GO2-20-070, 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

ML20114E265
Person / Time
Site:	Columbia
Issue date:	04/22/2020
From:	Dittmer J Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-20-070
Download: ML20114E265 (2)

Text




        

ENERGY J. Kent Dittmer Columbia Generating Station NORTHWEST P.O. Box 968, PE01 Richland, WA 99352-0968 Ph. 509-377-4248 l F. 509-377-2354 jkdittmer@energy-northwest.com April 22, 2020 GO2-20-070 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 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 criteria set forth in 10 CFR 50.46 (i.e.,

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 Ms. D.M.

Wolfgramm, Manager Regulatory Affairs, at (509) 377-4792.

Executed on this 22nd April

____ day of ___________, 2020.

Respectfully, J. Kent Dittmer Vice President, Engineering

Attachment:

Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2019 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector CD Sonoda - BPA




        

GO2-20-070 Attachment Page 1 of 1 Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2019 (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 The GE14 fuel was discharged from CGS core in May of 2019. There are no changes or errors to report through May 2019.

No other reporting will be provided for this fuel (GE14) going forward.

B. GNF2 Fuel - Prior 10 CFR 50.46 Changes or Error Corrections - This Year GEH - NL 2019-05 SAFER Lower Limit on PCT = 0 °F 0 °F Differential Pressure for Bypass Leakage GNF2 Fuel -Absolute Sum of 10 CFR 50.46 PCT = 0 °F 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 1730 °F for GE14 Fuel and 1700 °F for GNF2 fuel. The current PCT for this report is unchanged for both GE14 and GNF2.

References:

1. NE-02-03-08 Revision 6, 10CFR50.46 Cumulative PCT - Changes in ECCS LOCA Models

2. AR 402298, 10 CFR 50.46 (ECCS) Annual reporting requirements (187662)

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