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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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NuScaleDCRaisPEm Resource From: Cranston, Greg Sent: Thursday, October 3, 2019 7:59 AM To: Request for Additional Information Cc: Lee, Samuel; Chowdhury, Prosanta; Karas, Rebecca; Nolan, Ryan; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Information No. 526 eRAI No. 9719 Attachments: Request for Additional Information No. 526 (eRAI No. 9719).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 by October 23, 2019, to the 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: 577 Mail Envelope Properties (SN6PR09MB2896E17C747F4E44357FB46C909F0)
Subject:
Request for Additional Information No. 526 eRAI No. 9719 Sent Date: 10/3/2019 7:58:58 AM Received Date: 10/3/2019 7:59:01 AM From: Cranston, Greg Created By: Gregory.Cranston@nrc.gov Recipients:
"Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>
Tracking Status: None "Karas, Rebecca" <Rebecca.Karas@nrc.gov>
Tracking Status: None "Nolan, Ryan" <Ryan.Nolan@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: SN6PR09MB2896.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 363 10/3/2019 7:59:01 AM Request for Additional Information No. 526 (eRAI No. 9719).pdf 57918 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 526 (eRAI No. 9719)
Issue Date: 10/03/2019 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 06.03 - Emergency Core Cooling System Application Section: 6.3, and 14.2 QUESTIONS 06.03-8 Title 10 of the Code of Federal Regulations (10 CFR) Section 52.47, "Contents of applications; technical information," requires that an application for a design certification must include performance requirements and design information sufficiently detailed to permit its acceptance by the U.S. Nuclear Regulatory Commission (NRC). Specifically, §52.47(a)(2)(iii), states, in part, that the NRC will take into consideration the following reactor design characteristics that include, "the extent to which the reactor incorporates unique, unusual or enhanced safety features having a significant bearing on the probability or consequences of accidental release of radioactive materials."
10 CFR 50, Appendix A, GDC 37 requires, in part, the emergency core cooling system to be designed to permit appropriate functional testing to assure "the operability of the system as a whole and, under conditions as close to design as practical, the performance of the full operational sequence that brings the system into operation, including operation of applicable portions of the protection system."
The staff is seeking an as-built performance test of the ECCS to demonstrate the system meets fundamental design requirements of the safety analysis. The integrated functionality of a full scale NuScale ECCS system has not been tested and demonstrated. Although the staff has confidence that NuScale analytical codes have been adequately validated within the existing state of practice, performance of the full scale, as-built ECCS system can be impacted by the geometry and functional arrangement of key components, variations in as-built parameters, and uncertainties associated with complex thermal hydraulic phenomena, especially when considering the integrated system. Functional testing of the full scale ECCS would provide assurance that the as-built system response conforms to analytical predictions.
To date the staff held approximately eleven public meetings where the adequacy of the proposed ECCS performance test (Test #47) was at least one of the topics discussed. The most recent meeting was held on September 11, 2019. Currently, NuScale DCA Part 2, Tier 2, Table 14.2-47, Revision 3 identifies the acceptance criteria for ECCS Test #47 as:
- i. RPV riser level remains above the top of the core ii. CNV pressure remains below design pressure identified in Table 6.2-1 iii. CNV temperature remains below design temperature identified in Table 6.2-1 The proposed acceptance criteria above are not sufficient to demonstrate the as-built performance capability of the ECCS to satisfy design requirements because the stored energy during test conditions is significantly less than the full power stored energy corresponding to the proposed test acceptance criteria (accident acceptance criteria). Therefore, the applicant is requested to modify an existing ECCS test or develop a new test to demonstrate acceptable performance of the as-built ECCS, based on predicted system response under expected test conditions, to ensure the system as a whole meets fundamental design requirements of the safety analysis.
Given the fundamental purpose of this type of test - to confirm the performance of a first-of-a-kind safety system and verify the conservatism in the safety analyses in calculating the performance of a novel design feature - and expected standardization of the NuScale power module design and construction, the requested test is an appropriate candidate for a first-of-a-kind test to be performed for at least the first module only.