radiation safety

Approved by the Board on October 5, 2001

Atomic Energy Regulatory BoardMumbai 400 094

AERB SAFETY CODE NO. AERB/SC/IR-1

SAFETY CODEFOR

INDUSTRIAL RADIOGRAPHY

This document is subject to review, after a period of oneyear from the date of issue, based on the feedback received.

Price:

Orders for this Code should be addressed to:

Administrative OfficerAtomic Energy Regulatory Board

Niyamak Bhavan,Anushaktinagar

Mumbai - 400 094

i

FOREWORD

Widespread utilisation of ionising radiation for multifarious applications in

medicine, industry, agriculture, research etc. has brought in its wake the need

for exercising regulatory controls to ensure safety of the users and members of

the public and protection of the environment. The Atomic Energy Regulatory

Board (AERB), constituted under the Atomic Energy Act, 1962 by the Government

of India, is entrusted with the responsibility of developing and implementing

appropriate regulatory measures aimed at ensuring radiation safety in all

applications involving ionising radiation. One of the ways to meet these

responsibilities is to develop and enforce specific codes and standards dealing

with radiation safety aspects of various applications of ionising radiation to cover

the entire spectrum of operations, starting from design of radiation equipment,

their installation and use to their ultimate decommissioning/disposal.

In view of the fact that regulatory standards and requirements, techniques of

radiation safety engineering and type of equipment change with time, it becomes

necessary to review and revise codes and standards from time to time to

incorporate these changes.

AERB has in the past issued safety guides on "Enclosed Radiography

Installations", "Open Field Radiography Installations", and "Handling of Radiation

Emergencies in Industrial Radiography". While the mandatory framework for

radiation safety in industrial radiography is provided in the Radiation Surveillance

Procedures issued under the Radiation Protection Rules, 1971, and safety

requirements of exposure devices and source changers are spelt out in a standard

(specifications), the regulatory requirements specific to radiography practices have

not been stipulated. However, AERB has ensured that the radiography equipment

and source changers used in the country comply with the safety standards and

are type approved. The need for a safety code elaborating the regulatory

provisions of the surveillance procedures has been felt both by the radiography

industry and by the agencies carrying out regulatory inspections in the country

for verification of compliance with safety stipulations. This Safety Code has now

been prepared by a task group (Task Group VI) constituted by AERB.

This Code consolidates all the regulatory requirements relevant to industrial

radiography in one document along with material reproduced from other

mandatory documents of AERB. It is thus a stand-alone document on the subject.

ii

The Standing Committee for Review and Revision of AERB's Safety Documents

constituted by Chairman AERB has undertaken the scrutiny and finalisation of

this Code. Technical support has been provided by a committee constituted by

Chairman, AERB to assist in its finalisation. The Code was approved on October

5, 2001 by the Atomic Energy Regulatory Board for issuance in its present form

and is effective from its date of approval.

AERB wishes to thank all individuals and organisations who helped in the

preparation of the Code. The names of persons who participated in its preparation

are listed, along with their affiliations, for information.

(Suhas P. Sukhatme)

Chairman, AERB

iii

DEFINITIONS

A1

Maximum activity of special form radioactive material permitted in a Type A

Package.

A2

Maximum activity of radioactive material, other than special form radioactive

material, permitted in a Type A package.

Accelerator

A device in which charged particles are accelerated. Conventional X-ray tube is

not considered as an accelerator.

Accident

Any unintended event resulting in (or having potential to result in) injury or

damage to the equipment, which could cause release of unacceptable quantities

of radioactive materials.

Activity

The quantity A for an amount of radionuclide in a given energy state at a given

time, defined as:

A = dN/dt

where, dN is the expectation value of the number of spontaneous nuclear

transformations from the given energy state in a time interval dt. The SI unit of

activity is the reciprocal second, s-1, termed the becquerel (Bq).

Annual Limit on Intake (ALI)

The intake by inhalation, ingestion or through the skin of a given radionuclide

in a year by the Reference Man which would result in a committed dose equal

to the relevant dose limit. The ALI is expressed in units of activity.

iv

Applicant

Any person who applies to the competent authority for consent to undertake

any of the actions for which the consent is required.

Approval

A type of regulatory consent issued by the competent authority to a proposal.

Becquerel (Bq)

See 'Activity'

Competent Authority

Any officer or authority appointed, approved or recognised by the Government

for the purpose of the Rules promulgated under the Atomic Energy Act, 1962.

Consent

It is a written permission, issued to the consentee by the competent authority

to perform specified activities related to nuclear and radiation facilities. The types

of consents are 'License', 'Authorisation', 'Registration' and 'Approval', and will

apply depending upon the category of the facility, the particular activity and

radiation source involved.

Consentee

A person to whom consent is granted by the competent authority under the

relevant rules.

Contamination

Presence of radioactive substance in or on a material, or (in or on) the human

body in excess of quantities specified by the competent authority.

v

Dose

A measure of radiation received or absorbed by a target. The quantities termed

absorbed dose, organ dose, equivalent dose, effective dose, committed equivalent

dose or committed effective dose are used depending on the context. The

modifying terms are used when they are necessary for defining the quantity of

interest.

Effective Dose

The quantity E, defined as a summation of the tissue equivalent doses, each

multiplied by the appropriate tissue weighting factor:

E = Σ WT.HT

T

where HT is the equivalent dose in tissue T and WT is the tissue weighting factor

for tissue T. The unit of effective dose is J.kg−1, termed the sievert (Sv).

Enclosed Installation

In the case of industrial radiography, installation in which radiography operations

are carried out in an enclosure, which has walls providing adequate radiation

protection to persons working outside the enclosure, and which prevents

unauthorised entry of persons into the enclosure during radiography operations.

Such installations may include open top installations also.

Emergency

A radiation incident leading to unforeseen circumstances where the radiation

exposure to workers and members of the public is not under control and may

lead to a potentially hazardous situation.

Employer

Any person with recognised responsibility, commitment and duties towards a

worker in his or her employment by virtue of a mutually agreed relationship

(A self-employed person is regarded as being both a worker and employer).

Equivalent Dose

The quantity HT,R, defined as:

HT,R = DT,R .WR

where DT,R is the absorbed dose delivered by radiation type R averaged over

a tissue or organ T and WR is the radiation weighting factor for radiation

type R.

When the radiation field is composed of different radiation types with different

values of WR, the equivalent dose is:

HT = ∑ WR.DT,R

R

The unit of equivalent dose is J.kg−1, termed the sievert (Sv).

Licence

It is a type of regulatory consent, granted by the competent authority for all

sources, practices and uses for nuclear facilities involving the nuclear fuel cycle

and also certain categories of radiation facilities.

Occupancy Factor (T)

For the purpose of calculating protective shielding, the factor by which workload

is multiplied, in order to take account of the degree of occupancy.

Package

The packaging with its radioactive contents as prescribed for transport;

Packaging

The assembly of components necessary to enclose the radioactive contents

completely.

vi

vii

Personnel Monitoring

Determination or estimation of the dose received by a person from external and

internal radiation.

Quality Assurance

Planned and systematic actions necessary to provide adequate confidence that

an item or a facility will perform satisfactorily in service as per design

specifications.

Radioactive Waste

Material, whatever its physical form, remaining from the practices or interventions

and for which no further use is foreseen: (a) that contains or is contaminated

with radioactive substances and has an activity, or activity concentration, higher

than the level for clearance from regulatory requirements; and (b) exposure to

which is not excluded from regulatory control.

Radiography

Technique for obtaining, recording, and optionally processing, directly or after

transfer, information contained in an X-ray pattern at an image receptor area.

Radiography Source

A source sealed in one or more capsules, or an X-ray tube, or an electron

accelerator or a neutron source used for industrial radiography;

Radiography Technician/Radiography Technologist/Radiographer

A worker who performs radiography operations employing radiography sources

and possesses a valid qualification duly recognised by the competent authority

for the specific purpose.

Radiological Safety Officer (RSO)

Any person who is so designated by the employer and who, in the opinion of

the competent authority, is qualified to discharge the functions outlined in the

Radiation Protection Rules, 1971.

viii

Safety Site-in-charge

A person who has the qualifications and training prescribed for Level-II

Radiological Safety Officer and who is appointed by the consentee as the person

supervising industrial radiography operations at an authorised radiography site

with the approval of the competent authority.

Source Assembly

An assembly of components consisting of gamma radiography source and a

mechanism for connecting the drive system.

Source Changer

A device for transfer of radiography source(s) from or to exposure device, and

suitable for transport and storage of the source(s).

Source Drive Mechanism

A remotely operating mechanism which drives a radiography source out of, or

into, a storage container.

Source Guide Tube

A flexible or rigid tube through which the source holder moves from its secured

position in the source housing to its working position.

Special Form Radioactive Material

Either an indispersible solid radioactive material or a sealed capsule containing

radioactive material and approved by the competent authority as special form

radioactive material.

Type A Package

A package designed to withstand normal conditions of transport without loss

or dispersal of its contents or loss of shielding integrity. The radioactive material

ix

may be transported in a Type A package either in special form radioactive material

or other form with the proviso that the activity shall not exceed the applicable

limits prescribed in the relevant Code on Transport of Radioactive Materials (SC/

TR-1).

