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=Text=
=Text=
{{#Wiki_filter: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/
{{#Wiki_filter:November 9, 2018 MEMORANDUM TO:
Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors
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:==
==SUBJECT:==
Line 22: Line 25:
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.
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.
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
Docket No. 52-048  


==Enclosure:==
==Enclosure:==
: 1. NRC Staff Interim Audit Report for Containment and Ventilation Systems cc: NuScale DC ListServ CONTACT: Omid Tabatabai, NRO/DNRL 301-415-6616
: 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*
ML18291B228  
NAME     OTabatabai         MMoore*           DJackson (HWagage for)
*via email*
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  
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  
 
1 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==
==SUMMARY==
REPORT FOR APRIL 3, 2017 THROUGH AUGUST 31, 2018 NRC Audit Team:
REPORT FOR APRIL 3, 2017 THROUGH AUGUST 31, 2018 NRC Audit Team:
* Hanry Wagage, NRO, Audit Lead
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)
* Clinton Ashley, NRO
Diane Jackson, NRO, Branch Chief (Containment Branch)
* Anne-Marie Grady, NRO
Mohsen Khatib-Rahbar, ERI (NRC Contractor)
* Syed Haider, NRO
Alfred Krall, ERI (NRC Contractor)
* Alfred Hathaway, RES
Zhe Yuan, ERI (NRC Contractor)
* Raul Hernandez, NRO
Omid Tabatabai, NRO, Senior Project Manager I.
* Peter Lien, RES
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.
* Shanlai Lu, NRO
II.
* Jeffrey Schmidt, NRO
Background and Audit Basis In a {{letter dated|date=December 31, 2016|text=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.  
* 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.
1


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).
2 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.
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:
IV.
* containment peak pressure analysis;
Audit Activities and Summary of Findings The audit activities included the following review areas:
* containment heat removal;
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.
* methodology of mass and energy release from the reactor coolant system;
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  
* 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:
3 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.
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.
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.
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.
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 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.
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.
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.  
3


V. CONCLUSION This audit is currently in progress and the NRC staff will issue a final audit summary report after completing the audit.
4 V.
4
CONCLUSION This audit is currently in progress and the NRC staff will issue a final audit summary report after completing the audit.  


==Attachment:==
==Attachment:==
Documents Audited by the Staff No.                     File                           Document Name               Rev. #
Documents Audited by the Staff No.
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
File Document Name Rev. #
_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
1 00002090_1_RPV and CNV Flange Geometry Stud.pdf RPV and CNV Flange Geometry 1
_Model_and_RXB_Pool_Room.pdf Attachment 1
2 32-9257575-000 NuScale Reactor Core Chemical Deposition Analysis.pdf NuScale Reactor Core Chemical Deposition Analysis 3
51-9257323-000 AIS for NuScale GSI-191 Evaluation.pdf AIS for NuScale GSI-191 Evaluation 4
DD-F010-4444_R0_Bioshield_Re-Design_to_Support_Environmental_Qu alification_Profile.pdf Bioshield Re-Design To Support Environmental Qualification Profile 0
5 DI-0303-51058_R0.pdf NIST-1 Data Processing for Code Assessment Purposes 0
6 EC_0000_3853_R1_Calcs_to_Support
_NIST-1_Distortion_Analysis_and_Modeling_
of_Containment_and_Pool_Heat_Tran sfer Calculations to Support NIST-1 Distortion Analysis and Modeling of Containment and Pool Heat Transfer 1
7 EC_A013_00003036_01_CNV_Ultimat e_Pressure_Integrity_Analysis.pdf CNV Ultimate Pressure Integrity Analysis 1
8 EC_A013_3377_R0_CNV_Primary_Str ess_Analysis.pdf Primary Stress Analysis of the Containment Vessel 0
9 EC_B020_2877_R1 ECCS Combustible Gas Analysis.pdf ECCS Combustible Gas Analysis 1
10 EC_B020_4365_R0, Containment Gas Composition Calculation.pdf Containment Gas Composition Calculation 0
11 EC_F010_5233_00_CNV_Support_Int erface_with_RXB_Floor.pdf CNV Interface with RXB Floor 0
12 EC-0000-2250-R0_Feedwater_Piping_Failure_Analysi s.pdf Feedwater Piping Failure Analysis 0
13 EC-0000-2714-R0_Steam_System_Piping_Failure_An alysis.pdf Steam System Piping Failure Analysis 0
14 EC-0000-2786_R2_Failure_of_Small_Lines_Car rying_Primary_Coolant_Outside_Conta inment.pdf Failure of Small Lines Carrying Primary Coolant Outside Containment 2
15 EC-0000-4718_R0_GOTHIC_HELB_Cases_of_
NS_Top_of
_Model_and_RXB_Pool_Room.pdf GOTHIC HELB Cases of NuScale Top of Module RXB Pool Room 0


