Leaflet GALLIAPHARM 1.85 GBq radionuclide generator

Product code: W71594001 Quantity: 1

Indicated for: diagnostic imaging

Route of administration: intravenous

Substance: germanium (68Ge) chloride / gallium (68Ga) chloride (contrast agent)

ATC: V09X (Various | Other diagnostic radiopharmaceuticals)

Precautions:
Anaphylaxis
Anaphylaxis

Risk of severe allergic reaction. Seek urgent medical help if serious symptoms occur.

Additional monitoring
Additional monitoring

This medicine is subject to additional monitoring.

Germanium (68Ge) chloride - gallium (68Ga) chloride refers to a radiopharmaceutical generator used in nuclear medicine to produce radioactive gallium solution. This solution is not usually injected directly into the patient; it is used in authorised facilities to radiolabel diagnostic medicines for PET imaging.

Its main role is to prepare imaging agents that may help doctors visualise certain tumours, inflammation or biological processes, depending on the gallium-labelled medicine. Gallium (68Ga) has a short half-life, so its radioactivity falls quickly. The benefit for the patient depends on the final radiopharmaceutical and on the clinical question being investigated.

When needed, the patient receives the prepared radiopharmaceutical by intravenous injection before the PET scan. Nuclear medicine staff check identity, indication, radioactive dose and product quality before administration. Tell the doctor if you are pregnant, think you may be pregnant or are breastfeeding, because radiation exposure must be justified and adjusted to the situation.

Side effects are mainly related to the final labelled medicine rather than to the generator itself. Rarely, injection-site pain, allergic reactions or temporary discomfort may occur. After the scan, you may be advised to drink fluids and urinate often to help clear radioactivity. Follow any local instructions about close contact with pregnant women or small children after imaging.

General data about GALLIAPHARM 1.85 GBq

  • Substance: germanium (68Ge) chloride / gallium (68Ga) chloride
  • Product code: W71594001
  • Concentration: 1.85GBq
  • Pharmaceutical form: radionuclide generator
  • Quantity: 1
  • Product type: Generic medicine
  • Prescription status: S - Medicines dispensed with a restricted medical prescription, reserved for use in certain specialized fields.

Marketing authorisation

  • Manufacturer: ECKERT&ZIEGLER RADIOPHARMA GMBH - GERMANIA
  • Holder: ECKERT&ZIEGLER RADIOPHARMA GMBH - GERMANIA
  • Number: 1836/2024/03
  • Shelf life: Generator de radionuclizi -18 months de la data calibrarii;data calibrarii/expirarii-vezi eticheta

Concentrations available for germanium (68Ge) chloride / gallium (68Ga) chloride

  • 0.74-1.85GBq
  • 1.85GBq

Contents of the package leaflet for the medicine GALLIAPHARM 1.85 GBq radionuclide generator

1. NAME OF THE MEDICINAL PRODUCT

GalliaPharm 1.11 GBq radionuclide generator

GalliaPharm 1.48 GBq radionuclide generator

GalliaPharm 1.85 GBq radionuclide generator

GalliaPharm 2.22 GBq radionuclide generator

GalliaPharm 2.59 GBq radionuclide generator

GalliaPharm 2.96 GBq radionuclide generator

GalliaPharm 3.33 GBq radionuclide generator

GalliaPharm 3.70 GBq radionuclide generator

2. QUALITATIVE AND QUANTITATIVE COMPOSITION

The radionuclide generator contains germanium (68Ge) as mother nuclide which decays to the daughternuclide gallium (68Ga). The germanium (68Ge) used for the production of the (68Ge/68Ga) generator isno carrier added. The total radioactivity due to germanium (68Ge) and gamma-ray-emitting impuritiesin the eluate is not more than 0.001 %.

The GalliaPharm 1.11 - 3.70 GBq radionuclide generator is a system for the elution of sterile gallium(68Ga) chloride solution for radiolabelling in accordance with Ph. Eur. 2464. This solution is elutedfrom a column on which the mother nuclide germanium (68Ge), parent of gallium (68Ga), is fixed. Thesystem is shielded. Physical characteristics of both mother and daughter nuclides are summarised intable 1.

Table 1: Physical characteristics of germanium (68Ge) and gallium (68Ga)68Ge 68Ga

Half-life 270.95 days 67.71 minutes

Type of physical decay Electron capture Positron emission

X-rays 9.225 keV (13.1 %) 8.616 keV (1.37 %)9.252 keV (25.7 %) 8.639 keV (2.69 %)10.26 keV (1.64 %) 9.57 keV (0.55 %)10.264 keV (3.2 %)10.366 keV (0.03 %)

Gamma-rays 511 keV (178.28 %)578.55 keV (0.03 %)805.83 keV (0.09 %)1,077.34 keV (3.22 %)1,260.97 keV (0.09 %)1,883.16 keV (0.14 %)

Beta+ Energy max. Energy352.60 keV 821.71 keV (1.20 %)836.00 keV 1,899.01 keV(87.94 %)

Data derived from nudat (www.nndc.bnl.gov)5 ml of the eluate from the radionuclide generator with highest strength (3.70 GBq) contains apotential maximum of 3.70 GBq of 68Ga and 0.000037 GBq (37 kBq) of 68Ge (0.001 % breakthroughin the eluate). This corresponds to 2.4 ng of gallium and 0.14 ng of germanium.

The quantity of gallium (68Ga) chloride solution for radiolabelling Ph.Eur. that may be eluted from theradionuclide generator is dependent on the quantity of germanium (68Ge) present on the date/time ofelution, the volume of eluent used (typically 5 ml), and the lapsed time since the previous elution. Ifmother and daughter nuclides are in equilibrium, more than 60 % of the present gallium (68Ga) activitycan be eluted.

Table 2 summarises the activity on the radionuclide generator, the minimum activities obtained byelution at the start of the shelf-life and at the end of the shelf-life as well as the potential maxima of68Ga and 68Ge in the eluate.

