RADIATION SAFETY TRAINING

& the UNIVERSITY OF OTTAWARadiation Safety Program

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Presented by: Joy Moyle, Radiation SpecialistUniversity of Ottawajmoyle@uottawa.ca or 613-562-5800 Ext.3057 on Mon. & Wed., Ext. 8081 on Tues., Thurs & Fri.

Course outline:

Regulatory Framework (CNSC)

uO Radiation Safety Program

Radiation 101(characteristics, risk , detection and calculations)

Operational(acquisition, inventory, disposal, monitoring)

Safe Practices(personal protection, handling, lab safety)

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Module 1:

Regulatory Framework

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Ministries: of Labour, Environment

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Exempt Quantities (EQ)

Nuclear Substances and Radiation Devices

Naturally Occurring Radioactive MaterialAnd Environmental Samples

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Naturally Occurring Radioactive Material is called NORM

Sources:1. Cosmogenic radionuclides - created when cosmic radiation interacts with the atmosphere, soils, rocks or water

2. Primordial radionuclides – are radionuclides that have existed since the earth was formed and have not completed decayed due to their long half-life (U-238 t1/2 4.5 x 109 years)

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Regulation of NORM materials

• It is primarily regulated by provincial and territorial governments and each can have their own specific regulations on the handling and disposal of the NORM material.

• Federal Provincial Territorial Radiation Protection Committee (FPTRPC) created “Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials” http://www.hc-sc.gc.ca/ewh-semt/pubs/contaminants/norm-mrn/index-eng.php

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Other organizations with NORM regulations:

Health Canada Radiation Protection Bureau

Ontario Ministry of Labour Radiation Protection Service

Canadian Nuclear Safety

Commission

Environmental and Radiation

Protection and Assessment

Directorate

Why regulate what is naturally

occurring?

Dose implicationsRadon gas in homes

Mining, oil and gas (mineral scale on pipes,

sludge, contaminated equipment)

Construction (bricks, cement, granite counter

tops, glazed tiles)

Consumer products

(phosphate fertilizer, tobacco)

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NORM is Exempt from CNSC’s Nuclear Safety Control Act, UNLESS it is:

• associated with the development, production or use of nuclear energy (as set out in the CNSC-NSC Regs. )

• imported into Canada or exported from Canada (as set out in the CNSC - NPIEC Regs)

• transported when the specific activity is greater than the exempt material values (as set out in the CNSC - PTNS Reg.)

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What about other sources?

• Depleted Uranium

• Uranyl Acetate

• Uranyl Nitrate

• Thorium Nitrate

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By definition, CNSC exempt quantities (EQ) are radioisotope activities that are exempt from License requirements.

But, it is the activity sum for a radioisotope. This means all radioactive material must be tracked.

Refer to Permit Conditions to determine requirements.

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CNSC- Regulatory FrameworkNuclear Safety & Control Act

Key RegulationsGeneral Nuclear Safety & Control Radiation ProtectionNuclear Substance and Radiation DevicesPackaging and Transportation Nuclear SecurityNon-proliferation Import and Export ControlClass I Nuclear FacilityClass II Nuclear Facility and Prescribed Equipment

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Regulatory Vehicles

• Nuclear Substance and Radiation Device Licenses

consolidated, import, class 2 nuclear facility

• 5 year license renewal process

• Annual Compliance Reporting

• Inspection ( Type I & II )

• Reporting Criteria embedded in the regulations

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CNSC PERFORMANCE GRADINGSCA – Safety Control AreaType I and Type II Inspections

1. Radiation Protection2. Emergencies & Unplanned

Events

3. Environmental Protection

4. Security

5. Training & Qualification

6. Operational Procedures

7. Transportation

8. Organization & Management

9. Quality of Management

10. Non-radiological Health & Safety

11. Public Information Programs

12. Fire Protection

13. International Obligations & Safeguards

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Grade DefinitionRisk to Health, Safety, Security and the Environment

A exceeds requirements no unreasonable risk

B meets requirements no unreasonable risk

C below requirements no unreasonable risk but potential

D significantly below requirements

high potential for unreasonable risk if not corrected

E unacceptable very high potential for unreasonable risk

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Did I forget to mention about monetary penalties $ ?

• CNSC can impose monetary penalties for non-compliance by licensees.

• CNSC is very demanding about accuracy and compliance

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Module 2:

uO Radiation Safety Program

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uO Radiation Safety ProgramGoal- interpret the regulations, develop systems to allow for easy compliance and ensure reporting requirements are met.

