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ML19354D797
Show incoming properties
Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS
Accession number
ML19354D797  +
Atomic Element
Boron +, Nitrogen +, Hydrogen +, Lead +  and Tin +
Docket
05000482  +  and 00482  +
Drawing
FC-005 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Brookhaven National Laboratory +, Fresco A +  and Shier W +
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ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +, ML19354D797 +  and ML19354D797 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML19354D796 +
Issue date
December 31, 1989  +
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>.
21:30:26, 23 December 2024  +
NUREG
NUREG/CR-4550 +  and NUREG/CR-2497, Forwards Draft Abstract of NUREG/CR-2497, Precursors to Potential Severe Core Damage Accidents:1969-79. Comments Requested by 820220 +
Page count
156  +
Procedure
CP +, Emergency Plan +  and ES.34A +
SSC
1so-lation +
Scram
Manual Scram +  and Automatic Scram +
Site
Wolf Creek +
Start date
December 31, 1989  +
State
Washington +, Idaho +  and New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +
Title
Draft Rev 0 to Wolf Creek Generating Station Risk-Based Insp Guide (Based on Generic Insights from PRAs for Westinghouse Pwrs)  +
To
NRC +
Topic
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Mission time +, Probabilistic Risk Assessment +, Feedwater Controller Failure +, Loss of Offsite Power +, Fuel cladding +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1935/ML19354D797.pdf  +
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