ML18109A358

Submittal of 10 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 3, and 10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 3

ML18109A358
Person / Time
Site:	Browns Ferry
Issue date:	04/19/2018
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18109A358 (4)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 19, 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, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

10 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 3, and 10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 3

References:

1. TVA Letter to NRC, "1 O CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 3," dated April 5, 2017 (ML17095A243)

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 Annual 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), Units 1, 2, and 3.

• There have been no changes to the calculated peak cladding temperature (PCT) for BFN ,

Units 1 and 2, since the submittal of Reference 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 3 Refueling Outage 18, BFN, Unit 3, has a new calculated PCT for ATRIUM'-10 fuel of 2086 degrees Fahrenheit (°F) and a new calculated PCT for ATRIUM'-10XM fuel of 2016°F.

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 3.

This submittal satisfies the annual reporting requirement of 10 CFR 50.46(a)(3)(ii) for BFN ,

U.S. Nuclear Regulatory Commission Page 2 April 19, 2018 Units 1, 2, and 3, and also constitutes the required 30-day report for BFN , Unit 3. The BFN ,

Unit 3 Refueling Outage 18, ended on April 6, 2018; therefore, the 30-day report is due on May 6, 2018.

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

There are no regulatory commitments associated with this submittal. Should you have any questions, please contact J . L. Paul, Site Licensing Manager, at (256) 729-2636.

Re(;~Q\

D. L. Hughes Site Vice President

Enclosure:

10 CFR 50.46 30-Day and Annual Report for Browns Ferry Nuclear Plant, Unit 3 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 AND ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3 The Browns Ferry Nuclear Plant (BFN) , Unit 3, 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 3, was submitted on April 5, 2017. Since the issuance of Reference 1, a new baseline analysis supporting Extended Power Uprate (EPU) conditions was approved by the staff, effective with the startup of Cycle 19.

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 3 (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 E-1 of 2

ENCLOSURE 10 CFR 50.46 30-DAY AND ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3 ATRIUM'-10XM Fuel Evaluation The previous 10 CFR 50.46 report (Reference 1) for BFN, Unit 3, was submitted on April 5 2017.

Since the issuance of Reference 1, a new baseline analysis supporting EPU conditions was approved by the staff, effective with the startup of Cycle 19.

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 3 (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, "10 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 3," dated April 5, 2017 (ML17095A243)

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 E-2 of 2