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NUREG  and Draft

Boron +, Strontium +, Iodine +, Cesium +, Uranium +, Nitrogen +, Carbon +, Hydrogen +, Molybdenum +, Zirconium +, Lead +, Ruthenium +, Tin +, Tellurium +, Barium +, Lanthanum +  and Cerium +

Emergency Preparedness +  and Initiating Events +

H.6(f) +  and H.5(f) +

05000277  +  and 05000278  +

ML11118A0620 +, ML12157A466 +  and ML12166A378 +

ENS 2 +, ENS 3 +  and ENS 1 +

Office of Nuclear Regulatory Research +  and Sandia +

ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +, ML13189A145 +  and ML13189A145 +

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 7.75463e-4 d (0.0186 hours, 1.107804e-4 weeks, 2.54935e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.375e-4 d (0.0225 hours, 1.339286e-4 weeks, 3.08205e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +, 6.018519e-4 d (0.0144 hours, 8.597884e-5 weeks, 1.9786e-5 months)  +, 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, I-131 +, Iodine-131 +, C-14 +, Mo-99 +, Pu-238 +  and Pu-239 +

NUREG/CR-6928 +, NUREG/CR-7037 +, NUREG/CR-6545 +, NUREG/CR-4691 +, NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station +, NUREG/CR-5423 +, NUREG/CR-6025 +, NUREG/CR-6119 +, NUREG/CR-6864, Official Exhibit - NRC000068-00-BD01 - NUREG/CR-6864, Vol. 1, Identification and Analysis of Factors Affecting Emergency Evacuations +, NUREG/CR-6981 +, NUREG/CR-6244 +, NUREG/CR-6526 +, NUREG/CR-6953 +, NUREG-1860 +, NUREG/CR-4383 +, NUREG/CR-5582 +, NUREG/CR-5642 +, NUREG-14651 +, NUREG-14653 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, 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-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, NUREG-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +, 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) +

Jason Schaperow +, Richard Chang +  and Tina Ghosh +

Regulatory Guide 1.174 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.1.45 +

1x10-7 +, 2x10-6 +, 5x10-4 +, 3x10-8 +, 9x10-3 +, 6x10-3 +, 5x10-7 +, 3x10-6 +, 2x10-2 +, 8x10-4 +, 2nd-order +, 07-83-254 +, 07-91-127 +, 2M-2 +, 10x10-rn-set +, 10x10-rpv-cvh +, 10x10-rpv-fl +, 46BIn-Vessel +  and 47BEx-Vessel +

Tennessee +, Pennsylvania +, Maryland +, Washington +, New York +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Automatic Depressurization System +, Main Steam Line +  and Safety Relief Valve +

Reactor Vessel Water Level +, Probabilistic Risk Assessment +, Corrosion bonding +, Loss of Offsite Power +, Severe Accident Management Guideline +, Earthquake +, Fuel cladding +, Fatality +, Siren +, Power Uprate +, Diurnal +  and Restart +