ML22279A945

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Site Emergency Plan Implementing Procedure Revision. Includes EPIP-14, Revision 0024, Radiological Control Procedures
ML22279A945
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/06/2022
From: Sivaraman M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML22279A945 (2)


Text

Post Office Box 2000, Decatur, Alabama 35609-2000 October 6, 2022 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 (REP). The affected document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.

EPIP Revision Title Effective Date EPIP-14 0024 Radiological Control Procedures 09/06/2022 Description of Changes and Summary of Analysis EPIP-14 Revision 24 adds a note to Attachment 1 which ensures that the user understands exactly where to obtain the concentration data when considering the distribution of Potassium Iodide. 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 approval.

Planning Standard 50.47(b)(10) - Protective Response 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 constitute a reduction in effectiveness. Therefore, this change was allowed to be implemented without prior approval.

U.S. Nuclear Regulatory Commission Page 2 October 6, 2022 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, 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