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Radiation Protection Series C-4

Radiation Protection Requirements for Industrial Radiography i

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Radiation Protection Requirements for 3

Industrial Radiography 4

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Radiation Protection Series C-4 7 8

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14 This draft publication was prepared jointly with the Radiation 15 Health Committee. 16


Radiation Protection Requirements for Industrial Radiography i

The mission of ARPANSA is to protect people and the environment from the harmful effects of 17 radiation. 18

Published by the Chief Executive Officer of ARPANSA in <month year>. 19

Acknowledgement of Country 20

ARPANSA proudly acknowledges Australia's Aboriginal and Torres Strait Islander community and their 21 rich culture and pays respect to their Elders past and present. We acknowledge Aboriginal and Torres 22 Strait Islander people as Australia’s first peoples and as the Traditional Owners and custodians of the 23 land and water on which we rely. 24

We recognise and value the ongoing contribution of Aboriginal and Torres Strait Islander people and 25 communities to Australian life and how this enriches us. We embrace the spirit of reconciliation, 26 working towards the equality of outcomes and ensuring an equal voice. 27

© Commonwealth of Australia 2018 This publication is protected by copyright. Copyright (and any other intellectual property rights, if any) in this publication is owned by the Commonwealth of Australia as represented by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). ISBN ‘XXXXXXXXX’ ISSN ‘YYYYYYYYYY’

Creative Commons

With the exception of the Commonwealth Coat of Arms, any ARPANSA logos and any content that is marked as being third party material, this publication, Radiation Protection Requirements for Industrial Radiography (2018), by the Australian Radiation Protection and Nuclear Safety Agency is licensed under a Creative Commons Attribution 3.0 Australia licence (to view a copy of the licence, visit http://creativecommons.org/licenses/by/3.0/au). It is a further condition of the licence that any numerical data referred to in this publication may not be changed. To the extent that copyright subsists in a third party, permission will be required from the third party to reuse the material.

In essence, you are free to copy, communicate and adapt the material as long as you attribute the work to ARPANSA and abide by the other licence terms. The works are to be attributed to the Commonwealth as follows:-

“© Commonwealth of Australia 2018 as represented by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA)”

The publication should be attributed as: Radiation Protection Requirements for Industrial Radiography (2018) Use of the Coat of Arms

The terms under which the Coat of Arms can be used are detailed on the Department of the Prime Minister and Cabinet website (www.dpmc.gov.au/government/commonwealth-coat-arms).

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Radiation Protection Requirements for Industrial Radiography ii

Foreword 28

The management of risks from ionizing radiation requires actions that are based on 29 fundamental principles of radiation protection, safety and security. The Fundamentals for 30 Protection Against Ionizing Radiation (2014) (RPS F-1) was published as part of ARPANSA’s 31 Radiation Protection Series (RPS) to provide an understanding of the effects of ionizing 32 radiation and associated risks for the health of humans and of the environment. RPS F-1 is 33 the top tier document in the Australian national framework to manage risks from ionizing 34 radiation and explains how radiation protection, safety and security can work individually 35 and collectively to manage such risks. It presents ten principles and their application in 36 management of radiation risks. 37

The code Radiation Protection in Planned Exposure Situations (2016) sets out the 38 requirements in Australia for the protection of occupationally exposed persons, the public 39 and the environment in planned exposure situations. The primary means of controlling 40 exposure in planned exposure situations is by good design of facilities, equipment, 41 operating procedures and through training – all of which contribute to optimisation of 42 protection. 43

This code Radiation Protection Requirements for Industrial Radiography (2018) sets out 44 the specific radiation protection requirements in Australia for the protection of 45 occupationally exposed persons and the public from planned exposure situations in the 46 use of radiation for the purpose of conducting industrial radiography. 47

ARPANSA, jointly with state and territory regulators in the Radiation Health Committee 48 (RHC), developed this Code based on the requirements relating to industrial radiography 49 described in the Code of Practice for the Safe Use of Industrial Radiography Equipment, 50 Radiation Health Series No.31 (1989) and guidance in the International Atomic Energy 51 Agency (IAEA) publication Radiation Safety in Industrial Radiography, Specific Safety Guide 52 No. SSG-11 (IAEA 2011). 53

This publication, together with RPS C-1, supersede Radiation Health Series No.31 and is 54 intended to complement the requirements of the relevant Work Health and Safety 55 legislation in each jurisdiction. The relevant regulatory authority should be contacted 56 should any conflict of interpretation arise. A listing of such authorities is provided at 57 www.arpansa.gov.au/Regulation/Regulators. 58

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Carl-Magnus Larsson 61 CEO of ARPANSA 62

<day month year> 63

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http://www.arpansa.gov.au/Regulation/Regulators


Radiation Protection Requirements for Industrial Radiography iii

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Radiation Protection Requirements for Industrial Radiography iv

Contents 70

Acknowledgement of Country ................................................................................... i 71

Foreword ................................................................................................................. ii 72

1. Introduction .................................................................................................... 1 73

Citation ........................................................................................................... 1 74

Interpretation ................................................................................................. 1 75

Background ..................................................................................................... 1 76

Purpose ........................................................................................................... 1 77

Scope .............................................................................................................. 2 78

2. Sale or supply of sealed radioactive sources and radiation generators for 79 industrial radiography ..................................................................................... 2 80

Equipment Requirements .............................................................................. 2 81

3. Radiation protection requirements for Industrial radiography practices ........... 4 82

General Requirements ................................................................................... 5 83

Work Practices ................................................................................................ 6 84

Radiation Monitoring ..................................................................................... 8 85

Radiography within fully enclosed sites ......................................................... 8 86

Radiography within a partially enclosed site ................................................. 9 87

4. Requirements applying to operators of industrial radiography equipment ..... 10 88

General Requirements ................................................................................. 10 89

Additional requirements for open site radiography .................................... 11 90

5. Appendix A - Example work practices and protocols ....................................... 13 91

6. Glossary ........................................................................................................ 20 92

7. References .................................................................................................... 24 93

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Radiation Protection Series C-4 Radiation Protection Requirements for Industrial Radiography

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1. Introduction 120

Citation 121

This publication may be cited as the Industrial Radiography Code (2018). 122

Interpretation 123

The presence of the term ‘must’ when it appears in this Code indicates that the requirement to 124 which it refers is mandatory. 125

Each of the terms in bold type has the meaning given in the Glossary together with any 126 amplification given in this Code. In particular, the term ‘radiation’ means ‘ionizing radiation’, as 127 defined in the Glossary. 128

Background 129

Industrial radiography uses the penetrative properties of ionizing radiation to obtain non-130 destructive information on the internal state of inanimate objects and materials through 131 radiographic imaging. Its application is well established and, when used in a safe and 132 controlled manner, brings significant benefits to society. 133