Type B(U) Package

A package designed to contain an activity in excess of A1, if special form

radioactive material, or in excess of A2, if not special form radioactive material,

that is designed to withstand normal and accidental conditions of transport

specified in the relevant Code on Transport of Radioactive Materials (SC/TR-1).

Type B(M) Package

A package whose design or shipment requires multilateral approval because it

does not meet all the requirements of a Type B(U) package.

Type Approval

Approval issued by the competent authority based on evaluation of the device

to ensure that it conforms to safety standards.

Worker

Any person, who works, whether full-time, part-time or temporarily, for an employer

and who has recognised rights and duties in relation to occupational radiation

protection (self-employed person is regarded as having duties of both an employer

and worker).

Workload (W)

For the purpose of shielding computation, the radiation output or equivalent

quantity integrated usually over a working week.

Note: Words and expression not defined in this Code, but defined in the Act, Rules andSurveillance Procedures shall have the meanings respectively assigned to them in the Act,

Rules and Surveillance Procedures.

x

SPECIAL DEFINITIONS

Collimator

A device used for limiting the size and shape of the primary radiation beam.

Crawler Equipment

Self-powered remote-controlled equipment containing X-ray/gamma ray source,

which can be introduced in a pipeline for radiographic inspection of welds.

Field Radiography

Radiography operations carried out on shop floors, erection sites or other such

areas, with provisions for adequate radiological safety for radiography personnel

and others, including members of the public.

Industrial Gamma Radiography Exposure Device

An assembly of components necessary to make radiographic exposure and which

includes source housing, source assembly mechanism for securing source

assembly control, and other components associated with positioning the source,

such as source guide tubes.

Industrial Radiography Installation

A radiation installation employed for industrial radiography operation. It can be

open-field radiography or enclosed radiography.

Leakage Radiation

Any radiation coming from the source housing, other than useful beam or primary

beam.

Pigtail

A short flexible cable connecting the source holder with the operating end of

the drive cable in a remotely operated gamma exposure device.

xi

Radiation Level

The equivalent dose rate expressed in millisieverts per hour (mSv/h).

Radiation Monitoring Instrument

An active device or instrument used for detecting radiation fields and measuring

air kerma rate.

Scattered Radiation

Ionising radiation emitted by interaction of ionising radiation with matter, the

interaction being accompanied by a reduction in radiation energy and/or by a

change in direction of the radiation.

Shielding

Protective shielding in the form of attenuating material provided for radiological

protection.

Stray Radiation

The sum of leakage radiation and scattered radiation.

X-ray Equipment

Equipment consisting of a combination of X-ray generator, X-ray tube and

associated equipment.

CONTENTS

FOREWORD .................................................................................................. i

DEFINITIONS................................................................................................. iii

SPECIAL DEFINITIONS................................................................................ x

1. INTRODUCTION ................................................................................ 1

2. RADIOGRAPHY EQUIPMENT AND SOURCES ............................. 3

3. INDUSTRIAL RADIOGRAPHY INSTALLATION ............................ 10

4. PERSONNEL REQUIREMENTS AND RESPONSIBILITIES ............ 13

5. REGULATORY CONTROLS ............................................................... 20

6. EMERGENCY PREPAREDNESS ......................................................... 26

APPENDIX-I : DOSE LIMITS .............................................................. 28

APPENDIX-II : FORMAT OF THE "APPLICATION FOR TYPE

APPROVAL OF INDUSTRIAL GAMMA

RADIOGRAPHY EXPOSURE DEVICE

AND SOURCE CHANGER" ........................................ 29

APPENDIX-III : RADIATION SYMBOLS .............................................. 35

APPENDIX-IV : FORMAT OF THE "LOGBOOK TO BE

MAINTAINED BY THE CONSENTEE AT THE

RADIOGRAPHY SITE" ................................................ 36

APPENDIX-V : FORMAT OF THE "INFORMATION TO

BE FURNISHED BY THE CONSENTEE

REGARDING THE LOCATION

DETAILS OF THE INDUSTRIAL GAMMA

RADIOGRAPHY EXPOSURE DEVICE" ..................... 38

APPENDIX-VI : FORMAT OF THE "APPLICATION FOR

APPROVAL OF NOMINATION OF

RADIOLOGICAL SAFETY OFFICER

IN INDUSTRIAL RADIOGRAPHY" ........................... 40

APPENDIX-VII : FORMAT OF THE "INFORMATION TO

BE FURNISHED BY THE RADIOLOGICAL

SAFETY OFFICER IN INDUSTRIAL

RADIOGRAPHY INSTITUTION"................................ 46

APPENDIX-VIII : FORMAT OF THE "APPLICATION FOR

APPROVAL OF SAFETY SITE-IN-CHARGE/

CERTIFIED RADIOGRAPHER IN INDUSTRIAL

RADIOGRAPHY" ......................................................... 50

APPENDIX-IX : FORMAT OF THE "APPLICATION FOR

AUTHORISATION TO DISPOSE OF

RADIOACTIVE WASTES, DECAYED/

UNUSED SOURCES (BY SMALL

INSTALLATIONS) " .................................................... 54

BIBLIOGRAPHY ..................................................................................... 57

LIST OF PARTICIPANTS ............................................................................. 58

TASK GROUP VI: TASK GROUP FOR PREPARATION OF SAFETY

CODE FOR INDUSTRIAL RADIOGRAPHY ............................................... 58

STANDING COMMITTEE FOR REVIEW AND REVISION OF AERB'S .

RADIATION SAFETY DOCUMENTS (SCRCG) ......................................... 59

COMMITTEE TO FINALISE THE TEXT OF SAFETY CODE FOR

INDUSTRIAL RADIOGRAPHY .................................................................... 60

1. INTRODUCTION

1.1 Purpose

This Code stipulates the requirements for radiation safety of persons

handling industrial gamma radiography exposure devices and X-ray

generating equipment for industrial radiography, in order to:

(a) ensure that radiography workers and members of the public are

not exposed to radiation in excess of the limits specified by the

competent authority under the Radiation Protection Rules, 1971,

and under the safety directives issued from time to time

(Appendix-I);

(b) reduce radiation exposures below these limits to levels as low as

reasonably achievable;

(c) ensure safe custody, use, transportation, and disposal of

radiography sources and equipment; and

(d) provide for prevention of hazardous situations and initiate

appropriate actions to mitigate consequences of radiation

emergencies.

1.2 Scope

Radiation safety in handling radiation sources is governed by sections

14, 16 and 17 of the Atomic Energy Act, 1962, and the Radiation Protection

Rules (RPR), G.S.R. 1601, 1971 issued under the Act. The Industrial

Radiography (Radiation Surveillance) Procedures G.S.R. 735, 1980 issued

under Rule 15 of RPR specify the general requirements for radiation safety

of (a) persons handling gamma radiography sources and (b) members of

public. The Radiation Surveillance Procedures for Safe Transport of

Radioactive Materials, 1987; the Atomic Energy (Safe Disposal of

Radioactive Wastes) Rules, G.S.R. 125, 1987; AERB Safety Code for

Transport of Radioactive Materials (AERB/SC/TR-1); AERB Standard for

1

2

Testing and Classification of Sealed Radioactive Sources (AERB/SS-3);

and AERB Standard (Specifications) for Radiological Safety for the Design

and Construction of Industrial Gamma Radiography Exposure Devices and

Source Changers (AERB/SS-1), specify the mandatory requirements

applicable to industrial radiographic practice. This Safety Code elaborates

the provisions relevant to various industrial radiography operations.

Guidance on implementing the requirements of this Code is provided in

the supporting document1. This Code does not cover neutron

radiography.

1 Safety Guide on Industrial Radiography

3

2. RADIOGRAPHY EQUIPMENT AND SOURCES

2.1 Gamma Exposure Device

2.1.1 General

The industrial gamma radiography exposure device (henceforth referred

to as the device) shall be capable of remote operation and control and

shall be designed and built to comply with the AERB Standard entitled

"Radiological Safety for the Design and Construction of Gamma

Radiography Exposure Devices and Source Changers", AERB/SS-1.

2.1.2 Source Housing

The device is classified as portable, mobile or fixed, depending on its

overall weight as specified in AERB-SS-1. Shielding provided by source

housing shall be such that when the control mechanism is securely locked

in its 'OFF' condition and a radiography source of maximum rated activity

is in the housing, the leakage radiation outside the housing shall not

exceed the limits given in the Table 2.1 for the three classes. In order

to establish compliance, the radiation level at 5 cm from the surface of

the device shall be measured over an area of 10 cm2 with no linear

dimension greater than 5 cm. At 1 m, the area of measurement shall be

not less than 100 cm2 with no linear dimension greater than 20 cm. The

limits are averaged over these measurement areas.

TABLE 2.1: LIMITS ON LEAKAGE RADIATION LEVELS

C l a s s

Portable 2 0.5 0.02

Mobile 2 1.0 0.05

Fixed 2 1.0 0.10

On the externalsurface of source

hous ing(mSv/h)

At 5 cm from externalsurface of sourcehousing (mSv/h)

At 100 cm fromexternal surface of

source housing(mSv/h)

4

Source housing shall be so designed as to serve also as transport package

(either Type A or Type B) as appropriate. The maximum activity that can

be transported in a Type A package when the radioactive material is in

special form is as given in Table 2.2. The source housing shall comply

with the applicable design requirements for Type A/Type B package as

specified in the AERB Safety Code for Transport of Radioactive Material,

AERB-SC/TR-1.

