Transcript RADIATION SAFETY TRAINING

RADIATION
SAFETY
TRAINING
Presented by:
Ali Shoushtarian
Office of Risk Management, Environmental Health and Safety Service
Last revised Jan. 2009
Manager, 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
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Canadian Nuclear Safety Commission (CNSC)
City of Ottawa
Ontario Fire Marshall
Transport Canada
Ontario Ministry of Labour
STAKEHOLDERS
Radiation Safety Committee
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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
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Manages the radiation safety program
Conducts inspections
Monitors doses, inventory
Conducts training
STAKEHOLDERS
Radioisotope Permit Holder
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Ensures all University regulations, policies and requirements are met
Adheres to all permit limits and conditions
Ensures a safe work environment
Radioisotope User
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Complies with all elements of radiation safety program
Works in a safe fashion (self, colleagues, environment)
attends all appropriate training
PERMITS
1.
2.
3.
4.
Open Sources
Sealed Sources
Sealed Sources incorporated in a device
Exempt Quantities
with associated permit conditions
COURSE OUTLINE
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
WHAT
WHATIS
ISRADIATION
RADIATION??
RADIATION
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Spontaneous decay
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Half-life
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4 geometry
RADIATION
Excess p & n  alpha particles
Excess p  positron ( + )
Excess n  negatron (  - )
Excess nuclear E  gamma ray
Excess orbital E  X-ray
ALPHA EMISSION
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origin: DISINTEGRATING NUCLEUS (Mainly heavy nuclei)
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form of radiation:
PARTICLE
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energy range:
4-8 MeV
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range of travel:
2-8 cm in air
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other characteristics:
LARGE MASS, DOUBLE CHARGE,
HIGH SPECIFIC ACTIVITY
BETA EMISSION
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origin:
DISINTEGRATING NUCLEUS
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form of radiation:
NEGATRON (electron)
POSITRON (similar to an electron but
positive charge)
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energy range:
0.02 - 4.8 MeV
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range of travel:
0 - 10 m in air
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other characteristics: DIFFERS FROM AN ELECTON IN ORIGIN AND ENERGY; TRAVELS
ALMOST THE SPEED OF LIGHT; ALMOST NO MASS (9.1x 10-31 kg)
GAMMA EMISSION
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origin:
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form of radiation:
ELECTROMAGNETIC RADIATION
(emr - photon)
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energy range:
10 keV - 3 MeV
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range of travel:
100 m in air
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other characteristics: ZERO MASS, ELECTRICALLY NEUTRAL
NUCLEUS
X-RAY EMISSION
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origin: ORBITAL ELECTRON
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form of radiation:
ELECTROMAGNETIC RADIATION
(emr - photon)
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energy range:
10eV - 120 keV
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range of travel:
100 m in air
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other characteristics: ZERO MASS, ELECTRICALLY NEUTRAL
INTERACTION WITH MATTER
IONIZATION
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Electron is removed from an electron shell leaving a charged particle.
EXCITATION
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Electron is raised to a higher energy level but isn’t knocked out of the shell
INTERACTION WITH MATTER
BREMSSTRAHLUNG
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A negatron approaches the nucleus and is accelerated.
As it leaves the nucleus it decelerates and emits excess energy as emr.
