ML18291B228

Interim Audit Summary Report - Containment and Ventilation Systems

ML18291B228
Person / Time
Site:	NuScale
Issue date:	11/09/2018
From:	Tabatabai-Yazdi O NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Tabatabai-Yazdi O/NRO/415-6616
References
Download: ML18291B228 (12)

Text

November 9, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/

Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors

SUBJECT:

U.S. NUCLEAR REGULATORY COMMISSION STAFF INTERIM AUDIT REPORT FOR CONTAINMENT AND VENTILATION SYSTEMS (DOCKET NO.52-048)

In March 2017, the U.S. Nuclear Regulatory Commission (NRC) staff began a regulatory audit of certain documents of the NuScale Power, LLC (NuScale) design certification application (DCA) pertaining to the Containment and Ventilation Systems. The NRC staff issued its initial audit plan on March 29, 2017, and an addenda to the audit plan on June 28, 2018 (Agencywide Documents Access and Management System Accession Nos. ML17087A077 and ML18177A087). The intent of this audit, in part, was to gain a more detailed understanding of the NuScale design in technical areas associated with containment and ventilation systems and to identify information that will require docketing to support the basis of the regulatory decision.

This interim audit summary report documents the NRC staffs audit activities and progress from April 3, 2017 through August 31, 2018. The NRC staff conducted the audit in accordance with the Office of New Reactors (NRO) Office Instruction NRO-REG-108, Regulatory Audits.

Docket No.52-048

Enclosure:

1. NRC Staff Interim Audit Report for Containment and Ventilation Systems cc: NuScale DC ListServ CONTACT: Omid Tabatabai, NRO/DNRL 301-415-6616

ML18291B228 *via email* NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA* NRO/DSRA/SCVB: BC*

NAME OTabatabai MMoore* DJackson (HWagage for)

DATE 10/19/2018 10/22/2018 11/8/2018 U.S. NUCLEAR REGULATORY COMMISSION REGULATORY AUDIT OF CONTAINMENT AND VENTILATION SYSTEMS AS PART OF THE NUSCALE POWER, LLC DESIGN CONTROL DOCUMENT REVIEW INTERIM AUDIT

SUMMARY

REPORT FOR APRIL 3, 2017 THROUGH AUGUST 31, 2018 NRC Audit Team:

• Hanry Wagage, NRO, Audit Lead

• Clinton Ashley, NRO

• Anne-Marie Grady, NRO

• Syed Haider, NRO

• Alfred Hathaway, RES

• Raul Hernandez, NRO

• Peter Lien, RES

• Shanlai Lu, NRO

• Jeffrey Schmidt, NRO

• Carl Thurston, NRO

• Boyce Travis, NRO

• Rebecca Karas, NRO, Branch Chief (Reactor Systems Branch)

• Diane Jackson, NRO, Branch Chief (Containment Branch)

• Mohsen Khatib-Rahbar, ERI (NRC Contractor)

• Alfred Krall, ERI (NRC Contractor)

• Zhe Yuan, ERI (NRC Contractor)

• Omid Tabatabai, NRO, Senior Project Manager I. AUDIT LOCATION AND DATES The U.S. Nuclear Regulatory Commission (NRC) staff conducted the audit from NRC Headquarters in Rockville, Maryland, through NuScales electronic reading room (eRR) and also at (1) the NuScale Office at 11333 Woodglen Drive, Suite 205, Rockville, Maryland 20852 and (2) NuScale Integral System Test (NIST-1) facility located at Oregon State University in Corvallis, Oregon. This interim audit summary report is for the period of April 3, 2017, through August 31, 2018.

II. Background and Audit Basis In a letter dated December 31, 2016, NuScale submitted to the U.S. Nuclear Regulatory Commission (NRC) Revision 0 of the NuScale Standard Plant Design Certification Application (DCA) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17013A229). The NRC staff initiated this DCA review on March 27, 2017. NuScale submitted Revision 1 of DCA to the NRC on March 15, 2018 (ADAMS Accession No. ML18086A090). Application documents for the NuScale design are available at the NRC Website at https://www.nrc.gov/reactors/new-reactors/design-cert/nuscale/documents.html.

