L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
LR-N09-0014, Submittal of Biennial Decommissioning Funding Status Report
NL-08-009, Indian Point Energy Center - Hydrogeologic Site Investigation Report - Appendix H Through I
B16626, Application for Amend to License NPF-49,changing TS Bases Section 2.2 to Clarify Function of P-6 Interlock for Increasing as Well as Decreasing Reactor Power
ST-HL-AE-5654, Forwards Results for Hot,Full Flow Rod Drop Testing in Unit 2 Cycle 6,performed 970501.Core Map,Core Design Data & NRC Bulletin 96-001 Correspondence Table,Encl
1CAN079202, Requests Temporary Waiver of Compliance from TS LCO 3.1.6.9 Re Leakage Criteria for RCS Pressure Isolation Valves to Allow Corrective Actions to Be Implemented to Seat Unseated Check Valve
05000305/LER-1986-005, :on 860417,reactor Trip Occurred During Performance of Work Request on Intermediate-Range Nuclear Channel N35.Caused by Premature Removal of Control Power Fuse
05000286/LER-1985-004, :on 850320,during Plant Startup,Failure of Power Fuses for Nuclear Instrumentation intermediate-range Channel 36 Resulted in Three Reactor Trips.Caused by Intermittent Current Leak Across Test Switch
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
05000286/LER-1985-004-01, :on 850320,control Power Fuses for Nuclear Instrumentation Range Channel 36 Failed,Resulting in Three Reactor Trips.Caused by Current Leakage Across Test Switch. Testing Performed.Investigation Continuing
05000423/LER-1992-006-02, :on 920306,discovered That Intermediate power- Range Power Above Permissibe (P6) Bistable Calibr Lower than TS Trip Setpoint.Caused by Procedural Deficiency.Bistable Recalibrated to More Conservative Value
05000413/LER-1993-006, :on 930612,Unit 1 Reactor Trip Occurred.Caused by Blown Fuse in Range Channel.Control Room Operators Manually Throttled CA Flow to Control Nc Cooldown
05000483/LER-2019-006, Unrecognized Inoperability of Boron Dilution Mitigation System (Bdms) Train B
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
NMP1L3486, Radiological Emergency Plan Document Revision
05000483/LER-2019-003, Reactor Trip Due to Source Range Hi-Flux
LIC-17-0076, EP-FC-1001 Revision 3, Post-Shutdown Radiological Emergency Response Plan for Fort Calhoun Station
05000397/LER-1990-012, :on 900527,failure of Diesel Generator Slip Ring End Bearing Resulted in Fire in Bearing Area.Caused by Mfg Error,Design Deficiency & Personnel Error.Emergency Operating Procedures Used to Deal W/Fire
LIC-17-0063, EP-FC-1001, Rev. 2, Post-Shutdown Radiological Emergency Response Plan
LIC-17-0041, Independent Spent Fuel Storage Installation - Revision to Emergency Plan Update
L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report
HNP-15-009, 3 to Emergency Plan Procedure PLP-201, Emergency Plan
RNP-RA/14-0125, Response to NRC Request for Additional Information Related to Refueling Outage 28 Steam Generator Tube Inspection Report
L-2007-076, Steam Generator Tube Inservice Inspection Special Report