RBG-48254, Report of Changes and Errors to 10CFR50.46

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 RBG-48254 10CFR50.46 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.

Entergy Operations, Inc., River Bend Station, 5485 U.S. Highway 61N, St. Francisville, LA 70775

RBG-48254 Page 2 of 2 Estimated PCT Notification Effect °F Nature Of Change I Error Letter GNF3 NL-2023-01 Void in ECCS Piping After Final Check Valve +25 Previous Periods NL-2021-07 Incorrect Recirculation Piping Inside Diameter 0 Discrepancy in Inner Cladding Surface NL-2021-02 0 Rou hness NL-2021-01 Error in Fuel Pellet to Spring Conductance 0 Error in Dynamic Gap Conductance NL-2020-05 0 Calculation in TASC Incorrect fuel lattice elevation selected to NL-2020-04 +5 enerate SAFER in uts Bypass leakage modeling for control rod NL-2019-05 guide tube to control rod guide housing 0 interface Net of errors I changes +30 Sum of absolute magnitude of changes / errors 30 This letter does not contain any commitments.

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