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ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program
Show incoming properties 
Category
Inservice/Preservice Inspection and Test Report  and Letter type:ET
ASME section
ASME Section XI +
Accession number
ML032471663  +
Atomic Element
Boron +, Sodium +  and Hydrogen +
CFR
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#f +, 10 CFR 50.55a#b2viii +, 10 CFR 50.55a#b3iii +, 10 CFR 50.55a#f3v +  and 10 CFR 50.55a#b3iv +
Cross cutting aspect
P.4(t) +
Docket
05000482  +
Drawing
FC-1 +  and Drawing 3.1-1 +
Equipment trip
Reactor Trip +
From
Wolf Creek +  and Scherich K +
Generic letter
NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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>.
ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +, ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +  and ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +
Isotope
H-3 +
Issue date
August 26, 2003  +
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>.
12:54:58, 16 January 2025  +
NUREG
NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
187  +
Procedure
EP-2 +, EP-1 +, EP-201 +, EP-210 +, EP-207 +  and EP-206 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.137 +
SR
SR-3.5.2.1 +, SR-3.6.3.7 +, SR-3.4.14.1 +  and SR-3.6.3 +
SSC
2PR-1 +, 2PR-2 +, 2PR-3 +, 29B-002 +, 23D-001 +, 2PR-4 +, 2PR-X +, 2VR-XX +, 2VR-1 +, 2VR-2 +, 2VR-3 +, 2VR-4 +, 2VR-5 +, 2VR-7 +, 2VR-6 +  and 2VR-8 +
Site
Wolf Creek +
Start date
August 26, 2003  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Steam +  and Containment Spray +
TS
TS-3.4.14 +, TS-3.0.3 +, TS-3.5.2 +  and TS-3.4.12 +
Title
Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Boric Acid +, Stroke time +  and Water hammer +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML0324/ML032471663.pdf  +
 
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