No.                   File                           Document Name             Rev. #
2 No.
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_
File Document Name Rev. #
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
16 EC-0000-4720_R1_NS_High_Energy_Line_Bre ak_Scenario_Definition_Top_of_Modul e.pdf NuScale High Energy Line Break Scenario Definition - Top of Module 1
17 EC-0000-4721 1_GOTHIC_HELB_Causes_of_NS_To p_of_Module_and_RXB_Pool_Room GOTHIC HELB Cases of NuScale Top of Module RXB Pool Room 1
18 EC-0000-4745_R0_GOTHIC_HELIB_Cases_of_
NS_Top_of_Module_and RXB_Pool_Room_BioShield_Blowout_
Panels.pdf GOTHIC HELB Cases of NuScale Top of Module and RXB Pool Room with Bioshield Blowout Panels Design 0
19 EC-0000-4746_R0_GOTHIC_HELIB_Cases_of_
Revised_M&E_for_NS_Top_of_Modul e_and_RXB_Pool_Room.pdf GOTHIC HELB Cases of Revised M&E for NuScale Top of Module and RXB Pool Room 0
20 EC-0000-5435-R0_final.pdf Containment Pressure Initial Condition Sensitivity Calculations 0
21 EC-A010-2322-R3 Reactor Module Seismic Model.pdf Reactor Module Seismic Model 3
22 EC-A010-3559-R3 Reactor Module Seismic Calculation.pdf Reactor Module Seismic Calculation 3
23 EC-A010-4270-1.pdf Long Term Cooling Analysis 1
24 EC-A013-1691_R0 Containment Vessel Flange Bolting Calculation.pdf Containment Vessel Flange Bolting Calculation 0
25 EC-A013-2341 2 Contain Pressure Temperature Response Design Basis Events Analysis.pdf Containment Pressure and Temperature Response to Design Basis Events 2
26 EC-A013-2341_R1 Containment Pressure and Temperature Response Design Basis Events Analysis.pdf Containment Pressure and Temperature Response to Design Basis Events 1
27 EC-A030-4101, R0 Class 1 Piping Stress Analysis For RCS Discharge_Line.pdf Class 1 Piping Stress Analysis For RCS Discharge Line 0
28 EC-B060-4543 0.pdf GOTHIC Passive Cooling of NuScale Control Room Building 1
29 EC-B060-4544_
R0_GOTHIC_Passive_Cooling_Analys is_of_NS_RXB_Main_Pool_Room.pdf GOTHIC Passive Cooling Analysis of NuScale RXB Main Pool Room 1
30 EC-B175-3253_R0 Ultimate Heat Sink Boil Off Calculation.pdf Ultimate Heat Sink Boil Off Calculation 0
31 EC-F010-3108 Rev. 7.pdf Seismic Soil-Structure Interaction Analysis of NuScale Reactor Building for ISRS Generation 0


No.                   File                             Document Name               Rev. #
3 No.
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.
File Document Name Rev. #
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
32 ECN_A010_4189_R0_For EQ-A010-3642 Correction to Table 3-1.pdf Corrections to Table 3-1 Normal Operating Pressures and Temperatures for DHRS Lines (for EQ-A010-3642, 0) 0 33 ECN_A010_4575_R0 For EQ-A010-3642 Overpress Protect Require Steam Gen System Piping.pdf Revision of Overpressure Protection Requirements for Steam Generator System Piping (for EQ-A010-3642, 0) 0 34 ECN_A010_4614_R0 For EQ-A010-2224 2nd Systems Contain Isolat Valves Design Spec Term Change.pdf Secondary Systems Containment Isolation Valves Design Spec.
Terminology Change (for EQ-A010-2224, 0) 0 35 ECN_A010_4981_R0 For EQ-A010-3642,RXM Class 1, 2, 3 Piping Design Spec. Terminology Change.pdf RXM Class 1, 2, 3 Piping Design Spec. Terminology Change (for EQ-A010-3642, 0) 0 36 ECN_A010_5024_R0 For EQ-A010-2224 Material Specification Update.pdf Material Specification Update (for EQ-A010-2224, 0) 0 37 ECN_B020_4991_R0 Add Evaluation of Hydrogen Mixing during ECCS operation.pdf Add Evaluation of Hydrogen Mixing during ECCS Operation (for EC-BZ020-4365, 0) 0 38 ECN_B020_5023_R0 For EQ-B020-2140 Material Specification Update.pdf Material Specification Update (for EQ-A010-2140, 2) 0 39 ECN_B030_4700_R0_For EQ-B030-2258 ASME Design Specs Decay Heat Removal System Actuat Valves.pdf ASME Design Specification for Decay Heat Removal System Actuation Valves (for EQ-B030-2258, 0) 0 40 ECN_B030_4849_R0_For EQ-B030-2258 Decay Heat Remov Actuat Valves Load Combin Changes.pdf Decay Heat Removal Actuation Valves Design Specification Terminology and Load Combination Changes (for EQ-B030-2258, 0) 0 41 ECN_B090_4290_Deisgn Solution for the HELB FR.pdf Design Solution for the HELB FR (for SD-B090-1680, 0) 0 42 ECN_B090_4436_Add Passive Vent requirement to the FS.pdf Add Passive Vent Requirements to the FS (for FS-B090-0533, 3) 0 43 ECN-0000_4908_R0 Containment Pressure and Temperature Updates ER-0000-4316.pdf Containment Pressure and Temperature Updates (for ER-0000-4908, 1) 0 44 ECN-0000-4968_R0 Update Appendix A Table A-1 Environmental Zones ER-0000-4316.pdf Update Appendix A Table A-1, Environmental Zones Required Update (for ER-0000-4316, 1) 0 45 ECN-0000-4998_R0 Various Updates to ER-0000-4316 Body, Figures and Tables.pdf Various Updates to ER-0000-4316 Body, Figures and Tables (for ER-0000-436, 1) 0


