DOSAGE AND ADMINISTRATION
Sodium Pertechnetate Tc 99m Injection is usually
administered by intravascular injection. For imaging the urinary bladder and
ureters (direct isotopic cystography), the Sodium Pertechnetate Tc 99m
Injection is administered by direct instillation aseptically into the bladder
via a urethral catheter, following which the catheter is flushed with
approximately 200 mL of sterile saline directly into the bladder. The dosage
employed varies with each diagnostic procedure. When imaging the nasolacrimal
drainage system, instill the Sodium Pertechnetate Tc 99m Injection by the use
of a device such as a micropipette or similar method which will ensure the
accuracy of the dose.
The suggested dose range employed for various diagnostic
indications in the average ADULT PATIENT (70kg) is:
- Vesico-ureteral Imaging 18.5 to 37MBq (0.5 to 1mCi)
- Thyroid Gland Imaging 37 to 370MBq (1 to 10mCi)
- Salivary Gland Imaging 37 to 185MBq (1 to 5mCi)
- Nasolacrimal Drainage System Maximum 3.7MBq (100μCi)
The recommended dosage range in PEDIATRIC PATIENTS is:
- Vesico-ureteral Imaging 18.5 to 37MBq (0.5 to 1mCi)
- Thyroid Gland Imaging 2.22 to 2.96MBq (60 to
80μCi)/kg body weight
The patient dose should be measured by a suitable
radioactivity calibration system immediately prior to administration of the
dose.
Parenteral drug products should be inspected visually for
particulate matter and discoloration prior to administration whenever solution
and container permit. The solution to be administered as the patient dose
should be clear and contain no particulate matter. Do not use an eluate of the
TECHNELITE®, Technetium Tc 99m Generator later than one (1) working
day after elution (12 hours).
Radiation Dosimetry
The estimated absorbed radiation doses to an average
ADULT and Pediatric patient from an intravenous injection of a maximum dose of
1110MBq (30 millicuries) of Sodium Pertechnetate Tc 99m Injection distributed
uniformly in the total body are shown in Tables 5 and 6.
Table 5: Adult Absorbed Radiation Doses (mGy) from
Intravenous Injection
Organ |
Absorbed Radiation Dose (mGy) for a 1110 MBq (30mCi) dose |
Adrenals |
4.1 |
Urinary Bladder Wall |
20 |
Bone Surfaces |
6.2 |
Brain |
2.2 |
Breasts |
2 |
Gallbladder Wall |
8.3 |
Stomach Wall |
29 |
Small Intestine |
18 |
ULI Wall |
63 |
LLI Wall |
23 |
Heart Wall |
3.5 |
Kidneys |
6 |
Liver |
4.7 |
Lungs |
2.9 |
Muscle |
3.6 |
Ovaries |
11 |
Pancreas |
6.3 |
Red Marrow |
4.1 |
Skin |
2 |
Spleen |
4.8 |
Testes |
3.1 |
Thymus |
2.7 |
Thyroid |
24 |
Uterus |
9 |
Remaining Tissues |
3.9 |
Effective Dose (mSv) |
14 |
To obtain radiation absorbed
dose in rads (30 mCi dose) from the above table, divide individual organ values
by a factor of 10 (does not apply for effective dose).
Table 6: Pediatric Absorbed
Radiation Doses (mGy) from Intravenous Injection
Age |
15 years |
10 years |
5 years |
1 year |
Administered activity in MBq (mCi) |
1110 (30) |
740 (20) |
555 (15) |
370 (10) |
Organ |
Adrenals |
5.3 |
5.4 |
6.2 |
7.1 |
Urinary Bladder Wall |
26 |
22 |
18 |
22 |
Bone Surfaces |
7.6 |
7.5 |
8.1 |
10 |
Brain |
2.8 |
3.1 |
3.7 |
4.5 |
Breasts |
2.6 |
2.6 |
3.2 |
4.1 |
Gallbladder Wall |
11 |
12 |
13 |
13 |
Stomach Wall |
38 |
36 |
43 |
59 |
Small Intestine |
22 |
23 |
26 |
30 |
ULI Wall |
81 |
89 |
110 |
140 |
LLI Wall |
31 |
33 |
40 |
48 |
Heart Wall |
4.5 |
4.6 |
5.2 |
6.4 |
Kidneys |
7.2 |
6.9 |
7.8 |
8.5 |
Liver |
6 |
6.7 |
8 |
9.1 |
Lungs |
3.8 |
3.8 |
4.4 |
5.3 |
Muscle |
4.5 |
4.5 |
5 |
6 |
Ovaries |
14 |
13 |
14 |
17 |
Pancreas |
8.1 |
8.2 |
8.9 |
10 |
Red Marrow |
5.1 |
5 |
5.2 |
6 |
Skin |
2.5 |
2.6 |
3.2 |
3.8 |
Spleen |
6 |
6 |
6.7 |
7.8 |
Testes |
4.1 |
4.3 |
4.9 |
6 |
Thymus |
3.6 |
3.5 |
4.2 |
5.3 |
Thyroid |
40 |
41 |
67 |
81 |
Uterus |
11 |
11 |
12 |
14 |
Remaining Tissues |
4.8 |
4.8 |
5.4 |
6.4 |
Effective Dose (mSv) |
19 |
19 |
23 |
29 |
To obtain radiation absorbed
dose in rads (30 mCi dose) from the above table, divide individual organ values
by a factor of 10 (does not apply for effective dose). |
The estimated absorbed
radiation doses to an average ADULT from the instillation of Sodium
Pertechnetate Tc 99m Injection for imaging the nasolacrimal drainage system are
shown in Table 7.
