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IRRI
International Rice Research Institute
Analytical Service
Laboratory-
Radioisotope Lab
Document Control No.:
RL-RSM 00
Title: RADIATION SAFETY
MANUAL Issue Date:2011-01-31 Revision No.: 01 Page: 1 of 59
International Rice Research Institute Grain Quality and Nutrition Center
Analytical Service Laboratory-Radioisotope Laboratory
This document is issued under the authority of
MS. LILIA R. MOLINA
IRRI Radiation Safety Officer
THIS IS A CONTROLLED DOCUMENT
Copy No. 01
Revision No. 01
Issued To
Issue Date
IRRI
RADIATION SAFETY MANUAL
RL-RSM00-R01
IRRI
International Rice Research Institute
Analytical Service
Laboratory-
Radioisotope Lab
Document Control No.:
RL-RSM 00
Title: RADIATION SAFETY
MANUAL Issue Date:2011-01-31 Revision No.: 01 Page: 2 of 61
REVISION RECORD
Revision Description of Change Author Effective Date
0 Initial release R.Jimenez 2004-Oct.
1 Revision and updating LMolina 2011-Jan.23
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Title: RADIATION SAFETY
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TABLE OF CONTENTS
REVISION RECORD..................................................................................................................... 2
TABLE OF CONTENTS................................................................................................................ 3
PREFACE....................................................................................................................................... 5
1. INTRODUCTION................................................................................................................... 6
2. RADIATION SAFETY ORGANIZATIONAL STRUCTURE.............................................. 6
2.1. Radiation Safety Officer................................................................................................... 6
2.2. Assistant RSO .................................................................................................................. 8
2.3. Principal Investigator ....................................................................................................... 9
2.4. Workers (Authorized Staff)............................................................................................ 10
3. POLICIES AND REGULATIONS ON RADIATION USE ................................................ 11
3.1. ALARA Program ........................................................................................................... 11
3.2. Philippine Nuclear Research Institute ............................................................................ 12
3.3. Standards for Protection Against Radiation ................................................................... 13
3.4. Procedure for Obtaining Authorization to Use Radiation Sources ................................ 13
3.5. PNRI Inspection of Radiation Sources and Facilities .................................................... 14
3.6. Sanctions for Non-compliance ....................................................................................... 14
4. TRAINING PROGRAM ....................................................................................................... 16
4.1. Topics included in the Radiation Safety Course ............................................................ 17
4.3. Radioactivity and Radiation Units ................................................................................. 18
4.4. Biological Effects of Radiation ...................................................................................... 20
4.5. External and Internal Radiation Exposures.................................................................... 22
4.6. Nature and Properties of Some Radioisotopes Used in Agriculture .............................. 24
4.7. Exposure Limits for Workers and the General Public ................................................... 30
5. RADIOISOTOPE LABORATORY MANAGEMENT........................................................ 32
5.1. Radiation Facilities......................................................................................................... 32
5.1 General Lab Safety Rules............................................................................................... 32
5.2 Area Restrictions ............................................................................................................ 34
5.3 Radiation Survey Monitoring Procedure ....................................................................... 34
5.4 Decontamination Procedure ........................................................................................... 35
5.5 Decommissioning........................................................................................................... 38
6. RADIOACTIVE MATERIALS (RAM) MANAGEMENT ................................................. 39
6.1. Guidelines for Ordering and Receiving Radioactive chemicals/Instruments with sealed
sources............................................................................................................................ 39
6.2. Labeling Requirements .................................................................................................. 44
6.3. RAM Storage Procedure ................................................................................................ 44
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6.4. Transport of Radioactive Materials................................................................................ 45
6.5. Inventory and Security ................................................................................................... 45
6.6. Transfer .......................................................................................................................... 47
7. PERSONNEL MONITORING PROGRAM......................................................................... 48
7.1. Schedule ......................................................................................................................... 48
7.2. Reliability....................................................................................................................... 48
7.3. Records........................................................................................................................... 48
8.1. Minor Spills Involving No Radiation Hazard to Personnel ........................................... 49
8.2. Major Spills Involving Radiation hazard to Personnel .................................................. 50
8.3. Accidents Involving Radioactive Dusts, Mists, Fumes, Organic Vapors and Gases..... 50
8.4. Injuries to Personnel Involving Radiation Hazard ......................................................... 51
8.5. Fires or Other Major Emergencies ................................................................................. 51
9. RADIOACTIVE WASTE MANAGEMENT ....................................................................... 51
9.1. Segregation..................................................................................................................... 52
9.2. Labeling and Record Keeping Requirements................................................................. 53
9.3. Quantifying Levels of Radioactivity in Waste............................................................... 54
9.4. Interim Storage of Radioactive Wastes.......................................................................... 55
9.5. Methods of Disposal....................................................................................................... 55
10. APPENDICES ................................................................................................................... 58
10.1 Appendix 1 - Definition of Terms .................................................................................. 58
10.2 Appendix 2. Details on CPR Part 3 ................................................................................ 60
10.3 Appendix 3. – Required forms for obtaining Authorization to Use Radiation Sources 60
10.4 Appendix 4. - Code of PNRI Regulations (CPR Part 4)................................................. 61
11. REFERENCES .................................................................................................................. 61
12. IMPORTANT CONTACT NUMBERS............................................................................ 61
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PREFACE
The International Rice Research Institute strives to provide a safe and healthful environment for
all persons, including the research and administrative staff, students, and visitors, involved with
the handling of hazardous materials. Attainment of this goal requires the cooperation and
commitment of all persons involved.
While the IRRI Safety and Security Office plans and recommends policies in all matters
pertaining to safety and health in the workplace, organizational unit heads, managers, and
supervisors are directly responsible for maintaining an atmosphere that promotes full compliance
with safety policies and procedures.
With regard to radiation safety matters, the Radiation Safety Officer (RSO), nominated by the
Deputy Director General for Research, is responsible for the effective implementation of
radiation policies and procedures established in accordance with requirements set forth by the
Philippine Nuclear Research Institute (PNRI). The PNRI is the agency mandated by the
Philippine government to institute regulations on the peaceful uses of radiation sources and to
carry out enforcement of said regulations to protect the health and safety of radiation workers
and the general public.
This manual presents the essential elements of the IRRI’s Radiation Safety Program. It consists
of the policies, and procedures and relevant information intended to assist all users of
radioactive materials in meeting their safety responsibilities while utilizing the unique
advantages of radiation sources. The program supports the objective of maintaining all
exposures at levels "As Low As Reasonably Achievable" (ALARA).
It is essential that all members of the IRRI community become and remain thoroughly familiar
with their responsibilities for compliance with health and safety regulations, including the
radiation safety policies and procedures contained in this manual. Everyone involved with the
use of radioactive material in any way is required to be familiar with the provisions of this
manual.
IMPORTANT CONTACT NUMBERS:
Lily Molina (RSO) – loc. 2388 and 2435 (office)
Tel # : 049-501-7893 (residence)
Ruffy Manuel – loc. 2419 Safety Office – loc. 2222
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RL-RSM00-R01
RADIATION SAFETY MANUAL
1. INTRODUCTION
The International Rice Research Institute is authorized by the Philippine Nuclear Research
Institute (PNRI), to acquire, receive, possess, own, and use radioactive materials, as
described in Radioactive Material License No. R04.0262, for the purpose and place
specified and subject to the general and specific conditions stipulated therein. In planning an
experiment involving the use of radioisotopes, the Principal investigator must first submit
the proposal to IRRI’s Radiation Safety Officer (RSO) for review and approval. Although
the RSO allows flexibility in dealing with the research uses of radioisotopes on campus, the
responsibility rests on organizational unit heads and principal investigators to utilize
radioactive materials safely and to comply with state regulations.
This manual is a compilation of the regulations applicable to utilization of radioactive
material at IRRI. A copy must be available in each Authorized Staff's facility where
radioactive materials are used. As a general principle of radiation safety and as a policy of
the institute, exposure to radiation should be maintained at levels that are as low as
reasonably achievable (ALARA). The use of radioactive materials is a privilege, not a right.
Everyone concerned is expected to maintain a safe and compliant workplace.
2. RADIATION SAFETY ORGANIZATIONAL STRUCTURE
2.1. Radiation Safety Officer
A qualified Radiation Safety Officer (RSO), designated by IRRI management, shall be
responsible for implementing the radiation safety program. Through the RSO, IRRI shall
ensure that radiation safety activities are being performed in accordance with regulatory
requirements and approved procedures.
2.1.1 Qualifications and requirements of RSO:
a) The RSO shall have completed one hundred twenty (120) hours of formal training
and instructions on radiation physics, radiation safety, nuclear regulations and
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safe transport of radioactive materials, or an equivalent course as may be
determined by PNRI.
b) Official Designation/Appointment by IRRI Management. A copy of the document
that designates/appoints the individual who will be the RSO, together with a
resume of his/her relevant training and experience, must be submitted to PNRI.
The document should bear the signature of a representative of management,
usually the IRRI Deputy Director General for Research.
c) Proof of Consent/Acceptance by RSO. The submitted documents must show
proof that the designated RSO has accepted and consented to his designation in
writing.
d) Statement of Authority and Responsibilities. IRRI management shall provide the
RSO sufficient authority, organizational freedom, and management prerogative
to:
• Identify radiation safety problems
• Initiate, recommend, or provide corrective actions, and
• Verify implementation of corrective actions.
2.1.2 Duties and Responsibilities
a) Ensure that licensed material possessed by IRRI is limited to the kinds, quantities
and forms listed on the license.
b) Ensure that individuals using the material are properly trained and are informed of
all changes in regulatory requirements and deficiencies identified during annual
management audits or PNRI inspections.
c) Ensure that personnel monitoring devices are used as required and that reports of
personnel exposure are reviewed in a timely manner.
d) Ensure that material is properly secured against unauthorized removal at all times
when material is not in use.
e) Ensure that proper authorities are notified in case of accident, damage, fire or
theft, in accordance with the most recently approved emergency plan.
f) Ensure that audits are performed at least annually to determine that:
• IRRI complies with PNRI regulations and the terms and conditions of the
license.
• The radiation protection program content and implementation achieve
occupational doses and doses to members of the public that are ALARA; and
• Records with all required information (e.g. personnel exposure, receipt,
transfer, and disposal of licensed material, user training) are sufficient to
comply with PNRI requirements.
g) Ensure that the results of the audits, identification of deficiencies, and
recommendations for change are documented, provided to management for
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review, and maintained for at least 5 years. Ensure prompt action is taken to
correct deficiencies.
h) Ensure that all incidents, accidents, and personnel exposure to radiation more than
ALARA levels are investigated and reported to PNRI within the required time
limits.
i) Ensure that licensed material is transported in accordance with all applicable
PNRI requirements.
j) Ensure that spent licensed material and wastes contaminated with radioactive
material are disposed of properly.
2.2. Assistant RSO
Upon the recommendation of the RSO, the representative of IRRI management may also
designate an Assistant RSO who shall act for on behalf of the RSO in his/her absence.