Table 2: Activity on the radionuclide generator and activity obtained by elution

Strength, Activity Activity Eluted Potential Potential Eluted

GBq inside the inside the activity at maximum maximum activity atradionuclide radionuclide the start amount amount of the end ofgenerator at generator at of shelf- of 68Ga in 68Ge in shelf-life**,the start of the end of life**, 5 ml 5 ml GBqshelf-life*, shelf-life*, GBq eluate, eluate,

GBq GBq GBq/ng kBq/ng1.11 1.11 0.27 NLT 0.67 1.11/0.73 11.1/0.04 NLT 0.161.48 1.48 0.36 NLT 0.89 1.48/0.98 14.8/0.06 NLT 0.221.85 1.85 0.46 NLT 1.11 1.85/1.22 18.5/0.07 NLT 0.272.22 2.22 0.55 NLT 1.33 2.22/1.47 22.2/0.08 NLT 0.332.59 2.59 0.64 NLT 1.55 2.59/1.71 25.9/0.10 NLT 0.382.96 2.96 0.73 NLT 1.78 2.96/1.96 29.6/0.11 NLT 0.443.33 3.33 0.82 NLT 2.00 3.33/2.20 33.3/0.13 NLT 0.493.70 3.70 0.91 NLT 2.22 3.70/2.45 37.0/0.14 NLT 0.55

NLT = not less than

* The actual activity inside the radionuclide generator may deviate by ± 10 % from the nominalstrength

** In equilibrium

More detailed explanations and examples for elutable activities at various time points are given insection 12.

For the full list of excipients, see section 6.1.

3. PHARMACEUTICAL FORM

Radionuclide generator.

The radionuclide generator is presented as an unstained stainless-steel case with two handles and aninlet and an outlet port.

The radionuclide generator provides after elution a sterile gallium (68Ga) chloride solution forradiolabelling. The solution is clear and colourless.

4. CLINICAL PARTICULARS

4.1 Therapeutic indications

This radionuclide generator is not intended for direct use in patients.

The sterile eluate (gallium (68Ga) chloride solution) from the radionuclide generator GalliaPharm isindicated for in vitro radiolabelling of various kits for radiopharmaceutical preparation developed andapproved for radiolabelling with such eluate, to be used for positron emission tomography (PET)imaging.

4.2 Posology and method of administration

This medicinal product is for use in designated nuclear medicine facilities only and should only behandled by specialists experienced with in vitro radiolabelling.

Posology

The quantity of the eluate gallium (68Ga) chloride solution required for radiolabelling and the quantityof 68Ga-labelled radiopharmaceutical that is subsequently administered will depend on the kit that is tobe radiolabelled and its intended use. Refer to the Summary of Product Characteristics/package leafletof the particular kit for radiopharmaceutical preparation to be radiolabelled.

Paediatric population

Please refer to the Summary of Product Characteristics/package leaflet of the kit forradiopharmaceutical preparation to be radiolabelled with 68Ga for more information concerning itspaediatric use.

Method of administration

The gallium (68Ga) chloride solution is not intended for direct use in patients but is used for in vitroradiolabelling of various kits for radiopharmaceutical preparation. The route of administration of the68Ga-labelled radiopharmaceutical is defined in the Summary of Product Characteristics/packageleaflet of the respective kit for radiopharmaceutical preparation and should be adhered to.

For instructions on extemporary preparation of the medicinal product before administration, seesection 12.

4.3 Contraindications

Gallium (68Ga) chloride solution should not be administered directly to the patient.

The use of 68Ga-labelled medicinal products is contraindicated in case of hypersensitivity to the activesubstance or to any of the excipients listed in section 6.1.

For information on contraindications to particular 68Ga-labelled radiopharmaceuticals prepared byradiolabelling with gallium (68Ga) chloride solution, refer to the Summary of Product

Characteristics/package leaflet of the particular medicinal product to be radiolabelled.

4.4 Special warnings and precautions for use

Gallium (68Ga) chloride solution for radiolabelling is not to be administered directly to the patient butis used for in vitro radiolabelling of various kits for radiopharmaceutical preparation.

Unintended direct administration of gallium (68Ga) chloride solution may lead to increased radiationexposure to patients (see sections 4.9, pct. 5.2, and 11). Accidental administration of gallium (68Ga)chloride solution for radiolabelling containing 0.1 mol/l hydrochloric acid may also cause local venousirritation and, in case of paravenous injection, tissue necrosis. The catheter or affected area should beirrigated with 9 mg/ml (0.9 %) sodium chloride solution for injection.

Safe handling of GalliaPharm and its eluate in accordance with the instructions in this documentshould be permanently ensured to protect patients and healthcare professionals from unintentionalexcess radiation exposure (see sections 6 and 12).

68Ge breakthrough can increase in the eluate above 0.001 % if the radionuclide generator is not elutedfor several days (see section 12). All instructions provided in section 12 should be strictly followed toavoid the risk of excess exposure to 68Ge.

Individual benefit/risk justification

For each patient, the radiation exposure must be justifiable by the likely benefit.

The radioactivity administered should in every case be as low as reasonably achievable to obtain therequired information.

General warnings

For information concerning special warnings and special precautions for use of 68Ga-labelledradiopharmaceuticals refer to the Summary of Product Characteristics/package leaflet of the kit forradiopharmaceutical preparation to be radiolabelled.

Precautions with respect to environmental hazard are included in section 6.6.

4.5 Interaction with other medicinal products and other forms of interaction

No interaction studies of the gallium (68Ga) chloride solution for radiolabelling with other medicinalproducts have been performed, because it is used for in vitro radiolabelling of medicinal products.

For information concerning interactions associated with the use of 68Ga-labelled radiopharmaceuticals,refer to the Summary of Product Characteristics/package leaflet of the kit for radiopharmaceuticalpreparation to be radiolabelled.

4.6 Fertility, pregnancy and lactation

Women of childbearing potential

When an administration of radiopharmaceuticals to a woman of childbearing potential is intended, it isimportant to determine whether or not she is pregnant. Any woman who has missed a period should beassumed to be pregnant until proven otherwise. If in doubt about her potential pregnancy (if thewoman has missed a period, if the period is very irregular etc.), alternative techniques not usingionising radiation (if there are any) should be offered to the patient.

Pregnancy

Radionuclide procedures carried out on pregnant women also involve radiation dose to the foetus.

Only essential investigations should therefore be carried out during pregnancy, when the likely benefitfar exceeds the risk incurred by the mother and the foetus.

Breast-feeding

Before administering a radiopharmaceutical to a mother who is breast-feeding, consideration shouldbe given to whether the investigation could be reasonably delayed until the mother has ceased breast-feeding. If the administration is considered necessary, breast-feeding should be interrupted, and theexpressed feeds discarded.

