ML23347A209
| ML23347A209 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/17/2024 |
| From: | John Lamb NRC/NRR/DORL/LPL2-1 |
| To: | Coleman J Southern Nuclear Operating Co |
| Lamb J, NRR/DORL/LPL2-1 | |
| References | |
| Download: ML23347A209 (1) | |
Text
January 17, 2024 Ms. Jamie M. Coleman, Director Regulatory Affairs Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 VOLUNTARY REQUESTS FOR DATA, INFORMATION, AND/OR OBSERVATION
Dear Ms. Coleman:
The U.S. Nuclear Regulatory Commission (NRC) staff requests that Southern Nuclear Company (SNC, the licensee) to submit voluntarily the following data, information, and/or observation for Vogtle Electric Generating Plant (Vogtle), Units 3 and 4.
The NRC staff requests full core physics data for the first cycle of Vogtle, Unit 3, to validate the NRCs core physics methods.
The NRC staff requests a one-day onsite visit for NRC staff and Idaho National Laboratory researchers to observe the simulator training for Vogtle, Units 3 and 4, and meet with the instructors. This would support NRC Office of Nuclear Regulatory Research (RES) to design simulator experiments to study operator performance in the use of computerized procedures.
The NRC staff requests thermal-hydraulic test data from first-of-a-kind and third-of-a-kind design verification tests performed in China that supported the deletion of tests from the Vogtle Combined Licenses (COLs). The NRC staff will use the data to validate the NRC thermal hydraulics modelling for the AP1000. In particular, the NRC staff requests test reports that include the plant initial conditions and the sequence of events in the tests, and data (preferably in an easily readable electronic format) for the following tests:
o Passive Residual Heat Removal (PRHR) heat transfer and In-containment Refueling Water Storage Tank (IRWST) heat up, o Coolant Make-up Tank (CMT) recirculation and draindown, o Automatic Depressurization System (ADS) blowdown, and o Reactor Coolant Pump (RCP) trip flow coastdown.
Submission of the requested data and information on Certrex will enable the NRC to perform its mission critical functions. The observation of simulator training will support a RES study of the impact of computerized operation procedures on operator performance and reliability.
Please respond within 45 days of the date of this letter if SNC is willing to support these requests or SNC is not willing to support these requests. If SNC is willing to support these requests, the logistics for each request will be discussed separately with the cognizant staff.
If you have questions, you can contact me at John.Lamb@nrc.gov or 301-415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 52-025 and 52-026 cc: Listserv
ML23347A209 NRR-106 OFFICE NRR/DORL/LPLII-1/PM NRR/DORL/LPLII-1/LA RES/DRA/HFRB/BC NAME JLamb KGoldstein MValentin DATE 12/13/2023 12/14/2023 12/13/2023 OFFICE NRR/DORL/LPLII-1/BC NRR/DORL/LPLII-1/PM NAME MMarkley JLamb DATE 01/17/2024 01/17/2024