ML23271A170

Site Emergency Plan Implementing Procedure Revision

ML23271A170
Person / Time
Site:	Browns Ferry
Issue date:	09/28/2023
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML23271A170 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000 September 2, 2023 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 Dchange to the Browns Ferry Nuclear Plant (BFN)

Radiological Emergency Plan (REP). The affected documentLV the BFN Emergency Plan Implementing Procedure (EPIP) named below.

EPIP Revision Title Effective Date EPIP-12 0027 Emergency Equipment and Supplies 8/30/2023 Description of Changes and Summary of Analysis In accordance with changes to CECC EPIP-12 Revision 37, BFN EPIP-12 Revision 27 relocates the contents of CECC EPIP-12 Attachment 7, BFN Joint Information Center Quarterly Inventory to BFN EPIP-12, Emergency Equipment and Supplies, Attachment 17, BFN Joint Information Center (JIC). 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)(8) - Emergency Facility and Equipment 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 of 50.47(b) and 50 Appendix E, and that the change does not

U.S. Nuclear Regulatory Commission Page 2 September 2, 2023 constitute a reduction in effectiveness. Therefore, this change was allowed to be implemented without prior NRC approval.

EPIP-12 Revision 27 also contains a set of changes to the REP that were determined to be editorial or typographical in nature. Therefore, these changes were allowed to be implemented without performing a 50.54(q) reduction in effectiveness evaluation, and without prior NRC approval.

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, R sp Re pec e ttfful u ly, Manu Sivaraman BFN Site Vice President cc:

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