ML23292A360

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NPM-20 - NuScale SDAA Section 9A.5 - Request for Additional Information No. 007 (RAI-10102-R1)
ML23292A360
Person / Time
Site: 99902078
Issue date: 10/19/2023
From:
NRC
To:
NRC/NRR/DNRL/NRLB
References
Download: ML23292A360 (4)


Text

From:

Getachew Tesfaye Sent:

Thursday, October 19, 2023 5:11 PM To:

Request for Additional Information Cc:

Taylor Lamb (She/Her); Mahmoud Jardaneh; Griffith, Thomas; Osborn, Jim; NuScale-SDA-720RAIsPEm Resource

Subject:

NuScale SDAA Section 9A.5 - Request for Additional Information No. 007 (RAI-10102-R1)

Attachments:

SECTION 9A.5 - RAI-10102-R1-FINAL.pdf Attached please find NRC staffs request for additional information (RAI) concerning the review of NuScale Standard Design Approval Application for its US460 standard plant design (Agencywide Documents Access and Management System (ADAMS) Accession No. ML222339A066).

Please submit your technically correct and complete response by the agreed upon date to the NRC Document Control Desk.

If you have any questions, please do not hesitate to contact me.

Thank you, Getachew Tesfaye (He/Him)

Senior Project Manager NRC/NRR/DNRL/NRLB 301-415-8013

Hearing Identifier:

NuScale_SDA720_RAI_Public Email Number:

15 Mail Envelope Properties (BY5PR09MB5682F3F74610D529A96212458CD4A)

Subject:

NuScale SDAA Section 9A.5 - Request for Additional Information No. 007 (RAI-10102-R1)

Sent Date:

10/19/2023 5:11:16 PM Received Date:

10/19/2023 5:11:20 PM From:

Getachew Tesfaye Created By:

Getachew.Tesfaye@nrc.gov Recipients:

"Taylor Lamb (She/Her)" <Taylor.Lamb@nrc.gov>

Tracking Status: None "Mahmoud Jardaneh" <Mahmoud.Jardaneh@nrc.gov>

Tracking Status: None "Griffith, Thomas" <tgriffith@nuscalepower.com>

Tracking Status: None "Osborn, Jim" <josborn@nuscalepower.com>

Tracking Status: None "NuScale-SDA-720RAIsPEm Resource"

<NuScale-SDA-720RAIsPEm.Resource@usnrc.onmicrosoft.com>

Tracking Status: None "Request for Additional Information" <RAI@nuscalepower.com>

Tracking Status: None Post Office:

BY5PR09MB5682.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 585 10/19/2023 5:11:20 PM SECTION 9A.5 - RAI-10102-R1-FINAL.pdf 140850 Options Priority:

Normal Return Notification:

No Reply Requested:

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1 REQUEST FOR ADDITIONAL INFORMATION No. 007 (RAI-10102-R1)

BY THE OFFICE OF NUCLEAR REACTOR REGULATION NUSCALE STANDARD DESIGN APPROVAL APPLICATION DOCKET NO. 05200050 CHAPTER 9, AUXILIARY SYSTEMS SECTION 9A.5, FIRE HAZARDS ANALYSIS ISSUE DATE: 10/19/2023

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Background===

By letter dated December 15, 2022, NuScale Power, LLC (NuScale or the applicant),

submitted Part 2, Final Safety Analysis Report, (FSAR), Chapter 9, Auxiliary Systems, Revision 0 (Agencywide Documents Access and Management System Accession No. ML22364A281) of the NuScale Standard Design Approval Application (SDAA) for its US460 standard plant design. The applicant submitted the US460 plant SDAA in accordance with the requirements of Title 10 Code of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, Subpart E, Standard Design Approvals. The NRC staff has reviewed the information on the fire protection program provided in the FSAR and determined that additional information is required to complete its review.

Question 9A.5-1 REGULATORY BASIS 10 CFR 50.48, Fire protection, requires each operating nuclear power plant to have a fire protection plan that satisfies General Design Criterion 3, Fire protection, in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50. 10 CFR 50.48 require that the licensees to provide a fire protection plan to address, in part, the means to limit fire damage to structures, systems, or components important to safety so that the capability to shut down the plant safely is ensured.

Fire protection program guidance is provided in Regulatory Guide (RG) 1.189, Fire Protection for Nuclear Power Plants, Revision 4 to satisfy 10 CFR 50.48 and Criterion 3 of Appendix A to 10 CFR Part 50.

RG 1.189, Revision 4, Section 1.2, Fire Hazards Analysis, states, in part, A fire hazards analysis should be performed to demonstrate that the plant will maintain the ability to perform safe-shutdown functions.

ISSUE In reviewing the NuScale SDAA Appendix A, Section 9A.5, Fire Hazards Analysis (FHA), and Section 9A.6, Fire Safe Shutdown Plan, the staff identified inadequacies in the area-by-area safe shutdown analysis as the FHA and the Fire Safe Shutdown Plan collectively do not provide a complete description of the post-fire safe shutdown capability for each fire area. The staff is requesting this information to ensure that the applicants fire protection program meets the regulatory requirements of 10 CFR 50.48 and Criterion 3 of Appendix A to 10 CFR Part 50.

2 INFORMATION REQUESTED NuScale is requested to fully describe the safe shutdown functions and/or equipment and cables required for safe shutdown that are present in each fire area, if any, and clarify the plant fire protection design features and/or mitigation measures credited to ensure post-fire safe shutdown capability is maintained for each fire area of the plant in the FSAR.