2.1.3 Requirements:
a) The ARSO shall have completed at least one hundred twenty (120) hours of
formal training on radiation physics, radiation safety, nuclear regulations and safe
transport of radioactive materials OR forty (40) hours of formal training plus
relevant experience as an Authorized Staff in handling major radioisotopes
currently used at IRRI.
b) Official Designation/Appointment by IRRI Management. A copy of the document
that designates/appoints the individual who will be the ARSO, together with a
resume of his/her relevant training and experience, must be submitted to PNRI.
The document should bear the signature of a representative of management,
usually the IRRI Deputy Director General for Research.
c) Proof of Consent/Acceptance by ARSO. The submitted documents must show
proof that the designated ARSO has accepted and consented to his designation in
writing.
2.1.4 Duties and Responsibilities:
a) Act on behalf of the RSO in his/her absence.
b) In-charge of radioisotope facilities and activities in his work area.
c) Keep and maintain appropriate records of all radioisotope activities (routine
survey monitoring of facility, inventory of radioisotopes, type, volume and
activity of wastes generated and disposed of) and provide copies of these records
to the RSO.
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2.3. Principal Investigator
The Principal Investigator is directly responsible for compliance with all regulations
governing radiation safety in the laboratory, and for safe practices of individuals working
under his/her supervision.
2.1.5 Requirements: Relevant work experience and/or training.
2.1.6 Duties and Responsibilities:
a) Prepare and submit research proposal and justification for the use of radioactive
material in his/her research work, as required for inclusion in the PNRI
Radioactive Material License for IRRI, and for subsequent annual renewal of the
license.
b) Outline procedures to be followed in proposed activity, from introduction of
radiotracer up to analysis, indicating how the labeled material will be handled and
how the activity will be monitored.
c) Use radioactive materials according to statements, representations and conditions
set forth in the radioactive materials use license.
d) Responsible for individuals working under his/her control.
• Ensure that Authorized Staff (lab technicians, students, visitors, researchers,
scientists) in his work area are properly supervised, trained and informed of
the institute’s Radiation Safety Program to enable safe working habits and
prevent exposures to themselves and others and/or contamination of the work
areas or environment.
• Ensure that film badges are worn appropriately by Authorized Staff when
working with radioisotopes and are placed in a designated rack after use.
• Ensure timely submission of film badges and survey meters to the RSO for
proper evaluation and calibration at PNRI
• Ensure proper disposal of radioactive wastes generated from activities in his
work area
e) Ensure that radiation safety surveys and audits in the laboratory are conducted,
and maintain records for review.
f) Maintain inventory and record of the various forms (physical and chemical) and
quantities of radiation which are present in his work areas. Provide the RSO with
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current records of the receipt and the disposition of radioactive material in their
possession including use in research, waste disposal, transfer, storage, etc.
g) Maintain constant surveillance and immediate control of radioactive materials to
prevent unauthorized removal or tampering, and/or assure that all of the workers
occupying the area maintain security. Post warnings and restrict entry to areas that
contain potentially hazardous radioactivity or chemicals. Label radioactive use
equipment and work areas.
h) Notify the RSO of any changes in procedure or personnel, or licensed
activities/materials in his work area that would require an amendment to the
license, including transfer of radioactive materials/facilities, new radioisotope
users, and decommissioning of facilities. Changes from the approved procedures
must be approved by PNRI in an amendment or new application prior to the
implementation of the change.
i) Assure designation of a responsible individual to oversee radioisotope work
during short absences, and of a stand-in principal investigator during extended
absences.
2.4. Workers (Authorized Staff)
The term "Authorized Staff" is used to identify an individual who is authorized in the
license to use radioactive material in the course of his/her employment or study.
Authorized Staff may be a Principal Investigator, Assistant Scientist, Researcher,
Graduate student, Technician, Post-doctorate, Visitor, or any other individual who will
handle radioactive material. Since they are the direct handlers of the radioactive
material, the final responsibility lies with them for safety and compliance with laws and
regulations.
2.4.1 Requirements
a) The authorized staff shall have completed a basic radiation safety course that
includes forty (40) hours of training on radiation physics, radiation protection,
safe handling and transport of radioactive material, or an equivalent course as
may be determined by PNRI.
b) Official authorization. A list of persons who will use radioactive materials under a
certain project should be certified and submitted by the project’s Principal
Investigator for inclusion in the PNRI Radioactive Material License for IRRI.
c) Must fill out NRLSD/LRE-008a form and, together with a Certificate of
Training, submit to PNRI, through RSO.
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2.4.2 Duties and Responsibilities
a) Adhere to all laws, rules, regulations, license conditions and guidelines pertaining
to the use of radioactive materials.
b) Wear assigned film badge during handling of radioactive materials. (See
Personnel Monitoring for details on film badge requirements.)
c) Practice ALARA (As Low As Reasonably Achievable) in their work, and
minimize the potential for exposures, contamination or release of radioactive
materials.
d) Clean any contamination or spills that occur in his/her work area. The work area
must be monitored by the user after each use. If contamination is found, it must be
cleaned up immediately. DO NOT LEAVE IT FOR ANOTHER PERSON TO
CLEAN UP.
e) Follow strictly experimental procedures. No changes in procedures using
radioactive materials are to occur without the approval of the principal
investigator. (Do not take short cuts. Changes in experimental procedures
impacting upon safety must be approved by the RSO)
f) Report immediately any abnormal occurrence to the principal investigator, such
as spills, significant contamination, equipment failure, and loss of film badges.
g) Return the film badges on time and report any loss or contamination of the film
badge to the RSO.
h) Inform the RSO of any exposures which have occurred at a previous employer
when beginning employment at IRRI. Also, notify the RSO of termination of
employment and return the film badge at the end of employment.
i) Maintain security of radioactive materials.
j) Segregate and properly label radioactive and/or radioactive-contaminated wastes
for proper disposal.
3. POLICIES AND REGULATIONS ON RADIATION USE
3.1. ALARA Program
IRRI is committed to the program described herein for keeping individual and collective
doses As Low As Reasonably Achievable (ALARA). In accord with this commitment,
policies and procedures are hereby prescribed to ensure radiation exposures to all persons
associated with the organization are minimized:
3.1.1 The RSO will review annually radiation worker doses, to determine whether
exposures are being kept to a minimum. When levels are exceeded, the worker will be
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notified and work practices reviewed, in order to attempt to lower the exposure if
possible.
3.1.2 The RSO will brief management once per year regarding occupational exposure
levels.
3.1.3 The RSO will carefully review applications for radioactive material authorization, to
ensure that the applicant is qualified and that the proposal incorporates the ALARA
philosophy. Modifications or alternatives to operating procedures will be
recommended if they will reduce exposures unless the cost is considered justified.
3.1.4 The RSO will perform an annual review of the Radiation Safety Program, including
ALARA considerations. This will include reviews of operating procedures and past
dose records, inspections, etc., and consultations with PNRI or outside consultants.
3.2. Philippine Nuclear Research Institute
Republic Act 2067 and Republic Act 5207, both as amended, established and provided the
authority for the Philippine Atomic Energy Commission (PAEC), now the Philippine
Nuclear Research Institute (PNRI), to promote and at the same time regulate the
application and use of radioactive materials in the Philippines.
3.2.1. Nuclear Regulations, Licensing and Safeguards Division (NRLSD) of PNRI is
responsible for the regulatory control of radioactive materials. NRLSD is composed
of five (5) sections:
a) Standards Development Section – develops regulations, regulatory guides, and
standards related to atomic energy facilities and radioactive materials.
b) Licensing, Review and Evaluation Section – reviews license applications and
maintains the database of licensees and radioactive materials in its possession.
All licenses are issued on an annual basis, for which the licensee has to pay the
license fees. Records are kept of each license or licensee.
c) Inspection and Enforcement Section – conducts regulatory inspection and
enforcement activities. The section has developed inspection plans and
checklists for particular practices that are used during the inspection. The
inspections are conducted on a yearly basis. Follow-up or unannounced
inspections are conducted to verify implementation and completion of licensee’s
commitment on certain inspection findings.
d) Safeguards Section – maintains the system for accounting and control of nuclear
materials. It is responsible for the security of radioactive sources and maintains
the database of sealed sources based on information available from the LRE
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records. The section also maintains a database of reported missing or stolen
sources.
e) Radiological Impact Assessment Section – responsible for emergency planning
and preparedness for radiological accidents or incidents and dose assessments. It
also provides regulatory research activities in aid of the regulations.
3.2.2. Rules and Regulations on the Use of Radiation Sources in the Philippines.
PNRI has established the Code of PNRI Regulations containing the rules and
regulations for the specific category of use of radioactive materials. The rules
are identified as parts of the Code and are properly identified as CPR Part
Numbers.
3.3. Standards for Protection Against Radiation
3.3.1. Code of PNRI Regulations (CPR) Part 3. Standards for Protection Against
Radiation
The provisions of this Part prescribe the safety limits, standards, and procedures that
must be followed by authorized persons to protect its workers and the public against the
hazards of radiation and to protect the radioactive materials from unauthorized use. CPR
Part 3 adopts the recommendations of the International Basic Safety Standards for
Radiation Protection (IBSS) published by the International Atomic Energy Agency
(IAEA).(See Appendix 2. for details on CPR Part 3)
3.4. Procedure for Obtaining Authorization to Use Radiation Sources
Approval for the use of radioactive materials is given by PNRI for a period of one year,
and is reviewed annually. IRRI, through the RSO, should file the application with PNRI at
least 30 working days before the expiration date of the previous license. Normally, the
license expires at the end of February and application for renewal should be filed before
15th of January.
3.4.1 Requirements. To obtain authorization, the Principal Investigator or his designated
staff, must submit the following completed forms (see Appendix 3) to the RSO.
a) Application for Inclusion in the PNRI Radioactive Material License for IRRI
(RIL Form 1)
b) List of Radioactive Materials/Labeled Compounds (RIL Form 2a)
c) List of Radioactive Materials/Sealed Sources (RIL Form 2b)
d) Research Proposal (RIL Form 3)
e) List of Proposed Authorized Staff (RIL Form 4)
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f) Accomplish one NRLSD/LRE Form No. 008a for each person in the list and
enclose a copy of Certificate of Training
g) List of Survey Instruments for radiation detection use at the designated work
area (RIL Form 5)
PNRI may require additional conditions under which the use of the material must be
conducted. Upon approval of application, the Principal Investigator may then order,
receive, and use the material according to the statements and representations made in
the application, and any conditions set forth by PNRI in the license. Violations or non-
compliance may be cause for suspension or termination of the authorization to receive
and use radioisotopes.
3.5. PNRI Inspection of Radiation Sources and Facilities
PNRI conducts regulatory inspection on a yearly basis. Follow-up or unannounced
inspections are also conducted to verify implementation and completion of licensee’s
commitment on certain inspection findings. The RSO should provide pertinent records to
the PNRI inspectors upon their request and access to radioisotope laboratory facilities.
