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| | issue date = 07/13/2018 | | | issue date = 07/13/2018 |
| | title = 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 | | | title = 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 |
| | author name = Brown F D, Ordaz V L | | | author name = Brown F, Ordaz V |
| | author affiliation = NRC/NRO/DLSE/LB2 | | | author affiliation = NRC/NRO/DLSE/LB2 |
| | addressee name = Corradini M L | | | addressee name = Corradini M |
| | addressee affiliation = NRC/ACRS | | | addressee affiliation = NRC/ACRS |
| | docket = 05200046 | | | docket = 05200046 |
| | license number = | | | license number = |
| | contact person = Lauron C L / 415-2736 | | | contact person = Lauron C / 415-2736 |
| | case reference number = APR1400-F-TR-12004 Rev. 1, OEDO-18-00316 | | | case reference number = APR1400-F-TR-12004 Rev. 1, OEDO-18-00316 |
| | package number = ML18178A204 | | | package number = ML18178A204 |
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| =Text= | | =Text= |
| {{#Wiki_filter:/RA Vonna Ordaz Acting for/}} | | {{#Wiki_filter: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}} |
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Category:Letter
MONTHYEARML23353A1022023-12-19019 December 2023 Vendor Inspection of Korea Hydro & Nuclear Power Co. Safeguards Information Program Implementation ML20366A1162020-11-30030 November 2020 Korea Hydro & Nuclear Power Co., Ltd, APR1400 Response to NRC Regulatory Issue Summary 2020-02, Review of New Licensing Applications for Light-Water Reactors and Non-Light Water Reactors ML20143A0902020-05-13013 May 2020 Korea Hydro & Nuclear Power Co, Ltd., 10 CFR 50.46 Annual Report for the APR1400 Standard Plant Design ML21124A2362020-03-0404 March 2020 KHNP Request for Approval of New Reviewing Official ML19231A2092019-08-23023 August 2019 Nuclear Regulatory Commission Vendor Inspection Report of KHNP Washington, Dc. 05200046/2019201 ML19228A2142019-08-20020 August 2019 Signing Ceremony for the Advanced Power Reactor 1400 Design Certification ML19207A2742019-07-26026 July 2019 LLC Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19207A2572019-07-26026 July 2019 LLC Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19177A3522019-06-27027 June 2019 Vendor Inspection of KHNP Washington, DC Center Announcement Letter ML19116A2452019-04-26026 April 2019 Schedule to Complete Rulemaking and Certification of the Advanced Power Reactor 1400 Reactor Design ML19106A2642019-04-18018 April 2019 Response Letter to Charles J Poppe on APR1400 FSER ML19081A2042019-03-0808 March 2019 Letter from Charles Poppe to William Ward on APR1400 FSER ML18282A2182018-10-0909 October 2018 Korea Hydro & Nuclear Power Co., Ltd. - Review Result to Final Safety Evaluation Report for Chapter 18 ML18274A4032018-09-28028 September 2018 Korea Hydro & Nuclear Power Co., Ltd - Review Results to Final Safety Evaluation Report for Six Chapters ML18261A1872018-09-28028 September 2018 Letter from F. Brown to Kepco/Khnp Issuing the Standard Design Approval for the Advanced Power Reactor 1400 ML18263A2652018-09-28028 September 2018 Letter from R. Taylor to Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., Ltd, Issuing the Final Safety Evaluation Report for the Advanced Power Reactor 1400 Design ML18262A0632018-09-25025 September 2018 Advanced Power Reactor 1400 Design Certification Application - Final Safety Evaluation for Six Chapters - Letter ML18264A1272018-09-21021 September 2018 Korea Hydro & Nuclear Power Co., Ltd - Review Results to Final Safety Evaluation Report for Thirteen Chapters ML18262A0642018-09-19019 September 2018 Advanced Power Reactor 1400 Design Certification Application - Final Safety Evaluation for Thirteen Chapters ML18243A4652018-08-31031 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of LTR-RAM-17-81, Revision 4, Work Order 89: Response to Digital I&C Questions. ML18240A0422018-08-28028 August 2018 Korea Hydro & Nuclear Power Co., Ltd., Submittal of Confirmation of Final Safety Evaluation for the APR1400 Generic Report, Ptlm for RCS Heatup and Cooldown ML18199A3332018-08-23023 August 2018 APR1400, Generic Pressure-Temperature Limits Report, Final Safety Evaluation Report - Letter to KHNP ML18234A4292018-08-22022 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Submittal of Updated Technical Report ML18235A1572018-08-14014 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Revised Samdas Technical Reports ML18225A1372018-08-13013 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 520-8693 for Question 06.02.02-43 (Rev.1) ML18225A3342018-08-13013 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Submittal