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The intent of this audit, in part, was to gain a more detailed understanding of the NuScale design in technical areas associated with containment and ventilation systems and identify information that will require docketing to support the basis of the regulatory decision. The NRC staff issued an audit plan on March 29, 2017, and an addenda on June 28, 2017 (ADAMS Accession Nos. ML17087A077 and ML18177A087, respectively). The addenda narrowed the audit scope by limiting it to three specific areas: containment pressure analysis, containment integrated leakage rate testing (ILRT), and containment Isolation. This interim audit summary report has been prepared in accordance with NRO-REG-108, Regulatory Audits, Revision 0, April 2, 2009 (ADAMS Accession No. ML081910260).

III. DOCUMENTS AUDITED The NRC staff performed an audit of documents, as necessary, shown in the attachment.

IV. Audit Activities and Summary of Findings The audit activities included the following review areas:

• containment peak pressure analysis;

• containment heat removal;

• methodology of mass and energy release from the reactor coolant system;

• ASME qualification of the containment vessel;

• containment leak rate testing, including NuScale exemption request no. 7, 10 CFR 52, App. A, GDC 52 Containment Leakage Rate Testing;

• combustible gas control, including NuScale exemption request no. 2, 10 CFR 50.44 Combustible Gas Control;

• equipment survivability;

• containment isolation, including NuScale exemption request no. 9, 10 CFR 50, Appendix A, GDC 55, 56, and 57 Containment Isolation;

• containment flooding and drain;

• pipe break hazard analysis;

• NIST-1 test observation;

• range of reactor recirculation valve opening;

• containment stratification; and

• containment nodalization.

The NRC staff had numerous (more than 100) interactions with NuScale, including teleconferences, test observations, and face-to-face meetings. The audit enhanced the NRC staffs review of the NuScale DCA by providing an opportunity to review non-docketed 2

supporting design information that was not submitted with the DCA. Specifically, the audit documents that were made available to the NRC staff for review have enabled the staff to efficiently obtain the information that they need in order to continue their review and prepare their safety evaluation report. Furthermore, the audit allowed the NRC staff to limit issuing requests for additional information (RAIs), as needed, to:

• Gain a better understanding of the detailed calculations, analyses and/or bases underlying the formal application and confirm the staffs understanding of the NuScale application.

• Identify additional information, necessary for the applicant to supplement its application, assisting the staff to reach a regulatory decision.

• Establish an understanding in an area where the staff has identified potential concerns, and in turn allow the staff to issue clear RAIs enabling the applicant to provide quality and timely responses.

• Enhance the staffs understanding of the NuScale design in support of making a regulatory decision.

As stated in the June 28, 2018, addenda to the audit plan, the staffs supplemental containment audit involved three stages. Stage 1 included the staff visiting the NuScales NIST-1 testing facility in Corvallis, Oregon, and observing the HP-49 test. The HP-49 test was to show that NRELAP5 code was capable of appropriately modeling the containment thermal hydraulic phenomena that would result from an inadvertent RRV-opening event as the limiting liquid-space discharge event. NuScale has identified this as the limiting peak containment pressure design basis event in the design certification application. Stage 2 was to audit the raw HP-49 test data, which the staff conducted on August 7 and 8, 2018, at NuScales office in Rockville, Maryland. The main objective of Stage 2 was to verify the decay heat and peak containment pressure measurements at the NIST-1 test facility, and gather the initial conditions from the data set to be used in the staffs confirmatory NRELAP5 and TRACE calculations of the NIST-1 HP-49 test. The staff found that Stage 1 and Stage 2 audits met all stated objectives. Stage 3 is to audit NuScales HP-49 post-test assessment report. NuScale provided this report on its eRR for audit in mid-September and the staff is currently auditing it. The staff will provide more details about the audit activities related to Stages 1 through 3 in a final audit summary report after completing the containment audit.

