ML17037C896

Submittal of Site Emergency Plan Implementing Procedure Revisions

ML17037C896
Person / Time
Site:	Browns Ferry
Issue date:	02/06/2017
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
EPIP-13, Reb. 23
Download: ML17037C896 (2)

Text

Tennessee Valley Authority , 1101 Market Street, Chattanooga, Tennessee 37402 February 6, 2017 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 (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-13 0023 Dose Assessment 01/10/2017

U.S. Nuclear Regulatory Commission Page 2 February 6, 2017 Description of Changes and Summary of Analysis EPIP-13 was revised to perform editorial or typographical corrections to the Procedure Body and Attachments 1, 2, and 3. The revision also added instruction for requests for dose assessments for Independent Spent Fuel Storage Installation Releases . This proposed addition provides a means of assessing a radioactive release from one of the specific casks ; therefore , it ensures that the plan remains in compliance with the regulation .

There were also non-editorial or non-typographical changes made to the procedure. The value for the Noble Gas Release rate column of the "LOCA EPU Normal RCS" section of the table in was revised . Attachment 6 was also added to section 4.1 to ensure that the form is retained as a Quality Assurance record when used in response to an actual emergency.

These changes were evaluated in accordance with 10 CFR 50.54(q)(3) . It was determined that the changes did not reduce the effectiveness of the BFN REP , and the BFN REP , as revised ,

continues to meet the requirements of 10 CFR 50, Appendix E and the planning standards of 10 CFR 50.47(b) .

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.

cc (Enclosures):

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