Browse wiki

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 50.36a +, 10 CFR 50.38a +, 10 CFR 20.1301#d +  and 10 CFR 20.2203#b +

ND 147 +, L 39 +, ND-147 +  and NRC 1405 +

05000289  +, 05000320  +  and 00289  +

SE-6 +, SE-8 +, FE-59 +, FE-55 +, SE-7 +, FE-50 +, FE-69 +  and FE-65 +

ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +, ML20137B537 +  and ML20137B537 +

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 +, C-14 +, H-3 +, Mo-99 +, Cs-131 +  and Mn-54 +

ND 147 +  and ND-147 +

NUREG-0172 +, NUREG-4133 +, 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-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 +

RT +  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-3.2.2.1 +, SR-4.0.1 +, SR-3.2.1.1 +  and SR-3.2 +

1E-10 +, 1E-6 +, 1E-11 +, 1E-5 +, 1E-4 +, 1E-7 +, 2E-8 +, 1x10-7 +, 3E-3 +, 1E-S +, 2A3E-07 +, 661ptN-4200 +, 661MLN-4200 +, 9A1E-07 +, 2A6E-07 +, 8J6E-12 +  and G1r-G +

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

TS-3.5.1 +, TS-3.0.1 +, 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 +