ML23199A307

Site Emergency Plan Implementing Procedure Revision

ML23199A307
Person / Time
Site:	Browns Ferry
Issue date:	07/18/2023
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML23199A307 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000 July , 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 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 0067 Emergency Classification Procedure 6/20/2023 Description of Changes and Summary of Analysis EPIP-1 Revision 67 revises Fission Products Barrier Fuel Clad Loss 4.A, RCS Loss 4.A and Containment Potential Loss 4.A to truncate the existing numerical values for 1,2,3-RM-90-272A and 1,2,3-RM-90-273A to 2 decimal places to correspond to the number of decimal places on the Plant Engineering Data System display and Main Control Room Remote Monitoring System displays for these instruments. Revision 67 also revises Initiating Conditions CU5 Emergency Action Level (EAL) #2 and SU6 EAL #2 to reflect the addition, to TVA REP-Generic Revision 11, of the electronic notification capability for communicating emergency declarations, classifications upgrades, and Protective Action Recommendations to the responsible state and local offsite response organizations.

U.S. Nuclear Regulatory Commission Page 2 July , 2023 These changes were determined to be changes to the REP that were not editorial or typographical in nature. These changes were 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 these changes; therefore, it was concluded that the changes could not be implemented without performing a 50.54(q) reduction in effectiveness evaluation. Upon completion of the Effectiveness Evaluation Form for these changes, it was concluded that the changes continue to comply with the requirements of 50.47(b) and 50 Appendix E, and that the changes do not constitute a reduction in effectiveness. Therefore, these changes were 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 B. F. Tidwell at (256) 729-3666.

Respectfully, Sivaraman Manu Sivaram Site Vice President cc:

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