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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 - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20171A7312020-06-19019 June 2020 LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use ML20157A2232020-06-0303 June 2020 Letter to NuScale Requesting -A for TR-0716-50350 ML20150C5172020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0 ML20150E1772020-05-29029 May 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0 ML20150C8812020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0 ML20149M1192020-05-28028 May 2020 LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141N0122020-05-20020 May 2020 LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report ML20141M7642020-05-20020 May 2020 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3 ML20141L7872020-05-20020 May 2020 LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20128J3162020-05-18018 May 2020 OEDO-20-00167 - 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:Slides and Viewgraphs
MONTHYEARML20184A2872020-07-0101 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 ML20150C8812020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0 ML20150C5172020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, 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 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 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 ML20072H3272020-03-0909 March 2020 LLC - Public Meeting Presentation: Topic - Emergency Core Cooling System Boron (ECCS) Distribution, PM-0320-69218, Revision 0 ML20069A1632020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A9692020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision O ML20069A1542020-03-0404 March 2020 ACRS Full Committee Presentation: NuScale Topical Report- Non-Loss-of-Coolant Accident, PM-0320-69141, 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 ML20066F4672020-02-28028 February 2020 Enclosure 1: ACRS Subcommittee Presentation: NuScale FSAR Topic- Resolution of Chapter 15 Phase 2 Open Items, PM-0220-69062, Revision 0 ML20066G2772020-02-28028 February 2020 ACRS Full Committee Presentation: NuScale - Steam Generator Design, PM-0220-69051, Revision 0 ML20054A9622020-02-19019 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report - Non-Loss-of-Coolant Accident, PM-0220-68852, Revision 0 ML20054A4062020-02-17017 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report- Loss-of-Coolant Accident Evaluation Model, PM-0220-68917, Revision 0 ML20054B6342020-02-17017 February 2020 Nuscale - ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology, PM-1019-67365, Revision 0 ML20035C7892020-02-0404 February 2020 Nuscale - ACRS Subcommittee Presentation, FSAR, Steam Generator Design ML19340B5912019-12-0606 December 2019 Public Meeting - NuScale Incorporated by Reference (Ibr) Slides ML19324C8362019-11-13013 November 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Source Term Methodology Application, PM-1119-67928, Revision 0 ML19192A1662019-07-10010 July 2019 Presentation Entitled, Evaluation Methodology for Stability Analysis of the NuScale Power Module. ML19169A1662019-06-14014 June 2019 Mitigation of Beyond-Design-Basis-Events, NuScale FSAR Chapter 20, PM-0619-65964, Revision 0 ML19135A0642019-05-0909 May 2019 LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations, PM-0519-65533, Revision 0 ML19105A1352019-04-11011 April 2019 ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, Revision 0 ML19105A1312019-04-10010 April 2019 Enclosuacrs Presentation: Chapter 4, Reactor Overview, PM-0419-65096, Revision 0 ML19098A7802019-04-0202 April 2019 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Chapter 9, Auxiliary Systems, PM-0319-64807, Revision 0 ML19073A0482019-03-11011 March 2019 LLC - ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 1 ML19073A0512019-03-11011 March 2019 ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 1 ML19073A0532019-03-11011 March 2019 Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 1 ML19050A1632019-02-20020 February 2019 Enclosure 1: ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 0 ML19053A5182019-02-19019 February 2019 Nuscale - Dhrs and ECCS Logic Changes, PM-0219-64563, Revision 0 ML19050A3982019-02-13013 February 2019 Enclosure 1: ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 0 ML19045A3062019-02-12012 February 2019 PM-0219-64475-NP, Revision 0, Reactor Vessel Flange Tool (Rft) Design Plan and Schedule. ML19042A0732019-02-0505 February 2019 Nuscale - Chapters 2 and 17 ACRS Full Committee, PM-0219-64333, Revision 0 ML19024A2042019-01-23023 January 2019 ECCS Valve DCA Demonstration Testing, PM-0119-64160-NP, Revision 0 ML18360A1782018-12-19019 December 2018 Enclosure 2: Presentation Titled, Addressing Component Fatigue for NuScale Dca. ML18362A1422018-12-19019 December 2018 Enclosure 2: Absorption Coefficient for Pool Water and Reactor Building Floor Interaction, PM-1218-63882, Revision 0 ML18347A2032018-12-18018 December 2018 Enclosure 1: ACRS Presentation Chapter 17 - Quality Assurance and Reliability Assurance, PM-1218-63732, Revision 0 ML18347A2072018-12-18018 December 2018 ACRS Presentation Chapter 2 - Site Characteristics and Site Parameters, PM-1218-63753, Revision 0 ML19025A2212018-12-18018 December 2018 Enclosure 2: Slides Titled, Basis for an Rft Stand COL Item, PM-1218-63892-NP, Revision 0, Non-Proprietary Version ML18331A1602018-11-20020 November 2018 Enclosure 2: Addressing Component Fatigue for NuScale DCA, November 20, 2018 ML18338A1032018-11-14014 November 2018 Nuscale - LTC RAI Closure Plan, PM-1118-63594-NP, Revision 0, Nonproprietary Version ML18235A3152018-08-23023 August 2018 LLC - Presentation Materials Entitled ACRS Presentation: NuScale Instrumentation and Controls Design Overview, PM-0618-60212, Revision 0 ML18222A1932018-08-0808 August 2018 Enclosure 1: NuScale Accident Source Terms Methodology Options PM-0818-61166, Revision 0 ML18213A1572018-08-0101 August 2018 Risk-Informed Review of NuScale Initial Test Program, PM-0718-61123, Revision 0 ML18220A8742018-07-25025 July 2018 Enclosunuscale CIRLT-RAI 9474 ML18156A1262018-06-0101 June 2018 LLC Submittal of Presentation Materials Entitled, ACRS Presentation Chapter 8 Overview, for Use During a Public Meeting on June 6, 2018 ML18156A1272018-05-31031 May 2018 LLC Submittal of Presentation Materials Entitled NuScale Power Containment Leak Rate Test Program, PM-0518-59978, Revision 1 ML18116A4422018-04-24024 April 2018 Enclosure 2: NuScale Power Comprehensive Vibration Assessment Program - Audit Report Summary Discussion, Revision 0, PM-0218-58803-NP (Non-Proprietary Version) ML18037A6732018-02-0808 February 2018 PM-0218-58480, Revision 0, Shutdown Capability of the NuScale Power Module. 2020-07-01
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Text
.::.*:*.. NUS CALE
.:. .:. POWER" L0-0518-60037 May 31 , 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 Submittal of Presentation Materials Entitled "NuScale Power Containment Leak Rate Test Program," PM-0518-59978, Revision 1
REFERENCES:
- 1. Letter from NuScale Power LLC, to Nuclear Regulatory Commission ,
"NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application ," dated December 31 , 2016 (ML17013A229)
- 2. Letter from NuScale Power LLC, to Nuclear Regulatory Commission ,
"NuScale Power, LLC Submittal of Presentation Materials Entitled
'NuScale Power Containment Leak Rate Test Program,' PM-0518-59978 ,
Revision O, dated May 15, 2018 NuScale Power, LLC (NuScale) participated in a public meeting with the NRC technical staff on May 17, 2018, to discuss the NuScale Containment Design and Appendix J Exemption Request which was submitted to the NRC in the referenced Design Certification Application .
The purpose of this submittal is to provide the presentation materials that NuScale used during th is meeting. The enclosure to this letter contains the presentation entitled "NuScale Power Containment Leak Rate Test Program ," PM-0518-59978, Revision 1.
This letter makes no regulatory commitments and no revisions to any existing regulatory commitments .
If you have any questions, please contact ennie Wike at 541-360-0539 or at jwike@nuscalepower.com .