No.                   File                           Document Name             Rev. #
4 No.
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
File Document Name Rev. #
_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
46 ECN-0000-5032_R0 For ER-0000-3921 Reorganization of Chapter 5.0.pdf Reorganization of Chapter 5.0 (for ER-0000-3921, 0) 47 ECN-0000-5033_R0 For ER-0000-3921 Misc Wording Adjustments Licensing Purposes.pdf Miscellaneous Wording Adjustments for Licensing Purposes (for ER-0000-3921, 0) 0 48 ECN-0000-5036_R0 For ER-000-3921 Reorganization of Chapter 3.0.pdf Reorganization of Chapter 3.0 (for ER-0000-3921, 0) 0 49 ECN-A010-4742_R0 For EQ-A010-2224 ASME Design Specs Second Systems Contain Isolation Valves.pdf ECN for ASME Design Specification for Secondary Systems Containment Isolation Valves (for EQ-A010-2224,
: 0) 0 50 ECN-A013-5079_R0 For EC-A013-2341 Additional M&E Tables for Licensing.pdf ECN for EC-A013-2341, 2 (Containment Pressure and Temperature Response to Design Basis Events) 51 ECN-A013-5131_R2 For EC-A013-2341 O-RELAP v1.3.0 input decks for mass unit conversion.pdf Adding M&E Tables for Licensing (for EC-A013-2341, 2) 0 52 ECN-B030-4744_R0 For EQ-B030-2258 ASME Design Specs Decay Heat Remov System Activat Valves.pdf ECN for ASME Design Specification for Decay Heat Removal System Actuation Valves (for EQ-B030-2258,
: 0) 0 53 EC-T080-3822-R1.pdf NRELAP5 Assessment Against NuScale Separate Effects High Pressure Condensation Test Series NIST-1 HP-02 1
54 ED-F012-3661_
R2_BioShield_General_Arrangement_
and _Details.pdf BioShield General Arrangements Details 2
55 EQ_A010_00002235_01_ASME_Desi gn_Specification_for_Primary_System s_Containment_Isolation_Valves.pdf ASME Design Specification for Primary Systems Containment Isolation Valves 1
56 EQ_A011_00001775_01_ASME Design Specification for Reactor Pressure Vessel.pdf ASME Design Specification for Reactor Pressure Vessel 1
57 EQ_A013_00001826_01_ASME Design Specification for Containment_Vessel.pdf ASME Design Specification for Containment Vessel 1
58 EQ_B020_00002140_02_ASME_Desi gn_Specification_for_Emergency_Core
_Cooling_Valvespdf ASME Design Specification for Emergency Core Cooling System Valves 2
59 EQ-A010-2224_R0 ASME Design Specification for Secondary System Containment Isolation Valves.pdf ASME Design Specifications for Secondary Systems Containment Isolation Valves 0