TABLE 2.2: ACTIVITY LIMITS FOR TYPE A PACKAGE FORSPECIAL FORM RADIOACTIVE MATERIAL

Radionuclide Activity limit in TBq

60Co 0.4

137Cs 2.0

170Tm 4.0

192Ir 1.0

2.1.3 Marking and Labelling

Notwithstanding the permanent marking affixed by the manufacturer, as

specified in AERB-SS-1, the user shall attach to each device a durable,

legible, and clearly visible label bearing the (i) chemical symbol and mass

number of the radionuclide in the device; (ii) activity and the date on

which this activity was measured; (iii) model number and serial number

of the sealed source; (iv) manufacturer of the sealed source;

(v) consentee's name, address and telephone number; (vi) radiation

symbol (trefoil symbol); (vii) total weight of the device without removable

accessories; (viii) serial number of the device; and (ix) package design

approval identification number. If depleted uranium is used as shielding,

the device shall be so marked and the mass of depleted uranium shown.

2.1.4 Security and Safety

The device shall have tamper-proof lock for physical security of the

source to prevent unauthorised operation. It shall not be possible to

5

(i) operate the lock unless the source assembly is in fully shielded

position; or (ii) remove the source assembly/pigtail from the back of the

device even when the device is unlocked. Built-in features to prevent

system failures shall include means to ensure proper and firm connection

of the source assembly to drive cable and source housing to guide tube.

2.2 Source Changer

2.2.1 Source Housing

Source changer shall comply with the requirements of AERB-SS-1.

Leakage radiation (on the surface, at 5 cm, and at 1 m) with source(s)

of maximum capacity in the changer shall not exceed the limits specified

for portable class radiography device (Table 2.1). The method of

compliance shall be as specified in 2.1.2. Source changer shall also comply

with package design as specified in 2.1.2.

2.2.2 Marking and Labelling

Each source changer shall have attached to it by the user a durable, legible

and clearly visible label bearing (i) chemical symbol and mass number

of the radionuclide in the device; (ii) activity and the date on which this

activity was measured; (iii) model number and serial number of the sealed

source; (iv) manufacturer of the sealed source; (v) Consentee's name,

address and telephone number, (vi) trefoil symbol; (vi) serial number of

the source changer; and (vii) package design approval identification

number.

2.2.3 Security and Safety

Source changer shall have tamper-proof lock for physical security of the

source and to prevent unauthorised operation. It shall not be possible

to operate the lock unless the source or source assembly is in the fully

shielded position. Measures to ensure proper and firm connection of the

guide tube to the source changer shall be provided.

6

2.3 Sealed Source

The sealed source shall comply with the Standard (Specification) on

Testing and Classification of Sealed Radioactive Sources, AERB-SS-3. The

radiography source shall at least meet the requirement for 43313

classification (Table 2.3) of AERB-SS-3.

TABLE 2.3: TEST CONDITIONS FOR 43313 CLASSIFICATION

S. No. Test Conditions

1 Temperature −40°C (20 minutes), +400°C (1 hour) and

thermal shock +400°C to 20°C

2 External pressure 25 kPa absolute to 2 MPa absolute

3 Impact 200 g from 1 m

4 Vibration No test

5 Puncture 10 g from 1 m

2.4 X-Ray Equipment

(i) The protective tube housing shall be so constructed that the

stray radiation in any direction, averaged over an area of not more

than 100 cm2, shall not exceed 10 mGy per hour at a distance

of 1 m from the X-ray target when, with the beam portal shielded

adequately, the tube operates at its peak kilovoltage (kVp) and

maximum rated current.

(ii) The electrical cable shall be at least 7 m long for machines

operating up to 100 kVp, 10 m long for up to 200 kVp, 15 m long

for 200 - 250 kVp and 20 m long for above 250 kVp.

(iii) The control console shall have means to display the tube

potential, tube current, duration of exposure and X-ray beam

status. Energising the X-ray equipment shall be key-controlled to

prevent unauthorised use.

(iv) There shall be separate provision to terminate radiation

generation automatically after pre-set time and manually at any

time.

7

2.5 Crawler Equipment

(i) The gamma radiography crawler shall comply with requirements

specified in 2.1.2, and X-ray crawler shall comply with

requirements specified in sub-section 2.4.

(ii) Means shall be provided for external indication of the crawler

location in a pipeline. There shall be means to prevent exposure

when the external position indicator fails to function as intended.

(iii) The width of useful beam on the pipe surface shall not be greater

than 20 cm.

(iv) The crawler equipment shall shut 'OFF' automatically in the event

of any malfunction during use, i.e. X-ray crawler shall switch off

the beam and the gamma source shall retract to shielded position.

2.6 Accelerator Equipment

(i) The high energy particle accelerator generating X-rays shall meet

the requirements specified in sub-section 2.4 for X-ray equipment.

(ii) Key-controlled interlock shall be provided on the control console

to prevent unauthorised use.

(iii) The beam limiting system of a portable/mobile equipment meant

for use on shop floor or elevated locations shall restrict the

primary beam divergence to a cone of not more than 30° apex

angle.

(iv) An emergency push button shall be prominently located on the

control panel to terminate the radiation generation.

(v) When radiation generation is terminated, either by an interlock

or by action of emergency push button, it shall not be possible

to restart unless the exposure control is reset manually.

2.7 Type Approval of Radiography Equipment/Exposure Devices, SourceChanger and Sources

(i) Any X-ray equipment, accelerator or gamma radiography exposure

device/source changer shall be used only after it is type approved

by the competent authority.

8

(ii) The manufacturer/supplier seeking type approval shall submit an

application in writing along with detailed drawings of the

equipment/device and a report on safety analysis for type

approval (Appendix-II).

(iii) Safety analysis report shall provide evidence of compliance with

AERB-SS-1 and with applicable requirements of this Section and

the results of tests carried out on the prototype. The report shall

provide evidence on the quality assurance (QA) programme.

(iv) For gamma radiography exposure device manufactured in any

other country, type approval is granted based on documentary

evidence on their conformance to AERB-SS-1 Standard and

evidence that the device has the approval of Type A/Type B

package design by the competent authority of the country of

origin.

(v) Exposure device shall have an approval as package of appropriate

type for transport in public domain. Where necessary, the gamma

radiography source shall have been certified as meeting the

requirements of special form of radioactive material for transport

in accordance with AERB/SC/TR-1.

(vi) Exposure device, accelerator, X-ray equipment, or package shall

not be manufactured or supplied after expiry of validity period

specified in the type/package design approval unless the

approval is revalidated.

(vii) In case of certain equipment/device, the competent authority may

grant a No Objection Certificate (NOC) for import of one unit.

Type approval may be granted after evaluating the safety of the

equipment/device.

2.8 Servicing and Maintenance

(i) Servicing and maintenance of radiography exposure devices/

source changer or accelerator or X-ray equipment shall be

provided by service engineers certified by the competent

authority.

9

(ii) The manufacturer/supplier of radiation equipment, source changer

and device shall be responsible for providing servicing and

maintenance throughout the useful life of the equipment or device

or source changer by persons with appropriate qualification and

training. He/she shall also be responsible for safe disposal of

radioactive source and radioactive material.

(iii) The manufacturer or supplier shall also be responsible for supply

of spares and accessories.

10

3. INDUSTRIAL RADIOGRAPHY INSTALLATION

3.1 Enclosed Radiography

(i) The room housing radiography equipment (exposure device/X-ray

equipment/accelerator) shall be in a location where the occupancy

and traffic are as low as practicable and shall not be located in

a residential building or an office complex. The installation shall

be fully enclosed and shielded, or enclosed on all sides except

ceiling (open top) and shall be duly approved by the competent

authority.

(ii) Fully enclosed installations shall have structural shielding for

walls/doors, ceiling and floor so that radiation level outside the

shielding conforms to annual dose limits for occupational workers

and general public as appropriate. In case of open top installation,

the scattered radiation (sky-shine) shall also be considered.

(iii) The conduit/opening for cables between the control room and

exposure room shall prevent direct streaming of radiation.

(iv) The door interlock shall prevent operation of X-ray equipment

or accelerator when the door is open or improperly closed. The

interlock shall activate a warning light and illuminate a placard

to caution persons during exposure. A radiation zone monitor

shall be provided near the entrance to continuously indicate the

radiation level. The monitor shall be capable of detecting even

a partial opening of entrance door. Radiation interlock shall

interrupt radiation generation when the radiation zone monitor in

the controlled area detects radiation in excess of a pre-set level.

(v) Exposure controls for the device/X-ray equipment/accelerator

shall be located outside the shielded room. Identification of each

control shall be distinct and unambiguous.

(vi) The concentration of ozone in accelerator room shall not exceed

0.1 ppm at the time of entry.

11

(vii) The radiation symbol specified under Rule 17 of the Radiation

Protection Rules, 1971 shall be conspicuously posted at the

entrance (Appendix-III). A placard indicating "RADIATION

HAZARD: RESTRICTED ENTRY" shall be posted, alongwith its

equivalent in Hindi as well as in local language, alongside the

radiation symbol. An X-ray hazard symbol as prescribed in

Appendix -III, shall be conspicuously posted in case an X-ray

machine is used.

