RADIATION LABORATORY REFERENCE MANUAL · 4 Internal Permits University of Waterloo researchers who...

RADIATION LABORATORY REFERENCE MANUAL

University of Waterloo Safety Office

http://www.rstp.uwaterloo.ca/ Updated June 2010

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Table of Contents

Radiation Safety Program Administration of Radiation Safety Program......................................................................3 Internal Permits .................................................................................................................4 Non-Compliance................................................................................................................4 Laboratory Classification ...................................................................................................5 Laboratory Signage ...........................................................................................................6

Radiation Exposure Dosimetry ..........................................................................................................................6 Exemption Quantities.........................................................................................................9 Conversion Table ..............................................................................................................10

Radiation Protection Contamination Survey Procedures ....................................................................................11 Direct Measurement of Contamination ..............................................................................12 Indirect Measurement of Contamination ............................................................................13 Instrument Selection..........................................................................................................14 Contamination Monitoring Records ...................................................................................15 Regulatory Limits of Contamination...................................................................................16 Classification of Radionuclides ..........................................................................................17 Decontamination Protocols................................................................................................18 Ordering Radioisotopes.....................................................................................................19 Inventory............................................................................................................................20 Waste Disposal..................................................................................................................21 Laboratory Procedures ......................................................................................................22

Emergency Procedures Emergency Contacts .........................................................................................................23 Spills Procedures...............................................................................................................24 Contaminated Personnel ...................................................................................................25 Air Release ........................................................................................................................25

Radiation Data Sheets Isotopes .............................................................................................................................26

Forms Contamination Monitoring..................................................................................................36 Inventory............................................................................................................................37

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Administration of Radiation Safety Program Acts and Regulations The Government of Canada controls the uses and possession of nuclear substances using the following legislative tools:

1. The Nuclear Safety and Control Act which created the Canadian Nuclear Safety Commission (CNSC). The CNSC has the authority to create and enforces radiation regulations based on the latest scientific information.

2. Regulations created under the Nuclear Safety and Control Act, which describe operation responsibilities of the various persons involved in the use and handling of radioisotopes.

3. Licence Conditions which are set by the CNSC and outline operational requirements specific to the type of activity. UW's conditions are for University research.

Radiation Safety Committee The Radiation Safety Committee's (RSC) overall responsibility is to monitor all aspects of radionuclide use on campus. The RSC is advisory to the Provost.

Radiation Safety Officer The Radiation Safety Officer shall administer the consolidated use license issued to the institution by the C.N.S.C. by overseeing and coordinating all aspects of radiation safety within the institution.

Permit Holders Permit Holders are responsible for the day to day supervision of the workers. All permits are approved by the RSC and issued by the RSO.

Duties and Responsibilities of Permit Holders 1. The permit holder shall insure workers and students working under their supervision: 2. receive radioisotope training and are authorized to work with radioisotopes, 3. follow the rules and regulations set out by C.N.S.C. and the University of Waterloo

Radiation Safety Committee, 4. report incidents of loss or theft to the Radiation Safety Officer ( Ext. 6268) 5. be provided with adequate facilities, equipment and supervision to ensure that workers

or students follow the rules and regulations set out by C.N.S.C. and the University of Waterloo Radiation Safety Committee;

6. maintain inventories of all radioactive materials as well as storage and disposal records for inspection by the Radiation Safety Officer,

7. maintain area monitoring and/or wipe test records for inspection by the Radiation Safety Officer,

8. and wear the appropriate radiation dosimetry and participate in prescribed bioassay programs.

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Internal Permits University of Waterloo researchers who wish to use radioisotopes in their work must apply for a UW Radioisotope Permit. Information about the research project, permit holder qualifications, laboratory facilities, type of radioisotopes used and equipment used to monitor contamination are collected on a Permit Application Form. The Permit Application Form is forwarded to the Radiation Safety Officer (RSO), the RSO inspects the laboratory completing a Design Compliance form, the application and Design Compliance Form are sent to the members of the Radiation Safety Committee for comment. Pending approval by the Radiation Safety Committee a UW Radioisotope Permit is issued by the Radiation Safety Officer. Internal permits are issued for a period not to exceed 2 years.

Non-Compliance The Nuclear Safety Control Act and Regulations, Nuclear Substance and Radiation Devices licence conditions and operating procedures outlined in this manual have been developed to ensure the health and safety of workers/students at UW. Non-compliance with these standard and statutes place the worker/student in contravention of federal law and UW's Policy 34 - Health, Safety and Environment. To insure compliance, the Radiation Safety Officer will inspect all laboratories using radioisotope al least 4 times per year. Infractions will be dealt with as follows:

1. The Radiation Safety Officer (RSO) may stop unsafe work at any time 2. First infraction by a worker will result in notification by the RSO of the infraction to the

Permit Holder and a verbal warning to the worker/student. 3. A repetition of the infraction, the RSO notifies the Permit Holder and worker of to the

consequences of a second repetition of the infraction and instructs the worker to undergo retraining prior to resuming work with radioisotopes.

4. A second repetition of the infraction, the Radiation Safety Officer will ask the Permit Holder to prohibit the worker/student from working with radioisotopes for a period of time to be determined by the Radiation Safety Committee or alternatively the Permit Holder and all workers/students working with radioisotopes may under go retraining.

5. Refusal of the Permit Holder to enforce these penalties will result in removal of the Radioisotope Permit by the Radiation Safety Committee.

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Laboratory Classification A laboratory in which more than one "Exempt Quantity" of a nuclear substance is used will be designated a Basic, Intermediate or High Level.

Laboratory Designation 1. Non Regulated if the total quantity of radioisotopes stored or used does not exceed the

Exempt Quantity Limit for the radioisotope 2. Basic Level laboratory if the largest quantity of radioisotopes stored or used does not

exceed 5 ALI. 3. Intermediate Level laboratory if the largest quantity of radioisotopes stored or used does

not exceed 50 ALI. 4. High Level laboratory if the largest quantity of radioisotopes stored or used does not

exceed 500 ALI

Maximum Quantities of radioisotopes and Vial Sizes Vial size limits for the various classifications of labs

Vial limit Basic Level (5 x ALI)

Vial limit Intermediate Level (50 x ALI) Isotope

Exempt Quantity MBq

Exempt Quantity uCi

ALI estimate (ingestion) MBq/year mCi MBq mCi MBq

H – 3 1000 27000 1,000.00 135.00 5,000.00 1350.000 50,000.00 C – 14 100 2700 34.00 4.59 170.00 45.900 1,700.00 P – 32 0.01 0.27 8.00 1.08 40.00 10.800 400.00 P – 33 1 27 80.00 10.80 400.00 108.000 4,000.00 S – 35 100 2700 26.00 3.51 130.00 35.100 1,300.00 Cl – 36 0.01 0.27 20.00 2.70 100.00 27.000 1,000.00 Ca – 45 1 27 20.00 2.70 100.00 27.000 1,000.00 Fe – 59 0.1 2.7 10.00 1.35 50.00 13.500 500.00 I – 125 1 27 1.00 0.135 5.00 1.350 50.00

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Laboratory Signs 1. Rooms containing more than 100 Exempt Quantities of radioisotopes marked with:

a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO for labels

b. Procedure poster InfolO42I/Revl c. UW radioisotope permit. d. Copy of the Current UW Radioisotope Licence.

2. Areas where the radiation field is in excess of 25 mSv/hr (2.5 mR/hr) marked with a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO

for labels b. The rate of ionizing radiation in R/hr or Sv/hr.

3. Equipment containing more than 1 Exempt Quantity: a. Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO

for labels b. The name of the radioisotopes. c. The quantity in Bq or Ci. d. Contact person.

