INPRO Dialogue Forum on Global Nuclear Energy ... · Reactor Coolant Pump Upper Guide ... The...

Myung Jo Jhung

Korea Institute of Nuclear Safety / Republic of Korea

6th INPRO Dialogue Forum on Global Nuclear Energy Sustainability:

Licensing and Safety Issues for Small and Medium-sized

Nuclear Power Reactors (SMRs)

29 July - 2 August 2013

IAEA Headquarters, Vienna, Austria

Licensing Review of SMART

for Standard Design Approval

Contents

• Introduction

• SMART

• Legal Framework for SDA

• Licensing Review for SDA of SMART

• SDA Review

• Pre-Application Review

• Regulatory Research

• Summary

29 July-2 August 2013 6th IAEA INPRO Dialogue Forum on Licensing and Safety Issues 2

Introduction

• KAERI/KEPCO developed SMART (System-integrated Modular

Advanced ReacTor), an integral PWR type of SMR in 2010, and

applied for the standard design approval (SDA).

• Nuclear Safety and Security Commission (NSSC) requested

KINS for technical review.

• KINS reviewed documents related to the SMART for SDA

• NSSC approved standard design of SMART on July 4, 2012

• The followings will be presented in this presentation;

• Introduction of SMART

• Legal framework for SDA

• Experience of licensing review in KINS for SDA of SMART


SMART Characteristics (1/2)


Pressurizer

X X

X X X X

Loop Type PWR

Core

Pump

Enhanced Reactor Safety: No LBLOCA

S/G

Integral PWR

SMART Characteristics (2/2)


Control Rod Drive

Mechanism

Pressurizer

Reactor Coolant

Pump

Upper Guide

Structure

Core Support

Barrel

Flow Mixing Header

Ass’y

Core

ICI Nozzles

Steam

Nozzle

Feedwater

Nozzle

Steam

Generator

330 MWt (100 MWe) nominal output

Small core (57 fuel assemblies) and source term

Unit output enough to support electricity, water and

heat demand for population of 100,000

Integral PWR with no large RPV penetrations

Less than 2’’ penetrations

In-vessel Pressurizer, Steam Generator and

RCP (Canned Motor Pump)

Inherent Safety

Elimination of LB-LOCA by design

No core uncovery during SB-LOCA

Large Coolant Inventory per MW

Low Power Density (~2/3 of Large PWR)

Performance proved Fuel

Standard 17x17 UO2 (< 5 w/o U235) w/reduced height (2m)

Advanced Grid / IFM design

Peak Rod Burnup < 60 GWd/t

Performance proved @ operating PWRs

Improved Core Operability

Cycle length: 1,000 EFPD (~ 3 years)

Proven reactivity control measures

- CRDM, Soluble Boron, BP

SMART Design Information


General Information

Reactor Type Integral PWR

Thermal Power (MWt) 330

Electric Power (MWe) 100

Design Life Time (yr) 60

Fuel and Reactor Core

Fuel Type 1717 Square FA

Fuel Material UO2 (5.0 w/o)

Active Core Length (m) 2.0

Refuelling Cycle (months) 36

Reactor Coolant System

Design Pressure (MPa) 17

Design Temperature( oC) 360

Core Outlet Temperature (oC) 323

Core Inlet Temperature (oC) 296

Minimum Flow Rate (kg/s) 2,090

History of SMART Development (1/2)

29 July-2 August 2013 7

Conceptual Design (’97.7-’99.3)

NSSS & Desalination Concept (330 MWt) Fundamental T/H Experiment Mock-up Fabrication

NSSS Basic Design (’99.4-’02.3)

NSSS Design (330 MWt) Design Methodology & Computer Codes Preliminary Safety Analysis Desalination System

SMART-P Development (’02.7-’06.2)

Detailed Design (65 MWt) including Fuel & BOP Tech. Verification Tests Safety Analysis

SMART Pre-Project Service (’06.7-’07.6)

System Optimization Economic Feasibility Study (660 MWt)

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014

Conceptual

Design

Basic

Design

SMART-P

Development

Pre

Project

Design

Optimiz

-ation

Domestic Const.

& Export

Standard Design Approval (’09.1-’12.7)

Standard Design (330 MWt) Separate / Integral Effect & Performance Tests Design Methodology & Codes Verification

SMART Standard Design

Approval

6th IAEA INPRO Dialogue Forum on Licensing and Safety Issues

History of SMART Development (2/2)

29 July-2 August 2013 8 6th IAEA INPRO Dialogue Forum on Licensing and Safety Issues

Verification

Mockup Tests

S/G, RCP, CRDM, etc.

Separate Effect Tests for Transients

Digital Safety System Verification Tests

Integral T/H Verification Tests

Fuel Development & Test

License Standard Design

SSAR, CDM,

ITAAC, etc

Topical Report for Licensing Approval

0 10 20 30 40 50

0.00

0.50

1.00

1.50

Blockage Center Line (18.75 in)

Measured

COBRA (Uniform Axial Noding)

MATRA (Nonuniform Axial Noding)

No

rma

lize

d A

xia

l V

elo

city

Ublo

cked/U

bundle

Axial Location from Rod Bundle Inlet (in)

1k 10k 100k

1k

10k

100k

-40%

+40%

Henry and Fauske Model

Pre

dic

ted

Cri

tica

l M

ass F

lux [kg

/m2s]

Measured Critical Mass Flux [kg/m2s]

KAERI (w/o NC)

KAERI (with NC)

Celata et al. (w/o NC)

Celata et al. (with NC)

System Design and Analysis Methodology, Fuel Design Technology

SDA

Improvement/ Applicability Evaluation

SMART-330

NSSS Basic Design

Small Scale Component Tests

Separate Effect Tests

MMIS Essential Tech. Verification Tests

Small Scale Hi Temp. & Pres. Tests

Des

ign

&

Lic

ensi

ng

S/G, RCP, CRDM, etc.

Computer Program Development

Reactor Design Methodology

Har

dw

are

Val

idat

ion

Tes

ts

Met

ho

do

log

y

SMART Basic Design

Construction

Regulatory Authority in Korea


Chairperson

(Chief Regulatory Officer)

KINS

Radiation Emergency

Bureau

Nuclear Regulatory

Bureau

Advisory Committee

on Nuclear Safety

and Security

(15 members)

KINAC

Non-Executive

Commissioners (7)

NSSC (9 commissioners)

Public Relations and

International Cooperation

General Administration

Planning and Budget

Technical Support Organization

Standing Member

(Secretary General)

Working Mechanism in Regulation

29 July-2 August 2013 10 6th IAEA INPRO Dialogue Forum on Licensing and Safety Issues

Nuclear Safety & Security Commission

Korea Institute of Nuclear Safety

(KINS) Submit Information and Implementation Results

Conduct Inspection and Request Additional Information

Nuclear Industries

Licensing Process

• Normal protocol: 2 step licensing (C/P to O/L)

• SDA is an optional licensing process for design certification

• Approved items in the standard design are exempted from license

review

• Reduces licensing uncertainty and risk for construction

• Provides accredited reactor safety and environmental statement for

construction


Operation

SDA

Application (optional)

• SSAR

• CDM

• EOP etc.

• PSAR

• RER

• QA Program

CP

Application

• FSAR

• Tech. Spec.

• RER

• QA Program

OL

Application

Construction Standard

Design

Framework of Nuclear Laws


Industrial Codes and Standards

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

The Act provides the bases and fundamental matters

regarding the development and utilization of nuclear energy

and safety regulations

Nuclear

Safety Act

Enforcement

Decree of the Act

Enforcement Regulation

of the Act

Notice of NSSC

Regulatory Standards

Regulatory Guides

Safety Review & Inspection Guides

The Decree provides particulars entrusted by the Act and

necessary for the enforcement of the Act

The Regulation provides the technical standards and

particulars entrusted by the Act and the Decree such as

detailed procedures and format of documents

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 Regulatory Standards and Guides provide the

interpretation, detailed criteria, acceptable methods,

conditions, and specifications of the technical standards.

The Safety Review & Inspection Guides provides the staff

guidance in carrying out regulatory activities.

Nuclear Laws for SDA (1/2)

• SDA application

• (Article 12(1), Nuclear Safety Act) Any person who intends to repeatedly

construct the nuclear power reactor of the same design and install related

facilities may obtain approval for such design from the Commission

• Application submittals

• (Article 12(2), Nuclear Safety Act) 1. Specification on the standard design

and other documents

• (Article 11(3), Enforcement Regulation of the Nuclear Safety Act) 2.

Explanatory statement on the use of the nuclear reactor, 3. Explanatory

statement on technical capabilities in respect to the design of the nuclear

reactor, 4. Safety analysis report on the standard design, 5. Preparation

plan for emergency operating procedures, 6. Articles of incorporation (in the

case of a juridical person only).


Nuclear Laws for SDA (2/2)

• Valid period of SDA

• (Article 12(3), Nuclear Safety Act) The valid period of the approval shall be

ten(10) years, and the Commission may order any person who has been

granted the approval for the standard design to correct or supplement the

approved matters.

• Subject of exclusion from SDA

• (Article 12(6), Nuclear Safety Act) (Article 24, Enforcement Decree of the

Nuclear Safety Act) 1. Items that need continuous reflection of new

technology to enhance safety; and 2. Items for which the confirmation of

safety is impossible before purchase, installation and completion of

construction.

• Level of depth for SDA

• (Article 12(3), Enforcement Decree of the Nuclear Safety Act) A safety

analysis report on the standard design shall specify technical information in

such details that would allow the verification of the safety.


