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ML20246P684
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Category
LEGAL TRANSCRIPTS & ORDERS & PLEADINGS  and GRANTS OF EXEMPTION FROM & EXTENSION TO NRC REQUIREME
Accession number
ML20246P684  +
CFR
10 CFR 50.49 +  and 10 CFR 50.40 +
Docket
05000245  +  and 00245  +
FR
52 FR 23219 +
From
Varga S +  and 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>.
ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +, ML20246P684 +  and ML20246P684 +
In package
ML20246P670 +
Issue date
May 16, 1989  +
Letter
05000245/LER-1989-003-02, :on 890323,design Deficiencies Identified on Reactor Bldg Closed Cooling Water Sys.Caused by Original Analyses Considering Closed Cooling Water Sys Piping as closed-loop Sys.Design Change Initiated +  and 05000245/LER-1989-001-01, :on 890131,reported RWCU Sys May Not Isolate During Small Break LOCA Due to Questionable Environ Qualification.Sys Immediately Isolated & Design Change Processed to Provide Addl Sys Isolation +
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>.
02:59:44, 2 December 2024  +
Page count
3  +
Project stage
Approval  +
SSC
07-89-001 +
Site
Millstone +
Site license
DPR-21 +
Start date
May 16, 1989  +
State
Connecticut +  and Maryland +
Title
Exemption from Requirements of 10CFR50.49 Re Motor Operators for Valves 1-CU-2 & 1-CU-3 Revoked.Qualification of Valve Operators 1-CU-2 & 1-CU-3 Should Be Completed Prior to Restart of Plant from Current Refueling Outage  +
To
Northeast Nuclear Energy +
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http://pbadupws.nrc.gov/docs/ML2024/ML20246P684.pdf  +
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