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ML12339A677 +
10 CFR 50.48 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.4#a3 +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 54.21#d +, 10 CFR 54.21#a3 +, 10 CFR 54.21#c1 + and 10 CFR 54.21#a1 +
CR-IP3-2007-01852 +, CR-IP3-2002-04267 +, LO-IP3LO-2005-00328 +, 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 + and CR-IP2-174-00024 +
COR-05-02835 +, COR-05-02892 +, COR-04-00244 +, COR-05-00530 +, COR-04-00111 +, COR-04-00373 +, COR-05-0530 +, COR-06-00111 +, COR-06-00373 +, COR-04-0244 +, COR-06-001 +, COR-06-00178 +, 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-04-026, 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-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01 +, 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 COR 0244 +
EN-LI-102 +, EN-DC-310 +, ENN-DC-150 +, EN-OE-100 +, EN-LI-121 +, EN-DC-319 +, EN-DC-315 +, EN-DC-178 +, EN-QV-109 +, ENN-DC-121 +, EN-AD-103 +, EN-DC-128 +, ENN-DC-319 +, ENN-DC-334 +, ENN-DC-164 +, ENN-DC-315 + and ENN-LI-108 +
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 + and NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +
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ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 +, ML12339A677 + and ML12339A677 +
March 31, 2012 +
ML071140022 + and ML080840458 +
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01:27:36, 12 January 2025 +
NEI 97-06, Steam Generator Conditioning Monitoring Report +, 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 . + and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +
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-04-026, 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-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01 + 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 +
99 +
95 +
Request +
March 31, 2012 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Reactor Pressure Vessel +, Residual Heat Removal +, Stator Water +, Moisture Separator Reheater +, Main Steam +, Containment Spray + and Extraction steam +
Official Exhibit - NRC000108-00-BD01 - Audit Report for Plant Aging Management Programs and Reviews +
Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Coatings +, Nondestructive Examination +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Eddy Current Testing +, Hemyc +, License Renewal +, Maintenance Rule Program +, Pressure Boundary Leakage +, Fire Protection Program +, Power Uprate +, Stretch Power Uprate +, Thermography + and Thermal fatigue +
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WCAP-12866 +, WCAP-14575-A +, WCAP-12639 +, WCAP-12937 +, WCAP-12191 +, WCAP-16156-P +, WCAP-16211-P +, WCAP-16209-P +, WCAP-16169-P + and WCAP-15859 +