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• ML14015A286  + (Updated Safety Analysis Report, Revision 16, Appendix C - Computer Programs)
• ML14015A152  + (Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems, Figure 3.6-1. Sheet 63 of 111 Through Figure 3.6-1. Sheet 69 of 111)
• ML13016A350  + (Updated Safety Analysis Report, Revision 15, Appendix C - Computer Programs)
• ML14015A101  + (Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems, Figure 3.6-1. Sheet 1 of 111 Through Figure 3.6-1. Sheet 42 of 111)
• ML14015A291  + (Updated Safety Analysis Report, Revision 16, Chapter 15 - Accident Analysis)
• ML14015A246  + (Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems)
• ML14015A107  + (Updated Safety Analysis Report, Revision 16, Chapter 2 - Site Characteristics, Figure 2.4-19 Through Figure 2.4-53)
• ML14015A106  + (Updated Safety Analysis Report, Revision 16, Chapter 2 - Site Characteristics, Figure 2.1-1 Through Figure 2.4-18)
• ML13016A311  + (Updated Safety Analysis Report, Revision 15, Chapter 2 - Site Characteristics, Figures 2.4-19 Through 2.4-53)
• ML14015A134  + (Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems, Figure 3.6-1. Sheet 101 of 111 Through Figure 3.6-1. Sheet 111 of 111)
• ML13016A342  + (Updated Safety Analysis Report, Revision 15, Chapter 13 - Conduct of Operations)
• ML14015A290  + (Updated Safety Analysis Report, Revision 16, Chapter 14 - Initial Test Program)
• ML13016A332  + (Updated Safety Analysis Report, Revision 15, Chapter 4 - Table of Contents Through Figure 4.6-30)
• ML052010474  + (Updated Safety Analysis Report. USAR-02.03 Section 2 Site and Environs. Revision 19 Section 2.3 Meteorology)
• ML063630255  + (Updated Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station)
• ML16252A350  + (Updated Safety Evaluation Report Related to the Grand Gulf Nuclear Station License Renewal Application)
• ML17340A520  + (Updated Safety Evaluation Supporting Proposed Steam Generator Repairs at Facilities)
• ML18087A821  + (Updated Salem Restart Status Rept)
• BSEP 04-0062, Updated Schedule for License Renewal Application  + (Updated Schedule for License Renewal Application)
• CNRO-2007-00036, Updated Schedule for Submittal of Future License Renewal Applications for Entergy Plants  + (Updated Schedule for Submittal of Future License Renewal Applications for Entergy Plants)
• ML092450109  + (Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants: Waterford 3, Grand Gulf, and River Bend, Unit 1)
• RBG-47703, Updated Schedule of Submittal of Future License Renewal Application  + (Updated Schedule of Submittal of Future License Renewal Application)
• W3F1-2014-0012, Updated Schedule of Submittal of Future License Renewal Application  + (Updated Schedule of Submittal of Future License Renewal Application)
• CNRO-2012-00006, Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants  + (Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants)
• RBG-47436, Updated Schedule of Submittal of Future License Renewal Application River Bend Station - Unit 1  + (Updated Schedule of Submittal of Future License Renewal Application River Bend Station - Unit 1)
• CNRO-2006-00033, Updated Schedule of Submittal of License Renewal Applications for Entergy Plants  + (Updated Schedule of Submittal of License Renewal Applications for Entergy Plants)
• CNRO-2005-00025, Updated Schedule of Submittal of License Renewal Applications for Entergy Plants  + (Updated Schedule of Submittal of License Renewal Applications for Entergy Plants)

• L-PI-04-118, Updated Security Plan  + (Updated Security Plan)
• NG-04-0656, Updated Security Plan  + (Updated Security Plan)
• ML042950027  + (Updated Security Plan)
• ML042730164  + (Updated Security Plan)
• NRC 2004-0093, Updated Security Plan  + (Updated Security Plan)

• ML043020284  + (Updated Security Plan - Page Changes)
• ML042860182  + (Updated Security Plan, Training and Qualification (T&Q) Plan, and Safeguards Contingency Plans)
• ML17306A869  + (Updated Seismic Hazard Evaluation for PVNGS Wintersburg,Az Final Rept)
• ML13252A150  + (Updated Seismic Recommendation 2.3 Walkdown Report Requested by NRC Letter, Request for Information Re Recommendations 2.1, 2.3 & 9.3 of the Near-Term Task Force Review of Insights from Fukushima Dai Ichi Accident)
• NL-13-1236, Updated Seismic Recommendation 2.3 Walkdown Report Requested by NRC, Including SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 of 14  + (Updated Seismic Recommendation 2.3 Walkdown Report Requested by NRC, Including SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 of 14)
• ML14071A060  + (Updated Seismic Recommendation 2.3 Walkdown Report)
• ML14051A734  + (Updated Seismic Recommendation 2.3 Walkdown Report)
• 1CAN091301, Updated Seismic Walkdown Report  + (Updated Seismic Walkdown Report)
• 2CAN091302, Updated Seismic Walkdown Report  + (Updated Seismic Walkdown Report)
• ML13200A159  + (Updated Seismic Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident)
• RS-13-138, Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138  + (Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138)
• ML20205R598  + (Updated Semiannual Effluent Release Rept for First Half 1988, Covering Gaseous & Liquid Effluents)
• ML20034A416  + (Updated Semiannual Radioactive Effluent Release Rept Jul- Dec 1989, Incorporating Sr-89 & Sr-90 Results)
• NL-06-0691, Updated Significance Determination Process Information  + (Updated Significance Determination Process Information)
• NL-06-0692, Updated Significance Determination Process Information  + (Updated Significance Determination Process Information)
• ML20133P137  + (Updated Significant Deficiency Rept 414/85-06 Re Chemical & Vol Control Sys Piping & Equipment.Initially Reported on 850522.Affected Piping & Equipment Evaluated.Final Rept Due by 850815)
• ML20133P156  + (Updated Significant Deficiency Rept 414/85-08 Re All Outstanding Corrective Actions.Initially Reported on 850531. Design Evaluation of Areas of Overpressurization Completed. Flanges Replaced & HXs Inspected)
• ML20027B148  + (Updated Significant Deficiency Rept IE 78/02-5PS-413/414 Re Containment Isolation Valve Type C Leakage.Affected Valves Identified.Most Kerotest Valves Will Be Modified After Valves Installed in Piping)
• ML20077F666  + (Updated Significant Deficiency Rept SD 413-414/83-01.BIF Will Complete Valve Mods by 830815)
• TMI-23-004, Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1  + (Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1)
• ML18241A316  + (Updated Slide)
• AECM-84-0220, Updated Special Rept 83-104/1:on 831024,fire Rated Penetration CE-515D,located on West Wall of Room OC403 on 148-ft Elevation in Control Bldg,Discovered Open.Wrong Penetration Sealed.Permanent Labeling Now in Process  + (Updated Special Rept 83-104/1:on 831024,fire Rated Penetration CE-515D,located on West Wall of Room OC403 on 148-ft Elevation in Control Bldg,Discovered Open.Wrong Penetration Sealed.Permanent Labeling Now in Process)
• AECM-84-0174, Updated Special Rept 84-003/1:on 840112,standby Diesel Generator 12 Tripped on Reverse Power While Running Parallel W/Offsite Power.Caused by Faulty Control Rectifier Diode. Reactifier Replaced  + (Updated Special Rept 84-003/1:on 840112,standby Diesel Generator 12 Tripped on Reverse Power While Running Parallel W/Offsite Power.Caused by Faulty Control Rectifier Diode. Reactifier Replaced)