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ML20197J937
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20197J937  +
Atomic Element
Hydrogen +
Docket
05000317  +, 05000318  +, 00317  +  and 00318  +
Emergency Facility
Technical Support Center +  and Emergency Operations Facility +
From
Exelon +  and Tiernan J +
Generic letter
NRC Generic Letter 81-10, Post-TMI Requirements for the Emergency Operations Facility +
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>.
ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +, ML20197J937 +  and ML20197J937 +
Issue date
May 5, 1986  +
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>.
17:18:12, 10 December 2024  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
4  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
Site
Calvert Cliffs +
Start date
May 5, 1986  +
State
Maryland +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Service water +, Auxiliary Feedwater +, Safety Parameter Display System +, Decay Heat Removal +, Main Steam +  and Containment Spray +
Title
Clarifies Ae Lundrall Re Suppl 1 to NUREG-0737, Based on Review of Status of & Commitments Relative to Technical Support Ctr Computer.List of Variables Essential for Performance of Ctr Functions Per Reg Guide 1.97 Encl  +
To
Thadani A +  and Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Backfit +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2019/ML20197J937.pdf  +
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