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Pages with broken file links, TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES

ANSI N18.1-1971 +, ANSI N18.1 -1971 +, ANSI N16.7-1976 +, ANSI N45.2.9-1974 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

Environmental Protection Agency +  and Michigan Department of Environmental Quality +

Iodine +, Uranium +, Carbon +  and Plutonium +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50.36 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1001 +, 10 CFR 20.1003 +, 10 CFR 50.4 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.71 +, 10 CFR 50.120 +, 10 CFR 50.54 +, 10 CFR 50.36a +, 10 CFR 20.407 +, 10 CFR 30.1302 +, 10 CFR 50.55a +, 10 CFR 50.72#10 +, 10 CFR 50.54#q +, 10 CFR 50.54#a +, 10 CFR 50.54#m +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c1iA +, 10 CFR 50.36#c5 +, 10 CFR 50.36#a2 +...

05000155  +  and 00155  +

33 FR 18610 +, 60 FR 36957 +  and 62 FR 63974 +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +, NRC Generic Letter 93-07, Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans +  and NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +

ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +, ML20198K661 +...

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

Tritium +, Iodine-131 +  and Krypton-85 +

ML19196A241 +, ML20196G754 +, ML20199C181 +, ML20198J400 +, ML20248L546 +, IR 05000155/1998007 +, ML20236T665 +, ML20216J441 +  and ML20211P867 +

NUREG-1431 +, NUREG-1433 +, NUREG-0586, Forwards NUREG-0586, Final Generic Environ Impact Statement on Decommissioning of Nuclear Facilities, W/Re to 971113 Request for Info Pertaining to Expected Occupational Doses Associated w/long-term Storage.W/O Encl +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1302, Forwards Matl on CRGR Meeting 180 Re NUREG-1301 & NUREG-1302 & Summary of Discussions of Proposal to Eliminate CRGR Review of Certain Rev to 10CFR50.55a +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Regulatory Guide 1.25 +, Regulatory Guide 1.33 +, Regulatory Guide 1.21 +, Regulatory Guide 1.8 +  and Regulatory Guide 1.88 +

Washington +, Michigan +  and Maine +

Reactor Coolant System +, Feedwater +, Service water +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Core Spray +, Emergency Core Cooling System +, Safety Relief Valve +, Main Condenser +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Safe Shutdown +, Shutdown Margin +, High Radiation Area +, Grab sample +, Offsite Dose Calculation Manual +, Fire Barrier +, Probabilistic Risk Assessment +, Annual Radioactive Effluent Release Report +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Minimum staff +, Fire Protection Program +, Depleted uranium +, Control Room Habitability +  and Spent fuel rack +