1879-3
Nuclear Power Plant Simulators for Education
29 October - 9 November, 2007
lecture notes
S.-G. Moon International Atomic Energy Agency Division of Nuclear Power Vienna Austria EvolutionEvolution ofof FullFull--ScopeScope SimulatorsSimulators DevelopmentDevelopment---- KoreanKorean experienceexperience
Workshop on NPP Simulators for Education 2 November, 2007 Miramare- Trieste, Italy
1 ContentsContentsContents
I. Introduction of Nuclear Power in Korea
II. Evolution of Full –Scope Simulator in Korea - Status, Development History - Application of Advanced Simulator Technology III. Operator Training Program IV. Conclusion
2 Geological location
Population : 48.3 millions Area : 99,646 x 1000 km2
3 Brief History of Nuclear Power in Korea
• 1957 Joining the IAEA (International Atomic Energy Agency) • 1958 Promulgation of Atomic Energy Law • 1959 Start construction of 1st Research Reactor (TRIGA Mark-II) (completed • in 1962) • 1968 Set-up basic plan for introduction of 1st NPP • 1969 Set-up construction plan for 1st NPP, Kori #1 (PWR 587MWe) • 1971 Start construction of 1st NPP, Kori #1 • 1978 Commercial operation of 1st NPP, Kori #1 • 1983 Commercial operation of 2nd NPP(Kori #2) and 3rd NPP (Wolsong #1) • 1995 Exceed 500 Billion KWh of Nuclear Power Generation • (9 NPPs in Operation) • 1997 Exceed 10,000 MW of Nuclear Installed Capacity (12 NPPs in Operation) • 2001 Establish “ Basic Plan for Restructuring of the Electricity Supply Industry” • 2005 20 units in Operation (The installed capacity is 17,716 Mwe)
4 Korea’s Nuclear Related Organizations
PresidentPresident PrimePrime Minister Minister Scientific Technology Commission Atomic Energy Commission z Ministry of Commerce, Industry MOST(Ministry of & Energy Science & Technology) z Ministry of Planning & Budget Nuclear Safety Commission
Academia Nuclear Industries KAERI KINS z Utility : KHNP z Universities zNuclear Vendors : KOPEC, z Other Research KNFC, DOOSAN Institutes National R&D Safety & program Regulation
z KHNP: Korea Hydro & Nuclear Power Company z KNS: Korean Nuclear Society z KOPEC: Korea Power Engineering z KAIF: Korea Atomic Company Industrial Forum z KNFC: Korea Nuclear Fuel Company z KNEF: Korea Nuclear Energy Public z DOOSAN: DOOSAN Heavy Industries & Foundation Construction Company z News Media, NGOs, Local Society
5 NPPs & Operator Training Centers in Korea
20 NPPs - operating 8 NPPs – constructing or planning 4 Nuclear Power Training Centers - 7 NPP FSSs
Westinghouse (PWR)
Framatom (PWR)
OPR (PWR) Ulchin-1,2,3,4,5,6(PWR) Seoul OPR+ (PWR)
APR (PWR)
CANDU (PHWR) Wolsong-1,2,3,4(PHWR)
Kori-1,2,3,4 Yonggwang-1,2,3,4,5,6
Shin-Kori-1,2,3,4 6 Nuclear Power Plants in Operation 20 units, 17,716 MWe Reactor Capacity NSSS Plant Commercial Plant Type (MW) Supplier A/E Operation #1 PWR 650 W/H Gilbert ’78.04 Kori #2 PWR 587 W/H Gilbert ’83.07 #3 PWR 950 W/H Bechtel/KOPEC ’85.09 #4 PWR 950 W/H Bechtel/KOPEC ’86.04 Wolsong #1 PHWR 679 AECL AECL ’83.04 #2 PHWR 700 AECL/DOOSAN AECL/KOPEC ’97.06 #3 PHWR 700 AECL/DOOSAN AECL/KOPEC ’98.06 #4 PHWR 700 AECL/DOOSAN AECL/KOPEC ’99.09 #1 PWR 950 W/H Bechtel/KOPEC ’86.08 Yonggwang #2 PWR 950 W/H Bechtel/KOPEC ’87.06 #3 PWR 1,000 DOOSAN KOPEC ’95.03 #4 PWR 1,000 DOOSAN KOPEC ’96.01 #5 PWR 1,000 DOOSAN KOPEC ’02.05 #6 PWR 1,000 DOOSAN KOPEC ’02.12 #1 PWR 950 Framatome Framatome ’88.09 Ulchin #2 PWR 950 Framatome Framatome ’89.09 #3 PWR 1,000 DOOSAN KOPEC ’98.08 #4 PWR 1,000 DOOSAN KOPEC ’99.12 #5 PWR 1,000DOOSAN KOPEC ’04.07 #6 PWR 1,000 DOOSAN KOPEC ’05.04 NSSS : Nuclear Steam Supply System, A/E : Architect Engineering