INTERACTION WITH BIOLOGICAL
MATTER
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DIRECT
vital cell structures
INDIRECT
• ionizes H2O
• forms peroxides
• interacts with the vital cell structure
RADIATION RANGES IN TISSUE
(average linear dimension of a cell = 17.1 m )
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alpha particles of 210Po ……… 15m
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
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CRITICAL ORGANS
 3H – Body water or tissue
 14C – Fat tissue
 32P – Bones
 35S – Gonads
 125I – Thyroid
 57Co – Large Intestine
PREGNANCY
EXTERNAL DOSES
Gamma rays
Beta particles
Alpha particles
BIOLOGICAL RESPONSE TO
RADIATION
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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
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Genetic
» appears in latter generations
» due to cell damage of the reproductive organs
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Somatic
» appears in the irradiated individual
» immediate or delayed effects
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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:
Whole body, gonads,
bone marrow
Skin, thyroid, bone
Tissue of hands, feet,
and forearms
non-NEW
1 mSv
50 mSv
50 mSv
NEW
50 mSv
500 mSv
500 mSv
COMPARISON OF RISK
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exposure to 100 Sv ionizing radiation
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smoking 1.5 cigarettes
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travelling 50 miles by car
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being male and 60 years old for 20 minutes
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canoeing for 6 minutes
UNITS OF RADIATION
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ACTIVITY
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ABSORBED DOSE
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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
CALCULATIONS
1. DECAY CORRECTION
A
Ao
t

A = Aoe -  t
= activity at time “t”
= activity at time zero
= elapsed time
= decay constant ( = 0.693 / t 1/2)
CALCULATIONS
Example:
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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:
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 **)
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
= 2045 cpm
background = 65 cpm
source
= 220 Bq = 1.32 x 104 dpm
% efficiency
= 2045 - 65 cpm
=
15%
1.32 x 104 dpm
CALCULATIONS
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
CALCULATIONS
Step 3 Convert dpm to curie.
1 Bq = 1 dps = 2.7 x 10-11 Ci
60 dpm = 2.7 x 10-11 Ci
Since
Then
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
CLASSIFICATION OF RADIONUCLIDES
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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
DECAY PRODUCTS
32P
 Sulphur
14C
 Nitrogen
35S
 Chlorine
3H
 Helium-3
OPERATIONAL PROCEDURES
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Ordering
Receipt of Radioactive Material (TDG)
Inventory
Disposal
Monitoring
Inspection of Laboratories
ORDERING
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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)
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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
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
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:
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
DISPOSAL
Radioactive
Waste
Solid
Waste
Water-Soluble
Waste
Liquid Scintillation
Waste
Animal Carcasses
Waste
DISPOSAL
Solid Waste
Landfill
Short-Term Storage
Off-Site
(1 DL / kg)
(t 1/2 = 90 days)
Disposal
(1 DL/kg)
(e.g., sealed sources)
DISPOSAL LIMITS (DL) TO MUNICIPAL GARBAGE
C-14: 3.7 MBq (100 μCi)/kg; H-3: 37 MBq (1000 μ Ci)/kg
I-125: 0.037 MBq (1 μ Ci)/kg; P-32: 0.37 MBq (10 μ Ci)/kg
DISPOSAL
Labels
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On decay can
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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 (  = 0.693 / t 1/2 )
DISPOSAL
Example:
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100 μCi of 32P solid waste collected
Weight of waste = 0.785 kg
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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 = 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
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 = 0.0485/day)
t =
ln (7.85 Ci / 100 Ci) = 52.5 days
- 0.0485/day
DISPOSAL
Water Soluble
Waste
DL/Year/Building
C-14: 0.01 TBq, H-3: 1 TBq
I-125: 100 MBq, P-32: 4 GBq
DISPOSAL
Liquid Scintillation
Waste
Off-Site Disposal
DISPOSAL
DISPOSAL
A n im a l C a rc a s s es
W a s te
B io m ed ical W aste
(O ff-S ite
D is p o s a l)
R a d io a c tiv e W a s te
(O ff-S ite
D is p o s a l)
MONITORING
Survey Meters
versus
Contamination Monitors
MONITORING
• Leak testing
• Contamination monitoring
• Dose rate around storage, waste, use areas
* prior to repair of equipment
MONITORING
Leak Testing (Sealed Sources)
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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)
MONITORING
Contamination Monitoring (Open Sources)
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Map of lab
Weekly or after 5 x ALI
Decontaminate
Record “no radioisotope used”
After any spill
MONITORING
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 Criteria
0.3 Bq/cm2
Contamination Monitoring
Parameters of interest for contamination monitors-Efficiency
Detector Covering
Efficiency:
1) Distance: 1/r2
2) Beta Absorption
3) Size of window
Detector Volume
Surface
Not all decay emissions
Are detected!
Contamination Monitoring
Converting cpm results into Bq/cm2 for GM pancake
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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.
