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

ASTM A48 +  and ASTM A216 +

Boron +, Iodine +, Cesium +, Iron +, Yttrium +, Potassium +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Molybdenum +, Chloride +, Lead +  and Lithium +

10 CFR 50 Appendix B +  and 10 CFR 50 Appendix A +

NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2009-0116, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information +, NRC 2009-0057, Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control +, NRC 2009-0030, License Amendment Request 261, Extended Power Uprate +, NRC 2009-0015, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 +, NRC 2008-0075, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC 2008-0044, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control +

05000266  +, 05000301  +, 00266  +  and 00301  +

EC-12054 +, EC-11690 +, EC-12052 +, EC-273511 +, EC-13506 +, EC-15414 +  and EC-15413 +

ZIRLO +  and Zircaloy +

GDC 38 +, GDC 41 +, GDC 11 +, GDC 30 +, GDC 31 +, GDC 40 +, GDC 28 +, GDC 37 +, GDC 27 +, GDC 52 +, GDC 67 +, GDC 69 +, GDC 68 +, GDC 70 +, GDC 66 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +

ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +, ML16251A158 +  and ML16251A158 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Tritium +, Co-60 +, Cs-137 +, U-235 +, Sr-90 +, Fe-55 +, Cesium-137 +, Y-90 +, Kr-85 +, I-131 +, N-16 +, Mo-99 +, Mn-54 +, Deuterium +, Xe-138 +  and Xe-133 +

DPR-024  +  and DPR-027  +

NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2009-0116, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information +, NRC 2009-0057, Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control +, NRC 2009-0030, License Amendment Request 261, Extended Power Uprate +, NRC 2009-0015, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 +, NRC 2008-0075, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC 2008-0044, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control +

NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  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 +

AOP +  and Emergency Operating Procedure +

TAC:ME0219 +, TAC:ME1081 +, TAC:MF4379 +, TAC:MC1279 +, TAC:MD7864 +  and TAC:MB4630 +

1B-32 +, 1B-04 +, 2B-02 +, 2B-04 +, 2B-03 +, 2B-32 +, 1B-03 +, 1B-42 +, 2B-42 +, 98WE-G-0052 +  and 99WE-G-0043 +

DPR-24 +  and DPR-27 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Control Room Emergency Filtration System +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Room Envelope +, Control Rod +  and Containment Spray +

TS-3.7.11 +, TS-3.7.9 +, TS-3.3.5 +, TS-5.5.18 +, TS-3.7.12 +, TS-3.7.14 +, TS-4.3.1.1 +, TS-4.3 +, TS-4.3.1 +, TS-5.5.10 +  and TS-4.3.1.2 +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Loop seal +, Tornado Missile +, Time to boil +, Hydrostatic +, Zebra Mussel +, Incorporated by reference +, High Energy Line Break +, Surveillance Frequency Control Program +, Design basis earthquake +, Loss of Offsite Power +, License Renewal +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Fuel cladding +, Fire Protection Program +, Power change +, GOTHIC +, Power Uprate +, Overspeed +, Potassium iodide +, Spent fuel rack +, Gas accumulation +, Operational convenience +, Leak-Before-Break +, Pressure locking +...

WCAP-16541-NP +, WCAP-15107-P-A +, WCAP-15105-P-A +  and WCAP-16541-P +

WCAP-16541-NP +, WCAP-15107-P-A +, WCAP-15105-P-A +  and WCAP-16541-P +