Browse wiki

Jump to navigation Jump to search
L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML17214A565  +
Atomic Element
Iodine +
Correspondence
L-81-388, Application for Amend to License DPR-67 Submitted as Response to NRC 810728 Info Request & Proposed Amends to Tech Specs Re Boration Control,Moderator Temp Coefficient, Reactor Coolant Pumps & Boron Dilution & Addition +, L-82-381, Forwards Addl Analyses Re Reactor Coolant Pump Seized Rotor W/Loss of Offsite Power W/Worst Single Active Failure & Loss of All Nonemergency Ac Power W/Worst Single Active Failure, Per L-81-484 +, L-80-381, Application to Amend License DPR-67 by Upgrading Rated Power from 2,560 MW to 2,700 Mw.Forwards Proposed Tech Spec Changes & Supporting Matl +, L-81-439, Confirms That Proposed Stretch Power Tech Spec Changes & Analyses Are Appropriate for Cycle 5 Operation at 2700 Mwt Core Power,Per NRC .No Further Tech Spec Changes Required +, NRC 831012 +, L-81-306, Application for Amend to License DPR-67,revising Tech Specs to Incorporate TMI-2 Related Operational & Design Changes Re Shutdown Margin,Main Steam Isolation Sys Changes & Control Element Assembly Sleeving +  and L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +
Docket
05000335  +  and 00335  +
Engineering change
EC-1093 +
Equipment trip
Reactor Trip +
From
Williams J +  and NextEra Energy +
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-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +, L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +  and L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +
Issue date
November 21, 1983  +
L
L-81-388, Application for Amend to License DPR-67 Submitted as Response to NRC 810728 Info Request & Proposed Amends to Tech Specs Re Boration Control,Moderator Temp Coefficient, Reactor Coolant Pumps & Boron Dilution & Addition +, L-82-381, Forwards Addl Analyses Re Reactor Coolant Pump Seized Rotor W/Loss of Offsite Power W/Worst Single Active Failure & Loss of All Nonemergency Ac Power W/Worst Single Active Failure, Per L-81-484 +, L-80-381, Application to Amend License DPR-67 by Upgrading Rated Power from 2,560 MW to 2,700 Mw.Forwards Proposed Tech Spec Changes & Supporting Matl +, L-81-439, Confirms That Proposed Stretch Power Tech Spec Changes & Analyses Are Appropriate for Cycle 5 Operation at 2700 Mwt Core Power,Per NRC .No Further Tech Spec Changes Required +, L-81-306, Application for Amend to License DPR-67,revising Tech Specs to Incorporate TMI-2 Related Operational & Design Changes Re Shutdown Margin,Main Steam Isolation Sys Changes & Control Element Assembly Sleeving +  and L-83-567, Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon +
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>.
20:21:33, 8 January 2025  +
NRC
NRC 831012 +
Page count
25  +
Project stage
Request  +
Site
Saint Lucie +
Start date
November 21, 1983  +
State
Washington +  and Florida +
System
Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +, Main Steam Safety Valve +  and Main Steam Line +
Title
Forwards Addl Info Re Loss of Offsite Power,In Response to NRC & 830926 Telcon  +
To
John Miller +  and Office of Nuclear Reactor Regulation +
Topic
Loss of Offsite Power +
Training curricula
F-CE-7567 +
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.
http://pbadupws.nrc.gov/docs/ML1721/ML17214A565.pdf  +
 
Retrieved from "https://kanterella.com/Special:Browse/:L-2D83-2D567,-20Forwards-20Addl-20Info-20Re-20Loss-20of-20Offsite-20Power,In-20Response-20to-20NRC-20-26-20830926-20Telcon"