Guidance on completing
a Radiation Risk Assessment using Unsealed Radionuclides
These guidance
notes should be read before completing the radiation risk assessment form. They should be read in conjunction with the
Trust’s Risk Management Strategy and Policy (found on Freenet under Risk management
strategy and policy ). A separate risk assessment form should be
completed for each radionuclide used unless it is deemed sensible to put them
altogether. If this is the case, then an
explanation should be inserted. If the
radionuclides are the same but used in a very different way, then a separate
form is required. General risk assessment
may be added to this form if it is easier.
The radiation risk assessment form is not meant to be prescriptive but
may be tailored to the individual situation (eg removing control measures which are not relevant and adding others which
are) so long as the format is adhered to. This form may be used as a prior risk
assessment, reviewing current ones as well as when an event occurs.
1 Persons at Risk
Consider who might be harmed and if any pregnant or young people are
involved.
Enter the
maximum number of radiation workers who may be involved and if they have had
training.
Under the “other
persons involved” note down the number of people (not radiation workers) who
may be affected (eg domestics staff, builders etc..).
2 Dose Assessment
The whole body and extremity dose rates (mSv/h) can be calculated
using data from table 1 if there is no previous data available (eg data of
external exposure obtained from TLD/film badge results). Information on radionuclides not listed may
be obtained from the Radiation Safety Group (RSG).
|
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A
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B
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C
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Radionuclide
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Emission
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Point source at 30cm*
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Contact with 5ml syringe *
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Tenth Value Layer (TVL)#
of lead (mm) [γ
only]
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I-131
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β
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8.62 E-2
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1.1
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11
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γ
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7.29 E-4
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|||||
I-125
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γ
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3.90 E-4
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0.6
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<1
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I-123
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γ
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5.16 E-4
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0.6
|
2
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In-111
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γ
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9.94 E-4
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1.2
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3
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||
Tc-99m
|
γ
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2.61 E-4
|
0.4
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1
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||
Y-90
|
β
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1.08 E-1
|
43
|
|
||
Ga-67
|
γ
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2.79 E-4
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0.4
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6
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Cr-51
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γ
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6.04 E-5
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0.09
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7
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||
Tl-201
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γ
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1.97 E-4
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0.29
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1
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||
P-32
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β
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1.18 E-1
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24
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-
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||
S-35
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β
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-
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-
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-
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||
C-14
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β
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-
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-
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-
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H-3
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β
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-
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-
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-
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*
The external dose rates (mSv/h) for an activity of 1MBq
# TVL
is the thickness of shielding required to reduce the dose rates by a factor of
10
Values of WB and EX is obtained from table 1 columns A & B. Estimate the maximum time to be spent with the
radionuclide per year or per experiment for both a whole body and extremity
dose and the maximum activity to be used. There is a section at the end of the form to
note down all calculations and assumptions made.
To calculate EWB(b) and EEX(b) , the
following assumptions are made:
- Whole body dose EWB(b) : The radiation work will be at an
approximate distance of 30cm from the body.
If this is not the case, then the inverse square law must be used to
correct for the distance used.
- Extremity dose EEX(b) : Radiation
work entails handling radionuclide in a 5ml syringe with direct contact thereby
increasing the extremity dose.
Dose estimation before
control measures are put in place.
From the data in table 1 or data obtained from dose meter readings,
calculate the likely annual doses for the 2 situations before any control measures have been put in place. For those doing experiments, it may be more
suitable to calculate the dose per experiment rather than an annual dose which
may be very difficult to estimate. In
the latter situation, assumptions as to how that dose has been calculated needs
to be written on the form (under section 2 – dose assessment). Examples are given below :
EWB(b) example: If I-131 is
being used, then the whole body (WB) dose rate (mSv/h) (obtained from column
‘A’, table 1) is 8.62E-2 mSv/h for 1MBq.
If 10MBq is being used, then the doserate is 8.62E-2 x 10 = 0.862mSv/h. If the worker is likely to spend a maximum of
5 hrs a year working with the I-131, then the annual dose is 0.862 x 5 = 4.3mSv.
Note: Gamma radiation figures have been
used to obtain the WB doserate as it is more appropriate.
EEX(b) example: The amount of
time doing radiation work that involves direct extremity exposure to the source
in a syringe may differ from the whole body exposure times. For example, the
dose rate from I-131 is 1.1mSv/h (column ‘B’, table 1). But if only 10% of the 5 hours (0.1 x 5 = 0.5
hours) outlined above involves direct manipulation, then for the 10MBq dose in
a syringe, the annual extremity dose, EX(b) = 10 x 1.1 x 0.5 = 5.5mSv
Radiation Probability Calculation
Whole Body Dose
To provide a Risk Rating parallel with the schema adopted for other
risks, a pessimistic multiplicative risk probability (P) is set up looking at
the number of people (N) involved in
a work activity, and their estimated maximum annual whole body dose (E) arising from that work activity and
the radiation risk probability coefficient (C). ie P = N x E x C
#
(# -
Risk assessment for a radionuclide area – Nuclear Medicine communications 2003,
24: 1017-31)
For
effective doses less than or equal to 200mSv, C = 0.5 ´ 10 – 4
otherwise C =
1.0 ´ 10 –
4
As
the dose for most situations is < 200mSv a year, C is normally 0.5 ´ 10 – 4. Table 2 has been simplified to include C. Therefore the Radiation Risk Probability (P) may
be calculated using :
P = N ´ E
P is for the whole body dose, not
extremity or skin dose. P should be
calculated before the control measures are in place and noted.
