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| Site | Start date | Title | Description | |
|---|---|---|---|---|
| JAFP-23-0064, Emergency Plan Document Revision | FitzPatrick | 15 November 2023 | Emergency Plan Document Revision | |
| IR 05000254/2023003 | Quad Cities | 9 November 2023 | Integrated Inspection Report 05000254/2023003 and 05000265/2023003 | |
| ML23304A355 | 05200050 | 31 October 2023 | LLC Revision 1 to Standard Design Approval Application, Part 2, Chapter 9, Auxiliary Systems | |
| ML23353A157 | Nine Mile Point | 31 October 2023 | UFSAR Revision 28 (Redacted Version) | |
| ML23304A364 | 05200050 | 31 October 2023 | LLC Revision 1 to Standard Design Approval Application, Part 2, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria | |
| ML23304A358 | 05200050 | 31 October 2023 | LLC Revision 1 to Standard Design Approval Application, Part 2, Chapter 11, Radioactive Waste Management | |
| ML23291A109 | Monticello | 23 October 2023 | Subsequent License Renewal Application Requests for Confirmation of Information Environmental Review | |
| ENS 56811 | Cooper | 22 October 2023 16:49:00 | Secondary Containment Momentarily Inoperable | The following information was provided by the licensee via fax and phone: On October 22, 2023, at 1149 CDT, with the reactor at 100 percent core thermal power and steady state conditions, the Cooper Nuclear Station secondary containment differential pressure exceeded the Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.1 limit of -0.25 inches water gauge. The condition existed for approximately 80 seconds until the reactor building ventilation system responded to restore differential pressure to normal. Investigations identified a hinged duct access hatch found open. The hatch was closed and latched, and ventilation system parameters were returned to normal. There were no radiological releases associated with this event. Declaring secondary containment inoperable as a result of not meeting TS SR 3.6.4.1.1 is reportable under 10 CFR 50.72(b)(3)(v)(C) and (D) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material and mitigate the consequences of an accident. The NRC Senior Resident Inspector has been informed. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: At the time the licensee notified the NRC Headquarters Operations Officer, the cause of the hinged access duct being open had not been determined. This event has been added to the licensee's corrective action program. |
| ML23292A138 | Susquehanna | 12 October 2023 | 1 to Updated Final Safety Analysis Report, Chapter 9, Section 9.1, Fuel Storage and Handling | |
| ML23291A397 | Susquehanna | 12 October 2023 | 1 to Updated Final Safety Analysis Report, Chapter 6, Section 6.5, Fission Product Removal and Control Systems |