View source for 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

{{Adams
| number = ML23117A329
| issue date = 04/28/2023
| title = Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
| author name = Frank E
| author affiliation = DTE Electric Company
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000341
| license number = NPF-043
| contact person = 
| case reference number = NRC-23-0025
| document type = Annual Operating Report, Letter type:NRC
| page count = 1
}}

=Text=
{{#Wiki_filter: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&deg;F for GE14 fuel and 2150&deg;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&deg;F           PCT=2150&deg;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&deg;F)        (PCT = 0&deg;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&deg;F)        (PCT = 0&deg;F) 10 CFR 50.46 Notification Letter 2021-02 dated                                   Not applicable to February 18, 2021, Discrepancy in Inner Cladding               PCT = 0&deg;F           GNF3 fuel Surface Roughness (Reference 4)                                                   (PCT = 0&deg;F) 10 CFR 50.46 Notification Letter 2021-04 dated July 06, 2021, Noncondensable Gas Error in Zero Cell           PCT = 0&deg;F          PCT = 0&deg;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&deg;F           PCT = 0&deg;F (Reference 6) 10 CFR 50.46 Notification Letter 2021-09 dated October 14, 2021, TRACG04P Version 4.2.76.1               PCT = 0&deg;F           PCT = 0&deg;F (Reference 7)
Net PCT                                                   PCT=1980&deg;F           PCT=2150&deg;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.}}