RBG-48306, Report of Changes and Errors to 10CFR50.46

Report of Changes and Errors to 10CFR50.46

ML24268A150
Person / Time
Site:	River Bend
Issue date:	09/24/2024
From:	Crawford R Entergy Operations
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RBG-48306
Download: ML24268A150 (1)

Text

entergy RBG-48306 September 24, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Report of Changes and Errors to 1 0CFR50.46 River Bend Station -Unit 1 NRC Docket No. 50-458 Renewed Facility Operating License No. NPF-47 Randy Crawford

Manager, Regulatory Assurance 225-381-4177 10CFR50.46

Reference:

Letter RBG-48254, "Report of Changes and Errors to 1 0CFR50.46" dated September 21, 2023 (ADAMS Accession No. ML23264A146).

There have been no notice of changes or errors associated with the River Bend Station (RBS)

Emergency Core Cooling Systems (ECCS) analysis since the last 1 0CFR50.46 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 1 0CFR50.46 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 1880°F.

The PCT for the GNF3 fuel remains well below the 2200°F acceptance criteria of 1 0CFR50.46.

Entergy Operations, Inc., River Bend Station, 5485 U.S. Highway 61 N, St. Francisville, LA 70775 RBG-48306 Page 2 of 2 Notification Letter Previous Periods NL-2023-01 NL-2021-07 NL-2021-02 NL-2021-01 NL-2020-05 NL-2020-04 Nature Of Change / 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 TASC Incorrect fuel lattice elevation selected to enerate SAFER in uts Bypass leakage modeling for control rod NL-2019-05 guide tube to control rod guide housing interface Net of errors / changes Sum of absolute magnitude of changes / errors This letter does not contain any commitments. Estimated PCT Effect (°F)

GNF3

+25 0

0 0

0

+5 0

+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/tf cc: NRC Regional Administrator -Region IV NRC Project Manager -River Bend Station NRC Senior Resident Inspector -River Bend Station Entergy Operations, Inc., River Bend Station, 5485 U.S. Highway 61 N, St. Francisville, LA 70775