Due to the intense radiation fields used in industrial radiography, improper use could create 134 significant radiological health hazards including potentially lethal radiation doses. Harmful 135 radiation doses have been received in the past by both industrial radiographers and members 136 of the public from a variety of accidents, most of which could have been avoided had 137 appropriate safe working practices been followed. 138

Personal monitoring records consistently show that doses received by operators involved in 139 industrial radiography are amongst the highest of any group of radiation workers. 140

Dose rates of the order of a sievert (Sv) per second are not uncommon in the radiation beam. 141 Accidental exposure for a few seconds to such high dose rates would lead to doses of several 142 sieverts, which will cause severe radiation damage to any limbs or tissues exposed. Doses 143 above 10 Sv or more to the trunk of the body can be fatal. 144

Industrial radiography is carried out in a variety of environments including remote locations. At 145 open sites, in particular, radiographs may have to be made in circumstances that involve 146 serious risk of accidental exposure unless site working rules are rigorously followed. 147

Purpose 148

This code specifies the requirements to be followed to ensure that any unnecessary exposure 149 of persons to ionizing radiation is avoided, that all exposures are kept as low as reasonably 150 achievable, and that the dose limits specified in the Radiation Protection in Planned Exposure 151 Situations (Radiation Protection Series RPS C-1) are complied with. 152


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The implementation of these requirements serve to minimise accidents, incidents or 153 emergency exposure situations or mitigate their consequences. 154

The radiation protection requirements in this publication apply to Responsible Persons, and to 155 operators authorised to carry out industrial radiography work. 156

The numbered paragraphs can be used as licence conditions, either singly or in toto, by the 157 relevant regulatory authority or authorities as deemed appropriate. 158

Scope 159

This code applies to industrial radiography utilising radiation generators, sealed radioactive 160 sources and industrial radiography equipment to form an image of the surface or internal 161 state of an inanimate object or material which may be evaluated visually, instrumentally or 162 digitally. 163 164

2. Sale or supply of sealed radioactive sources and radiation 165

generators for industrial radiography 166

To ensure that unnecessary exposure of persons to radiation is avoided and that all exposures 167 are kept as low as reasonably achievable, it is important that all radiation generators, sealed 168 radioactive sources, exposure containers and industrial radiography equipment supplied for 169 industrial radiography comply with appropriate standards and the requirements of this Code. 170

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Equipment requirements

A Responsible Person that offers for sale or supply an exposure container, a sealed radioactive 172 source, a radiation generator or industrial radiography equipment for the purposes of 173 industrial radiography must ensure that: 174

a) the requirements of Radiation Protection in Planned Exposure Situations Radiation, 175 Protection Series RPS C-1 are complied with 176

b) a Radiation Management Plan, as required by RPS C-1, is implemented which 177 includes the work practices and protocols to be followed1, and emergency 178 preparedness plans and emergency response procedures to be followed2 179

c) the requirements of the Code for the Safe Transport of Radioactive Material, 180 Radiation Protection Series Publication RPS C-2 are complied with 181

d) the requirements of the Code of Practice for the Security of Radioactive Sources, 182 Radiation Protection Series No.11 are complied with 183 184 185

1 Appendix A: Example Work Practices and Protocols (including Warning Signs and Notices) 2 Refer to Radiation Safety in Industrial Radiography, Specific Safety Guide No. SSG-11, IAEA (2011) for guidance on

emergency preparedness and response.


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e) they hold an appropriate authorisation issued by the relevant regulatory authority 186 which permits the sale or supply of the sealed radioactive sources or radiation 187 generators under their control 188

f) for sealed source: 189 (i) sealed radioactive sources sold or supplied conform to ISO 2919 190

Radiological protection – Sealed radioactive sources – General 191 requirements and classification (or equivalent standard) 192

(ii) the purchaser is provided with a ‘dummy source’, and if required a 193 dummy source holder of the same appearance, or a photograph or other 194 documentation necessary to enable the operator to recognise an 195 accidentally detached source, by size and appearance in an emergency 196 exposure situation 197

(iii) the purchaser is provided with the manufacturer’s operating manual 198 which details the safe instruction to operate the item and the 199 maintenance to be undertaken to ensure the item continues to operate 200 as intended 201

(iv) when supplying a replacement sealed radioactive source in an exposure 202 container, that the source holder and couplings are inspected and 203 replaced if worn, frayed or damaged beyond the manufacturer’s 204 specifications or recommendations 205

g) for exposure containers: 206 (i) exposure containers and associated industrial radiography equipment 207

conform to ISO 3999 Radiation protection – Apparatus for industrial 208 gamma radiography – Specifications for performance, design and tests 209 or an equivalent standard (subject to written agreement with the 210 relevant regulatory authority) 211

h) for radiation generators: 212 (i) that the radiation generator is shielded to ensure that dose rate values 213

for leakage radiation do not exceed (typically) 100 µSv·h-1 at 1m from 214 the target under continuous operation at maximum energy and output 215

(ii) the radiation generator has a warning light (‘fail-to-safe’) which 216 illuminates when radiation is produced. Where the generator is not 217 fitted with such a warning light, a remote flashing warning light (‘fail-to-218 safe’) must be supplied for use in close proximity to the radiation 219 generator housing 220

(iii) the radiation generator is durably labelled to indicate where the primary 221 radiation beam exits the radiation generator 222

i) the radiation generator control panel includes the following features: 223 (i) a label incorporating the radiation symbol (trefoil), a notice indicating 224

that radiation is emitted when in operation, and a warning label 225 prohibiting unauthorised use 226

(ii) a key switch, or other mechanism, to prevent unauthorised use. Where 227 a key is used, the key should be removable only when the switch is in 228 the ‘off’ or ‘standby’ position (i.e. it should not be possible to lock the 229 system in the ‘on’ condition). Key positions must be clearly marked 230

(iii) a labelled warning light (‘fail-to-safe’) that indicates when the radiation 231 generator is enabled 232

(iv) a labelled warning light (‘fail-to-safe’) that indicates when the radiation 233 generator is emitting radiation 234

(v) a timer that controls the exposure duration and which terminates the 235 exposure after a pre-set interval, or an ‘on’ switch that requires 236


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continuous pressure by the operator to maintain the generation of 237 radiation 238

(vi) indicators that show the kilovolts (kV) and the current in milliamperes 239 (mA) when radiation is being emitted. For radiation generators 240 operating at fixed mA, a durable label specifying the mA must be affixed 241 to the radiation generator 242

(vii) a clear and durably labelled means of immediately terminating the 243 generation of radiation 244

