Automated radiochemical synthesis of pharmaceutical grade [18 F]FLT using 3-N-Boc-5'-O-dimethoxytrityl-3'-O-nosyl-thymidine precursor and its Sep-Pak® purification employing selective elution from reversed phase.

Pharmaceutical grade 3'-deoxy-3'-[18 F]fluorothymidine [18 F]FLT was synthesized using 3-N-Boc-5'-O-dimethoxytrityl-3'-O-nosyl-thymidine (BOC-Nosyl) precursor, in the general purpose TRACERlab FX modules. Purification of [18 F]FLT, via solid phase extraction (SPE) after radiosynthesis, using a combination of different SPE cartridges, yielded satisfactory results, with radiochemical and chemical purity >99%. While the non-decay corrected radiochemical yield (RCY) with 20 mg (24 µmole) of BOC-Nosyl precursor was found to be 6.80 ± 0.16%, the decay corrected radiochemical yield (RCY) was 9.95 ± 0.24%. Residual acetone, acetonitrile, and ethanol levels were found to be 22.97 ± 0.76, 109.08 ± 0.93, and 7,666.45 ± 3.7 ppm, respectively. A simplified method for solid-phase purification of [18 F]FLT was developed, circumventing the need for HPLC purification. Biodistribution in C57BL/6 mice with B16F10 cell line-induced melanoma showed tumor to blood ratio of ~3.8 at 90 min. PET/CT imaging of normal rabbit injected with [18 F]FLT shows selective uptake in the bone marrow and small intestine. [18 F]FLT was found to be excreted through the kidneys and get collected in the urinary bladder, 120 min post injection. PET/CT imaging performed in rabbit model at 30, 60, 90, and 120 min post [18 F]FLT injections showed concordance with tissue distribution kinetics of mice tumor model.

Production of pharmaceutical grade [201Tl]Thallous chloride using 30 MeV cyclotron.

Multiple patient doses of [201Tl]TlCl has been produced using electrodeposited enriched 203Tl in 30 MeV cyclotron (Cyclone-30) with 28 MeV proton energy at 50 µA beam current for 8 h. Ion Exchange Column Chromatography (IECC) and liquid-liquid extraction has been employed for semi-automated radiochemical separation and purification of produced [201Tl]TlCl. The produced [201Tl]TlCl was used in coronary artery disease (CAD) patients.

Intricacies in the Preparation of Patient Doses of [177Lu]Lu-Rituximab and [177Lu]Lu-Trastuzumab Using Low Specific Activity [177Lu]LuCl3: Methodological Aspects.

The development of humanized monoclonal antibodies (MAbs) with Lutetium-177 ([177Lu]Lu3+) has brought a paradigm shift in the arena of targeted therapy of various cancers. [177Lu]Lu-DOTA-Rituximab and [177Lu]Lu-DOTA-Trastuzumab have gained prominence due to their improved therapeutic efficacy in the treatment of lymphoma and breast cancer. The clinical dose formulation of these radiolabeled MAbs, using low specific activity [177Lu]LuCl3, requires extensive optimization of the radiolabeling protocol. The present study merits the development of a single protocol which has been optimized for conjugation of Rituximab and Trastuzumab with p-NCS-benzyl-DOTA and further radiolabeling these immunoconjugates (ICs) with low specific activity [177Lu]LuCl3. Herein, we report a consistent and reproducible protocol for clinical dose formulations of [177Lu]Lu-DOTA-Rituximab and [177Lu]Lu-DOTA-Trastuzumab (~9.25 GBq each, equivalent to ~2 patient doses) with radiochemical yield (RCY) between 84 and 86% and radiochemical purities (RCP) >99%. The in vitro stabilities of both these radioimmunoconjugates (RICs) were retained up to 120 h post-radiolabeling, upon storage with L-ascorbic acid as stabilizer (concentration: ~ 220-240 µg/37MBq) at -20 °C. The ready-to-use formulation of clinical doses[177Lu]Lu-DOTA-Rituximab and [177Lu]Lu-DOTA-Trastuzumab has been successfully achieved by employing a single optimized protocol. While [177Lu]Lu-DOTA-Rituximab has exhibited a high degree of localization in retroperitoneal nodal mass of refractory lymphoma patient, high uptake of [177Lu]Lu-DOTA-Trastuzumab has been observed in metastatic breast carcinoma patient with multiple skeletal metastases.

