Muhammad Saeed ul Haque

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Radiation Protection
Implementation of
Optimization Principle in Pakistan

• Muhammad Saeed ul Haque
• Principal Scientist

Directorate of Nuclear Power Safety
Pakistan Atomic Energy Commission
2
Layout of Presentation

• PAEC objectives
• Safety is the hallmark of PAEC
• Independent regulatory Authority
• Regulation on radiation protection
• Optimization principle
• Facilities in PAEC
• What are we doing for optimization of radiation
  protection?
• Performance indicators at NPP
• Occupational exposure
• Occupational exposure control at NPP
• Public exposure control
• Services Provision by PAEC at National Level
• Future program
• What we expect from ARAN?

3
PAEC Objectives

• It is the objective of PAEC to plan and conduct
  its radiological activities in a manner that
  protects the health and safety of all its
  personnel, the general public and the
  environment.
• In achieving this objective, PAEC shall ensure
  that efforts are taken to reduce radiological
  exposures and releases to as low as reasonably
  achievable (ALARA), economic and social factors
  taken into account.
• The effective dose to individuals shall not
  exceed the limits recommended by Pakistan Nuclear
  Regulatory Authority (PNRA).

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Safety is the Hallmark of PAEC

• Obligation of Directorate of Nuclear Power Safety
  (DNPS) within PAEC
• Main mandate of DNPS
• To improve safety culture
• To assess and to perform internal safety audit
  of all PAEC establishments in the light of PNRA
  regulations.
• To act as a focal point for interaction between
  Pakistan Nuclear Regulatory Authority (PNRA) and
  the relevant projects/establishments of PAEC.
• To facilitate all PAEC establishments in the
  implementation of PNRA regulations.

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Independent Regulatory Authority

• Pakistan Nuclear Regulatory Authority (PNRA)
• An independent regulatorresponsible for
• To control
• To regulate.
• To supervise
• All nuclear safety and radiation protection
  activities to meet the national and
  international standards.

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Regulation on Radiation Protection

• PNRA Regulation on Radiation Protection PAK/904
  is based on BSS-115.
• The main feature of this regulation are
• No practice shall be licensed or authorized
  unless it produces sufficient benefit to
  individuals to be exposed or to society to offset
  the radiation harm that it might cause, taking
  into account social, economic and other relevant
  factors.
• The annual occupational exposure is limited up to
  20mSv

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Optimization Principle

• For exposure from sources in use, radiation
  safety shall be optimized in order that
• The magnitude of individual doses, the number of
  people exposed and the likelihood of incurring
  exposures all be kept as low as reasonably
  achievable (ALARA), economic and social factors
  being taken into account , within the restriction
  that the dose to individuals delivered by the
  source be subject to dose constraints.
• Released radioactive substances to the
  environment - dose constraints (fraction of dose
  limit) shall be established.

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Optimization Principle ..Cont.

• ANNUAL DOSE LIMITS FOR RADIATION WORKERS

Organ or Tissue Dose Quantity Dose Limits (mSv)
Whole body Effective dose 20
Lens of the eye Equivalent dose 150
Extremities (hand and feet) or Skin (average dose over 1 cm2 of the most highly irradiate area) Equivalent dose 500
In special circumstances, an effective dose of
up to 50mSv in a single year provided that the
average dose over five consecutive years does not
exceed 20mSv/year

• ANNUAL DOSE LIMITS FOR APPRENTICES/STUDENTS

Organ or Tissue Dose Quantity Dose Limits (mSv)
Whole body Effective dose 6
Lens of the eye Equivalent dose 50
Extremities (hand and feet) or Skin (average dose over 1 cm2 of the most highly irradiate area) Equivalent dose 150

• ANNUAL DOSE LIMITS FOR PUBLIC

Organ or Tissue Dose Quantity Dose Limits (mSv)
Whole body Effective dose 1
Lens of the eye Equivalent dose 15
Skin Equivalent Equivalent dose 50
In special circumstances, an effective dose of
up to 5mSv in a single year provided that the
average dose over five consecutive years does not
exceed 1mSv/year
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Facilities in PAEC

• PAEC has the following operational facilities in
  his domain
• Two nuclear power plants, KANUPP-1, CNPP-1
• Two nuclear research reactors, PARR-1PARR-2
• Four agriculture research centres
• Fourteen nuclear medical centres

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What are we doing for optimizing radiation
safety?

• DNPS performs review and assessment of
• Shielding design
• Facilities layout
• Available radioactive materials
• Safety and security of radioactive sources
• Competence of radiation workers
• Authorized radiation protection officer
• Radiation protection plan

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What are we doing for optimizing Radiation
safety? Conti.

• Inspection program
• Type of inspection
• Planned and unplanned inspections
• Periodic inspections
• Outage inspections
• Inspection ALARA RP checklists
• Assess regulatory requirements are
  comprehensively meets
• Availability and periodic calibrated required
  radiation monitoring equipments
• Ensuring availability and analysis of radiation
  dose records
• Recommendations and follow-up

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Performance indicators at NPP

• Parameters for assessment of effectiveness of
  radiation protection program

• Dose rates
• Contamination levels
• Occurrence of fuel failures/defects
• Personal doses
• Dose equity
• Outage collective dose

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Occupational Exposure

• Establishment of Occupational Database at NPP

Following information are available in this
database

• No. of persons exposed
• Average dose
• Collective dose
• Internal and External dose
• Maximum personal dose
• No. of workers in different dose ranges
• Outage dose
• Area dose rate

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Occupational Exposures Control at NPPs

• NPPs in Pakistan developed policies and
  procedures-for the protection of workers, public
  and environment
• Personnel monitoring programs
• Radiation Controlled Area-Electronic pocket
  dosimeter -TLD badges
• Contamination controlled program
• Environment monitoring program
• Internal radiation dose-respiratory
  equipment-bioassay sampling
• Issuance of radiation work permit (RWP)
• Job planning
• Job briefing
• Regular training

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Public Exposures Control

• Controlling the release of radioactive effluents
  from the plant.
• On-line monitoring of release effluents
• Filtration of gases effluent
• Decay and dilution of liquid effluent
• Collection, processing and storage of solid
  radioactive waste

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CNPP-1 Annual Collective Individual Dose (2004-06)
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CNPP-1 Average Individual Dose (2004-06)
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CNPP-1Occupational Exposure(2004-06)
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KANUPP Annual Collective Individual Dose (2004-06)
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KANUPP Average Individual Dose (2004-06)
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KANUPP Occupational Exposure(2004-06)
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Services Provision by PAEC at National Level

• Provision of protection level and therapy level
  calibration beam output measurement services at
  national level by Secondary Standard Dosimetry
  Laboratory (SSDL).
• Provision of personal radiation monitoring
  services for the measurement of occupational
  doses of workers at national level by film badges
  and thermoluminesence dosimeters.

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Future Program

• Centralization of dosimetry database
• Protection level calibration facility at
  Islamabad and Karachi
• Installation of Whole Body Counting facilities at
  Islamabad and Karachi

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What we expect from ARAN?

• Sharing of informations, experiences and feedback
• Event related discussions among the participants
  countries
• On line experts opinion/support in identifying
  problems, solutions and in making appropriate
  decision
• Harmonization in the implementation of radiation
  protection program in the region
• Interconnect groups of experts
• Sharing of research outcome among the
  participants countries
• Workshop/training on good ALARA implementation
  programs and practices
• Technical guidance and support in improving and
  in sustaining radiation protection infrastructure.

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The End