GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46

Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46

ML23072A464
Person / Time
Site:	Columbia
Issue date:	03/13/2023
From:	Hauger J Energy Northwest
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
GO2-23-034
Download: ML23072A464 (1)

Text

 
!

     

ENERGY Jeremy S. Hauger Columbia Generating Station NORTHWEST P.O. Box 968, PE30 Richland, WA 99352-0968 Ph. 509-377-8727 jshauger@energy-northwest.com March 13, 2023 GO2-23-034 10 CFR 50.46(a)(3)(ii)

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

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 REPORT OF CHANGES OR ERRORS IN EMERGENCY CORE COOLING SYSTEM LOSS OF COOLANT ACCIDENT ANALYSIS MODELS PURSUANT TO 10 CFR 50.46

Dear Sir or Madam:

This report is provided in accordance with 10 CFR 50.46(a)(3)(ii), which requires, in part, annual reporting of changes to, or errors in, evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis.

There were no changes or errors reported to Columbia by the fuel vendor. The attached report provides the details related to changes affecting the analysis of record for this reporting period. The licensing basis Peak Clad Temperature for all fuel types in the core remains within the acceptance FULWHULDVHWIRUWKLQ&)5 LH °F).

There are no commitments being made to the Nuclear Regulatory Commission herein. If you have any questions, or require additional information, please contact Mr. R.M. Garcia, Acting Manager, Regulatory Affairs, at (509) 377-8463.



Executed on this _______ 

day of ___________, 2023.

Respectfully, IA

~it~

DocuSigned by:

Jeremy S. Hauger Vice President, Engineering

Attachment:

Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2022 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector CD Sonoda - BPA

 
!

     

GO2-23-034 Attachment Page 1 of 1 Loss of Coolant Accident Margin Summary Sheet - Annual Report (Per NFM-4-1 Table 7-b)

Plant Name: Columbia Generating Station Utility Name: Energy Northwest Evaluation Model: (Description or Name) GNF-2: SAFER/PRIME-LOCA Models Net PCT Absolute Effect PCT Effect GNF2 Fuel - Prior 10 CFR 50.46 Changes 0 °F or Error Corrections - Prior year (2022)

GNF2 Fuel - Prior 10 CFR 50.46 Changes 0 °F or Error Corrections - This year (2023)

GNF2 Fuel - Absolute Sum of 10 CFR 3&7 0 °F 50.46 Changes The sum of the PCT (Peak Cladding Temperature) from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200 °F. PCT prior to this report was 1700 °F for GNF2 fuel.

The current PCT for this report is unchanged for GNF2 fuel.

References:

1. NE-02-03-08 Revision 8, 10CFR50.46 Cumulative PCT - Changes in ECCS LOCA Models

2. AR 00439717, Provide Licensing information per 10 CFR 50.46(a)(3)(ii)

3. NFM-4-1 Revision 3, Tracking Changes in ECCS LOCA Analysis