NOC-AE-16003330, Transmittal of Information of Foreign Ownership, Control, or Influence (FOCI)
NG-13-0102, Response to Request for Additional Information, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
L-12-142, Supplemental Information to a Request for Licensing Action on a Proposed Emergency Preparedness Plan Revision
L-10-246, 10 CFR 50.55a Requests in Support of the Third 10-Year In-Service Inspection Interval
RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 700 - 749, Part 12 of 15
NL-16-0169, Enclosures 10, 11, 12, 13 & 14: Vogtle (Units 1 & 2) Staffing - Detailed Description and Technical Evaluation, Standard Emergency Plan Annex, Justification Matrix, Staffing-Detailed Description and Technical Evaluation and Standard Emerge
RS-14-014, Attachment 1: Kld TR-633, Rev. 0, LaSalle County Generating Station Development of Evacuation Time Estimates, Cover Through Page 5-21
LR-N10-0355, Salem, EAL Comparison Matrix
LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
LR-N10-0355, EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
TMI-10-030, Annual Radiological Environmental Operating Report
NL-08-009, Indian Point Energy Center - Hydrogeologic Site Investigation Report - Appendix H Through I
NRC 2008-0044, Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control
ST-HL-AE-3385, Semiannual Radioactive Effluent Release Rept for Second Half 1989
05000278/LER-1989-006-04, :on 891023,during Reactor Temp Adjustment, Reactor High Pressure Scram Occurred.Caused by Improper Planning & Coordination of Multiple Evolutions.Surveillance & Hydrostatic Test Revised
E910-05-011, Experimental Corporation, 2004 Radiological Environmental Monitoring Report
BVY 04-038, Change to the Emergency Plan, Revision 39
IA-85-230, Affidavit of Jm Puckett Re V English Allegations Concerning Activities at GE Fuel Fabrication Facility in Wilmington,Nc. Supporting Documentation Encl
RBG-26874, Forwards Supplemental Info to Util Initial Rept on ATWS Rule,Per Wa Paulson 870916 request.W/30 Oversize Drawings, Including Nine Final Design Changes
U-602804, Forwards Addl Info in Response to 970730 RAI Re Review of Application for Temporary Partial Exemption from 10CFR50,App a General Design Criterion 17 & Amend to License NPF-62
AECM-88-0232, Submits Info Re Tech Spec Position Statements,In Response to 880928 Meeting & 881006 & 20 Telcons
AECM-84-0100, Summarizes Review & Results of Util Training Programs Not Included within Scope of Recertification Program & Presents Conclusions Re Adequacy of Training Programs.Util Plans to Address Certain Program Areas Also Discussed
NRC-94-0077, Provides Util Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,
TXX-4157, Forwards marked-up Proposed Amend to Chapter 17.1 of FSAR, for Review
05000333/LER-1989-002-01, :on 890302,HPCI Sys Declared Inoperable While Required by Tech Spec 3.5.C.1.Caused by Wiring Error That Existed Since Plant Const.Wiring Error Corrected & Stop Valve Opening Time Adjusted
05000425/LER-1989-019, :on 890502,overspeed Trip Device Malfunctioned During Weekly Turbine Trip Device Operability Test.When Button Pushed Turbine Tripped,Resulting in Reactor Trip. Caused by Defective Weld Joint.Weld Repaired
05000414/LER-1988-018, :on 880427,feedwater Isolation Occurred While Cycling Steam Generator power-operated Relief Valve.Caused by Receipt of 2 Out of 4 Channels Indicating Hi Hi Level. Affected Valves Realigned
05000341/LER-1989-015, :on 890707,power Lost to Div I Reactor Protection Sys Bus a Due to Motor Generator Overvoltage Condition.Caused by Single Phase Sensing Potentiometer. Component Replaced W/Fixed Resistor
