ML18066A497

Site Emergency Plan Implementing Procedure Revisions

ML18066A497
Person / Time
Site:	Browns Ferry
Issue date:	03/07/2018
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
EPIP-13, Rev. 24
Download: ML18066A497 (2)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 7, 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 Revisions 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 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 Effective Date EPIP-13 0024 Dose Assessment 02/05/2018

U.S. Nuclear Regulatory Commission Page 2 March 7, 2018 Description of Changes and Summary of Analysis EPIP-13, Revision 24, was revised to incorporate both editorial changes and a non-editorial or typographical changes. This revision added methodology for performing a dose assessment of material released using the Hardened Containment Vent System (HCVS). The revision also added methodology for performing a dose assessment using an electronic spreadsheet. Attachment 6 (Multi Unit Release Dose Assessment Flowchart) and Attachment 7 (BFN Maximum Noble Gas Release Rates Based on Accident Types) were removed and a reference to Attachment 22 in Central Emergency Control Center (CECC) EPIP-8 was added . Lastly, a number of editorial/typographical changes were implemented throughout the procedure.

This change was evaluated in accordance with 10 CFR 50.54(q)(3). The Emergency Preparedness Department Procedure (EPDP)-17, Attachment 2, Screening Evaluation Form concluded that this activity could not be implemented without performing a 10 CFR 50.54(q) reduction in effectiveness evaluation. Through the EPDP-17, Attachment 4, Effectiveness Evaluation Form, it was determined that the revised REP continues to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E. 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 regulatory commitments in this letter. If you have any questions regarding this submittal, please contact B. F. Tidwell at (256)729-3666 .

D. L. Hughes Vice President cc:

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