Using the example above, for
EWB(b), if N = 2, then PWB(b)
= 2 x 4.3 = 8.6
Users of H-3 and C-14 will not register an
external dose but hazards from ingestion / inhalation still apply. Security measures and control of the spread
of contamination also needs to be taken into account.
3 Hazard Identification & Risk Quantification before control
measure in place
List the hazards (ie something
with the potential to do harm) in the boxes provided. If there are more than 5 hazards identified,
please add more rows and number them accordingly.
a Obtaining the Consequence Score
After calculating P, use Table 2
to obtain the appropriate severity level, using the column corresponding to the
number of people affected. The colour/pattern
obtained corresponds to a consequence score (1 – 5) given in table 2a. Note the score for each hazard in the boxes
provided.
Risk
Probability
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Individual
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2
– 10 people
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11
– 100 people
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> 2,000
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> 20,000
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> 40,000
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200 – 2,000
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2,000 – 20,000
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20,000 – 40,000
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20 - 200
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200 – 2,000
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2,000 – 20,000
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2 - 20
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20 – 200
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200 – 2,000
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0.2 – 2
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2 – 20
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20 - 200
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0.02 – 0.2
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0.2 – 2
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2 - 20
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< 0.02
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< 0.2
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< 2
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Consequence score
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5
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Catastrophic
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4
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Major
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3
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Moderate
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2
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Minor
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|
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1
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Negligible
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Table 2 Table
2a
In the example given above, for 2 people and with PWB(b) = 8.6, the consequence score
is 2.
Extremity and
Skin Doses
For
skin and extremity doses, the consequence score can be obtained from table 2b.
(Do not multiple by number of persons
involved.)
Consequence
score
|
Annual Dose (mGy)
|
Reasons for categorisation
|
|
5
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Catastrophic
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>
50,000
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Skin Necrosis
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4
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Major
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2,000
– 50,000
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Below
erythema level
|
3
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Moderate
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150 –
2,000
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500 : legal
limit , < 2Gy early transient erythema – ICRP85
|
2
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Minor
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50 –
150
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< 150 : non classified level
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1
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Negligible
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< 50
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(100mGy) No
clinically relevant functional impairment – ICRP 103. Also including
non-radiation worker (50mGy)
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Table 2b
In the example given above, the max extremity dose EEX(b)
= 5.5 which gives a consequence score is 1.
b Obtaining the Likelihood Score
The likelihood
score (between 1 – 5) can be obtained from the table 3 for each hazard and then
noted down in the boxes provided
Score
|
Frequency
|
Description
|
1
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Rare
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This will probably never happen or recur
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2
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Unlikely
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Do not expect it to happen or recur but it
is possible it may do so
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3
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Possible
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Might happen or recur occasionally
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4
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Likely
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Will probably happen or recur, but it is
not a persisting issue / circumstance
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5
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Almost Certain
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Will undoubtedly happen or recur, possibly
frequently.
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Table 3
c Obtaining the Risk Score
The risk is the
likelihood of harm occurring together with an indication of how serious that
harm could be.
Risk rating = Likelihood
score x
Consequence score
Using table 4, find the risk rating (1 –
25).
CONSEQUENCE
|
LIKELIHOOD
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||||
Rare (1)
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Unlikely (2)
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Possible (3)
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Likely (4)
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Almost certain
(5)
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Catastrophic (5)
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5
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10
|
15
|
20
|
25
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Major (4)
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4
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8
|
12
|
16
|
20
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Moderate (3)
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3
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6
|
9
|
12
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15
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Minor (2)
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2
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4
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6
|
8
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10
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Negligible (1)
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1
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2
|
3
|
4
|
5
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Table 4
If the likelihood score is
thought to be 3 and the consequence score is 2 (from whole body dose calculations
above), then the risk rating = 3 x 2 =
6
The risk rating (between
1-25) corresponds to a risk score (between 1 – 4) as given in table 5. Note this down in the table.
Risk
Score
|
Risk
|
Description
|
1
|
Very Low risk
|
Local investigation where appropriate
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2
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Low risk
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Contributory
factor(s) to be identified; discuss with local management the need for any
changes in practice, policies, procedures, education or training.
