radioactive pollution in pakistan and its side affects on the people of pakistan.

1. Current Status of
Radioactive Waste
Management in
Pakistan
By:
Zahir Shah
Manager (Repository)-DGNR
PAKISTAN ATOMIC ENERGY COMMISSION
PAEC-IAEA National Workshop on Strategy and Methodologies for the
Development of Near Surface Disposal Facilities
February 24-28, 2014, NCP Islamabad

2. Contents
1. General Perspective
2. Pakistan’s Perspective
2

3. GENERAL
PERSPECTIVE
3

4. Radioactive Waste
(RAW)
Material that contains or is contaminated with
radionuclides at concentrations or activities
greater than clearance levels as established
by the regulatory body and no intended use
of this material is foreseen
4

5. Radioactive Waste Sources
Radioactive Materials
Radioactive Waste
Nuclear Power Research
Medicine
& Agri.
Industry
Defense
5

6. Radioactive Waste Management
(RWM)
All activities, administrative and operational,
that are involved in the handling, pretreatment,
treatment, conditioning, transport, storage and
disposal of radioactive waste
6

7. Classification by IAEA
No. Waste classes Typical characteristics Disposal options
1 Exempt waste (EW) Activity levels at or below clearance levels
which are based on an annual dose to members
of the public of less than 0.01 mSv
No radiological
restrictions
2 Low and
intermediate
level waste (LILW)
Activity levels above clearance levels and
thermal power below about 2kW/m3
Near surface or
geological
disposal facility
2.1 Short lived waste
(LILW-SL)
T1/2 < 30 yr
Restricted long lived radionuclide
concentrations (limitation of long lived alpha
emitting radionuclides to 4000 Bq/g in individual
waste packages and to an overall average of 400
Bq/g per waste package)
2.2 Long lived waste
(LILW-LL)
Long lived radionuclide concentrations
exceeding limitations for short lived waste
Geological
disposal facility
3 High level waste
(HLW)
Thermal power above about 2kW/m3 and
long lived radionuclide concentrations
exceeding limitations for short lived waste
Geological
disposal facility
[Source: IAEA SAFETY SERIES No. 111-G-1.1, 1994]
IAEA aims at adoption of one classification scheme by all member states for harmonization of
management practices
7

8. Basic Principles of RWM
Observance of following principles will ensure that objectives of safe
management of RAW are met [IAEA’S Safety Series No. 111-F, 1995]
 Protection of human health
Radioactive waste shall be managed in such a way to
secure an acceptable level of protection for human health
 Protection of the environment
Radioactive waste shall be managed in such a way to
provide an acceptable level of protection for environment
 Protection beyond national borders
Radioactive waste shall be managed in such a way to
ensure that possible effects on human health and the
environment beyond national borders will be taken into
account
8

9. Basic Principles of RWM
 Protection of future generations
Radioactive waste shall be managed in such a way that
predicted impacts on the health of future generations will
not be greater than relevant levels of impact that are
acceptable today
 Burdens on future generations
Radioactive waste shall be managed in such a way that
will not impose undue burdens on future generations
 National legal framework
Radioactive waste shall be managed in such a way within
an appropriate national legal framework including clear
allocation of responsibilities and provision for independent
regulatory functions
Continued
9

10. Basic Principles of RWM
 Control of radioactive waste generation
Generation of radioactive waste shall be kept to the
minimum practicable
 Radioactive waste generation and management
interdependencies
Interdependencies among all steps in radioactive waste
generation and management shall be appropriately
taken into account
 Safety of facilities
The safety of facilities for radioactive waste management
shall be appropriately assured during their lifetime
Continued
10

11. Parts of RWM System
A comprehensive RWM system consists of
two interdependent parts:
 Pre-disposal management system
 Disposal management system
11

12. Pre-disposal Management
Pre-disposal management includes many steps
depending on the characteristics of the waste
streams/categories.
Major Steps involved:
 Pre-treatment
 Treatment
 Conditioning
 Interim Storage
12

13. Pre-Treatment
All the activities carried out prior to treatment of
Radwaste are called pre-treatment
Pre-treatment Techniques:
 Collection & segregation
 Chemical adjustment
 Physical adjustment
 Size reduction
 Decontamination
 Packaging
 Storage
13

14. Treatment
Operations intended to improve safety and/or economy by
changing the characteristics of the radioactive waste. After
treatment, the waste may or may not be immobilized to
achieve an appropriate waste form.
Treatment Techniques:
 Volume reduction
 Compaction
 Incineration
 Removal of radionuclides
 Change of composition
14

15. Conditioning
Includes all those operations that produce a
waste package suitable for handling,
transportation, storage and/or disposal
Conditioning mainly includes:
 Solidification
 Enclosure of the waste in containers
 Provision of an over pack (if required)
15

16. Packaging
 Conditioned waste is provided with additional
packaging for ease of handling and
transportation
 Packaging may cause increase in
weight/volume of waste package
16