Table 7: Absorbed Radiation Dose from
DacryoscintigraphyUsing Sodium Pertechnetate Tc 99m
Target Organ |
Absorbed Dose mGy/ 3.7MBq |
(rad/ 100μCi) |
Eye Lens: |
|
|
If lacrimal fluid turnover is 16%/min |
0.140 |
0.014 |
If lacrimal fluid turnover is 100%/min |
0.022 |
0.002 |
If drainage system is blocked |
4.020 |
0.402 |
Total Body* |
0.011 |
0.001 |
Ovaries* |
0.030 |
0.003 |
Testes* |
0.009 |
0.001 |
Thyroid* |
0.130 |
0.013 |
* Assuming no blockage of drainage
system |
In pediatric patients, an
average 30 minute exposure to 37MBq (1 millicurie) of Sodium Pertechnetate Tc
99m Injection following instillation for direct cystography, results in an
estimated absorbed radiation dose shown in Table 8.
Table 8: Pediatric Absorbed
Radiation Dose from Cystography
Age |
Bladder wall dose, mGy (rad) |
Gonadal dose, mGy (rad) |
1 year |
3.6 (0.36) |
0.15 (0.015) |
5 years |
2.0 (0.2) |
0.095 (0.0095) |
10 years |
1.3 (0.13) |
0.066 (0.0066) |
15 years |
0.92 (0.092) |
0.046 (0.0046) |
HOW SUPPLIED
Lantheus Medical Imaging
TECHNELITE®, Technetium Tc 99m Generator is available in the following
quantities of radioactivity: 37.0 (NDC #11994-090-36), 74.0 (NDC
#11994-090-73), 92.5 (NDC #11994-090-92), 111.0 (NDC #11994-090-01), 148.0 (NDC
#11994-090-03), 166.5 (NDC #11994-090-04), 185.0 (NDC #11994-090-05), 222.0
(NDC #11994-090-06), 277.5 (NDC #11994-090-07), 370.0 (NDC #11994-090-09),
462.5 (NDC #11994-090-10), 555.0 (NDC #11994-090-11), 666.0 (NDC #11994-090-12),
740 (NDC #11994-090-13) GBq (1, 2, 2.5, 3, 4, 4.5, 5, 6, 7.5, 10, 12.5, 15 18,
20 Ci) of Mo99 on the calibration date (date of manufacture) as specified on
the product lot identification label affixed to the generator. Each generator
is supplied with the following standard components:
1 Collect Needle Seal Vial
6 Eluant Charge Vials (may be supplied separately)
6 Eluate Collection Vials (may be supplied separately)
1 Package Insert 6 Radiation Labels (Collection Vial)
6 Radiation Labels (Eluting Shield)
First order generators are shipped with the following
accessory components:
2 Eluting Shields
Extra quantities of these components may be obtained at
the customer's request.
Storage
Controlled room temperature 20° to 25°C (68° to 77°F)
[See USP].
Expiration
The expiration time of the Sodium Pertechnetate Tc 99m
solution is not later than 12 hours after elution. If the eluate is to be used
to reconstitute a kit for the preparation of a Technetium Tc 99m radiopharmaceutical,
the kit should not be used after 12 hours from time of Generator elution or
after the expiration time stated on the labeling for the prepared drug,
whichever is earlier.
The generator should not be used after the expiration
date stated on the label.
Elution Instructions -Total Elution Method
- Waterproof gloves should be worn during elution.
- Remove dust (clear plastic) cover of generator.
- Perform all subsequent operations aseptically.
- Remove silicone needle seal from eluant charge well. Discard
as radioactive waste.
- Remove flip-off seal and swab septum of eluant charge
vial with a bactericide (such as 70% isopropyl alcohol), allow to dry, and
insert the vial into charge well. Vial should be firmly inserted to assure
puncture of septum. Caution: Excessive use of bactericides containing alcohol
may adversely affect Technetium Tc99m yield.
- Open elution shield base and insert an eluate collection
vial from which the flip-off seal has been removed. Screw base back on
securely. Swab the exposed vial septum with a bactericide and allow to dry.
- Remove vented needle cover from collect well. Discard as
radioactive waste.
- Insert shielded eluate collection vial in collect well.
