RBG-48375, Report of Changes and Errors to 10 CFR 50.46
| ML25272A235 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/29/2025 |
| From: | Mccoy J Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RBG-48375 | |
| Download: ML25272A235 (1) | |
Text
- ) entergy RBG-48375 September 29, 2025 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 Jack McCoy
- Manager, Regulatory and Emergency Planning River Bend Station 225-378-3310 10CFR50.46
Reference:
Letter RBG-48306, "Report of Changes and Errors to 1 0CFR50.46" dated September 24, 2024 (ADAMS Accession No. ML24268A150).
There has 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.
RBS is currently in Cycle 24 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-48375 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 NL-2019-05 Nature Of Change/ Error Void in ECCS Piping After Final Check Valve Incorrect Recirculation Piping Inside Diameter Discrepancy in Inner Cladding Surface Roughness Error in Fuel Pellet to Spring Conductance Error in Dynamic Gap Conductance Calculation in TASC Incorrect fuel lattice elevation selected to generate SAFER inputs 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.
Estimated PCT Effect (°F)
+25 0
0 0
0
+5 0
+30 30 If you have any questions or require additional information, please contact Mr. Jack McCoy at (225) 378-331 O or jmccoy1@entergy.com.
Respectfully, Jack McCoy Jack McCoy JM/tf Digitally signed by Jack McCoy ON: cn=Jack McCoy, o=REP Manager, ou=RBS, emait=jmccoy1@entergy.com Date: 2025.09.29 07:48:45 -05'00' 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