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Licensee Event Report, TEXT-SAFETY REPORT  and LICENSEE EVENT REPORT (SEE ALSO AO RO)

Nitrogen +  and Lead +

05000482  +  and 00482  +

Turbine Trip +  and Reactor Trip +

WOLF CREEK NUCLEAR OPERATING CORP. +  and Angus M +

05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +, 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +  and 05000482/LER-1998-001, :on 980304,noted That Pressurizer Code Safety Valves Indicate Five Random Failures in Last Twelve Tests. Caused by Incapability of Valves to Meet Restrictive Tolerance of +/-1% of Valve Pressure.Ts Will Be Amended +

NRC Form 366A +  and NRC Form 366, Licensee Event Report +

NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and 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 +

Reactor Coolant System +, Main Steam Safety Valve +, Emergency Core Cooling System +  and Main Steam +

TS-4.0.5 +  and TS-3.4.2.2 +

Unanalyzed Condition +  and Loop seal +

https://lersearch.inl.gov/Index.aspx?Page=PDFView?Doc::4821998001R00.pdf  +  and http://pbadupws.nrc.gov/docs/ML2023/ML20238E755.pdf  +