KNOWLEDGECOMPLIANCE

CRADLE TO GRAVE MANAGEMENT

ACCOUNTABILITY

Radiation Safety Committee

• Reports to the Board• Chaired by Vice-Rector, Research• Ensures compliance with CNSC regulations

and license conditions

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Office of Risk Management • Manages the radiation safety program• Conducts inspections• Monitors doses, inventory• Conducts training

Radioisotope Permit Holder• Ensures all University regulations, policies & requirements are met• Adheres to all permit limits and conditions• Ensures a safe work environment

Radioisotope User• Complies with all elements of radiation safety program• Works in a safe fashion (self, colleagues, environment)• Attends all appropriate training

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1. Internal permits (open, sealed, sealed in a device, EQ, NORM)

2. Authorized users

3. Training, user comprehension

4. Inventory control

5. Disposal limits

6. Exposure Monitoring

7. Monitoring: contamination, leak testing, radiation field, ALARA

8. Safe work practices

9. Inspections and Compliance monitoring

10. Security (radioactive material, personnel and environment)

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Performance Grading Major Offence:

High risk- immediate health, safety or security risk

Moderate Offence:

Medium Risk – health, safety or security risk, but not immediate

Minor Offence:

Low Risk - no health, safety or security risk; administrative issues

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Module 3:

Radiation 101

(characteristics, risk , detection and calculations)

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Radiation – the full spectrum

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Regardless of the source of the nuclear radiation its objective is

always to achieve stability!

Release of excess energy (particles)

Release of excess energy (emr)

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Fundamental Building Blocks - atoms

Radioisotope:unstable nuclide

emits excess energy

spontaneous emission

characteristic half-life

4 modes of decay ( , , ,x rays)

http://dorrscienceclass.blogspot.ca

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The disintegration process is referred to as the rate of decay of the nuclide.It is the # of disintegration per time (min) and hence dpm.

1 gm of Radium was discovered to emit 3.7 x 1010 dps, and this is a CurieIt was named after Marie and Pierre Curie.

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Imperial System 1 Curie = 3.7 x 1010 dps(disintegration per second )

Systèm International 1 dps = 1 Becquerel

Radioisotopes, emit unique

quantifiable energies:

• the time required for half of the

radioactive nuclides to decay to

a stable state

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Half-Life

http://rsh.nst.pku.edu.cn

81 stable elements

275 isotopes,

> 800 radioisotopes

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Alpha Emission

origin: Disintegrating nucleus

form of radiation: Particle

energy range: 4-8 MeV

range of travel: 2-8 cm in air

other characteristics: Large mass, double charge; high specific activity; external damage limited; highly ionizing particle which

causes greater internal damage

Usually associated with high atomic mass

http://www.umich.edu

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Beta Emission

origin: Disintegrating nucleus

form of radiation: Negatron (electron)Positron (similar to an electron butpositive charge)

energy range: 0.02 - 4.8 MeV

range of travel: 0 - 10 m in air

other characteristics: Differs from an electron in origin and energy; travels almost the speed of light;almost no mass (9.1x 10-31 kg)

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http://www.umich.edu

Gamma Emission

http://www.umich.edu

origin: Nucleus

form of radiation: Electromagnetic radiation (emr - photon)

energy range: 10 keV - 3 MeV

range of travel: 1-100’s m in air

other characteristics: Zero mass, electrically neutral

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X-Ray Emission

• origin: Orbital electron

• form of radiation: Electromagnetic radiation (emr - photon)

• energy range: 10eV - 120 keV

• range of travel: 1-100’s m in air

• other characteristics: Zero mass, electrically neutral

Bremmstrahlunghttp://www.astro.wisc.edu

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Characteristic X-rays

Other means of emission:Electron Capture:

Inner orbital electron is captured by the nucleus with a net effect of transforming proton to a neutron

As the electron shells re-arrange to fill the vacancy, x-rays are produced

Internal Conversion:Excited nucleus interacts electromagnetically with inner electron

to expel the electron from the orbital shellAs the electron shells re-arrange to fill the vacancy, characteristic

x-rays are produced

Auger Electron:After Electron Capture or Internal Conversion the outer

electrons re-arrange to fill vacancies in outer orbitals and the energy produced is measured as fluorescence

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Photoelectric Effect:a ray transfers all of its energy to an orbital electron, the result

being the electron is expelled with high energy

Compton Effect:a ray transfers part of it’s energy to an orbital electron, the

result being he electron is expelled with energy proportional to the amount of energy transferred.

Cerenkov Radiation:when a charged particle travels through a transparent medium at

a speed greater than the speed of light the excess energy is given off as blue light.

