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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Boron +  and Lead +

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

Turbine Trip +  and Reactor Trip +

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

ML20154J326 +, ML20154J326 +, ML20154J326 +, ML20154J326 +, ML20154J326 +, ML20154J326 +  and ML20154J326 +

General Electric +  and Westinghouse +

NUREG/CR-4387 +, NUREG/CR-3958 +, NUREG/CR-4326 +, NUREG/CR-4047 +, NUREG/CR-4262 +, NUREG/CR-4265 +, NUREG/CR-4386 +, NUREG/CR-4385 +, NUREG/CR-3991 +, NUREG/CR-4449 +, NUREG/CR-4758 +, NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-1177, Advises That Facility May Resume Power Operations Based on Operational Readiness of Plant & 850910 & 861210 Responses to NRC Concerns.Changes in Organizational Structure Subj to NRC Approval +, 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-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-0153, NRC Staff Response to ASLB Questions Concerning Generic Safety Issues.Conclusions in Perkins SER Re Issuance of Const Permits Will Not Be Affected by Results of Generic Tasks.W/Certificate of Svc.Supporting Documents Encl +, NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +, 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 +, NUREG-1070, 07-18-84 ACRS Report on NUREG-1070, NRC Policy on Future Reactor Designs - Decisions on Severe Accident Issues +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

7E-6 +, 4E-4 +, 6E-3 +, 9E-6 +, 3E-3 +, 9E-3 +, 2E-8tt +, 4E-Stt +  and 9E-6t +

Tennessee +, Maryland +, Washington +, California +, Idaho +, New York +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Core Spray +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, Probabilistic Risk Assessment +, Abnormal operational transient +, Earthquake +, Commercial Grade +  and Manual Operator Action +