ML19309E017

Reconciliation - NRR Response to Acrs'S September 24 2019 Letter on NuScale External Forces Topical Report

ML19309E017
Person / Time
Site:	NuScale
Issue date:	10/31/2019
From:	Renee Taylor Office of Nuclear Reactor Regulation
To:	Riccardella P Advisory Committee on Reactor Safeguards
Snodderly M
References
Download: ML19309E017 (2)

Text

From: Taylor, Robert To: Riccardella, Peter Cc: Moore, Scott; Burkhart, Larry; Snodderly, Michael; Bradford, Anna; Nieh, Ho; Caldwell, Bob; Dudek, Michael; Cranston, Greg; Bavol, Bruce

Subject:

Response to ACRS"s September 24, 2019 Letter on NuScale Topical Report TR-0716-50351 Date: Thursday, October 31, 2019 8:36:28 AM

Dear Chairman Riccardella,

In your letter dated September 24, 2019 (ML19268A109), the ACRS reported on the Committees review of the NRC staffs safety evaluation of the NuScale topical report TR 0716 50351, Revision 0, NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces.

Your letter contained the following two conclusions and recommendations:

1. The fuel assembly structural response methodology described in TR-0716-50351 is acceptable for use in performing NuScale fuel system structural response analyses. The associated safety evaluation report should be issued.

2. The modifications to the approved ANP-10337P-A methodology will ensure that the seismic analysis of the NuScale fuel will be in conformance with General Design Criterion 2; 10 CFR Part 50, Appendix S; and related staff guidance.

The NRC staff appreciates the ACRSs review and recommendation and plans to issue the approved version of the topical report by mid-January 2020. Additionally, the staff has concluded that the AREVA fuel assembly structural response methodology described in TR-0716-50351 can be used, with the stated modifications, to perform NuScale fuel system structural response analyses in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix A, General Design Criteria for Nuclear Power Plants, General Design Criterion 2, Design Bases for Protection Against National Phenomena, and 10 CFR Part 50, Appendix S, Earthquake Engineering Criteria for Nuclear Power Plants, for fuel assembly structural responses to external forces.

The NRC staff also appreciates the time and effort the ACRS has devoted to this important subject, as reflected in meetings held with the ACRS Subcommittee for NuScale on August 20, 2019 and the ACRS Full Committee on September 4-7, 2019, and looks forward to future interactions with the Committee as part of its NuScale review activities.

Best regards, Rob Robert M. Taylor Deputy Director for New Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (office) 301-415-1270