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Manual  and Calculation

Strontium +, Iodine +  and Uranium +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 20.1003 +, 10 CFR 20.1302 +, 10 CFR 20.2203 +, 10 CFR 50 Appendix I +, 10 CFR 61.56 +, 10 CFR 50.36a +, 10 CFR 20.2203a#4 +, 10 CFR 20.1301#a +  and 10 CFR 61.56#b +

H.3(n) +, H.3(s) +  and H.3(o) +

05000133  +  and 00133  +

NRC Generic Letter 79-65, Radiological Environmental Monitoring Program Requirements – Enclosing Branch Technical Position, Revision 1 +  and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +

ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +, ML14091A437 +  and ML14091A437 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.861111e-4 d (0.0117 hours, 6.944444e-5 weeks, 1.5981e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 7.75463e-4 d (0.0186 hours, 1.107804e-4 weeks, 2.54935e-5 months)  +

Tritium +, Strontium-90 +, Am-241 +, Co-60 +, Cs-137 +, U-235 +, U-238 +, Sr-90 +, Fe-55 +, Y-90 +, Americium-241 +, Co-57 +, Ni-63 +, C-14 +, Tc-99 +, U-233 +, H-3 +, Th-228 +, Th-230 +, Th-232 +, Pu-238 +  and Pu-239 +

NUREG/CR-4013 +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +  and NUREG-1166, Forwards Fes on Decommissioning of Facility.Comments on Des & Responses to Comments Incorporated in Fes.W/O Fes +

Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.15 +, Regulatory Guide 1.145 +, Regulatory Guide 1.111 +, Regulatory Guide 1.113 +  and Regulatory Guide 4.13 +

SR-2.8.2 +, SR-2.9.2 +, SR-2.11.2 +, SR-2.12.2 +, SR-6.0 +, SR-2.0 +, SR-2.2.2 +, SR-2.4.2 +, SR-2.5.2 +, SR-2.10.2 +, SR-2.13.3 +  and SR-8.0 +

1E-5 +, 1E-2 +, 1x10-4 +, 8E-6 +, 2E-14 +, 1I-1 +, 1xlO-7 +, 1I-29 +  and 1I-41 +

Offsite Dose Calculation Manual +, Annual Radioactive Effluent Release Report +  and Process Control Program +