ML24263A295

Site Emergency Plan Implementing Procedure Revision

ML24263A295
Person / Time
Site:	Browns Ferry
Issue date:	09/19/2024
From:	Komm D Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24263A295 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000 September 19, 2024 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 documents are the BFN Emergency Plan Implementing Procedures (EPIPs) named below.

EPIP Revision Title Effective Date EPIP-5 0067 General Emergency 08/21/2024 EPIP-6 0049 Activation and Operation of the Technical Support Center (TSC) 08/21/2024 Description of Changes and Summary of Analysis

1. EPIP-6 Revision 49 changes the Operational Responsibilities in the Operations Manager, Operations Communicator, and Control Room Communicator Checklists to align with responsibilities listed with the TVA Radiological Emergency Plan. 10 CFR 50.47(b) Planning Standards 50.47(b)(1) - Assignment of Responsibility (Organization Control) and 50.47(b)(2) -

Onsite Emergency Organization were impacted by this change.

U.S. Nuclear Regulatory Commission Page 2 September 19, 2024

2. EPIP-6 Revision 49 also adds instruction to the Site Emergency Director, Operations Communicator, and NRC Coordinator Checklists to ensure that all applicable NRC notifications have been made. 10 CFR 50.47(b) Planning Standard 50.47(b)(5) - Notification Methods and Procedures was impacted by this change.

3. EPIP-5 Revision 67 and EPIP-6 Revision 49 add Protective Action Recommendation (PAR) upgrades to instructions related to PAR notifications. 10 CFR 50.47(b) Planning Standard 50.47(b)(5) - Notification Methods and Procedures was impacted by this change.

4. REP Generic Revision 117 revises the PAR logic chart provided in Figure 10-1 to update the Continuous Assessment Flowchart to address the actions specified in CR 1933181. As a result of this change, EPIP-5, Revision 67, and EPIP-6, Revision 49, are also being revised to reflect the change to the REP. 10 CFR 50.47(b) Planning Standard 50.47(b)(10) - Protective Response was impacted by this change.

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 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