As part of the evaluation of NuScales Exemption Request #7 on ILRT, staff issued RAI 9474 asking NuScale to show (through analysis, testing, or combination) that the maximum containment allowable leak rate is met and that containment leak tight integrity is restored after each refueling outage. Staff is currently evaluating NuScales RAI response, including a revised analysis provided in EC-A013-1691, Revision 2, on the eRR. The staff is also reviewing this analysis for the containment ASME III design, and ASME inspection of flange bolts 2-inch diameter and smaller.

The June 28, 2017, addenda to the audit plan included containment isolation because of a staffs expectation that the audit may be needed to support reviewing NuScales response to RAI 8836, Question 3.6.2-2, which was expected later on August 30, 2018. This RAI response was delayed until December 2018. However, the staff does not foresee now any plan for using the present audit to support reviewing the RAI-8836 response.

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V. CONCLUSION This audit is currently in progress and the NRC staff will issue a final audit summary report after completing the audit.

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Attachment:

Documents Audited by the Staff No. File Document Name Rev. #

1 00002090_1_RPV and CNV Flange RPV and CNV Flange Geometry 1 Geometry Stud.pdf 2 32-9257575-000 NuScale Reactor NuScale Reactor Core Chemical Core Chemical Deposition Analysis.pdf Deposition Analysis 3 51-9257323-000 AIS for NuScale GSI- AIS for NuScale GSI-191 Evaluation 191 Evaluation.pdf 4 DD-F010-4444_R0_Bioshield_Re- Bioshield Re-Design To Support 0 Design_to_Support_Environmental_Qu Environmental Qualification Profile alification_Profile.pdf 5 DI-0303-51058_R0.pdf NIST-1 Data Processing for Code 0 Assessment Purposes 6 EC_0000_3853_R1_Calcs_to_Support Calculations to Support NIST-1 1

_NIST- Distortion Analysis and Modeling of 1_Distortion_Analysis_and_Modeling_ Containment and Pool Heat Transfer of_Containment_and_Pool_Heat_Tran sfer 7 EC_A013_00003036_01_CNV_Ultimat CNV Ultimate Pressure Integrity 1 e_Pressure_Integrity_Analysis.pdf Analysis 8 EC_A013_3377_R0_CNV_Primary_Str Primary Stress Analysis of the 0 ess_Analysis.pdf Containment Vessel 9 EC_B020_2877_R1 ECCS ECCS Combustible Gas Analysis 1 Combustible Gas Analysis.pdf 10 EC_B020_4365_R0, Containment Gas Containment Gas Composition 0 Composition Calculation.pdf Calculation 11 EC_F010_5233_00_CNV_Support_Int CNV Interface with RXB Floor 0 erface_with_RXB_Floor.pdf 12 EC-0000-2250- Feedwater Piping Failure Analysis 0 R0_Feedwater_Piping_Failure_Analysi s.pdf 13 EC-0000-2714- Steam System Piping Failure Analysis 0 R0_Steam_System_Piping_Failure_An alysis.pdf 14 EC-0000- Failure of Small Lines Carrying 2 2786_R2_Failure_of_Small_Lines_Car Primary Coolant Outside Containment rying_Primary_Coolant_Outside_Conta inment.pdf 15 EC-0000- GOTHIC HELB Cases of NuScale 0 4718_R0_GOTHIC_HELB_Cases_of_ Top of Module RXB Pool Room NS_Top_of

_Model_and_RXB_Pool_Room.pdf Attachment 1

No. File Document Name Rev. #

16 EC-0000- NuScale High Energy Line Break 1 4720_R1_NS_High_Energy_Line_Bre Scenario Definition - Top of Module ak_Scenario_Definition_Top_of_Modul e.pdf 17 EC-0000-4721 GOTHIC HELB Cases of NuScale 1 1_GOTHIC_HELB_Causes_of_NS_To Top of Module RXB Pool Room p_of_Module_and_RXB_Pool_Room 18 EC-0000- GOTHIC HELB Cases of NuScale 0 4745_R0_GOTHIC_HELIB_Cases_of_ Top of Module and RXB Pool Room NS_Top_of_Module_and with Bioshield Blowout Panels Design RXB_Pool_Room_BioShield_Blowout_

