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Boron +, Iodine +, Cobalt +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Lithium +, Zinc +  and Plutonium +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 71 +, 10 CFR 20.1302 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +  and 10 CFR 20.101 +

RS-26-69 +, RS-26-90 +, RS-26-70 +, RS-26-13 +, RS-26-14 +  and L-2023-109, Amendment 28 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +

FE-59 +, FE-55 +  and Drawing 11.5-2 +

EC-282514 +  and EC-278372 +

GDC 60 +, GDC 64 +, GDC 63 +  and GDC 19, Control room +

ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +, ML23254A174 +  and ML23254A174 +

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 0.00539 d (0.129 hours, 7.705026e-4 weeks, 1.77313e-4 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +  and 0.00132 d (0.0317 hours, 1.884921e-4 weeks, 4.3377e-5 months)  +

Tritium +, Co-60 +, Cs-137 +, U-235 +, U-238 +, Sr-90 +, Fe-55 +, Y-90 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Nitrogen-16 +, C-14 +, Carbon-14 +, H-3 +, Mo-99 +, Mn-54 +, Deuterium +, Pu-239 +, N16 +, Xe-138 +  and Xe-133 +

NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

ST +  and CP +

RS-26-69 +, RS-26-90 +, RS-26-70 +, RS-26-13 +  and RS-26-14 +

Regulatory Guide 1.183 +, Regulatory Guide 1.143 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.15 +  and Regulatory Guide 8.8 +

12E-06 +, 5x10-5Ci +, 4x10-6Ci +, 3x10-7Ci +, 1x10-7Ci +, 5x10-7Ci +, 5x10-6Ci +, 1x10-6Ci +, 1x10-5Ci +, 1x10-3Ci +  and 1x10-1Ci +

Connecticut +, Florida +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Shutdown Cooling +, Steam Jet Air Ejector +, Main Steam Line +, Main Condenser +, Main Steam +  and Turbine Gland Sealing System +

Boric Acid +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Annual Radioactive Effluent Release Report +, Process Control Program +, Annual Radiological Effluent Release Report +, Fuel cladding +, Pressure Boundary Leakage +, GOTHIC +, Power Uprate +  and Spill +