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| number = ML17265A118
| number = ML17265A118
| issue date = 03/23/2018
| issue date = 03/23/2018
| title = 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.
| title = 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.
| 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 G
| addressee name = Kim H
| addressee affiliation = Korea Hydro & Nuclear Power Co, Ltd
| addressee affiliation = Korea Hydro & Nuclear Power Co, Ltd
| docket = 05200046
| docket = 05200046
| license number =  
| license number =  
| contact person = Steckel J A
| contact person = Steckel J
| package number = ML17265A104
| package number = ML17265A104
| document type = Letter, Safety Evaluation
| document type = Letter, Safety Evaluation
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION
{{#Wiki_filter:OFFICIAL USE ONLY - PROPRIETARY INFORMATION March 23, 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 305-343 Korea (Republic of)
March 23, 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  
 
305-343 Korea (Republic of)  


==SUBJECT:==
==SUBJECT:==
ADVANCED POWER REACTOR 1400 DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR TOPICAL REPORT APR1400-F-A-TR-12004, "REALISTIC EVALUATION METHODOLOGY FOR LARGE-BREAK LOSS OF COOLANT ACCIDENT OF  
ADVANCED POWER REACTOR 1400 DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR TOPICAL REPORT APR1400-F-A-TR-12004, REALISTIC EVALUATION METHODOLOGY FOR LARGE-BREAK LOSS OF COOLANT ACCIDENT OF THE APR1400
 
THE APR1400"


==Dear Dr. Kim:==
==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 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 staff review the Topical Report APR1400-F-A-TR-12004, Revision 0, "Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400" (ML130230128). Proprietary Revision 1 of the Topical Report was submitted on August 11, 2017 (ML17240A229) and Non-Proprietary Revision 1 was submitted on August  
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 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 staff review the Topical Report APR1400-F-A-TR-12004, Revision 0, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400 (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).
 
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 meetings of the ACRS Subcommittee, scheduled to be held on April 17 - 19, 2018.
25, 2017 (ML17250A233).  
The enclosed TRSE with no OIs 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.
 
Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.
Unless otherwise stated in the TRSE, the staff's review was based on Revision 1 of the Topical Report. The staff's 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 meetings of the ACRS Subcommittee, scheduled to be held on April 17 - 19, 2018.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
The enclosed TRSE with no OIs 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 staff's conclusion that the TRSE contains exempt information, but contains no factual errors.Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is "DECONTROLLED."
 
OFFICIAL USE ONLY - PROPRIETARY INFORMATION H. Kim OFFICIAL USE ONLY - PROPRIETARY INFORMATION 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 NRC's Public Document Room and the Publicly Available Records component of NRC's Agencywide Documents Access and Management System and placed on the NRC's 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/
OFFICIAL USE ONLY - PROPRIETARY INFORMATION H. Kim                                        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.
William R. Ward, Senior Project Manager Licensing Branch 2 Division of New Reactor Licensing Office of New Reactors Docket No. 52-046  
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 New Reactor Licensing Office of New Reactors Docket No. 52-046


==Enclosure:==
==Enclosure:==


As stated  
As stated cc w/enclosure: See Next Page OFFICIAL USE ONLY - PROPRIETARY INFORMATION
 
cc w/enclosure: See Next Page  
 
Pkg: ML17265A104 Letter: ML17265A118 SER: ML17265A433  -email*    NRO-002 OFFICE DNRL/LB2: PM DNRL/LB2: L A*DNRL/LB2: PM NAME JSteckel CSmithWWardDATE 9/21/2017 12/13/2017 3/23/2018 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]
Pkg: ML17265A104 Letter: ML17265A118 SER: ML17265A433                 -email*                          NRO-002 OFFICE DNRL/LB2: PM                DNRL/LB2: LA*      DNRL/LB2: PM NAME      JSteckel                CSmith            WWard DATE      9/21/2017              12/13/2017         3/23/2018 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
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.oh5@gmail.com                      [Jiyong Andy Oh] ahn.daegeun@khnp.co.kr , daegeun.ahn@gmail.com         [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]


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.oh5@gmail.com          [Jiyong Andy Oh]
ahn.daegeun@khnp.co.kr, daegeun.ahn@gmail.com      [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]
Page 2 of 2}}
Page 2 of 2}}

Latest revision as of 10:16, 4 February 2020

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.
ML17265A118
Person / Time
Site: 05200046
Issue date: 03/23/2018
From: William Ward
NRC/NRO/DNRL/LB2
To: Kim H
Korea Hydro & Nuclear Power Co, Ltd
Steckel J
Shared Package
ML17265A104 List:
References
Download: ML17265A118 (5)
v • d • e


Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION March 23, 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 305-343 Korea (Republic of)

SUBJECT:

ADVANCED POWER REACTOR 1400 DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS 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 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 staff review the Topical Report APR1400-F-A-TR-12004, Revision 0, Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400 (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).

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 meetings of the ACRS Subcommittee, scheduled to be held on April 17 - 19, 2018.

The enclosed TRSE with no OIs 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.

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 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 New Reactor Licensing Office of New Reactors Docket No.52-046

Enclosure:

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

Pkg: ML17265A104 Letter: ML17265A118 SER: ML17265A433 -email* NRO-002 OFFICE DNRL/LB2: PM DNRL/LB2: LA* DNRL/LB2: PM NAME JSteckel CSmith WWard DATE 9/21/2017 12/13/2017 3/23/2018 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.oh5@gmail.com [Jiyong Andy Oh]

ahn.daegeun@khnp.co.kr, daegeun.ahn@gmail.com [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]

Page 2 of 2

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