4. Storage areas where radioisotopes such as refrigerators and freezers are to be marked with Radiation Warning Symbol and the words "Radiation Hazard " Contact the RSO for labels

5. Work Areas and radioactive materials, contaminated equipment are to be clearly identified with radioactive warning tape. (Tape available from Chemistry Stores)

6. Misuse (marking non radioactive material) of radioactive warning tape or signs is a federal offence.

Dosimetry Requirements for Dosimetry

1. Both external and internal exposures may be monitored using dosimetry and bioassays.

2. The following are the dosimetry requirements for the University of Waterloo: a. Persons working with radioisotopes that are external radiation hazards (i.e. 32P)

will be issued a TLD (Thermal Luminescence Badge). b. Ring Badges will be worn by radioisotope workers handling more than 50 MBq of

Phosphorous32, Strontium89, Strontium90 or Yttrium90. c. Neutron dosimetry will be worn by radioisotope workers handling unshielded

neutron sources in excess of 20 GBq.

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3. Radioisotope workers using 125I or 131I in the following manner must participate in a

bioassay program:

*Processes which involve the generation of significant quantities of volatile iodine must be carried out in a fume hood. 4. All records of dosimetry will be kept by the Radiation Safety Officer in the Safety Office

and available for inspection at anytime. 5. The University of Waterloo shall ensure that the effective dose received by and

committed to a person described in the table below (Effective Dose Limits) is not exceeded. Effective dose is derived from the total dose received from all sources within the body (i.e. ingested or inhaled radioisotopes plus the doses from external radiation man made sources and x-rays)

6. Persons expected to receive a dose in excess of 1.0 mSv per year whole body will be designated as Nuclear Energy Workers (NEW). Workers performing general laboratory tasks related to university research would not receive a whole body dose in excess of 1 mSv per year and therefore would not be designated as Nuclear Energy Workers.

7. The University of Waterloo shall ensure that the equivalent dose received by and committed to an organ or tissue set out in Table Equivalent Dose Limits is not exceeded.

Equivalent Dose Limits to Organs Organ Nuclear Energy Worker Other WorkersLens of eye 150 mSv 15 mSv Hands and feet 500 mSv 50 mSv Skin 500 mSv 50 mSv

Operation Maximum Activity

*Open Bench 5 MBq Fume Hood 50 MBq Glove Box (vented) 500 MBq Involved in a spill 5 MBq External contamination any

Effective Dose Limits Nuclear Energy Worker Pregnant Nuclear

Energy Worker Other Workers

One Year Dosimetry Period

Five Year Dosimetry Period

Balance of Pregnancy

One Calendar Year

50 mSv 100 mSv 4 mSv 1 mSv

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8. Every female nuclear energy worker who becomes aware that she is pregnant shall immediately inform the University of Waterloo Radiation Safety Officer in writing.

9. The University of Waterloo shall make accommodation to ensure that the effective dose to the pregnant worker dose does not exceed 4 mSv for the duration of the pregnancy.

10. All workers must apply the ALARA principle when working with radioisotopes to ensure that they receive the lowest possible dose of ionizing radiation.

Action Levels 1. Any dose exceeding 0.2 mSv will be reported to the worker. 2. Any dose exceeding 0.5mSv the Radiation Safety Officer will::

a. conduct an investigation to determine the magnitude of the dose and to establish the causes of the exposure;

b. identify and take any action required to prevent the occurrence of a similar incident; and

c. report the findings to the worker and the Radiation Safety Committee. 3. When the University of Waterloo becomes aware that a dose of radiation received by

and committed to a person or an organ or tissue may have exceeded the dose limits in table Effective Dose Limits or table Equivalent Dose Limits to Organs. The Radiation Safety Officer will:

a. immediately notify the worker and the Canadian Nuclear Safety Commission of the dose;

b. require the person to leave any work that is likely to add to the dose; c. conduct an investigation to determine the magnitude of the dose and to establish

the causes of the exposure; d. identify and take any action required to prevent the occurrence of a similar

incident; and e. within 21 days after becoming aware that the dose limit has been exceeded,

report to the Canadian Nuclear Safety Commission the results of the investigation or on the progress that has been made in conducting the investigation; and report the findings to the worker and the Radiation Safety Committee.

4. If thyroid screening detects more than 10 kBq of I -125 or I -131 a. a preliminary report shall be made immediately to the Canadian Nuclear Safety

Commission b. have a bioassay performed on the worker with in 24 hours by a person licensed

by the Canadian Nuclear Safety Commission. c. conduct an investigation to determine the magnitude of the dose and to establish

the causes of the exposure; d. identify and take any action required to prevent the occurrence of a similar

incident; and e. report the findings to the Canadian Nuclear Safety Commission, the Radiation

Safety Committee and the worker.

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Exemption Quantities Exemption Quantities are the amounts, which if exceeded come under the control of the Nuclear Safety and Control Act. This quantity is also used to define various regulator criteria. Exemption Quantities of Various Radioisotopes

