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Boron +, Nitrogen +, Hydrogen +, Xenon +, Chloride +, Lead +, Aluminum +, Silicon +  and Platinum +

10 CFR 50 Appendix K +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50.54#f +  and 10 CFR 50.62#c1 +

P.6(n) +, P.8(b) +  and P.8(r) +

05000266  +  and 05000301  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 20 +, GDC 15 +, GDC 12 +, GDC 14 +, GDC 11 +, GDC 13 +, GDC 31 +, GDC 25 +, GDC 6 +, GDC 23 +, GDC 29 +, GDC 7 +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +

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 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +

NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +  and NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control +

8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

IEEE 384 +, IEEE 344 +, IEEE 279 +, IEEE 279-1968 +  and IEEE 279a +

NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls +, NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +  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 +

TAC:MB4956 +  and TAC:M86858 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.100 +

2B-04 +, 1B-03 +, 2Y-06 +, 5POST-ACCIDEN +, 1LT-4038 +, 2RM-SPING-21 +, 2RM-SPING-23 +, 2PT-2844 +, 3LIT-1001 +, 3PT-1036 +, 2D-05 +, 2D-01 +, 2G-01 +, 2G-01-AP1 +, 2LT-3932 +  and 2PT-3083 +

Manual Scram +  and Automatic Scram +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Safety Parameter Display System +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Grab sample +, Fire Barrier +, Post Accident Monitoring +, Emergency Lighting +, High Energy Line Break +, Loss of Offsite Power +, Operability Determination +, Earthquake +, Power change +, Core Exit Thermocouple +, Power Uprate +, Measurement Uncertainty Recapture +, Manual Operator Action +  and Control Room Habitability +

WCAP-16983-P +, WCAP-7306 +  and WCAP-10858-P-A +

WCAP-16983-P +, WCAP-7306 +  and WCAP-10858-P-A +