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

ANSI N18.1-1971 +  and ANSI/ANS 3.1-1993 +

ASME Section IV +  and ASME Section XI +

Boron +, Iodine +, Uranium +, Krypton +, Oxygen +, Sodium +, Hydrogen +, Xenon +  and Chloride +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 40 +, 10 CFR 51 +, 10 CFR 140 +, 10 CFR 20.1302 +, 10 CFR 50.47 +, 10 CFR 50.82 +, 10 CFR 50.90 +, 10 CFR 73.21 +, 10 CFR 50.36a +, 10 CFR 50.51 +, 10 CFR 50.54#p +, 10 CFR 50.54#0 +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c5 +, 10 CFR 50.36#c4 +, 10 CFR 50.36#c2iiC +, 10 CFR 50.36#c2iiB +, 10 CFR 50.36#c2iiD +, 10 CFR 54.29#a +, 10 CFR 50.65#a4 +, 10 CFR 54.21#d +, 10 CFR 54.21#a1 +...

05000285  +  and 00285  +

Regulatory Guide 1.183 +, ML12326A805 +, LIC-17-0065, Submittal of Response to Request for Additional Information Re Fort Calhoun Request to Revise Their Technical Specifications to Align to Those Requirements for Decommissioning +, ML12346A463 +, ML003734190 +, LIC-17-0001, License Amendment Request (LAR) 17-01; Revised Technical Specifications to Align to Those Requirements for Decommissioning +, ML17165A465 +, ML013030027 +, LIC-16-0074, Certification of Permanent Removal of Fuel from the Reactor Vessel +, LIC-16-0092, License Amendment Request 16-03, Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning +, LIC-16-0043, Certification of Permanent Cessation of Power Operations +, ML082330233 +  and ML18010A087 +

James Kim +  and Special Projects and Process Branch +

ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +, ML18010A087 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

Tritium +  and U-235 +

LIC-17-0065, Submittal of Response to Request for Additional Information Re Fort Calhoun Request to Revise Their Technical Specifications to Align to Those Requirements for Decommissioning +, CAC:MF9567 +, CAC:MF8437 +, LIC-16-0074, Certification of Permanent Removal of Fuel from the Reactor Vessel +, LIC-16-0043, Certification of Permanent Cessation of Power Operations +  and ML13091A387 +

NUREG-1625 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

JF +  and TOP +

CAC:MF9567 +  and TAC:M94789 +

Regulatory Guide 1.183 +, Regulatory Guide 1.33 +, Regulatory Guide 1.182 +  and Regulatory Guide 1.8 +

SR-3.0.1 +, SR-3.0.4 +, SR-3.0.2 +, SR-3.3 +, SR-3.1 +  and SR-3.2 +

Washington +, Missouri +  and Nebraska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6 +, TS-1.1 +, TS-2.0.1 +, TS-2.4 +, TS-3.1 +, TS-2.8.1 +, TS-2.5 +, TS-2.2 +, TS-2.2.1 +, TS-2.1.1 +, TS-3.0 +, TS-3.8 +, TS-2.16 +, TS-2.3 +, TS-2.1.2 +, TS-2.6 +, TS-2.21 +, TS-3.16 +, TS-4.2 +, TS-4.0 +, TS-2.15 +, TS-4.3 +, TS-4.3.1 +, TS-5.0 +, TS-3.5 +, TS-5.4.1 +, TS-3.3 +, TS-1.0 +, TS-2.9 +, TS-3.9 +...

Omaha Public Power District +  and Fisher M +

Boric Acid +, Time of Discovery +, Shutdown Margin +, High Radiation Area +, Offsite Dose Calculation Manual +, Hydrostatic +, Probabilistic Risk Assessment +, Cyber Security +, Locked High Radiation Area +, Missed surveillance +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Safeguards Contingency Plan +, Exemption Request +, Fuel cladding +, Pressure Boundary Leakage +, Fire Protection Program +, Unidentified leakage +, Manual Operator Action +, Potassium iodide +, Control Room Habitability +  and Spent fuel rack +