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Programme of Self Assessment and Programme of Self Assessment and Condition Report at Qinshan NPPCondition Report at Qinshan NPP
IAEA Conference 27 June – 2 July 2004 Russia
Jiapeng YANJiapeng YANQinshan Nuclear Power Company,
Haiyan, Zhejiang, 314300
CHINA
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YAN Jia-Peng, the Deputy General Manager of Qinshan Nuclear Power Company(QNPC)
20 year’s of experience in nuclear power industry
To receive the RO, SRO license in 1985 & 1990 and work as RO and Shift-Supervisor for seven years
Assistant General Manager in 2001 and responsible for all aspects of plant operations safety, nuclear safety surveillance and QA
Deputy General Manager in Sept. 2002 and responsible for plant operating, planning, system engineering, physical health and technical support
RESUMERESUME
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Introduction System Development Practice of SA and CR Conclusion
TOPICSTOPICS
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IntroductionIntroduction
Part onePart one
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Introduction-QNPPIntroduction-QNPP
QNPP is the first NPP of 310MWe PWR in China Mainland which was designed, constructed and operated domestically. It is located inside Haiyan county, Zhejiang province and is 100km west to Shanghai city and 90km east to Hangzhou city.
QNPP began to construction on March 21th,1985,
QNPP first connected to the grid on December 15th, 1991
QNPP Carried out the OSART mission on Jan, 1997
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QNPP has continuously improved its safety, reliability and achieved the better operation performance through upgrading equipment and system, developing five-year goal, enforcing operating experience feedback, carrying out ten-year Periodic Safety Review (PSR) and Probability Safety Analysis (PSA) etc.
QNPP has been continuously operated 443 days without scram in the 7th fuel cycle.
WANO Performance Indicator Index of the plant reached the world median level first time in 2002.
Introduction-QNPPIntroduction-QNPP
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No. Indicator 2001 2002 2003
1 Unit Capability Factor 93.9% 67.8% 89.2%
2 Unplanned Capability Loss Factor 0.5% 2.8% 0.20%
3 Forced Loss Rate 0.22
4 Unplanned Automatic Scrams Per 7000H Critical
1.7 0 0
5 Safety System Performance
HPSIS 0.0009 0.0003 0.0004
AFWS 0.0052 0 0.0018
E D/G 0 0 0.0004
6 Fuel Reliability (Bq/g) 0.46 0.64 0.46
7 Chemistry Performance 1.31 1.11 1.07
8 Collective Radiation Exposure (Man.Sv) 0.15 1.24 0.80
9 Industrial Safety Accident Rate 0.20 0 0.10
10 PI Index 75 88 92
Introduction-QNPPIntroduction-QNPP
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1998 2003 Performance I ndi cator I ndex-
86
7275
8588
90
92
88
60
70
80
90
100
Medi aQNPC
Medi a 86 85 88 90
QNPC 72 75 88 92
2000 2001 2002 2003
Introduction-QNPPIntroduction-QNPP
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Unit Capability Factor
76. 8
81. 9
93. 9 89. 2
86. 1 85. 8
87. 285. 9
50
100
2000 2001 2002 2003
%
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Unplanned Automatic Scram per 7000 Hours Critical
0
1. 70
01. 00
00 0
00. 000. 200. 400. 600. 801. 001. 201. 401. 601. 80
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Safety System Performancehi gh pressure safety i nj ecti on system-
0. 0004
0. 001
0. 00030. 001 0. 0009
0. 001
0. 0010. 001
0
0. 001
0. 002
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Safety System Performanceauxi l i ary feedwater system-
0. 0052
0. 0005
0. 001 0. 00180. 001
0. 001
0. 0010. 001
0
0. 001
0. 002
0. 003
0. 004
0. 005
0. 006
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Safety System Performanceemergency AC power system-
0. 011
0 0 0. 0004
0. 003 0. 0020. 003
0. 002
0
0. 002
0. 004
0. 006
0. 008
0. 01
0. 012
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Collective Radiation Indicator
0. 81. 24
0. 150. 65
0. 77
0. 71
0. 710. 85
0
0. 4
0. 8
1. 2
1. 6
2000 2001 2002 2003
man.Sv QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Chemistry Performance Indicator
1. 071. 111. 311. 09
1. 01 1. 011. 021. 08
0
0. 4
0. 8
1. 2
1. 6
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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I ndustri al Safety Acci dent Rate
0. 10. 0
0
0. 2
0. 31
0. 280. 330. 33
0
0. 2
0. 4
2000 2001 2002 2003
QNPC
Medi an
Introduction-QNPPIntroduction-QNPP
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Purpose of Self-Assessment(SA)/Condition Report (CR) establishment is to sustain improvement of plant’s safe operation and good performance
The establishment of the SA and CR systems were supported by IAEA CPR/0/009 TC Project (2000 to 2001). There were 46 QNPP’s senior managers and 24 host plant’s experts involved this project.
