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Letter  and Request for Additional Information (RAI)

IWB-3640 +, IWB-2420 +, IWB-3242 +, IWA-3300 +  and IWA-4310 +

ASME Section III +  and ASME Section XI +

10 CFR 50.55a +, 10 CFR 54.3#a +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#c +  and 10 CFR 50.55a#3i +

LD-83-053, Forwards Basis for Design of Plant W/O Pipe Whip Restraints for RCS Main Loop Piping, to Demonstrate That guillotine-type Failure of RCS Main Loop Piping Need Not Be Considered in Design Basis for Sys 80 +  and LD-83-108, Forwards Responses to NRC Comments on Leak Before Break Evaluation of Main Loop Piping of C-E RCS, Per 831026 Meeting & 830614 Submittal.Max Seismic Moment Has No Impact on Loading of Axial Slot in Elbow +

05000528  +, 05000529  +, 05000530  +, 00528  +, 00529  +  and 00530  +

ML053130275 +, ML043130170 +, ML042010289 +, ML013650419 +, ML041750296 +, ML042450041 +  and ML051890145 +

Arizona Public Service +  and Hesser J +

ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +, ML100680518 +  and ML100680518 +

NRC Inspection Manual 3778 +, NRC Inspection Manual 3779 +, NRC Inspection Manual 360 +, NRC Inspection Manual 3607 +  and NRC Inspection Manual 3608 +

LD-83-053, Forwards Basis for Design of Plant W/O Pipe Whip Restraints for RCS Main Loop Piping, to Demonstrate That guillotine-type Failure of RCS Main Loop Piping Need Not Be Considered in Design Basis for Sys 80 +  and LD-83-108, Forwards Responses to NRC Comments on Leak Before Break Evaluation of Main Loop Piping of C-E RCS, Per 831026 Meeting & 830614 Submittal.Max Seismic Moment Has No Impact on Loading of Axial Slot in Elbow +

ML093290298 +, ML17298A729 +  and ML17298A409 +

NUREG/CR-6260 +, NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

Palo Verde +, NPF-51 +  and NPF-74 +

Texas +, Arizona +  and Washington +

Steam Generator +, Reactor Coolant System +  and Shutdown Cooling +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Weld Overlay +, Nondestructive Examination +, VT-2 +, Incorporated by reference +, Aging Management +, Stress corrosion cracking +, License Renewal +, Through-Wall Leak +, Power Uprate +, Thermal fatigue +, Leak-Before-Break +  and Leak Before Break +