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3
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Moderate risk
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Identify
contributory factors. Discuss at the
local radiation governance meeting. Action
plans to be monitored centrally.
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4
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High risk
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Report incident
immediately to manager/head of department.
Inform risk manager. Full
investigation to be undertaken including interview with staff and
identification of root causes. Action
plans to be monitored centrally. To
be reported to the Radiation Board.
|
Table 5
From the example above, with the risk rating being 6, the risk score
(obtained from table 5) = 2
4 Control Measures
State the type
of shielding suitable for the radionuclide used (e.g. lead for I-131, Perspex
for P-32). If shielding is adopted, it should have an appropriate thickness:
Gamma Radiation: The thickness of lead should be greater than or
equal to the TVL of the radionuclide (see table 1, column C). However, the attenuated dose should still be
checked to ensure that it does not exceed any dose limit given in table 6.
Beta Radiation: 10mm
of Perspex should provide adequate shielding for all Beta emitters listed in
table 1 excluding Y-90 and I-131.
A list of
control measures have been given as a prompt.
These may or may not be applicable to the situation being assessed. If it is not applicable or not being carried
out, explain why not under the “If no,
explain why not” column. Otherwise
give details under the other column. For
other control measures which are relevant but not listed, please add extra
rows.
The chance of
contamination spread can be significantly reduced by ensuring that gloves are
used and that all work is carried out on spill trays which are lined with
absorbent materials. Movement of radioactive materials also needs to be considered
to ensure that accidental spillages are not a regular occurrence and the chance
of significant contamination from the spillage is minimised by adopting an
appropriate movement procedure
5 Radiation Risk Quantification after control measures
are in place
Assess what the
doses will be (as above) after control measures are put in place and note these
down. Again these values should be
annual doses.
EWB(a) example: There is a significant reduction in dose
rate after introducing shielding (control measure) to stand behind during
manipulations and shielded storage when the activity is not being used. If a
shield containing 11mm of lead is introduced, then the whole body annual dose
can be calculated as EWB(a) = 4.31/ 10 = 0.431 mSv.
6mm Perspex is also added before the lead shield to absorb the beta
particles.
EEX(a) example: Dose-sharing techniques are now
introduced during syringe manipulation resulting in half the time spent being exposed from direct
extremity contact. The annual extremity dose is then calculated as EEX(a)
= 5.5/2 = 2.75 mSv.
The limit for
non-classified workers and members of the public are given in table 6. Pregnant staff may come under the category of
“members of the public” in this exercise.
If any of the annual dose values after control measures have been
adopted exceeds the respective limits given in table 6 then further action
needs to be taken reduce this to within the limits. If this is not possible, then the member of
staff would need to be classified. This
should be noted in section 6.
|
Non-classified Radiation
workers (mSv)
|
Members of the public
(mSv)
|
Whole
body
|
6
|
1
|
Extremities
|
150
|
50
|
Skin
(Contamination)
|
150
|
50
|
Table 6
Calculate the
risk probability (described above) using the dose estimations post control measures EWB(a) and
EEX(a). Obtain the
consequence score, the likelihood rating and the risk score as before.
If any further
action is needed to reduce the risk score for each hazard, note that in the
appropriate column. The number of
hazards identified in section 3 should be the same number as those in section 5
after control measures are in place.
6 Hazard Identification & Control Measures
for Incident Situations
Note down
situations where incidents could occur.
Identify the best action to take when the incident occurs so that people
are as safe as possible first. ( This could mean shutting down an area !)
7 Action Plan
Any action as
well as improvements required to reduce the risks should be included in the
“Action required” section. The person responsible
for carrying out the action and the date the action should be done needs to be
inserted. When the action has been
carried out, the “date completed” needs to be added as well as a signature from
the person who carried it out.
8 Area Designation
Risk assessments
are a way of indication what an area should be designated as. Sometimes after carrying out the risk
assessment, the area may change its designation. All this needs to be addressed in the space
provided. An area can be designated as controlled or supervised for various
different reasons. Areas need not be
permanent. Some reasons for designating
an area are as follows :
Controlled Area: If increased security and restriction of access to that
area is required.
- To reduce the spread of contamination which
is likely.
- If a person is likely to receive a dose
higher than the dose limits given in table 6
Supervised Area: to
keep conditions under review to determine if the area needs to be controlled
- In labs
where only small quantities of very low energy radioactive materials are used.
- To reduce
the spread of contamination which may occur.
9 Approval
Once the form is
completed, the person(s) carrying out the risk assessment should sign and date
it and get the Head of department / section or lab manager to approve it. A member of the Radiation Safety Group should
then sign it to say that it has been noted.
10 Summary
All the hazards and
control measures (group them if possible) far should noted in the summary
table. A small list has been provided but it may not all be relevant or
sufficient and extra columns may need to be added. A tick should be placed in the appropriate
box to demonstrate how the each hazard has been addressed by at least one
control measure.
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