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Australian Government

Australian Radiation Protection and Nuclear Safety Agency

Facility Licence Application: Nuclear Installation

This form is to be used Commonwealth entities to apply for a fac ility licence for a nuclear

installation under section 32 of the Australian Radiation Protection and Nuclear Safety Act 1998. Applicants should refer to Regulatory Guide: Applying for a Facility Licence for a Nuclear Installation when completing this form .

REGULATORY SERVICES

REG·LA-FORM-240C

October 2013

SECTION A - APPLICANT INFORMATION

DEPARTMENT OR COMMON WEAL TH ANSTO

BODY:

PORTFOLIO: Industry Portfolio

PERSON MAKING THE APPL/CAT/ON: Department Secretary or CEO ar other authorised de/egate1

Name: Adi Paterson

Position: Chief Executive Officer

Business address: Locked Bag 2001 Kirrawee DC NSW 2232

Ph:0297173702 Fax: 0297176111

Email: [email protected]

NOMINEE {Where Applicable):

Name: Hefin Griffiths

Position: Head, Nuclear Services


Ph: 02-97173295 Fax:

Email: hwg@ansto .gov.au

RAD/AT/ON SAFETY OFFICER OR CONTACT PERSON:

Name: Robin Foy

Position: Manager - Radiation Protection Services


Ph: 02 9717 9787 Fax:

Email: [email protected]

DECLARATION (To be signed by the person making the application or other authorised person)

I hereby declare that the information provided on this form and in support of this application is, to the best of

my knowledge, complete and true in every particular.

~UC~ Date:

1 A copy of the instrument of authorisa tion must accompany the application .

SECTION B- KIND OF NUCLEAR INSTALLATION AND TYPE OF AUTHORISATION Indicate the kind of nuclear installation and type of authorisation for which a licence is sought.

ITEM KIND OF NUCLEAR INSTALLATION AND TYPE OF AUTHORISATION REQUIRED CHECK

l Preparing a site for a controlled facility, being a nuclear reactor that is designed:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D {b) to have maximum thermal power of less than 1 megawatt

2 Constructing a controlled facility, being a nuclear reactor that is designed :

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b} to have maximum thermal power of less than 1 megawatt

3 Possessing or controlling a controlled facility, being a nuclear reactor:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) with maximum thermal power of less than 1 megawatt

4 Operating a controlled facility, being a nuclear reactor:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) with maximum thermal power of less than 1 megawatt

5 De-commissioning, disposing of or abandoning a controlled facility, being a nuclear reactor that:

(a) was used for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b} had maximum thermal power of less than 1 megawatt

6 Preparing a site for a controlled facility, being a nuclear reactor that is designed:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) to have maximum thermal power of 1 megawatt or more

7 Constructing a controlled facility, being a nuclear reactor that is designed:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) to have maximum thermal power of 1 megawatt or more

KEG·LA-FORM-240C \lll.l October 2013 of 21


8 Possessing or controlling a controlled facility, being a nuclear reactor:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) with maximum thermal power of 1 megawatt or more

9 Operating a controlled facility, being a nuclear reactor:

(a) for research or production of nuclear materials for industrial or medical use (including critical and subcritical assemblies); and D (b) with maximum thermal power of 1 megawatt or more

10 De-commissioning, disposing of or abandoning a controlled facility, being a nuclear reactor that:

(a) was used for research or production of nuclear materials for industrial or medical use (including critical an_d subcritical assemblies); and D (b) had maximum thermal power of 1 megawatt or more

11 Preparing a site for a controlled facility, being a plant for preparing or storing fuel for use in a nuclear reactor of a kind mentioned in any of items 1 to 9 D 12 Constructing a controlled facility, being a plant for preparing or storing fuel for use in a nuclear reactor of a kind mentioned in any of items 1 to 9 D 13 Possessing or controlling a controlled facility, being a plant for preparing or storing fuel for use in a nuclear reactor of a kind mentioned in any of items 1 to D 9

14 Operating a controlled facility, being a plant for preparing or storing fuel for use in a nuclear reactor of a kind mentioned in any of items 1 to 9 D 15 De-commissioning, disposing of or abandoning a controlled facility, being a plant that was used for preparing or storing fuel for use in a nuclear reactor of a D kind mentioned in any of items 1 to 9

