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| number = ML18156A045
| number = ML18156A045
| issue date = 06/05/2018
| issue date = 06/05/2018
| title = APR1400 Topical Report Safety Evaluation, Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400 - Letter to Khnp
| title = APR1400 Topical Report Safety Evaluation, Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400 - Letter to KHNP
| author name = Ward W R
| author name = Ward W
| author affiliation = NRC/NRO/DNRL/LB2
| author affiliation = NRC/NRO/DNRL/LB2
| addressee name = Kim H
| addressee name = Kim H
Line 9: Line 9:
| docket = 05200046
| docket = 05200046
| license number =  
| license number =  
| contact person = Ward W R / 415-7038
| contact person = Ward W / 415-7038
| package number = ML18156A042
| package number = ML18156A042
| document type = Letter
| document type = Letter
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Code of Federal Regulations
{{#Wiki_filter:OFFICIAL USE ONLY - PROPRIETARY INFORMATION June 5, 2018 Dr. Han-Gon Kim, Project Manager APR1400 Design Certification Advanced Reactors Development Laboratory Korea Hydro and Nuclear Power Co., Ltd.
/RA/}}
70-1312-gil, Yuseong-daero Yuseong-Gu, Daejeon 34101 Korea (Republic of)
 
==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
 
==Dear Dr. Kim:==
 
The U.S. Nuclear Regulatory Commission (NRC) staff is preparing a Topical Report Safety Evaluation (TRSE) with no open items (OIs) for each topical report of the Advanced Power Reactor 1400 (APR1400) Design Certification Application submitted by Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co., Ltd. (KHNP) on December 23, 2014. 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.
Unless otherwise stated in the TRSE, the staffs review was based on Revision 1 of the Topical Report. The staffs TRSE with no OIs for Topical Report APR1400-F-A-TR-12004, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400, is being provided to the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee to support upcoming meeting of the ACRS Subcommittee, scheduled to be held on June 6, 2018.
Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
 
OFFICIAL USE ONLY - PROPRIETARY INFORMATION H. Kim                                          The enclosed TRSE is being provided only to KHNP for review of proprietary information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public Inspections, Exemptions, Requests for Withholding. The staff concludes that the enclosed TRSE does contain information for which exemption from public disclosure has been sought or approved, and does not contain any factual errors. However, the NRC will withhold the enclosed TRSE from public disclosure for ten business days from the date of this letter to allow you the opportunity to verify the staffs conclusion that the TRSE contains exempt information, but contains no factual errors. If within that ten day period you do not request that all or portions of the TRSE be withheld from public disclosure, a decision will be made by staff on whether the enclosure will be made available for public inspection through the NRCs Public Document Room and the Publicly Available Records component of NRCs Agencywide Documents Access and Management System and placed on the NRCs public web page for this application.
If you have any questions or comments concerning this matter, I can be reached at (301) 415-7038, or via e-mail address at William.Ward@nrc.gov.
Sincerely,
                                        /RA/
William R. Ward, Senior Project Manager Licensing Branch 2 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No. 52-046
 
==Enclosure:==
 
As stated cc w/enclosure: See Next Page OFFICIAL USE ONLY - PROPRIETARY INFORMATION
 
Pkg: ML18156A042 Letter: ML18156A045 SER: ML18156A043                  email*                        NRO-002 OFFICE DLSE/LB2: PM                DLSE/LB2: LA*      DLSE/LB2: PM NAME      JSteckel                CSmith            WWard DATE      06/4/2018              06/05/2018          06/5/2018 KHNP Mailing List 3/03/2017 Daegeun Tony Ahn Director KHNP Washington DC Center 8100 Boone Blvd, Suite 620 Vienna, VA 22182 Page 1 of 2
 
Email kimhg1108@khnp.co.kr            [Han-Gon Kim]
hansang.kim@khnp.co.kr          [Hansang Kim]
dohwan.lee@khnp.co.kr            [Do-Hwan Lee]
junghokim@khnp.co.kr            [Jung-Ho Kim]
yunho.kim@khnp.co.kr            [Yun Ho Kim]
jiyong.oh@khnp.co.kr            [Jiyong Andy Oh]
ahn.daegeun@khnp.co.kr          [Daegeun Tony Ahn]
jksuh@khnp.co.kr                [Jeong Kwan Suh]
hachewung@khnp.co.kr            [Che Wung Ha]
kang.deogji@khnp.co.kr          [Deog Ji Kang]
sunguk.kwon@khnp.co.kr          [Sun Guk Kwon]
ptmaster300@kepco.co.kr          [Hyun Chul Park]
sisk1rb@westinghouse.com                [Rob Sisk]
david.wagner@aecom.com                  [David Wagner]
robert.sweeney@consultant.aecom.com    [Robert Sweeney]
Page 2 of 2}}