Preparation of [68Ga]Ga-Chloride from 68Zn solid target for the synthesis of pharmaceutical grade [68Ga]Ga-PSMA-11 and [68Ga]Ga-DOTA-TATE.

68Ga is produced from enriched zinc-68 target electrodeposited on copper base material which was irradiated with 15 MeV proton energy in 30 MeV cyclotron. A modified semi-automated separation and purification module was used to obtain pharmaceutical grade [68Ga]GaCl3 in 35 ± 5 min. The quality of [68Ga]GaCl3 produced was in accordance with Pharmeuropa 30.4. The [68Ga]GaCl3 was utilized for the formulation of multiple doses of [68Ga]Ga-PSMA-11 and [68Ga]Ga-DOTATATE. The quality of [68Ga]Ga-PSMA-11 and [68Ga]Ga-DOTATATE were also in accordance with Pharmacopeia.

A method to prevail false positive responses due to excess cations and viscous nature of Radiopharmaceuticals in Limulus Amebocyte Lysate Gel Clot test.

Objectives: Bacterial endotoxin test (BET) for detection and quantification of endotoxin in radiopharmaceuticals (RPs), used for therapy or diagnosis, is prerequisite to administration in patients. Out of the two established methods used for this purpose (Kinetic Chromogenic Assay: KCM and Gel Clot Bacterial Endotoxin Test: GC-BET), GC-BET is recommended by pharmacopeias to evaluate the interferences exhibited during the assay due to presence of various ingredients in samples. In the present study, the influence of excess of cations in [177Lu]Lu-DOTATATE, used for Peptide Receptor Radionuclide Therapy (PRRT), were studied and a protocol to negate the enhancement observed was developed. Additionally, a protocol for carrying out GC-BET for extremely viscous [131I]I-Lipiodol was standardized. Methods: GC-BET was performed for [177Lu]Lu-DOTATATE and [131I]I-Lipiodol at maximum valid dilution (MVD), using LRW as a diluent. To negate the false positivity observed in case of [177Lu]Lu-DOTATATE, various concentrations of calcium chloride (CaCl2) were added and evaluated for the reversal of the interference observed initially. To prevail the difficulty in performing GC-BET for [131I]I-Lipiodol various modification in the protocols like orbital vortexing at different rpm and time intervals were performed. KCM assays were also performed for studied RPs at MVD. Results: It was observed that at MVD, [177Lu]Lu-DOTATATE exhibited false positivity in GC-BET. However, all the individual reagents used in labeling of [177Lu]Lu-DOTATATE did not show any false positivity. Finally, performing the assay with an addition of 2mM CaCl2 (final concentration) nullified the false positivity. Further, intricacy in performing GC-BET for [131I]I-Lipiodol due to its viscosity was resolved by orbital vortexing at 3000 rpm for 5 minutes. Conclusions: Our study proved that false positivity was observed in GC-BET for [177Lu]Lu-DOTATATE due to the presence excess M3+ ions. Further, our study is the first of its kind which demonstrated methods for negating these false positive results by using modified protocol and hypothesizing the reason behind the enhancement. Additionally, ours is the first study which proved that a simple step of vortexing the viscous RPs like [131I]I-Lipiodol can resolved the problems encountered during performing GC-BET due to viscosity of RPs.

Clinical Dose Preparation of [177Lu]Lu-DOTA-Pertuzumab Using Medium Specific Activity [177Lu]LuCl3 for Radioimmunotherapy of Breast and Epithelial Ovarian Cancers, with HER2 Receptor Overexpression.

Background: The overexpression of human epidermal growth factor receptor 2 (HER2) is commonly associated with metastatic breast cancer and epithelial ovarian cancer. The U.S. Food and Drug Administration (FDA) has approved Trastuzumab as an anti-HER2 agent for the metastatic breast and epithelial ovarian cancer. However, Trastuzumab has severe limitations in the treatment of metastatic breast cancer associated with ligand-dependent dimerization of HER2 receptor at the extracellular domain-II (ECD-II) region. The therapeutic approach in combination of pertuzumab and trastuzumab is found to be effective in preventing HER2 dimerization at the ECD-II region. The radioimmunotherapeutic approach, utilizing both these anti-HER2 agents (trastuzumab/pertuzumab), radiolabeled with [177Lu]Lu3+, has proved to be clinically efficacious with promising potential. Toward this, the formulation for clinical doses of [177Lu]Lu-DOTA-pertuzumab has been optimized using medium specific activity (0.81 GBq/µg) [177Lu]LuCl3. Materials and Methods: Preconcentrated pertuzumab was conjugated with p-NCS-benzyl-DOTA. Purified DOTA-benzyl-pertuzumab conjugate was radiolabeled with carrier-added [177Lu]LuCl3. Quality control parameters were evaluated for the [177Lu]Lu-DOTA-pertuzumab. In vivo biodistribution was carried out at different time points postadministration. Specific cell binding, immunoreactivity, and internalization were investigated by using SKOV3 and SKBR3 cells. Results: In this study, the authors reported a consistent and reproducible protocol for clinical dose formulations of [177Lu]Lu-DOTA-pertuzumab, with a radiochemical yield of 86.67% ± 1.03% and radiochemical purity (RCP) of 99.36% ± 0.36% (n = 10). Preclinical cell binding studies of [177Lu]Lu-DOTA-pertuzumab revealed specific binding with SKOV3 and SKBR3 cells up to 24.4% ± 1.4% and 23.2% ± 0.8%, respectively. The uptakes in SKOV3- and SKBR3-xenografted tumor in severe combined immunodeficiency mice were observed to be 25.9% ± 0.8% and 25.2% ± 1.2% ID/g at 48 and 120 h postinjection, respectively. Conclusions: A protocol was optimized for the preparation of ready-to-use clinical dose of [177Lu]Lu-DOTA-pertuzumab, in hospital radiopharmacy settings. The retention of RCP of the radiopharmaceutical, on storage in saline and serum, at -20°C, up to 120 h postradiolabeling, confirmed its in vitro stability.

Clinical doses production of pharmaceutical grade Sodium[18F]Fluoride using modified integrated fluidic processor in a SYNTHERA® module.

A fully automated large-scale production of sodium [18F]fluoride ([18F]NaF) using SYNTHERA module with a modification in integrated fluidic processor (IFP) is reported. This modified IFP module is used to prepare [18F]NaF with more than 98% non-decay corrected radiochemical yield (RCY) within 5 min with specifications in accordance with United State Pharmacopeia (USP) monograph. The graphical user interface (GUI) is designed to perform the synthesis steps either manually or automatically and give information to the operator during the course of production. The desired clinical results add support to indigenously produced [18F]NaF as a pharmaceutical grade diagnostic radiopharmaceutical.

Initial clinical evaluation of indigenous 90Y-DOTATATE in sequential duo-PRRT approach (177Lu-DOTATATE and 90Y-DOTATATE) in neuroendocrine tumors with large bulky disease: Observation on tolerability, 90Y-DOTATATE post- PRRT imaging characteristics (bremsstrahlung and PETCT) and early adverse effects.

