This information is intended for use by health professionals

 This medicinal product is subject to additional monitoring. This will allow quick identification of new safety information. Healthcare professionals are asked to report any suspected adverse reactions. See section 4.8 for how to report adverse reactions.

1. Name of the medicinal product

SomaKit TOC 40 micrograms kit for radiopharmaceutical preparation

2. Qualitative and quantitative composition

Each vial of powder contains 40 micrograms of edotreotide.

The radionuclide is not part of the kit.

Excipient with known effect

The vial of buffer contains approximately 32.5 mg of sodium.

For the full list of excipients, see section 6.1.

3. Pharmaceutical form

Kit for radiopharmaceutical preparation containing:

- Powder for solution for injection: the vial contains a white lyophilised powder.

- Reaction buffer: the vial contains a clear, colourless solution.

For radiolabelling with gallium (68Ga) chloride solution.

4. Clinical particulars
4.1 Therapeutic indications

This medicinal product is for diagnostic use only.

After radiolabelling with gallium (68Ga) chloride solution, the solution of gallium (68Ga) edotreotide obtained is indicated for Positron Emission Tomography (PET) imaging of somatostatin receptor overexpression in adult patients with confirmed or suspected well-differentiated gastro-enteropancreatic neuroendocrine tumours (GEP-NET) for localizing primary tumours and their metastases.

4.2 Posology and method of administration

The medicinal product should only be administered by trained healthcare professionals with technical expertise in using and handling nuclear medicine diagnostic agents and only in a designated nuclear medicine facility.

Posology

The recommended activity for an adult weighing 70 kg is 100 to 200 MBq, administered by direct slow intravenous injection.

The activity will be adapted to patient characteristics, the type of PET camera used and acquisition mode.

Elderly population

No special dosage regimen for elderly patients is required.

Renal impairment / Hepatic impairment

The safety and efficacy of gallium (68Ga) edotreotide have not been studied in patients with renal or hepatic impairment.

Paediatric population

The safety and efficacy of gallium (68Ga) edotreotide has not been established in paediatric populations, where the effective dose might be different than in adults. There is no recommendation for use of SomaKit TOC in paediatric patients.

Method of administration

SomaKit TOC is for intravenous use and for single use only.

This medicinal product should be radiolabelled before administration to the patient.

The activity of gallium (68Ga) edotreotide must be measured with an activimeter immediately prior to injection.

The injection of gallium (68Ga) edotreotide must be administered intravenously in order to avoid local extravasation resulting in inadvertent radiation to the patient and imaging artefacts.

For instructions on extemporaneous preparation of the medicinal product before administration, see sections 6.6 and 12.

For patient preparation, see section 4.4.

Image acquisition

Radiolabelled SomaKit TOC is suitable for PET medical imaging. The acquisition must include a whole body acquisition from skull to mid-thigh. The recommended time for imaging is 40 to 90 minutes post injection. Imaging acquisition start time and duration should be adapted according to the equipment used, the patient and the tumour characteristics in order to obtain the best image quality possible.

4.3 Contraindications

Hypersensitivity to the active substance, to any of the excipients listed in section 6.1 or to any of the components of the labelled radiopharmaceutical.

4.4 Special warnings and precautions for use

Potential for hypersensitivity or anaphylactic reactions

If hypersensitivity or anaphylactic reactions occur, the administration of the medicinal product must be discontinued immediately and intravenous treatment initiated, if necessary. To enable immediate action in emergencies, the necessary medicinal products and equipment such as endotracheal tube must be immediately available.

Individual benefit/risk justification

For each patient, the radiation exposure must be justifiable by the likely benefit. The activity administered should in every case be as low as reasonably achievable to obtain the required diagnostic information.

Renal / Hepatic impairment

Careful consideration of the benefit risk ratio in these patients is required since an increased radiation exposure is possible.

Paediatric population

For information on the use in paediatric population, see section 4.2.

The safety and efficacy of gallium (68Ga) edotreotide has not been established in paediatric populations, where the effective dose might be different than in adults.

Patient preparation

The patient should be well hydrated before the start of the examination and urged to void as often as possible, during the first hours after examination in order to reduce radiation.

