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ML19087A288
Show incoming properties 
Category
Letter, Legal-Affidavit  and Topical Report
ANSI code
ANSI/ANS 58.2 +, ANSI/ANS 58.2-1988 +  and ANSI/ANS-58.2-1988 +
ASME section
ASME Section III +  and ASME Section II +
Accession number
ML19087A288  +
Atomic Element
Carbon +, Chloride +  and Lead +
CFR
10 CFR 50 Appendix A +
Correspondence
ND-3653 +
Docket
05200048  +
Document
ML18311A006 +, ML11203A432 +  and ML1835B400 +
Equipment trip
Reactor Trip +
From
Rad Z +  and NuScale +
General design criterion
GDC 57 +, GDC 55 +  and GDC 4, Environmental and dynamic effects design bases +
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>.
ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +, ML19087A288 +  and ML19087A288 +
In package
ML19087A287 +
Issue date
March 28, 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>.
09:01:31, 5 January 2025  +
ND
ND-3653 +
NUREG
NUREG/CR-6004 +, NUREG/CR-4878 +, NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads, +, NUREG/CR-5128 +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +
Page count
55  +
Person
Gregory Cranston +  and Samuel Lee +
Project stage
Request  +
SSC
07-52-048 +
Site
NuScale +
Start date
March 28, 2019  +
State
Oregon +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Extraction steam +
Title
LLC Updates to Final Safety Analysis Report, Section 1.6,Materials Referenced, Section 3.6, Protection Against Dynamic Effects Associated with Postulated Rupture of Piping, and the Pipe Rupture Hazards Analysis, TR-0818-61384  +
To
Document Control Desk +  and Office of New Reactors +
Topic
Ultimate heat sink +, Safe Shutdown Earthquake +, Stress corrosion cracking +, Excess Flow Check Valve +, Earthquake +, Through-Wall Leakage +, Affidavit +, Water hammer +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML1908/ML19087A288.pdf  +
 
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