CNL-17-006, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

ML17011A150
Person / Time
Site:	Browns Ferry, Watts Bar, Sequoyah
Issue date:	01/10/2017
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CNL-17-006
Download: ML17011A150 (2)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-006 January 10, 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 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 (EPIPs) named below.

Document Revision Title Effective Date CECC EPIP-6 40 CECC Plant Assessment Staff Procedure for 12/21/16 Alert, Site Area Emergency, and General Emergency CECC EPIP-9 56 Emergency Environmental Radiological 01/06/17 Monitoring Procedures

U.S. Nuclear Regulatory Commission CNL-17-006 Page 2 January 10, 2017 Description of Changes and Summary of Analysis CECC EPIP-6 was revised to ensure that appropriate plant information is being distributed to the Radiological Assessment Managers through previously established communication lines. CECC EPIP-6 terminology was also updated to reflect release type options included in other implementing procedures. Other editorial changes were made to the procedure as well.

CECC EPIP-9 was revised to update phone numbers, update dosimeter terminology, move information from notes and footnotes to the body of the procedure, and update and relocate the barium source activity chart used for scaler set-up. These changes did not impact the performance of the procedure.

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.

Respe ti lly, ~

J.

Vice 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