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ACI-318 +, ACI-301 +, ACI-214 +  and ACI-349 +

ANSI N45.2.6 +, ANSI N18.1-1971 +, ANSI N18.5-1974 +, ANSI N18.2-1973 +, ANSI N101.6-1972 +, ANSI N101.6 +, ANSI N45.2.13-1976 +, ANSI N45.2.6-1978 +, ANSI N45.2.10-1973 +, ANSI N45.2.9-1974 +, ANSI/ANS-2.2-1988 +  and ANSI/ANS-4.5-180 +

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

Boron +, Uranium +, Copper +, Oxygen +, Hydrogen +, Xenon +, Chlorine +, Chloride +, Lead +, Lithium +, Tungsten +  and Plutonium +

10 CFR 55 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50.44 +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +  and 10 CFR 50.48#c +

ASME Code Case N-640 +, ASME Code Case N-641 +  and ASME Code Case N-411 +

05000413  +, 05000414  +, 00414  +, 00369  +, 00370  +  and 00413  +

Turbine Trip +  and Reactor Trip +

74 FR 40244 +, 72 FR 36737 +, 74 FR 18000 +, 73 FR 7766 +, 74 FR 39349 +, 73 FR 32750 +, 56 FR 36175 +, 46 FR 37579 +  and 74 FR 58324 +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps +  and NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +

ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +, ML20106E902 +  and ML20106E902 +

2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-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)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 0.00377 d (0.0906 hours, 5.390212e-4 weeks, 1.24043e-4 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

IEEE 382 +, IEEE 279 +, IEEE 323-1971 +  and IEEE 344-1971 +

Tritium +, N-16 +  and Deuterium +

ML061360319 +, ML20058H250 +, ML20203D904 +, ML20263K874 +, ML20211C925 +, 05000413/LER-1985-043, :on 850622,manual Reactor Shutdown Initiated Following Automatic Trip of Main Feedwater Pump Turbine 1B Due to Loss of Condenser Vacuum.Caused by Personnel Error. Incident Discussed W/Personnel +, IR 05000413/1981012 +, ML20031F225 +  and IR 05000413/1980003 +

Alternate Source Term +  and License Renewal Application +

Westinghouse +  and General Electric +

NUREG-0623 +, NUREG/CR-2919 +, 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-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-0954, Advises That 860619 Submittal Summarizing Results of Survey Quantifying Insulation in Containment by Type & Location Complies W/Guidance in Generic Ltr 85-22 & Sser 2 (NUREG-0954) +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

TAC:MB3758 +, TAC:MB7014 +  and TAC:M94403 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.25 +, Regulatory Guide 1.27 +, Regulatory Guide 1.1 +, Regulatory Guide 1.163 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.137 +, Regulatory Guide 1.205 +, Regulatory Guide 1.63 +, Regulatory Guide 1.74 +, Regulatory Guide 1.9 +, Regulatory Guide 1.155 +, Regulatory Guide 1.147 +, Regulatory Guide 1.194 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.76 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.33 +, Regulatory Guide 1.49 +, Regulatory Guide 1.121 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.160 +...

NPF-52 +  and NPF-35 +

Georgia +, North Carolina +, California +, Massachusetts +, Virginia +  and South Carolina +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Remote shutdown +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.7.10 +, TS-3.7.11 +, TS-3.9.3 +, TS-5.5.11 +, TS-4.7.1.2 +  and TS-3.7.13 +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Safe Shutdown Earthquake +, Coatings +, Nondestructive Examination +, Incorporated by reference +, Shift Technical Advisor +, Loss of Offsite Power +, VETIP +, Earthquake +, Commercial Grade +, Turbine Missile +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Fire Protection Program +, Core Exit Thermocouple +, Coast down +, Measurement Uncertainty Recapture +, Overspeed +, Loss of condenser vacuum +, Water hammer +, Control Room Habitability +, Basic Component +, Gas accumulation +  and Vendor Equipment Technical Information Program +

WCAP-14040 +, WCAP-10271 +, WCAP-12610-P-A +, WCAP-15440 +, WCAP-9601 +, WCAP-7817 +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-9600 +, WCAP-10444-P-A +, WCAP-10021-P-A +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-8305 +, WCAP-8218-P-A +, WCAP-8219-A +...

WCAP-14040 +, WCAP-10271 +, WCAP-12610-P-A +, WCAP-15440 +, WCAP-9601 +, WCAP-7817 +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-9600 +, WCAP-10444-P-A +, WCAP-10021-P-A +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-8305 +, WCAP-8218-P-A +, WCAP-8219-A +...