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ML16256A201
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +
ASME section
ASME Section III +
Accession number
ML16256A201  +
Atomic Element
Boron +, Carbon +, Hydrogen +  and Tungsten +
CFR
10 CFR 50.67 +
DRN
DRN-00-1121 +, DRN-00-1032 +, DRN-03-2056 +, DRN-05-127 +, DRN-00-0958 +, DRN-06-291 +, DRN-06-803 +, DRN-06-913 +, DRN-99-2063 +  and DRN-06-883 +
Docket
05000382  +
Engineering change
EC-19087 +, EC-29816 +, EC-8433 +  and EC-8439 +
From
Entergy +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +
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ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +, ML16256A201 +  and ML16256A201 +
In package
ML16256A115 +
Issue date
August 25, 2016  +
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01:24:10, 10 January 2025  +
NUREG
NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +
Page count
51  +
Procedure
RAP +, TP +, Emergency Plan +  and TP-304H +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.45 +  and Regulatory Guide 1.46 +
SSC
1SI-VI502B +, 1SI-V1504A +, 07-06-803 +, 2FW-20-14B +, 2CC-8-158B2 +, 2CC-8-91B2 +, 2CC-8-157A2 +, 2CC-8-158B1 +, 2CS-10-12A +, 2SI-14-18B +, 2SI-14-18A +, 2FP-3-47 +, 2SI-2-80A +, 2CC-8-88A2 +, 2DW-1-1 +  and W3F1-2016-0053, Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-47 +
Site
Waterford +
Start date
August 25, 2016  +
State
Illinois +, California +  and New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Primary containment +, Shutdown Cooling +, HVAC +, Shield Building +, Circulating Water System +, Main Steam Line +, Main Steam +, Containment Spray +  and Emergency Feedwater System +
Title
09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.6 - Protection Against Dynamic Effects Associated with Postulated Rupture of Piping  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Safe Shutdown Earthquake +, Weld Overlay +, Post Accident Monitoring +, Finite Element Analysis +, High Energy Line Break +, Loss of Offsite Power +, Earthquake +, Pressure Boundary Leakage +, Through-Wall Leakage +, Power Uprate +, Water hammer +, Leak-Before-Break +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML1625/ML16256A201.pdf  +
WCAP
WCAP-17187-P +
Westinghouse report
WCAP-17187-P +
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