of APR1400 Applicant'S Environmental Report (Rev.2) ML18222A2582018-08-10010 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Revised Technical Report on CCF Coping Analysis ML18222A3492018-08-10010 August 2018 Korea Hydro & Nuclear Power Co., Ltd. - Transmittal of Response to RAI Er 1-8428 for Question EIS ACC/SA-15 (Rev.4) ML18232A1412018-08-10010 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Submittal of Accepted Versions of Topical Report APR1400-F-M-TR-13001-P-A/-NP-A, PLUS7 Fuel Design for the APR1400. ML18233A4322018-08-10010 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Accepted Versions of Topical Report APR1400-F-A-TR-12004-P-A/-NP-A, Realistic Evaluation Methodology for Large-Break LOCA of the APR1400 ML18221A5152018-08-0909 August 2018 Korea Hydro & Nuclear Power Co., Ltd. - Submittal of Response to RAI 452-8545 for the Question 10.03.06-21 (Rev.1) ML18218A2042018-08-0606 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 312-8343 for Question 19-16 (Rev. 3) ML18218A2092018-08-0606 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 271-8290 for Question 19-15 (Rev. 5) ML18218A1962018-08-0606 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 434-8352 for Question 19-92 (Rev.5) ML18180A3272018-07-31031 July 2018 APR1400 Topical Report Safety Evaluation, Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400 - KHNP Letter ML18212A3462018-07-31031 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Revised Technical Reports for APR1400 Design Certification ML18207A2252018-07-30030 July 2018 LTR-18-0307-1 - Letter from M. Doane to M. Corradini Report on the Safety Aspects of the APR1400 Pressurized-Water Reactor ML18225A1182018-07-27027 July 2018 Ametek Solidstate Controls - Notification of Potential Defect-10CFR Part 21 ML18206B0862018-07-26026 July 2018 Report on the Safety Aspects of the APR1400 Pressurized-Water Reactor ML18269A2412018-07-26026 July 2018 APR1400 Final Safety Evaluation Report, Appendix F - ACRS Report on APR1400 Design ML18214A5642018-07-25025 July 2018 Korea Hydro - Transmittal of Revised Technical Reports for APR1400 Design Certification ML18205A6382018-07-24024 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 356-7881 for the Question 07-18 (Rev.3) ML18205A7322018-07-24024 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 558-9456 for Question 14.03.01-1 (Rev.1) ML18204A4082018-07-23023 July 2018 Korea Hydro & Nuclear Power Co, Ltd., Transmittalof Revised Response to RAI 374-8481 for the Question 18-101 (Rev.1) ML18204A4332018-07-23023 July 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 63-7983 for Question 06.02.02-13 (Rev.2) ML18207A4572018-07-20020 July 2018 Korea Hydro - Transmittal of Revised Response to RAI 112-8015 for Question 13.05.02.01-5, Revision 3 ML18201A4002018-07-20020 July 2018 LLC Response to NRC Request for Additional Information No. 491 (Erai No. 9557) on the NuScale Design Certification Application ML18207A4512018-07-20020 July 2018 Korea Hydro - Transmittal of Revised Response to Section 19.1 Issue #PRA-135, Revision 1 ML18199A5612018-07-18018 July 2018 Korea Hydro & Nuclear Power Co, Ltd., Submittal of Revised Technical Reports for APR1400 Design Certification ML18194A4152018-07-13013 July 2018 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 2023-12-19
[Table view] Category:Safety Evaluation
MONTHYEARML18194A4152018-07-13013 July 2018 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 ML18142A5172018-05-21021 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Markup of the APR1400 DCA - Safety Evaluation with No Open Items for Chapter 19, Section 19.2 ML18128A2992018-05-0808 May 2018 APR1400 Chapter 17, Quality Assurance and Reliability Assurance, Safety Evaluation Report with No Open Items - Memorandum to ACRS ML18099A2872018-04-0909 April 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Markup of the APR1400 DCA - Safety Evaluation with No Open Items for Topical Report APR1400-F-A-TR-12004 ML18089A6132018-03-30030 March 2018 Korea Hydro & Nuclear Power Co, Ltd - Markup of the APR1400 DCA - Safety Evaluation with No Open Items for Chapter 3 ML17265A1182018-03-23023 March 2018 Letter to KHNP for the Safety Evaluation Report for Topical Report APR1400-F-A-TR-1200A-P Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400. ML18012A6272018-01-25025 January 2018 Chapter_9_Phase_4_Letter ML18011A8232018-01-11011 January 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Confirmation of the APR1400 DCA - Safety Evaluation with No Open Items for Chapter 4 2018-07-13
[Table view] |
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