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TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST/INSPECTION/OPERATING PROCEDURES

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

Iodine +, Uranium +, Oxygen +, Hydrogen +, Radon +  and Plutonium +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1301 +, 10 CFR 20.1302 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 20.1301#d +, 10 CFR 20.1301#a1 +, 10 CFR 20.1302#b1 +  and 10 CFR 20.1302#b2 +

Ra-226 +, L-206 +, ND 147 +, ND-149 +, ND-97 +, PM 149 +, PM-145 +  and PM 148 +

05000010  +, 05000237  +, 05000249  +, 05000254  +, 05000265  +, 05000295  +, 05000304  +, 05000373  +, 05000374  +, 05000454  +, 05000455  +, 05000456  +, 05000457  +, 00237  +, 00249  +, 00254  +, 00265  +, 00295  +, 00304  +, 00373  +, 00374  +, 00454  +, 00455  +, 00456  +  and 00457  +

SE-4 +, FE-59 +, FE-55 +, SE-75 +, FE-52 +  and SE-73 +

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 +

ML20211C331 +, ML20211C331 +, ML20211C331 +, ML20211C331 +, ML20211C331 +, ML20211C331 +, ML20211C331 +, ML20211C331 +  and ML20211C331 +

0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Tritium +, Sr-85 +, Strontium-90 +, Am-241 +, Co-60 +, Cs-137 +, U-238 +, Sr-90 +, Fe-55 +, Cesium-137 +, Y-90 +, Rb-84 +, Lu-177 +, Ra-226 +, Co-57 +, Ni-63 +, Kr-85 +, K-40 +, Cu-64 +, N-16 +, Nitrogen-16 +, C-14 +, Carbon-14 +, H-3 +, Cd-109 +, Mo-99 +, Th-232 +, In-111 +  and Mn-54 +

ND 147 +, ND-149 +  and ND-97 +

NUREG/CR-2919 +, NUREG-0172 +, NUREG-0543 +, NUREG/CR-3332 +, NUREG-0002 +, 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 Guidance +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, 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) +

PM 149 +, PM-145 +  and PM 148 +

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 +

2E-4 +, 4E-10 +, 20E-10 +, 0E-01 +, 53E-09 +, 80E-09 +, 40E-11 +, 07E-10 +, 89E-09 +, 91E-10 +, 00E-09 +, 60E-10 +, 94E-10 +, 33E-10 +, 59E-10 +, 40E-09 +, 48E-09 +, 00E-08 +, 535E-10 +, 814E-12 +, 92E-9 +, 155E-9 +  and 50E-9 +

Dresden +, Byron +, Braidwood +, Quad Cities +, Zion +  and LaSalle +

Illinois +, Washington +  and Idaho +

Steam Generator +, Service water +  and Main Steam Line +

Offsite Dose Calculation Manual +, B.5.b +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +  and Deep Dose Equivalent +

Cooling Tower +, Mississippi River +  and Lake Michigan +