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ML19114A195
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +
ASME section
ASME Section III +
Accession number
ML19114A195  +
Atomic Element
Hydrogen +, Xenon +, Lead +  and Tin +
CFR
10 CFR 20 +, 10 CFR 100 +  and 10 CFR 50.34 +
Code case
ASME Code Case N-411-1 +
Committee
Advisory Committee on Reactor Safeguards +
Docket
05000277  +, 05000278  +, 00277  +, 00278  +, 00259  +, 00260  +, 00237  +, 00249  +, 00245  +, 00324  +, 00325  +, 00296  +, 00321  +, 00293  +, 00298  +, 00263  +, 00331  +  and 00388  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Exelon +
Fuel cladding
Zircaloy +
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>.
ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +, ML19114A195 +  and ML19114A195 +
IEEE
IEEE 279 +
In package
ML19114A265 +
Issue date
April 8, 2019  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +
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>.
08:00:03, 5 January 2025  +
Page count
73  +
Project stage
Request  +
Report
NEDO-10174 +, NEDO-10173 +, NEDO-10527 +, NEDO-10029 +, NEDO-10045 +  and NEDO-10179 +
Site
Peach Bottom +
Start date
April 8, 2019  +
State
Texas +, Pennsylvania +, Washington +  and Vermont +
System
Reactor Coolant System +, Service water +, Reactor Protection System +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Circulating Water System +, Core Standby Cooling System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +  and Main Steam +
Test
Bench test +
Title
7 to Updated Final Safety Analysis Report, Appendix J, Identification-Resolution of AEC-ACRS and Staff Concerns  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Shutdown Margin +, Tornado Missile +, Operating Basis Earthquake +, Tornado-Generated Missile +, Main Steam Line Radiation Monitor +, Earthquake +, Fuel cladding +, Liquid penetrant +  and Failure to Scram +
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http://pbadupws.nrc.gov/docs/ML1911/ML19114A195.pdf  +
Ultimate Heat Sink
Cooling Tower +
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