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ML11178A157
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML11178A157  +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Sodium +, Hydrogen +, Lead +  and Lithium +
CFR
10 CFR 50 +  and 10 CFR 50.49 +
Docket
05000391  +
Drawing
Drawing 1.7-1 +, Drawing 6.3-2 +, Drawing 7.2-19 +, Drawing 7.3-8 +, Drawing 6.3-17 +, Drawing 4.2-23 +  and Drawing 5.1-6 +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Tennessee Valley Authority +
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>.
ML11178A157 +, ML11178A157 +, ML11178A157 +, ML11178A157 +, ML11178A157 +, ML11178A157 +, ML11178A157 +  and ML11178A157 +
IEEE
IEEE 387-1984 +
Isotope
Tritium +  and U-238 +
Issue date
June 3, 2011  +
Manufacturer
Westinghouse +
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10:41:38, 13 January 2025  +
NUREG
NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +
Page count
60  +
Procedure
TOP +
Project stage
Request  +
SR
SR-3.8 +
SSC
15A-1 +, 7A-1 +, 8A-1 +, 7A-4 +, 7A-3 +, 15A-2 +, 11A-1 +, 11A-2 +, 11A-3 +, 8A-3 +, 8A-5 +, 8A-6 +  and 8A-8 +
Site
Watts Bar +
Start date
June 3, 2011  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Auxiliary Feedwater +, Primary containment +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Core Spray +, Residual Heat Removal +, Shield Building +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Turbine Gland Sealing System +
TS
TS-6.2 +
Title
Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 1.0, Introduction & General Description of Plant, Through Section 17.2, Quality Assurance for Station Operation  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Fitness for Duty +, Shutdown Margin +, Ultimate heat sink +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Incorporated by reference +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Control of Heavy Loads +, Turbine Missile +  and Unidentified leakage +
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http://pbadupws.nrc.gov/docs/ML1117/ML11178A157.pdf  +
 
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