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ML19003A348
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Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML19003A348  +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Vanadium +, Copper +, Carbon +, Oxygen +, Hydrogen +, Xenon +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.34 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 50.55a +  and 10 CFR 50.55a#a3 +
Correspondence
L-2018-237, Integrated Final Safety Analysis Report Tier 1, Rev. 0 +
Docket
05200040  +  and 05200041  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
NextEra Energy +
Fuel cladding
Zircaloy +
General design criterion
GDC 38 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 55 +, GDC 56 +, GDC 61 +, GDC 35 +, GDC 18 +, GDC 39 +, GDC 40 +, GDC 17, Electric power systems +  and GDC 19, Control room +
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ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +, ML19003A348 +  and ML19003A348 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML19003A318 +
Isotope
Tritium +
Issue date
December 21, 2018  +
L
L-2018-237, Integrated Final Safety Analysis Report Tier 1, Rev. 0 +
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>.
11:23:14, 5 January 2025  +
Page count
29  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.82 +  and Regulatory Guide 1.139 +
Scram
Automatic Scram +
Site
Turkey Point +
Start date
December 21, 2018  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Shield Building +, Automatic Depressurization System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  and Emergency Feedwater System +
Title
To Integrated Final Safety Analysis Report, Chapter 3, Section 3.1, Conformance with Nuclear Regulatory Commission General Design Criteria  +
To
Office of New Reactors +
Topic
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Weld Overlay +, Loss of Offsite Power +, Earthquake +, Pressure Boundary Leakage +, Offsite Circuit +, Power change +, Unidentified leakage +, Control Room Habitability +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML1900/ML19003A348.pdf  +
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