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ANSI/ANS-18.1-1984 +, ANSI/ANS-18.1-1999 +, ANSI/ANS-18.1 +, ANSI/ANS-18.1-2016 +  and ANSI/ANS-55.3-1976 +

Strontium +, Iodine +, Cobalt +, Cesium +, Uranium +, Yttrium +, Rubidium +, Krypton +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chlorine +, Technetium +, Molybdenum +, Lead +, Fluorine +, Phosphorus +, Argon +, Zinc +  and Bromine +

Regulatory Guide 1.140 +, ML091910213 +, ML012750471 +, ML081710299 +, ML070320241 +, ML112720411 +, ML070790010 +, ML003740190 +, ML102560187 +, ML102460323 +  and ML102560188 +

Pacific Northwest National Laboratory +, Office of Nuclear Regulatory Research +, John Tomon +, Geelhood K +  and Colameco D +

NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +  and NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +

0.00193 d (0.0464 hours, 2.761243e-4 weeks, 6.35435e-5 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 9.259259e-4 d (0.0222 hours, 1.322751e-4 weeks, 3.044e-5 months)  +

Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Cesium-137 +, Ni-63 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Iodine-131 +, Carbon-14 +, H-3 +, Mo-99 +  and Mn-54 +

NUREG/CR-0140 +, NUREG/BR-0167 +, NUREG/CR-0715 +, NUREG/CR-1629 +, NUREG/CR-4397 +, NUREG/CR-2348 +, NUREG/CR-0143 +, NUREG/CR-0142 +, NUREG/CR-0141 +, NUREG/CR-0724 +, 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/CR-0395 +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +

Richard Clement +, Elijah Dickson +, Zachary Gran +  and John Tomon +

NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +  and NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +

Regulatory Guide 1.112 +  and Regulatory Guide 1.140 +

Tennessee +, Washington +, New York +  and Vermont +

Steam Generator +, Feedwater +, Primary containment +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Condenser +, Main Steam +  and Turbine Gland Sealing System +

Anticipated operational occurrence +, Feedwater Heater +, Fuel cladding +  and Power Uprate +