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2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design InstituteZheng MingguangSNERDI Vice President, China
• Graduated (Ph.D. Nuclear Engineering & Science) from Shanghai JiaotongUniversity.
• Responsible for PM of the design of Hongyanhe NPP (4X1100MWe) and Chashma 2 in Pakistan
• Chief Engineer to develop China Advanced Fast Reactor
• Technical supporting service for Operating nuclear power plants
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
2
Prospects of PLiM in ChinaProspects of PLiM in China
SNERDI/SNPTCSNERDI/SNPTCSNERDI/SNPTCSNERDI/SNPTC
Oct. 15, 2007 Shanghai China
Dr. Zheng Mingguang
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
Briefing about SNERDIBriefing about SNERDI
3
1.1. SNERDI SNERDI is specialized in design of NSSS, main is specialized in design of NSSS, main component, I&C, civil engineering, plant engineering and component, I&C, civil engineering, plant engineering and overall design of NPP, located in Shanghai, east China, overall design of NPP, located in Shanghai, east China, was established in 1970, and was established in 1970, and currently with ~900 currently with ~900 staffs. staffs.
2.2. SNERDI is the designer of the first NPP in China SNERDI is the designer of the first NPP in China and one of the major research and design and one of the major research and design institutes on nuclear power plant in China.institutes on nuclear power plant in China.
3.3. SNERDI was a subsidiary of China National SNERDI was a subsidiary of China National Nuclear Corporation (CNNC) and now is unit in Nuclear Corporation (CNNC) and now is unit in State Nuclear Power Technology Corporation of State Nuclear Power Technology Corporation of China (SNPTC) . China (SNPTC) .
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
Brief about SNPTCBrief about SNPTCThe functions of SNPTC are to The functions of SNPTC are to •• Organize and coordinate negotiation Organize and coordinate negotiation
and technology importation and and technology importation and introduction of Gen. III.introduction of Gen. III.
•• Put into commercial operation of 4 pilot Put into commercial operation of 4 pilot units of AP1000 safely and timelyunits of AP1000 safely and timely
•• Ensure Gen. III localization in Ensure Gen. III localization in engineering, manufacturing and project engineering, manufacturing and project managementmanagement
•• Be responsible for the development of Be responsible for the development of Chinese Advanced PWRChinese Advanced PWR
4
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
ContentsContents1. Operating NPPs and prospects in China1. Operating NPPs and prospects in China2. Challenges encountering2. Challenges encountering3. Main AM/PLiM in China3. Main AM/PLiM in China4. Prospective activities of PLiM in China4. Prospective activities of PLiM in China5. Summary and suggestion5. Summary and suggestion6. Acknowledgement 6. Acknowledgement
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2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 1/61/6------Qinshan IQinshan I--19911991
LING AOLING AO
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 2/62/6——DayabayDayabay--19931993
DAYA BAYDAYA BAY
LING AOLING AO
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 3/6 3/6 ––Qinshan IIQinshan II--20022002
QINSHAN IIQINSHAN IIQINSHAN IIQINSHAN IIQINSHAN IIQINSHAN IIQINSHAN IIQINSHAN II
LING AOLING AO
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 4/64/6——Qinshan IIIQinshan III--20022002
LING AOLING AO
Qinshan Qinshan
IIII
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Shanghai Nuclear Engineering Research and Design Institute
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 5/65/6——LingaoLingao--0202
sino-us JCC
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
1. OPERATING NPPS IN CHINA 1. OPERATING NPPS IN CHINA 6/66/6----TianwanTianwan
TIANWANTIANWAN
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
12
1. Prospects1. Prospects–– plants to be built plants to be built •• LingaoLingao II 2X1000MWe II 2X1000MWe (FCD Dec 15 2005)(FCD Dec 15 2005)
•• Qinshan II extension 2X650MWe Qinshan II extension 2X650MWe (FCD Apr 28 2006) (FCD Apr 28 2006)
•• HongyeheHongyehe NPP 4X1000MWe NPP 4X1000MWe (FCD Aug 18 2007)(FCD Aug 18 2007)
•• SanmenSanmen NPP 2XAP1000 NPP 2XAP1000 (FCD Beginning2009)(FCD Beginning2009)
•• HaiyangHaiyang NPP 2XAP1000 NPP 2XAP1000 (6months after SM)(6months after SM)
•• Fangjiashan(QinshanFangjiashan(Qinshan+) 2X1000MWe+) 2X1000MWe•• YangjiangYangjiang NPP 2X1000MWeNPP 2X1000MWe•• NingdeNingde NPPNPP•• FuqingFuqing NPPNPP•• TaishanTaishan
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
ZhejiangZhejiang SanmenSanmen site viewsite view
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
Shandong Shandong HaiyangHaiyang Site viewSite view
sino-us JCC
YangjiangYangjiang SiteSite
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
sino-us JCC
Qinshan (Qinshan (Fangjiashan)SiteFangjiashan)Site viewview
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
17• Yangjiang NPP
• Dayabay siteDaya Bay 2 ××××900 MW PWR, 1994Ling’ao 2 ××××1000MW PWR 2002Ling’ao-II 2××××1000 MW
Sanmen NPP2 units of AP1000
• Qinshan siteQ1 300MW, PWR, 1991Q1 300MW, PWR, 1991Q1 300MW, PWR, 1991Q1 300MW, PWR, 1991
Q2 2××××600MW, PWR, 2002Q3 2×××× 728MW, CANDU, 2003Q2 extend 2×××× 600MW, PWRQ1 extend (Fangjiashan) 2 ××××1000
• Tianwan NPP 2×××× 1000MW, WWER,
• Haiyang 2 units of AP1000
• Hongyanhe NPP4 ×××× 1000 MW
1. Prospects up to 2020 in China1. Prospects up to 2020 in China
18
Nuclear Power Plan in Mainland China up to 2020
2.11.20.3
4.36.0 6.7
8.5
12.5
40
0
5
10
15
20
25
30
35
40
1 99 1
1 99 2
1 99 3
2 00 2
2 00 3
2 00 4
2 00 5
2 01 0
2 02 0
GWe
40 GW in operation
18 GW under construction
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
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Quick economic development Quick economic development Needs more EnergyNeeds more EnergyWhile oil price risingWhile oil price rising
Clean Environment Clean Environment and Sustainable and Sustainable Development need Development need less greenhouse gasless greenhouse gas
How to do? need more NPPsHow to do? need more NPPs
2. Challenges encountering 2. Challenges encountering --11 more Nuclear Power neededmore Nuclear Power needed
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Shanghai Nuclear Engineering Research and Design Institute
2. Challenges encountering 2. Challenges encountering ––22 various supports neededvarious supports needed
20
Government support
Public understanding Safety guaranty
Return of investmentSufficient fuel
supply
Sufficient spare parts supply
Outstanding Achievement of operational NPPs
Sustainable and long-term development for nuclear
power
Two key factorsTwo key factorsSafety and EconomySafety and Economy
2. Challenges encountering 2. Challenges encountering ––33 over 100 aged plantsover 100 aged plants
21
1
5
2
6
3
6
4 43
65 5
9
6
4
1011
14
22
24
3233
21
19
2221
7
15 1516
11
23
15
1011
5
7
3
12 2
0
5
10
15
20
25
30
35
40
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40
Num
ber o
f Rea
ctor
s
Number of units
According to IAEA’s information
~100 units more than 30 years
Ages of totally 435 units in operation 327 units more than 20 yeas
Years of operation
2007-10-15SNERDI/SNPTC
上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院上海核工程研究设计院
Shanghai Nuclear Engineering Research and Design Institute
2. Challenges encountering 2. Challenges encountering ––44 how to get the way outhow to get the way out
1.1. How toHow to have more NPPshave more NPPs and and to maintain to maintain sustainable development : sustainable development : All the operating NPPs shall be operated safely, All the operating NPPs shall be operated safely, reliably and economically reliably and economically as Nuclear industry is as Nuclear industry is sensitive, fragile and no boundarysensitive, fragile and no boundary
2.2. How to ensure safety of operational NPPs:How to ensure safety of operational NPPs:Active and effective plant life management Active and effective plant life management ieiePLiM from the beginning is indispensable PLiM from the beginning is indispensable furthermore 327 units operated over 20 years furthermore 327 units operated over 20 years and 100 over 30 yearsand 100 over 30 years
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2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
2. Challenges encountering2. Challenges encountering––55 differences and difficultiesdifferences and difficulties
In China, only 3 of the 11 operational units have In China, only 3 of the 11 operational units have operated more than 10 years and PSR performed in operated more than 10 years and PSR performed in time. time. Others are to be built. Others are to be built. But followingBut following aspects aspects shall be observedshall be observed: : 1.1. Different types of reactors Different types of reactors (PWR,PHWR)(PWR,PHWR)
2.2. Different technology Different technology (active and passive)(active and passive)
3.3. Different power level Different power level (300 ~ 1250MWe)(300 ~ 1250MWe)
4.4. Different standards Different standards (China(China、、USUS、、FrenchFrench
、、RussiaRussia
、、CanadaCanada and others)and others)
So some challenges encountering in setting So some challenges encountering in setting up the uniform technical platform for up the uniform technical platform for implementing PLiM and sharing the resourcesimplementing PLiM and sharing the resources
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Shanghai Nuclear Engineering Research and Design Institute
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Plant Life Management (PLiM) shall Integrate with AM (considered in design, operation and maintenance actions to control the ageing degradation of SSCs) and Economic Planning to:
(1) Optimize the operation, maintenance and service life of SSCs
(2) Maintain an acceptable level of performance and safety
(3) Maximize return on investment over the service life of the plant.
2. Challenges encountering 2. Challenges encountering ––6 6 PLiM requirementsPLiM requirements
2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
25
Through effective PLiM NPPs should be able to: (1) show cost-benefit and optimization; (2) ensure safety and functionality; (3) show competitiveness of nuclear power over
conventional source of energy by long-term operation over the service life;
(4) maintain the drive of sustainable development of nuclear power.
2. Challenges encountering 2. Challenges encountering ––7 7 target of the effective PLiM target of the effective PLiM
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Shanghai Nuclear Engineering Research and Design Institute
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3. Main AM/PLiM in China3. Main AM/PLiM in China----DemandsDemands
Senses of mission and duty on nuclear safety (to public)
Strategic consideration for long term safety and chasing return of investment as much as possible
nuclear safety regulatory requirements
Demand and urge utility to implement effective PLim
R&D institutes carry out research & provide tech. support to NPP
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3. Main AM/PLiM in China3. Main AM/PLiM in China--Responsibilities
Nuclear Safety regulatory
UtilitiesDesign and R&D orgs.
•• Safety requirementsSafety requirements•• Acceptable criteriaAcceptable criteria•• Safety surveillanceSafety surveillance•• LR Review and approvalLR Review and approval•• Keep safety Keep safety
marginsmargins•• AMP AMP implementationimplementation•• Ageing Ageing detectiondetection•• Ageing Ageing mitigationmitigation•• Return back of Return back of investmentinvestment
•• AM in designAM in design•• R&D in AMR&D in AM•• Detection Detection methodmethod•• Mitigation Mitigation measuresmeasures•• LR supportLR supportIAEA supportIAEA support
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Shanghai Nuclear Engineering Research and Design Institute
3.1 Nuclear safety requirements3.1 Nuclear safety requirements
NNSA issued a series of PLiM related NNSA issued a series of PLiM related requirements, basically equivalent to those requirements, basically equivalent to those made by IAEA. made by IAEA.
•• HAF series: nuclear safety requirements HAF series: nuclear safety requirements covered from design to operationcovered from design to operation
•• HAD series: nuclear safety guidelinesHAD series: nuclear safety guidelines•• Safety performance indication systemSafety performance indication system
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2007-10-15SNERDI/SNPTC
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Shanghai Nuclear Engineering Research and Design Institute
29
HAF 102 Safety of NPP Design (2004)
HAF 103 Safety of NPP Operation(2004)
HAD xx HAD xx HAD103/11PSR(2006)
HAD xx…
Codes
Guidelines
3.1 Nuclear safety requirements3.1 Nuclear safety requirements--structuresstructures
other HAF
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•• Appropriate margin should be provided in the Appropriate margin should be provided in the design for all design for all SSCsSSCs important to safety. important to safety.
•• Sufficient consideration of ageing and wear out Sufficient consideration of ageing and wear out effects in order to ensure capability to perform effects in order to ensure capability to perform safety functions through lifetime.safety functions through lifetime.
•• Provision should also be made for monitoring, Provision should also be made for monitoring, testing, sampling and inspection to asses testing, sampling and inspection to asses predicted and identify unanticipated ageing predicted and identify unanticipated ageing mechanisms.mechanisms.
•• PSA to be used to check the balance of designPSA to be used to check the balance of design
3.1 Nuclear safety requirements3.1 Nuclear safety requirements——example HAF 102 Designexample HAF 102 Design
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Shanghai Nuclear Engineering Research and Design Institute
31
•• Emphasizing comparison of current codes and Emphasizing comparison of current codes and standards to judge safety status of NPPsstandards to judge safety status of NPPs
•• Ageing is one of the 14 safety factors to be reviewedAgeing is one of the 14 safety factors to be reviewed•• Ageing review focuses onAgeing review focuses on::①① AMPAMP;;②② list of list of SSCsSSCs covered by AMPcovered by AMP;;③③ Understanding of ageing mechanismsUnderstanding of ageing mechanisms;;④④ Ageing effects to safety function; Ageing effects to safety function; ⑤⑤ Availability of data; Availability of data; ⑥⑥ Detection and mitigation of ageing degradation; Detection and mitigation of ageing degradation; ⑦⑦ Acceptance criteria and safety margins; Acceptance criteria and safety margins; ⑧⑧ Actual ageing status and safety margins of Actual ageing status and safety margins of SSCsSSCs
3.1 Nuclear safety requirements3.1 Nuclear safety requirements——example HAD example HAD 103/11 PSR103/11 PSR
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•• Nuclear safety performance indicating system Nuclear safety performance indicating system established is required to be implementedestablished is required to be implemented
•• Three barriers of radioactivity and 24 factors Three barriers of radioactivity and 24 factors are required to be assessed and reported are required to be assessed and reported timely and quantitativelytimely and quantitativelyIt is additional demonstration of effective PLiMIt is additional demonstration of effective PLiM
3.1 Nuclear safety requirements3.1 Nuclear safety requirements——example Safety performance indicationexample Safety performance indication
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– PSR orientedPSR oriented
•• These 3 units finished their first PSR from 2001 to 2004. These 3 units finished their first PSR from 2001 to 2004. •• During PSR, 11 safety factors were carefully reviewed During PSR, 11 safety factors were carefully reviewed
and relevant supporting materials were handed over to and relevant supporting materials were handed over to NNSANNSA..
