ML25084A247
| ML25084A247 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/26/2025 |
| From: | Hammock J NRC/NRR/DNRL/NLRP |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML25084A247 (1) | |
Text
1 REQUEST FOR CONFIRMATION OF INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION BROWNS FERRY SLRA SAFETY REVIEW TENNESSEE VALLEY AUTHORITY BROWNS FERRY, UNITS 1, 2, 3 DOCKET NO. 05000259, 05000260, 05000296 ISSUE DATE: 03/25/2025 Regulatory Basis:
Part 54 of Title 10 of the Code of Federal Regulations (10 CFR), Requirements for Renewal of Operating Licenses for Nuclear Power Plants, is designed to elicit application information that will enable the U.S. Nuclear Regulatory Commission (NRC, staff) to perform an adequate safety review and the Commission to make the necessary findings. Reliability of application information is important and advanced by requirements that license applications be submitted in writing under oath or affirmation and that information provided to the NRC by a license renewal applicant or required to be maintained by NRC regulations be complete and accurate in all material respects. Information that must be submitted in writing under oath or affirmation includes the technical information required under 10 CFR 54.21(a) related to assessment of the aging effects on structures, systems, and components subject to an aging management review.
Thus, both the general submission requirements for license renewal applications and the specific technical application information requirements require that submission of information material to NRCs safety findings (see 10 CFR 54.29 standards for issuance of a renewed license) be submitted by an applicant as part of the application.
Background:
By Subsequent License Renewal Application Appendix E, Applicant’S Environmental Report-Operating License Renewal Stage|letter dated January 19, 2024]] (Agencywide Documents Access and Management System (ADAMS) Package Accession No.ML24019A009), as supplemented by letters dated January 22, 2024 (ML24022A292), October 9, 2024 (ML24283A091), November 1, 2024 (ML24306A203), December 17, 2024 (ML24352A216), January 8, 2025 (ML25008A150),
February 12, 2025 (ML25043A270 & ML25043A035), and March 4, 2025 (ML25063A184),
Tennessee Valley Authority (TVA, the applicant) submitted an application for subsequent license renewal of Renewed Facility Operating License Nos.DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant (BFN, Browns Ferry), Units 1, 2, and 3, respectively, to the NRC.
TVA submitted the application pursuant to 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, for subsequent license renewal.
The NRC staff is in the process of reviewing the application. Based on our review, the NRC staff has identified the attached request for confirmation of information (RCI).
Request:
RCI-NCSG-3.5.2 The letter dated November 1, 2024 (ML24306A203), revised SLRA Table 3.5.2-36 to cite generic note J and plant-specific note 18 for non-ferrous-aluminum electrical and I&C penetrations exposed to concrete. However, the letter dated February 12, 2025 (ML25043A035), includes the following revision to plant-specific note 18 for SLRA Table 3.5.2-36:
2 The components were noted to have SLR intended functions (including:
Structural Support / Shelter and Protection / Flood Barrier / Pressure Boundary);
however, an applicable aging effect was not identified with the materials of stainless steel or steel exposed to the environment of concrete.
Embedded/encased steel that is exposed to moisture has the potential for loss of material due to corrosion. The Structures Monitoring Aging Management Program (B.2.1.33) or the Inspection of Water-Control Structures Associated with Nuclear Power Plants Aging Management Program (B.2.1.34) will inspect the accessible surfaces of the steel and the concrete surrounding the embedment/encasement for any signs of degradation. If the condition of the accessible surfaces indicates the presence of, or could result in, degradation to the embedded/encased and inaccessible steel, the condition will be entered into the corrective action program (CAP) and an evaluation will be performed, as required by the Structures Monitoring Aging Management Program (B.2.1.33) and Inspection of Water-Control Structures Associated with Nuclear Power Plants Aging Management Program (B.2.1.34).
The staff notes that the revised plant-specific note does not refer to aluminum and only refers to accessible surfaces of steel and embedded/encased and inaccessible steel.
Please confirm that the above revision to plant-specific note 18 for SLRA Table 3.5.2-36 applies to the following components exposed to concrete:
non-ferrous-aluminum electrical and I&C penetrations stainless steel mechanical penetrations steel conduits steel support members, welds, bolted connections, support anchorage to building structures steel structural components steel hatch/plugs steel electrical and I&C penetrations steel mechanical penetrations steel piles RCI-ESEB-B.2.1.33-1 The letter dated February 12, 2025 (ML25043A035), provides Enhancement 34 to the Structures Monitoring program element 4 for monitoring ground water chemistry on PDF page 275.
However, on PDF page 300 provides Enhancement 34 to the Structures Monitoring program element 4 for monitoring raw water and ground water chemistry.
GALL-SLR Report AMP XI.S6 recommended monitoring of groundwater chemistry.
Confirm that Enhancement 34 to the Structures Monitoring program on PDF Page 275 of SLRA Supplement 4 can be deleted.
Confirm that the wording raw water and groundwater chemistry can be changed into groundwater chemistry in Enhancement 34 to the Structures Monitoring program on PDF page 300 of SLRA Supplement 4
3 RCI-ESEB-B.2.1.33-2 The letter dated February 12, 2025 (ML25043A035) describes Enhancement 38 to the Structures Monitoring program on PDF page 427. However, the staff noted that there is no Enhancement 37 to the Structures Monitoring program in the SLRA.
Confirm that there is no Enhancement 37 to the Structures Monitoring program and Enhancement 38 to the Structures Monitoring program can be renumbered into Enhancement 37 to the Structures Monitoring program OFFICE NRR/DNRL/
NLRP/BC NRR/DNRL/
NLRP/PM NRR/DEX/
ESEB/BC NRR/DNRL/
NCSG/BC NAME BRogers JHammock ITseng SBloom DATE 03/17/2025 03/17/2025 03/12/2025 03/19/2025 ADAMS Accession No.: ML25084A247