No.                   File                             Document Name             Rev. #
5 No.
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
File Document Name Rev. #
_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 -
60 EQ-A010-2235_R0 ASME Design Specification for Primary Systems Containment Isolation Valves.pdf ASME Design Specifications for Primary Systems Containment Isolation Valves 0
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
61 EQ-A010-3642_R0 ASME Design Specification for RXM Class 1 2 3 Piping.pdf ASME Design Specifications for RXM Class 1, 2, and 3 Piping 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
62 EQ-A013-5418 R0 - ASME Design Specification for Containment EPAs.pdf Design Specification for CNV Electrical Penetration Assemblies 0
_DHRS__Reactor_Recirculation_Valve      Recirculation Valves Open (Loss of
63 EQ-B030-2258_R0 ASME Design Specification for Decay Heat Removal System Activation Valves.pdf ASME Design Specification for Decay Heat Removal System Actuation Valves 0
_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
64 ER_A010_2009_4_NuScale__Reactor
_Module_Design_Parameters.pdf NuScale Reactor Module Design Parameters 4
65 ER_A013_3246_R1 Containment Vessel Structural Eval for Combustible Gas.pdf Containment Vessel Structural Evaluation for Combustible Gas 1
66 ER_B020_4364_R0_GSI_191_Assess ment_of_Debris_Accumulation_on_P WR_Sump_Performance_Evaluation_
of_Ex_Vessel_and_In_Vessel GSI-191, Assessment of Debris Accumulation on Pressurized Water Reactor [PWR] Sump Performance -
Evaluation of Ex-vessel and In-vessel Effects 0
67 ER_P000_7002_R0_PRA_Quantificati on_Notebook_.pdf Probabilistic Risk Assessment Quantification Notebook 0
68 ER_P010_7007_R0_Accident_Sequen ce_Analysis_Notebook_wECN.pdf Accident Sequence Analysis Notebook 0
69 ER_P010_7008_R0_Success_Criteria
_Notebook_wECN.pdf Success Criteria Notebook 0
70 ER_P020_00004896_00_Severe_Acci dent_Selection_Methodology.pdf Severe Accident Selection Methodology 0
71 ER_P020_00004904_00_Hydrogen_D eflagration___Adiabatic_Isochoric_Co mplete_Combustion.pdf Hydrogen Deflagration-Adiabatic Isochoric Complete Combustion 0
72 ER_P020_7024_R0_Level_2_Probabili stic_Risk_Assessment_Notebook_wE CN Level 2 Probabilistic Risk Assessment Notebook 0
73 ER_P060_00007077_A_TRN_16T__G eneral_Transient_with_Two_Trains_of
_DHRS__Reactor_Recirculation_Valve
_Open__Loss_of_DC_Power_.pdf TRN-16T: General Transient with Two Trains of DHRS and Reactor Recirculation Valves Open (Loss of DC Power)
A 74 ER_P060_4715_R0_TRN_07T__Gene ral_Transient_with_Stuck_Open_RSV_
and_No_Mitigation.pdf TRN-07: General Transient with Stuck Open Reactor Safety Valve and No Mitigation, from a PRA Level 2 Perspective 0
75 ER_P060_4724_R0 NuScale MELCOR Basemodel.pdf NuScale MELCOR Basemodel 0  


No.                   File                             Document Name           Rev. #
6 No.
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
File Document Name Rev. #
_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
76 ER_P060_4748_R0_LEC_06T__RVV_
_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)
LOCA_with_No_Mitigation.pdf LEC-06T: Reactor Vent Valve LOCA with No Mitigation, from a PRA Level 2 Perspective 0
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
77 ER_P060_4749_R0_LCC_05T__Char ging_Line_Break_Inside_Containment
_with_No_Mitigation.pdf LCC-05T: Charging Line Break Inside Containment with No Mitigation, from a PRA Level 2 Perspective 0
78 ER_P060_4750_00_LCU_03T__Uniso lated_Charging_Line_LOCA_Outside_
Containment, No_Mitigation.pdf LCU-03T: Unisolated Charging Line LOCA Outside Containment with No Mitigation, from a PRA Level 2 Perspective 0
79 ER_P060_4857_R0_LCC_05T__Char ging_Line_Break_Inside_Cntmt_Compl ete_ECCS_Failure_wECN.pdf LCC-05T: Charging Line Break Inside Containment with Complete ECCS Failure, from a PRA Level 2 Perspective 0
80 ER_P060_7047_R0_LCU_05T__Uniso l_Chging_LOCA_Outside_CNV_w_CF DS, ECCS.pdf LOU-05T: Unisolated Charging Line LOCA Outside Containment with CFDS and ECCS 0
81 ER_P060_7050_R0_LEC_09T__ECC S_Valve_LOCA_with_Charging_Injecti on.pdf LEC-09T: ECCS Valve LOCA with Charging Injection 0
82 ER_P060_7075_00_TRN_08T__Gene ral_Transient_RSVs_Fail_to_Open_No
_Mitigation.pdf TRN-08T: General Transient with Reactor Safety Valves Failed to Open and No Mitigation 0
83 ER_P060_7076_R0_TRN_14A__Gene ral_Transient_with_Cycling_RSV__AT WS_.pdf TRN-14A: General Transient with Cycling Reactor Safety Valve (ATWS) 0 84 ER_P060_7082_R0_NRELAP5_PRA_
Base_Model.pdf NuScale NRELAP5 Probabilistic Risk Assessment Base Model 0
85 ER-0000-2486 4 Safety Analysis Analytical Limits report.pdf Safety Analysis Analytical Limits Report 4
86 ER-0000-2486 Revision 5.pdf Safety Analysis Analytical Limits Report 5
87 ER-0000-3921_R0 Long Term Core Cooling Methodology Report.pdf Long Term Core Cooling Methodology Report 0
88 ER-0000-4316_R1 Environ Service Conditions Electrical and Mechanical Equipment Qualification.pdf Environmental Service Conditions for Electrical and Mechanical Equipment Qualifications 1
89 ER-0000-4391 0_Mass_and_Energy_Release_and_C ontainment_Vessel_Pressure_and_Te mp_Response_Method Mass and Energy Release and Containment Vessel Pressure and Temperature Response Methodology 0
90 ER-A013-3246_R0 Containment Vessel Structural Eval for Combustible Gas.pdf Containment Vessel Structural Evaluation for Combustible Gas 0


