ML19038A164

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Site Emergency Plan Implementing Procedure Revision
ML19038A164
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/07/2019
From: Hughes D
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML19038A164 (2)


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 7, 2019 10 CFR 50.4 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 Effective Date EPIP-12 0021 Emergency Equipment and Supplies 01/08/2019 Description of Changes and Summary of Analysis EPIP-12, Revision 21 , was revised to add a functional check of the five portable satellite phones in the Technical Support Center (TSC) to the Functional Checks-Misc. Equipment table in . This activity was evaluated using EPDP-17, Attachment 2 (Screening Evaluation Form) and determined to be a change to the radiological emergency plan that was not editorial or typographical. This change did not conform to an activity that was previously approved . The activity effected the Emergency Facility and Equipment Planning Standard [10 CFR 50.47(b)(8)];

therefore, it was determined that this activity could not be implemented without performing a 50.54(q) reduction in effectiveness evaluation . Upon completion of the EPDP-17, Attachment 6 Effectiveness Evaluation Form , it was determined that the activity continues to comply with the requirements of 50.47(b) and 50 Appendix E and the activity does not constitute a reduction in effectiveness Therefore, the activity was implemented without prior approval.

U.S. Nuclear Regulatory Commission Page 2 February 7, 2019 This revision also proposed several changes that were editorial/typographical in nature. The appropriate source note documentation related to commitment 114096292 was added to (Technical Support Center) and Attachment 3 (Main Control Room) . Attachment 17, "Source Notes," was also added. This change did not propose the addition of a new commitment.

The addition of the commitment notation and the related source note document does not change any of the inventories contained within EPIP-12. This revision also contained several additional editorial/typographical changes throughout the document. These changes were evaluated using EPDP-17, Attachment 2 and were determined to be editorial or typographical in nature; therefore, it was determined that the activity could 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.

R ~tK D. L. Hughes Site Vice President cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS