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ML18200A080
Show incoming properties 
Category
Letter  and Inservice/Preservice Inspection and Test Report
Accession number
ML18200A080  +
Atomic Element
Nitrogen +, Sodium +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#z1 +, 10 CFR 50.55a#a +, 10 CFR 50.55a#z2 +, 10 CFR 50.55a#z +, 10 CFR 50.55a#b3ii +  and 10 CFR 50.55a#b3ivA +
Code case
ASME Code Case OMN-21 +  and ASME Code Case OMN-19 +
Docket
05000373  +, 05000374  +  and 00373  +
Document
Regulatory Guide 1.192 +, ML17024A265 +, ML14178A769 +, ML16014A174 +, ML15134A002 +, ML14337A449 +, ML15030A232 +, ML072620373 +  and ML080930122 +
Engineering change
EC-358662 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Exelon +  and Trafton W +
GE report
MPR-1807 +
General design criterion
GDC 57 +  and GDC 56 +
Generic letter
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, 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>.
ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +, ML18200A080 +  and ML18200A080 +
ISTC
ISTC-5221 +, ISTC-3522 +  and ISTC-3521 +
In package
ML18200A230 +
Issue date
July 18, 2018  +
Letter
RA06-063, Proposed Third Ten-Year Interval Inservice Testing Program +  and ML20097C885 +
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>.
22:21:03, 5 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 +
Operating procedure
OP-3 +
Page count
174  +
Procedure
ST +, SAP +, RT +, TP +, CP +, ST-0 +, TP-05 +, TP-10 +, TP-12 +, TP-13 +, TP-03 +, TP-01 +, TP-04 +, TP-02 +, TP-06 +, ST-C +, TP-07 +, TP-08 +, TP-09 +, TP-11 +  and ST-LAS-PLAN +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.192 +
SR
SR-3.4.6.1 +, SR-3.6.1.1.1 +  and SR-3.3.n.2 +
SSC
2B21-F010A +, 2B21-F022C +, 1E12-F041A +, 1E51-F040 +, 1E12-F041C +, 1B21-F032A +, 2E51-F028 +, 2B21-F028C +, 2B21-F028A +, 2B21-F022A +, 1E51-C003 +, 1E51-C001 +, 1E22-C001 +, 1G33-F001 +, 1B21-F028C +, 1B21-F022A +, 1E22-F005 +, 1E51-F030 +, 1E21-C001 +, 1E12-C002A +, 1B21-F010A +, 2E12-F050A +, 1B21-F070 +, 2E51-C001 +, 1E12-F050A +, 1E12-C300A +, 1E22-C002 +, 1E22-C003 +, 1E12-C002B +, 1B21-F361 +...
Scram
Automatic Scram +
Site
LaSalle +
Site license
LaSalle +
Start date
July 18, 2018  +
State
Washington +  and Illinois +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, High Pressure Core Spray +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Main Steam +
TS
TS-3.5.3 +, TS-3.6.3 +, TS-3.4.4 +, TS-3.1.7 +, TS-3.6.3.2 +, TS-3.6.1.5 +, TS-3.5.1.1 +, TS-3.5.2.3 +  and TS-3.5.3.1 +
Title
Submittal of Fourth 10-Year Interval Inservice Testing (IST) Program Plan  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Packing leak +, Stroke time +, Squib +, Scram Discharge Volume +, Excess Flow Check Valve +, Cold shutdown justification +, Power-Operated Valves +, Power Operated Valves +, Fuel cladding +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1820/ML18200A080.pdf  +
 
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