No.                 File                             Document Name             Rev. #
7 No.
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}}
File Document Name Rev. #
91 ER-A013-3635_R0 Containment System Failure Modes and Effects Analysis.pdf Containment System Failure Modes and Effects Analysis 0
92 ER-A013-4785 0.pdf 10 CFR 50 Appendix J Containment Leakage Testing Assessment 0
93 ER-P020-5092_Rev_0 Assessment of LRSAP for NuScale level 2 PRA.pdf Assessment of Low-Risk Severe Accident Phenomena for the NuScale Level 2 PRA 0
94 FS_B080_00000542_02_Control_Roo m_Normal_Ventilation.pdf Control Room HVAC System (CRVS)
Functional Specification 2
95 MSS SDD SD-C010-1722 0 Main Steam System Design Description.pdf Main Steam System Design Description 0
96 OP-0000-10842_R0 Module Refueling Operations.pdf NuScale Model Refueling Operations 0
97 RP-1215-19690 - concept of automation.pdf Concept of Automation A
98 SD_B090_00001680_R0_Reactor_Buil ding_HVAC_System_Design_Descripti on.pdf reactor Building HVAC System (RBVS) System Design Description 0
99 SDR-0615-15509_R4.pdf OSU NIST-1 Facility Description Report 4
100 SwUM-0304-15495 3 - NRELAP5 Version 1.3 Code Manual Appendix A -
Input Requirements.pdf NRELAP5 Version 1.3 Input Data Requirements 3
101 TR-0216-21604.pdf Superseded Document NuScale Power Containment Vessel Integrated Leak Rate Testing Options 0
102 TR-0916-51502-P.pdf NuScale Power Module Seismic Analysis 0}}

Latest revision as of 10:55, 5 January 2025

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)
v • d • e


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

1 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.

2 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

3 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.

4 V.

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

Attachment:

Documents Audited by the Staff No.

File Document Name Rev. #

1 00002090_1_RPV and CNV Flange Geometry Stud.pdf RPV and CNV Flange Geometry 1

2 32-9257575-000 NuScale Reactor Core Chemical Deposition Analysis.pdf NuScale Reactor Core Chemical Deposition Analysis 3

51-9257323-000 AIS for NuScale GSI-191 Evaluation.pdf AIS for NuScale GSI-191 Evaluation 4

DD-F010-4444_R0_Bioshield_Re-Design_to_Support_Environmental_Qu alification_Profile.pdf Bioshield Re-Design To Support Environmental Qualification Profile 0

5 DI-0303-51058_R0.pdf NIST-1 Data Processing for Code Assessment Purposes 0

6 EC_0000_3853_R1_Calcs_to_Support

_NIST-1_Distortion_Analysis_and_Modeling_

of_Containment_and_Pool_Heat_Tran sfer Calculations to Support NIST-1 Distortion Analysis and Modeling of Containment and Pool Heat Transfer 1

