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ML20062G031
Show incoming properties 
Category
TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST REPORT
ANSI code
ANSI N45.4-1972 +
Accession number
ML20062G031  +
Atomic Element
Copper +, Nitrogen +, Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix J +
Correspondence
PM-78-411, Forwards Reactor Containment Bldg Integrated Leak Rate Test for Subj Facil +
Docket
05000321  +, 00321  +, 00135  +  and 00900  +
From
Southern Nuclear +  and Manry M +
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ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +, ML20062G031 +  and ML20062G031 +
Hours
2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +
In package
ML20062G030 +
Issue date
June 30, 1978  +
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>.
04:24:11, 17 December 2024  +
PM
PM-78-411, Forwards Reactor Containment Bldg Integrated Leak Rate Test for Subj Facil +
Page count
70  +
Procedure
RT +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20062G031 +
Project stage
Request  +
SSC
40C-F +  and 6MA-2-AH +
Site
Hatch +
Site license
Hatch +
Start date
June 30, 1978  +
State
Texas +, Georgia +  and Washington +
System
Feedwater +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +  and Main Steam +
Title
Reactor Containment Bldg Integrated Leakage Rate Test. Type a & Suppl Verification Tests Performed in Accordance W/Tech Specs Using Formulas from ANSI N45.4-1972 & BN-Top-1, Rev 1  +
Topic
Reactor Vessel Water Level +  and Integrated leak rate test +
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http://pbadupws.nrc.gov/docs/ML2006/ML20062G031.pdf  +
 
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