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ML21286A364
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Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML21286A364  +
CFR
10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.49b#3 +  and 10 CFR 54.21#c1 +
Docket
05000259  +, 05000260  +  and 05000296  +
From
Tennessee Valley Authority +
Generic letter
NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +
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ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +, ML21286A364 +  and ML21286A364 +
IEEE
IEEE 323-1971 +
In package
ML21286A574 +
Issue date
October 4, 2021  +
Letter
ML18025B687 +, IR 05000259/1988031 +  and ML18029A789 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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02:46:54, 28 November 2024  +
NUREG
NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
10  +
Project reference
CAC:MF6741 +
Project stage
Request  +
Site
Browns Ferry +
Start date
October 4, 2021  +
State
Tennessee +
System
Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Primary Containment Isolation System +, Primary containment +, Reactor Recirculation Pump +, Core Spray +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Core Standby Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-1.1 +
Title
Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Section 7.1, Summary Description  +
To
Office of Nuclear Reactor Regulation +
Topic
Reactor Vessel Water Level +, Anticipated operational occurrence +, Abnormal operational transient +, Main Steam Line Radiation Monitor +, License Renewal +, Power Uprate +  and Overspeed +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2128/ML21286A364.pdf  +
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