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FEDERAL REGISTER NOTICES  and TEXT-CODE OF FEDERAL REGULATIONS

Iodine +  and Chlorine +

10 CFR 50 +, 10 CFR 50.55 +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#a3 +  and 10 CFR 50.55a#g4 +

05000457  +, 00457  +  and 00456  +

Sands S +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 87-14, Operator Licensing Examinations +, NRC Generic Letter 87-13, Integrity of Requalification Examinations at Non-Power Reactors +  and NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +

ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +, ML20149C664 +  and ML20149C664 +

ML20205S356 +, IR 05000456/1987029 +, ML20235H278 +, IR 05000457/1987013 +, 05000456/LER-1987-056, :on 871009,main Control Room Outside Air Intake Radiation Monitor Gas Channel Processed Spurious High Radiation Signal to ESF Causing Recirculation Charcoal to Realign Ventilation Dampers to Emergency Mode +  and 05000456/LER-1986-001-01, :on 861021-1202,inoperable Fire Suppression Sys Led to Imposition of Continuous Fire Watch.Incidents of Inattentiveness,Confusion,Or Miscommunication Among Fire Watch Patrolmen Led to Dismissal or Retraining +

NUREG-1026, Intervenor Exhibit I-1,consisting of Table 5.11 & App F to NUREG-1026, Fes Related to Operation of Braidwood Station, Units 1 & 2, June 1984 +, NUREG-1002, Forwards Sser 4 (NUREG-1002) Re Operation of Facility,For Use.Rept Being Placed in Pdr.W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Regulatory Guide 1.97 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.68 +

2NR-8 +, 2RC-11-05 +, 07-50-45E +  and 25I-02-45 +

Byron +, Braidwood +, NPF-66 +  and NPF-75 +

Illinois +, Maryland +, Washington +  and Virginia +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Safety Parameter Display System +, Residual Heat Removal +, Remote shutdown +, Control Room Envelope +  and Control Rod +

Safe Shutdown +, Incorporated by reference +, Process Control Program +, Turbine Missile +, Fire Protection Program +  and Control Room Habitability +