ML19269B682
| ML19269B682 | |
| Person / Time | |
|---|---|
| Issue date: | 09/25/2019 |
| From: | Riccardella P Advisory Committee on Reactor Safeguards |
| To: | Margaret Doane NRC/EDO |
| Snodderly, M, ACRS | |
| References | |
| Download: ML19269B682 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 September 25, 2019 Ms. Margaret M. Doane Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
PROPOSED FOCUS AREA REVIEW APPROACH OF THE ADVANCED SAFETY EVALUATION REPORT WITH NO OPEN ITEMS FOR THE DESIGN CERTIFICATION APPLICATION OF THE NUSCALE SMALL MODULAR REACTOR
Dear Ms. Doane:
During the 666th meeting of the Advisory Committee on Reactor Safeguards, September 4-6, 2019, the Committee adopted a recommendation to conduct a focus area approach to review the advanced safety evaluation report (SER) with no open items associated with the NuScale design certification application (DCA) review. The Committee has completed its review of the SER with open items (Phase 3) and is anticipating receipt of the staffs advanced SER with no open items (Phase 4) on December 12, 2019, with the objective of completing our review (Phase 5) by June 23, 2020.
To meet these objectives, we propose to have our chapter leads conduct a completeness review of the advanced SER chapters. However, unless the review of an individual chapter warrants a subcommittee meeting, we would focus our attention on potentially safety-significant issues that are cross-cutting over multiple DCA chapters, as documented in our letter reports during Phase 3. The currently identified areas of focus include:
- Emergency Core Cooling System and Valve Performance;
- Helical Tube Steam Generator Design;
- Boron Dilution and Return to Criticality;
- Source Term; and
We recognize that this is a departure from past reviews of design certification applications; however, we see considerable merit in this approach in assuring a more complete, in-depth
review of matters that are inherently cross-cutting regarding integrated system safety performance. We request your support and the cooperation of the staff in planning and implementing this approach for the new calendar year.
Sincerely,
/RA/
Peter C. Riccardella Chairman REFERENCE
- 1. U.S. Nuclear Regulatory Commission, Review Schedule for the NuScale Power, LLC, Standard Design Certification of a Small Modular Reactor, May 22, 2017 (ML17103A380).
September 25, 2019
SUBJECT:
PROPOSED FOCUS AREA REVIEW APPROACH OF THE ADVANCED SAFETY EVALUATION REPORT WITH NO OPEN ITEMS FOR THE DESIGN CERTIFICATION APPLICATION OF THE NUSCALE SMALL MODULAR REACTOR Accession No: ML19269B682 Publicly Available Y Sensitive N Viewing Rights: NRC Users or ACRS Only or See Restricted distribution *via email OFFICE ACRS/TSB SUNSI Review ACRS/TSB ACRS ACRS ACRS NAME MSnodderly MSnodderly LBurkhart SMoore WKirchner PRiccardella DATE 9/24/2019 9/24/2019 9/24/2019 9/24/2019 9/25/2019 9/25/2019 OFFICIAL RECORD COPY