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Report  and Technical

Iodine +, Cesium +, Uranium +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Thorium +, Chloride +, Lead +, Helium +, Lithium +, Fluorine +, Silicon +  and Tin +

10 CFR 50.67 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 52 +, 10 CFR 50.109 +, 10 CFR 50 Appendix E +, 10 CFR 51.30 +, 10 CFR 51.53 +, 10 CFR 100.11 +, 10 CFR 50.160 +  and 10 CFR 50.34#a1iv +

Emergency Preparedness +  and Initiating Events +

Amy Cubbage +  and Office of New Reactors +

ML19093B404 +, ML19093B404 +, ML19093B404 +, ML19093B404 +, ML19093B404 +, ML19093B404 +  and ML19093B404 +

1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 0.00347 d (0.0833 hours, 4.960317e-4 weeks, 1.1415e-4 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.787037e-4 d (0.0139 hours, 8.267196e-5 weeks, 1.9025e-5 months)  +  and 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +

Tritium +  and K-40 +

NUREG/CR-6525 +, NUREG-2161 +, NUREG/CR-7009 +, NUREG/CR-4691 +, NUREG/CR-6244 +, NUREG/CR-7161 +, NUREG/CR-7245, State-of-the-Art Reactor Consequence Analyses (Soarca) Project +, NUREG/CR-6944 +, NUREG/CR-1465 +, NUREG/Cr-6613 +, NUREG/BR-0524 +, NUREG/CR-7107 +, NUREG/CR-2523 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-2206, Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments +, NUREG/CR-6853, Exhibit L - NUREG/CR-6853 - Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model +, NUREG/CR-6613, Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - Users Guide +  and NUREG/CR-7110, Official Exhibit - ENT000457-00-BD01 - NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) +

MP +, ISP +  and TOP +

Regulatory Guide 1.183 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.203 +

1E-11 +, 1E-13 +, 1E-09 +  and 8E-5 +

Washington +, Idaho +  and Oregon +

Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +  and Control Rod +

Anticipated operational occurrence +, Probabilistic Risk Assessment +, License Renewal +, Earthquake +, Uranium Hexafluoride +, Fatality +, Potassium iodide +  and Control Room Habitability +