CNL-23-034, 10 CFR 50.46 Annual Report

10 CFR 50.46 Annual Report

ML23116A290
Person / Time
Site:	Browns Ferry
Issue date:	04/26/2023
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
CNL-23-034
Download: ML23116A290 (1)

Text

1101 Market Street, Chattanooga, Tennessee 37402 CNL-23-034 April 26, 2023 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:

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

References:

1. TVA letter to NRC, CNL-22-051, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - 10 CFR 50.46 Annual Report, dated April 29, 2022 (ML22119A207)

2. NRC letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos. 325, 348, and 308 Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564-A, Revision 2, Safety Limit MCPR, in Support of ATRIUM 11 Fuel Use (EPID L-2021-LLA-0132),

dated January 13, 2023 (ML22348A066)

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 evaluation model for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3.

Since the previous submittal of an annual report (Reference 1), Unit 2 has now implemented the first reload of ATRIUM 11 fuel as approved per Reference 2.

This submittal satisfies the annual reporting requirement of 10 CFR 50.46(a)(3)(ii) for BFN Units 1, 2, and 3.

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.

U.S. Nuclear Regulatory Commission CNL-23-034 Page 2 April 26, 2023 There are no new regulatory commitments associated with this submittal. Please address any questions to Chris L. Vaughn, Manager, Site Licensing, at clvaughn@tva.gov.

Respectfully, Manu Sivaraman Site Vice President Browns Ferry Nuclear Plant

Enclosure:

10 CFR 50.46 Annual Report for BFN Units 1, 2, and 3 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant

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 ATRIUMTM-10XM fuel designs.

The previous Title 10 of the Code of Federal Regulations (10 CFR) 50.46 annual report for BFN was submitted per Reference 1.

Fuel Evaluation Table 1 details 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). PCT analysis was previously re-baselined per Reference 2.

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

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1) + 0°F Increased Access Hole Cover and low pressure coolant injection (LPCI) + 0°F Leakages (Reference 3)

RDX2_2_RDX4 Corrections (Reference 3) + 0°F New licensing PCT 2052°F Absolute value of accumulated changes since last baseline analysis 0°F References (Unit 1)

1. TVA letter to NRC, CNL-22-051, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -

10 CFR 50.46 Annual Report, dated April 29, 2022 (ML22119A207)

2. Framatome Inc., ANP-3547P, Revision 2, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel (EPU MELLLA+), dated January 2020.

3. Framatome Inc., FS1-0044279, Revision 4, 10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU/MELLLA+ Conditions, dated November 19, 2021.

CNL-23-034 E1 of 4

Enclosure 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 2 The BFN Unit 2 core contains the ATRIUMTM-10XM and ATRIUM-11 fuel designs. The previous 10 CFR 50.46 Annual Report for BFN was submitted per Reference 1. Since the issuance of References 1 and 4, Unit 2 has begun operation with ATRIUM-11 fuel.

Fuel Evaluation Tables 2 and 3 detail the accumulated PCT impact due to errors and changes in the loss of coolant accident analysis since the previously reported AOR (References 1 and 4).

Table 2: Cumulative Effect of PCT Changes - BFN, Unit 2 (ATRIUMTM-11)

Baseline PCT (Reference 4) 1898°F S-RELAP5 Cladding Thermal Conductivity (Reference 5) + 0°F Cladding Hydrogen Content (Reference 5) + 0°F Cladding Oxide Thickness (Reference 5) + 0°F MICROBURN-B2 Provides Inappropriate Flow in Inlet Node for ACE + 0°F Calculations (Reference 5)

Increased Access Hole Cover and LPCI Leakages (Reference 5) + 0°F New licensing PCT 1898°F Absolute value of accumulated changes 0°F Table 3: Cumulative Effect of PCT Changes - BFN, Unit 2 (ATRIUMTM-10XM)

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1) + 0°F Access Hole Cover and LPCI Leakages (Reference 3) + 0°F RDX2_2_RDX4 Corrections (Reference 3) + 0°F New licensing PCT 2052°F Absolute value of accumulated changes since last baseline analysis 0°F CNL-23-034 E2 of 4

Enclosure References (Unit 2)

1. TVA letter to NRC, CNL-22-051, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -

10 CFR 50.46 Annual Report, dated April 29, 2022 (ML22119A207)

2. Framatome Inc., ANP-3547P, Revision 2, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel (EPU MELLLA+), dated January 2020

3. Framatome Inc., FS1-0044279, Revision 4, 10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU/MELLLA+ Conditions, dated November 19, 2021

4. Framatome Inc., ANP-3905P, Revision 2, Browns Ferry Units 1, 2, and 3 LOCA Analysis for ATRIUM 11 Fuel, dated June 2022

5. Framatome Inc., FS1-0063865, Revision 2, 10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 ATRIUM 11 Fuel, dated December 13, 2022 CNL-23-034 E3 of 4

Enclosure 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3 The BFN Unit 3 core contains the ATRIUMTM-10XM fuel designs. The previous 10 CFR 50.46 Annual Report for BFN was submitted per Reference 1.

Fuel Evaluation Table 4 details the accumulated PCT impact due to errors and changes in the loss of coolant accident analysis since the previously reported AOR (Reference 1). PCT analysis was previously re-baselined per Reference 2.

Table 4: Cumulative Effect of PCT Changes - BFN, Unit 3 (ATRIUMTM-10XM)

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1) + 0°F Increased Access Hole Cover and LPCI Leakage. (Reference 3) + 0°F RDX2_2_RDX4 Corrections (Reference 3) + 0°F New licensing PCT 2052°F Absolute value of accumulated changes since last baseline analysis 0°F References (Unit 3)

1. TVA letter to NRC, CNL-22-051, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -

10 CFR 50.46 Annual Report, dated April 29, 2022 (ML22119A207)

2. Framatome Inc., ANP-3547P, Revision 2, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel (EPU MELLLA+), dated January 2020.

3. Framatome Inc, FS1-0044279, Revision 4, 10 CFR 50.46 PCT Error Report for Browns Ferry Units 1, 2, and 3 with EPU/MELLLA+ Conditions, dated November 19, 2021.

CNL-23-034 E4 of 4