16 Preparing a site for a controlled facility, being:

(a) a nuclear waste storage facility that is designed to contain controlled materials with an activity that is greater than the applicable activity level

D prescribed by regulation 7; or

(b) a nuclear waste disposal facility that is designed to contain controlled materials with an activity that is greater than the applicable activity level

prescribed by regulation 8

17 Constructing a controlled facility, being:

(a) a nuclear waste storage facility that is designed to contain controlled materials with an activity that is greater than the applicable activity level


(b) a nuclear waste disposal facility that is designed to contain controlled materials with an activity that is greater than the applicable activity level


: G-LA-FORM-240( v8.l October 2013 of 21


18 Possessing or controlling a controlled facility, being:

(a) a nuclear waste storage facility that contains controlled materials with an activity that is greater than the applicable activity level prescribed by

D regulation 7; or

(b) a nuclear waste disposal facility that contains controlled materials with an activity that is greater than the applicable activity level prescribed by

regulation 8

19 Operating a controlled facility, being:

(a) a nuclear waste storage facility that contains controlled materials with an activity that is greater than the applicable activity level prescribed by

[g] regulation 7; or

(b) a nuclear waste disposal facility that contains controlled materials with an activity that is greater than the applicable activity level prescribed by

regulation 8

20 De-commissioning, disposing of or abandoning a controlled facility, being:

(a) a nuclear waste storage facility that formerly contained controlled materials with an activity that was greater than the applicable activity level


(b) a nuclear waste disposal facility that formerly contained controlled materials with an activity that was greater than the applicable activity level


21 Preparing a site for a controlled facility, being a facility to produce radioisotopes, that is designed to contain controlled materials with an activity that is D greater than the applicable activity level prescribed by regulation 11

22 Constructing a controlled facility, being a facility to produce radioisotopes, that is designed to contain controlled materials with an activity that is greater D than the applicable activity level prescribed by regulation 11

23 Possessing or controlling a controlled facility, being a facility producing radioisotopes and containing controlled materials with an activity that is greater D than the applicable activity level prescribed by regulation 11

24 Operating a controlled facility, being a facility producing radioisotopes and containing controlled materials with an activity that is greater than the D applicable activity level prescribed by regulation 11

25 De-commissioning, disposing of, or abandoning a controlled facility, being a facility that formerly produced radioisotopes and contained controlled D materials with an activity that was greater than the applicable activity level prescribed by regulation 11

KtG·LA-FORM-240( v8.l Oct ober 2013 of 21

SECTION C - FACILITY DETAILS

Address of the nuclear installation

The address of the proposed nuclear installation is as follows:

Lucas Heights Science and Technology Centre (LHSTC)

New lllawarra Road, Lucas Heights NSW.

Purpose of the nuclear installation

The nuclear installation is a purpose-built store for housing Intermediate Level Solid

Radioactive Waste (ILW) returned from France following the reprocessing of HIFAR used fuel

assemblies. The facility is an above-ground building called the Interim Waste Store (IWS).

Australia is obliged under international contracts and agreements to accept return of this

waste: in the case of the waste reprocessed in France, it must be shipped from France no later

than December 2015.

In the absence of a National Radioactive Waste Management Facility (NRWMF), ANSTO is

obliged to store this waste as an interim measure until the NRWMF becomes available. Should

the NRWMF not be completed by the end of this decade, Australia is obligated to receive an

additional shipment of reprocessed waste from the UK which could also be stored in this

facility. This will be the subject of a separate licence application (or licence variation)

A further detail of the purpose and scope of the IWS is provided in the IWS Safety Analysis

Report (IWS-0-LA-SAR) and Licence Application Summary (IWS-0-LA-SUM).