17. Intended for storage of waste packages before transportation
to or placement in the disposal facility. Design/construction of
Interim storage is influenced by following factors:-
 Type of radioactive waste
 Characteristics and hazards
 Radioactive inventory
 Anticipated storage period
 Site characteristics
 Potential accident scenarios
Interim Storage
17

18. Disposal
Emplacement of waste in an appropriate facility
or a location without the intention of retrieval
Activity, half-life
VSLW VLLW LLW ILW HLW
18

19. Aims of Disposal
 To contain the waste over the period for which the waste
remains hazardous
 To isolate the waste from biosphere and to substantially
reduce the likelihood of inadvertent human intrusion into
the waste over the period for which the waste remains
hazardous
 To limit and reduce migration of radionuclides from the waste
to the biosphere and, as far as practicable, delay such
migration
 To ensure that the concentrations of radionuclides
eventually reaching the biosphere due to any migration
from the disposal facility are below harmful limits
19

20. Dukovany Near Surface Disposal Facility,
Czech Republic
20

21. Concrete disposal vaults at the Centre de l’Aube
LILW Repository, France
21

22. Aerial View of El Cabril LLW
Repository, Spain
22

23. PAKISTAN
PERSPECTIVE
Radioactive Waste
Management in Pakistan
is carried out in the light of
National Policy on RWM
23

24. PUBLIC SECTOR PRIVATE SECTOR
PAEC NON PAEC
Industries
(OGDC, PAF Kamra etc.)
Universities
Hospitals
NUCLEAR
MEDICINE
Shifa Int.
Islamabad
SKMH Lahore
BAQAI Karachi
INDUSTRY
(Users of
SRS)
Fertilizers
Petroleum
etc.
NUCLEAR POWER
KANUUP Karachi
KNC-1 Kundian
CHASNUPP-1 Chashma
CHASNUPP-2 Chashma
……………………………
28830 MWe by 2141
NUCLEAR RESEARCH
PINSTECH Islamabad
PIEAS Islamabad
NUCLEAR MEDICINE/
AGRICULTURE
NORI, INMOL, KIRAN
etc.
NIAB, NIBGE, NIFA etc.
Sources of RAW in Pakistan
24

25. National Policy on RWM
(Approved Document-2011)
Approved statement of National Policy, issued on 17th February
2011, is as under:-
1.Radioactive waste is generated by Nuclear Power Plants,
Nuclear Research Reactors, radioactive sources used by
industry and hospitals and research establishments. This
radioactive waste needs to be properly managed and stored at
safe and secure purpose built sites to protect human health and
environment. PAEC, the main producer of the radioactive
waste, is managing it with safety and security and storing it at
PINSTECH and KANUPP. Safe management of radioactive
waste in Pakistan will be ensured by Government of Pakistan.
The finances of radioactive waste will be managed through
Central Radioactive Waste Management Fund (RWMF)
established and maintained by PAEC for the safe management
of radioactive sources in the country. 25

26. National Policy on RWM
(Approved Document-2011)
2. As regards radioactive sources, used by hospitals and industry, these
will be imported and returned to the supplier as per PNRA
Regulations. Those radioactive sources which could not be returned
to supplier or orphan source will be stored at safe and secured sites
in the country. As there is no other site developed for the safe
storage/disposal of disused and orphan radioactive sources utilized
by private/public sector, PAEC will also be responsible for
storage/disposal of disused and orphan radioactive sources and
ownerless waste. Every generator of radioactive waste will be
responsible for safe and secure management of radioactive waste
until such time the radioactive waste is sent to designated storage
sites of PAEC for ultimate disposal and shall pay its cost for the safe
disposal to PAEC. PAEC will work out charges required for such
disposal. In case of management of orphan sources, sources cleared
by PNRA for disposal, the expenditure will be borne by Government
of Pakistan.
Continued
26

27. 3. Radioactive waste except for Disused
Sealed Radioactive Sources (DSRS) will neither
be imported nor exported as a policy until and
unless specifically permitted by Government of
Pakistan. Pakistan Nuclear Regulatory Authority
shall ensure safe control of all radioactive waste
including DSRS that is generated in the country.
National Policy on RWM
(Approved Document-2011)
Continued
27

28. National RAW Strategy
 PAEC has prepared “National Strategy on Safe Management of
Radioactive Waste Management in Pakistan”
 The strategy is approved and under implementation
 The strategy fixes obligations of following stakeholders
Responsibilities of Stakeholders:
 Regulatory body (PNRA)
Responsible for development of requirements and procedures for
the licensing of various types of radioactive waste management
facilities
 Waste Generators
Pre-disposal Activities: Pretreatment, Treatment, Conditioning,
Packaging (as per WAC) and Interim storage
 Directorate General National Repository (DGNR)
Disposal Activities: Off site transportation, Siting and
development of disposal facilities 28

