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ACI-201 +  and ACI-349 +

ANSI B31.1 +  and ANSI 831.1 +

IWB-2500 +, IWB-3131 +, IWB-2430 +  and IWB-3400 +

ASME Section XI +, ASME Section III +  and ASME Section VIII +

Boron +, Iron +, Copper +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Molybdenum +, Chloride +, Lead +, Aluminum +  and Manganese +

10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 1 +, 10 CFR 4 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 51.21 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 54.24 +, 10 CFR 64.21 +, 10 CFR 64.21#c1i +, 10 CFR 514.21#c1i +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a +, 10 CFR 50.59#c1 +, 10 CFR 51.21#c1 +, 10 CFR 51.21#G +...

COR-05-02835 +, COR-05-02892 +, COR-05-0530 +, COR-06-00111 +, COR-06-00373 +, COR-04-0244 +, COR-06-001 +  and COR-06-00178 +

CR-IP3-2007-01852 +, CR-IP3-20-00015 +, CR-IP3-2002-04267 +, CR-IP2-2002-04224 +, CR-IP2-2002-05637 +, CR-IP3-2002-02170 +, CR-IP3-2002-02836 +, CR-IP3-2004-03242 +, CR-IP3-2005-03993 +, CR-IP3-04-20717 +, CR-IP3-05-21330 +, CR-IP2-2002-10610 +, CR-IP2-2002-10052 +, CR-IP2-2003-00682 +, CR-IP2-2003-00959 +, CR-IP2-2004-05180 +, CR-IP2-2005-03557 +, CR-IP2-2005-04433 +, CR-IP2-2004-01347 +  and CR-IP3-05-21329 +

ASME Code Case N-481 +  and ASME Code Case N-532-1 +

NL-07-153 +, NL-07-138 +, COR-05-02835 +, COR-05-02892 +, COR-05-0530 +, COR-06-00111 +, COR-06-00373 +, COR-04-0244 +, COR-06-001 +, COR-06-00178 +, NL-08-057, Amendment 3 to License Renewal Application (LRA) +, NL-08-021, License Renewal Application Amendment 2 +, NL-08-005, Reply to Request for Additional Information Regarding License Renewal Application-(Balance of Plant Systems) +, NL-07-133, Review of the Draft Environmental Impact Statement for SPDES Permits for Bowline Point 1 & 2, Indian Point 2 & 3, and Roseton 1 & 2 Steam Electric Generating Stations, Cover - Enclosure 7a +, NL-07-124, Supplement to License Renewal Application (LRA) +, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application +, NL-07-040, License Renewal Drawing - Page 8 of Drawings List +, NL-07-039, License Renewal Application. Appendix E Figure 2-24 Through Figure 2-29 +, NL-07-041, License Renewal Application Environmental Report References +, NL-05-044, Reactor Vessel Upper Head Inspection Results; Indian Point Unit 3. Spring 2005 Refueling Outage (3R13) +, NL-05-001, Reactor Vessel Upper Head Inspection Results; Indian Point 2. Fall 2004 Refueling Outage (2R16) +, NL-04-090, Indian, Units 2 and 3, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used in Pressurizer Penetrations and Steam Space Piping Connections +, NL-04-069, Stretch Power Uprate License Amendment Request Package, Sections 6.4 Through 11.7 +, NL-04-026, Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Stations 2 and 3, Answer to February 20, 2004 Revised NRC Order Regarding Interim Inspection Requirements for Reactor Pressure Vessel Heads +, NL-04-005, Supporting Information for License Amendment Request Regarding Indian Point 2 Stretch Power Uprate (TAC Mc 1865) +, NL-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01 +, L 044 +, NL-07039 +, NL 133 +...

