ML18208A298

Summary of Public Teleconference with Nuscale to Discuss Responses to Rais Associated with the Nuscale Design Certification Application

ML18208A298
Person / Time
Site:	NuScale
Issue date:	08/01/2018
From:	Getachew Tesfaye NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Tesfaye G / 415-8013
References
Download: ML18208A298 (6)

Text

August 1, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Getachew Tesfaye, Senior Project Manager /RA/

Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors

SUMMARY

OF THE JULY 3, 2018, CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on July 3, 2018, to discuss responses to the NRC staff requests for additional information associated with the NuScale Power, LLC (NuScale) design certification application. Participants included personnel from NuScale and a member of the general public.

The public meeting notice dated July 3, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18183A003. This meeting notice was also posted on the NRC public website.

Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosure 2), and overview (Enclosure 3).

Docket No.52-048

Enclosures:

1. Meeting Agenda

2. List of Attendees

3. Meeting Overview cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Getachew Tesfaye NRO/DLSE 301-415-8013

ML18208A298 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DLSE/RPAC DLSE/LB1:PM NAME GTesfaye MMoore RLavera* GTesfaye (signed)

DATE 07/27/2018 07/30/2018 07/31/2018 08/01/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA July 3, 2018 2:30 - 2:35 PM Introductions and Identification of topics 2:35 - 3:50 PM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Responses to Requests for Additional Information 9266 and 9263.

3:50 - 4:00 PM Public Comments/Questions 4:00 PM Meeting Closure Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES July 3, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC)

Ronald LaVera NRC Michael Dudek NRC Sean Meighan NRC Carrie Fosaaen NuScale Power, LLC (NuScale)

Jim Osborn NuScale Karl Gross NuScale Scott Harris NuScale Mark Shaver NuScale Jim Osborn NuScale Sara Fields Member of the public Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE JULY 3, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power LLCs (NuScale) Responses to Requests for Additional Information (RAI) 9266 and 9263.

The following is the summary of NRC staff feedback and agreed upon next steps for the resolution of the remaining issues.

1. RAI No. 9266, Questions 12.02-12 and 12.02-13, Reactor Buliding airborne tritium:

a. NRC Feedback: In RAI 9266, dated January 8, 2018, the NRC staff identified that NuScale Design Control Document (DCD) Tier 2 Revision 0, Subsections 12.2.2.1, Reactor Building Atmosphere, 9.4.2, Reactor Building and Spent Fuel Pool Area Ventilation System, and the supporting information do not contain the information necessary for the staff to perform their evaluation of airborne activity in the Reactor Building.

• In NuScales response it is stated,

[t]he calculated airborne activity in the airspace above the reactor pool water is based on an evaporation rate from the reactor pool while the pool water temperature is at the design basis temperature for the Reactor Building heating Heating, ventilation, and air conditioning (HVAC) Reactor Building ventilation system (RBVS), which is 100°F.

The technical specification limit for the pool water temperature is 140 degrees Fahrenheit (F). The NRC staff would like to understand the reason for the use of 100°F versus 140°F for pool temperature.

• The calculated RVBS air velocity over the pool is 30 feet per minute (ft/min).

The NRC would request an understanding of the design features provided for maintaining the required air flow rate over the pool.

• Please provide rational for the use of the following values in equation provided in response to this RAI.

pw = saturation vapor pressure of water (@ 100 F) = 1.93 in Hg (0.949 in wg).

pa = saturation pressure at room air dew point = 0.547 in Hg (0.27 in wg).

1 Enclosure 3

V = air velocity over water surface = 30 ft/min.

• Can NuScale provide the airborne equilibrium value for tritium with technical specification bounding conditions for pool temperature and air RXB air temperature?

b. Next Step: NuScale understood the NRC staffs question and agreed to provide supplemental response to RAI 9266 with Final Safety Analysis Report (FSAR) mark up.

2. RAI No. 9263, Question 12.02-06, Low Reactor Coolant System (RCS) flow rate:

a. NRC Staff Feedback: In RAI 9263 dated January 8, 2018, the NRC staff looked to understand how the DCD addresses the potential radiological impacts during crud burst of low flow RCS.

• Provide information on how the application factored in and addressed the aspects of design as it related to mitigation of larger than expected crud bursts due to low flow RCS.

• Address any impacts to Table 12.2-33, Reactor Building Airborne Concentrations, as a result of potential increase in radionuclide in the pool water.

• Address how NuScale intends to ensure adequate mixing during peak crud burst to ensure representative RCS sample is obtained to calculate dose rate from the pool.

• Address potential need to update DCD section 12.2 to include adjustment factors for lack of forced flow RCS mixing.

b. Next Step: After some discussion, the NRC staff agreed to reevaluate the response and engage NuScale at a later date if needed.

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