ML24074A334

Site Emergency Plan Implementing Procedure Revision

ML24074A334
Person / Time
Site:	Browns Ferry
Issue date:	03/14/2024
From:	Komm D Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24074A334 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000

March 14, 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-8 0037 Personal Accountability and Evacuation 02/14/2024

Description of Changes and Summary of Analysis

EPIP-8 Revision 37 adds notes to step 1.0[6] in Attachments 3 and Attachment 4, and to step 1.0[5] in Attachment 4, to not conduct a Public Address System (PA) announcement until at least three minutes after the time documented in step 1.0[5.3].

Additionally, EPIP-8 Revision 37 rewrites Attachment 4 to align the process of sounding the Assembly/Accountability sirens with the process found in Attachment 3.

These changes were determined to be changes to the REP that were not editorial or typographical in nature. These changes were also determined to not conform to activities that had prior NRC approval. Planning Standard 10 CFR 50.47(b)(10) - Protective Response was impacted by these U.S. Nuclear Regulatory Commission Page 2 March 14, 2024

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.

ReReReReReReReReReRReRReReRRRRespectfully, specececececeececececececececectfttftftfttfttttttttfuuuuluuuuuuuuuuuuly,

Manu Sivaraman Site Vice President

cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant