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Inservice/Preservice Inspection and Test Report  and Letter type:

Boron +  and Nitrogen +

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.55a +, 10 CFR 50.55a#z1 +, 10 CFR 50.55a#z +, 10 CFR 50.55a#b3xi +, 10 CFR 50.55a#b3i +, 10 CFR 50.55a#b3iv +, 10 CFR 50.55a#b3iiD +, 10 CFR 50.55a#b3x +, 10 CFR 50.55#a +  and 10 CFR 50#a +

ASME Code Case OMN-13 +, ASME Code Case OMN-16 +  and Code Case OMN-20, Inservice Test Frequency +

2CAN091901, Entergy Operations, Inc. - Request for Alternatives Subject to the Fifth 10-Year Interval of the Inservice Testing Program +, 2CAN022001, Response to Request for Additional Information Related to Alternative VRR-ANO2-2019-1 +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +  and STC-3521 +

05000368  +  and 00368  +

ML13295A020 +, ML18117A264 +, ML093370316 +, ML091801039 +  and ML20121A193 +

EN-DC-174 +  and EN-DC-332 +

Entergy +  and Keele R +

2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +, 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +  and 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval +

ISTC-3630 +, ISTC-3522 +  and ISTC-3521 +

NUREG/CP-0137 +  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 +

ST +, RT +  and TOP +

CAC:MG0064 +, TAC:ME2407 +, TAC:ME0921 +  and EPID:L-2019-LLR-0086 +

2CV-5043-2 +, 2K-4A +, 2P-60A +, 2K-4B +, 2P-7A +, 2P-7B +, 2VE-1A +, 2K-48 +, 2CV-1010-1 +, 2CV-5035-1 +, 2BS-3A +, 2BS-3B +, 2PSV-5089 +, 2CV-5017-1 +, 2P-36C +, 2E-35A +, 2T-2D +, 2T-2C +, 2P-4C +, 2T-3 +, 2P-35A +, 2PSV-5082 +, 2CV-1036-2 +, 2CV-1074-1 +, 2P-89B +, 2CV-0340-2 +, 2P-89A +, 2P-36A +, 2HPS-36 +, 2HPS-38 +...

Washington +, Idaho +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, HVAC +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

TS-3.0.3 +, TS-3.5.1 +, TS-3.5.2 +, TS-3.6.1.6 +, TS-3.5.4 +  and TS-4.5.2.f +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Stroke time +, Incorporated by reference +, Cold shutdown justification +  and Power Operated Valves +

Cooling Tower +  and Lake Dardanelle +