ML21039A509

Site Emergency Plan Implementing Procedure Revision

ML21039A509
Person / Time
Site:	Browns Ferry
Issue date:	02/08/2021
From:	Rasmussen M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
EPIP-8, Rev 0033
Download: ML21039A509 (2)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 8, 2021 10 CFR 50.54(q) 10 CFR 50, Appendix E 10 CFR 72.44(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 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. The affected document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.

EPIP Revision Title Effective Date EPIP-8 0033 Personnel Accountability and Evacuation 01/08/2021 Description of Changes and Summary of Analysis EPIP-8, Revision 33 revised all instructions to notify the Central Emergency Control Center (CECC) Director to, instead, notify the CECC Nuclear Security Manager. This activity was determined to be a change to the radiological emergency plan that was not editorial or typographical in nature. This change was also determined to not conform to an activity that has prior approval. Planning Standard 50.47(b)(6) - Emergency Communications was determined to be impacted by this change; therefore, it was concluded that this activity could not be implemented without performing a 10 CFR 50.54(q) reduction in effectiveness evaluation. Upon completion of the Effectiveness Evaluation Form, it was concluded that the activity continues to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E, and the activity does not constitute a reduction in effectiveness. Therefore, the activity was allowed to be implemented without prior approval.

U.S. Nuclear Regulatory Commission Page 2 February 8, 2021 There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact B. F. Tidwell at (256) 729-3666.

Respectfully, M.

M M M. Rasmussen Site Vice President cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS