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

ACI-318 +, ACI-349 +  and ACI-447 +

ASCE 43-05 +, ASCE 4-16 +  and ASCE 4-13 +

Hydrogen +  and Lead +

10 CFR 50 +  and 10 CFR 50.54#f +

Initiating Events +  and Mitigating Systems +

05000315  +, 05000316  +  and 00315  +

Regulatory Guide 1.174 +, ML12053A340 +, ML12333A170 +, ML15194A015 +, ML16308A086 +, ML15097A196 +, AEP-NRC-2016-79, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident +, ML18011A217 +, AEP-NRC-2014-93, Inclusion of Beach Sand Layer in Seismic Risk Assessment Structures Response Modeling +, AEP-NRC-2014-25, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, ML17146A200 +, ML18017A963 +, ML100570203 +  and ML17146A206 +

EC-54959 +, EC-55035 +, EC-55458 +, EC-54649 +, EC-54611 +, EC-54911 +, EC-54651 +, EC-55034 +, EC-55973 +, EC-56066 +, EC-53363 +  and EC-53364 +

Indiana Michigan Power Co +  and Lies Q +

AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +, AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +  and AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic +

NEI 12-13 +  and NEI 12-06, Ne 12-06, Appendix H, Revision 2, H.4.3 Path 3: GMRS ≫ SSE ≪ IHS, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information +

NUREG-2115 +, NUREG/CR-6728 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

CAC:MF3873 +  and TAC:MF3873 +

Regulatory Guide 1.200 +, Regulatory Guide 1.122 +  and Regulatory Guide 1.17 +

1E-06 +, 5E-7 +, 1E-02 +, 1E-05 +, 5E-8 +, 1E-04 +, 0E-01 +, 13Q3208-RPT-005 +, 15C4313-RPT-007 +, 15C4313-CAL-010 +, 15C4313-RPT-003 +, 15C4313-RELAY +, 15C4313-Cal-024 +, 15C4313-Cal-026 +, 15c4313-RPT-007 +, 15C4313-Cal-020 +, 12-0ME-250-SDG2 +, 15C4313-RPT-001 +, 15C4113-RPT-007 +, 15C4313-CAL-021 +, 15C4313-System +, 15C4313-CAL-023 +, 15C4313-PNLS +, 15C4313-CAL-Limi +, 15C4313-TB1 +, 15C4313-RPT-FPTE +, 15C4313-CEIL-3 +, 15C4313-CEIL-2 +, 15C4313-CAL-026 +, 4a-4b +...

Colorado +, Washington +, California +, Michigan +  and Indiana +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Auxiliary Feed Water +  and Main Steam +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Mission time +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Finite Element Analysis +, FLEX +, Fukushima Dai-Ichi +, Large early release frequency +, Loss of Offsite Power +, Earthquake +  and Turbine Missile +

F-FLD-1 +, F-TFP-PNL +, F-SCIC-CONT1 +, F-NSCIB-TB1 +, F-SDG-AM +, F-BATCD-AM +, F-SCIC-AB1 +, F-SCIV-AB1 +, F-SCIB-CONT +, F-SCIB-LINER +, F-SCIB-AB +, F-SCIC-CONT1-SEISMIC +, F-SCIB-CONTC-SEISMIC +, F-A11-Failure +, F-NSCIB-Turbine +, F-SCIB-SC-I +, F-NS-Seismic-Induced +, F-A11-Relay +, F-FLD-Seismic-Induced +  and F-CR-Control +