1. Current Status of Radiological Protection in NPPs of Korea
2010_ISOE_Asian ALARA Symposium
Current Status of Radiological
Protection in NPPs of Korea
Byoung-il, Lee
Korea Hydro & Nuclear Power Co., LTD
Radiation Health Research Institute

2. Contents National accreditation program of radiation dosimetry system3
NPP’s dosimetry system 3
NPP’s ALARA program 3 3
Exposure trends of NPP workers 3
RHRI’s activity for NPP’s RP

3. National accreditation program of radiation dosimetry system
KHNP - Radiation Health Research Institute
Current Status of Radiological Protection in NPPs in Korea
National accreditation program of
radiation dosimetry system

4. National accreditation program of radiation dosimetry Sys
Ministry of Education, Science & Technology
Korea Institute of
Nuclear Safety
Dose
Registry
Dose quality &
Radiation safety
control
Korea Radio-Isotope
Association
Yearly inspection
Yearly blind test with unknown TLD
yearly report
Internal dose
Quarterly report
External dose
Monthly TLD reading
Nuclear Power Plants
Yearly blind test with unknown bioassay sample by RHRI
Yearly professional training of EX/IN dose assessment by RHRI
Every two reactors have a TLD reading facility and an internal dosimetry facility

5. Quality Assurance Manual
Legislation of dose quality control – External dosimetry
Routine check < 1 month
Periodic check < 6 months
ANSI N 13.11
[8 Criteria-blind
test < 1 year]
Perfor-
mance
Criteria
Reader QC
Reader < 6 months
Chip < 2 years
Algorithm < 6 months
Calib-
ration
Quality Assurance Manual
Technical
Skills
Training < 1 year
Proce-
dure
LLD
Reader quality management
Reader & Chip calibration
Algorithm operation
Chip reading, annealing & management
Management of system & document
Management of person in charge
Lower Limit of Detection
TLD < 0.10 mSv

6. Legislation of dose quality control – Internal dosimetry
Internal dose
assessment
Management
of document
Measurement
method
Workers
required
bioassay
Internal
Dosimetry
legislation
If unobtainable,
Air sampling
Bioassay
Procedure
Requirements
of the bioassay
system
System operation
Technical skills
Surveillance and calibration Dose evaluation

7. Current Status of Radiological Protection in NPPs in Korea
KHNP - Radiation Health Research Institute
Current Status of Radiological Protection in NPPs in Korea
NPP’s dosimetry system

8. Present state of nuclear power plants in Korea
Kori unit 1 started commercial operation in 1978
The first Korea Standard Nuclear Power Plant(Ulchin unit 3, OPR-1000) completed the construction in1998
The first concrete casting for 1.4 million kW-level(APR-1400) Shin-Kori uint 3 in 2008
20 units in operation
(16-PWR, 4-PHWR)
24 % of power facility &
36 % of electricity use

9. Optimal radiation protection
NPP’s dose registry system
Dose report to the MEST
Dose control
Dose statistics
Optimal radiation protection
ERP(RAM) System
External
Shallow, deep, neutron,
extremity
Management of
radiation workers
Issue of radiation
work permit
Radiation dose
registry
Internal
Designation of
radiation worker
Control of RCA
entrance / exit

10. NPP’s radiation exposure control
Start
Satisfaction of the dose limit, training,
medical test, WBC or H-3 check
Non-homogeneous Exposure
Exposure exceeding 3 mSv, &
1.5 times of chest dose, &
Dose rate exceeding 1mSv/hr
Radiation
Work Permit ?
Exposure exceeding 4 mSv,
& 2 times of whole body dose
Yes No
+ Neutron
γ, β emitters ?
Yes
Wearing the Neutron TLD & PD No No
Homogeneous
Exposure ?
Whole body
Extremity ?
Wearing the extremity TLD
Yes
Yes
Wearing the additional TLD & Alarm dosimeter
(Chest & Back) 1

11. NPP’s radiation exposure control1
Wearing the Chest TLD
& Alarm dosimeter
Airborne
Radioactive
Materials
> 1 DAC
Yes
Wearing the mask No
ERP(RAM) System
RWP & Dose
& Entrance
requisite
RCA
Control
system 2

12. NPP’s radiation exposure control2
Radiation work
ERP(RAM) System
Alarm dosime-
ter dose &
Work record
RCA
Control
system
Yes
Abnormal
situation of alarm
dosimeter ?
TLD dose reading
promptly No
When alarm dosimeter is lost / destroyed
or displayed over-range / higher dose 3

13. Biological or mathematical
NPP’s radiation exposure control 3
Site inspection
- Dose rate & energy measurement
- Simulation of work situation
- Fellow’s dose & interview
Yes
Abnormally
exposed worker ? No No
> Dose Limit ?
Yes
Professional institute (RHRI)
Biological or mathematical
dose reconstruction
Worker who exceeded
annual dose limit or lost
/ destroyed his personal
dosimeter
National dose evaluation committee
Determination of the abnormally
exposed worker’s dose 4

