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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - 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Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20104A0792020-04-27027 April 2020 OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 ML20098G2372020-04-0707 April 2020 Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items ML20097F1922020-04-0606 April 2020 Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0 ML20094H6742020-04-0303 April 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20072M6682020-03-30030 March 2020 Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content ML20072H3332020-03-0909 March 2020 LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0 ML20057D9002020-03-0606 March 2020 Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant ML20062F7262020-03-0505 March 2020 Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public ML20069A1572020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A1772020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20069A9632020-03-0404 March 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0 ML20066G2802020-03-0303 March 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0 ML20066G2882020-02-28028 February 2020 LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0 2023-06-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - 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Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
[Table view] |
Text
RAIO-1218-63935 December 20, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No.
164 (eRAI No. 8935) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
164 (eRAI No. 8935)," dated August 11, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 8935:
03.07.02-25 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.
Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Marieliz Vera, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 8935 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-1218-63935 :
NuScale Response to NRC Request for Additional Information eRAI No. 8935 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8935 Date of RAI Issue: 08/11/2017 NRC Question No.: 03.07.02-25 10 CFR 50 Appendix S requires that the safety functions of structures, systems, and components (SSCs) must be assured during and after the vibratory ground motion associated with the Safe Shutdown Earthquake (SSE) through design, testing, or qualification methods.
Tables 3.7.2-23, 24 and 25 in the FSAR respectively provide SSI analysis results for one particular example shell, beam, and solid element, respectively. However, analysis results at other key locations are not provided. The applicant is requested to provide the design-basis seismic demands (e.g., forces, moments, soil pressures, accelerations, displacements, ISRS),
at all applicable critical section locations of the RXB and CRB, that are used in structural design evaluations in FSAR Sections 3.8.4 and 3.8.5.
NuScale Response:
The following is a list of tables and figures of accelerations and in-structure response spectra (ISRS) at critical section locations used in the structural design evaluations of the reactor building (RXB) and control building (CRB) in FSAR Sections 3.8.4 and 3.8.5:
Section 3.7 Tables o FSAR Table 3.7.3-13 provides bioshield accelerations.
Section 3.7 Figures o FSAR Figures 3.7.1-1 and 3.7.1-2 provide horizontal and vertical certified seismic design response spectra (CSDRS).
NuScale Nonproprietary
o FSAR Figures 3.7.1-3 and 3.7.1-4 provide horizontal and vertical high frequency certified seismic design response spectra (CSDRS-HF).
o FSAR Figures 3.7.1-5a through 3.7.1-10f provide original and CSDRS/CSDRS-HF-compatible time histories.
o FSAR Figures 3.7.2-36 & 37, and Figures 3.7.2-40 through 45 provide maximum wall accelerations from ANSYS for the fluid-structure interaction (FSI) analysis.
o FSAR Figures 3.7.2-107 through 3.7.2-122b provide ISRS for the RXB and CRB floors, NuScale Power Module (NPM) restraints, and reactor building crane (RBC) wheels.
o FSAR Figures 3.7.2-156 through 3.7.2-163 provide ISRS for the containment vessel (CNV) skirt and lug support locations at NPMs 1 and 6.
o FSAR Figure 3.7.3-4a, Figure 3.7.3-4b, and Figure 3.7.3-4c provide ISRS for the bioshields.
Section 3.8 figures o FSAR Figures 3.8.5-17 through 3.8.5-25 provide input acceleration time histories for Soil Types 7, 8, and 11, used for the RXB nonlinear sliding analysis.
o FSAR Figures 3.8.5-28 through 3.8.5-33 provide Capitola input acceleration time histories for Soil Type 11, used for the CRB basemat nonlinear analysis.
The following is a list of tables and figures of soil pressures used in the structural design evaluations of the RXB and CRB in FSAR Sections 3.8.4 and 3.8.5:
Section 3.7 Tables o FSAR Table 3.7.2-48: North RXB Wall Soil Pressure Comparison Section 3.8 Tables o FSAR Table 3.8.4-15: Seismic and Static Soil Pressures on CRB Walls for Standalone Model o FSAR Table 3.8.4-16: Seismic and Static Soil Pressures on CRB Walls for Triple Building Model o FSAR Table 3.8.4-17: Enveloping Seismic Soil Pressures on CRB Walls o FSAR Table 3.8.4-18: Seismic and Static Soil Pressures on RXB Walls for Standalone Model NuScale Nonproprietary
