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ANSI/ANS-5.1-1979 +  and ANSI/ANS-5.1 1979 +

AR 01688483 +  and AR 01943430 +

Boron +, Strontium +, Iodine +, Cesium +, Uranium +, Rubidium +, Nitrogen +, Carbon +, Xenon +, Zirconium +  and Lead +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +  and 10 CFR 50.46#b +

SECY-83-472 +, NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2011-0086, Clarification/Comments on NRC Safety Evaluation Report, Amendment Nos. 238 (Unit 1) and 242 (Unit 2), Auxiliary Feedwater System Modification +, NRC 2011-0025, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information +, NRC 2009-0027, Response to Request for Additional Information, License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analyses Using ASTRUM +, NRC 2005-0094, Request for Review of Heavy Load Analysis +  and NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM +

05000266  +, 05000301  +  and 00244  +

EC-122 +, EC-196 +, EC-12604 +, EC-153 +, EC-11691 +, EC-281807 +, EC-08109 +, EC-12732 +, EC-112 +, EC-14534 +, EC-3900 +, EC-207 +, EC-402 +, EC-597 +, EC-792 +, EC-348 +  and EC-543 +

Turbine Trip +  and Reactor Trip +

GDC 49 +, GDC 10 +  and GDC 52 +

NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +  and NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis +

1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 7.523148e-4 d (0.0181 hours, 1.074735e-4 weeks, 2.47325e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-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)  +, 6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 0.00644 d (0.154 hours, 9.193122e-4 weeks, 2.11558e-4 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 8.217593e-4 d (0.0197 hours, 1.173942e-4 weeks, 2.70155e-5 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 0.00347 d (0.0833 hours, 4.960317e-4 weeks, 1.1415e-4 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

U-235 +, Kr-85 +  and I-131 +

NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2011-0086, Clarification/Comments on NRC Safety Evaluation Report, Amendment Nos. 238 (Unit 1) and 242 (Unit 2), Auxiliary Feedwater System Modification +, NRC 2011-0025, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information +, NRC 2009-0027, Response to Request for Additional Information, License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analyses Using ASTRUM +, NRC 2005-0094, Request for Review of Heavy Load Analysis +  and NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM +

NUREG/CR-5950 +, NUREG-1774 +, NUREG/CR-2858 +, NUREG/CR-5249 +, NUREG-5950 +, 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/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1839, (2:2) Section 3 - End, Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 & 2 +

4.16KV +  and 4.16kV +

TAC:MA1152 +, TAC:MC7980 +, TAC:MC7650 +, TAC:ME4006 +  and TAC:71062 +

Regulatory Guide 1.183 +, Regulatory Guide 1.25 +, Regulatory Guide 1.194 +, Regulatory Guide 1.70 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.157 +

2oo-a +, 5o-0 +, 19oo-0 +, 60-5o-0 +, 24Fuel-Claddin +, 0Low-Low +, 20Low-Low +, 2I-13 +, 5I-13 +  and 5I-1358 +

Cook +, DPR-24 +  and DPR-27 +

Idaho +, Michigan +  and Wisconsin +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Steam Bypass Control System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Loop seal +, Ultimate heat sink +, Anticipated operational occurrence +, Aging Management +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Deep Dose Equivalent +, Turbine Missile +, Fuel cladding +, Coast down +, GOTHIC +, Power Uprate +, Measurement Uncertainty Recapture +, Overspeed trip +, Overspeed +, Manual Operator Action +, Control Room Habitability +, Diurnal +  and Leak-Before-Break +

WCAP-10698 +, WCAP-12610-P-A +, WCAP-8822 +, WCAP-15029 +, WCAP-10325-P-A +, WCAP-16054-P +, WCAP-11525 +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-8305 +, WCAP-10965 +, WCAP-7908 +, WCAP-10965-P-A +, WCAP-10326-A +, WCAP-8327 +, WCAP-8326 +, WCAP-7907-P-A +, WCAP-7979-P-A +, WCAP-8028-A +, WCAP-8860 +, WCAP-8423 +, WCAP-11397 +, WCAP-11397-P-A +, WCAP-11397-A +, WCAP-16009-P-A +, WCAP-12945-P-A +, WCAP-14882-P-A +, WCAP-14565-P-A +, WCAP-15306-NP-A +...

WCAP-10698 +, WCAP-12610-P-A +, WCAP-8822 +, WCAP-15029 +, WCAP-10325-P-A +, WCAP-16054-P +, WCAP-11525 +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-8305 +, WCAP-10965 +, WCAP-7908 +, WCAP-10965-P-A +, WCAP-10326-A +, WCAP-8327 +, WCAP-8326 +, WCAP-7907-P-A +, WCAP-7979-P-A +, WCAP-8028-A +, WCAP-8860 +, WCAP-8423 +, WCAP-11397 +, WCAP-11397-P-A +, WCAP-11397-A +, WCAP-16009-P-A +, WCAP-12945-P-A +, WCAP-14882-P-A +, WCAP-14565-P-A +, WCAP-15306-NP-A +...