177Lu-DOTATATE peptide receptor radionuclide therapy (PRRT) alone has lesser potential in the clinical setting of neuroendocrine tumor (NET) with large bulky disease and nonhomogeneous somatostatin receptors (SSTR) distribution, owing to lower energy (Eßmax 0.497 MeV) and a shorter particle penetration range (maximum 2-4 mm) of 177Lu. In large bulky NETs, 90Yttrium (90Y) has the theoretical advantages because of a longer beta particle penetration range (a maximum soft tissue penetration of 11 mm). Therefore, a combination of 177Lu and 90Y is a theoretically sound concept that can result in better response in metastatic NET with large-bulky lesion and non-homogeneous SSTR distribution. The aim of the study was to determine the feasibility of combining 90Y-DOTATATE with 177Lu-DOTATATE PRRT as sequential duo-PRRT in metastatic NET with (≥5 cm) including the post 90Y-DOTATATE-PRRT imaging and also to determine early toxicity of the duo-PRRT approach. A total of 9 patients received combination of 177Lu-DOTATATE with 90Y-DOTATATE (indigenously prepared and approved) through sequential duo-PRRT approach. These 9 NET patients were included and analyzed in this study. All 9 patients had undergone post-PRRT 90Y-DOTATATE imaging, including a whole-body planar bremsstrahlung imaging followed by regional single-photon emission computed tomography (SPECT)-computed tomography (CT) imaging and also a regional positron emission tomography-computed tomography imaging. Grading of 90Y-DOTATATE and 177Lu-DOTATATE uptake was done on post-PRRT imaging by both modalities. The size of the lesions ranged from 5.5 cm to 16 cm with average size of 10 cm before sequential duo-PRRT was decided. Sequential duo-PRRT was administered because of stable, unresponsive disease following 177Lu-DOTATATE in 5 patients (55.6%), progressive disease after 177Lu-DOTATATE in 2 patients (22.2%), and with neoadjuvant intent in 2 patients (22.2%). The total cumulative dose of 177Lu-DOTATATE before duo-pRRT ranged from 11.84 GBq to 37 GBq per patient and average administered dose of 27.21 GBq per patient in this study. Out of 9 patients, 8 patients received single cycle of 90Y-DOTATATE (ranging from 2.66 GBq to 3.4 GBq per patient with average administered dose of 3.12 GBq per patient). One patient received two cycles of 90Y-DOTATATE (total dose of 6.2 GBq). Out of 9 patients, 8 patients showed excellent tracer concentration in lesions on post-PRRT 90Y-DOTATATE imaging and the remaining 1 patient showed fairly adequate 90Y-DOTATATE tracer uptake in lesion on visual analysis. There was matched 90Y-DOTATATE uptake with 68Ga-DOTATATE and also with 177LuDOTATATE in all 9 patients. The sequential duo-PRRT was well tolerated by all patients. Two patients (22.2%) developed mild nausea, one patient (11.1%) developed transient mild-grade hemoglobin toxicity, and one patient (11.1%) developed mild-grade gastrointestinal symptoms (loose motion and abdominal pain). No nephrotoxicity, hepatotoxicity, and other hematological toxicity was observed. The combination of the indigenous 90Y-DOTATATE with 177Lu-DOTATATE PRRT in NET as sequential duo-PRRT was well tolerated, feasible and safe in stable, unresponsive/progressive disease following single isotope 177Lu-DOTATATE therapy and also in neoadjuvant PRRT setting with large bulky lesion (≥≥5cm). Post-PRRT 90Y-DOTATATE imaging showed excellent 90Y-DOTATATE uptake in nearly all NET patients. Mild-grade early adverse effects were easily manageable and controllable in this sequential duo-PRRT approach.

Therapeutic Multidose Preparation of a Ready-to-Use 177Lu-PSMA-617 Using Carrier Added Lutetium-177 in a Hospital Radiopharmacy and Its Clinical Efficacy.

