|
---|
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
[Table view] |
Text
NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Friday, December 15, 2017 9:11 AM To: RAI@nuscalepower.com Cc: NuScaleDCRaisPEm Resource; Lee, Samuel; Chowdhury, Prosanta; Graizer, Vladimir; Dudek, Michael; Vera Amadiz, Marieliz
Subject:
Request for Additional Information No. 298 RAI No. 9228 ()3.7.4 Attachments: Request for Additional Information No. 298 (eRAI No. 9228).pdf Attached please find NRC staffs request for additional information 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. The NRC Staff recognizes that NuScale has preliminarily identified that the response to this question in this RAI is likely to require greater than 60 days.
If you have any questions, please contact me.
Thank you.
Gregory Cranston, Senior Project Manager Licensing Branch 1 (NuScale)
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-0546 1
Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 325 Mail Envelope Properties (MWHPR09MB1200E25780469F7F86C74017900B0)
Subject:
Request for Additional Information No. 298 RAI No. 9228 ()3.7.4 Sent Date: 12/15/2017 9:10:32 AM Received Date: 12/15/2017 9:10:37 AM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:
"NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>
Tracking Status: None "Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>
Tracking Status: None "Graizer, Vladimir" <Vladimir.Graizer@nrc.gov>
Tracking Status: None "Dudek, Michael" <Michael.Dudek@nrc.gov>
Tracking Status: None "Vera Amadiz, Marieliz" <Marieliz.VeraAmadiz@nrc.gov>
Tracking Status: None "RAI@nuscalepower.com" <RAI@nuscalepower.com>
Tracking Status: None Post Office: MWHPR09MB1200.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 713 12/15/2017 9:10:37 AM Request for Additional Information No. 298 (eRAI No. 9228).pdf 42753 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 298 (eRAI No. 9228)
Issue Date: 12/15/2017 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 03.07.04 - Seismic Instrumentation Application Section: 03.07.04 QUESTIONS 03.07.04-2 Appendix S to 10 CFR Part 50 requires that suitable instrumentation be provided for the evaluation of the seismic response of nuclear plant features important to safety after an earthquake. On the public meeting conducted October 10, 2017, to discuss NuScales response to DCA RAI 8927, Question 03.07.04-1, NRC staff mention the importance regarding the use of the updated Regulatory Guide (RG) 1.12, Revision 3, Nuclear Power Plant Instrumentation for Earthquakes and/or the American National Standard (ANS)-2.2-2016, Earthquake Instrumentation for Nuclear Power Plants. Both of these documents specify the current acceptable means for the placement of seismic instrumentation at a site and in structures (in lieu of RG 1.12, Revision 2, which was published in 1997).
The updated RG 1.12 was first released by the NRC for public comment as a draft DG-1332 in September 2016 (ML16104A220), and the final version became publically available on November 8, 2017 (ML17094A831). The revision to the RG 1.12 incorporates ANS-2.2-2016 and addresses the current state-of-practice for seismic instrumentation that allows for a more reliable evaluation for seismic response of the reactor building (RXB) after an earthquake. Specifically, this would include the following:
A. downhole seismic instrument. NuScales proposed basemat is located at the depth of 86 ft. below the plant grade. According to RG 1.12, Rev. 3, if the depth of the site specific Ground Motion Response Spectra (GMRS) or Foundation Input Response Spectra (FIRS) exceeds 40 ft. below the plant grade, two free-field seismic instruments are recommended:
(a) one located at the ground surface and (b) the second one in the borehole to record ground motion at the elevation corresponding to the GMRS or FIRS.
B. Additional seismic instrumentation on the basemat. Considering the length (approximately 350 ft.) and the irregularity of the weight distribution in the RXB, RG 1.12, Rev. 3, recommends more than one seismic instrument on the basemat for such structures. The instruments should be appropriately placed to record the rocking or torsional responses predicted by the engineering analyses.
In order for the NRC staff to determine if the site, RXB, and CRB are adequately instrumented with seismic monitors in accordance with Appendix S to 10 CFR Part 50, please update Section 3.7.4 consistent with the RG 1.12, Rev. 3, and/or ANS-2.2-206 recommendations stated above; or provide an equivalent methodology and justification that would meet their intent for the placement of instrumentation that would allow for a reliable evaluation of the RXBs seismic response after an earthquake.