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ML20059C731
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Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
ASME section
ASME Section XI +
Accession number
ML20059C731  +
Atomic Element
Uranium +, Thorium +  and Lead +
CFR
10 CFR 20 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 72 +, 10 CFR 50.55a +  and 10 CFR 550.55A +
CY
CY 1993 +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
SECY-91-270 +, SECY-92-219 +, SECY-92-290 +, SECY-92-337 +, CY 1993 +  and SECY 270 +
Docket
05000373  +, 05000374  +  and 05000400  +
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>.
ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +, ML20059C731 +  and ML20059C731 +
Hurricane
Hurricane Andrew +
INPO document
INPO-91-018 +
Issue date
January 30, 1993  +
Manufacturer
Westinghouse +
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08:09:42, 17 December 2024  +
NRC information notice
Information Notice 92-61 +
NUREG
NUREG/BR-0058 +, NUREG-1462, Notification of 921209 Meeting w/ABB-C-E in Rockville,Md to Discuss Status of Closure of Open Items in Draft SER for Sys 80+ (NUREG-1462).Meeting Agenda Encl +  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
38  +
Person
Jeff Circle +, Michael Case +, Annette Vietti-Cook +, Ralph Beedle +, Meena Khanna +, Tony Gody +, Samuel Lee +  and John Brons +
Procedure
ESP +  and Emergency Operating Procedure +
Regulatory Guide
Regulatory Guide 1.9 +
SECY
SECY-91-270 +, SECY-92-219 +, SECY-92-290 +, SECY-92-337 +  and SECY 270 +
SSC
10E-9 +
Site
Harris +  and LaSalle +
Start date
January 30, 1993  +
State
Washington +, Idaho +  and New York +
System
Steam Generator +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Main Turbine +, Main Steam Line +, Safety Relief Valve +  and Main Condenser +
Test
Post maintenance test +
Title
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip  +
To
Advisory Committee on Reactor Safeguards +
Topic
Reactor Vessel Water Level +, High Radiation Area +, Systematic Assessment of Licensee Performance +, License Renewal +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML2005/ML20059C731.pdf  +
Vendor
Vega +
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