NL-08-009, Indian Point Energy Center - Hydrogeologic Site Investigation Report - Appendix H Through I
NRC Generic Letter 79-23, NRC Staff Review of Responses to I&E Bulletin 79-08
L-2001-082, Revised Emergency Plan Implementing Procedures
NUREG/CR-5342, Forwards NUREG/CR-5342, Assessment & Recommendations for Fissile Matl Packaging Exemptions & General License Provisions within 10CFR71. Without Encl
IA-87-658, FIN Listing by DOE Ofc/Contractor/Nrc Ofc,Fy 79 & FY82-86
ST-HL-AE-1298, Forwards marked-up FSAR Pages in Response to Instrumentation & Control Sys Branch 850326-29 Meetings Re Auxiliary Feedwater Turbine Control.Fsar Pages Will Be Incorporated Into Future FSAR Amend
05000213/LER-1989-008, :on 890425,discrepancy Discovered in Facility Design Basis Large Break LOCA Analysis.Caused by Use of non-LOCA Model Vol in LOCA Model Applications.Administrative Control to Reduce Tech Specs Limit Implemented
05000302/LER-1989-010, :on 890331,determined That Electrical Cable Splices Associated W/One of Main Feedwater Pump Suction Valves Wrongly Installed.Caused by Personnel Error.Procedure Governing Splice Installation Revised
05000277/LER-1989-009-01, :on 890505,while Performing HPCI Operability Testing,Hpci Sys Did Not Respond Properly to Flow Control Signals.Caused by Failure to Follow Installation Instructions.Mod Process Enhancements Planned
05000260/LER-1989-003-01, :on 890203,discovered That Scram Function for source-range Monitors Not Operational & Two Jumpers Installed in Reactor Protection Sys Logic Not Removed.Caused by Personnel Error.Jumpers Removed
05000416/LER-1987-021, :on 871130,shutdown Cooling Suction Valve E12-F009 Isolated.Caused by Personnel Error.Future Power Outages & Restorations Will Have Procedures to Ensure That Actions Properly Completed
05000341/LER-1987-016, :on 870510,reactor Protection Sys Actuated & ESFs Challenged Due to Transient in Common Ref Leg.Caused by Repairman Attempt to Crack Open Ref Leg Isolation Valve. Valves to Improve Repairman Control Installed
05000250/LER-1986-023, :on 860504,discovered That Transfer of Motor Control Ctr D from Potentially Operable Bus to Potentially Inoperable Bus Could Occur.Caused by Failure to Account for Failure Mode for auto-transfer
05000250/LER-1986-013, :on 860312,bi-weekly Protection Surveillance T Average/Delta T Exceeded Allowable Grace Period. Caused by Failure to Sign Work Order & Data Sheets & Process Data in Timely Manner.Procedure AP 0190 Revised
05000285/LER-1988-013, :on 880509,Channel C Reactor Coolant Low Flow Trip Setpoint Found to Be Out of Tolerance Low.Caused by Failed Power Supply to Trip Unit.Supply Replaced,Unit Returned to Operability & Memo Issued
05000278/LER-1985-025-01, :on 851101,Tech Specs Violated Due to Inoperable Snubbers.Caused by Procedure Not Indicating That CRD Sys Considered Inoperable Pending Repair of Inoperable Snubbers.Procedures Revised
05000263/LER-1986-005, :on 860209,isolation of Reactor Bldg Ventilation Sys & Initiation of Standby Gas Treatment Sys Occurred Due to Reactor Bldg Vent wide-range Gas Monitor Trips.Caused by Personnel Error.Manual Revised
05000395/LER-1984-042-01, :on 841026,while Investigating Event Associated W/Radiation Monitor RM-A4,determined That Plant Design May Not Satisfy Intent of Tech Spec 3.3.2 Re ESF Actuation Sys Instrumentation
05000254/LER-1984-002, :on 840307,while Performing Refueling Outage Local Leak Rate Testing,Measured Combined Leakage Rate for All Penetrations & Valves Found in Excess of Tech Specs. Valves,Hatches & Penetrations Repaired