05000370/LER-1989-007-04, :on 890810,discovered That Unit Operated in Violation of Tech Specs 3.1.2.1a & 3.1.2.3 When Both Centrifugal Charging Pumps Inoperable During Refueling. Caused by Mgt/Qa Deficiency
05000277/LER-1989-008-01, :on 890415,incorrect Undervoltage Trip Fuses Placement by Operator Occurred Due to Inadequacy of Training Resulting in Isolation of RWCU Sys.Caused by Administrative Deficiency.Training Ltr Will Be Issued
05000369/LER-1988-036, :on 881118,third Test on Vg Header a Did Not Conclude Past Operability Because Blackout Header Loads During Blackout Conditions Are Unknown.Caused by Design Deficiency.Vg Sys Will Be Upgraded
05000443/LER-1989-007-06, :on 890610,ESF Actuation Occurred Causing Containment Ventilation Sys to Isolate.Caused by Faulty Geiger-Muller Tube.Defective Tube Replaced & Monitor Tested & Declared Operational on 890611
05000458/LER-1989-014, :on 890405,operator Inadvertently Initiated Standby Svc Water Sys During Svc Water Vacuum Release Valve Testing,Causing CRD Pump to Trip.Caused by Operator Error. Operator Reinstructed Re Board Manipulations
05000483/LER-1987-016, :on 870625,monthly Sampling & Analysis of Unit Vent Gaseous Effluents Not Performed as Required by Tech Specs.Caused by Personnel Error.All Technicians Instructed to Follow Appropriate Surveillance Procedures
05000354/LER-1987-050, :on 871204,determined Surveillance Missed for MSIV Outboard Steam Sealing Gas Test Line Isolation Valve on 871111 Test.Caused by Personnel Error.Procedure for Tracking Surveillance Testing Reinforced W/Personnel
05000423/LER-1987-043-01, :on 871118,as-found Leakage on Valve 3CDS*CTV91B Exceeded Tech Spec 3.6.1.2.C.Caused by Improper Installation of Valve Seating surface.T-ring Replaced & Rev of Maint Procedures & Training Program Planned
05000245/LER-1987-022-01, :on 870702,unacceptable Inclusions Discovered in Base Metal of Isolation Condenser Bl Return Line Piping. Caused by Mfg Defect.Piping Replaced W/Matl More Resistant to IGSCC
05000369/LER-1987-019, :on 870904,auxiliary Feedwater Autostart Occurred.Caused by Defective Procedure Due to Insufficient Instructions to Prevent Loss of Both Main Feedwater Pumps During Shutdown.Pump Control Valves Reset
DCL-84-161, Advises That Util Revised Pipe Support Design to Require Base Plates to Be Welded to Fan Cooler Structure in Lieu of Using A-325 Bolted Connection.Design Issued & Mods Ready for NRC Insp.Related FOIA Documents Encl
05000278/LER-1987-004-01, :on 870402,leak Rate of Inboard D MSIV Exceeded Tech Spec Limit.Msiv Will Be Inspected to Determine Cause of Leakage.Msiv Will Be Repaired & Retested Prior to Returning to Operable Status
05000414/LER-1986-043-01, :on 861009,fire Barrier Declared Inoperable Due to Two Hole Penetrations Discovered in Fire Wall.Caused by Technician Error.Fire Watch Established & Holes Sealed W/ Fire Plugs
05000529/LER-1986-015-01, :on 860404,automatic Actuation of All Four Channels of Reactor Protection Sys Occurred Due to Low RCS Flow Through Steam Generator 2.Strainer Flushed & Seal Injection Flow Restored
05000373/LER-1997-029, :on 970723,full Scram Signal Generated During Performance of LES-PC-108, Main Steam Isolation Actuation Logic Sys Functional Test. Caused by Poor Mgt Decision to Defer Scheduled Maint.Sspvs Replaced
05000370/LER-1988-007-04, :on 880724,inadvertent ESF Actuation Due to Failure of Signal Comparator Card in Reactor Protection Sys. Failed Signal Computer Card Replaced & Channel III Tested Satisfactorily
