ML19122A029

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 2

ML19122A029
Person / Time
Site:	Browns Ferry
Issue date:	05/01/2019
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML19122A029 (8)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 1, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR 50.4 10 CFR 50.46 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 2

References:

1. TVA Letter to NRC, "10 CFR 50.46 Annual Report for Browns Ferry Nuclear Plant, Units 1, 2, and 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. MF67 41,

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.

Since the previous submittal of an Annual Report, (Reference 1 ), all three BFN units have now implemented their approved extended power uprate operation per Reference 2.

In accordance with 1 O CFR 50.46, "Acceptance Criteria for ECCS for Light-Water Nuclear Power Reactors," paragraph (a)(3)(ii), Enclosure 1 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 2.

This submittal satisfies the annual reporting requirement of 1 O CFR 50.46(a)(3)(ii) for BFN Units 1, 2, and 3 and also constitutes the required 30-day report for BFN Unit 2. The BFN Unit 2 spring refueling outage (2R20) ended on April 10, 2019. Therefore, the 30-day report is due on May 10, 2019.

U. S. Nuclear Regulatory Commission Page 2 May 1, 2019 As presented in this report, compliance with 10 CFR 50.46 requirements is demonstrated by the calculated peak cladding temperature for all three BFN units remaining below the 2200 degrees Fahrenheit limit. Therefore, TVA 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.

Res~tt D. L. Hughes Site Vice President Browns Ferry Nuclear Plant

Enclosure:

10 CFR 50.46 Unit 2 30-Day and All Unit Annual Report for BFN 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 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1 The Browns Ferry Nuclear Plant (BFN), Unit 1, core contains the ATRIUM'-10XM fuel designs, and a small number of legacy ATRIUM-10 assemblies. The previous 10 CFR 50.46 Annual Report for BFN, was submitted per Reference 1. Additionally, TVA submitted a 10 CFR 50.46 30-day report in Reference 6. Since the issuance of Reference 1, a new baseline analysis supporting Extended Power Uprate (EPU) conditions has been generated using the approved methodology; effective with the startup of Cycle 13.

Fuel Evaluation Tables 1 and 2 detail the accumulated peak cladding temperature (PCT) impact due to errors and changes in the loss of coolant accident analysis since the previously reported analysis of record (AOR) Reference 1.

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

Baseline PCT for EPU conditions (Reference 2) 2086°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape)

+ 0°F (original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°F Accumulated changes since baseline analysis

+ 0°F New licensing PCT 2086°F Absolute value of accumulated changes 0°F Table 2: Cumulative Effect of PCT Changes - BFN, Unit 1 (ATRIUM'-10XM)

Baseline PCT (Reference 3) 2008°F Cycle specific fuel design limiting lattice (Reference 4)

+ 8°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape Error)

+ 0°F (original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°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 E-1

References ENCLOSURE 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1

1. Letter from TV A to NRC, "10 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.

5. Framatome Inc, "10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU Conditions," FS1-0037856, Revision 1, December 2018.

6. Letter from TVA to NRC, "10 CFR 50.46 30-Day Report for Browns Ferry Nuclear Plant, Unit 1," dated December 14, 2018. (ML183488097)

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ENCLOSURE 10 CFR 50.46 30-DAY AND ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 2 The Browns Ferry Nuclear Plant (BFN), Unit 2, core contains the ATRIUM'-10XM fuel designs, and a limited number of ATRIUM-11 lead fuel assemblies. The previous 10 CFR 50.46 Annual Report for BFN, was submitted per Reference 1. Since the issuance of Reference 1, a new baseline analysis supporting Extended Power Uprate (EPU) conditions has been generated using the approved methodology; effective with the startup of Cycle 21.

Fuel Evaluation Tables 3 & 4 detail the accumulated peak cladding temperature (PCT) impact due to errors and changes in the loss of coolant accident analysis since the previously reported analysis of record (AOR) Reference 1.

Table 3: Cumulative Effect of PCT Changes - BFN, Unit 2 (ATRIUM'-11 LFA's)

Baseline PCT for EPU conditions (Reference 5) 1903°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape)

+ 0°F (original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°F Accumulated changes since baseline analysis

+ 0°F New licensing PCT 1903°F Absolute value of accumulated changes 0°F Table 4: Cumulative Effect of PCT Changes - BFN, Unit 2 (ATRIUM'-10XM)

Baseline PCT (Reference 3) 2008°F Cycle specific fuel design limiting lattice (Reference 4)

+ 8°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape)

+ 0°F

( original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°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 E-3

References ENCLOSURE 10 CFR 50.46 30-DAY AND ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 2

1. Letter from TVA to NRC, "10 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.

5. Framatome Inc, "10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU Conditions," FS1-0037856, Revision 1, December 2018.

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ENCLOSURE 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3 The Browns Ferry Nuclear Plant (BFN), Unit 3, core contains the ATRIUM'-10XM fuel designs, and a small number of legacy ATRIUM-10 assemblies. The previous 10 CFR 50.46 Annual Report for BFN, was submitted per Reference 1. Since the issuance of Reference 1, a new baseline analysis supporting Extended Power Uprate (EPU) conditions has been generated using the approved methodology; effective with the startup of Cycle 20.

Fuel Evaluation Tables 5 & 6 detail the accumulated peak cladding temperature (PCT) impact due to errors and changes in the loss of coolant accident analysis since the previously reported analysis of record (AOR) Reference 1.

Table 5: Cumulative Effect of PCT Changes - BFN, Unit 3 (Legacy ATRIUM'-10)

Baseline PCT for EPU conditions (Reference 2) 2086°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape)

+ 0°F (original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°F Accumulated changes since baseline analysis

+ 0°F New licensing PCT 2086°F Absolute value of accumulated changes 0°F Table 6: Cumulative Effect of PCT Changes - BFN, Unit 3 (ATRIUM'-10XM)

Baseline PCT (Reference 3) 2008°F Cycle specific fuel design limiting lattice (Reference 4)

+ 8°F All thermal conductivity degradation effects (Reference 5)

(Top Lattices Utilizing Top Peaked Power Shape Error)

+ 0°F (original disposition in the EPU LAR; summarized per References 3-4, Section 5.1)

+ 0°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 E-5

References ENCLOSURE 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3

1. Letter from TV A to NRC, "10 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.

5. Framatome Inc, "10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU Conditions," FS1-0037856, Revision 1, December 2018.

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