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ML18033A463
Show incoming properties 
Category
SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT
ASME section
ASME Section III +
Accession number
ML18033A463  +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.48 +  and 10 CFR 50 +
Control panel
25-32 +
Docket
05000259  +, 05000260  +, 05000296  +  and 00259  +
From
NRC OFFICE OF SPECIAL PROJECTS +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +
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ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +, ML18033A463 +  and ML18033A463 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +
In package
ML18033A462 +
Issue date
December 8, 1988  +
Letter
ML18033A319 +  and 05000259/LER-1985-051-01, :on 850925,cable Connecting Reactor Protection Sys Panel 9-17 Supply Breaker to Terminal Block Dried & Insulation Cracked.Caused by Loose Breaker Connection. Defective Cable Replaced W/Larger Gauge Cables +
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>.
07:08:51, 7 January 2025  +
NRC information notice
Information Notice 85-09 +
NUREG
NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +
Page count
26  +
Power source
4kV +
Procedure
SP +  and OSP +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML18033A463 +
Project stage
Request  +
Scram
Automatic Scram +  and Manual Scram +
Site
Browns Ferry +
Start date
December 8, 1988  +
State
Washington +  and Tennessee +
System
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Remote shutdown +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
Title
Safety Evaluation Accepting Util App R Submittal as Applied to Adequacy of Minimum Safe Shutdown Sys  +
Topic
Safe Shutdown +, Emergency Lighting +, Loss of Offsite Power +, Exemption Request +, Fuel cladding +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML1803/ML18033A463.pdf  +
 
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