GO2-18-056, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46
| ML18106A501 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/12/2018 |
| From: | Javorik A Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-18-056 | |
| Download: ML18106A501 (3) | |
Text
April 12, 2018 ENERGY NORTHWEST G02-18-056 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555-0001 Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 Richland, WA 99352-0968 Ph. 509-377-8555 IF. 509-377-2354 aljavorik@energy-northwest.com 10 CFR 50.46(a)(3)(ii)
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 1 O CFR 50.46 report dated April 17, 2017, there were two notices of errors reported to Columbia by the fuel vendor Global Nuclear Fuel. The impact of the changes to the Peak Clad Temperature is estimated to be O °F. 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 1 O CFR 50.46 (i.e., s 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 at (509) 377-4792.
Executed on this I 2~ay of April, 2018 Respectfully,
~r-A. L. Javo Vice President, Engineering
GO2-18-056 Page 2 of 2
Attachment:
Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2017 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C CD Sonoda - BPA/1399 WA Horin - Winston & Strawn
GO2-18-056 Attachment Page 1 of 1 Loss of Coolant Accident Margin Summary Sheet - Annual Report for 2017 (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 Effect Absolute PCT Effect A. GE14 Fuel - Prior 10 CFR 50.46 Changes or Error Corrections - This Year GEH - NL 2017 Fuel Rod Plenum Temperature Update PCT =
0 °F 0 °F GE14 Fuel - Absolute Sum of 10 CFR 50.46 Changes PCT =
0 °F B. GNF2 Fuel - Prior 10 CFR 50.46 Changes or Error Corrections - This Year GEH - NL 2017 GNF2 Lower Tie Plate Leakage PCT =
0 °F 0 °F GEH - NL 2017 Fuel Rod Plenum Temperature Update PCT =
0 °F 0 °F GNF2 Fuel - Absolute Sum of 10 CFR 50.46 Changes PCT =
0 °F 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 374826374826 10 CFR 50.46 (ECCS) Annual reporting requirements (187662)