ML20036D336

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LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 4
ML20036D336
Person / Time
Site: NuScale
Issue date: 01/16/2020
From: Bergman T
NuScale
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LO-0120-68358
Download: ML20036D336 (3)


Text

L0-0120-68358 January 16, 2020 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 Submittal of the NuScale Standard Plant Design Certification Application , Revision 4

REFERENCES:

1. Letter from NuScale Power, LLC to U.S. Nuclear Regulatory Commission , "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application (NRC Project No.

0769) ," dated December 31 , 2016 (ML17013A229)

2. Letter from NuScale Power, LLC to U.S. Nuclear Regulatory Commission , "Nu Scale Power, LLC Submittal of the Nu Scale Standard Plant Design Certification Application , Revision 1," dated March 15, 2018 (ML18086A090)
3. Letter from NuScale Power, LLC to U.S. Nuclear Regulatory Commission , "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application , Revision 2," dated October 30 , 2018 (ML18311A006)
4. Letter from NuScale Power, LLC to U.S. Nuclear Regulatory Commission, "Nu Scale Power, LLC Submittal of the Nu Scale Standard Plant Design Certification Application , Revision 3," dated August 22 , 2019 (ML19241A315)
5. Letter from NuScale Power, LLC to U.S. Nuclear Regulatory Commission , "NuScale Power, LLC Submittal of the Accepted Version of NuScale Licensing Topical Report Titled 'NuScale Topical Report:

Quality Assurance Program Description for the NuScale Power Plant,'

NP-TR-1010-859-NP-A, Revision 4," dated January 13, 2020 (ML20013F566)

NuScale Power, LLC (NuScale) is pleased to submit to the U.S. Nuclear Regulatory Commission (NRC) Revision 4 of the NuScale Standard Plant Design Certification Application (DCA) in accordance with the requirements of 10 CFR 52 , Subpart B, Standard Design Certifications. NuScale requests NRC review, approval , and granting of standard design certification for the NuScale Standard Plant Design .

Revision 4 of the NuScale DCA includes the following parts:

Part 1, "General and Financial Information" - Part 1 provides general and financial information in accordance with the requirements of 10 CFR 52.46 and pursuant to 10 CFR 50.33 (a) through (c) and U) .

NuScale Power, LLC 1100 NE Circle Blvd ., Suite 200 Corvallis, Oregon 97330 Office 541 .360-0500 Fax 541.207 .3928 www.nuscalepower.com

L0-0120-68358 Page 2 of 3 01/16/2020 Part 2, Tier 1 and 2, "Final Safety Analysis Report" - Part 2, Tier 1 and 2 provide the NuScale Final Safety Analysis Report in accordance with 10 CFR 52.47(a).

Part 3, "Applicant's Environmental Report - Standard Design Certification" - Part 3 provides the NuScale Environmental Report in accordance with 10 CFR 52.47(b)(2) as required by 10 CFR 51.55 .

Part 4, Technical Specifications" - Part 4 provides the NuScale Technical Specifications and Bases in accordance with 10 CFR 52.47(a)(11 ); the Technical Specifications and Bases are referenced in Part 2, Tier 2, Chapter 16.

Part 5, "Emergency Plans" - Emergency plans are not applicable to design certification applications and , therefore , not provided in this application .

Part 6, "Security Plans" - Security plans are not applicable to design certification applications and , therefore , are not provided in this application .

Part 7, "Exemptions" - Part 7 provides exemption requests necessary to accommodate the unique safety features of the NuScale Power Plant.

Part 8, "Licensing Conditions; Inspections, Tests , Analyses & Acceptance Criteria" (ITAAC) have been developed in accordance with 10 CFR 52.47(b)(1) . The ITAAC are located in Chapters 2 and 3 of Part 2, Tier 1 and are based on information found in Part 2, Tier 2. The description of the process used to develop the ITAAC is provided in Part 2, Tier 2, Final Safety Analysis (FSAR) Section 14.3. Licensing conditions are not applicable to the design certification applications.

Part 9, "Withheld Information" - Part 9 identifies the location of security-related information within the FSAR that is to be withheld from public disclosure in accordance with 10 CFR 2.390 .

Part 10, "Quality Assurance Program Description" - In accordance with 10 CFR 52.47(a)(19) ,

Nu Scale Topical Report NP-TR-1010-859-NP-A, Revision 4 , is referenced in Part 2, Tier 25 ,

Section 17.5.

The DCA Revision 4 is being submitted electronically as Enclosures 1 and 2 on two digital versatile discs (DVDs).

  • Enclosure 1 (DVD 1) includes certain information, designated in accordance with NRG guidance as sensitive unclassified nonsafeguards information (SUNSI) and referred to as security-related information (SRI) , that is to be withheld from public disclosure under 10 CFR 2.390.
  • Enclosure 2 (DVD 2) omits the SUNSI/SRI mentioned above and is suitable for public disclosure.

L0-01 20-68358 Page 3 of 3 01/16/2020 Please contact Thomas A. Bergman , Vice President, Regulatory Affairs at 541-360-0740 if you have any questions.

This letter makes no regulatory commitments and no revisions to any existing regulatory commitments.

Sincerely, Thomas A. Ber Vice President , lat NuScale Power, LLC Enclosure 1: DVD 1, NuScale Standard Plant Design Certification Application Revision 4 ,

Non-Public Version-Withhold under 10 CFR 2.390 Enclosure 2: DVD 2, NuScale Standard Plant Design Certification Application Revision 4, Public Version-NuScale Nonproprietary NuScale Power, LLC 1100 NE Circle Blvd. , Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541 .207.3928 www .nuscalepower.com