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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 - 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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NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Wednesday, June 20, 2018 2:36 PM To: Request for Additional Information Cc: Lee, Samuel; Mitchell, Matthew; Yeshnik, Andrew; Bavol, Bruce; Chowdhury, Prosanta; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Information No. 492 eRAI No. 9551 (5.2.3)
Attachments: Request for Additional Information No. 492 (eRAI No. 9551).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application. Password will be sent separately.
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: 522 Mail Envelope Properties (BN3PR09MB035516B10D61995CCE16ECC890770)
Subject:
Request for Additional Information No. 492 eRAI No. 9551 (5.2.3)
Sent Date: 6/20/2018 2:36:21 PM Received Date: 6/20/2018 2:36:25 PM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:
"Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Mitchell, Matthew" <Matthew.Mitchell@nrc.gov>
Tracking Status: None "Yeshnik, Andrew" <Andrew.Yeshnik@nrc.gov>
Tracking Status: None "Bavol, Bruce" <Bruce.Bavol@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: BN3PR09MB0355.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 402 6/20/2018 2:36:25 PM Request for Additional Information No. 492 (eRAI No. 9551).pdf 60541 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 492 (eRAI No. 9551)
Issue Date: 06/20/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 05.02.03 - Reactor Coolant Pressure Boundary Materials Application Section: 5.2.3 QUESTIONS 05.02.03-18 Regulatory basis: 10 CFR Part 50, Appendix A, GDC 1 and GDC 30 require that components in the reactor coolant pressure boundary shall be designed, fabricated, erected, and tested to the highest quality standards practicable. 10 CFR Part 50, Appendix A, GDC 4 requires SSCs to be designed and fabricated to accommodate the effects of environmental conditions during normal, off normal, and accident conditions.
On December 18, 2017 the applicant provided a response to RAI 9193 Question 05.02.03-11. The applicant states that the description of "weld filler classifications compatible with low alloy base metal" is sufficient in detail to meet NRC regulations. The applicant cites the AP1000 and the US-EPR designs as the basis for this conclusion. The staff has reviewed the applicant's response and disagrees.
The staff has requested information on the weld filler materials for the RPV from multiple DCD applicants. This includes the System 80+ (10 CFR Part 52, Appendix C) and the ESBWR (10 CFR Part 52, Appendix E). The staff has also requested this information as part of the DCD review for the US-APWR and the APR1400.
The applicant's requirement of "compatible with the base metal" does not provide sufficient detail to determine of the filler material is suitable for service in the reactor coolant system. The term "compatibility" is not term a commonly used in welding or weldment design.
Define "compatible with low allow base metal," describe how "compatibility with the base metal" ensures that the RPV welds can be made under fabrication conditions (including any process requirements), and how "compatibility with the base metal" provides a sufficient technical assurance that the probability of RPV failure is consistent with the GDC 4 requirements.
Alternatively, if the applicant utilizes the term "compatible with the base metal" because the weld filler material will be chosen at a later time (during procurement when a component fabricator determines the optimal chemical composition for the weldment) the applicant may revise the DCD Tier 2, FSAR information to identify the weld filler material as a COL Action Item.
05.02.03-19 Regulatory basis: 10 CFR Part 50, Appendix A, GDC 1 and GDC 30 require that components in the reactor coolant pressure boundary shall be designed, fabricated, erected, and tested to the highest quality standards practicable. GDC 30 also requires the means for detecting and identifying, to the extent practical, the location of the source of RCS leakage.
On December 18, 2017, the applicant provided a response to RAI 9193 Question 05.02.03-14. The staff has reviewed the applicant's response and agrees that the applicant's approach is acceptable. However, the staff notes that the containment environment monitoring element described by the applicant in the RAI response is not reflected in the Tier 2 DCD information.
One acceptable approach to revising the information in the DCD would be:
COL Item 5.2-5 A COL applicant that references the NuScale Power Plant design certification will develop and implement a Boric Acid Control Program that includes: inspection elements to ensure the integrity of the reactor coolant pressure boundary components for subsequent service, monitoring of the containment atmosphere for evidence of RCS leakage, the type of visual or other nondestructive inspections to be performed, and the required inspection frequency.