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ML17139C013
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.7 +  and ANSI B31.1.0 +
ASME section
ASME Section III +
Accession number
ML17139C013  +
Act
Atomic Energy Act of 1954 +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Uranium +, Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Thorium +, Lead +, Mercury +, Tin +  and Curium +
CFR
10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 72 +, 10 CFR 54 +, 10 CFR 72.212 +  and 10 CFR 50.71#e +
Contact
Shawn Williams +
Correspondence
NL-17-0534, Technical Requirements Manual +, U-166243, Functional Diagrams Feedwater Control & Isolation.Sheet 13 +, U-166242, Functional Diagrams Pressurizer Heater Control.Sheet 12 +, U-166238, Functional Diagrams Safeguard Actuation Signals.Sheet 8 +, U-166237, Functional Diagrams Steam Generator Trip Signals.Sheet 7 +, U-166235, Functional Diagrams Primary Coolant System Trip Signals. Sheet 5 +, U-166232, Functional Diagrams Reactor Trip Signals.Sheet 2 +, U-166231, Functional Diagram Index & Symbols.Sheet 1 of 1 +, U-166244 +, U-167647 +, U-165665 +, U-166233 +, U-166234 +, U-166236 +, U-166239 +, U-166240 +, U-166241 +, U-166245 +, U-167650 +, U-167651 +, U-167652 +, U-170148 +, U-202225 +, U-261455 +, U-264612 +, U-419610 +, U-419916 +, U-419917 +, U-419918 +, U-419920 +...
Docket
05000348  +  and 05000364  +
Drawing
Drawing 1.7-1 +  and Drawing 1.6-14 +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Southern Nuclear +
Fuel cladding
Zircaloy +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +, ML17139C013 +  and ML17139C013 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 323-1974 +
In package
ML17136A052 +
Isotope
Tritium +
Issue date
April 20, 2017  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +  and General 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>.
01:54:10, 9 January 2025  +
NL
NL-17-0534, Technical Requirements Manual +
Page count
185  +
Person
None none +
Power source
345kV +
Project stage
Request  +
SSC
2A-1 +, 2A-3 +, 2A-4 +, 2A-2 +, 3B-1 +, 10A-6 +, 3E-1 +, 2B-1 +, 2B-5 +, 2B-22 +, 2B-2 +, 6A-1 +, 6A-2 +, 6A-3 +, 3C-1 +, 15A-1 +, 3F-1 +, 2B1-2 +, 3F-2 +, 2B-6 +, 2B-7 +, 2B-8 +, 2B-4 +, 2B-3 +, 3A-1 +, 17A-1 +, 3B-2 +, 15C-1 +, 6A-4 +, 6A-5 +...
Scram
Manual Scram +
Site
Farley +
Start date
April 20, 2017  +
State
Texas +, Ohio +, Tennessee +, Pennsylvania +, Connecticut +, Kansas +, Georgia +, Illinois +, Minnesota +, North Carolina +, California +, Massachusetts +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Wisconsin +, Florida +, Missouri +, Indiana +, Arkansas +, New Hampshire +  and Oregon +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Extraction steam +  and Turbine Gland Sealing System +
TS
TS-1.5.4 +
Title
Updated Final Safety Analysis Report, Revision 27, Effective Page Listing, Table of Contents, Chapter 1 Redacted, Introduction and General Description of the Plant  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Coatings +, Nondestructive Examination +, Emergency Lighting +, Incorporated by reference +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Sewage Treatment Plant +, License Renewal +, Earthquake +, Turbine Missile +, Fuel cladding +, Fire Protection Program +, Flow Induced Vibration +, Uranium Hexafluoride +, Power Uprate +, Overspeed +  and Leak-Before-Break +
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/ML1713/ML17139C013.pdf  +
Ultimate Heat Sink
Cooling Tower +, Lake Ontario +, Lake Michigan +  and Lake Anna +
WCAP
WCAP-7665 +, WCAP-8822 +, WCAP-7817 +, WCAP-7571 +, WCAP-6065 +, WCAP-8183 +, WCAP-8377 +, WCAP-8381 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-7800 +, WCAP-8446 +, WCAP-8449 +, WCAP-8623 +, WCAP-8289 +, WCAP-8290 +, WCAP-8305 +, WCAP-7973 +, WCAP-7907 +, WCAP-7908 +, WCAP-7669 +, WCAP-7306 +, WCAP-7819 +, WCAP-7744 +, WCAP-7979 +, WCAP-7810 +, WCAP-7809 +, WCAP-7208 +, WCAP-7811 +...
Westinghouse report
WCAP-7665 +, WCAP-8822 +, WCAP-7817 +, WCAP-7571 +, WCAP-6065 +, WCAP-8183 +, WCAP-8377 +, WCAP-8381 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-7800 +, WCAP-8446 +, WCAP-8449 +, WCAP-8623 +, WCAP-8289 +, WCAP-8290 +, WCAP-8305 +, WCAP-7973 +, WCAP-7907 +, WCAP-7908 +, WCAP-7669 +, WCAP-7306 +, WCAP-7819 +, WCAP-7744 +, WCAP-7979 +, WCAP-7810 +, WCAP-7809 +, WCAP-7208 +, WCAP-7811 +...
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