ML19038A164

Site Emergency Plan Implementing Procedure Revision

ML19038A164
Person / Time
Site:	Browns Ferry
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 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 1 0 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 Revision In acco r dance 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 EPIP-12 Revision 0021 Emergency Equipment and Supplies Description of Changes and Summary of Analysis Effective Date 01/08/2019 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 i n Attachment

1. 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 o r 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 i n 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 i n effectiveness Therefore , the activity was implemented without prior approval.

U.S. Nuclear Regulatory Commission Page 2 February 7 , 2019 This revis i on also proposed several changes that were editorial/typographical in nature. The appropriate source note documentation related to commitment 114096292 was added to Attachment 1 (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 ed i toria l/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. H u ghes 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