1. Status and Prospect of Korean Korea Electric Power Research Institute
Core University Program between Japan and Korea on EAC & PSR, ~27, Seoul
Status and Prospect of Korean
PSR
Tae-Ryong Kim (
Korea Electric Power Research Institute

2. Prospect of PSR in Korea
Contents
Background of PSR
Status of PSR in Korea
Result of PSR on Kori-1
Prospect of PSR in Korea
Conclusion

3. Background of PSR(1) Chronicle of PSR in Korea
’96.10: IAEA recommended adoption of PSR
at Convention on Nuclear Safety
’99.12: Policy for PSR decided by Government
’00.5 : Basic plan of PSR setup by KEPCO
’00.5 : Start of PSR on Kori-1
’01.7 : Legal system for PSR established
’02.11: PSR report on Kori-1 submitted to MOST
’03.6 : PSR report on Wolsong-1 submitted
’03.12: PSR report on Kori-2 submitted
’04.2 : PSR on other operating NPPs on-going

4. Background of PSR(2) PSR goals
Review what extent the plant meets current safety
standards and practices
Confirm whether adequate arrangement are in place to maintain plant safety
Evaluate safety margin for safe operation in next 10 years
Suggest corrective actions to enhance the plant safety

5. Operation Experience and Research
Background of PSR(3)
Scope and contents of PSR:
11 Safety factors recommended by IAEA N P P S A F E T Y
Actual Condition
Aging Management
Equipment Qual.
Safety Analysis
Safe Performance
Organ./Admin.
Procedures
Human Factors
Emergency Plan
Environment
Operation Experience and Research

6. Background of PSR(4) Legal background of PSR Atomic Energy Act
(Article 23 : PSR)
PSR Responsibility
of NPP Owner
Enforcement Decree of the Act
(Article 42 : Content of PSR)
11 Safety Factors
Enforcement Regulation of the Act
(Article 19 : Details of PSR)
55 Detailed Items
of Safety Factors
Associate Regulatory Guides of MOST
Codes & Standards in FSAR

7. Status of PSR in Korea (1)

8. Status of PSR in Korea (2)
Typical overall procedure of PSR
Agreement between
Owner/Operator and Regulator
Starting Point
of PSR
Preparation of PSR project
Activities
of the
Regulator
PSR Reviews
Preparation of the Program
of Corrective Actions
Approval of an
Integrated Program of
Corrective Actions
End Point
of PSR

9. Status of PSR in Korea (3)
Procedure of the Review
Set Safety Standard for the Review
Define Detailed Scopes and Contents
Define Specific Standards for each Safety Factor
Deterministic
Analysis
Propose Corrective Actions
Final report
Take
Immediate
Actions
Probabilistic
Expert
Judgement
urgent ?
Prioritize Corrective Actions

10. Status of PSR in Korea (4)
Cut-off date of the Review
Period to be reviewed: from initial criticality to end of the year when the PSR starts
Safety standards: 6 months prior to the PSR ends
For instance, cut-off date of Kori-1
Period to be reviewed
Safety standards used ’
Initial Criticality ’
PSR start ’ ’
PSR end ’
6 month prior

11. Status of PSR in Korea (5)
Assessment methodologies
Basic strategy
Adopt methodologies presented in the PSR rules
Various methods in accordance with the characteristic of
each safety factor
Methods used
Document review
Re-analysis and re-calculation
Site walk-down
Simulation
Questionnaire and interview

12. Results of PSR on Kori-1(1)
Kori Nuclear Unit 1

13. Results of PSR on Kori-1(2)
Actual physical condition of the NPP
Determine the adequacy of the plant design, its
documentation and actual physical condition of SSC
Population density, industrial and traffic facilities around
the plant, natural phenomena reviewed
Plant improvements up to date
Implementation of post-TMI actions
Replacement of steam generators, low-pressure rotor,
I&C equipment, aged pipes about 1,200m long
Installation of remote shutdown panel
Current safety standards satisfied
Cumulative electricity generated: 89,274GWh
50 heat-ups/cool-downs recorded (designed: 200)
SSC: systems, structures & components

14. Results of PSR on Kori-1(3)
Management of ageing
Determine whether ageing is being effectively managed
and an effective ageing management program is in place
Safety-related SSC maintained in good physical condition
Current safety standards satisfied
RPV integrity confirmed for 40 years or more
Fire hazard analysis done
Corrective action items recommended
Installation of ex-vessel dosimetry
Installation of fatigue monitoring system
Implementation of Alloy 600 program
Upgrade safe shutdown capability against fire

