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ASME Section XI +, ASME Section III +, ASME Section IX +  and ASME Section II +

Boron +, Iodine +, Iron +, Nickel +, Vanadium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Aluminum +, Silicon +, Phosphorus +, Titanium +, Chromium +  and Silver +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50 Appendix G +, 10 CFR 50.55a +, 10 CFR 50.2#V +, 10 CFR 50.55a#g +  and 10 CFR 50 Appendix G#a +

ASME Code Case N-416 +  and ASME Code Case N-416-1 +

L-80-343, Forwards Stress Analysis of Drain & Fill Method for Cooling Reactor & Responses to NRC Re Potential Effects of Rapid RCS Depressurization.No Excessive Stress Levels Occurred During Normal Cooldown +, L-80-431, Forwards Analysis of Natural Circulation Cooldown W/O Upper Head Voiding for St Lucie Unit 1, in Response to NRC 801017 Request for Info Re 800611 Natural Circulation Cooldown Event +, L-88-552, Responds to Generic Ltr 88-17, Loss of Dhr. Plans for Plant Programmed Enhancement Will Be Submitted by 890202. Util Will Use Existing Core Exit Thermocouples When Reactor Vessel Head Installed +, L-84-68 +, L-97-233 +, L-89-38 +  and L 136 +

SE-02-2 +, SE-02-1 +, SE-02-4 +, SE-02-3 +, Drawing 5.1-2 +, FE-2202 +, FE-03-21 +, FE-03-1 +  and FE-03-2 +

Turbine Trip +  and Reactor Trip +

Lisa Regner +  and Plant Licensing Branch II +

GDC 2, Design bases for protection against natural phenomena +, GDC 1, Quality standards and records +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 04-02 +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +, NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +, ML14084A568 +  and ML14084A568 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.375e-4 d (0.0225 hours, 1.339286e-4 weeks, 3.08205e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0.00104 d (0.025 hours, 1.488095e-4 weeks, 3.4245e-5 months)  +, 0.00417 d (0.1 hours, 5.952381e-4 weeks, 1.3698e-4 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +, 0.00132 d (0.0317 hours, 1.884921e-4 weeks, 4.3377e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 9.606481e-4 d (0.0231 hours, 1.372354e-4 weeks, 3.15815e-5 months)  +, 3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

IEEE 279 +  and IEEE 279-1971 +

L-80-343, Forwards Stress Analysis of Drain & Fill Method for Cooling Reactor & Responses to NRC Re Potential Effects of Rapid RCS Depressurization.No Excessive Stress Levels Occurred During Normal Cooldown +, L-80-431, Forwards Analysis of Natural Circulation Cooldown W/O Upper Head Voiding for St Lucie Unit 1, in Response to NRC 801017 Request for Info Re 800611 Natural Circulation Cooldown Event +, L-88-552, Responds to Generic Ltr 88-17, Loss of Dhr. Plans for Plant Programmed Enhancement Will Be Submitted by 890202. Util Will Use Existing Core Exit Thermocouples When Reactor Vessel Head Installed +, L-84-68 +, L-97-233 +, L-89-38 +  and L 136 +

Westinghouse +  and Limitorque +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +

ST +, SP +, RT +, TP +, TOP +  and TP-316 +

ML14084A568 +  and ML14084A568 +

Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.6 +, Regulatory Guide 1.43 +, Regulatory Guide 1.14 +, Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.68 +, Regulatory Guide 1.83 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.36 +, Regulatory Guide 1.71 +, Regulatory Guide 1.85 +, Regulatory Guide 1.66 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

E308L-16 +, F9P4-EG-G +, E309L-16 +, 04W81-1-1 +, 04W24-1-1 +, 04W84-1-1 +, 04W25-1-1 +, 04D358-1-1 +, 04D477-1-1 +, 04W110-1-1 +, 04D593-1-1 +, 04W92-1-1 +, 04W92-1-2 +, 04D518-1-1 +, 04D359-1-1 +, 04D478-1-1 +, 04W111-1-1 +, 04D663-1-1 +, 04W144-1-1 +, 04W144-1-2 +, 04D515-1-1 +  and 5E-6pCilcc +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Packing leak +, Non-Destructive Examination +, Tornado Missile +, Time to boil +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Nondestructive Examination +, Design basis earthquake +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Earthquake +, Power-Operated Valves +, Liquid penetrant +, Pressure Boundary Leakage +, Dissimilar Metal Weld +, DM weld +, Core Exit Thermocouple +, Coast down +, Unidentified leakage +, Unidentified leak +, Power Uprate +, Overspeed +, Loss of condenser vacuum +, Water hammer +...

ER309L +, ER316L +, ER308L +  and ERNiCrFe-7 +