•• The principle of PSR in two plants are the same, however The principle of PSR in two plants are the same, however the way of practice is somewhat different.the way of practice is somewhat different.�� For For QinshanQinshan--I,I, as a prototype unit, a more thorough as a prototype unit, a more thorough
review was carried outreview was carried out�� For For DayaDaya BayBay, as they are similar to those of , as they are similar to those of NPP in NPP in
FranceFrance, more focused on , more focused on differencesdifferences and and EDFEDF’’ssexperience experience referredreferred•• A lot of followA lot of follow--up work towards establishment of AMP is up work towards establishment of AMP is
being carried out by the two plants. being carried out by the two plants.
34
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I
•• 11 safety factors were reviewed in accordance with 11 safety factors were reviewed in accordance with HAF 0312 (equivalent to HAF 0312 (equivalent to IAEAIAEA’’ss NSNS--G 2G 2--10)10)
•• A series of review reports were prepared by NPP A series of review reports were prepared by NPP and TSOand TSO and and handhandeded over to NNSA for reviewover to NNSA for review
•• Suggestions and conclusions were put forward by Suggestions and conclusions were put forward by NNSANNSA
•• MidMid-- and longand long--term actions were taken step by step term actions were taken step by step during next 10 yearsduring next 10 years……
•• An example of Ageing Management review were An example of Ageing Management review were providedprovided……
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Shanghai Nuclear Engineering Research and Design Institute
35
QNPC/SNERDI info. centers
CNIC
Reviewing applicability and effectiveness of AMP and making suggestions for revision
NRC series(GALL, SRP )
ASME series
Learning domestic and oversea experiences
AMR guideline
Equipment list according to screening criteria
Codes and standards, guidelines, regulations and documents relating to AMP and methodology
HAF series
IAEA series
Screening method recommended in HAF- J0068
PSR-P-001 (QNPC))))
Identifying ageing mechanisms for individual components
AMR (including historic info. , operating transient, maintenance records, analysis reports, present statues of components, organization, etc.)
Present status of NPP
EQ
Design documents
Ageing analysis reports; suggestions on operation, monitoring, database system, and countermeasures for mitigation; detailed analyses on actual safety margin for some components are necessary
Management department
Mid- or long term modification plan
Corrective action
yes
Identifying whether existing programs and procedures are suitable for AM; forming AMP frame and formulation plan for AMP
Making AMP
Report on AM reviewfeedback
no
Procedure of AMR during PSR Submission to NNSA for approval
HAF0312 (NNSA)
Whether AMP exists?