SMART SDA – Process (1/3)

• Application of SMART for SDA

• Applicant : KAERI/KEPCO

• Reactor Type : Integral PWR(330 MWth)

• Design Life : 60 years

• Application Date : December 30, 2010

• Code Cut-off Date : December 31, 2008

• Submittals

• Standard Design Description

• Objectives of Reactor Applications

• Specification of the Standard Design(Certified Design Material)

• Standard Safety Analysis Report

• Preparation Plan for Emergency Operating Procedures



• Regulatory review by KINS

• Review Period

• January 2011 - May 2012(17 months)

• Standards

• Article 12 (Approval for Standard Design) of Nuclear Safety Act

• Review Results

• The location, structures, equipment and performance of a SMART

conformed to the technical standards prescribed by the Regulation of

the Commission

• It conformed to the standards prescribed by the Presidential Decree in

order to protect public health and environment from the radioactive

materials generated by its construction and operation.



• Review by Advisory Committee on NSSC

• Items to be Reviewed

• Standard design of SMART and KINS review results

• Review Results

• Standard design of SMART conformed to the technical standards as

prescribed by the regulations

• Approval by NSSC

• Standard design approval of SMART issued on July 4, 2012


SMART SDA – Major Licensing Issues

• Basis for the accident classification of single rod withdrawal

• Evaluation of source terms from radioactive waste system based

on ANSI/ANS 18.1-1999 for long-cycle operation

• Basis for the design application of ALARA concept

• Verification of safety analyses code

• Scalability of small integral test facility

• Depth and scope for SDA

• Completeness of design and level of design enough to SDA

• Comprehension of information concerning operation and

maintenance


SMART SDA – Fukushima Action Plans

• After Fukushima accident, regulatory authority in Korea

performed detailed safety inspection on operating plants

• 50 items were derived to enhance safety, reflection of them was recommended for

SMART

• For SMART, 34 items were applicable

• 10 items for standard design, 8 items for construction, and 16 items for operation

• Fukushima actions implemented in standard design

• Adding automatic seismic trip system @ earthquake > 0.18g

• Strengthening a seismic design for MCR panel

• Providing watertight door & drain pump

• Securing mobile generator & battery

• Preparation of measure to cool-down spent fuel pool

• Providing external safety injection flow path

• Providing passive autocatalytic hydrogen recombiner etc.


Pre-Application Review (1/2)

• Overview of pre-application review

• To resolve the safety issues prior to SDA review

• Review period : Feb. 2010 ~ Dec. 2010 (Application date of SDA)

• Documents to be reviewed

• System Description

• Preliminary Standard Safety Analysis Report

• Phenomena Identification and Ranking Table (PIRT) of Thermal

Hydraulic Phenomena

• Technology Validation Test Program

• Technical Reports for Design Methodologies and Codes


Pre-Application Review (2/2)

• Issues from pre-application review

• Applicability of the existing regulatory requirements

• Not necessary to make a new regulatory rule for SMART application

• Major review comments and suggestions for SDA

• Additional validation of safety analysis code

• Basis for the elimination of large break LOCA

• Verification test for PRHRS performance

• Test for flow measurement at pump suction, etc


Regulatory Research for Audit Calculation (1/2)

• Overview of regulatory research

• For efficient licensing review, identifying and resolving the safety issues

from the early design stage were necessary.

• The regulatory research had been performed to develop regulatory

assessment technologies considering specific characteristics of the SMART

design.

• Research period : Dec. 2008 ~ July 2012 (Approval)

• Audit calculations were made for several important areas using

the regulatory assessment technologies developed ;

• Reactor core analysis

• Safety analysis

• Severe accident analysis

• Probabilistic safety assessment

• Structural integrity assessment, etc.


Regulatory Research for Audit Calculation (2/2)

• The results of audit calculations showed that the important

design parameters were properly established with sufficient

safety margin, satisfying the acceptance criteria required in the

relevant design basis.


Summary

• For the licensing of SDA of SMART developed by

KAERI/KEPCO, KINS reviewed documents related to the

SMART.

• The location, structures, equipment, performance and the

construction of a SMART were found to confirm to the technical

standards.

• Therefore, the standard design of SMART was approved by

NSSC on July 4, 2012.


Lessons-Learned


1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013

Conceptual

Design

Basic

Design

SMART-P

Development

Pre-

Project

Design

Optimiz

-ation

Next

Step

SMART Standard Design

Approval

Regulatory Research

for Audit Calculation

Pre-

App.

Review

SDA

Review

Design

Regulatory

Research

Licensing

Review

Additional activities, pre-application review and regulatory research, contributed to a successful SDA review by providing

regulatory insight for safety review and licensing process in a timely manner.

For Safe and Smart

SMART

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