05000374/LER-1984-047, :on 840805,digital Volt Meter Inadvertently Connected Causing Turbine Control Valves to Shut & Reactor to Scram on High Neutron Flux.Caused by Personnel Error. Personnel Retrained on Startup Procedures
05000265/LER-1992-006-01, :on 920128,unit Operating W/Mode Switch in Shutdown Position W/No Fuel in Reactor Vessel.On 920211, Discovered That Temporary Procedure 7270 Not Logged.Caused by Procedure Deficiency.Procedure Changed
05000277/LER-1991-035, :on 911025,trip of Emergency Bus Breaker Caused Automatic Fast Transfer Resulting in CR Emergency Ventilation Sys Actuation.Caused by Personnel Incorrectly Installing Test Equipment.Personnel Counseled
05000277/LER-1994-010-02, :on 941024,setpoint Drift Associated W/Main Steam Relief Valves & Safety Valves Occurred.Caused by Small Drift in Setpoint of Valves.Refurbished Valves Properly Setup at Test Facility & Installed
05000302/LER-1994-007, :on 941012,failure to Perform Surveillance Resulting in Violation of Ts.Caused by Cognitive Personnel Error.Standardized MAR Review Program Has Been Included in Sys Engineering Manual
05000498/LER-1991-011, :on 910408,Tech Spec Required Shutdown Due to Failure of Feedwater Isolation Valve Solenoid.Caused by Failure of One of Two Redundant FWIV Solenoid Valves to Operate Due to Hydraulic Fluid.Mod Implemented
05000369/LER-1991-006, :on 910215,containment Air Return & Hydrogen Skimmer Sys Declared Inoperable.Caused by Design Deficiency. to Procedures Revised to Exclude Hydrogen Skimmer Fans & Dampers
05000213/LER-1990-021, :on 901002,surveillance Frequency Exceeded for Turbine Bldg Heat Detector Test
SNRC-1011, Forwards Monthly Status of Equipment Summary List,Including balance-of-plant & NSSS Equipment,Per SER Issue 8, Dynamic Qualification. Rept Forwarded to Bnl,Per Rl Tedesco
CLI-90-04, Request for Clarification from Commission.* Requests Clarification of Whether Refs in CLI-90-04 to Accidents W/ 10-4 Probability Mean That Contention Should Be Read on Remand to Encompass Accident Scenario in That Range
05000213/LER-1993-002, :on 930323,control Rods 31 & 32 Malfunctioned When Operators Attempted to Insert Control Bank B.Caused by Inadequate Procedural Verification on Maint of Control Rod Contactors.Mechanical Fasteners Tightened
05000482/LER-1990-020, :on 900827,portable Sump Pump Installed W/Pump Discharge Directed to Storm Drains,Bypassing Turbine Bldg Drain Monitor LE-RE-59.Caused by Lack of Communication Between Involved Groups
05000029/LER-1979-018-01, /01T-0 on 790727:informed of Deviation from Specified Value in Fuel Pin Pressure.Caused by Mfg Techniques.Mfg Changed Method of Prepressurization Employed at Fabrication Facility
L-89-227, Forwards Results of Field Survey for Plant Beach Survey Procedure Completed on 890524 & Reduction of Field Survey Data Completed on 890605.Dune Condition Acceptable,Per Unit 1 Tech Spec 5.1.3
L-89-260, Rept of Changes Made Under Provision of 10CFR50.59 for Period Ending 890122
RS-13-165, Request for License Amendment to Revise Battery Surveillance Requirements
L-04-028, January 2003 NPDES Discharge Monitoring Report
DCL-84-049, Public Version of Emergency Plan Implementing Procedures, Including Procedure EP G-4 Personnel Accountability & Assembly & EP RB-12 Re Mid & high-range Plant Vent Radiation Monitors & Jm Felton 840302 Release Memo
05000416/LER-1992-001-03, :on 920108,RHR Sys Pump Suction Valve Failed to Open During Alignment.Caused by Valve Phenomenon Known as Pressure Locking.Interim Procedural Controls Implemented for Problem Until Sys Mods Implemented