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Manual, Calculation  and Operating Procedures

ANSI N13.10-1974 +, ANSI N45.2.1 +, ANSI N45.2.1-197 +, ANSI/ANS-6.6.1 +, ANSI N45.2.1-1 +  and ANSI N4.5.2.1-1973 +

Boron +, Iodine +, Cesium +, Uranium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Radon +, Zirconium +, Chloride +, Lead +, Lithium +, Fluorine +, Aluminum +, Sulfur +, Mercury +  and Zinc +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1301 +, 10 CFR 20.2203 +, 10 CFR 50 Appendix I +  and 10 CFR 50.36a +

H.3(n) +  and H.3(o) +

Union Electric Co +, Kerrigan J +  and Abernathy J +

ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +, ML041270279 +  and ML041270279 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.0127 d (0.306 hours, 0.00182 weeks, 4.1855e-4 months)  +, 0.00579 d (0.139 hours, 8.267196e-4 weeks, 1.9025e-4 months)  +, 0.00174 d (0.0417 hours, 2.480159e-4 weeks, 5.7075e-5 months)  +, 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

Tritium +, Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Y-90 +, Co-57 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Iodine-131 +, H-3 +, Cd-109 +, Mo-99 +  and Mn-54 +

NUREG/CR-2919 +, NUREG-0543 +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1058, Forwards Rev 1 to NUREG-1058,presenting Tech Specs for Plant at Time Util Received Full Power License,Per T Lang Request. W/O Encl +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +  and NUREG-0324, Forwards Crac Code Input for 790328-0402 at Site.Wind Speeds Corrected to 10 Meter Level Using Procedures Outlined in NUREG-0324 +

MP +  and SP +

Regulatory Guide 1.97 +, Regulatory Guide 1.1 +, Regulatory Guide 1.7 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 1.23 +, Regulatory Guide 1.111 +, Regulatory Guide 1.113 +, Regulatory Guide 4.13 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

1E-6 +, 1E-11 +, 1E-7 +, 1E-9 +, 5E-7 +, 5E-9 +, 4E-7 +, 1E-02 +, 1E-12 +, 5E-8 +, 9E-6 +, 9E-3 +, 7E-2 +, 1E-01 +, 3r-89 +, 51E-9 +  and T3a-140 +

Missouri +  and Washington +

Steam Generator +, Reactor Coolant System +, Residual Heat Removal +  and Emergency Core Cooling System +

TS-3.0.1 +, TS-5.4.1 +, TS-5.5.1 +, TS-6.9.1.6 +, TS-5.5.4 +, TS-6.14 +, TS-5.6.3 +, TS-6.9.1.7 +, TS-5.6.2 +, TS-6.8.4.F +, TS-4.9.4.2 +, TS-6.8.4.E +  and TS-6.8.1.F +

Boric Acid +, Grab sample +, Offsite Dose Calculation Manual +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +, Stress corrosion cracking +, Annual Radiological Effluent Release Report +, Fuel cladding +  and Power change +