Isotope Quantity Bq Americium 241 1 x 10 3

Americium 243 1 x 10 3

Antimony 124 1 x 10 4

Antimony 125 1 x 10 5

Arsenic 73 1 x 10 5

Arsenic 74 1 x 10 4

Arsenic 76 1 x 10 4

Barium 131 1 x 10 5

Barium 133 1 x 10 5

Barium 140 1 x 10 4

Beryllium 7 1 x 10 6

Bismuth 206 1 x 10 5



Bromine 82 1 x 10 5

Cadmium 107 1 x 10 7


Cadmium 113 m 1 x 10 4


Cadmium 115 m 1 x 10 4

Calcium 45 1 x 10 6

Calcium 47 1 x 10 4

Carbon 11 1 x 10 5

Carbon 14 1 x 10 8

Cerium 139 1 x 10 6

Cerium 141 1 x 10 6

Cerium 144 1 x 10 5

Cesium 134 1 x 10 5

Cesium 134 m 1 x 10 7

Cesium 137 1 x 10 4

Chlorine 36 1 x 10 4

Chlorine 38 1 x 10 4

Chromium 49 1 x 10 5

Chromium 51 1 x 10 6

Cobalt 56 1 x 10 5

Cobalt 57 1 x 10 5

Cobalt 58 1 x 10 5

Cobalt 58 m 1 x 10 7

Isotope Quantity BqCobalt 60 1 x 10 5

Copper 60 1 x 10 5

Copper 64 1 x 10 5

Copper 67 1 x 10 5

Dysprosium 159 1 x 10 6

Erbium 169 1 x 10 6

Erbium 171 1 x 10 4

Fluorine 18 1 x 10 4

Gadolinium 153 1 x 10 4

Gallium 67 1 x 10 6

Gallium 68 1 x 10 4

Germanium 68 1 x 10 4

Gold 195 1 x 10 5

Gold 198 1 x 10 4

Hydrogen 3 1 x 10 9

Indium 111 1 x 10 5

Indium 113 m 1 x 10 5

Indium 115 1 x 10 5

Iodine 123 1 x 10 7

Iodine 125 1 x 10 6

Iodine 129 1 x 10 6

Iodine 131 1 x 10 4

Iridium 192 1 x 10 4

Iron 52 1 x 10 4

Iron 55 1 x 10 6

Iron 59 1 x 10 5

Krypton 77 1 x 10 10



Lead 210 1 x 10 4

Magnesium 28 1 x 10 4

Manganese 52 1 x 10 5

Manganese 54 1 x 10 5

Mercury 203 1 x 10 5

Molybdenum 99 1 x 10 4

Nickel 59 1 x 10 8

Nickel 63 1 x 10 7

Nickel 65 1 x 10 4

Isotope Quantity BqNiobium 95 1 x 10 5

Nitrogen 13 1 x 10 5

Oxygen 15 1 x 10 6

Phosphorous 32 1 x 10 4

Phosphorous 33 1 x 10 6

Polonium 210 1 x 10 4

Potassium 42 1 x 10 4

Promethium 147 1 x 10 7

Radium 226 1 x 10 4

Rubidium 86 1 x 10 4

Samarium 153 1 x 10 4

Scandium 46 1 x 10 5

Scandium 47 1 x 10 5

Selenium 75 1 x 10 5

Selenium 79 1 x 10 7

Sodium 22 1 x 10 4

Sodium 24 1 x 10 4

Strontium 85 1 x 10 5

Strontium 87 m 1 x 10 5



Sulphur 35 1 x 10 8

Technetium 99 1 x 10 6

Technetium 99 m 1 x 10 7

Thallium 201 1 x 10 6

Thallium 204 1 x 10 4

Thorium 232 1 x 10 2

Tin 113 1 x 10 5

Uranium dispersible 1 x 10 4

Uranium non-dispersible 1 x 10 7

Xenon 123 1 x 10 11

Xenon 129 m 1 x 10 11

Xenon 133 1 x 10 11

Xenon 135 1 x 10 10

Yttrium 90 1 x 10 4

Zinc 65 1 x 10 6

Zirconium 95 1 x 10 5

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Conversion Table

GRAY RAD 1 gray (Gy) 100 rad (rad) 1 milligray (mGy) 100 millirad (mrad) 1 microgray (µGy) 100 microrad (µrad) 1 nanogray (ηGy) 100 nanorad (η rad) RAD GRAY 1 kilorad (krad) 10 gray (Gy) 1 rad (rad) 10 milligray (mGy) 1 millirad (mrad) 10 microgray (µGy) 1 microrad (µrad) 10 nanogray (η Gy) REM SIEVERT 1 kilorem (krem) 10 sievert (Sv) 1 rem (rem) 10 millisievet (mSv) 1 millirem (mrem) 10 microsievert (µSv) 1 microrem (µrem) 10 nanosievert (η Sv) SIEVERT REM 1 sievert (Sv) 100 rem (rem) 1 millisievet (mSv) 100 millirem (mrem) 1 microsievert (µSv) 100 microrem (µrem) 1 nanosievert (η Sv) 100 nanorem (ηrem) CURIE BECQUEREL 1 kilocurie (kCi) 37 tetrabecquerel (TBq) 1 curie (Ci) 37 gigbecquerel (Gbq) 1 millicurie (mCi) 37 megabecquerel (MBq) 1 microcurie (µCi) 37 kilobecquerel (kBq) 1 nanocurie (η Ci) 37 becquerel (Bq) BECQUEREL CURIE 1 tetrabecquerel (TBq) 27 curie (Ci) 1 gigbecquerel (GBq) 27 millicurie (mCi) 1 megabecquerel (MBq) 27 microcurie (µCi) 1 kilobecquerel (kBq) 27 nanocurie (ηCi) 1 becquerel (Bq) 27 picocuries (pCi)

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Contamination Survey Procedures Method of Measurement Radioactive contamination may be measured directly or indirectly. Direct measurement means the use of portable radiation detection instruments to detect both fixed and removable decontamination. Direct measurement may be used when background radiation levels are negligible and the detector has sufficient sensitivity. Indirect measurement detects removable contamination by means of wipe tests but usually have higher sensitivity and will work in areas with high background. Method of contamination monitoring must be approved by the RSO. Locations of Measurement The locations that are to be monitored should be numbered on a plan of the radioisotope work area. These locations should include working surfaces, such as benches, counter tops, fume hoods, etc., storage areas, and non-working surfaces such as floors, instruments and equipment, door handles, light switches, sink taps and telephone receivers. Several random locations should also be monitored. Too rigid a set of locations may overlook problem areas. Instrument Checks and Calibration Non-portable instruments used for counting wipes, such as liquid scintillation counters, well-crystal type gamma counters, gas-flow proportional counters, semiconductor gamma spectrometers and gamma cameras, should be routinely serviced according to the manufacturer's instructions. Keep a record of the service information and dates. Portable contamination survey meters are checked for efficiency annually by the RSO. Before monitoring for contamination, portable instruments should be given operational checks as specified by the manufacturer (i.e. Battery check, high-voltage check, response check, etc.) And the background radiation level should be measured. Record the operational checks and background measurement. Similarly, non-portable instruments used to count wipes should count and record a blank and standard with each set of wipes. Frequency of Monitoring Monitoring is to be completed at least once per week when working with radioisotopes. The Contamination Survey Forms are to be completed and available at all times for inspection by the RSO and CNSC. Your work area should be surveyed with a survey meter during and at the end of each workday or work period(note: low energy Beta emitters such as 3H can not be monitored using a survey meter). This ensures that radioactive contamination is not inadvertently spread about or taken home. The results of these surveys do not have to be recorded.

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Direct Measurement of Contamination Depending upon the detector and the radioisotopes, direct measurement is often convenient for monitoring large areas. Direct measurement instrument readings include both fixed and non-fixed contamination. Thus a reading, which satisfies the licence criteria, gives a conservative estimate of non-fixed contamination.

1. Monitor the locations marked on the plan of the working area by slowly passing the detector over each area.

2. Keep the detector face towards the surface being monitored and keep the distance between the detector and the surface as small as possible without touching (and possible contaminating) the detector.

3. If contamination is detected, stop and obtain a measurement. Clean the area until the instrument is below the licence criteria. A reading in excess of licence criteria after repeated cleaning is an indication of fixed contamination or a high radiation background.

4. Identify and mark the contaminated area on the plan. 5. Record the highest measurement for each area and the final measurement after

decontamination.

Calculating Fixed Contamination The readings from contamination metres can be related to regulatory criteria if the efficiency of the instrument for a specific radioisotope is known. For mixtures of radioisotopes, do all calculations using the radioisotope for which the instrument has the lowest detection efficiency. Using the following equation, calculate the measurement results in Bq/cm2

WHERE: N = is the total count rate in counts per minute (CPM) measured directly or on the wipe. Nb = is the normal background count rate (in CPM) from the survey instrument. E = is the instrument efficiency factor (expressed as a decimal, i.e. for 26% efficiency, E = 0.26) for the radioisotope being measured. Efficiency for each isotope is determined by the RSO 60 = sec/min A = area or the detector in cm2

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Indirect Measurement of Contamination Indirect measurement of contamination is used when portable instruments are not sensitive enough or when the radiation background is too high. Indirect methods can only be used to monitor non-fixed or removable contamination. This is the most common method of contamination measurement used at the University of Waterloo.

1. Wear protective disposable gloves and a lab coat. 2. Wipe each of the locations shown on the plan of the working area with a filter paper

lightly moistened with alcohol or water. Use one numbered wipe per location. One "screening" wipe can be used to monitor several locations. If contamination is found, the areas must be identified and decontaminated.

3. Wipe an area of 100 cm2. Using uniform and constant pressure, ensure the entire area is wiped.

4. If necessary, carefully dry the wipe to prevent loss of activity. Since the contamination may be absorbed into the wipe material, the use of a wetting agent may lead to a significant underestimate of alpha and low-energy beta (3H) contamination with some counting methods.

5. Count the wipes in a low-background area and record all results. 6. If the wipes are to be counted on a contamination meter, the wipe should be smaller

than or equal to the sensitive area of the detector. 7. Record results on a contamination monitoring form before and after decontamination. 8. Clean any contaminated areas and re-monitor.

Calculating Removable Activity The readings from non-portable instruments can be related to regulatory criteria if the efficiency of he instrument for a specific radioisotope is known. For mixtures of radioisotopes, do all calculations using the radioisotope for which the instrument has the lowest detection efficiency. Using the following equation, calculate the measurement results in Bq/cm2

WHERE: N = is the total count rate in counts per minute (CPM) measured directly or on the wipe. Nb = is the count rate of the blank (in CPM) E = is the instrument efficiency factor (expressed as a decimal, i.e. for 26% efficiency, E = 0.26) for the radioisotope being measured (consult the manufacturer) 60 = sec/min A = area wiped (not to exceed 100 cm2) F = is the collection factor for the wipe . Use a value of F = 0.1 (i.e., 10%).

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Instrument Selection Instrument selection for weekly wipe tests is to be approved by the RSO.

Beta Contamination Survey Meters (GM Meters) All radioisotope laboratories except those using exclusively 3 H or 63 Ni will have available a functioning survey meter. Most laboratories will use a GM meter with a pancake type probe. These GM type (Geiger Muller) meters are useful for detecting the spread of contamination but are not sensitive enough to detect low energy beta emitters below regulatory levels. This type of meter must not be used as a dose meter for gamma radiation or X-rays. Meters are to be tested by the RSO annually. They will be marked with the following:

GM Survey Meter Beta Counting Efficiency Energy 160 keV 300 keV 1.17 keV Efficiency 10% 33% 47%

Do not use mR/hr Scale Date_________ UW Safety Office

Gamma Survey Meters These meters are to be sent away annually for calibration. A gamma dose rate meter is available at the Safety Office.

Liquid Scintillation Counters Liquid scintillation counters are generally acceptable for most contamination monitoring. Their higher efficiency, low background and multiple sample counting makes them ideal for contamination survey work. Liquid Scintillation counters will easily meet regulator criteria for detection radioactive contamination.

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Contamination Monitoring Records Contamination monitoring records are used to audit a laboratories contamination control program. Monitoring records are a licence requirement and must be legible, complete and available for inspection by the RSO or CNSC at all times. Radiation Contamination Survey Forms are available from the RSO (Ian Fraser Ext 6268) or by downloading the forms as a PDF file Radiation Contamination Survey Forms from the "FORMS" section of the Radiation Safety Page. Below is an example of a completed contamination survey form.

RADIATION CONTAMINATION SURVEY FORM

BUILDING___HS____ ROOM___125_____ SURVEY EQUIPMENT Packard 7500 LSC

Name Ian Fraser Name Ian Fraser Name Date Nov. 27, 2000 Date Nov. 27, 2000 Date AREA

CPM Bg/cm2 AREA CPM Bg/cm2 AREA CPM Bg/cm2

1 45 1 1 2 44 2 2 3 53 3 3 4 42 4 4 5 61 5 5 6 6 6 7 7 7 8 1894 9.4 2 8 45 2 8 9 9 9 10 10 10 11 11 11 12 12 12 Bkg 42 Bkg 44 Bkg

Notes: 1. Wipe areas and equipment that has been used that week. Also do one or two random

areas. 2. If contamination in area or equipment is above regulatory limits, clean and re-wipe.

Place results in next row.

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Regulatory Limits of Contamination

Minimum Levels of Contamination 1. For control areas, removable surface contamination limit criteria averaging over an area

not exceeding 100 cm2 are as follows: a. 0.3 Becquerel per square centimeter averaged over an area not to exceed 100

square centimeters for all Class A Radionuclides; b. 3 Becquerel per square centimeter over an area not to exceed 100 square

centimeters for all Class B Radionuclides and c. 30 Becquerel per square centimeter over an area not to exceed 100 square

centimeters for all Class C Radionuclides.

2. For supervised public areas and for decommissioning, removable surface contamination limit criteria averaging over an area not exceeding 100 cm2 are as follows:

a. 0.3 Becquerel per square centimeter averaged over an area not to exceed 100 square centimeters for all Class A Radionuclides;

b. 3 Becquerel per square centimeter over an area not to exceed 100 square centimeters for all Class B Radionuclides and

c. 30 Becquerel per square centimeter over an area not to exceed 100 square centimeters for all Class C Radionuclides.

3. The dose rate due to fixed contamination does not exceed 0.5 mSv at 0.5 meter from any surface.

Frequency of Contamination Monitoring Contamination monitoring must be done as follows:

1. Basic Laboratories at least weekly 2. Intermediate laboratories at least weekly 3. High level Laboratories at least daily 4. After a spill or incident 5. Before equipment is released for non-radioactive use 6. Before decommissioning room for non-radioactive work

Records Records of all contamination measurements shall be maintained and available for inspection by the RSO or the C.N.S.C. for at least 3 years.

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Classification of Radionuclides Class A Radionuclides Na-22 Na-24 Co-60 Zn-65 Sb-124 Ir-192 Ta-182 All Alpha Emitter and their daughter isotope

Class B Radionuclides As-74 Fe-59 In-111 Sc-46 Sr-85 Au-198 Ga-67 In-114m Se-75 Sr-90 Br-82 Gd-153 Nb-95 Sm-153 Co-58 Hg-203 Rb-84 Sn-113 F-18 I-131 Rb-86 Sn-123

Class C Radionuclides Au-195m Cl-36 Kr-81m Re-188 TI-201 C-14 Co-57 Nb-98 Ru-103 Xe-127 Ca-45 Cr-51 Ni-63 S-35 Xe-133 Cd-109 H-3 P-32 Sr-89 Y-90 Ce-133 I-123 P-33 Tc-99 Yb-169 Ce-144 I-125 Re-186 Tc-99m

Note: Most commonly used radioisotopes used at UW are Class C.

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Decontamination Procedures for Areas and Equipment HEPA Vacuum High efficiency vacuum cleaning is good on dry porous surfaces and avoids water reactions. All dust must be filtered out using only HEPA filters and the machine is left contaminated. Hot Water and Detergent For spills covering small areas blot up liquid and rinse with hot water and detergent. Hot water and detergent may be used on glassware and clothing if immersed and agitated. This method is extremely effective if done immediately after the spill on a non-porous surface, but is ineffective for decontaminating large areas or long standing contamination. Decon 75 or Alconox Complexing agents are very effective on nonporous surfaces. To use make a solution of 3% complexing agent with water, spray surface with solution, keep moist for 30 minutes. Remove solution and rinse. Smaller objects can be immersed in solution. Complexing agents keep contamination in solution, are non-toxic and very effective but require long soaking time (30 minutes) and have little penetration power. Organic Solvents Contaminated organic material (oil, paint etc.) can be dissolved by immersion or applying solvent to the surface, and then blotting up the liquid and wiping clean. This method requires good ventilation because most solvents are flammable and toxic. Inorganic Acids Contaminated metal and deposits on porous surfaces can be decontaminated using inorganic acids. Immerse smaller objects or brush on in a 1-2 N acid solution then flush with water. The material must then be scrubbed with detergent water mixture and rinsed. Acids may cause excessive corrosion and are hazardous to skin and eyes. Abrasion (Old Dutch Steel Wool) Nonporous surfaces can be decontaminated using abrasives by abrading the surface. Apply abrasive to surface and rub then rinse with water. Use on non-porous surfaces.

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Ordering Radioisotopes

1. Fill out a Purchase Requisition (Systems Contract Orders will not be processed) and include:

a. UW internal permit number b. quantity in Bq or Ci c. Radioisotope.

2. Orders are not to exceed quantities or isotopes specified on UW internal permit. 3. Send Purchase Requisition to the Purchasing Department. 4. The Radiation Safety Officer (RSO) reviews orders for approval. 5. When ordering "equipment" which contains a radioisotope, state this fact on the

purchase order and provide information as noted above.

