ML20015A270
| ML20015A270 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/15/2020 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML20015A270 (2) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 January 15, 2020 10 CFR 50.54(q) 10 CFR 50, Appendix E 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
Subject:
Browns Ferry Nuclear Plant - Site Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q); 10 CFR 50, Appendix E; and 10 CFR 72.44(f), the Tennessee Valley Authority (TVA) is submitting a description of changes to the Browns Ferry Nuclear Plant (BFN) Radiological Emergency Plan. The affected document is the BFN Emergency Plan Implementing Procedure (EPIP) named below.
EPIP Revision Title Effective Date EPIP-6 0041 Activation and Operation of the Technical Support Center (TSC) 12/16/2019 EPIP-7 0036 Activation and Operation of the Operations Support Center (OSC) 12/16/2019 Description of Changes and Summary of Analysis EPIP-6 Revision 41 and EPIP-7 Revision 36 were revised to add instruction related to making appropriate notifications when sample results exceeding Emergency Action Level (EAL) thresholds are received. These changes were screened collectively because the justification for making them was the same. This activity was determined to be a change to the radiological emergency plan that was not editorial or typographical in nature. This change was also determined to not conform to an activity that has prior approval. Planning Standard 10 CFR 50.47(b)(1) - Assignment of Responsibility was determined to be impacted by this change; therefore, it was concluded that this activity could not be implemented without performing a 50.54(q) reduction in effectiveness evaluation. Upon completion of the Effectiveness Evaluation Form it was concluded that the
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U.S. Nuclear Regulatory Commission Page 2 January 15, 2020 activity continues to comply with the requirements of 50.47(b) and 50 Appendix E, and the activity does not constitute a reduction in effectiveness. Therefore, the activity was allowed to be implemented without prior approval.
Also EPIP-6 Revision 41 proposes updating Appendix X, Site Emergency Director Turnover Data Sheet, to improve the efficiency of completing the form and the level of detail related to plant system status, affected equipment, and protective actions taken. The activity was determined to be a change to the radiological emergency plan that was not editorial or typographical in nature.
The change did not conform to an activity that had prior approval; however, it was also determined that none of the Planning Standards were impacted by the change. The activity did not involve a site specific EP commitment; therefore, it was determined that this activity could be implemented without performing a 50.54(q) reduction in effectiveness evaluation.
There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact B. F. Tidwell at (256) 729-3666.
cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRC Director - Division of Spent Fuel Management, NMSS