CNL-20-001, Central Emergency Control Center Emergency Plan Implementing Procedure Revision

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Central Emergency Control Center Emergency Plan Implementing Procedure Revision
ML20010D255
Person / Time
Site: Browns Ferry, Watts Bar, Sequoyah  
Issue date: 01/09/2020
From: Polickoski J
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CNL-20-001
Download: ML20010D255 (2)


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-001 January 9, 2020 10 CFR 50.54(q) 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 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-21 18 Emergency Duty Officer Procedure for Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency 12/11/2019

U.S. Nuclear Regulatory Commission CNL-20-001 Page 2 January 9, 2020 Description of Changes and Summary of Analysis CECC EPIP-21 TVA revised this EPIP to add an action for the Emergency Duty Officer regarding the web based emergency management platform (WebEOC).

The above change was evaluated in accordance with 10 CFR 50.54(q)(3) and 10 CFR 72.44(f). TVAdetemiined that the change 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 in this letter. Please address any questions regarding this submittal to Kimberly D. Hulvey, Fleet Licensing Manager, at (423) 751-3275.

Respectfully, V

Jmes T. Polickoski Director, Nuclear Regulatory Affairs cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Feny 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