QNPP developed and implemented improvement’s plans and made significant achievements in ten areas on the past three years. The SA and CR systems are the two most successful areas.
Introduction-SA/CRIntroduction-SA/CR
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Introduction-SA/CRIntroduction-SA/CR
IAEA CPR/0/009 Final Review Meeting
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System DevelopmentSystem Development
Part twoPart two
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System Development-System Development- OBJECTIVESOBJECTIVES
1. Detect and report the weakness of plant conditions and management problems to maintain the plant’s continuing improvement system and good performance.
2. Ensure all the management, plant system and equipment were under well controlled, the abnormal conditions are identified and corrected in time.
3. Ensure to carry out the Root Cause Analysis and develop Corrective Actions Enhancing personnel Safety Culture consciousness.
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System Development-System Development- PROCEDUREPROCEDURE
1. Condition Report Management Procedure (QSZ-D-044)
2. Methodology of Root Cause Analyze (Manual)
3. Operation Experience Feedback Management Procedure (QSZ- D-022)
4. Operation Event Report Procedure (QSZ-D-053)
5. Operation Experience Feedback Engineer Procedure (QSZ-D-050)
6. Self-Assessment Management Procedure (QSZ-D-051)
7. Self-Assessment Committee Programme (QSZ-A)
8. Self-Assessment Criteria and Guidelines (Manual)
9. Self-Assessment Methodology (Manual)
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System Development-System Development- PROCEDUREPROCEDUREManual Example:
Root cause Analysis
Self Assessment
Operation Experience
Human Performance
WANO PI
Self Assessment
C&O
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System Development -System Development - PROCESSPROCESS
Departments decide and submit the SA plan to NSLD
Departments decide and submit the SA plan to NSLD
SA committee hold meeting to review the SA plan
SA committee hold meeting to review the SA plan
NSLD develop the plant SA plan.
NSLD develop the plant SA plan.
General manager review and approve the SA plan
General manager review and approve the SA plan
SA plan distributed to departments/Training
SA plan distributed to departments/Training
Department establish assessment team and implement the plan
Department establish assessment team and implement the plan
SA report was submitted to NSLD and reviewed by SA Committee
SA report was submitted to NSLD and reviewed by SA Committee
The AFIs and correction actions development / CR process
The AFIs and correction actions development / CR process
Self-Assessment (SA) Process flow Chart (simplified)
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System Development-System Development- PROCESSPROCESS
Condition Report (CR) Process Chart (simplified)Condition Report (CR) Process Chart (simplified)
Equipment Deficiency
Equipment Deficiency
License Dep. Review
License Dep. Review
Discu. and Review daily CR Meeting
Discu. and Review daily CR Meeting
Close/ transfe
r ?
Close/ transfe
r ?
Classify
Sig. ?
Classify
Sig. ?
Analyze Root
Cause
Analyze Root
Cause
Develop CA &
Approve
Develop CA &
Approve
Develop Correct Actions
Develop Correct Actions
Implement CA
Implement CA
EvaluateEvaluate
CloseRepor
t
CloseRepor
t
Other programs
Manag. Weakness & SA AFIs
Manag. Weakness & SA AFIs
Outside Events (SOER, SER)
Outside Events (SOER, SER)
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System Development-System Development- PROCESSPROCESS
Corrective Actions (CA) Process Chart (simply)Corrective Actions (CA) Process Chart (simply)
Determine Problem Determine Problem Investigate Investigate Analyze investigated Result
Analyze investigated Result
Determine Root Cause Determine Root Cause Develop Corrective Actions
Develop Corrective Actions
Approve Report Approve Report
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System Development-System Development- ORGANIZATIONORGANIZATION
Self-Assessment (SA) committee.