Interpretation of gallium (68Ga) edotreotide images and limitations of use

PET images with gallium (68Ga) edotreotide reflect the presence of somatostatin receptors in the tissues.

The organs with high physiological uptake of gallium (68Ga) edotreotide include spleen, kidneys, liver, pituitary gland, thyroid gland and adrenals. High physiological uptake of gallium (68Ga) edotreotide by the pancreas uncinate process can also be observed.

In GEP-NET, a more intense gallium (68Ga) edotreotide uptake than normal background is a consistent finding. However, lesions of GEP-NET not expressing sufficient density of somatostatin receptors cannot be visualised with gallium (68Ga) edotreotide. PET images with gallium (68Ga) edotreotide should be interpreted visually, and semiquantitative measurement of gallium (68Ga) edotreotide uptake should not be used for clinical interpretation of images.

Data supporting efficacy of gallium (68Ga) edotreotide for predicting and monitoring of therapeutic response to peptide receptor radionuclide therapy (PRRT) in histologically confirmed metastatic NET are limited (see section 5.1).

In case of Cushing syndrome, a long-term exposure to endogenous hypercortisolism may down regulate somatostatin receptor expression and negatively influence the results of somatostatin receptor imaging with gallium (68Ga) edotreotide. Thus, in patients with GEP-NET and Cushing syndrome, normalisation of hypercortisolism should be suggested before performing PET with gallium (68Ga) edotreotide.

An increased uptake of gallium (68Ga) edotreotide is not specific for GEP-NET. Positive results require evaluating the possibility that another disease, characterised by high local somatostatin receptor concentrations, may be present. As an example, an increase in somatostatin receptor density can also occur in the following pathological conditions: subacute inflammations (areas of lymphocyte concentrations), thyroid diseases (e.g. thyroid autonomy and Hashimoto's disease), tumours of the pituitary gland, neoplasms of the lungs (small-cell carcinoma), meningiomas, mammary carcinomas, lympho-proliferative disease (e.g. Hodgkin's disease and non-Hodgkin lymphomas) and tumours arising from tissue embryologically derived from the neural crest (e.g. paragangliomas, medullary thyroid carcinomas, neuroblastomas, pheochromocytomas).

Splenectomy should also be considered as a relevant factor when reporting the outcome of somatostatin receptor targeted diagnostics.

Concomitant use of somatostatin analogues

It is preferable to perform imaging with gallium (68Ga) edotreotide the day(s) before the next administration of a somatostatin analogue. See section 4.5.

After the procedure

Close contact with infants and pregnant women should be restricted during the first 12 hours after administration.

Specific warnings

Depending on the time when you administer the injection, the content of sodium may in some cases be greater than 1 mmol. This should be taken into account in patient on low sodium diet.

Due to the acidic pH of the radiolabelled gallium (68Ga) edotreotide solution, accidental extravasation may cause local irritation. In case of extravasation, the injection must be stopped, the site of injection must be changed and the affected area should be irrigated with sodium chloride solution.

Precautions with respect to environmental hazard are in section 6.6.

4.5 Interaction with other medicinal products and other forms of interaction

Somatostatin and its analogues are probably competing to bind to the same somatostatin receptors. Therefore, when treating patients with somatostatin analogues, it is preferable to perform imaging with gallium (68Ga) edotreotide the day(s) preceding the next administration of a somatostatin analogue.

A long-term exposure to endogenous hypercortisolism may down-regulate somatostatin receptor expression and negatively influence the results of somatostatin receptor imaging with gallium (68Ga) edotreotide. In patients with Cushing syndrome, the normalisation of hypercortisolism should be considered before performing PET with SomaKit TOC.

Some evidence exists that corticosteroids can induce down-regulation of somatostatin subtype 2 receptors (SSTR2). Repeated administration of high-doses of glucocorticosteroids prior to gallium (68Ga) edotreotide administration may cause insufficient SSTR2 expression for adequate visualization of somatostatin receptor-positive NETs.

4.6 Fertility, pregnancy and lactation

Women of childbearing potential

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

Pregnancy

No data are available regarding the use of this product during pregnancy. Radionuclide procedures carried out on pregnant women also involve radiation doses to the fœtus. Only essential investigations should therefore be carried out during pregnancy, when the likely benefit far exceeds the risk incurred by the mother and fœtus.