IEEE series
Corrective action
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Shanghai Nuclear Engineering Research and Design Institute
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSRup PSR
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SSC ScreeningAgeing degradation mechanism Detection
Mitigation
AMP
AMP DATABASE
Ageing assessment
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Shanghai Nuclear Engineering Research and Design Institute
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSRup PSR
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AMP + PLiM
RPV SGSurge Line
Cable Containment
I&C
PSR
…
Next PSR
TurbineRCP
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Shanghai Nuclear Engineering Research and Design Institute
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSRup PSR
•• PSR (2001~2003) PSR (2001~2003) •• Development of Systematic AMPDevelopment of Systematic AMP (2006 ~ 2008) (2006 ~ 2008) •• SG ageing management program (2005 ~ 2007)SG ageing management program (2005 ~ 2007)•• RPV ageing management program (2005 ~ 2007)RPV ageing management program (2005 ~ 2007)•• Temperature online monitoring and life Temperature online monitoring and life assessment for pressurizer surge line (2006 ~ assessment for pressurizer surge line (2006 ~ 2007) 2007)
•• More More ……
Lifetime Assessment and AMP for RPV
Irradiation effects and RPV integrity analysis
♦10CFR50 App.H♦ASTM E185♦GB 2038♦GB/T 228、229
Fatigue analysis based on transient statistic
Transient records and classifying
♦Requirement of RPV specification(CLB)♦10CFR54(LR)
RTNDT increment USE decrement
P/T limits PTS Limits USE limits
♦10CFR50 App.G♦ASME XI App.G♦R.G 1.99 R.2
♦10CFR50.61♦R.G 1.154♦IAEA-EBP-WWER-08
♦10CFR50 App.G(USE > 68J)♦R.G 1.161(USE < 68J)
Surveillance test results
envelope
Transient + stress
FA
CUF
♦ASME XI App.L, E♦ASTM E 1049
Assessment for special events
AMP procedure
♦10CFR54♦NUREG1800♦NUREG1801♦NEI95-10 R.6
RPV AMP development
Existing programs and procedures
SER to LR
Residual lifetime
V&V for software
Evaluation of testing methodologies
RPV ageing management database
Modification of surveillance program
Provide to nuclear safety regulatory
RPV Assessment & AMP RPV Assessment & AMP 3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSR RPVup PSR RPV
RPV AMP document system for Qianshan I NPP
AMP coordination
Checking, monitoring and assessment
PLAN
DO
CHECK
ACT
Ageing Mechanisms operationMitigation, maintenance
Hydrochemistry management Proc. of chemistry
monitoring management
Refrigerant leaking of PRV
Procedure of NPP
Operation monitoring and analysis management system
Proc. of operation record
management
Operation experience feedback system
transient statistic for PRV
Core monitoring management system
inspection management
Service inspection program for Qinshan1 NPP
Service inspection management system
Monitoring management
PRV material irradiation monitoring program for Qinshan1 NPP
System for alteration management of system equipment
Proc. of patrol inspection
Procedure of monitoring checking and test for Qianshan1 NPP
Assessment management
Proc. Of mitigation and maintenance
Rule of maintenance and repair for PRV
Procedure of teardown and installment of PRV closure head
Ageing management system for PRV
PRV AMP procedure
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSR RPV up PSR RPV
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSR SGup PSR SG
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IAEA guidelines GALLs Operation
experience
1. Research program on SG ageing management2. SG ageing management project
SG Ageing Mechanism
Analysis
SG Ageing Management
Program Development
SG Ageing Management database de
velopment
SG Ageing assessment techniques
Based on information presented by RINPO Based on information presented by RINPO
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– Qinshan IQinshan I followfollow--up PSRup PSR
•• During PSR, pressurizer During PSR, pressurizer surge linesurge line was identified as was identified as sensitive to thermal fatigue and furthermore, thermal sensitive to thermal fatigue and furthermore, thermal stratification effect was not taken into account. stratification effect was not taken into account.
•• An online temperature monitoring system installed during An online temperature monitoring system installed during outage in 2006.outage in 2006.
•• A detailed statistic of operational transient is carried out A detailed statistic of operational transient is carried out taking account of monitored data. taking account of monitored data.
•• A detailed fatigue analysis and lifetime assessment will be A detailed fatigue analysis and lifetime assessment will be done taking account of thermal stratification effect. done taking account of thermal stratification effect.
•• After lifetime assessment being finished, further ageing After lifetime assessment being finished, further ageing management action will be taken. management action will be taken.