Receiving 1. All persons receiving radioactive material must successfully complete the UW

Transportation of Radioactive Material Training Course. 2. If upon receipt of a package containing radioactive material there is :

a. noticeable damage to the package b. leakage from the package c. packages without a UW Purchase Order d. mislabeled packages

3. Central Stores receiving personal will immediately notify UW Radiation Safety Officer Ian Fraser Ext 6268 If unavailable notify UW Police 4911

4. All goods marked with radioactive material labels are to be transferred to Greg Friday ESC Rm. 150.

5. On receipt of radioisotopes the contents are checked for leakage by the RSO/designate. 6. Any leakage will be reported immediately to the CNSC by the RSO. 7. The following sections of an inventory form will be completed by the RSO/designate:

a. Permit Holder b. Isotope c. Quantity d. Lot Number e. Material f. Date Received g. Vial id, if there are 2 or more vials with the same lot number h. Record of package contamination monitoring

8. Radioisotopes will be delivered with the inventory form directly to or picked up by the permit holder/designate.

9. A record of receipt will be maintained br the RSO/designate. 10. The permit holder shall:

a. Store the radioisotopes in a secure area(locked refrigerator, freezer or cabinet). b. Remove the inventory form from the package and make it available for

inspection. 11. If package is not checked for leaks by the RSO/designate, the contents must be

checked for leakage by the permit holder. Any leakage is to be reported immediately to the RSO (Ext. 6268)

20

Inventory 1. When a package is received remove the inventory form from the package and place in

your record book. 2. If no inventory form comes with the package, contact the RSO, check the package for

contamination and start an inventory form yourself. 3. UW inventory forms must be kept up to date and available for inspection by the RSO or

the CNSC. Information to include: a. Amount of radioisotope used b. User's initials c. Wipe test date d. Waste information e. Final disposal information

UNIVERSITY of WATERLOO RADIOISOTOPE INVENTORY Location ___HS 125____ Supervisor: __Fraser_______ Permit #: ___54___

Isotope: ______32 P______ Date Received (D/M/Y):__18/12/99______ Material: __CTP_ Lot #: ____Ad99Cxs______ Activity (mCi): _0.25_____ Vial Id:_______ Volume (μL): ___125____

Date Used User Initials

Wipe Test Date

Amount Used (μL)

Type of Waste

Waste Stream

% of material in each waste stream

Jan. 23, 2001

Jan. 26/2001 25 L 2 10

L 3 90 S 3 100 Jan.29,2001 Feb.2, 2001 45 L 2 10 L 3 90 S 3 100 Remainder to waste Feb 16, 20001

Type of Waste Waste Stream L= Aqueous O= Organic S=Solid A= Animal Carcass

1=Municipal Garbage 2= Municipal Sewer 3=U W Environmental Safety Facility 4= Other (specify)

Package Contamination___None Detected__ Signature___Ian Fraser___ PO No._43994_

21

Disposal of Radioisotopes Disposal limits for radioisotopes insure that no member of the public is exposed to any significant quantities of radioisotopes.

Liquid Waste 1. Liquid waste is to be separated according to isotope, placed in a 4L Jug supplied by the

Environmental Safety Facility (ESF). 2. Containers must not be more than 80% full. 3. No solid waste in the containers.

Containers are to be marked with a Radioactive Waste Label.

Solid Waste 1. Solid waste is to be separated according to isotope, placed in a 20 L Pails lined with a 6

mil poly bag supplied by the Environmental Safety Facility (ESF). 2. Containers must be closed tightly 3. No liquid waste in the containers. 4. Containers are to be marked with a Radioactive Waste Label. 5. Solid waste less than limits listed in table below may be disposed of in regular garbage.

Scintillation Vials 1. Scintillation vials are to be placed in a 20 L Pails lined with a 6 mil poly bag supplied by

the Environmental Safety Facility (ESF). Vials can be of any isotopes. 2. Pails must be closed tightly 3. Containers are to be marked with a Radioactive Waste Label.

Disposal Limits Radionuclide Solid Waste

MBq/kg Solid Waste uCi/kg

Liquid Waste MBq/L

Liquid Waste uCi/L

C-14 3.7 100 0.37 10 Cr-51 3.7 100 0.37 10 Fe-59 307 100 0.001 0.027 H-3 37 1000 3.7 100 I-125 0.037 1 0.0037 0.1 I-131 0.037 1 0.0037 0.1 P-32 0.37 10 0.01 0.27 P-33 1 27 1 27 S-35 0.37 10 0.037 1

22

General Laboratory Procedures

1. Keep laboratory locked when unattended. 2. All radioisotopes must be stored in a locked cabinet, refrigerator or freezer. 3. Keep active and inactive work separated as far as possible. 4. Mark radioactive work area and equipment with radioactive label tape. 5. Work over a spill tray lined with absorbent paper and in a fume hood or glove box when

working with dry powders or volatile substances. 6. Fume hood sash must be no higher than use indicator arrow. 7. Fume hoods are to be tested annually. 8. Use a flow indicator to insure that the fume hood is operational. 9. Mark storage areas with radioactive labels. 10. Use the minimum quantity of radioactivity possible. 11. Wear protective clothing, safety glasses and gloves when handling radioactivity. 12. Remove gloves, wash hands and monitor yourself and your work area before leaving an

active area. 13. Label containers of radioactive material clearly, indicating nuclide, total activity, date

and the level of radiation at the surface of the container. 14. Never eat, drink, smoke or apply cosmetics in an area where unsealed radioactivity is

handled. 15. Never work with unprotected cuts or breaks in the skin. 16. Never pipette radioactive solutions by mouth. 17. In order to assist the R.S.O. in exchanging TLD badges, please store them in a central

location when not in use. 18. To minimize the dose to the extremities, tongs or other remote handling equipment

should be used where appropriate. 19. Contamination monitoring must be done at least once per week while working with

radioisotopes. Records must be maintained and available for inspection. 20. Inventories of all radioisotopes must be carefully maintained and available for

inspection. 21. Glassware and equipment used for radioactive work must be segregated until it has

been decontaminated.

23

Emergency Contacts

Radiation Safety Officer • work

o On Campus Ext. 6268 o Off campus (519) 8884567 Ext. 6268

• home (519) 884-6354 • if unavailable contact UW Police

o On Campus Ext. 4911 o Off campus(519) 888-4911

Permit Holder Permit holders home phone number is located on the Radioisotope Permit

24

Emergency Procedures Spills General Precautions

1. Inform persons in the area that a spill has occurred. Keep them away from the contaminated area.

2. Cover the spill with absorbent material to prevent the spread of contamination.

Minor Spills (less than 1 Exempt Quantities)

1. If you feel comfortable in cleaning up the spill proceed, if not, contact the RSO for help. 2. Limit movement near the spill. 3. Put on 2 pairs of disposable gloves, lab coat and respiratory protection if required. 4. Mark the location of the spill with a wax pencil and begin approved decontamination

procedures as soon as possible. 5. Place absorbent paper on spill if wet 6. If spill is a powder, wet with water/organic solvent and place absorbent paper on wetted

material. 7. To avoid spreading the contamination, work from the outside of the spill towards the

centre. 8. Do not track contaminants away from the spillage area. 9. Place contaminated absorbent paper in sealable container and label. 10. Following decontamination, check the area for any residual contamination. Repeat

decontamination, if necessary, until contamination-monitoring results meet the radioisotope licence criteria. If the spill cannot be cleaned up call the Radiation Safety Officer at Ext. 6268 or contact UW Police Ext. 4911.

