ML20209A410

Site Emergency Plan Implementing Procedure Revision

ML20209A410
Person / Time
Site:	Browns Ferry
Issue date:	07/27/2020
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML20209A410 (2)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 27, 2020 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 0032 Activation and Operation of the Technical 4/7/2020 Support Center (TSC)

Description of Changes and Summary of Analysis This revision of EPIP-8 (Revision 32) was made effective as of April 7, 2020. Contrary to 10 CFR 50.54(q)(5), this submittal is being made greater than 30 days from the effective date.

This has been entered into the licensees corrective action program (CR 1619972).

EPIP-8 Revision 32 was revised to add instruction to contact the Plant Technical Information Center (TIC) and notify them of the activation of the Assembly and Accountability system. 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 Standards 10 CFR 50.47(b)(1) - Assignment of Responsibility, 50.47(b)(6) - Emergency Communications, and 50.47(b)(10) - Protective Response, were determined to be impacted by this change; therefore, it was concluded that this activity could not be implemented without performing a 50.54(q) reduction in effectiveness evaluation. Upon

U.S. Nuclear Regulatory Commission Page 2 July 27, 2020 completion of the Effectiveness Evaluation Form it was concluded that the activity continues to comply with the requirements of 50.47(b) and 50 Appendix E, and the activity does not constitute a reduction in effectiveness. Therefore, the activity was allowed to be implemented without prior approval.

Additionally, EPIP-8, Revision 32 included various changes throughout the document which were determined to be editorial or typographical in nature and could therefore 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 B. F. Tidwell at (256) 729-3666.

Respectfully, p y S. M M. Bo Bono B no 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