Further information concerning the use of a 68Ga-labelled radiopharmaceutical in pregnancy andbreast-feeding is specified in the Summary of Product Characteristics/package leaflet of the kit forradiopharmaceutical preparation to be radiolabelled.

Fertility

Further information concerning the use of a 68Ga-labelled radiopharmaceutical concerning fertility isspecified in the Summary of Product Characteristics/package leaflet of the kit for radiopharmaceuticalpreparation to be radiolabelled.

4.7 Effects on ability to drive and use machines

Effects on ability to drive and use machines following administration of 68Ga-labelledradiopharmaceutical will be specified in the Summary of Product Characteristics/package leaflet of thekit for radiopharmaceutical preparation to be radiolabelled.

4.8 Undesirable effects

Possible adverse reactions following the use of a 68Ga-labelled radiopharmaceutical will be dependenton the specific kit for radiopharmaceutical preparation being used. Such information will be suppliedin the Summary of Product Characteristics/package leaflet of the kit for radiopharmaceuticalpreparation to be radiolabelled.

Exposure to ionising radiation is linked with cancer induction and a potential for development ofhereditary defects.

Reporting of suspected adverse reactions

Reporting suspected adverse reactions after authorisation of the medicinal product is important. Itallows continued monitoring of the benefit/risk balance of the medicinal product. Healthcareprofessionals are asked to report any suspected adverse reactions via the national reporting systemlisted in Appendix V.

4.9 Overdose

Excess radiation exposure may occur if higher than recommended activity of a 68Ga-labelledradiopharmaceutical is administered to a patient. For further information refer to the Summary of

Product Characteristics/package leaflet of the kit for radiopharmaceutical preparation to beradiolabelled.

No toxic effects are to be expected from the free 68Ga after an inadvertent administration of the eluate.

The administered free 68Ga decays almost completely to stable 68Zn within a short time (97 % aredecayed in 6 hours). During this time, 68Ga is mainly concentrated in the blood/plasma (bound totransferrin) and in the urine. The patient should be hydrated to increase the excretion of the 68Ga.

Forced diuresis as well as frequent bladder voiding are recommended.

Human radiation dose in case of an inadvertent administration of the eluate should be estimated usingthe information given in section 11.

5. PHARMACOLOGICAL PROPERTIES

5.1 Pharmacodynamic properties

Pharmacotherapeutic group: Diagnostic radiopharmaceuticals; other diagnostic radiopharmaceuticals,

ATC code: V09X.

The pharmacodynamic properties of 68Ga-labelled radiopharmaceutical prepared by radiolabellingwith the radionuclide generator eluate prior to administration will be dependent on the nature of thecarrier molecule to be labelled. Refer to the Summary of Product Characteristics/package leaflet of thekit for radiopharmaceutical preparation to be radiolabelled.

Paediatric population

The European Medicines Agency has waived the obligation to submit the results of studies with

GalliaPharm 1.11 - 3.70 GBq radionuclide generator in all subsets of the paediatric population as it isa radiolabelling agent. See section 4.2 for information on paediatric use.

5.2 Pharmacokinetic properties

Gallium (68Ga) chloride solution is not intended for direct use in patients but is used for in vitroradiolabelling of various kits for radiopharmaceutical preparation. Therefore, the pharmacokineticproperties of 68Ga-labelled radiopharmaceuticals will depend on the nature of carrier molecules to beradiolabelled.

The absorption, distribution, and excretion of free 68Ga following direct injection of gallium (68Ga)chloride solution were investigated in rats. The rat study has shown that following direct intravenousadministration of gallium (68Ga) chloride, 68Ga is slowly cleared from the blood with a biological half-life of 188 h in male and 254 h in female rats. This is because free Ga3+ likely behaves in a similar wayas Fe3+. However, as the biological half-life of 68Ga is much longer than its physical half-life(67.71 min), at 188 h or 254 h almost all 68Ga anyway decays to inactive 68Zn. Already in 6 h approx.97 % of the initial 68Ga disappear via decay to 68Zn.

In rats, 68Ga was excreted predominantly into the urine, with some retention in the liver and kidneys.

The organs with the highest 68Ga activity, other than blood, plasma, and urine, were liver, lungs,spleen, and bones. In female rats, the 68Ga activity in female genital organs, i.e., uterus and ovaries,was comparable to that seen in the lungs. 68Ga activity in the testes was very low.

Extrapolating from the rat data, the estimated sex-averaged effective dose resulting from aninadvertently intravenously injected gallium (68Ga) chloride would be 0.0216 mSv/MBq for an adult(see section 11 for more details).

The activity resulting from 68Ge breakthrough in the rat study was extremely low and is not of clinicalimportance.

5.3 Preclinical safety data

The toxicological properties of 68Ga-labelled radiopharmaceuticals prepared by in vitro radiolabellingwith gallium (68Ga) chloride solution will depend on the nature of the kit for radiopharmaceuticalpreparation to be radiolabelled.

6. PHARMACEUTICAL PARTICULARS

6.1 List of excipients

Column matrix

Titanium dioxide

Solution for elution

Sterile ultrapure 0.1 mol/l hydrochloric acid

6.2 Incompatibilities

Radiolabelling of carrier molecules with gallium (68Ga) chloride is very sensitive to the presence oftrace metal impurities.

It is important that all glassware, syringe needles etc., used for the preparation of the radiolabelledmedicinal product are thoroughly cleaned to ensure freedom from such trace metal impurities. Onlysyringe needles (for example, non-metallic) with proven resistance to dilute acids should be used tominimise trace metal impurity levels.

It is recommended not to use uncoated stoppers for the elution vial as they may contain considerableamounts of zinc that is extracted by the acidic eluate.

6.3 Shelf life

Radionuclide generator18 months from calibration date.

The calibration date and the expiry date are stated on the label.

Gallium (68Ga) chloride solution for radiolabelling

After elution, immediately use the eluate.

Sterile ultrapure hydrochloric acid solution for elution2 years.

