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ML20202E643 +
SECY-83-472 +, SECY 93-087 +, SECY-90-016 +, SECY 90-016 +, SECY 90 016 +, SECY-94 084 + and SECY-90 016 +
NRC Generic Letter 80-19, Resolution of Enhanced Fission Gas Release Concern +, NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +, NRC Generic Letter 80-01, NUREG-0630 "Cladding, Swelling and Rupture - Models for LOCA Analysis" +, NRC Generic Letter 83-22, Safety Evaluation of "Emergency Response Guidelines" +, NRC Generic Letter 83-11, Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" + and NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +
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ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 +, ML20202E643 + and ML20202E643 +
January 9, 1998 +
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08:00:44, 8 December 2024 +
NUREG-4933 +, NUREG/CR-5374 +, 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-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, 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-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +
30 +
SECY-83-472 +, SECY 93-087 +, SECY-90-016 +, SECY 90-016 +, SECY 90 016 +, SECY-94 084 + and SECY-90 016 +
January 9, 1998 +
Forwards Update to AP600 Final Ser,Chapter 20,GIs Addressing Issues for Which Srxb Has Primary Responsibility.Issues That Remain Open includes,A-31, RHR Shutdown Requirements, A-9, ATWS & A-105, Isloca +
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