(viii) is fitted with a device to connect a remote flashing light or a series of 245 flashing lights which can be used to define a boundary or provide a 246 visible warning 247

j) for radiation generators to be used in open site situations, the length of the cable 248 connecting the control panel to the generator must not (typically) be less than: 249

(i) 7 m for a 100kV or less generator 250 (ii) 10 m for a 200kV or less generator 251 (iii) 15 m for a 250kV or less generator 252 (iv) 20 m for generators 250 kV or greater 253

k) radiation generators used for fluoroscopy: 254 (i) designed or configured for direct-viewing fluoroscopy are shielded such 255

that the dose rate at any accessible position does not exceed 20 µSv·h-1 256 (ii) are designed or configured such that, when in use, the primary beam is 257

totally intercepted 258 l) radiation generator pipeline crawlers: 259

(i) have an audible alarm fitted to it so that when the pipeline crawler 260 reaches the exposure position, the klaxon must automatically operate 261 for a warning period of 10 seconds immediately prior to the exposure. 262 While the exposure takes place, the klaxon must continue in a manner 263 distinguishable from the 10 second warning 264

(ii) are operable by remote control or by an automatic device such as a trip 265 wheel, and fitted with a safety device which prevents unintentional 266 exposure 267

(iii) incorporate a safety device which disconnects power from the pipeline 268 crawler propulsion unit in the event of a malfunction during operation 269

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3. Radiation protection requirements for industrial 271

radiography practices 272

The overall responsibility for radiation protection in an industrial radiography practice lies with 273 the Responsible Person. 274

The Responsible Person is obliged to ensure that radiation generators, sealed radioactive 275 sources, exposure containers, industrial radiography equipment, fully enclosed sites and 276 partially enclosed sites for industrial radiography comply with appropriate standards and the 277 requirements of this Code. 278

The Responsible Person must also ensure that a Radiation Management Plan is implemented, 279 which includes the local rules and practices to be followed by operators when carrying out 280 industrial radiography work. 281


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General requirements

The Responsible Person must ensure that: 282 (a) the requirements of Radiation Protection in Planned Exposure Situations Radiation, 283

Protection Series RPS C-1 are complied with 284 (b) a Radiation Management Plan, as required by RPS C-1, is implemented which 285

includes the work practices and protocols to be followed3, and emergency 286 preparedness plans and emergency response procedures to be followed4 287

(c) an in-house Radiation Safety Officer5 is appointed to carry out the duties specified 288 in the Radiation Management Plan 289

(d) the requirements of the Code for the Safe Transport of Radioactive Material, 290 Radiation Protection Series Publication RPS C-2 are complied with 291

(e) the requirements of the Code of Practice for the Security of Radioactive Sources, 292 Radiation Protection Series No.11 are complied with 293

(f) they hold an appropriate authorisation issued by the relevant regulatory authority 294 which permits the possession and use of the sealed radioactive sources or radiation 295 generators under their control 296

(g) sealed radioactive sources used for industrial radiography conform to ISO 2919 297 Radiological protection – Sealed radioactive sources – General requirements and 298 classification or an equivalent standard (subject to written agreement with the 299 relevant regulatory authority) 300

(h) exposure containers and industrial radiography equipment conform to ISO 3999 301 Radiation protection – Apparatus for industrial gamma radiography – 302 Specifications for performance, design and tests or an equivalent standard (subject 303 to written agreement with the relevant regulatory authority) 304

(i) a durably marked and fire resistant label is attached to each exposure container 305 which incorporates the following information: 306

(i) the maximum radiation level at one metre from the container 307 (ii) the name, address and telephone number of the Responsible Person or 308

emergency contact person 309 (j) radiation generators meet the requirements of paragraphs 2.1(h)-(k) of this Code; 310

and 311 (k) exposure containers, radiation generators and industrial radiography equipment 312

under their control are serviced and maintained in accordance with the 313 manufacturer’s requirements 314

(l) the necessary equipment and facilities are available to enable the work practices 315 and protocols, and emergency preparedness plans as specified in the Radiation 316 Management Plan to be followed 317 318

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3 Appendix A: Example Work Practices and Protocols (including Warning Signs and Notices) 4 Refer to Radiation Safety in Industrial Radiography, Specific Safety Guide No. SSG-11, IAEA (2011) for guidance on

emergency preparedness and response. 5 Refer to SSG-11 for guidance on the role and duties of a Radiation Safety Officer. Note that SSG-11 uses the term

Radiation Protection Officer in place of Radiation Safety Officer.


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Work practices

The Responsible Person must ensure that: 320 (a) industrial radiography is performed only by persons authorised to do so by the 321

relevant regulatory authority 322 (b) under no circumstances are untrained, inappropriately qualified, or unauthorised 323

persons to use, remove, maintain, adjust, modify or in any way interfere with an 324 exposure container, radiation generator or industrial radiography equipment6 325

(c) a second person to the operator, a suitably trained assistant operator, is available 326 at an open site or a partially enclosed site. In case of an emergency, the assistant 327 operator must be capable of: 328

(i) ensuring that no person remains unnecessarily in an area where the 329 dose rate exceeds or might exceed 20 µSv·h-1 330

(ii) using any of the exposure containers, radiation generators or industrial 331 radiography equipment, or any other equipment at their disposal to 332 render the exposure situation safe 333

(iii) using a radiation survey meter in order to confirm the situation; 334 (iv) recognising a loose sealed radioactive source or source holder by being 335

familiar with the dummy source (or its photograph) supplied with the 336 sealed radioactive source 337

(v) informing the Radiation Safety Officer and the Responsible Person of the 338 details of the emergency without delay 339

(d) exposure containers, radiation generators and industrial radiography equipment 340 are inspected prior to first use and at intervals specified by the relevant regulatory 341 authority. Inspections must include tests to ensure that all safety interlocks, 342 shutters and control mechanisms operate effectively and that no components are 343 unacceptably worn or damaged 344

(e) if damage to an exposure container or radiation generator, or any variation in 345 radiation pattern comes to their attention, the container or generator must not be 346 further used until inspected, and declared safe, by a suitably competent or 347 authorised person. After repair, the container or generator must be tested for 348 proper functioning and, before re-use, must comply with all applicable standards 349 or the requirements of this Code. Details of the repairs must be kept and be made 350 available to the relevant regulatory authority upon request 351

(f) sealed radioactive sources and exposure containers loaded with sealed radioactive 352 sources are kept in a radiation store that is not used for any other purpose and in a 353 manner that ensures safe and secure storage 354

(g) the radiation store must be designated as a controlled area or supervised area, 355 where appropriate, and must be: 356

(i) resistant to fire, to minimise the potential for loss of shielding and 357 containment in the event of a fire in the vicinity 358

(ii) located at a remote distance from any corrosion and explosion hazards 359 (iii) made of materials that provide sufficient shielding so that radiation 360

levels at any readily accessible position outside the store do not result in 361

6 The relevant regulatory authority should be contacted for advice on the qualifications or training requirements for

gaining authorisation to use radiation generators or sealed radioactive sources for industrial radiography. Refer to SSG-11 for guidance on training and qualifications for industrial radiography personnel.