o FSAR Table 3.8.4-19: Seismic and Static Soil Pressures on RXB Walls for Triple Building Model o FSAR Table 3.8.4-20: Enveloping Seismic Soil Pressures on RXB Walls o FSAR Table 3.8.5-9: CRB Total Static Lateral Soil Pressure o FSAR Table 3.8.5-13: Average Soil Bearing Pressures (Toe Pressures) along Edges of RXB Basemat o FSAR Table 3.8.5-15: Average Soil Bearing Pressures (Toe Pressures) along Edges of CRB Basemat Section 3.8 Figures o FSAR Figure 3.8.4-27: Total Static Lateral Soil Pressure Distribution Reactor Building o FSAR Figure 3.8.4-28: Seismic Soil Pressures on CRB Walls of Standalone Model o FSAR Figure 3.8.4-29: Seismic Soil Pressures on CRB Walls of Triple Building Model o FSAR Figure 3.8.4-30: Enveloping Seismic Soil Pressures on CRB Walls of Standalone and Triple Building Models o FSAR Figure 3.8.4-31: Seismic Soil Pressure on RXB Walls from Standalone Model o FSAR Figure 3.8.4-32: Seismic Soil Pressure on RXB Walls from Triple Building Model o FSAR Figure 3.8.4-33: Enveloping Soil Pressure on RXB Walls by Standalone and Triple Building Models o FSAR Figure 3.8.5-37: Static Soil Pressure on CRB Outer Walls o FSAR Figure 3.8.5-38: CRB Static Soil Pressure from Poisson's Ratio Effect -
Soil Type 11 o FSAR Figure 3.8.5-39: CRB Static Soil Pressure from Poisson's Ratio Effect -
Soil Type 7 The following is a list of tables and figures of displacements used in the structural design evaluations of the RXB and CRB in FSAR Sections 3.8.4 and 3.8.5:
Section 3.7 Tables o FSAR Table 3.7.2-26: Selected Reactor Building Locations for Relative Displacement NuScale Nonproprietary
o FSAR Table 3.7.2-27: Selected Control Building Locations for Relative Displacement Calculation o FSAR Table 3.7.2-28: Relative Displacement at Selected Locations on Reactor Building o FSAR Table 3.7.2-29: Relative Displacement at Selected Locations on Control Building o FSAR Table 3.7.2-44: Relative Displacement at Critical Locations of Standalone CRB Model o FSAR Table 3.7.2-47: Comparison of RXB Relative Displacements between 7P and DM Section 3.8 Tables o FSAR Table 3.8.5-7a: Displacement at Bottoms of Foundations of Uncracked Triple Building Model o FSAR Table 3.8.5-7b: Displacement at Bottoms of Foundations of Cracked Triple Building Model o FSAR Table 3.8.5-11: Reactor Building Sliding Displacements for Soil Type 7, 8 and 11 (Dead Weight + Buoyancy) o FSAR Table 3.8.5-12: Control Building Sliding and Uplift Displacements for Soil Type 7 and 11 o FSAR Table 3.8.5-17: CRB Tunnel Foundation Corner Displacements Section 3.7 Figures o FSAR Figure 3.7.2-94: Reactor Building Locations Selected for Relative Displacement o FSAR Figure 3.7.2-95: Control Building Locations Selected for Relative Displacement Section 3.8 Figures o FSAR Figure 3.8.5-50: Relative Displacement (Uplift) at Location A (S11 -
Vertical Excitation) o FSAR Figure 3.8.5-51: Lateral Relative Displacements (Sliding) at Location A (S11 - Vertical Excitation) o FSAR Figure 3.8.5-53: Lateral Relative Displacements (Sliding) at Location A (S7
- E-W Excitation)
NuScale Nonproprietary
o FSAR Figure 3.8.5-54: Lateral Relative Displacements (Sliding) at Location B (S7
- E-W Excitation) o FSAR Figure 3.8.5-55: Lateral Relative Displacements (Sliding) at Location C (S7 - E-W Excitation) o FSAR Figure 3.8.5-56: Lateral Relative Displacements (Sliding) at Location D (S7 - E-W Excitation) o FSAR Figure 3.8.5-57: Lateral Relative Displacements (Sliding) at Location A (S7
- N-S Excitation) o FSAR Figure 3.8.5-58: Lateral Relative Displacements (Sliding) at Location B (S7
- N-S Excitation) o FSAR Figure 3.8.5-59: Lateral Relative Displacements (Sliding) at Location C (S7 - N-S Excitation) o FSAR Figure 3.8.5-60: Lateral Relative Displacements (Sliding) at Location D (S7 - N-S Excitation) o FSAR Figure 3.8.5-61: Lateral Relative Displacements (Sliding) at Location A (S11 - E-W Excitation) o FSAR Figure 3.8.5-62: Lateral Relative Displacements (Sliding) at Location B (S11 - E-W Excitation) o FSAR Figure 3.8.5-63: Lateral Relative Displacements (Sliding) at Location C (S11 - E-W Excitation) o FSAR Figure 3.8.5-64: Lateral Relative Displacements (Sliding) at Location D (S11 - E-W Excitation) o FSAR Figure 3.8.5-65: Lateral Relative Displacements (Sliding) at Location A (S11 - N-S Excitation) o FSAR Figure 3.8.5-66: Lateral Relative Displacements (Sliding) at Location B (S11 - N-S Excitation) o FSAR Figure 3.8.5-67: Lateral Relative Displacements (Sliding) at Location C (S11 - N-S Excitation) o FSAR Figure 3.8.5-68: Lateral Relative Displacements (Sliding) at Location D (S11 - N-S Excitation) o FSAR Figure 3.8.5-69: Lateral Relative Displacements (Sliding) at Location A (S8
- E-W Excitation) o FSAR Figure 3.8.5-70: Lateral Relative Displacements (Sliding) at Location B (S8
- E-W Excitation) o FSAR Figure 3.8.5-71: Lateral Relative Displacements (Sliding) at Location C (S8 - E-W Excitation)
NuScale Nonproprietary
o FSAR Figure 3.8.5-72: Lateral Relative Displacements (Sliding) at Location D (S8 - E-W Excitation) o FSAR Figure 3.8.5-73: Lateral Relative Displacements (Sliding) at Location A (S8
- N-S Excitation) o FSAR Figure 3.8.5-74: Lateral Relative Displacements (Sliding) at Location B (S8
- N-S Excitation) o FSAR Figure 3.8.5-75: Lateral Relative Displacements (Sliding) at Location C (S8 - N-S Excitation) o FSAR Figure 3.8.5-76: Lateral Relative Displacements (Sliding) at Location D (S8 - N-S Excitation)
The bounding static, dynamic (seismic), and final design forces and moments at critical sections are provided in response to RAI 8971, Question 03.08.04-11.
Impact on DCA:
There are no impacts to the DCA as a result of this response.
NuScale Nonproprietary