| | Site | Start date | Title | Description |
|---|
| NUREG-1022, DFC, Rev. 4, Event Reporting Guidelines: 10 CFR 50.72 and 10 CFR 50.73 | | 30 September 2026 | NUREG-1022, DFC, Rev. 4, Event Reporting Guidelines: 10 CFR 50.72 and 10 CFR 50.73 | |
| ML26261A426 | 05000614 | 18 September 2026 | Long Mott Energy, LLC, Rev. 1, Construction Permit Application, Part IV, Technical Specifications | |
| ML26260A338 | Arkansas Nuclear | 17 September 2026 | License Amendment Request, Allowance to Eliminate Movement of Control Element Assembly 29 from Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 32 | |
| ML26225A137 | Diablo Canyon | 15 September 2026 | Issuance of Amendment Nos. 263 and 265 Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 7, Development of Emergency Action Levels for Non-Passive Reactors | |
| ML26257A532 | | 14 September 2026 | ACRS Sc 15 Sep 15, 2026 Lmgs CPA - NRC Staff Presentation - Open Session | |
| ML26224A353 | | 9 September 2026 | LTR-26-0220 Summary Report and Certified Minutes for the 737th Meeting of the Advisory Committee on Reactor Safeguards for July 8 Through 9 2026 | |
| ML26251A173 | | 8 September 2026 | Summary of August 13, 2026, Public Observation Meeting with Nuclear Energy Institute Concerning Status of NEI 25-09 and NEI 26-02 | |
| RS-26-116, License Amendment Request to Revise HPCI & RCIC Steam Supply Pressure - Low Allowable Values | Limerick | 4 September 2026 | License Amendment Request to Revise HPCI & RCIC Steam Supply Pressure - Low Allowable Values | |
| ENS 58436 | Dresden | 3 September 2026 09:31:00 | Manual Reactor Trip | The following information was provided by the licensee via phone and email:
At 0431 CDT on September 3, 2026, with Unit 2 in mode 1 at 100 percent power, the reactor was manually tripped due to indication of control rod movement and reactor protection system 'A' channel half scram, caused by nuclear instrumentation failure. The trip was not complex with all systems responding normally post-trip. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
Operations responded using station operating procedures and stabilized the plant in mode 3, (hot shutdown). Decay heat is being removed by using the main turbine bypass valves. Unit 3 is not affected.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| ML26243A348 | | 31 August 2026 | Long Mott Generation Station - ACRS Subcommittee Meeting September 1, 2026 - Open Session | |