05000301/LER-1986-003, :on 860603,turbine Runback Occurred Due to Loss of Power on Instrument Bus.Caused by Trip of White Inverter Output Breaker.Procedures for Placing Inverter on Line Will Be Revised by 860901
05000409/LER-1986-014, :on 860418,determined That During Discharge of 3,000 Gallon Waste Tank,Water from 4,500 Gallon Waste Tank Also Pumped.Caused by Open Suction Valve Leading to Operating Waste Transfer Pump.Valve Closed
05000354/LER-1986-035, :on 860704,reactor Trip Occurred Due to Reactor Protection Sys Channels A1 & A2 Tripping from APRM Channel E Caused by Momentary Upscale Spike of Local power-range Monitor 1C-24-57.Origin of Spike Unknown
05000331/LER-1986-009, :on 860329,w/reactor in Cold shutdown,one-half Group III Primary Containment Isolation & Standby Gas Treatment Sys Actuation Occurred During Outage Maint.Caused by Human Error
05000334/LER-1997-034, :on 971008,identified That Rhrs TS Requirements Were Not Satisfied During Refueling Cavity Draining.Caused by Inadequate Procedures.Revised Procedure 1OM-20.4.E, Draining Refueling Cavity, to Satisfy TS
05000321/LER-1986-020, :on 860425,RWCU Sys Inboard & Outboard Primary Containment Isolation Valves 2G31-F001 & 2G31-F004 Isolated on High Leakage Flow Signal.Caused by Disconnected Jumper During Functional Test.Isolation Reset
05000293/LER-1988-013, :on 880425,inadvertent Manual Start of Emergency Diesel Generator (EDG) B Occurred.Caused by Personnel Error.Improvements to Local Control Panel to EDG Identified & Tracked
B17438, Submits Response to Violations Noted in Insp Rept 50-336/98-201.Corrective Actions:Ist Program Has Been Revised Designating Valves 2-CS-16.1A&B as Periodically Leak Tested Valves.Commitments,Encl
05000458/LER-1986-015, :on 860131,containment HVAC Purge Exhaust Valves Failed Local Leak Rate Test.Cause Not Stated.Valve Seats Replaced & Penetration Successfully Retested
05000413/LER-1988-009, :on 880206,Limitorque Valve Actuator T-drains Found Painted Over or Missing on 27 Valves.Caused by Lack of Communication & Mgt Deficiency.Painters Will Receive Periodic Retraining.Drains Repaired
05000366/LER-1987-013, :on 871019,RCIC Primary Containment Isolation Sys Logic Actuation Occurred.Caused by Missing Insulation on HPCI Steam Supply Piping.Steam Leaks Checked & Required Tech Spec Actions Taken & Temporary Fans Installed
05000528/LER-1986-007, :on 860226,particulate Air Filter from Plant Vent Radiation Monitoring Unit RU-143 Inadvertently Discarded.Caused by Chemistry Technician Error.Applicable Procedure Revised to Include Caution Statement
05000528/LER-1985-080, :on 851220,reactor Tripped on High Pressurizer Pressure.Caused by out-of-tolerance Setpoint in Turbine Demand Runback Module.Module Setpoint Reset & Procedures Changed Re Observing Proper Caution
AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas
05000348/LER-1985-018, :on 851009,air-operated Valve Failed to Stroke During Testing.Caused by Valve Actuator Cylinder Exhaust Breather Cap Being Painted Over During Installation.Breather Caps on Affected Unit 1 & 2 Valves Replaced
05000322/LER-1985-025, :on 850706,Temporary Mod Tm 85-03-010 to Steam Air Ejector Radiation Elements Made in Mar 1985 Discovered Improperly Implemented.Cause Not Stated.Mod Revised to Include Checklist for Temporary Mod Review
05000334/LER-1985-011, :on 850516,chemical Addition Pump a Failed to Start.Caused by Breaker Cubicle Motor Control Ctr Wiring Catching on Breaker While Being Racked In.Wiring Tied Back. Testing Procedure Following Racking Added