6.4 Special precautions for storage

Warm temperatures substantially exceeding 25 °C can reversibly reduce the yield of 68Ga in the eluateto below 60 %. Therefore, to obtain optimal elution yield (> 60 %), the radionuclide generator shouldbe operated at temperatures not exceeding 25 °C. If the radionuclide generator is routinely stored athigher temperatures, make sure to equilibrate it at < 25 °C for several hours before elution. Elutions attemperatures above 25 °C are nevertheless possible and will not harm the radionuclide generator orhave an impact on the quality of the eluate except for the possibly reduced yield of 68Ga.

Storage of radiopharmaceuticals should be in accordance with national regulations on radioactivematerials.

6.5 Nature and contents of container

The glass column consists of a borosilicate glass tube (type I) and Polyetheretherketone (PEEK) endplugs which are attached to PEEK inlet and outlet lines via HPLC-style fingertight fittings. These linesare connected to two ports that pass through the outer case of the radionuclide generator.

The column is contained within the lead shield assembly. The shield assembly is secured in astainless-steel outer case with two handles.

Accessories supplied with the radionuclide generator (minimum amounts):

1. 1 x PP - container with the eluent, 250 ml sterile ultrapure 0.1 mol/l hydrochloric acid(including a separate hanger for PP-bottles; PP = Polypropylene)2. 1 x Vented spike (ABS = Acrylonitrile Butadiene Styrene/PE = Polyethylene)3. 2 x Adapter 1/16' to male LUER (PEEK)4. 2 x Tubing 60 cm (PEEK)5. 1 x Tubing 40 cm (PEEK)6. 1 x Tubing 20 cm (PEEK)7. 3 x Fingertight fitting 1/16' 10-32 (PEEK)8. 1 x Fingertight fitting 1/16' M6 (PEEK)9. 1 x Stopcock manifold (TPX = Polymethylpentene/HDPE = High Density

Polyethylene)10. 1 x Male LUER union (PP)

Pack sizes:

The radionuclide generators are supplied with the following 68Ge activity amounts at calibration date:1.11 GBq, 1.48 GBq, 1.85 GBq, 2.22 GBq, 2.59 GBq, 2.96 GBq, 3.33 GBq, and 3.70 GBq.

Sectional view of the radionuclide generator

Handle

Stainless steel case

Inlet port Lead shielding

Fluid lines

Outlet port

Front plate withinlet and outletports

TiO2 column

Front view of the radionuclide generator Handles

Inlet port

Stainless-steel case

Outlet port

Front plate withinlet and outletports

Size: 230 mm x 132 mm x 133 mm (H x W x D)

Weight: approx. 14 kg

6.6 Special precautions for disposal and other handling

General warnings

Radiopharmaceuticals should be received, used, and administered only by authorised persons indesignated clinical settings. Their receipt, storage, use, transfer and disposal are subject to theregulations and/or appropriate licenses of the competent official organisation.

Radiopharmaceuticals should be prepared in a manner which satisfies both radiation safety andpharmaceutical quality requirements. Appropriate aseptic precautions should be taken.

The radionuclide generator must not be disassembled for any reason as this may damage the internalcomponents and possibly lead to a leak of radioactive material. Also, disassembly of the stainless-steel case will expose the lead shielding to the operator.

Administration procedures should be carried out in a way to minimise risk of contamination of themedicinal product and irradiation of the operators. Adequate shielding is mandatory.

The administration of radiopharmaceuticals creates risks for other persons from external radiation orcontamination from spill of urine, vomiting, etc. Radiation protection precautions in accordance withnational regulations must therefore be taken.

The residual activity of the radionuclide generator must be estimated before disposal.

Any unused gallium (68Ga) chloride solution for radiolabelling or radiolabelled medicinal product orwaste material should be disposed of in accordance with local requirements.

7. MARKETING AUTHORISATION HOLDER

Eckert & Ziegler Radiopharma GmbH

Robert-Rössle-Str. 1013125 Berlin

Germany

8. MARKETING AUTHORISATION NUMBER(S)

EU/1/24/1836/001 - GalliaPharm 1.11 GBq radionuclide generator

EU/1/24/1836/002 - GalliaPharm 1.48 GBq radionuclide generator

EU/1/24/1836/003 - GalliaPharm 1.85 GBq radionuclide generator

EU/1/24/1836/004 - GalliaPharm 2.22 GBq radionuclide generator

EU/1/24/1836/005 - GalliaPharm 2.59 GBq radionuclide generator

EU/1/24/1836/006 - GalliaPharm 2.96 GBq radionuclide generator

EU/1/24/1836/007 - GalliaPharm 3.33 GBq radionuclide generator

EU/1/24/1836/008 - GalliaPharm 3.70 GBq radionuclide generator

9. DATE OF FIRST AUTHORISATION/RENEWAL OF THE AUTHORISATION

Date of first authorisation: 01 August 2024

11. DOSIMETRY

The radiation dose received by the various organs following intravenous administration of a 68Ga-radiolabelled medicinal product is dependent on the specific kit for radiopharmaceutical preparationbeing radiolabelled. Information on radiation dosimetry of each different 68Ga-labelledradiopharmaceutical following its administration will be available in the Summary of Product

Characteristics of the particular kit for radiopharmaceutical preparation.

The dosimetry tables 3 and 4 below are presented in order to support the assessment of thecontribution by unbound 68Ga to the radiation dose following the administration of 68Ga-labelledradiopharmaceutical or of the radiation dose resulting from an inadvertent intravenous injection ofgallium (68Ga) chloride solution.

The dosimetry estimates were based on a rat distribution study. Time points for measurements were5 minutes, 30 minutes, 60 minutes, 120 minutes, and 180 minutes.

The effective radiation dose of 68Ga for an adult is 0.0216 mSv/MBq, resulting in an approximateeffective radiation dose of 5.6 mSv from an accidental intravenously injected activity of 259 MBq.