Latest revision as of 22:23, 2 February 2020

APR1400 Topical Report Safety Evaluation, Realistic Evaluation Methodology for Large Break Loss of Coolant Accident of the APR1400 - Letter to KHNP
ML18156A045
Person / Time
Site: 05200046
Issue date: 06/05/2018
From: William Ward
NRC/NRO/DNRL/LB2
To: Kim H
Korea Hydro & Nuclear Power Co, Ltd
Ward W / 415-7038
Shared Package
ML18156A042 List:
References
Download: ML18156A045 (5)
v • d • e


Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION June 5, 2018 Dr. Han-Gon Kim, Project Manager APR1400 Design Certification Advanced Reactors Development Laboratory Korea Hydro and Nuclear Power Co., Ltd.

70-1312-gil, Yuseong-daero Yuseong-Gu, Daejeon 34101 Korea (Republic of)

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

Dear Dr. Kim:

The U.S. Nuclear Regulatory Commission (NRC) staff is preparing a Topical Report Safety Evaluation (TRSE) with no open items (OIs) for each topical report of the Advanced Power Reactor 1400 (APR1400) Design Certification Application submitted by Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co., Ltd. (KHNP) on December 23, 2014. 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.

Unless otherwise stated in the TRSE, the staffs review was based on Revision 1 of the Topical Report. The staffs TRSE with no OIs for Topical Report APR1400-F-A-TR-12004, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400, is being provided to the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee to support upcoming meeting of the ACRS Subcommittee, scheduled to be held on June 6, 2018.

Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

OFFICIAL USE ONLY - PROPRIETARY INFORMATION H. Kim The enclosed TRSE is being provided only to KHNP for review of proprietary information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public Inspections, Exemptions, Requests for Withholding. The staff concludes that the enclosed TRSE does contain information for which exemption from public disclosure has been sought or approved, and does not contain any factual errors. However, the NRC will withhold the enclosed TRSE from public disclosure for ten business days from the date of this letter to allow you the opportunity to verify the staffs conclusion that the TRSE contains exempt information, but contains no factual errors. If within that ten day period you do not request that all or portions of the TRSE be withheld from public disclosure, a decision will be made by staff on whether the enclosure will be made available for public inspection through the NRCs Public Document Room and the Publicly Available Records component of NRCs Agencywide Documents Access and Management System and placed on the NRCs public web page for this application.

If you have any questions or comments concerning this matter, I can be reached at (301) 415-7038, or via e-mail address at William.Ward@nrc.gov.

Sincerely,

/RA/

William R. Ward, Senior Project Manager Licensing Branch 2 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No.52-046

Enclosure:

As stated cc w/enclosure: See Next Page OFFICIAL USE ONLY - PROPRIETARY INFORMATION

Pkg: ML18156A042 Letter: ML18156A045 SER: ML18156A043 email* NRO-002 OFFICE DLSE/LB2: PM DLSE/LB2: LA* DLSE/LB2: PM NAME JSteckel CSmith WWard DATE 06/4/2018 06/05/2018 06/5/2018 KHNP Mailing List 3/03/2017 Daegeun Tony Ahn Director KHNP Washington DC Center 8100 Boone Blvd, Suite 620 Vienna, VA 22182 Page 1 of 2

Email kimhg1108@khnp.co.kr [Han-Gon Kim]

hansang.kim@khnp.co.kr [Hansang Kim]

dohwan.lee@khnp.co.kr [Do-Hwan Lee]

junghokim@khnp.co.kr [Jung-Ho Kim]

yunho.kim@khnp.co.kr [Yun Ho Kim]

jiyong.oh@khnp.co.kr [Jiyong Andy Oh]

ahn.daegeun@khnp.co.kr [Daegeun Tony Ahn]

jksuh@khnp.co.kr [Jeong Kwan Suh]

hachewung@khnp.co.kr [Che Wung Ha]

kang.deogji@khnp.co.kr [Deog Ji Kang]

sunguk.kwon@khnp.co.kr [Sun Guk Kwon]

ptmaster300@kepco.co.kr [Hyun Chul Park]

sisk1rb@westinghouse.com [Rob Sisk]

david.wagner@aecom.com [David Wagner]

robert.sweeney@consultant.aecom.com [Robert Sweeney]

Page 2 of 2

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