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ML18036A698
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Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
ACAD
ACAD 91-017 +
ANSI code
ANSI N45.2 +
ASME section
ASME Section XI +
Accession number
ML18036A698  +
Atomic Element
Cobalt +, Nitrogen +, Carbon +, Hydrogen +, Lead +  and Tin +
CFR
10 CFR 50.59 +, 10 CFR 2.201 +  and 10 CFR 55#s45 +
Cornerstone
Emergency Preparedness +
Docket
05000260  +, 00260  +, 00259  +  and 00296  +
Emergency Facility
Technical Support Center +
From
Tennessee Valley Authority +  and Zeringue O +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +, ML18036A698 +  and ML18036A698 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +
Issue date
May 8, 1992  +
Letter
ML18036A453 +  and ML18036A385 +
Manufacturer
General Electric +
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06:39:20, 7 January 2025  +
NRC bulletin
NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas +
NUREG
NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
136  +
Procedure
ST +
Regulatory Guide
Regulatory Guide 1.68 +
SSC
07-87-009 +
Scram
Automatic Scram +
Site
Browns Ferry +
Site license
Browns Ferry +
Start date
May 8, 1992  +
State
Tennessee +, Georgia +, Maryland +, Washington +, California +  and Alabama +
System
High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Safety Parameter Display System +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Main Steam Line +, Control rod blade +  and Control Rod +
Title
Forwards Util self-assessment of Plant Performance During Period Beginning 910523 to Present,For NRC Consideration in Reviewing Unit 2 SALP & Documents Info Presented to NRC at 920417 Meeting in Atlanta,Ga  +
To
Office of Information Resources Management +
Topic
Fitness for Duty +, High Radiation Area +, Notice of Violation +, Foreign Material Exclusion +, Feedwater Heater +, Shift Technical Advisor +, Systematic Assessment of Licensee Performance +, Eddy Current Testing +, Fire Protection Program +, Unidentified leakage +  and Siren +
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http://pbadupws.nrc.gov/docs/ML1803/ML18036A698.pdf  +
 
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