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ML22193A081
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML22193A081  +
Area
Switchyard +
Atomic Element
Boron +, Uranium +, Nitrogen +, Sodium +, Hydrogen +  and Xenon +
CFR
10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +  and 10 CFR 50.46#b +
CR
LO-LAR-15-00571 +
Committee
Advisory Committee on Reactor Safeguards +
Docket
05000245  +, 05000336  +  and 05000423  +
Document
ML16068A312 +
Drawing
Drawing 7.2-2 +, Drawing 7.2-5 +, Drawing 7.2-11 +, Drawing 7.2-6 +  and Drawing 7.2-4 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Dominion Energy Nuclear Connecticut +
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>.
ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +, ML22193A081 +  and ML22193A081 +
IEEE
IEEE 317 +
In package
ML22193A089 +
Issue date
June 23, 2022  +
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>.
21:30:56, 27 November 2024  +
NUREG
NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +
Page count
95  +
Power source
345kV +
Procedure
MP-20-04 +  and AOP +
Project reference
CAC:MF5838 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
SSC
15G-10T-4 +  and 15G-18T-8 +
Site
Millstone +
Start date
June 23, 2022  +
State
Connecticut +  and Massachusetts +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
0 to Updated Final Safety Analysis Report  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Shutdown Margin +, Loop seal +, Tornado Missile +, Operating Basis Earthquake +, Incorporated by reference +, Aging Management +, Design basis earthquake +, Feedwater Heater +, Loss of Offsite Power +, License Renewal +, Earthquake +  and Spent fuel rack +
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http://pbadupws.nrc.gov/docs/ML2219/ML22193A081.pdf  +
 
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