RADIATION SAFETY TRAINING Presented by: Ali Shoushtarian Office of Risk Management, Last revised May. 2012

RADIATIONSAFETY

TRAINING

Presented by: Ali Shoushtarian Office of Risk Management,

Last revised May. 2012

Assistant Director, Radiation and Biosafety

Lois Sowden-Plunkett

ext. 3058 [email protected]

Compliance Inspector

Ali Shoushtarian

ext. 3057 [email protected]

Radiation Safety Program Web Page http://www.uottawa.ca/services/ehss/ionizing.htm

REGULATORY AGENCIES

• Canadian Nuclear Safety Commission (CNSC)• City of Ottawa • Ontario Fire Marshall• Transport Canada• Ontario Ministry of Labour

Radiation Safety Committee• Reports to the Board of Governors• Chaired by Vice-Rector, Research• Ensures compliance with CNSC regulations

and license conditions, issues permits

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

STAKEHOLDERSSTAKEHOLDERS

Radioisotope Permit Holder• Ensures all University regulations, policies and 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

STAKEHOLDERSSTAKEHOLDERS

PERMITS

1. Open Sources

2. Sealed Sources

3. Sealed Sources incorporated in a device

4. Exempt Quantities

with associated permit conditions

COURSE OUTLINE

GENERAL INTRODUCTIONphysical and biological characteristicsrisk analysisunits and calculations

OPERATIONAL PROCEDURESordering and receipt of materialinventory and disposal

monitoring

SAFE PRACTICES

personal protection

handling procedures

laboratory safety

MOVIE

WHAT IS RADIATION ? WHAT IS RADIATION ?

RADIATION

• Spontaneous decay

• Half-life

• 4 geometry

Excess p & n alpha particles

Excess p positron ( + )

Excess n negatron ( - )

Excess nuclear E gamma ray

Excess orbital E X-ray

RADIATIONRADIATION

ALPHA EMISSION

• origin: DISINTEGRATING NUCLEUS (Mainly heavy nuclei)

• 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

• static eliminator typically use Polonium-210, an alpha emitter, to ionize air, allowing the 'static cling' to more rapidly dissipate. (half-life of 138.376 days)

• Americium-241 is used in smoke detector

ALPHA EMISSION

It is the decay of the element polonium discovered by Marie-Cuire, with Mass number 210. The 210Po is the second last

member of the uranium-radium- decay series; it decays into a stable lead isotope with a half-life of 138 days. In almost all cases,

the decay is via the emission of an alpha particle of 5.305 MeV

BETA EMISSION

• origin: DISINTEGRATING NUCLEUS

• form of radiation: NEGATRON (electron) POSITRON (similar to an electron but

positive charge)

• energy range: 0.02 - 4.8 MeV

• range of travel: 0 - 10 m in air

• other characteristics: DIFFERS FROM AN ELECTON IN ORIGIN AND ENERGY; TRAVELS ALMOST THE SPEED OF LIGHT; ALMOST NO MASS

(9.1x 10-31 kg)

• beta decay is a type of radioactive decay in which a beta particle (an electron or a positron) is emitted from an atom. There are two types of beta decay: beta minus and beta plus. In the case of beta decay that produces an electron emission, it is referred to as beta minus (β−), while in the case of a positron emission as beta plus (β+)

• Tritium and contains one proton and two neutrons in its nucleus. It is radioactive, decaying into Helium-3 through β− decay with a half-life of 12.32 years

GAMMA EMISSION

• origin: NUCLEUS

• form of radiation: ELECTROMAGNETIC RADIATION (emr - photon)

• energy range: 10 keV - 3 MeV

• range of travel: 100 m in air

• other characteristics: ZERO MASS, ELECTRICALLY NEUTRAL

• Gamma radiation is composed of photons, which have neither mass nor electric charge. Gamma radiation penetrates much further through matter than either alpha or beta radiation.

• Example Co-60, I-125, Tc 99m

Decay chains

An example is the natural decay chain of 238U, which is as follows:

decays, through alpha-emission, with a half-life of 4.5 billion years to thorium-234which decays, through beta-emission, with a half-life of 24 days to protactinium-234which decays, through beta-emission, with a half-life of 1.2 minutes to uranium-234which decays, through alpha-emission, with a half-life of 240 thousand years to thorium-230which decays, through alpha-emission, with a half-life of 77 thousand years to radium-226which decays, through alpha-emission, with a half-life of 1.6 thousand years to radon-222which decays, through alpha-emission, with a half-life of 3.8 days to polonium-218which decays, through alpha-emission, with a half-life of 3.1 minutes to lead-214which decays, through beta-emission, with a half-life of 27 minutes to bismuth-214which decays, through beta-emission, with a half-life of 20 minutes to polonium-214which decays, through alpha-emission, with a half-life of 160 microseconds lead-210which decays, through beta-emission, with a half-life of 22 years to bismuth-210which decays, through beta-emission, with a half-life of 5 days to polonium-210which decays, through alpha-emission, with a half-life of 140 days to lead-206, which is a stable nuclide.