Table 3: Absorbed dose per unit activity administered - inadvertent administration of the eluate

- gallium (68Ga) chloride - in women

Absorbed dose per administered unit of activity (mGy/MBq)

Organ Adult1 15 years2 10 years2 5 years2 1 year2 Newborn2(60 kg) (50 kg) (30 kg) (17 kg) (10 kg) (5 kg)

Adipose/residual tissue 0.0121 0.0199 0.0327 0.0531 0.1050 0.2680

Adrenals 0.0398 0.0304 0.0440 0.0618 0.0959 0.1020

Bone marrow 0.0299 0.0202 0.0331 0.0606 0.1540 0.6050

Bone surface 0.0169 ND ND ND ND ND

Brain 0.0081 0.0048 0.0061 0.0081 0.0126 0.0282

Colon wall 0.0210 0.0224 0.0373 0.0609 0.1170 0.2930

Heart wall 0.0838 0.0263 0.0407 0.0639 0.1150 0.2280

Kidneys 0.0424 0.0333 0.0474 0.0712 0.1280 0.3250

Liver 0.0640 0.0598 0.0906 0.1360 0.2630 0.6080

Lungs 0.0552 0.0497 0.0708 0.1090 0.2160 0.5840

Muscle 0.0131 0.0131 0.0248 0.0698 0.1370 0.1950

Osteogenic cells 0.05672 0.0558 0.0869 0.1420 0.3310 1.0100

Ovaries 0.0372 0.0332 0.0944 0.1650 0.3720 0.7550

Pancreas 0.0309 0.0276 0.0533 0.0704 0.1490 0.4730

Salivary glands 0.0194 ND ND ND ND ND

Skin 0.0115 0.0115 0.0189 0.0311 0.0612 0.1570

Small intestine wall 0.0256 0.0273 0.0459 0.0749 0.1460 0.3630

Spleen 0.0407 0.0263 0.0403 0.0642 0.1180 0.3030

Stomach wall 0.0284 0.0188 0.0293 0.0482 0.0939 0.2540

Thymus 0.0129 0.0094 0.0115 0.0157 0.0261 0.0518

Thyroid 0.0265 0.0282 0.0434 0.0923 0.1730 0.2490

Urinary bladder wall4 0.0174 0.0155 0.0251 0.0419 0.0770 0.2000

Uterus/cervix 0.0291 0.0325 0.4560 0.6900 1.2500 0.5360

Effective dose (mSv/MBq) 0.02163

ND = not determined as organ/tissue not available in OLINDA/EXM v1.0.1 calculations made in IDAC-Dose 2.1 v1.01 software.2 calculations made in OLINDA v1.0 software.3 sex-averaged dose derived according to ICRP Publication 103.4 Due to the methodological limitations of the underlying distribution study in rats, it was not feasible toconsider urinary bladder content as an explicit source region for the dosimetry. Since gallium (68Ga)chloride is excreted predominantly into the urine according to the rat data, the reported effective dose isthus possibly underestimated.

Table 4: Absorbed dose per unit activity administered - inadvertent administration of the eluate

- gallium (68Ga) chloride - in men

Absorbed dose per administered unit of activity (mGy/MBq)

Organ Adult1 15 years2 10 years2 5 years2 1 year2 Newborn2(73 kg) (50 kg) (30 kg) (17 kg) (10 kg) (5 kg)

Adipose/residual tissue 0.0065 0.0128 0.0210 0.0341 0.0672 0.1720

Adrenals 0.0189 0.0200 0.0289 0.0405 0.0628 0.0669

Bone marrow 0.0124 0.0149 0.0244 0.0454 0.1120 0.4180

Bone surface 0.0079 ND ND ND ND ND

Brain 0.0046 0.0034 0.0043 0.0056 0.0088 0.0196

Colon wall 0.0121 0.0162 0.0274 0.0449 0.0865 0.2150

Heart wall 0.0335 0.0195 0.0303 0.0478 0.0858 0.1710

Kidneys 0.0221 0.0239 0.0340 0.0510 0.0915 0.2340

Liver 0.0307 0.0388 0.0588 0.0881 0.1700 0.3940

Lungs 0.0262 0.0327 0.0466 0.0718 0.1420 0.3850

Muscle 0.0072 0.0111 0.0219 0.0658 0.1300 0.1800

Osteogenic cells 0.03082 0.0402 0.0633 0.1050 0.2440 0.7550

Pancreas 0.0167 0.0211 0.0412 0.0540 0.1150 0.3720

Salivary glands 0.0132 ND ND ND ND ND

Skin 0.0073 0.0063 0.0102 0.0166 0.0326 0.0828

Small intestine wall 0.0126 0.0167 0.0282 0.0460 0.0892 0.2220

Spleen 0.0238 0.0259 0.0400 0.0634 0.1170 0.3060

Stomach wall 0.0145 0.0116 0.0179 0.0295 0.0573 0.1570

Testes 0.0098 0.0182 0.1210 0.1410 0.1910 0.2770

Thymus 0.0092 0.0082 0.0093 0.0122 0.0193 0.0384

Thyroid 0.0163 0.0248 0.0383 0.0825 0.1550 0.2200

Urinary bladder wall4 0.0116 0.0095 0.0151 0.0252 0.0458 0.1190

Small intestine wall 0.0126 0.0167 0.0282 0.0460 0.0892 0.2220

Effective dose (mSv/MBq) 0.02163

ND = not determined as organ/tissue not available in OLINDA/EXM v1.0.1 calculations made in IDAC-Dose 2.1 v1.01 software.2 calculations made in OLINDA v1.0 software.3 sex-averaged dose derived according to ICRP Publication 103.4 Due to the methodological limitations of the underlying distribution study in rats, it was not feasible toconsider urinary bladder content as an explicit source region for the dosimetry. Since gallium (68Ga)chloride is excreted predominantly into the urine according to the rat data, the reported effective dose isthus possibly underestimated.

External radiation exposure

The average surface or contact radiation for the radionuclide generator is less than 0.14 µSv/h per

MBq of 68Ge, but local hot spots of higher radiation can occur. Nevertheless, a 3.70 GBq radionuclidegenerator will reach an overall average surface dose rate of approx. 518 µSv/h. It is generallyrecommended that the radionuclide generator is stored within auxiliary shielding to minimise dose tooperating personnel.

12. INSTRUCTIONS FOR THE PREPARATION OF RADIO PHARMACEUTICAL MEDICINAL PRODUCTS

Elution of the radionuclide generator must be performed in premises complying with the nationalregulations concerning the safety of use of radioactive products.

The general handling, the attachment of tubing, the exchange of the sterile ultrapure 0.1 mol/lhydrochloric acid container, the elution of the generator and other activities potentially exposing thegenerator to the environment should be undertaken using aseptic techniques in an appropriate cleanenvironment according to current national legislation.