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http://geoscienceworld.org/

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Interaction with MatterIONIZATION

Electron is removed from the electron shell, leaving a charged particle (free radical)

EXCITATION

Electron is raised to a higher energy state but is not knocked out, when it returns to it orbital shell excess energy is released

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EFFECTS OF IONIZING RADIATION ON THE HUMAN BODY

Genetic (appears in later generations, due to cell damage of reproductive organs)

Somatic (appears in irradiated individual, immediate or delayed)

Stochastic (refers to a probability of biological effect due to ionizing radiation which is assumed to increase with in proportion to an increase in radiation dose at low doses or low dose rate )

IMPLICATIONS :No change

Mutation and repairPermanent change with limited effect

Changes leading to cancer or other effectsDeath of cell / organism (minutes - years)

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CRITICAL ORGANS

3H – Body water or tissue14C – Fat tissue32P – Bones35S – Gonads125I – Thyroid57Co – Large Intestine

Depleted Uranium- Liver, spleen and kidney

PREGNANCY

First trimester most sensitiveDose limits are setGood vs Harm not all

exposures are harmful and medical needs must be considered

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http://healthphysics.georgetown.edu

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Radiation MeasurementInternational

System Old units

Radioactivity Amount of ionizing radiation Bequerel Curie

Exposure Amount of ionization in air by xray or gamma radiation

(C/kg) Roentgen

Absorb Dose Amount of radiation absorb Gray Rad

Dose Equivalent Express exposure in terms of theimpact of the form and energydeposited

Sv Rem

Dose Effective Express exposure in terms of theorgans and tissues impacted

Sv Rem

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Radiation Measurement - conversions

1 Coulomb/kg (C/kg) = 3876 Roentgen (R)

1 Becquerel (Bq) = 1 decay per second (dps)Note: dpm (disintegration per minute) is not equal to cpm (counts per minute)

1 Bq = 2.7 x 10 11 Curie (Ci) 1 Ci = 3.7 x 1010 Bq

1 Gray (Gy) = 100 rad 1 rad = 0.01 Gy

1 Sievert (Sv) = 100 rem 1 rem = 0.01 Sv

1 Gy = approximately 100 R

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Equivalent DoseEquivalent Dose = Absorbed Dose x Radiation Weighting Factor

Weighting Factor takes into consideration the type and amount of radiation being deposited ( ie , , )

Type of Radiation and Energy RangeSee foot notes in RP Regulations

Weighting factor

Photons all energies 1Electrons and muons all energies 1

Neutrons energy < 10 keV 5

Neutrons energy 10 keV to 100 keV 10

Neutrons energy > 100 keV to 2 MeV 20

Neutrons energy > 2 MeV to 20 MeV 10

Neutrons energy > 20 MeV 5

Protons, other than recoil protons energy > 2 MeV 5

Alpha particles, fission fragments and heavy nuclei 20

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Effective Dose LimitsEffective Dose = Equivalent Dose x Organ/Tissue Weighting factorsAccounts for radio sensitivities of various tissues and organs

Source: CNSC Radiation Protection Regulations

Organ or Tissue ( see foot notes in RP Regs.) Weighting FactorGonads (testes or ovaries) 0.2Red bone marrow, colon, lung, stomach 0.12Bladder, breast, oesophagus, thyroid gland 0.05Skin, Bone surfaces 0.01All organs and tissues not listed such as theadrenal gland, brain, extra thoracic airway, smallintestine, kidney, muscles, pancreas, spleen,thymus and uterus

0.05

Whole body 1

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Equivalent Dose Limits

Organ or tissue Person Period Equivalent Dose(mSV)

Lens of Eye NEW 1 yr dosimetry period 150Lens of Eye Non NEW 1 calendar year 15

Skin NEW 1 yr dosimetry period 500Skin Non NEW 1 calendar year 50

Hands and Feet NEW 1 yr dosimetry period 500Hands and Feet

Whole BodyWhole Body

Non NEW

NEWNon NEW

1 calendar year

1 yr dosimetry period1 calendar year

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201

NEW – nuclear energy worker

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CNSC criteria … that impact day to day operations

• ALARA

• Annual Limit Intake (ALI)

• Radioisotope Class A,B or C

• Exempt quantities (EQ)

• Transportation of dangerous goods

• Security

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ALARA – as low as reasonably achievable

• taking into account economic, and social factors

• ALARA is not only a sound safety principle, but is a regulatory requirement for all radiation safety programs

• CNSC Regulatory Guide G-129 Keeping Radiation Exposures and Doses “As Low as

Reasonably Achievable (ALARA)”

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Mitigation of: EXTERNAL Radiation Exposures

• 1) TIME – minimizing the time of exposure directly reduces radiation dose.

