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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

ANSI B31.1 +, ANSI B16.9 +, ANSI B31.1. 0 +  and ANSI-B96.1 +

ASME Section XI +, ASME Section III +  and ASME Section II +

Carbon +  and Hydrogen +

10 CFR 50 +, 10 CFR 50 Appendix G +  and 10 CFR 50.55a +

ND-3652 +, ND-3600 +, ND-3622 +  and ND-3645 +

05000458  +  and 05000459  +

GULF STATES UTILITIES CO. +  and Booker J +

RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +, RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +  and RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports +

ND-3652 +, ND-3600 +, ND-3622 +  and ND-3645 +

NUREG/CR-1677 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

ES +, CH +, RT +  and TP +

Regulatory Guide 1.26 +, Regulatory Guide 1.43 +, Regulatory Guide 1.50 +, Regulatory Guide 1.20 +  and Regulatory Guide 1.34 +

NEDO-21778 +, NEDO-10029 +, NEDO-21821 +, NEDE-24057 +, NEDO-24057 +  and NEDE-22146 +

3A-2 +, 48C-1 +, 38A-1 +, 42A-1 +, 38B-1 +, 37C-1 +, 38C-1 +, 39C-1 +, 47C-1 +, 38D-1 +, 39D-1 +, 3B-74 +, 79SA9An-SS +, 97D-0 +, C2D-1 +, 10f-11fy +  and 1FWS-PRR-811 +

Texas +, Georgia +, Washington +, California +, Massachusetts +  and New York +

Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Intermediate Range Monitor +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

Office of Nuclear Reactor Regulation +  and Harold Denton +

Safe Shutdown +, Anticipated operational occurrence +, Weld Overlay +, Operating Basis Earthquake +, High Energy Line Break +, Scram Discharge Volume +, Liquid penetrant +  and Flow Induced Vibration +