-Review and approve the SA plan and Review the state of SA;
-Evaluate the implement of overall SA plan and Review SA report;
-Review the implementation of AFI.
Nuclear Safety Licensing Department.
-Accept and review CRs and report to the CR Review Meeting;
-Tracking the completion of the CA;
-The secretariat of the SA committee;
-Following up the state of SA plan implementation and AFIs;
-Provide supports to OEF engineers.
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OEF Engineer System (more 20 engineers)
-Support their department managers to analyze the root cause, develop correct actions and follow-up;
-Promote OEF improvement in their departments
Condition Report Review Meeting (daily routine meeting at 11:00 AM )
-Report the coming CRs, review and clarify them.
-Assign the CRs to responsible department for develop the CA.
-Review class A CRs’ Root Cause Analysis results and Correct Actions.
-Review the industrial OE information.
System Development-System Development- ORGANIZATIONORGANIZATION
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System Development-System Development- CR CR REPORTABLE AREA REPORTABLE AREA
1. Operational/Material/Maintenance/Welding-Related Conditions
2. Configurations/Systems/Equipment
3. Radiological Protection/Industrial Safety/Fire Protect/ Security Conditions.
4. Human Performance/Administrative .
5. Internal/External Operating Experience
6. Self-assessment AFIs
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System Development-System Development- CR CR CLASSIFCATIONCLASSIFCATION
Category A: Significant CRs.Root Cause Aanalysis and Corrective Action are needed
Category B: Non-Significant CRs.Only corrective action is needed
Category C: No need further action, Condition can be directly closed or transferred to other process (Below A &B)
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SigCRs
Non-SigCRs
CR B Threshold
CR A Threshold
OtherSystems
IndusSafety
QAQC
Ops Depart.
Impr Plan Equip
related cond.
Maint. Prob.
doc.Contl.
Plant Managers focus
Dep. Managers focus
Staffs focus
CR C Threshold
System Development-System Development- CR CR CLASSIFCATIONCLASSIFCATION
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Practice of SA and CRPractice of SA and CR
Part threePart three
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Practice-Practice- SELF-ASSESSMENTSELF-ASSESSMENT
Establish Committee and Procedures, Training, Planning, Team setup
Maintenance, Chemistry and Production Planning areas finished in 2003 as follow
Area AFIs Number
Strengths Number
1 Maintenance 32 5
2 Chemistry 7 2
3 Production planning
16 1
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Plan in 2004: five areas as Operation, Radiological Protection, Training, Engineering Support and In-Service Inspection
Most reviewers come from own plant, but some external experts are invited
Practice-Practice- SELF-ASSESSMENTSELF-ASSESSMENT
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Practice-Practice- SELF-ASSESSMENTSELF-ASSESSMENT
Self Assessment Plan in 2004
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Practice-Practice- CONDITION REPORTCONDITION REPORT
Condi ton Report Number Trendi ng i n 2002
11 15 17 26 29 33 41 41 41 42 43 5032 45
5985 96
113136
156 164 174 180 186
5976 88
128150 160 171
192 201 211 219 222
0
50
100
150
200
Number
A 11 15 17 26 29 33 41 41 41 42 43 50
B 32 45 59 85 96 113 136 156 164 174 180 186
C 59 76 88 128 150 160 171 192 201 211 219 222
J an- f eb- Mar- Apr - May- J un- J ul - Aug- Sep- Oct - Nov- Dec-
CR report number in 2002
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Practice-Practice- CONDITION REPORTCONDITION REPORT
CR report number in 2003
Condition Report Number Trending in 2003
0 1 2 4 8 11 12 14 15 19 20 247 10 19
5581
100114 126 133 145
159 169
12 2545
7495
114 128141 149 160
196 210
0
50
100
150
200
250
A 0 1 2 4 8 11 12 14 15 19 20 24
B 7 10 19 55 81 100 114 126 133 145 159 169
C 12 25 45 74 95 114 128 141 149 160 196 210
J an- Feb- Mar - Apr - May- J un- J ul - Aug- Sep- Oct - Nov- Dec-
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Administrative control
Configuration control
Equipment deficiency
Work practice
Area
Operation
Maintenance
Engineering support
Material condition
Radiation protection
Security
Training
Org. &admin
Emergency planning
Chemistry
Practice-Practice- CONDITION REPORTCONDITION REPORT
CR Problem Trending by Areas (one month sample)
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Number of CR
cl osi ng
Number of
under CA
i mpl ement i ng
Number of
Devel opi ng
CA not i n
t i me
Number of CR
cl osi ng not
i n t i me
Number of Devel opi ng CA not i n t i meNumber of under CA i mpl ementi ng
Number of CR cl osi ngNumber of CR cl osi ng not i n t i me
Practice-Practice- CONDITION REPORTCONDITION REPORT
Follow up CR Corrective Actions implementation
