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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 - 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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: Monday, July 23, 2018 9:27 AM To: NuScaleDCRaisPEm Resource Cc: Chowdhury, Prosanta
Subject:
Request for Additional Information No. 429 eRAI No. 9396 (18.1)
Attachments: Request for Additional Information No. 429 (eRAI No. 9396).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 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.
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: 530 Mail Envelope Properties (BN1PR09MB0258038CC864FE8C3B8C8E7C90560)
Subject:
Request for Additional Information No. 429 eRAI No. 9396 (18.1)
Sent Date: 7/23/2018 9:26:39 AM Received Date: 7/23/2018 9:26:43 AM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:
"Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>
Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>
Tracking Status: None Post Office: BN1PR09MB0258.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 566 7/23/2018 9:26:43 AM Request for Additional Information No. 429 (eRAI No. 9396).pdf 87356 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 429 (eRAI No. 9396)
Issue Date: 04/23/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 18 - Human Factors Engineering Application Section: 18 QUESTIONS 18-44 Title 10 of the Code of Federal Regulations (10CFR) Section 52.47(a)(8) requires an applicant for a design certification to provide a final safety analysis report (FSAR) that must include the information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10 CFR 50.34(f), except paragraphs (f)(1)(xii), (f)(2)(ix), and (f)(3)(v). Section 10 CFR 50.34(f)(2)(iii) requires an applicant to "Provide, for Commission review, a control room design that reflects state-of-the-art human factor principles prior to committing to fabrication or revision of fabricated control room panels and layouts. Chapter 18, Human Factors Engineering, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, and NUREG-0711, "Human Factors Engineering Program Review Model, identify criteria the staff uses to evaluate whether an applicant meets the regulation. The applicant stated in the FSAR, Tier 2, Section 18.0, "Human Factors Engineering - Overview," that its human factors engineering (HFE) program incorporates accepted HFE standards and guidelines including the applicable guidance provided in NUREG-0711, Revision 3.
NUREG-0711, Section 11.4.3.3, Validation Testbeds, Criterion 9 states, The applicant should verify the conformance of the testbed to the testbed-required characteristics before validation tests are conducted. NuScale provided the veification and validation (V&V) implementation plan (IP) for review. The staffed reviewed the V&V IP. In Section 4.3.9 the applicant states, The testbed is verified to conform with the required characteristics before validation tests are conducted. However, no further information is provided. As part of an audit of documents in NuScales electronic reading room, the staff had the opportunity to review an Integrated Systems Validation Test Plan. In sections 9.2 and 9.3 of this document, the applicant provides more information regarding the methods used to verify the conformance of the testbed to the testbed-required characteristics. Please either update theV&V IP to include this information or reference sections 9.2 and 9.3 of the Integrated Systems Validation Test Plan." If referencing ISV test plan, pleaswe indicate revision number.