RADIATION SAFETY TRAINING

RADIATION SAFETY TRAINING
Presented by: Ali Shoushtarian Office of Risk Management, Environmental Health and Safety Service Radiation: energy in transit 1. Kinetic: particles 2. EMR: photon (heat, UV, radiofrequency) Ionizing Radiation any radiation displacing electrons from atoms or molecules thereby producing positively and negatively charged ions. Last revised Jan

Manager, Radiation and Biosafety Lois Sowden-Plunkett ext
Manager, Radiation and Biosafety Lois Sowden-Plunkett ext Compliance Inspector Ali Shoushtarian ext Radiation Safety Program Web Page Start training session by viewing: Howard Hughes Medical Institute Video: “ Safety in the Research Laboratory – Radionuclide Hazards”

REGULATORY AGENCIES Canadian Nuclear Safety Commission (CNSC)
City of Ottawa Ontario Fire Marshall Transport Canada Ontario Ministry of Labour CNSC: Risk Based Regulatory Program: Identifies 13 Safety Control Areas (Radiation Protection, Emergencies and Unplanned Events, Environmental Protection, Training and Qualifications, Operational Procedures, Organization and Management, Security, International Obligations/ Safeguards, Packaging and Transportation) Inspections + Audits + Annual Reports Consolidated License, License Conditions, Internal Permits University HIGH RISK City of Ottawa Regulates sewer limit, water soluble Ontario Fire Marshall Quantity of radioactive material in lab, can refuse to respond Transport Canada Transportation of Radioactive Material International Regulations also apply (ICAO, IATA) TC/ CNSC cross jurisdictional agreement MOL X-ray emitting devices Workers health and safety

STAKEHOLDERS 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 RSC – -Vice-Rector Academic, Associated Vice- Rector Research, All Deans, Principle Investigators, Resource Personnel (Legal Council, OHDL) - receives report on compliance status, risk rating, CNSC activities, program development/status ORM - ensures adherence: compliance monitoring: record review, program review, inspections, investigations - rate performance ( inspection / overall: low, med. High) - authority to close lab

STAKEHOLDERS Radioisotope Permit Holder Radioisotope User
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 All must comply with Permit Conditions, Program (manual, web, SOP) Basic issues: Start Up: signage, work areas, procedures, records, defining responsible persons) authorized users approved (not the same as coming to training) see forms Use: Permit accurate, complete inventory, forwarded forms, monitoring, disposal Decommissioning: - signage, inventory, monitoring

PERMITS 1. Open Sources 2. Sealed Sources
3. Sealed Sources incorporated in a device 4. Exempt Quantities with associated permit conditions List: radioisotopes, activites, contact info, authorized users: may also list ALI, EQ, Leak testing frequency, locations Accountability: Individual performance, impact the research community at large Measurable criteria: -inspections, tld, records Consequences: discussion with supervisor, chair, dean, RSC….Board of Governors ERRORS AND OVERSIGHTS CAN OCCUR: BUT MUST BE ADDRESSED QUICKLY AND PROCEDURES PUT IN PLACE TO PREVENT REOCCURENCE. DILIGENCE CRITICAL (CNSC: reports 1 missed recorded as records incomplet)

COURSE OUTLINE personal protection handling procedures
GENERAL INTRODUCTION physical and biological characteristics risk analysis units and calculations OPERATIONAL PROCEDURES ordering and receipt of material inventory and disposal monitoring SAFE PRACTICES personal protection handling procedures laboratory safety MOVIE Videos At very start of training: Howard Hughes Medical Institute Video: “ Safety in the Research Laboratory – Radionuclide Hazards” 2. After operation procedures: University of Calgary: “ Radiation Safety II: Key to Contamination Detection” 3. After Safe Practices “ Radiation Safety II: The Key to Decontamination Procedures”

WHAT IS RADIATION ? WHAT IS RADIATION ?

