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Oxygen +, Hydrogen +  and Lead +

ML041340009 +, ML18243A521 +, ML18247A003 +, ML18352A703 +, ML20078L336 +, ML062920249 +, ML11171A411 +, ML13206A152 +  and ML19352E278 +

51 FR 28044 +  and 64 FR 38557 +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0308 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609 Appendix G +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0609/Appendix A +

NUREG/CR-6595 +, NUREG/CR-4330 +, NUREG-2195 +, NUREG/CR-1493 +, 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/CR-5432, Forwards Draft NUREG/CR-5432, Scoping Study of Potential Impacts of Inadvertent Fire Suppression Sys Actuations in Commercial Nuclear Power Plants, for Comment +, NUREG-1765, NSP000017-Revised Testimony of Steven Skoyen-NUREG-1765 Excerpts +  and NUREG/CR-6427, Information Provided by Duke Corp Related to Severe Energy Accident Mitigation Alternatives in Its License Renewal Application for the McGuire Nuclear Station, Units 1 & 2 +

Regulatory Guide 1.174 +  and Regulatory Guide 1.160 +

1E-6 +, 1E-7 +, 3E-6 +, 3E-5 +, 2E-7 +, 9E-7 +, 4E-8 +, 8E-7 +  and 1x10-X +

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

Loop seal +, Probabilistic Risk Assessment +, Significance Determination Process +, Large early release frequency +, Loss of Offsite Power +  and Fatality +