ML18067A520

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LLC - Supplemental Response to NRC Request for Additional Information No. 200 (Erai No. 9021) on the NuScale Design Certification Application
ML18067A520
Person / Time
Site: NuScale
Issue date: 03/08/2018
From: Wike J
NuScale
To:
Document Control Desk, Office of New Reactors
References
RAIO-0318-59022
Download: ML18067A520 (4)


Text

RAIO-0318-59022 March 08, 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 Supplemental Response to NRC Request for Additional Information No. 200 (eRAI No. 9021) on the NuScale Design Certification Application

REFERENCES:

1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 200 (eRAI No. 9021)," dated August 25, 2017
2. NuScale Power, LLC Response to NRC "Request for Additional Information No. 200 (eRAI No.9021)," dated October 23, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) supplemental

response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's supplemental response to the following RAI

Question from NRC eRAI No. 9021:

v 03.09.03-5 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 Marty Bryan at 541-452-7172 or at

mbryan@nuscalepower.com.

Sincerely, Jenniei Wike Wik Manager, Licensing NuScale Power, LLC Distribution: Omid Tabatabai, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Prosanta Chowdhury NRC, OWFN-8G9A : NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 9021 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0318-59022 :

NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 9021 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.: 9021 Date of RAI Issue: 08/25/2017 NRC Question No.: 03.09.03-5 As part of the staffs evaluation of the applicants compliance with the requirements of GDCs 1,

2, 4, 14, and 15; 10 CFR 50.55a; and 10 CFR Part 50, Appendix S, this section evaluates

component supports the ASME Code Class 1, 2, and 3 component and core support structures.

In DCD Tier 2 Section 3.9.3.1.2, the applicant states that piping supports are designed in

accordance with ASME BPVC Section III, Subsection NF. The core support structures are

design to ASME BPVC Section III Subsection NG. The applicant also stated that the SG tubes

supports are internal supports and, therefore, are also designed using Subsection NG. The

applicant is requested to discuss the effects of the friction and wearing between the tubes and

tag supports when the tubes are subject to the fluid induced vibration from the vertical cross

flow for 60 years of plant life.

NuScale Response:

The initial response to this RAI 9021, Question 03.09.03-5 was provided by NuScale letter RAIO-1017-56765, dated October 23, 2017. The following supplements that response with additional discussion of the methodology used to calculate steam generator (SG) tube fretting wear.

The predicted SG tube wear value and acceptance criterion are provided in FSAR Section 5.4.1.3.

The Connors method for fretting wear is used to determine this value, as the geometry of the SG tube within the support can be approximated by a tube in a circular support hole. A zero-to-peak root mean square (RMS) vibration for sinusoidal whirling of the tube is used (per pages 343 and 361 of Au-Yang, M.K., Flow-Induced Vibration of Power and Process Plant Components, ASME Press, New York, NY, 2001). This approximation is equal to square root of two times the calculated RMS vibration value.

While design analysis is performed to estimate wear, these estimates are predictive in nature NuScale Nonproprietary

and actual wear performance is monitored over the life of the SG design in accordance with NEI 97-06, Revision 3, "Steam Generator Program Guidelines." NuScale SG inspection requirements are provided in Section 5.5.4 of the Technical Specifications, "Steam Generator (SG) Program." Additional information related to periodic SG tube inspections is provided in FSAR Section 5.4.1.4.

Impact on DCA:

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

NuScale Nonproprietary