ML19114A552

LLC Submittal of Changes to Final Safety Analysis Report, Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria.

ML19114A552
Person / Time
Site:	NuScale
Issue date:	04/24/2019
From:	Melton M NuScale
To:	Document Control Desk, Office of New Reactors
References
LO-0419-65256
Download: ML19114A552 (3)

Text

LO-0419-65256 April 24, 2019 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Submittal of Changes to Final Safety Analysis Report, Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria

REFERENCES:

Letter from NuScale Power, LLC to Nuclear Regulatory Commission, NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 2, dated October 30, 2018 (ML18311A006)

During a public teleconference with NRC Staff, NuScale Power, LLC (NuScale) discussed a potential update to Final Safety Analysis Report (FSAR), Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria. As a result of this discussion, NuScale changed Section 14.3. The Enclosure to this letter provides a mark-up of the FSAR page incorporating revisions to Section 14.3, in redline/strikeout format. NuScale will include this change as part of a future revision to the NuScale Design Certification Application.

This letter makes no regulatory commitments or revisions to any existing regulatory commitments.

If you have any questions, please feel free to contact Carrie Fosaaen at 541-452-7126 or at cfosaaen@nuscalepower.com.

Sincerely, Michael Melton Manager, Licensing NuScale Power, LLC Distribution: Samuel Lee, NRC, OWFN-8H12 Gregory Cranston, NRC, OWFN-8H12 Cayetano Santos, NRC, OWFN-8H12 : Changes to NuScale Final Safety Analysis Report, Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

LO-0419-65256 :

Changes to NuScale Final Safety Analysis Report, Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

Table 14.3-2: Shared/Common Structures, Systems, and Components and Non-Structures, Systems, and components Based Tier 2 NuScale Final Safety Analysis Report Design Features and Inspections, Tests, Analyses, and Acceptance Criteria Cross Reference(1) (Continued)

ITAAC No. System Discussion DBA Internal/External Radiological PRA & Severe FP Hazard Accident 03.16.01 SEC Section 13.6 discusses that the physical security system design provides the capabilities to detect, assess, impede, and delay threats up to and including the design basis threat, and to provide for defense-in-depth through the integration of systems, technologies, and equipment. Technical Report TR-0416-48929, "NuScale Design of Physical Security Systems," provides safeguards and security-related information that describes security design bases and requirements for security SSC. Vital equipment and vital area are discussed in the report.

An ITAAC inspection is performed of the as built vital equipment to verify that the equipment is located in a vital area.

03.16.02 SEC Section 13.6 discusses that the physical security system design provides the capabilities to detect, assess, impede, and delay threats up to and including the design basis threat, and to provide for 14.3-91 defense-in-depth through the integration of systems, technologies, and equipment. Technical Report TR-0416-48929, "NuScale Design of Certified Design Material and Inspections, Tests, Analyses, and Physical Security Systems," provides safeguards and security-related information that describes security design bases and requirements for security SSC. Provisions for accessing vital equipment are discussed in the report.

An ITAAC inspection is performed of the as built vital equipment location to verify that access to vital equipment, within the nuclear island and structures, requires passage through at least two physical barriers., or as otherwise identified in Technical Report TR-0416-48929, "NuScale Design of Physical Security Systems."

Acceptance Criteria Draft Revision 3