ML18219D571

SMR DC RAI - Request for Additional Information No. 431 Erai No. 9412 (14.3.9)

ML18219D571
Person / Time
Site:	NuScale
Issue date:	08/07/2018
From:	NRC
To:	NRC/NRO/DLSE/LB1
References
Download: ML18219D571 (3)

Text

NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Tuesday, August 7, 2018 4:49 PM To: NuScaleDCRaisPEm Resource

Subject:

Request for Additional Information No. 431 eRAI No. 9412 (14.3.9)

Attachments: Request for Additional Information No. 431 (eRAI No. 9412).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application.

Please submit your technically correct and complete response within 60 days of the date of this RAI to the NRC Document Control Desk.

If you have any questions, please contact me.

Thank you.

Gregory Cranston, Senior Project Manager Licensing Branch 1 (NuScale)

Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-0546 1

Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 532 Mail Envelope Properties (BN1PR09MB025815BE092C8409E6F176EF90270)

Subject:

Request for Additional Information No. 431 eRAI No. 9412 (14.3.9)

Sent Date: 8/7/2018 4:48:45 PM Received Date: 8/7/2018 4:48:49 PM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:

"NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>

Tracking Status: None Post Office: BN1PR09MB0258.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 561 8/7/2018 4:48:49 PM Request for Additional Information No. 431 (eRAI No. 9412).pdf 108246 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Request for Additional Information No. 431 (eRAI No. 9412)

Issue Date: 04/23/2018 Application

Title:

NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 14.03.09 - Human Factors Engineering - Inspections, Tests, Analyses, and Acceptance Criteria Application Section: 14..9 QUESTIONS 14.03.09-4 10 CFR 52.47(a)(2) requires that a standard design certification application include a final safety analysis report (FSAR) that describes the design of the facility including the principal design criteria for the facility, for which NuScale used the 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants." General Design Criterion (GDC) 19 requires, in part, that equipment is provided at appropriate locations outside the control room (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.

NuScale DCD Tier 2, Section 1.2.2.1, Main Control Room, states that in the event that the Main Control Room (MCR) becomes uninhabitable, a remote shutdown station in the Reactor Building provides a secondary location for safe shutdown of the reactors.

10 CFR 52.47(b)(1) requires a design certification application to contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and should operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations.

The letter from the NRC to NuScale dated April 8, 2016 (ML16096A121), contained a set of draft standard ITAAC that could be used in the NuScale Design Certification Application. Standard ITAAC No.

I-22 pertains to the Main Control Room (MCR) and Remote Shutdown Station (RSS) displays and alarms

for various systems. Standard ITAAC No. I-23 pertains to plant system controls at the operator

workstation in the MCR and RSS. The standard ITAAC do not specify which displays, alarms, and

controls that should be verified by ITAAC No. I-22 and I-23.

NuScale DCD Tier 1, Table 2.5-7, Module Protection System and Safety Display and Indication System ITAAC, identifies the displays, alarms, and controls that NuScale has selected to be verified by ITAAC. The staff would like to understand the basis for selecting ITAAC to verify the displays, alarms and controls listed in DCD Tier 1, Table 2.5-7, and why there are no ITAAC to verify any displays, controls or alarms in the RSS.

Please explain the basis for selecting ITAAC to verify the displays, alarms, and controls listed in DCD Tier 1, Table 2.5-7, and also why the ITAAC does not verify any displays, controls and alarms at the RSS.