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Pages with broken file links, TEXT-SAFETY REPORT  and DECOMMISSIONING PLANS

Cesium +  and Oxygen +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 50.82 +, 10 CFR 73.2 +, 10 CFR 50.59#a2 +, 10 CFR 51.53#b +  and 10 CFR 50.82#a +

Emergency Preparedness +  and Physical Protection +

NRC-1832 +  and L 13 746 +

S.1(s) +  and S.6(u) +

05000322  +  and 00322  +

53 FR 24018 +, 55 FR 31915 +  and 55 FR 12258 +

ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +, ML20114A631 +  and ML20114A631 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 3.819444e-4 d (0.00917 hours, 5.456349e-5 weeks, 1.25565e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00185 d (0.0444 hours, 2.645503e-4 weeks, 6.088e-5 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

Co-60 +, Cs-137 +, Fe-55 +, Ni-63 +, Cf-252 +, C-14 +, Krypton-85 +  and H-3 +

NUREG/CR-2082 +, NUREG/CR-2241 +, NUREG/CR-5512, Submits Comments on NUREG/CR-5512,Vol 2, Residual Radioactive Contamination from Decommissioning - Users Manual,Draft for Review, Per 970203 Request +, NUREG/CR-0672, Forwards NUREG/CR-0672,Addendum 3, Technology,Safety & Costs of Decommissioning Ref BWR Power Station, Estimating Decommission Costs for Plant,Per 880706 Meeting.W/O NUREG/CR-0672,Addendum 3 +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG/CR-0586, Responds to 930427 Request by Forwarding List of Nuclear Power Plants in Us & Decommissioning Status.Interpretations of Safstor Definitions in NUREG/CR-0586 Somewhat Subjective. Assumptions Listed +  and NUREG-0041, Request Addl Info Re Requested Clarifications/Exceptions to NUREG-0041,respiratory Protection Program.Nrc Comments Encl +

AM +  and CP +

Regulatory Guide 1.109 +, Regulatory Guide 8.15 +, Regulatory Guide 1.86 +  and Regulatory Guide 1.159 +

1s-a +, L8NRC-1055 +, L8NRC-1859 +, L8NRC-1874 +, 8NRC-1832 +, 2g2-jl +  and L8NkC-1859 +

Indian Point +, FitzPatrick +  and NPF-82 +

Washington +, South Carolina +  and New York +

Steam Generator +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Reactor Building Closed Loop Cooling +, Steam Jet Air Ejector +, Control rod blade +, Main Condenser +, Control Rod +  and Main Steam +

Non-Destructive Examination +, Offsite Dose Calculation Manual +, Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, Process Control Program +, Earthquake +, Chernobyl +, Fire Protection Program +, Scaffolding +, Exclusive Use +  and Spent fuel rack +