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Report  and Administrative

Strontium +, Iodine +, Cesium +, Uranium +, Krypton +, Xenon +, Molybdenum +, Zirconium +, Lead +, Chromium +, Tellurium +, Barium +  and Cerium +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 2.206 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 52.17 +, 10 CFR 100.11 +, 10 CFR 100.21 +, 10 CFR 50.67#b2iii +, 10 CFR 50.67#64 +, 10 CFR 50.34#a1 +, 10 CFR 50.36#c2ii +, 10 CFR 50.47#a9 +  and 10 CFR 50.46#b +

SECY-98-154 +, SECY-94-302 +  and SECY 98-154 +

H.1(o) +  and H.1(n) +

Regulatory Guide 1.174 +, Regulatory Guide 1.195 +, ML041040063 +, ML053460347 +, ML090960464 +, ML063460464 +, ML100130305 +, ML081770075 +, ML021750625 +, ML063480542 +, ML15238A066 +, ML011860407 +, Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency +, ML083180196 +, ML12332A053 +, ML13031A448 +, NL-07-0894, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Power Sources for the Turbine Building Ventilation System +, ML100130186 +, ML19149A294 +, ML003708141 +, ML19248C647 +, ML20050M894 +, ML17156A603 +, ML992880064 +, ML20093F003 +, ML12005A043 +, ML20150A328 +, ML19094A465 +, ML20140A070 +, ML20241A190 +...

60 FR 42622 +, 87 FR 23891 +, 87 FR 44281 +  and 64 FR 71992 +

NRC/NRR/DRA/ARCB +  and Blumberg W +

ML23243B014 +, ML23243B014 +, ML23243B014 +, ML23243B014 +, ML23243B014 +, ML23243B014 +  and ML23243B014 +

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 0.00223 d (0.0536 hours, 3.191138e-4 weeks, 7.34365e-5 months)  +, 2.199074e-4 d (0.00528 hours, 3.141534e-5 weeks, 7.2295e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

Kr-85 +, I-131 +, Iodine-131 +  and Krypton-85 +

MD 8.4 +, MD 6.4 +  and MD 6.6 +

General Electric +  and Westinghouse +

Information Notice 90-08 +  and Information Notice 88-31 +

NUREG-1431 +, NUREG/CR-5950 +, NUREG/CR-6928 +, NUREG-1430 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG-1940 +, NUREG/CR-7003 +, NUREG/CR-6153 +, NUREG-1560, Forwards Draft NUREG-1560 Public Workshop Summary Rept from Workshop Held on 970407-09 in Austin,Texas.Rept Summarizes Discussions Held During Workshop & Documents All of Presentation Matl Distributed to Workshop by Attendees +, 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-465 +, NUREG/CR-7282, Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radiological Releases +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Paul Clifford +  and Robert Lukes +

Regulatory Guide 1.183 +, Regulatory Guide 1.4 +, Regulatory Guide 1.174 +, Regulatory Guide 1.194 +, Regulatory Guide 1.3 +, Regulatory Guide 1.195 +, Regulatory Guide 1.29 +, Regulatory Guide 1.89 +, Regulatory Guide 1.145 +, Regulatory Guide 1.236 +  and Regulatory Guide 1.249 +

RIS 2006-04, Draft RAI on Meteorology for Full-Scope AST Application +  and RIS 2001-19, Deficiencies in the Documentation of Design Basis Radiological Analyses Submitted in Conjunction with License Amendment Requests +

SECY-98-154 +, SECY-94-302 +  and SECY 98-154 +

1E-4 +  and 1E-6 +

Pennsylvania +, Washington +, Idaho +  and Oregon +

Steam Generator +, Reactor Coolant System +, Secondary containment +, Main Steam Isolation Valve +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Control Room Emergency Filtration System +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.7 +  and TS-3.4.16 +

Shutdown Margin +, Probabilistic Risk Assessment +, FLEX +, Seismically rugged +, Backfit +, Accident Tolerant Fuel +, Power Uprate +  and Control Room Habitability +