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ML17214A160 +
L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup + and L-83-309, Reschedules 830520 Meeting on Plant Recovery Program - Loose Parts Monitor & ex-core Detector,For 830603,w/followup Documentation to Be Provided by 830606 +
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>.
L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting + and L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +
June 7, 1983 +
L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup + and L-83-309, Reschedules 830520 Meeting on Plant Recovery Program - Loose Parts Monitor & ex-core Detector,For 830603,w/followup Documentation to Be Provided by 830606 +
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>.
20:26:19, 8 January 2025 +
6 +
Request +
June 7, 1983 +
Florida + and Washington +
Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +
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.