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ML20092C183
Show incoming properties 
Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
Accession number
ML20092C183  +
Atomic Element
Carbon +  and Lead +
CFR
10 CFR 50 +
Cross cutting aspect
P.1(o) +, S.3(i) +  and P.4(r) +
Docket
05000605  +  and 00605  +
Effective date
November 27, 1987  +
From
GENERAL ELECTRIC CO. +  and Recasha Mitchell +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
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>.
ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +, ML20092C183 +  and ML20092C183 +
Issue date
February 3, 1992  +
Manufacturer
General Electric +
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>.
16:31:25, 13 December 2024  +
NUREG
NUREG/CR-3464 +, NUREG/CR-4575 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +  and NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +
Page count
85  +
Procedure
AM +  and RT +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.70 +
Report
NEDE-24351 +
SSC
4e-A +, 3f-2 +, 3E3-3 +, 3E3-4 +, 3E3-6 +, 3E3-9a +, 3E3-8 +, 3ES-4 +, 4he-leaje +, 3Et-If +, 3EJ-1 +, 3EJ-il +, 3F4-CThe +, 3E4-9 +  and 3EJ1-Elastic +
Site
05000605 +
Start date
February 3, 1992  +
State
Washington +  and New York +
System
Feedwater +, Secondary containment +, Primary containment +, Reactor Pressure Vessel +, Main Steam Line +, Safety Relief Valve +  and Main Steam +
Title
Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend SSAR W/Response in Future Amend  +
To
Pierson R +, Office of Nuclear Reactor Regulation +  and Office of Information Resources Management +
Topic
Intergranular Stress Corrosion Cracking +, Earthquake +, Unidentified leak +, Thermal fatigue +, Water hammer +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML2009/ML20092C183.pdf  +
 
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