CNL-22-051, 10 CFR 50.46 Annual Report

10 CFR 50.46 Annual Report

ML22119A207
Person / Time
Site:	Browns Ferry
Issue date:	04/29/2022
From:	Rasmussen M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-22-051
Download: ML22119A207 (6)

Text

10 CFR 50.4 10 CFR 50.46 1101 Market Street, Chattanooga, Tennessee 37402 CNL-22-051 April 2, 2022 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, Browns Ferry Nuclear Plant, Units 1, 2, and 3, 10 CFR 50.46 Annual Report, dated April 30, 2021 (ML21120A164) 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) 3.

NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -

Issuance of Amendment Nos. 310, 333, and 293 Regarding Maximum Extended Load Line Limit Analysis Plus (EPID L-2018-LLA-0048), dated December 26, 2019 (ML19210C308)

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.

As noted in the previous submittal of the annual report (Reference 1), all three BFN units have now implemented their Extended Power Uprate operation, as approved in Reference 2, and their Maximum Extended Load Line Limit Analysis Plus operation, as approved in Reference 3.

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

U. S. Nuclear Regulatory Commission CNL-22-051 Page 2 April 2, 2022 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, Tennessee Valley Authority has concluded that no proposed schedule for providing a reanalysis or other action is required.

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, Matthew M. Rasmussen 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 Respecctfully, Matthew M Rasmusse

Enclosure CNL-22-051 E1 of 4 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.

The previous Title 10 of the Code of Federal Regulations (10 CFR) 50.46 Annual Report for BFN was submitted per Reference 1. Since the issuance of Reference 1, no new baseline analysis supporting Extended Power Uprate (EPU) Maximum Extended Load Line Limit Analysis Plus (MELLLA+) conditions has been generated.

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

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

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1)

Increased Access Hole Cover and low pressure coolant injection (LPCI)

Leakages (Reference 3)

RDX2_2_RDX4 Corrections (Reference 3)

+ 0°F

+ 0°F

+ 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, Browns Ferry Nuclear Plant, Units 1, 2, and 3, 10 CFR 50.46 Annual Report, dated April 30, 2021 (ML21120A164)

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

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

Enclosure CNL-22-051 E2 of 4 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 2 The BFN Unit 2 core contains the ATRIUM-10XM fuel designs and a limited number of ATRIUM-11 lead fuel assemblies (LFAs). The previous 10 CFR 50.46 Annual Report for BFN was submitted per Reference 1. Since the issuance of Reference 1, no new baseline analysis supporting EPU MELLLA+ conditions has been generated.

Fuel Evaluation Tables 2 and 3 detail the accumulated PCT impact due to errors and changes in the LOCA analysis since the previously reported AOR (Reference 1).

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

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1)

Increased Access Hole Cover and LPCI Leakages (Reference 3)

RDX2_2_RDX4 Corrections (Reference 3)

+ 0°F

+ 0°F

+ 0°F New licensing PCT 2052°F Absolute value of accumulated changes since last baseline analysis 0°F Table 3: Cumulative Effect of PCT Changes - BFN Unit 2 (ATRIUM-11 LFAs)

Baseline PCT (Reference 3) 1903°F All thermal conductivity degradation effects (Reference 1)

RODEX4 Axial Pellet-Cladding Mechanical Interaction Onset (Reference 3)

AUTOHUP inputs preparation of RODEX2-2A inputs (Reference 3)

Increased Access Hole Cover and LPCI Leakages (Reference 3)

RDX2_2_RDX4 Corrections (Reference 3)

+ 0°F

+ 0°F

+ 2°F

+ 0°F

+ 0°F New licensing PCT 1905°F Absolute value of accumulated changes 2°F

Enclosure CNL-22-051 E3 of 4 References (Unit 2)

1. TVA Letter to NRC, Browns Ferry Nuclear Plant, Units 1, 2, and 3, 10 CFR 50.46 Annual Report, dated April 30, 2021 (ML21120A164)

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

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

Enclosure CNL-22-051 E4 of 4 10 CFR 50.46 ANNUAL REPORT FOR BROWNS FERRY NUCLEAR PLANT, UNIT 3 The BFN Unit 3 core contains the ATRIUM-10XM fuel designs. The previous 10 CFR 50.46 Annual Report for BFN was submitted per Reference 1. Since the issuance of Reference 1, no new baseline analysis supporting EPU MELLLA+ conditions has been generated.

Fuel Evaluation Table 4 details the accumulated PCT impact due to errors and changes in the LOCA analysis since the previously reported AOR (Reference 1).

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

Baseline PCT (Reference 2) 2052°F All thermal conductivity degradation effects (Reference 2, Section 5.1)

Increased Access Hole Cover and LPCI Leakages (Reference 3)

RDX2_2_RDX4 Corrections (Reference 3)

+ 0°F

+ 0°F

+ 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, Browns Ferry Nuclear Plant, Units 1, 2, and 3, 10 CFR 50.46 Annual Report, dated April 30, 2021 (ML21120A164)

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

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