14. NPP’s radiation exposure control4
Urine analysis
for H-3
Working in the airborne
radioactive materials or
high contamination area
When nose contamination
is detected
Yes
LSC
PHWR ? No
WBC
Yes
Necessity
of the internal
dosimetry ? No
TLD reading monthly
RAM System
Non-homogeneous Exposure
HE = 0.55[HP(10)] (chest) +
0.50 [HP(10)] (Back)
End

15. Current Status of Radiological Protection in NPPs in Korea
KHNP - Radiation Health Research Institute
Current Status of Radiological Protection in NPPs in Korea
NPPs’ ALARA Program

16. Laws regarding ALARA Korea atomic energy law Enforcement Ordinance
1995 :
Adoption of the “ALARA” concept
Korea atomic energy law
Release quantities of radioactive material to the environment
and occupational radiation doses are maintained ALARA
1999 :
Requirement to implement “ALARA””
Enforcement Ordinance
2000 :
Requirement to implement “ALARA””
MEST notice

17. Equipment improvements for ALARA in existing NPP
KHNP’s ALARA program
Equipment improvements for ALARA in existing NPP
KHNP has performed a substantial amount of equipment
improvements in order to meet the dose limitations
PSAR
preliminary safety analysis report
ALARA Design of Korea standard nuclear power plant
KSNPs are being constructed with an enhanced design based
on the experiences of the existing plants.
Year of 2008, average individual dose  1.1 mSv/yr
KSNP  0.5 mSv/yr

18. ALARA Procedure in operating NPP
KHNP’s ALARA program
ALARA Procedure in operating NPP
Any Works
Expected dose
Under 10 man-mSv
Expected Dose
10 ~ 70 man-mSv
Expected Dose
70 ~ 200 man-mSv
Expected Dose
Over 200 man-mSv
Use general RWP
- Use RWP
Evaluate expected dose
Work group should make
- Expected Dose sheet and ALARA check list
ALARA Subcommittee( Committee)
Review & approve
Review after works and
If actual dose exceeds 25% of expected dose
Feedback
ALARA subcommittee (Committee) Review, discuss
& apply : dose reduction method to repeated works

19. Current Status of Radiological Protection in NPPs in Korea
KHNP - Radiation Health Research Institute
Current Status of Radiological Protection in NPPs in Korea
Exposure trends of NPP workers

20. Dose distribution by operation state (1990 ~ 2007)
Normal operation
23 %
Refueling
77 %

21. Dose distribution by exposure type (1990 ~ 2007)
Neutron dose
2.7 %
Internal dose
5.3%
PWR 0.01%
Gamma
92.0 %

22. Annual individual dose trend of NPP workers

23. Radiation dose distribution of NPP workers
≥20
≥15
≥10
Year

24. Annual collective dose trend of NPP workers
(man/unit)

25. WANO PI report

26. Current Status of Radiological Protection in NPPs in Korea
KHNP - Radiation Health Research Institute
Current Status of Radiological Protection in NPPs in Korea
RHRI’s Activity for NPP’s RP

27. Radiation emergency medical preparedness for NPP
WHO/REMPAN Liaison Institute
24hr Emergency Response Program
Maintenance of REMP system with
NPP appointed hospitals
Education/ Training Program
-Primary H.
Secondary H.
* REMP : Radiation Emergency Medical Preparedness

28. Radiation Dose Assessment
Accidental dose evaluation system
Decision-making for the treatment of patient caused
by radiation exposure
Biological Assessment
Clinical Evaluation
CA, FISH, MN, PCC
Clinic symptoms
Radiation Dose
Assessment
Physical Assessment
Mathematical Assessment
ESR, WBC, LSC
Body Activation Analysis
MCNP, VOXEL

29. Electron Spin Resonance System
Tooth
Ring
Watch
C.P.
Sugar
Ceramics
Quartz
Spectrum in teeth
Dose response curve

30. Body Activation Analysis System
Modified BOMAB : 製作
血液分析
Neutron spectrum
: Excel 開發 照射
NPP
AAS
HPGe
KBADA
BSS
Water Slab Phantom : 製作
Dose assessment S/W:Visual Basic 開發
線量評價
MCNP-X 模寫

31. Development of Korean Phantom

32. Technical support about Internal dosimetry for
Study on internal dosimetry
Fast Scan
MCNP
CRM 改善
Inter-Comparison
Accu-Scan
HPGe
Technical support about
Internal dosimetry for
NPPs in Korea
Korean Phantom 開發
Measurement system 構築
Guide
Guideline
Training of
NPP members
IDEAS Guideline
Wound model
Guide S/W 開發

33. Program for Estimating Probability of Causation
Radiation dose reconstruction, PC calculation &
epidemiologic investigation
Program for Estimating
Probability of Causation

34. Low dose radiation research

35. Application study of ICRP new recommendation
2011(?)
(?)

36. Thank You ! Korea Hydro & Nuclear Power Co., LTD
Radiation Health Research Institute