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IWB-3600 +  and IWB-3514 +

ASME Section XI +, ASME Section III +, ASME Section V +  and ASME Section X +

Boron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Zirconium +, Chloride +, Lead +  and Zinc +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +  and 10 CFR 54.21#c1iii +

SECY-95-245 +, SECY-99-148 +, NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-12-089, Official Exhibit - ENT000554-00-BD01 - NL-12-089, Letter from F. Dacimo, Entergy, to NRC, Reply to Request for Additional Information Regarding the License Renewal Application Indian Point Nuclear Generating Unit Nos. 2 & 3 +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-11-032, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000151, Entergy Response (NL-11-032) to Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 50-247 +, NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +, NL-08-092, Amendment 5 to License Renewal Application (LRA) +, NL-08-084, Reply to Request for Additional Information Regarding License Renewal Application Time-Limited Aging Analyses and Boraflex +, NRC 43 +, NL 032 +, NL 052 +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +

05000247  +  and 05000286  +

MRP-227 +, MRP-175 +, MRP-191 +  and MRP-210 +

Entergy +, Morgan, Lewis & Bockius +, LLP +, Morgan +  and Sutton K +

ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +, ML15261A833 +  and ML15261A833 +

Westinghouse +  and A109 +

NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-12-089, Official Exhibit - ENT000554-00-BD01 - NL-12-089, Letter from F. Dacimo, Entergy, to NRC, Reply to Request for Additional Information Regarding the License Renewal Application Indian Point Nuclear Generating Unit Nos. 2 & 3 +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-11-032, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000151, Entergy Response (NL-11-032) to Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 50-247 +, NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +, NL-08-092, Amendment 5 to License Renewal Application (LRA) +, NL-08-084, Reply to Request for Additional Information Regarding License Renewal Application Time-Limited Aging Analyses and Boraflex +, NL 032 +, NL 052 +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +

NRC Bulletin 88-11 +  and NRC Bulletin 88-08 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-6815 +, NUREG-6260 +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-2101, Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station +, NUREG-1916, Correction to Renewed Operating License Page Issued with NUREG-1916, Volume 2 Issued on 12/17/2008 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Regulatory Guide 1.99 +  and Regulatory Guide 1.207 +

SECY-95-245 +  and SECY-99-148 +

Pennsylvania +, Connecticut +, Maryland +, Washington +, New York +, Michigan +, Wisconsin +, Oklahoma +, Missouri +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +  and Control Rod +

Boric Acid +, Non-Destructive Examination +, Safe Shutdown Earthquake +, Incorporated by reference +, Finite Element Analysis +, Aging Management +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, Fuel cladding +, Pressure Boundary Leakage +, Dissimilar Metal Weld +, Stretch Power Uprate +  and Thermal fatigue +

WCAP-17199-P +, WCAP-17200-P +, WCAP-16898-P +, WCAP-17577 +, WCAP-12191 +, WCAP-17199 +  and WCAP-17200 +

WCAP-17199-P +, WCAP-17200-P +, WCAP-16898-P +, WCAP-17577 +, WCAP-12191 +, WCAP-17199 +  and WCAP-17200 +