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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

10 CFR 50 Appendix R +, 10 CFR 50 +  and 10 CFR 50.109 +

NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +  and Szukiewicz A +

ML20154J248 +, ML20154J248 +, ML20154J248 +, ML20154J248 +, ML20154J248 +, ML20154J248 +  and ML20154J248 +

General Electric +  and Westinghouse +

NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG/CR-3568 +, NUREG/CR-4387 +, NUREG/CR-3958 +, NUREG/CR-3058 +, NUREG/CR-4386 +, NUREG/CR-4385 +, NUREG-1216, Safety Evaluation Supporting Amend 16 to License NPF-35 +, NUREG-1032, Draft Reg Guide,Task SI 501-4, Station Blackout. Draft NUREG-1109 & NUREG-1032 Re Regulatory/Backfit Analysis for Resolution of USI A-44 & Evaluation of Station Blackout Accidents at Nuclear Power Plants,Respectively,Encl +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco +, 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-0748, Summarizes Operating Reactors Licensing Actions Summary Revisions to non-computer Originated Pages for NUREG-0748 +, 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 +  and NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +

Illinois +, Maryland +, Washington +, California +, Idaho +, New York +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Emergency Feedwater Initiation and Control +, Main Steam Line +, Main Steam +, Low Pressure Coolant Injection +  and Emergency Feedwater System +

Safe Shutdown +, Probabilistic Risk Assessment +, Abnormal operational transient +, Loss of Offsite Power +, Earthquake +, Commercial Grade +, Backfit +  and Water hammer +