ML18086B789

2018/03/27 Nuscale SMR TR RAIs - Request for Additional Information Letter No. 9417 (Erai No. 9417) Topical Report, Thermal Hydraulic Stability, 15.09, Srsb

ML18086B789
Person / Time
Site:	PROJ0769
Issue date:	03/27/2018
From:	NRC
To:	NRC/NRO/DNRL/LB1
References
Download: ML18086B789 (3)

Text

1 NuScaleTRRaisPEm Resource From: Chowdhury, Prosanta Sent: Tuesday, March 27, 2018 10:29 PM To: Request for Additional Information Cc: Lee, Samuel; Cranston, Gregory; Karas, Re becca; Skarda, Raymond; Bavol, Bruce; NuScaleTRRaisPEm Resource

Subject:

Request for Additional Information Lett er No. 9417 (eRAI No. 9417) Topical Report, Thermal Hydraulic Stability, 15.09, SRSB Attachments:

Request for Additional Inform ation No. 9417 (eRAI No. 9417).pdf Attached please find NRC staff's request for additional in formation (RAI) concerning review of the NuScale Topical Report.

The NRC staff recognizes that NuScale has preliminarily identified that the response to one or more questions in this RAI is likely to require greater than 60 days. NuScale is expected to provide a schedule for the RAI

response by email within 14 days.

If you have any questions, please contact me.

Thank you.

Prosanta Chowdhury, Project Manager Licensing Branch 1 (NuScale) Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission

301-415-164 Hearing Identifier: NuScale_SMR_DC_TR_Public Email Number: 77 Mail Envelope Properties (BN7PR09MB2609CD30638AF3D08767DF919EA30)

Subject:

Request for Additional Information Letter No. 9417 (eRAI No. 9417) Topical Report, Thermal Hydraulic Stability, 15.09, SRSB Sent Date: 3/27/2018 10:28:36 PM Received Date: 3/27/2018 10:28:41 PM From: Chowdhury, Prosanta Created By: Prosanta.Chowdhury@nrc.gov Recipients: "Lee, Samuel" <Samuel.Lee@nrc.gov> Tracking Status: None "Cranston, Gregory" <Gregory.Cranston@nrc.gov> Tracking Status: None "Karas, Rebecca" <Rebecca.Karas@nrc.gov>

Tracking Status: None "Skarda, Raymond" <Raymond.Skarda@nrc.gov> Tracking Status: None "Bavol, Bruce" <Bruce.Bavol@nrc.gov> Tracking Status: None "NuScaleTRRaisPEm Resource" <NuScaleTRRaisPEm.Resource@nrc.gov>

Tracking Status: None "Request for Additional Information" <RAI@nuscalepower.com> Tracking Status: None

Post Office: BN7PR09MB2609.namprd09.prod.outlook.com

Files Size Date & Time MESSAGE 650 3/27/2018 10:28:41 PM Request for Additional Information No. 9417 (eRAI No. 9417).pdf 88058 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

Request for Additional Information No. 9417 (eRAI No. 9417)

Issue Date: 03/28/2018 Application Title: NuScale Topical Report Operating Company: NuScale Docket No. PROJ0769 Review Section: 15.09 - A.DSRS NuScale Thermal Hydraulic Stability Application Section:

QUESTIONS 15.09-4 Title 10 Code of Federal Regulations (10 CFR), Part 50, Appendix A, General Design Criterion (GDC), "Reactor design," requires that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences (AOOs). Title 10 CFR, Part 50, Appendix A, GDC 12, "Suppression of Reactor Power Oscillations," requires that the reactor core and associated coolant, control, and protection system shall be designed to assure that power oscillation which can result in conditions exceeding SAFDLs are not possible or can be reliably and readily detected and suppressed. Title 10 CFR Part 52.47, "Contents of applications; technical information,"

Standard Review Plan (SRP) Section 15.0.2, "Review of Transient and Accident Analysis Method," and Regulatory Guide (RG) 1.203, "Transient and Accident Methods," provide guidance for complying with GDCs 10 and 12. Standard Review Plan 15.0.2 and RG 1.203 state that documentation must include a complete description of the code assessment, including showing a model nodalization diagram and all code options used for the calculations. Assessments must also compare code predictions to analytical solutions, where possible, to show the accuracy of the numerical methods in the mathematical models. RG 1.203 states that numerical solution convergence studies, including the basis for the time steps used and the chosen convergence criteria should be provided. The staff reviewed the response to the original RAI, RAI 8801, and found that the response was insufficient for the staff to reach a conclusion regarding the adequacy of the stability analysis methodology. The following supplemental information is therefore requested:

Provide a summary of numerical results of the sensitivity studies described in the original response.

Quantify the impact on the decay ratio for the different nodalization and time step cases analyzed. It is acceptable to respond to this request by providing the results as a table that in one column describes the nodalization, in a second column provides the time step, in a third column provides the Courant number, and in a fourth column provides the decay ratio.

Compare the sensitivity of the results to nodalization/time-step to the uncertainty in the decay ratio.