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ML19151A810
Show incoming properties
Category
Letter, Legal-Affidavit, Report  and Technical
ASME section
ASME Section I +
Accession number
ML19151A810  +
Atomic Element
Lead +
CFR
10 CFR 2.390 +
Docket
05200048  +
Document
ML17334B822 +
Equipment trip
Reactor Trip +
From
Bergman T +  and NuScale +
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>.
ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +, ML19151A810 +  and ML19151A810 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML19151A809 +
Issue date
May 31, 2019  +
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>.
07:14:27, 5 January 2025  +
NUREG
NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +
Page count
107  +
Person
Prosanta Chowdhury +, Gregory Cranston +  and Samuel Lee +
Procedure
Emergency Operating Procedure +
Project stage
Request  +
SSC
07-52-048 +
Site
NuScale +
Start date
May 31, 2019  +
State
Washington +  and Oregon +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +  and Main Condenser +
Title
LLC Submittal of Technical Report NuScale Generic Technical Guidelines, TR-1117-57216, Revision 1  +
To
Document Control Desk +  and Office of New Reactors +
Topic
Safe Shutdown +, Ultimate heat sink +, Probabilistic Risk Assessment +, Incorporated by reference +, Severe Accident Management Guideline +, Core Exit Thermocouple +  and Affidavit +
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http://pbadupws.nrc.gov/docs/ML1915/ML19151A810.pdf  +
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