Preparation

Unpacking of the radionuclide generator:

1. Check outer shipping package for shipping damage. If damaged, perform radiation wipe surveyof the damaged area. If counts exceed 40 counts per second per 100 cm2, notify your Radiation

Safety Officer.

2. Cut security seal on top of shipping package. Remove the inner foam support from the shippingpackage. Separate the foam elements carefully.

3. Carefully remove radionuclide generator.

CAUTION: Drop hazard: The radionuclide generator weighs approx. 14 kg. Handle with careto avoid potential injuries. If radionuclide generator is dropped or if shipping damage extendsinto the shipping package, check for leaks and perform a wipe survey of the radionuclidegenerator. Also check for internal damage by slowly tilting the radionuclide generator 90°.

Listen for broken/loose parts.

4. Perform wipe survey of shipping package inserts and radionuclide generator outer surface. Ifwipes exceed 40 counts per second per 100 cm2, notify your Radiation Safety Officer.

5. Check sealed inlet and outlet ports for damage. Do not remove the port plugs before the elutionlines are prepared and ready for installation.

Optimal positioning:

1. When installing the radionuclide generator in its final position, i.e., with a synthesis device orfor manual elutions, it is recommended to keep the outlet line as short as possible as the lengthof this tubing may influence the yield in the receiving/reaction vial. For this reason, theradionuclide generator is supplied with three different lengths of tubing to choose theappropriate length.

2. Local auxiliary shielding is recommended when positioning the radionuclide generator.

Please note: Moving the radionuclide generator after installation in its final position should be avoided.

Assembly of the radionuclide generator:

Accessories supplied with the radionuclide generator (minimum amounts):

1. 1 x PP - container with the eluent, 250 ml sterile ultrapure 0.1 mol/l hydrochloric acid(including a separate hanger for PP-bottles; PP = Polypropylene)2. 1 x Vented spike (ABS = Acrylonitrile Butadiene Styrene/PE = Polyethylene).3. 2 x Adapter 1/16' to male LUER (PEEK)4. 2 x Tubing 60 cm (PEEK)5. 1 x Tubing 40 cm (PEEK)6. 1 x Tubing 20 cm (PEEK)7. 3 x Fingertight fitting 1/16' 10-32 (PEEK)8. 1 x Fingertight fitting 1/16' M6 (PEEK)9. 1 x Stopcock manifold (TPX = Polymethylpentene/HDPE = High Density

Polyethylene)10. 1 x Male LUER union (PP)

Assemble the radionuclide generator in an appropriately clean environment. Aseptic workingtechnique must be maintained during the whole assembly process. Wear gloves during preparation andconnecting of the lines to the radionuclide generator and to the eluent container. This is critical for themaintenance of sterility.

Picture of assembled elution accessories before connection to the radionuclide generator (Theindicated identification numbers of accessories are as presented in the list above. They are also useda ccordingly in the pictures and assembly instructions following below.):

1. Assembling the inlet line:

Please note: the inlet port has a customised thread toavoid misconnection. Only the special fingertightfitting 1/16' M6 will fit into this port. Forassembling the inlet line, connect the vented spike(2) to one end of the stopcock manifold (9) using themale LUER union (10) [I]. On the other end of thestopcock manifold (9) connect the adapter 1/16' tomale LUER (3) [II]. Attach one of the 60 cm long

PEEK tubing (4) with a 1/16' 10-32 fingertightfitting (7) [III]. Put the special 1/16' M6 fingertightfitting (8) on the other end of the line, but do notconnect yet [IV].

2. Assembling the outlet line:

For the outlet line, choose the appropriate length oftubing (20 cm, 40 cm, or 60 cm) based on your localsetting. Use the shortest line possible. Attach thechosen PEEK line (4,5 or 6) to the second adapter1/16' to male LUER (3) using a 1/16' 10-32fingertight fitting (7) [V]. Put the third 1/16” 10-32fingertight fitting (7) on the other end of theprepared outlet line, but do not connect yet [VI].3. Connecting the hydrochloric acid containerto the inlet line:

Hang the PP - container with the 250 ml sterileultrapure 0.1 mol/l hydrochloric acid solution closeto the inlet port above the radionuclide generator.

The valves of the stopcock manifold have a T-typeflow pattern with three openings inside - one in eachdirection of the external prongs. Turn the valves atthe stopcock manifold in the appropriate direction(3-6-9 clock position ┳) so that no liquid can enterthrough the spike [VII]. Remove the lid of thevented spike and push the vented spike into the PP -container connection [VIII].

Now the air must be removed from the stopcockmanifold and the attached inlet line. Be aware, thathydrochloric acid will thereby flow through andmay drip out of the line and the side ports. Beprepared to remove the drops immediately.

To remove the air, start by turning both valves of thestopcock manifold as shown in the picture [IX] (theprongs of both valves should be in the 6-9-12 clockposition ┫). This will fill the inlet line with liquidand push the air out of it. Then turn the upper valveinto the 9-12-3 clock position ┻ and remove the capof the upper side port to remove the air [X].

Afterwards, close the upper side port again with thecap. Now turn the upper valve back into the 6-9-12clock position ┫. Turn the lower valve into the 9-12-3 clock position ┻ and remove the cap of thelower side port to remove the air [XI]. Close thelower side port again with the cap. Finally, place theupper valve into the 3-6-9 clock position ┳ to stopflow of the liquid from the hydrochloric acidcontainer [XII].

4. Connecting the inlet line to the port of theradionuclide generator:

Remove the plug from the inlet port of theradionuclide generator [XIII]. To connect preparedand filled inlet line using the 1/16' M6 fingertightfitting, push the line into the inlet port [XIV] andscrew in the fingertight fitting [XV]. Avoid hardbending or pinching of the line.

5. Connecting the outlet line to the port of theradionuclide generator:

Remove plug from the outlet port of the radionuclidegenerator [XVI]. To connect prepared outlet lineusing the 1/16' 10-32 fingertight fitting, push theline into the outlet port [XVII] and screw in thefingertight fitting [XVIII]. Avoid hard bending orpinching of the line.

The radionuclide generator is now ready for the first elution:

Please note: The radionuclide generator is designed not to drain itself, when no lines are connectedto the inlet and outlet ports, but it is not recommended to leave the ports open at any time.

