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

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.46a#b +, 10 CFR 50.69#d2 +, 10 CFR 50.69#e +, 10 CFR 50.69#c1 +, 10 CFR 50.69#b +, 10 CFR 50.69#b2ii +, 10 CFR 50.69#b2iii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#b2 +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#c +, 10 CFR 50.69#c1i +, 10 CFR 50.69#c1ii +, 10 CFR 50.49#iv +, 10 CFR 50.72#viii +, 10 CFR 50.69#c1iii +, 10 CFR 50.69#c1v +, 10 CFR 50.69#c2 +, 10 CFR 50.69#f +, 10 CFR 50.55a#vi +, 10 CFR 51.22#b +, 10 CFR 21#ii +  and 10 CFR 50#x +

05000261  +  and 00261  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML090930246 +, ML083430462 +, ML090970525 +, ML16343A058 +, ML16337A264 +, ML051160213 +, ML16167A444 +, ML17079A427 +, ML17086A431 +, ML14365A203 +, ML061090627 +, ML052900163 +, ML122400044 +, ML102230049 +, ML092870592 +, ML18099A130 +, ML17062A466 +, ML18162A147 +, ML19205A289 +, ML18274A263 +, RA-18-0193, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power +, ML19072A024 +, RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors +  and RNP-RA/15-0090, Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test Interval and +

69 FR 68008 +  and 83 FR 26101 +

Natreon Jordan +  and Plant Licensing Branch II +

ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +, ML19205A289 +...

RA-17-0024, Duke Energy Corp. - Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations +, ML18099A130 +  and RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors +

NEI 00-04 +, NEI 07-12 +, NEI 05-04 +, NEI 12-13 +  and NEI 0-04 +

NUREG-1792 +, NUREG-2180, Enclosure, NRC Response to NEI Concerns Dated July 28, 2016, Regarding Tabletop Pilot Results Using NUREG-2180 +  and 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 +

EPID:L-2018-LLA-0095 +, EPID:L-2018-LLA-0104 +, TAC:MD5250 +  and TAC:M83688 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.201 +  and Regulatory Guide 1.17 +

Washington +, South Carolina +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Shutdown Cooling +  and Decay Heat Removal +

TS-5.5.16 +, TS-5.5.17.c +  and TS-5.5.17.d +

Duke Energy +  and Kapopoulos E +

Safe Shutdown +, High winds +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, Large early release frequency +, Loss of Offsite Power +  and Integrated leak rate test +