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ML021710227
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Category
Inservice/Preservice Inspection and Test Report
ASME section
ASME Section XI +, ASME Section III +  and ASME Section X +
Accession number
ML021710227  +
Atomic Element
Nitrogen +, Oxygen +, Sodium +, Hydrogen +  and Tin +
CFR
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.55a +  and 10 CFR 50.55a#f4iv +
Code case
ASME Code Case N-465 +
Cross cutting aspect
P.1(i) +
Docket
05000263  +
From
Xcel Energy +
Generic letter
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +, ML021710227 +  and ML021710227 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +
Issue date
June 6, 2002  +
Letter
05000263/LER-1993-007-01, :on 930604,ESF Actuation Occurred Due to Loss of Reactor Protection Sys Power Supply.Replaced Failed Relay & Returned Motor Generator Set to Svc +
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22:54:17, 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
123  +
Person
None none +
Procedure
AM +, ES +, ST +, SP +  and ST-90 +
Project reference
TAC:M88972 +, TAC:M82638 +, TAC:M86939 +  and TAC:M90341 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.147 +  and Regulatory Guide 1.26 +
SSC
1B-i +, 07-11-14A +, 09A-D +, E1WI-09 +, N2N-2K +, 0V-1729 +, 7RHRSW-12 +, 238w-2 +, W6DW-5 +  and 7RHRSW-18 +
Site
Monticello +
Start date
June 6, 2002  +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Residual Heat Removal Service Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Main Steam +
TS
TS-4.6.E +, TS-4.1 +, TS-4.2.1 +, TS-6.5 +  and TS-4.1.1 +
Title
Inservice Testing Program for Engineering Work Instruction, Revision 8  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
High Radiation Area +, Stroke time +, Squib +, Local Leak Rate Testing +, Scram Discharge Volume +, Excess Flow Check Valve +, Breakaway torque +, Power-Operated Valves +, Power Operated Valves +  and Water hammer +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML0217/ML021710227.pdf  +
 
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