7 NPPs Under Construction / Preparation/Planning
8 Units : 9,600 MWe
Reactor Capacity Commercial Project Plant Type Type (MW) Operation*
#1 PWR 1000 OPR1000+ Dec. 2010 #2 PWR 1000 OPR1000+ Dec. 2011 Shin-Kori #3 PWR 1400 APR1400 Jul. 2012 #4 PWR 1400 APR1400 Jul. 2013 Shin- #1 PWR 1000 OPR1000+ Oct. 2011 Wolsong #2 PWR 1000 OPR1000+ Oct. 2012 Shin- #1 PWR 1400 APR1400 June. 2014 Ulchin #2 PWR 1400 APR1400 June. 2015 * The target dates for commercial operation are being adjusted project due to the local governments’ construction work licensing process.
8 Status of Electric Power
Korea is the 6th largest nuclear power country in the world. KHNP is the world’s 5th largest nuclear power company.
3,879 17,716 22,254 5,822 130,715 4,666 130,715 6.5% 56,004 6.5% 1.7% 7.8% 27.9% 16.4% 38.2% 26.2% 29.1% 37.2%
15,746 17,954 127,164 Installed Capacity: 59,961 MW Generation: 341,959 GWh
Nuclear Coal Gas Oil Hydro
9 Operational Performance
100 Trend of Average Capacity Factors
(%)90 95.5 80
70 78.3
60 KHNP Wo rld 50 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 01 03 04 05 KHNP 78.1 81.5 73.0 76.2 79.3 84.4 84.5 87.2 87.4 87.3 87.5 87.6 90.2 88.2 90.4 93.2 92.7 94.2 91.8 95.5 World 66.9 66.7 65.9 64.8 65.7 67.8 67.3 69.4 70.2 71.6 72.9 72.1 73.7 75.6 76.4 78.9 78.9 76.5 78.8 79.3 Korean reactors have shown excellent performance !
10 II. Nuclear power plant simulation Full scope simulator of nuclear power plant
Standard Requirement: ANSI/ANS3.5-1998 • Nuclear Power Plant Simulators for Use in Operator Training and Examination
11 Simulator Regulatory Relationships
Part 55 ES-301-3 ES-604 Scope & ANSI 3.5 10 CFR 55 Comments RG 1.149 Scenario Attchmt 3 Desing Standard Summary Checklist B.1.c
ES-604-1 Scenario Verification NRC NUREG Checklist Form 474 1262
Validation Simulator Acceptance Periodic Testing NRC NUREG Simulator 1258 Evaluation Simulator Training, Fidelity Testing & Exam Feedback
Content SAT Plant Difficulty Validity Programs Mods Exam Training
12 Role of Full Scope Simulator Training
Maintain the required level of competence of operations personnel as defined for the initial training
Train all significant modifications of plant operation caused by improvements and alterations of the Plant or Procedure
Emphasize on Emergency Procedures in the handling of unforeseen Events
13 Types of Simulator and Uses
Full-scope simulator - A replica control room and simulates the NSSS and the BOP system for a reference plant Part-task simulator - Designed for training on a specific subset of plant operation or on a special phenomenon ex) Thermo hydraulic simulators and simulators for training in relation to steam generator tube rupture Basic principle simulator - Illustrates general concepts, demonstrating and displaying the fundamental physical processes of the plant. - ex) Based on PCs and Specific system modeling (RCS,etc.)