• 2) DISTANCE – doubling the distance between your body and the radiation source will divide the radiation exposure by a factor of 4

• 3) SHIELDING - using absorber materials such as Plexiglas for beta particles and lead for X-rays and gamma rays is an effective way to reduce radiation exposures. (beware of Bremstrahling radiation with - radiation and lead shielding.)

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Good hygiene techniques

no food and drink in the lab, avoid “hand-to-face” contacts.

Frequent swipe surveys and lab area monitoring

of work areas

Control contamination

with absorbent paper and spill tray

Contain airborne radioactivity

(e.g., vapours, dust, aerosols, etc.) – use fumehood

Proper protective equipment (PPE)

such as disposable gloves, safety glasses, lab coats, etc.

Mitigation Of : INTERNAL Radiation Exposures

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Annual Limit In-take (ALI)

• Defined by CNSC

• expressed in becquerel (Bq),

• effective dose of 20 mSv during the 50-year period

• after the radionuclide is taken into the body

• of a person 18 years old or older

• Specific to each radioisotope

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RADIOISOTOPES

ANNUAL LIMIT OF INTAKE (ALI)*

INGESTION

MBq mCi3H 1000 27

14C 34 0.90

22Na 6 0.16

32P 8 0.22

33P 80 2.20

35S 26 0.70

36Cl 20 0.54

42K 47 1.27

45Ca 20 0.54

51Cr 530 14.3

57Co 95 2.5

60Co 6 0.16

86Rb 8 0.22

109Cd 9 0.24

125I 1 0.03

133Ba 20 0.54

137CS 1 0.03

201Tl 210 5.67

210Po 0.02 0.0005

226Ra 0.07 0.002* Values taken from the CNSC RD-52 Rev 1

Classification of Laboratories

Basic level if the quantity does not exceed 5 ALI

Intermediate level if the quantity does not exceed 50 ALI

High level if the quantity does not exceed 500 ALI

Containment level if the quantity does exceed 500 ALI; or

Special purpose if approved in writing by CNSC or a person authorized by CNSC

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Radioisotope Class – A,B,CCLASS RADIONUCLIDE

Class A All alpha emitters and their daughter isotopes

Na-22 Na-24 Co-60 Ir-192 Sb-124

Ta-182 Zn-65

Class B As-74 Au-198 Br-82 Co-58 F-18

Fe-59 Ga-67 Gd-153 Hg-203 I-131

In-111 In-114m Nb-95 Rb-84 Rb-86

Sc-46 Se-75 Sm-153 Sn-113 Sn-123

Sr-85 Sr-90

Class C Au-195m C-14 Ca-45 Cd-109 Ce-144

Cl-36 Co-57 Cr-51 H-3 I-123

I-125 Ni-63 P-32 P-33 Re-186

Re-188 Ru-103 S-35 Sr-89 Tc-99

Tc-99m Tl201 Y-90 Yb-169

• based upon their radiological properties

• commonly used radionuclides are listed

• if not listed contact RSO

• determines contamination criteria

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Exempt Quantities

Impact the labs:

• If > 10000 EQ of a radionuclide at a single time, CNSC and RSO approval required

• >100 EQ radiation warning sign to be posted at entrance to the laboratory (or probability of an effective dose rate of > 25 Sv/hr)

Exempt from CNSC licensing

requirements, BUT

if you have a license, your license

conditions apply

RADIO-ISOTOPES

EXEMPTION QUANTITY

(MBq)*

RADIO-ISOTOPES

EXEMPTION QUANTITY

(MBq)*

3H 1000 239Pu n/a14C 10 63Ni 1018F 0.01 65Zn 1

22Na 0.01 86Rb 0.0132P 0.1 90Sr 0.0133P 1 109Cd 135S 100 125I 1

36Cl 0.01 133Ba 0.142K 0.01 137CS 0.01

45Ca 10 151Sm n/a51Cr 1 152Eu n/a57Fe 1 155Eu n/a57Co 1 204Tl 0.0160Co 0.1 210Bi 0.0163Ni 10 226Ra 0.01

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Transportation of Dangerous Goods Transport Canada (TC)

• TDG Act and Regulations has been recently updated and directly refers to the CNSC regulations

CNSC

•Packaging and Transport Regulations

•Consolidated License Requirements

• In house approvals

- radionuclide dependent- energies- chemical forms- potential biological effect

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Radiation Warning Labels

Category I-White: less than 5 Sv/h

Category II-Yellow: less than 500 Sv/h,TI less than 1

Category III-Yellow: less than 2 mSv/h, TI less than 10

TI (Transport Index): maximum radiation level in Sv/h at 1 meter from the external surface of

the package, divided by 10.