Sincerely, J~ (µ~
Manager, Licensing NuScale Power, LLC Distribution : Samuel Lee, NRC, OWFN-8G9A Omid Tabatabai, NRC, OWFN-8G9A Prosanta Chowdhury, NRC, OWFN-8G9A Bruce Bavol , NRC , OWFN-8G9A
Enclosure:
"NuScale Power Containment Leak Rate Test Program", PM-0518-59978, Revision 1 D II)
NuScale Power, LLC 1100 NE Circle Blvd ., Suite 200 Corvallis, Oregon 97330 Office 541 .360-0500 www nuscalepower com Fax 541.207.3928 tJ /(D
.:: . * :*.. NU SCALE
.:. .:. POWER" L0-0518-60037
Enclosure:
"NuScale Power Containment Leak Rate Test Program", PM-0518-59978, Revision 1 NuScale Power, LLC 1100 NE Circle Blvd ., Suite 200 Corvallis, Oregon 97330 Office 541 .360-0500 Fax 541 .207.3928 www.nuscalepower.com
NuScale Nonproprietary NuScale Power Containment Leak Rate Test Program May 17, 2018 Jennie Wike Manager, Licensing, NuScale Zack Houghton Manager, NSSS Design, NuScale PM-0518-59978
- NuSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC.
- POWER-Template #: 0000-21727-F01 R3
Acknowledgement & Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0000633.
This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.
Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
2 PM-0518-59978 *. NUSCALE Revision: 1 Copyright 201 8 by NuScale Power, LLC. : POWE:R-Template #: 0000-21 727-F01 R3
Agenda
- Overview of the NuScale Containment Leak Rate Testing (CLRT) program
- Initial design pressure testing and flange contact analysis
- Planned responses to eRAI 9474 3
PM-0518-59978 ;- *. NUSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC. .. ~ .= Powe:R-Temp1a1e #: 0000-21727-F01 R3
Containment Leak Rate Testing
- After shutdown , all Type Band C penetrations are as-found tested Type B penetrations Process Penetrations Electrical Penetrations CNV Closure Flange l&C Division 1 Penetration CNV Head Manway Flange l&C Division 2 Penetration CNV Head CRDM Access Flange Electrical 1 - PZR Power Penetration CNV Manway Electrical 2 - PZR Power Penetration SG Inspection Port 1 l&C Channel A Penetration Flange SG Inspection Port 2 l&C Channel B Penetration Flange SG Inspection Port 3 SG Inspection Port 4 l&C Channel C Penetration Flange PZR Heater Port 1 l&C Channel D Penetration Flange PZR Heater Port 2 CRDM Power Penetration ECCS Trip and Rest Valves (11) RPI Group 1 Penetration CIV Test Port Covers (8) RPI Group 2 Penetration 4
PM-0518-59978 *. NUSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC . .' POWE:: R-Template #: 0000-21727-F01 R3
Containment Leak Rate Testing
- After shutdown, all Type Band C penetrations are as-found tested Type C penetrations Description Quantity CVCS Injection CIV 2 eves Discharge CIV 2 CVCS PZR Spray CIV 2 RPV High Point Degasification CIV 2 Containment Flood & Drain CIV 2 1
Containment Evacuation CIV 2 RCCWS Supply CIV 2 RCCWS Return CIV 2 SG Thermal Relief Valves 2 5
PM-0518-59978 *~ NUSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC.
