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ML17353A662
Show incoming properties 
Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
Accession number
ML17353A662  +
Atomic Element
Lead +  and Hydrogen +
Cornerstone
Emergency Preparedness +, Initiating Events +  and Mitigating Systems +
Docket
05000250  +, 05000251  +, 00250  +  and 00251  +
Equipment trip
Reactor Trip +
From
Croteau R +  and NRC (Affiliation Not Assigned) +
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>.
ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +, ML17353A662 +  and ML17353A662 +
Hours
0.00139 d (0.0333 hours, 1.984127e-4 weeks, 4.566e-5 months)  +
Issue date
April 24, 1996  +
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>.
13:34:45, 7 January 2025  +
NUREG
NUREG-4200 +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG/CR-4674, Forwards NUREG/CR-4674,Vols 9 & 10, 1988 Accident Sequence Precursor Rept. Rept Describes & Evaluates Significant Operational Events Reported by LERs for CY88. W/O Encl +  and NUREG/CP-4140 +
Page count
45  +
Procedure
RT +
SSC
1E-02 +, 1E-01 +  and 63E-s +
Site
Turkey Point +
Start date
April 24, 1996  +
State
Georgia +, Washington +  and Florida +
System
Steam Generator +, Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Residual Heat Removal +, Decay Heat Removal +  and Control Rod +
TS
TS-3.3 +
Title
Forwards Excerpts from Draft ASP Rept for 1982-83.Rept Documents ASP Program Analyses of Operational Events Which Occurred During Period 1982 - 1983  +
To
Plunkett T +  and NextEra Energy +
Topic
Probabilistic Risk Assessment +
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http://pbadupws.nrc.gov/docs/ML1735/ML17353A662.pdf  +
 
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