Description of the nuclear installation and its site

The IWS is a single storey building and has been constructed 2 for the purpose of interim

storage of the intermediate level wastes arising from the reprocessing of used HIFAR fuel in

France. The building has a floor area of approximately 845 m2 with a height of 21 m. The

perimeter walls are of precast concrete panels approximately 170 mm thick measuring 5 min

height from the floor level and fixed to a structural steel portal. The rest of the perimeter walls

which is fixed on top of the precast concrete panels have been constructed with 200 mm thick

2 This form is completed with the view of describing the operation of the IWS when it is installed and

commissioned although the facility is currently being constructed. Therefore, some of the descriptions given

below are written as if the facility is already in existence

insulated sheet-metal sandwich panels with thermal insulation. The roof of the facility has

been constructed from 150 mm thick sheet-metal sandwich panel. It has shutter doors for the

entry and exit of the ILW consignments.

The location of the IWS within the LHSTC is between existing buildings 64 and 19, just to the

north of building 61. It required the demolition of building 63. The final site for the interim

store was selected after considering a number of site locations.

The IWS is essentially surrounded by other ANSTO buildings, and approximately 350m from

the southern-most point of the fenced site (at gate 13); 182 m from the fence at Gate 14; and

112m from the nearest point on the fence (at the point where the fence has an internal

corner, near building 27). The facility has road access from Dalton Avenue.

A further description of the IWS is provided in Description of the structures, Components,

Systems and Equipment', Document No. IWS-0-LA-FD and Safety Analysis Report, Document

No. IWS-0-LA-SAR.

Type of Authorisation [complete relevant section]

Prepare a site for a nuclear installation

a) A detailed site evaluation establishing the suitability of the site.

b) The characteristics of the site, including the extent to which the site may be affected by natural and

man-made events.

c) Any environmental impact statement requested or required by a government agency, and the

outcome of the environmental assessment.

Construct a nuclear installation

a) The design of the controlled facility, including ways in which the design deals with the physical and

environmental characteristics of the site.

b) Any fundamental difficulties that will need to be resolved before any future authorisation is given.

c) The construction plan and schedule.

d) A preliminary safety analysis report that demonstrates the adequacy of the design of the facility and

identifies structure, components and systems that are safety related items.

e) The arrangements for testing and commissioning safety related items.

Possess or control a nuclear installation

a) The arrangements for maintaining criticality safety during loading, moving or storing nuclear fuel

and other fissile materials at the controlled facility.

b) The arrangements for safe storage of controlled material and maintaining the controlled facility.

Operate a nuclear installation

a) A description of the structures, components, systems and equipment of the controlled facility as

they have been constructed.

See 'Description of the structures, Components, Systems and Equipment' , Document No. IWS-0-LA

FD.

b) A final safety analysis report that demonstrates the adequacy of the design of the controlled facility,

and includes the results of commissioning tests.

See 'IWS Safety Analysis Report', Document No. IWS-0-LA-SAR.

c) The operational limits and conditions of the controlled facility.

See 'IWS Operational Limits and Conditions', Document No. IWS-0-LA-OLC.

d) The arrangements for commissioning the controlled facility.

See 'IWS Arrangements for Commissioning', Document No. IWS-0-LA-COM.

e) The arrangements for operating the controlled facility.

See 'Arrangements for Operating the IWS', Document No. IWS-0-LA-PRO.

Decommission a nuclear installation

a) The decommissioning plan for the controlled facility.

b) The schedule for decommissioning the controlled facility.

Abandon a nuclear installation

I 1

a) The results of decommissioning activities at the controlled facility.

b) Details of any environmental monitoring program proposed for the site.

I I "

SECTION D - PLANS & ARRANGEMENTS FOR MANAGING SAFETY Describe the plans and arrangements for managing the nuclear installation and any associated sou rces in

the space provided AND/OR provide clear references to where this information may be found within

accompanying documentation.

Effective control arrangements

See ' IWS Effective Control Plan', Document No. IWS-0-LA-Dl.

Safety management plan

See 'IWS Safety management Plan', Document No. IWS-0-LA-D2.

Radiation protection plan

See 'IWS Radiation protection Plan', Document No. IWS-O-LA-D3.

Radioactive waste management plan

See 'IWS Waste Management Plan', Document No. IWS-O-LA-04.

Security plan

See 'IWS Security Plan', Document No. IWS-0-LA-DS.

Emergency plan

See 'IWS Emergency Plan', Document No. IWS-O-LA-D6.

'I I · 1 I!• t , I 1't , 1. -., •r11 .

