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ML20210N688
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML20210N688  +
Atomic Element
Boron +, Nitrogen +  and Hydrogen +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 10 +, 10 CFR 50.2 +, 10 CFR 50.44 +  and 10 CFR 50.44#e +
Docket
05000327  +, 05000328  +, 00327  +, 00328  +, 00512  +, 00513  +, 00547  +, 00548  +, 00556  +  and 00555  +
From
Tennessee Valley Authority +  and Gridley R +
General design criterion
GDC 57 +, GDC 55 +  and GDC 56 +
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>.
ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +, ML20210N688 +  and ML20210N688 +
Issue date
September 24, 1986  +
Letter
05000327/LER-1986-021, :on 860502,control Room Isolation Occurred Due to Spike on Train B Chlorine Detector.Cause Unknown.Chlorine Detector Reset & Control Room Ventilation Returned to Normal +
Manufacturer
Westinghouse +
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>.
06:54:47, 6 December 2024  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
63  +
Project stage
Request  +
SSC
07-70-140 +, 07-63-640 +, 07-63-643 +, 07-63-157 +, 07-43-309 +, 07-63-511 +, 07-52-505 +, 07-63-172 +, 07-63-112 +, 07-43-202 +, 07-62-505 +, 07-63-557 +, 07-63-534 +, 07-63-626 +, 07-70-703 +, 07-52-501 +, 07-52-503 +, 07-67-107 +, 07-26-243 +, 07-67-141 +, 07-67-130 +, 07-67-138 +, 07-67-133 +, 07-59-522 +, 07-26-240 +, 07-78-557 +, 07-52-507 +, 07-63-627 +, 07-43-318 +, 07-70-134 +...
Site
Sequoyah +
Start date
September 24, 1986  +
State
Tennessee +, Georgia +, Maryland +  and Washington +
System
Feedwater +, Primary containment +, Shield Building +, Emergency Core Cooling System +, Safety Relief Valve +, Main Steam +  and Containment Spray +
TS
TS-4.5.2 +
Title
Suppls 860530 Response to Request for Addl Info Re Unresolved Items 50-327/86-20-09 & 50-328/86-09 from Insp Repts 50-327/86-20 & 50-328/86-20 Concerning Containment Isolation Design.Agreements Reflected  +
To
Youngblood B +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Fuel cladding +  and Backfit +
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http://pbadupws.nrc.gov/docs/ML2021/ML20210N688.pdf  +
 
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