14 ⅡⅡ.. Evolution Evolution ofof SimulatorSimulator DevelopmentDevelopment
15 Status of Full Scope Simulator in Korea
Reference Operation Location Manufacturer Application Remarks Plant Date PWR #1 KOR #2 Nov. ’98 Samsung KOR #1&2 KOR 650MWe T/C PWR #2 KOR #3 Dec. ’86 W/H(USA) KOR #3&4 950MWe Thomson- PWR #1 UCN #1 Jan. ’89 UCN #1&2 UCN CSF(France) 950MWe T/C PWR #2 UCN #3 Mar. ’02 Samsung UCN #3,4,5,6 1000MWe PWR #1 YGN#3 Apr. ’96 Samsung YGN #3,4,5,6 YGN 1000MWe T/C PWR #2 YGN#1 Sept. ’06 Samsung YGN #1,2 950MWe WSN PHWR WSN #2 Dec. ’98 CAE(Canada) WSN #1,2,3,4 T/C 700MWe
Originally, KOR #1 Simulator was the copy of Surry Simulator, in 1979, but KHNP has changed into Reference Plant of Kori #2 manufactured by Samsung in 1998
16 Evolution of Full Scope Simulator in Korea
1970's1970's 1980's1980's 1990's1990's 2000's2000's nd 1ststStage 2 ndStage 1 Stage 2 Stage 3rd3rd Stage Stage 4th4th Stage Stage TechnologyTechnology Turn-KeyTurn-Key NonNon Turn-Key Turn-Key Localization TransferTransfer Localization UCN#3(OPR)(2002), KRNKRN #1(W #1(W)) KRN#2(WKRN#2(W)(1998),)(1998), UCN#3(OPR)(2002), KRNKRN #2(W #2(W)(1986),)(1986), YGN #2(OPR)(2006), (1979)(1979) YGNYGN #1(OPR)(1996), #1(OPR)(1996), YGN #2(OPR)(2006), UCNUCN #1(F)(1989) #1(F)(1989) SKN#1(OPR+) WSN#2(PHWR)(1998)WSN#2(PHWR)(1998) SKN#1(OPR+) SKN#3(APR)SKN#3(APR) Foreign Prime Contractors Local Prime Contractors Local Prime Contractors Foreign Contractor Foreign Prime Contractors Local Prime Contractors Local Prime Contractors Foreign Contractor Local Sub-contractors Foreign Simulation SW Local Sub-contractors ForeignForeign Simulation Simulation SW SW Foreign Simulation SW VRVR Technology Technology Technology Technology Technology Technology TechnologyTechnology TechnologyTechnology Dependency Acquisition Dependency Acquisition Self-RelianceSelf-Reliance Self-DevelopmentSelf-Development
17 Evolution of Full Scope Simulator in Korea (Stage I – Buying a ready made simulator)
1970's1970's
st 11stStageStage
Turn-KeyTurn-Key
KRNKRN #1(W #1(W)) (1979)(1979)
ForeignForeign Contractor Contractor (EAI:USA)(EAI:USA)
TechnologyTechnology DependencyDependency Vendor( ) has supplied the Kori-1 NPP and a full scope simulator which is a copy of the Surry simulator Kori#1( W PWR 3 loops ) vs. Surry (W PWR 4 loops)
18 Evolution of Full Scope Simulator in Korea (Stage II- Replica FSSs / local sub contractor)
1980's1980's
nd 22ndStageStage
NonNon Turn-Key Turn-Key
KRNKRN #3(W #3(W)(1986),)(1986), UCNUCN #1(F)(1989) #1(F)(1989)
Foreign Prime Contractors Foreign Prime Contractors Local Sub-contractors Local Sub-contractors
TechnologyTechnology AcquisitionAcquisition Vendor( ) has supplied a full scope simulator for KRN#2 with the co-work of local engineering company,KOPEC. Vendor( Framatom) has supplied a full scope simulator for UCN#1 with the co-work of local engineering company,KOPEC.