The daughter nuclide of a decay event may be unstable (radioactive). In this case, it will also decay, producing radiation. The resulting second daughter nuclide may also be radioactive. This can lead to a sequence of several decay events. Eventually, a stable nuclide is produced. This is called a decay chain

Decay chains

X-RAY EMISSION

• origin: ORBITAL ELECTRON

• form of radiation: ELECTROMAGNETIC RADIATION (emr - photon)

• energy range: 10eV - 120 keV

• range of travel: 100 m in air

• other characteristics: ZERO MASS, ELECTRICALLY NEUTRAL

What is Depleted Uranium (DU)?

• Depleted uranium (DU) is a by-product of the uranium enrichment process.

• DU is mildly radioactive, about 60% less radioactive than natural uranium.

• The main difference between DU and natural uranium is its content of an isotope called U235

• DU contains less U235 than natural uranium. • The material left over from the production of enriched uranium is

classified as DU. • DU typically contains U238 (99.8% by mass), U235 (0.2% by

mass) and U234 (0.001% by mass).

What Canadian regulations for DU are in place?

• Depleted uranium, like other uranium in Canada, is subject to the Nuclear Safety and Control Act and its Regulations.

• DU, imported or exported, may also be subject to Bilateral nuclear cooperation agreements concluded between Canada and other states.

• The import and export of all DU, regardless of quantity, requires a licence issued under the Nuclear Non-Proferation Import and Export Control Regulations.

• transport Canada regulates the DU waste disposal

Challenges

General Understanding

• “depleted uranium” there is a perception that this material is not

radioactive. This belief is reinforced as the material is sold as a chemical and arrives in a package without radioactive labelling. Nor does the supplier require any proof of authorization, which is typical when ordering radioactive material.

Challenges (continue)Regulatory Requirements

• One of the key challenges associated with its use and disposal is to determine what federal and provincial bodies may regulate this material. CNSC regulates radioactive material, yet not all of its regulations apply to Depleted Uranium. The criteria used to determine which specific regulations apply depend on the activity associated with the depleted uranium and its intended use. Transport Canada (TC) will regulate this material during transport, through the application of the Transportation of Dangerous Good Regulation.

• For these reasons, depleted uranium must be managed as radioactive material with detail monitoring of the activity and volume/mass of waste generated.

IONIZATION• Electron is removed from an electron shell leaving a charged particle.

EXCITATION• Electron is raised to a higher energy level but isn’t knocked out of the shell

INTERACTION WITH MATTER

BREMSSTRAHLUNG• A negatron approaches the nucleus and is accelerated.

• As it leaves the nucleus it decelerates and emits excess energy as emr.

INTERACTION WITH MATTERINTERACTION WITH MATTER

INTERACTION WITH BIOLOGICAL MATTER

DIRECT

• vital cell structuresINDIRECT

• ionizes H2O

• forms peroxides

• interacts with the vital cell structure

RADIATION RANGES IN TISSUE

(average linear dimension of a cell = 17.1 m )

• alpha particles of 210Po ……… 15m• beta particles of 3H …………… 5 m• beta particles of 32P ……….. 300 m• gamma rays of 60Co …………. infinity

RADIOSENSITIVITY OF CELLS

• Blood producing and reproductive cells are the most sensitive

• Muscle, nerve and bone cells are the least.At low doses, the effects of radiation are not known.

