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ML20148C959
Show incoming properties 
Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME section
ASME Section XI +
Accession number
ML20148C959  +
CFR
10 CFR 50 +, 10 CFR 50.55a#g +  and 10 CFR 50.55a#g6i +
Docket
05000298  +  and 00298  +
From
Office of Nuclear Reactor Regulation +
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ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +, ML20148C959 +  and ML20148C959 +
In package
ML20148C951 +
Issue date
January 13, 1988  +
Letter
NLS8600248, Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes +  and PNO-IV-84-013B, on 840615,licensee Determined That Water Level in Missouri River Had Reached 897 Feet Above Mean Sea Level +
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>.
17:05:30, 11 December 2024  +
Page count
9  +
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ML20148C959 +
Project stage
Request  +
Site
Cooper +
Start date
January 13, 1988  +
State
Nebraska +  and Idaho +
System
Feedwater +, Service water +, Primary containment +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Control Rod +  and Main Steam +
Title
Safety Evaluation Concluding That Inservice Testing Program Submitted w/860730 Ltr as Modified in Subj Safety Evaluation Will Provide Reasonable Assurance of Operational Readiness of safety-related Pumps & Valves  +
Topic
Stroke time +, Cold shutdown justification +  and Power Operated Valves +
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http://pbadupws.nrc.gov/docs/ML2014/ML20148C959.pdf  +
 
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