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ML20132B730
Show incoming properties 
Category
OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING  and TEXT-LICENSE APPLICATIONS & PERMITS
ASME section
ASME Section XI +, ASME Section III +  and ASME Section I +
Accession number
ML20132B730  +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.4 +, 10 CFR 50.91 +, 10 CFR 50.91#b1 +, 10 CFR 50.91#a1 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +
Docket
05000259  +, 05000260  +, 05000296  +, 00259  +  and 00260  +
From
Tennessee Valley Authority +  and Abney T +
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>.
ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +, ML20132B730 +  and ML20132B730 +
In package
ML20132B735 +
Issue date
December 11, 1996  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +  and Target Rock +
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>.
15:20:54, 12 December 2024  +
NUREG
NUREG-1433 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
20  +
Project stage
Request  +
Report
NEDC-31753P +, NEDC-which +  and NEDC-results +
Site
Browns Ferry +
Site license
Browns Ferry +
Start date
December 11, 1996  +
State
Tennessee +, Georgia +, Maryland +, Washington +  and Alabama +
System
Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Core Spray +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.6.D +, TS-6.9.1.7 +, TS-4.6.D +  and TS-2.2.A +
Title
Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS-386,increasing TS 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity.Rev 3 to J11-02761SRLR Rept Encl  +
To
Office of Information Resources Management +
Topic
Anticipated operational occurrence +, Abnormal operational transient +, Earthquake +, Fuel cladding +  and Overspeed trip +
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http://pbadupws.nrc.gov/docs/ML2013/ML20132B730.pdf  +
 
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