ML25091A128
| ML25091A128 | |
| Person / Time | |
|---|---|
| Issue date: | 04/02/2025 |
| From: | Matthew Sunseri Advisory Committee on Reactor Safeguards |
| To: | Walter Kirchner Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML25091A128 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 April 2, 2025 MEMORANDUM TO:
Walter L. Kirchner, Chairman NuScale Subcommittee Advisory Committee on Reactor Safeguards FROM:
Matthew Sunseri, Member NuScale Subcommittee Advisory Committee on Reactor Safeguards
SUBJECT:
INPUT FOR ACRS REVIEW OF THE NUSCALE STANDARD DESIGN APPROVAL APPLICATION - SAFETY EVALUATION REPORT FOR CHAPTER 14, INITIAL TEST PROGRAM AND INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA In response to the Subcommittees request, I have reviewed the NRC staffs safety evaluation report (SER) provided to support ACRS review of the standard design approval application (SDAA), and the associated section of the applicants submittal for Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria. The following is my recommended course of action concerning further review of this chapter and the staffs associated safety evaluation.
SER Summary Chapter 14 describes the Initial Test Program comprised of preoperational tests, initial fuel loading, initial criticality, low-power tests, and power-ascension tests. The verification programs ensure that the as-built facility configuration and operation comply with the approved plant design and applicable regulations. Preoperational testing is conducted for each NuScale Power Module (NPM) following completion of construction testing but before fuel load. Completion of preoperational testing for each NPM is necessary to ensure the NPM is ready for fuel loading and startup testing. The staffs review was thorough, and their assessment found that the NuScale design and associated combined license items met regulatory criteria.
Discussion NuScale is exempt from the requirements of General Design Criterion 52 to provide a design that allows pre-operational and period integrated containment leakage testing. Staff SER Section 14.3.11, Containment SystemsInspections, Tests, Analyses, and Acceptance Criteria, discusses Combined License (COL) Item 6.2-1, which states that an applicant that references the NuScale Power Plant US460 standard design approval will verify that the final design of the containment vessel meets the design-basis requirement to maintain flange contact pressure at accident temperature, concurrent with peak accident pressure. The Committee will
W.
want to follow up on the exemption from General Design Criterion 52 and the bases for this COL item during the Chapter 6 review.
Table 14.2-65: Test # 65 Steam Generator (SG) Flow-Induced Vibration - The test references the Comprehensive Vibration Assessment Program (CVAP) technical reports referred to in Section 3.9.2, Dynamic Testing and Analysis of Systems, Components and Equipment. The SG flow-induced vibration testing is performed consistent with the requirements of the NuScale CVAP as described in the NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-121353-P, and the NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-121354-P. The SG tube testing consists of in-air and in-water modal testing and primary side flow testing. The SGs are discussed in Section 5.4.1. We will want to follow up on this topic during our review of Chapter
- 5.
I did not identify any specific deficiencies or concerns in my review. The application was well documented, and the staffs evaluation thorough.
Recommendation As lead reviewer for NuScale Chapter 14, I recommend that the Committee not perform any additional review of this chapter.
Follow up is needed during Chapter 5 and 6 reviews as noted above.
This memo does not cover portions of this chapter dealing with density-wave oscillations in Dynamic Testing and Analysis of Systems, Components, and Equipment (3.9.2), Seismic Design (3.7) or Design of Category I Structures (3.8). References to Chapter 3 in this memo carry this caveat throughout.
References
- 1. U. S. Nuclear Regulatory Commission, Safety Evaluation of NuScale SDAA Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, October 31, 2024 (ADAMS Accession No. ML24254A463).
- 2. NuScale Power, LLC, Standard Design Approval Application, Part 2, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, Revision 1, October 31, 2023 (ADAMS Accession No. ML23304A364).
- 3. NuScale Power, LLC, Summary of Significant Changes to NuScale Standard Design Approval Application for Chapters 3, 8, and 14, October 28, 2024 (ADAMS Accession No. ML24302A030).
W.
April 2, 2025
SUBJECT:
INPUT FOR ACRS REVIEW OF THE NUSCALE STANDARD DESIGN APPROVAL APPLICATION - SAFETY EVALUATION REPORT FOR CHAPTER 14, INITIAL TEST PROGRAM AND INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA Package Accession No: ML25091A091 Accession No: ML25091A128 Publicly Available (Y/N): Y Sensitive (Y/N): N If Sensitive, which category?
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NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI Review ACRS ACRS NAME MSnodderly MSnodderly LBurkhart MSunseri DATE 3/31/25 3/31/25 3/31/25 4/01/25 OFFICIAL RECORD COPY