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Inservice/Preservice Inspection and Test Report  and Letter type:U

Nitrogen +, Hydrogen +  and Lead +

10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#b3 +, 10 CFR 50.55a#f4 +, 10 CFR 50.55a#b3vi +, 10 CFR 50.55a#b6 +  and 10 CFR 50.55#a +

U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +  and U-601736, Forwards Rev 8 to Pump & Valve Testing Program Plan. Rev Will Change Stroke Time Frequency from Three Months to Cold Shutdown for Listed Valves +

05000461  +  and 00461  +

L-08-347, Eight Separate In-Service Testing Program 10 CFR 50.55a Alternatives Requests in Support of the Third Ten-Year Interval +  and RS-08-144, Request for Relief from ASME OM Code 5-Year Test Interval for Safety Relief Valves (Relief Request No. 2210) +

Turbine Trip +  and Reactor Trip +

ER-AA-321 +  and ER-AA-302-1006 +

Exelon +  and Kemper D +

MPR-1807 +  and MPR-2524-A +

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 +

U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +, U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +  and U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval +

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

NRC Inspection Manual 3387 +, NRC Inspection Manual 3383 +, NRC Inspection Manual 3384 +, NRC Inspection Manual 3385 +, NRC Inspection Manual 3386 +, NRC Inspection Manual 3388 +, NRC Inspection Manual 3389 +, NRC Inspection Manual 4421 +, NRC Inspection Manual 4422 +  and NRC Inspection Manual 3382 +

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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

SAP +, RT +, TST +, CP +  and Emergency Plan +

Regulatory Guide 1.11 +, Regulatory Guide 1.192 +  and Regulatory Guide 1.19.2 +

1E22-F004 +, 1B21-F032B +, 1E21-F005 +, 1E12-F041A +, 1E51-F040 +, 1E12-F042C +, 1E12-F041C +, 1B21-F032A +, 1E51-F063 +, 1E22-F012 +, 1B21-F022B +, 1E12-F004B +, 1E12-F004A +, 1E51-F031 +, 1B21-F047A +, 1E12-F025C +, 1E51-C003 +, 1E51-F066 +, 1E22-F035 +, 1E12-F005 +, 1B21-F028C +, 1B21-F022A +, 1B21-F028B +, 1B21-F028D +, 1E32-F001A +, 1E12-F024A +, 1E12-F064A +, 1E51-F068 +, 1E12-F037A +, 1E12-F042A +...

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

TS-3.6.1.3 +, TS-3.6.2.2 +, TS-3.6.1.4 +  and TS-3.6.5.3 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Packing leak +, Stroke time +, Squib +, Incorporated by reference +, Scram Discharge Volume +, Excess Flow Check Valve +, Cold shutdown justification +, Power-Operated Valves +, Power Operated Valves +, Scaffolding +, Grace period +, Thermal fatigue +  and Water hammer +