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ML20149A898
Show incoming properties
Category
NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT
Accession number
ML20149A898  +
Atomic Element
Boron +, Iodine +, Cesium +, Carbon +, Oxygen +, Hydrogen +, Zirconium +  and Lead +
CFR
10 CFR 50.109 +  and 10 CFR 50.55a +
Cornerstone
Initiating Events +  and Mitigating Systems +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +
Generic letter
NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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>.
ML20149A898 +, ML20149A898 +, ML20149A898 +, ML20149A898 +, ML20149A898 +  and ML20149A898 +
Issue date
June 30, 1997  +
Manufacturer
Westinghouse +
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>.
22:15:29, 24 May 2025  +
NRC form
NRC Form 335 +  and NRC Form 334 +
NUREG
NUREG/CR-4550 +, NUREG/CR-6144 +, NUREG/CR-4840 +, NUREG/CR-6372 +, NUREG/CR-5928 +, NUREG/CR-2300 +, NUREG/CR-4551 +, NUREG/CR-4691 +, NUREG/CR-6338 +, NUREG-0492, Summary of 870617-18 Meetings W/Util Re Review of Licensee Draft Proposal Re Specific Sections of Upgraded Tech Specs. List of Attendees & Agenda Encl +, NUREG/CR-5032 +, NUREG/CR-4839 +, NUREG/CR-6025 +, NUREG/CR-6119 +, NUREG/CR-5535 +  and NUREG/CR-2728 +
Page count
150  +
Power source
4V +
Procedure
Emergency Operating Procedure +
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.
ML20149A898 +
Project stage
Draft Other  +
SSC
1E-6 +
Scram
Manual Scram +  and Automatic Scram +
Start date
June 30, 1997  +
State
Utah +, Washington +, Idaho +  and New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +  and Emergency Core Cooling System +
Title
The Use of PRA in RISK-INFORMED Applications.Draft Rept for Comment  +
Topic
Safe Shutdown +, High winds +, Ultimate heat sink +, Mission time +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, Finite Element Analysis +, Shift Technical Advisor +, Large early release frequency +, Loss of Offsite Power +, Earthquake +, Scaffolding +, Weak link +, Fatality +  and Manual Operator Action +
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http://pbadupws.nrc.gov/docs/ML2014/ML20149A898.pdf  +
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