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Section 1
Section 2
Section 3
Section 4
Online Temperature Monitoring for Pressurizer Surge Line
6 0 °
点测 1
点测 2
点测 3
点测 4
点测 5
Distribution of sensors in every section
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Temperature monitoring for surge lineTemperature monitoring for surge line
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– DayabayDayabay followfollow--up PSR AMRup PSR AMR
Based on international experience feedback and Based on international experience feedback and according to actual status of NPP, AMR focused according to actual status of NPP, AMR focused on the following topics: on the following topics:
•• Chemical controlChemical control•• Transient statisticTransient statistic•• ISIISI•• Spare parts managementSpare parts management•• ContainmentContainment•• RPVRPV
、、SGSG、
、RCPRCP•• Power cable and I&C cablePower cable and I&C cable•• Other componentsOther components
Based on information presented by CGNPC Based on information presented by CGNPC
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– DayabayDayabay followfollow--up PSR AMRup PSR AMR
Experience feedback C&S, guidelines Actual status in NPP
Scope of review
Data collection
Summary of collection Good international practiceComparison
Review conclusionsBased on information presented by CGNPC Based on information presented by CGNPC
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– DayabayDayabay followfollow--up PSR AMRup PSR AMR
Topic AMR
Programmatic review
AM activities review
Review on sensitive SSCs
� Policy� Screening � Sensitive SSC
list � Data collection
and record keeping
� ISI� Transient
statistic� Chemical
control� Spare parts
Sensitive SSCsfeedback from outside� RPV� Containment� SG� RCP� Cable
Sensitive SSCsfeedback from inside�Emergency DE�Class 1 MOV�Motor�Transformer�battery�I&C
Based on information presented by CGNPC Based on information presented by CGNPC
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– DayabayDayabay followfollow--up PSR AMRup PSR AMR
3 periods for ageing management and PLiM: 3 periods for ageing management and PLiM: •• First 20 years: AMP, database, tendency and First 20 years: AMP, database, tendency and lifetime lifetime prediction prediction model, monitoring, mitigation model, monitoring, mitigation measuresmeasures
•• 2020--30 years: tendency and lifetime prediction, 30 years: tendency and lifetime prediction, lifetime extension preparationlifetime extension preparation
•• 3030--40 years: supplement and update documents 40 years: supplement and update documents according to assessment resultsaccording to assessment results
Based on information presented by CGNPC Based on information presented by CGNPC
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– DayabayDayabay followfollow--up PSR AMRup PSR AMR
Currently work covered: Currently work covered: ①① RI AMP / RPV AMP / SG AMPRI AMP / RPV AMP / SG AMP②② PWSCC for 600 materialsPWSCC for 600 materials③③ Thermal ageing for cast stainless steelThermal ageing for cast stainless steel④④ FAC countermeasuresFAC countermeasures⑤⑤ Cable ageing managementCable ageing management⑥⑥ Thermal fatigue for auxiliary piping of primary loopThermal fatigue for auxiliary piping of primary loop⑦⑦ ByBy--pass piping vibrationpass piping vibration⑧⑧ Thermal fatigue for primary loop pipingThermal fatigue for primary loop piping⑨⑨ Containment AMPContainment AMP⑩⑩ Transformer AMP /Generator AMPTransformer AMP /Generator AMP
Based on information presented by CGNPC Based on information presented by CGNPC
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3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– TQNPCTQNPC
A CANDU two units started operation in 2002 and 2003A CANDU two units started operation in 2002 and 2003•• The owner TQNPC initiated ageing management at very The owner TQNPC initiated ageing management at very
beginning of the plant operation. beginning of the plant operation. •• A systematic screening for AMP A systematic screening for AMP SSCsSSCs was carried out in was carried out in
assistance of its technical support SNERDI (2003~2004) assistance of its technical support SNERDI (2003~2004) �� Fuel channel, reactor assembly, SG, pressurizer, feeder, Fuel channel, reactor assembly, SG, pressurizer, feeder,
primary piping, reactor collector piping, HTP, emergency primary piping, reactor collector piping, HTP, emergency cooling pump, heavy water isolation valve, cable, cooling pump, heavy water isolation valve, cable, containmentcontainment…… were selected as AM itemswere selected as AM items
•• Detailed ageing mechanism analysis for AM components Detailed ageing mechanism analysis for AM components and structures is under way. After that, component based and structures is under way. After that, component based AMP and database will be developed.AMP and database will be developed.
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Also including pressurizer, primary pipe, header, HTPs, ECC pumps and heavy water isolate valves
Cable
SG
Fuel channel Feeder Containment
Reactor assembly
3.2 Activities of PLiM in NPPs 3.2 Activities of PLiM in NPPs –– TQNPC TQNPC Screening result
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3.3 PLiM R&D to support NPPs3.3 PLiM R&D to support NPPsUnderstand, Apply and Develop Relevant Codes and Standards�ASME series ASME-B&PV III,ASME-B&PV XI,ASME-O&M Code, S/G�USNRC related, 10CFR50、54、51, NEI, RG1.199、1.154、1.188、NUREG 1800�IAEA series AM guidesSafety series, technical series and review seriesEJ/T 1033-96(Anti-fast fracture), �EJ/T 918-94(P-T limits)Compile related technical codes and standards
Inspection and Monitoring Techniques�Researches on methodology and apparatus development of online fatigue monitoring system�Researches on online thermal stratification monitoring method�Researches on in-service NDE and assessment techniques for dissimilar metals�Researches and applications on pre- & in-service monitoring system for rotating equipment and piping�Researches on LPMS �Researches on NDE techniques for cables�FAC countermeasures and piping thiningdetection techniques
Researches on Material Properties and Aging Degradation Mechanism�Fatigue properties of austenitic & low-alloy SS�Reliability of domestic 508-Ⅲ steel�Surveillance and lifetime assessment technology for RPV & RI�Researches on material properties and structural integrity for SG tubes�Researches on pres. Boundary materials�Develop database of comp. materials�Property researches for Class 1E cables�Researches on aging degradation mechanism and their measures for comps.�Researches on corrosion protection for water system piping or off-shore NPPs
Dispose and Develop Tool Software�ANSYS:General purpose FEA program�MARC:Fracture mechanics(J-integral, ASME XI)�PATRAN:FEM common platform�FATIGUE:Fatigue fracture(da/dN)�CFX:CFD analysis�SHOCK:PTS analysis based on ASME code]�PFMAC:Probability fracture mechnics analysis�specific AM software(e.g.,CHECWORKS, COMSY,etc.)
