Browse wiki

Iodine +, Uranium +, Carbon +, Oxygen +, Hydrogen +  and Sulfur +

10 CFR 50 Appendix R +, 10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 20.1302 +, 10 CFR 50.4 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix I +, 10 CFR 55.4 +, 10 CFR 50.54 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50.36a +, 10 CFR 20.106 +, 10 CFR 50.55a +, 10 CFR 50.54#m2i +, 10 CFR 50.54#o +, 10 CFR 50.54#p +, 10 CFR 50.54#m2iv +, 10 CFR 50.54#a +, 10 CFR 50.54#k +, 10 CFR 50.54#a3 +...

ML110660285 +, ML071360456 +, ML111751792 +, ML103410243 +, ML052990324 +, ML17324A840 +, ML081230640 +, TSTF-10-07, Transmittal of TSTF-493, Revision 4, Errata, Clarify Application of Setpoint Methodology for LSSS Functions +, ML030760293 +, ML18346A358 +, ML19066A008 +, ML19094A799 +, ML042040164 +, ML031430416 +, ML052930172 +, ML20197G501 +, ML21053A117 +, ML20211N553 +, ML20211N544 +, ML23037A971 +, ML23234A192 +, ML011760502 +  and ML003770220 +

NRC Generic Letter 99-02 +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +

ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +, ML24142A445 +  and ML24142A445 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 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)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

Iodine-131 +  and Tritium +

NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +  and NEI 04-10, E-mail from J. Whited to D. Filchner: Susquehanna Steam Electric Station Acceptance of License Amendment Request Implementation of TSTF-425 (TAC Nos. MF5151 and MF5152) +

NUREG-1433 +, NUREG-0373 +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.163 +, Regulatory Guide 1.52 +, Regulatory Guide 1.33 +, Regulatory Guide 1.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.197 +  and Regulatory Guide 1.129 +

NEDC-31681 +  and NEDO-32991 +

SR-4.6.3.1 +, SR-3.0.3 +, SR-3.0.2 +, SR-3.8.3.3 +, SR-4.7.2.1.c +, SR-4.0.2 +, SR-4.6.1.1 +, SR-4.8.2.1.c +, SR-4.4.6 +, SR-4.8.2.1 +, SR-4.6.1.2.a +  and SR-4.11.1.4 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Control Room Emergency Filtration System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Main Condenser +  and Control Rod +

TS-3.3.2.2 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.3.6.1 +, TS-5.5.9 +, TS-3.3.1.2 +, TS-3.3.2.1 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.8.6 +, TS-5.5.12 +, TS-3.2.3 +, TS-3.4.1 +, TS-5.5.18 +, TS-3.3.6.2 +, TS-3.3.3.1 +, TS-3.3.5.2 +, TS-5.5.11 +, TS-3.2.2 +, TS-2.1.2 +, TS-3.3.8.1 +, TS-3.0.6 +, TS-3.3.8.2 +, TS-3.3.4.2 +, TS-5.5.9.c +, TS-5.5.7 +, TS-3.2.1 +, TS-5.5.15 +, TS-5.5.6 +, TS-3.3.4.1 +...

TSTF-493 +, TSTF-500 +, TSTF-258 +  and TSTF-360 +

Time of Discovery +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Water Inventory Control +, Post Accident Monitoring +, Hydrostatic +, Squib +, Annual Radioactive Effluent Release Report +, Surveillance Frequency Control Program +, Feedwater Heater +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Process Control Program +, Loss of Offsite Power +, Excess Flow Check Valve +, Fire Protection Program +, Power Uprate +  and Pressure Temperature Limits Report +