Panels.pdf 19 EC-0000- GOTHIC HELB Cases of Revised 0 4746_R0_GOTHIC_HELIB_Cases_of_ M&E for NuScale Top of Module and Revised_M&E_for_NS_Top_of_Modul RXB Pool Room e_and_RXB_Pool_Room.pdf 20 EC-0000-5435-R0_final.pdf Containment Pressure Initial 0 Condition Sensitivity Calculations 21 EC-A010-2322-R3 Reactor Module Reactor Module Seismic Model 3 Seismic Model.pdf 22 EC-A010-3559-R3 Reactor Module Reactor Module Seismic Calculation 3 Seismic Calculation.pdf 23 EC-A010-4270-1.pdf Long Term Cooling Analysis 1 24 EC-A013-1691_R0 Containment Containment Vessel Flange Bolting 0 Vessel Flange Bolting Calculation.pdf Calculation 25 EC-A013-2341 2 Contain Pressure Containment Pressure and 2 Temperature Response Design Basis Temperature Response to Design Events Analysis.pdf Basis Events 26 EC-A013-2341_R1 Containment Containment Pressure and 1 Pressure and Temperature Response Temperature Response to Design Design Basis Events Analysis.pdf Basis Events 27 EC-A030-4101, R0 Class 1 Piping Class 1 Piping Stress Analysis For 0 Stress Analysis For RCS RCS Discharge Line Discharge_Line.pdf 28 EC-B060-4543 0.pdf GOTHIC Passive Cooling of NuScale 1 Control Room Building 29 EC-B060-4544_ GOTHIC Passive Cooling Analysis of 1 R0_GOTHIC_Passive_Cooling_Analys NuScale RXB Main Pool Room is_of_NS_RXB_Main_Pool_Room.pdf 30 EC-B175-3253_R0 Ultimate Heat Sink Ultimate Heat Sink Boil Off 0 Boil Off Calculation.pdf Calculation 31 EC-F010-3108 Rev. 7.pdf Seismic Soil-Structure Interaction 0 Analysis of NuScale Reactor Building for ISRS Generation 2

No. File Document Name Rev. #

32 ECN_A010_4189_R0_For EQ-A010- Corrections to Table 3-1 Normal 0 3642 Correction to Table 3-1.pdf Operating Pressures and Temperatures for DHRS Lines (for EQ-A010-3642, 0) 33 ECN_A010_4575_R0 For EQ-A010- Revision of Overpressure Protection 0 3642 Overpress Protect Require Requirements for Steam Generator Steam Gen System Piping.pdf System Piping (for EQ-A010-3642, 0) 34 ECN_A010_4614_R0 For EQ-A010- Secondary Systems Containment 0 2224 2nd Systems Contain Isolat Isolation Valves Design Spec.