Example: 1 Sv/h (0.1 mrem/h) at 1 m equals aTI = 0.1

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PACKAGE TYPES:

Excepted packages

- The safety mark ‘RADIOACTIVE’ must be visible on opening the package

- The radiation level at any point on the external surface of the package

must not exceed 5 Sv/h

Industrial packages – Categories I, II and III

Type A packages – lower amounts

Type B (U) packages – large amounts; 700 kPa

Type B (M) packages – large amounts; > 700 kPa

Type C packages – for air transport of high activity

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Security

1. physical barriers

2. psychological barriers

3. monitoring activities

4. personnel clearance

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General Nuclear Safety and Control Regulations

Sections 12 - Obligations of the Licensee (Uottawa)

(c) take all reasonable precautions to protect the environment and the health and safety of persons and to maintain the security of nuclear facilities and of nuclear substances;

(h) implement measures for alerting the licensee to acts of sabotage or attempted sabotage anywhere at the site of the licensed activity;

(j) instruct the workers on the physical security program at the site of the licensed activity and on their obligations under that program;

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Section 17 - Obligation of the Worker

(b) comply with the measures established by the licensee to protect the environment and the health and safety of persons, maintain security, control the levels and doses of radiation, and control releases of radioactive nuclear substances and hazardous substances into the environment;

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(c) promptly inform the licensee (ORM – Radiation Specialist) or the worker’s supervisor of any situation in which the worker believes there may be:- a significant increase in the risk to the environment or the

health and safety of persons, - a threat to the maintenance of the security of nuclear facilities

and of nuclear substances or an incident with respect to such security,

- a failure to comply with the Act, the regulations made under the Act or the licence,

- an act of sabotage, theft, loss or illegal use or possession of a nuclear substance, prescribed equipment or prescribed information, or

- a release into the environment of a quantity of a radioactive nuclear substance or hazardous substance that has not been authorized by the licensee;

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Section 29 - General Reports

Every licensee who becomes aware of a risk to security, environment or the health and safety of persons shall immediately make a report to ORM – Radiation Specialist (ext 5411) with the following information:

(a) the date, time and location of becoming aware of the situation;

(b) a description of the situation and the circumstances;

(c) the probable cause of the situation;

(d) the effects on the environment, the health and safety of persons and the maintenance of security that have resulted or may result from the situation;

(e) the effective dose and equivalent dose of radiation received by any person as a result of the situation; and

(f) the actions that the licensee has taken or proposes to take with respect to the situation.

The Radiation Specialist will immediately forward information to CNSC

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Module 4:

Operational

(acquisition, inventory, signage, disposal, monitoring)

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InternalPermits:

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Acquisitions:• Radioactive materials purchase procedures

- Radioisotopes Purchase Requisition form

- Form must be complete (PO number, signature)

- ORM approval before ordering

- Documentation (packing slips, shipper’s declaration)

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PURCHASEREQUISITION

FORM

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Receipt of Radioactive Material

- Confirm the purchase you received is the purchase you ordered or are expecting.

- Review shipping label for possible exposure risk

- Inspect packaging both externally and internally for damage or leakage

- Perform contamination monitoring on the package,

- Deface wording and labels prior to disposal of the package

- Start an Inventory of Use and Disposition form

Report any anomalies to the supervisor and RSO

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Category I-White: less than 5 Sv/h

Category II-Yellow: less than 500 Sv/h, TI less than 1

Category III-Yellow: less than 2 mSv/h, TI less than 10

TI: maximum radiation level in Sv/h at 1 meter from

the external surface of the package, divided by 10.

Ex: 1 Sv/h (0.1 mrem/h) at 1 m equals a TI = 0.1

RADIATION WARNING LABELS – will tell you of the exposure risk and hence if shielding and/or distance is required to transport youpackage to the lab

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Remember:EXCEPTED PACKAGES

The safety mark ‘RADIOACTIVE’ must be visible onlyupon opening the package

The radiation level at any point on the external surfaceof the package must not exceed 5 Sv/h

All other packages must be categorized by radiation level and display the corresponding radiation warninglabels as follows:

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INVENTORY: RecordsMUST be accurate:

...........reflect current inventory

...........transfers

Sealed Sources- encapsulated, incorporated in a device, check sources- calibration date- manufacturer & serial number- CNSC tracking requirements- Current activity – leak test requirements

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Open Sources (filled in upon receipt, forward to ORM upon final use)

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Do I need to post signage ?Required when:

radioactive nuclear substance> 100 EQ

and/or

where there is reasonable probability that a person might be exposed to an effective dose rate of greater than 25 Sv/hr

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Caution Radioactive Use Area

No signage:

- If less than 1 EQ of a radioisotope is found in the location or used/stored in that location