15. Results of PSR on Kori-1(4)
Phase I: Feasibility Study of Continued Operation
Prelim. Life
Evaluation
Economic
Analysis
Review
Regulation .
Feasible?
by PSR
Phase II: Detailed Life Evaluation
AMP
AMPs
Detailed
Life
Develop
Technical
Guidelines
Field Test
Perf. Monitor
PLiM DB
Regulator’s Review
of PSR Results
Phase III: Field Implementation of AMPs Y N
Revise
Input to
Aging management of PSR
Accept
Recommendations
Data
Collection
Screening
SSCs

16. Results of PSR on Kori-1(5)
Screening of critical structures and components
Screening Criteria based on mainly USA practice
License Renewal Rule (10CFR54)
Maintenance Rule (10CFR50.65)
NRC GALL report
Long life, passive components selected
Active components included in PSR

17. Results of PSR on Kori-1(6)
47 Critical structures and components selected and
categorized into 12 groups
RPV
Pressurizer
Safety class 1 supports
Heat exchanger group
Cables
Concrete/steel structures
Select critical sub-components affecting the integrity
and function of structures and components selected
Reactor internals
Safety class 1 piping
Non-safety class 1 piping
PV group
Distribution panels
Underground facilities

18. Results of PSR on Kori-1(7)
Engineering evaluation
Most important step in aging management (PLiM)
Identify aging mechanisms for the selected groups
List generic age-related degradation mechanisms (ARDMs)
in each critical sub-component
Choose potential ARDMs to a sub-component based
on technical rationales

19. Results of PSR on Kori-1(8)
Aging mechanisms in Reactor Pressure Vessel

20. Results of PSR on Kori-1(9)
Evaluate the remaining life of the selected components
Reactor pressure vessel for instance
Evaluation of pressurized thermal shock
Evaluation of irradiation embrittlement
Evaluation of upper shelf impact energy
Evaluation of fatigue life

21. Results of PSR on Kori-1(10)

22. Results of PSR on Kori-1(11)
Aging management program (AMP)
Review current AMP and other NPP experience
Reactor pressure vessel for instance
Surveillance test
In-Service Inspection per ASME Sec. XI
Visual leak inspection
Primary water chemistry control
Recommend additional AMP
Ex-vessel dosimetry
Re-evaluation of RTNDT by Master curve method
Alloy 600 program, etc

23. Results of PSR on Kori-1(12)
Recommend performance monitoring system for AMP

24. Results of PSR on Kori-1(13)
Summary of PSR results on Kori-1
The safety of Kori Unit 1 re-confirmed
Safe operation expected until the next PSR
Some corrective action items recommended
to enhance the plant safety further
Korean unique PSR established

25. Prospect of PSR in Korea (1)
PSR results should be used
To confirm the comprehensive safety of a NPP
To secure safe operation until the next PSR
To identify corrective action items for enhancement of
the plant safety further
Recommended PSR strategy
Initial Criticality
PSR
10 years
20 years
30 years
Design life +
AMP

26. Prospect of PSR in Korea (2)
Operating license terms vs. design life
Operating license issued on Unlimited terms
(cf. OL of NPP in USA: 40 years)
FSAR of Kori Unit 1 describes design life as 30 years
(components designed for 40 years)
Problem?
Regulatory position not established
Anti-nuclear party considers design life as OL term
End of design life (2008) : not enough to prepare

27. Prospect of PSR in Korea (3)
Regulatory position under consideration
for plant life extension
PSR could be utilized in determining the plant life
extension by adding
PSA
Evaluation of environmental effects
Update of FSAR and TS
Introduction of Licensing Renewal rule

28. Development of PSR Technology
National Project
Aging management technology ($2.9M)
Operational transient analysis and new safety analysis
methodologies for NPP ($2.8M)
Seismic capacity evaluation of equipment ($2.1M)
Environmental radiation monitoring technology ($1.2M)
Assessment technology of effect of human and
organizational factors on NPP safety ($0.8M)
Project Period: Sept. 2000~Feb (4 years)

29. Conclusion PSR with AMP : Very useful tool for long term
operation beyond NPP design life
PSR – Overall safety review
AMP – Aging management program
Development of aging management technology
to establish AMP should be continued

30. Thank you for your attention !!