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an ambient dose equivalent rate or directional dose equivalent rate, as 362 appropriate, exceeding 10 μSv·h-1 363

(iv) kept locked and the keys must be held only by authorised personnel; 364 (v) affixed with a warning sign bearing the word ‘CAUTION’ and a trefoil 365

symbol and lettering that makes it clear that it is a store for radioactive 366 material7. A sign or separate notice must contain instructions for 367 contacting the Radiation Safety Officer (or appointed deputy) in an 368 emergency 369

(h) whenever an exposure container loaded with a sealed radioactive source is moved 370 within a site for radiography work, it must be kept in secure storage until it is 371 moved to the new location 372

(i) whenever an exposure container is moved within a site or when placed in a 373 radiation store, the source control or source control mechanism must be locked or 374 otherwise secured in the fully shielded position and all required port plugs and 375 caps secured in place. A radiation survey meter must be used to verify that the 376 sealed radioactive source is correctly located in the fully shielded position and that 377 the radiation exposure pattern is as expected 378

(j) any storage compartment in which the exposure container is stowed for transport 379 must be locked when the vehicle is left unattended. An exposure container must 380 not be left unattended in the back of an open vehicle 381

(k) operators of exposure containers are familiar with the nature and physical 382 appearance of any sealed radioactive source or source holder for which they have 383 responsibility 384

(l) all sealed radioactive sources within their control are accounted for at all times by 385 reference to a documented Radiation Source Movement Book 386

(m) an up to date record is maintained of the following information for all sealed 387 radioactive sources within their control: 388

(i) their date of receipt of and the name of the supplier 389 (ii) their location and identification numbers 390 (iii) the radionuclide in each sealed radioactive source 391 (iv) the activities and dates of measurement of the sealed radioactive 392

sources 393 (v) the make, model and identification number of the exposure container 394 (vi) inspection reports and details of repairs, if any 395 (vii) any prior approvals issued by the relevant regulatory authority for the 396

disposal of any sealed radioactive source 397 (viii) on disposal, the date and manner of disposal 398

(n) a record is kept of the following information for all radiation generators within 399 their control: 400

(i) radiation generator type 401 (ii) the location and identification number of the radiation generator 402 (iii) the maximum tube potential difference (kV (peak)) and current (mA), 403

and maximum energy (keV) 404 (iv) any inspection reports and details of repairs 405 (v) any prior approvals issued by the relevant regulatory authority obtained 406

for the disposal of any radiation generator 407

7 Appendix A: Example Work Practices and Protocols (Including Labels and Warning Signs)


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(vi) on disposal, the date and manner of disposal 408 (o) the relevant regulatory authority is notified as soon as possible, or within a 409

timeframe specified by the regulatory authority, if a sealed radioactive source or 410 radiation generator cannot be accounted for. 411

412

Radiation monitoring

The Responsible Person must ensure that: 413 (a) personal dosimeters issued to personnel directly involved in industrial radiography 414

operations: 415

(i) are capable of responding to the range of energies of the radiation 416 emitted during industrial radiography 417

(ii) continue to give a maximum audible response when exposed to dose 418 rates in excess of 500 mGy·h-1 in air 419

(b) all radiation survey meters provided provided to personnel for surveillance must 420

(i) have sufficient measurement range to measure radiation levels at least 421 through the ranges 1 µSv·h-1 to 10 mSv·h-1 for the radiations emitted 422 from the sources under control of the owner or operator 423

(ii) when radiation levels exceed the maximum readings in their 424 measurement ranges, continue to indicate that fact and should provide 425 an audible warning; 426

(iii) indicate the measured quantity with a measurement uncertainty not 427 greater than ±25%, inclusive of uncertainty due to response variation 428 with energy over the range of energies of the radiation to be measured. 429

(iv) be calibrated by a calibration facility recognised by the relevant 430 regulatory authority at intervals not exceeding 12 months and following 431 any damage or repairs to the working components. The most recent 432 calibration certificate must be kept and available for inspection by the 433 regulatory authority if required. 434

435 Note: While many types of radiation survey meter are suitable for measuring gamma radiation 436

levels, some may not be suitable for accurately measuring low energy X rays, which could 437 result in a significant underestimation of the true dose rate. Information and guidance on the 438 suitability of monitors should be obtained from radiation survey meter manufacturers and 439 qualified experts. 440

441

Radiography within fully enclosed sites

The Responsible Person must ensure that a fully enclosed site: 442 (a) is designed and engineered to provide adequate shielding from ionizing radiation 443

to persons in the vicinity and prevent or minimise the potential exposure of 444 persons who might enter the enclosure when the sources are exposed or 445 energised 446

(b) is designed so that exposure controls for exposure containers and radiation 447 generator are located outside the shielded enclosure 448


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(c) is designed to keep all direct and scattered radiation arising from radiographic 449 exposures within a totally enclosed volume and the dose rates do not exceed 20 450 µSv·h-1 measured at 5 cm from any accessible surface of the enclosure 451

(d) is clearly identified as a fully enclosed site through the use of warning notices at 452 access points. A warning light must be provided which is illuminated during 453 exposure and which is clearly visible from outside the enclosure 454

(e) is fitted with interlocks to all access points which will activate a visible and audible 455 alarm if an interlock is opened during exposure. In the use of radiation generators, 456 the opening of an interlock must automatically interrupt the power supply to the 457 radiation generator, and subsequently closing of the interlock must not 458 automatically re-energise the radiation generator 459

(f) is fitted with visible and audible warning devices inside the enclosure which must 460 be activated during exposure 461

(g) has suitable means of exit to enable any person accidentally within the enclosure 462 to exit without delay. The opening of any exit during exposure must activate an 463 alarm and subsequent closing of the exit must not automatically reset the alarm or 464 re-energise the radiation generator 465

(h) has conduits for feeding cabling, including wind out cables, electric power or other 466 services through the walls, incorporate a dog-leg or baffle that leaves no line-of-467 site aperture through the walls, so that the radiation shielding integrity of the 468 walls is not impaired. 469

470

Radiography within a partially enclosed site

The Responsible Person must ensure that a partially enclosed site: 471 (a) has walls at least 2.1m high and have sufficient shielding such that the dose rate 472

measured outside the enclosure must not exceed 20 µSv·h-1 measured 5cm from 473 any accessible surface 474

