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List of results

• ML14015A135  + (Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems, Figures 3.6-2 Through Figure 3.6-16)
• ML13016A312  + (Updated Safety Analysis Report, Revision 15, Chapter 2 - Site Characteristics, Figures 2.5-1 Through 2.5-299)
• ML13016A333  + (Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems)
• ML13016A339  + (Updated Safety Analysis Report, Revision 15, Chapter 10 - Steam and Power Conversions System)
• ML14015A105  + (Updated Safety Analysis Report, Revision 16, Chapter 2 - Site Characteristics)
• ML101540176  + (Updated Safety Analysis Report, Revision 23, Section 9.1A, Fuel Storage Rack Analysis)
• ML14015A250  + (Updated Safety Analysis Report, Revision 16, Chapter 13 - Conduct of Operations)
• ML101540175  + (Updated Safety Analysis Report, Revision 23, Section 9.1, Auxiliary Systems)
• 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)