Valves Design Spec Term Change.pdf Terminology Change (for EQ-A010-2224, 0) 35 ECN_A010_4981_R0 For EQ-A010- RXM Class 1, 2, 3 Piping Design 0 3642,RXM Class 1, 2, 3 Piping Design Spec. Terminology Change (for EQ-Spec. Terminology Change.pdf A010-3642, 0) 36 ECN_A010_5024_R0 For EQ-A010- Material Specification Update (for EQ- 0 2224 Material Specification Update.pdf A010-2224, 0) 37 ECN_B020_4991_R0 Add Evaluation Add Evaluation of Hydrogen Mixing 0 of Hydrogen Mixing during ECCS during ECCS Operation (for EC-operation.pdf BZ020-4365, 0) 38 ECN_B020_5023_R0 For EQ-B020- Material Specification Update (for EQ- 0 2140 Material Specification Update.pdf A010-2140, 2) 39 ECN_B030_4700_R0_For EQ-B030- ASME Design Specification for Decay 0 2258 ASME Design Specs Decay Heat Heat Removal System Actuation Removal System Actuat Valves.pdf Valves (for EQ-B030-2258, 0) 40 ECN_B030_4849_R0_For EQ-B030- Decay Heat Removal Actuation 0 2258 Decay Heat Remov Actuat Valves Design Specification Valves Load Combin Changes.pdf Terminology and Load Combination Changes (for EQ-B030-2258, 0) 41 ECN_B090_4290_Deisgn Solution for Design Solution for the HELB FR (for 0 the HELB FR.pdf SD-B090-1680, 0) 42 ECN_B090_4436_Add Passive Vent Add Passive Vent Requirements to 0 requirement to the FS.pdf the FS (for FS-B090-0533, 3) 43 ECN-0000_4908_R0 Containment Containment Pressure and 0 Pressure and Temperature Updates Temperature Updates (for ER-0000-ER-0000-4316.pdf 4908, 1) 44 ECN-0000-4968_R0 Update Appendix Update Appendix A Table A-1, 0 A Table A-1 Environmental Zones ER- Environmental Zones Required 0000-4316.pdf Update (for ER-0000-4316, 1) 45 ECN-0000-4998_R0 Various Updates Various Updates to ER-0000-4316 0 to ER-0000-4316 Body, Figures and Body, Figures and Tables (for ER-Tables.pdf 0000-436, 1) 3

No. File Document Name Rev. #

46 ECN-0000-5032_R0 For ER-0000- Reorganization of Chapter 5.0 (for 3921 Reorganization of Chapter ER-0000-3921, 0) 5.0.pdf 47 ECN-0000-5033_R0 For ER-0000- Miscellaneous Wording Adjustments 0 3921 Misc Wording Adjustments for Licensing Purposes (for ER-0000-Licensing Purposes.pdf 3921, 0) 48 ECN-0000-5036_R0 For ER-000-3921 Reorganization of Chapter 3.0 (for 0 Reorganization of Chapter 3.0.pdf ER-0000-3921, 0) 49 ECN-A010-4742_R0 For EQ-A010- ECN for ASME Design Specification 0 2224 ASME Design Specs Second for Secondary Systems Containment Systems Contain Isolation Valves.pdf Isolation Valves (for EQ-A010-2224, 0) 50 ECN-A013-5079_R0 For EC-A013- ECN for EC-A013-2341, 2 2341 Additional M&E Tables for (Containment Pressure and Licensing.pdf Temperature Response to Design Basis Events) 51 ECN-A013-5131_R2 For EC-A013- Adding M&E Tables for Licensing (for 0 2341 O-RELAP v1.3.0 input decks for EC-A013-2341, 2) mass unit conversion.pdf 52 ECN-B030-4744_R0 For EQ-B030- ECN for ASME Design Specification 0 2258 ASME Design Specs Decay Heat for Decay Heat Removal System Remov System Activat Valves.pdf Actuation Valves (for EQ-B030-2258, 0) 53 EC-T080-3822-R1.pdf NRELAP5 Assessment Against 1 NuScale Separate Effects High Pressure Condensation Test Series NIST-1 HP-02 54 ED-F012-3661_ BioShield General Arrangements 2 R2_BioShield_General_Arrangement_ Details and _Details.pdf 55 EQ_A010_00002235_01_ASME_Desi ASME Design Specification for 1 gn_Specification_for_Primary_System Primary Systems Containment s_Containment_Isolation_Valves.pdf Isolation Valves 56 EQ_A011_00001775_01_ASME ASME Design Specification for 1 Design Specification for Reactor Reactor Pressure Vessel Pressure Vessel.pdf 57 EQ_A013_00001826_01_ASME ASME Design Specification for 1 Design Specification for Containment Vessel Containment_Vessel.pdf 58 EQ_B020_00002140_02_ASME_Desi ASME Design Specification for 2 gn_Specification_for_Emergency_Core Emergency Core Cooling System

_Cooling_Valvespdf Valves 59 EQ-A010-2224_R0 ASME Design ASME Design Specifications for 0 Specification for Secondary System Secondary Systems Containment Containment Isolation Valves.pdf Isolation Valves 4

