AEP-NRC-2010-50, Notification of Intent to Apply Previously Approved 10 CFR Part 50 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities
AEP-NRC-2010-33, Submittal of Core Operating Limits Report (COLR) for Cycle 23 in Accordance with Technical Specification 5.6.5
AEP-NRC-2010-30, Schedule for Submittal of Revised Small Break Loss of Coolant Accident Analyses Addressing Residual Heat Removal System Spray Issue
AEP-NRC-2009-78, Comment (13) of Raymond Hruby on Behalf of Indiana Michigan Power on ANPR 50 Regarding Performance-Based Emergency Core Cooling System Acceptance Criteria
AEP-NRC-2009-70, Revised Technical Justification for Deviation from EPRI MRP-139 Inspection Requirements for Reactor Vessel Alloy 600/82/182 Welds at DC Cook Nuclear Plant
AEP-NRC-2009-54, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes
AEP-NRC-2009-58, Notification of MRP-139 Deviation
AEP-NRC-2009-51, Inservice Inspection Summary Report, Cycle 18, 2009 Refueling Outage
AEP-NRC-2009-42, Response to Request for Additional Information Regarding Relief Request (ISIR-28) for Use of Weld Inlays as an Alternate Repair Technique for Alloy 82/182 Dissimilar Metal Welds in Reactor Vessel Safe End-to-Primary Nozzles
AEP-NRC-2009-31, Core Operating Limits Report, Revision 0
AEP-NRC-2009-25, Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis
AEP-NRC-2009-17, Cycle 17 End of Life Moderator Temperature Coefficient Limit Report
AEP-NRC-2009-26, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-30
AEP-NRC-2009-47, Nine-Month Supplemental Response to Generic Letter 2008-01 Issued Pursuant to 10 CFR 50.54(f), Managing Gas- Accumulation in Emergency Core Cooling, Decay Heat Removal.