Introduction: [177Lu]Lu-prostate-specific membrane antigen (PSMA)-617 has emerged as a promising radiopharmaceutical for targeting PSMA in metastatic castrate-resistant prostate carcinoma (mCRPC). We have optimized the radiolabeling protocol for a multidose formulation (27-28.8 GBq equivalent to 6-7 patient-doses) of [177Lu]Lu-PSMA-617 using [177Lu]Lu3+ produced via 176Lu(n,γ)177Lu route with moderate specific activity (0.66-0.81 GBq/µg). Methods: [177Lu]Lu-PSMA-617 was synthesized using moderate specific activity [177Lu]LuCl3 (0.74 GBq/µg) with PSMA-617 having metal-to-ligand molar ratio ∼1: 2.5 in CH3COONH4 buffer (0.1 M) containing gentisic acid at pH 4.0-4.5. Human prostate carcinoma cell line LNCaP cell (high PSMA expression) was used for in vitro cell-binding studies and generating tumor xenograft models in nude mice for tissue biodistribution studies. Several batches of the present formulation have been clinically administered in mCRPC patients (single patient dose: 4.44-5.55 GBq per cycle). Results: In this study we report a consistent and reproducible protocol for multidose formulations of [177Lu]Lu-PSMA-617 for adopting in a hospital radiopharmacy setting. Although the radiochemical yield of [177Lu]Lu-PSMA-617 was found to be 97.30% ± 1.03%, the radiochemical purity was 98.24% ± 0.50% (n = 19). In vitro and serum stability of [177Lu]Lu-PSMA-617 was retained up to 72 and 120 h after radiolabeling and upon storage at -20°C with a radioactive concentration between 0.37 and 0.74 GBq/mL upon using stabilizer concentration as low as 43-48 µg/mCi. Preclinical cell-binding studies of [177Lu]Lu-PSMA-617 revealed specific binding with LNCaP cells of 17.4% ± 2.4%. The uptake in LnCaP xenografted tumor (nude mice) was 7.5 ± 2.6% ID/g for ∼1.5-2.0 cm3 tumor volume at 24-h post-injection. Post-therapy (24 h) SPECT image of mCRPC patients with prior orchidectomy and various hormone therapy showed specific localization of [177Lu]Lu-PSMA-617 in the tumor region. Conclusions: Formulation of a ready-to-use multidose formulation of [177Lu]Lu-PSMA-617 was successfully achieved and the procedure was optimized for routine preparation at a hospital radiopharmacy set-up. High degree of localization of [177Lu]Lu-PSMA-617 in post-therapy SPECT scan and the post-therapeutic response confirms its therapeutic efficacy. Clinical Trials.gov ID: RPC/51/Minutes/Final dated 16th October, 2019.

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of 90Y-DOTATATE Patient Dose.

Introduction: The quality control parameters of in-house-produced 90Y-Acetate from high-level liquid waste (HLLW) using supported liquid membrane (SLM) technology were validated and compared with the pharmacopeia standard. The radiolabeling of DOTATATE yielding 90Y-DOTATATE in acceptable radiochemical purity (RCP), with expected pharmacological behavior in in vivo models, establish the quality of 90Y-Acetate. Clinical translation of 90Y-Acetate in formulation of 90Y-DOTATATE adds support toward its use as clinical-grade radiochemical. Methods: Quality control parameters of 90Y-Acetate, namely radionuclide purity (RNP), were evaluated using ß- spectrometry, γ-spectroscopy, and liquid scintillation counting. RCP and metallic impurities were established using high-performance liquid chromatography and inductively coupled plasma optical emission spectrometry, respectively. The suitability of 90Y-Acetate as an active pharmaceutical ingredient radiochemical was ascertained by radiolabeling with DOTATATE. In vivo biodistribution of 90Y-DOTATATE was carried out in nude mice bearing AR42J xenografted tumor. Clinical efficacy of 90Y-DOTATATE was established after using in patients with large-volume neuroendocrine tumors (NET). Bremsstrahlung imaging was carried out in dual-head gamma camera with a wide energy window setting (100-250 keV). Results: In-house-produced 90Y-Acetate was clear, colorless, and radioactive concentration (RAC) in the range of 40-50 mCi/mL. RCP was >98%. 90Sr content was <0.85 µCi/Ci of 90Y. Gross λ content was <0.8 nCi/Ci of 90Y and no γ peak was observed. Fe3+, Cu2+, Zn2+, Cd2+, and Pb2+ contents were <1.7 µg/Ci. The radiolabeling yield (RLY) of 90Y-DOTATATE was >94%, RCP was >98%. The in vitro stability of 90Y-DOTATATE was up to 72 h postradiolabeling, upon storage at -20°C. Post-therapy (24 h) Bremsstrahlung image of patients with large NET exhibit complete localization of 90Y-DOTATATE in tumor region. Conclusions: This study demonstrates that the in-house-produced 90Y-Acetate from HLLW can be used for the formulation of various therapeutic 90Y-based radiopharmaceuticals. Since 90Y is an imported radiochemical precursor available at a high cost in India, this study which demonstrates the suitability of indigenously sourced 90Y, ideally exemplifies the recovery of "wealth from waste." The Clinical Trial Registration number: (P17/FEB/2019).

