ML24102A285

Site Emergency Plan Implementing Procedure Revision

ML24102A285
Person / Time
Site:	Browns Ferry
Issue date:	04/11/2024
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24102A285 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000

April 11, 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-1 0068 Emergency Classification Procedure 03/13/2024

Description of Changes and Summary of Analysis

EPIP-1 Revision 68 revises the bases for Initiating Conditions (ICs) RG1, RS1, and RA1 to align the first sentence of the bases for these ICs with the wording of the corresponding ICs and Emergency Action Levels by deleting the or equal to wording used in those sections.

This change was determined to be a change to the REP that was not editorial or typographical in nature. This change was also determined to not conform to activities that had prior NRC approval.

Planning Standard 10 CFR 50.47(b)(4) - Emergency Classification System was impacted by this change; therefore, it was concluded that the change 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 U.S. Nuclear Regulatory Commission Page 2 April 11, 2024

of 50.47(b) and 50 Appendix E, and that the change does not constitute a reduction in effectiveness. Therefore, this change was 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.

ReReReReReReReReReReReReRReRRRRespectfully, specececececececececececececectftftftftftftfttftttttfuuluuuuuuuuuuuuuly,

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