(viii) There shall be sequentially operated search buttons in high

energy accelerator installation with long maze which does not

offer direct view from the control panel or entry door to ensure

that no person remains in the room when the machine is

energised. A trip wire shall be provided at easily accessible height

around the inside periphery of large X-ray or accelerator rooms

so that a person inadvertently present in the room when the

machine is 'ON' may pull the wire to trip off the radiation. There

shall be audible alarm inside the radiography room during

radiation generation.

3.2 Field Radiography

(i) Field radiography includes radiography in shop floors,

construction/erection sites and public areas and radiography

operations outside an enclosed installation. Field radiography

shall be carried out in locations where occupancy and traffic are

as low as practicable.

(ii) Field radiography shall not be carried out without the use of

collimator except in case where it is not physically possible. In

such a situation, field radiography shall be carried out with the

written permission of RSO Level-II.

(iii) The immediate surroundings of a radiation source shall be

cordoned off with a placard displayed at boundary to warn

against unauthorised presence inside or near the radiography site.

The cordon-off distance shall be determined on the basis of

12

workload and occupancy outside the boundary subject to

limitation of annual dose as specified in clause (ii) of sub-section

3.1.

(iv) The radiation symbol specified in clause (vii) of sub-section 3.1

shall be posted at the cordon along with placards with the legend

'RADIATION HAZARD--KEEP AWAY' and its equivalent in Hindi

as well as in local language. A red warning light shall be displayed

at night.

(v) An exclusive storage room conforming to the requirements of

clause (ii) of sub-section 3.1 shall be provided for safe custody

of sources in exposure devices during periods of non-use.

13

4. PERSONNEL REQUIREMENTS ANDRESPONSIBILITIES

4.1 Consentee

In any radiography institution, the consentee shall:

(a) employ a minimum staff of (i) one certified radiographer for each

exposure device/equipment, (ii) one safety site-in-charge for each

radiography site (radiography operations being carried out at

places 5 km or more from each other are considered as separate

sites), and (iii) one radiological safety officer (RSO) level-III for

each institution engaged in radiography operations in more than

two sites at a time;

(b) have an organisational hierarchy with clear lines of authority and

responsibility and lines of communication in accordance with this

code;

(c) inform the competent authority of any change in the organisation;

(d) provide adequate facilities and resources to the RSO/safety site-

in-charge to discharge his duties and safety functions in

accordance with this Code;

(e) provide adequate facilities and resources to ensure that all

workers and trainees are provided with personnel monitoring

devices and these persons are instructed in writing to wear the

personnel monitoring devices while working with radiation;

(f) inform the competent authority immediately if RSO, safety site-

in-charge, or radiographer leaves the institution and suspend the

radiography work until the replacement personnel have assumed

charge of their tasks;

(g) ensure that industrial radiography installation is approved by the

competent authority and constructed according to the approved

design;

(h) ensure that gamma radiography exposure devices/X-ray

equipment/accelerators/source changers to be used are of the

type approved by the competent authority;

14

(i) ensure that the dose limits for workers and trainees are not

exceeded;

(j) investigate and initiate prompt remedial measures in respect of

any situation that could lead to personnel dose in excess of limits;

(k) ensure that reports on all hazardous situations, along with details

of any immediate remedial measures that may have been initiated,

are sent to the competent authority within 24 hours;

(l) ensure that the ultimate disposal of radiography sources is carried

out in a manner approved by the competent authority in

accordance with the Atomic Energy (Safe Disposal of Radioactive

Waste) Rules, 1987;

(m) ensure that at least one calibrated radiation monitoring instrument

in working condition is earmarked for every radiography

equipment;

(n) ensure that procedures for handling an emergency situation are

prepared in accordance with section 6 of this Code and a copy

sent to the competent authority;

(o) establish an internal inspection/audit procedure or other

management control to ensure that safe operating and emergency

procedures are observed by workers and the emergency

procedures rehearsed;

(p) maintain complete and up-to-date records of (i) doses, (ii) reports

of medical examinations, and (iii) occupational histories of workers

of the site applicable to standard industrial workers, with special

investigation of skin, hands, fingers and eyes;

(q) ensure that every worker is subjected to medical investigation

as specified by the competent authority prior to commencing

radiation work, and subsequently at intervals stipulated by the

competent authority and at the termination of work;

(r) maintain medical reports as specified in (p) and (q) above for

inspection at the site by any person authorised by the competent

authority;

15

(s) not loan radiography facilities, e.g. storage room, radiography

equipment, emergency accessories etc. to another radiography

agency without the consent of the competent authority;

(t) not borrow another consentee's facilities such as storage room,

equipment or personnel without the consent of the competent

authority;

(u) display the consent for site authorisation granted by the

competent authority and emergency procedures at the place of

radiography work;

(v) not employ any person below 18 years of age for radiation work

and not take any person of below 16 years as a trainee in radiation

work;

(w) maintain records of radiography exposures carried out in the

format specified in Appendix-IV;

(x) submit information regarding location details of the industrial

gamma radiography exposure devices in the format specified in

Appendix-V; and

(y) dispose/transfer any exposure device(s), containing depleted

uranium only after prior permission of the competent authority

and in accordance with sub-section 5.10 of this Code.

4.2 Radiological Safety Officer

4.2.1 Minimum Qualification for RSO Level-III:

(a) a degree in science with physics as one of the subjects;

(b) a post-graduate degree/diploma in radiological physics, or

five years experience as safety site-in-charge (RSO Level-II) and

appropriate up-gradation training course recognised by the

competent authority; and

(c) a certificate from the competent authority to function as

radiological safety officer (RSO).

16

4.2.2 RSO shall advise and assist the consentee on all aspects of radiation

safety. The responsibilities of RSO shall include:

(a) instructing workers on safety measures and safe work practices

aimed at minimising exposure to radiation and contamination;

(b) regulating safe movement of radioactive materials and ensuring

that packages containing radiography sources are properly

packed, labelled and declared as per AERB/SC/TR-1;

(c) ensuring that radiography sources and other radioactive materials

are not transported by public transport;

(d) investigating and initiating suitable remedial measures in

situations that could lead to radiation hazards;

(e) ensuring that reports of all hazardous situations along with details

of any immediate remedial actions taken are made available to the

consentee for reporting to the competent authority and a copy

endorsed to the competent authority;

(f) arranging for safe disposal of radioactive wastes by transfer of

decayed sources to the waste management agency approved by

the competent authority;

(g) maintaining inventories of radiography sources, calibration of

radiation monitoring instruments, log books, records of (i)

unusual occurrences, (ii) personnel monitoring, (iii) source

calibration, (iv) periodic survey of installation or site, (v) periodic

contamination checks on the radiography sources and guide

tubes, (vi) disposal of decayed radiography sources,

(vii) checking the performance and safety functions of the device

regularly and after servicing and maintenance, and

(viii) movement of exposure device to different site(s); and

(h) developing suitable emergency schemes to deal with radiation

emergencies.

17

4.3 Safety Site-in-Charge/RSO Level-II

4.3.1 Minimum Qualifications:

(a) a diploma in engineering or degree in science with physics as

one of the subjects; or

seven years experience as certified radiographer;

(b) training in radiography testing and safety (level-II) or equivalent

recognised by the competent authority; and

(c) a certificate from the competent authority to work as safety site-

in-charge.

4.3.2 The safety site-in-charge shall ensure that the radiographers carry out

the work safely.

4.3.3 The safety site-in-charge shall perform the functions of RSO specified in

sub-section 4.2.1 pertaining to the operations at site, transport of

radioactive sources from one site to another site, and storage of sources

and maintenance of records. The safety site-in-charge shall be deemed

to be RSO Level-II.

4.4 Certified Radiographer

4.4.1 Minimum Qualifications:

(a) 10+2 with physics and mathematics;

(b) training in radiography testing and safety (RT level-I) or its

equivalent recognised by the competent authority; and

(c) certificate from the competent authority to work as radiographer.

4.4.2 The radiographer shall refrain from any act that could be radiologically

detrimental to himself/herself, other workers and/or members of the public.

4.4.3 The radiographer shall:

(a) provide to the consentee information about his/her past radiation

work, if any;

18

(b) make proper use of protective equipment, radiation monitors and

personnel monitoring devices provided;

(c) promptly inform the safety site-in-charge and RSO of any accident

or potentially hazardous situation that may come to his/her

notice;

(d) comply with instructions of RSO/safety site-in-charge/consentee

concerning radiation protection; and

(e) ensure that trainees operate any radiography exposure device or

equipment in the presence of radiographer/safety site-in-charge/

RSO after wearing personnel monitoring badges.

4.5 Trainee

4.5.1 Minimum Qualification:

10+2 with physics and mathematics.

4.5.2 The trainee shall:

(a) not operate any radiography exposure device or equipment in the

absence of a certified personnel;

(b) make use of proper radiation monitoring instruments and

personnel monitoring devices and protective accessories

provided;

(c) comply with the instructions of radiographer/safety site-in-

charge/RSO on radiation protection; and

(d) give an undertaking to the competent authority in the prescribed

format and appear for radiography testing and safety (RT

level-I) course immediately after completing six months of field

experience/training.

4.6 Radiography Source Supplier

The radiography source supplier shall provide a certificate specifying

dimensional drawing of the source capsule and materials of construction,

19

radionuclide, activity with date of measurement, leak test results and

method. The source supplier shall be responsible for disposal of decayed

radiography sources.

