ML18304A216

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Revised Summary Report for 656th Full Committee Meeting - September 6-8, 2018
ML18304A216
Person / Time
Issue date: 10/24/2018
From: Michael Corradini
Advisory Committee on Reactor Safeguards
To: Kristine Svinicki
NRC/Chairman
Banks A
References
Download: ML18304A216 (5)
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UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 October 24, 2018 The Honorable Kristine L. Svinicki Chairman U.S. Nuclear Regulatory Commission Washington, D.C.

20555-0001

SUBJECT:

SUMMARY

REPORT - 656th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, SEPTEMBER 6-7, 2018

Dear Chairman:

During its 656th meeting, September 6-7, 2018, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following letters and memoranda:

LETTERS Letters to Margaret M. Doane, Executive Director for Operations, NRC, from Michael L. Corradini, Chairman, ACRS:

  • Safety Evaluation of the NuScale Power, LLC Topical Report TR-0915-17564-P, Revision 1, Subchannel Analysis Methodology, dated September 26, 2018
  • Interim Letter: Chapters 7 and 8 of the NRC Staffs Safety Evaluation Report with Open Items Related to the Certification of the NuScale Small Modular Reactor, dated September 26, 2018 MEMORANDA Memoranda to Margaret M. Doane, Executive Director for Operations, NRC, from Andrea D. Veil, Executive Director, ACRS:

2

  • Regulatory Guides, dated September 13, 2018 o RG 1.206, Revision 1, Applications for Nuclear Power Plants (No review) o RG 3.71, Revision 3, Nuclear Criticality Safety Standards for Nuclear Materials Outside Reactor Cores (No review) o RG 1.160, Revision 4, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (No review) o DG-1352, Instrument Sensing Lines (No review at this time, but opportunity to review after the public comment period)

HIGHLIGHTS OF KEY ISSUES

1. NuScale Topical Report TR-0915-17564, Subchannel Analysis Methodology The Committee met with representatives of the NRC staff and representatives of NuScale Power, LLC to review the staffs safety evaluation of NuScales topical report, TR-0915-17564-P, Subchannel Analysis Methodology, Revision 1. Subchannel analysis methodologies and nuclear methods are used to design and determine reactor core performance under steady-state and normal operations, as well as anticipated operational occurrences and selected accidents. NuScale proposes to utilize the VIPRE-01 code series (versions MOD-01 and MOD-02) for its subchannel analysis methodologies.

The staffs review of the topical report addressed the general applicability of VIPRE-01 to a NuScale power module for steady-state and transient subchannel analyses and fulfillment of the NRCs nine conditions described in the safety evaluation reports for VIPRE-01 MOD-01 and MOD-02; the independence of the methodology for any specific critical heat flux correlation; the applicability if methodology requirements are met with an NRC-approved critical heat flux correlation; and the appropriate treatment of uncertainties in the methodology.

Committee Action The Committee issued a report to the NRC Executive Director for Operations on this matter, dated September 26, 2018, with the following conclusion and recommendation: 1) Topical report TR-0915-17564-P, Revision 1, provides an acceptable methodology for performing steady-state and most transient and accident analyses, subject to the staffs limitations and conditions, and 2) The staffs safety evaluation report should be issued.

2. NuScale Design Certification Application, Chapter 7, Instrumentation & Control and Chapter 8, Electrical Power The Committee met with the NRC staff and representatives of NuScale Power, LLC to review Chapter 7, Instrumentation and Controls, and Chapter 8, Electric Power, of the safety evaluation report with open items associated with the NuScale design certification application. The ACRS review is being conducted on a chapter-by-chapter basis to identify

3 issues that may merit further consideration by the staff. This process will aid in the resolution of concerns and facilitates timely completion of the design certification review.

Committee Action The Committee issued a report to the NRC Executive Director for Operations on this matter, dated September 26, 2018, with the following conclusions and recommendation: 1) We have identified no major issues at this time. However, there are items, such as those noted below that need to be resolved because they may alter this conclusion, 2) The staff should ensure that the unidirectional communication interfaces labeled on Figure 7.0-1 in Chapter 7 of NuScales design certification application as PCS Unidirectional Data Diode and MCS Unidirectional Data Diode are one-way, hardware-based devices that neither use nor are configured by software to demonstrate complete isolation from external communications, and

3) The staffs safety evaluation report for Chapter 8 has not yet resolved the significant open item of whether the design certification application meets the specifications of topical report TR-0815-16497-P-A and its associated safety evaluation limitations and conditions.

RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS

  • The Committee considered the Executive Director for Operations response of July 30, 2018, to the July 26, 2018 ACRS letter, Report on the Safety Aspects of the APR 1400 Pressurized-Water Reactor. The Committee was satisfied with the Executive Director for Operations response.
  • The Committee considered the Executive Director for Operations response of July 13, 2018, to the June 15, 2018 ACRS letter, Safety Evaluation for Topical Report APR1400-F-A-TR-12004-P, Revision 1, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400. The Committee was satisfied with the Executive Director for Operations response.
  • The Committee considered the Executive Director for Operations response of July 13, 2018, to the June 15, 2018 ACRS letter, Long-Term Core Cooling for the APR1400. The Committee was satisfied with the Executive Director for Operations response.
  • The Committee considered the Executive Director for Operations response of June 27, 2018, to the May 10, 2018 ACRS letter, Draft SECY Paper, Functional Containment Performance Criteria for Non-Light Water Reactor Designs. The Committee was satisfied with the Executive Director for Operations response.
  • The Committee considered the Executive Director for Operations response of June 29, 2018, to the June 15, 2018 ACRS letter, Safety Evaluation of the NuScale Power, LLC Topical Report TR-0616-48793, Revision 0, Nuclear Analysis Codes and Methods Qualification and Safety Evaluation of the NuScale Power, LLC Topical Report TR-0116-21012, Revision 1, NuScale Power Critical Heat Flux Correlations. The Committee was satisfied with the Executive Director for Operations response.
  • The Committee considered the Executive Director for Operations response of July 20, 2018, to the February 26, 2018 ACRS letter, Biennial Review and

4 Evaluation of the NRC Safety Research Program. The Committee was satisfied with the Executive Director for Operations response.

SCHEDULED TOPICS FOR THE 657th ACRS MEETING The following topics are scheduled for the 657th ACRS meeting, to be held October 4-6, 2018:

  • Annual Operating Reactor Experience Briefing
  • Assessment of the Quality of Selected NRC Research Projects Sincerely,

/RA/

Michael Corradini Chairman

5 October 24, 2018

SUBJECT:

SUMMARY

REPORT - 656th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, SEPTEMBER 6-7, 2018 Accession No: ML18303A159 Publicly Available (Y/N): _Y___ Sensitive (Y/N): N If Sensitive, which category?

Viewing Rights: NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI Review ACRS ACRS NAME MBanks MBanks AVeil MCorradini (AVeil for)

DATE 10/ 24 /18 10/ 24 /18 10/ 24 /18 10/24 /18 OFFICIAL RECORD COPY

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