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RA18-059, Inservice Testing Program Plan, Technical Position TP-05
Show incoming properties 
Category
Inservice/Preservice Inspection and Test Report
Accession number
ML18200A087  +
Atomic Element
Nitrogen +, Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.54 +
Cross cutting aspect
S.3(c) +  and S.4(c) +
Docket
05000373  +  and 05000374  +
Engineering change
EC-353154 +
From
Exelon +
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RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +, RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +  and RA18-059, Inservice Testing Program Plan, Technical Position TP-05 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +
ISTC
ISTC-5221 +
In package
ML18200A230 +
Isotope
Tritium +
Issue date
July 18, 2018  +
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22:20:56, 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 +
Page count
174  +
Procedure
ES +, ST +, RT +, TP +, CP +, ST-0 +, TP-05 +, TP-10 +, TP-12 +, TP-13 +, TP-03 +, TP-01 +, TP-02 +, TP-06 +, ST-C +, TP-07 +, TP-08 +, TP-09 +, TP-11 +, ST-LAS-PLAN +  and TP-OS +
Project stage
Request  +
SSC
1E22-F004 +, 2B21-F028D +, 1E22-F015 +, 2E12-F042A +, 2E12-F042B +, 1E12-F008 +, 2E51-F010 +, 1E51-F076 +, 2B21-F010A +, 2B21-F010B +, 1E21-F005 +, 2E22-F319 +, 1E12-F041A +, 1E51-F040 +, 1E12-F042C +, 1E12-F041C +, 1B21-F032A +, 1E12-F009 +, 2E51-F028 +, 1E51-F063 +, 1E22-F012 +, 1E12-F004C +, 2B21-F028C +, 2E51-F008 +, 1B21-F013K +, 1E12-F004B +, 2E12-F009 +, 2B21-F067D +, 1E51-F069 +, 1E51-F028 +...
Site
LaSalle +
Start date
July 18, 2018  +
System
Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, High Pressure Core Spray +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
Title
Inservice Testing Program Plan, Technical Position TP-05  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Grab sample +, Hydrostatic +, Squib +, Excess Flow Check Valve +, Power Operated Valves +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1820/ML18200A087.pdf  +
 
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