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ML16257A129
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N18.2 +
Accession number
ML16257A129  +
Atomic Element
Iodine +
DRN
DRN-05-543 +, DRN-02-526 +, DRN-00-592 +, DRN-06-1062 +, DRN-04-704 +, DRN-00-119 +  and DRN-05-1551 +
Docket
05000382  +  and 00470  +
Engineering change
EC-13881 +, EC-8458 +, EC-5000081470 +  and EC-40444 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Entergy +
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>.
ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +, ML16257A129 +  and ML16257A129 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +
In package
ML16256A115 +
Isotope
Cs-137 +
Issue date
August 25, 2016  +
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>.
01:20:33, 10 January 2025  +
Page count
20  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +
SSC
07-05-543 +, 07-04-704 +, W3F192-0020 +  and W3F1-2016-0053, Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-47 +
Site
Waterford +
Start date
August 25, 2016  +
System
Steam Generator +, Feedwater +, Shutdown Cooling +, Main Steam Safety Valve +, Main Steam +  and Emergency Feedwater System +
Title
09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Section 15.3  +
To
Office of Nuclear Reactor Regulation +
Topic
Anticipated operational occurrence +  and Loss of Offsite Power +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML1625/ML16257A129.pdf  +
 
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