ML24348A042

Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-29

ML24348A042
Person / Time
Site:	05200050
Issue date:	12/13/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
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Download: ML24348A042 (1)

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Response to NuScale Topical Report Audit Question Question Number: A-NonLOCA.LTR-29 Receipt Date: 04/15/2024 Question:

Revise the TR to reference the current versions of TR-0915-17564-P-A and TR-108601-P-A.

Section 4.3.1.1.2 of the TR references TR-0915-17564-P-A and TR-108601-P-A. However, there are newer versions of these twothis reference referenced that are developed for the NPM-20 design. These references need to be updated. Provide proposed markups to the TR.

Response

Section 4.3.1.1.2 of the non-LOCA topical report (TR-0516-494160-P Revision 4) includes cross-references to References 6 and 28. As identified in Section 11.0, References 6 and 28 correspond to Subchannel Analysis Methodology, TR-0915-17564-P-A, Revision 2, and Statistical Subchannel Analysis Methodology, TR-108601-P, Revision 2, respectively. NuScale has confirmed that the information in Reference 6 for the Subchannel Analysis Methodology is accurate and current; there is no newer version and no changes are required. NuScale agrees that there is a newer revision for Reference 28 and the information is revised accordingly.

In addition, to the change associated with this audit question, NuScale is updating other references in Section 11.0 to the latest version, as applicable.

Markups of the affected changes, as described in the response, are provided below:

NuScale Nonproprietary NuScale Nonproprietary

Non-Loss-of-Coolant Accident Analysis Methodology TR-0516-49416-NP Draft Revision 5

© Copyright 2024 by NuScale Power, LLC 728 11.0 References

1.

U.S. Nuclear Regulatory Commission, Transient and Accident Analysis Methods, Regulatory Guide 1.203, December 2005.

2.

NuScale Power, LLC, Loss-of-Coolant Accident Evaluation Model, TR-0516-49422-P, Revision 3.

Audit Question A-NonLOCA.LTR-29

3.

NuScale Power, LLC, NuScale Power, LLC Quality Assurance Program Description, MN-122626-A, Revision 10.

4.

U.S. Code of Federal Regulations, General Design Criteria for Nuclear Power Plants, Appendix A, Part 50 Chapter I, Title 10, Energy, (10 CFR 50 Appendix A).

5.

U.S. Code of Federal Regulations, Contents of applications; technical information, Section 52.47, Part 52 Chapter I, Title 10, Energy, (10 CFR 52.47).

6.

NuScale Power, LLC, Subchannel Analysis Methodology, TR-0915-17564-P-A, Revision 2.

7.

Not Used

8.

NuScale Power, LLC, Accident Source Term Methodology, TR-0915-17565-P-A, Revision 4.

9.

U.S. Nuclear Regulatory Commission, Standard Review Plan, Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment, NUREG-0800, Chapter 15, Section 15.6.2, Rev. 2, July 1981.

10. NuScale Power, LLC, Evaluation Methodology for Stability Analysis of the NuScale Power Module, TR-0516-49417-P-A, Revision 1.

11. S.M. Modro et al., Multi-Application Small Light Water Reactor Final Report, Idaho National Engineering and Environmental Laboratory, INEEL/EXT-04-01626, December 2003.

12. Electric Power Research Institute, RETRAN-3D - A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems, Volumes 1-5, EPRI NP-7450-A, Revision 10, September 2014.

13. Moghanaki, S. K. and Rahgoshay, M., Pressurizer Modeling: Using Different Thermodynamic Models and Comparing Results with RELAP Code Results, Applied Mechanics and Materials (Volumes 423-426), pp. 1444-1448, 2013.

14. U.S. Nuclear Regulatory Commission, Combined License Applications for Nuclear Power Plants, Regulatory Guide 1.206, June 2007.

Non-Loss-of-Coolant Accident Analysis Methodology TR-0516-49416-NP Draft Revision 5

© Copyright 2024 by NuScale Power, LLC 729

15. U.S. Nuclear Regulatory Commission, Standard Review Plan, Transient and Accident Analyses, NUREG-0800, Chapter 15, Revision 3, March 2007 and various Chapter 15 subsections.

16. U.S. Code of Federal Regulations, Definitions, Section 50.2, Part 50 Chapter I, Title 10, Energy, (10 CFR 50.2).

17. American National Standards Institute / American Nuclear Society, Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems, ANSI/ANS-58.9-2002 R2015.

18. U.S. Nuclear Regulatory Commission, Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs, SECY-94-084, March 1994.

19. U.S. Code of Federal Regulations, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Appendix B, Part 50 Chapter I, Title 10, Energy, (10 CFR 50 Appendix B).

20. American Society of Mechanical Engineers, Quality Assurance Program Requirements for Nuclear Facility Applications, ASME NQA-1-2008, NQA-1a-2009 Addenda.

Audit Question A-NonLOCA.LTR-29

21. NuScale Power, LLC, Rod Ejection Accident Methodology, TR-0716-50350-P, Revision 32.

22. NuScale Power, LLC, Applicability of AREVA Fuel Methodology for the NuScale Design, TR-0116-20825-P-A, Revision 1.

23. NuScale Power, LLC, Nuclear Analysis Codes and Methods Qualification, TR-0616-48793-P-A, Revision 1.

24. Kim, S.J., Turbulent film condensation of high pressure steam in a vertical tube of passive secondary consensation system, PhD thesis, Korea Advanced Institute of Science and Technology, 2000.

25. SwUM-0304-17023, Revision 8, NRELAP5 Version 1.4 Theory Manual.

26. NuScale Power, LLC, Extended Passive Cooling and Reactivity Control Methodology, TR-124587-P, Revision 0.

27. U.S. Code of Federal Regulations, Contents of applications; technical information, Section 52.137, Part 52 Chapter I, Title 10, Energy, (10 CFR 52.137).

Audit Question A-NonLOCA.LTR-29

28. NuScale Power, LLC, Statistical Subchannel Analysis Methodology, TR-108601-P-A (Supplement 1 to TR-0915-17564-P-A, Revision 2), Revision 42.

Non-Loss-of-Coolant Accident Analysis Methodology TR-0516-49416-NP Draft Revision 5

© Copyright 2024 by NuScale Power, LLC 730

29. SwUM-0304-17023, Revision 10, NRELAP5 Version 1.6 Theory Manual.

Audit Question A-NonLOCA.LTR-29

30. NuScale Power, LLC, Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), TR-131981-P, Revision 10.