RADIATION Spontaneous decay Half-life 4 geometry
Radioactivity: spontaneous transformation of unstable nuclides to a stable state. Stability is provided by a specific proton/neutron ratio for each nuclide. This process is referred to as radioactive decay. The associated energy is either kinetic or electromagnetic. Radioactive Decay: spontaneous random naturally occurring energy emitted in all directions Sources: cosmic (latitude, altitude, Dever Col. Sandy Hill vs Kanata) terrestrial (land, water, incorporated food: peanuts-pCi , bodies) man-made (particle accelerators, x-rays) Half-Life Although decay is random over a given period of time the activity of the radionuclide will be reduced by half. This associated period of time is referred to half-life and may be second, days, years. P-32 (14 days), Ca-45 (165 days), H-3 (12 yrs), C-14 ( 5730 yrs), U (109 yrs)

RADIATION Excess p & n  alpha particles Excess p  positron ( + )
Excess n  negatron (  - ) Excess nuclear E  gamma ray Excess orbital E  X-ray Nomenclature: A (atomic mass = P + N) CHEMICAL SYMBOL Z (atomic number = P) Isotopes = nuclides with same number of protons ( Z= 6 Stable ( C12, C13) Radioisotopes = unstable isotopes ( C14) Decay Schemes Excess P+N nuclide emits 2P + 2N Excess P converts P to N Emits positron plus a anit-neutrion Can only exist in transitory state, interacts with electrons, annihilation of both particles = EMR Excess N converts N to P emits negatron and neutrino E = mass loss btwn parent and progeny E can be min. Emax is associated with neutrino Excess Nuclear E after alpha and beta emission, excess nuclear E emitted as EMR Internal conversion gamma rat interact with orbital electron emitted. Electron same mass and chare as beta but mono energetic

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 Excess P+N..emits 2P + 2N heavy mass (7,000 x the mass of electron) Travel distance small…..therefore risk inhalation or ingestion ext. Uranium, Radium

BETA EMISSION origin: DISINTEGRATING NUCLEUS
form of radiation: NEGATRON (electron) POSITRON (similar to an electron but positive charge) energy range: MeV range of travel: m in air other characteristics: DIFFERS FROM AN ELECTON IN ORIGIN AND ENERGY; TRAVELS ALMOST THE SPEED OF LIGHT; ALMOST NO MASS (9.1x kg) Excess N….emit a negatron… N>P Excess P,….emit a positron If unstable interact with orbital electron..anniliated

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 High energy, short wavelength, neutral therefore does not interact with material able to penetrate many types of matter. lead

X-RAY EMISSION origin: ORBITAL ELECTRON
form of radiation: ELECTROMAGNETIC RADIATION (emr - photon) energy range: 10eV keV range of travel: 100 m in air other characteristics: ZERO MASS, ELECTRICALLY NEUTRAL Electron excited to higher energy state…when return to stable state emits emr REMEMBER RADIONUCLIDES CAN UNDERGO ALL TYPES OF DECAY MAY DECAY TO ANOTHER RADIONUCLIDE WHICH MAY EMIT DIFFERENT FORMS OF RADIATION WITH DIFFERENT ENERGIES.

INTERACTION WITH MATTER
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 Ionization sufficient energy is present to cause another atom or molecular to be split into ion pairs +/- Excitation emr is released in the form of electron, returns to orbital shell releases excess energy

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. EMR = incident E (electron) + E (electrical field) Greater in nuclides with higher atomic numbers (Z) X-rays are produced in the interaction of P-32 beta particle and lead Therefore lead is not recommended

INTERACTION WITH BIOLOGICAL MATTER
DIRECT vital cell structures INDIRECT ionizes H2O forms peroxides interacts with the vital cell structure Membrane proteins, DNA, mitochondria,

RADIATION RANGES IN TISSUE
(average linear dimension of a cell = 17.1 m ) alpha particles of 210Po ……… 15m beta particles of 3H …………… 5 m beta particles of 32P ……… m gamma rays of 60Co …………. infinity During transit it will deposit the energy in the travel path thus a cell and all of its components may be exposed to a great deal of energy.

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. Bone marrow White blood cells Lymphocytes Monocytes etc

INTERNAL DOSES CRITICAL ORGANS 3H – Body water or tissue
14C – Fat tissue 32P – Bones 35S – Gonads 125I – Thyroid 57Co – Large Intestine PREGNANCY Critical Organs: I-125 thyroid H-3 DNA C-14 spleen, fatty tissue Co-57 lower large intestine P-32 bone Cr-51 spleen S-35 testis Pregnancy: 1St trimester (8 wks) most sensitive to the developing fetus Remember decay energy and form must be able to penetrate into womb (internal or external source.) More detail info available on request ORM must be informed to assess current protocols, past exposures…Risk Monitoring requirement may increase

EXTERNAL DOSES Gamma rays Beta particles Alpha particles

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) Acute change to white cell count = 250 X annual limit Heredity ill health in children conceived after a parent is exposed to 1000 mSv is 1% YOUR ANNUAL LIMIT IS = 1 mSv

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

THERMOLUMINESCENT DOSIMETRY
Dose Limits: non-NEW NEW Whole body, gonads, mSv mSv bone marrow Skin, thyroid, bone mSv mSv Tissue of hands, feet, mSv mSv and forearms Monitoring with TLD LiF Chip behind foil = external dose LiF Chip behind aluminum plug = internal dose Wrist Badges and Ring badges also available Dose to Natural Radiation = 2-3 mSv /yr

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
Important Dates & the Background to the Naming of Units W. Roentgen – discovered x-ray H. Becquerel – discovered uranium salts exposed film Marie and Pierre Currie – isolated Po form ore and identified alpha particle 1915 International Commission on Radiological Protection (ICRP) created 1928 first health effects noted (skin burns, deformed fingers, cancer) Atom was split and release of nuclear energy

ACTIVITY UNITS CURIE (Ci) 1 Ci = 3.7 x 1010 dps BECQUEREL (Bq)
Non - S.I. (Système international) CURIE (Ci) 1 Ci = 3.7 x 1010 dps S.I. BECQUEREL (Bq) 1 Bq = 1 dps 1 gm of Radium was discovered to emit 3.7 x 1010 dps

ABSORBED DOSE UNITS RAD (rad) 1 rad = 100 ergs of energy/g GRAY (Gy)
Non - S.I. RAD (rad) 1 rad = 100 ergs of energy/g S.I. GRAY (Gy) 1 Gy = 1 joule of energy/kg RADIATION ABSORBED DOSE = RAD

1 rem = rad x Quality Factor
DOSE EQUIVALENT UNITS Non - S.I. REM (rem) 1 rem = rad x Quality Factor S.I. SIEVERT (Sv) 1 Sv = Gy x Quality Factor ROETGEN EQUIVALENT MAN = REM 1 rem = coulombs / kg tissue QF = quality factor ……takes into account the form of decay alpha = 20 beta = 1 gamma = 1

CALCULATIONS 1. Decay correction 2. Converting cpm to Curies
TWO IMPORTANT CALCULATIONS: 1. Decay correction 2. Converting cpm to Curies

CALCULATIONS A = Aoe -  t 1. DECAY CORRECTION
A = activity at time “t” Ao = activity at time zero t = elapsed time  = decay constant ( = / t 1/2)

CALCULATIONS 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?

CALCULATIONS Solution:  = decay constant (0.693 / 87 days = 0.00797)
A = A0e - t A = activity at time ‘t’ ( ? ) A0 = activity at time zero ( = 150 Ci) t = elapsed time (42 days)  = decay constant (0.693 / 87 days = ) A = (150)e - ( )(42) A = Ci (** SAVINGS **)

2. CONVERTING CPM TO CURIES
CALCULATIONS 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.

CALCULATIONS 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 = cpm background = 65 cpm source = 220 Bq = x 104 dpm % efficiency = cpm = % 1.32 x 104 dpm

CALCULATIONS Step 2 Convert cpm to dpm. dpm = 4925 - 65 = 32,400
dpm = corrected cpm efficiency Ex. Sample = 4925 cpm background = 65 cpm efficiency = 15% dpm = = 32,400 0.15

Step 3 Convert dpm to curie.
CALCULATIONS Step 3 Convert dpm to curie. Since 1 Bq = 1 dps = 2.7 x Ci Then 60 dpm = 2.7 x Ci Therefore 32,400 dpm = 1.48 x 10-8 Ci or, # Bq = __1.48 x 10-8 Ci_ = 540 Bq 2.7 x 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: X ALI High: 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

CLASSIFICATION OF RADIONUCLIDES
Contamination levels Decommissioning levels Class A (high): Na-22, Zn-65 Class B (med): Rb-86 Class C (low): H-3, C-14 , S-35, Ca-45, P-33, P-32, I-125 AT THE END OF THIS SLIDE ITS VIDEO TIME!!!!!!!!!!!!1 WATCH VIDEO ON CONTAMTINATION DETECTIONS

DECAY PRODUCTS 32P  Sulphur 14C  Nitrogen 35S  Chlorine
3H  Helium-3 The unstable atoms are moved toward attaining stability much like an unstable car on top of a hill rolls to the bottom to become more stable. The process of going from an unstable to a more stable form is the process that is called radioactive decay An unstable radioactive atom which stabilizes by radioactive decay always forms a different element. P-32 decays to stable S-32 (non radioactive) P-32 > S-32 + electron + electron antineutrino + energy

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

PURCHASE REQUISITION FORM

RECEIPT OF RADIOACTIVE MATERIAL
TDG – Class 7 - Definition of radioactive materials - Radioactive packages - Radiation warning labels - Receipt of radioactive material Transportation of Dangerous Goods or (TDG) acts classifies different potential hazards material for transportation purpose and according to its acts radioactive materials marked as class 7. This acts also defines the type of packages and labels requirements for different kind of radioactive materials.

