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ML20247A580
Show incoming properties
Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
Accession number
ML20247A580  +
Atomic Element
Lead +
CFR
10 CFR 50.62 +
Docket
05000423  +  and 00423  +
Equipment trip
Turbine Trip +
From
Office of Nuclear Reactor Regulation +
Generic letter
NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +
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>.
ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +, ML20247A580 +  and ML20247A580 +
In package
ML20247A570 +
Issue date
July 17, 1989  +
Letter
05000336/LER-1987-003-01, :on 870129,reanalysis of Steam Generator Tube Exam Data Identified Tube Containing Repairable Defect. Caused by Incorrect Recording of Original Test.Tube Retested & Analyzed +  and B12743, Forwards Relief Request Providing Justification for Not Full /Part Stroke Exercising Valves Quarterly in Open to Close Position During Plant Operation,In Response to NRC 880115 Safety Evaluation on Rev 2 to Inservice Testing Program +
Manufacturer
Westinghouse +
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02:43:17, 2 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 +
Page count
12  +
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.
ML20247A580 +
Project stage
Request  +
Site
Millstone +
Start date
July 17, 1989  +
System
Steam Generator +, Feedwater +, Reactor Protection System +  and Auxiliary Feedwater +
Title
Safety Evaluation Supporting Util ATWS Mitigating Sys Actuation Circuitry Designs  +
Topic
Anticipated operational occurrence +, Loss of Offsite Power +  and Loss of condenser vacuum +
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http://pbadupws.nrc.gov/docs/ML2024/ML20247A580.pdf  +
WCAP
WCAP-10858-P-A +  and WCAP-10858 +
Westinghouse report
WCAP-10858 +  and WCAP-10858-P-A +
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