CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
| ML24108A034 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 04/17/2024 |
| From: | Hulvey K Tennessee Valley Authority |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| CNL-24-033 | |
| Download: ML24108A034 (1) | |
Text
10 CFR 50.54(q) 10 CFR 72.44(f) 1101 Market Street, Chattanooga, Tennessee 37402 CNL-24-033 April 17, 2024 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) listed below.
Document Revision Title Effective Date CECC EPIP-1 78 Central Emergency Control 03/19/2024 Center (CECC) Operations CECC EPIP-19 27 Post Accident Fuel Damage 03/19/2024 Assessment
U.S. Nuclear Regulatory Commission CNL-24-033 Page 2 April 17, 2024 Description of Changes and Summary Analysis CECC EPIP-1 TVA revised this EPIP as follows.
Appendix J, State Communicator Checklist Editorial change to Appendix J, Step 3 of CECC Activation to change operational to activated without a change to meaning or intent. This change aligns the procedure with the wording contained in the REP.
Editorial change to Appendix J, Step 1 and 7 of General Operations to combine the two steps into a single step without changing meaning or intent. Editorial change to Appendix J, Step 3 of General Operations to align step syntax with the rest of the checklist without changing meaning or intent.
Appendix R, TVA PAR Recommendations for Areas at or Beyond the 10-Mile EPZ Editorial change to Appendix R to include actual dose in addition to projected dose considerations on the form for Protective Action Recommendations (PARs) beyond 10 miles to align with the existing guidance in Appendix G, Appendix H, and Appendix Q of CECC EPIP-1 which direct evaluation of actual and projected dose when determining PARs beyond 10 miles.
CECC EPIP-19 TVA revised this EPIP as follows.
Attachments 2, 3, 4, 9, 10, and 11 The revision of CECC EPIP-19, Post Accident Fuel Damage Assessment, incorporates editorial/typographical changes to Attachments 2, 3, 4, 9, 10, and 11 to change references for DATAWARE to the generic term Data Historian without changing the meaning or intent.
The above changes were evaluated in accordance with 10 CFR 50.54(q)(3). TVA 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).
U.S. Nuclear Regulatory Commission CNL-24-033 Page 3 April 17, 2024 There are no new regulatory commitments in this letter. Please address any questions regarding this submittal to Stuart L. Rymer, Senior Manager, Fleet Licensing, at slrymer@tva.gov.
Respectfully, Kimberly D. Hulvey Director, Nuclear Regulatory Affairs 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 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 Digitally signed by Edmondson, Carla Date: 2024.04.17 07:05:28 -04'00'