CNL-18-055, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

ML18103A215
Person / Time
Site:	Browns Ferry, Watts Bar, Sequoyah
Issue date:	04/11/2018
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CNL-18-055
Download: ML18103A215 (2)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-055 April 11, 2018 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 REVISIONS 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 documents are the Central Emergency Control Center (CECC) Emergency Plan Implementing Procedures (EPIP) named below.

Document Revision Title Effective Date CECC EPIP-9 58 Emergency Environmental Radiological 4/6/2018 Monitoring Procedures

U.S. Nuclear Regulatory Commission CNL-18-055 Page 2 April 11, 2018 Description of Changes and Summary of Analysis CECC EPIP-9 was revised to clarify data fields for logging field team readings, to clarify that the Scintrex tritium monitors apply to the inventory requirements for the Watts Bar Nuclear Plant only, and to update instructions for use of the environmental monitoring van global positioning system (GPS) units. Other minor/editorial changes were also made as part of the revision.

These changes were evaluated in accordance with 10 CFR 50.54(q)(3). TVA determined that the changes do 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 comm itments in this letter. If you have any questions regarding this submittal, please contact Ed Schrull at (423) 751-3850 .

. Shea President, Nuclear Regulatory Affairs and Support Services 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