ML18040A373
| ML18040A373 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/09/2018 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18040A373 (2) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 9, 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 (TVA) 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-12 Revision 0020 Effective Date Emergency Equipment and Supplies 01/10/2018
U.S. Nuclear Regulatory Commission Page 2 February 9, 2018 Description of Changes and Summary of Analysis EPIP-12, Revision 20, was revised to incorporate both editorial changes and a non-editorial or typographical change. This revision added functional checks of the Emergency Communication Notification System phones that are located in each main Control Room and the Alternate Facility.
This change also proposed several editorial changes 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 and 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.
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