ML18194A415

OEDO-18-00316 - Letter from M. Doane to M. Corradini Safety Evaluation of Topical Report, APR1400-F-A-TR-12004-P, Revision 1, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400

ML18194A415
Person / Time
Site:	05200046
Issue date:	07/13/2018
From:	Frederick Brown, Vonna Ordaz NRC/NRO/DLSE/LB2
To:	Michael Corradini Advisory Committee on Reactor Safeguards
Lauron C / 415-2736
Shared Package
ML18178A204	List: ML18194A415
References
APR1400-F-TR-12004 Rev. 1, OEDO-18-00316
Download: ML18194A415 (2)

Text

July 13, 2018 Dr. Michael L. Corradini, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

SAFETY EVALUATION OF TOPICAL REPORT APR1400-F-A-TR-12004, REVISION 1, REALISTIC EVALUATION METHODOLOGY FOR LARGE-BREAK LOSS OF COOLANT ACCIDENT OF THE APR1400

Dear Dr. Corradini:

On behalf of the U.S. Nuclear Regulatory Commission staff, I would like to thank you for the letter from the Advisory Committee on Reactor Safeguards (ACRS) dated June 15, 2018, on the safety evaluation for Topical Report APR1400-F-A-TR-12004, Revision 1, Realistic Evaluation Methodology for Large-Break LOCA [Loss of Coolant Accident] of the APR1400, issued August 2017. Your letter was in response to the discussions on the staffs large-break LOCA (LBLOCA) methodology safety evaluation that took place during the 653rd and 654th meetings of the ACRS on May 3-4, 2018, and June 6-7, 2018, respectively. The ACRS concluded that the code-accuracy based realistic evaluation methodology is acceptable for the APR1400 LBLOCA evaluations, subject to conditions and limitations identified by the staff. Additionally, the ACRS recommended that the staff should issue the safety evaluation report.

As discussed during the meetings, the staff found the LBLOCA analysis methodology acceptable with conditions and limitations. Any applicant or licensee referencing the topical report must address the staffs limitations and conditions as stated in the safety evaluation.

The staff expects to issue its safety evaluation report in August 2018.

The staff appreciates the ACRS thorough review as it completes its review of the APR1400 design certification and related topical reports.

Sincerely,

/RA Vonna Ordaz Acting for/

Frederick D. Brown, Director Office of New Reactors Docket No.: 52-046 cc: Chairman Svinicki Commissioner Baran Commissioner Burns Commissioner Caputo Commissioner Wright SECY

ML18178A204-pkg *via e-mail EDO-002 OFFICE NRO/DLSE/LB2:PM NRO/DLSE/LB2:LA QTE NRO/DLSE/LB2:PM NRO/DLSE/LB2:BC NAME CLauron* CSmith* JDougherty* WWard MMcCoppin DATE 07/10/2018 07/09/2018 07/11/2018 07/11/2018 07/11/2018 OFFICE OGC/NLO NRO/DLSE:D NRO:OD NAME MCarpentier* RTaylor FBrown DATE 07/11/2018 07/12/2018 07/13/2018