No. File Document Name Rev. #

60 EQ-A010-2235_R0 ASME Design ASME Design Specifications for 0 Specification for Primary Systems Primary Systems Containment Containment Isolation Valves.pdf Isolation Valves 61 EQ-A010-3642_R0 ASME Design ASME Design Specifications for RXM 0 Specification for RXM Class 1 2 3 Class 1, 2, and 3 Piping Piping.pdf 62 EQ-A013-5418 R0 - ASME Design Design Specification for CNV 0 Specification for Containment Electrical Penetration Assemblies EPAs.pdf 63 EQ-B030-2258_R0 ASME Design ASME Design Specification for Decay 0 Specification for Decay Heat Removal Heat Removal System Actuation System Activation Valves.pdf Valves 64 ER_A010_2009_4_NuScale__Reactor NuScale Reactor Module Design 4

_Module_Design_Parameters.pdf Parameters 65 ER_A013_3246_R1 Containment Containment Vessel Structural 1 Vessel Structural Eval for Combustible Evaluation for Combustible Gas Gas.pdf 66 ER_B020_4364_R0_GSI_191_Assess GSI-191, Assessment of Debris 0 ment_of_Debris_Accumulation_on_P Accumulation on Pressurized Water WR_Sump_Performance_Evaluation_ Reactor [PWR] Sump Performance -

of_Ex_Vessel_and_In_Vessel Evaluation of Ex-vessel and In-vessel Effects 67 ER_P000_7002_R0_PRA_Quantificati Probabilistic Risk Assessment 0 on_Notebook_.pdf Quantification Notebook 68 ER_P010_7007_R0_Accident_Sequen Accident Sequence Analysis 0 ce_Analysis_Notebook_wECN.pdf Notebook 69 ER_P010_7008_R0_Success_Criteria Success Criteria Notebook 0

_Notebook_wECN.pdf 70 ER_P020_00004896_00_Severe_Acci Severe Accident Selection 0 dent_Selection_Methodology.pdf Methodology 71 ER_P020_00004904_00_Hydrogen_D Hydrogen Deflagration-Adiabatic 0 eflagration___Adiabatic_Isochoric_Co Isochoric Complete Combustion mplete_Combustion.pdf 72 ER_P020_7024_R0_Level_2_Probabili Level 2 Probabilistic Risk Assessment 0 stic_Risk_Assessment_Notebook_wE Notebook CN 73 ER_P060_00007077_A_TRN_16T__G TRN-16T: General Transient with Two A eneral_Transient_with_Two_Trains_of Trains of DHRS and Reactor

_DHRS__Reactor_Recirculation_Valve Recirculation Valves Open (Loss of

_Open__Loss_of_DC_Power_.pdf DC Power) 74 ER_P060_4715_R0_TRN_07T__Gene TRN-07: General Transient with Stuck 0 ral_Transient_with_Stuck_Open_RSV_ Open Reactor Safety Valve and No and_No_Mitigation.pdf Mitigation, from a PRA Level 2 Perspective 75 ER_P060_4724_R0 NuScale NuScale MELCOR Basemodel 0 MELCOR Basemodel.pdf 5

No. File Document Name Rev. #

76 ER_P060_4748_R0_LEC_06T__RVV_ LEC-06T: Reactor Vent Valve LOCA 0 LOCA_with_No_Mitigation.pdf with No Mitigation, from a PRA Level 2 Perspective 77 ER_P060_4749_R0_LCC_05T__Char LCC-05T: Charging Line Break Inside 0 ging_Line_Break_Inside_Containment Containment with No Mitigation, from

