GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis
| ML20351A255 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/16/2020 |
| From: | Franssen R Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2020/00045 | |
| Download: ML20351A255 (2) | |
Text
10 CFR 50.46 GNRO-2020/00045 December 16, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
2020 Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 NRC Docket No. 50-416 Renewed Facility Operating License No. NPF-29
REFERENCE:
- 1. Entergy letter to NRC, GNRO-2019/00052, 2019 Report of Changes and Errors to 10CFR50.46, dated December 13, 2019 (ADAMS Accession No. ML19354A508).
In accordance with 10 CFR 50.46(a)(3)(ii), Grand Gulf Nuclear Station, Unit 1 (GGNS), is required to report to the Nuclear Regulatory Commission, at least annually, the estimated effect on the limiting Emergency Core Cooling System (ECCS) analysis caused by changes to, or errors discovered in, the acceptance ECCS evaluation model.
Since the last 10 CFR 50.46(a)(3)(ii) report, dated December 13, 2019 [Reference 1], through December 1, 2020, there has been one error identified in the PRIME coding. The PRIME code calculates fuel rod conditions as input to the ECCS Loss Of Coolant Accident (LOCA) evaluation model. PRIME provides fuel rod conditions as input to SAFER and TRACG for ECCS LOCA calculations. The PRIME coding errors for input data generation are considered reportable under interpretation of 10 CFR 50.46. For these findings with the PRIME code, an assessment was performed by General Electric Hitachi (GEH) for a span of representative plants with the SAFER and TRACG evaluation models. Using input from the corrected PRIME code, the results confirmed a Peak Clad Temperature (PCT) impact of zero (0) degrees Fahrenheit.
Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Robert Franssen Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500
GNRO-2020/00045 Page 2 of 2 This letter contains no new commitments. Should you have any questions or require additional information, please contact Jim Shaw at 601-437-2103.
Sincerely, Robert Franssen RF/fas
Attachment:
None.
cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
~/