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

Boron +, Iodine +, Iron +, Copper +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +  and Aluminum +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +  and 10 CFR 50.49 +

NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2009-0015, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 +  and 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 +

05000266  +  and 05000301  +

GDC 38 +, GDC 41 +, GDC 44 +, GDC 15 +, GDC 16 +, GDC 12 +, GDC 61 +, GDC 60 +, GDC 46 +, GDC 39 +, GDC 45 +, GDC 40 +, GDC 64 +, GDC 62 +, GDC 37 +, GDC 42 +, GDC 43 +, GDC 27 +, GDC 63 +, GDC 52 +, GDC 48 +, GDC 47 +, GDC 58 +, GDC 59 +, GDC 65 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +...

NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +, NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +  and NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T +, NRC 2009-0015, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 +  and 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 +

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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

TP-304 +, SP-66 +  and SP-61 +

TAC:ME0219 +, TAC:ME1081 +, TAC:MD7864 +  and TAC:MC9035 +

Regulatory Guide 1.183 +  and Regulatory Guide 1.97 +

1HS-15Conta +, 1HS-18REMOV +, 1HS-19Incor +, 2HS-21REMOV +, 2HS-22Benea +, 2HS-26SIS +, 2HS-27In +, 2HS-29PZR +, 2HS-31In +, 2HS-32 +, 2HS-33 +, 2HS-34 +, 2HS-35 +, 2HS-36 +, 2HS-37 +, 2HS-38 +, 2HS-39 +, 2HS-40 +, 2HS-41 +, 2R-EB-2-2 +, 2R-EB-2-3 +, 2R-EB-2-6 +, 34kilo-curie +  and 300MS-C +

Ohio +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Boric Acid +, Stroke time +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, High Energy Line Break +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Time Critical Operator Action +, Liquid penetrant +, Power Uprate +, Water hammer +, Gas accumulation +, Leak-Before-Break +  and Leak Before Break +

WCAP-7829 +, WCAP-7153 +  and WCAP-15107-P-A +

WCAP-7829 +, WCAP-7153 +  and WCAP-15107-P-A +