Breastfeeding

Before administering radiopharmaceuticals to a mother who is breastfeeding, consideration should be given to the possibility of delaying the administration of radionuclide until the mother has ceased breastfeeding, and to what is the most appropriate choice of radiopharmaceuticals, bearing in mind the secretion of activity in breast milk. If the administration is considered necessary, breastfeeding should be interrupted for 12 hours and the expressed feeds discarded.

Close contact with infants should be restricted during the initial 12 hours following injection.

Fertility

No studies were conducted to assess the impact on fertility

4.7 Effects on ability to drive and use machines

Gallium (68Ga) edotreotide has no or negligible influence on the ability to drive and use machines.

4.8 Undesirable effects

Exposure to ionising radiation is linked with cancer induction and a potential for development of hereditary defects. As the effective dose is about 4.5 mSv when the maximal recommended activity of 200 MBq is administered, these adverse reactions are expected to occur with a low probability.

Adverse reactions are divided into groups according to the MedDRA convention frequencies: Very common (≥ 1/10), common (≥ 1/100 to < 1/10), uncommon (≥ 1/1,000 to < 1/100), rare (≥ 1/10,000 to < 1/1,000), very rare (< 1/10,000), not known (cannot be estimated from the available data).

General disorders and administration site conditions

Not known: injection site pain

Reporting of suspected adverse reactions

Reporting suspected adverse reactions after authorisation of the medicinal product is important. It allows continued monitoring of the benefit/risk balance of the medicinal product. Healthcare professionals are asked to report any suspected adverse reactions via the national reporting system:

Yellow Card Scheme

Website: www.mhra.gov.uk/yellowcard or search for MHRA Yellow Card in the Google Play or Apple App Store.

4.9 Overdose

In the event of administration of a radiation overdose, the absorbed dose to the patient should be reduced where possible by increasing the elimination of the radionuclide from the body by reinforced hydration and by frequent micturition. It might be helpful to estimate the effective dose that was applied.

5. Pharmacological properties
5.1 Pharmacodynamic properties

Pharmacotherapeutic group: Other diagnostic radiopharmaceuticals for tumour detection, ATC code: V09IX09.

Mechanism of action

Gallium (68Ga) edotreotide binds to somatostatin receptors. In vitro, this radiopharmaceutical binds with high affinity mainly to SSTR2 but also, to a lesser extent, to SSTR5.

In vivo, semiquantitative correlation was not assessed between gallium (68Ga) edotreotide uptake in tumours and the density of SSTR in histopathological samples neither in GEP-NET patients nor in normal organs. Moreover, the in vivo binding of gallium (68Ga) edotreotide to structures or receptors other than SSTR remains unknown.

Pharmacodynamic effects

At the chemical concentrations used for diagnostic examinations, gallium (68Ga) edotreotide does not appear to have any clinically relevant pharmacodynamic effect.

Edotreotide is a somatostatin analogue. Somatostatin is a neurotransmitter in the central nervous system, but also a hormone which binds to cells of neuroendocrine origin and inhibits the release of growth hormone, insulin, glucagon, and gastrin. There is no data if the intravenous administration of edotreotide produces variation of serum gastrin and serum glucagon levels.

Clinical efficacy and safety

For the detection of the primary GEP-NET site in case of rising levels of a relevant biochemical tumour marker or in case of proven NET metastasis, patient-based sensitivity and specificity of gallium (68Ga) edotreotide PET were 100% (4/4) and 89% (8/9), respectively, in the prospective study of Gabriel et al. 2007. Lesion-detection rate was 75% (3/4) in the subgroup of patients with unknown primary tumour site of the prospective study of Frilling et al. 2010. In the retrospective paper of Schreiter et al. 2014, the intra-individual comparison in a subgroup of 20 patients showed that gallium (68Ga) edotreotide permitted to localise the primary tumour in 9/20 (45%) patients while indium (111In) pentetreotide did in 2/20 (10%).

