ML26027A223
| ML26027A223 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/28/2026 |
| From: | Daniel Bacon NRC/RGN-II/DORS/EB2 |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2026011 | |
| Download: ML26027A223 (0) | |
Text
Delson C. Erb Vice President, Fleet Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 & 2 - NOTIFICATION OF CONDUCT OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS FOR NUCLEAR POWER REACTORS, INSPECTION (NRC INSPECTION REPORT 05000327/2026011, 05000328/2026011) AND REQUEST FOR INFORMATION (RFI)
Dear Delson C. Erb:
The purpose of this letter is to notify you that U.S. Nuclear Regulatory Commission (NRC) staff will conduct a Title 10 of the Code of Federal Regulations (10 CFR) 50.69 program inspection at Sequoyah Nuclear Plant, Units 1 & 2, in April 2026. The inspection team will be composed of personnel from the Region II Office and led by Philipp Braaten. The inspection will be conducted in accordance with Inspection Procedure 37060, 10 CFR 50.69 Risk-informed Categorization and Treatment of Structures, Systems, and Components Inspection. The inspection is being performed because the requirements of 10 CFR 50.69 have been implemented at Sequoyah Nuclear Plant, Units 1 & 2.
The schedule for the inspection is as follows:
Week 1 of onsite inspection: April 20-24, 2026 Week 2 of onsite inspection: May 04-08, 2026 An initial list of the documents that the team will review during the conduct of the inspection are listed in the Enclosure. The team leader will contact you with any additional specific document requests prior to the start of the inspection. Your cooperation and support during this inspection will be appreciated.
If you have questions concerning this inspection, or the inspection team's information request or logistical needs, please contact Philipp Braaten, Team Leader at (404) 997-4651 or philipp.braaten@nrc.gov or me at (404) 997-4518.
January 28, 2026
D. Erb 2
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget under control number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Daniel Bacon, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-327, 50-328 License No. DPR-77, DPR-79
Enclosure:
10 CFR 50.69 Program Supporting Documentation cc w/ encl: Distribution via GovDelivery Signed by Bacon, Daniel on 01/28/26
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFIC E
RII/DORS RII/DORS NAME P. Braaten D. Bacon DATE 1/27/2026 1/28/2026
10 CFR 50.69 Program Supporting Documentation 1
If you have any questions regarding this information request, please contact Philipp Braaten, as soon as possible, at (404) 997-4651 or via e-mail at Philipp.braaten@nrc.gov. Electronic format is the preferred media, except where specifically noted. If electronic media is made available via an internet based remote document management system, then the remote document access must allow inspectors to download, save, and print the documents in the NRC's Regional office.
Paper records (hard copy) are acceptable. At the end of the inspection, the documents in the team's possession will not be retained.
This document request is based on typical documents that a generic plant might have. As such, this generic document request is not meant to imply that any specific plant is required to have all of the listed documents. It is recognized that some documents listed below may not be available for your plant. In addition, the document titles listed below are based on typical industry document names; your plant specific document titles may vary.
Information Requested by February 27, 2026 1.
Licensing bases documents:
a.
Sequoyah 10 CFR 50.69 License Amendment Request (LAR).
b.
Responses to Requests for Additional Information (RAI) regarding the Sequoyah 10 CFR 50.69 LAR.
c.
U.S. NRC Safety Evaluation Report and approval of 10 CFR 50.69 LAR.
d.
Updated Final Safety Analysis changes associated with the implementation of 10 CFR 50.69 at Sequoyah.
2.
Copy (latest revision) of 10 CFR 50.69 program procedures.
3.
10 CFR 50.69 categorization documents (Word portion only) for all systems which have completed system categorization.
4.
Probabilistic Risk Assessment (PRA) system notebooks for systems that have completed system categorization.
5.
List of Risk-Informed Safety Class (RISC)-1, RISC-2, and RISC-3 component failures (issue report designator and title will be acceptable) since implementing the program requirements on associated systems. If applicable, provide any performance indicators utilized to monitor performance of RISC-1, RISC-2, and RISC-3 SSCs consistent with categorization process assumptions and in the PRA model.
6.
Administrative procedures that are utilized to implement alternative treatment of regulatory requirements under 10 CFR 50.69 (example: changes to In-service Testing Program procedures, Maintenance Rule Program procedures, Reportability Manual, etc.).
7.
Meeting Minutes for all IDP meetings to date.
8.
Audits and self-assessments of the Sequoyah/Corporate 10 CFR 50.69 Program since the issuance of the 10 CFR 50.69 license amendment.
9.
List of all changes or upgrades made to the PRA model of record utilized for 10 CFR 50.69 Program since the issuance of the 10 CFR 50.69 license amendment.
- 10. Applicable credentials of IDP members.
10 CFR 50.69 Program Supporting Documentation 2
- 11. Provide program requirements that implement the requirement for feedback and process adjustments per 10 CFR 50.69(e). Provide a summary of updates, if applicable, to the categorization or treatment processes as a result of changes to the plant, operational practices, operating experience, or as a result of the performance issues of RISC-1, 2, or 3 SSCs.
- 12. Licensee event reports associated with any reportable events per 10 CFR 50.69(g) since implementation of the program at Sequoyah.
- 13. PRA model information (e.g., Excel spreadsheet) providing a listing of all basic events with all available importance measures (e.g., Birnbaum, F-V, RAW and RRW) and an associated list of cutsets. This information shall be taken from the PRA model of record used in the 10 CFR 50.69 categorization process.
- 14. If a seismic PRA was not used for passive risk categorization, please provide the Safe Shutdown Equipment List (used for Seismic Margins Analysis).
- 15. The plants Individual Plant Examination of External Events.