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Manual  and Calculation

ANSI N13.1-1969 +  and ANSI N13.10-1974 +

ASME Section IV +  and ASME Section III +

Iodine +, Uranium +, Carbon +, Hydrogen +, Radon +, Lead +  and Plutonium +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1001 +, 10 CFR 72 +, 10 CFR 61 +, 10 CFR 20.1301 +, 10 CFR 50 Appendix I +, 10 CFR 72.104 +, 10 CFR 72.212 +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 20.1301#d +, 10 CFR 20.1301#a1 +, 10 CFR 20.1301#a +, 10 CFR 20.1301#e +, 10 CFR 20#25 +, 10 CFR 20.1302#b2 +  and 10 CFR 20.2203#a4 +

H.3(s) +  and H.3(j) +

05000454  +  and 05000455  +

Drawing 11.2-15 +  and Drawing 11.2-17 +

EC-378382 +  and EC-378383 +

NRC Generic Letter 79-41, Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard +  and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +

ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +, ML13161A202 +  and ML13161A202 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

Tritium +, Sr-85 +, Am-241 +, Co-60 +, Cs-137 +, U-238 +, Sr-90 +, Fe-55 +, Cesium-137 +, Y-90 +, Rb-84 +, Ra-226 +, Co-57 +, Ni-63 +, Kr-85 +, K-40 +, Cu-64 +, N-16 +, Iodine-131 +, C-14 +, Carbon-14 +, H-3 +, Mo-99 +, Th-232 +  and Mn-54 +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG/CR-2919 +, NUREG-0172 +, NUREG-0543 +, NUREG/CR-4007 +, NUREG/CR-3332 +, NUREG-0002 +, NUREG-4013 +, NUREG-01 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, 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 Guidance +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0348, Responds to Re Rural & Urban Characteristics of Proposed & Existing Nuclear Power Plants.Data Re Plant Site Characteristics & Current Licensing Status Contained in NUREG-0348 & NUREG-0380 +  and NUREG-0511, Forwards NUREG-0511, Draft Generic EIS on U Milling & Fr Notice.Rept Withheld (Ref 10CFR2.790) +

Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.1 +, Regulatory Guide 4.15 +, Regulatory Guide 4.8 +, Regulatory Guide 1.23 +, Regulatory Guide 8.29 +, Regulatory Guide 1.111 +, Regulatory Guide 1.112 +, Regulatory Guide 4.2 +  and Regulatory Guide 1.113 +

1E-07 +, 1E-02 +, 1E-05 +, 2E-4 +, 1E-01 +, 7E-02 +, 1RE-AR011 +, 12E-02 +, 1RE-PR028 +, 2RE-PR028 +, 2RE-PR027 +, 2RE-PR009 +, 1RE-PR002 +, 1RE-PR003 +, 16E-02 +, 1E-20 +, 6E-12 +, 1OE-09 +, 00E-08 +, 2RE-PR030 +, 2RE-PROO2 +, 2RE-PRO03 +, 2RE-PRO09 +, 1RE-PRO01 +, 2RE-PRO01 +, 2RE-AR01 +, 1RE-PRO02 +, 2RE-PRO02 +, 1RE-AR012 +, 2E-PRO1 +...

Illinois +, Idaho +  and Oregon +

Steam Generator +, Reactor Coolant System +, Service water +  and HVAC +

Grab sample +, Offsite Dose Calculation Manual +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +, Deep Dose Equivalent +  and Power Uprate +