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Inside the lab •Copy of the internal permit•Current list of authorize users•CNSC safety poster for appropriate lab category•CNSC spill procedure poster•CNSC proper care and use of personal dosimeters poster•CNSC guidelines for handling packages containing nuclear substances poster

Other signage :

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Waste: Waste: 1 Solid Waste

2 Water Soluble

3 Liquid Scintillation

4 Animal Carcases

Procedures for Radioactive Waste Management

Open Source - Use and Disposition Form

Liquid Scintillation Waste Log

Radioactive Solid Waste Log

Procedures for Radioactive Animal Carcasses Waste Disposal

PROCEDURES AND FORMS ARE ON THE

WEB SITE

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How to store waste:

• Waste should be stored in 20 litre waste pails that are double lined with plastic bag

• Logs such as liquid scintillation (LS) waste logs should be placed on lid of pail, or

• Pail should have a label indicating where log is• Pails must be labelled with appropriate label such as LS

waste or solid waste label• Once radioactive material is removed from the pail, all

radioactive labels must be removed or de-faced

Solid WasteShort lived Radioisotopes

T ½ < 90 daysHold for decay until 1DL/KG

is attained

Off-site TransfersWhen the activity is too great for other disposal options, or CNSC does not allow disposal

Disposal to Landfill

1 DL* / KG

Disposal Limits (DL)Listed on uOttawa’s CNSC License

C-14: 3.7 MBq (100 Ci)/kg;

H-3: 37 MBq (1000 Ci)/kg

I-125: 0.037 MBq (1 Ci)/kg;

P-32: 0.37 MBq (10 Ci)/kg

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Check 2nd page of Permit for Disposal Limits

• Stick on decay container

• Calculate total activity on date

transfer for decay

• Calculate the length of time

required for decay to disposal

limits

• Establish a disposal date

• Record date and time

• Transfer

• Stick on decay container

• Calculate total activity on date

transfer for decay

• Calculate the length of time

required for decay to disposal

limits

• Establish a disposal date

• Record date and time

• Transfer

Decay Solid Waste Labels

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Time required for decayTime required for decay

A = Ao e - t

t = ln (A/Ao)-

A = activity at time ‘t’ Ao = activity at time zerot = elapsed time

= decay constant ( = 0.693 / t 1/2 )

RadPro calculator: http://www.radprocalculator.com/Decay.aspx

A = Ao e - t

t = ln (A/Ao)-

A = activity at time ‘t’ Ao = activity at time zerot = elapsed time

= decay constant ( = 0.693 / t 1/2 )

RadPro calculator: http://www.radprocalculator.com/Decay.aspx

Retention time

Disposal Date

Its your waste until disposal – so your responsible for keeping records

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Step 1 Determine activity (A) permitted at disposal

Weight = 0.785 kg1 DL/kg = 10 Ci / kg

A = Weight X 1 DL / kg A = 0.785 kg X 10 Ci / kgA = 7.85 Ci

Step 1 Determine activity (A) permitted at disposal

Weight = 0.785 kg1 DL/kg = 10 Ci / kg

A = Weight X 1 DL / kg A = 0.785 kg X 10 Ci / kgA = 7.85 Ci

Ex: Decay calculation • 100 Ci of 32P solid waste collected• Weight of waste = 0.785 kg• Disposal limit of 32P is 0.37 MBq/kg (10 Ci)• half life (t1/2) of 32P is 14.3 days

Step 2: Determine Length of Decay Period (t)

t = ln (A/Ao) -

A = activity at time ‘t’ (7.85 Ci)Ao = activity at time zero (100 Ci)t = elapsed time (?)

= decay constant (0.693 / 14.3 days = 0.0485/day)

t = ln (7.85 Ci / 100 Ci) = 52.5 days- 0.0485/day

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Water Soluble Radioactive Waste•Disposal limits are assigned by building.

•Assessed at the time of your user registration form – use profile

•Regularly monitored

•Municipal Sewer Disposal

Ex:C-14 0.01 TBqH-3 1 TBqI-125 100 MBqP-32 4 GBq

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For disposal by drain, ensure chemical matrix

is not hazardous and can be disposed via the drain

Liquid Scintillation Waste

•Do not hold for extended periods as vials can leak

•Waste should be stored in pails that are double lined with plastic bag

•Log should

•Where activities are low we will verify if they can be declassified as radioactive waste which result in cost savings

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Radioactive Animal Carcasses

Radioactive Animal Carcasses Waste Disposal Procedure

Animal Carcass Waste Log

Sent for incineration, activities must meet CNSC,TC and Ministry of Environment (MOE)

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MONITORING ACTIVITIES

• Contamination monitoring

• Dose rate around storage, waste, use areas

• Leak testing

• Dosimetry

• Pregancy

• Thyroid

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Radiation Detection

Survey Meters (Dose Rate) Contamination Monitors

• Measures radiation fields

• Must be calibrated yearly

• Specific meter types must be selected to measure , , , n etc.

