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ML20136E999
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Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML20136E999  +
Atomic Element
Nitrogen +, Carbon +, Hydrogen +  and Tungsten +
Correspondence
NSD-NRC-97-5008 +, L 11 +  and NSD-NRC-97-4998, Forwards Informal Correspondence Previously Sent to NRC Re SSAR +
Docket
05200003  +
From
Diane Jackson +  and NRC (Affiliation Not Assigned) +
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>.
ML20136E999 +, ML20136E999 +, ML20136E999 +, ML20136E999 +, ML20136E999 +, ML20136E999 +, ML20136E999 +  and ML20136E999 +
Issue date
March 7, 1997  +
L
L 11 +
Manufacturer
Westinghouse +
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06:02:08, 12 December 2024  +
NRC bulletin
NRC Bulletin 88-11 +
NSD-NRC
NSD-NRC-97-5008 +  and NSD-NRC-97-4998, Forwards Informal Correspondence Previously Sent to NRC Re SSAR +
NUREG
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 +
Page count
54  +
Person
None none +
Regulatory Guide
Regulatory Guide 1.45 +
SSC
3E-5 +, 3B-1 +, 07-52-003 +, 3B-25 +, 3B-3 +, 3B-4 +, 3B-5 +, 3B-6 +, 3B-7 +, 3B-9 +, 3B-10 +, 3B-12 +, 3B-15 +, 3B-16 +, 3B-17 +, 3B-20 +, 3B-27 +, 3B-40 +, 3B-30 +, 3B-59 +, 3B-63 +, 3B-61 +, 3B-62 +, 4r-4 +, 10T-2 +, 16Y-1 +, 3B-Jl +  and 3f-msu +
Site
05200003 +
Start date
March 7, 1997  +
State
Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, HVAC +, Residual Heat Removal +, Shield Building +, Automatic Depressurization System +, Main Steam Safety Valve +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Summary of 970130 Telcon Between Listed Members of W & NRC Re W Retraction of Request to Apply leak-before-break Methodology to AP600 Feedwater Line  +
To
NRC (Affiliation Not Assigned) +
Topic
Safe Shutdown Earthquake +, Nondestructive Examination +, High Energy Line Break +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Liquid penetrant +, Dissimilar Metal Weld +, Water hammer +, Control Room Habitability +, Leak-Before-Break +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML2013/ML20136E999.pdf  +
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