19 Evolution of Full Scope Simulator in Korea (Stage III - Replica FSSs / localization project) PWR
1990's1990's
3rd3rd Stage Stage TechnologyTechnology TransferTransfer KRN#2(WKRN#2(W)(1998),)(1998), YGNYGN #1(OPR)(1996), #1(OPR)(1996), WSN#2(PHWR)(1998)WSN#2(PHWR)(1998)
LocalLocal Prime Prime Contractors Contractors PHWR ForeignForeign Simulation Simulation SW SW
TechnologyTechnology Self-RelianceSelf-Reliance
20 Evolution of Full Scope Simulator in Korea (Stage III – 3 Pack Project) 1994 Jump starting strategy
UNIX based Two(2) NPP FSSs + One(1) FP FSS
21 Evolution of Full Scope Simulator in Korea (Stage IV – Self Development)
RehostingRehosting,, Unix Æ Windows 2000's 2000's UpgradeUpgrade WS Æ PC server 4th4th Stage Stage RETRAN, RELAP LocalizationLocalization UCN#3(OPR)(2002),UCN#3(OPR)(2002), BestBest Estimate, Estimate, based real-time TH model YGN #2(OPR)(2006), YGN #2(OPR)(2006), TH,TH, CR CR model model MASTER based real- SKN#1(OPR+)SKN#1(OPR+) SKN#3(APR)SKN#3(APR) time 3D core model (Under(Under Development) Development)
LocalLocal Prime Prime Contractors Contractors MAAP4-DOSE based ForeignForeign Simulation Simulation SW SW SevereSevere VR Technology VR Technology AccidentAccident real-time severe accident TechnologyTechnology model Self-DevelopmentSelf-Development Virtual Plant VirtualVirtual reality reality Virtual MCR
CBT 22 Evolution of Full Scope Simulator in Korea (Stage IV – Rehosting & Upgrade) KNPEC-2 Simulator Upgrade
In January 2001, KEPRI rehosted and upgraded the KNPEC-2(KRN#2) Simulator.
23 Evolution of Full Scope Simulator in Korea (Stage IV – Rehosting & Upgrade) ScopeScope ofof KNPECKNPEC--22 SimulatorSimulator UpgradeUpgrade
I/O Upgrade
GOULD MPX-> PC NT
Updating of Design V&V Change GUI based I/S VRCATS New Neutronics & NSSS New Aux. & BOP System T/H Model
24 Evolution of Full Scope Simulator in Korea (Stage IV – Re-hosting & Upgrade)
Technology KNPEC-2 Simulator TM Operating System & Executive Windows- NT, SSP3.4 Core Model 2 Group REMARKTM NSSS RETRAN-3D based ARTS-01 Thermal-hydraulics (Advanced Real time Thermal-hydraulic Simulation model) Fluid System Models Single and Two phase model builder FlownetTM, GflowTM ,TOPMERETTM Instructor Station DataviewsTM Classroom Training System VRCATS -Ⅰ(Virtual Reality Computer Assisted Training System) Personal Training System PCATS -Ⅰ(Personal CATS) DBA included
25 Evolution of Full Scope Simulator in Korea (Stage IV – Developing Advanced FSS)
OPR1000(Korea Standard Nuclear Power)
26 Evolution of Full Scope Simulator in Korea (Feature of OPR1000 FSS)
Technology KSNP Simulator Operating System & Executive Windows-NT, SSP3.4
Core Model REMARKTM NSSS Thermal-hydraulics ARTS ( ÅRETRAN3D) Severe Accident Model RSAM ( ÅMAAP4-DOSE) Fluid System Models Single and Two phase model builder GFlowTM, TOPMERETTM Logic and Central Models CLASCTM, Logic builder Instructor Station DataviewsTM Classroom Training System VRCATS-Ⅱ Personal Training System PCATS -Ⅱ
27 Evolution of Full Scope Simulator in Korea (Main Features of APR1400 MCR)
Large Display Panel Advanced Alarm System
Soft Control Safety Console (Backup Panel)
Computerized Procedure System
Compact Operator Console
28 Evolution of Full Scope Simulator in Korea (Feature of APR1400 FSS)
Operator Console Safety Console
MMI xxxMMI xxx MMI
CPS GMC Sim. Data HUPES Server Server Server Server S
•CPS: Computerized Procedure System •HUPESS: Human Performance Evaluation Support System •GMC: General MMIs Control
29 Evolution of Full Scope Simulator in Korea (Stage IV – Best estimate engineering)
Fidelity Improvement by employing BE code as NSSS T/H engine for training simulator • avoid negative training possibility due to overly simplified models and assumptions and can be used as safety evaluation tool for the transient analysis Essential technology for developing the state-of-art training simulators • Based on BE codes : USA ( RELAP-R/T, theater.. ), France (CATHARE2 ), etc.
