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ML20077H863
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Category
TEXT-SAFETY REPORT  and REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
ASME section
ASME Section IX +  and ASME Section II +
Accession number
ML20077H863  +
Atomic Element
Boron +, Iodine +, Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Lithium +, Sulfur +, Chromium +  and Tin +
CFR
10 CFR 50 +
Docket
05000289  +  and 00209  +
Equipment trip
Reactor Trip +
From
FirstEnergy +  and Moran T +
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>.
ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +, ML20077H863 +  and ML20077H863 +
Hours
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML20077H862 +
Isotope
Tritium +  and N-16 +
Issue date
March 29, 1983  +
Letter
ML20078B558 +  and ML20028C053 +
Manufacturer
Westinghouse +
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>.
06:28:25, 15 December 2024  +
NUREG
NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +  and NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +
Page count
169  +
Power source
4V +
Procedure
ES +, SP +, SP-1101-22-009 +, SP-1101-22-008 +, SP-1101-12-030 +, SP-1101-12-029 +, SP-1101-22-006 +  and SP-1101-22-007 +
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ML20077H863 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.109 +
SSC
52E-3 +  and 28E-2 +
Site
Crane +
Start date
March 29, 1983  +
State
Maryland +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Main Steam +  and Emergency Feedwater System +
Title
Rev 2 to Topical Rept 008, Assessment of TMI-1 Plant Safety for Return to Svc After Steam Generator Repair  +
Topic
Boric Acid +, Non-Destructive Examination +, Grab sample +, Stress corrosion cracking +, Eddy Current Testing +, Liquid penetrant +, Pressure Boundary Leakage +, Power change +, Flow Induced Vibration +, Eddy Current Test +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML2007/ML20077H863.pdf  +
WCAP
WCAP-10084 +
Westinghouse report
WCAP-10084 +
 
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