ML18066A497

Browns Ferry, Units 1, 2, and 3 - Site Emergency Plan Implementing Procedure Revisions

ML18066A497
Person / Time
Site:	Browns Ferry
Issue date:	03/07/2018
From:	Hughes D L 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 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1 , 2 , and 3 10 CFR 50.4 10 CFR 50.54(q) 10 CFR 50 , Appendix E 10 CFR 72.44(f) 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 EPIP-13 Revision 0024 Effective Date 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 i n Centra l Emergency Control Center (CECC) EPIP-8 was added. Lastly , a number of ed i tor i al/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 F orm concluded that this activity could not be implemented without performing a 10 CFR 50.54(q) reduction i n 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 1 O CFR 50 Appendix E. The activity does not constitute a reduction i n effectiveness

therefore , it was concluded that the activity could be implemented withou t pr i or approval.

There are no new regulatory commitments in this letter. If you have any questions regarding th i s submittal , please contact B. F. Tidwell at (256)729-3666. D. L. Hughes V i ce P r es i dent 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