INTERNAL DOSES

• CRITICAL ORGANS 3H – Body water or tissue 14C – Fat tissue 32P – Bones 35S – Gonads 125I – Thyroid 57Co – Large Intestine Depleted Uranium- Liver, spleen and kidney

PREGNANCY

EXTERNAL DOSES

Alpha particles

Beta particlesGamma rays

BIOLOGICAL RESPONSE TO RADIATION

• No change• Mutation and repair• Permanent change with limited effect• Changes leading to cancer or other effects• Death of cell / organism (minutes - years)

THE EFFECTS OF RADIATION ON THE HUMAN BODY

• Genetic

» appears in latter generations

» due to cell damage of the reproductive organs• Somatic

» appears in the irradiated individual

» immediate or delayed effects• Stochastic

» refers to probability of biological effect due to ionizing radiation

» assumes effect is proportional to dose / dose rate, i.e., no safe threshold

Dose Limits:non-NEWnon-NEW NEWNEW

Whole body, gonads, 1 mSv 50 mSvbone marrowSkin, thyroid, bone 50 mSv 500 mSvTissue of hands, feet, 50 mSv 500 mSv and forearms

THERMOLUMINESCENT DOSIMETRYTHERMOLUMINESCENT DOSIMETRY

COMPARISON OF RISK

• exposure to 100 Sv ionizing radiation

• smoking 1.5 cigarettes

• travelling 50 miles by car

• being male and 60 years old for 20 minutes

• canoeing for 6 minutes

UNITS OF RADIATION

• ACTIVITY

• ABSORBED DOSE

• DOSE EQUIVALENT

ACTIVITY UNITS

Non - S.I. (Système international)

CURIE (Ci)

1 Ci = 3.7 x 1010 dps

S.I.

BECQUEREL (Bq)

1 Bq = 1 dps

ABSORBED DOSE UNITS

Non - S.I.

RAD (rad)

1 rad = 100 ergs of energy/g

S.I.

GRAY (Gy)

1 Gy = 1 joule of energy/kg

DOSE EQUIVALENT UNITS

Non - S.I.

REM (rem)

1 rem = rad x Quality Factor

S.I.

SIEVERT (Sv)

1 Sv = Gy x Quality Factor

CALCULATIONS

TWO IMPORTANT CALCULATIONS:

1. Decay correction

2. Converting cpm to Curies

1. DECAY CORRECTION

A = Aoe - t

A = activity at time “t”

Ao = activity at time zero

t = elapsed time

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

CALCULATIONSCALCULATIONS

Example:

• 250 Ci of 35S arrived on May 19, 2005• 100 Ci was removed and used the same day.• The remaining amount was stored in a freezer for future use.• On June 30, 2005, it is decided to repeat the experiment.

? Does another order of 35S have to be placed or is there enough remaining activity that the experiment may proceed?


Solution:

A = A0e - t

A = activity at time ‘t’ ( ? )

A0 = activity at time zero (250 - 100 = 150 Ci)t = elapsed time (42 days)

= decay constant (0.693 / 87 days = 0.00797)

A = (150)e - (0.00797)(42)

A = 107.32 Ci

(** SAVINGS **)


2. CONVERTING CPM TO CURIES

Step 1 Determine counting

efficiency of the detector.

Step 2 Convert cpm to dpm.

Step 3 Convert dpm to Curie.


Step 1 Determine counting efficiency of the detector using a source with a known activity.

% efficiency = observed cpm - background cpm x 100 source of emission rate (dpm)

Ex. count rate = 2045 cpm

background = 65 cpm

source = 220 Bq = 1.32 x 104 dpm

% efficiency = 2045 - 65 cpm = 15% 1.32 x 104 dpm


Step 2 Convert cpm to dpm.

dpm = corrected cpm

efficiency

Ex. Sample = 4925 cpm

background = 65 cpm

efficiency = 15%

dpm = 4925 - 65 = 32,400

0.15


Step 3 Convert dpm to curie.Since 1 Bq = 1 dps = 2.7 x 10-11 Ci

Then 60 dpm = 2.7 x 10-11 Ci

Therefore 32,400 dpm = 1.48 x 10-8 Ci

or, # Bq = __1.48 x 10-8 Ci_ = 540 Bq 2.7 x 10 -11 Ci/Bq


CLASSIFICATION OF LABORATORY

Annual Limit on Intake (ALI)The activity, in Becquerel (Bq), of a radionuclide that will deliver an effective dose of 20 mSv after the radionuclide is taken into the body Basic: 5 X ALI Intermediate: 5-50 X ALI High: 50-500 X ALI

Exemption Quantity (EQ)

The quantity, in Becquerel (Bq), of a radionuclide, below which no licence is required

10000 EQ: Written approval from CNSC

EQ does not apply to the licensee (i.e. contamination monitoring)

CLASSIFICATION OF RADIONUCLIDES

• Contamination levels• Decommissioning levels

Class A (high): Na-22, Zn-65Class B (med): Rb-86Class C (low): H-3, C-14 , S-35, Ca-45,