Why RETRAN? • RETRAN is one of the most widely used in many utilities in the world. • Most of utilities have RETRAN specialist and input deck data base. • Using the safety analysis input for developing simulator T/H model gives cost and time saving Easy for maintenance and upgrade • Easy to replace with an up-to-dated RETRAN if needed • Usually no need to develop / improve NSSS T/H engine for training simulator
30 Evolution of Full Scope Simulator in Korea ARTS(Advanced Real Time Thermal-Hydraulic Simulation)
Development of backup calculation model for robustness • Limitation of RETRAN: difficult to simulate LBLOCA, mid-loop operation • Developed to insure the continuous calculation when ARTS fails RCS modeling: HEM (Homogenous Equilibrium Model) • Primary system two regions of pressurizer and RCS (mass, energy, momentum) • Secondary side of SGs single region for each SG (mass, energy) • ARTS Properties of all volumes and junctions are obtained explicitly using the calculation results of backup model
31 Evolution of Full Scope Simulator in Korea ARTS(Advanced Real Time Thermal-Hydraulic Simulation)
March 2004 ~ September 2006 (30 Months) Geometric modeling - Reference plant : YGN unit 1, Westinghouse type, 900MWe, 3-loop plant - Nodalization: 62 volumes, 125 junctions (for real-time calculation on 4 Pentium III 500MHz CPUs machine)
A: Atmosphere (900) B: SG Blowdown Flash Tank(914) C: Containment atmosphere (902) D: Condenser (904) SL P: Pressurizer relief tank (906) SL SL T: Turbine (908) 619 F22 639 F23 659 F23 SL: Steam Line PORV(Compensated)
W: Component Cooling Water System(912) PORV(Actual) 618 638 658
SVs 617 617 From RCDT 637 637 657 657 751 752 753 Vent N source 615 2 V15 V16 V17 635 655 Spray
614 C FLB 634 C FLB 654 C FLB Vent 826 V33 755 743 827 V34 828 V35 V18 235 MAIN P 335 MAIN 435 MAIN 761 F16 PR ZR C 763 F18 765 F20 Head Vent 807 AUX V26 AUX 430 440 AUX 240 230 762 F17 330 340 764 F19 766 F21
520 610 610 Drain to RCDT 245 630 345 630 650 445 650
225 Head Vent 325 425 Flange Open C Vent C RHR Suction Loop C RHR Suction Loop A & Leak 707 250 220 320 350 420 450 706 V9 709 822 515 823 821 V8 V11 V31 V30 V32 611 611 631 631 651 651 SI Break SI Break SI Break 510 818 C 190 C 819 C 820 255 215 315 355 415 455 V51 714 721 804 715 805 V52 716 722 806 V53 185 F4 F7 V23 F5 V24 F6 F8 V25 260 210 505 310 360 410 460 B B B 181 183 182 183 265 B/D 701 200 300 702 B/D 365 400 703 B/D 465 V4 V5 V6 205 180 305 405 C V1 V2 C V3 C Crossover Leg Leak 181 182 Crossover Leg Leak Crossover Leg Leak C 285 385 C 485 C 808 V54 280 290 390 380 809 V55 490 480 810 V56 295 119 139 129 395 495 CVCS L/D Loop A 495 171 170 470 F9 270 370 725 155 C TYGON HOSE CVCS EX L/D Loop C 133 169 168 704 V7 726 F10 711 728 741 712 727 742 Drain 713 Drain C W 167 166 C C W C C W C Drain F1 F12 F13 110 130 120 F2 F11 F14 F3 C 150 732 V13 733 V14 SI/RHR CVCS ALT Chg Loop ChgCVCS A ALT SI/RHR RCS to Inj. Seal RCP Chg. CVCS Spray 731 V12 SI/RHR Spray 801 811 800 802 812 803 813 165 164 V20 V27 113 V19 V21 V28 V22 V29
275 Leak Chg. CVCS CL Break 375 475 RCP Leak T/B CL Break RCP Leak T/B CL Break CL RCP T/B Leak
163 162 123
115 135 161 160 125
145 159
140 Loop A Loop B Loop C 708 V10
C 32 Drain Evolution of Full Scope Simulator in Korea Improvement of RETRAN for ARTS
