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Category:E-Mail
MONTHYEARML21287A4512021-10-15015 October 2021 Email for NuScale Topical Report Quality Assurance Program Description Topical Report -A Version Verification ML21154A1322021-05-26026 May 2021 Final Safety Evaluation Transmittal Email ML21053A2662021-02-22022 February 2021 SMR DC Docs - FW: NuScale EPZ Review Path Forward ML20203M1872020-07-14014 July 2020 Control Room Staffing Topical Report - NRC Staff'S Documentation of the Results of the Completeness Review ML20190A2352020-07-0808 July 2020 SMR DC Docs - Approved Version of NuScale Topical Report, Rod Ejection Accident Methodology, TR-0716-50350, Revision 1 ML20141L6102020-05-20020 May 2020 SMR DC Docs - NuScale Topical Report - Approved Version of NuScale Applicability of Areva Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces, TR-07116-50351, Revision 1 ML20090A8642020-03-30030 March 2020 SMR DC Docs - NuScale Topical Report - Approved Version of TR-0516-49417, Evaluation Methodology for the Stability of the NuScale Power Module, Revision 1 ML19331A7302019-11-27027 November 2019 SMR DC Docs - FW: Ibr Flow Chart ML19331A7382019-11-27027 November 2019 SMR DC Docs - FW: Chapter 18 (Di IP) Related (non-prop) ML19331A7262019-11-26026 November 2019 SMR DC Docs - (External_Sender) Ibr Flow Chart ML19329E7132019-11-25025 November 2019 SMR DC Docs - FW: Chapter 18 (Di IP) Related ML19323F6982019-11-19019 November 2019 DCA Technical Specification Confirmatory Items - Email Commitments ML19329E7022019-11-0606 November 2019 SMR DC Docs - (External_Sender) Chapter 18 (Di IP) Related ML19309D7862019-10-31031 October 2019 Reconciliation - NRR Response to Acrs' September 20 2019 Letter on NuScale Stability Analysis Topical Report ML19309E0172019-10-31031 October 2019 Reconciliation - NRR Response to Acrs'S September 24 2019 Letter on NuScale External Forces Topical Report ML19309F8612019-10-31031 October 2019 Reconciliation - NRR Response to Acrs'S September 25, 2019 Letter on the Focus Area Review Approach ML19276D2812019-10-0303 October 2019 SMR DC RAI - Request for Additional Information No. 526 Erai No. 9719 ML19235A1092019-08-23023 August 2019 SMR DC RAI - Request for Additional Information No. 525 Erai No. 9705 (19.02) ML19206B0772019-07-25025 July 2019 SMR DC Docs - FW: FW: NuScale Chapter 5 Section 5.2.3 - Changes to Information on Check Valves ML19171A0092019-06-20020 June 2019 SMR DC RAI - Request for Additional Information No. 524 Erai No. 9691 (3.9.4) ML19157A0352019-06-0606 June 2019 SMR DC RAI - Request for Additional Information No. 523 Erai No. 9682 (12.3-12.4, 9.3.2) ML19150A3172019-05-30030 May 2019 SMR DC RAI - Request for Additional Information No. 522 Erai No. 9681 (14) ML19151A0272019-05-30030 May 2019 SMR DC RAI - Request for Additional Information No. 522 Erai No. 9681 (14) ML19099A1272019-04-0909 April 2019 SMR DC Docs - FW: NuScale Comments Chapter 5 SER W/Ois ML19098A2362019-04-0808 April 2019 SMR DC Docs - FW: NuScale Comments Chapter 5 SER W/Ois ML19089A0112019-03-29029 March 2019 SMR DC Docs - NuScale Topical Report - Approved Version of Subchannel Analysis Methodology, TR-0915-17564, Revision 2 ML19081A2722019-03-22022 March 2019 SMR DC RAI - 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NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Friday, August 31, 2018 2:09 PM To: Request for Additional Information Cc: Lee, Samuel; Lupold, Timothy; Wong, Yuken; Vera Amadiz, Marieliz; Chowdhury, Prosanta; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Information No. 502 eRAI No. 9546 (3.9.2)
Attachments: Request for Additional Information No. 502 (eRAI No. 9546).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application.