P-33, P-32, I-125

DECAY PRODUCTS

32P Sulphur

14C Nitrogen

35S Chlorine

3H Helium-3

OPERATIONAL PROCEDURES

• Ordering• Receipt of Radioactive Material (TDG)• Inventory• Disposal• Monitoring• Inspection of Laboratories

ORDERING

• Radioactive materials purchase procedures

- Radioisotopes Purchase Requisition form

- Form must be complete (PO number, signature)

- EHSS approval before ordering

- Documentation (packing slips, shipper’s declaration)

• Permit conditions

• Material purchased for other labs

• Inventory records

PURCHASEPURCHASEREQUISITIONREQUISITION

FORMFORM

RECEIPT OF RADIOACTIVE MATERIAL

• TDG – Class 7

- Definition of radioactive materials

- Radioactive packages

- Radiation warning labels

- Receipt of radioactive material

TDG – CLASS 7DEFINITION OF RADIOACTIVE MATERIAL FOR TRANSPORT

Former: - 70kBq/kg

New: - radionuclide dependent - types of radiation - energies - chemical forms

- potential biological effect on persons

TDG – CLASS 7

Radioactive packages may be shipped as:

- Excepted packages

- 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

TDG – CLASS 7

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

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

TDG – CLASS 7

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: 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

TDG – CLASS 7

RECEIPT OF RADIOACTIVE MATERIAL

- Radioactive packages must be delivered to the laboratory using a cart to increase distance between the transporter and the package in order to minimize radiation exposure - Inspect packaging both externally and internally for damage or leakage - Perform contamination monitoring on the package, vial holder and vial - Deface wording and labels prior to disposal of the package - Complete an Inventory of Use and Disposition form

Report any anomalies to the supervisor and RSO

INVENTORY

• Sealed Sources

(encapsulated, incorporated in a

device, check sources)• Open Sources• Transfers

** HISTORICAL

INVENTORY

DISPOSALDISPOSAL

Solid

Waste

Water-Soluble

Waste

Liquid Scintillation

Waste

Animal Carcasses

Waste

Radioactive

Waste

Landfill

(1 DL / kg)

Short-Term Storage

(t 1/2 = 90 days)

(1 DL/kg)

Off-Site

Disposal

(e.g., sealed sources)

Solid Waste

DISPOSAL LIMITS (DL) TO MUNICIPAL GARBAGE

C-14: 3.7 MBq (100 μCi)/kg; H-3: 37 MBq (1000 μ Ci)/kgI-125: 0.037 MBq (1 μ Ci)/kg; P-32: 0.37 MBq (10 μ Ci)/kg

DISPOSALDISPOSAL

Labels Labels

• On decay can

• Deface contents

• On decay can

• Deface contents

DISPOSALDISPOSAL

DISPOSALDISPOSAL

Time required for decayTime required for decay

A = Ao e - t

t = ln (A/Ao)

-

A = activity at time ‘t’


t = elapsed time

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

A = Ao e - t

t = ln (A/Ao)

-

A = activity at time ‘t’


t = elapsed time

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

DISPOSALDISPOSAL

Example:

• 100 μCi of 32P solid waste collected

• Weight of waste = 0.785 kg

• Disposal limit of 32P is 0.37 MBq/kg (10 μ Ci)

• half life (t1/2) of 32P is 14.3 days

DISPOSALDISPOSAL

Step 1 Determine activity (A) permitted at disposal

Weight = 0.785 kg

1 DL/kg = 10 Ci / kg

A = Weight X 1 DL / kg

A = 0.785 kg X 10 Ci / kg

A = 7.85 Ci

Step 1 Determine activity (A) permitted at disposal

Weight = 0.785 kg

1 DL/kg = 10 Ci / kg

A = Weight X 1 DL / kg

A = 0.785 kg X 10 Ci / kg

A = 7.85 Ci

Solution:

DISPOSALDISPOSAL

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

Step 2: Determine Length of Decay Period (t)

DISPOSALDISPOSAL

DL/Year/Building

Water SolubleWaste

C-14: 0.01 TBq, H-3: 1 TBqI-125: 100 MBq, P-32: 4 GBq

DISPOSALDISPOSAL

Off-Site Disposal

Liquid ScintillationWaste

DISPOSALDISPOSAL

DISPOSALDISPOSAL

Biom edical W aste(Off-Site

D isposal)

Radioactive W aste(Off-Site

D isposal)

