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ML100250132 +
L-10-027, Response to Request for Additional Information Related to License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds + and L-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping +
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>.
ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 +, ML100250132 + and ML100250132 +
January 11, 2010 +
L-10-027, Response to Request for Additional Information Related to License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds + and L-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping +
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>.
12:03:36, 14 January 2025 +
NUREG/CR-4513 +, NUREG/CR-6907 +, NUREG/CR-6004 +, NUREG/CR-6142 +, NUREG/CR-6721 +, NUREG/CR-6300 +, NUREG/CR-1061 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting + 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 +
107 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
Other +
January 11, 2010 +
California + and Virginia +
0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.