NRC-23-0025, Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report

Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report

ML23117A329
Person / Time
Site:	Fermi
Issue date:	04/28/2023
From:	Frank E DTE Electric Company
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC-23-0025
Download: ML23117A329 (1)

Text

DTE Electric Company 6400 . Dixie Highway Newport, MI 48166 DTE April 28, 2023 TS 5.6.6 NRC-23-0025 10 CFR 50.46 U.S. Nuclear Regulat01y Commission Attention: Document Control Desk Washington, DC 20555-0001 Penni 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Submittal of2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Elrnrs Rep01t The Fe1mi 2 Technical Specifications (TS) contain a requirement for submitting an annual report for safety relief valve challenges (TS 5.6.6).Enclosure 1 provides the Safety Relief Valve Challenge Report for 2022. provides the Service Life of tl1e Main Steam Bypass Lines Rep01t for 2022. This satisfies the commitment stated in Detroit Edison's letter to the NRC dated ovember 7, 1986 (VP-86-0154). provides the annual Emergency Core Cooling System (ECCS) Cooling Performance Evaluation Model Changes or EITors Repo1t. This report is provided in accordance with 10 CFR 50.46(a)(3)(ii).

No new commitments are being made in this submittal.

Should you have any questions or require additional inf01mation, please contact me at (734) 586-4772.

Eric Frank Manager - Nuclear Licensing

Enclosure:

1. Safety Relief Valve Challenge Report 2022

2. Service Life of Main Steam Bypass Lines Repo1t 2022

3. ECCS Cooling Pe1f01mance Evaluation Model Changes or Elrnrs Repo1t cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III

Enclosure 1 to NRC-23-0025 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Safety Relief Valve Challenge Report 2022 to NRC-23-0025 Page 1 of 1 Safety Relief Valve Challenges (January 1, 2022 to December 31, 2022)

There were no instances in 2022 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were also no instances in 2022 where an SRV actuation was demanded by an automatic logic system.

Enclosure 2 to NRC-23-0025 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Service Life of Main Steam Bypass Lines Report 2022 to NRC-23-0025 Page 1 of 1 Service Life of Main Steam Bypass Lines (January 1, 2022 to December 31, 2022)

In accordance with Detroit Edisons letter to the NRC dated November 7, 1986 (VP-86-0154),

the cumulative time the main steam bypass lines are operated with the bypass valves between 30 and 45 percent open will be reported annually. A cumulative value of 100 days is not to be exceeded, for a calendar year, without prior NRC notification.

As discussed in Detroit Edisons letter number VP-86-0154, the bypass lines are acceptable for safe operation when operated within the 100-day constraint.

As of December 31, 2022, the main steam bypass lines cumulative usage was 50.2 days.

Enclosure 3 to NRC-23-0025 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 ECCS Cooling Performance Evaluation Model Changes or Errors Report to NRC-23-0025 Page 1 of 2 Emergency Core Cooling System (ECCS) Cooling Performance Evaluation Model -

Analysis of Record On April 8, 2020, DTE Energy submitted a re-analysis of the Loss of Coolant Accident (LOCA) using TRACG-LOCA (Reference 1). This re-analysis established a new licensing basis Peak Clad Temperature (PCT) of 1980°F for GE14 fuel and 2150°F for GNF3 fuel which are both associated with the limiting small break LOCA.

ECCS Cooling Performance Evaluation Model Changes or Errors Since the time of the submittal of the analysis of record identified above, General Electric -

Hitachi (GEH) and Global Nuclear Fuel (GNF) have issued the following notifications which indicated that changes had been made in the ECCS-LOCA analyses inputs that affect Fermi 2.

2020-01 April 14, 2020 Reference 2 2021-01 February 18, 2021 Reference 3 2021-02 February 18, 2021 Reference 4 2021-04 July 06, 2021 Reference 5 2021-08 October 14, 2021 Reference 6 2021-09 October 14, 2021 Reference 7 A tabulated summary of the impacts of all errors is provided below.

Current LOCA Model Assessment Description GE14 PCT GNF3 PCT 10CFR 50.46 Baseline Licensing Basis PCT PCT=1980°F PCT=2150°F (Reference 1) 10 CFR 50.46 Notification Letter 2020-01 dated April Not applicable to Not applicable to 14, 2020, PRIME Coding Errors for Zircaloy Fermi 2 LOCA Fermi 2 LOCA Irradiation Growth and Zr Barrier Thermal Analysis-of- Analysis-of-Conductivity as Input to ECCS LOCA Analyses Record Record (Reference 2) (PCT = 0°F) (PCT = 0°F)

Not applicable to Not applicable to 10 CFR 50.46 Notification Letter 2021-01 dated Fermi 2 LOCA Fermi 2 LOCA February 18, 2021, Error in Fuel Pellet to Plenum Analysis-of- Analysis-of-Spring Conductance (Reference 3) Record Record (PCT = 0°F) (PCT = 0°F) 10 CFR 50.46 Notification Letter 2021-02 dated Not applicable to February 18, 2021, Discrepancy in Inner Cladding PCT = 0°F GNF3 fuel Surface Roughness (Reference 4) (PCT = 0°F) 10 CFR 50.46 Notification Letter 2021-04 dated July 06, 2021, Noncondensable Gas Error in Zero Cell PCT = 0°F PCT = 0°F Side Branch (Reference 5) to NRC-23-0025 Page 2 of 2 Description GE14 PCT GNF3 PCT 10 CFR 50.46 Notification Letter 2021-08 dated October 14, 2021, Incorrect Upper Plenum Volume PCT = 0°F PCT = 0°F (Reference 6) 10 CFR 50.46 Notification Letter 2021-09 dated October 14, 2021, TRACG04P Version 4.2.76.1 PCT = 0°F PCT = 0°F (Reference 7)

Net PCT PCT=1980°F PCT=2150°F

References:

1. DTE Letter to USNRC, Submittal of Plant Specific Emergency Core Cooling System (ECCS) Evaluation Model Reanalysis, NRC-20-0010, dated April 8, 2020 (ML20100B567)

2. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2020-01, dated April 14, 2020.

3. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2021-01, dated February 18, 2021.

4. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2021-02, dated February 18, 2021.

5. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2021-04, dated July 06, 2021.

6. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2021-08, dated October 14, 2021.

7. General Electric-Hitachi, 10 CFR 50.46 Notification Letter 2021-09, dated October 14, 2021.