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Inservice/Preservice Inspection and Test Report, Code Relief or Alternative  and Letter type:NOC

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

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

05000498  +, 05000499  +, 00498  +  and 00499  +

ML15327A367 +, L-2017-026, Inservice Inspection Plans Fourth Ten-Year Interval Unit 1 Relief Request 12 +, ML17044A440 +, ML17018A283 +, ML15201A067 +, ML15259A004 +, ML15104A192 +, ML14283A044 +, ML15091A687 +, ML15030A008 +, ML15036A252 +, ML15125A361 +, ML15349A956 +, ML16076A431 +, ML16292A761 +, 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 +, ML17222A162 +, CP-201500430, Relief Request lB3-4 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Head Penetration Weld Inspection +  and L-PI-14-095, 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program +

MRP-115 +, MRP-375 +, MRP-117 +, MRP-237 +, MRP-335 +, MRP 117 +  and MRP-386 +

South Texas +  and Page M +

NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +, NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +  and NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) +

Texas +, Washington +  and Arkansas +

Steam Generator +  and Reactor Pressure Vessel +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Reactor Vessel Water Level +, VT-2 +  and Stress corrosion cracking +