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

Nickel +, Carbon +, Lead +  and Chromium +

10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.6 +  and 10 CFR 54.21#a3 +

NL-14-13 +, NL-14-113, Steam Generator Examination Program Results 2014 Refueling Outage (2R21) +, NL-14-001, Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair +, NL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage +, NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-11-074, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000152, Entergy Response (NL-11-074) to Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 50-247 +, 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-11-101, Clarification for Request for Additional Information (RAI) Aging Management Programs +, NRC 19 +, NRC 111 +, NRC 11 +, NRC 1041 +, NRC 460 +, NRC 461 +, NRC 135 +, NRC 282 +, NRC 21 +, NRC 1076 +, NRC 301 +, NRC 449 +, NRC 43 +, NRC 1193 +, NRC 246 +, NRC 235 +, NRC 255 +, NRC 365 +, NRC 419 +, NRC 293 +, NRC 163 +...

05000247  +, 05000286  +, 00247  +  and 00286  +

ML12047A308 +, ML15044A491 +, ML15044A492 +, ML14343A757 +, ML11273A195 +, ML11273A196 +, ML11314A211 +, ML11298A380 +, ML11298A379 +, ML11325A433 +, ML11335A363 +, ML11340A088 +, ML12114A248 +, ML12188A747 +, ML12198A548 +, ML12229A432 +, ML13007A515 +, ML13007A516 +, ML15044A500 +, ML15044A498 +, ML15044A502 +, ML15069A677 +, ML15069A590 +, ML15090A346 +, ML15147A567 +  and ML15174A081 +

MRP-227 +  and MRP-175 +

ML15337A319 +, ML15337A319 +, ML15337A319 +, ML15337A319 +, ML15337A319 +, ML15337A319 +, ML15337A319 +, ML15337A319 +  and ML15337A319 +

IR 05000247/2013010 +  and IR 05000247/2014001 +

LBP-13-13 +  and LBP-08-13 +

A109 +  and Westinghouse +

NL-14-13 +, NL-14-113, Steam Generator Examination Program Results 2014 Refueling Outage (2R21) +, NL-14-001, Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair +, NL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage +, NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-11-074, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000152, Entergy Response (NL-11-074) to Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 50-247 +, 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-11-101, Clarification for Request for Additional Information (RAI) Aging Management Programs +  and NL-11-090, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000153, Entergy Response (NL-11-090) to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Number 2 and 3 (Jul. 27, 2011) (Entergys Ju +

NRC 19 +, NRC 111 +, NRC 11 +, NRC 1041 +, NRC 460 +, NRC 461 +, NRC 135 +, NRC 282 +, NRC 21 +, NRC 1076 +, NRC 301 +, NRC 449 +, NRC 43 +, NRC 1193 +, NRC 246 +, NRC 235 +, NRC 255 +, NRC 365 +, NRC 419 +, NRC 293 +  and NRC 163 +

CLI-09-07, Staff Assessment of the Oyster Creek 3-D Finite Element Analysis of the Drywell Shell +, CLI-01-17 +, CLI-15-06 +, CLI-83-19 +, CLI-05-15 +, CLI-10-14 +, CLI-04-21 +, CLI-10-17 +, CLI-06-01 +, CLI-03-02 +, CLI-03-08 +, CLI-01-22 +, CLI-08-23 +, CLI-85-02, Response Opposing TMI Alert 860228 Motion to Dismiss & for Stay of Decisions in CLI-85-02 & 850905 Notice of Hearing to C Husted.Motion Untimely & W/O Merit.Certificate of Svc Encl +, CLI-12-05, 6/12/2012 - Seabrook Lr Certified Index +  and CLI-06-24, SRM-M070226-Affirmation: I. SECY-06-0243 Amergen Energy Oyster Creek; Ii. SECY-06-0245 Nuclear Management Palisades; Iii. SECY-06-0246 System Energy Resources ESP Grand Gulf; Iv. SECY-07-0006 Pacific Gas & Electric Diablo Canyon ISFSI +

NUREG/CR-6260 +, NUREG-1950, Official Exhibit - ENT000528-00-BD01 - NUREG-1950, Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 (Apr. 2011) (Excerpted) +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

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

Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +

Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, EVT-1 +, Dissimilar Metal Weld +, Stretch Power Uprate +, Affidavit +  and Thermal fatigue +