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ML20202E643
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
ANSI code
ANSI 5.1 +
Accession number
ML20202E643  +
Atomic Element
Boron +, Oxygen +  and Lead +
CFR
10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 60 +, 10 CFR 50.62 +, 10 CFR 55.45 +, 10 CFR 50.34#f +, 10 CFR 50.62#c1 +, 10 CFR 50.62#c2 +, 10 CFR 52.47#a1 +  and 10 CFR 52.47#b2 +
Correspondence
SECY-83-472 +, SECY 93-087 +, SECY-90-016 +, SECY 90-016 +, SECY 90 016 +, SECY-94 084 +  and SECY-90 016 +
Cross cutting aspect
S.3(f) +
Docket
05200003  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
NRC (Affiliation Not Assigned) +  and Collins T +
General design criterion
GDC 34 +  and GDC 30 +
Generic letter
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 +
Hours
4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +
Issue date
January 9, 1998  +
Letter
ET-NRC-93-3895, Forwards Responses to NRC Requests for Addl Info on AP600 from Ltrs of 930126,0312 & 0413 +
Manufacturer
Westinghouse +
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08:00:44, 8 December 2024  +
NRC information notice
Information Notice 92-36 +
NUREG
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 +
Page count
30  +
Person
David Diec +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.133 +  and Regulatory Guide 1.139 +
SECY
SECY-83-472 +, SECY 93-087 +, SECY-90-016 +, SECY 90-016 +, SECY 90 016 +, SECY-94 084 +  and SECY-90 016 +
SR
SR-3.4.16.1 +
Site
05200003 +
Start date
January 9, 1998  +
State
Texas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +  and Control Rod +
TS
TS-3.4.16 +
Title
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  +
To
NRC (Affiliation Not Assigned) +  and Quay T +
Topic
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Internal Flooding +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Pressure Boundary Leakage +, Core Exit Thermocouple +  and Loss of condenser vacuum +
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http://pbadupws.nrc.gov/docs/ML2020/ML20202E643.pdf  +
WCAP
WCAP-14425 +, WCAP-14477 +  and WCAP-1447 +
Westinghouse report
WCAP-14425 +, WCAP-14477 +  and WCAP-1447 +
 
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