ML18180A224

Summary of the May 1, 2018, Category 1 Public Teleconference with Nuscale Power, LLC in Response to Requests for Additional Information 9002 and 9004 Related to Nuscale Standard Design Certification - 52-048 - 14.03.02

ML18180A224
Person / Time
Site:	NuScale
Issue date:	07/26/2018
From:	Omid Tabatabai NRC/NRO/DNRL/LB1
To:	Samson Lee NRC/NRO/DNRL/LB1
Tabatabai O / 415-6616
References
Download: ML18180A224 (6)

Text

July 26, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/

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

SUMMARY

OF THE MAY 1, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION 9002 AND 9004 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION SECTION 14.3.2, STRUCTURAL AND SYSTEMS ENGINEERING - INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA, QUESTIONS 30378 AND 30376 The U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public teleconference with NuScale Power, LLC (NuScale) on May 1, 2018, to discuss NuScales response to Request for Additional Information (RAI) No. 9002 and 9004, Chapter 14, Section 14.3, Structural and Systems Engineering - Inspections, Tests, Analyses, and Acceptance Criteria. Participants included personnel from NuScale and NRC.

The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18120A266. This meeting notice was also posted on the NRC public website. The meeting agenda and list of participants can be found in Enclosures 1 and 2, respectively. The technical issues discussed are included in Enclosure 3.

Enclosure:

1. Meeting Agenda

2. List of Attendees

3. Comments presented by NRC staff cc: w/encls.: DC NuScale Power LLC Listserv CONTACT: Omid Tabatabai, NRO/DLSE 301-415-6616

ML18180A224 *via email NRO-002 NRO/DLSE/LB1/PM NRO/DLSE/LB1/PM NRO/DLSE/LB1/LA NRO/DEI/SEB OFFICE OTabatabai DMurray* MBrown* SSamadar*

NAME 7/25/2018 6/12/2018 7/25/2018 7/26/2018 DATE

U.S. NUCLEAR REGULATORY COMMISSION PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION 9002 AND 9004 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION SECTION 14.3.2, STRUCTURAL AND SYSTEMS ENGINEERING - INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA May 1, 2018 1:00 p.m. - 3:00 p.m.

AGENDA Public meeting 1:00 - 1:10 pm Introductions 1:10 - 1:50 pm Discussion of Request for Additional Information (RAI) 9002 1:50 - 2:55 pm Discussion of RAI 9004 2:55 - 3:00 Public comments Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION 9002 AND 9004 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION SECTION 14.3.2, STRUCTURAL AND SYSTEMS ENGINEERING - INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA List of Attendees May 1, 2018 NAME AFFLIATION Demetrius Murray NRC Bhagwat Jain NRC Thomas Vaughn NRC Robert Roche-Rivera NRC George Wang NRC Steven Pope NuScale Steven Mirsky NuScale Nicholas Brown NuScale Josh Parker NuScale Evren Ulku NuScale Chris Maxwell NuScale Carl Dumsday NuScale Tom Ryan NuScale Marty Bryan NuScale Sarah Fields Uranium Watch (Public)

Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION

SUMMARY

OF MAY 1, 2018 TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION 9002 AND 9004 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION SECTION 14.3.2 STRUCTURAL AND SYSTEMS ENGINEERING - INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA During this teleconference, the U.S. Nuclear Regulatory Commission (NRC) staff provided the following feedback and comments concerning NuScale Power LLCs (NuScale) response to Requests for Additional Information (RAIs) Nos. 9002 and 9004:

Response to RAI 9002

1. The NRC staff finds the NuScale response to RAI with regards to the exclusion of the dimensions of the seismic Category I structure critical sections in Tier 1 unacceptable.

The NRC staff discussed, with NuScale, its expectations with respect to the Tier 1 information for critical sections as briefly summarized below. The NRC staff also confirmed NuScales attendance to previous public meetings with Korea Hydro &

Nuclear Power (KHNP) representatives concerning the staffs expectations with respect to the Tier 1 seismic analysis and structural design information, including critical sections.

2. Include a list of the critical sections in its Tier 1 application along with the design attributes such as provided area of steel per unit length or demand over capacity ratios for the critical sections.

3. Include the figures (i.e. critical sections) and their dimensions for seismic Category I structures in Tier 1.

4. Clarify design description in Design Control Document Tier 1, Section 3.11, Reactor Building, to include the reactor pool, refueling pool (RFP), and the spent fuel pool (SFP) as well since they are seismic Category I structures. Include the critical sections and their dimension if the reactor pool, RFP, and SFP contain critical sections.

5. Correct the error in the statement, ITAAC 03.14.01 verifies that the pool liner withstands design basis loads, because inspections, tests, analyses, and acceptance criteria (ITAAC) 03.14.01 is intended for the Seismic and Dynamic Qualification of Mechanical and Electrical Equipment and not for pool liner as stated.

6. Clarify the statement in the RAI response that the reactor building (RXB) does not contain the ultimate heat sink (UHS).

1 Enclosure 3

7. Include the control building (CRB) underground tunnel in the ITAAC for clarity, including the dimensions and figures.

8. Revise the first bullet in Tier 1 Table 3.13-1 under the acceptance criteria for ITAAC No.

5, The collapse of the non-seismic Category I structure will not cause the non-seismic Category I structure to strike a seismic Category I SSC, in order to be consistent with the discussion of ITAAC 3.13.05 for the CRB in Tier 2, Table 14.3.2.

Response to RAI 9004

1. Address the inconsistency in the RAI response and the final safety analysis report (FSAR) mark-up. The RAI response states, there is a truck ramp for radwaste building (RWB) only; there is no truck ramp for the CRB. Mark-up to FSAR Sections 3.4.1.4 and 3.4.2.1 state that, there is a truck ramp on the south side of the RWB and the CRB tunnel.

2. Clarify if the thickness of the exterior walls of the RXB and the CRB are inspected through the RXB and the CRB ITAACs.

Follow-up Actions:

The following actions were identified at the end of the telecom. The NRC staff from this telecom concluded that although NuScale clearly understood the staffs expectations but it resisted to include the critical section information (figures, dimension, attributes, etc.) in Tier I. NuScale committed to provide a supplemental response to RAIs 9002 and 9004. Based on its review of the supplemental response the NRC staff committed to issue a supplemental RAI.

Enclosure 2