Anim al CarcassesW aste

Biom edical W aste(Off-Site

D isposal)

Radioactive W aste(Off-Site

D isposal)

Anim al CarcassesW aste

DISPOSALDISPOSAL

MONITORING

Survey Meters

versus

Contamination Monitors

MONITORING

• Leak testing• Contamination monitoring• Dose rate around storage, waste, use areas

* prior to repair of equipment

Leak Testing (Sealed Sources)

• Sources 1.35 mCi• frequency [6 (in use), 12 (in a device), or 24 months (storage)], • CNSC procedures, • certificates• reporting criteria (200 Bq leakage)• transfers, incidents (immediately)

MONITORINGMONITORING

MONITORING

• Map of lab• Weekly or after 5 x ALI • Decontaminate • Record “no radioisotope used”• After any spill

Contamination Monitoring (Open Sources)Contamination Monitoring (Open Sources)

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 EHSS Criteria0.3 Bq/cm2

MONITORINGMONITORING

Contamination Monitoring

3 easy steps to convert counts per minute (CPM) to Becquerel per centimeter squared (Bq/Cm2)?

Step 1: Determine the Radionuclide Class

The CNSC has grouped radionuclide into 3 classes. The 3 classes are shown below:

Class A Radionuclide: are long-lived or emit alpha radiation

Na-22

Class B Radionuclide: are long-lived or emit beta or gamma radiation

Rb-86,Co-58,Sr-90

Class C Radionuclide: are short-lived and emit beta or gamma radiation

C-14 ,Co-57, H-3,P-32,Ca-45,I-125,Cl-36

Step 2: Determine the regulatory limit

Step 3: Convert CPM to Bq/cm2

Class A (Bq/cm2) Class B (Bq/cm2) Class C (Bq/cm2)

In Lab where Radioactive is used

3 30 300

In Offices 0.3 3 30


Parameters of interest for contamination monitors-Efficiency

Surface

Detector Volume

Detector Covering

Efficiency:1) Distance: 1/r22) Beta Absorption3) Size of window

Not all decay emissionsAre detected!


Converting cpm results into Bq/cm2 for GM pancake

• Bq/cm2 = (Cpm – Bkg) / Ec X Ew X 60 X A• where 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, 35S• 75% (0.75) for 125I• 50% (0.5) for 3H and unknowns

INSPECTIONS

1. General Condition of lab

2. Inventory/Disposal

3. Contamination Monitoring

4. Measurements

5. Questionnaire

Dose rate measurements should be undertaken:

• 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

SAFE HANDLING PRACTICESSAFE HANDLING PRACTICES

A AsL LowA AsR ReasonablyA Achievable

TIME

D = d X t

D = radiation dose

d = radiation dose rate

t = time duration of exposure


DISTANCEInverse Square Law

D1 s12 = D2 s2

2

D1 = dose at distance 1

s1 = distance 1

D2 = dose at distance 2

s 2 = distance 2


SHEILDING• reduces or stops radiation

• dependent on:

- energy of radiation

- type of shielding

remember: 4 geometry


PERSONAL PROTECTION EQUIPMENT

• LAB COAT

• GLOVES

• SAFETY GLASSES

SPILL RESPONSE

1. REPORTING

2. CLEAN-UP

3. LEAVING CONTAMINATED AREA

4. PERSONAL DECONTAMINATION

1. REPORTING

Inform co-workers & supervisor.

Inform Protection Services (5411)

Inform ORM

(3058, 3057)

SPILL RESPONSESPILL RESPONSE

2. CLEAN-UP

1. Attend to injured person and ensure personal safety.

2. Assess the size of the spill.

3. Obtain necessary supplies.

4. Cover spill with absorbent.


5. Push spill towards centre.

6. Decontaminate area in sections.

7. Check for contamination (record).

8. Re-clean as necessary.

9. Inform Radiation Safety Officer of fixed contamination.


3. LEAVING A CONTAMINATED AREA

• Monitor self (especially feet, hands and lab coat).

• Leave lab coat behind if contaminated and remove dosimeter badge.

• Put up sign and lock door.


DO NOT ENTER!Name

Telephone #Nature of Spill

LocationTime of Return


4. PERSONAL DECONTAMINATION

• Use tepid water and mild soap.

• Avoid causing abrasions to skin.

• Wash for a few minutes, dry and monitor. (fingernails too!)

• Carefully monitoring is the only way to measure progress.


WHAT IS RADSECURITY?

