RBG-48254, Report of Changes and Errors to 10CFR50.46
| ML23264A146 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/21/2023 |
| From: | Crawford R Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RBG-48254 | |
| Download: ML23264A146 (2) | |
Text
Randy Crawford
- Manager, Regulatory Assurance 225-381-4177 Entergy Operations, Inc., River Bend Station, 5485 U.S. Highway 61N, St. Francisville, LA 70775 10CFR50.46 RBG-48254 September 21, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Report of Changes and Errors to 10CFR50.46 River Bend Station - Unit 1 NRC Docket No. 50-458 Renewed Facility Operating License No. NPF-47
Reference:
Letter RBG-48198, "Report of Changes and Errors to 10CFR50.46" dated September 22, 2022 There has been one notice of changes or errors associated with the River Bend Station (RBS)
Emergency Core Cooling Systems (ECCS) analysis since the last 10CFR50.46 report provided to the NRC as documented in the reference of this letter. The Table on Page 2 of this letter summarizes the effects on the current ECCS analysis performed by General Electric - Hitachi Nuclear Energy (GEH). The ECCS-LOCA GNF3 analysis is based on the SAFER/PRIME ECCS-LOCA methodology.
Since the last 10CFR50.46 report provided to the NRC, RBS is currently in Cycle 23 with the RBS core composed of the GNF3 fuel type with a peak cladding temperature (PCT) of 1880ºF.
The PCT for the GNF3 fuel remains well below the 2200ºF acceptance criteria of 10CFR50.46.
RBG-48254 Page 2 of 2 Notification Letter NL-2023-01 Previous Periods NL-2021-07 NL-2021-02 NL-2021-01 NL-2020-05 NL-2020-04 NL-2019-05 Nature Of Change I Error Void in ECCS Piping After Final Check Valve Incorrect Recirculation Piping Inside Diameter Discrepancy in Inner Cladding Surface Rou hness Error in Fuel Pellet to Spring Conductance Error in Dynamic Gap Conductance Calculation in T ASC Incorrect fuel lattice elevation selected to enerate SAFER in uts Bypass leakage modeling for control rod guide tube to control rod guide housing interface Net of errors I changes Sum of absolute magnitude of changes / errors This letter does not contain any commitments.
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+30 30 If you have any questions or require additional information, please contact Mr. Randy Crawford at (225) 381-4177 or rcrawfo@entergy.com.
Respectfully, Randy Crawford RC/bj cc:
NRC Regional Administrator - Region IV NRC Project Manager - River Bend Station NRC Senior Resident Inspector - River Bend Station