SECTION E-ASSOCIATED SOURCES

Is there controlled material and/or controlled apparatus used in connection with the facility? ~ NO Proceed to Section H 0 YES Indicate kind

GROUP ITEM KIND OF CONTROLLED MATERIAL OR CONTROLLED APPARATUS Check

l Sealed source for calibration purposes of activity of 40 MBq or less 0

2 Sealed source in a fully enclosed analytical device D

3 '

Sealed source with activity of 400 MBq or less in a fixed gauge 0 I

4 Sealed source in a blood irradiator D

5 Sealed source in a bone densitometer D

6 Sealed source that:( a) is in storage and awaiting disposal; and (b) has a nuclide with a maximum activity of not more than 109 times the amount mentioned in column 4 of Part 2 of D Schedule 2 for that kind of nuclide

7 Unsealed source, or sources, in a laboratory or premises, having nuclides amount mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide D

8 Unsealed source, or sources, in a laboratory or premises, having nuclides such that when the maximum activity of each nuclide in the source, or sources, is divided by the amount 0 mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide, the total of the results for all nuclides in the source, or sources, is not more than 100

9 Mammographic x-ray unit D

10 Conventional dental x-ray unit D

11 X-ray unit used for bone densitometry D

l2 X-ray unit used for veterinary radiography D

H Fully enclosed x-ray analysis unit LJ

i q. Baggage inspection x-ray unit u 15 Mobile or portable medical x-ray unit D

ktC LA-FORM-240( v8.1 October 20.13 of 21


16 Magnetic field non-destructive testing device D

1 17 Induction heater or induction furnace D

18 Industrial radiofrequency heater or welder D

19' Radiofrequency plasma tube D

20 Microwave or radiofrequency diathermy equipment 0

21 Industrial microwave or radiofrequency processing system D

22 Optical source, other than a laser product, emitting ultraviolet radiation, infra-red or visible light. D

23 A laser product with an accessible emission level more than the accessible emission limit of a Class 3R laser product as set out AS/NZS 2211.1:2004 Safety of Laser Products -D

Equipment Classification, Requirements and Users Guide

24 An optical fibre communication system exceeding Hazard Level 3R as defined by AS/NZS 2211.2:2006 Safety of Laser Products -Safety of Optical Fibre Communications Systems D (OFCS)

2.5 Sealed source for calibration purposes of activity of more than 40 MBq u 26 Sealed source in a partially enclosed analytical device D

21 Sealed source of activity of more than 400 MBq in a fixed gauge D

28 Sealed source in a mobile gauge D

29 Sealed source for medical or veterinary diagnostic nuclear medicine use D

30 Unsealed source, or sources, in a laboratory or premises, having nuclides of 1 kind only with a maximum activity of more than 100, but not more than 10 000, times the amount D mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide

3l Unsealed source, or sources, in a laboratory or premises, having nuclides such that when the maximum activity of each nuclide in the source, or sources, is divided by the amount D

mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide, the total of the results for all nuclides in the source, or sources, is more than 100 but not more than 10 000

32 Unsealed sources used for tracer studies u

33 Industrial radiography x-ray unit D

t(i t.A FORM-240C v8.1 October 2013 of 21


2 34 Fixed medical x-ray unit, including a unit used for fluoroscopy, tomography and chiropractic radiography 0

35 Partially enclosed x-ray analysis unit 0

36 Medical therapy simulator 0

37 CT scanner 0

38 Sealed source for industrial radiography 0

39 Sealed source for medical and veterinary radiotherapy 0

40 Sealed source in a bore hole logger 0

41 Sealed source of controlled material not mentioned in another item of Schedule 3C of the ARPANS Regulations 1999 0

42 Unsealed source, or sources, in a laboratory or premises, having nuclides of 1 kind only with a maximum activity of more than 10 000, but not more than 1 000 000, times the 0 amount mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide

43 Unsealed source, or sources, in a laboratory or premises, having nuclides such that when the maximum activity of each nuclide in the source, or sources, is divided by the amount

mentioned in column 4 of Part 2 of Schedule 2 for that kind of nuclide, the total of the results for all nuclides in the source, or sources, is more than 10 000 but not more than 1 000 0 000

