CNL-20-097, Submittal of Emergency Plan Implementing Procedure Revision
| ML20337A438 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 12/02/2020 |
| From: | Polickoski J Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| CNL-20-097 | |
| Download: ML20337A438 (2) | |
Text
10 CFR 50.54(q) 10 CFR 72.44(f)
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-097 December 2, 2020 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 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390, 50-391, and 72-1048
Subject:
TENNESSEE VALLEY AUTHORITY - CENTRAL EMERGENCY CONTROL CENTER EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISION In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q) and 10 CFR 72.44(f), Tennessee Valley Authority (TVA) is submitting a description of changes to the TVA Radiological Emergency Plan (REP). The affected document is a Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP).
Document Revision Title Effective Date CECC EPIP-19 24 Post Accident Fuel Damage Assessment 11/14/2020
U.S. Nuclear Regulatory Commission CNL-20-097 Page 2 December 2, 2020 Description of Changes and Summary of Analysis CECC EPIP-19 TVA revised this EPIP to update the values and plots in the attachments for fuel damage assessment for Watts Bar Unit 2 such that they reflect the new tritium producing core.
The above changes were evaluated in accordance with 10 CFR 50.54(q)(3) and 10 CFR 72.44(f). TVA determined that the changes did not reduce the effectiveness of the TVA REP. The TVA REP, as revised, continues to meet the requirements in Appendix E to 10 CFR 50 and the planning standards of 10 CFR 50.47(b).
There are no new regulatory commitments associated with this submittal. If you have any questions regarding this information, please contact Kimberly D. Hulvey, Senior Manager, Fleet Licensing at (423) 751-3275.
Respectfully, James T. Polickoski Director, Nuclear Regulatory Affairs cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS