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ML18025B878
Show incoming properties
Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC, TEXT-PROCUREMENT & CONTRACTS  and NUREG REPORTS
Accession number
ML18025B878  +
Atomic Element
Lead +
Cornerstone
Initiating Events +  and Mitigating Systems +
Docket
00259  +  and 05000259  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Sullivan J +, INC. +, EG&G +, ENERGY +, Mays S +, Bertucio R +, Leahy T +, Poloski J +, Sullivan W +  and Trainer J +
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>.
ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +, ML18025B878 +  and ML18025B878 +
Issue date
August 31, 1982  +
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>.
08:54:30, 7 January 2025  +
NRC bulletin
NRC Bulletin 79-27 +
NUREG
NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +
Page count
72  +
Person
None none +
Power source
4kV +  and 24V +
SSC
15W500-1 +, 45N-724-1 +, 45N-751-1 +, 15N500-1 +, 45N712-2 +, 45N712-3 +, 45H710-9 +  and 45H710-4 +
Scram
Manual Scram +
Site
Browns Ferry +
Start date
August 31, 1982  +
State
Tennessee +, Washington +, Idaho +  and Arkansas +
System
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Main Turbine +, Shutdown Cooling +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Core Standby Cooling System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +...
Title
Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix A-Event Trees. Docket No. 50-259.(Tennessee Valley Authority)  +
To
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +
Topic
Half scram +, Probabilistic Risk Assessment +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Overspeed +  and Loss of condenser vacuum +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML1802/ML18025B878.pdf  +
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