ML21112A262

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Site Emergency Plan Implementing Procedure Revision 27 to EPIP-13, Dose Assessment
ML21112A262
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/22/2021
From: Rasmussen M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML21112A262 (2)


Text

Post Office Box 2000, Decatur, Alabama 35609-2000 April 22, 2021 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. The affected document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.

EPIP Revision Title Effective Date EPIP-13 0027 Dose Assessment 03/29/2021 Description of Changes and Summary of Analysis Non-Editorial Changes without Prior Approval I. EPIP-13 Revision 27 adds instruction to subsection 1.1 related to the transfer of the responsibility for performing dose assessment from the site to the Central Emergency Control Center (CECC).

II. EPIP-13 Revision 27 updates all instruction related to the results of performing actions in SPDS/PEDS when performing dose assessment.

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 an activity that has prior approval. 10 CFR 50.47(b) Planning Standard 50.47(b)(9) - Accident Assessment was determined to be impacted by these changes; therefore, it was concluded that these activities could not be implemented without performing 50.54(q) reduction in effectiveness

U.S. Nuclear Regulatory Commission Page 2 April 22, 2021 evaluations. Upon completion of the Effectiveness Evaluation Form for each activity it was concluded that all activities continue to comply with the requirements of 50.47(b) and 50 Appendix E, and the activity does not constitute a reduction in effectiveness. Therefore, these activities were allowed to be implemented without prior approval.

Editorial/Typographical Changes EPIP-13 Revision 27 includes various changes which were determined to be editorial or typographical in nature and could therefore be implemented without performing a 50.54(q) reduction in effectiveness evaluation.

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, Respectf fully, M

M. MM. Rasmussen Site Vice President cc:

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