DEFINITION OF RADIOACTIVE MATERIAL FOR TRANSPORT
TDG – CLASS 7 DEFINITION 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 - Radioisotopes are most frequently shipped as Excepted Packages or as Type A Packages. “Excepted package" means a package that meets the requirements of IAEA Regulations Industrial Package differ as to the degree to which they are required to be capable of withstanding damage. 700 kPa maximum normal operating pressure

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 warning labels as follows: Any package shipped as "Excepted Package -Limited Activity" must be indicated as such by the shipper on the shipping documentation and the word "radioactive" must be visible on opening the package.

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 Report any anomalies to the supervisor and RSO
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 - Radioisotope Inventory should include the sealed source (including the sealed sources in a device, open source and some source borrowed from some other users. - Historical means you are working in a lab and found some old sealed source either disposed off before or no records of previous owner

INVENTORY

DISPOSAL Solid Waste Water-Soluble Liquid Scintillation
Animal Carcasses Radioactive Radioactive waste includes surplus of radioisotope material in any form, material that has come into direct contact with radioactive material (e.g., gloves, culture dishes, pipettes, flasks, etc.). materials used for radioactive decontamination (e.g., paper towels, sponges, etc.). Solid non-sharp waste for disposal must be placed in designated radioactive waste containers Water-soluble liquid waste if have insignificant amounts of activity and meeting the criteria of CNSC can be defined as non radioactive chemical waste and may be disposed to the regular drain, followed by several litres of running water to ensure that the sink trap is flushed completely. LSW Depending upon the activity associated with this waste it may be subsequently sent off-site either as low level radioactive material or chemical waste

DISPOSAL LIMITS (DL) TO MUNICIPAL GARBAGE
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)/kg I-125: MBq (1 μ Ci)/kg; P-32: 0.37 MBq (10 μ Ci)/kg Use 20 L pails …line with plastic bag …..deface all material before placing in pail …label pail with 2 waste labels on opposite sides ….place log sheet on pail, update as material is placed in pail

DISPOSAL Labels On decay can Deface contents

DISPOSAL

DISPOSAL Time required for decay A = Ao e -  t t = ln (A/Ao) - 
A = activity at time ‘t’ Ao = activity at time zero t = elapsed time  = decay constant (  = / t 1/2 )

DISPOSAL Example: 100 μCi of 32P solid waste collected
Weight of waste = kg Disposal limit of 32P is 0.37 MBq/kg (10 μ Ci) half life (t1/2) of 32P is 14.3 days

DISPOSAL Solution: Step 1 Determine activity (A) permitted at disposal
Weight = kg 1 DL/kg = 10 Ci / kg A = Weight X 1 DL / kg A = kg X 10 Ci / kg A = 7.85 Ci

Step 2: Determine Length of Decay Period (t)
DISPOSAL 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 = /day) t = ln (7.85 Ci / 100 Ci) = days /day

DL/Year/Building Water Soluble Waste
DISPOSAL DL/Year/Building Water Soluble Waste C-14: 0.01 TBq, H-3: 1 TBq I-125: 100 MBq, P-32: 4 GBq

Off-Site Disposal Liquid Scintillation Waste

DISPOSAL

DISPOSAL Animal waste: Use double bag (black)
Fill out necropsy tag (available from ACVS) Place in disposal bin in ACVS Complete Radioactive Animal Waste Log… Verify your understanding with ORM

Survey Meters versus Contamination Monitors
MONITORING Survey Meters versus Contamination Monitors ALL METERS are not created equal Survey meter are calibrated annually (CNSC requirement) to calibrate dose rate uSv/hr or mR/hr Contamination meters are initially calibrated to detect radiation. Efficiency depends upon the detector, and decay mode Various types: gas, liquid, solid Geiger muler, liquid scintillation, NaI, Proportional strength and weakness depending on what energy and form of energy is being detected (particle vs emr) See web page . CNSC Safety Guide on Monitoring page