3

44 Veterinary or medical radiotherapy unit u

45 Controlled apparatus that produces ionising radiation not mentioned in another item of Schedule 3C of the ARPANS Regulations 1999 D

OTHER Description

D For item not described

hcu LA-FORM-240( v8.l October 2013 of 21

SECTION F- SOURCE DETAILS Section G is an Excel Spreadsheet known as the Source Inventory Workbook (SIW)

C ick here ,or .te.m late

Details of all controlled apparatus and/or controlled material associated with the nuclear installation must be

recorded in a SIW. An explanation of terms and required information appears in the first worksheet. The

completed SIW must be submitted in electronic form either on CD-ROM or to [email protected].

Note: A copy of any sealed source certificate or special form certificate should be provided.

SECTION G - MATTERS TO BE TAKEN INTO ACCOUNT BY THE CEO 3

International Best Practice in Radiation Protection and Nuclear Safety

Describe how international best practice in radiation protection and nuclear safety will be

considered with respect to the facility.

In designing the IWS, ANSTO has adopted relevant safety requirements and guidelines,

particularly the IAEA's Safety Requirements for Site Evaluation for Nuclear Installation (IAEA NS-R-

3), IAEA's Safety Guide for Storage of Radioactive Waste ( WS-G-6.1, Vienna 2006) and IAEA Safety

Requirement for Safe Transport of Radioactive Material (TS-R-1, Vienna 2009).

The waste items stored in the facility have the following characteristics that ensure compliance

with the international best practice for radiation protection and nuclear safety:

•The reprocessing waste is immobilised in vitrified form (i.e. CSD-U) which are then placed in a

massively shielded TN 81 container including the high density resin filled in the aluminium

profiles. Also, the closure system (primary and secondary lids) of the TN 81 container provides the

confinement of the vitrified waste;

•The technological waste is immobilised in a fibre-concrete mixture which are then placed inside

an IP-2 certified ISO container (DV78);and

•There is no nuclear safety design issues with the Facility because the wastes are in vitrified or

cemented form which do not use or involve the production of any fissionable material. There is no

criticality issues associated with the amounts of fissionable material present in the vitrified wastes

or technological wastes.

ANSTO is committed to protecting the environment, and this is demonstrated through its

certification to the international environmental management system standard, ISO 14001.

The IWS is designed to meet the relevant standards for buildings containing nuclear materials and

high levels of radioactivity and in line with relevant ARPANSA Safety Guides. It is noted that

radiation shielding will be achieved by the dual transport/storage containers and not by any

specific building design features.

Information asked for by the CEO

Confirm that all information asked for by the CEO has been provided.

This application is prepared in accordance with the requirements for a Nuclear Installation

licence application under the AR PANS Act and Regulation.

3 Under regulation 42 of the Australian Radiation Protection and Nuclear Safety Regulations 1999, the CEO will also take

into account the content of any submissions made by members of the public about the application, pursuant to a notice

issued under regulation 40.

The following additional documents are included in this licence application package to provide

the information asked by the CEO of ARPANSA:

(a) IWS Contingency Plan, Document No. IWS-0-LA-WCP.

(b) IWS Radioactive Inventory, Document No. IWS-0-LA-INV.

(c) IWS Summary Safety Case, Document No. IWS-0-LA-SC.

(d) IWS Licence Application Summary, Document No. IWS-0-LA-SUM.

Undue Risk

Provide information to show that there is no undue risk from radiation associated with the

facility.

There is no undue risk for the facility . This is detailed in the attached Safety Assessment Report

(ANSTO/T/TN/2012-03, rev 3), Waste Management Plan (IWS-O-LA-04) and Radiation Protection Plan (IWS

O-LA-03) .

Net Benefit

Provide information that demonstrates a net benefit from the proposed conduct.

The net benefit of the conduct is to meet the Australia's international obligation to take receipt of

the ILW generated from the reprocessing of HIFAR used fuel assemblies in France and the UK.

