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ML061800088
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Category
Letter  and Technical Specifications
ANSI code
ANSI/ANS-3.5-1998 +
Accession number
ML061800088  +
CFR
10 CFR 50.90 +  and 10 CFR 51.22#c9 +
Contact
Brown Eva, NRR/DLPM, 415-2315 +
Docket
05000259  +  and 00259  +
Equipment trip
Turbine Trip +
From
Tennessee Valley Authority +  and Crouch W +
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ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +, ML061800088 +  and ML061800088 +
Inspection Manual Chapter
NRC Inspection Manual 3812 +  and NRC Inspection Manual 7208 +
Inspection procedure
IP 72580 +, IP 72582 +, IP 72517 +, IP 72514 +  and IP 72510 +
Issue date
May 16, 2006  +
Letter
ML053400203 +  and ML051150476 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
13:14:46, 15 January 2025  +
Page count
42  +
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ML061800088 +
Project
TAC:MC3743 +
Project reference
TAC:MC3743 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.68 +
Report
NEDC-32424P +
SSC
1A-BFN +, 2C-BFN +, 1C-BFN +, 6A-C +, 5M-C +, 4T-C +  and 1E-BFN +
Scram
Automatic Scram +
Site
Browns Ferry +
Start date
May 16, 2006  +
State
Tennessee +, Georgia +, Maryland +, Washington +  and Alabama +
System
Steam Generator +, Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
Title
Technical Specifications Change TS-431 Request for Extended Power Uprate Operation  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Half scram +, Anticipated operational occurrence +, Abnormal operational transient +, Feedwater Heater +, Scram Discharge Volume +, Feedwater Controller Failure +, Loss of Offsite Power +, Earthquake +, Power Uprate +, Overspeed trip +, Overspeed +  and Loss of condenser vacuum +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML0618/ML061800088.pdf  +
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