ML25363A184
| ML25363A184 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 01/12/2026 |
| From: | NRC/NMSS/DFM/FFLB |
| To: | |
| Shared Package | |
| ML25363A182 | List: |
| References | |
| EPID L-2025-LLA-0094 | |
| Download: ML25363A184 (0) | |
Text
Enclosure 1 DOCKET:
07003103 LICENSE:
SNM2010 LICENSEE:
LOUISIANA ENERGY SERVICES, LLC
SUBJECT:
SAFETY EVALUATION REPORT FOR LOUISIANA ENERGY SERVICES, LLC, LICENSE AMENDMENT REQUEST 25-02, LICENSING AMENDMENT FOR CHANGES TO INTEGRATED SAFETY ANALYSIS METHODOLGY (ENTERPRISE PROJECT IDENTIFICATION NUMBER L-2025-LLA-0094)
BACKGROUND In license amendment request 25-02 (LAR 25-02), Urenco USA (UUSA) requested to update its integrated safety analysis (ISA) methodology to adopt the most current, more conservative version of the Radiological Assessment System for Consequence Analysis (RASCAL) Code software for making independent dose and consequence projections during radiological incidents and emergencies and well as associated changes for future chemical consequence analyses to support continued plant expansion. Specifically, UUSA desired to change from RASCAL 3.0.5 to RASCAL 4.3.4. The proposed changes are intended to increase the flexibility in the future design, construction, and operation of the UUSA facility, while preserving a conservative ISA methodology.
REGULATORY REQUIREMENTS AND GUIDANCE The U.S. Nuclear Regulatory Commission (NRC) staff conducted its review of the LAR to ensure that the requested changes are consistent with the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 70, including:
10 CFR 70.62, Safety program and integrated safety analysis 10 CFR 70.65, Additional content of applications 10 CFR 70.72, Facility changes and change process The NRC staff used the guidance in Chapter 3 of NUREG-1520, Revision 2, Standard Review Plan for Fuel Cycle Facilities License Applications. The acceptance criteria for the NRCs review of UUSAs ISA are outlined in Sections 3.4.3.1 and 3.4.3.2 of NUREG-1520, Revision 2.
The acceptance criteria in Section 3.4.3.1 pertain to the performance of an ISA, while the criteria in Section 3.4.3.2 cover the content of the ISA Summary.
NRC STAFF REVIEW AND ANALYSIS The NRC reviewed the information provided in Enclosure 2 of the LAR in addition to the tracked changes in the ISA Summary and the Safety Analysis Report (SAR).
The changes requested in the LAR are:
- 1) Adding an updated version of RASCAL to the UUSA Licensing Code of Record to use for future consequence analyses;
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- 2) Utilizing Emergency Response Planning Guidelines (ERPG) limits for the offsite public in lieu of Acute Exposure Guideline Level (AEGL) limits for hydrogen fluoride and soluble uranium;
- 3) Assuming a 1-hour release duration unless otherwise calculated;
- 4) Increasing the number of significant figures used in the AEGL-1 limit in the SAR; and
- 5) Using Stability Class F with a wind speed of 1.0 m/s rather than the current Stability Class F with a wind speed of 0.6 m/s.
In response to a request for additional information dated September 2, 2025 (Agencywide Documents Access and Management System Accession No. ML25245A252), UUSA provided a revision to the LAR to add that the 1-hour release duration is used where an assumption is reasonable (or conservative).
EVALUATION FINDINGS The NRC staff evaluation of the proposed changes is that:
- 1) RASCAL is a tool developed by the NRC and the newer version of RASCAL incorporates improvements to modeling techniques and assumptions. The NRC encourages the use of the updated code.
- 2) As noted in the request, NUREG-1520 notes that the ERPG limits are acceptable for assessing consequences.
- 3) Assuming the entire source term is released within 1-hour, where an assumption is reasonable (or conservative), is acceptable.
- 4) The increase in the number of significant figures is a minor change and is acceptable.
- 5) The slight increase in windspeed is a small change and is still acceptably conservative.
ENVIRONMENTAL ASSESSMENT The NRC staff also considered whether there would be any significant environmental impacts associated with this request. The NRC staff has determined that implementation of the changes resulting from the RASCAL Code change are considered administrative in nature and do not involve an increase in any effluents, radiation exposures, construction impacts, or consequences from radiological accidents. The NRC staff has determined that the updates are categorically excluded from the requirement to prepare a site-specific environmental assessment. Therefore, in accordance with 10 CFR 51.22(c)(11), neither an environmental assessment nor an environmental impact statement is warranted for this action.
CONCLUSION The NRC staff has completed its review of LAR 25-02, in conjunction with the response to the NRC request for additional information. The NRC staff finds that the changes proposed are acceptable. Therefore, LAR 25-02 is approved.