A prospective intra-individual comparison showed that gallium (68Ga) edotreotide is able to detect lesions better than indium (111In) pentetreotide. A lesion detection rate of 100% (40/40) versus 85% (34/40) was observed in the study of Hofmann et al. 2001 recruiting patients with histologically proven bronchial (n=2) or midgut (n=6) NETs. In the study of Buchmann et al. 2007, conducted in 27 patients mostly with GEP-NET (59%) or NETs of unknown primary (30%), gallium (68Ga) edotreotide identified 279 lesions versus 157 lesions seen with indium (111In) pentetreotide. In the study of Van Binnebeek et al. 2015 in 53 patients with metastatic GEP-NET [mostly GEP-NET (n=39) or NET of unknown origin (n=6)], the lesion-based detection rate of gallium (68Ga) edotreotide was 99.9% (1098/1099) versus 60% (660/1099) for indium (111In) pentetreotide based on the follow-up scans. In the study of Lee et al. 2015 in 13 GEP-NET patients, a total of 35 positive lesions were detected in 10 patients on either gallium (68Ga) edotreotide PET/CT or indium (111In) pentetreotide SPECT/CT while 3 patients did not exhibit any positive lesions on either imaging method. Gallium (68Ga) edotreotide detected 35/35 (100%) lesions vs 19/35=54% for indium (111In) pentetreotide SPECT/CT. In the study of Kowalski et al. 2003 in 4 patients with GEP-NET, gallium (68Ga) edotreotide showed better patient-based detection rate (100%) than indium (111In) pentetreotide (50%).

Data available on clinical efficacy of gallium (68Ga) edotreotide for the indication of predicting and monitoring of therapeutic response to peptide receptor radionuclide therapy (PRRT) in histologically confirmed metastatic NET are limited. Five studies have been submitted, one of them prospective (Gabriel et al. 2009) and four retrospective studies (Kroiss et al. 2013, Ezziddin et al. 2012, Kratochwil et al. 2015 and Luboldt et al.2010a). In the study by Gabriel et al. 2009 pre-PRRT gallium (68Ga) edotreotide was compared with CT or MRI using the Response Evaluation Criteria in Solid Tumors (RECIST). Gallium (68Ga) edotreotide PET and CT showed a concordant result in 32 patients (70%) and discrepancies in 14 patients (30%) presenting 9 with progressive disease and 5 with remission.

The retrospective study of Kroiss et al. 2013 in 249 NET patients showed that PRRT does not significantly influence semiquantitative uptake of gallium (68Ga) edotreotide PET, except in liver metastases of patients with NET, but the study lacked histological confirmation. The three remaining retrospective studies recruited small samples (ranging from 20 to 28 GEP-NET patients or those with cancer of unknown origin) and found that semiquantitative uptake in the pre-PRRT gallium (68Ga) edotreotide PET scan correlated with the tumour-absorbed doses per injected activity of the subsequent first treatment cycle, differed between those lesions classified as responding and non-responding after three PRRT cycles, and helped to separate hepatic metastases from normal liver tissue.

5.2 Pharmacokinetic properties

Distribution

After intravenous injection, gallium (68Ga) edotreotide is rapidly cleared from the blood following bi-exponential elimination of activity with half-lives of 2.0 ± 0.3 min and 48 ± 7 min respectively.

Organ uptake

The organ with the highest physiological uptake of gallium (68Ga) edotreotide is the spleen, followed by the kidneys. The uptake in the liver and in the pituitary, thyroid and adrenal glands is lower. High physiological uptake of gallium (68Ga) edotreotide by the pancreas uncinate process can also be observed. About 50 minutes after intravenous administration, gallium (68Ga) edotreotide accumulation shows plateauing in all organs.

The organ uptake has been shown to be age-independent in normal adult human tissues and also predominantly gender-independent (except for the thyroid and head of pancreas).

Elimination

No radioactive metabolites were detected in serum within 4 hours after intravenous injection of gallium (68Ga) edotreotide.

Approximately 16% of gallium (68Ga) edotreotide activity is removed from the body in the urine within 2 to 4 hours. The peptide is excreted via kidneys as intact compound.

Half-life

Given that the elimination rate is substantially slower than the physical half-life of gallium (68Ga) (68 min), the biological half-life will have little impact on the effective half-life of the product which then would be expected to be somewhat less than 68 minutes.

Renal/Hepatic impairment

The pharmacokinetics in patients with renal or hepatic impairment has not been characterized.

