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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 4.1, Purpose and Scope +, 10 CFR 50.49 +  and 10 CFR 50.52 +

00275  +, 00323  +  and 00286  +

NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +  and Thatcher D +

ML20245K735 +, ML20245K735 +, ML20245K735 +, ML20245K735 +, ML20245K735 +, ML20245K735 +, ML20245K735 +  and ML20245K735 +

Information Notice 83-44 +, Information Notice 83-41 +, Information Notice 85-85 +  and Information Notice 87-14 +

NUREG/CR-2300 +, NUREG/CR-4261 +, NUREG/CR-3922 +, NUREG/CR-4470 +, NUREG/CR-4207 +, NUREG/CR-4179 +, NUREG/CR-4306 +, 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-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0824, Safety Evaluation Concluding Util 831228,840111 & 0202 Responses to NUREG-0824,Section 4.12 Re Design Codes,Design Criteria & Loading Combinations Complete Except for Listed Issues Requiring Resolution +, 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/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, 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-0572, Response in Support of Jf Doherty Contention 46 Re Control Rods Leading to Fuel Damage.Contention Involves New Info Appearing in ACRS Review of LERs 1976-78 rept,NUREG-0572. Certificate of Svc 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 +, 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 +

Maryland +, Washington +  and New York +

Steam Generator +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Decay Heat Removal +  and Safety Relief Valve +

Safe Shutdown +, Internal Flooding +, Probabilistic Risk Assessment +, Scram Discharge Volume +  and Earthquake +