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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 - 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1 NuScaleDCRaisPEm Resource From: Chowdhury, Prosanta Sent: Wednesday, March 21, 2018 4:37 PM To: Request for Additional Information Cc: Lee, Samuel; Cranston, Gregory; Markley, Anthony; Dias, Antonio; Hernandez, Raul; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Informat ion No. 396 eRAI No. 9328 (09.01.02)
Attachments:
Request for Additional Inform ation No. 396 (eRAI No. 9328).pdf Attached please find NRC staff's request for additional in formation (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.
Prosanta Chowdhury, Project Manager Licensing Branch 1 (NuScale)
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission
301-415-1647 Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 426 Mail Envelope Properties (BN7PR09MB26096BDE9E0BBF74148776949EAA0)
Subject:
Request for Additional Information No. 396 eRAI No. 9328 (09.01.02) Sent Date: 3/21/2018 4:37:15 PM Received Date: 3/21/2018 4:37:20 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 "Markley, Anthony" <Anthony.Markley@nrc.gov> Tracking Status: None "Dias, Antonio" <Antonio.Dias@nrc.gov> Tracking Status: None "Hernandez, Raul" <Raul.Hernandez@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: BN7PR09MB2609.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 551 3/21/2018 4:37:20 PM Request for Additional Information No. 396 (eRAI No. 9328).pdf 75261
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
Request for Additional Information No. 396 (eRAI 9328)
Issue Date: 03/21/2018 Application Title: NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 09.01.02 - New and Spent Fuel Storage Application Section: Section 9.1.2 and 9.2.5 QUESTIONS 09.01.02-36 Appendix A to 10 CFR Part 50 -General Design Criteria for Nuclear Power Plants Criterion 61
- "Fuel storage and handling and radioactivity control," states that the fuel storage and handling, radioactive waste, and other systems which may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. These systems shall be designed with a capability to permit appropriate periodic inspection and testing of components important to safety.
NUREG-800, SRP 9.1.2, "New and Spent Fuel Storage,"Section III.2.K instructs the staff to verify that the detection and collection of spent fuel pool liner leaks are incorporated into the design with capability to collect pool liner leaks (e.g. drains and sumps) to prevent uncontrolled releases of radioactive material to the environment and to keep radiation exposure as low as reasonably achievable for personnel.
In RAI 03.08.05-23, the staff requested the applicant to describe the leak chase system in detail. In its response to the RAI dated October 17,2017, the applicant stated that pool leakage detection system (PLDS) consists of floor leakage channels, perimeter leakage channels, channel drainage lines, leak collection headers, leakage rate measuring lines, and valves. The floor leakage channels are embedded in the concrete beneath the field welded seams of the pool floor liner plates in the UHS pools and the dry dock. A perimeter channel is embedded in concrete at the wall and floor liner joint area.
The guidance provided in SRP 9.1.2 states that the SFP should be provided with a leakage detection system. A typical leakage detection system monitors all wetted surfaces (walls and floor welds). The applicant's PLDS does not monitor leakage through the wall welds; therefore, the staff finds that the applicant's design of the PLDS does not follow the recommendations of SRP 9.1.2.
Operational experience has shown that slow, undetected leakage of borated water has the capability of degrading reinforced concrete. Without a leakage detection system on the walls of the UHS/SFP, it is not clear to the staff how the applicant is capable of detecting slow leakages capable of compromising the structural integrity of the concrete walls (which are safety-related and risk-significant) of the UHS/SFP.
The staff requests the applicant to modify the design of the PLDS, to include monitoring of the pool wall leakage, or to provide a justification as to how the current design of the PLDS is capable of detecting pool leakage, preventing degradation of the safety-related concrete structure of the pools and the spread of contamination.