ML18348B097

Transmittal of 10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 1

ML18348B097
Person / Time
Site:	Browns Ferry
Issue date:	12/14/2018
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18348B097 (4)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 December 14, 2018 10 CFR 50.4 10 CFR 50.46 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259

Subject:

10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 1

References:

1. TVA Letter to NRC, "10 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1 and 2, and 3 and 10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 3," dated April 19, 2018 (ML18109A358)

2. NRC Letter to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741 ,

MF6742, and MF6743)," dated August 14, 2017 (ML17032A120)

The purpose of this letter is to provide the 30-Day Report, as required by Title 10 of the Code of Federal Regulations (10 CFR) 50.46, of changes or errors discovered in the Emergency Core Cooling System (ECCS) evaluation model for Browns Ferry Nuclear Plant (BFN), Unit 1. In accordance with 10 CFR 50.46, "Acceptance Criteria for ECCS for Light-Water Nuclear Power Reactors," paragraph (a)(3)(ii), the Enclosure describes the nature and the estimated effect on the limiting ECCS analysis, of changes or errors discovered since submittal of Reference 1 for BFN , Unit 1.

In Reference 2, BFN Units 1, 2, and 3 were approved for extended power uprate (EPU) conditions. As a result, a new Loss of Coolant Accident (LOCA) analysis performed at EPU conditions revises the calculated PCT values for BFN. Therefore, at the conclusion of the BFN Unit 1 Fall refueling outage (1R12), BFN Unit 1 has a new calculated PCT for ATRIUM'-10 fuel of 2086 degrees Fahrenheit (°F) and a final calculated PCT for ATRIUM'-10XM fuel of 2016°F. The 1R12 refueling outage ended on November 22, 2018; therefore, the 30-day report is due on December 22, 2018.

As presented in this report, compliance with 10 CFR 50.46 requirements is demonstrated by the calculated PCT for BFN Unit 1 remaining below the 2200°F limit. Therefore, TVA has concluded that no proposed schedule for providing a reanalysis or other action is required .

U.S. Nuclear Regulatory Commission Page 2 December 14, 2018 There are no regulatory commitments associated with this submittal. Should you have any questions, please contact M. W . Oliver, Site Licensing Manager, at (256) 729-7874.

Enclosure:

10 CFR 50.46 30-Day Report for BFN , Unit 1 cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant State Health Officer, Alabama Department of Public Health

ENCLOSURE 10 CFR 50.46 30-DAY REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1 The Browns Ferry Nuclear Plant (BFN), Unit 1, core contains both the ATRIUM'-10 and ATRIUM'-10XM fuel designs.

ATRIUM'-10 Fuel Evaluation The previous 10 CFR 50.46 report (Reference 1) for BFN, Unit 1, was submitted on April 19 2018. Since the issuance of Reference 1, a new baseline analyses supporting Extended Power Uprate (EPU) conditions has been approved by the staff; effective with the startup of Cycle 13.

Table 1 details the accumulated peak cladding temperature (PCT) impact due to errors and changes in the loss of coolant accident (LOCA) analyses since the analysis of record (AOR) in Reference 2 of this enclosure.

Table 1: Cumulative Effect of PCT Changes - BFN, Unit 1 (ATRIUM'-10)

Baseline PCT (Reference 2) 2086°F Accumulated changes since baseline analysis + 0°F New licensing PCT 2086°F Absolute value of accumulated changes 0°F 1

ENCLOSURE 10 CFR 50.46 30-DAY REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1 ATRIUM'-10XM Fuel Evaluation The previous 10 CFR 50.46 report (Reference 1) for BFN, Unit 1, was submitted on April 19 2018. Since the issuance of Reference 1, a new baseline analyses supporting EPU conditions has been reviewed and approved by the staff; effective with the startup of Cycle 13.

Table 2 details the accumulated PCT impact due to errors and changes in the LOCA analyses since the AOR in Reference 3 of this enclosure. The table also identifies the new AOR (re-baseline) using the approved methodology, per Reference 4.

Table 2: Cumulative Effect of PCT Changes - BFN, Unit 1 (ATRIUM'-10XM)

Baseline PCT (Reference 3) 2008°F Cycle 19 fuel design specific limiting lattice (Reference 4) + 8°F Accumulated changes since baseline analysis + 8°F New licensing PCT 2016°F Absolute value of accumulated changes 8°F Re-baselined analysis using Approved Method, (Reference. 4, New AOR) 2016°F References

1. Letter from TVA to NRC, "1 0 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 3," dated April 19, 2018. (ML18109A358)

2. AREVA NP Inc., "Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM'-10 Fuel (EPU)," ANP-3384P Revision 3, August 2015.

3. AREVA NP Inc., "Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM' 10XM Fuel (EPU)," ANP-3378P Revision 3, August 2015.

4. AREVA NP Inc., "Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM' 10XM Fuel (EPU)," ANP-3378P Revision 4, December 2017.

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