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List of results

• ML043200167  + (Unit 1 - License Amendment Request, Extension of Implementation Period for License Amendment 294 (Technical Specification (TS) Change 00-14))
• LR-N12-0108, Unit 1 - License Amendment Request: Revision to Technical Specification (TS) 6.8.4.i, Steam Generator (SG) Program, and TS 6.9.1.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criteria  + (Unit 1 - License Amendment Request: Revision to Technical Specification (TS) 6.8.4.i, Steam Generator (SG) Program, and TS 6.9.1.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criteria)
• IR 07200077/2021401  + (Unit 1 - NRC Independent Spent Fuel Storage Security Inspection Report No. 07200077/2021401)
• AEP-NRC-2025-19, Unit 1 - Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) OG-23-63, NEI-03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements  + (Unit 1 - Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) OG-23-63, NEI-03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements)
• RA-08-116, Unit 1 - Notification of Expected Date of Transfer of Nuclear Units to Exelon Generation Company, LLC  + (Unit 1 - Notification of Expected Date of Transfer of Nuclear Units to Exelon Generation Company, LLC)
• ML031010008  + (Unit 1 - Proposed Exigent License Amendment Request Change No. WBN-TS-03-11 - Emergency Core Cooling System - Venting Hot Leg Injection Lines)
• ML053530127  + (Unit 1 - Proposed License Amendment Request Change No. WBN-TS-05-06 to Change the Steam Generator Secondary Side Water Level to Greater than or Equal to 321 Percent of Narrow Range)
• ML082750072  + (Unit 1 - Public Safety Evaluation by the Office of Nuclear Reactor Regulation Direct Transfer of Facility Operating Licenses from Amergen Energy Co., LLC to Exelon Generation Co., LLC)
• ML030700581  + (Unit 1 - Regulatory Framework for Restart of Unit 1)
• RS-16-069, Unit 1 - Report on Status of Decommissioning Funding for Shutdown Reactors and Reactors within 5 Years of Shutdown  + (Unit 1 - Report on Status of Decommissioning Funding for Shutdown Reactors and Reactors within 5 Years of Shutdown)
• ML14059A345  + (Unit 1 - Request for Additional Information, Requests for Relief PR-03 and PR-05, ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval)
• RS-22-044, Unit 1 - Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System  + (Unit 1 - Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System)
• EPID:L-2022-LLE-0014  + (Unit 1 - Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System)
• ML18114A282  + (Unit 1 - Response to 12/9&15/1977 Requesting FP&L to Complete Questionnaires Concerning Steam Generators and Standby Diesel Generators, FP&L Cant Justify Expenditure of Time by Personnel to Complete Questionnaire)
• ML032230507  + (Unit 1 - Response to Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2003-01: Control Room Habitability)
• RS-14-028, Unit 1 - Response to Request for Additional Information Related to 2013 Report on Status of Decommissioning Funding for Reactors  + (Unit 1 - Response to Request for Additional Information Related to 2013 Report on Status of Decommissioning Funding for Reactors)
• ML031630811  + (Unit 1 - Response to Request for Supplemental Information on the Regulatory Framework for the Restart of Unit 1)
• IR 05000289/2020401  + (Unit 1 - Security Baseline Inspection Report 05000289/2020401)
• ML12342A094  + (Unit 1 - Seismic Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima)
• NL-04-2362, Unit 1 - Special Report No. 2004-001-00, Inoperable Radiation Monitor R-60D  + (Unit 1 - Special Report No. 2004-001-00, Inoperable Radiation Monitor R-60D)
• ML14098A475  + (Unit 1 - Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident)
• 1CAN021501, Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report  + (Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report)
• RBG-46926, Unit 1 - Supplement to License Amendment Request (Lar), to Implement Changes Consistent with TSTF-163 on Diesel Generator Surveillance Requirements  + (Unit 1 - Supplement to License Amendment Request (Lar), to Implement Changes Consistent with TSTF-163 on Diesel Generator Surveillance Requirements)
• L-15-149, Unit 1 - Supplement to Requests to Change Cyber Security Implementation Plan Milestone 8 Completion Date  + (Unit 1 - Supplement to Requests to Change Cyber Security Implementation Plan Milestone 8 Completion Date)
• ML043020256  + (Unit 1 - Supplemental Response to the Design Basis Threat Order Dated April 29, 2004 - NRC Order EA-03-086)

• ML043070356  + (Unit 1 - Technical Requirements Manual Unit 1)

• ML022960514  + (Unit 1 - Technical Specification (TS) Change No. 02-02, Steam Generator (SG) Alternate Repair Criteria (ARC) Deletion and SG Inspection Interval Revision - Partial Withdrawal)
• ML041040255  + (Unit 1 - Technical Specification (TS) Change TS-03-16, Revision of Ultimate Heat Sink (UHS) Temperature)
• ML021020324  + (Unit 1 - Technical Specification (TS) Change No. 02-02, Steam Generator (SG) Alternate Repair Criteria (ARC) Deletion & SG Inspection Interval Revision)
• ML091610066  + (Unit 1 - Technical Specification Change 09-10 - Request to Correct Logic Connector Between TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Condition I, Actions 1.2.1 and 1.2.2)
• ML052500560  + (Unit 1 - Technical Specifications (TS) Change 05-07 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity)
• ML083450065  + (Unit 1 - Technical Specifications (TS) Change TS-446 - Safety Limit Minimum Critical Power Ratio (SLMCPR) - Cycle 8 Operation - Response to Request for Additional Information (RAI))
• ML082680184  + (Unit 1 - Technical Specifications (TS) Change 08-03, Request for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process)
• ML080530256  + (Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments)
• CNRO-2008-00032, Unit 1 - Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants  + (Unit 1 - Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants)
• ML25147A126  + (Unit 1 - Verbal Authorization - Relief Request I5R-01 - Verbal Approval from 48-hour Hold Time)
• IR 07200077/2022401  + (Unit 1 -NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200077/2022401)
• ML040290659  + (Unit 1 ASME Section XI Inservice Inspection Program Relief Requests Partial Examination of Reactor Pressure Vessel Head-to-flange Welds)
• ML23208A009  + (Unit 1 Amendment 32 to Updated Final Safety Analysis Report, Cover Letter)
• ML043220101  + (Unit 1 Amendment to Technical Specification)
• ML042710014  + (Unit 1 Amendments to Relocated the Independent Onsite Safety Review Group Function to the Quality Assurance Topical Report)
• ENS 52547  + (Unit 1 Automatic Reactor Scram Due to Main Generator Trip on Differential Current)
• ENS 52710  + (Unit 1 Automatic Reactor Scram Due to Partial Loss of Offsite Power)
• 05000315/LER-2007-001, Unit 1 Automatic Reactor Trip  + (Unit 1 Automatic Reactor Trip)
• ENS 53056  + (Unit 1 Automatic Reactor Trip Due to Main Unit Generator Over Current)
• 05000400/LER-2004-003, Unit 1 Automatic Reactor Trip Due to Rod Control Card Failure  + (Unit 1 Automatic Reactor Trip Due to Rod Control Card Failure)
• ENS 49106  + (Unit 1 Automatic Reactor Trip Due to the Loss of a Start-Up Transformer)
• ENS 48617  + (Unit 1 Automatic Reactor Trip on Turbine Trip)
• ENS 55616  + (Unit 1 Automatic Scram)
• ML20265C519  + (Unit 1 Aux Bldg Area 10 Structural Steel Framing Plan - Floor El 166 Ft)
• ML20265C462  + (Unit 1 Aux Bldg Area 10 Structural Steel Framing Plan - Floor El 185 Ft)