7 EC_A013_00003036_01_CNV_Ultimat e_Pressure_Integrity_Analysis.pdf CNV Ultimate Pressure Integrity Analysis 1

8 EC_A013_3377_R0_CNV_Primary_Str ess_Analysis.pdf Primary Stress Analysis of the Containment Vessel 0

9 EC_B020_2877_R1 ECCS Combustible Gas Analysis.pdf ECCS Combustible Gas Analysis 1

10 EC_B020_4365_R0, Containment Gas Composition Calculation.pdf Containment Gas Composition Calculation 0

11 EC_F010_5233_00_CNV_Support_Int erface_with_RXB_Floor.pdf CNV Interface with RXB Floor 0

12 EC-0000-2250-R0_Feedwater_Piping_Failure_Analysi s.pdf Feedwater Piping Failure Analysis 0

13 EC-0000-2714-R0_Steam_System_Piping_Failure_An alysis.pdf Steam System Piping Failure Analysis 0

14 EC-0000-2786_R2_Failure_of_Small_Lines_Car rying_Primary_Coolant_Outside_Conta inment.pdf Failure of Small Lines Carrying Primary Coolant Outside Containment 2

15 EC-0000-4718_R0_GOTHIC_HELB_Cases_of_

NS_Top_of

_Model_and_RXB_Pool_Room.pdf GOTHIC HELB Cases of NuScale Top of Module RXB Pool Room 0

2 No.

File Document Name Rev. #

16 EC-0000-4720_R1_NS_High_Energy_Line_Bre ak_Scenario_Definition_Top_of_Modul e.pdf NuScale High Energy Line Break Scenario Definition - Top of Module 1

17 EC-0000-4721 1_GOTHIC_HELB_Causes_of_NS_To p_of_Module_and_RXB_Pool_Room GOTHIC HELB Cases of NuScale Top of Module RXB Pool Room 1

18 EC-0000-4745_R0_GOTHIC_HELIB_Cases_of_

NS_Top_of_Module_and RXB_Pool_Room_BioShield_Blowout_

Panels.pdf GOTHIC HELB Cases of NuScale Top of Module and RXB Pool Room with Bioshield Blowout Panels Design 0

19 EC-0000-4746_R0_GOTHIC_HELIB_Cases_of_

Revised_M&E_for_NS_Top_of_Modul e_and_RXB_Pool_Room.pdf GOTHIC HELB Cases of Revised M&E for NuScale Top of Module and RXB Pool Room 0

20 EC-0000-5435-R0_final.pdf Containment Pressure Initial Condition Sensitivity Calculations 0

21 EC-A010-2322-R3 Reactor Module Seismic Model.pdf Reactor Module Seismic Model 3

22 EC-A010-3559-R3 Reactor Module Seismic Calculation.pdf Reactor Module Seismic Calculation 3

23 EC-A010-4270-1.pdf Long Term Cooling Analysis 1

24 EC-A013-1691_R0 Containment Vessel Flange Bolting Calculation.pdf Containment Vessel Flange Bolting Calculation 0

25 EC-A013-2341 2 Contain Pressure Temperature Response Design Basis Events Analysis.pdf Containment Pressure and Temperature Response to Design Basis Events 2

26 EC-A013-2341_R1 Containment Pressure and Temperature Response Design Basis Events Analysis.pdf Containment Pressure and Temperature Response to Design Basis Events 1

27 EC-A030-4101, R0 Class 1 Piping Stress Analysis For RCS Discharge_Line.pdf Class 1 Piping Stress Analysis For RCS Discharge Line 0

28 EC-B060-4543 0.pdf GOTHIC Passive Cooling of NuScale Control Room Building 1

29 EC-B060-4544_

R0_GOTHIC_Passive_Cooling_Analys is_of_NS_RXB_Main_Pool_Room.pdf GOTHIC Passive Cooling Analysis of NuScale RXB Main Pool Room 1

30 EC-B175-3253_R0 Ultimate Heat Sink Boil Off Calculation.pdf Ultimate Heat Sink Boil Off Calculation 0

31 EC-F010-3108 Rev. 7.pdf Seismic Soil-Structure Interaction Analysis of NuScale Reactor Building for ISRS Generation 0

3 No.

File Document Name Rev. #

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

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

4 No.

File Document Name Rev. #

46 ECN-0000-5032_R0 For ER-0000-3921 Reorganization of Chapter 5.0.pdf Reorganization of Chapter 5.0 (for ER-0000-3921, 0) 47 ECN-0000-5033_R0 For ER-0000-3921 Misc Wording Adjustments Licensing Purposes.pdf Miscellaneous Wording Adjustments for Licensing Purposes (for ER-0000-3921, 0) 0 48 ECN-0000-5036_R0 For ER-000-3921 Reorganization of Chapter 3.0.pdf Reorganization of Chapter 3.0 (for ER-0000-3921, 0) 0 49 ECN-A010-4742_R0 For EQ-A010-2224 ASME Design Specs Second Systems Contain Isolation Valves.pdf ECN for ASME Design Specification for Secondary Systems Containment Isolation Valves (for EQ-A010-2224,