05000324/LER-1980-002-03, /03L-0:on 800102,during Normal Reactor Startup,Rod Sequence Control Sys Would Not Allow Rods to Be Pulled Until Rod 34-27 Was Bypassed full-in. Caused by Defective full- in Reed Switch.Switch Will Be Repaired or Replaced
05000282/LER-1992-013, :on 920925,main Generator Was Taken Off Line & Turbine Manually Tripped.Caused by Equipment Failure.Failed Detector Replaced & Source Range Channel 1N-31 Tested Satisfactorily
05000263/LER-1996-006-01, :on 960609,reactor Scram Occurred.Caused by Loss of Stator Water Cooling Flow.Rebuilt Pumps,Replaced Oilers W/Different Type of Device & Installed Grounding Strap/Brush on Both Stator Water Cooling Pumps
05000397/LER-1985-022, :on 850307,two HPCS Initiation Status Lamps Damaged During Process of Replacing Nameplate Tags on Control Room Panel P-625.HPCS Sys Automatic Initiation Logic Rendered Inoperable While Bulbs Replaced
05000261/LER-1985-005-02, :on 850109,reactor Trip Occurred at 14% Power in Steam Generator A.Caused by Turbine Trip.Feedwater Control Valves Observed & Determined to Be Stable
05000321/LER-1985-002, :on 850113,safety Relief Valve B Failed to Open.Caused by Open Links.Links Closed
05000271/LER-1984-013, :on 840721,during Maint on Standby Liquid Control Sys,Relief Valves SR-11-39A & B Found to Have Setpoints Below Required Range.Caused by Testing Technique. Valves Reset,Retested & Reinstalled
05000285/LER-1984-014, :on 840703,during Weekly Replacement of Iodine Collection Cartridge on RM-060,actuation of Ventilation Isolation Actuation Sys Occurred.No Cause given.RM-060 Will Be Out of Svc During Filter Replacement
05000263/LER-1984-026, :on 840910,reactor Bldg Isolation & Initiation of Standby Gas Treatment Occurred.Caused by Closure of Wrong Sample Valve.Caution Statement Placed on wide-range Gas Monitor Sample Filter Changeout Procedure
05000311/LER-1984-003-01, :on 840215,pressurizer Overpressure Protection Sys Actuated Due to Induced Pressure Transient.Caused by Starting Reactor Coolant Pump.Operating Procedure OPII-1.3.4 Amended
05000413/LER-1991-029, :on 911126,discovered That Surveillance Requirement for Turbine Startup Pressure Switch Alarm Not Performed During Turbine Startups.Caused by Inappropriate Operator Actions.Procedure Revised
05000293/LER-1991-018, :on 910710,setpoints of Degraded Voltage Relays Discovered Too Low Probability Degraded Voltage Conditions. Cause Unknown.Mods Planned to Replace Applicable Control Power Transformers
05000324/LER-1991-010-02, :on 910806,RWCU Sys Automatically Isolated on High Differential Flow While Being Restored to Svc.Caused by Inadequate Procedures.Rwcu Reject to Main Condenser Isolation Valve Replaced
05000260/LER-1983-017-03, /03L-0:on 830409,hydrogen Analyzer B,H2AN-76-104 Declared Inoperable Due to Receipt of loss-of-flow Light 76-88.Caused by Moisture Collecting in Sample Lines.Lines Blown Down & Dried.Moisture Collection Devices to Be Added
NSD-NRC-97-5251, Forwards Evaluation of Seismic Responses & Effects on Structural Design Changes for Post 72-hour Requirements. Info Provided to Support Review Meeting W/Nrc Staff Scheduled for Week of 970811
05000369/LER-1990-024-01, :on 900822,discovered Air Inleakage on Train a of Control Room Ventilation Sys Exceeded Acceptable Levels. Cause Unknown.Personnel Will Further Investigate Probable Failure or Deficiency Cause for Fan Damage
05000293/LER-1990-011, :on 900703,automatic Actuation of RHR Sys Portion of Primary Containment Isolation Control Sys Occurred While Shut Down.Caused by Hydrodynamic Transient. Procedure Revised