Please submit your technically correct and complete response within 60 days of the date of this RAI to the NRC Document Control Desk.
If you have any questions, please contact me.
Thank you.
1
Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 539 Mail Envelope Properties (BN1PR09MB0258DFEC9DD6A93F31D8456D900F0)
Subject:
Request for Additional Information No. 502 eRAI No. 9546 (3.9.2)
Sent Date: 8/31/2018 2:08:45 PM Received Date: 8/31/2018 2:08:52 PM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:
"Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>
Tracking Status: None "Wong, Yuken" <Yuken.Wong@nrc.gov>
Tracking Status: None "Vera Amadiz, Marieliz" <Marieliz.VeraAmadiz@nrc.gov>
Tracking Status: None "Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>
Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>
Tracking Status: None "Request for Additional Information" <RAI@nuscalepower.com>
Tracking Status: None Post Office: BN1PR09MB0258.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 369 8/31/2018 2:08:52 PM Request for Additional Information No. 502 (eRAI No. 9546).pdf 66430 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 502 (eRAI No. 9546)
Issue Date: 08/31/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 03.09.02 - Dynamic Testing and Analysis of Systems Structures and Components Application Section: 3.9.2 QUESTIONS 03.09.02-78 10 CFR 52.47 requires the design certification applicant to include a description and analysis of the structures, systems, and components (SSCs) sufficient to permit understanding of the system designs. 10 CFR 50, Appendix A, GDC 2 requires systems, structures, and components important to safety be designed to withstand appropriate combinations of the effects of normal and accident conditions with the effects of natural phenomena including earthquake. TR-1016-51669-P, "NuScale Power Module Short-Term Transient Analysis," Rev. 0, Section 3.2.3.2, "Flow Acceleration at Break Locations" states that the acoustic elements representing the fluid inside the pipe in the ANSYS blowdown and asymmetric cavity pressurization models and the flow acceleration is applied as a body force to the acoustic element nodes on the break face. The staff needs to ensure that the input loading is appropriately captured in the blowdown and asymmetric cavity pressurization models, and the description is insufficient for staff to reach a safety finding. Explain how the flow acceleration is converted to body force at the acoustic element nodes on the break face for liquid and steam so that the staff can understand the input loading is appropriately captured in the analysis model.
Include the requested information in the NPM Short-Term Transient Analysis Report or other appropriate documentation in the design certification application.
03.09.02-79 10 CFR 52.47 requires the design certification applicant to include a description and analysis of the structures, systems, and components (SSCs) sufficient to permit understanding of the system designs. 10 CFR 50, Appendix A, GDC 2 requires systems, structures, and components important to safety be designed to withstand appropriate combinations of the effects of normal and accident conditions with the effects of natural phenomena including earthquake. TR-1016-51669-P, "NuScale Power Module Short-Term Transient Analysis," Rev. 0, Table 6-3, "Case Numbers with Valve Opening or Break Locations" contains seven cases of the axisymmetric pressurization and blowdown analysis. However, no discussion of analysis results is provided in the technical report. SRP 3.9.2 states that staff review of dynamic system analysis covers the methods of analysis, the considerations in defining the mathematical models, the descriptions of the forcing functions, the calculation scheme, the acceptance criteria, and the interpretation of analysis results. The technical report lacks interpretation of analysis results and only provides the bounding values of forces and moments in Table 6-5, "Maximum Forces and Moments at Component Interfaces" and Table 6-6, "Maximum Forces and Moments on Containment Vessel, Reactor Pressure Vessel, Riser, and Core Barrel Assembly" for all the seven pipe break and valve opening cases. The description is insufficient for staff to reach a safety finding. The applicant is requested to identify which are the dominant valve opening cases that attribute to the bounding values of forces and moments in Tables 6-5 and 6-6. Explain why they are the dominant cases. The RCS injection line terminates in the riser, break of RCS injection line will result in a pressure wave traveling internally to the risers. Provide the maximum blowdown loads in the risers due to break of the RCS injection line.
Include the requested information in the NPM Short-Term Transient Analysis Report or other appropriate documentation in the design certification application.