When the container with the sterile ultrapure 0.1 mol/l hydrochloric acid is connected and the fluidpath is open, the radionuclide generator will be eluted by gravity. Therefore, it is necessary to keepthe inlet and outlet lines as well as the positions of the stopcock valves under control.

First manual elution:

1. Prepare additional necessary materials:

− Personal protective equipment: elutions should be performed while wearing eye and handprotection, and appropriate laboratory cloth.

− Sterile syringe with 10 ml volume (avoid syringes with rubber plunger, preferably use two-piece syringes).

− Shielded receiving vial or vessel with 10 ml or larger volume. Avoid uncoated stoppers asthey may contain considerable amounts of zinc that is extracted by the acidic eluate.

2. Attach the syringe to the upper side port of thestopcock manifold and fill with 10 ml ofsterile ultrapure 0.1 mol/l hydrochloric acidfrom the PP - container by turning the valveinto the shown position, then moving theplunger of the syringe in the indicateddirection while avoiding any air inside thesyringe [XIX].

3. Connect the shielded receiving vessel to the outlet line using the appropriate connector. Thevessel must have sufficient capacity to accept the eluate volume. Avoid using metal syringeneedles for connection.

4. Turn both valves of stopcock manifoldtowards the inlet port of the radionuclidegenerator. Push the 10 ml sterile ultrapure0.1 mol/l hydrochloric acid at a flow rate notgreater than 2 ml/minute [XX]. Eluting at afaster flow rate may reduce the shelf-life ofthe radionuclide generator. Five millilitres ofeluent will fully elute the radionuclidegenerator, but for the first elution it is recommended to use 10 ml. If high resistance isencountered, do not force solution into radionuclide generator. If a peristaltic pump is used forelution, it should be set to a flow rate of not more than 2 ml/minute. The user should also verifythat eluent is flowing without unusual resistance. If high resistance is noticed, discontinue elution.

CAUTION:

Be sure to introduce eluent through the inlet port; do not elute the radionuclide generator inreverse direction.

Elution efficiency (68Ga yield) may be reduced if air is introduced into the radionuclidegenerator column.

5. Collect eluate in shielded receiving vessel and measure solution with a calibrated dose calibratorto determine the yield. If less than 5 ml of eluate have been collected, measurement may notrepresent the total potential yield of radionuclide generator. Please decay correct the measuredactivity to the starting time of the elution. For optimal yield of the radionuclide generator in itsfinal position it is recommended to determine the elution peak by collecting small fractions of0.5 ml.

6. The first eluate should be discarded due to the potential 68Ge breakthrough in this eluate.

It is recommended to test the eluate for 68Ge breakthrough after the first elutions by comparing theactivity level of the 68Ga and the 68Ge. For further details please refer to Ph. Eur. monograph 2464.

Routine elution:

CAUTION:

Free 68Ge ions can accumulate in the column over time. If the radionuclide generator has not beenused for a period of 96 hours or more, the column should be pre-eluted once, at least 7 hours prior toeluting for radiolabelling. If the radiolabelling procedure does not require maximum achievable eluateactivity, the time between the pre-elution and the elution for radiolabelling can be reduced (see alsotable 6 and calculation example below it). The pre-elution should be done using 10 ml of sterileultrapure 0.1 mol/l hydrochloric acid.

1. Repeat the steps of the first elution but use only 5 ml eluent for the routine elution. Theradionuclide generator is designed to elute all of the available 68Ga activity in a volume of 5 ml.

2. The eluate is a clear, sterile, and colourless gallium (68Ga) chloride solution, with a pH between0.5 and 2.0 and a radiochemical purity greater than 95 %. Check the clarity of the eluate beforeuse and discard it if the solution is not clear.

3. It is recommended to test the eluate for 68Ge breakthrough during routine elutions by comparingthe activity level of the 68Ga and the 68Ge. For further details please refer to Ph. Eur. monograph2464.

CAUTION:

If fluid leaks are observed at any time, immediately stop eluting and attempt to contain the leakingfluid.

The radionuclide generator is supplied with 250 ml of sterile ultrapure 0.1 mol/l hydrochloric acid.

This amount is usually sufficient for at least 40 elutions. The radionuclide generator should only beeluted with sterile ultrapure 0.1 mol/l hydrochloric acid supplied by the marketing authorisationholder. Additional containers may be purchased as consumables from the marketing authorisationholder only.

Exchange of sterile ultrapure 0.1 mol/l hydrochloric acid container:

CAUTION:

Aseptic technique is critical for maintenance of sterility and must be used during the exchangeprocedure.

1. When the sterile ultrapure 0.1 mol/l hydrochloric acid is almost consumed, the empty containercan be replaced by a new sterile ultrapure 0.1 mol/l hydrochloric acid container.

CAUTION:

No air should enter the radionuclide generator.

Before disconnecting the empty container, close allvalves at the stopcock manifold and cap the sideports so that no air can enter into the manifold andspike [XXI]. Disconnect the container from thevented spike [XXII]. It is recommended to replacethe vented spike with the new sterile vented spikesupplied with each new sterile ultrapure 0.1 mol/lhydrochloric acid container.

2. Hang the new container with the 250 ml sterile ultrapure 0.1 mol/l hydrochloric acid close to theinlet port above the radionuclide generator.

3. Push the connected vented spike into the container stopper; carefully check for air bubbles andslowly remove all air from the stopcock manifold using the valves. It is not necessary to detachthe attached inlet line from the radionuclide generator or from the stopcock manifold. Enteringof air into the radionuclide generator should be avoided.

4. When stopcock manifold is filled, close valves to stop flow. The radionuclide generator is nowready for elution again.

Radionuclide generator elution yield:

The activity stated on the label of the radionuclide generator is expressed in 68Ge available at thecalibration date (12:00 CET). The available 68Ga activity depends on the 68Ge activity at the time ofelution and the elapsed time since the previous elution.

A radionuclide generator in full equilibrium yields more than 60 % of 68Ga using an elution volume of5 ml sterile ultrapure 0.1 mol/l hydrochloric acid.

The output will decrease with decay of the parent nuclide 68Ge over time. For example, after 9 months'decay (39 weeks), the 68Ge will be reduced by 50 % (see table 5). To calculate the current 68Geactivity, multiply the 68Ge activity at calibration date with the respective decay factor of thecorresponding elapsed time in weeks.

