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ML20059C764
Show incoming properties 
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20059C764  +
Atomic Element
Uranium +, Hydrogen +  and Tin +
CFR
10 CFR 70 +  and 10 CFR 21#50 +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
SECY-93-020 +, SECY-92-381 +, SECY-91-161 +, SECY-92-393 +  and SECY-88-203 +
Docket
05000333  +
Equipment trip
Reactor Trip +
From
Advisory Committee on Reactor Safeguards +  and Shewmon P +
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>.
ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +, ML20059C764 +  and ML20059C764 +
Hours
1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +
Hurricane
Hurricane Andrew +
Issue date
May 7, 1993  +
Letter
ML20128G231 +
Manufacturer
General Electric +  and 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>.
08:09:12, 17 December 2024  +
NUREG
NUREG/CR-5420 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
43  +
Person
Ralph Beedle +  and Michael Colomb +
Procedure
RAP +  and CP-1 +
SECY
SECY-93-020 +, SECY-92-381 +, SECY-91-161 +, SECY-92-393 +  and SECY-88-203 +
SSC
3c5-3084 +
Site
FitzPatrick +
Start date
May 7, 1993  +
State
Connecticut +, Washington +, California +  and Idaho +
System
Steam Generator +, HVAC +, Core Spray +, Residual Heat Removal +, Remote shutdown +, Decay Heat Removal +  and Control Rod +
Title
Summary of 394th ACRS Meeting on 930211-13 in Bethesda,Md Re Key Policy Issues for Advanced Reactor Designs,Schedules for NRC Review of Proposed Reactor Designs & Reactor Operating Experience on Restart of FitzPatrick Nuclear Plant  +
To
Advisory Committee on Reactor Safeguards +
Topic
High Radiation Area +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, License Renewal +, Pre-application +  and Seal weld +
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http://pbadupws.nrc.gov/docs/ML2005/ML20059C764.pdf  +
 
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