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ML20235G605
Show incoming properties 
Category
TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST/INSPECTION/OPERATING PROCEDURES
Accession number
ML20235G605  +
Atomic Element
Boron +, Iodine +  and Hydrogen +
CR
LO-PROC-8706-00030 +
Correspondence
L 00 +
Docket
05000382  +  and 00302  +
Equipment trip
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>.
ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +, ML20235G605 +  and ML20235G605 +
In package
ML20235G604 +
Issue date
June 30, 1987  +
L
L 00 +
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>.
10:37:19, 3 December 2024  +
NUREG
NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
47  +
Power source
4.16KV +
Procedure
AM +, SP +, CP +, CP-33 +, CP-8 +, Emergency Operating Procedure +, Emergency Plan +, CP-4 +  and CP-14 +
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.
ML20235G605 +
Project stage
Request  +
SSC
W3P84-1007, Forwards Safety Parameter Display Sys (Spds), Providing Details of SPDS Implementation,Per NUREG-0737,Suppl 1. Detailed Description of SPDS Display Hierarchy Included in Rept +
Site
Waterford +
Start date
June 30, 1987  +
State
Louisiana +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, Qualified Safety Parameter Display System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Steam +, Containment Spray +  and Emergency Feedwater System +
Title
Functional Design Spec for SPDS Enhancement Program  +
Topic
Safe Shutdown +, Boric Acid +, Main Steam Line Radiation Monitor +  and Fuel cladding +
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http://pbadupws.nrc.gov/docs/ML2023/ML20235G605.pdf  +
 
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