Sequential Duo-Peptide Receptor Radionuclide Therapy With Indigenous 90Y-DOTATATE and 177Lu-DOTATATE in Large-Volume Neuroendocrine Tumors: Posttherapy Bremsstrahlung and PET/CT Imaging Following 90Y-DOTATATE Treatment.

The efficacy of Lu-DOTATATE in large neuroendocrine tumors (NETs) is reduced because of the lower energy (Eßmax 0.497 MeV) and shorter range of Lu. The pure ß-emitter Y with its longer ß range is more effective in larger tumors. This should be balanced with the greater risk of Y-DOTATATE-related nephrotoxicity. Sequential duo-peptide receptor radionuclide therapy may result in a better response with minimal adverse effects in large-volume heterogeneous NETs. A 56-year-old man with large rectal NET liver metastases, treated with Y-DOTATATE and Lu-DOTATATE and sequential duo-peptide receptor radionuclide therapy, presented with post-Y-DOTATATE bremsstrahlung and PET/CT in comparison with Ga-DOTATATE PET/CT and Lu-DOTATATE scans.

Clinical Efficacy of Sodium [99mTc] Pertechnetate from Low Specific Activity 99Mo/99mTc Autosolex Generator in Hospital Radiopharmacy Centre.

BACKGROUND: Few nuclear reactors in the world producing high specific activity (HSA) 99Mo using enriched 235U (HEU), are aging and are planned for shut down in the near future. Further, HEU will not be freely available, due to safeguards, and the technology for 99Mo from low-enriched 235U (LEU) is not yet widely accepted since 239Pu contamination in the product is an issue. Production of 99mTc from low specific activity (LSA) 99Mo obtained from 98Mo(n,)99Mo reaction in research reactor and 100Mo(,n)99Mo reaction in accelerator or directly from 100Mo(p,2n)99mTc nuclear reaction in cyclotron, has been explored [1]. The methyl ethyl ketone (MEK) based solvent extraction technique is n well known method for the separation of 99mTc from low specific activity 99Mo. The 99Mo/99mTc autosolex generator [2], a computer controlled automated module, utilizes the conventional MEK solvent extraction method for extraction of 99mTc. Herein, we have validated the usage of autosolex for preparation of pharmacopoeia grade 99mTcO4- from 7.40-27.5 GBq of LSA 99Mo-SodiumMolybdate (99MoO42-) solution and validated the quality of the 99mTcO4- by preparing wide range of 99mTc-radiopharmaceuticals (99mTc-RP). MATERIALS AND METHODS: The 99mTcO4- was extracted from the autosolex as described in [2] starting from 7.40-27.5 GBq of LSA 99MoO42- and subjected to the required physico-chemical and biological quality control (QC) tests. The eluted 99mTcO4- labeled various fourth generation 99mTc radiopharmaceuticals cold kits (99mTc-cold kits) apart from regular 99mTc-cold kits in our centre. Various 99mTc-RP extracted 99mTcO4- using standard procedures [3] were prepared and subjected to required QC as Indian Pharmacopeia monograph [4] and used in scintigraphic imaging in patients. The radiation exposure dose to the operator were compared between autosolex and manual MEK based solvent extraction generator. RESULTS: The extracted 99mTcO4- from autosolex is a clear and colorless solution with pH between 5.0-6.5. The elemental molybdenum (Mo) and aluminum (Al) content <10µg/mL, MEK levels <0.1%, 99Mo breakthrough <0.030% and radiochemical purity (RCP) >98%. All the extracted 99mTcO4- batches complies sterility test, endotoxin limit (EL) <5EU/mL. The RCP of all the labeled 99mTc-RP >95%. The autosolex delivers much less radiation dose to the operator than the convention manually handled MEK based solvent extraction generator. CONCLUSIONS: Autosolex Generator was successfully used to obtain pharmaceutical grade 99mTcO4- from LSA 99MoO42- and generator is safe in radiological and pharmacological point of view. The suitability of the autosolex for use in hospital radiopharmacy was shown by using the 99mTcO4- to prepare various 99mTc-RP and using these 99mTc-RP for scintigraphic imaging in patients.