Elution should commence within 30 seconds and can be visually checked by the
appearance of bubbles in the eluant charge vial.**
**NOTE: If bubbles do not appear in the eluant charge vial within 30
seconds, either one of the vials has not been properly placed on its needle or
the eluate vial has no vacuum. Remove the eluate collection vial to prevent
vacuum loss; then remove and reinsert the charge vial. Reinsert the eluate
collection vial and if elution does not commence, use a second shielded
collection vial.
Caution: Tampering with the internal components could compromise sterility
and present a radiation hazard. This generator should not be dismantled.
- To assure proper yield and functioning, elution must
proceed to completion as evidenced by emptying of the charge vial. Allow
generator to elute for at least 3 minutes after the charge has been drained, or
for a total of 6 minutes.
- After elution has been completed, remove shield
containing the collection vial. Obtain the collect needle seal vial, and using
a bactericide, swab the septum of the collect needle seal vial and insert over
the collect needle. The eluant vial is sterile and should stay in place until
the next elution, functioning as a seal for the needles within the charge well. Upon initiating the next elution, discard the empty eluant vial as
radioactive waste.
- Fill out and attach the appropriate supplied pressure
sensitive radioactivity labels to the elution shield containing the filled
eluate collection vial. Do not use an eluate of the Technetium Tc 99m Generator
later than 1 working day after the time of elution (12 hours).
- Use a shielded syringe when introducing the Sodium
Pertechnetate Tc 99m solution into mixing vials.
- Maintain adequate shielding during the life of the
radioactive preparation by using a lead vial shield and cover, and use a
shielded syringe for withdrawing and injecting the preparation.
Assay Instructions For The Technelite®,
Technetium Tc 99m Generator Eluate
The TECHNELITE®, Technetium Tc 99m Generator
Eluate may be assayed using an ionization chamber dose calibrator. The
manufacturer's instructions for operation of the dose calibrator should be
followed for measurement of Technetium Tc 99m and Molybdenum Mo99 activity in
the generator eluate. The Molybdenum 99/Technetium 99m ratio should be
determined at the time of elution prior to administration, and from that ratio,
the expiration time (up to 12 hours) of the eluate mathematically determined.
Each eluate should meet or exceed the purity requirements of the current United
States Pharmacopeia; that is, not more than 0.0056MBq (0.15 microcurie) of
Molybdenum 99 per 37MBq (1 millicurie) of Technetium 99m per administered dose
at the time of administration.
Radiometric Molybdenum Test Procedure
This method is based on the fact that most Technetium Tc
99m radiation can be readily shielded and only the more energetic gamma rays
from Molybdenum Mo99 (739KeV and 778KeV) are counted in the 550-850KeV energy
range. The entire eluate may be assayed for Molybdenum Mo99 activity as
follows:
- A Cesium Cs 137 reference source which has the same geometry
as the generator eluate must be used to standardize the well counter.
- Determine the background after setting the window to the
550-850KeV energy range.
- Count the Technetium Tc 99m eluate in its lead shield
(thereby shielding out Technetium Tc 99m) by placing over the well or probe.
- Count the Cs 137 reference source in the same shield
geometry for the same time period.
- Compute Molybdenum Mo99 activity in the eluate as
follows:
μCi Molybdenum Mo99 (total) = μCi simulated
Mo99 x net cpm Eluate /net cpm simulated Mo99 reference source
Divide this number by the mCi of Technetium Tc 99m. This
result (μCi Mo99/mCi Tc 99m) can be converted to MBq Mo99/MBq Tc 99m by
multiplying by 10-3. The U.S. Pharmacopeia and the U.S. Nuclear
Regulatory Commission or equivalent Agreement State regulations specify a limit
of 0.00015MBq Molybdenum Mo99 per MBq of Technetium Tc 99m (0.15μCi
Mo99/mCi Tc 99m) at the time of administration to each patient.
Colorimetric Aluminum Ion Test Procedure
Obtain an aluminum ion indicator kit and determine the
aluminum ion concentration of the eluate per the manufacturer's instructions.
The concentration must not exceed 10 micrograms per milliliter of eluate.
Disposal
All components shipped with the TECHNELITE®,
Technetium Tc 99m Generator should be monitored for contamination prior to
disposing into routine trash systems. The Technetium Tc 99m should not be
disposed of into routine trash systems. The generator should be disposed
through a USNRC or Agreement State licensed disposal agency or by a method approved
by the appropriate regulatory authority. Spent generators may be returned; complete
return instructions available on request.
This radioactive drug is approved for distribution to
persons licensed pursuant to the Code of Massachusetts Regulations 105 CMR
120.100 for the uses listed in 105 CMR 120.547 or 120.552 or under equivalent
regulations of the U.S. Nuclear Regulatory Commision, an Agreement State or a
Licensing State.
Lantheus Medical Imaging, 331 Treble Cove Road, N.
Billerica, MA 01862 USA