(b) is clearly identified as a partially enclosed site through the use of warning notices 475 at its perimeter and at access points. A warning light must be provided which is 476 illuminated during exposure and which is clearly visible from outside the enclosure 477

(c) is fitted with interlocks at all entrances to activate a visible and audible alarm 478 should any interlock be opened during exposure. In the case of the use of 479 radiation generators, the opening of an interlock must automatically interrupt the 480 power supply to the radiation generator, and subsequently closing of the interlock 481 must not automatically re-energise the generator 482

(d) is provided with visible and audible warning devices to be activated during 483 exposure and which can be seen and heard from both inside and outside the 484 enclosure 485

(e) is provided with a suitable means of exit to enable any person accidentally shut in 486 to leave the enclosure without delay. Opening of the exit during exposure must 487 activate an alarm and subsequent closing of the exit must not automatically reset 488 the alarm or re-energise the generator 489

(f) is fitted with doors or panels covering access apertures into partially enclosed sites 490 that overlap to prevent the leakage of scattered radiation 491

(g) has incorporated in its structure a maze used for access by personnel, a lockable 492 door or barrier must be incorporated and connected to an interlock, the opening 493 of the interlock must automatically interrupt the power supply to the radiation 494


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generator, and subsequently closing of the interlock must not automatically re-495 energise the radiation generator 496

(h) designed with a minimal or no roof, the scattered radiation (or ‘skyshine’) from the 497 roof or objects outside the enclosure must not present a radiation hazard in 498 occupied areas 499

(i) is clear of personnel during an exposure. 500

4. Requirements applying to operators of industrial 501

radiography equipment 502

While the primary responsibility for radiation safety lies with the Responsible Person, 503 operators have a responsibility to work safely in accordance with this Code and the working 504 rules and work practices to be followed as detailed in the Radiation Management Plan 505 approved by the Responsible Person, and to take all reasonable actions to restrict their own 506 exposure and those of other workers and members of the public. 507

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509

General requirements

Operators must ensure that: 510 (a) they comply with the Radiation Management Plan approved by the Responsible 511

Person, including any working rules, work practices to be followed, and emergency 512 procedures 513

(b) prior to commencing industrial radiography work: 514

(i) all interlocks, shielding, collimators, signs, barriers and other protective 515 devices are properly positioned 516

(ii) all persons not involved in the operation are at safe locations 517 (iii) a suitable radiation survey meter is available for immediate use 518

(c) they wear an approved personal radiation monitoring device which records their 519 cumulative radiation dose and a personal dosimeter, which provides an audible 520 indication of changing dose rate, at all times during industrial radiography work 521

(d) the following details of the movement of exposure containers and radiation 522 generators are legibly entered in a Radiation Source Movement Book: 523

(i) the identification number of the exposure container or radiation 524 generator 525

(ii) for exposure containers, the sealed radioactive source involved and its 526 activity at the time of transfer 527

(iii) the location of sites where the exposure container or radiation 528 generator is to be used 529

(iv) the date and time of removal from the radiation store 530 (v) the estimated date and time of return to the radiation store 531 (vi) the date and time of return to the store 532 (vii) the name of the operator 533

(e) on removing an exposure container from the store, verify that the sealed 534 radioactive source has been transferred to their custody by checking the exposure 535


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rate from the exposure container with a radiation survey meter and record this 536 fact in the Radiation Source Movement Book 537

(f) at the completion of each radiographic exposure, ensure by using a suitable 538 radiation survey meter that the sealed radioactive source has been returned to the 539 fully shielded position, or for radiation generators, that it is no longer emitting 540 radiation 541

(g) on returning an exposure container to the radiation store, ensure that the source 542 control or source control mechanism is locked or otherwise secured in the fully 543 shielded position and that all port plugs are firmly secured in place, and check with 544 a radiation survey meter that the sealed radioactive source is correctly located in 545 the fully shielded position 546

(h) they not operate any exposure container, radiation generator, or industrial 547 radiography equipment which is known or reasonably suspected to be 548 malfunctioning, deteriorated or damaged, and to report such circumstances 549 promptly to the Responsible Person or Radiation Safety Officer for appropriate 550 investigative action 551

(i) they immediately cease industrial radiography by returning the sealed radioactive 552 source to its fully shielded position within the exposure container or by de-553 energising the radiation generator, as applicable, should: 554

(i) a malfunction occur during operation 555 (ii) any person other than the operator or assistant operator enters an area 556

where the dose rate exceeds or might exceed 20 µSv·h-1; or 557 (iii) the only available radiation survey meter fails to function 558

(j) in the event of an incident, promptly take the appropriate measures in accordance 559 with any emergency preparedness and response plans implanted in the Radiation 560 Management Plan to bring the incident under control. The operator must 561 immediately inform the Radiation Safety Officer and the Responsible Person of the 562 circumstances of the incident. 563

564

Additional requirements for open site radiography

Operators must ensure that: 565 (a) prior to commencing industrial radiography, a well-defined and clearly visible 566

boundary is established using warning signs and devices such as barriers and ropes 567 around, above and below the site as appropriate 568

(b) a boundary is located such that the calculated dose rates at the boundary during 569 exposure must not exceed 20 µSv·h-1. The dose rates at the boundary must be 570 measured during exposure using a radiation survey meter and rectified if 571 necessary 572

(c) site radiography work is carried out in an area designated as a controlled area. No 573 other work is to be permitted in this area until the radiography work has been 574 finished and the controlled area is no longer so designated 575

(d) if boundaries overlap, close communication is to be maintained between 576 operators to avoid accidental exposure 577

(e) the control position (the position at which the operator controls the radiography 578 work) is located such that the dose rate to operators is ALARA and the dose rate is 579 checked regularly by means of a radiation survey meter 580


12

(f) exposure position (the position at which the radiography exposure takes place) is 581 clearly visible to the operator from the control position 582

(g) the area inside the boundary is inspected prior to exposure to ensure no person is 583 within it and must be kept under constant observation during exposure to ensure 584 no person enters it 585

(h) one or more warning lights and an audible alarm located immediately adjacent to 586 the exposure position must be used to indicate when an exposure in underway 587

(i) when a radiation generator is being used, a beam stop is used when performing 588 warm up operations for any purpose other than the production of a radiographic 589 image 590

(j) beam stops or collimators are used wherever practicable to ensure the dose rates 591 outside of the boundary are ALARA. 592

593

594


13

5. Appendix A - Example work practices and protocols 595

Example work practices and protocols for industrial 596

radiography 597

(Including Labels and Warning Signs) 598

599 The following example work practices and protocols for industrial radiography sites serve as a 600 guide in developing such work practices and protocols for inclusion in a Radiation 601 Management Plan8. 602 603

