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ML20206B537
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
Accession number
ML20206B537  +
Docket
05000341  +  and 00341  +
From
Office of Nuclear Reactor Regulation +
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>.
ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +, ML20206B537 +  and ML20206B537 +
In package
ML20206B526 +
Issue date
April 7, 1987  +
Letter
ML20203N968 +, ML20207S483 +, ML20213A585 +, ML20210D903 +, ML20203B119 +  and 05000341/LER-1986-044, :on 861210,during Postulated Accident Event, Potentially Degraded Torus Relief Line Isolation Identified. Caused by Design Deficiency.Mod Installed to Prevent Drywell Vacuum Breaker Limit Switch Failure +
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07:23:33, 7 December 2024  +
NUREG
NUREG-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +
Page count
4  +
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ML20206B537 +
Project stage
Request  +
Site
Fermi +
Site license
NPF-43 +
Start date
April 7, 1987  +
State
Washington +
System
Emergency Diesel Generator +
Title
Safety Evaluation Supporting Util Request to Amend License Condition 2.C(10), Emergency Diesel Generator Lube Oil Surveillance Program. NRC Does Not Agree Condition Should Be Revised by Substituting for Mar 1985 Ltr  +
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http://pbadupws.nrc.gov/docs/ML2020/ML20206B537.pdf  +
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