3.6. Sanctions for Non-compliance
Each radioactive materials user should understand and remember that there is only one
license for the entire institute. Any individual or any action that endangers the license
compromises the permission of all researchers to utilize radioactive material at IRRI.
Hence, the license places significant responsibility on each individual who uses
radioactive materials to conform with safe work practices, and to conduct and complete all
required duties, however large or small they may be.
3.6.1 Sanction system. IRRI confers authority upon the RSO to “police” the ranks of all
users and handlers of radioactive materials in the institute and to impose sanctions for
noncompliance. A sanction system for violations or instances of noncompliance consists
of the following:
a) A report is sent to the Principal Investigator, detailing the violation or
noncompliance and the corrective action/s required.
b) If the problems are corrected, no further actions will be required. If not corrected,
a Notice of Noncompliance may be sent to the Principal Investigator requiring a
response in writing and further corrective actions.
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c) Sanctions will be imposed depending on the severity level of the violation or
noncompliance shown in Table 1.
Table 1. Levels of violation and corresponding sanctions.
Level Violation Sanction/s
I Serious violation
which cause
immediate risk
or danger to
safety, health,
release to the
environment of
substantial
quantities, doses
to humans.
a) Violation noted by RSO and sent to IRRI Safety and
Security Office
b) Letter to PI from RSO; response is required in writing
c) Require PI to immediately submit written corrective
actions to RSO
d) Require PI to appear before an investigation committee
e) Close surveillance by SSO and RSO to ensure corrective
measures are enforced
f) Require involved personnel to attend refresher course on
radiation safety
g) Place restrictions on staff causing non-compliance
h) Suspend shipments of radioactive materials to PI
i) Decrease scope or limits of radioactive materials
approval
j) Require PI to reapply for radioisotope use
k) Confiscate radioactive materials in possession of PI
l) Permanently terminate approval to use radioactive
materials
II Serious Violation
but does not
present immediate
risk to health,
safety, the
environment or the
license
a) Violation noted by RSO and sent to IRRI Safety and
Security Office
b) Letter to PI from RSO; response is required in writing
c) Require PI to immediately submit written corrective
actions to RSO
d) Require PI to appear before an investigation committee
e) Close surveillance by RSO to ensure corrective
measures are done
f) Require involved personnel to attend refresher course on
radiation safety
g) Place restrictions on staff causing non-compliance
III A minor a) Violation noted by RSO and memo sent to Authorized
Staff
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violation,
typically a
technical matter
such as failure to
properly label
materials and
wastes with all
the required
information;
record keeping
errors of minor
impact. Poses no
immediate risk
to health, safety
or environment.
A minor
noncompliance
issue, but when
seen repeatedly,
may be escalated
to a higher level.
b) Require Authorized Staff to immediately correct
violation
c) Close surveillance by RSO to ensure corrective
measures are done
d) Require involved personnel to attend refresher course on
radiation safety
IRRI, through the RSO, should within twenty-four (24) hours notify PNRI by telephone or by
any other fast means of any incident involving licensed radioactive materials which may have
caused or threatens to cause unnecessary risk to the health and safety of the public. A
subsequent written report detailing the circumstances and the corresponding actions undertaken
shall be submitted within thirty (30) calendar days from the time the report was made.
4. TRAINING PROGRAM
Before assuming duties involving use of radioisotopes or handling of equipment with sealed
sources, it is mandatory that all workers, including principal investigators attend at least 40 hours
training course on handling of radioactive materials at the Philippine Nuclear Research Institute
(PNRI). Certification is obtained after successful completion of the course and passing the
examination.
Radiation workers new to IRRI but with significant training and experience in handling
radioactive materials, including new IRS and/or short-term visitors, should submit a copy of
certification of training obtained elsewhere and/or of relevant work experience. The RSO may
request prior radiation dose histories from past employers.
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4.1. Topics included in the Radiation Safety Course
4.1.1. Basics on Radioactivity and Radioactive Decay
4.1.2. Quantities and Units / Interaction of Radiation
4.1.3. Radiation Detection
4.1.4. Biological Effects of Radiation
4.1.5. Basic Principles of Radiation Protection
4.1.6. Radiation Control Practices and Handling Techniques
4.1.7. Radioactive Waste Management
4.1.8. Radiation Monitoring
4.1.9. Calculations Basic to the Use and Measurement of Radioactivity
4.1.10. Nature and Properties of Radioisotopes Used in Agriculture
4.1.11. Laboratory Design
4.1.12. Contamination / Decontamination (lecture/demo)
4.1.13. Emergency Procedures
4.1.14. Safe Transport of Radioactive Materials
4.1.15. Licensing Rules and Regulations
4.1.16. Characteristics of Geiger-Mueller Detector / Statistics of Counting
4.2. Additional instructions / orientation should be given by the Principal Investigator or
his designated Authorize Staff to new users on the following subjects:
4.2.1. IRRI’s Radiation Safety Program
4.2.2. In-house laboratory rules and procedures.
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4.2.3. Areas where radioactive materials are used or stored.
4.2.4. Potential hazards associated with radioactive material in each area where the
employees will work.
4.2.5. Each individual’s obligation to report unsafe conditions to the RSO.
4.2.6. Location where the licensee has posted or made available, notices, copies of
pertinent regulations, and copies of pertinent licenses and pertinent conditions.
4.3. Radioactivity and Radiation Units
Radioactive material is defined as any material or combination of materials that
spontaneously emits ionizing radiation. Ionizing radiation has the ability to remove electrons
from atoms, creating ions; hence, the term "ionizing radiation". The result of ionization is
the production of negatively charged free electrons and positively charged ionized atoms.
There are four types of ionizing radiation involved that can be classified into two groups: 1)
photons, such as gamma and x-rays, and 2) particles, such as beta particles (positrons or
electrons), alpha particles (similar to helium nuclei, 2 protons and 2 neutrons), and neutrons
(particles with zero charge, electrically neutral). Photons are electromagnetic radiation
having energy, but no mass or charge; whereas particles have typically both mass and charge
as well as energy. Neutrons have mass and energy, but no charge, and are typically produced
by man with machines, such as cyclotrons. All types of ionizing radiation can remove
electrons, but interact with matter in different ways.
Ionized atoms (free radicals), regardless of how they were formed, are much more active
chemically than neutral atoms. These chemically active ions can form compounds that
interfere with the process of cell division and metabolism. Also, reactive ions can cause a
cascade of chemical changes in the tissue. The degree of damage suffered by an individual
exposed to ionizing radiation is a function of several factors: type of radiation involved,
chemical form of the radiation, intensity of the radiation flux (related to the amount of
radiation and distance from the source), energy, and duration of exposure.
Radioactive materials have an associated half-life, or decay time characteristic of that
isotope. As radiation is emitted, the material becomes less radioactive over time, decaying
exponentially. Since it is impossible or impractical to measure how long one atom takes to
decay, the amount of time it takes for half of the total amount of radioactive material to decay
is used to calculate half-life.
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4.3.1 Radioactive decay.
The equation which is used to calculate radioactive decay is shown below.
A = A0e−λλλλt
Where:
A = Current amount of radioactivity
A0 = Original amount of radioactivity
e = base natural log = 2.718
λ= the decay constant = 0.693 / t1/2 (where t 1/2 = half-life)
t = the amount of time elapsed from A0 to A
It is important to be careful of the units used for the time. Days, hours and years must not
be mixed in the calculation.
4.3.2 Units of Activity.
Quantify the amount of radiation emitted by a given radiation source. Activity can be
measured with an appropriate radiation detection instrument. Most of these measurements
are made with a liquid scintillation counter, gamma well counter or Geiger-Mueller (GM)
survey meter with appropriate detection probes. These instruments detect a percentage of
the disintegrations and display in counts per minute (CPM).
It is important to note that the CPM readings from survey instruments are not the true
amount of radiation present, since there are factors which decrease the detection capability
of even the most sensitive instruments. Two factors influence radiation detection
sensitivity: the geometry of the counting system and the energy of the radionuclide being
measured. Lower energy radionuclides are detected with lower efficiencies than higher
energy radionuclides. Detection instruments are calibrated with known sources with
different energy levels to determine the efficiency of the instrument in order to account for
these variables. To make the necessary conversion to the microcurie unit, the following
formula must be used in all records of surveys, waste materials or radioactive solutions
generated within the facility.
CPM/Efficiency = DPM
DPM/2.22 x 106 = uCi
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Special Units International Units (SI)
Curie, Ci = 3.7 x 1010
DPS disintegrations
(particles or photons) per second
= 2.22 x 1012
DPM
Becquerel, Bq = 1 DPS
(disintegration per
second.)
Millicurie, mCi = 0.001 Ci Megabecquerel
, MBq
= 106 Bq
Microcurie,uCi = 0.000001 Ci Gigabecquerel,
GBq
= 109 Bq
4.3.3 Units of Exposure (Dose)
Quantify the amount of radiation absorbed or deposited in a specific material by a
radiation source.
Special Units International Units
(SI)
Roentgen, R = quantity of γ or x-
radiation to produce ions
with charge of 2.58 x 10-4
coulombs per kg air
Coulomb/Kg = 3.876 x 103 R
Radiation
Absorbed Dose,
rad
= 100 ergs of energy
deposition per gram of
absorber
Absorbed Dose,
Gray, Gy
= 100 rads
Equivalent Dose,
rem
= rad x ΣWR
Equivalent Dose,
Sievert, Sv
= 100 rem
Effective Dose,
J/kg
= rem x ΣWT
Equivalent Dose,
Sievert, Sv
= 100 rem
WR = radiation weighing factor for the type and energy of radiation incident and is
independent of tissue or organ
ΣWT = tissue weighing factor for tissue T
4.4. Biological Effects of Radiation
4.4.1. Injury due to irradiation is caused mainly by ionization within the tissues of the
body. When radiation interacts with a cell, ionizations and excitations are
produced in either biological macromolecules or in the medium in which the
cellular organelles are suspended, predominantly water. Based on the site of
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interaction, the radiation-cellular interactions may be termed as either direct or
indirect.
4.4.2. Direct action occurs when an ionizing particle interacts with and is absorbed by a
macromolecule in a cell (DNA, RNA, protein, enzymes, etc.). These
macromolecules become abnormal structures which initiate the events that lead to
biological changes.
4.4.3. Indirect action involves the absorption of ionizing radiation in the medium in
which the molecules are suspended. The molecule which most commonly
mediates this action is water. Through a complex set of reactions the ionized
water molecules form free radicals that can cause damage to macromolecules.
4.4.4. The most important target for radiation in the cell is DNA in the nucleus.
Biological effects result when DNA damage is not repaired or is improperly
repaired. Extensive damage to DNA can lead to cell death. Large numbers of cells
dying can lead to organ failure and death for the individual. Damaged or
improperly repaired DNA may develop into lymphoma and cancers in somatic
cells.
4.4.5. Two kinds of effects
a) Acute, or nonstochastic, effects are health effects, the severity of which
varies with the dose and for which a threshold is believed to exist. Radiation-
induced cataract formation is an example of a nonstochastic effect (also
known as a deterministic effect).
b) Delayed, or stochastic, effects, are health effects that occur randomly and for
which the probability of the effect occurring, rather than the severity, is
assumed to be a linear function of the dose without threshold. Genetic effects
and cancer incidence are examples of stochastic effects.
4.4.6 Sensitivity. Various degrees of sensitivity to radiation exist due to the type of
tissue which receives the exposure, and are shown below:
Radiosensitive Less Radiosensitive
Breast tissue Heart tissue
Bone marrow cells Large arteries
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Mucosa lining of small intestines Large veins
Sebaceous (fat) glands of skin Mature blood cells
Immune response cells Neurons
All stem cell populations Muscle cells
Lymphocytes
4.5. External and Internal Radiation Exposures
4.5.1 External hazards
These hazards arise when radiation from a source external to the body penetrates the body
and causes a dose of ionizing radiation. These exposures can be from gamma or x-rays,
neutrons, or beta particles; they are dependent upon both the type and energy of the radiation.
Most beta particles do not normally penetrate beyond the skin, but when sufficiently intense,
can cause skin and/or eye damage. Very energetic beta particles, such as those emitted by
32P, can penetrate several millimeters into the skin. Shielding is needed in order to reduce
the external radiation exposure. Typically, a maximum of 1/2 inch thick sheet of Plexiglas is
an effective shield for most beta particles.
Alpha particles, because of higher mass, slower velocity, and greater electrical charge
compared to beta particles, are capable of traveling a few inches in air and rarely penetrate
the outer dead skin layer of the body. Therefore, alpha particles typically are not an external
radiation hazard.
X and gamma rays, along with neutron radiation, are very penetrating, and are of primary
importance when evaluating external radiation exposure and usually must be shielded.
The onset of first observable effects of acute radiation exposure, diminished red blood cell
count, may occur at a dose of approximately 100 rads of acute whole body radiation
exposure. The LD50 for humans (lethal dose where 50% of the exposed population may die
from a one time exposure of the whole body) is about 500 rads, assuming no medical
intervention.
Exposure to external radiation may be controlled by limiting the working time in the
radiation field, working at a distance from the source of radiation, inserting shielding
between the worker and the source, and by using no more radioactive material than
necessary.
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4.5.2 Internal exposures
These arise when radiation is emitted from radioactive materials present within the body.
Radioactive materials may be internally deposited in the body when an intake occurs through
one of the three routes of entry: inhalation, ingestion and skin contact. These exposures can
occur when radioactive material is airborne; is inhaled and absorbed by the lungs and
deposited in the body; is present in contaminated food, drink or other consumable items and
is ingested; or is spilled or aerosolizes onto the skin and absorbed or enters through cuts or
scratches. Internal deposition may also result from contaminated hands, with subsequent
eating or rubbing of eyes.
Although external hazards are primarily caused by x-rays, gamma rays, high energy betas
and neutrons, all forms of radiation (including low energy betas, gammas and alphas) can
cause internal radiation exposures. Alpha particles create a high concentration of ions along
their path, and can cause severe damage to internal organs and tissues when they are inhaled,
ingested or are present on the skin. Once these particles get into the body, damage can occur
since there is no protective dead skin layer to shield the organs and tissues. Internal
exposures are not limited to the intake of large amounts at one time (acute exposure).
Chronic exposure may arise from an accumulation of small amounts of radioactive materials
over a long period of time.
It is known that many substances taken into the body will accumulate in certain body organs,
called target organs. For example, iodine will accumulate in the thyroid gland. When iodine
is inhaled or ingested, the body cannot distinguish stable iodine from radioactive iodine; a
significant portion of the inhaled iodine will be deposited in the thyroid gland within 24
hours.
Other elements, such as calcium, strontium, radium and plutonium accumulate in the bones.
Here, high doses to bones can occur over very long periods of time, since the body eliminates
these materials very slowly once they are incorporated into the bone structure. The blood
forming organs, such as the bone marrow, are very radiosensitive, since bone marrow cells
are in the S-phase of mitotic activity more often than other cells. Hence, if there is a
significant long-term exposure to radioisotopes, chronic diseases such as leukemia and/or
osteosarcoma can occur. The induction time for the onset of these types of diseases is
typically in excess of 20 years.
A rule of thumb used to assist in biological risk assessment for radiation is that most mature
cells are radioresistant; all immature cells are very radiosensitive. It is very important for
radioactive materials users to be aware of the target organs for the nuclides they handle.
Precautions may then be taken to prevent exposures.
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4.6. Nature and Properties of Some Radioisotopes Used in Agriculture
4.6.1. Phosphorus – 32 (32P)
4.6.1.1 Physical Data
• Beta energy: 1.709 MeV (maximum)
0.690 MeV (average, 100% abundance)
• Physical half-life: 14.3 days
• Biological half-life: 1155 days
• Effective half-life: 14.1 days (bone) / 13.5 days (whole body)
• Specific activity: 285,000 Ci/gm
• Maximum range in air: 610 cm = 240 inches = 20 feet
• Maximum range in water/tissue: 0.76 cm = 1/3 inch
• Maximum range in Plexiglas/lucite/plastic: 0.61 cm = 3/8 inch
• Half-Value Layer (HVL): 2.00 mm (water/tissue)
4.6.1.2 Radiological Data
• Critical organ (biological destination) (soluble forms): Bone
• Critical organs (insoluble forms or non-transportable 32
P compounds): Lung
(inhalation) and G.I. tract/lower large intestine (ingestion)
• Routes of intake: Ingestion, inhalation, puncture, wound, skin contamination
(absorption)
• External and internal exposure from 32
P
• Committed Dose Equivalent (CDE): 32 mrem/uCi (ingested)
(Organ Doses) 37 mrem/uCi (puncture)
96 mrem/uCi (inhaled/Class W/lungs)
22 mrem/uCi (inhaled/Class D/bone
marrow)
• Committed Effective Dose Equivalent (CEDE): 7.50 mrem/uCi
(ingested/WB)
5.55 mrem/uCi (inhale/Class D)
13.22 mrem/uCi (inhale/Class W)
• Skin contamination dose rate: 8700-9170 mrem/uCi/cm 2 /hr. (7 mg/cm 2 or
0.007 cm depth in tissue).
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• Dose rate to basal cells from skin contamination of 1.0 uCi/cm 2 (localized
dose) = 9200 mrad/hr.
• Bone receives approximately 20% of the dose ingested or inhaled for soluble 32
P compounds.
• Tissues with rapid cellular turnover rates show higher retention due to
concentration of phosphorous in the nucleoproteins.
• 32
P is eliminated from the body primarily via urine.
• Phosphorus metabolism; see 33
P Fact Sheet.
4.6.1.3 Shielding
• 3/8 inch thick Plexiglas/acrylic/lucite/plastic/wood.
• Do not use lead foil or sheets! Penetrating Bremsstrahlung x-ray will be
produced!
• Use lead sheets or foil to shield Bremsstrahlung x-rays only after low density
Plexiglas/acrylic/lucite/wood shielding.
4.6.1.4 Survey Instrumentation
• GM survey meter and a pancake probe.
• Low-energy NaI probe is used only to detect Bremsstrahlung x-rays.
• Liquid scintillation counter (indirect counting) may be used to detect
removable surface contamination of 32
P on smears or wipes.
4.6.1.5 Dose Rates (from unshielded 1.0 mCi isotropic point source)
Distance Rads/hr
1.00 cm 348
15.24 cm 1.49
10.00 ft 0.0015
• 78,000 mrad/hr at surface of 1.0 mCi 32
P in 1 ml liquid.
• 26,000 mrad/hr at mouth of open vial containing 1.0 mCi 32
P in 1.0 ml liquid.
4.6.1.6 General Precautions
• Because it is a bone seeker, special precautions must be taken to minimize any
chance of introducing into the body.
• Airborne contamination can be generated through drying (dust), rapid boiling,
or expelling solutions through syringe needles and pipette tips, due to
aerosols.
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• Personnel radiation monitors (whole body and finger rings) are required when
handling > 1.0 mCi of 32
P at any time.
• Never work directly over an open container; avoid direct eye exposure from
penetrating 32
P beta particles.
• Always wear a lab coat and disposable gloves when handling 32
P.
• Monitor personnel work areas and floors using a GM survey meter equipped
with a pancake (beta) probe for surface contamination.
• Monitor for removable surface contamination by smearing or wiping where 32
P is used.
• Use low-density (low atomic number) shielding material to shield 32
P and
reduce the generation of Bremsstrahlung x-rays. The following materials are
low atomic number materials: Plexiglas, acrylic, lucite, plastic, wood, or
water.
• Do NOT use lead foil, lead sheets, or other high density materials (metals) to
shield 32
P directly. Materials with atomic number higher than that of
aluminum (Z = 13) should NOT be used. Penetrating Bremsstrahlung x-rays
will be generated in lead and other high density shielding material.
• Safety glasses or goggles are recommended when working with 32
P.
• Typical GM survey meter with pancake probe efficiency is ³45%. Typical
liquid scintillation counter counting efficiency for 32
P (full
window/maximum) > 85%.
• Typical detection limit of 32
P in urine specimens using a liquid scintillation
counter = 1.1 E -7 uCi/ml.
4.6.2. Phosphorus – 33 (33P)
4.6.2.1 Physical Data
• Beta energy: 0.249 MeV (maximum, 100% abundance)
0.085 MeV (average)
• Physical half-life: 25.4 days
• Biological half-life: 19 days (40% of intake; 30% rapidly
eliminated from body, remaining 30%
decays)
• Effective half-life: 24.9 days (bone)
• Specific activity: 1,000 - 3,000 Ci/millimole
• Maximum beta range in air: 89 cm = 35 inches = 3 feet
• Maximum range in water/tissue: 0.11 cm = 0.04 inch
• Maximum range in plexiglas/lucite/plastic: 0.089 cm = 0.035 inch
• Half-Value Layer (HVL): 0.30 mm (water/tissue)
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4.6.2.2 Radiological Data
• Critical organ (biological destination) (soluble forms): Bone marrow
• Critical organs (insoluble forms or non-transportable 33P compounds): Lung
(inhalation) and G.I. tract/Lower large intestine (ingestion)
• Routes of intake: Ingestion, inhalation, puncture, wound, skin contamination
(absorption)
• Internal exposure and contamination are the primary radiological concerns
• Committed Dose Equivalent (CDE): 0.5 mrem/mCi (inhalation)
• Skin contamination dose rate: 2,910 mrem/hr/uCi/cm 2 (7 mg/cm 2 or 0.007
cm depth in tissue)
• Fraction of 33P beta particles transmitted through the dead skin layer is about
14%.
• Tissues with rapid cellular turnover rates show higher retention due to
concentration of phosphorus in the nucleoproteins.
• 33P is eliminated from the body primarily via urine.
• Phosphorus metabolism: 30% is rapidly eliminated from body
40% has a 19-day biological half-life
60% of 33P (ingested) is excreted from body in first 24 hrs
4.6.2.3 Shielding
• Not required; however low density material is recommended, e.g., 3/8 inch
thick plexiglas, acrylic, lucite, plastic or plywood.
4.6.2.4 Survey Instrumentation
• GM survey meter with a pancake probe.
• Liquid scintillation counting of wipes may be used to detect removable
surface contamination.
4.6.2.5 Personnel Dosimeters
• Are not required, since they do not detect this low energy nuclide.
4.6.2.6 General Precautions
• Inherent volatility (STP): Insignificant
• Skin dose and contamination are the primary concerns.
• Drying can form airborne 33P contamination.
• Monitor work areas for contamination, using smears or wipes to check for
removable contamination.
4.6.3. Carbon – 14 (14C)
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4.6.3.1 Physical Data
• Beta Energy: 156 keV (maximum)
� 49 keV (average) (100% abundance)
• Physical Half-Life: 5730 years
• Biological Half-Life: 12 days
• Effective Half-Life: 12 days (bound)
• Effective Half-Life: 40 days (unbound)
• Specific Activity: 4460 mCi/gram
• Maximum Beta Range in Air: 24.00 cm = 10 inches
• Maximum Beta Range in Water/Tissue: *0.28 mm = 0.012 inches
• Maximum Range in Plexiglas/Lucite/Plastic: 0.25 mm = 0.010 inches
*Fraction of 14C beta particles transmitted through dead layer of skin: At 0.007 cm
depth = 1%
4.6.3.2 Radiological Data
• Critical Organ: Fat Tissue
• Routes of Intake: Ingestion, Inhalation, Skin Contact
• External exposure: Deep dose from weak 14C beta particles is not a
radiological concern
• Internal exposure & contamination: Primary radiological concerns
• Committed Dose Equivalent (CDE): 2.08 mrem/uCi (ingested)
(Fat Tissue) 2.07 mrem/uCi (puncture)
2.09 mrem/uCi (inhalation)
• Committed Effective Dose Equivalent (CEDE): 1.54 mrem/uCi (ingested)
• Annual Limit on Intake (ALI)*: 2 mCi (ingestion of labeled organic
compound)
2000 mCi (inhalation of carbon monoxide)
200 mCi (inhalation of carbon dioxide)
*[1.0 ALI = 2 mCi (ingested C-14 organic compound) = 5,000 mrem CEDE]
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• Skin Contamination Dose Rate: 1090-1180 mrem per 1.0 uCi/cm 2 (7 mg/cm
2 depth)
• Dose Rate to Basal Cells from Skin Contamination, 1.0 uCi/cm 2 = 1400
mrad/hour.
• Immersion in 14C Contaminated Air = 2.183E7 mrem/year per uCi/cm 3 at 70
um depth of tissue and 4.07E6 mrem/year per uCi/cm 3 value averaged over
dermis.
4.6.3.3 Shielding
• None required ( ≤ 3 mm Plexiglas)
4.6.3.4 Survey Instrumentation
• Can detect 14C using a thin-window G-M survey meter; survey meter probe
must be at close range (1 cm.)
• G-M survey meters have very low counting efficiency for 14C (5%).
• Liquid scintillation counter (indirect counting) may be used to detect
removable 14C on wipes.
4.6.4. Hydrogen – 3 (3H)
4.6.4.1 Physical Data
• Beta Energy: 18.6 keV (maximum)
5.7 keV (average) (100% abundance)
• Physical Half-Life: 12.3 years
• Biological Half-Life: 10 - 12 days
• Effective Half-Life: 10 - 12 days *
* Forcing liquids to tolerance (3-4 liters/day) will reduce the effective half-life of 3 H
by a factor of 2 or 3. (Relatively easy to flush out of system with fluids.)
• Specific Activity: 9640 Ci/gram
• Maximum Beta Range in Air: 6 mm = 0.6 cm = 1/4"
• Maximum Beta Range in Water: 0.006 mm = 0.0006 cm = 3/10,000"
• Penetrability in Matter or Tissue: Insignificant*
*[0% of beta particle energy transmitted through dead layer of skin]
4.6.4.2 Radiological Data
• Least radiotoxic of all radionuclides
• Critical Organ: Body Water or Tissue
• Routes of Intake: Ingestion, Inhalation, Puncture, Wound, Skin Contamination
(Absorption)
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• External exposure from weak 3H beta energy - not a radiological concern
• Internal exposure & contamination are primary radiological concerns
• Committed Dose Equivalent (CDE): 64 mrem/mCi (ingested)
64 mrem/mCi (inhaled)
64 mrem/mCi (puncture)
• Committed Effective Dose Equivalent (CEDE): 90 mrem/mCi (ingested)
63 mrem/mCi (inhaled)
• Annual Limit on Intake (ALI)*: 80 mCi (ingestion or inhalation) [3H2O]
* [1.0 ALI = 80 mCi (3H) = 5,000 mrem CEDE]
• Skin Contamination Exposure Rate: 57,900 mrad/hr/mCi (contact)*
* Exposure rate to dead layer of skin only
* Skin contamination of 1.0 uCi/cm2 = 0 mrad/hr dose rate to basal
cells
• Rule of Thumb: 0.001 uCi/ml of 3H in urine sample is indicative of a total
integrated whole body dose of approximately 10 mrem (average person) if no
treatment is instituted (i.e., flush with fluids) [NCRP-65, 1980]
4.6.4.3 Shielding
• None required
4.6.4.4 Survey Instrumentation
• Cannot detect 3H using a G-M or NaI survey meter
• Liquid scintillation counter (indirect) is the only monitoring method
4.6.4.5 Radiation Monitoring Dosimeters
• Whole Body Badge or Finger Rings: Not needed (beta energy too low)
4.7. Exposure Limits for Workers and the General Public
4.7.1 Occupational Dose Limits
Each licensee shall ensure that the occupational exposure of any radiation worker under
his license shall be so controlled that the following limits will not be exceeded:
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4.7.1.1. An effective dose of 20 mSv per year averaged over five consecutive
years;
4.7.1.2. An effective dose of 50 mSv in any single year;
4.7.1.3. An equivalent dose to the lens of the eye of 150 mSv in a year; and
4.7.1.4. An equivalent dose to the extremities (hands and feet) or the skin of 500
mSv in a year.
4.7.2. Dose Limits for Apprentices, Trainees and Students
No person under the age of 16 years shall be subjected to occupational exposure.
No person under the age of 18 years shall be allowed to work in a controlled area unless
supervised and only for training purposes.
For apprentices that are 16 to 18 years of age who are training for employment involving
exposure to radiation, and for students of age 16 to 18 who are required to use radioactive
sources in the course of their studies, the occupational exposure shall be controlled so
that the following limits are not exceeded:
4.7.2.1. An effective dose of 6 mSv in a year;
4.7.2.2. An equivalent dose to the lens of the eye of 50 mSv in a year; and
4.7.2.3. An equivalent dose to the extremities or the skin of 150 mSv in a year.
4.7.3. Dose Limits for Members of the Public.
Each licensee shall ensure that the estimated average dose to any member of the public
does not exceed the following dose limits:
4.7.3.1. An effective dose of 1 mSv in a year;
4.7.3.2. 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;
4.7.3.3. An equivalent dose to the lens of the eye of 15 mSv in a year; and
4.7.3.4. Equivalent dose to the skin of 50 mSv in a year.
4.7.4 Dose Limits for Pregnant Radiation Workers.
A female worker should notify the Principal Investigator about her pregnancy in order
that her working conditions maybe modified, if necessary. Modification to working
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conditions with respect to occupational exposure should ensure that the embryo or fetus
is afforded the same broad level of protection as required for members of the public.
Every reasonable effort should be made to avoid substantial variation above a uniform
monthly exposure rate to a declared pregnant worker so as not to exceed 1 mSv in a
year.
5. RADIOISOTOPE LABORATORY MANAGEMENT
5.1. Radiation Facilities
At IRRI, licensed activity is authorized only in the Radioisotope Laboratory (RL) - Analytical
Service Laboratories 3rd
Floor, Kenzo Hemmi Building.
5.1 General Lab Safety Rules
5.2.1 Personal belongings, including books (except those required for work) should not
be brought into a laboratory where they may become contaminated.
5.2.2 Eating, drinking, storing, or preparing food, smoking or applying cosmetics are
forbidden in any area where radioactive materials are stored or used.
5.2.3 Direct contact with radioactive materials must be avoided by using protective
laboratory coats and by wearing rubber or disposable plastic gloves. Special care
should be taken when breaks on the skin of the hands are present. Such protective
clothing should not be removed from the laboratory.
5.2.4 Pipetting liquids by mouth or performance of any similar operation by mouth
suction is not permitted.
5.2.5 Complete records of receipts, transfers, and disposal of radioactive materials
should be kept.
5.2.6 A film badge should be worn at all times when working with radioactivity, except
for the case of 3H, 14C, or other low energy β-emitters.
5.2.7 Work should be carried out under a hood in all cases where radioactive material
maybe lost by volatilization, dispersion or dust, or by spraying or splattering.
Wherever possible, work with closed containers.
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5.2.8 All radioactive samples should be properly labeled with the isotope and activity
indicated and should be covered.
5.2.9 Liquid waste should not be poured into the drain or contaminated apparatus
washed in the sink unless the levels of activity entering the sewer system have
been calculated as permissible.
5.2.10 Solid waste and contaminated articles (corks, paper wipes, and the like) should be
disposed of in designated containers and should never be placed in ordinary trash
receptacles.
5.2.11 The disposal of gaseous wastes through the hood can be carried out only after
careful examination of the air dilution factor.
5.2.12 The storage of all radioactive material must be in properly designated locations.
5.2.13 At the close of a working period, the laboratory work surfaces should be carefully
monitored and readings recorded.
5.2.14 Before leaving the laboratory after working with active materials, each person
should wash his hands thoroughly and check them with monitoring instrument.
5.2.15 All laboratory glassware and equipment used in the Radioisotope Laboratory
should be properly decontaminated after use and may be returned to the general
usage only with the approval of the Researcher in charge.
5.2.16 It is desirable to decontaminate one’s hands and work surface completely, but the
following arbitrary surface contamination tolerances (as measured by a G-M
survey meter with a thin window) may be allowed after efforts at
decontamination.
Hands 350 cpm
Working surface 250 cpm
5.2.17 All spills of radioactive materials must be reported to RSO, Assistant RSO or
Researcher in charge immediately. In the event of a spill,
• Any liquid should be blotted out immediately.
• Attempts should be made to prevent spreading of the activity.
• The spill area should be isolated, identified as to the nature of the
contaminant, and access to the area restricted.
• A contamination survey of the area and all involved personnel should be made
immediately.
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5.2.18 If a wound is contaminated with radioactive material, do the following
procedures:
• Flush wound in running water.
• Immediately seek the aid of the person responsible for radiation safety (RSO
or ARSO).
5.2.19 Routine urine analyses should be carried out by means of liquid scintillation
counting whenever millicurie levels of carbon or tritium are handled. Records of
analyses should be kept.
5.2 Area Restrictions
5.3.1 Controlled Areas - areas wherein workers could receive total exposures of ≥ ≥ ≥ ≥ 3/10
of the annual equivalent dose limits
a) “High Radiation Area” sign is posted within the Controlled Area where a
body could receive an equivalent dose in excess of 1 mSv in one hour at 30
cm from any radiation source.
b) Entry is limited to Authorized Staff provided with individual film badges
and only with supervision of Person in charge of the Controlled Area.
5.3.2 Supervised Areas – areas where annual radiation level exposure is most unlikely to
exceed 3/10 but may exceed 1/10 of the equivalent dose limits
a) “Caution : Radiation Area” sign is posted on the door or entrance of the
Supervised Area
b) Entry is limited to Authorized personnel but does not require wearing of
monitoring device (film badge) but with prior knowledge and permission of
Person in charge of the Supervised Area
5.3 Radiation Survey Monitoring Procedure
5.4.1 Area monitoring should be done before, during and after any work in a specific work
area. Area monitoring of radiation facilities is done regularly every three months.
5.4.2 Use a suitable, appropriate, and calibrated survey meter.
5.4.3 Use a form with the drawing of the layout of the radiation facility indicating probable
"hot areas" and fixed points for monitoring. The layout would include adjacent area
specifically those occupied or frequented by people.
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5.4.4 Establish the background radiation level.
5.4.5 Hold the survey meter with the detector at waist level and start from the entrance of
the facility going around the work areas and the designated fixed points. Take
readings of the adjacent areas.
5.4.6 Take a "smear or swab" samples of spots or area where there are registered "high
readings".
5.4.7 Record all readings (measured dose rates in mR/hr or contamination levels in
dpm/100 sq cm, as appropriate).
5.4.8 Compile and maintain records of area monitoring. Include the date, area surveys,
equipment used, name or initials of the person who made the survey. Action taken in
the case of excessive dose rates or contamination and follow up survey information.
5.4.9 Immediately notify the RSO if you find unexpectedly high levels.
5.4.10 The RSO will make periodic checks on the findings of these surveys by individual
users and conduct additional surveys when indicated by an increasing or high level of
activity. The RSO will also be responsible for air sampling and wipe tests when
indicated.
5.4 Decontamination Procedure
5.5.1 Personnel Decontamination
Personnel contamination usually occurs on the skin of the hands, face, hair and in some
cases in wounds inflicted during the accident. As have been pointed out, the life and
safety of the person is first and foremost in dealing with the decontamination. Hence,
when there is an open wound, bleeding should be induced or encouraged while washing
with mild soap under a steady flow of tap water. If the wound is large enough, the
medical unit should be immediately called to take care of the personnel.
If there are no wounds and only the skin is contaminated, scrub the skin with mild soap
with the use of soft brush or bristle under a steady flow of tap water 2 to 3 times. Ensure
that the ridges between the finders and hand and the inside of the nails are brushed off to
remove any contaminant. Dry skin with absorbent material and apply soft cream or
talcum powder.
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If the face has been contaminated with “splatters” of the radioactive material, rinse the
face with mild soap allowing the formation of lather. Isolated spots of contaminated skin
should be scrubbed. Rinse under a steady flow of tap water. While rinsing the face, be
sure that the eyes and mouth of the personnel are closed to prevent the ingestion of the
radioactive material. Wipe the face with soft tissue but avoid rubbing and apply soft
cream or talcum powder.
Contaminated hair should be washed several times with efficient shampoo or mild soap
under the steady flow of tap water. While the rinsing is going on, close the ears, nose, or
eyes. Dry the hair by rubbing briskly with paper towels or other absorbent materials.
5.5.2 Area or surface decontamination
Before implementing the decontamination procedures, ensure that the contaminated area
is properly identified, marked, and barricaded. The contamination should be identified as
to loose or fixed contamination.
Removal of loose contamination maybe accomplished with special vacuum cleaners
fitted with special filters. In case of slight contamination on the floor, apply a wet
medium such as damped sawdust sprinkled over the contaminated area. Allow a certain
period of time for the contaminants to be absorbed and then collect the sawdust with a
brush and closed dustpan. Continue by swabbing with soap or detergent and water. Be
sure that all materials used are collected, monitored, segregated and stored as radioactive
waste. Provide clearance of the area when the contamination levels have been reduced to
permissible levels.
For very persistent loose contamination, apply a suitable strippable lacquer on the
contaminated surface. Allow the lacquer to dry up and then removed. The contaminant
will adhere to the lacquer when stripped.
Removal of fixed contamination maybe accomplished only by wet decontamination
method. The use of suitable detergent solutions is the first step. Afterwards, use soap
and water with constant swabbing or mopping. Dry the area with adequate amount of
absorbent materials. All washing, swabs and absorbent materials used in the procedure
should be collected as radioactive wastes.
Stubborn contamination left after these procedures can be removed by further washings
with suitable decontaminating chemical reagent containing complexing agent that will
prevent the re-deposition of the contaminating radionuclide. The decontaminating
solution should remain in contact with the contaminated surface for as long as possible to
allow the chemical reactions to take place.
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*If the fixed contamination persists, it might be necessary to physically remove the
contaminated surface. However, if left in situ, precautions should be taken by sealing the
contaminated surface with concrete, paint or other appropriate material and the area
declared off-limits for use. The specific location of the sealed-in contamination should
be properly identified and recorded so that in future modifications of the radiation
facility, proper precautions can be taken against dispersing the contamination and
creating radiation hazards.
5.5.3 Equipment Decontamination
The three ways of dealing with contaminated equipment and laboratory tools are:
a) Removal of the contamination without damaging the surface of the equipment
or the equipment itself
b) Removal of the contaminated surface or the part of the equipment with
retained contamination.
c) Discarding totally the equipment
Contaminated equipment should be removed from the area and placed in a designated
contamination area. The contaminated surface should be washed with water taking care
that the washings are collected as wastes. Avoid the seepage of the water into the inner
section of the equipment. Persistent contamination should be treated with strong
reagents, acids, or abrasives.
Some equipment for reasons of economy could be spared, dispensed with or discarded as
radioactive wastes if the implementation of the decontamination procedures would be
very expensive compared to buying a new one.
5.5.4 Clothing Decontamination
All protective clothing such as gowns, coveralls, cloth caps, etc. should be monitored
after the radiation work to determine any contamination that may be present.
Contaminated clothing should be segregated from the clean ones to avoid cross-
contamination. Contaminated clothing should be collected and stored in specific bins.
In doing decontamination procedures for protective clothing, choices have to be made
considering economic factors. If there is a surplus of protective clothing, discarding
contaminated clothing might be more economical than subject each one to
decontamination procedures. If, however, decontamination procedures have to be
implemented, the following procedures should be applied:
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a) Monitor the presence and extent of contamination.
b) Prepare a strong mixture of detergent soap.
c) Soak the contaminated clothing in the soap and water mixture overnight.
d) Wash the clothing and collect the soap mixture.
e) Repeat the laundry washings until the contamination shall have been removed.
f) Monitor and clear the clothing for re-use.
5.5 Decommissioning
5.6.1 Vacating/TransferingLaboratory Spaces
The RSO must be informed of all changes in authorized laboratory spaces, including
transfers or laboratory relocations. The Principal Investigator, through his Authorized
Staff, is responsible for surveying all spaces and equipment and proper disposal of all
radioactive waste and transfer of unspent radioactive sources to the RSO prior to the
changes.
Wipe tests should be performed to survey and document possible removable
contamination levels. The area of interest is wiped with a filter paper disk and the activity
is measured in a counter calibrated for the suspected radionuclide. Area or surface
decontamination (see section on Decontamination) should be done if significant levels of
contamination are found.
5.6.2 Transfer or Removal of Laboratory Equipment
Any equipment in the laboratory which could have been contaminated with radioactive
material must also be surveyed before removal to another laboratory, transfer to a repair
shop, or transfer to Property Disposal. Before the equipment is transferred and following
a satisfactory survey, all warning signs and stickers must be removed. Only the RSO may
remove radiation warning signs.
5.6.3 Survey Report
A Decommissioning Report must be submitted to the RSO, who will complete the final
clearance of the authorized laboratory spaces and/or equipment and make the necessary
application for amendment of the PNRI license. It should include the following items as
part of the survey record.
a) Diagram of area surveyed
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b) List of items and equipment surveyed
c) Specific locations where wipe tests were taken
d) Ambient radiation levels with appropriate units (mrem/hr)
e) Contamination levels found with appropriate results (dpm/100 cm. sq.)
f) Make and model number of survey instrument used
g) Background levels (mrem/hr)
h) Name of the person making the survey and recording the results, and date
6. RADIOACTIVE MATERIALS (RAM) MANAGEMENT
6.1. Guidelines for Ordering and Receiving Radioactive chemicals/Instruments
with sealed sources
All radioactive materials (RAM) at IRRI should be listed in the license issued by PNRI for
IRRI. The list specifies both the kind of radionuclide and the maximum activity allowed for
each kind. Additional materials have to be cleared with the PNRI through the RSO.
The RAMs used at IRRI fall under two categories: Chemicals with radioactive label (Open
Sources), and Equipment with sealed radioactive source (Sealed Sources)
The following guidelines should be observed when ordering a radioactive chemical or an
equipment with a radioactive source, and picking-up, transporting and opening the package.
containing a radioactive material.
6.1.1 Procedure for Centralized Ordering of RAM at IRRI
The RSO shall provide the IRRI Purchasing Office with a photocopy of the license. This
should be sent to the supplier together with the corresponding purchase order.
a) Only authorized user will apply for RAM Request to the RSO and once
approved, the RSO will make online PR of RAM using the PI’s budget
code. This will ensure proper control and monitoring of the amount of
RAM ordered as per specified in our RAM License.
b) RAM Request must contain the ff. and upon completion must be sent to
the RSO by e-mail.
• Type of radioactive material (nuclide)
• Chemical form
• Physical form
• Supplier
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• Catalog number
• Activity / Activity Date (when purchased)
• Calculated Current Activity (based on Half-life of nuclide)
• Organizational Unit / Authorized Staff Responsible
• Purpose or intended use
• Principal Investigator’s Budget Code
c) PMMS Purchaser must notify supplier to provide a 2-day advanced notice
(by e-mail) for each RAM delivery to [email protected] with cc to
[email protected] and [email protected] to allow sufficient time
for staff scheduling and preparation at Radioisotope Lab (RL).
d) Supplier will deliver the package to RL and receipt will be done by RL
staff (RManuel) or the RSO. Delivery & receipt of RAM will be done at
RL located at the 3rd floor of KHemmi Building from Monday to
Thursday from 1-3 pm only to allow RManuel to do the necessary package
inspection and contamination test of RAM.
e) Authorized users may order only those radioisotopes listed on their permit,
and in activities not greater than that listed.
f) Authorized user will be informed of the availability of his/her package by
RManuel once it is approved for release by the RSO. RAM package will
be stored at RL.
6.1.2 Picking up and receiving the package.
a) To facilitate the pick-up and receipt of a RAM package, the shipper should be
required to notify the consignee of the
• Date of shipment,
• Expected arrival and
• Any special loading/unloading instructions
b) The Materials Management Services Senior Manager shall designate a person
(and preferably, an alternate) from the Shipping Unit to be responsible for
picking up the package containing the radioactive material, transporting it to
IRRI and delivering it to ASL-RL without delay. The IRRI RSO shall arrange
for training of the designated person/s on the properties and hazards of
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radioactive materials, regulations pertinent to transportation of radioactive
materials, and emergency procedures.
c) Upon receipt of the Airway bill of a shipment, the Shipping representative
should arrange to pick up the package expeditiously and shall obtain the
following from RSO before processing to claim the RAM package:
• Information on the RAM
• A copy of the license
• Certificate of Transport
• An appropriate survey meter
d) Shipments of radioactive chemicals for IRRI research purposes usually just
exceed the exempt quantities, i.e. they fall in the lower range of Type A
quantities. Such packages should be monitored for radioactive contamination
caused by possible leakage of the contents. Dose rate reading should be
within the limits shown in Table 2.
Table 2. Dose Rate Limits for Type A RAM Packages (mrem/hr)
Package Label At surface of Package At 1 m from external
surface of package
Radioactive White (Fig. 1) 0.5 0
Radioactive-Yellow II (Fig. 2) 50 1.0
e) However, monitoring of the external surfaces may NOT be necessary for
packages containing:
• 3.7 MBq or less of P-32
• 0.37 MBq or less of C-14
• 0.37 MBq or less of S-35
f) Instruments of which radioactive material is a non-readily dispensable
form is a component part, usually come securely packed in their own
transport case. The transport case is physically and legally suitable for
transporting the instrument by road or air and conforms with Type A
specification, i.e., the package is such that the radiation dose-rate at any
time during transport does not exceed the limits given. Examples of such
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instruments are moisture and density probes, and gas chromatographs with
Ni-63 containing electron capture detector.
g) With the permission of the Customs Inspector, the Shipping representative
shall subject the package to ocular inspection for any damage in transit or
for evidence of tampering of the seal and shall monitor the external
surfaces of the package. If damage is evident or if the seal is broken, the
broker shall be requested to notify immediately the final delivering carrier
who should take steps to investigate the matter. Evidence of damage to
the package or dose rate readings that are significantly higher than the
above limits shall be cause for refusal to accept the shipment from the
broker. The broker shall request instruction from the supplier regarding
disposal or shipping back of the package. A bad order report must be
submitted by the Shipping representative to the Materials Management
Services Senior Manager with copy to the RSO who shall inform the end
user.
h) If radioactive materials have leaked or have been spilled or otherwise
dispersed in any conveyance, building, area or equipment used for
transport or storage, qualified persons shall be called in to direct the
decontamination work as soon as possible. Such conveyance, building,
area or equipment shall not be put into service until declared safe for use.
i) In the event of a shipment of RAM suffering breakage or leakage, or
becoming involved in a crash, wreck or fire, the affected area shall be
isolated to prevent all contact of persons with any loose radioactive
material and, when practicable, posting or fencing shall be provided. No
persons shall be allowed to remain within the isolated area until qualified
persons are available to check radiation hazards and supervise the
handling or salvage. The IRRI RSO and the Philippine Nuclear Research
Institute (Tel. No. 929 6010 to 19) must be notified immediately. Rescue
operations or fighting of fire by qualified persons should not be barred.
Any person who may have become contaminated with radioactive
materials shall be subject to appropriate control and examination
measures.
6.1.3 Transporting the package to IRRI
As soon as the Shipping representative is satisfied that the RAM package is in good
condition, he should bring the package to IRRI via the most direct route and under no
circumstance leave it unattended in an unlocked vehicle. The package should then be
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received at ASL-RL without delay. The transport vehicle has to be checked for
contamination and decontaminated, if necessary, with the help of the end user before it is
used for other trips.
6.1.4. Protocol for Receiving Open Sources RAM package at RL
a) Package arrives at ASL-RL for inspection.
b) RSO representative (RManuel) stores package to the lab.
c) Before inspection- put on gloves.
d) Inspect PO and package for any incorrect information and box damage.
e) Take wipe test of outer surface and analyze in the LSC.
f) Action limit for outer surface wipe test: 2200 dpm/100cm2
g) Take exposure rate reading on outer surface.
h) Action limit for pancake surface survey: 200 mR/hr.
i) Record results in log book.
j) Call Supervisor and RSO immediately if action limit is exceeded.
For P-32 packages – no wipe test is needed, surface survey is suitable.
a) Record package surface survey in mR/hr.
b) Packages must be secured from unauthorized removal when not under your
direct surveillance.
c) Authorized user will be informed of the availability of his/her package by
Rufino Manuel once it is approved for release by the RSO.
6.1.5 Opening the package
The RAM package shall be received from the RL staff and opened only by a licensed
user. The user shall check the package and shall take does rate readings on the external
surfaces and at 1 m from the package. If the readings are higher than the limits cited
above, the user should determine the presence of removable contamination on the surface
by swipe or smear test. The permissible levels of surface contamination for a 300 cm2
area are:
a) 0.04 Bq/cm2 for the alpha emitters, and
b) 0.4 Bq/cm2 for beta and gamma emitter.
If the amount of removable contamination exceeds the permissible levels, the package
shall be placed on a tray and the tray placed in a storage area with appropriate shielding
and the matter immediately reported to the RSO who shall implement necessary actions.
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It the contamination is within permissible levels, the package shall be opened with due
consideration given to special instructions provided by the manufacturer. After opening
of the package, the dose rate monitoring shall be done on the container before it is stored.
A record of the dose-rate readings and the results of the swipe or wipe tests shall be
submitted to the RSO and shall form part of the records of the IRRI RIL.
6.2. Labeling Requirements
Labeling equipment and lab supplies is the responsibility of the Authorized User. A copy
of the Radiation Safety Manual must be readily available. All doors accessing areas that
contain radioactive materials must be posted. All refrigerators, freezers and other
equipment which contains radioactive materials must be labeled with "Caution:
Radioactive Material" signs or tape.
Any unattended container of radioactive material, such as beakers or flasks, must be
labeled. A rack of radioactive test tubes should be labeled, but not necessarily each test
tube. Common sense should prevail. Labeling prevents someone from unknowingly
disturbing the materials or getting unnecessary exposure from them.
6.3. RAM Storage Procedure
6.3.1. All radioactive materials obtained or purchased, are stored at the Radioactive
Materials Storage Room of the Radioisotope laboratory of the Analytical Service
Laboratory (ASL).
6.3.2. Soft beta emitters should be stored in physically secure, leak-proof containers of
glass or plastic sufficiently thick to reduce radiation levels at the surface of the
container to 2.0 Mr/hr or less.
6.3.3. Appropriate warning signs using the standards radiation symbol are displayed
conspicuously in all areas where radionuclides are stored and/or used.
6.3.4. All containers should be appropriately labeled with the following information
a) Owner’s name
b) Division
c) Type of radionuclide
d) Chemical form
e) Quantity
f) Activity
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g) Activity Date
h) Date received
6.3.5. List of radioactive materials received shall be submitted to the RSO for update of
inventory with PNRI.
6.3.6. All neutron probe units are kept at a common storage room of the ASL. “Rules for
Issuance and Return of Neutron Probe and Gamma Meters” and “Guideline on the
Handling of Neutron Probe” are attached
6.4. Transport of Radioactive Materials
6.4.1. Within IRRI
When transporting radioactive materials between rooms or buildings, precautions must be
taken to minimize the risk of accidents and the risk of exposing the public to radiation.
Secondary containers should be used to avoid breakage of the primary container and
absorbent material to retain the isotope in case of breakage. Appropriate shielding should
also be provided.
Transporting may involve walking or driving the radioactive material to another building.
In either case, the RSO must be notified of the following information:
a) Type of radioisotope(s) being moved
b) Chemical form of the isotope
c) Total activity in MBq / Activity Date
d) Number of containers
e) Date of move
f) Names of persons sending and receiving the material
g) Sending and receiving locations (only where licensed activity is authorized)
h) Any special conditions
6.4.2. External
Transport of radioactive materials outside the confines of the institute is regulated by the
Code of PNRI Regulations (CPR Part 4), “Rules and Regulations for the Safe Transport
of Radioactive Materials” (See Appendix 4. for details on CPR Part 4)
6.5. Inventory and Security
PNRI requires that all licensees maintain records tracking the receipt, use and disposal of
radioactive materials. This is done with an inventory maintained in a database by the RSO for
IRRI. Important information included in the database are:
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6.5.1. Open Sources
a) Type of radioactive material (nuclide)
b) Chemical form
c) Physical form
d) Supplier
e) Activity / Activity Date (when purchased)
f) Calculated Current Activity (based on Half-life of nuclide)
g) Organizational Unit / Authorized Staff Responsible
h) Purpose or Intended Use
i) Authorized Location of Use or Storage
6.5.2. For Sealed Sources or Equipment containing sealed sources,
a) Type of radioactive material (nuclide)
b) Manufacturer / Serial No. / Model No.
c) Quantity (Number of units)
d) Activity / Activity Date (when purchased)
e) Calculated Current Activity (based on Half-life of nuclide)
f) Type of Equipment / Model
g) Organizational Unit / Authorized Staff Responsible
h) Purpose or Intended Use
i) Authorized Location of Use or Storage
Before the annual renewal of license in January, electronic (MicroSoft Excel) files will be
sent by the RSO to the Organizational Unit Heads and/or Principal Investigators for
verification. The information must be updated and necessary corrections made. This
information is a legal record subject to inspection by PNRI. Efforts must be made to keep
records as accurate and complete as possible to prevent violations.
Licensed material must be under the immediate control and constant surveillance of the
Principal Investigator or his designated Authorized Staff, or otherwise be locked and
secured to prevent tampering or unauthorized removal. When working with radioactive
materials, the room must be secured whenever a radiation worker is not present, or the
radioactive materials must themselves be secured. Refrigerators or cabinets containing
radioactive materials must be locked to prevent unauthorized access or should be located
inside a lockable room. Logbooks are required in laboratories for the use of radioisotopes.
The log should contain records of amounts used, who used them and dates of use for each
shipment received. Any loss of radioactive materials must be reported to the RSO
immediately.