Work practices and protocols for a fully enclosed site (exposure room) 604 605 The inherent safety of a fully enclosed site affords adequate protection of persons outside 606 during an exposure, provided the following conditions are met. 607

(a) Only operations for which the fully enclosed site provides adequate shielding must 608 be carried out. The dose rate must be periodically measured by the operator and 609 must not exceed 20 µSv·h-1 in any readily accessible position outside the fully 610 enclosed site. 611

(b) Before commencing an exposure, the operator must ensure by visual inspection 612 that the fully enclosed site is unoccupied. 613

(c) All entrances to the fully enclosed site must be locked, or interlocked to an audible 614 and visible alarm, during radiographic exposure. 615

(d) A personal radiation monitoring device and a personal dose meter must be worn 616 by the operator and assistant operator at all times during industrial radiography 617 operations. 618

(e) At the completion of an exposure, the operator must ensure, by using a radiation 619 survey meter, that the radiation generator has been switched off or the sealed 620 radioactive source has returned to its fully shielded position within the exposure 621 container. 622

(f) The operator must, according to appropriate advice prepared by the Radiation 623 Safety Officer, ensure that dose rates in occupied areas are such that no member 624 of the public will receive a dose exceeding 1 mSv per year from radiography 625 performed within the site. 626

627

Work practices and protocols for a partially enclosed site (exposure bay) 628 629

(a) A second person, who is capable of promptly taking charge in an emergency, must 630 be immediately available to assist during industrial radiographic exposures. This 631 second person must be able to: 632

(i) ensure that no person remains unnecessarily in an area where the dose 633 rate exceeds or might exceed 20 µSv·h-1 634

8 Refer to Radiation Protection in Planned Situations, Radiation Protection Series C-1 (2016) for requirements on the

development and implementation of a Radiation Management Plan


14

(ii) use the source control equipment or any other means at their disposal 635 to render the situation safe and under control, if necessary; use a 636 radiation survey meter in order to confirm the situation 637

(iii) recognise a loose sealed radioactive source or pigtail by being familiar 638 with the dummy source or its photograph; and 639

(iv) inform the Radiation Safety Officer and the Responsible Person of the 640 circumstances of the emergency without delay. 641

This person must not be in charge of any work at an adjacent site, unless scheduling 642 arrangements are made such that they are not simultaneously responsible for work taking 643 place at both sites. 644

(a) Before commencing an exposure, the operator must ensure by visual inspection 645 that the partially enclosed site is unoccupied. 646

(b) All openings into the partially enclosed site must be closed during exposure and 647 when ‘radiation on’ indicators are activated. 648

(c) The dose rate must be periodically measured by the operator particularly when 649 radiographic exposure configurations are changed, and must not exceed 20 µSv·h-650 1 in any readily accessible position outside the partially enclosed site. 651

(d) Unnecessary occupancy of the area immediately adjacent to the partially enclosed 652 site should be avoided during exposure, unless radiation survey measurements 653 show that dose rates there are negligible. In particular, the area above a partially 654 enclosed site must be kept under surveillance during exposure to ensure that no 655 persons (for example, gantry drivers, personnel on a higher floor or roof) stray into 656 a position where the dose rate exceeds or might exceed 20 µSv·h-1. 657

(e) A personal radiation monitoring device and a personal dose meter must be worn 658 by operators and assistant operators at all times during industrial radiography 659 operations. At the completion of an exposure, the operator must ensure, by using 660 a radiation survey meter, that the radiation generator has been switched off or the 661 sealed radioactive source has returned to its fully shielded position within the 662 exposure container. 663

(f) The operator must, according to appropriate advice prepared by the Radiation 664 Safety Officer ensure that dose rates in occupied areas are such that no member 665 of the public will receive a dose exceeding 1 mSv per year from radiography 666 performed within the site. 667

668

Work practices and protocols for an open site (field site) 669 670 General work practices and protocols 671 672

(a) On first arriving at the site, the operator must: 673

674 (i) advise the person responsible for the area in which the radiography site 675

will be set up of the intended operations and the estimated amount of 676 time required to complete the work; and 677

(ii) ascertain the nature, duration and location of all other work to be 678 performed in the vicinity of the site and the possible points of entry to 679 the site. 680

(b) Before commencing exposures, a well-defined and clearly visible boundary must 681 be established (using, for example, flagged rope) around the site, including above 682


15

and below as necessary, such that the dose rate at the boundary must not exceed 683 20 µSv·h-1 during exposures. This must be checked periodically by the operator by 684 means of a radiation survey meter. The boundary must be marked with radiation 685 warning signs. An example of a suitable warning sign to be used during exposure is 686 given in this appendix. Warning lights must be used to indicate that an exposure is 687 underway. The area within the boundary must be kept under surveillance at all 688 times during exposures to ensure that no person enters it or remains within it. 689 Unnecessary occupation of areas near the boundary should be avoided. 690

(c) The boundaries of adjacent exposure sites should not overlap. If an overlap is 691 unavoidable, close liaison must be maintained between operators responsible for 692 the overlapping sites to avoid accidental exposures. 693

(d) The operator must, according to appropriate advice prepared by the Radiation 694 Safety Officer, ensure that dose rates in occupied areas are such that no member 695 of the public will receive a dose exceeding 1 mSv per year from radiography 696 performed within the site. 697

(e) A sealed radioactive source must not be partially or wholly exposed outside its 698 exposure container nor a radiation generator switched on except when it is 699 positioned within the site boundary. The immediate surroundings of the exposure 700 position must be clearly visible from the control position. The control position 701 must be in an appropriately safe place, as far as practicable from the exposure 702 position. The dose rate at the control position or at the position taken up by the 703 operator during exposure must be checked regularly by means of a radiation 704 survey meter. 705

(f) A second person, who is capable of promptly taking charge in an emergency, must 706 be immediately available to assist during industrial radiographic exposures. This 707 person must be able to: 708

(i) ensure that no person remains unnecessarily in an area where the dose 709 rate exceeds or might exceed 20 µSv·h-1; 710

(ii) use the source control equipment or any other means at their disposal 711 to render the radiography equipment safe, if necessary; 712

(iii) use a radiation survey meter in order to confirm the situation; 713 (iv) recognise a sealed radioactive source or pigtail by being familiar with the 714

dummy source or its photograph; and 715 (v) inform the Radiation Safety Officer and the Responsible Person of the 716

circumstances of the emergency without delay. 717 This person must not be in charge of any work at an adjacent site, unless 718 scheduling arrangements are made such that they are not 719 simultaneously responsible for work taking place at both sites. 720

(g) Where applicable, collimators must be used to restrict the area of the primary 721 radiation beam to the minimum necessary for radiography. The beam should be 722 directed towards the ground, but if this is not possible, a back shield should be 723 used. Shielding should also be used to reduce stray radiation, when practicable. 724