Improvement of robustness and real-time calculation capability • Simplifying state equation for liquid + noncondensiable condition (drain operation) • Simplifying interfacial heat / mass transfer and heat transfer correlations and removing discontinuities
33 Evolution of Full Scope Simulator in Korea (Full scope simulator - Classroom – Personal Training)
1150 RETRAN SIMULATOR
1100
1050
1000 S/G 1 Pressure 950
900 0 10 0 20 0 3 00 4 00 5 00 Time After Scram (Sec)
Classroom Training Sys Personal Training Sys Full Scope Simulator VRCATS PCATS
-For MCR Operators - For MCR/Local Operators -For Operators/Personnel of the NPP - Operations, Skills, Rule - Knowledge, Concepts Symptom - S/W : Full Scope - S/W : Limited Scope - S/W : Full Scope - H/W Scope : MCR/Local Plant - GUI - H/W Scope : MCR - VR, Multimedia, MMI - Requirements of - Instructor Assistance Tool Standard - Self training System
34 Application fields of simulation technology
Not only training but many engineering fields.
Virtual Prototyping - HFE V&V
Human-System Interface Training Engineering - Operator, I&C - Design, Analysis Real time Simulation
Best estimated engineering codes Integration test - DCS V&V
35 Application fields of simulation technology
Training Full Scope Simulator
Integration test Engineering
Virtual Prototyping
36 Application fields of simulation technology (cont’d) MMIS-Nuclear plant analyzer
37 Application fields of simulation technology (cont’d) CBT-VR MCR
38 Application fields of simulation technology (cont’d) V&V of Human Factors Engineering (HFE)
APR1400(SKN-3&4) MCR HUPESS
Physiological Data
Virtual MCR APR1400(SKN-3&4) PLANT
Simulator HFE VV Support System 39 Application fields of simulation technology (cont’d) HFE Verification & Validation Activities for APR1400
Stage Activities Objective
SV Demonstrating no existence of “show stopper ” Stage 1 (1998) HED (Human Engineering Deficiency) identification Development PV Evaluate ACR MMI against conventional MMI
Stage 2 Demonstrating basic adequacy for the various MMI resources (2000~2003) ACR (Advance Control Room) issue testing Development and PV1 (&SV1) HED identification Design Evaluate ACR MMI against conventional MMI Certification
PV2 (&SV2) Demonstrating that MCR ensemble fundamentally supports safety operation PV3 ACR issue testing PV4 HED identification Evaluate ACR MMI against conventional MMI
PV5 Addressing the HFE issues raised by the regulatory body HED identification
Stage 3 PV6 (&SV3) Demonstrating that MCR ensemble supports safety operation and (2007~2010) power production operation Construction Demonstrating basic adequacy for DCS/PLC MMI adopted PV7 (&SV4) ACR issue testing HED identification Evaluate ACR MMI against conventional MMI
Final HFE V&V Final Demonstrating that MCR ensemble supports safety operation for the Operating License of APR1400 HED identification
40 Application fields of simulation technology (cont’d) Validation of Operating Procedure
Validating Operating Computerized Procedure Procedure by Using the System for APR1400 Simulator
41 Application fields of simulation technology (cont’d) DCS Integration test and V&V
ITS System for DCS V&V, MCR upgrades 42 Staff Training Program
Training Process
KNPEI Each Site Each Site Each Site
Recruit Operator Operator Recruit FundamentalFundamental PlantPlant Operator Operator OnlyOnly Training programprogram coursescourses FamiliarizationFamiliarization Training 13 weeks 20 weeks SpecialSpecial TrainingTraining beforebefore majormajor Commissioning teststests ExperiencedExperienced Commissioning OOOO J JJJ TTT QualificationQualification ProgramProgram CommissioningCommissioning 1 weeks LevelLevel2 weeks 1~31~3 GeneralGeneral
