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  • CNRA International Workshop on CNRA International Workshop on New Reactor Siting, Licensing and Construction ExperienceNew Reactor Siting, Licensing and Construction Experience

    Licensing Experience of New Reactor (APR1400) in KoreaLicensing Experience of New Reactor (APR1400) in Korea

    Woo-Ho Lee, Seon Ho Song, Yong Lak Paek

    Nuclear Regulation Division

    Korea Institute of Nuclear Safety (KINS)

    15 September 2010

  • Slide - 2-

    Table of ContentsTable of Contents

    Introduction

    Licensing Process Pre-application Safety Review Standard Design Approval Construction Permit (CP) for Nuclear Installation Operating License (OL) for Nuclear Installation Pre-Operational Inspection

    Design Features of APR1400

    Safety Review

    Standard Design Approval

    Shin-Kori unit 3&4

    Conclusion

  • Slide - 3-

    IntroductionIntroduction

    Current status of NPPs in Korea

    Korea has achieved a remarkable growth in nuclear power since commercial operation of Kori Unit 1 in 1978

    Korea has now 20 operating NPPs : 16 PWRs and 4 PHWRs

    Total licensed output of 20 units is 17,716MW

    - generation capacity : 32.9%

    - actual production : over 40 %

    6 PWRs are now under construction and 2 additional units are planned

    4 PWRs (1,000MW) and 2 PWRs (1,400MW) are under const.

    2 PWRs (1,400MW) are under docket review for CP

    Total units in operation by 2016 : 28 units

  • Slide - 4-

    IntroductionIntroduction

    Location of NPPs in Korea

    Ulchin 1,2,3,4,5,6

    Shin-Ulchin 1,2

    Wolsong 1,2,3,4

    Shin-Wolsong 1,2

    Kori 1,2,3,4

    Shin-Kori 1,2 and 3,4

    Yonggwang

    1,2,3,4,5,6

    KINS

    PWR PWR

    PHWR & PWR

    PWR

  • Slide - 5-

    IntroductionIntroduction

    Plant Type MW Commercial

    Operation

    Commercial

    Operation Type

    Shin-Kori #1 #1

    #2

    PWR PWR

    PWR

    1,000 1,000

    1,000

    Dec. 2010 Dec. 2010

    Dec. 2011

    OPR1000

    OPR1000

    OPR1000

    Shin-

    Wolsong

    #1

    #2

    PWR

    PWR

    1,000

    1,000

    Mar. 2012

    Jan. 2013

    Shin-Kori #3 #3

    #4

    PWR PWR

    PWR

    1,400 1,400

    1,400

    Sep. 2013 Sep. 2013

    Sep. 2014

    OPR1000

    OPR1000

    APR1400 APR1400

    APR1400

    Shin-Shin-

    Ulchin

    #1 #1

    #2

    PWR PWR

    PWR

    1,400 1,400

    1,400

    Dec. 2015 Dec. 2015

    Dec. 2016

    APR1400 APR1400

    APR1400

    : Under Construction, : Under Docket Review, : Under Construction & DR for OL

    OPR 1000 : Improved KSNP (Korea Standard Nuclear Power Plant, 1000MW PWR)

    APR 1400 : Advanced Power Reactor (1400MW PWR)

    Current Status of New Reactor

  • Slide - 6-

    IntroductionIntroduction

    Background & Current status of APR1400

    Launch of a 10-year National Project : 1992

    To develop technologies involved in the design of an advanced

    reactor

    Application for Pre-application Safety Review (PSR) : 2000

    Application for Standard Design Approval (SDA) : 2001

    The SDA was issued in 2002 after two years of safety review

    Shin-Kori units 3&4(APR1400)

    KHNP applied a Construction Permit *(CP) in 2003 , CP was

    granted in 2008

    Structure & Installation inspection are undergoing

    Shin-Uljin units 1&2 (APR1400)

    KHNP applied a CP in October 2008, Review for CP are undergoing

  • Slide - 7-

    IntroductionIntroduction

    Shin-Kori Units 3 and 4 (APR 1400) May 2002: DC issued , April 2008: CP granted

    Structure inspection are undergoing

  • Slide - 8-

    IntroductionIntroduction

    Shin-Uljin units 1&2

    PWR-type reactor (1,400 MWe APR)

    Almost same design as Shin-Kori units 3&4

    Docket Review & Safety Review for CP are undergoing since Oct. 2008

    Scheduled to begin commercial operation in Dec. 2015 and Dec. 2016, respectively.