05000277/LER-1993-008, :on 930409,Tech Spec Violation Occurred.Caused by Setpoint Drift of Pressure Switch in Conjunction W/Less than Adequate Communication.Event Discussed W/Involved Individuals
05000370/LER-1990-010, :on 880615 & 27,discovered Wire Placed on Wrong Terminal Point on Valve Actuator Terminal Block.Caused by Personnel Error & Mgt Deficiency.Appropriate Maint Procedures Will Be Revised
05000458/LER-1990-010, :on 900320,rope Barricade for High Radiation Area Removed.Caused by Personnel Error.Training on Radiation Protection Practices Will Be Provided to Plant Operators to Emphasize Importance of Requirements
05000285/LER-1990-008, :on 900306,electrician Was Connecting Leads as Part of Control Room Ventilation Mod & Caused Short Circuit While Working on Energized Circuit.Caused by Electrician Error.Enhanced General Guidelines Issued
W3P84-0405, Forwards Info Re Changes to Component Cooling Water Sys to Ensure Cooling to Reactor Coolant Pump Seals in Event of Inadvertent Safety Injection Actuation Signal.Info Includes Summary,Safety Evaluation & marked-up FSAR Pages
05000321/LER-1980-102-03, /03L-0:on 800821,while at Steady State Power,B LPCI Inverter Tripped Making B Loop of RHR Inoperable.Caused by High Ambient Temp.Temporary Cooling Is Being Used Until Installation of Permanent Chillers Is Complete
05000278/LER-1979-011-01, /01T-0 on 790323:during Routine Insp of Drywell & Torus Ventilation Valves,Inflatable Disc Seals Were Found Depressurized.Caused by Procedural Deficiency Following Mod to Drywell & Torus Vent Valves.Procedures Revised
05000280/LER-1990-004-03, :on 900522,reactor Trip/Turbine Trip Occurred. Caused by Inadvertent Actuation on a Main Transformer. C/A:Main Transformer Was Inspected
GO2-94-292, Forwards Updated Response to Deviations Noted in EOPs Insp Rept 50-397/91-27,satifying Commitment Made in 940425 Response to Insp Rept 50-397/94-01
GO2-83-983, Documents Applicability of Battery Level Correction Only for Levels Out of Spec & Provides Basis for Not Applying Level Correction to Specific Gravity,Provided Battery Levels Maintained within Spec
L-83-453, Forwards Rev 1 to App R Exemption Request Section, Summary of App R Analysis by Fire Area, Effective 830630.Encl Revises 830412 Fire Protection Submittal
RNP-RA/08-0121, WCAP-15621-NP, Rev 1, Handbook on Flaw Evaluation for the H.B. Robinson Unit 2 Reactor Vessel
NLS2005031, Enclosure 2, NLS2005031, Cooper Nuclear Station, Offsite Dose Assessment Manual
Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers
ELV-00840, Semiannual Rept Plant Radioactive Effluent Releases Jan-June 1989
AEP-NRC-2024-86, Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation
05000249/LER-1987-001-09, :on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established
05000318/LER-1984-008-01, :on 841003,automatic Trip Occurred Due to Steam Generator Feed Pump (SGFP) 22 Trip.Possibly Caused by Spurious Fault in Common SGFP Control Circuitry.Sgfp Control Oil & Lube Oil Sys Checked
05000346/LER-1984-006, :on 840515,unidentified RCS Leakage in Excess of 1 Gpm.Caused by Failure to Perform Surveilance Test on Reactor Protection Sys Shutdown Bypass Channels.Line Permitted to Depressurize Prior to Maint
05000454/LER-1984-015-07, :on 841125,auxiliary Bldg Vent Stack Monitor Inoperable & Gas Grab Sample Missed.Caused by Personnel Error.Control Room Personnel & rad-chem Foremen Required to Verify Action Prior to Sampling Termination
05000324/LER-1984-008-02, :on 840727,reactor Protection Sys Actuated Due to Electronic Noise Spike.Caused by Section of Fallen Grating Resulting from Snagged Technician Respirator Air Line.Grating Replaced