L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models

2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models

ML23104A087
Person / Time
Site:	Beaver Valley
Issue date:	04/14/2023
From:	Blair B Energy Harbor Nuclear Corp
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-23-053
Download: ML23104A087 (1)

Text

energy Energy Harbor Nuclear Corp.

harb or Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Barry Blair 440-280-7300 Site Vice President, Beaver Valley Nuclear April 14, 2023 L-23-053 10 CFR 50.46(a)(3)(ii)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergenc y Core Cooling System Evaluation Models In accordance with 10 CFR 50.46(a)(3)(ii), Energy Harbor Nuclear Corp. hereby submits the 2022 annual report of changes to or errors in emergency core cooling system (ECCS) evaluation model, or in the application of such model, for the Beaver Valley Power Station, Unit Nos. 1 (BVPS-1) and 2 (BVPS-2). The attached report covers the period of January 1, 2022, to December 31, 2022.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Manager -

Fleet Licensing, at 330-696-7208.

Beaver Valley Power Station, Unit Nos. 1 and 2 L-23-053 Page2

Attachment:

2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative

Attachment L-23-053 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Page 1 of 2 Title 10 of the Code of Federal Regulations, Part 50, Section 50.46(a)(3) states that each holder of an operating license shall report to the Nuclear Regulatory Commission (NRC), at least annually, each change to or error in an acceptable emergency core cooling system (ECCS) evaluation model (EM), or in the application of such a model, that affects the calculation of peak cladding temperature (PCT). The nature of the change or error and its estimated effect on the limiting ECCS analysis is to be included in the report.

During the 2022 calendar year, there were no changes or errors in the evaluation model for the current reporting period currently being used to support the design basis at BVPS-1 and BVPS-2.

Therefore, a net PCT change of 0°F (analyzed) from the end of 2021 to the end of 2022 is reported for the Small Break LOCA and Large Break LOCA analyses.

The estimated effects on the peak cladding temperatures for this reporting period are summarized in Table 1.

Attachment L-23-053 Page 2 of 2 Table 1 10 CFR 50.46 Summary for 2022 Beaver Valley Power Station, Unit 1 Large Break Small Break LOCA LOCA PCT or PCT PCT or PCT Change Change Licensing Basis PCT at BEGINNING of 2022 1840°F 1895°F 2022 Activity EM Changes I None 0°F 0°F EM Errors I None 0°F 0°F Licensing Basis PCT at END of 2022 1840°F 1895°F Beaver Valley Power Station, Unit 2 Large Break Small Break LOCA LOCA PCT or PCT PCT or PCT Change Change Licensing Basis PCT at BEGINNING of 2022 1839°F 1917°F 2022 Activitv EM Changes I None 0°F 0°F EM Errors I None 0°F 0°F Licensing Basis PCT at END of 2022 1839°F 1917°F