4.7 Manufacturer/Vendor of Equipment

(a) Manufacturer/vendor shall supply radiography exposure device/

source changer/X-ray equipment/accelerator only after obtaining

a Type approval/NOC from the competent authority and only to

users authorised by the competent authority.

(b) Vendor shall provide user along with the equipment (i) technical

specifications; (ii) operating/servicing/ maintenance manuals; and

(iii) instructions for handling emergencies.

(c) Vendor shall provide user with detailed procedures for quality

assurance tests and checks to be carried out with specified

frequency to verify correct performance of the device/equipment.

(d) Manufacturer/vendor shall be responsible for installation,

commissioning, servicing and maintenance, decommissioning/

dismantling of equipment and for arranging disposal of the

decayed radiography sources and any other radioactive material

in the shielding.

(e) Manufacturer/vendor shall keep a record of radiography exposure

devices/source changers supplied, together with performance,

quality assurance and safety status of the device/source changer.

4.8 Servicing/Maintenance Personnel

Servicing and maintenance of any radiography equipment shall be carried

out only by persons authorised by the competent authority. The

authorised person shall ensure that no repair and maintenance is carried

out on radiography exposure device/source changer when it contains

radiography source. After repair and maintenance, he/she shall test the

safety of the equipment, certify its safety and enter details of repair and

maintenance in the logbook. While handling the equipment with

radioactive sources, he/she shall wear personnel monitoring devices and

direct reading dosimeters. He/she shall use radiation monitoring

instruments as and when required for ensuring safe radiation levels during

work.

20

5. REGULATORY CONTROLS

5.1 Consent

(i) Possession, use, import, export, transport and disposal of a

radioactive material/substance by any person is prohibited except

in accordance with the terms and conditions of a written consent

granted under sections 14, 16 and 17 of the Atomic Energy Act,

1962. The written consent may be a licence granted in accordance

with Rule 3 of Radiation Protections Rules (RPR), 1971. The

consents are not transferable.

(ii) The applicant for consent shall provide evidence that:

(a) the radiography equipment meets the requirements of

applicable standard as specified in section 2 of this Code;

(b) the installation/site is according to the requirements of

section 3 of this Code;

(c) trained persons specified in section 4 of this Code are

available;

(d) personnel monitoring devices are provided to all workers;

and

(e) radiation monitoring instruments are available and are in

good condition for use.

(iii) The consentee shall ensure that persons handling radiography

sources and radiation generating equipment comply with relevant

provisions of Radiation Protection Rules, Industrial Radiography

(Radiation Surveillance) Procedures, Radiation Surveillance

Procedures for Transport of Radioactive Material, Atomic Energy

(Radioactive Waste Disposal) Rules, Testing and Classification of

Sealed Sources, AERB/SS-3 and this Code. They shall also

comply with any safety directives issued by the competent

authority from time to time.

21

5.2 Installation/Site Plan

Layout plan for radiography installation shall provide radiation safety of

workers and members of public as specified in section 3 of this Code.

Approval shall be obtained from competent authority prior to construction

or commissioning. Detailed drawings showing the layout of rooms,

position of radiation source (exposure device/X-ray equipment/

accelerator), doors and windows, control room, work-areas and public

areas to a scale 1:500 shall be submitted to the competent authority. Any

change in radiation shielding or modification to the approved plan shall

be carried out only with the written concurrence of the competent

authority.

5.3 Procurement of Radiography Sources

Consentee shall obtain authorisation from the competent authority for

procuring radiography sources on the first occasion and replacement

sources subsequently.

5.4 Radiological Safety Officer

In pursuance of Rule 12 of Radiation Protections Rules, 1971 the employer

shall designate with the approval of the competent authority a qualified

person to function as RSO. The format of application for nomination of

an RSO is given in Appendix-VI. RSO shall submit reports to the

competent authority on radiation safety status in the institution once

every six months in the format given in Appendix-VII.

5.5 Commissioning of Radiography Installation or Radiography Site

(i) Any new radiography installation or site shall not be

commissioned unless compliance with the requirements of section

3 of this Code is verified and certified by the consentee.

(ii) When an installation is structurally modified or when the

equipment is repaired or modified, or any change in radiography

procedure is adopted, verification of compliance with provisions

of section 3 of this Code shall be repeated prior to

re-commissioning. Commissioning or re-commissioning shall be

22

subject to terms and conditions in the written approval of the

competent authority.

5.6 Operation and Use of Radiography Sources

(i) The exposure device shall be operated by a certified radiographer

and under the direct supervision of an approved safety site-in-

charge or RSO. The application form for approval of safety site-

in-charge/radiographer is given in Appendix-VIII.

(ii) Exposure for field radiography shall be collimated as specified in

clause (ii) of sub-section 3.2. The primary beam shall not be

directed towards occupied areas.

(iii) The radiographer shall ensure smooth operation of exposure

device prior to commencement of radiography work on each day.

Operational checks shall be recorded. The radiographer shall

measure the radiation levels around the radiography premises and

record the results.

(iv) Radioactive contamination in any accessible area of source

housing and source guide tube shall be checked at least once

in six months to verify the integrity of the sealed source. In case

the contamination is in excess of 185 Bq the device shall not be

used, and the competent authority shall be informed.

5.7 Transport of Radiography Source

(i) Not withstanding any requirements or regulations of carrier, the

transport of radiography source in public domain shall be in

accordance with AERB/SC/TR-1.

(ii) Consentee shall ensure that the radiography source is securely

immobilised and locked in the device or source changer before

being transported.

23

5.8 Change of Radiography Site

(i) Radiography sources shall not be used outside the installation

or site authorised by the competent authority.

(ii) When it becomes unavoidable to carry out radiography work at

a place other than the one authorised, the consentee shall notify

the competent authority of the intended change and obtain

written permission prior to commencing radiography operation at

the new site. This shall be followed by written request within 48

hours. The records of such movements shall be maintained as

per clause (g) sub-section 4.2.2.

5.9 Safe Custody of Radiography Sources and Radioactive Material

(i) Consentee shall be responsible for keeping the radiography

source and radioactive materials in his/her possession for safe

custody and providing adequate physical security. Exposure

device containing radiography source shall be kept under lock

and key when not in use and the key of the exposure device

kept in the custody of the certified personnel. The physical

security of exposure device shall be ensured at all times by

storing it in an approved storage room.

(ii) Radioactive sources shall not be lent/leased, gifted or transferred

to any other person except with the permission of the competent

authority.

(iii) Consentee shall send to the competent authority during the first

week of every month a statement of sources in his/her custody

in the format specified in Appendix-IV.

5.10 Disposal of Radiography Sources and Radioactive Material

Radiography source and radioactive material shall be disposed off only

after obtaining an authorisation as per the Atomic Energy (Safe Disposal

of Radioactive Wastes) Rules, 1987 from the competent authority. The

form for application for authorisation is given in Appendix-IX.

24

5.11 Inspection and Enforcement

(i) In pursuance of Rules 29 to 32 of Radiation Protection Rules,

1971, the competent authority or its authorised representative may

inspect:

(a) any site where radiography work is being carried out;

(b) any radiography equipment, installation, radiography

source; and

(c) any monitoring instrument, logbook, record of:

(i) unusual occurrences, (ii) personnel monitoring,

(iii) source calibration, (iv) periodic survey of installation

or site, (v) periodic contamination check on the

radiography sources/guide tubes, and (vi) source

movement and site authorisation.

(ii) If any violation is observed on inspection, the authorised

representative of the competent authority may:

(a) seal any radiation installation or any transport or

conveyance carrying radioactive materials or seize any

radioactive material or contaminated equipment; and/or

(b) indicate in writing to the consentee any modification

aimed at providing adequate protection, and the

consentee shall comply with the same.

(iii) If any violation is observed on inspection, the competent

authority may withdraw or revoke or modify the certificate issued

to the certified radiographer/safety site-in-charge/RSO.

5.12 Revocation, Modification or Withdrawal of Consent

In accordance with rules 8 and 9 of the Radiation Protection Rules, 1971,

the competent authority, if it considers necessary in public interest

pertaining to radiation safety, or if any of the provisions of Rules,

Surveillance Procedures, Standards and Codes have been contravened,

may, after giving a show cause notice to the person to whom the consent

has been issued, and after giving him/her an opportunity to make a

25

representation against the action proposed to be taken and consideration

of his representation, suspend the operation of a consent or revoke or

modify the terms and conditions of a consent at any time during the

currency of the consent.

5.13 Offences and Penalties

In pursuance of rule 11 of Radiation Protections Rules (RPR), 1971, any

person who contravenes the provisions of (a) RPR and (b) the Atomic

Energy Act, 1962, in so far as it concerns section 17 of the Act, (c) this

Code, or (d) terms and conditions of consent granted to him/her by the

competent authority, shall be punishable under sections 24, 25 and 26

of the Atomic Energy Act, 1962 and the relevant provisions of RPR, 1971.

The punishment may include imprisonment or fine or both, depending on

the nature of contravention.

26

6. EMERGENCY PREPAREDNESS

6.1 Emergency Action Plan

(i) Consentee shall prepare action plans for all foreseeable

emergencies including the following:

(a) source failing to return to safe shielded position;

(b) loss/theft of radiography source at the installation/site

during use, in storage, in transport, or during natural

calamities; and

(c) fire.

Consentee shall ensure that all workers are familiar with the

emergency action plan.