0) 0 50 ECN-A013-5079_R0 For EC-A013-2341 Additional M&E Tables for Licensing.pdf ECN for EC-A013-2341, 2 (Containment Pressure and Temperature Response to Design Basis Events) 51 ECN-A013-5131_R2 For EC-A013-2341 O-RELAP v1.3.0 input decks for mass unit conversion.pdf Adding M&E Tables for Licensing (for EC-A013-2341, 2) 0 52 ECN-B030-4744_R0 For EQ-B030-2258 ASME Design Specs Decay Heat Remov System Activat Valves.pdf ECN for ASME Design Specification for Decay Heat Removal System Actuation Valves (for EQ-B030-2258,
0) 0 53 EC-T080-3822-R1.pdf NRELAP5 Assessment Against NuScale Separate Effects High Pressure Condensation Test Series NIST-1 HP-02 1

54 ED-F012-3661_

R2_BioShield_General_Arrangement_

and _Details.pdf BioShield General Arrangements Details 2

55 EQ_A010_00002235_01_ASME_Desi gn_Specification_for_Primary_System s_Containment_Isolation_Valves.pdf ASME Design Specification for Primary Systems Containment Isolation Valves 1

56 EQ_A011_00001775_01_ASME Design Specification for Reactor Pressure Vessel.pdf ASME Design Specification for Reactor Pressure Vessel 1

57 EQ_A013_00001826_01_ASME Design Specification for Containment_Vessel.pdf ASME Design Specification for Containment Vessel 1

58 EQ_B020_00002140_02_ASME_Desi gn_Specification_for_Emergency_Core

_Cooling_Valvespdf ASME Design Specification for Emergency Core Cooling System Valves 2

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

5 No.

File Document Name Rev. #

60 EQ-A010-2235_R0 ASME Design Specification for Primary Systems Containment Isolation Valves.pdf ASME Design Specifications for Primary Systems Containment Isolation Valves 0

61 EQ-A010-3642_R0 ASME Design Specification for RXM Class 1 2 3 Piping.pdf ASME Design Specifications for RXM Class 1, 2, and 3 Piping 0

62 EQ-A013-5418 R0 - ASME Design Specification for Containment EPAs.pdf Design Specification for CNV Electrical Penetration Assemblies 0

63 EQ-B030-2258_R0 ASME Design Specification for Decay Heat Removal System Activation Valves.pdf ASME Design Specification for Decay Heat Removal System Actuation Valves 0

64 ER_A010_2009_4_NuScale__Reactor

_Module_Design_Parameters.pdf NuScale Reactor Module Design Parameters 4

65 ER_A013_3246_R1 Containment Vessel Structural Eval for Combustible Gas.pdf Containment Vessel Structural Evaluation for Combustible Gas 1

66 ER_B020_4364_R0_GSI_191_Assess ment_of_Debris_Accumulation_on_P WR_Sump_Performance_Evaluation_

of_Ex_Vessel_and_In_Vessel GSI-191, Assessment of Debris Accumulation on Pressurized Water Reactor [PWR] Sump Performance -

Evaluation of Ex-vessel and In-vessel Effects 0

67 ER_P000_7002_R0_PRA_Quantificati on_Notebook_.pdf Probabilistic Risk Assessment Quantification Notebook 0

68 ER_P010_7007_R0_Accident_Sequen ce_Analysis_Notebook_wECN.pdf Accident Sequence Analysis Notebook 0

69 ER_P010_7008_R0_Success_Criteria

_Notebook_wECN.pdf Success Criteria Notebook 0

70 ER_P020_00004896_00_Severe_Acci dent_Selection_Methodology.pdf Severe Accident Selection Methodology 0

71 ER_P020_00004904_00_Hydrogen_D eflagration___Adiabatic_Isochoric_Co mplete_Combustion.pdf Hydrogen Deflagration-Adiabatic Isochoric Complete Combustion 0

72 ER_P020_7024_R0_Level_2_Probabili stic_Risk_Assessment_Notebook_wE CN Level 2 Probabilistic Risk Assessment Notebook 0

73 ER_P060_00007077_A_TRN_16T__G eneral_Transient_with_Two_Trains_of

_DHRS__Reactor_Recirculation_Valve

_Open__Loss_of_DC_Power_.pdf TRN-16T: General Transient with Two Trains of DHRS and Reactor Recirculation Valves Open (Loss of DC Power)

A 74 ER_P060_4715_R0_TRN_07T__Gene ral_Transient_with_Stuck_Open_RSV_

and_No_Mitigation.pdf TRN-07: General Transient with Stuck Open Reactor Safety Valve and No Mitigation, from a PRA Level 2 Perspective 0