29. CURRENT PRACTICES
29

30. Karachi Nuclear Power Plant
(KANUPP)
30

31. Waste Mangement at KANUPP
(Solid Waste)
Storage
Incinerator
Ash collection &
sealing in plastic bags
Storage in
Trenches
Compaction
(planned)
Direct Storage
in Trenches
Wet Storage
Conditioning
in cement
Storage
Spent Resin
LLW
(Combustible)
LILW
(Non-combustible)
Spent Fuel
DSRS and used Ra Needles
(from Sindh, Balochistan)
Dry Storage
31

32. Waste Management at KANUPP
(Liquid & Gaseous Waste)
Collection
Delay &
Decay Tanks
Further Storage
if act. is not
within limits
If act. is within limits
Dilution
Discharge
in Sea
Filters
All liquid waste
Gas
Discharge
through stack
32

33. Spent Fuel Storage at KANUPP
33

34. Storage of Conditioned Waste at
KANUPP
34

35. Conditioning of DSRS at
KANUPP
35

36. PINSTECH
36

37. Waste Management at PINSTECH
(Solid Waste)
Collection in
200 L MS drums Compaction
Conditioning in
200 L CS drums
Collection in
200 L MS drums
Interim Storage
Disposal in near
surface trench
Conditioning
in cement
Storage
Reuse at
Other places
DSRS (from Punjab,
KPK & Federal Area
& AJK)
ILW
ILW
(Non-Copmpactable)
LLW
(compactable)
37

38. Waste Management at PINSTECH
(Liquid & Gaseous Waste)
*HEPA -high efficiency particulate absorbing
Delay &
Decay Tanks
When activity is < 3.7 MBq/m3
Storage in underground
trench for delay & decay
Disposal in shallow
Ground pits
Treatment &
dilution
Cementation in
200 L MS drums
Storage
Disposal in near
surface trench
Filters (*HEPA
& charcoal)
Discharge through Stack
Gas
ILW
LLW
38

39. Compaction Unit at PINSTECH
39

40. Near Surface Trench at PINSTECH
40

41. CHASNUPP
41

42. Waste Management at CHASNUPP
(Solid Waste)
Storage
Spent Resin
Activated Carbon
De-iodinator
Conditioning in 200 L
CS drums
Decontaminated
Equipment
Cutting to
manageable size
Conditioning in
200 L CS drums
Spent Primary Filters Conditioning in
200 L CS drums
Contaminated
Soft Waste
Collection &
Segregation
Compaction in
200 L CS drums
Interim Storage
Spent Fuel Wet Storage Status yet to be decided
Conditioning
(Cementation)
Dry Storage
42

43. Waste Management at CHASNUPP
(Liquid & Gaseous Waste)
Chemical drains
Collection
In Sump
Delay &
Decay Tanks
Evaporator
Concentrate
Conditioning in
CS 200 L drums
Collection
In Sump
Collection
In Sump
Delay &
Decay Tanks
Discharged to environment
if sp. act. is within limits
If sp. act. is not within limits
Collection
Conditioning in
CS 200 L drums
Collection Delay &
Decay Discharge
OR
Interim
Storage
Clean drains
Process drain
Floor drains
Gas
43

44. Spent Fuel Storage at CHASNUPP
44

45. Solidified Drum Storage at CHASNUPP
45

46. Cementation at CHASNUPP
46

47. Hydraulic Compactor at CHASNUPP
47

48. Management of DSRS
Potential reuse
DSRS
Categorization
T½>30 years,
Bore
Hole/Geological
Disposal
T½ =100 d to <30y
Surface/Near
Surface Disposal
T½<100 days
Decay storage
Disposal as non-
radioactive
waste
Cleared material/waste
SRS from supplier
T½> 1 year and Act.>
100GBq
Others
*
DSRS
From Punjab, KPK, Federal
territory, FATA and AJK
From Sindh and
Balochistan
PINSTECH
(Interim
Storage)
KANUPP
(Interim
Storage)
Collection
Collection
Potential reuse
Conditioning
Conditioning
48

49. Status of Disposal Facilities
 As 90% of total volume of Radioactive waste
comprises of LLW, it is therefore, DGNR has
opted for a near surface repository.
 DGNR is performing area survey stage siting
studies for the identification of favorable potential
areas on the basis of site selection criteria.
 DGNR prefers to identify / locate potential sites in
northern half of the country.
49

50. Status of Interim Storage
Development of regional interim storage facilities:
 KANUPP
 CHASNUPP
Facility at KANUPP is under planning stage, while
at CHASNUPP is under construction
50

51.  Facility is Under Construction at C-1,
consists of two prefab buildings
Over-packing Building
Storage Building
Regional Interim Storage
Facility, CHASNUPP
51

52. Over-packing Building
 Dimensions: 22x22x5 m
 Process: Over-packing of 04 MS waste
(solid/solidified) drums in RCC container
(1.5x1.5x1.26 m)
 Filling of void space with concrete in RCC
container
 Capping of RCC container with concrete
52

53. STORAGE BUILDING
 Dimensions: 65x22x5 m
 Capacity: 1000 RCC containers in 3-
stackings
53