5.3 Preclinical safety data

Non-clinical data did not reveal any special hazard for gallium (68Ga) edotreotide in humans.

Local tolerance assessment resulted in mild to moderate inflammation signs in the perivascular region of some animals which can be attributed to the acidic pH of the solution.

No studies on fertility, embryology, mutagenicity or long-term carcinogenicity have been conducted.

Regarding the novel excipient (1,10-phenanthroline), during the toxicity study conducted with the kit formulation of SomaKit TOC including 1,10-phenanthroline at a dose 400 fold higher than the human dose, no toxicity signs were observed.

Genotoxicity studies on 1,10-phenanthroline available in the literature show negative results in bacterial mutation assay (Ames test), while in a mouse lymphoma assay an indication of possible genotoxicity was obtained at concentrations 750 times higher than the maximum 1,10-phenanthroline blood concentration achievable in patients. However, even taking as worst case reference the limits for genotoxic and carcinogenic impurities, the risk related to the trace amounts of 1,10-phenanthroline in SomaKit TOC formulation is considered negligible at the dose to be administered in patients: the exposure to 1,10-phenanthroline (5 µg/dose) is 24 fold lower than the acceptable daily intake for a genotoxic impurity (120 µg/day for exposures <1 month).

6. Pharmaceutical particulars
6.1 List of excipients

Powder

1,10-phenanthroline

Gentisic acid

Mannitol (E421)

Buffer

Formic acid

Sodium hydroxide (E524)

Water for injections

After radiolabelling, the solution obtained also contains, as excipient, hydrochloric acid from the generator eluate.

6.2 Incompatibilities

Radiolabelling of carrier molecules with gallium (68Ga) chloride is very sensitive to the presence of trace metal impurities. Only syringe and syringe needles able to minimise trace metal impurity levels (for example, non-metallic or coated with silicone needles – not supplied –) should be used.

This medicinal product must not be mixed with other products except those mentioned in section 12.

6.3 Shelf life

Kit as packaged for sale

2 years.

After radiolabelling

4 hours.

Do not store above 25°C after radiolabelling.

From a microbiological point of view, the product should be used immediately. If not used immediately, in-use storage times and conditions prior to use are the responsibility of the user.

6.4 Special precautions for storage

Store in a refrigerator (2°C to 8°C).

Store in the original package in order to protect from light.

For storage conditions after radiolabelling of the medicinal product, see section 6.3.

Storage of radiopharmaceuticals should be in accordance with national regulation on radioactive materials.

6.5 Nature and contents of container

Each pack contains:

• One vial of powder for solution for injection: 10 ml Type I glass vial closed with a bromobutyl rubber stopper and sealed with a flip-off cap. Each vial contains 40 micrograms of edotreotide.

One vial of buffer: 10 ml cyclic olefin polymer vial closed with a teflon stopper and sealed with a flip-off cap. Each vial contains 1 ml of reaction buffer.

6.6 Special precautions for disposal and other handling

General warnings

Radiopharmaceuticals should be received, used and administered only by authorized persons in designated clinical settings. Their receipt, storage, use, transfer, and disposal are subject to the regulations and/or appropriate licenses of the competent official organization.

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

Contents of the vials are intended only for use in the preparation of gallium (68Ga) edotreotide solution for injection and are not to be administered directly to the patient without first undergoing the preparative procedure.

Each 40 microgram vial contains an excess of product. However, it is recommended that the vial be prepared as instructed and used for a single patient dose, based on the activity to be injected; any remaining material should be discarded after radiolabelling and use.

Precautions to be taken before handling or administration of the medicinal product

For instructions on radiolabelling of the medicinal product before administration, see section 12.

If at any time in the preparation of this product the integrity of the vials is compromised it should not be used.

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

The content of the kit before radiolabelling is not radioactive. However, after gallium (68Ga) chloride solution is added, adequate shielding of the final preparation must be maintained.

The administration of radiopharmaceuticals creates risks for other persons from external radiation or contamination from spills of urine, vomiting, blood, etc. Radiation protection precautions in accordance with national regulations must therefore be taken.

