ML20086N597
| ML20086N597 | |
| Person / Time | |
|---|---|
| Issue date: | 03/25/2020 |
| From: | Matthew Sunseri Advisory Committee on Reactor Safeguards |
| To: | Kristine Svinicki NRC/Chairman |
| Burkhart, L, ACRS | |
| References | |
| Download: ML20086N597 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 March 25, 2020 The Honorable Kristine L. Svinicki Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
SUBJECT:
SUMMARY
REPORT - 670th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, FEBRUARY 5 - 7, 2020
Dear Chairman Svinicki:
During its 670th meeting, February 5 - 7, 2020, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following correspondence:
LETTER Letter to Raymond Furstenau, Director, Office of Nuclear Regulatory Research, NRC, from Matthew W. Sunseri, Chairman, ACRS:
ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2019, dated March 10, 2020, ADAMS Accession No. ML20062E857 MEMORANDA Memoranda to Margaret M. Doane, EDO, NRC, from Scott W. Moore, Executive Director, ACRS:
Documentation of Receipt of Applicable Official NRC Notices to the Advisory Committee on Reactor Safeguards for February 2020, dated February 11, 2020, ADAMS Accession No. ML20043C565.
Regulatory Guides, dated February 11, 2020, ADAMS Accession No. ML20043C532.
Memorandum to Ho K. Nieh, Director, Office of Nuclear Reactor Regulation (NRR), NRC, from Scott W. Moore, Executive Director, ACRS:
ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19, and 20, dated February 21, 2020, ADAMS Accession No. ML20044D595.
HIGHLIGHTS OF KEY ISSUES ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2019 The Committee assessed the quality of the following research projects and provided a letter and enclosure regarding the Committees views as follows:
NUREG/CR-7249, Overview of Nuclear Data Uncertainty in SCALE and Application to Light Water Reactor Uncertainty Analysis
- This project was found to be satisfactory. With minor limitations, the results meet the research objectives.
NUREG/CR-7244, Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions
- This project was found to be more than satisfactory, a professional work that satisfies research objectives.
These projects were selected from a list of projects provided by the Office of Nuclear Regulatory Research.
Committee Action The Committee issued a letter to the Director of the Office of Nuclear Regulatory Research on March 10, 2020.
MEETING WITH THE INSTITUTE OF NUCLEAR POWER OPERATIONS (INPO)
The Committee met with representatives of INPO to discuss INPO inspection and plant performance capabilities and industry performance trends. This portion of the meeting was closed to the public due to discussion of proprietary and sensitive information. This meeting was an information exchange and no Committee action was taken on this matter.
NUSCALE PHASE 5 DISCUSSIONS With the exceptions as documented in the memorandum, dated February 21, 2020, and attachments, from Scott Moore, ACRS Executive Director, to Ho Nieh, Director, NRR, the Committee decided that no further briefing by the staff is needed to support the Committees Phase 5 review as it pertains to Chapter 1, Introduction and General Description of the Plant, Chapter 3, Design of Structures, Systems and Components, Chapter 4, Reactor, Chapter 6, Engineered Safety Features, Chapter 9, Auxiliary Systems, Chapter 13, Conduct of Operations, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, Chapter 15, Transient and Accident Analyses, Chapter 16, Technical Specifications, Chapter 18, Human Factors Engineering, Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, and Chapter 20, Mitigation of Beyond-Design-Basis Events, of the NuScale design certification application.
The Committee does request a briefing by the staff on selected topics from Chapters 9, 15, and 20 as described in the attachments to the February 21, 2020, memoranda.
This memorandum completes the Committee chapter lead reviews of the advanced safety evaluation report chapters in accordance with the Committees letter of September 25, 2019, ADAMS Accession No. ML19269B682.
ACRS SUBCOMMITTEE STRUCTURE AND MEMBERSHIP During the planning and procedures portion of the meeting, the Committee discussed slight revisions to the structure, naming, and membership of the various subcommittees of the ACRS.
The changes were necessitated by the departure of members in calendar year 2019, the anticipated workload in the advanced reactor area, and transformation efforts. The Committee approved the changes and will post the new structure and membership on the ACRS internal webpage.
LICENSE AMENDMENT REQUESTS AND TOPICAL REPORTS WITH PRECEDENCE The Committee discussed an approach to determine the need for ACRS review and reporting on license amendment requests and topical reports that have an established precedent that has already been reviewed by the Committee. The Committee approved the approach of one member who is a subject matter expert taking the lead to review such actions. Then the assigned member would prepare a recommendation to the Full Committee with an opinion as to whether or not a review and/or report is warranted. The Full Committee would then decide the necessary actions to be taken.
RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The Committee considered the correspondence from the Director of the Division of Safety Systems, Office of Nuclear Reactor Regulation (NRR), dated January 15, 2020, ADAMS Accession No. ML20017A115, in response to the Committees letter dated November 26, 2019, ADAMS Accession No. ML19331A067. The topic was the NUREG/KM-0013, Credibility Assessment Framework for Critical Boiling Transition Models - A Generic Safety Case to Determine the Credibility of Critical Heat Flux and Critical Power Models, Draft Report for Comment. The Committee accepted the staffs response.
The Committee also considered the correspondence from the Director of the Office of Nuclear Regulatory Research, dated December 23, 2019, ADAMS Accession No. ML19352E588, in response to the Committees letter dated November 27, 2019, ADAMS Accession No. ML19331A231. The topic was assessment of the continued adequacy of revision 2 of Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials.
The Committee accepted the staffs response and looks forward to presentation of the draft revision of RG 1.99.
The Committee also considered the correspondence from the NRR Director dated January 16, 2020, ADAMS Accession No. ML20027B996, in response to the Committees letter dated December 19, 2019, ADAMS Accession No. ML19353D382. The topic was the report on the safety aspects of the subsequent license renewal application review of the Peach Bottom Atomic Power Station, Units 2 and 3. The Committee accepted the staffs response.
The Committee also considered the correspondence from the Deputy Director for Engineering, NRR, dated November 27, 2019, ADAMS Accession No. ML20028E360, in
response to the Committees letter dated November 4, 2019, ADAMS Accession No. ML19308A004. The topic was the safety evaluation of topical report ANP-10346P, revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA. The Committee accepted the staffs response.
Finally, the Committee considered the correspondence from the Acting Deputy Director, Reactor Safety Programs and Corporate Support, NRR, dated October 31, 2019, ADAMS Accession No. ML19283A540, in response to the Committees letter dated September 26, 2019, ADAMS Accession No. ML19269D514. The topic was the safety evaluation of Westinghouse topical report WCAP-17794-NP, Revision 0, 10X10 SCEA Fuel Critical Power Experiments and new CPR Correlation: D5 for SVEA-96 OPTIMA3. The Committee accepted the staffs response.
SCHEDULED TOPICS FOR THE 671st ACRS MEETING The following topics were placed on the agenda for the 671st ACRS meeting which was held on March 5 - 6, 2020:
NuScale design certification application areas of focus on steam generator design, containment evacuation system and hydrogen and oxygen monitoring Biennial review of NRC safety research program NuScale topical reports on loss-of-coolant accident (LOCA), non-LOCA, and rod ejection accident evaluation methodologies Sincerely,
/RA/
Matthew W. Sunseri, Chairman
March 25, 2020
SUBJECT:
SUMMARY
REPORT - 670th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, FEBRUARY 5 - 7, 2020 Accession No: ML20086N597 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 LBurkhart (CBrown for)
LBurkhart (CBrown for)
SMoore MSunseri DATE 3/16/20 3/16/20 3/25/20 3/24/20 OFFICIAL RECORD COPY