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ML20206B884
Show incoming properties 
Category
SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT
Accession number
ML20206B884  +
CFR
10 CFR 50 +  and 10 CFR 50 Appendix J +
Docket
05000331  +  and 00331  +
From
Office of Nuclear Reactor Regulation +
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>.
ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +, ML20206B884 +  and ML20206B884 +
In package
ML20205N261 +
Issue date
April 8, 1987  +
Letter
05000331/LER-1984-037, :on 840929,reactor Scrammed on hi-hi Intermediate Range Monitor Signals from Channel E & F. Cause May Be Attributed to Spurious Electrical Noise.Review of Design & Installation Performed +, 05000331/LER-1985-017, :on 850411,during Testing at Wyle Labs,Four Main Steam Safety/Relief Valves Lifted Below Min Allowable Pressure.Caused by Leakage Due to Minor Steam Cutting of Valve Seating Surfaces.Valves Rebuilt +  and ML20086L850 +
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07:20:56, 7 December 2024  +
Page count
4  +
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ML20206B884 +
Project stage
Approval  +
SSC
M0V-1902 +
Site
Duane Arnold +
Start date
April 8, 1987  +
State
Washington +  and Iowa +
System
Residual Heat Removal +, Containment Spray +  and Low Pressure Coolant Injection +
Title
Safety Evaluation Supporting Exemption from Certain Requirements of 10CFR50,App J Re Type C Testing of Containment Spray Isolation Valves  +
Topic
Exemption Request +  and Integrated leak rate test +
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http://pbadupws.nrc.gov/docs/ML2020/ML20206B884.pdf  +
 
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