ML24305A169

Site Emergency Plan Implementing Procedure Revision

ML24305A169
Person / Time
Site:	Browns Ferry
Issue date:	10/31/2024
From:	Komm D Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24305A169 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000

October 31, 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 document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.

EPIP Revision Title Effective Date

EPIP-7 0043 Activation and Operation of the Operations 10/01/2024 Support Center (OSC)

Description of Changes and Summary of Analysis

EPIP-7, Revision 43 removed the instruction to utilize the volume control pot located in the OSC from Attachment 2, OSC Manager Checklist, because the volume control pot no longer exists in the room. This change was determined to be a change to the radiological emergency plan that was not editorial or typographical in nature. This change was determined to not conform to activities that had prior NRC approval. 10 CFR 50.47(b)(6) (Emergency Communications) Planning Standard was impacted; therefore, it was concluded that the activity could not be implemented without performing a 50.54(q) reduction in effectiveness evaluation. Upon completion of the Effectiveness Evaluation Form for this change, it was concluded that the change continues to comply with the requirements of 50.47(b) and 50 Appendix E and the activity does not constitute a U.S. Nuclear Regulatory Commission Page 2 October 31, 2024

reduction in effectiveness. Therefore, the change was allowed to be implemented without prior NRC approval.

This revision also added instruction for the OSC Staging Area Manager to sign in on the OSC staffing board to Attachment 19, OSC Staging Area Manager Checklist. The addition of this step results in steps following the instruction stepping up by one each. This change was determined to be a change to the radiological emergency plan that was not editorial or typographical in nature.

This change was determined to not conform with an activity had prior NRC approval. No Planning Standard was impacted by this change and the activity did not involve a site specific EP commitment. Therefore, the activity was implemented without performing a 50.54(q) reduction in effectiveness evaluation.

Lastly, the revision made editorial/typographical changes to Attachment 2, OSC Manager Checklist. These changes were determined to be changes to the REP that were editorial or typographical in nature. The changes did not involve a site -specific EP commitment; therefore, these changes were allowed to be implemented without performing a 50.54(q) reduction in effectiveness evaluation.

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