_with_No_Mitigation.pdf a PRA Level 2 Perspective 78 ER_P060_4750_00_LCU_03T__Uniso LCU-03T: Unisolated Charging Line 0 lated_Charging_Line_LOCA_Outside_ LOCA Outside Containment with No Containment, No_Mitigation.pdf Mitigation, from a PRA Level 2 Perspective 79 ER_P060_4857_R0_LCC_05T__Char LCC-05T: Charging Line Break Inside 0 ging_Line_Break_Inside_Cntmt_Compl Containment with Complete ECCS ete_ECCS_Failure_wECN.pdf Failure, from a PRA Level 2 Perspective 80 ER_P060_7047_R0_LCU_05T__Uniso LOU-05T: Unisolated Charging Line 0 l_Chging_LOCA_Outside_CNV_w_CF LOCA Outside Containment with DS, ECCS.pdf CFDS and ECCS 81 ER_P060_7050_R0_LEC_09T__ECC LEC-09T: ECCS Valve LOCA with 0 S_Valve_LOCA_with_Charging_Injecti Charging Injection on.pdf 82 ER_P060_7075_00_TRN_08T__Gene TRN-08T: General Transient with 0 ral_Transient_RSVs_Fail_to_Open_No Reactor Safety Valves Failed to Open

_Mitigation.pdf and No Mitigation 83 ER_P060_7076_R0_TRN_14A__Gene TRN-14A: General Transient with 0 ral_Transient_with_Cycling_RSV__AT Cycling Reactor Safety Valve (ATWS)

WS_.pdf 84 ER_P060_7082_R0_NRELAP5_PRA_ NuScale NRELAP5 Probabilistic Risk 0 Base_Model.pdf Assessment Base Model 85 ER-0000-2486 4 Safety Analysis Safety Analysis Analytical Limits 4 Analytical Limits report.pdf Report 86 ER-0000-2486 Revision 5.pdf Safety Analysis Analytical Limits 5 Report 87 ER-0000-3921_R0 Long Term Core Long Term Core Cooling Methodology 0 Cooling Methodology Report.pdf Report 88 ER-0000-4316_R1 Environ Service Environmental Service Conditions for 1 Conditions Electrical and Mechanical Electrical and Mechanical Equipment Equipment Qualification.pdf Qualifications 89 ER-0000-4391 Mass and Energy Release and 0 0_Mass_and_Energy_Release_and_C Containment Vessel Pressure and ontainment_Vessel_Pressure_and_Te Temperature Response Methodology mp_Response_Method 90 ER-A013-3246_R0 Containment Containment Vessel Structural 0 Vessel Structural Eval for Combustible Evaluation for Combustible Gas Gas.pdf 6

No. File Document Name Rev. #

91 ER-A013-3635_R0 Containment Containment System Failure Modes 0 System Failure Modes and Effects and Effects Analysis Analysis.pdf 92 ER-A013-4785 0.pdf 10 CFR 50 Appendix J Containment 0 Leakage Testing Assessment 93 ER-P020-5092_Rev_0 Assessment of Assessment of Low-Risk Severe 0 LRSAP for NuScale level 2 PRA.pdf Accident Phenomena for the NuScale Level 2 PRA 94 FS_B080_00000542_02_Control_Roo Control Room HVAC System (CRVS) 2 m_Normal_Ventilation.pdf Functional Specification 95 MSS SDD SD-C010-1722 0 Main Main Steam System Design 0 Steam System Design Description.pdf Description 96 OP-0000-10842_R0 Module Refueling NuScale Model Refueling Operations 0 Operations.pdf 97 RP-1215-19690 - concept of Concept of Automation A automation.pdf 98 SD_B090_00001680_R0_Reactor_Buil reactor Building HVAC System 0 ding_HVAC_System_Design_Descripti (RBVS) System Design Description on.pdf 99 SDR-0615-15509_R4.pdf OSU NIST-1 Facility Description 4 Report 100 SwUM-0304-15495 3 - NRELAP5 NRELAP5 Version 1.3 Input Data 3 Version 1.3 Code Manual Appendix A - Requirements Input Requirements.pdf 101 TR-0216-21604.pdf Superseded Document NuScale 0 Power Containment Vessel Integrated Leak Rate Testing Options 102 TR-0916-51502-P.pdf NuScale Power Module Seismic 0 Analysis 7