ML25076A301
| ML25076A301 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/17/2025 |
| From: | Komm D Tennessee Valley Authority |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML25076A301 (1) | |
Text
Post Office Box 2000, Decatur, Alabama 35609-2000 March 17, 2025 10 CFR 50.54(q) 10 CFR 50, Appendix E 10 CFR 72.44(f)
ATTN: Document Control Desk Director, Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296, and 72-052
Subject:
Browns Ferry Nuclear Plant - Site Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q); 10 CFR 50, Appendix E; and 10 CFR 72.44(f), the Tennessee Valley Authority (TVA) is submitting a description of changes to the Browns Ferry Nuclear Plant (BFN) Radiological Emergency Plan (REP). The affected document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.
EPIP Revision Title Effective Date EPIP-17 0038 Fire Emergency Procedure 02/26/2025 Description of Changes and Summary of Analysis EPIP-17 was updated to include Athens Limestone Ambulance support to the notification of offsite agencies in response to an onsite fire. This ensures that any available ambulance support could be provided to the site. EPIP-17 was also updated to require these responding organization to contact site Security to ensure a smoother access process once the fire department/ambulance arrives onsite.
These changes were determined to be changes to the REP that were not editorial or typographical in nature. These changes were determined to not conform to activities that had prior NRC approval. 10 CFR 50.47(b) Planning Standards were impacted by these changes; therefore, it was concluded that the changes could not be implemented without performing a 50.54(q) reduction in 1\\14 TENNESSEE VALLEY AUTHORITY
U.S. Nuclear Regulatory Commission Page 2 March 17, 2025 effectiveness evaluation. Upon completion of the Effectiveness Evaluation Form for these changes, it was concluded that the changes continue to comply with the requirements of 50.47(b) and 50 Appendix E, and that the changes do not constitute a reduction in effectiveness. Therefore, these changes were allowed to be implemented without prior NRC approval.
There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact E. J. Cole at (256) 729-4742.
Respectfully, Daniel A. Komm Site Vice President cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant