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Presented by:
Vangeline K ParamiLRE/NRLSD
Baguio City, May 2008
CPR Part 3: Standards for Protection
Against Radiation
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ICRP basic framework
CPR Part 3:
Standards for protection against radiation
Outline
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The International Commission
On Radiological Protection (ICRP)
Basic Framework
Everyone in the world is exposed to radiation
from natural and artificial sources
Primary aim-
to provide an appropriate standard of protection
for man without unduly limiting the beneficial
practices giving rise to radiation exposure
include socialas well as scientific judgments
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Global Average Individual
Background Radiation Doses
(mSv/y)
TOTAL = 2.69Source: UNSCEAR
Cosmic
0.39
Terrestrial
0.46
Internal K-40, C-140.23
Radon
1.3
Medical 0.3
Fallout 0.007
Occupational
0.002
Discharges0.001
Products
0.0005
TOTAL FROM
NATURAL - 2.38
TOTAL FROM ARTIFICIAL- 0.31
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Practices
human activities that increase the overall
exposure to radiation, either by introducing
new sources, pathways, and individuals, or
by modifying the pathways from existing
sources to man and thus increasing the
exposure of individuals or the number of
individuals exposed
The ICRP Basic Framework
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Intervention
Other human activities that decrease the
overall exposure by such activities asremoving existing sources, modifying
pathways, or reducing the number of
exposed individuals
The ICRP Basic Framework
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Stochastic effectscannot be completely avoided becausethere is no threshold for them, even small radiation dosesmay produce deleterious health effects.
Since there are thresholds for deterministic effectsit ispossible to avoid them by restricting the doses toindividuals.
The ICRP Basic Framework
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The ICRP Basic Framework
The basic framework is intended toprevent the occurrence of deterministiceffects, by keeping doses below the
relevant thresholds, and to ensure thatall reasonable steps are taken toreduce the induction of stochastic
effects.
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Stochastic effect -
based on probability
as the dose increases, the probability (chance) of
the effect increases
not more serious for larger doses
the same for a small dose as a large dose
Only probability of it occurring increases with dose
Stochastic Effects
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Stochastic Effects
Example:
Cancer can be considered a yes or no
effect. You either get it or you dont. Youmay get it with only a small dose or you maynot get it even with a large dose, but in eithercase (small or large dose) if you get it, its
the same effect
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The fact that there are regulatory dose limits would tendto imply that as long as the limit is not exceeded, there isno danger of harm.
However, it is also required that steps be taken tomaintain doses As Low As Reasonably Achievable
This is necessary assuming that the dose responsemodel is correct and that any dose, no matter how small,
incurs some risk.
The regulatory limit designates an acceptable risk but itdoesnt hurt to lower the risk even more if it isreasonable to do so.
ALARA
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A non-stochastic effect is one based on severity. As
the dose increases, the severity (amount of injury)
increases.
Some examples of non-stochastic effects are:
- skin damage (reddening, peeling, blistering, necrosis)
- hair loss (epilation)
- cataracts (eye damage)
- sterility
Deterministic Effects
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(103) The effectiveness of protection can be related to:
A source giving rise
to individual doses
(source-related)
Individual dose received
from all the relevant
sources (individual-related)
The ICRP Basic Framework
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The basic Safety Standards of the IAEA detail
how to implement the System for Radiation
Protection described in ICRP Publication 60
The Standards specify the basic requirements
for protection of people against exposure to
ionizing radiation and for the safety of radiation
sources
Part 3 is based on IAEA basic safety standards
System of Radiological Protection
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Part 3: Standards for protection against radiation
I. General provisions
Section 1. Purpose.
(a) establishes the standards for protection against ionizingradiation arising from the use of radioactive materialsand related activities conducted under licenses issued bythe PNRI.
(b) establishes the basic requirements for the safety ofradiation sources.
(c) to control all activities by any licensee involvingradioactive material in such a manner that the total doseto an individual, except exposures to radiation fromnatural background sources or medical diagnosis andtherapy, does not exceed the Standards prescribed inthis Part.
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Part 3: Standards for protection
against radiationSection 2. Scope.
(a) The requirements in this Part apply to all holders ofPNRI licenses issued pursuant to the regulations of theCode of PNRI Regulations (CPR).
(b) The requirements in this Part are in addition to, and notin substitution for, other requirements of the CPR.
(c) Specific provisions of the IAEA Safety Series No. 115,International Basic Safety Standards (IBSS) forProtection Against Ionizing Radiation and for the Safetyof Radiation Sources which are applicable in this Part,may be addressed pursuant to PNRI AdministrativeOrder No. 1, Series of 2001.
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Part 3: Standards for protection
against radiationSection 3. Exemptions.
(a) The requirements in this Part do not apply to:
(1) practices and sources involving radioactive materials that meet theexemption levels given in Appendix A; and
(2) any exposure whose magnitude or likelihood is essentially unamenableto control through the requirements of this Part.
(b) The dose limits prescribed in this Part do not apply to:(1) radiation exposures due to background radiation;
(2) radiation exposure from individuals who have been administered withradioactive material and subsequently released in accordance with CPRPart 13; and
(3) medical exposures which include:
(i) radiation exposure incurred by patients as part of their own medicalor dental diagnosis or treatment; and
(ii) radiation exposure of comforters and visitors of patientsundergoing medical diagnosis or treatment.
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Section 4. Definitions.
ACTION LEVEL; ACTIVITY; ALARA;Authorized Worker; bioassay; chronic
exposure. . .
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Section 5. Interpretation.
Except as specifically authorized by the Director in writing,no interpretation of the meaning of the regulations in thisPart by any officer or employee of the PNRI other than a
written interpretation by the Director will be recognizedto be binding upon PNRI.
Section 6. Communication.
All communication and reports concerning the regulationsin this Part should be addressed to the Director,Philippine Nuclear Research Institute, Commonwealth
Avenue, Diliman, Quezon City.
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II. RADIATION PROTECTION AND
SAFETY PROGRAM
Section 7. Radiation Protection and Safety Program.
a. Each licensee shall use and observe, to the extent practicable theregulations in this Part and the radiation protection and safetyprinciples subscribed by PNRI.
b. Each licensee shall establish, document, and implement aradiation protection and safety program that is commensurate withthe scope and extent of authorized activities and sufficient to ensurecompliance with the requirements of this Part and the conditions ofthe license.
c. Each licensee shall review at least annually the content andimplementation of its radiation protection and safety program.
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II. RADIATION PROTECTION AND SAFETY
PROGRAM (2)Section 8. Format and Content of the Radiation Protection and Safety
Program.
The Radiation Protection and Safety Program shall include the followinginformation, as may
be applicable:
(a) A description of the radiation protection and safety organization
(b) A description of the duties and responsibilities of the Radiological Health
and Safety Officer (RHSO).(c) A description of the radiation facility
(d) The number and type of equipment and devices incorporating radioactivesubstances, instruments and monitoring devices used and their propermaintenance;
(e) Arrangement made for the assessment of the occupational exposure of
workers and the maintenance of exposure records;(f) Methods for the implementation of the program that includes radiationexposure control, control of the workplace, monitoring of the workplace andassessment of the consequences of radioactive releases;
(g) Methods for evaluating the performance of radiation protection and safetyprogram ;
(h) An emergency plan
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The System of Radiological Protection
The system of radiological protection for
proposed and continuing practices is
based on the following general principles:
Section 9. Justification of practices
No practice involving exposures to
radiation should be adopted unless it
produces sufficient benefit to theexposed individuals or to society to
offset the radiation detriment it causes.
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Detriment defined
The total harm that would be eventually
experienced by an exposed group and its
descendants as a result of the groups
exposure to radiation from a source
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Section 10. Optimization of protection and safety
For any particular source within a practice, the
magnitude of individual doses, the number of
people exposed, and the likelihood of incurring
exposures should all be kept as low asreasonably achievable (ALARA), economic and
social factors being taken into account
Dose and risk constraints should be used tolimit the inequity likely to result from the
inherent economic and social judgments
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Section 11. Dose constraint
(a) Do not exceed either the appropriate values established oragreed to by PNRI for such a source or values which can cause thedose limits to be exceeded; and
(b) Ensure, for any source (including radioactive waste managementfacilities) that can release radioactive substances to theenvironment, that the cumulative effects of each annual release fromthe source be restricted so that the effective dose in any year to anymember of the public, including people distant from the source andpeople of future generations, is unlikely to exceed any relevant doselimit, taking into account cumulative releases and the exposures
expected to be delivered by all other relevant sources and practicesunder control.
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The exposure of individuals shall be
subject to dose limits, or to some control of
risk in the case of potential exposures.
This ensures that no individual is exposed
to radiation risks that are judged to be
unacceptable from these practices in any
normal circumstances.
Section 12. Individual dose and risk limits
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Either by controlling the practice or by intervention theexposure of individuals can be restricted by applying
action to the source, to the environment, or to the
individual.
Where available, controls applied
at the sourceare preferred
Examples:self shielded irradiator
Gamma exposure device
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Exposures are divided into three types:
occupational exposure (exposure incurred at work
principally as a result of work) - Section 13
medical exposure (principally the exposure of
persons as part of their diagnosis or treatment)
Section 14
public exposure (all other exposures)Section 15
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Occupational Exposure
For occupational exposures, controls occur at three
points:
at the source (e.g., containment)
in the environment (e.g., shielding
or ventilation)
at the individual (e.g., administrativecontrols and protective clothing)
For public exposures, controls should be applied at the
source
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Exposures may be known and
predictable or possible but without
certainty. These latter types are called
potential exposures.
Section 16. Potential exposure
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Individual Dose Limits
Apply to exposures attributable to practices,
except medical exposures and of exposures
from natural sources
Not relevant for the control of potentialexposures
Not relevant for decisions on whether and
how to undertake an intervention
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External Radiation Dose
Gamma, beta or neutron radiationemitted by radioactive material
outsidethe body exposing the skin,
lens of the eye, extremities & the
whole body (i.e. internal organs)
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Internal Radiation Dose
Alpha, beta orgamma radiation
emitted by
radioactive material
insidethe bodyexposing internal
organs such as:
thyroid
bone
GI System
lung
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Individual Dose Limits
Occupational Limit (adults):
effective dose of 20 mSvper year averaged over five
(5) consecutive years
an effective dose of 50 mSvin any single (1) year
an equivalent dose to the lens of the eye of 150 mSv
in a (1) year
an equivalent dose to the extremities (hands and
feet) or the skin (averaged over 1 cm2)of 500 mSv in
a (1) year
Ad lt O ti l
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Adult Occupational
Dose Limits
Whole Body (everything except extremities)
50 mSv maximum per year
20 mSv averaged over 5 years
Extremities500 mSv per year
Skin of the Whole Body
500 mSv per year
Lens
150 mSv
per year
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The dose to the lens of the eyeis measured at a depth of 0.3 cm
The shallow (skin) dose is
measured at a depth of 0.007 cm
The whole body dose is
measured at a depth of 1 cm
Depths at which External
Radiation Dose is Measured
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Individual Dose Limits
December 31, 2007
January 1, 2003
1
December 31, 2012
January 1, 2008
2
December 31, 2017
January 1, 2013
3
December 31, 2022
January 1, 2018
4
January 1, 2003
December 31, 2007
1January 1, 2004
December 31, 2008
2
December 31, 2009
January 1, 2005
3
December 31, 2010
January 1, 2006
4
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Individual Dose Limits
December 31, 2007
January 1, 2003
1
December 31, 2012
January 1, 2008
2
January 1, 2003
December 31, 2007
1
January 1, 2004
December 31, 2008
2
5 mSv
10 mSv
15 mSv
20 mSv
50 mSv
5 mSv
10 mSv
15 mSv
20 mSv
50 mSv
5 mSv
10 mSv
15 mSv
20 mSv50 mSv
50 mSv
50 mSv20 mSv
15 mSv
10 mSv20 mSv Avg
20 mSv Avg
20 mSv Avg
29 mSv Avg
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Individual Dose Limits
Occupational Limit (apprentices and students 16 to 18
years of age):
effective dose of 6 mSvin a year
equivalent dose to the lens of the eye of 50 mSv in a
year
equivalent dose to the extremities or the skin(averaged over 1 cm2)of 150 mSv in a year
L
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1618 Year Old Occupational
Dose Limits
Whole Body (everything except extremities)
6 mSv maximum per year
Extremities150 mSv per year
Skin of the Whole Body
150 mSv per year
Lens
50 mSv
per year
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Individual Dose Limits
The estimated average doses to the relevant criticalgroups of members of the publicattributable to
practices shall not exceed the following limits:
an effective dose of 1 mSv in a year;
in special circumstances, an effective dose of up to
5 mSv in a single year provided that the average
dose over five consecutive years does not exceed
1 mSv per year;
an equivalent dose to the lens of the eye of 15 mSv ina year; and
an equivalent dose to the skin of 50 mSv in a year.
L
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Public
Dose Limits
Whole Body (everything except extremities)
1 mSv per year
**Special circumstances**
5 mSv maximum per year
1 mSv averaged over 5 years
Extremities50 mSv per year
Skin of the Whole Body
50 mSv per year
Lens
15 mSv
per year
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Patient Comforter and Visiting
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Patient Comforter and Visiting
Children Dose Limits
Whole Body (everything except extremities)
Patient Comforters
5 mSv per examination or treatment
Children Visiting Patients
1 mSv per patient hospital stay
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Dose Limit Summary
Whole
Body
(max)
Whole Body
(average)
Lens
of
Eyes
Skin Extremity
Adult 50
50
20 over 5 yrs
20 over 10 yrs
150 500 500
Minor 6 None 50 150 150
Public 1
5
None
1 over 5 yrs
15 50 None
Comforter 5 None None None None
Child Visitor 1 None None None None
NOTE: All numerical dose limits have units of mSv in one year except for
the limits for comforters and visiting children. The limit for these last two
groups is per patient diagnostic procedure or treatment
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The dose limits apply to the sum of:
the doses from external exposure in the specified
period
the committed doses from intakes in the same period
The period for calculating the committed dose shall be:
50 years for intakes by adults
to age 70 years for intakes by children
Individual Dose Limits
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For compliance with dose limits, the sum of:
the personal dose equivalent from external exposure
to penetrating radiation in the specified period
the committed equivalent dose or committed effective
dose, as appropriate, from intakesof radioactive
substances in the same period
Individual Dose Limits
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Estimates of probabilities of effects
Effect Population Exposureperiod
Exposuremodes
Probability
Fatal cancer
(total)
workers lifetime Low dose,
low dose
rate
4 x 10-2/Sv
Fatal cancer
(total)
General
population
lifetime Low dose,
low dose
rate
5.0 x 10-2/Sv
Hereditary Whole
population
All
generations
Low dose,
low dose
rate
1.0 x 10-2/Sv
R di i d ff i
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Radiation dose effects at various
dose levels(Health Physics Journal, Vol. 89, No. 5, Nov 2005)
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Section 17. Emergency Exposure Situations
Emergency plan
Intervention
Protection of workers during intervention
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Intervention
The system of radiological protection for interventionisbased on the following general principles:
The proposed intervention shall do more good than
harm (the reduction in detriment shall be sufficientto justify the harm and the costs, including social
costs of the intervention)
The net benefit of the intervention shall bemaximized (the reduction in radiation detriment,
less the detriment associated with the intervention)
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Dose limits do not apply in the case of intervention.
There will be some level of projected dose above whichintervention will almost always be justified.
Intervention
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IV. SAFETY MEASURES AND CONTROL OF
RADIOACTIVE MATERIAL
Section 18. Surveys and Safety of
Equipment
Section 19. Transport of radioactivematerial
Section 20. Storage and control of
radioactive material
V PRECAUTIONARY REQUIREMENTS
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V. PRECAUTIONARY REQUIREMENTS
Section 21. Caution Signs, Labels, and Posting Requirements.
(a) Caution Signs and Labels.
(1) Signs and labels prescribed by this section shall use contrasting colors. Theradiation
caution symbol prescribed by this section is the conventional three-bladed design:
RADIATION SYMBOL
(i) cross-hatched area is black, and (ii) background is to be yellow.
(2) In addition to the contents of signs and labels prescribed in this section, thelicensee
may provide on or near such signs or labels any additional information which may be
appropriate in aiding individuals minimize their exposure to radiation or to radioactive
material.
(2) Each licensee shall, prior to removal or disposal of empty uncontaminated
containers, remove or deface the radioactive material label or otherwise clearly
indicate that the container no longer contains radioactive materials.
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(b) Posting.
(1) Posting of RadiationAreas. The licensee shall posteach radiation area with a
conspicuous sign or signs
bearing the radiation symboland the words "CAUTION,
RADIATION AREA".
(2) Posting of High RadiationAreas. The licensee shall posteach high radiation area
with a conspicuous sign or
signs bearing the radiationsymbol and the words
"CAUTION, HIGH RADIATIONAREA" or "DANGER, HIGHRADIATION AREA".
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(c) Labelling of Containers. (1) Each licensee shall ensure that each container of licensed
material bears a durable,
clearly visible label bearing the radiation symbol and the words,"CAUTION,
RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVEMATERIAL". The label
must also provide sufficient information (such as the radionuclide(s)present, an
estimate of the quantity of radioactivity, the date for which theactivity is estimated,
radiation levels, kinds of materials, and mass enrichment) to permitindividuals
handling or using the containers, or working in the vicinity of thecontainers, to take
precautions to avoid or minimize exposures.
S ti 22 P ti f N ti d
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Section 22. Posting of Notices and
Important Documents
(a) Each licensee shall post at conveniently visiblelocations in the licensed facility current copies
of the following documents:
(1) the regulations, the license, and license conditions; (2) the operating procedures applicable to licensed
activities; (3) the emergency procedures and local rules;and
(4) the "Notice to Employees" form issued by PNRI.Refer to Appendix C.
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Section 23. Instructions to Workers
Each licensee shall ensure that all individuals working in or frequenting any portion of a
controlled or supervised area are:
(a) Kept informed of the storage, transfer, or use of radioactive materials or of the presence of
radiation in such portions of the area;
(b) Instructed on the health protection problems associated with exposure to such radioactive
materials or radiation, in the precautions or procedures to minimize exposure, and in the
purposes and functions of protective devices employed;
(c) Instructed to observe, to the extent within the worker's control, the applicable provisions of the
regulations of the Code and the specific conditions of the license for the protection of
personnel from exposures to radiation or radioactive material;
(d) Instructed of their responsibility to report promptly to the RHSO or the licensee any condition
which may lead to or cause a violation of the regulation of the Code or license conditions, or
to cause unnecessary exposure to radiation or to radioactive material;
(e) Instructed on the appropriate response to warnings made in the event of any unusual
occurrence or malfunction that may involve exposure to radiation or radioactive material; and (e) Advised as to the radiation exposure records which workers may request.
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VI. WASTE MANAGEMENT AND DISPOSAL OF
LICENSED RADIOACTIVE MATERIAL
Section 24. General Requirements.
(a) Each licensee shall dispose of licensed radioactive material only:
(1) by transfer to an authorized recipient as provided in the regulations in Parts 2, 11, 12,
13, 14, 16 and 20;
(2) by decay in storage;
(3) by discharge to the environment within the limits specified in Appendix D of this Part;
(4) as authorized to dispose of as ordinary waste; or
(5) by disposal as radioactive waste in accordance with an approved radioactive waste
management program.
(b) A person must be specifically authorized by PNRI to receive radioactive waste from PNRI
licensees for:
(1) treatment prior to disposal; or
(2) interim storage; or
(3) disposal at its facility specifically authorized by PNRI; or
(4) disposal in accordance with a procedure not otherwise approved under this Part. (c) The facility design, capacity and radiological safety considerations of the facility for the
disposal or interim storage of radioactive waste must be reviewed and approved by PNRI.
S ti 25 T f f Li d
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Section 25. Transfer of Licensed
Radioactive Material
(a) Any licensed radioactive material or sealed source that is disused or no longer suitable as
originally intended in the license may be transferred to another person authorized by PNRI to
receive such material in accordance with the requirement provided correspondingly in Parts
2, 11, 12, 13, 14, 16 and 20 of the CPR.
(b) If the transfer of disused sealed source to another person authorized by PNRI is not possible,
the disused sealed source shall be returned to the supplier or manufacturer or disposed as
radioactive waste to a person authorized by PNRI in Section 24 (a).
(c) In the transport of disused sealed source to the supplier or manufacturer, the disused sealed
source shall be packaged and shipped in the original shipping container, or provisions should
be made to acquire another acceptable container if the original container is not available. The
regulations of CPR Part 4, Rules and Regulations for the Safe Transport of Radioactive
Materials in the Philippines, shall apply.
.
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Section 26. Storage of Radioactive Waste
(a) All radioactive wastes that are for disposal shall be appropriatelystored in on-site facilities
under controlled conditions. Interim storage of unconditioned wasteshall be as short as
possible and not to exceed five (5) years.
(b) Containers used for decay-in-storage shall be properly labeledincluding the date when the
source may be disposed of as non-radioactive waste.
(c) Storage facilities for radioactive wastes shall be constructed andsecured to prevent
unauthorized access to the wastes and such that subsequenthandling, transport and
disposal will not be endangered
Section 27 Required Conditions During Normal
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Section 27. Required Conditions During Normal
Operation Involving Radioactive
discharges
(a) All radioactive discharges shall be kept as far belowthe authorized clearance levels as is
reasonably achievable.
(b) Radioactive discharges shall be monitored withsufficient detail and accuracy to demonstrate
compliance with authorized clearance levels and topermit proper assessment of the
exposure of critical groups.
(c) Results of monitoring and exposures must berecorded and reported to the PNRI annually.
(d) Radioactive discharges that exceed the authorizedclearance levels must be reported to PNRI
in accordance with Section 38 of this Part.
S ti 28 Di l b R l t th
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Section 28. Disposal by Release to the
Atmosphere
(a) Work with radioactive gases or aerosols shall be done in a fumecupboard or in the
immediate vicinity of an extraction hood. Fume cupboard exhausttrunking from active
laboratories shall be isolated from normal ventilation systems andexhausted to the
atmosphere through stacks so as not to re-enter the building oradjacent buildings.
(b) If filtration of exhaust has been deemed necessary in particularcircumstances, then the
appropriate type of filter must be employed for trapping theemission; the installation must
have been approved; the assembly tested and the performancecontinuously monitored.
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Section 30. Waste Management Program Section 31. Characterization, Segregation and Collection of Radioactive Waste.
Section 32. Treatment and Conditioning of Radioactive Waste.
.
Section 33. Radioactive Waste that are Exempt from Regulatory Control.
PNRI may exempt from regulatory control the discharge of radioactive waste if:
(a) The effective dose expected to be received by any member of the public due to the waste is
of the order of 10 Sv or less in a year; and
(b) The activity of the waste does not exceed the clearance levels given in Appendix D of this
Part.
Section 34. Land Disposal of Radioactive Wastes.
Exposure to members of the general public from off-site releases of radioactive material
emanating from a land disposal facility shall not exceed the limits set forth in Section 15 of thisPart.
Section 35. Compliance with Environmental and Health Protection Regulations.
Nothing in this Part relieves the licensee from complying with other government regulations that cover any other toxic or hazardous properties of materials that may be disposed of under this
Part.
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VII. RECORDS, REPORTS AND NOTIFICATIONS
Section 36. Records of Radiation Protection andSafety Program.
(a) Each licensee shall maintain records of the radiationprotection and safety program and shall
(1) the provisions of the program; and
(2) results of audits and other reviews of program
content and implementation. (b) The records required by this Section shall be retainedfor 3 years or until PNRI orders
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Section 37. Documentation of Records. Each record required by this Part must be legibly written or printed on a specified form
throughout the retention period. Each record must be authenticated by authorized personnel and shall
have adequate safeguards against tampering or loss.
Section 38. Reports of Overexposures and Excessive Levels and Concentrations.
(a) In addition to any report or notification required by this Part, each licensee shall make a report
in writing to PNRI concerning any one of the following incidents within 30 days of its
occurrence:
(1) exposure to individuals in excess of the limits of this Part allowed for occupational, or
public exposures or as may be indicated in the license conditions; (2) levels of radiation or concentration of radioactive material in a controlled area in
excess of any applicable limit in this Part or in the license; or
(3) levels of radiation or concentrations of radioactive material, whether or not involving
exposures of any individual, in a supervised area in excess of 10 times of any
applicable limit set forth in this Part or in the license issued by PNRI.
(b) Each report required under this Section must describe the extent of exposure of individuals to
radiation or to radioactive material, including estimates of each individual's total exposure;
levels of radiation and concentrations of radioactive material involved; the cause of the
exposure; and corrective steps taken or planned to prevent a recurrence. (c) In any case where a licensee is required to report to PNRI any exposure of an individual to
radiation or to radioactive material, the licensee shall also notify such individual of the nature
and extent of exposure. Such notice shall be in writing and a copy shall be furnished to PNRI.
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Section 39. Reports of Theft or Loss of Radioactive Material. (a) Each licensee shall immediately notify PNRI by telephone or by any other fast means of
communication, of any lost, stolen, or missing radioactive material.
(b) In addition to the notification required above, each licensee shall, within 30 days after the
occurrence, make a report in writing to PNRI that shall include the following information:
(1) a description of the radioactive material involved including kind, quantity, chemical,
and physical form;
(2) a description of the circumstances under which the loss or theft occurred;
(3) a statement of disposition or probable disposition of the radioactive material involved;
(4) estimated radiation exposures to individuals, circumstances under which the
exposures occurred, and the extent of possible hazards;
(5) actions which have been taken, or will be taken, to recover the material; and
(6) procedures or measures which have been or will be adopted to prevent a recurrence
of the circumstances which led to the loss or theft of the licensed material.
(c) Notwithstanding the requirement to file a written report, the licensee shall also report
immediately any substantive additional information on the loss or theft which becomes available to the licensee.
(d) Any report filed with PNRI pursuant to this section shall identify the individuals who may be
exposed to radiation or may be involved in the incident.
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Section 40. Notification of Incidents. (a) Each licensee shall notify PNRI within 24 hours by telephone, or by any other fast
means of
communication, of any incident involving a licensed activity, licensed facility, sourcematerial,
special fissionable material or any other radioactive material possessed by thelicensee that
may have caused, or threatens to cause: (1) exposure of the whole body of any individual in excess of 0.05 Sv; or
(2) the release of radioactive material inside or outside of a controlled area, so that, ifan
individual is present in the area for 24 hours, the individual could have received an
intake in excess of one occupational annual limit on intake.
(b) Any report filed with PNRI pursuant to this Section shall specify the names of
individuals who have received exposure to radiation and other persons involved in the incident,
including
telephone numbers and addresses as may be practicable.
VIII EXEMPTIONS AND ADDITIONAL
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VIII. EXEMPTIONS AND ADDITIONAL
REQUIREMENTS
Section 41. Applications for Exemptions.
The PNRI may, upon application by any licensee or upon its owninitiative, grant such
exemptions from the requirements of the regulations in this Part as itdetermines are authorized by law
and will not result in undue hazard to life or property.
Section 42. Additional Requirements.
The PNRI may, by rule, regulation, or order impose upon anylicensee such requirements, in
addition to those established in these regulations, as it deemsappropriate or necessary to protect
health and safety of the public or to minimize danger to life orproperty.
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IX. ENFORCEMENT
Section 43. Violations.
(a) Any person found to have violated any rule, regulation, or order issued by PNRI, or any term,
condition, or limitation of any license issued thereunder shall be notified of such violation and
required to take corrective steps to prevent recurrence.
(b) Any license may be modified, suspended, or revoked, after due process, for any violation
which PNRI determines to adversely affect the health and safety of the workers and the
public.
(c) Any person who willfully violates, attempts to violate, or conspires to violate any rule or
regulation or order by PNRI issued hereunder may be guilty of a crime, and upon conviction,
may be punished by a fine or imprisonment or both as provided by Sections 64 and 65 of
Republic Act No. 5207.
Section 44. Effective Date.
The regulations in this Part shall take effect fifteen (15) days following its publication in the
Official Gazette or in a newspaper of general circulation. Approved:
(Signed)
ALUMANDA M. DELA ROSA, Ph.D.
Director, PNRI
Date: July 2, 2004
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the production of sources and the use of radiation or
radioactive substances for medical, industrial, veterinary
or agricultural purposes, or for education, training or
research the generation of nuclear power, including activities in the
nuclear fuel cycle
practices involving exposure to natural sources specified
by the Regulatory Authority as requiring control
any other practice specified by the Regulatory Authority
(2.1) The practices to which the CPR Part 3, Standardsfor protection against radiation (based on IBSS) apply
include the following and any related activities which
involve or could involve exposure to radiation or
radioactive substances:
System of Radiological Protection
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No practice shall be:
System of Radiological Protection
Adopted
Introduced Conducted
Discontinued
Ceased
(continued on next slide)
S f
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System of Radiological Protection
and no source within a practice shall be: mined milled processed designed
manufactured constructed assembled acquired imported exported
distributed sold loaned hired
received sited located commissioned possessed used
operated maintained repaired transferred
decommissioned disassembled transported stored disposed of
except in accordance with the appropriate requirementsof the Standards, unless the exposure from suchpractice or source is excluded or exempted
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System of Radiological Protection
(2.10) Any legal personintending to carry out any of the
actions specified on the previous slide shall submit a
notification to the Regulatory Authority of such an
intention
Notification for consumer products is required only with
respect to:
manufacturing
assembling importing
distributing
S t f R di l i l P t ti
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System of Radiological Protection
Any legal person applying for an authorization shall:
submit relevant information necessary to support theapplication;
refrain from carrying out any of the actions describedon the previous slides until the registration or license,has been granted;
make an assessment of the nature, magnitude andlikelihood of the exposures attributed to the source
and take all necessary steps for the protection andsafety of both workers and the public; and have a safety assessment made and submitted as part
of the application if the potential for an exposure isgreater than any level specified
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System of Radiological Protection
Typical practices that are amenable to registration arethose for which:
safety can largely be ensured by the design of the
facilities and equipment;
the operating procedures are simple to follow;
the safety training requirements are minimal; and
there is a history of few problems with safety
Registration is best suited to those practices for which
operations do not vary significantly.
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System of Radiological Protection
Registrants and licensees shall notify the RegulatoryAuthority of their intentions to introduce modifications to
any practice or source for which they are authorized,
whenever the modifications could have significant
implications for protection or safety, and shall not carryout any such modification unless specifically authorized
by the Regulatory Authority.
Sources, including substances, materials and objects,
within notified or authorized practices may be released
from further requirements of the Standards subject to
complying with clearance levels approved by the
Regulatory Authority.
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References:
International Commission On RadiologicalProtection, 1990 Recommendations of the
International Commission on Radiological
Protection, Publication No. 60, Ann. ICRP 21 1-3,
Pergamon Press, Oxford and New York (1991) International Basic Safety Standards for Protection
against Ionizing Radiation and for the Safety of
Radiation Sources, Safety Series No. 115, IAEA,
Vienna (1996)
CPR Part 3, Standards for protection against
radiation, Phil. Official Gazette, 2004
IAEA training modules
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hank you for your attentionAny questions?
Th ICRP B i F k
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(134) Occupational exposure - exposures incurred at workas the result of situations that can reasonably be
regarded as being the responsibility of the operating
management
Thus potassium-40 in the body, cosmic rays at ground
level, and radionuclides in the earths crust are alloutside any reasonable scope of control
Only radon in workplaces and work with materials
containing natural radionuclides can reasonably be
regarded as the responsibility of management
The ICRP Basic Framework
Th ICRP B i F k
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(139) Medical exposure - exposures incurred byindividuals as part of their own medical diagnosis or
treatment or to exposures incurred knowingly and
willingly by individuals helping in the support and comfort
of patients undergoing diagnosis or treatment
Exposures incurred by volunteers as part of a programme
of biomedical research are also dealt with on the same
basis as medical exposure
(140) Public exposure - all exposures other than
occupational and medical mostly from natural sources
The ICRP Basic Framework
Q titi d U it
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the main physical quantities used in the Safety
Standards are:
the rate of nuclear transformation of radionuclides
called the activity which has units of reciprocalseconds (sec-1) or disintegrations per second
(dps) and is termed the Becquerel (Bq)
the energy absorbed by a unit mass of asubstance from the radiation to which it is
exposed called the absorbed dose which has units
of joule per kilogram and is termed the gray (Gy)
Quantities and Units
Q titi d U it
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The absorbed dose is the basic physical dosimetric
quantity of the Standards
However, the effectiveness in damaging human tissue
differs for different types of ionizing radiation
The absorbed dose averaged over a tissue or organ is
multiplied by a radiation weighting factor (wR) to take
account of the effectiveness of the given type ofradiation in inducing health effects; the resulting
quantity is termed the equivalent dose
(absorbed dose x wR)
Quantities and Units
Quantities and Units
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The likelihood of stochastic effects due to a given
equivalent dose differs for different organs andtissues
The equivalent dose to each organ and tissue ismultiplied by a tissue weighting factor (w
T
) to takeaccount of the organs radiosensitivity
The sum total of such weighted equivalent doses forall exposed tissues in an individual is termed the
effective dose whose unit is the same as that of theequivalent and absorbed dose, namely joule perkilogram, but the name sievert (Sv) is used to avoidconfusion with the unit of absorbed dose (Gy)
Quantities and Units
Quantities and Units
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In summary:
Absorbed Dose x wRx wT= Effective Dose
Quantities and Units
Equivalent Dose
Absorbed Dose x wR= Equivalent DoseEquivalent Dose x wT= Effective Dose
Quantities and Units
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When radionuclides are taken into the body, the
resulting dose is received throughout the period of
time during which they remain in the body
The committed dose is the total dose delivered duringthis period of time, and is calculated as a time integral
of the rate of receipt of the dose
Quantities and Units
Q titi d U it
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The impact of the radiation exposure from a given
practice or source depends on the number of
individuals exposed and on the doses they receive
The collective dose, defined as the summation of theproducts of the mean dose in the various groups of
exposed people and the number of individuals in each
group may therefore be used to characterize the
radiation impact of a practice or source
The unit of collective dose is the man-sievert (man-Sv)
Quantities and Units
C ll ti D
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The Linear No Threshold (LNT) dose-responserelationship assumes that all radiation dose produces
some stochastic effect and that the probability of the
effect increases linearly with dose
small dose small chance of effect
large dose large chance of effect
Therefore, the total stochastic effectproduced in the
population is dependent on the total dosereceived by the
population. Therefore, the Collective Dose is important.
Collective Dose
Collective Dose
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Theoretically, a radiation dose of 0.1 Sv to one individualwould result in the same probability of a stochasticeffect as 0.01 Sv each to 10 different individuals.
For example, the one individual exposed to 0.1 Sv would
have a certain probability (P) of developing cancer.
The LNT theory states that the 10 individuals exposed to0.01 Sv each would each have 1/10 the probability (0.1P)of developing cancer.
Thus the total probability of cancer in the population of10 individuals would be 10 x 0.1P = P, the same as theone individual who was exposed to 0.1 Sv.
Collective Dose
Collective Dose
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Of course, there is one big difference between the twoscenarios. If you happen to be the one individualexposed to 0.1 Sv, you have incurred all the risk. Theprobability of getting or not getting cancer rests solelyon your shoulders.
However, if you happen to be in the group of 10receiving 0.01 Sv each, your individual probability is1/10 as large. That may sound comforting, butremember, the probability of getting cancer for thegroup was the same as for the individual. Therefore,just as above, you may or may not get cancer. If youdo, it will be the same cancer. It wont be 1/10 of acancer.
Collective Dose
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Where to Get More Information
International Commission On Radiological
Protection, 1990 Recommendations of the
International Commission on Radiological
Protection, Publication No. 60, Ann. ICRP 21 1-3,
Pergamon Press, Oxford and New York (1991)
International Basic Safety Standards for Protection
against Ionizing Radiation and for the Safety of
Radiation Sources, Safety Series No. 115, IAEA,
Vienna (1996)