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

Boron +, Iodine +, Uranium +, Nitrogen +, Oxygen +, Hydrogen +, Radon +, Lead +  and Gold +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 20.1301 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 20.1301#d +  and 10 CFR 20.2203#b +

ND 147 +, L 72 +, ND-147 +  and NRC 1405 +

H.4(l) +  and H.3(d) +

SE-6 +, SE-8 +, FE-59 +, FE-55 +, SE-7 +  and FB-148 +

GDC 60 +  and GDC 64 +

ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +, ML20084N354 +  and ML20084N354 +

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)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Cesium-137 +, Y-90 +, Ni-63 +, Kr-85 +, I-131 +, Cu-64 +, Iodine-131 +, C-14 +, H-3 +, Mo-99 +  and Mn-54 +

ND 147 +  and ND-147 +

NUREG-0172 +, NUREG-4133 +, NUREG-4017 +, 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-4683 +, NUREG-4172 +, NUREG-0683, Provides EPA W/Final Suppl 3 to Programmatic EIS Which Addresses Environ Considerations Under Natl Environ Policy Act of 1969 +  and 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 +

ST +  and ES-1 +

Regulatory Guide 1.100 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 1.111 +, Regulatory Guide 1.112 +, Regulatory Guide 1.113 +  and Regulatory Guide 4.13 +

SR-3.1.2.1 +, SR-4.0.1 +, SR-3.1.1.1 +  and SR-3.2.1.1 +

1E-10 +, 1E-11 +, 1E-5 +, 1E-4 +, 2E-8 +, 3E-3 +, 72E-07 +, 20E-09 +, 28E-10 +, 27E-10 +, 33E-08 +, 41E-12 +, 01E-08 +, 2N-65 +, 127E-07 +, 126E-07 +, 42E-12 +, 523E-08 +, 422E-10 +, 1MI-1 +, 66E-12 +, 134E-09 +, 143E-12 +, 6S10-PLN-4200 +, 881tNU4-4200 +, 881MLN-4200 +, 1A4E-09 +, 6A1E-10 +, 2A7E-00 +...

Crane +  and Prairie Island +

Steam Generator +, Decay Heat Removal +  and Control Rod +

TS-3.5.1 +, TS-3.1.2 +, TS-6.9.4 +  and TS-6.7.4.a +

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

Cooling Tower +  and Susquehanna River +