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Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation  and Technical Specifications

10 CFR 50 +, 10 CFR 70 +, 10 CFR 51 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 70.24 +, 10 CFR 50.69#b1 +, 10 CFR 50.69#d2ii +, 10 CFR 50.69#c1 +, 10 CFR 50.69#e1 +, 10 CFR 50.69#b2i +, 10 CFR 50.69#b2iii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#c +, 10 CFR 50.69#c1i +, 10 CFR 50.69#c1ii +, 10 CFR 50.54#f +, 10 CFR 50.69#c1iii +, 10 CFR 50.69#c1v +, 10 CFR 50.69#c2 +, 10 CFR 50.69#e3 +, 10 CFR 50.59#c1v +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000410  +, 00410  +  and 00220  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML14099A196 +, ML090930246 +, ML15153A660 +, ML070810400 +, ML14153A410 +, ML17079A427 +, ML17086A431 +, ML070650650 +, ML130740943 +, ML14365A203 +, ML061090627 +, ML052900163 +, ML12240A027 +, ML102230049 +, ML092870592 +, ML17062A466 +, ML17031A269 +, NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, ML19330D909 +, NMP2L2729, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components +, NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 +, ML20332A115 +  and NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b +

Marshall M +  and Plant Licensing Branch I +

GDC 50 +, GDC 55 +  and GDC 2, Design bases for protection against natural phenomena +

ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +, ML20332A115 +...

RS-17-070, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations +, NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) +, ML20113F041 +, NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 +  and NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b +

NEI 00-04 +, NEI 16-06 +, NEI 07-12 +, NEI 05-04 +  and NEI 12-13 +

NUREG/CR-6928 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +  and NUREG/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +

Jigar Patel +, Mihaela Biro +, Keith Tetter +  and Zach Coffman +

CAC:MF1104 +, TAC:MF3973 +  and EPID:L-2018-LLA-0482 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.201 +

1E-6 +, 1E-06 +  and 1x10-7 +

Washington +, New York +  and Arkansas +

Service water +, Main Steam Isolation Valve +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +

TS-3.6.1.7 +, TS-3.7.1.C +  and TS-3.7.1.D +

Exelon +  and Rhoades D +

High winds +, Ultimate heat sink +, Mission time +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, Large early release frequency +  and Flooding Focused Evaluation +