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ML19211D168
Show incoming properties 
Category
Pages with broken file links, INTERROGATORIES; RESPONSES TO INTERROGATORIES  and LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
Accession number
ML19211D168  +
Atomic Element
Iodine +, Uranium +, Lead +  and Tin +
CFR
10 CFR 52.740 +
Docket
05000466  +  and 00466  +
From
Moon C +  and Office of Nuclear Reactor Regulation +
Fuel cladding
Zircaloy +
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>.
ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +, ML19211D168 +  and ML19211D168 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
January 10, 1980  +
Manufacturer
General Electric +
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>.
00:59:13, 5 January 2025  +
NUREG
NUREG-0558 +, NUREG-0581 +, NUREG-101 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0152, Comments on Pressure Interlocks on Valves Interfacing Between Low Pressure ECCS & Reactor Pressure Vessel. Redundant Protection Against Overpressurization of Low Pressure Sys Should Be Provided,Per NUREG-0152 +, NUREG/CR-0687 +, NUREG-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl +, NUREG-0515, Second Errata Suppl to NUREG-0515,Suppl 2 to SER +  and NUREG/CR-687 +
Page count
26  +
Site
Allens Creek +
Start date
January 10, 1980  +
State
Texas +, Pennsylvania +, Connecticut +, Georgia +, Washington +  and Oregon +
System
Feedwater +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, High Pressure Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Standby Liquid Control +  and Safety Relief Valve +
Title
Response to Jf Doherty Eighth Set of Interrogatories. Provides Name of Sys Relied on to Mitigate Consequences of ATWS Events.Affidavit & Certificate of Svc Encl  +
To
Doherty J +, DOHERTY +  and J.F. +
Topic
Affidavit +  and Fuel cladding +
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http://pbadupws.nrc.gov/docs/ML1921/ML19211D168.pdf  +
WCAP
WCAP-2923 +
Westinghouse report
WCAP-2923 +
 
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