(h) Radiography equipment and the item to be radiographed must be set up so that 725 each of the components, particularly the radiation generator or the sealed 726 radioactive source, are stable and therefore will not move during the exposure. 727

(i) Before commencing an exposure, the operator must ensure by inspection that all 728 unauthorised persons are outside the boundary and that the assistant operators 729 are in an area where the dose rate is as low as, or lower than, where the operator 730 is located. 731

(j) Just prior to commencing an exposure, a warning signal must be given to warn 732 persons within a reasonable distance that an exposure is about to take place. 733


16

(k) A personal radiation monitoring device and a personal dose meter must be worn 734 by the operator and assistant operators at all times during industrial radiography 735 operations. 736

(l) The operator must continually check the radiation level at their location during 737 exposure using a radiation survey meter. 738

(m) The operator alone must exercise control over: 739

(i) the radiation exposure; and 740 (ii) the occupancy of the site during the period of exposure by continuous 741

and competent supervision of the site. 742 (n) Care must be taken at all times to ensure that unauthorised persons cannot 743

operate the exposure container or radiation generator. 744 (o) Exposure containers and radiation generators should not be left unattended. If it is 745

necessary to leave these items unattended for a short period, the sealed 746 radioactive source must be returned to its fully shielded condition or switched off, 747 as appropriate, and locked. The operator must retain the key in their possession 748 and before re-inserting the key, confirm that the equipment has not been 749 tampered with in any way. If the equipment has been tampered with, this fact 750 must be reported immediately to the Responsible Person. For long periods without 751 use the exposure container or radiation generator must be returned to an 752 appropriate storage location. 753

(p) Before a site is vacated, the operator must ensure, by monitoring, that all 754 radioactive sources are locked in the fully shielded condition or radiation 755 generators switched off, as appropriate, and returned to an appropriate store or 756 to the transport vehicle and that all boundary defining equipment has been 757 removed. The operator must inform the person responsible for the area when this 758 has been carried out. 759

Additional work practices and protocols for radiation generators 760 761 (a) Radiation generators must be transported or relocated only with the power supply 762

disconnected. 763 (b) When setting up, the power cable must be laid out to ensure as large a distance as 764

possible between the radiation generator and the control panel and in such a way 765 that the cable is unlikely to be damaged, for example, by falling objects or by being 766 run over by vehicles. 767

(c) The window on the radiation generator must be completely shielded during warm-768 up procedures. 769

(d) Immediately after each exposure, the operator must use a radiation survey meter 770 to confirm that the radiation generator is de-energised and must first turn the kV 771 control back to its lowest setting, if it does not automatically reset, before other 772 controls are changed. 773

(e) The radiation generator must be properly earthed. 774

Additional work practices and protocols for pipeline crawler equipment 775 776

(a) Where a right of way is situated adjacent to the pipeline in which a pipeline 777 crawler is operating; the boundary that is established must restrict the passage of 778 vehicles and personnel along that right of way while the pipeline crawler is 779 activated. 780

(b) In a very noisy industrial environment in which the pipeline crawler audible alarm 781 may not be readily audible to all those who should be warned by it, particular 782


17

attention must be given to competent and continuous supervision of access to the 783 site and to the possible use of a high-intensity flashing (strobe) light or an ancillary 784 klaxon outside the pipe. 785

(c) While a pipeline crawler is not in operation in a pipeline and prior to its transfer 786 into or out of a pipeline, the exposure control must be made safe so that it is not 787 possible for an exposure to be initiated by unintentional tripping of the exposure 788 initiation device. Where there is no exposure control safety device, the power 789 supply must be disconnected. When a fault condition causes a battery-operated 790 pipeline crawler to be continually energised, with the consequence that the 791 battery voltage falls, the energy of the radiation generated may be below the 792 range of the survey meter. If such a fault occurs, it must be assumed that the 793 pipeline crawler is emitting radiation until the battery supply has been 794 disconnected. 795

(d) A pipeline crawler must not be handled manually unless the power supply is 796 disconnected or the equipment is otherwise made safe. 797

798 799 Additional work practice and protocols for radiography using exposure containers 800 801

(a) Only radiation workers, who are wearing personal dose meters, are to travel in 802 road vehicles which transport sealed radioactive sources around or between 803 industrial radiography sites or between such sites and the Responsible Person’s 804 premises or the radiography equipment store. There must be at least one 805 functional radiation survey meter and one audible alarm dose meter also in the 806 vehicle, and the latter should be left operating during the journey. 807

(b) When setting up source control cables, collimators and exposure containers for 808 exposure, the equipment must be laid out to ensure as large a distance as possible 809 between the exposure container and the control mechanism and in such a way 810 that the control cable is unlikely to be damaged, for example, by falling objects or 811 by being run over by motor vehicles. Control cables and guide tubes must be laid 812 out such that they do not contain sharp bends or kinks which might cause the 813 cable or source to jam or which cause excessive wear of the control cable. 814

(c) Radiography equipment and the item to be radiographed must be set up so that 815 each of the components, particularly the sealed radioactive source or source 816 holder in its exposure position, is stable and therefore will not move during the 817 exposure. 818

(d) Before exposure, the correct operation of the wind out cable must be verified - the 819 mechanism should be wound out through two revolutions and back through two 820 revolutions, and a radiation survey meter used to confirm movement of the sealed 821 radioactive source. 822

(e) Wind-out and wind-in operations should be performed quickly but carefully. 823 (f) A correctly operating radiation survey meter must be placed adjacent to the wind 824

out mechanism during winding so as to confirm the status of the sealed 825 radioactive source. In particular, the radiation survey meter must be used to 826 confirm that the sealed radioactive source has been returned to the exposure 827 container at the completion of the exposure. The operator must use a radiation 828 survey meter when approaching the source, irrespective of its operating status. 829

830

831


18

Example radiation label and warning signs for Industrial 832

radiography 833

834

835

836

837 Label for attachment to an exposure container 838

839

840

841

842


19

843

844

845

Warning sign for a radiation store 846

847

848

849 850

Warning sign for display during 851 industrial radiography 852

853 854 855


20

6. Glossary 856

Control cable 857

A component of a source control mechanism which, for shutter type exposure containers, 858 controls the shutter from a location remote from the exposure area or, for a projection type 859 exposure container is a wind out cable. 860

Controlled area 861

A defined area in which specific protection measures and safety provisions are or could be 862 required for controlling exposures or preventing the spread of contamination in normal 863 working conditions, and preventing or limiting the extent of potential exposures. 864

Emergency exposure situation 865

A situation of exposure that arises as a result of an accident, a malicious act, or any other 866 unexpected event, and requires prompt action in order to avoid or reduce adverse 867 consequences. 868