Table 5: Decay Chart for 68Ge

Elapsed Time Decay Factor Elapsed Time Decay Factorin weeks in weeks1 0.98 40 0.492 0.96 41 0.483 0.95 42 0.474 0.93 43 0.465 0.91 44 0.456 0.90 45 0.457 0.88 46 0.448 0.87 47 0.439 0.85 48 0.4210 0.84 49 0.4211 0.82 50 0.4112 0.81 51 0.4013 0.79 52 0.3914 0.78 53 0.3915 0.76 54 0.3816 0.75 55 0.3717 0.74 56 0.3718 0.72 57 0.3619 0.71 58 0.3520 0.70 59 0.3521 0.69 60 0.3422 0.67 61 0.3423 0.66 62 0.3324 0.65 63 0.3225 0.64 64 0.3226 0.63 65 0.3127 0.62 66 0.3128 0.61 67 0.3029 0.59 68 0.3030 0.58 69 0.2931 0.57 70 0.2932 0.56 71 0.2833 0.55 72 0.2834 0.54 73 0.2735 0.53 74 0.2736 0.52 75 0.2637 0.52 76 0.2638 0.51 77 0.2539 0.50 78 0.25

After elution, the 68Ga will be built up by the continuous decay of the parent 68Ge. The radionuclidegenerator requires at least 7 hours to achieve almost full yield after being eluted, but in practice it isalso possible to elute the radionuclide generator earlier, depending on its strength and the activityrequired for radiolabelling. Table 6 shows the build-up factor of 68Ga activity over time, up to410 minutes after an elution.

Table 6: Build-up factors of 68Ga

Elapsed Time Build-Up Elapsed Time Build-Upin minutes Factor in minutes Factor0 0.00 210 0.8810 0.10 220 0.8920 0.19 230 0.9130 0.26 240 0.9140 0.34 250 0.9250 0.40 260 0.9360 0.46 270 0.9470 0.51 280 0.9480 0.56 290 0.9590 0.60 300 0.95100 0.64 310 0.96110 0.68 320 0.96120 0.71 330 0.97130 0.74 340 0.97140 0.76 350 0.97150 0.78 360 0.97160 0.81 370 0.98170 0.82 380 0.98180 0.84 390 0.98190 0.86 400 0.98200 0.87 410 0.98

Calculation examples

A 1.85 GBq radionuclide generator is 12 weeks old. According to table 5, the activity of 68Ge on thecolumn can be calculated as follows:

1.85 GBq × 0.81 = 1.50 GBq

In full equilibrium, the activity of 68Ga on the column is also 1.50 GBq.

The radionuclide generator is eluted and the collected 68Ga activity is 1.05 GBq which corresponds toa yield of 70 %.

The same radionuclide generator is eluted 4 hours later. The 7 hours needed to reach the 68Ge/68Ga-equilibrium have not elapsed yet. The 68Ga activity built up on the column in 4 hours (240 minutes)post-elution can be calculated according to table 6 as follows:

1.50 GBq × 0.91 = 1.37 GBq

With a typical yield of 70 % 68Ga, the collected activity would then be:

1.37 GBq × 0.70 = 1.00 GBq

Note:

The activity of 68Ga in the eluate can be measured to check the quality with regard to identity andcontent. The activity should be measured immediately after elution but may also be measured up to5 half-life periods after elution.

Due to the short half-time of 68Ga (67.71 minutes), the elapsed time between the elution and themeasurement of the activity has to be decay-corrected to determine the actual yield at the elution timewith the decay chart of 68Ga, table 7.

Calculation Example

A new 1.85 GBq radionuclide generator is eluted. The activity of 68Ga measured 10 minutes after theelution was 1.17 GBq.

The yield at the time of the elution can be obtained by dividing the measured activity by thecorresponding decay factor of the elapsed time stated in table 7:1.17 GBq/0.90 = 1.30 GBq

This corresponds to a yield of 68Ga of 70 % at the time of the elution:1.30 GBq/1.85 GBq × 100 % = 70 %

Table 7: Decay chart of 68Ga

Elapsed Time Decay Factor Elapsed Time Decay Factorin minutes in minutes1 0.99 35 0.702 0.98 36 0.693 0.97 37 0.694 0.96 38 0.685 0.95 39 0.676 0.94 40 0.677 0.93 41 0.668 0.92 42 0.659 0.91 43 0.6510 0.90 44 0.6411 0.89 45 0.6312 0.89 46 0.6313 0.88 47 0.6214 0.87 48 0.6115 0.87 49 0.6116 0.85 50 0.6017 0.84 51 0.6018 0.83 52 0.5919 0.82 53 0.5820 0.82 54 0.5821 0.82 55 0.5722 0.80 56 0.5723 0.79 57 0.5624 0.78 58 0.5525 0.78 59 0.5526 0.77 60 0.5427 0.76 61 0.5428 0.75 62 0.5329 0.74 63 0.5330 0.74 64 0.5231 0.73 65 0.5232 0.72 66 0.5133 0.71 67 0.5134 0.71 68 0.50

Quality control

If possible, clarity of the solution, pH and the radioactivity should be checked before radiolabelling.

68Ge breakthrough

A small amount of 68Ge is washed from the radionuclide generator column with each elution. 68Gebreakthrough is expressed as a percentage of total 68Ga activity eluted from the column, corrected fordecay, and does not exceed 0.001 % of the eluted 68Ga activity. 68Ge breakthrough can, however,increase above 0.001 % if the radionuclide generator is not eluted for several days. Therefore, if theradionuclide generator has not been eluted for 96 hours or more, it should be pre-eluted with 10 ml ofsterile ultrapure 0.1 mol/l hydrochloric acid at least 7 hours prior to the intended use (the time betweenthe pre-elution and the elution for radiolabelling can be reduced if the intended radiolabellingprocedure does not require maximum achievable eluate activity). When this instruction is followed,the 68Ge breakthrough should constantly stay below 0.001 % in eluates obtained for radiolabelling. Fortesting the 68Ge breakthrough, the activity levels of 68Ga and 68Ge in the eluate should be compared.

For further details please refer to Ph. Eur. monograph 2464.

Any unused medicinal product or waste material should be disposed of in accordance with localrequirements.

Detailed information on this medicinal product available on the website of the European Medicines

Agency http://www.ema.europa.eu.