ML18109A201

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Site Emergency Plan Implementing Procedure Revisions
ML18109A201
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/19/2018
From: Hughes D
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML18109A201 (2)


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 19, 2018 10 CFR 50.4 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 Revisions 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 (REP). The affected documents are the BFN Emergency Plan Implementing Procedures (EPIPs) named below.

EPIP Revision Effective Date EPIP-1 0055 Emergency Classification Procedure 03/22/2018 EPIP-14 0021 Radiological Control Procedures 03/20/2018

U.S. Nuclear Regulatory Commission Page 2 April 19, 2018 Description of Changes and Summary of Analysis EPIP-1, Revision 55, was revised to incorporate non-editorial changes. This revision was conducted to update BFN Emergency Action Level (EAL) 1.1-G2, Table 1.1-G2, BFN EAL 1.2-G, Curve 1.2-G, and BFN EAL 1.5-S, Curve 1.5-S. The Minimum Steam Cooling Pressure and Heat Capacity Temperature Limit Curve changed for Unit 3 due to the new Extended Power Uprate conditions and power level. Consequently, the values for Unit 3 were updated . The new table provides data for all three units having different values reflecting a different fuel load. In addition to the Table , the EAL Information Bar was revised to add the unit specific designator.

EPIP-14, Revision 21 , was revised to incorporate a non-editorial change. The revision rewrote step 3.6.A.2. The revision also removed a statement from the step that implies that thyroid blockage requires 30 to 60 minutes. This statement was removed since no information could be found to validate that thyroid blockage requires 30 to 60 minutes. As it relates to when to take potassium iodide (Kl) , the World Health Organization recommends "Taking Kl shortly before or immediately at the time of exposure to radioactive iodine offers the most effective protection.".

These changes were evaluated in accordance with 10 CFR 50.54(q)(3). The Emergency Preparedness Department Procedure (EPDP)-17, Attachment 2, Screening Evaluation Form concluded that these activities could not be implemented without performing a 10 CFR 50.54(q) reduction in effectiveness evaluation . Through the EPDP-17, Attachment 4, Effectiveness Evaluation Form , it was determined that the revised REP continues to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E. The activity does not constitute a reduction in effectiveness; therefore, it was concluded that the activity could be implemented without prior approval.

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.

Resp~ ~

D. ~ ghes Vice President 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