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ML16256A199
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML16256A199  +
DRN
DRN-03-2056 +
Docket
05000382  +, 00382  +, 00317  +, 00318  +  and 00335  +
Engineering change
EC-480 +, EC-8458 +, EC-350 +, EC-430 +  and EC-592 +
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>.
ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +, ML16256A199 +  and ML16256A199 +
In package
ML16256A115 +
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>.
01:24:11, 10 January 2025  +
NUREG
NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +
Page count
42  +
Procedure
ST +
Project stage
Request  +
SSC
1RC42-2RL2 +, 1RC14-45RL2 +, 1RC12-40RL2B +, 1RC14-44RL1 +, 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 +, 1RC12-38RL1B +, 1RC12-39RL2A +  and 1RL14-45RL2 +
Site
Waterford +
Start date
August 25, 2016  +
State
Idaho +, New York +  and Florida +
System
Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +
Title
09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Appendix 3.9E - Asymmetric Loads  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown Earthquake +, Finite Element Analysis +, Power Uprate +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML1625/ML16256A199.pdf  +
 
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