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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
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INSPECTIONS
1.
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3.
4.
5.
General Condition of lab
Inventory/Disposal
Contamination Monitoring
Measurements
Questionnaire
Dose rate measurements should be
undertaken:
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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
L
A
R
A
As
Low
As
Reasonably
Achievable
SAFE HANDLING PRACTICES
TIME
D=dXt
D = radiation dose
d = radiation dose rate
t = time duration of exposure
SAFE HANDLING PRACTICES
DISTANCE
D1 = dose at distance 1
s1 = distance 1
D2 = dose at distance 2
s 2 = distance 2
Inverse Square Law
D1 s12 = D2 s22
SAFE HANDLING PRACTICES
SHEILDING
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reduces or stops radiation
• dependent on:
- energy of radiation
- type of shielding
remember: 4 geometry
PERSONAL PROTECTION EQUIPMENT
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LAB COAT
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GLOVES
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SAFETY GLASSES
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.
SPILL RESPONSE
3.
LEAVING A CONTAMINATED AREA
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Monitor self (especially feet, hands and lab coat).
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Leave lab coat behind if contaminated and remove
dosimeter badge.
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Put up sign and lock door.
SPILL RESPONSE
DO NOT ENTER!
Name
Telephone #
Nature of Spill
Location
Time of Return
SPILL RESPONSE
4.
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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?
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The security of radioactive material is of concern to the
University of Ottawa, CNSC and the general public.
For this reason, measures have been implemented to ensure
this material is appropriately stored and access is only allowed
to authorize individuals. The primary mechanism to ensure
radioactive material is secure is through access control, while a
secondary means is through personnel clearance.
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.
WHAT IS RADSECURITY?
• The primary goal is the establishment of a security culture,
which involves individuals monitoring their own activities, as well
as others, to ensure only authorized access and appropriate use
of radioactive material. This means that an authorized person
must at all times be in the laboratory or surrounding area where
he or she is in a position to monitor for unauthorized persons
entering the laboratory and to intervene upon observing
someone who could walk away with the material. This can be as
basic as questioning strangers in the hallways, to establishing
an integrated monitoring system.
• Only authorized persons may have access to radioactive
materials. Radioactive materials that are stored or used in areas
common to both authorized and unauthorized personnel must
be secured at all times from unauthorized personnel.
WHAT IS RADSECURITY?
• Access control is accomplished by ensuring an integrated
approach between research laboratory procedures and the
infrastructure support of the faculties and departments in which
they work. This process must address: before, during and after
hour activities
• All radioactive wastes are considered as radioactive materials.
Radioactive wastes, including dry waste, liquid waste, and liquid
scintillation waste should be secured at all times.
• Persons performing work in the area, such as engineering or
maintenance personnel, contractors or commercial service
representatives should also be accompanied by an authorized
person at all times.
WHAT IS RADSECURITY?
• Other security control is gained by minimizing and tracking
inventory of radioactive material in the lab. This can be
accomplished by:
a) adherence to the inventory control program
b) reducing inventory by disposing of any stock by which
has insufficient activity for research purposes or whose chemical
integrity is questionable
Means of access control are:
a) physical barriers
structural design to increase the level of security to reflect the transition from general public to laboratory zones
departmental design to control traffic flow patterns control access: locks, key card access, self-locking doors
b) psychological barriers:
obvious presence of identifiable security personnel
obvious presence of security culture
use of cameras, mirrors, mirrored domes (90o,180o, 360o) and other monitoring tools
c) monitoring activities:
patrols of facilities by security personnel
support staff monitoring of departments (secretariat staff located at entrance of departments to monitor access,
all staff questioning strangers)
key control programs
d) personnel clearance:
identifying and restricting access to only authorized personnel
Other security control is gained by minimizing and tracking inventory of radioactive material in the lab. This can
be accomplished by:
a) adherence to the inventory control program
b) reducing inventory by disposing of any stock
i) which has insufficient activity for research purposes
ii) whose chemical integrity is questionable
Responsibilities pertaining to security of radioactive
materials in laboratory as outlined by CNSC
The 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
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