Establishment of Assessment and AM Methodology�Structural integrity analysis for RPV under PTS�Assessment methodology for key components with flaws detected by NDE�Reliability analysis and prediction techniques for nuclear piping under abnormal and abrupt events�Integrity analysis for surge line under thermal stratification.�Probability fracture mechanics analysis method�Modification of P-T limits based on irradiation surveillance�Ageing evaluation for containment.�Pre-and in-service condition assessment for safety related rotating equipment in NPPs�Researches on failure, diagnosis analyses and design improvement for NPP components�Aging assessment and database for class 1E cables�Methodology on AMP development for NPPs
Equipment Assessment and AM for Operational NPPs�PSR (AM, EQ), RPV mid-term assessment, AMP development, surge line for Qinshan-Ⅰ�Ageing mechanism analysis for critical equipment, PSR preparation for TQNPC, CANDU�Operational condition assessment, AMP development for C1�Vibration qualification of rotating equipment and piping for Q1, Q2, Q3 and C1�Vibration mechanism analysis and site treatment for Tianwan VVER1000 NPP
Main Technical Main Technical Supporters to NPPsSupporters to NPPs
BINE/CNNCBINE/CNNC
CIAE/CNNCCIAE/CNNC
SNERDI/SNPTCSNERDI/SNPTC
SNPI/CGNPCSNPI/CGNPC
RINPO/CNNCRINPO/CNNC
NPIC/CNNCNPIC/CNNC
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3.4 IAEA support in PLiM in China
In recent years, IAEA provides lots of supports in In recent years, IAEA provides lots of supports in promoting and spreading of AM/PLiM concepts promoting and spreading of AM/PLiM concepts and activities in China, especially viaand activities in China, especially via
•• TC projects, i.e. CPR 4/026, Development of AMP in TC projects, i.e. CPR 4/026, Development of AMP in NPPsNPPs
•• EBP projects on related topics, mainly conducted by EBP projects on related topics, mainly conducted by NPPsNPPs
•• Taking part in IAEA TWGTaking part in IAEA TWG--LMNPPLMNPP•• Taking part in coordination research projects, such as Taking part in coordination research projects, such as CRPCRP--9, Benchmark and good practice handbook for 9, Benchmark and good practice handbook for RPV integrity under PTSRPV integrity under PTS
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3.4 IAEA support in PLiM in ChinaExample: TC 4/026 Development of AMP for NPPsExample: TC 4/026 Development of AMP for NPPs•• 17 person17 person--time expert missionstime expert missions•• 11 person11 person--time SV or FE or training coursetime SV or FE or training course•• 8 Chinese organizations benefit from the TC8 Chinese organizations benefit from the TCTopics included:Topics included:�� Integrity analysis for pressure boundary componentsIntegrity analysis for pressure boundary components�� Methodology for AMP developmentMethodology for AMP development�� FAC countermeasuresFAC countermeasures�� RPV life assessment for WWERRPV life assessment for WWER�� Cable ageing detection and managementCable ageing detection and management
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4. Prospective activities of PLiM in ChinaNeedsNeeds��More new NPPsMore new NPPs��Some of NPPs agedSome of NPPs aged��MultiMulti--type unitstype unitsWaysWays��Digest inter. C&S plus Digest inter. C&S plus domestic practicedomestic practice��R&D supportR&D support��Cooperation of Cooperation of international related international related partiesparties
1. Localization 1. Localization and continuous and continuous improvement of improvement of nuclear safety nuclear safety regulatory system regulatory system for AM and PLiMfor AM and PLiM
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4. Prospective activities of PLiM in ChinaNeedsNeeds�� More than 50% design life More than 50% design life passed for Qinshanpassed for Qinshan--II�� LR policy should be set upLR policy should be set upWaysWays�� IAEA requirements + IAEA requirements + practicabilitypracticability�� Establishment of technical Establishment of technical foundation for LR and LTOfoundation for LR and LTO�� Demonstrational function of Demonstrational function of prototype unit, Qinshanprototype unit, Qinshan--II
2. Establishment 2. Establishment Chinese license Chinese license renewal and renewal and LTO systemLTO system
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Shanghai Nuclear Engineering Research and Design Institute
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4. Prospective activities of PLiM in ChinaNeedsNeeds�� IAEA DS382 requires AM IAEA DS382 requires AM being considered in FASRbeing considered in FASR�� how to do as more new how to do as more new NPPs being designed in NPPs being designed in China next 20 years China next 20 years WaysWays�� Supplementary Regulatory Supplementary Regulatory requirements for designrequirements for design�� Technical guidance for Technical guidance for implementationimplementation
3. Practices for 3. Practices for AM to be AM to be considered at considered at design stagedesign stage
