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

Iodine +, Uranium +, Radon +  and Lead +

10 CFR 20 Appendix B +, 10 CFR 50 Appendix I +  and 10 CFR 20.106 Appendix B +

H.3(n) +  and H.3(o) +

05000483  +  and 00483  +

SE-9 +, SE-3 +, SE-11 +, SE-07 +  and SE-7 +

ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +, ML20140G233 +  and ML20140G233 +

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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

Tritium +, Co-60 +, Cs-137 +, U-235 +, U-238 +, Sr-90 +, Fe-55 +, Y-90 +, Ra-223 +, Ac-225 +, Co-57 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Iodine-131 +, U-233 +, H-3 +, Cd-109 +, Mo-99 +, Th-228 +, Th-230 +, Mn-54 +, Pu-238 +, Pu-239 +, Xe-138 +  and Xe-133 +

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-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 +

AM +  and CH +

Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 1.23 +, Regulatory Guide 1.111 +, Regulatory Guide 1.113 +  and Regulatory Guide 4.13 +

1E-10 +, 1E-6 +, 1E-11 +, 1E-5 +, 1E-7 +, 1E-9 +, 2E-9 +, 3E-7 +, 5E-9 +, 3E-06 +, 7E-7 +, 4E-7 +, 1E-12 +, 2E-10 +, 2E-4 +, 3E-10 +, 9E-6 +, 9E-3 +, 4E-10 +, 7E-2 +, 3E-05 +, 5E-02 +, 2n-65 +, 13E-6 +, 230E-07 +, 830E-01 +, 43E-9 +  and 2IE-7 +

Missouri +  and Washington +

Steam Generator +  and Reactor Coolant System +

TS-3.0.3 +, TS-3.0.1 +, TS-3.9.9 +, TS-6.9.2 +, TS-6.8.4.e +, TS-6.9.1.6 +, TS-6.14 +, TS-6.8.4 +, TS-6.9.1.7 +, TS-5.1.4 +, TS-5.1.2 +, TS-1.17 +, TS-6.5.3.1 +, TS-4.9.4.2 +, TS-6.8.4.E +  and TS-6.4.8.e +

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