• Monitors direct and indirect

contamination

• Do not have to be calibrated

• But must be able to

demonstrate sensitivity and

operation status can measure

the CNSC fixed /non-fixed

levels or radioactivity

Geiger Muller, Scintillation,

GeLi Detectors,Ionization

Chamber…..

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ContaminationMonitoring• Basic level lab – weekly

• Intermediately after use

• Decontaminate re-measure

• Wipe Test Procedures

• Direct Measurement

• > 50 MBq (1.35 mCi) sealedsource requires leak testing

• Leak testing frequency: In use – every 6 monthsIn use in a device– every 12 monthIn storage – every 24 month

• Follow approved procedures• Reporting Criteria is a leakage

of 200 Bq

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Leak Testing

Instrumentation Checks calibration (or verification)

evidence of wear

Pre-operations check:

Battery check, audible response, calibration check, response

setting, electronic connections

Calibration standards

**Express as Bq (cpm, 2x Background must still be able to demonstrate capacity to detect criteria (Class ABC radioisotopes)

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Reading a Survey meter

With range selected to x10, what is the radiation field in

Sv/hr?

- Use 2nd scale- reading 11- multiply by 10- radiation field is 110

Sv/hr

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• Map of lab

• Weekly if < 5 ALI, or if > 5 ALI, after each use

• Decontaminate

• Record “no radioisotope used”

• After any spill

• Prior to decommissioning

Contamination Monitoring (Open Sources)

Wipe test areas100

Bq/cm2

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• Energies not generally detectable by survey or

contamination monitors

• Require use of Liquid scintillation counters

Monitoring for low energy (soft beta ) radioisotopes such as H-3 & C-14

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Liquid Scintillation counters

For contamination monitoring it is important thatyou:• Select the appropriate energy range• If wipe testing for decommissioning, use the

“open” (entire) energy range• Know the efficiency for the radioisotope you are

monitoring• Know how to do an operational check to ensure

your results are accurate

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Contamination Criteria

Class A: 3.0 Bq/cm2

Class B: 30 Bq/cm2

Class C: 300 Bq/cm2

Decommissioning Criteria

Class A: 0.3 Bq/cm2

Class B: 3.0 Bq/cm2

Class C: 30 Bq/cm2

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(uOttawa “Best Practice” is to meet 0.3 Bq/cm2 for all contamination monitoring)

Contamination Monitoring cpm>Bq/cm2

Bq/cm2 = (Cpm – Bkg) / Ec X Ew X 60 X A

• Cpm = counts per minute for the wipe,• Bkg = counts per minute of the background filter,• Ec = scintillation counter efficiency (see note below), or GM efficiency• Ew = wipe efficiency, assume 10% (0.1), and• A = area wiped in cm2.

Note: As a rule of thumb, when the counter efficiency (Ec) is unknown, the following efficiencies can be used for the purpose of counting wipes:

100% (1) for 32P, 14C, 35S75% (0.75) for 125I50% (0.5) for 3H and unknowns

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Dose Rate Measurements:

• Routinely to ensure doses are ALARA

• Around storage, waste and use areas

• Whenever new sources arrive, or new

radioisotopes are used

• When new experimental procedures are

implemented

If your meter is not calibrated, make sure it

is verified with a calibrated meter

If your meter is not calibrated, make sure it

is verified with a calibrated meter

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PERSONAL EXPOSURE: Dosimetry

• Direct readout/alarm vs passive detection

• TLD thermoluminescence, bubble detectors …

• Whole Body, extremities (ring, wrist)

• Dose limits set, action level (1 mSv), reporting criteria

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avoid exposing them to high temperatures, water, direct sunlight and fluorescence light

avoid storage in areas of high radiation fields

Wear securely with the badge facing the source of radiation

if contaminated or damage stop wearing, replace with a new dosimeter

Review of all doses that meet action criteria

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Thryroid

UNBOUND IODINE – 125 & - 131 Screening is required when in a 24-hour period that exceeds the amounts:

ConfinementQuantity of I-125 or I-131

Gases, volatile liquids and powders

None 2 MBq

Fumehood 200 MBq

Glovebox 20,000 MBq

RD-58: Thyroid Screening for Radioiodine

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Module 5:

Safe Practice

(personal protection, handling, lab safety)

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AS LOW AS REASONABLY ACHIEVABLE

Undertaking activities to keep your exposure to a minimum by:

• knowledge of radioisotope characteristics

• risk assessment, where / what would result in an exposure

• how can I minimize my exposure

• lab design, experimental design, storage and waste management

practices

• try dry runs “cold runs” to test new experimental designs & equipment

• monitor exposures

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Inventory DISPOSE old stock and samples where the chemical and radiological integrity is in question.

