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ML19255F531
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML19255F531  +
Atomic Element
Iron +, Nickel +, Carbon +, Oxygen +  and Lead +
CFR
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.29 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#A +, 10 CFR 54.21#d +, 10 CFR 54.21#c +, 10 CFR 54.21#a +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b2viii +  and 10 CFR 50.48#c +
Docket
05000395  +  and 00395  +
From
South Carolina Electric & Gas Company +  and Dominion Energy Co +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +
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>.
ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +, ML19255F531 +  and ML19255F531 +
In package
ML19255F498 +
Issue date
May 31, 2019  +
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>.
09:32:59, 4 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NFPA
NFPA 805 +
NUMARC
NUMARC 93-01 +
NUREG
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG-1787, Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
Page count
31  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.89 +
SR
SR-4.6.1.2 +  and SR-4.6.1.6.3 +
Site
Summer +
Site license
Summer +
Start date
May 31, 2019  +
State
South Carolina +
System
Steam Generator +, Reactor Coolant System +, Service water +  and Reactor Pressure Vessel +
TS
TS-4.4.5 +
Title
Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Fire Barrier +, Coatings +, Aging Management +, Stress corrosion cracking +, Integrated leak rate test +, Moisture barrier +, License Renewal +, Liquid penetrant +, Fire Protection Program +, Thermal fatigue +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML1925/ML19255F531.pdf  +
WCAP
WCAP-16298-NP +, WCAP-16306-NP +  and WCAP-16305-NP +
Westinghouse report
WCAP-16298-NP +, WCAP-16306-NP +  and WCAP-16305-NP +
 
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