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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

Carbon +, Hydrogen +  and Lead +

10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 61 +  and 10 CFR 61.56 +

Technical Support Center +  and Emergency Operations Facility +

GENERAL ELECTRIC CO. +  and Fox J +

ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +, ML20056G814 +  and ML20056G814 +

NUREG-1433 +, NUREG/CR-4261 +, NUREG/CR-3922 +, NUREG-4933 +, NUREG-4471 +, NUREG-41933 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, 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-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, NUREG-1229, Forwards Revised Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Package Requested to Be Revised to State More Explicitly Proposed Actions Taken by Licensees & by Nrc.Issue Identified as Category 2 Action +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, 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 +  and NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 +

Regulatory Guide 1.27 +, Regulatory Guide 1.8 +, Regulatory Guide 1.142 +, Regulatory Guide 1.13 +  and Regulatory Guide 1.57 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Core Spray +, Residual Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Poslusny C +

Safe Shutdown +, Ultimate heat sink +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Feedwater Heater +, Scram Discharge Volume +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, License Renewal +, Earthquake +, Biofouling +, Water hammer +  and Control Room Habitability +