ML18129A125

Submittal of Site Emergency Plan Implementing Procedure Revision

ML18129A125
Person / Time
Site:	Browns Ferry
Issue date:	05/09/2018
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML18129A125 (2)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 9, 2018 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 (REP). The affected documents are the BFN Emergency Plan Implementing Procedures (EPIPs) named below.

EPIP Revision Effective Date EPIP-5 0053 General Emergency 04/09/2018 EPIP-10 0037 Medical Emergency Procedure 04/09/2018

U.S. Nuclear Regulatory Commission Page 2 May 9, 2018 Description of Changes and Summary of Analysis EPIP-5, Revision 53 , was revised to incorporate editorial changes . This revision corrected a typographical error in the "10 Mile Downwind Sectors" section of Appendix A , Protective Action Recommendation Worksheet, and Appendix J, Protective Action Recommendation (PAR)

Worksheet. All instances of "Peer Check" were also replaced with "Peer Review."

EPIP-10, Revision 37 , was revised to incorporate non-editorial changes. The revision implemented changes to section 4.2, Non-QA Records , to ensure that Attachments 1 and 2 are identified as non-quality assurance records in the procedure.

These changes were evaluated in accordance with 10 CFR 50.54(q)(3) . The Emergency Preparedness Department Procedure (EPDP)-17 , Attachment 2, Screening Evaluation Form concluded that these activities could be implemented without performing a 10 CFR 50 .54(q) reduction in effectiveness evaluation . The activity does not constitute a reduction in effectiveness; therefore, it was concluded that the activity could be implemented without prior approval.

There are no new regu latory commitments in this letter. If you have any questions regarding this subm ittal , please contact 8 . F. Tidwell at (256)729-3666 .

Respectfully, Lr~&-ae)

D. L. Hughes 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