(ii) The action plan shall specify:

(a) persons familiar with emergency action plan and

responsibilities and functions, line of authority and line

of communication;

(b) initial training and periodic re-training of persons in their

respective tasks;

(c) appropriate tools, radiation monitoring instruments, and

personnel monitoring devices to be kept and maintained

in working condition;

(d) most direct and alternate means of communication; and

(e) authorities to be contacted at the initial phase, during

progress and at termination of an emergency.

6.2 Reporting an Emergency

(i) RSO/safety site-in-charge shall:

(a) immediately report to the consentee on any emergency

situation and initiate remedial actions and endorse a copy

to the competent authority; and

27

(b) carry out prompt investigation on causes of the

emergency, evolve means to prevent recurrence and

submit a detailed report on the incident to the competent

authority.

(ii) Consentee shall:

(a) inform the competent authority of the incident within 24

hours of its occurrence and submit a detailed report on

the incident after carrying out investigations; and

(b) lodge a written compliant with the police in case of loss

or theft if the radiography source(s) are not traced within

24 hours.

28

APPENDIX-I

DOSE LIMITS

Workers

(i) The cumulative effective dose over a block of five years shall not exceed

100 mSv.

(ii) The effective dose in any calendar year during the five year block shall

not exceed 30 mSv.

(iii) (a) The equivalent dose in any calendar year to the lens of the eye

shall not exceed 150 mSv; and

(b) The effective dose in any calendar year to the skin, the hands

and feet, shall not exceed 500 mSv.

(iv) In the case of a woman worker of reproductive age, once pregnancy has

been established, the conceptus shall be protected by applying a

supplementary equivalent dose limit to the surface of the woman's

abdomen (lower trunk) of 2 mSv for the remainder of the pregnancy.

Internal exposures shall be controlled by limiting intakes of radionuclides

to about 1/20 of ALI. The employment shall be such that it does not

carry a probability of high accidental doses and intakes.

Trainees

The effective dose in any calendar year shall not exceed 6 mSv.

Public

(i) The effective dose for any calendar year shall not exceed 1 mSv.

(ii) In special circumstances, a higher value of effective dose could be allowed

in a single year, provided that the effective dose averaged over five years

does not exceed 1 mSv/y.

29

APPENDIX-II

Government of IndiaAtomic Energy Regulatory Board

Niyamak Bhavan, AnushaktinagarMumbai-400094

FORMAT OF THE "APPLICATION FOR TYPE APPROVALOF INDUSTRIAL GAMMA RADIOGRAPHY EXPOSURE DEVICE AND

SOURCE CHANGER"

To be submitted by the applicant to the Chairman, Atomic Energy Regulatory Board, Niyamak

Bhavan, Anushaktinagar, Mumbai-400094 with a copy to the Head, Radiological Physics andAdvisory Division (RP&AD), Bhabha Atomic Research Centre (BARC), CT&CRS, Building,Anushaktinagar, Mumbai-400094.

A. Manufacturer/Vendor

1. (a) Name and address of the applicant with PIN code (in block letters):

(b) Mode of communication:

Telephone with STD code

Fax

Telex

Telegram

E-mail

2. (a) Name and address of the manufacturer with PIN code:

30

(b) Mode of communication:


Fax

Telex

Telegram

E-mail

3. Person to be contacted regarding this application:


4. Name and type of gamma radiography exposure device to be type approved:

5. This application is for:

Type approval

Renewal of type Ref No.: Date: Valid till: approval

B. Exposure Device

1. Name and type :

2. Class of exposure device : Portable/Mobile/Fixed

3. Gross weight : ............................... kg

4. Overall external dimensions : ............mm x ...........mm x ..............mm(provide detailed drawing ofthe device)

31

5. Maximum source capacity : ..................GBq of ........................................(specify the radionuclide)

6. Exposure mechanism : ......................................................................

C . Source Housing

1. Material of shielding : ......................................................................

2. Maximum thickness and : ........................... mm, maximumminimum thickness .......................... mm, minimum

3. Source locationfrom external reference : ...................cm ..................................

points (specify)

4. Leakage radiation levels measured at maximum source rating

a) at 5 cm from source housing : ........................................ mSv/haveraged over an area of 10 cm2

b) at 100 cm from source housing : .........................................mSv/haveraged over an area of 100 cm2

D. Safety Features

1. Locks (describe briefly the types of safety locks provided, locking mechanism etc.)

2. Can the source assembly be pushed/ : Yes/No

pulled out of the equipment withoutoperating the driving mechanism

3. Collimators (specify the type of : ......................................................................collimator such as panoramic/straightbeam/diaphragms, their radial angles,

material of construction etc.)

4. Any other safety device :

E Radioactive Source Assembly

1. Name and address of the manufacturer:

32

2. Name and address of supplier:

3. External dimensions : ........... mm x ..........mm x .......... mm

4. Gross weight : ..................... g

5. Materials of construction (specify the materials of source capsule, and source holder, andprovide a separate drawing giving the dimensions of various components of the source

assembly)

(a) Source capsule : ......................................................................

(b) Source holder : ......................................................................

6. Classification number and certificate : C/E................................................................issued along with the source

7. Type of coupling provided between : ......................................................................the source assembly and drivingmechanism

F. Source Drive System

1. Model/type :

2. Gross weight : .................................. kg

3. Overall external dimensions : ........ ......cm x .........cm x...........cm

4. Source guide tube assembly

(a) Material : ...............................

(b) Diameter : ..................... mm

(c) Length : ........................ cm

33

5. Source drive cable

(a) Material : ............................

(b) Diameter : ......................... mm

(c) Length : ......................... cm

6. End fittings (Specify material, dimensions of end fittings to source guide tube and drive

cable)

(a) Material : ..............................

(b) Diameter : .......................... mm,(c) Length : ............................ cm

7. Maximum distance between exposure : ........................................ mdevice and control unit

8. Maximum distance between exposure : .........................................mdevice and source in extremeexposure positions when guide tube

is connected

9. Operational mechanism of remote :

control (describe briefly about anyspecial lock, source position indicator,mechanical counter etc. provided in

the cranking unit)

10. (a) Is the guide tube flexible or : Flexible/rigid

rigid?

(a) Material and dimensions of : ...................................................

the guide tube

11. Type of mounting provided for : .........................................................

cranking unit (stand type/spooltype/pistol grip type/any other)

G. Quality Assurance

(a) For first approval:

Furnish quality assurance procedures for entire manufacturing as well as proceduresfor servicing and maintenance

(b) Renewal of type approval:

(i) Number of devices supplied on : ...............................................

the date of application(Give serial numbers)

34

(ii) Any modification to the present :design or changes in components/

materials of construction/QAprocedures incorporated in theapproved model. If so, give details

(iii) Any change in the radioactive :material or its quantity in the

approved model

(iv) Field use feedback on performance :

of devices supplied so far

(Attach details on the following):

(a) Availability of spares;(b) Servicing and maintenance;(c) Average frequency of failures or radiological malfunctions;

(d) Common failures in the order of frequency of their occurrence;(e) Generic deficiencies/operational problems reported by the users; and(f) Major incidents and causes.

H. Specify the national/international standards to which the equipment, sourcechanger and source comply and give details of tests conducted and their results:

I. Any other relevant information :

J. List of supportive documents (such as instruction manual, drawings, etc.) attachedwith the application:

I certify that all the information furnished by me is correct to the best of knowledge and belief.

Place: Signature of the applicant:Date : Name:

Designation:

(Seal of the institution)

35

APPENDIX-III

RADIATION SYMBOLS

Fig. III.1 TREFOIL SYMBOL INDICATING PRESENCE OF RADIATION FROM ARADIOACTIVE SOURCE

Fig.III.2 WARNING SYMBOL INDICATING POSSIBILITY OF RADIATION FROM AN X-RAY GENERATING EQUIPMENT

MYK MYK

MYK MYK

36

APPENDIX-IV



FORMAT OF THE "LOGBOOK TO BE MAINTAINED BY THE CONSENTEE ATTHE RADIOGRAPHY SITE"

Logbook to be maintained by the Consentee at the site and to be made available during

inspection by the representative(s) of the Chairman, Atomic Energy Regulatory Board,Niyamak Bhavan, Anushaktinagar, Mumbai-400094

1. Name of the institution:

2. Location of use:

3. Details of exposure device, source pencil and radiography source:

Exposure device Source pencil Radiography source

Model Serial number Serial number, if Radionuclide Activity As on (date)

applicable

4. Details of radiation survey meter(s) available at the site:

Model Serial number Date of calibration

5. Name of the safety site-in-charge/RSO:

6. Personnel monitoring service number:

7. Details of exposures:

Note: Logbooks shall be maintained separately for each industrial gamma radiography exposure device

Date Name(s) of

the operator(s)

Average

duration of

exposure

Number of

exposures

(Use P for

panoramic

and C for

collimated)

Details of

radiography

job

Duration in

hours

Maximum

radiation

level along

cordon

Whether

source

returned to

safe

position in

exposure

device

Whether

exposure

device

returned

to storage

pit

Name(s)

and

signature(s)

of the

operator(s)

From To

37

38

APPENDIX-V



FORMAT OF THE "INFORMATION TO BE FURNISHED BY THE CONSENTEEREGARDING THE LOCATION DETAILS OF THE INDUSTRIAL GAMMARADIOGRAPHY EXPOSURE DEVICE"

To be submitted by the Consentee to the Chairman, Atomic Energy Regulatory Board,Niyamak Bhavan, Anushaktinagar, Mumbai-400094

Part-A and Part-B should be submitted in the first week of every month.