11. Report the spill and cleanup to the supervisor and the Radiation Safety Officer at Ext. 6268.

12. Record spill details, contamination-monitoring results and adjust inventory records.

Major Spills (More than 1 Exempt Quantities)

1. Clear the room. Persons not involved in the spill clean up should be prevented entry. 2. Call the Radiation Safety Officer at Ext.6268 ( do not leave a voice mail message). If

not in, contact UW Police at Ext. 4911. 3. Limit the movement of all personnel who may be contaminated until they are monitored. 4. Leave the fume hood running to minimize the release of volatile radioactive materials

into adjacent rooms and hallways. 5. Close off and secure the spill area to prevent entry. Post warning signs.

25

Contaminated Personnel Contact Radiation Safety Officer at Ext. 6268 or UW Police at Ext. 4911. Scan with survey metre to determine contaminated body areas.

1. If skin appears to be intact: a. wet hands and apply mild soap b. work up good lather, keep lather wet c. work lather into contaminated area by rubbing gently for 3 minutes d. rinse thoroughly with lukewarm water e. repeat above procedures twice, if necessary

2. If cuts, abrasions, or open wounds are observed: a. obtain medical assistance through the Radiation Medical Advisor b. dry clean the effected area with suction and swabs c. if skin is contaminated in the area of cuts, abrasions, or open wounds, use wet

swabs in a direction away from the area, taking care not to spread activity over body or into wound

3. If ingestion has occurred: a. obtain medical advice and/or assistance immediately from the Radiation Medical

Advisor

Release of Airborne Radioisotopes

1. If possible, cut off the release of radioactive material from the source into the environment.

2. Close windows and any doors to other areas, call Plant Operations to place building on 100% fresh air (Ext. 3793).

3. Contact Radiation Safety Officer at Ext. 6268 or UW Police Ext. 4911. 4. Evacuate personnel and prevent further personnel access to radiation area by closing

and locking doors. 5. Monitor all persons who may be contaminated and determine which persons may have

been exposed to external radiation and/or inhalation of radionuclides and to what degree.

6. Perform simple decontamination and obtain medical assistance promptly from the Radiation Medical Advisor.

7. The Radiation Safety Officer will submit a report if required to the C.N.S.C..

26

Tritium Data Sheet

Physical Characteristics Isotope 3H Half Life 12.26 Years Mode of Decay Beta 100% Energy Maximum 0.0186 MeV Average 0.0057 MeV Decay Product 3He

Biological Data Biological Half Life 30 Days Effective Half Life 12.0 Days Target Organ Body Fluids

Legislative Limits Exempt Quantity 1000 MBq (27 mCi) ALI Ingestion 1000 MBq (27 mCi) Sewage discharge (institutional Limit) 1,000,000 MBq/yr (2,7000 mCi/yr) Sewage discharge (laboratory limit) 3.7 MBq/L (100 uCi/L) Landfill discharge 37 MBq/kg (1.0 mCi/Kg)

Shielding Data Maximum range in air 6 mm Maximum range in water 6 x10-3 mm Shielding required None

Dose Rate from External Exposures The low energy Beta particle emitted by tritium is not an external radiation hazard, as it can not penetrate the skin or travel very far in air. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 0 mSv/hr 0.05 ml droplet 1 kBq = 0 mSv/hr

External Dose form a 1 MBq Source in: Point source at 30 cm = 0 mSv/hr 10 ml glass vial at 100 cm = 0 mSv/hr Contact with 5ml plastic syringe = 0 mSv/hr

Contamination Monitoring Method

Liquid scintillation Limits of Contamination

Controlled Areas = 300 Bq/cm2 Uncontrolled Areas = 30 Bq/cm2

Notes: Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much longer. Consider tritium as an example: tritiated water has an effective biological half-life of 12 days whereas tritiated thymidine has a 190 day half life. ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .

Handling Procedures 1. Disposable gloves and lab coat should be worn when handling 3H. 2. Use a spill tray and absorbent paper to contain spills. 3. Handle potentially volatile compounds in ventilated enclosures. 4. Bioassay must be done if 3H is used as follows :

Operation Tritiated Water Nucleic Acid Precursors Tritiated compounds Open Bench 400 MBq (10 mCi) 400 MBq (10 mCi) 4 GBq(100 mCi) Fume hood 700 MBq (19 mCi) 2 GBq (54 mCi) 20 GBq(540 mCi)

27

Carbon 14 Data Sheet Physical Characteristics

Isotope 14C Half Life 5730 Years Mode of Decay Beta 100% Energy Maximum 0.356 MeV Average 0.049 MeV Decay Product l4N

Biological Data Biological Half Life 12.0 Days Effective Half Life 10.0 Days Target Organ Fatty Tissue

Legislative Limits Exempt Quantity 100 MBq (2.7 mCi) ALI Ingestion 34 MBq (0.9 mCi) Sewage discharge (institutional Limit) 10,000 MBq/yr ( 270 mCi/yr) Sewage discharge (laboratory limit) 0.37 MBq/L(10 uCi/L) Landfill discharge 3.7 MBq/kg (100 uCi/L)

Shielding Data Maximum range in air 24 cm Shielding required None

Dose Rate from External Exposures The low energy Beta particle emitted by tritium is not an external radiation hazard, as it can not penetrate the skin or travel very far in air. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 3.2 10-1 mSv/hr 0.05 ml droplet 1 kBq = 2.7X 10-3 mSv/hr

External Dose form a 1 MBq Source in: Point source at 30 cm = 0 mSv/hr 10 ml glass vial at 100 cm = 0 mSv/hr Contact with 5ml plastic syringe = 0 mSv/hr

Contamination Monitoring Method Liquid scintillation Geiger Counter

Limits of Contamination Controlled Areas = 300 Bq/cm2 Uncontrolled Areas = 30 Bq/cm2

Notes: Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much longer. ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .

Handling procedures

1. Disposable gloves and lab coat should be worn when handling. 2. Use a spill tray and absorbent paper to contain spills. 3. Use extra caution when handling l4C labeled nucleic acid or their precursors. 4. All work with labeled l4C solvents or materials with a low boiling point must be done in a

fume hood.

28

Phosphorous 32 Data Sheet

Physical Characteristics Isotope 32P Half Life 14.28 Days Mode of Decay Beta 100% Energy Average 0.7 MeV Maximum 1.710 MeV Decay Product 32S

Biological Data Biological Half Life 257 Days Effective Half Life 13.5 Days Target Organ Bone

Legislative Limits Exempt Quantity 0.01 MBq (0.27 uCi) ALI Ingestion 8 MBq(216 uCi) Sewage discharge (institutional Limit) 1 MBq/yr (27 uCi) Sewage discharge (laboratory limit) 0.0037 MBq/L(0.1 uCi/L) Landfill discharge 0.037 MBq/kg (1 uCi/Kg)

Shielding Data Maximum range in air 6 m Shielding required 1 cm plexiglass

Dose Rate from External Exposures The high energy Beta particle emitted by Phosphorous 32 is an external radiation hazard, close contact will add significantly to total dose. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 1.9 mSv/hr 0.05 ml droplet 1 kBq =1.3 mSv/hr

External Dose form a 1 MBq Source in: Point source at 30 cm = 0.12 mSv/hr 10 ml glass vial at 100 cm = 1.30 mSv/hr Contact with a 50 ml glass beaker = 7.1 X 10-4 mSv/hr Contact with 5ml plastic syringe = 240 mSv/hr



ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .

Precautions 1. Phosphorus 32 is the highest radionuclide commonly encountered in research

laboratories and as such requires special care. 2. Disposable gloves and lab coat should be worn when handling. 3. Use a spill tray and absorbent paper to contain spills. 4. Double glove ( all direct contact with 32P must be avoided). 5. Safety glasses or Plexiglas shielding are to be used if handling quantities in excess of

37 MBq. 6. Finger Badges are to worn if handling quantities in excess of 50 MBq. 7. Remote handling devices (tongs etc.) should be used when handling amounts of more

than 37 MBq. 8. Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq. 9. The use of low density shielding should be used to minimize the production of gamma

radiation (Bremsstrahlung). Some lead shielding may be required in addition to Plexiglas when tens of millicuries are used.

