ML25232A016
| ML25232A016 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/04/2025 |
| From: | Bauer L, Hammock J NRC/NRR/DNRL/NLRP |
| To: | Erb D Tennessee Valley Authority |
| References | |
| EPID L-2023-SLR-0000 | |
| Download: ML25232A016 (1) | |
Text
Delson C. Erb Vice President, OPS Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - CORRECTION TO FINAL SAFETY EVALUATION FOR THE SUBSEQUENT LICENSE RENEWAL APPLICATION REVIEW (EPID NO. L-2023-SLR-0000)
Dear Delson C. Erb:
On July 18, 2025, the U.S. Nuclear Regulatory Commission (NRC) issued Safety Evaluation Related to the Subsequent License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3, (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML25169A140), hereinafter referred to as the Safety Evaluation (SE).
Tennessee Valley Authority (TVA) performed a review of the SE during which an error was identified in Commitment No. 33, paragraph 5, found on SE page A-53 of Appendix A, License Renewal Commitment. The SE paragraph reads:
5.
Revise implementing procedures to ensure the aging effects for aluminum, non-ferrous copper alloys, stainless steel, and steel components are adequately monitored for each material type In Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application for Subsequent Renewed Operating Licenses, Fourth Safety Supplement, dated February 12, 2025 (ML25043A035),
changes were made to the original Commitment in its entirety which included the verbiage adequately monitored. TVA later submitted Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Response to Request for Additional Information, Set #4, dated April 24, 2025 (ML25114A206) where the Commitment was again revised, however, the term adequately had been removed from this paragraph. The proposed correction does not change any of the conclusions in this SE. Please find a corrected SE page A-53 in Enclosure 1.
September 4, 2025
D. Erb 2
If you have any questions regarding this matter, please contact Jessica Hammock, Project Manager, for the safety review of the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3 subsequent license renewal application (SLRA) at Jessica.Hammock@nrc.gov.
Sincerely, Laurel M. Bauer, Chief License Renewal Projects Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket Nos: 50-259, 50-260, and 50-296
Enclosure:
1.
Corrected page A-53 to the BFN SLRA Safety Evaluation cc w/encl: Browns Ferry Listserv Signed by Bauer, Laurel on 09/04/25
ML25232A016 NRR-106 OFFICE PM/NLRP/DNRL LA/NLRP/DNRL (A) BC/NLRP/DNRL NAME JHammock KBratcher (ltr)
LBauer DATE 08/20/2025 08/20/2025 Corrected page A-53 to the BFN SLRA Safety Evaluation
A-53 Appendix A Item No.
Program or Topic (Section)
Commitment Implementation Schedule Source 2.
Include preventive actions to ensure bolting integrity for replacement and maintenance activities by specifying proper selection of bolting material and lubricants, and appropriate installation torque or tension to prevent or minimize loss of bolting preload and cracking of high-strength bolting. For structural bolting consisting of ASTM A325, ASTM A490, ASTM F1852 and/or ASTM F2280 bolts, the preventive actions for storage, lubricant selection, and bolting and coating material selection discussed in Section 2 of the Research Council for Structural Connections publication, Specification for Structural Joints Using High-Strength Bolts, dated August 2014, will be used.
3.
Revise implementing procedures to be consistent with ACI 349.3R-02 and SEI/ASCE 11-99 for selection of parameters to be monitored or inspected for concrete and steel structural elements and for steel liners, and joints.
4.
Ensure inspections include the following indicators to identify cracking due to expansion from reaction with aggregates:
Surface aggregate popouts Pattern cracking with darkened crack edges Water ingress Misalignment Inspections.
5.
Revise implementing procedures to ensure the aging effects for aluminum, non-ferrous copper alloys, stainless steel, and steel components are monitored for each material type:
later than the last refueling outage prior to the subsequent period of extended operation.