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Response to Request for Additional Information (RAI)  and Letter type:L

IWB-3500 +, IWB-2500 +, IWC-2500 +, IWC-3500 +, IWC-3510 +, IWA-2430 +  and IWA-3500 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Nickel +, Carbon +  and Tungsten +

10 CFR 54 +, 10 CFR 50.55a +  and 10 CFR 50.55a#z1 +

L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9 +, L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8 +  and L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +

05000346  +  and 00346  +

ML102450572 +, L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8 +, ML20225A141 +, ML20258A002 +, ML21034A576 +, ML20352A155 +, ML21081A136 +, ML21167A355 +, L-21-214, Proposed Inservice Inspection Alternative RR-A2 +, ML21321A379 +  and NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections +

Turbine Trip +  and Reactor Trip +

Tony Brown +  and Energy Harbor Nuclear Corp +

L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +, L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +  and L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 0.00579 d (0.139 hours, 8.267196e-4 weeks, 1.9025e-4 months)  +

L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9 +, L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8 +  and L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 +

NUREG/CR-6260 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

SP-SG-1-1-W65 +, SP-SG-1-1-W69 +, SP-SG-1-2-W65 +  and SP-SG-1-2-W69 +

EPID:L-2020-LLR-0097 +, EPID:L-2020-LLR-0109 +  and EPID:L-2021-LRR-0067 +

205S-B6 +, 205S-O +  and 205S-SR-02-R0 +

Ohio +, Connecticut +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Decay Heat Removal +, Control Rod +  and Main Steam +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Loop seal +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Finite Element Analysis +, Feedwater Heater +, License Renewal +, Earthquake +, Pressure boundary leak +, Through-Wall Leak +, Power change +, Unidentified leakage +  and Unidentified leak +