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

7. Marketing authorisation holder

Advanced Accelerator Applications

20 rue Diesel

01630 Saint Genis Pouilly

France

8. Marketing authorisation number(s)

PLGB 35145/0004

9. Date of first authorisation/renewal of the authorisation

Date of first authorisation: 01 January 2021

10. Date of revision of the text

20 May 2021

11. DOSIMETRY

Gallium-68 decays with a half-life of 68 min to stable zinc-68, 89% through positron emission with a mean energy of 836 keV followed by photonic annihilation radiations of 511 keV (178%), 10% through orbital electron capture (X-ray or Auger emissions), and 3% through 13 gamma transitions from 5 excited levels.

The dosimetry of gallium (68Ga) edotreotide was calculated by Sandstrom et al. (2013), using OLINDA/EXM 1.1 software (table 1).

Table 1: Dosimetry of gallium (68Ga) edotreotide

Absorbed dose in selected organs

mGy/MBq

Organs

Mean

Adrenals

0.077

Brain

0.010

Breasts

0.010

Gallbladder wall

0.015

Lower large intestine wall

0.015

Small intestine

0.023

Stomach wall

0.013

Upper large intestine wall

0.020

Heart wall

0.020

Kidneys

0.082

Liver

0.041

Lungs

0.007

Muscle

0.012

Ovaries

0.015

Pancreas

0.015

Red marrow

0.016

Osteogenic cells

0.021

Skin

0.010

Spleen

0.108

Testes

0.011

Thymus

0.011

Thyroid

0.011

Urinary bladder wall

0.119

Uterus

0.015

Total body

0.014

Effective dose

mSv/MBq

0.021

The effective dose resulting from the administration of an activity of 200 MBq to an adult weighing 70 kg is about 4.2 mSv.

For an administered activity of 200 MBq the typical radiation dose to the critical organs, which are the urinary bladder wall, the spleen, the kidneys and the adrenals, are about 24, 22, 16 and 15 mGy, respectively.

12. INSTRUCTIONS FOR PREPARATION OF RADIOPHARMACEUTICALS

Radiation safety – Product handling

Use waterproof gloves, effective radiation shielding, and appropriate safety measures when handling the radiolabelled SomaKit TOC to avoid unnecessary radiation exposure to the patient, occupational workers, clinical personnel, and other persons.

Radiopharmaceuticals should be used by or under the control of healthcare professionals who are qualified by specific training and experienced in the safe use and handling of radionuclides, and whose experience and training have been approved by the appropriate governmental agency authorised to license the use of radionuclides.

The gallium (68Ga) edotreotide solution must be prepared in accordance with radioprotection and pharmaceutical quality standards, especially concerning aseptic technique. If at any time in the preparation of this product the integrity of the vials is compromised, the product should not be used.

A low dead space 1 ml plastic syringe must be used in order to precisely measure the adequate volume of reaction buffer to be added during the preparation. Glass syringe must not be used.

For administration, the solution should be withdrawn via the stopper using a single dose syringe fitted with suitable protective shielding and a disposable sterile needle or using an authorised automated application system.

Method of preparation

SomaKit TOC is supplied as a kit containing two vials. It is intended to be radiolabelled with a gallium (68Ga) chloride solution compliant with the Ph. Eur. monograph 2464 Gallium (68Ga) chloride solution for radiolabelling and that, in addition, is sterile and has been tested for compatibility with SomaKit TOC. Only generators that have been authorised as medicinal products in the EU should be used. Refer to the Summary of Product Characteristics of the particular generator for more information.

The following authorised generators have shown to be compatible with SomaKit TOC:

• GalliaPharm, 0.74 – 1.85 GBq, radionuclide generator (Eckert & Ziegler Radiopharma GmbH),

• Galli Ad, 0.74 – 1.85 GBq, radionuclide generator (IRE-Elit).

The gallium (68Ga) edotreotide solution for intravenous injection must be prepared according to aseptic procedure, local regulation and the following instructions.

