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Environmental Protection Agency +, Virginia Department of Health +, Office of Emergency Management +  and American Society of Civil Engineers +

Iodine +, Cesium +, Uranium +, Iron +, Rubidium +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Cadmium +, Molybdenum +, Zirconium +, Indium +, Lead +, Ruthenium +, Silver +, Tin +, Tellurium +, Barium +, Lanthanum +  and Cerium +

10 CFR 50 +, 10 CFR 50.54 +, 10 CFR 50.47 Appendix E +  and 10 CFR 50.54 Appendix E +

Emergency Preparedness +  and Initiating Events +

05000247  +  and 05000286  +

Technical Support Center +  and Emergency Operations Facility +

EC-151 +, EC-125 +, EC-111 +, EC-165 +, EC-136 +  and EC-179 +

Office of Nuclear Regulatory Research +  and Sandia +

ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +, ML12090A797 +  and ML12090A797 +

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 7.638889e-4 d (0.0183 hours, 1.09127e-4 weeks, 2.5113e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 5.324074e-4 d (0.0128 hours, 7.60582e-5 weeks, 1.7503e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.680556e-4 d (0.0208 hours, 1.240079e-4 weeks, 2.85375e-5 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 4.976852e-4 d (0.0119 hours, 7.109788e-5 weeks, 1.63615e-5 months)  +, 3.240741e-4 d (0.00778 hours, 4.62963e-5 weeks, 1.0654e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.597222e-4 d (0.0158 hours, 9.424603e-5 weeks, 2.16885e-5 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +...

Am-241 +, Co-60 +, Cs-137 +, U-235 +, Sr-90 +, Cesium-137 +, Y-90 +, Kr-85 +, I-131 +, Iodine-131 +, C-14 +, Tc-99 +, Mo-99 +, Pu-238 +  and Pu-239 +

General Electric +  and Westinghouse +

NUREG/CR-2726 +, NUREG/CR-4334 +, NUREG/CR-6863, Official Exhibit - NYS000406-00-BD01 - NUREG/CR-6863, Development of Evacuation Time Estimate Studies for Nuclear Power Plants (January 2005) Excerpted: Pp. Inside Cover, III, and 5-6 +, NUREG/CR-6906 +, NUREG-0917 +, NUREG/CR-6119 +, NUREG/CR-6244 +, NUREG/CR-6953 +, NUREG/CR-6285 +, NUREG/CR-7008 +, NUREG-1781 +, NUREG-1788 +, NUREG/CR-5214 +, NUREG/CR-6995 +, NUREG/CR-5121 +, NUREG/CR-6075 +, NUREG/CR-5671 +, NUREG/CR-6131 +, NUREG/CR-6810 +, NUREG/CR-4913 +, NUREG/CR-6678 +, NUREG/CP-0153 +, 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/CR-7002, Rev. 1 Criteria for Development of Evacuation Time Estimate Studies +, NUREG-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +, 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-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +, NUREG/CR-6613, Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - Users Guide +...

Pamela Longmire +, Ata Istar +, Jason Schaperow +, Richard Chang +  and Terry Brock +

AM +, Emergency Operating Procedure +, Emergency Plan +, ES-1 +, ES-2 +  and ES-3 +

Regulatory Guide 1.174 +, Regulatory Guide 1.23 +  and Regulatory Guide 1.83 +

4x10-7 +, 1x10-6 +, 7x10-7 +, 1x10-7 +, 1x10-8 +, 1x10-4 +, 1x10-5 +, 2x10-3 +, 2x10-6 +, 3x10-7 +, 3x10-8 +, 5x10-5 +, 2x10-5 +, 5x10-7 +, 5x10-8 +, 1x10-10 +, 7x10-5 +, 3x10-6 +, 9x10-5 +, 4x10-6 +, 8x10-7 +, 2x10-4 +, 3x10-4 +, 2x10-11 +, 3x10-10 +, 6x10-11 +, 7x10-10 +, 9x10-12 +  and 600g-840g +

Pennsylvania +, Washington +, Virginia +, Idaho +, New York +, New Mexico +  and Oregon +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Emergency Response Data System +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +

Boric Acid +, Reactor Vessel Water Level +, Loop seal +, Ultimate heat sink +, Mission time +, Internal Flooding +, Hydrostatic +, Probabilistic Risk Assessment +, Finite Element Analysis +, B.5.b +, Fukushima Dai-Ichi +, Large early release frequency +, Loss of Offsite Power +, Severe Accident Management Guideline +, Earthquake +, Fuel cladding +, Fatality +, Siren +, Power Uprate +, Potassium iodide +  and Spill +