MONITORING Leak testing Contamination monitoring
Dose rate around storage, waste, use areas * prior to repair of equipment Make sure detector is operating correctly…..verify with ORM check battery ..last survey = 7 low

Leak Testing (Sealed Sources)
MONITORING 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)

Contamination Monitoring (Open Sources)
Map of lab Weekly or after 5 x ALI Decontaminate Record “no radioisotope used” After any spill Map of the areas radioactive material is used. Include: lab benches, the fume hood, pipettors, vortexors, and liquid scintillation counters. Monitoring is required weekly whenever radioactive material has been used. And after any use of greater then 1000 SQ (Scheduled quantities are license exempt from CNSC). Use a the proper instrument for your isotope, minimum counting efficiency permitted for the isotope is 20 %. - Before you start, check that the battery is OK, - Go slow enough to find to allow the monitor to work. - Make sure probe is close enough to surface being monitored, keep in mind to avoid contaminating the probe, remember the none obvious locations like the fridge/freezer handles. If an area above twice background is found it must be decontaminated. (Our licence requires that all areas with a radiation level above 5 Bq/cm2 averaged over 100 cm, If no use record the fact, no blanks should be in the records, if monitoring was forgotten record this. Monitor after any spill of suspect spill.

MONITORING EHSS Criteria 0.3 Bq/cm2 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 The areas listed in the monitoring records must correspond to the map. To summarise: use an instrument that will detect the radio-isotope being used check that the instrument is working remember the none obvious locations decontaminate and record the activity after decontaminate compared to a new background Record if no radioactive material has been used - Non-fixed contamination does not exceed 0.3 Bq /cm2 averaged over an area not exceeding 100 sq.cm2. EHSS Criteria 0.3 Bq/cm2

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 PRACTICES
A As L Low R Reasonably A Achievable PLAN, PREPARE, REVIEW Undertake “cold runs” Ask others Don’t rush Consider Types of radioactive decay critical organs associated energy

TIME D = d X t D = radiation dose d = radiation dose rate t = time duration of exposure

DISTANCE Inverse Square Law D1 s12 = D2 s22 D1 = dose at distance 1 s1 = distance 1 D2 = dose at distance 2 s 2 = distance 2 Increase distance by 10 cm…….decrease dose by 1/100 If time and distance are constant Radiation dose received id decreased in proportion to the square of the distance from the radiation source. Use: forceps step back move stock to a distant location Especially important during a spill.

SHEILDING reduces or stops radiation dependent on: - energy of radiation - type of shielding remember: 4 geometry Can calculate the shielding required by determining the Half- Layer Value ……see manual H-3, C-14, S-35 no shielding required I mm lead P-32 2 cm Plexiglas Na cm lead bricks adequate

PERSONAL PROTECTION EQUIPMENT
LAB COAT GLOVES SAFETY GLASSES Examples of failure to wear PPE Contaminated clothes Face (near eye) splashed with radioactive solution

SPILL RESPONSE 1. REPORTING 2. CLEAN-UP 3. LEAVING CONTAMINATED AREA
4. PERSONAL DECONTAMINATION

SPILL RESPONSE 1. REPORTING  Inform co-workers & supervisor.
 Inform Protection Services (5411)  Inform ORM (3058, 3057)

SPILL 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.

SPILL RESPONSE 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
SPILL RESPONSE 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.

SPILL RESPONSE DO NOT ENTER! Name Telephone # Nature of Spill Location Time of Return

4. PERSONAL DECONTAMINATION
SPILL RESPONSE 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. Use mild warm water (tepid)

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

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

SUMMARY External Dose: time distance shielding Internal Dose: critical organs prevent: …. ingestion …….absorption …….inhalation

THINK SAFETY PLAN PRACTICE REVIEW
CNSC AND THE UNIVERSITY EXPECTS EVERYONE TO: IMPLEMENT ALARA BE DILIGENT EXPECTATIONS OUTLINED IN PERMIT CONDITIONS, RADIATION SAFETY PROGRAM, INSPECTION CHECK LIST MEASURABLE: INSPECTIONS, TLD, RECORDS CONSEQUENCES YOU, YOUR SUPERVISOR, THE UNIVERSITY SHOW LAST VIDEO ON DECONTAMINATION

RADIATION SAFETY TRAINING

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