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| | number = ML18101B418 | | | number = ML18101B418 |
| | issue date = 04/11/2018 | | | issue date = 04/11/2018 |
| | title = 2018/04/11 Nuscale SMR DC RAI - Request for Additional Information No. 419 Erai No. 9502 (15) | | | title = SMR DC RAI - Request for Additional Information No. 419 Erai No. 9502 (15) |
| | author name = | | | author name = |
| | author affiliation = NRC | | | author affiliation = NRC |
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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 - Request for Additional Information No. 521 Erai No. 9672 (19) ML19079A3632019-03-20020 March 2019 SMR DC RAI - Request for Additional Information No. 520 Erai No. 9642 (16) ML19077A2852019-03-18018 March 2019 SMR DC RAI - Request for Additional Information No. 519 Erai No. 9656 (12.03) ML19063D4042019-03-0404 March 2019 SMR DC RAI - Request for Additional Information No. 518 Erai No. 9659 (19) ML19062A0012019-03-0303 March 2019 SMR DC RAI - Request for Additional Information No. 518 Erai No. 9659 (19) ML19057A4382019-02-26026 February 2019 SMR DC Docs - March 5, 2019, Public/Closed Meeting on NuScale EPZ Sizing Methodology Topical Report_Nrc Staff Talking Points (Public) ML19056A5062019-02-25025 February 2019 SMR DC RAI - FW: Request for Additional Information No. 365 RAI No. 9309 (3.8.4) Rev 1 (to Remove Prop from Previous Subject Line) ML19046A0672019-02-15015 February 2019 SMR DC RAI - Request for Additional Information No. 517 Erai No. 9657 (12.03) ML19032A1202019-02-0101 February 2019 SMR DC RAI - Request for Additional Information No. 516 Erai No. 9647 (15.0.6) ML19016A2692019-01-16016 January 2019 SMR DC RAI - Request for Additional Information No. 515 Erai No. 9607 (12.02) Revision 1 ML19015A2782019-01-15015 January 2019 SMR DC RAI - Request for Additional Information No. 366 RAI No. 9292 (12.3) ML19015A2742019-01-15015 January 2019 SMR DC RAI - Request for Additional Information No. 486 Erai No. 9296 (12.3) ML19014A0882019-01-14014 January 2019 SMR DC RAI - Request for Additional Information No. 515 Erai No. 9607 (12.02) ML19014A0842019-01-14014 January 2019 SMR DC RAI - FW: Request for Additional Information No. 371 RAI No. 9373 (15.06.06) ML19003A1772019-01-0303 January 2019 SMR DC Docs - Approved Version of NuScale Topical Report TR-0616-48793, Nuclear Analysis Codes and Methods Qualification, Revision 1 ML19003A4612019-01-0303 January 2019 SMR DC Docs - Approved Version of Topical Report TR-0116-21012, NuScale Power Critical Heat Flux Corrections, Revision 1 ML18352B0812018-12-18018 December 2018 SMR DC RAI - Request for Additional Information No. 513 Erai No. 9643 (4.04) ML18352B0852018-12-18018 December 2018 SMR DC RAI - Request for Additional Information No. 514 Erai No. 9645 (4.04) ML18341A3452018-12-0707 December 2018 SMR DC RAI - NuScale Request for Additional Information -eRAI No. 9631, Section 6.2.6 - Cancelled ML18333A0212018-11-29029 November 2018 SMR DC RAI - Request for Additional Information No. 512 Erai No. 9634 (16) ML18324A8142018-11-20020 November 2018 SMR DC RAI - Request for Additional Information No. 511 Erai No. 9613 (12.02) ML18312A2492018-11-0808 November 2018 SMR DC Docs - FW: NuScale FSAR Draft Changes in Section 2.4.4 ML18309A2642018-11-0505 November 2018 SMR DC RAI - Request for Additional Information No. 510 Erai No. 9631 (6.2.6) ML18296A2342018-10-23023 October 2018 SMR DC RAI - Request for Additional Information No. 509 Erai No. 9608 (14.3.8) 2021-05-26
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Text
NuScaleDCRaisPEm Resource From: Chowdhury, Prosanta Sent: Wednesday, April 11, 2018 5:10 PM To: Request for Additional Information Cc: Lee, Samuel; Cranston, Gregory; Franovich, Rani; Karas, Rebecca; Schmidt, Jeffrey; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Information No. 419 eRAI No. 9502 (15)
Attachments: Request for Additional Information No. 419 (eRAI No. 9502).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application.
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 301-415-1647 1
Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 450 Mail Envelope Properties (BN7PR09MB26099A53DD9BA1C23866FAEB9EBD0)
Subject:
Request for Additional Information No. 419 eRAI No. 9502 (15)
Sent Date: 4/11/2018 5:09:46 PM Received Date: 4/11/2018 5:09:51 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 "Franovich, Rani" <Rani.Franovich@nrc.gov>
Tracking Status: None "Karas, Rebecca" <Rebecca.Karas@nrc.gov>
Tracking Status: None "Schmidt, Jeffrey" <Jeffrey.Schmidt2@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 675 4/11/2018 5:09:51 PM Request for Additional Information No. 419 (eRAI No. 9502).pdf 26571 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 419 (eRAI No. 9502)
Issue Date: 04/11/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 15 - Introduction - Transient and Accident Analyses Application Section:
QUESTIONS 15-4 General Design Criterion (GDC) 10, "Reactor design," in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, 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).
To confirm whether margin to the SAFDLS is met for the Chapter 15 events, the staff needs to understand whether appropriate initiating events and single failures have been considered in the analyses.
Final Safety Analysis Report (FSAR) Section 15.0.0.6.6, Treatment of Non-safety-related systems, states that the application assumes the worst single failure of a control system unless the following conditions are met:
x a single failure in the nonsafety-related system does not impact DBEs.
x a detectable, non-coincident, random independent failure does not disable the system.
x the system is capable of functioning under the licensing assumptions for the event being analyzed.
The staff notes the non-loss of coolant accident (LOCA) topical report, TR-0516-49416, which is incorporated by reference into the FSAR, states, "...if operation of the control system leads to a less severe plant response, then the actions of the control system are not simulated for the transient of interest. Conversely, if operation of the control system causes the event consequences to be more severe, the [plant control system (PCS)] is assumed to operate as designed. Under no circumstances is the control system assumed to malfunction, since such an occurrence would be considered an initiating event."
The staff requests the applicant reconcile the apparent difference between FSAR Section 15.0.0.6.6 and the non-LOCA topical report and identify if any FSAR Section 15 events assume the worst possible failure of a control system. If FSAR Section 15.0.0.6.6 contains the appropriate language, the staff further requests how bullets two and three above are evaluated.