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ASME Section XI +  and ASME Section III +

Nickel +, Carbon +, Chloride +, Lead +, Aluminum +  and Chromium +

10 CFR 50.48 +, 10 CFR 15 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 54.4 +, 10 CFR 50.591#1 +, 10 CFR 54.4#a2 +  and 10 CFR 50.61#b4 +

NL-07-153 +, SECY-95-245 +, 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-09-111, Additional Information Regarding License Renewal Application - IPEC RAI 2.3A.3.11-1 and Buried Piping and Tanks Inspection Clarifications +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, NL-09-106, Response to Questions Regarding Buried Piping Inspections +, NL-09-079, Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event +, NL-09-056, Reply to Request for Additional Information - Open Items +, NL-09-018, Reply to Request for Additional Information - Miscellaneous Items +, NL-08-074, Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074) +, NL-08-127, Additional Information Re License Renewal Application - Structural OE Clarifications, Clarifications for Electrical RAIs and Audit Questions, License Renewal Application Amendment +, NL-08-057, Amendment 3 to License Renewal Application (LRA) +, NL-08-021, License Renewal Application Amendment 2 +, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application +, NL-07-039, License Renewal Application. Appendix E Figure 2-24 Through Figure 2-29 +, NRC 135 +, NRC 328 +, NRC 43 +, NRC 195 +, NRC 279 +, NRC 229 +, NRC 318 +, NRC 727 +, NRC 289 +, NRC 170 +, NRC 905 +, NRC 115 +, NRC 658 +, NL 107 +, NL-11-107, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000314, License Renewal Application- Completion of Commitment 30 Regarding the Reactor Vessel Internals Inspection Plan +...

05000286  +, 05000247  +, 00247  +  and 00286  +

ML083300592 +  and ML071350410 +

MRP-146 +, MRP-227 +, MRP-228 +  and MRP-191 +

NRC/OGC +  and Roth D +

ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +, ML11298A379 +  and ML11298A379 +

LBP-08-13 +, LBP-06-22 +, LBP-08-14 +, LBP-08-26 +  and LBP-09-04 +

LRA B.1.6 +, LRA B.1.28 +, LRA B.1.25 +, LRA B.1.27 +, LRA B.1.33 +, LRA B.1.23 +  and LRA B.1.37 +

NL-07-153 +, 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-09-111, Additional Information Regarding License Renewal Application - IPEC RAI 2.3A.3.11-1 and Buried Piping and Tanks Inspection Clarifications +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, NL-09-106, Response to Questions Regarding Buried Piping Inspections +, NL-09-079, Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event +, NL-09-056, Reply to Request for Additional Information - Open Items +, NL-09-018, Reply to Request for Additional Information - Miscellaneous Items +, NL-08-074, Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074) +, NL-08-127, Additional Information Re License Renewal Application - Structural OE Clarifications, Clarifications for Electrical RAIs and Audit Questions, License Renewal Application Amendment +, NL-08-057, Amendment 3 to License Renewal Application (LRA) +, NL-08-021, License Renewal Application Amendment 2 +, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application +, NL-07-039, License Renewal Application. Appendix E Figure 2-24 Through Figure 2-29 +, NL 107 +, NL-11-107, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000314, License Renewal Application- Completion of Commitment 30 Regarding the Reactor Vessel Internals Inspection Plan +, NL-08-014, Clarifications to Reactor Vessel Surveillance Program and Neutron Embrittlement Time-Limited Aging Analyses and Audit Item 105; and Revision to License Renewal Regulatory Commitment List +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +

NRC 135 +, NRC 328 +, NRC 43 +, NRC 195 +, NRC 279 +, NRC 229 +, NRC 318 +, NRC 727 +, NRC 289 +, NRC 170 +, NRC 905 +, NRC 115 +  and NRC 658 +

CLI-09-07, Staff Assessment of the Oyster Creek 3-D Finite Element Analysis of the Drywell Shell +, CLI-06-17 +, CLI-99-10 +, CLI-99-11 +, CLI-03-13 +, CLI-08-28 +, CLI-10-17 +, CLI-09-05 +, CLI-10-27 +, CLI-93-03, Transcript of 930315 Affirmation/Discussion & Vote in Rockville,Md Re SECY-93-061, Environ & Resource Conservation Organization Petition for Reconsideration of CLI-93-03. Pp 1-5 +, CLI-93-25 +  and CLI-08-23 +

NUREG/CR-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-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 +

William Dean +, Robert Walpole +  and David Wrona +

Regulatory Guide 1.99 +  and Regulatory Guide 1.207 +

013NL-07-153 +  and N1L-08-143 +

Pennsylvania +, Connecticut +, Washington +, New Jersey +, New York +, Florida +, Louisiana +, Oklahoma +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, HVAC +, Reactor Pressure Vessel +  and Control Rod +

Non-Destructive Examination +, Coatings +, Nondestructive Examination +, VT-2 +, Emergency Lighting +, Functionality Assessment +, Incorporated by reference +, Aging Management +, Stress corrosion cracking +, Eddy Current Testing +, License Renewal +, EVT-1 +, Fire Protection Program +, Thermography +  and Thermal fatigue +