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Letter  and Updated Final Safety Analysis Report (UFSAR)

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Xenon +, Chloride +  and Lead +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 50.4 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.36#c2ii +, 10 CFR 50.65#a4 +, 10 CFR 50.59#d +, 10 CFR 50.59#d2 +, 10 CFR 50.59#a2i +, 10 CFR 50.59#a2ii +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g6i +, 10 CFR 50.48#c +, 10 CFR 50.48#a +, 10 CFR 31.5#c +, 10 CFR 31.5#c2ii +, 10 CFR 2.390#d1 +, 10 CFR 2.390#d +, 10 CFR 50.71#e +  and 10 CFR 50.71#e4 +

Initiating Events +  and Mitigating Systems +

RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications +, RA-20-0134, Amendment 63 to Updated Final Safety Analysis Report, Drawings (Redacted) Part 2 of 2 +  and L-11 +

P.6(n) +, P.8(n) +  and P.7(n) +

05000400  +  and 00400  +

Turbine Trip +  and Reactor Trip +

Duke Energy +  and Maza K +

GDC 54 +, GDC 30 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 3, Fire protection +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +  and NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes +

ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +, ML20136A163 +  and ML20136A163 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00181 d (0.0433 hours, 2.579365e-4 weeks, 5.9358e-5 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 9.027778e-4 d (0.0217 hours, 1.289683e-4 weeks, 2.9679e-5 months)  +, 0.00162 d (0.0389 hours, 2.314815e-4 weeks, 5.327e-5 months)  +, 0.00174 d (0.0417 hours, 2.480159e-4 weeks, 5.7075e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 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)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 279 +  and IEEE-450 +

I-131 +  and H-3 +

NEI 99-03 +, NEI 96-07 +, NEI 97-07 +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NUREG-1431 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

RT +  and CP-T +

RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications +  and RA-20-0134, Amendment 63 to Updated Final Safety Analysis Report, Drawings (Redacted) Part 2 of 2 +

Regulatory Guide 1.97 +, Regulatory Guide 1.25 +, Regulatory Guide 1.196 +, Regulatory Guide 1.27 +, Regulatory Guide 1.45 +, Regulatory Guide 1.93 +, Regulatory Guide 1.121 +, Regulatory Guide 1.187 +, Regulatory Guide 1.160 +, Regulatory Guide 1.106 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.129 +

SR-4.7.1.2.1 +, SR-4.0.3 +, SR-4.0.2 +, SR-4.7.6.a +, SR-4.4.4.1 +, SR-4.2.2.2.e +, SR-4.4.5.1 +, SR-4.4.5.2 +, SR-4.4.1.3.4 +, SR-4.2.2.2 +, SR-4.4.6.2.1 +, SR-4.4.4.2 +, SR-4.4.4.3 +, SR-4.2.3.2.b +, SR-4.2.3.2.c +, SR-4.4.4.1.b +, SR-4.7.6.b +, SR-4.7.6.g +, SR-4.7.6.d.1 +, SR-4.2.2.2.c +, SR-4.2.3.2.a +, SR-4.7.6.d.2 +, SR-4.4.4.1.a +  and SR-4.2.2.2.d +

1B-SB +, 1A-SA +, 1A31-SA +, 1B-SA +, 1C-SAB +, 1A-SB +, 1A21-SA +, 1CT-22 +, 438B-4 +, 438B-5 +, 438B-6 +, 439B-4 +, 439B-5 +, 439B-6 +, 1X-SB +, 30A-40A +  and 70A-90A +

Manual Scram +  and Automatic Scram +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Control Room Emergency Filtration System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +  and Containment Spray +

TS-3.0.3 +, TS-3.7.4 +, TS-3.5.2 +, TS-3.8.3.1 +, TS-3.6.2.1 +, TS-3.9.9 +, TS-3.0.4 +, TS-3.6.2.3 +, TS-3.4.5 +, TS-3.4.6.2 +, TS-3.4.8 +, TS-3.4.1.2 +, TS-3.4.6.1 +, TS-3.0.6 +, TS-3.7.13 +, TS-3.4.1.4 +, TS-4.8.1.1 +, TS-3.8.3.2 +, TS-3.4.1.3 +, TS-3.4.1.1 +, TS-3.1.2.4 +, TS-3.4.9.4 +, TS-3.9.4.b +  and TS-6.8.4.n +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Tornado Missile +, Internal Flooding +, Hydrostatic +, Past operability +, Fire impairment +, Nondestructive Examination +, Incorporated by reference +, High Energy Line Break +, Surveillance Frequency Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Offsite Circuit +, Power change +, GOTHIC +, Unidentified leakage +, Overspeed +, Operational leakage +, Water hammer +, Control Room Habitability +, Spent fuel rack +...

WCAP-13632-P-A +  and WCAP-10271 +

WCAP-10271 +  and WCAP-13632-P-A +