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ML23208A068
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML23208A068  +
Atomic Element
Boron +, Nitrogen +, Oxygen +, Sodium +, Hydrogen +, Chloride +  and Lead +
CFR
10 CFR 50 Appendix J +
Docket
05000395  +
Effective date
June 30, 2021  +
Equipment trip
Reactor Trip +
From
Dominion Energy South Carolina +
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>.
ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +, ML23208A068 +  and ML23208A068 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +
In package
ML23208A088 +
Issue date
July 18, 2023  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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>.
22:36:29, 2 January 2025  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
1  +
Power source
115kV +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.68 +  and Regulatory Guide 1.58 +
Scram
Manual Scram +
Site
Summer +
Start date
July 18, 2023  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, HVAC +, Reactor Building Ventilation +, Residual Heat Removal +, Circulating Water System +, Decay Heat Removal +, Main Condenser +, Control Rod +, Main Steam +  and Emergency Feedwater System +
TS
TS-1.0 +
Test
Bench test +
Title
3 to Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Shutdown Margin +, Stroke time +, Hydrostatic +, Emergency Lighting +, Feedwater Heater +, Loss of Offsite Power +, Integrated leak rate test +, Overspeed trip +, Overspeed +, Negative rate trip +  and Spent fuel rack +
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http://pbadupws.nrc.gov/docs/ML2320/ML23208A068.pdf  +
 
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