Australia is obliged by international contracts and agreements to accept the reprocessed waste

from HIFAR used fuel assemblies. An exception to this is the used fuel assemblies of US origin

returned to the US. Radioactive waste from future reprocessing of US origin spent fuel returned

to the US will remain in the US as part of the US Foreign Research Reactor Spent Nuclear Fuel

(FRRSNF) acceptance program. The benefit to the Australian community has been in the safe

operation of the HIFAR reactor for approximately 49 years, producing radio-isotopes for industry,

radiopharmaceuticals for diagnostic and therapeutic uses, irradiation of high quality silicon ingots

for the electronics industry, materials research, scientific research in relation to neutron beam

work etc.

Whilst ultimately it is the intention for the returned wastes to be stored in a National Facility

(NRWMF), the waste can be safely stored at ANSTO's Lucas Heights campus until the NRWMF

becomes operational. ANSTO's robust safety systems will mitigate all risks to ensure the safety of

its staff, the community and the environment is maintained during the interim storage period at

Lucas Heights.

A LARA

Provide information in relation to the proposed conduct to show that the magnitude of

individual doses, the number of people exposed, and the likelihood that exposure will happen,

are as low as reasonably achievable, having regard to economic and social factors.

Refer to the attached IWS Safety Assessment Report (ANSTO/T/TN/2012-03, rev 3) and the IWS

Radiation Protection Plan (IWS-O-LA-03).

Capacity to Comply

Provide information to show that the applicant has the capacity to comply with the Regulations

and any licence conditions that may be imposed.

The Australian Nuclear Science and Technology Organisation (ANSTO) is Australia's national

nuclear organisation. Its functions and activities are set down by the ANSTO Act and Regulation.

ANSTO is a Commonwealth agency with its own Board. ANSTO's responsible Minister is the

Minister for Industry.

ANSTO produces 85 per cent of Australia's nuclear medicine and undertakes research in areas of

radioactive waste processing and conditioning as well as the following activities:

(a) The application, manufacture and supply of radiopharmaceuticals;

(b) Irradiation services including radioactivity and dosimetry standardisation;

(c) Radiation protection and work, health and safety;

(d) Environmental monitoring and dosimetry services;

(e) The design, construction, installation and testing of equipment and facilities to meet rigorous

regulatory standards;

(f) Risk, reliability and safety management; and

(g) The management of radioactive wastes.

ANSTO is thus well equipped to manage the returned ILW on an interim basis and has safely

managed and stored radioactive waste (including ILW) at its LHSTC site for more than 50 years.

During the operation of the facility, the IWS will be managed by ANSTO's Waste Operations

section who conduct waste management operations under the existing ARPANSA Licence (F0260)

and are experienced in these operations. ANSTO has adequate funding from the Federal

Government to oversee the return of the ILW from France, its interim storage at LHSTC and future

relocation to the NRWMF.

Authorised Signatory

Confirm that the application has been signed by an office holder of the applicant or a person

authorised by an office holder of the applicant.

CHECKLIST

ITEM Check N/A

1. Completed and signed Section A - Applicant information ~ D 2. Instrument of authorisation for authorised person ~ D 3. Organisational chart showing nominee ~ D 4. Completed Section B - Kind of facility & type of authorisation ~ D 5. Completed Section C - Facility Details ~ D 6. Documents to support Section C ~ D 7. Completed Section D - Plans and Arrangements ~ D 8. Documents to support Section D ~ D 9. Completed Section E -Associated Sources D ~ 10. Documents to support Section E D ~ 11. Completed Section F - SIW (on CD-ROM or email attachment) D ~ 12. A copy of any Sealed Source or Special Form Certificates D ~ 13. Completed Section G - Matters to be considered by the CEO ~ D 14. Documents to support Section G ~ D 15. CD-ROM of entire application including Section G (SIW) and all supporting

~ D documentation

16. CD-ROM of application suitable for public review

NOTE: Must include alternative format of all document (besides pd/) to satisfy ~ D Australian Government Web Accessibilitv_ guidelines

17. The appropriate application fee [:gJ D

SUBMITTING THE APPLICATION This application form, all accompanying documentation and application fee should be sent to:

CEO of ARPANSA

PO Box 655

MIRANDA NSW 1490

OR

licenceadmin @arpansa.gov.au

Note: If the email option is chosen, prior arrangements must be made for payment of the application fee either by cheque

or electronic funds transfer before the application can be accepted. Arrangements should also be made for delivery of CDs.