• KNPEI : KHNP Nuclear Power Education Institute • Each Site (Kori, Wolsong, Ulchin, Yonggwang) has Training Center
43 Staff Training Program (cont’d)
Recruitment Program
No. Course Location Duration
1 Orientation KNPEI 3wks
2 Nuclear Theory Fundamentals KNPEI 7wks
3 Nuclear Plant System Fundamentals KNPEI 3wks
4 Plant Familiarization (OJT-Ⅰ) Site 7wks
5 System Details (Each Reactor Type) Training Center 7wks
6 Plant Familiarization (OJT-Ⅱ) Site 6wks
* Totally 33 weeks required to cover all the fundamental courses.
44 Staff Training Program (cont’d)
Operator Training
No. Course Location Duration
1 Operator Local Training Site 6 weeks
2 FCO and OM Training Site 4 weeks
3 MCR Operator Applicant Training Center 10 weeks Renewal training for 4 Training Center 7 weeks RO/SRO License
5 MCR Operator Refresher Training Center 6 weeks
* The training center is one of the divisions in each NPP station.
45 Staff Training Program (cont’d)
MCR operators/unit ¾1 Shift supervisor/ 1 Safety supervisor ¾1 Reactor operator/ 1 Turbine operator ¾1 Electrical operator Training Plan ¾6 weeks simulator training before initial fuel loading and then 2 weeks retraining every 4 month ¾All MCR operators have to be trained using exactly same design simulator ¾Seven simulators based on reactor design differences in KHNP
46 Organization of Staff Training (cont’d)
KNPEI : KHNP Nuclear Power Education Institute ¾Established as a Training Section in Kori NPP site ¾Authorized as the Training Center for Reactor Operators and RO/SRO Licensee Renewal Training Center by government ¾ Awarded the “Letter of Recognition” as an excellent Training Center by IAEA ¾Taking charge of fundamental courses ; Nuclear theory, Plant system, C&I, Electrical maintenance,Safety culture, chemical control
Training Center ¾ Simulator training for operators including MCR and Local operator retraining course includes System and practical training for staffs each NPP division ¾ Each NPP division (Kori, Wolsong, Ulchin, Yonggwang) has four training center
47 Concluding Remarks
New Opportunities for Nuclear Power • Energy and the environmental issues are at the core of future economic development • Climate Change Conventions and today’s outstanding reliability of nuclear power can open new opportunities
New trend of energy policy seems to already begin • Many countries think over nuclear power and phase-out policies • License renewal and power uprating are active worldwide • Worldwide efforts to develop new reactor systems are on the way
Simulation and VR technology are becoming new emerging technology for nuclear industries
48 Concluding Remarks
Simulation and VR technology are becoming new emerging technology for nuclear industries . Application fields of NPP Simulation technology • Training ; Full Scope Training Simulator • Engineering ; Nuclear Plant Analyzer • HFE V&V, DCS V&V etc.
Virtual Reality Applications on Nuclear Power industry • VRCATS, a web based classroom training system, is developed by KEPRI and it is one of example of the intelligent VR system which is connected with real time simulator. • VR is evolving from simple 3D interactive viewer to universal engineering interfacing solution and HSI V&V tools.
49 …Thank you for your attention 50