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4. Prospective activities of PLiM in ChinaNeedsNeedsSignificance and sensitivity of critical secondary loop equipment to economy of NPPsNot sufficiently studied comparing with those in primary loopWaysWaysRegulatory requirements cover to secondary loopR&D with more cooperation with conventional power plants
4. Extending 4. Extending attention to attention to secondary loop secondary loop equipmentequipment
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4. Prospective activities of PLiM in ChinaNeedsNeeds�� Limited resource vs. large Limited resource vs. large amount of amount of SCCsSCCs�� Screening based on PSA Screening based on PSA achievementachievementWaysWays�� AM regulatory requirements AM regulatory requirements reflect riskreflect risk--informed informed technologytechnology�� PSA personnel involve in PSA personnel involve in AM activitiesAM activities
5. Application 5. Application of riskof risk--informed informed technologytechnology
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5. Summary and suggestion•• PLiM is a fundamental aspect to guarantee safe and PLiM is a fundamental aspect to guarantee safe and economic operation of NPPs. It is indispensable for the economic operation of NPPs. It is indispensable for the sustainable developmentsustainable development of nuclear powerof nuclear power
•• Many efforts in ageing management and lifetime Many efforts in ageing management and lifetime assessment for NPPs have been made by related assessment for NPPs have been made by related organizations in China, however, much more work should organizations in China, however, much more work should be done in the futurebe done in the future
•• International cooperation acts as a very important role to International cooperation acts as a very important role to promote PLiM related R&D and practice in Chinese NPPspromote PLiM related R&D and practice in Chinese NPPs. . It should be encouraged and strengthened in many It should be encouraged and strengthened in many aspects in the futureaspects in the future
•• Prospective PLiM activities on 5 aspects are suggestedProspective PLiM activities on 5 aspects are suggested
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5. Summary and Suggestionto Setup an IAEA cooperation platform in China①① Human resource trainingHuman resource trainingTwo levels of human resource training. Two levels of human resource training. �� Research and high level managementResearch and high level management�� Implementation personnel; Implementation personnel; Both Chinese and foreign engineers being trained in Both Chinese and foreign engineers being trained in parallel parallel
②② Human resource sharing Human resource sharing �� Challenge of shortage of human resourceChallenge of shortage of human resource�� Establishment of International Expert Pool or BankEstablishment of International Expert Pool or BankCurrently, China needs more foreign experts, In the future, Currently, China needs more foreign experts, In the future, Chinese experts will do more services internationallyChinese experts will do more services internationally……
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③③ Collaborative research and developmentCollaborative research and development�� Select typical topics, such as PTS analysis, Select typical topics, such as PTS analysis,
RiskRisk--Informed Technology and its Informed Technology and its implementationimplementation
�� More involvement of Chinese organizations to More involvement of Chinese organizations to international collaborative research projects, international collaborative research projects, such as those organized by IAEA, EC, such as those organized by IAEA, EC, OECD/NEA, etcOECD/NEA, etc……
�� Membership of industrial R&D institution, such Membership of industrial R&D institution, such as EPRI, TWI, etcas EPRI, TWI, etc……
5. Summary and Suggestionto Setup an IAEA cooperation platform in China
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6. Acknowledgement
•• Gratitude to IAEA, especially to Mr. Yuri Sokolov, for Gratitude to IAEA, especially to Mr. Yuri Sokolov, for his continuous support for implementation of PLiM in his continuous support for implementation of PLiM in China and encouraging China to host the Second PLiM China and encouraging China to host the Second PLiM Symposium. Symposium.
•• Special thanks to Mr. KSpecial thanks to Mr. K--S Kang, Mr. T. Inagaki S Kang, Mr. T. Inagaki and and our Douyikang for their untiring efforts and fruitfully our Douyikang for their untiring efforts and fruitfully hard working for spreading AM concepts and hard working for spreading AM concepts and promoting its practice in China in the past 5 years.promoting its practice in China in the past 5 years.
•• Thanks to CNNC/Qinshan Nuclear Power Base for Thanks to CNNC/Qinshan Nuclear Power Base for successful arrangement successful arrangement
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Thank for your attention !