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ML13330B485
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML13330B485  +
Atomic Element
Lead +  and Nitrogen +
Docket
05000206  +  and 00206  +
Equipment trip
Reactor Trip +
From
Nandy F +  and SOUTHERN CALIFORNIA EDISON CO. +
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>.
ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +, ML13330B485 +  and ML13330B485 +
IEEE
IEEE 279 +
Issue date
March 11, 1989  +
Letter
ML20211G403 +, 05000206/LER-1987-015-02, :on 871007,determined That Engineered Safety Sys Design Failed to Meet Single Criteria.Caused by Newly Identified time-dependent Single Failure Susceptibilty. Special Operator Training Provided +, ML13330B415 +, ML13311B143 +  and ML13330B166 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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06:09:55, 11 January 2025  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +
Page count
25  +
Power source
4kV +
SSC
07-87-015 +  and 07-88-019 +
Scram
Automatic Scram +
Site
San Onofre +
Start date
March 11, 1989  +
State
California +  and Washington +
System
Steam Generator +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Containment Spray +
TS
TS-3.1.2 +
Title
Forwards Update of Single Failure Analysis Review Submitted on 881031,per Request.Engineering for Resolution of Single Failure Continues & Expected to Be Completed Shortly.Summary Description Will Be Provided by 890320  +
To
Office of Information Resources Management +
Topic
Safe Shutdown +, Loop seal +, Loss of Offsite Power +, Manual Operator Action +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1333/ML13330B485.pdf  +
 
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