ML25014A044
| ML25014A044 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/14/2025 |
| From: | Hammock J NRC/NRR/DNRL |
| To: | Erb D Tennessee Valley Authority |
| Shared Package | |
| ML25014A041 | List: |
| References | |
| Download: ML25014A044 (1) | |
Text
Browns Ferry Nuclear Plant, Units 1, 2, and 3 Subsequent License Renewal Application (SLRA) Safety Review Requests for Confirmation of Information 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) and January 8, 2025 (ML25008A150),
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:
During the audit, the staff reviewed several documents that contain information which will likely be used in conclusions documented in the Safety Evaluation (SE). To the best of the staff's knowledge, this information is not on the docket. Any information used to reach a conclusion in the SE must be included on the docket by the applicant. We request that you submit confirmation that the information gathered from the documents and listed below is correct or provide the associated corrected information.
RCI-ESEB-3.5.2.2.1.2-2 During a breakout session associated with SLRA Section 3.5.2.2, AMR Results for Which Further Evaluation is Recommended by the GALL-SLR Report, the applicant informed the staff that each drywell is cooled during normal operation of the unit by a closed loop ventilation system designed to hold the average temperature in the drywell to < 150°F, and the Containment and RBCCW (Reactor Building Closed Cooling Water) Systems are used to maintain the function of the drywell coolers in the closed loop ventilation system in removing heat and maintaining the temperature in the drywell. The applicant also informed the staff that the External Surfaces Monitoring of Mechanical Components AMP described in SLRA Section B.2.1.23 and the One-Time Inspection AMP described in SLRA Section B.2.1.20 are used for managing aging effects of the Containment System; and the Closed Treated Water Systems AMP described in SLRA Section B.2.1.12 and the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Component AMP described in SLRA Section B.2.1.24 are used for managing aging effects of the RBCCW System.
Confirm that the closed loop ventilation system that is described in SLRA Section 3.5.2.2.1.2 is referring to the style of the drywell coolers and drywell ventilation systems being a closed loop arrangement and not a system labeled as the closed loop ventilation system.
Confirm that the function of the drywell coolers in the closed loop ventilation system described in SLRA Section 3.5.2.2.1.2 is maintained by the Containment and RBCCW Systems described in SLRA Sections 2.3.2.1 and 2.3.3.23, respectively.
Confirm that the External Surfaces Monitoring of Mechanical Components AMP described in SLRA Section B.2.1.23 and the One-Time Inspection AMP described in SLRA Section B.2.1.20 are used for managing aging effects of the Containment System.
Confirm that the Closed Treated Water Systems AMP described in SLRA Section B.2.1.12 and the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Component AMP described in SLRA Section B.2.1.24 are used for managing aging effects of the RBCCW System.