate Procedure Resulted in Main Steam Line Drain Isolations.Caused by Procedure Deficiency.Instruction Revised to Include or Ref Steps to Bypass MSL Radiation Monitors
05000412/LER-1990-024, :on 901112,discovered That Boric Acid Storage Tank Sample Exceeded 7-day Surveillance Required by Ts. Caused by Abnormal Evolution.Personnel Counseled
05000424/LER-1990-018-01, :on 900907,discovered That Surveillance Required by Tech Spec 4.0.5 & ASME Section XI Inadequately Performed.Caused by Procedure Inadequacy.Procedure Corrected & Operability of Check Valve Reverified
05000445/LER-1994-001-01, :on 940201,low Flow Condition on Primary Water to Main Generator Stator Caused Turbine/Reactor Trip.Caused by Spurious Signal.Key Points Monitored for Power Supply & Instrument Signal Stability
05000315/LER-1982-018-03, /03L-0:on 820329,containment Hydrogen Sample Valves ECR-10,-11,-13,-21 & -23 Failed to Open.Caused by Two Open Solenoid Coils,Mfg by Asco,Model 103-834-2. Solenoids Replaced,Valves Timed & Returned to Svc
05000322/LER-1993-001, :on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings Held
05000416/LER-1990-007, :on 900516,discovered That Actions Taken for Inoperable Reactor Water Level Transmitter Not Adequate to Comply W/Requirements for Tech Spec 3.3.2.Caused by Personnel Error.Meetings Held W/Personnel
05000334/LER-1981-098-03, /03L-0:on 811107,w/reactor at 92%,technicians Performing 1B H2 Analyzer Maint Surveillance Procedure Reported Smoke Originating from H2 Analyzer Cabinet.Caused by Electrical Short within Wiring Harness.Short Repaired
05000269/LER-1993-003-01, :on 930218,determined That Ssf Rcmu Pump Was Inoperable Due to Design Deficiency.Pressure Vented from Rcmu Pump Suction Stabilizers,Procedures Revised & Design Basis Document Completed
05000370/LER-1990-004-03, :on 900213,reactor Power Mismatch Exceeded Tech Spec Interpretation Requirement for Power Maneuvers After 50 % Main Turbine Runback Occurrence.Caused by Design Deficiency.Design Study Performed
05000413/LER-1990-003, :on 900112,FSAR Dose Limits Set for LOCA Offsite Dose Analysis Could Have Been Exceeded by 10% If LOCA Occurred Coincident W/Loss of Train B Electrical Power. Caused by Mgt Deficiency.Procedures Revised
05000321/LER-1990-002-01, :on 900131,discovered That Functional Test of Turbine Stop Valve Position Limit Switches Not Performed. Caused by Personnel Error When Writing Recent Rev.Rev to Procedure 34SV-C71-001-1S/2S Written
05000293/LER-1989-034, :on 891108,determined That Reactor Pressure Exceeded 150 Psig on 891107 W/O Performing Surveillance Procedure 8.5.4.4, HPCI Valve Operability Test. Caused by Personnel Error.Procedure Initiated
05000346/LER-1978-041-03, /03L-1:on 780423,containment Hydrogen Dilution Blower 1-1 & Discharge Valve of Blower 1-2 Found Tagged for Maint.Caused by Personnel Mistakenly Listing Discharge Valve Circuit Breaker of Blower 1-2 Instead of Blower 1-1
05000336/LER-1988-010-01, :on 880921,observed That Test/Operate Switch for Each of Containment Atmosphere Gaseous Radiation Monitors Was in Test Position.Caused by Operator Error. Switch Placed in Operate Position
05000316/LER-1989-018, :on 891108,discovered That P-250 Computer Contained Incorrect Blowdown Constants for Thermal Output Program Entered on 891025.Caused by Lack of Administrative Controls.Zero Value for Blowdown Reentered
GO2-82-400, Forwards Specific Discussions Supplementing FSAR W/Addl Geologic Info,Per Geosciences Branch Verbal Requests
CY-05-059, License Termination Plan Supplemental Information - Results of the Unconfined Aquifer Pumping Test Conducted in the Industrial Area
L-MT-03-031, Operability Evaluation of the EDG Exhaust Piping for a Tornado Event, Rev 0, Attachments F Through H
W3P82-2639, Forwards Informal Record of Seismic Qualification Review Team Audit.Schedule for Confirmatory Items Will Be Provided by 821003.Pages 6 & 7 Will Not Be Included in Formal Rept Issued by Eg&G
05000339/LER-1989-008-01, :on 890806,ESF Valve 2-RS-MOV-201B Closed Inadvertently During Initial Performance of 2-PT-36.5.3A. Caused by Misidentification of Interlock for 2-RS-MOV-201B. Tech Spec 3.0.3 Entered & Deviation Rept Done
05000327/LER-1986-054, :on 861201,discovered That Discrepancy Existed Between Data Contained on Drawings for 125-volt Dc Vital Battery Sys & Data Used in Surveillance Instruction (SI)- 105.Instruction Will Be Revised