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Environmental Protection Agency +, Department of Homeland Security +, Federal Emergency Management Agency +  and Centers for Disease Control +

Iodine +, Cesium +, Uranium +, Nitrogen +, Carbon +, Hydrogen +, Xenon +, Molybdenum +, Lead +, Ruthenium +, Tellurium +, Barium +, Lanthanum +  and Cerium +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.47 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 100.11 +  and 10 CFR 50.54 +

Emergency Preparedness +  and Initiating Events +

SECY-11-0093 +, SECY-11-0089 +, SECY-08-0036 +  and NRC-2012-0022, Comment (5) of Thomas Gurdziel, on NRC-2012-0022-0005, State-of-the-Art Reactor Consequence Analyses Reports +

05000247  +, 05000286  +  and 00300  +

ML062500078 +  and ML12024A295 +

Technical Support Center +  and Emergency Operations Facility +

51 FR 30028 +  and 51 FR 28044 +

Jason Schaperow +, Ghosh S +, Richard Chang +, NRC/RES/DSA +, Jonathan Barr +, Stutzke M +  and Tinkler C +

ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +, ML12090A794 +  and ML12090A794 +

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)  +, 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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 8.101852e-4 d (0.0194 hours, 1.157407e-4 weeks, 2.6635e-5 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 5.208333e-4 d (0.0125 hours, 7.440476e-5 weeks, 1.71225e-5 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.74537e-4 d (0.0114 hours, 6.779101e-5 weeks, 1.56005e-5 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

Cs-137 +, Cesium-137 +, I-131 +  and Iodine-131 +

General Electric +  and Westinghouse +

NUREG/CR-4550 +, NUREG/CR-4334 +, NUREG-0340 +, NUREG-0917 +, NUREG/BR-0359 +, 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-6953 +, NUREG-1860 +, NUREG/CR-5582 +, NUREG/CR-7008 +, NUREG/CR-5214 +, NUREG-0773 +, NUREG/CR-5942 +, NUREG-6953 +, NUREG/CR-6261 +, NUREG-1738, Yellow Ticket 020010064 - Nuclear Energy Institute Comments on NUREG-1738, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants +, 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-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-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR +, 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-0771, Transcript of 810521 Public Meeting Re Briefing on SECY-81- 240,draft NUREG-0771 & 0772 Re Accident Source Term Assumptions,In Washington,Dc.Pp 1-67.Meeting Outline & Viewgraphs Encl +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +, 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 +, 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) +...

Brian Holian +, Carol Gallagher +, Cindy Bladey +, Jimi Yerokun +, Jason Schaperow +, Scott Burnell +, Richard Chang +, Tina Ghosh +, Thomas Weaver +, Donald Chung +, Jonathan Barr +  and Terry Brock +

Emergency Operating Procedure +  and ISP-46 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.23 +  and Regulatory Guide 3.54 +

SECY-11-0093 +, SECY-11-0089 +  and SECY-08-0036 +

4x10-7 +, 1x10-6 +, 7x10-7 +, 1x10-7 +, 1x10-5 +, 2x10-3 +, 2x10-6 +, 1x10-11 +, 3x10-7 +, 3x10-8 +, 5x10-5 +, 5x10-6 +, 2x10-5 +, 5x10-7 +, 1x10-12 +, 1x10-10 +, 7x10-5 +, 3x10-6 +, 9x10-5 +, 1x10-9 +, 2x10-4 +, 3x10-4 +, 5x10-11 +, 3x10-11 +, 2x10-11 +, 3x10-10 +, 6x10-11 +, 7x10-10 +, 9x10-12 +, 5x10-12 +...

Texas +, Pennsylvania +, Washington +, Massachusetts +, Virginia +, Idaho +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Auxiliary Feed Water +  and Containment Spray +

Reactor Vessel Water Level +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Severe Accident Management Guideline +, License Renewal +, Earthquake +, Hardened vent +, Chernobyl +, Fuel cladding +, Fatality +, Siren +, Power Uprate +, Potassium iodide +  and Diurnal +