ML24184A114

Site Emergency Plan Implementing Procedure Revision

ML24184A114
Person / Time
Site:	Browns Ferry
Issue date:	07/02/2024
From:	Komm D Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24184A114 (1)

Text

10 CFR 50.54(q) 10 CFR 50, Appendix E 10 CFR 72.44(f)

Post Office Box 2000, Decatur, Alabama 35609-2000 July 2, 2024 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-5 0066 General Emergency 06/04/2024 EPIP-10 0040 Medical Emergency Procedure 06/04/2024 Description of Changes and Summary of Analysis Changes Implemented with Prior NRC Approval:

EPIP-10 Revision 40 replaces all instances of Emergency Medical Technician (EMT) with Emergency Medical Professional (EMP) and replaces all instances of EMT with EMP.

By letter dated July 31, 2020 (ML20213C730), the Tennessee Valley Authority (TVA) submitted a license amendment request for Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2. The requested changes would

U.S. Nuclear Regulatory Commission Page 2 July 2, 2024 revise the Radiological Emergency Plan REP for Browns Ferry, Sequoyah, and Watts Bar by changing the emergency response organization at each of the sites to require an on-shift EMP rather than an on-shift EMT and would remove the requirement for an on-site TVA ambulance at each site. On November 19, 2020, the NRC issued a Safety Evaluation Report approving the amendments (Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment NOS. 313, 336, and 296 Regarding Request to Revise Emergency Plan requirement from having an on-shift emergency medical technician to a requirement for an on-shift emergency medical professional.

ML20282A345).

This change was determined to be a change to the REP that was not editorial or typographical in nature but was determined to conform to activities that had prior NRC approval. Therefore, it was concluded that the change could be implemented without performing a 50.54(q) reduction in effectiveness evaluation.

Changes Implemented without Prior NRC Approval:

EPIP-10 Revision 40 updates phone numbers for ambulance services, in Attachment 7, due to changes in phone line monitoring at the Limestone County 9-1-1 Center.

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

10 CFR 50.47(b) Planning Standard 50.47(b)(12) - Medical and Public Health Support 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 the 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 constitute a reduction in effectiveness. Therefore, this change was allowed to be implemented without prior NRC approval.

Additionally, EPIP-5 Revision 66 and EPIP-10 Revision 40 contain 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 E. J. Cole at (256) 729-4742.

U.S. Nuclear Regulatory Commission Page 3 July 2, 2024 Respectfully, Daniel A. Komm Site Vice President cc:

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

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