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ML051300624
Show incoming properties 
Category
Report  and Technical
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML051300624  +
Atomic Element
Boron +, Sodium +  and Lead +
CFR
10 CFR 100 +  and 10 CFR 50.72 +
Correspondence
L 59 +
Cross cutting aspect
S.0(o) +
Docket
05000289  +
Equipment trip
Reactor Trip +
From
AmerGen +
Generic letter
NRC Generic Letter 04-01 +
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>.
ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +, ML051300624 +  and ML051300624 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +
Issue date
May 3, 2005  +
L
L 59 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
00:20:05, 16 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NUREG
NUREG/CR-3464 +, NUREG/CR-3475 +  and NUREG-1019, Forwards Response to 860915 & 30 Questions Re Steam Generator Tube Rupture & Turbine Bypass Valve +
Page count
110  +
Procedure
ST +  and TOP +
Project stage
Request  +
SSC
460E-6 +, 10I-224-E520-063 +, 3MU-1 +, 8OSdeL-L +  and 12R-IR15 +
Site
Crane +
Start date
May 3, 2005  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Pressure Vessel +, Main Steam Safety Valve +, Decay Heat Removal +  and Main Steam Line +
TS
TS-4.19 +
Title
Draft ECR 02-01121, Rev. 2, Inspection Acceptance Criteria and Leakage Assessment Methodology for TMI OTSG Kinetic Expansion Examinations  +
To
Office of Nuclear Reactor Regulation +
Topic
Shutdown Margin +, Non-Destructive Examination +, Finite Element Analysis +, Stress corrosion cracking +, Flow Induced Vibration +, GOTHIC +, Eddy Current Test +  and Leak-Before-Break +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML0513/ML051300624.pdf  +
Vendor
Framatome +  and MPR Associates +
 
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