Monitor the radiation field around your inventory

Old fridges and freezers are a pain to clean when

they fail, get rid of what you don’t use!

Minimize your inventory

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1• Elimination – can the goal be achieved using another procedures

2• Substitution – can I use another radioisotope or activity

3• Engineering – have I done a risk assessment and determined where the

risk of exposure is, can I use shielding, have I mitigated a risk of a spill

4• Administration – am I compliant, permit, use, disposal , etc

5• PPE – do I have the right equipment to protect myself

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5 Checks

TimeROLLING BACK TIME!

Reduce the amount of time you are exposed, by:

Returning the stock vial back to storage once you have your aliquot

Know and avoid areas of higher radiation

Plan your experiments with time reduction in mind

gettingto5050.blogspot.com

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Distance - Inverse Square Log

Where:

I1 = Intensity 1 at D1

I2 = Intensity 2 at D2

D1 = Distance 1 from source

D2 = Distance 2 from sourcehttp://www.ndt-ed.org

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Half-value layer (HVL):

the thickness of any given material

where 50% of the incident energy

has been attenuated .

Shielding

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Spill Response & ERP• Mitigated by: training, appropriate

experimental design and good work practices.

• Anticipate the type of spill(minor spill < 100 times EQ, major spill > 100 times EQ)

• Risk Assessment: the type of spill (liquid, solid, aerosol), size of spill, activity involved, physical characteristic of the radioisotope (decay energy, type of emission, half-life), biological risk and any other hazard that may exist.

• Permit Holder and RSO must be informed to determine potential exposure / release and if CNSC reporting criteria is met

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Spill ProcedureSPILL RESPONSE PROCEDURE

For major spills (> 100 times exception quantity, or contamination of personnel, or release of voliatile), immediately inform ORM

1. Notify all individuals in the immediate area that a spill has occurred.

2. Increase distance from the spill. If the spill is severe, this may require evacuating the area.

3. If evacuation is required, lock and sign door. The warning sign should include your name, as well as a location of spill and timeof return.

4. Limit access to only those individual responding to the spill.

5. If personal contamination has occurred, gently wash skin with a mild soap and tepid water.

6. If personal (skin) contamination has occurred, immediately contact ORM

If safe to do:

1. Contain the spill with absorbent material (paper towels).

2. Obtain any additional supplies and/or personal protective equipment (overalls, shoe coverings)

3.Push spill toward its centre. Clean from outside to inside. Collect all contaminated material in one appropriately labelled bag.

4. Decontaminate area with appropriate solutions (keep in mind biological or chemical hazards).

5. If fixed contamination above twice background remains, contact the ORM.

Leaving the scene after cleaning up:

1. Monitor self (especially feet, hands and lab coat) for contamination.

2. Leave lab coat behind if contaminated. Remove and take dosimetry badge to avoid erroneous readings.

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For major spills (> 100 times exception quantity, or contamination of personnel, or release of voliatile), immediately inform ORM

Information from the course that needs to be emphasized

• CNSC requires all reporting to be in bequerels which means all disposal orcontamination monitoring records must be in bequerels.

• CNSC requires proof that instruments are calibrated, working and capableof detecting CNSC contamination criteria

• CNSC is performing more inspections, if they come into your lab you needto know

if your instrument is working properlythe level of your lab. i.e. Basic, Intermediate (look at your internal permit)the class (A, B or C) of your laboratory (found in your internal permit)You cannot rely on others since they may specifically ask you!

INSPECTIONS

Goal to Determine Compliance And Competency

( Knowledge and Application)

Focus on individual users

Mimics CNSC Inspections

We are always available to help you make sure your lab is compliant.

It is always better that we fix things

before CNSC finds things.

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IN SUMMARY

CNSC is asking you how and why you know you are compliant.

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You can ask questions now

or later, butjust make sure you

ask them ?

Resources:

Radiation Safety Web Page

Radiation Safety Specialist rad.safety@uottawa.caExt. 3057(Mon. & Wed.) Ext 8081 (Tues., Thurs. & Fri.)

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Where to find the Radiation Safety Training Quiz

• Link to Quiz is located on the same page as course registration

• https://web47.uottawa.ca/en/lrs/node/1401

• Must be completed in 2 weeks, deadline

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February 14, 2018