View source for NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023

{{Adams
| number = ML24011A183
| issue date = 01/10/2024
| title = Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023
| author name = Dewhirst L
| author affiliation = Nebraska Public Power District (NPPD)
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000298
| license number = DPR-046
| contact person = 
| case reference number = NLS2024004
| document type = Annual Operating Report, Letter type:NLS
| page count = 1
}}

=Text=
{{#Wiki_filter:Nebraska Public Power District Always there when you need us NLS2024004                                                                        50.46(a)(3 )(ii)
January 10, 2024 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

==Subject:==
Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 Cooper Nuclear Station, Docket No. 50-298, DPR-46

==Reference:==
Letter from Linda Dewhirst, Nebraska Public Power District, to U.S. Nuclear Regulatory Commission, dated January 19, 2023, "Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022"

==Dear Sir or Madam:==

The purpose of this letter is to submit the 2023 annual report of changes and errors in the Emergency Core Cooling System (ECCS) evaluation models pursuant to 10 CFR 50.46(a)(3)(ii) for Cooper Nuclear Station (CNS).
Per the reference letter, Nebraska Public Power District previously reported errors/changes in the ECCS evaluation models for GNF2 fuel. These errors continued to apply to the ECCS evaluation methodologies for 2023. There were no new changes or errors affecting the licensing basis peak clad temperature (PCT) in 2023. CNS continues to comply with the PCT limit of 2200&deg;F specified in 10 CFR 50.46(b)(1 ). to this letter itemizes the changes/errors in the ECCS evaluation models that remained applicable in 2023 and Attachment 2 provides data that demonstrates compliance with the ECCS performance requirements of 10 CFR 50.46.
This letter makes no regulatory commitments.
If you have any questions regarding this report, please contact Ryan VanderPlas, Fuels Engineer, at (40      5-5409.
Lind Dewhirst Regulatory Affairs & Compliance Manager
/jo COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: {402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

NLS2024004 Page 2 of2 Attachments: 1) Changes/Errors in Emergency Core Cooling System Evaluation Models Applicable in 2023
: 2) 10 CFR 50.46 Criteria in Emergency Core Cooling System Evaluation Models for 2023 cc:    Regional Administrator w/attachments USNRC - Region IV Cooper Project Manager w/attachments USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/attachments USNRC-CNS NPG Distribution w/attachments CNS Records w/attachments

NLS2024004 Page 1 of 1 Changes/Errors in Emergency Core Cooling System Evaluation Models Applicable in 2023 GNF2 Fuel GE Hitachi             Date                 Subject           PCT Impact 10 CFR 50.46 Notification Letter 2017-01            6/12/17        GNF2 Lower Tie              -20&deg;F Plate Leakage 2017-02             8/2/17        Fuel Rod Plenum               ooF Temperature Update 2019-05            11/1/19        SAFER Lower Limit             ooF on Differential Pressure for Bypass Leakage 2020-01            4/14/20        PRIME Code Errors             ooF for Evaluation Model Fuel Rod Condition Inputs 2021-01             2/18/21        Fuel Pellet to Plenum         ooF Spring Conductance Input to ECCS LOCA Calculations 2021-02             2/18/21        Inner Cladding                ooF Surface Roughness Input to Gap Conductance Model Total = -20&deg;F

NLS2024004 Page 1 of 1 10 CFR 50.46 Criteria in Emergency Core Cooling System Evaluation Models for 2023 Fuel Type       Licensing Basis PCT      Local Oxidation      Core-Wide Metal-Water Reaction GNF2                 2130&deg;F                 <6.00%               <0.10%}}