ML18113A641

LLC Response to NRC Request for Additional Information No. 382 (Erai No. 9402) on the NuScale Design Certification Application

ML18113A641
Person / Time
Site:	NuScale
Issue date:	04/23/2018
From:	Rad Z NuScale
To:	Document Control Desk, Office of New Reactors
References
RAIO-0418-59635
Download: ML18113A641 (7)

Text

RAIO-0418-59635 April 23, 2018 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 Response to NRC Request for Additional Information No.

382 (eRAI No. 9402) on the NuScale Design Certification Application

REFERENCE:

U.S. Nuclear Regulatory Commission, "Request for Additional Information No.

382 (eRAI No. 9402)," dated March 12, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 9402:

18-20 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.

If you have any questions on this response, please contact Steven Mirsky at 240-833-3001 or at smirsky@nuscalepower.com.

Sincerely, Z ckary W. Rad Za Zackary Director Regulatory Affairs

Director, NuScale Power, LLC Distribution: Samuel Lee, NRC, OWFN-8G9A Prosanta Chowdhury NRC, OWFN-8G9A Demetrius Murray, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 9402 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0418-59635 :

NuScale Response to NRC Request for Additional Information eRAI No. 9402 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

Response to Request for Additional Information Docket No.52-048 eRAI No.: 9402 Date of RAI Issue: 03/12/2018 NRC Question No.: 18-20 Title 10 of the Code of Federal Regulations (10 CFR) Section 52.47(a)(8) requires an applicant for a design certification to provide a final safety analysis report (FSAR) that must include the information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10 CFR 50.34(f), except paragraphs (f)(1)(xii),

(f)(2)(ix), and (f)(3)(v). Section 10 CFR 50.34(f)(2)(iii) requires an applicant to "Provide, for Commission review, a control room design that reflects state-of-the-art human factor principles prior to committing to fabrication or revision of fabricated control room panels and layouts.

Chapter 18, Human Factors Engineering, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, and NUREG-0711, "Human Factors Engineering Program Review Model, identify criteria the staff uses to evaluate whether an applicant meets the regulation. The FSAR, Tier 2, Section 18.0, "Human Factors Engineering - Overview," indicates that the HFE program incorporates the applicable guidance provided in NUREG-0711, Revision 3.

Chapter 18, Human Factors Engineering, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, lists NUREG-0711, "Human Factors Engineering Program Review Model, and NUREG-0700, Human-System Interface Design Review Guidelines, as the sources of acceptance criteria the staff uses to evaluate whether an applicant meets the regulation.

NUREG-0711, Section 8.4.4.6(1), states that, The applicant should describe the basis for deciding which HSIs will be included in the MCR design, and which will be provided locally.

The staff reviewed the application and could not find where NuScale addressed this criterion.

Describe the basis NuScale used for deciding which HSIs to include in the MCR and which to provide locally or why this criterion does not apply to the NuScale design.

NuScale Response:

NuScale used the following process as a basis for determining which human-system interface NuScale Nonproprietary

(HSI) to include in the main control room (MCR) and which HSIs to provide locally. Those systems having a control room interface provided the starting point for associating systems to the functional requirements identified in the functional requirements analysis/ functional analysis phase. The components in these systems were associated with specific tasks identified in the Task Analysis phase. Plant operations subject matter experts (SMEs) followed the methodology discussed in the Human Factors Engineering Task Analysis Result Summary Report (RP-0316-17616) when deciding which HSIs to include in the MCR and which to provide locally.

Those systems determined to be operated locally were not included in further HFE evaluations unless subsequent HFE program phases identified a need for their inclusion. The current engineering results are shown in the Tables 1 and 2 below entitled "List of plant systems simulated" and "List of plant systems not simulated," respectively. These results will be further confirmed during integrated systems validation testing.

Table 1 List of plant systems simulated System Code System Title AB Auxiliary Boiler System BAS Boric Acid System BPSS Backup Power Supply System CAR Condenser Air Removal System CE Containment Evacuation System CFD Containment Flooding and Drain System CHW Chilled Water CPS Condensate Polisher Resin Regeneration System CRDS Control Rod Drive System CRH Control Room Habitability System CRV Normal Control Room HVAC System CNT Containment System CRA Control Rod Assembly CVC Chemical and Volume Control System CW Circulating Water System DHR Decay Heat Removal System DW Demineralized Water System ECC Emergency Core Cooling System EDNS Normal DC Power System EDS Highly Reliable DC Power System EHV 13.8 KV and Switchyard ELV Low Voltage AC Electrical Distribution System EMV Medium Voltage AC Electrical Distribution System FD Fire Detection System FP Fire Protection System FW Condensate and Feedwater System GRW Gaseous Radioactive Waste Management System HVD Heater Vents and Drain System NuScale Nonproprietary

System Code System Title IA Instrument and Control Air System ICI In-core Instrumentation System LRW Liquid Radioactive Waste Management System MCS Module Control System MEM Meteorological and Environmental Monitoring System MHS Module Heatup System MPS Module Protection System MS Main Steam System NDS Nitrogen Distribution System NMS Neutron Monitoring System PCS Plant Control System PCU Pool Cleanup System PLD Pool Leakage Detection Systems PPS Plant Protection System PSC Pool Surge Control System PZR Pressurizer RBV Reactor Building HVAC System RCS Reactor Coolant System RCCW Reactor Component Cooling Water System RM Fixed Area Radiation Monitoring System RPC Reactor Pool Cooling System RPV Reactor Pressure Vessel RXC Reactor Core System RXF Reactor Fuel Assembly RXM Reactor Module RXS Reactor System SA Service Air System SCW Site Cooling Water SDI Safety Display and Indication SG Steam Generator System SM Seismic Monitoring System SFPC Spent Fuel Pool Cooling System TG Turbine Generator System UHS Ultimate Heat Sink Table 2 List of plant systems not simulated System System Title Reason Code ABV Annex Building HVAC No control room interface BPD BOP Drains System No control room interface NuScale Nonproprietary

System System Title Reason Code The simulator does not model the EFS networking scheme but does provide similar functions for communication COM Communication Systems systems. The simulator mimics the plant communication systems with a Private Branch Exchange PBX phone system for the Training Center.

CP Cathodic Protection System No control room interface DGBV Diesel Generator Building HVAC No control room interface Grounding and Lightning Protection GLP No control room interface System CP Cathodic Protection System No control room interface FHE Fuel Handling Equipment No control room interface FWT Feedwater Treatment No control room interface System is designated but currently HPN Health Physics Network undefined MAE Module Assembly Equipment No control room interface Module Assembly Equipment -

MAEB No control room interface Bolting NFS New Fuel Storage System No control room interface NSA Neutron Source Assembly No control room interface PL Plant Lighting System No control room interface Not required for control room task PVM Plant-wide Video Monitoring System performance PSS Process Sampling System No control room interface PW Potable Water System No control room interface RBSS Reactor Building Spray System No control room interface RVI Reactor Vessel Internals No control room interface Radioactive Waste Building RWBV No control room interface Ventilation RWD Radioactive Waste Drain System No control room interface Radioactive Waste Management RWM No control room interface System SBV Security Building HVAC No control room interface SDS Site Drainage System No control room interface SEC Plant Security System No control room interface SFS Spent Fuel Storage System No control room interface Solid Radioactive Waste SRW No control room interface Management System SP Security Power System No control room interface TBV Turbine Building Ventilation No control room interface TLOS Turbine Lube Oil Storage System No control room interface UW Utility Water System No control room interface NuScale Nonproprietary

Impact on DCA:

There are no impacts to the DCA as a result of this response.

NuScale Nonproprietary