Muhammad Saeed ul HaquePrincipal Scientist

Radiation ProtectionRadiation Protection

Optimization Principle in PakistanOptimization Principle in PakistanImplementation of Implementation of

Directorate of Nuclear Power SafetyDirectorate of Nuclear Power SafetyPakistan Atomic Energy Commission

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…?

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).

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.

Independent Regulatory Authority

■ Pakistan Nuclear Regulatory Authority (PNRA)

◘ An independent regulator…responsible for

● To control

● To regulate.

● To supervise

All nuclear safety and radiation protection activities to meet the national and international standards.

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

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.

Optimization Principle ……..Cont.

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

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

■ ANNUAL DOSE LIMITS FOR RADIATION WORKERS

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

* 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

■ ANNUAL DOSE LIMITS FOR PUBLIC

* 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

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-1&PARR-2

◘ Four agriculture research centres

◘ Fourteen nuclear medical centres

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

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

Performance indicators at NPP

◘ Dose rates

◘ Contamination levels

◘ Occurrence of fuel failures/defects

◘ Personal doses

◘ Dose equity

◘ Outage collective dose

■ Parameters for assessment of effectiveness of radiation protection program

Occupational Exposure

◘ 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

■ Establishment of Occupational Database at NPP

Following information are available in this database

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

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

CNPP-1 Annual Collective Individual Dose (2004-06)

CNPP-1 Annual Collective Dose(2004-06)

575.175

423.79

37.45

0

100

200

300

400

500

600

700

2004 2005 2006

Man

-mS

v

CNPP-1 Average Individual Dose (2004-06)

CNPP-1 Average Individual Dose (2004-06)

0.42

0.276

0.03

0

0.05

0.1

0.15

0.2

0.25

0.3

0.35

0.4

0.45

2004 2005 2006

mS

v

CNPP-1Occupational Exposure(2004-06)

KANUPP Annual Collective Individual Dose (2004-06)

KANUPP Annual Collective Individual Dose (2004-06)

1594.211430.9

5049.5

0

1000

2000

3000

4000

5000

6000

2004 2005 2006

Man

-mS

v

KANUPP Average Individual Dose (2004-06)

KANUPP Average Individual Dose (2004-06)

1.861.61

4.25

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

2004 2005 2006

mS

v

KANUPP Occupational Exposure(2004-06)

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.

Future Program

■ Centralization of dosimetry database ■ Protection level calibration facility at Islamabad and

Karachi■ Installation of Whole Body Counting facilities at

Islamabad and Karachi

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.

The End