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Updated Final Safety Analysis Report (UFSAR)  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ASME Section II +  and ASME Section XI +

Iodine +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Lead +, Aluminum +  and Zinc +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 100 Appendix A +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g5 +, 10 CFR 50.55a#f +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#f4 +  and 10 CFR 50.55a#f5 +

05000275  +, 05000323  +  and 00323  +

GDC 38 +, GDC 41 +, GDC 49 +, GDC 15 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 56 +, GDC 21 +, GDC 11 +, GDC 37 +, GDC 42 +, GDC 70 +, GDC 65 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 3, Fire protection +

NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +, DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +  and DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 +

NUREG/CR-5966 +, NUREG/CR-5732 +, 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-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.194 +, Regulatory Guide 1.7 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.111 +

95th-percent +, 63E-05 +, 20E-04 +, 24E-03 +, 99E-05 +, 43E-04 +, 86E-04 +, 99E-04 +, 8E-04 +, 12E-04 +, 55E-03 +, 22E-03 +, 98E-03 +, 40E-03 +, 25E-04 +, 88E-04 +, 07E-03 +, 59E-04 +, 47E-04 +, 29E-04 +, 39E-02 +, 17E-04 +, 15E-04 +, 10E-05 +, 61E-04 +, 86E-M4 +, 526E-05 +, 43E-n +, 296E-04 +, A42E-04 +...

Steam Generator +, Reactor Coolant System +, Feedwater +, HVAC +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Non-Destructive Examination +, Grab sample +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Incorporated by reference +, Design basis earthquake +, Stress corrosion cracking +, Earthquake +, Exclusive Use +  and Gas accumulation +

WCAP-8776 +, WCAP-8264-P-A +, WCAP-8312-A +, WCAP-7977 +, WCAP-8077 +, WCAP-8078 +  and WCAP-7548 +

WCAP-8776 +, WCAP-8264-P-A +, WCAP-8312-A +, WCAP-7977 +, WCAP-8077 +, WCAP-8078 +  and WCAP-7548 +