GO2-19-066, 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

ML19107A493
Person / Time
Site:	Columbia
Issue date:	04/17/2019
From:	Javorik A Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-19-066
Download: ML19107A493 (3)

Text

ENERGY Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 NORTHWEST Richland, WA 99352-0968 Ph. 509-377-8555 J F. 509-377-2354 aljavorik@energy-northwest.com April 17, 2019 GO2-19-066 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.

The Columbia Generating Station (Columbia) core consists of a mixture of Global Nuclear Fuel GE14 fuel and Global Nuclear Fuel GNF2 fuel. The attached report provides the details related to changes affecting the analysis of record for this reporting period.

Since the last 10 CFR 50.46 report dated April 12, 2018, there were no changes or errors reported to Columbia by the fuel vendor Global Nuclear Fuel. There have been no changes to the evaluation models used for calculating ECCS performance. The licensing basis Peak Clad Temperature for all fuel types in the core remains within the acceptance criteria set forth in 10 CFR 50.46 (i.e., :5 2200 °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. S. A. Nappi at (509) 377-4598.

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Executed on this /1--day of April, 2019 Respectfully, A. L. Jav Vice President, Engineering

GO2-19-066 Page 2 of 2

Attachment:

Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2018 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C CD Sonoda - BPA/1399 WA Horin - Winston & Strawn

GO2-19-066 Attachment Page 1 of 1 Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2018 (Per NFM-4-1 Table 7-b)

Plant Name: Columbia Generating Station Utility Name: Energy Northwest Evaluation Model: (Description or Name) GE14: SAFER/GESTR-LOCA Models, GNF-2: SAFER/PRIME-LOCA Models Net PCT Absolute Effect PCT Effect A. GE14 Fuel - Prior 10 CFR 50.46 Changes or Error Corrections - This Year 2018 - GE14 Fuel - No Changes PCT = 0 °F 0 °F GE14 Fuel - Absolute Sum of 10 CFR 50.46 PCT = 0 °F Changes B. GNF2 Fuel - Prior 10 CFR 50.46 Changes or Error Corrections - This Year 2018 - GNF2 Fuel - No Changes PCT = 0 °F 0 °F GNF2 Fuel - Absolute Sum of 10 CFR 50.46 PCT = 0 °F Changes The sum of the Peak Cladding Temperature (PCT) 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 1730 °F for GE14 Fuel and 1700 °F for GNF2 fuel. The current PCT for this report is unchanged for both GE14 fuel and GNF2 fuel.

References:

1. NE-02-03-08 Revision 5, 10 CFR 50.46 Cumulative PCT - Changes in ECCS LOCA Models

2. AR 387871, 10 CFR 50.46 (ECCS) Annual reporting requirements (187662)

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