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ML12340A595
Show incoming properties
Category
Legal-Exhibit
Accession number
ML12340A595  +
Atomic Element
Sodium +, Zirconium +, Lead +  and Titanium +
CFR
10 CFR 50 +  and 10 CFR 50.55a +
Committee
Committee To Review Generic Requirements +
Contact
SECY RAS +
Correspondence
RA-1429 +
Docket
05000247  +, 05000286  +, 00247  +  and 00286  +
Drawing
MSK-64 +
From
International Atomic Energy Agency (IAEA) +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +
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>.
ML12340A595 +, ML12340A595 +, ML12340A595 +, ML12340A595 +, ML12340A595 +, ML12340A595 +, ML12340A595 +, ML12340A595 +  and ML12340A595 +
Hours
0 d (0 hours, 0 weeks, 0 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
Issue date
June 29, 2012  +
Manufacturer
Westinghouse +
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01:24:10, 12 January 2025  +
NUREG
NUREG/CP-0077 +, NUREG/CP-0109 +, 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-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +
Page count
57  +
Procedure
ST +
Project stage
Request  +
RA
RA-1429 +
RAS
RAS 22867 +
Regulatory Guide
Regulatory Guide 1.45 +
SSC
07-97-105 +  and 2d-leakage +
Site
Indian Point +
Start date
June 29, 2012  +
State
Washington +  and New York +
System
Steam Generator +, Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Emergency Feedwater System +
Title
Official Exhibit - RIV000119-00-BD01 - Applicability of the Leak Before Break Concept, Report of the IAEA Extrabudgetary Programme on the Safety of WWER-440 Model 230 Nuclear Power Plants, Status Report on a Generic Safety Issue, IAEA-TECDO  +
To
Atomic Safety and Licensing Board Panel +
Topic
Safe Shutdown +, Non-Destructive Examination +, Safe Shutdown Earthquake +, Hydrostatic +, Finite Element Analysis +, Design basis earthquake +, Stress corrosion cracking +, Earthquake +, Pressure Boundary Leakage +, Backfit +, Water hammer +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML1234/ML12340A595.pdf  +
Vendor
Framatome +
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