NLS2015137, Phase 1 and Phase 2 Overall Integrated Plan in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
AEP-NRC-2015-01, Steam Generator Tube Inspection Report
NLS2014101, First Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109)
2CAN081402, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360
1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
NRC-13-0013, DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15, Accident Analysis - Classification of Plant Conditions
NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 1, Updated Seismic Recommendation 2.3 Walkdown Report, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachme
NL-16-118, Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 2.0 - Site Characteristics, Table of Contents Through Table 2.5-35
ULNRC-05902, Callaway, Unit 1, Enclosure 7: Preliminary Jurisdictional Wetland & Stream Determination Report for the Callaway Nuclear Plant
NRC 2009-0123, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information for Calculation of the Auxiliary Feedwater Pump Low Suction Pressure Setpoint
CP-200900707, Revision to Relief Request No. P-2 for the Units 1 & 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
RS-06-036, Egc/Amergen, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.
NLS2019001, Completion of Required Action for NRC Order EA-13-109 - Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Cooper Nuclear Station, Docket No. 50-298, DPR-46
DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
L-01-220, Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept
BVY 03-103, Rev. 25 to OP 3505, Rev. 17 to OP 3531, Rev. 3, LPC1 to OP 3540, and Rev. 2, LPC1 to OP 3545
ST-HL-AE-2206, Forwards Annotated Revs to FSAR App 3.6.A, Isolation Valve Cubicle Subcompartment Analysis. Rev Due to Calculation Results Showing That Some High Energy Line Break Effects Worse than Main Steam Line Break.Rev Will Be in FSAR Amend
05000315/LER-1985-070, :on 851210 & 11,while in Mode 5,fire Penetrations & Seals Found Nonfunctional.Fire Watches Posted & Seals Repaired.Final Rept Will Be Submitted When Safety Evaluations Complete
PY-CEI-NRR-0222, Discusses Review of Reg Guides in FSAR Table 1.8-1 Re Preoperational Testing,Operations,Operational QA, Surveillance & Maint,Per Util .Clarifications to Be Added to FSAR Table 1.8-1 in Future Amend Encl
SNRC-1697, Lilco 1989 Annual Financial Rept
05000244/LER-1996-006, :on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2
DCL-15-154, Response to NRC Request for Additional Information Dated October 1, 2015, and November 13, 2015, Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report
CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage
NRC 2010-0113, License Amendment Request 261 Extended Power Uprate, Transmittal of Sample Reactor Protection System/Engineered Safety Features Actuation System Instrumentation Setpoint Calculations
NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years
BVY 03-103, Rev. 25 to OP 3505, Rev. 17 to OP 3531, Rev. 3, Lpc 1 to OP 3540, and Rev. 2, Lpc 1 to OP 3545
GO2-81-042, Forwards Response to Reactor Sys Branch Request for Addl Info Re Open Items,Per 811007 Telcon.Response Will Be Incorporated Into FSAR Amend 21
A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737