75 ER_P060_4724_R0 NuScale MELCOR Basemodel.pdf NuScale MELCOR Basemodel 0

6 No.

File Document Name Rev. #

76 ER_P060_4748_R0_LEC_06T__RVV_

LOCA_with_No_Mitigation.pdf LEC-06T: Reactor Vent Valve LOCA with No Mitigation, from a PRA Level 2 Perspective 0

77 ER_P060_4749_R0_LCC_05T__Char ging_Line_Break_Inside_Containment

_with_No_Mitigation.pdf LCC-05T: Charging Line Break Inside Containment with No Mitigation, from a PRA Level 2 Perspective 0

78 ER_P060_4750_00_LCU_03T__Uniso lated_Charging_Line_LOCA_Outside_

Containment, No_Mitigation.pdf LCU-03T: Unisolated Charging Line LOCA Outside Containment with No Mitigation, from a PRA Level 2 Perspective 0

79 ER_P060_4857_R0_LCC_05T__Char ging_Line_Break_Inside_Cntmt_Compl ete_ECCS_Failure_wECN.pdf LCC-05T: Charging Line Break Inside Containment with Complete ECCS Failure, from a PRA Level 2 Perspective 0

80 ER_P060_7047_R0_LCU_05T__Uniso l_Chging_LOCA_Outside_CNV_w_CF DS, ECCS.pdf LOU-05T: Unisolated Charging Line LOCA Outside Containment with CFDS and ECCS 0

81 ER_P060_7050_R0_LEC_09T__ECC S_Valve_LOCA_with_Charging_Injecti on.pdf LEC-09T: ECCS Valve LOCA with Charging Injection 0

82 ER_P060_7075_00_TRN_08T__Gene ral_Transient_RSVs_Fail_to_Open_No

_Mitigation.pdf TRN-08T: General Transient with Reactor Safety Valves Failed to Open and No Mitigation 0

83 ER_P060_7076_R0_TRN_14A__Gene ral_Transient_with_Cycling_RSV__AT WS_.pdf TRN-14A: General Transient with Cycling Reactor Safety Valve (ATWS) 0 84 ER_P060_7082_R0_NRELAP5_PRA_

Base_Model.pdf NuScale NRELAP5 Probabilistic Risk Assessment Base Model 0

85 ER-0000-2486 4 Safety Analysis Analytical Limits report.pdf Safety Analysis Analytical Limits Report 4

86 ER-0000-2486 Revision 5.pdf Safety Analysis Analytical Limits Report 5

87 ER-0000-3921_R0 Long Term Core Cooling Methodology Report.pdf Long Term Core Cooling Methodology Report 0

88 ER-0000-4316_R1 Environ Service Conditions Electrical and Mechanical Equipment Qualification.pdf Environmental Service Conditions for Electrical and Mechanical Equipment Qualifications 1

89 ER-0000-4391 0_Mass_and_Energy_Release_and_C ontainment_Vessel_Pressure_and_Te mp_Response_Method Mass and Energy Release and Containment Vessel Pressure and Temperature Response Methodology 0

90 ER-A013-3246_R0 Containment Vessel Structural Eval for Combustible Gas.pdf Containment Vessel Structural Evaluation for Combustible Gas 0

7 No.

File Document Name Rev. #

91 ER-A013-3635_R0 Containment System Failure Modes and Effects Analysis.pdf Containment System Failure Modes and Effects Analysis 0

92 ER-A013-4785 0.pdf 10 CFR 50 Appendix J Containment Leakage Testing Assessment 0

93 ER-P020-5092_Rev_0 Assessment of LRSAP for NuScale level 2 PRA.pdf Assessment of Low-Risk Severe Accident Phenomena for the NuScale Level 2 PRA 0

94 FS_B080_00000542_02_Control_Roo m_Normal_Ventilation.pdf Control Room HVAC System (CRVS)

Functional Specification 2

95 MSS SDD SD-C010-1722 0 Main Steam System Design Description.pdf Main Steam System Design Description 0

96 OP-0000-10842_R0 Module Refueling Operations.pdf NuScale Model Refueling Operations 0

97 RP-1215-19690 - concept of automation.pdf Concept of Automation A

98 SD_B090_00001680_R0_Reactor_Buil ding_HVAC_System_Design_Descripti on.pdf reactor Building HVAC System (RBVS) System Design Description 0

99 SDR-0615-15509_R4.pdf OSU NIST-1 Facility Description Report 4

100 SwUM-0304-15495 3 - NRELAP5 Version 1.3 Code Manual Appendix A -

Input Requirements.pdf NRELAP5 Version 1.3 Input Data Requirements 3

101 TR-0216-21604.pdf Superseded Document NuScale Power Containment Vessel Integrated Leak Rate Testing Options 0

102 TR-0916-51502-P.pdf NuScale Power Module Seismic Analysis 0

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