- POWE::R-Template #: 0000-21727-F01 R3
CLRT Overview
- As-left Type B or C test on any penetration impacted during maintenance
- Local leak rate test (LLRT) results shall meet< 0.6 La
- Module moved to operating bay 6
PM-0518-59978 NuSC A LE Revision: 1 Copyright 2018 by NuScale Power, LLC. . Powi:R-Template #: 0000-21727-F01 R3
Closure Flange Integrity Test
- New test proposed to confirm integrity of the closure flange seal after module movement
- Containment vessel pressurized with air during startup
- Test port monitored to provide assurance of leak tight condition of the closure flange joint with pressure inside containment 7
PM-0518-59978
..-..,.... NUSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC. . P O W E:R-Template #: 0000-21 727-F01 R3
Design Pressure Testing and Contact Force Analysis
- For the initial module, NuScale plans to perform initial design pressure testing of an assembled containment vessel with:
- design bolting materials
- bolt preload tensioning
- design double a-ring seals
- Subsequent modules may be initial design pressure tested as upper and lower module sections based on manufacturer limitations
- Initial design pressure testing requirements will ensure no leakage through any bolted joint at design basis pressure
- NuScale plans to complete analysis to show that contact force is maintained at the sealing joint for all Type B bolted connections
- Combination of initial design pressure testing and flange contact force analysis provides reasonable assurance that test program is sufficiently representative of accident conditions 8
PM-0518-59978
- NuSCA LE Revi sion: 1 Copyright 2018 by NuScale Power, LLC.
- P O W E: R-Template #: 0000-21727-F01 R3
NuScale RAI 9474 Response Summary 6.2.6-22 Provide the technical basis for concluding Analysis and initial design pressure testing ensure that Type B and C testing are sufficiently leakage characteristics not substantively different at representative of accident conditions. ambient vs design pressure. Type B and C testing sum to less than 0.6 La .
6.2.6-23 Confirm that the factory hydrotest will be Proposed initial design pressure test as requested on performed on an assembled containment completely assembled initial unit with allowance to test vessel under design conditions. Add an separate upper and lower assemblies on subsequent ITAAC for the ASME code required hydro. units, maintaining design assembly configuration, and captured ITAAC.
6.2.6-24 Confirm intent to demonstrate leak tight As-found Type B for all flanges and as-left Type B on all integrity after each refueling outage. opened flanges prior to return to operations. Closure flange integrity test proposed to ensure maintaining integrity at main seal following transport.
6.2 .6-25 Identify key attributes and inspections verified Inspection of bolting and cover, install of new seals, for vessel reassembly. Add flange bolting preload , verify preload of closure flange. Standard inspection elements to TR-1116-51962. industry practices for bolted joint procedures. Closure flange integrity test proposed to ensure no gross main seal failure during transport.
6.2 .6-26 Provide calculations for total expected Analysis will be completed to show no flange gap at leakage for all flanges, preload , and flange design preload and accident conditions. Calculation will gaps at design pressure. be provided to evaluate potential total leakage from joints. Leakage assumption will be preliminary estimates to show margin only.
9 PM-0518-59978 *. NUSCALE Revi sion: 1 Copyright 2018 by NuScale Power, LLC. ** POWl:R-Tem plate # : 0000-21727-F01 R3
Summary
- NuScale is proposing a new test to confirm integrity of the closure flange seal after module movement
- Maximum allowable leak rate (L 8 ) is demonstrated by
- Type B testing (as-left and as-found)
- Type C testing (as-left and as-found)
- analysis and initial design pressure test assure seal performance during design basis pressure conditions 10 PM-0518-59978 :* *. NUSCALE Revision: 1 Copyright 2018 by NuScale Power, LLC. .. .' POWE:R-Template # : 0000-21727-F01 R3
Portland Office Richland Office 6650 SW Redwood Lane, 1933JadwinAve., Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541 .360.0500 971 .371.1592 Arlington Office Corvallis Office 2300 Clarendon Blvd., Suite 1110 1100 NE Circle Blvd., Suite 200 Arlington, VA 22201 Corvallis, OR 97330 541 .360.0500 London Office 1st Floor Portland House Rockville Office Bressenden Place 11333 WoodglenAve ., Suite 205 London SW1 E 5BH Rockville, MD 20852 United Kingdom 301 . 770.0472 +44 (0) 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980.349.4804 http://www.nuscalepower.com
'ti Twitter: @NuScale_Power
.::.*:*.. N USCALE
-~. .:. POWERTM 11 PM-0518-59978
- NuSCALE Revision: 1 Copyright 20 18 by NuScale Power, LLC. P OWER-Template #: 0000-21727-F01 R3