Reconstitution with GalliaPharm generator:

a) If possible, for more convenience in the preparation of radiolabelled SomaKit TOC, the heating platform should be placed right beside the generator.

b) Set the temperature of the shielded dry bath at 95°C and wait for the temperature to reach the set point and stabilize.

c) Flip off cap from the vial of powder and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, and then allow the stopper to dry.

d) Pierce the Vial 1 septum with a 0.2 µm sterile vent filter in order to maintain atmospheric pressure within the vial during the radiolabelling process.

e) Flip off cap from the Vial 2 (Reaction buffer) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, and then allow the stopper to dry. With a low dead space 1 ml sterile syringe carefully withdraw 0.5 ml reaction buffer, and keep the reaction buffer in syringe for step “i”.

f) Connect the male luer of the outlet line of the 68Ge/68Ga generator with a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace – not supplied).

g) Connect the Vial 1 to the outlet line of the generator by pushing the needle through the rubber septum.

h) Elute the generator directly into the Vial 1 (through the needle) according to the generator manufacturer instructions for use, in order to reconstitute the powder with the eluate. The elution can be performed either manually or by means of a pump.

i) At the end of the elution, disconnect the generator from the Vial 1 withdrawing the needle from the rubber septum and immediately add the reaction buffer previously dosed in the 1 ml sterile syringe. Withdraw the syringe and the 0.2 µm sterile vent filter and move the vial to the hole of the dry bath at 95°C, using a plier. Leave the vial at 95°C for at least 7 minutes (do not exceed 10 minutes heating) without agitation or stirring.

j) After 7 minutes, remove the vial from the dry bath, place it in an appropriately labelled lead shield and let it cool down at room temperature for approximately 10 minutes.

k) Assay the vial radioactivity using a suitable radioactivity calibration system and record the result. Report the activity value, the calibration time, the batch number and the expiry time on the shield label included in the pack to be applied on the lead shielding container after radiolabelling.

l) Perform the quality control according to the recommended methods in order to check the compliance to the specifications (see section, “Quality control”).

m) The solution should be visually inspected prior to use. Only clear solutions, free from visible particles should be used. The visual inspection should be performed under a shielded screen for radioprotection purposes.

n) Store the vial containing the gallium (68Ga) edotreotide solution below 25°C until use. At the time of administration, the product must be aseptically withdrawn and the radioprotection standards must be followed. The patient dose should be measured by a suitable radioactivity calibration system immediately prior to patient administration. Product administration data should also be recorded.

A schematic representation of the radiolabelling procedure is shown in Figure 1.

Figure 1: Radiolabelling procedure when using GalliaPharm generator

Reconstitution with Galli Ad generator:

a) If possible, for more convenience in the preparation of radiolabelled SomaKit TOC, the heating platform should be placed right beside the generator.

b) Set the temperature of the shielded dry bath at 95°C and wait for the temperature to reach the set point and stabilize.

c) Flip off cap from the vial of powder and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, and then allow the stopper to dry.

d) Pierce the Vial 1 septum with a 0.2 µm sterile vent filter in order to maintain atmospheric pressure within the vial during the radiolabelling process.

e) Flip off cap from the Vial 2 (Reaction buffer) and swab the top of the vial closure with an appropriate antiseptic to disinfect the surface, and then allow the stopper to dry. With a low dead space 1 ml sterile syringe carefully withdraw 100 µl and keep the reaction buffer in syringe for step “g”.

f) With a 5 mL sterile syringe and a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace – not supplied) carefully withdraw 4 mL of water for injections (not supplied) and reconstitute the powder in Vial 1.

g) Add the reaction buffer previously dosed in the 1 ml sterile syringe.

h) Connect the male luer of the outlet line of the 68Ge/68Ga generator with a sterile needle (coated with silicone or other appropriate material able to reduce metal impurity trace – not supplied).

i) Connect the Vial 1 to the outlet line of the generator by pushing the needle through the rubber septum. Turn the button by 90° to loading position then wait 10 seconds before turning the button back to initial position, according to the generator's instructions for use.

j) Connect Vial 1 through the 0.2 µm sterile vent filter to a vacuum vial or to a pump to start the elution. Elute the generator directly into the Vial 1 (through the needle).

k) At the end of the elution, first withdraw the needle from the vacuum vial in order to establish atmospheric pressure into Vial 1, then disconnect Vial 1 from the generator by removing the needle from the rubber septum. Finally remove the 0.2 µm sterile vent filter and move the vial to the hole of the dry bath at 95°C, using a plier. Leave the vial at 95°C for at least 7 minutes (do not exceed 10 minutes heating) without agitation or stirring.

