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ASME Section XI +  and ASME Section I +

Nickel +, Carbon +, Sodium +, Chlorine +, Chloride +, Aluminum +  and Chromium +

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 54.21 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +, 10 CFR 54.29#a +, 10 CFR 50.59#c1 +, 10 CFR 50.61#b4 +, 10 CFR 54.21#d +, 10 CFR 54.21#a3 +, 10 CFR 54.21#b +  and 10 CFR 50#90 +

CR-IP2-20-00015 +  and CR-IP2-20-00013 +

NL-07-153 +, 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-11-096, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000154, Entergy Clarification (NL-11-096) for Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 5 +, 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 +, NL-09-111, Additional Information Regarding License Renewal Application - IPEC RAI 2.3A.3.11-1 and Buried Piping and Tanks Inspection Clarifications +, 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-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +, 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-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 +, NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +  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 +

05000286  +, 05000247  +, 00458  +, 00459  +, 00247  +  and 00286  +

ML111600498 +, ML080230637 +, ML110190809 +, ML090160204 +, ML103430502 +, ML110250634 +, ML112620529 +, ML11229A803 +, ML11201A160 +, ML11215A128 +, ML11139A447 +, ML1014501190 +, ML110180529 +, ML11090A078 +, ML11102A006 +, ML11XXXXXXX +, ML11215A056 +, ML11215A088 +, ML112270145 +, ML952780376 +, ML1117BA335 +, NL-10-076, Amendment 10 to License Renewal Application +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, ML110960360 +, NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

MRP-146 +  and MRP-227 +

EC-947 +, EC-222 +  and EC-251 +

New York +, Office of the Attorney General +, Riverkeeper +, Sipos J +, Brancato D +  and Musegaas P +

ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +, ML11273A196 +...

LRA B.1.6 +, LRA B.1.28 +, LRA B.1.27 +, LRA B.1.33 +, LRA B.1.23 +  and LRA B.0.4 +

IR 05000286/2011003 +, IR 05000247/2010404 +, ML110871459 +, ML11208C309 +, ML102110086 +, ML11139A447 +, ML110180529 +, ML11234A470 +, CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 +, ML083500409 +, ML071140022 +  and 05000247/LER-2009-003, Regarding Loss of Single Train 21 Pressurizer Backup Heater Required for Remote Plant Shutdown from the Control Room Due to an Inoperable Breaker +

NL-07-153 +, 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-11-096, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000154, Entergy Clarification (NL-11-096) for Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 5 +, 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 +, NL-09-111, Additional Information Regarding License Renewal Application - IPEC RAI 2.3A.3.11-1 and Buried Piping and Tanks Inspection Clarifications +, 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-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +, 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-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 +, NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +  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 +

CLI-01-17 +, CLI-10-17 +  and CLI-74-23 +

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 +

SP-152 +  and SP-153 +

1O-year +, 1O-inch +  and 1a-year +

Connecticut +, Washington +, New York +, Florida +, Indiana +  and Vermont +

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

Non-Destructive Examination +, Coatings +, Nondestructive Examination +, Emergency Lighting +, Condition Adverse to Quality +, Aging Management +, Stress corrosion cracking +, License Renewal +, Fire Protection Program +, Thermography +  and Thermal fatigue +

WCAP-2013 +  and WCAP-12866 +

WCAP-12866 +  and WCAP-2013 +