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Letter  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ANSI N18.1-1971 +  and ANSI 3.1 +

Boron +, Iodine +, Uranium +  and Xenon +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 20.1001 +, 10 CFR 60 +, 10 CFR 20.1302 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix I +, 10 CFR 55.4 +, 10 CFR 50.36a +, 10 CFR 20.106 +, 10 CFR 3 +, 10 CFR 60.36a +, 10 CFR 60 Appendix I +, 10 CFR 60.54#o +, 10 CFR 201302 +, 10 CFR 50.73#a2 +, 10 CFR 50.54#m2i +, 10 CFR 50.54#o +, 10 CFR 50.54#k +, 10 CFR 50.54#m +, 10 CFR 50.54#m2iii +, 10 CFR 50.36#c1iA +, 10 CFR 50.36#c +...

05000250  +, 05000251  +, 00250  +  and 00251  +

Jones T +  and NextEra Energy +

NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +  and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +

ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +, ML050250313 +  and ML050250313 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +  and 0.00608 d (0.146 hours, 8.680556e-4 weeks, 1.997625e-4 months)  +

Tritium +, U-235 +  and Iodine-131 +

ML020990345 +  and 05000251/LER-1987-012, :on 870705,component Cooling Water (CCW) Pump Auto Started During Engineered Safeguards Integrated Test Due to Low Header Pressure Upon Increased CCW Flow. Integrated Test Revised +

NEI 9-011 +  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 +

NUREG-1431 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +  and NUREG-1366, Amends 170 & 152 to Licenses NPF-9 & NPF-17,respectively, Incorporating Guidance & Recommendations for Diesel Generators Contained in NUREG-1366,GL 93-05,Gl 94-01 & NUREG-1431 +

Regulatory Guide 1.8 +  and Regulatory Guide 1.163 +

SR-3.7.5.2 +, SR-4.7.1.2.1 +, SR-3.0.2 +, SR-4.1.3.1.1 +, SR-4.3.1.1 +, SR-3.4.9.2 +, SR-4.4.3.1 +, SR-4.2.4.1 +  and SR-4.4.3.2 +

Automatic Scram +  and Manual Scram +

DPR-3 +  and Saxton +

Texas +, Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Line +, Control Rod +, Auxiliary Feed Water +  and Containment Spray +

TS-3.7.5 +, TS-3.2.3 +, TS-3.1.3.1 +, TS-3.7.1.2 +, TS-3.3.1 +, TS-3.1.4 +, TS-3.7.1.1 +, TS-3.2.2 +, TS-5.3 +, TS-3.9.8.2 +, TS-5.6.4 +, TS-5.5.2 +, TS-3.2.4 +, TS-3.2.1 +, TS-5.2 +, TS-3.9.6 +, TS-2.1 +, TS-5.7 +, TS-5.3.1 +, TS-5.5.4 +, TS-6.7 +, TS-5.2.2 +  and TS-6.8.4.f +

TSTF-361 +, TSTF-258 +, TSTF-299 +, TSTF-5 +, TSTF-308 +, TSTF-95 +, TSTF-101 +  and TSTF-93 +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Shutdown Margin +, High Radiation Area +, Offsite Dose Calculation Manual +, Time to boil +, Annual Radioactive Effluent Release Report +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Process Control Program +  and Pressure Boundary Leakage +