ML25136A025
| ML25136A025 | |
| Person / Time | |
|---|---|
| Site: | 99902035 |
| Issue date: | 05/20/2025 |
| From: | Licensing Processes Branch |
| To: | |
| References | |
| EPID L-2025-TOP-0002 | |
| Download: ML25136A025 (3) | |
Text
REGULATORY AUDIT PLAN FOR STUDSVIK TOPICAL REPORT SSP-14-P01/028-TR-S1, REVISION 0, SUPPLEMENT 1, GENERIC APPLICATION OF THE STUDSVIK SCANDPOWER CORE MANAGEMENT SYSTEM TO PRESSURIZED WATER REACTORS; SUPPLEMENT FOR EXTENDED ENRICHMENT, BURNUP, AND SMRS DOCKET NO. 99902035 EPID: L-2025-TOP-0002
1.0 BACKGROUND
By letter dated January 28, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25028A255), Studsvik Scandpower, Inc. (Studsvik) submitted Topical Report (TR) SSP-14-P01/028-TR Supplement 1, Generic Application of the Studsvik Scandpower Core Management System to Pressurized Water Reactors: Supplement for Extended Enrichment, Burnup, and SMRs (ADAMS Package Accession No. ML25028A254), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval for licensing applications. The primary focus of the audit is to review analyses and calculations described in the TR.
The NRC staff will perform a regulatory audit in accordance with Office of Nuclear Reactor Regulation Office Instructions LIC-111, Revision 2, Regulatory Audits (ADAMS Accession No. ML24309A281), and LIC-500, Revision 9, Topical Report Review Process (ADAMS Accession No. ML20247G279). The audit will facilitate the NRC staff with discussions on technical issues, in determining whether requests for additional information are needed, and with drafting the safety evaluation.
2.0 REGULATORY AUDIT BASES While there are no directly applicable regulatory requirements for a generic application of a core simulator, a core simulator must adequately model core designs with an acceptable amount of uncertainty, as the core design establishes a basis for downstream safety analyses, which are used to demonstrate compliance with General Design Criteria 10, 11, 12, 13, 20, 25, 26, 27, and 28, as discussed in Section 4.3, Revision 3, Nuclear Design, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (ADAMS Accession No. ML070740003).
3.0 LOGISTICS The NRC staff will conduct a three-day in-person audit from Tuesday, June 24, 2025, to Thursday, June 26, 2025, in Idaho Falls, Idaho.
The NRC will also utilize an online portal to prepare for the in-person audit. The use of the online reference portal will be in accordance with the following restrictions:
The online reference portal will be password-protected, and passwords will be distributed to NRC staff members and contractors directly involved in the TRopical Report (TR) SSP-14-P01/028-TR Supplement 1 review on a need-to-know basis.
The online reference portal will not support any printing, saving, or downloading functions.
NRC staff members and contractors given password access to the online reference portal will be informed of the conditions of use of the online reference portal by NRC project managers.
The conditions associated with the online reference portal will be maintained throughout its use during the TRopical Report (TR) SSP-14-P01/028-TR Supplement 1 review process.
Documents posted to the online reference portal will be limited to basis and other reference material cited in the TR, unless otherwise agreed upon by Studsvik and NRC management.
5.0 TEAM ASSIGNMENTS Alex Collier, Technical Reviewer (NRR/DSS/SFNB)
Kevin Heller, Technical Reviewer (NRR/DSS/SFNB)
Devin Bradshaw, General Engineer (NRR/DSS/SCPB)
Demetrius Murray, Project Manager (NRR/DORL/LLPB) 6.0 REQUESTED DOCUMENTS AND DISCUSSION TOPICS Noting the early stages of staff review, the following general topics have been developed. More detailed questions can be developed during the remainder of the review.
A description of the fuel thermal-mechanical module, including inputs, outputs, models, or correlations implemented within the module and validations performed.
The range of applicability of the fuel thermal-mechanical module and any validation or verification at increased enrichments and higher burnups.
Predicted concentrations of isotopes of high importance at higher burnups and comparisons to either experimental data or code-to-code comparisons.
Validation of the nuclear uncertainty factors (NUFs) and nuclear reliability factors (NRFs) methodologies at increased enrichment and higher burnup.
The effects of increased enrichment and higher burnup on radial pellet power profiles.
The nuclear design of the lattices used for the analyses in Sections 2.2, 3.2, and 3.3.
Availability of experimental data at higher enrichments and burnups and Studsviks plans to benchmark the code system as data becomes available.
Generic applicability to light pressurized water small modular reactors.
The NRC staff request the following documents to be made available via electronic reading room 21 days in advance of the in-person audit to facilitate the staffs review and discussion in the regulatory audit.
B. Haugh, R.M. Ferrer, and J.D. Rhodes, "CASM05 PWR Methods and Validation Report," SSP-14-P01/012-R Rev. 1, Waltham, MA, 2015.
J. Hykes, R.M. Ferrer, "Benchmarking SIMULATES with Halden Fuel Temperature Measurements," SSP-14-P01/022-C, Waltham, MA, 201S.
B. Haugh, D. Dean, "S5C Case Matrix Assessment," SSP-14-P01/020-C, Waltham, MA, 2015.
J. Hykes, B. Haugh, "SIMULATE5 Pin-To-Box Uncertainties," SSP-14-P01/016-C Rev. 1, Waltham, MA, 2015.
E. Wehlage, M. Kruners, "Benchmarking the SIMULATE5 BEAVRS Model with CASM05 MxN," SSP-14-P01/023-C, Waltham, MA, 2015.
T. Bahadir, G. Grandi, R.M. Ferrer and J.D. Rhodes, "SIMULATES Methodology,"
SSP-10/46S, Rev. 3, Waltham, MA, 2014.
J.D. Rhodes, R.M. Ferrer, and J. Hykes, "CASM05 A Fuel Assembly Burnup Program User's Manual," SSP-07/431, Rev. 8, Waltham, MA, 2013.
P. Forslund Guimares, CASMO5-Serpent2 Fuel Pin Cell and Lattice Reactivity, Fission Rate and Number Density Comparisons for Higher Burnups and Enrichments, SSP-24-P01/009-CN, Idaho Falls, ID, 2024.
EPRI-1019102, Assessment of Hot Cell Examination of AREVA M5(R) Guide Tubes and Fuel Rods Irradiated in North Anna 1 and 2, Sep 2009.
E. Frishholtz, Summary of CMS5 Burnup Comparison for North Anna High Burnup Fuel Assembly FM3, Dominion Energy Engineering Technical Evaluation ETE-NAF-2024-0113, Rev. 0, Jan 2025.
J. Hykes, R. Ferrer, CASMO5-MCNP6 Uniform Lattice Reactivity Comparisons and Computational Benchmarks for Higher Enrichments, SSP-24-P01/006-CN, Idaho Falls, ID, 2024.
7.0 DELIVERABLES A regulatory audit summary will be provided within 90 days of the completion of the audit.