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ML19296C780
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI C37.06-1971 +, ANSI C37.90-1971 +, ANSI C37.13-1973 +  and ANSI C57.12.00-1973 +
Accession number
ML19296C780  +
Area
Switchyard +
Atomic Element
Boron +, Copper +, Hydrogen +, Xenon +, Lead +, Aluminum +, Silicon +  and Tin +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.65 +  and 10 CFR 50.54#f +
Correspondence
NL-19-1193, Submittal of Revision 22 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes and Revised NRC Commitments Report +
Docket
05000424  +  and 05000425  +
Emergency Facility
Technical Support Center +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Southern Nuclear +
General design criterion
GDC 50 +, GDC 18 +, GDC 25 +, GDC 23 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +
Generic letter
NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +  and NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +
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ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +, ML19296C780 +  and ML19296C780 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
IEEE
IEEE 384 +, IEEE 383 +, IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 279-1971 +, IEEE 383-1974 +, IEEE 603 +, IEEE 485 +, IEEE 308-1974 +, IEEE 308 +, IEEE 485-1983 +, IEEE 344-1975 +, IEEE-450 +, IEEE 379-1972 +, IEEE 336-1971 +, IEEE 387 +, IEEE 387-1977 +, IEEE 384-1981 +, IEEE 334-1974 +, IEEE 382-1972 +, IEEE 317-1976 +, IEEE 338-1977 +, IEEE 484-1975 +, IEEE 628-1987 +, IEEE 472 +, IEEE 142-1972 +, IEEE 80-1971 +...
In package
ML19296D008 +
Issue date
October 21, 2019  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +  and Reliance Electric +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
12:21:23, 2 January 2025  +
NL
NL-19-1193, Submittal of Revision 22 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes and Revised NRC Commitments Report +
NUREG
NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
150  +
Person
None none +
Power source
4.16kV +, 115kV +  and 4V +
Procedure
SP +  and CH +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.47 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.100 +, Regulatory Guide 1.106 +, Regulatory Guide 1.53 +, Regulatory Guide 1.81 +, Regulatory Guide 1.6 +, Regulatory Guide 1.29 +, Regulatory Guide 1.32 +, Regulatory Guide 1.118 +, Regulatory Guide 1.41 +, Regulatory Guide 1.30 +, Regulatory Guide 1.89 +, Regulatory Guide 1.129 +, Regulatory Guide 1.22 +, Regulatory Guide 1.68 +, Regulatory Guide 1.40 +, Regulatory Guide 1.62 +, Regulatory Guide 1.73 +, Regulatory Guide 1.128 +  and Regulatory Guide 1.131 +
SSC
2X3D-AA-A01A +, 2X3D-AA-G01A +, 1X3D-AA-A01A +, 1X3D-AA-G01A +, 1X3D-AA-K02A +, 2X3D-AA-K02A +, 1X3D-AA-K02B +, 2X3D-AA-K02B +, 1X3D-AA-G02A +, 1X3D-AA-G02C +, 1X3D-AA-G01B +, 2X3D-AA-02B +, 2X3D-AA-G02A +, 2X3D-AA-G02C +  and 2X3D-AA-G01B +
Site
Vogtle +
Start date
October 21, 2019  +
State
Tennessee +, Georgia +, Alabama +, South Carolina +, Florida +  and Mississippi +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Electrohydraulic Control +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.8.1 +
Title
2 to Updated Final Safety Analysis Report, Chapter 7, (Part 2), Chapter 8, (Part 1)  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Reactor Vessel Water Level +, Fire Barrier +, Anticipated operational occurrence +, Water Inventory Control +, FLEX +, High Energy Line Break +, Aging Management +, Open Phase Condition +, Loss of Offsite Power +, Residual voltage transfer +, Power change +, Core Exit Thermocouple +, Overspeed trip +, Overspeed +  and Manual Operator Action +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1929/ML19296C780.pdf  +
WCAP
WCAP-8255 +  and WCAP-8587 +
Westinghouse report
WCAP-8255 +  and WCAP-8587 +
 
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