Exposure container 869

One of three types of container designed to house a sealed radioactive source and to provide, 870 through shielding, protection of persons from the high levels of radiation close to the source, 871 and to which a source control mechanism can be attached. 872

• A shutter type container fully encloses the radioactive source except during 873 exposure,when the shutter is opened, and in some cases the source is moved to a 874 window, to permit the passage of radiation. 875

• A projection type container retains the radioactive source in a shielded position except 876 during exposure, when it is propelled from the container along a guide tube to its 877 exposure position. 878

• A projection-shutter type container combines features of both of the above types. 879

Fully enclosed site 880

A purpose built enclosure used specifically for industrial radiography in which the irradiation 881 area is completely enclosed by shielding, including walls, floor and ceiling, and within which no 882 person is permitted to remain during exposure. 883

Guide tube 884

A tube, typically of flexible construction, designed to provide an enclosed path along which a 885 radioactive source may be moved from its source container to its exposure position and back 886 again. 887

Incident 888


21

Any unintended event, including operating errors, equipment failures, initiating events, 889 accident precursors, near misses or other mishaps, or unauthorised act, malicious or non-890 malicious, the consequences or potential consequences of which are not negligible from the 891 point of view of protection and safety. 892

Industrial radiography equipment 893

Ancillary equipment used in industrial radiography such as control cables, guide tubes, 894 collimators, wind out cables, source control mechanisms, and imaging devices. 895

Ionizing radiation 896

For the purposes of radiation protection, radiation capable of producing ion pairs in biological 897 material(s). 898

Open site 899

A radiography site at which, due to operational requirements, the shielding afforded by a fully 900 enclosed site or a partially enclosed site cannot be provided and for which a clearly marked 901 boundary is set up and strict control of access and occupancy is observed. 902

Operator 903

A person who is involve in conducting industrial radiography by operating industrial 904 radiography equipment, exposure containers or radiation generators and who, having 905 successfully completed a suitable course of training, has the approval of the appropriate 906 regulatory authority to do so. 907

Partially enclosed site 908

A radiography site at which all objects exposed to direct radiation are completely contained 909 inside a permanent, shielding enclosure having walls at least 2.1 m high but typically open at 910 the top to permit the transfer in and out of the objects to be radiographed, and within which 911 no person is permitted to remain during exposure. 912

Pipeline crawler 913

A device designed to travel automatically or by remote control through pipes; and which 914 contains either a sealed radioactive source or radiation generator, which is typically used to 915 radiograph pipeline welds through the pipe wall. 916

Radiation 917

In this Code, the term ‘radiation’ refers only to ionizing radiation unless otherwise stated. 918

For the purposes of radiation protection, ionizing radiation is capable of producing ion pairs in 919 biological material(s). 920


22

For most practical purposes, it may be assumed that strongly penetrating radiation includes 921 photons of energy above about 12 keV, electrons of energy more than about 2 MeV, and 922 neutrons. 923

For most practical purposes, it may be assumed that weakly penetrating radiation includes 924 photons of energy below about 12 keV, electrons of energy less than about 2 MeV, and 925 massive charged particles such as protons and alpha particles. 926

Radiation generator 927

A device capable of generating ionizing radiation, such as X rays, neutrons, electrons or other 928 charged particles, that may be used for scientific, industrial or medical purposes. 929

Radiation survey meter 930

A hand-held instrument which measures radiation dose rate. 931 932 Responsible person9 933

In relation to any radiation source, prescribed radiation facility or premises on which radiation 934 sources are stored or used means the legal person: 935

(a) having overall management responsibility including responsibility for the 936 security and maintenance of the radiation source, facility or premises 937

(b) having overall control over who may use the radiation source, facility or 938 premises 939

(c) in whose name the radiation source, facility or premises would be 940 registered if this is required. 941

Sealed radioactive source 942

A radioactive source in which the radioactive material is: 943 (a) permanently sealed in a capsule, or 944 (b) closely bonded and in a solid form. 945

Sievert (Sv) 946

The SI unit of equivalent dose and effective dose, equal to 1 J/kg. 947

Source control mechanism 948

A system or device that operates a shutter or projection mechanism on an exposure container 949 by remote control. Such a control mechanism may operate mechanically, electrically or 950 pneumatically, and includes a device to lock the shutter in the closed position or to lock the 951 sealed radioactive source in its shielded position. 952

Supervised area 953

9 Note: A Responsible Person has the same meaning as a Person Conducting a Business or Undertaking (PCBU), as

defined in the Commonwealth Work Health and Safety Act 2011, who is conducting a business or undertaking that uses radiation and requires an authorisation under relevant legislation.


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A defined area not designated as a controlled area but for which occupational exposure 954 conditions are kept under review, even though specific protection measures or safety 955 provisions are not normally needed. 956

Wind out cable 957

A control cable which can be attached to an exposure container of projection type to move the 958 sealed radioactive source through a guide tube between its fully shielded position and its 959 exposure position, and which can be wound out and in from a location remote from the 960 exposure area. 961

962


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7. References 963

Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 2014. Fundamentals for 964 Protection Against Ionizing Radiation. Radiation Protection Series F-1 965 www.arpansa.gov.au/Publications/codes/rpsF-1.cfm 966 967 Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 2016. Radiation 968 Protection in Planned Exposure Situations. Radiation Protection Series C-1 969 www.arpansa.gov.au/regulation-and-licensing/regulatory-publications/radiation-protection-970 series/codes-and-standards/rpsc-1 971 972 Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 2014. Code for the Safe 973 Transport of Radioactive Material, Radiation Protection Series C-2 974 www.arpansa.gov.au/regulation-and-licensing/regulatory-publications/radiation-protection-975 series/codes-and-standards/rpsc-2 976 977 Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 2007. Code of Practice 978 for the Security of Radioactive Sources. Radiation Protection Series No.11. 979 www.arpansa.gov.au/regulation-and-licensing/regulatory-publications/radiation-protection-980 series/codes-and-standards/rps11 981 982 International Atomic Energy Agency (IAEA) 2011. Radiation Safety in Industrial Radiography 983 Safety Standards. Specific Safety Guide, No SSG-11 984 www-pub.iaea.org/books/IAEABooks/8500/Radiation-Safety-in-Industrial-Radiography 985 986 International Organization for Standardization (ISO) 2012. Radiological Protection – Sealed 987 radioactive sources – General requirements and classification. ISO 2919:2012. 988 www.iso.org/standard/54441.html 989 990 International Organization for Standardization (ISO) 2004. Radiation protection - Apparatus for 991 industrial gamma radiography - Specifications for performance, design and tests. ISO 992 3999:2004. 993 www.iso.org/standard/40447.html 994 995

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