ML25105A283: Difference between revisions
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| number = ML25105A283 | | number = ML25105A283 | ||
| issue date = 04/29/2025 | | issue date = 04/29/2025 | ||
| title = LOCA Analysis of FFRD for Westinghouse 2-Loop, 3-Loop and 4-Loop Plants Audit Report Cover Letter | | title = LOCA Analysis of FFRD for Westinghouse 2-Loop, 3-Loop and 4-Loop Plants Audit Report Cover Letter (EPID L-2024-NTR-0003) | ||
| author name = Delosreyes J | | author name = Delosreyes J | ||
| author affiliation = NRC/NRR/DORL/LLPB | | author affiliation = NRC/NRR/DORL/LLPB | ||
| Line 13: | Line 13: | ||
| document type = Letter | | document type = Letter | ||
| page count = 1 | | page count = 1 | ||
}} | }} | ||
| Line 24: | Line 22: | ||
==Dear Dr. Aylin Kucuk:== | ==Dear Dr. Aylin Kucuk:== | ||
By | By letter dated April 26, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24121A203), Electric Power Research Institute (EPRI) submitted (1) EPRI Report 3002028673, Loss-of-Coolant-Accident [(LOCA)]-Induced Fuel Fragmentation, Relocation, and Dispersal [(FFRD)] with Leak-Before-Break Credit - Alternative Licensing Strategy [ALS], (2) EPRI Reports 3002028675 (NP)/3002028674 (P), LOCA Analysis of Fuel Fragmentation, Relocation, and Dispersal for Westinghouse 2-Loop, 3-Loop, and 4-Loop Plants | ||
- Proprietary, Evaluation of Cladding Rupture in High Burnup Fuel Rods Susceptible to Fine Fragmentation (collectively called ALS for LOCA Analysis of FFRD), and (3) EPRI Report 3002023895, Materials Reliability Program: xLPR [Extremely Low Probability of Rupture] | - Proprietary, Evaluation of Cladding Rupture in High Burnup Fuel Rods Susceptible to Fine Fragmentation (collectively called ALS for LOCA Analysis of FFRD), and (3) EPRI Report 3002023895, Materials Reliability Program: xLPR [Extremely Low Probability of Rupture] | ||
Estimation of PWR [Pressurized Water Reactor] Loss-of-Coolant Accident Frequencies (MRP-480), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. | Estimation of PWR [Pressurized Water Reactor] Loss-of-Coolant Accident Frequencies (MRP-480), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. | ||
Revision as of 04:35, 11 February 2026
| ML25105A283 | |
| Person / Time | |
|---|---|
| Site: | Electric Power Research Institute |
| Issue date: | 04/29/2025 |
| From: | Delosreyes J Licensing Processes Branch |
| To: | Kucuk A Electric Power Research Institute |
| References | |
| EPID L-2024-NTR-0003, 3002028675 (NP), 3002028674 (P) | |
| Download: ML25105A283 (1) | |
Text
OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLYPROPRIETARY INFORMATION April 29, 2025 Dr. Aylin Kucuk Program Manager, Nuclear Fuels Electric Power Research Institute Palo Alto Office 3420 Hillview Avenue, Palo Alto, CA 94304-133
SUBJECT:
REPORT FOR THE U.S. NUCLEAR REGULATORY COMMISSION REGULATORY CLOSED AUDIT CONDUCTED ON NOVEMBER 26, 2024-JANUARY 31, 2025, FOR THE REVIEW OF ELECTRIC POWER RESEARCH INSTITUTE TECHNICAL REPORT 3002028674/5, LOCA [LOSS-OF-COOLANT-ACCIDENT] ANALYSIS OF FUEL FRAGMENTATION, RELOCATION, AND DISPERSAL FOR WESTINGHOUSE 2-LOOP, 3-LOOP, AND 4-LOOP PLANTS (EPID L-2024-NTR-0003)
Dear Dr. Aylin Kucuk:
By letter dated April 26, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24121A203), Electric Power Research Institute (EPRI) submitted (1) EPRI Report 3002028673, Loss-of-Coolant-Accident [(LOCA)]-Induced Fuel Fragmentation, Relocation, and Dispersal [(FFRD)] with Leak-Before-Break Credit - Alternative Licensing Strategy [ALS], (2) EPRI Reports 3002028675 (NP)/3002028674 (P), LOCA Analysis of Fuel Fragmentation, Relocation, and Dispersal for Westinghouse 2-Loop, 3-Loop, and 4-Loop Plants
- Proprietary, Evaluation of Cladding Rupture in High Burnup Fuel Rods Susceptible to Fine Fragmentation (collectively called ALS for LOCA Analysis of FFRD), and (3) EPRI Report 3002023895, Materials Reliability Program: xLPR [Extremely Low Probability of Rupture]
Estimation of PWR [Pressurized Water Reactor] Loss-of-Coolant Accident Frequencies (MRP-480), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval.
The NRC staff conducted a virtual regulatory closed audit on November 26, 2024, to January 31, 2025, to discuss major topics of the Technical Report 3002028674/5 topical report (TR) review. The non-proprietary (Enclosure 1) and proprietary (Enclosure 2) versions (based on the proprietary markup of the audit report provided by EPRI) of the audit report are enclosed.
NOTICE: Enclosure 2 to this letter contains Proprietary Information. Upon separation from Enclosure 2, this letter is DECONTROLLED.
OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLYPROPRIETARY INFORMATION If you have any questions, please contact me via phone at 301-415-4141 or via email at James.Delosreyes@nrc.gov.
Sincerely,
/RA/
James Delosreyes, Project Manager Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 99902021
Enclosures:
- 1. Non-Proprietary audit report
- 2. Proprietary audit report
Package: ML25105A282 Cover letter: ML25105A283 Non-proprietary Enclosure 1: ML25105A284 Proprietary Enclosure 2: ML25105A285 OFFICE DORL/LLPB/PM DORL/LLPB/LA DSS/SFNB/BC DNRL/NPHP/BC NAME JDelosreyes DHarrison SKrepel MMitchell DATE 4/16/2025 4/23/2025 4/24/2025 4/16/2025 OFFICE DORL/LLPB/BC DORL/LLPB/PM DORL/LLPB/PM NAME JRankin LJames JDelosreyes DATE 4/24/2025 4/28/2025 4/29/2025