RS-17-072, Fourth 10-Year Interval Inservice Inspection Program Relief Requests
RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
RS-15-218, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NL-13-082, Report on Inoperable Core Exit Thermocouple
NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities
RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
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
W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 2022
05000498/LER-1988-041, :on 880710,high Toxic Gas Alarm Occurred W/O Automatic Actuation of Control Room Ventilation to Recirculation Mode.Caused by Incorrect Configuration of Wiring.Wiring Corrected
05000282/LER-1997-008-01, :on 970602,Unit 1 Reactor Trip Occurred.Caused by Electrical Ground in Rod Control Sys.Troubleshooting Activities Were Conducted
05000454/LER-1984-023-04, :on 841208,during Digital Rod Position Indication Surveillance,Single Control Rod in Control Bank D Moved Out of Core.Caused by Reversed CRD Mechanism Coils. Wiring Corrected
05000446/LER-1994-014, :on 941007,manual Reactor Trip Initiated.Caused by Digital Rod Position Indication Failure for Control Bank D Control Rod H-8.Loose Connector Will Be Corrected During Refueling Outage
ST-HL-AE-3638, Forwards Evaluation of Plugged Tubes in Steam Generators Where 106 Stub Tubes Are Capped Approx 6 Inches Above Tube Sheet Which Were Not Included in Preservice Insp Program
05000237/LER-1977-014-03, /03X-1 on 770402:during Normal Startup Oper,Crd H-8 Was Found to Uncouple & Overtravel When Withdrawn to Pos 48.Caused by an Unlatched Inner Filter & Abnormally Long Uncoupling Rod
05000247/LER-2010-007, Regarding Automatic Reactor Trip Due to a Turbine Trip as a Result of a High Steam Generator Level Trip After Transition to Single Feedwater Pump Operation
RA-22-0037, Emergency Plan Annex, Revision 1 and Emergency Plan Annex, Revision 1, Emergency Action Level (EAL) Wallchart, Revision 2, and EAL Technical Basis Document
RA17-055, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report