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TECHNICAL SPECIFICATIONS  and TECHNICAL SPECIFICATIONS & TEST REPORTS

ASME Section XI +  and ASME Section IV +

Uranium +, Oxygen +  and Hydrogen +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 20.1302 +, 10 CFR 20.1601 +, 10 CFR 20.2206 +, 10 CFR 50.4 +, 10 CFR 50.49 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.54#m2i +, 10 CFR 50.36#c2ii +  and 10 CFR 50.71#e +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +

ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +, ML20249B323 +  and ML20249B323 +

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)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Tritium +  and U-235 +

NUREG-0133, Informs That Rev 3 to Offsite Dose Calculation Manual (ODCM) Uses Documented & Approved Methods Consistent W/Methodology & Guidelines in NUREG-0133 & Acceptable.Revised ODCM Containing Simplified Block Diagrams Requested +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Regulatory Guide 1.33 +  and Regulatory Guide 1.8 +

NEDC-31312 +  and NEDC-31852P +

SR-4.8.1.1 +, SR-4.8.2.3 +, SR-3.12 +, SR-3.6 +, SR-3.1 +, SR-3.8 +, SR-4.8.2.2 +, SR-4.8.2.1 +, SR-4.8 +, SR-3.8.2.3 +  and SR-4.8.2.4 +

Reactor Coolant System +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +  and Main Steam +

Shutdown Margin +, Packing leak +, High Radiation Area +, Offsite Dose Calculation Manual +, Scram Discharge Volume +, Annual Radiological Environmental Operating Report +, Fuel cladding +, Pressure Boundary Leakage +, Fire Protection Program +  and Unidentified leakage +