CNL-17-048, Central Emergency Control Center Emergency Plan Implementing Procedure Revision
| ML17101A740 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 04/06/2017 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| CNL-17-048 | |
| Download: ML17101A740 (2) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-048 April 6, 2017 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), the Tennessee Valley Authority (TVA) is submitting a description of changes to the TVA Radiological Emergency Plan (REP). The affected document is the Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP) named below.
Document Revision Title Effective Date CECC EPIP-21 16 Emergency Duty Officer Procedure for Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency 03/17/2017
U.S. Nuclear Regulatory Commission CNL-17-048 Page 2 April 6, 2017 Description of Changes and Summary of Analysis CECC EPIP-21 was revised to update organization and position titles, add references to other pertinent procedures, update references within the procedure, and correct grammar and punctuation issues.
These changes were evaluated in accordance with 10 CFR 50.54(q)(3). It was 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 in this letter. If you have any questions regarding this submittal, please contact Ed Schrull at (423) 751-3850.
Res~
J.t. ~hea ViJ°e President, Nuclear Licensing 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 NRR Project Manager - Browns Ferry Nuclear Plant NRR Project Manager - Sequoyah Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS