CNL-17-025, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions

ML17058A455
Person / Time
Site:	Browns Ferry, Watts Bar, Sequoyah, 07200104
Issue date:	02/27/2017
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CNL-17-025
Download: ML17058A455 (2)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-025 February 27, 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 - RADIOLOGICAL EMERGENCY PLAN AND 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 REP Appendix and Central Emergency Control Center (CECC) Emergency Plan Implementing Procedures (EPIPs) named below.

Document Revision Title Effective Date REP Appendix A 108 Appendix A: Browns Ferry Nuclear Plant 01/31/2017 CECC EPIP-12 31 Operational Readiness Check of the CECC and 01/31/2017 the Field Coordination Centers for SQN, BFN, &

WBN and Joint Information Centers (JIC)

CECC EPIP-7 38 CECC Radiological Assessment Staff Procedure 02/07/2017 for Alert, Site Area Emergency, and General Emergency

U.S. Nuclear Regulatory Commission CNL-17-025 Page 2 February 27, 2017 Description of Changes and Summary of Analysis REP, Appendix A, was revised to correct the specified flow of information from the control room to the state as a result of changes in technology that were previously implemented . In addition, this revision updated calculation references, corrected several grammatical/typographical errors, and corrected references to specific sections in the Generic REP.

CECC EPIP-12 was revised to update inventories for the CECC and Joint Information Centers in order to reflect equipment changes resulting from technological advances and equipment obsolescence. Two changes to procedure requirements were also made to ensure that completed inventories were properly retained and to replace supervisory reviews of the inventories with reviews by any staff member. In addition, the revision included updates to position titles, organizational titles, attachment references , acronyms , and section headings.

CECC EPIP-7 was revised to update terminology and instructions to reflect hardware and software enhancements associated with CECC dose assessment, information display, and information transmittal. Additionally, the responsibilities of the Radiological Assessment Manager were updated to provide procedure references and to ensure that information is distributed within the CECC.

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.

Respectfully, J. W. Shea 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