l) After 7 minutes, remove the vial from the dry bath, place it in an appropriately labelled lead shield and let it cool down at room temperature for approximately 10 minutes.

m) Assay the vial radioactivity using a suitable radioactivity calibration system and record the result. Report the activity value, the calibration time, the batch number and the expiry time on the shield label included in the pack to be applied on the lead shielding container after radiolabelling.

n) Perform the quality control according to the recommended methods in order to check the compliance to the specifications (see section, “Quality control”).

o) The solution should be visually inspected prior to use. Only clear solutions, free from visible particles should be used. The visual inspection should be performed under a shielded screen for radioprotection purposes.

p) Store the vial containing the gallium (68Ga) edotreotide solution below 25°C until use. At the time of administration, the product must be aseptically withdrawn and the radioprotection standards must be followed. The patient dose should be measured by a suitable radioactivity calibration system immediately prior to patient administration. Product administration data should also be recorded.

A schematic representation of the radiolabelling procedure is shown in Figure 2.

Figure 2: Radiolabelling procedure when using Galli Ad generator

Gallium (68Ga) edotreotide solution is stable up to 4 hours after preparation. Therefore, the radiolabelled solution can be used within 4 hours after preparation according to the radioactivity required for the administration.

Radioactive waste must be disposed of in accordance with relevant national regulations.

After radiolabelling with the correct volume of reaction buffer and generator eluate, any further dilution with any diluent is prohibited.

Quality control

Table 2: Specifications of the gallium (68Ga) edotreotide

Test

Acceptance Criteria

Method

Appearance

Clear solutions free of visible particles

Visual inspection

pH

3.2 – 3.8

pH-indicator strips

Labelling efficiency

colloidal gallium-68 species

≤ 3%

Thin layer chromatography

(ITLC1, see details below)

Labelling efficiency

% Free gallium-68

≤ 2%

Thin layer chromatography

(ITLC2, see details below)

The quality controls should be performed under a shielded screen for radioprotection purposes.

Recommended method for determining labelling efficiency of gallium (68Ga) edotreotide:

ITLC1:

Material

• Glass-fibre ITLC paper (e.g. Agilent ITLC SGI001) pre-cut to 1 cm x 12 cm strips

• Mobile phase: 77 g/L solution of ammonium acetate in water /Methanol 50:50 V/V

• Developing tank

• Radiometric ITLC scanner

Sample Analysis

a. The TLC developing tank is prepared by pouring the mobile phase to a depth of 3 to 4 mm. Cover the tank and allow to equilibrate.

b. Apply a drop of the gallium (68Ga) edotreotide on a pencil line 1 cm from the bottom of the ITLC strip.

c. Place the ITLC strip in the developing tank and allow it to develop for a distance of 9 cm from the point of application.

d. Scan the ITLC with a radiometric ITLC scanner

e. The retention factor (Rf) specifications are as follows:

Not complexed gallium (68Ga) = 0 to 0.1

gallium (68Ga) edotreotide = 0.8 to 1

The labelling efficiency is calculated by integration of peak with Rf = 0 to 0.1 that must be ≤ 3%.

ITLC2:

Material

• Glass-fibre ITLC paper (e.g. Agilent ITLC SGI001) pre-cut to 1 cm x 12 cm strips Mobile phase: sodium Citrate 0.1 M (pH 5) in water

• Developing tank

• Radiometric ITLC scanner

Sample Analysis

a. The TLC developing tank is prepared by pouring the mobile phase to a depth of 3 to 4 mm. Cover the tank and allow to equilibrate.

b. Apply a drop of the gallium (68Ga) edotreotide solution on a pencil line 1 cm from the bottom of the ITLC strip.

c. Place the ITLC strip in the developing tank and allow it to develop for a distance of 9 cm from the point of application.

d. Scan the ITLC with a radiometric ITLC scanner

The retention factor (Rf) specifications are as follows: gallium (68Ga) edotreotide = 0.1 to 0.2

Free gallium-68 = 0.9 to 1

The labelling efficiency is calculated by integration of peak with Rf = 0.9 to 1.0 that must be ≤ 2%.

LEGAL CATEGORY

POM