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ML11291A099
Show incoming properties 
Category
Report  and Technical
Accession number
ML11291A099  +
Atomic Element
Boron +, Iodine +, Copper +, Nitrogen +, Oxygen +, Hydrogen +, Chloride +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.44 +  and 10 CFR 50.49 +
Docket
05000390  +, 05000391  +, 00750  +  and 00700  +
Emergency Facility
Technical Support Center +
Equipment trip
Reactor Trip +
From
Tennessee Valley Authority +  and Pachigolla R +
General design criterion
GDC 13 +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +
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>.
ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +, ML11291A099 +  and ML11291A099 +
Isotope
C-14 +  and Iodine-131 +
Issue date
October 12, 2010  +
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>.
06:31:42, 13 January 2025  +
NUREG
NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG/CR-2644 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
89  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.28 +
SR
SR-5.1 +  and SR-5.1.1 +
SSC
5x10-1 +, 0E-3 +, 5x10-10 +, 47E235-Series +, 47W610-series +  and 47B601-series +
Site
Watts Bar +
Start date
October 12, 2010  +
State
Tennessee +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Primary containment +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Shield Building +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.3.3 +
Title
WB-DC-30-7, Revision 23, Post Accident Monitoring Instrumentation  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Grab sample +, Post Accident Monitoring +, Commercial Grade +, Fuel cladding +, Core Exit Thermocouple +  and Manual Operator Action +
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http://pbadupws.nrc.gov/docs/ML1129/ML11291A099.pdf  +
 
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