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QNPC Main Web Page QNPC Main Web Page
Nuclear Safety Nuclear Safety
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NSLD Main Web Page NSLD Main Web Page
Condition Report Condition Report Self Assessment Self Assessment
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Condition Report Main Web Page Condition Report Main Web Page
CR list in latest 30 days CR list in latest 30 days
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One of Condition Reports in Web Page One of Condition Reports in Web Page
WANO SER 2003-2WANO SER 2003-2
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One of Condition Reports in Web Page One of Condition Reports in Web Page
Root Cause Root Cause
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One of Condition Reports in Web Page One of Condition Reports in Web Page
Correct ActionsCorrect Actions
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CR Search Web Page CR Search Web Page
Easy to searchEasy to search
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Practice-Practice- CORRECT ACTIONCORRECT ACTION
Case Study –RCA and Corrective Actions development
On May 2001,QNPP had an event “Loss of Power to Protection System Results in RCP A/B Trip Signal Actuation, followed with Reactor and Turbine Trip Automatically”. (EAR TYO 01-004)
The Root Cause Analysis by Event Cause Factors was developed. Human error,Equipment deficiency, Lack of patrol control, Lack of safety culture consciousness were main 4 factors to cause this events
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One workertwist the DC24V
power supply bushing as another
worker’s suggestion
Loss of power supply because of the shaking of power supply input lead, which connected
in a wrong pattern
RCPA/B trip intermediate relays in
the CP5414 lost its power supply
Reactor and turbine tripped
automatically
Position of the DC24V and DC220V breaker is near, even the input line
was tied together
DC220V power supply connected with the terminal in wrong
pattern
Preventive maintenance never carried out to these breakers
since the beginning of operation
Deficiency in equipment acceptance
The plant management system do not cover the preventive maintenance,
reliability and risky analysis of some
key equipments
Number labeled on the DC24V bushing toward
inside
Maintenance staff lack of the awareness in safety culture
and safety risk
Maintenance staff violating the plant safety regulation
and program
Maintenance staff lack of question attitude and the self
check requirement
Deficiency in safety culture, risk awareness management
and education
Two I&C maintenance workers cannot see the number labeled on the lead of DC24 branch power supply
management/ safety culture
management/ safety culture
Programe Programe
Work practice Work practice
Establishment and acceptance of equipment
Establishment and acceptance of equipment
Equipment maintenance / test/ surveillance
Equipment maintenance / test/ surveillance
EAR TYO 01-004, Loss of Power to Protection System Results in RCP A/B Trip Signal Actuation, followed by Reactor and Turbine Trip Automatically EVENT DATE: 10 May 2001
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Conclusion Conclusion
Part fourPart four
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Conclusion-1Conclusion-1
1. Develop a window and allow all the reportable condition and abnormalities covering all near missed incidents as well as management problems to report and follow up by this window.
2. The Plant Managers understand and timely control the unit’s conditions and significant issues by the systems
3. The Operation Experience Feedback (OEF) system has been significantly improved by the establishment of CR system.
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4. The Operation Experience Feedback (OEF) system has been significantly improved by the establishment of CR system.
-Reportable number increased (50 to 400)
-Clearly classify to A B C
-OEF Engineers contributing to Root Cause Analysis
-More external events into CR system (Approximately 50 international OEF reports and all WANO SOER and SERs)
Conclusion-2Conclusion-2
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Conclusion-3Conclusion-3
5. SA and CR systems made significant contributions to increase the plant’s risk control capability, and decreased the human error events , and improve the unit’s operation safety management and performance.
QNPC clearly recognizes that the plant will contiQNPC clearly recognizes that the plant will continue to recognize weaknesses and avoid complacenue to recognize weaknesses and avoid complacency in the future by continually striving for both ncy in the future by continually striving for both improving safety and operational perfoimproving safety and operational performancermance
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THANKTHANK
YOU!YOU!