Report for the month of Year

1. Name and address of the institution:

2. Telephone and Fax with STD code:

Telephone Fax

3. Personnel monitoring service number:

4. Number of films/TLD cards received:

39

Part-A: Site(s), industrial gamma radiography exposure device, trained personnel and monitorsavailable at site(s):

Part-B: Details of decayed sources returned:

5. I hereby certify that all safety/emergency accessories are available at site(s), that theyare in working order and that they are being used regularly.

Place: Signature of the head of institutionDate: Name:

Designation:

(Office seal of the institution)

S.No Contract

awarding

party,

site(s) and

last

inspection

date

Safety site-

in-charge,

his/her

certificate

number

and its

validity

Exposure

device model,

serial number

and date(s)

of movement

Source

activity

received and

pencil

number

Certified

radiographer,

his/her

certificate

number and

its validity

Trainee

radiographer,

his date of

appointment

and PMS

number

Survey meter

model, serial

number and

date of

calibration

Pocket

dosimeter and

charger model

and their

serial

numbers

Job type

and number

of exposures

during the

month

S.No. Exposure device model

and serial number

Date of decayed

source return

Radionuclide, its activity on the

date of return

40

APPENDIX-VI



FORMAT OF THE "APPLICATION FOR APPROVAL OF NOMINATION OFRADIOLOGICAL SAFETY OFFICER IN INDUSTRIAL RADIOGRAPHY"


Bhavan, Anushaktinagar, Mumbai-400094

Part-1: Particulars of the institution

1. Name and address of the institution with PIN code:

2. Name, designation and address of the head of the institution with PIN code (the applicant)

in block letters:

S.No. Name of the

manufacturer

Make and Type Year of

installation

kVp

max.

mA

max.

Full address of

location of use

S.No. Radiography equipment,

model, and serial number

Manufacturer's name

and address

Radionuclide used

as radiography

source

Maximum

activity

(GBq)

Full address of

the location of

use

41

3. Mode of communication:

Telephone with STD code:

- During office hours

- After officer hours

Fax

Telex

Telegram

E-mail


RSO approval

Renewal of Ref No.: Date: Valid till:

RSO approval

5. Details of radiation equipment/facilities/sources available in the institution

A. X-ray Radiography Equipment:

1.

2.

B. Gamma Radiography Equipment:

1.

2.

42

C Any other sealed radioactive source (Give description, radionuclide, and activity ona specified date):

6. Details of radiation measuring/monitoring instruments:

1.

2.

7. Details of unusual occurrences that have taken place in the past. Include any radiationemergencies, loss of source or other incidents:

1.

2.

8. Details of radiation workers in the institution:

1.

2.

3.

4.

5.

6.

S.No. Name of the

manufacturer

Make and type Radion type

detected

Scale

ranges

Date of

purchase

Date of most

recent calibration

S.No. Date of incident Radiation equip-

ment or source

involved

Nature of

incident

Details of

action

taken

Number of

persons

involved

Maximum dose received

by an individual as a

result of the incident

S.No Name of employee

and date of birth

Designation Responsibilities

and functions

Date of

commencement of

radiation work

Personnel monitoring

service number

43

Part-2: Particulars of the RSO-designate

1. Name (with initials expanded) of the person to bedesignated as RSO (in block letters):

2. Present designation of the nominee:

3. Address with PIN code (in block letters):

Office address:


Residential address:


Permanent home address:


PLEASE AFFIX A

RECENTPASSPORT SIZEPHOTOGRAPH

44

4. Academic qualifications and training courses in radiation safety:

Academic 1.

2.

3.

Training 1. courses in radiation 2.

safety

5. Experience in radiation work:

1.

2.

3.

6. Radiation equipment/radioactive materials for which the RSO will be responsible:

Radiation equipment

Radioactive material

7. Additional responsibilities proposed to be assigned to the RSO

8. (a) I hereby certify that the information furnished above is correct to the best of

my knowledge and belief;

(b) I undertake to abide by the conditions stipulated by the competent authority from

time to time and follow guidelines in discharging the duties and responsibilitiesas RSO; and

Qualifications S.No. University/Examining body Degree/

DiplomaYear of

passing

Subject(s) of study

S.No. Year(s) of work Name of institution

and address

Radiation

equipment, sources

handled

Maximum

activity

handled

PMS number

45

(c) I further undertake to inform the Atomic Energy Regulatory Board immediatelyin case I am relieved of my services as RSO.

Date: Signature of RSO-designate

Name:

9. (a) I hereby certify that all the statements made in the application are correct tothe best of my knowledge and belief;

(b) I hereby undertake to provide all necessary facilities to the RSO to discharge his/her duties and functions effectively; and

(c) I further undertake to inform Atomic Energy Regulatory Board immediately incase the RSO is relieved of his duties.

Place: Signature of the head of the institution(the applicant).

Date: Name:

Designation:


46

APPENDIX-VII


Niyamak Bhavan, Anushaktinagar

Mumbai-400094

FORMAT OF THE "INFORMATION TO BE FURNISHED BY THE RADIOLOGICALSAFETY OFFICER IN INDUSTRIAL RADIOGRAPHY INSTITUTION"

To be submitted by the Radiological Safety Officer to the Chairman, Atomic EnergyRegulatory Board, Niyamak Bhavan, Anushaktinagar, Mumbai-400094

Reporting period from .................................. to ...............................................

1. Name and address of the institution with PIN code (in block letters):


2. Name, designation and address of the head of the institution:


3. Site(s) for which RSO is responsible:

4. Performance and radiation safety status of radiation equipment(s). (Fill in Form-A. Useseparate Form-A for each unit):

(a) Industrial radiography exposure device;

(b) Industrial X-ray equipment;

47

(c) Industrial accelerator; or

(d) Any other (specify).

5. Status of sealed radioactive sources:

(a) Total activity of each radionuclide at the beginning of the reporting period;

(b) Additional sources procured during the reporting period.

6. Transport of radioactive material:

(a) How many times were the radiography sources/radiography exposure devicestransported from one site to another site? Give full details;

(b) How many times were the decayed radioactive sources transported to BRIT/ BARC?(Give full details).

State whether

(i) the packing, marking and labelling were properly done;

(ii) radiation levels for each package were measured prior to transportation;

(iii) transport index was assigned;

(iv) prior intimation was sent to the consignee;

(v) transport certificate was issued by the RSO to the carrier; and

(vi) the package was received at BRIT in proper condition.

(c) Details of any incident or unusual occurrence during transport, with information onnature of incident, location, radionuclide and activity involved, exposure to transport

workers and public etc., and consequence of incident. If any source was lost in transport,state whether the source was recovered. State the nature of investigations carried outby RSO on the causes and consequences of the incident and steps taken to prevent such

recurrence.

7. Status of radiation measuring and monitoring instruments:

(a) Name(s) and model(s) of the instrument;

(b) Date(s) of procurement;

(c) Frequency and method of calibration check;

(d) Date(s) of recent calibration;

(e) Present status of the instrument.

48

8. Maintenance of records:

(a) Personnel exposure records are maintained up-to-date : Yes/No

(b) Inventory of sealed radioactive sources : Yes/No

(c) Radioactive waste disposal : Yes/No

(d) Radiation protection surveillance : Yes/No

(e) Incidents and unusual occurrences : Yes/No

(f) Calibration of radiation detection instruments : Yes/No

(g) Movement of radiography exposure devices : Yes/No

(h) Medical records of radiation workers : Yes/No

9. Details of inspections performed by AERB/RP&AD officials during reporting period:

10. Details of any training programme conducted by RSO for radiation workers during the

reporting period:

11. Control and surveillance measures for the storage and radiography area. Furnish details:

12. Details of over-exposures received by workers during the reporting period. Include details ofinvestigations carried out by RSO on the circumstances causing overexposures and stepsinitiated to prevent such recurrence:

13. Any other information on radiation safety matters in the institution:

Place: Signature :Date: Name of RSO :

49

Form-A

Attachment to the "Information to be furnished by the Radiological SafetyOfficer in an Industrial Radiography Institution"

INDUSTRIAL RADIOGRAPHY EXPOSURE DEVICES

(a) Make and type of the radiography :exposure device

(b) Date of procurement :

(c) Date of recent source replacementand source strength :

(d) Average number of exposures

taken daily :

(e) Details of any major repair/servicing :

(f) In case any worn out part was :replaced, state whether the replacedpart is original from the

manufacturer or improvised locally

(g) Details of any radiation emergency :which had occurred in the reportingperiod

(h) General assessment on the

performance of the :radiography exposure device

50

APPENDIX-VIII



FORMAT OF THE "APPLICATION FOR APPROVAL OF SAFETY SITE-IN-CHARGE/CERTIFIED RADIOGRAPHER IN INDUSTRIAL RADIOGRAPHY"

To be submitted by the applicant to the Head, Radiological Physics and Advisory Division,Bhabha Atomic Research Centre, CT & CRS Building, Anushaktinagar, Mumbai-400094 witha copy to the Chairman, Atomic Energy Regulatory Board, Niyamak Bhavan, Anushaktinagar,

Mumbai-400094

1. Name in full (with initials expanded) in block letters:

Date of birth

2. Father's name:

3. Permanent home address with PIN code:


PLEASE AFFIX A

RECENTPASSPORT SIZEPHOTOGRAPH

51

4. Name, designation and address of the head of the institution with PIN code (in blockletters):


5. Mode of communication with the institution:

Telephone with STD code:

- During office hours

- After officer hours

Fax

Telex

Telegram

E-mail

6. Type of certificate: (a) Safety Site-in-charge/Radiographer

(b) Original/Duplicate


Renewal of Safety Ref No.: Date: Valid till:

Site-in-charge/Radiographer approval

8. Month and year of enrolment in personnel monitoring service (PMS):

Write institution and personnel monitoring numbers:

Safety Site-in-charge/

Radiographer approval

52

9. Academic qualifications and training courses in radiation safety (enclose copy of passand other certificates):

10. Experience in radiation work:

1.

