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

10 CFR 50.55a +, 10 CFR 50.55a#z1 +, 10 CFR 50.55a#g6iiD +  and 10 CFR 50.55#a +

ASME Code Case N-729-1 +, ASME Code Case N-729 +, ASME Code Case N-729-4 +  and ASME Code Case N-729-6 +

05000261  +  and 00261  +

ML15327A367 +, ML041680506 +, L-2017-026, Inservice Inspection Plans Fourth Ten-Year Interval Unit 1 Relief Request 12 +, ML17044A440 +, ML14275A460 +, ML17018A283 +, ML14290A140 +, ML14363A409 +, ML15201A067 +, ML15259A004 +, ML15156A906 +, ML15104A192 +, ML14283A044 +, ML15091A687 +, ML15036A252 +, ML15349A956 +, ML14273A011 +, ML16076A431 +, ML16292A761 +, ML17299B333 +, RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 +, ML17219A174 +, 1CAN061601, Request for Alternative from Volumetric/Surface Examination Frequency - Requirements of ASME Code Case N-729-1 - Arkansas Nuclear One, Unit 1 +, NL-15-0718, Proposed Inservice Inspection Alternative FNP-ISI-ALT-17, Version 2.0 +, LR-N15-0036, Request for Relief from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth (4th) 10-Year Interval +, AEP-NRC-2014-99, Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code N-729-1 Request Number Isir 04-02 +, RNP-RA/14-0124, Response to Request for Additional Information Associated with Relief Request (RR)-11 for Relief from Volumetric/Surface Examination Frequency Requirements to ASME Code Case N-729-1 +, RNP-RA/14-0092, Relief Request (RR)-11 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1 +, L-2014-246, Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request No. 8, Revision 0 +, 1CAN041402, Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1 +...

MRP-110 +, MRP-375 +  and MRP-111 +

Duke Energy +  and Ellis K +

RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +, RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +  and RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head +

TAC:MF4801 +  and EPID:L-2017-LLR-0089 +

Washington +  and Arkansas +

Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, VT-2 +  and Stress corrosion cracking +