Measures employed to protect Radioactive materials, or critical relevant information, against theft or diversion by those who intend to pursue intentional misuse.

Achieved through; Physical barriers

Psychological barriers Monitoring Activities Personnel Clearance

WHAT IS RADSECURITY?

• The primary goal is the establishment of a security culture

• Access is only allowed to authorize individuals.

• When a room containing radioactive material (stocks, samples or waste) is unoccupied for extended periods of time such as in the evenings or when all laboratory personnel are attending a meeting or seminar, the room must be locked.

Responsibilities pertaining to security of radioactive materials in laboratory as outlined by CNSCThe General Nuclear Safety and Control Regulations outline the obligations of the Licensees and the Workers. With regards to ensuring security and reporting any potential breaches or threats, there are three significant sections: Sections12 - Obligations of the Licensee, Section 17 Obligation of the Worker, and Section 29 General Reports.

Summary of Key Clauses are:

Sections 12 - Obligations of the Licensee

(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;

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;

(c) promptly inform the licensee 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,

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

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

Section 29 - General Reports

29. (1) Every licensee who becomes aware of any of the following situations shall immediately make a preliminary report to the Office of Risk Management of the location and circumstances of the situation and of any action that the licensee has taken or proposes to take with respect to it:

information that reveals the incipient failure, abnormal degradation or weakening of any component or system at the site of the licensed activity, the failure of which could have a serious adverse effect on the environment or constitutes or is likely to constitute or contribute to a serious risk to the health and safety of persons or the maintenance of security;

Every licensee who becomes aware of a situation referred to in subsection (1) the report shall contain 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.

Authorized lab Personnel (non-Users)

An Authorized lab personnel is an individual in a lab who have access to radioactive material, but are not authorized users. An application for authorization to access laboratories containing radioactive material for non-radioactive users that are not on the radioisotope permit but they work in a lab can be found under “Internal Radioisotopes Permit”.

The individual who has access to this material must sign a declaration that they have read and agree to the general reporting requirement pertaining to security of radioactive material in laboratory as outlined by CNSC.

Nuclear Safety and Control Act ( 1997, c. 9 ) outlines the general reporting requirements:

Summary of the key clause:

Section 29 - General Reports

(1) Every licensee who becomes aware of any of the following situations shall immediately call Office of Risk management (ORM):

(a) no eat or Drink in the laboratory

(b) no access authorized of anyone not on 1) permit, and 2) Authorized individual.

(c) a release, not authorized by the ORM, of a quantity of radioactive nuclear substance into the environment;

(d) no mixing waste. Do not put any non radioactive waste into a radioactive bucket.

(e) an attempted or actual breach of security or an attempted or actual act of sabotage at the site of the licensed activity;

(f) information that reveals the incipient failure, abnormal degradation or weakening of any component or system at the site of the licensed activity, the failure of which could have a serious adverse effect on the environment or constitutes or is likely to constitute or contribute to a serious risk to the health and safety of persons or the maintenance of security;

(g) an actual, threatened or planned work disruption by workers;

(h) a serious illness or injury incurred or possibly incurred as a result of the licensed activity;

(i) do not touch or handle any radioactive material

(2) Every licensee who becomes aware of a situation referred shall file a full report of the situation, and report to ORM and the report shall contain 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;

Suspicious packages

Unopened

Do not open and do not shake Place in secondary container or cover Inform others of the situation Clear the room and section off the area All individuals who may have come into contact with the material

must wash their hands Call Protection Services and wait for their arrival List all the individuals present in the room or area when the package

arrived. Give this list to Protection Services for follow-up

Suspicious packages

Opened

• Contents Intact• Do not manipulate contents further• Cover the package• Inform others of the situation• Clear the room and section off the area• All individuals who may have come into contact with the material

must wash their hands• Call Protection Services and wait for their arrival• List all the individuals present in the room or area when the package


Suspicious packages

Contents not intact (spilled)

• Do not try to clean up the spill• Gently cover the spill• Inform others of the situation• All individuals who may have come into contact with the material

must wash their hands• Call Protection Services• Remove heavily contaminated clothing (place in bag) and shower

using soap and water• List all the individuals present in the room or area when the package


SUMMARY

External Dose: time distance shielding

Internal Dose: critical organs

prevent: …. ingestion

…….absorption

…….inhalation

THINK SAFETY

PLAN

PRACTICE

REVIEW

Documents

RADIATION SAFETY TRAINING Presented by: Ali Shoushtarian Office of Risk Management, Last revised May. 2012