2.

3.

11. (a) I hereby certify that the information furnished above is correct to the best of

my knowledge and belief;

(b) I undertake to abide by the conditions stipulated by the Competent Authority

from time to time and follow guidelines in discharging the duties and responsibilitiesas safety site-in-charge/radiographer; and

(c) I further undertake to inform the Chairman, Atomic Energy Regulatory Boardand the Head, Radiological Physics and Advisory Division, Bhabha Atomic ResearchCentre, CT&CRS Building, Anushaktinagar, Mumbai-400094, immediately in case

of change of employment or employer.

Place: Signature of Site-in-charge/Radiographer

Date: Name:

Qualifications S.No. University/Examining body Degree/

DiplomaYear of

passing

Subject(s) of study

Academic 1.

2.

Training courses 1.

in radiationsafety: IRG-1, 2.RT-2, RT-1, any

other (specify)

S.No. Year(s) of work Name of institution

and address

Radiation

equipment, sources

handled

Maximum

activity

handled

PMS number

53

12. (a) I hereby certify that all the statements made in the application are correct tothe best of my knowledge and belief;

(b) I hereby undertake to provide all necessary facilities to the safety site-in-charge/radiographer to discharge his/her duties and functions effectively; and

(c) I further undertake to inform the Atomic Energy Regulatory Board/RadiologicalPhysics and Advisory Division immediately in case the safety site-in-charge/

radiographer leaves this institution.

Place: Signature of the head of the institution(the applicant)

Date: Name:Designation:


54

APPENDIX-IX



FORMAT OF THE "APPLICATION FOR AUTHORISATION TO DISPOSE OFRADIOACTIVE WASTES, DECAYED/UNUSED SOURCES

(BY SMALL INSTALLATIONS)


Bhavan, Anushaktinagar, Mumbai-400094

FORM-V

S. No.________

Part-A : Particulars of Institution

1. Name, Designation and Official address :of the applicant (with Telephone numberswith STD Code during and after office hours

and Telex/FAX No.)

2. Name and Address of the Head of institution :

3. Address of Agency to whom the :Radioactive waste, decayed/

unused sources are to be sent fordisposal (if applicable)

4. Authorisation of AERB/BARC (with No. :and date) to use radioactive source/

equipment

5. Name of the Radiological Safety Officer :of the installation

6. No. of staff members in the installation :

experienced in radioactive waste disposal

To be filled byAERB

Authorisation No._______________________

Date___________________________________

55

Part-B

Radiography Sources:

Part-C

1. Facilities and procedures for waste management operations:

Solid Liquid Gas

(a) Collection :

(b) Transfer :

(c) Interim storage :

(d) Disposal :

(e) Monitoring and :

Surveillance forradioactivity

2. Please enclose a layout indicating the location(s) of radioactive waste disposal site(s).Specify the nature of environment and occupancies up to a radius of 200 m from pit(s)and effluent discharge point(s).

3. Any other relevant information:

Details of camera Radionuclide Number of

source

replacements

per year

Maximum activity of

the decayed source to

be sent for

replacement

Remarks

Make Model S.No.

56

4. Undertaking

We hereby certify that:

(a) all the statements made above are correct to the best of our knowledge and

belief;

(b) the radioactive waste will not be disposed of except as specified in this application;

(c) radioactive waste will not be moved from the authorised site without prior approvalof the competent authority;

(d) any change in personnel, equipment and working conditions from those given

in this application will be made only with the approval of the competent authority;

(e) full facilities will be accorded to any authorised representative of the competentauthority to inspect the installation where the radioactive waste is handled;

(f) radiation monitoring and surveillance will be regularly carried out to ensure adequateprotection for workers and public;

(g) the radioactive waste will not be sold, rented or transferred to any other institution,without prior approval of the competent authority; and

(h) all stipulations that may be made from time to time by the Competent Authority,

under Radiation Protection Rules, 1971 and Atomic Energy (Safe Disposal ofRadioactive Wastes) Rules, 1987 will be duly implemented.

Place: Signature of the applicantDate: Name:

Designation:

Signature of the head of institution

Name:Designation:


57

BIBLIOGRAPHY

1. Atomic Energy Act, 1962 (33 of 1962).

2. Radiation Protection Rules, G.S.R. 1601, 1971.

3. Atomic Energy Regulatory Board; its powers and functions: Constitution

Order by Government of India (Order No. 25/2/83-ER dated 15.11.83),

S.O. - 4772, 1983.

4. Industrial Radiography (Radiation Surveillance) Procedures, G.S.R. 735, 1980.

5. Atomic Energy (Safe Disposal of Radioactive Wastes) Rules, G.S.R. 125, 1987.

6. Radiation Surveillance Procedures for Safe Transport of Radioactive

Materials, 1988.

7. Code for Safety in Transport of Radioactive Material, AERB Code No.

SC/TR-1.

8. Safety Guide for Compliance Assurance Programme for Safe Transport of

Radioactive Material, AERB Guide No. SG/TR-1, 1991.

9. Safety Guide for Procedure for Forwarding, Transport, Handling and Storage

of Radioactive Consignments, AERB Guide No. SG/TR/3, 1991.

10. Standard for Testing and Classification of Sealed Radioactive Sources,

AERB/SS/3, 2000.

11. Standard (Specifications) for Radiological Safety for the Design and

Construction of Industrial Gamma Radiography Exposure Devices and Source

Changers, AERB/SS/1, 1992.

12. International Standard — Apparatus for gamma radiography — Specification

ISO - 3999, 1977.

58

LIST OF PARTICIPANTS

TASK GROUP VI

TASK GROUP FOR PREPARATION OFSAFETY CODE FOR INDUSTRIAL RADIOGRAPHY

Members of the Task Group:

Dr. I.S.S. Rao (Convenor) : Atomic Energy Regulatory Board, Mumbai

Dr. S.K. Mehta : Bhabha Atomic Research Centre, Mumbai

(Formerly)

Shri S.P. Agarwal : Bhabha Atomic Research Centre, Mumbai

Shri S.S. Ali : MERADO, Pune

Shri E. B. Ardhanari : WIL, Walchandnagar, (Formerly)

Shri V.G.R. Subramanian : Board of Radiation and Isotope Technology,

Mumbai

Shri P. Subrahmanyam : Bhabha Atomic Research Centre, Mumbai,

(Formerly)

Shri K.D. Pushpangadan : Atomic Energy Regulatory Board, Mumbai

(Member-Secretary)

59

STANDING COMMITTEE FOR REVIEW AND REVISIONOF AERB'S RADIATION SAFETY DOCUMENTS (SCRCG)

Members participating in the meeting:

Shri A. Nagaratnam (Chairman) : Defence Research and Development

Organisation, Hyderabad, (Formerly)

Shri E.B. Ardhanari : Walchandnagar Industries Limited,

Walchandnagar, (Formerly)

Shri P.K. Ghosh : Atomic Energy Regulatory Board, Mumbai

Dr. P.S. Iyer : Bhabha Atomic Research Centre, Mumbai,

(Formerly)

Dr. S.K. Mehta : Bhabha Atomic Research Centre, Mumbai

(Formerly)

Dr. B.K.S. Murthy : Bhabha Atomic Research Centre, Mumbai

(Formerly)

Dr. A.R. Reddy : Defence Research and Development,

Organisation, Delhi

Dr. I.S.S. Rao : Atomic Energy Regulatory Board, Mumbai

(Formerly)

Shri P.S. Viswanathan : Apollo Cancer Hospitals, Chennai, (Formerly)

Dr. B.C. Bhatt : Bhabha Atomic Research Centre, Mumbai

(Co-opted Member, since 1-9-1997)

Shri J.S. Bisht : Bhabha Atomic Research Centre, Mumbai

(Co-opted Member) (Formerly)

Dr. M.S.S. Murthy : Bhabha Atomic Research Centre, Mumbai,

(Co-opted Member, till 31-8-1997) (Formerly)

Dr. A.N. Nandakumar : Bhabha Atomic Research Centre, Mumbai

(Co-opted Member)

Shri K.D. Pushpangadan : Atomic Energy Regulatory Board, Mumbai

(Member-Secretary)

60

COMMITTEE TO FINALISE THE TEXT OF SAFETY CODE FOR INDUSTRIAL RADIOGRAPHY

Shri P.K. Ghosh : Atomic Energy Regulatory Board,

(Chairman) Mumbai

Shri K.D. Pushpangadan : Atomic Energy Regulatory Board,

Mumbai

Shri A.U. Sonawane : Atomic Energy Regulatory Board,

(Member-Secretary) Mumbai