10. After each use the worker and area must be monitored using a Geiger-Mueller counter.

29

Phosphorous 33 Data Sheet Physical Characteristics

Isotope 33P Half Life 25.6 Days Mode of Decay Beta 100% Energy Average 0.076 MeV Maximum 0.249 MeV Decay Product 33S

Biological Data Biological Half Life 257 Days Effective Half Life 13.5 Days Target Organ Bone

Legislative Limits Exempt Quantity 1 MBq (27 uC1) ALI Ingestion 80 MBq (2.2 mCi) Sewage discharge (institutional Limit) 10 MBq/yr (270 uCi/yr) Sewage discharge (laboratory limit) 0.1 MBq/L(2.7 uCi/L) Landfill discharge 1 MBq/kg (27 uCi/Kg)

Shielding Data Maximum range in air 46 cm Shielding required non

Dose Rate from External Exposures Low energy Beta particle emitted by Phosphorus 33 is not an significant external radiation hazard, as it can not penetrate the skin or travel very far in air. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 0.86 mSv/hr 0.05 ml droplet 1 kBq =0.14 mSv/hr

External Dose form a 1 MBq Source in: Point source at 30 cm = 0 mSv/hr 10 ml glass vial at 100 cm = 0 mSv/hr Contact with a 50 ml glass beaker = 0 mSv/hr Contact with 5ml plastic syringe = 0 mSv/hr



Notes: Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv . Precautions

1. Disposable gloves and lab coat should be worn when handling. 2. Use a spill tray and absorbent paper to contain spills. 3. Handle 33 P compounds that are potentially volatile or in powder form in ventilated

enclosures.

30

Sulfur 35 Data Sheet Physical Characteristics

Isotope 35S Half Life 87.9 Days Mode of Decay Beta 100% Energy Maximum O. 167 MeV Average 0.049 MeV Decay Product 35Cl

Biological Data Biological Half Life 90.0 Days Effective Half Life 44.3 Days Target Lungs

Legislative Limits Exempt Quantity 100 MBq (2.7 mCi) ALI Ingestion 26 MBq (0.7 mC1) Sewage discharge (institutional Limit) 1000 MBq/yr (27 mCi/yr) Sewage discharge (laboratory limit) 0.037 MBq/L (1 uCi/L) Landfill discharge 0.37 MBq/kg (10 uCi/kg)

Shielding Data Maximum range in air 30 cm Shielding required None

Dose Rate from External Exposures Low energy Beta particle emitted by Sulfur 35 is not an external radiation hazard, as it can not penetrate the skin or travel very far in air. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 3.5 10-1 mSv/hr 0.05 ml droplet 1 kBq = 4.1X 10-3 mSv/hr



Liquid scintillation Geiger Counter


Notes: Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much longer. ALI is defined as the Annual Limit of Intake by ingestion or inhalation which would produce a dose of 20 mSv .

Handling Procedures 1. Disposable gloves and lab coat should be worn when handling 35S. 2. Disposable gloves and lab coat should be worn when handling. 3. Use a spill tray and absorbent paper to contain spills. 4. Radio-lysis of 35S radiolabeled compounds may occur during storage, causing the

release of volatile 35S compounds. Vials should be opened only in fume hoods. 5. Radio-lysis may also occur during heating. Insure that all processes which heat 35S

compounds are done in a fume hood.

31

Calcium 45 Data Sheet Physical Characteristics

Isotope 45Ca Half Life 165 Days Mode of Decay Beta 100% Energy Maximum 0.252 MeV Average 0.76 MeV Decay Product 45Sc

Biological Data Biological Half Life 1.8 x 104 Days Effective Half Life 162 Days Target Organ Bone

Legislative Limits Exempt Quantity 1 MBq ALI Ingestion 26 MBq

Shielding Data Maximum range in air 48 cm shielding required none

Dose Rate from External Exposures Dose rates are not given for the week Beta emitters such as 45Ca because such figures are negligible in most practical circumstances. Dose from these radionuclides is only important when the activity is ingested, or when on direct contact with the skin. Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 0.84 mSv/hr 0.05 ml droplet 1 kBq = 0.1 mSv/hr


Contamination Monitoring Method Liquid Scintillation Geiger Counter


Notes: Effective biological half-life applies to the radionuclide in a simple inorganic form. If the nuclide is ingested in the form of an organic molecule which can become incorporated or absorbed by a metabolic process, the half-life in the body may be much longer. ALI is defined as the Annual Limit of Intake by ingestion which would produce a dose of 20 mSv .

Handling Procedures 1. Disposable gloves and lab coat should be worn when handling 45Ca. 2. Use a spill tray and absorbent paper to contain spills. 3. Use extra caution when handling 45Ca due to its high affinity for bone tissue. Its long

biological half life could result in damage to blood producing tissues within the bone.

32

Chromium 51 Data Sheet Physical Characteristics

Isotope 51Cr Half Life 27.7 Days Mode of Decay XRAY Gamma and Auger Electrons Energy X-Ray 0.005 MeV 22.3% Gamma 0.320 MeV 9.8% Auger Electrons 0.004 MeV 66.9% Decay Product 51 V

Biological Data Biological Half Life 616 Days Effective Half Life 26.6 Days Target Organ Lungs

Legislative Limits Exempt Quantity 1 MBq (27 uCi) ALI Ingestion 530 MBq (14.32 mCi) Sewage discharge (institutional Limit) 100 MBq/yr (2.7 mCi/yr) Sewage discharge (laboratory limit) 0.37 MBq/L (10 uCi/L) Landfill discharge 3.7 MBq/kg (100 uCi/kg)

Shielding Data Half Value Layer of Lead = 1.7mm

Dose Rate from External Exposures Dose from Skin Contamination

Uniform Deposit 1 kBq/cm2 = 1.5 X 10-2 mSv/hr 0.05 ml droplet 1 kBq = 5.7 X 10-4 mSv/hr

External Dose form a 1 MBq Source in: Point source at 30 cm

Skin =0 mSv/hr Deep tissue= 6 X10-5 mSv/hr

10 ml glass vial at 100 cm = 5.4 X10-6 mSv/hr Contact with a 50 ml glass beaker = 1.92 X10-2mSv/hr Contact with 5ml plastic syringe = 8.7 X10-2 mSv/hr


Liquid Scintillation Crystal Scintillation Geiger Counter



Handling Procedures 1. Disposable gloves and lab coat should be worn when handling 51Cr. 2. Use spill tray and absorbent material. 3. Use of lead shielding is required when handling quantities in excess of 37 MBq. 4. Remote handling devices (tongs etc.) should be used when handling quantities in

excess of 37 MBq. 5. Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq.

