| | Site | Start date | Title | Description |
|---|
| LG-25-132, License Amendment and Alternative Request Related to One-Time Exception of Primary Containment Isolation Valve Testing | Limerick | 9 October 2025 | License Amendment and Alternative Request Related to One-Time Exception of Primary Containment Isolation Valve Testing | |
| ML25273A236 | | 30 September 2025 | Draft Appendix a to LIC-112, Power Uprate Process Graded Approach for Determining Power Uprate Level of Review | |
| U-604846, Submittal of the Core Operating Limits Report Cycle 23, Revision 19 | Clinton | 26 September 2025 | Submittal of the Core Operating Limits Report Cycle 23, Revision 19 | |
| L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change | Monticello | 24 September 2025 | Site Specific Emergency Action Level Technical Basis Documents Change | |
| RA-25-0197, Cycle 25 Core Operating Limits Report (Colr), Revision 2 | Brunswick | 22 September 2025 | Cycle 25 Core Operating Limits Report (Colr), Revision 2 | |
| ML25260A487 | Technical Specifications Task Force
99902042 | 17 September 2025 | Correction to TSTF-585, Revision 5, Revise LCO 3.0.3 to Require Managing Risk | |
| TSTF-25-06, TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5 | Technical Specifications Task Force
99902042 | 10 September 2025 | TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5 | |
| ML25239B557 | Clinton | 8 September 2025 | Issuance of Amendment No. 257 to Revise Updated Safety Analysis Report to Approve Alternate Method of Verifying Main Steam Isolation Valve Closure Reactor Protection System Response Time | |
| PMNS20251083, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 | Browns Ferry | 4 September 2025 | Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 | |
| 05000254/LER-2025-003-01, Main Steam Isolation Valves Local Leak Rate Test Exceed Technical Specification Limits | Quad Cities | 27 August 2025 | Main Steam Isolation Valves Local Leak Rate Test Exceed Technical Specification Limits | |