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Category:Memoranda
MONTHYEARML17013A1462018-08-29029 August 2018
Audit Summary to Review KHNP APR1400 Non-LOCA Chapter 15, Transient and Accident Analyses - Memo
ML18158A3422018-08-15015 August 2018
KHNP Environmental Assessment: APR1400 Design Certification (Rin 3150-AJ67; NRC-2015-0225
ML18150A6472018-06-11011 June 2018
APR1400, Supplementary Information for Safety Evaluation with No Open Items for Chapter 14.3, Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) - Memorandum
ML18156A0462018-06-0505 June 2018
APR1400 Topical Report Safety Evaluation, Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400 - Memorandum to ACRS
ML18149A5502018-05-31031 May 2018
APR1400 Chapter 14.3.2, Structural and Systems Engineering - ITAAC, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML18147A0032018-05-31031 May 2018
APR1400 Chapter 13, Conduct of Operations, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML17188A3032018-05-21021 May 2018
APR1400 Chapter 6, Engineered Safety Features, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML18054A6862018-05-20020 May 2018
APR1400 Chapter 14.3, Verification Programs, Safety Evaluation Report with Open Items - Memorandum to ACRS Memo
ML18128A2992018-05-0808 May 2018
APR1400 Chapter 17, Quality Assurance and Reliability Assurance, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML18128A1112018-05-0808 May 2018
APR1400 Chapter 19, Section 19.0 and Section 19.1, Probabilistic Risk Assessment and Severe Accident Evaluation, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML18122A2242018-05-0808 May 2018
APR1400 Chapter 19, Section 19.2, Severe Accident Evaluation, Safety Evaluation Report with No Open Items - Memorandum to ACRS
ML18073A2552018-03-26026 March 2018
Summary of March 14, 2018 Public Meeting with KHNP to Discuss Human Factors Engineering
ML18068A1292018-03-26026 March 2018
March 7, 2018 Summary of Public Meeting with KHNP to Discuss Proposed ITAAC for the APR1400
ML17265A2692018-03-23023 March 2018
Transmittal Memo to ACRS of the LBLOCA Safety Evaluation for KHNP Topical Report APR1400-F-A-TR-1200A-P, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400.
ML18017A2422018-03-20020 March 2018
Chapter_3_Phase_4_Memorandum
ML18074A0322018-03-19019 March 2018
APR1400 P4 Chapter 7 ACRS
ML17269A3152018-03-19019 March 2018
Transmittal Memo to ACRS of the Chapter 15 Phase 4 Safety Evaluation Report Transient and Accident Analyses, APR1400 Design Certification
ML17166A1142018-02-23023 February 2018
APR1400 Chapter 2 Phase 4 - Section 2.5 - Memo to ACRS
ML18012A6282018-01-26026 January 2018
Chapter_9_Phase_4_Memorandum
ML17243A2462018-01-26026 January 2018
Memo Advanced Power Reactor 1400 Design Certification Application - Safety Evaluation with No Open Items for Section 19.4, Loss of Large Areas of the Plant Due to Explosions or Fire
ML17271A0982018-01-26026 January 2018
APR1400 P4 Chapter 19.3 ACRS Memo
ML17276A0342018-01-26026 January 2018
Memo for Transmittal to ACRS the Phase 4 Chapter 19.5, Aircraft Impact Assessment Safety Evacuation Report for the APR1400 Design Certification
ML17276B5182017-12-28028 December 2017
APR1400 P4 Chapter 18 ACRS Memo
ML17188A3152017-12-28028 December 2017
APR1400 Chapter 16 Phase 4 ACRS Memorandum
ML17324B2882017-12-28028 December 2017
APR1400 P4 Chapter 14.1-14.2 ACRS Memo
ML17334A1042017-12-27027 December 2017
APR1400 Chapter 4 Phase 4 Memorandum
ML17132A2862017-12-26026 December 2017
Audit Report of Structural and Seismic Design Supporting Chapter 3, Design of Structures, Systems, Components, and Equipment, of the Advanced Power Reactor 1400 Design Control Document
ML17058A3932017-03-17017 March 2017
APR1400 Chapter 14, Phase 3, ACRS Memo
ML16300A1842016-12-0707 December 2016
Memorandum - Audit Summary for the Korea Hydro and Nuclear Power Co. Ltd Advanced Power Reactor 1400 Electric Power System
ML16211A3512016-08-0404 August 2016
Supplemental Safety Evaluation Report for Topical Report APR1400-K-Q-TR-11005-NP, Revision 5, Knhp Quality Assurance Program Description for the APR1400 Design Certification.
2018-08-29
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June 5, 2018 MEMORANDUM TO: Andrea Veil, Executive Director Advisory Committee on Reactor Safeguards FROM: Anna H. Bradford, Deputy Director /RA Andy Campbell for/
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
TOPICAL REPORT SAFETY EVALUATION FOR TOPICAL REPORT APR1400-F-A-TR-12004, REALISTIC EVALUATION METHODOLOGY FOR LARGE-BREAK LOSS OF COOLANT ACCIDENT OF THE APR1400 By letter dated December 23, 2014, as supplemented by letters dated March 10, 2017, and March 8, 2018, Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co (KHNP), Ltd. submitted an application to the U.S. Nuclear Regulatory Commission (NRC) for a design certification of the Advanced Power Reactor 1400 (APR1400) Standard Design, pursuant to Title 10 of the Code of Federal Regulations Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. By letter dated January 7, 2013, KHNP submitted, for the staffs review, Topical Report APR1400-F-A-TR-12004, Revision 0, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML130230128).
Proprietary Revision 1 of the Topical Report was submitted on August 11, 2017 (ML17240A229) and Non-Proprietary Revision 1 was submitted on August 25, 2017 (ML17250A233).
The initial version of this TRSE was issued on March 23, 2018 (ML17265A104). However, on April 25, 2018 (ML18115A426), KHNP submitted a letter providing additional information related to condition (1) in the TRSE. The staff reviewed the letter and revised the TRSE to remove condition (1) and re-word condition (4), based on the additional information.
Based on our review of the application, the staff is providing the Advisory Committee on Reactor Safeguards (ACRS) its Topical Report Safety Evaluation (TRSE) with no Open Items for Topical Report APR1400-F-A-TR-12004, (ML18156A043). Unless otherwise stated in the TRSE, the staffs review was based on Revision 1 of the Topical Report. The TRSE is being provided to support a meeting of the full committee of the ACRS scheduled for June 6, 2018.
CONTACTS: James A. Steckel, NRO/DLSE (301) 415-1026 William R. Ward, NRO/DLSE (301) 415-7038
A. Veil The staff concludes that the TRSE does contain information exempt from public disclosure.
However, the U.S. Nuclear Regulatory Commission will withhold the SE from public disclosure for ten business days to allow KHNP the opportunity to verify the staffs conclusion that the SE contains exempt information. Therefore, the staff requests that the ACRS withhold the SE from public disclosure unless the information can be released publicly in the ADAMS.
The staff will inform the ACRS immediately if KHNP requests that any of the information in the SE be released for public disclosure.
Docket No.: 52-046
PKG: ML18156A042 MEMO: ML18156A046 SER: ML18156A043 *via email NRO-002 OFFICE DLSE/LB2: PM DLSE/LB2: LA* DLSE/LB2: PM DLSE/LB2 BC DLSE:DD NAME JSteckel CSmith WWard MMcCoppin ABradford (WWard for) (ACampbell for)
DATE 06/4/2018 06/05/2018 06/4/2018 06/4/2018 06/5/2018