P.3(o) +, P.2(o) +, P.3(s) +, S.3(s) +  and S.9(c) +

05000247  +, 05000286  +, 00247  +  and 00286  +

EN-DC-335 +, ENN-DC-150 +, EN-OE-100 +, EN-DC-184 +, EN-DC-319 +, EN-DC-315 +, EN-DC-178 +, EN-QV-109 +, EN-DC-128 +, ENN-DC-315 +, ENN-LI-108 +, ENN-DC-120 +  and EN-OC-184 +

Reactor Trip +  and Turbine Trip +

Dacimo F +  and Entergy +

NRC Generic Letter 2006-03 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +  and NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +

ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +, ML12090A667 +  and ML12090A667 +

LRA B.1.36 +, LRA B.1.24 +, LRA B.1.28 +, LRA B.1.25 +, LRA B.1.27 +, LRA B.1.33 +, LRA B.1.22 +, LRA B.1.23 +, LRA B.1.37 +, LRA B.1.38 +, LRA B.1.29 +, LRA B.1.20 +, LRA B.1.26 +, LRA B.1.41 +, LRA B.1.8 +, LRA B.1.12 +, LRA B.1.14 +, LRA B.1.40 +, LRA B.1.9 +  and LRA B.1.36.2 +

NEI 93-01 +, NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +, NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +

NL-07-153 +, NL-07-138 +, NL-08-057, Amendment 3 to License Renewal Application (LRA) +, NL-08-021, License Renewal Application Amendment 2 +, NL-08-005, Reply to Request for Additional Information Regarding License Renewal Application-(Balance of Plant Systems) +, NL-07-133, Review of the Draft Environmental Impact Statement for SPDES Permits for Bowline Point 1 & 2, Indian Point 2 & 3, and Roseton 1 & 2 Steam Electric Generating Stations, Cover - Enclosure 7a +, NL-07-124, Supplement to License Renewal Application (LRA) +, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application +, NL-07-040, License Renewal Drawing - Page 8 of Drawings List +, NL-07-039, License Renewal Application. Appendix E Figure 2-24 Through Figure 2-29 +, NL-07-041, License Renewal Application Environmental Report References +, NL-05-044, Reactor Vessel Upper Head Inspection Results; Indian Point Unit 3. Spring 2005 Refueling Outage (3R13) +, NL-05-001, Reactor Vessel Upper Head Inspection Results; Indian Point 2. Fall 2004 Refueling Outage (2R16) +, NL-04-090, Indian, Units 2 and 3, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used in Pressurizer Penetrations and Steam Space Piping Connections +, NL-04-069, Stretch Power Uprate License Amendment Request Package, Sections 6.4 Through 11.7 +, NL-04-026, Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Stations 2 and 3, Answer to February 20, 2004 Revised NRC Order Regarding Interim Inspection Requirements for Reactor Pressure Vessel Heads +, NL-04-005, Supporting Information for License Amendment Request Regarding Indian Point 2 Stretch Power Uprate (TAC Mc 1865) +, NL-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01 +, NL-07039 +, NL 133 +  and 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 +

NRC Bulletin 04-01 +, NRC Bulletin 02-01 +, NRC Bulletin 80-11 +, NRC Bulletin 88-09 +, NRC Bulletin 03-02 +  and NRC Bulletin 88-11 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG-6260 +, NUREG/CR-5643 +, NUREG-79 +, NUREG-2015 +, NUREG-1344, Advises That Util 890710 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion &/Or Corrosion Acceptable,Based on Confirmation That Erosion/Corrosion Program Meets or Exceeds App a to NUREG-1344 Requirements +, 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 +

600V +  and 4kV +

AM +, RT +, TOP +  and JF +

Regulatory Guide 1.137 +, Regulatory Guide 1.147 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.99 +

202L-R2 +, 349R-85 +, 2PT-R1 +, 3PT-M051 +, 1P3-05-21329 +, 013NL-07-153 +, 23R-2 +  and 2PT-R156 +

Washington +, New York +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Stator Cooling Water +, Stator Water +, Moisture Separator Reheater +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, Emergency Lighting +, Aging Management +, Design basis earthquake +, Flow Accelerated Corrosion +, Feedwater Heater +, Eddy Current Testing +, Moisture barrier +, Hemyc +, License Renewal +, Earthquake +, Maintenance Rule Program +, Pressure Boundary Leakage +, Fire Protection Program +, Power change +, Power Uprate +, Stretch Power Uprate +, Eddy Current Test +, Thermography +, Thermal fatigue +, Water hammer +...

WCAP-12866 +, WCAP-15666 +, WCAP-12937 +, WCAP-16156 +, WCAP-16211 +, WCAP-12191 +, WCAP-16169 +  and WCAP-13491 +

WCAP-12866 +, WCAP-15666 +, WCAP-12937 +, WCAP-16156 +, WCAP-16211 +, WCAP-12191 +, WCAP-16169 +  and WCAP-13491 +