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ASME Section III +, ASME Section IX +  and ASME Section VIII +

Boron +, Strontium +, Iodine +, Cesium +, Iron +, Nickel +, Potassium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chlorine +, Molybdenum +, Zirconium +, Chloride +, Lead +, Magnesium +, Aluminum +, Calcium +, Titanium +, Mercury +, Zinc +, Chromium +, Palladium +, Tellurium +, Barium +  and Cerium +

10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.44 +, 10 CFR 50.49 +  and 10 CFR 50.67#i +

GDC 38 +, GDC 41 +, GDC 44 +, GDC 15 +, GDC 16 +, GDC 12 +, GDC 61 +, GDC 60 +, GDC 46 +, GDC 39 +, GDC 45 +, GDC 40 +, GDC 62 +, GDC 37 +, GDC 42 +, GDC 43 +, GDC 52 +, GDC 48 +, GDC 58 +, GDC 59 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 1, Quality standards and records +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 04-02 +, NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety- Related Power-Operated Gate Valves +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +  and NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 323-1974 +  and IEEE 344-1975 +

Tritium +  and Co-60 +

Westinghouse +  and Limitorque +

NEI 02-01 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +

NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

SP +, SP-66 +, SP-61 +  and SP-67 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.7 +  and Regulatory Guide 1.54 +

6A-1 +, 6A-2 +, 6A-3 +, 6A-4 +, 6A-5 +, 6C-1 +, 6C-2 +, 6C-3 +, 6C-4 +, 6C-5 +, 6C-6 +, 6C-7 +, 6C-8 +, 6C-10 +, 6C-11 +, 6C-12 +, 6C-9 +, 6D-1 +, 6D-2 +, 6D-3 +, 6D-4 +, 6D-5 +, 6D-6 +, 6D-7 +  and 77-1C6-QUAEQ-M5 +

Ohio +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Control Rod +, Main Steam +  and Containment Spray +

TS-4.4 +, TS-6.2.5.1 +, TS-6.3.5.1 +, TS-6.5.5.1 +  and TS-6.6.5.1 +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Loop seal +, Mission time +, Hydrostatic +, Coatings +, Stress corrosion cracking +, Integrated leak rate test +, Earthquake +, Power-Operated Valves +, Fuel cladding +, Liquid penetrant +  and Eddy Current Test +

WCAP-16406-P-A +, WCAP-8776 +, WCAP-8587 +, WCAP-7803 +, WCAP-16793-NP +, WCAP-7153 +, WCAP-7198 +, WCAP-16530-NP-A +, WCAP-9003 +, WCAP-16596-NP +, WCAP-8659 +, WCAP-7153A +, WCAP-14495 +, WCAP-16406 +  and WCAP-14542 +

WCAP-16406-P-A +, WCAP-8776 +, WCAP-8587 +, WCAP-7803 +, WCAP-16793-NP +, WCAP-7153 +, WCAP-7198 +, WCAP-16530-NP-A +, WCAP-9003 +, WCAP-16596-NP +, WCAP-8659 +, WCAP-7153A +, WCAP-14495 +, WCAP-16406 +  and WCAP-14542 +