  • Slide - 9-

    IntroductionIntroduction

    Development of Regulatory Requirements of APR1400

    KINS developed a set of

    regulatory requirements

    To achieve a higher level

    of safety for APR1400

    Based on the existing

    requirements and

    international safety

    standards

    legislated as a Ministerial

    Ordinance on Technical

    Standards for Nuclear

    Facilities in July 2001

    Reg. Guide, Criteria, SRGs

    Industrial Codes and Standards

    (ASME, IEEE, ACI, KEPIC, etc.)

    Atomic

    Energy Act

    Enforcement

    Decree of the Act

    (Presidential Decree)

    Enforcement

    Regulations of the Act

    (Ministerial Ordinances)

    Notice of the Minister of

    Education, Science and Technology

    The Act provides the bases and

    fundamental matters concerning the

    development and utilization of atomic

    energy and safety regulations

    The Decree provides particulars

    entrusted by the Act and necessary for

    the enforcement of the Act

    The Notice provides detailed

    particulars for the technical standards

    and guidelines

    Codes and Standards for materials,

    design, test, and inspection of

    components and equipment

    The Regulation provides the technical

    standards and particulars entrusted by the Act

    and the Decree such as detailed procedures and

    format of documents

    Industrial Codes and Standards

    (ASME, IEEE, ACI, KEPIC, etc.)

    Atomic

    Energy Act

    Enforcement

    Decree of the Act

    (Presidential Decree)

    Enforcement

    Regulations of the Act

    (Ministerial Ordinances)

    Notice of the Minister of

    Education, Science and Technology

    The Act provides the bases and

    fundamental matters concerning the

    development and utilization of atomic

    energy and safety regulations

    The Act provides the bases and

    fundamental matters concerning the

    development and utilization of atomic

    energy and safety regulations

    The Decree provides particulars

    entrusted by the Act and necessary for

    the enforcement of the Act

    The Decree provides particulars

    entrusted by the Act and necessary for

    the enforcement of the Act

    The Notice provides detailed

    particulars for the technical standards

    and guidelines

    The Notice provides detailed

    particulars for the technical standards

    and guidelines

    Codes and Standards for materials,

    design, test, and inspection of

    components and equipment

    Codes and Standards for materials,

    design, test, and inspection of

    components and equipment

    The Regulation provides the technical

    standards and particulars entrusted by the Act

    and the Decree such as detailed procedures and

    format of documents

    The Regulation provides the technical

    standards and particulars entrusted by the Act

    and the Decree such as detailed procedures and

    format of documents

    Legal System of Nuclear Safety RegulationLegal System of Nuclear Safety Regulation

  • Slide - 10-

    Licensing ProcessLicensing Process

    Structure of Licensing Process

  • Slide - 11-

    Licensing ProcessLicensing Process

    New Licensing Process

  • Slide - 12-

    PrePre--application Safety Review (PSR)application Safety Review (PSR)

    Licensing Process Licensing Process

    Prepare Preliminary Safety

    Information Documents (PSIDs)PSR Approach Safety Evaluation Results

    - Prepare PSIDs In the design

    development stage - The applicable current regulations,

    and codes & standards are applied

    first

    - When necessary, enquired

    regulatory requirements for the new

    design features will be developed as

    appropriate

    - Major information including in the

    PSIDs

    . Accident Calculation

    . Containment performance

    . Calculation of source-term

    . Probabilistic Safety Assessment

    . Safety test Program, etc.

    - Not official licensing review

    in accordance with formal

    licensing process

    - Reflected to the preparation of

    application Documents (SARs,

    SSARs) for formal licensing

    process

  • Slide - 13-

    Standard Design Approval (SDA)Standard Design Approval (SDA)

    Licensing Process Licensing Process

    Purpose

    Encourage the use of standard plant designs to enhance plant

    safety, to improve the efficiency, and to reduce the complexity of

    the regulatory process

    Improve the efficiency of licensing review by early resolution of

    safety issues for the timely construction of nuclear power plants

    Documents submitted for SDA

    Standard Design Safety Analysis Report (SSAR)

    Description on the technical capability for the design of the reactor

    Preparation plan for the Emergency Operating Procedure (EOP)

  • Slide - 14-

    Construction Permit (CP)Construction Permit (CP)

    Purpose

    to ensure that the technical standards for the location, structure,

    facility, and performance of NPP are met

    Documents submitted for CP

    Radiation Environmental Report (RER)