Radiochemical studies, pre-clinical investigation and preliminary clinical evaluation of 170Tm-EDTMP prepared using in-house freeze-dried EDTMP kit.

The objective of the present work is to formulate 170Tm-EDTMP using an in-house freeze-dried EDTMP kit and evaluate its potential as a bone pain palliation agent. Patient dose of 170Tm-EDTMP was prepared with high radiochemical purity using the lyophilized kit at room temperature within 15min. Pre-clinical evaluation in normal Wistar rats revealed selective skeletal accumulation with extended retention. Preliminary clinical investigation in 8 patients with disseminated skeletal metastases exhibited selective uptake in the bone and retention therein for a long duration.

Limulus amebocyte lysate testing: adapting it for determination of bacterial endotoxin in 99mTc-labeled radiopharmaceuticals at a hospital radiopharmacy.

UNLABELLED: A bacterial endotoxin test (BET) is required to detect or quantify bacterial endotoxin that may be present in radiopharmaceutical preparations. The test uses Limulus amebocyte lysate, which, in the presence of bacterial endotoxin and divalent calcium ions, causes the formation of a coagulin gel. (99m)Tc-labeled radiopharmaceuticals have chelating ligands such as diethylene triamine pentaacetic acid (DTPA), ethylene dicysteine (EC), L,L-ethyl cysteinate dimer (ECD), N-[2,4,6-trimethyl-3 bromoacetanilid] iminodiacetic acid (mebrofenin), dimercapto succinic acid-III (DMSA-III), dimercapto succinic acid-V (DMSA-V), and several others, which form a coordination complex with Na-(99m)Tc-O4 in the presence of reducing agents. During BET by the gel-clot method, the free sulfhydryl (-SH) and carboxyl (-COOH) in some of the chelating agents in the final (99m)Tc-labeled radiopharmaceuticals decrease the free divalent calcium ion concentration, which in turn inhibits coagulin gel formation. This study was designed using the premise that addition of calcium chloride solution to the reaction mixture would nullify this effect. METHODS: We present here the data obtained from BET assay analysis of (99m)Tc-labeled radiopharmaceuticals and the cold kits from which they are made (EC, ECD, methoxyisobutylisonitrile, DTPA, mebrofenin, methylene diphosphonic acid [MDP], DMSA-III, and DMSA-V) using 2 different dilutions, maximum valid dilution (MVD) and half maximum valid dilution (MVD/2), with and without the addition of calcium chloride at a final concentration of 300 µM. RESULTS: It was observed that at MVD and MVD/2 all of the (99m)Tc-labeled kits exhibited interference in coagulin gel formation with the exception of (99m)Tc-methoxyisobutylisonitrile, (99m)Tc-MDP, (99m)Tc-mebrofenin, and (99m)Tc-ECD. However, only the cold kits of methoxyisobutylisonitrile and MDP did not show inhibition. An addition of calcium chloride solution nullified this interference at both MVD and MVD/2 in all of the (99m)Tc-labeled radiopharmaceuticals in which interference was observed. CONCLUSION: In practice, Limulus amoebocyte lysate testing is not a method of choice for (99m)Tc-labeled radiopharmaceuticals because these radiopharmaceuticals exhibit interference. However, our study proves the hypothesis that the addition of calcium chloride can circumvent this problem. The addition of calcium chloride provides an enhanced biologic quality control testing option for the final formulation of (99m)Tc-labeled radiopharmaceuticals at the hospital radiopharmacy end.