33

Iron 59 Data Sheet Physical Characteristics

Isotope 59Fe Half Life 45.60 Days Mode of Decay Beta and Gamma Energy Beta 0.478 MeV 53% 0.281 MeV 45% Gamma 1.095 MeV 55% MeV 43% Decay Product 59Co

Biological Data Biological Half Life 600 Days Effective Half Life 42.0 Days Target Organ Spleen

Legislative Limits Exempt Quantity 0.1 MBq (2.7 uCi) ALI Ingestion 10 MBq (270 uCi) Sewage discharge (institutional Limit) 1 MBq/yr (27 uCi/yr) Sewage discharge (laboratory limit) 0.001 MBq/L(0.027 uCi/L) Landfill discharge 0.01 MBq/kg (0.27uCi/kg)

Shielding Data Half Value Layer Lead 10mm


Uniform Deposit 1 kBq/cm2 = 0.97 mSv/hr 0.05 ml droplet 1 kBq = 0.3 mSv/hr


Skin =0.037 mSv/hr Deep tissue= 1.9 X 10-3

10 ml glass vial at 100 cm = 1.6 10-4 mSv/hr Contact with a 50 ml glass beaker = 0.58 mSv/hr Contact with 5ml plastic syringe = 2.7 mSv/hr





Handling Procedures

1. Double glove (all direct contact with 59Fe must be avoided). 2. Finger Badges are to worn if handling quantities in excess of 50 MBq. 3. Remote handling devices (tongs etc.) should be used when handling mCi amounts. 4. Use syringe or pipette shields when manipulating stock solutions in excess of 37 MBq.

34

Iodine 125 Data Sheet Physical Characteristics

Isotope 125I Half Life 60.28 Days Mode of Decay Electron Capture Energy Gamma 0.035 MeV 7% X-ray 0.027 MeV 128% Decay Product 125Te

Biological Data Biological Haft Life 138 Days Effective Half Life 41.9 Days Target Organ Thyroid

Legislative Limits Exempt Quantity 1 MBq (27 uCi) ALI Ingestion 1 MBq (27 uCi) Sewage disposal (University Limit) 100 MBq/yr (2.7 mCi/yr) Sewage disposal (lab. limit) 0.0037 MBq/L (0.1uCi/L) Landfill discharge 0.037 MBq/kg (1 uCi/Kg)

Shielding Data Half Value Layer of Lead = 0.03 mm


Uniform Deposit 1 kBq/cm2 = 2.1 X 10-2 mSv/hr 0.05 ml droplet 1 kBq = 6.3 X 10-3 mSv/hr


Skin =0 mSv/hr Deep tissue= 3.9 X 10-4 mSv/hr

10 ml glass vial at 100 cm = 1.4 X10-5 mSv/hr Contact with a 50 ml glass beaker = 4.1 X10-2 mSv/hr Contact with 5ml plastic syringe = 0.34 mSv/hr





Handling Procedures 1. Solutions containing iodine ions should not be made acidic nor stored frozen, both lead to

formation of volatile elemental iodine. As some iodo-compounds can gradually penetrate certain types of gloves, it is advisable to change gloves often unless it has been determined that the gloves are impervious to the compound being used. Note however, that the quantity of radioiodine in normal RIA kits (usually <10 uCi) is such that these can be handled safely with reasonable care on the open bench.

2. Double gloves and lab coat should be worn when handling 125I . 3. Bioassay are require if 1251 is used as follows:

a. Open Bench greater than 135 uCi (5 MBq) b. Fume Hood greater than 1.35 mCi (50 MBq) c. Glove Box(vented) greater than 13.5 mCi (500 MBq)

*Process which involve the generation of volatile iodine must be carried in a fume hood. 4. If a spill occurs the spill should be treated with a solution of excess Sodium Thiosulphate. 5. When possible keep radioiodine solutions above pH 8.0. 6. Vials containing radioiodine should be opened in the fume hood. 7. Avoid direct contact with unshielded containers of radioiodine. 8. Waste radioiodine should be kept in a fume hood or other well ventilated area. (Volatile Iodine

can pass through most plastics)

35

Iodine 131 Data Sheet Physical Characteristics

Isotope 131I Half Life 8.06 Days Mode of Decay Beta & Gamma Energy Gamma 0.364 MeV Beta Max 0.806 MeV 0.637 MeV Avg. 0.180 MeV Decay Product 131Xe

Biological Data Biological Half Life 138 Days Effective Half Life 7.6 Days Target Organ Thyroid

Legislative Limits Exempt Quantity 0.01 MBq (0.27 uCi) ALI Ingestion 1 MBq (27uCi) Sewage discharge (institutional Limit) 10 MBq/yr (270 uCi/yr) Sewage disposal (laboratory limit) 0.0037 MBq/L(0.1 uCi/L) Landfill discharge 0.037 MBq/kg (1 uCi/Kg)

Shielding Data Half Value Layer of Lead = 3mm

Dose Rate from External Exposures Dose from Skin Contamination Uniform Deposit 1 kBq/cm2 = 1.6 mSv/hr 0.05 ml droplet 1 kBq = 0.5.7 mSv/hr


Skin =8.6 X 10-4 mSv/hr Deep tissue= 3.9 X 10-4 mSv/hr

10 ml glass vial at 100 cm = 6.4 X10-5 mSv/hr Contact with a 50 ml glass beaker = 0.22 mSv/hr Contact with 5ml plastic syringe = 1.1 mSv/hr





Handling Procedures 1. Volatilization of iodine is the most significant problem with this isotope. Solutions containing

iodine ions should not be made acidic nor stored frozen, both lead to formation of volatile elemental iodine. As some iodo-compounds can gradually penetrate certain types of gloves, it is advisable to change gloves often unless it has been determined that the gloves are impervious to the compound being used. Note however, that the quantity of radio-iodine in normal RIA kits (usually <10 uCi) is such that these can be handled safely with reasonable care on the open bench.

2. Double gloves and lab coat should be worn when handling 131I . 3. Bioassay are require if 1311 is used as follows:

a. Open Bench greater than 135 uCi (5 MBq) b. Fume Hood greater than 1.35 mCi (50 MBq) c. Glove Box (vented) greater than 13.5 mCi (500 MBq)

*Process which involve the generation of volatile iodine must be carried in a fume hood. 4. If a spill occurs the spill should be treated with a solution of excess Sodium Thiosulphate. 5. When possible keep radio-iodine solutions above pH 8.0. 6. Vials containing radio-iodine should be opened in the fume hood. 7. Avoid direct contact with unshielded containers of radio-iodine. 8. Waste radio-iodine should be kept in a fume hood or other well ventilated area. (Volatile Iodine

can pass through most plastics)

36

RADIATION CONTAMINATION SURVEY FORM BUILDING___________ ROOM________________ SURVEY EQUIPMENT ________________________________

Name

Name

Name

Date Date Date AREA CPM Bg/cm2 AREA CPM Bg/cm2 AREA CPM Bg/cm2 1

1

1

2

2

2

3

3

3

4

4

4

5

5

5

6

6

6

7

7

7

8

8

8

9

9

9

10

10

10

11

11

11

12

12

12

Bkg

Bkg

Bkg

Name

Name

Name

Date Date Date AREA CPM Bg/cm2 AREA CPM Bg/cm2 AREA CPM Bg/cm2 1

1

1

2

2

2

3

3

3

4

4

4

5

5

5

6

6

6

7

7

7

8

8

8

9

9

9

10

10

10

11

11

11

12

12

12

Bkg

Bkg

Bkg

37

UNIVERSITY of WATERLOO RADIOISOTOPE INVENTORY

Location Room: _________ Supervisor: __________________ Permit #: ______

Isotope:___________ Date Received(D/M/Y)__________ Material: _________________ Lot #: _______________ Activity (mCi): ___________ Vial Id:_____________ Volume (μL): __________

DATE USED

User Initials

Contamination Monitoring Date

Amount Used (μL)

Type of Waste

Waste Stream

% of material in each waste stream

Type of Waste

Waste Stream

L= Aqueous O= Organic S=Solid A= Animal Carcass

1=Municipal Garbage 2= Municipal Sewer 3=U W Environmental Safety Facility 4= Other (specify)

Package Contamination_______________ Signature_________________ PO No.________

RADIATION LABORATORY REFERENCE MANUAL · 4 Internal Permits University of Waterloo researchers who...

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