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Likewise, the responsibility for radioactive sealed source containing equipment lies with
the Principal Investigator or his designated staff in-charge of the equipment. A logbook for
each equipment is required and should include records of use, repairs, changes,
maintenance, and leak tests in particular. The source holder must be labeled with the
radiation symbol. Any change in location or status of the equipment must be reported to
the RSO. Prior to disposal of equipment, the radioactive sealed source must be removed
and transferred to the RSO for disposal to PNRI or returned to the supplier or
manufacturer.
Each sealed source containing more than 3.7 MBq of beta and gamma emitters or 370 kBq
of alpha emitters with a half-life greater than 30 days shall be tested for contamination
and/or leakage at intervals not exceed six (6) months. Records of test results shall be kept
in units of becquerels and maintained for six (6) months after the next required leak test is
performed or until the sealed sources are transferred and disposed of. Sources that are
being stored or that have not been used for more than a year must be leak tested before
being returned to service.
It is the principal investigator's responsibility to assure that the sources are used according
to the laws and regulations pertaining to the source. In particular, the leak tests must be
performed by the required deadline. If non-compliance is found with sealed sources,
sanctions may be imposed.
6.6. Transfer
Transfer of radioactive material between investigators of different projects must be
reported by email to the RSO prior to the transfer. These transfers must be between
authorized Principal Investigators, and within the limits of the approved quantities. The
transfer should not take place until the authorization to do so have been given by the RSO,
who documents the transfer in the inventory database.
Likewise, the Principal Investigator or his designated staff who is in-charge of any
equipment containing a radioactive sealed source is responsible for notifying the RSO prior
to transfer of the equipment to another project or division.
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7. PERSONNEL MONITORING PROGRAM
7.1. Schedule
Radiation monitoring devices (film badges) must be worn routinely by personnel while
working with radioactive materials. Films badges are exchanged every two (2) months. New
ones will be issued to Authorized Staff, before the collection of the used badges for
evaluation at PNRI. Each Authorized Staff is therefore responsible for seeing that his/her
badge has the current dosimeter within the holder and for returning his/her badge to the RSO
at the proper time. Delays in processing and reading the badge may invalidate the results.
Also, chances of the badge being lost are increased with late badge returns.
7.2. Reliability
These badges provide legal documentation of external radiation exposure received while
working with radioactive materials at a given facility. When leaving the work area, they are
to be placed in racks assigned near the door of the facility and should not be taken home or to
any other location, since non-occupational exposures may occur. Badges are heat and light
sensitive, and if worn or left outside or in a place where the temperature may be high, a false
exposure will be recorded. It will then become difficult to distinguish a true radiation dose
from a dose caused by exposure to excessive heat or light.
Care should also be taken to make sure that badges do not become contaminated with
radioactive materials. Lost or misplaced badges should be reported immediately to the RSO
in order to receive a replacement. Under no circumstances should workers wear a film badge
belonging to another individual. It is a legal requirement that doses be tracked for the worker
to whom the dosimeter is assigned.
Although the film badges are not assigned for work with certain radionuclides (e.g. 3H,
14C,
35S,
33P,
63Ni) since the energies are beneath the detection limit of the badge, it may be
sensible to wear them anyway when working in a licensed facility where contamination from
other radionuclides may be present.
7.3. Records
An Authorized Staff should inform the RSO in writing (or email) when his/her authorization
to use radioactive materials is temporarily changed to inactive status or when employment
with the institute is terminated. His/her film badge must be returned to the RSO. If badges are
not returned and proper notification of termination of employment/study has not occurred, it
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is a noncompliance with regulatory requirements. This is also necessary since the next place
of employment may require a record of radiation exposure from previous employer/s before
the individual will be allowed to work with radioactive materials.
Authorized Staff can contact the RSO for their exposure data. It typically takes 4 to 6 weeks
to have the badges sent off and processed. The Film Badge Service of PNRI will provide the
RSO with the Dose Report of film badges submitted for evaluation. Any doses that are
significantly higher than normal will immediately be reported by the RSO to the worker. If
you suspect that you have received a significant exposure, you may ask the RSO
immediately, potential exposure will be evaluated, and the badge may be sent immediately
for an emergency reading.
8. EMERGENCY PROCEDURE
8.1. Minor Spills Involving No Radiation Hazard to Personnel
Notify all other persons in the room at once. Only the minimum number of persons necessary
to clean up the spill should be allowed in the area. Confine the spill immediately.
8.1.1 Liquid spills:
a) Wear protective gloves.
b) Drop absorbent paper on spill.
c) Dispose absorbent paper according to proper protocol.
8.1.2 Dry spills:
a) Wear protective gloves.
b) Dampen thoroughly, taking care not to spread the contamination. (Use water
if chemical reaction with water will not generate an air contaminant;
otherwise, oil should be used.)
c) Notify the RSO as soon as possible.
d) Decontaminate
e) Monitor all persons involved in the spill and cleaning.
f) Permit no person to resume work in the area until a survey is made, and
approval of the RSO is secured.
g) Prepare a complete report of the accident and subsequent related activity for
the laboratory records. A copy of the report should be given to the RSO.
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8.2. Major Spills Involving Radiation hazard to Personnel
a) Notify all persons not involved in the spill cleanup to vacate the room at
once.
b) If liquid has been spilled, protect hands with gloves and put the container
upright.
c) If the spill is on the skin, flush skin thoroughly.
d) If the spill is on clothing, discard outer or protective clothing at once.
e) Switch off all fans.
f) Vacate the room.
g) Notify the RSO as soon as possible
h) Take immediate steps to decontaminate personnel involved, as necessary.
i) Decontaminate the area. Personnel involved in decontamination must be
adequately protected.
j) Monitor all persons involved in the spill and cleaning to determine adequacy
of decontamination.
k) No person should be allowed to resume work in the area until a radiation
survey is completed and approval of the RSO is secured.
l) Prepare a complete report of the accident and subsequent related activity for
the laboratory records. A copy of the report should be given to the RSO.
8.3. Accidents Involving Radioactive Dusts, Mists, Fumes, Organic Vapors and
Gases
a) Notify all other persons to vacate the room immediately.
b) Hold breath or don appropriate mask and close escape valves, switch off air
circulating devices, etc., if time permits.
c) Vacate the room.
d) Notify the RSO at once.
e) Ascertain that all doors giving access to the room are closed and post
conspicuous warnings or guards to prevent accidental opening of doors.
f) Report at once all known or suspected inhalations of radioactive materials.
g) Evaluate the hazard and the necessary safety devices for safe reentry.
h) Determine the cause of contamination and rectify the condition.
i) Decontaminate the area.
j) Perform air survey of the area before permitting work to be resumed.
k) Monitor all persons suspected of contamination.
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l) Prepare a complete report of the accident and subsequent related activity for
the laboratory records. A copy of the report should be given to the RSO.
8.4. Injuries to Personnel Involving Radiation Hazard
a) Wash minor wounds immediately, under running water, while spreading the
edges of the gash.
b) Report all radiation accidents (wounds, overexposure, ingestion, inhalation) to
the RSO as soon as possible.
c) Call a qualified physician to treat radiation injuries at once.
d) No person involved in a radiation injury shall be allowed to return to work
without the approval of the RSO and the attendant physician.
e) Prepare a complete report of the accident and subsequent related activity for
the laboratory records. A copy of the report should be given to the RSO.
8.5. Fires or Other Major Emergencies
a) Notify all other persons in the room and building at once.
b) Attempt to put out fires if radiation hazard is not immediately present.
c) Notify the IRRI Fire Brigade (Tel. 2222) and the RSO.
d) Govern fire fighting or other emergency activities by the restrictions of the
RSO.
e) Following the emergency, monitor the area and determine the protective
devices necessary for safe decontamination.
f) Decontaminate.
g) No person should be allowed to resume work without approval of the RSO.
h) Monitor all persons involved in combating the emergency.
i) Prepare a complete report of the emergency and subsequent related activity
for the laboratory records. A copy of the report should be given to the RSO.
9. RADIOACTIVE WASTE MANAGEMENT
IRRI, under the license, is required to establish and implement a Radioactive Waste
Management program to ensure effective control and disposal of radioactive wastes
generated for the protection of the public and the environment. The program should be
relevant to the projected activities, volumes and types of radionuclides likely to be
discharged, and the expected frequency of discharge. The following general guideline should
be followed:
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9.1. Segregation
All radioactive wastes should be separated from non-radioactive wastes. Under no
circumstances is it permissible to dispose of any radioactive material into the non-radioactive
trash or into any drains. It is also necessary to segregate
a) Different types of radioisotopes from each other
b) Chemically hazardous waste from other radioactive waste
c) Solids from liquids
9.1.1 Solids
Place solid wastes contaminated with radioactive materials into segregated and
adequately shielded waste containers lined with plastic bags. When full, secure the
plastic bag (please use tape), and properly label the bag.
Liquids should not be placed in solid waste containers. Small volumes of aqueous liquid,
such as spills, may be adsorbed onto appropriate adsorbent material and placed in a solid
radioactive waste container. Additionally, segregate solid wastes according to type of
radionuclide, as follows:
a) Short -lived radionuclides : Half-life ≤65 days (ex. P-32, P-33)
b) Long-lived radionuclides : Half-life >65 days (ex. H-3, C-14)
c) transuranics elements (atomic numbers greater than 92)
Further, the following radioactive-contaminated wastes must be segregated and placed in
separate containers:
• Glass pipettes and broken glasswares
• Paper towels, tissues, and other paper materials
• Disposable plastic including pipette tips, gloves, aprons, and nylon
membranes.
9.1.2 Mixed wastes – contain both radioactive and hazardous chemical waste.
Liquid scintillation vials are an example, because it also contains toluene which is
hazardous due to flammability. Mixed waste containers must comply with all the rules for
radioactive waste and hazardous waste (e.g., must have a "Hazardous Waste" label, date
the container is full, list of the contents, etc.)
It is recommended not to mix freshly collected wastes contaminated with higher
radioactivity with older wastes (already partially decayed and with lower activity). This
will facilitate efficient disposal of short-lived wastes by “decay in storage”.
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9.1.3 Liquids
Store all liquid wastes in labeled containers that are compatible with the waste materials.
Liquid wastes must not contain solids; such as pipette tips, gels, or filters, and should be
segregated into the following categories:
a) Water soluble, biodegradable, non-hazardous aqueous liquids
b) Liquids containing biohazards - must be sterilized (by autoclave or chemical
methods) prior to disposal
c) Mixed waste
9.1.3.1 Scintillation fluids - segregate scintillation fluids into transuranics and
non-transuranics. Normal, flammable cocktail (flash point less than 140_F) and
“biodegradable" cocktail should be combined. Use of biodegradable fluid is
encouraged, as it minimizes the amount of flammable liquid in the laboratory, but
it still must be treated as hazardous. Bulk scintillation fluids must be placed into
appropriate containers. Empty cocktail containers may be used to collect waste
scintillation fluids. Do not mix bulk scintillation fluid with non-scintillation
radioactive waste or with other hazardous fluids.
9.1.3.2 Non-scintillation fluids - The production of this waste is strongly
discouraged as they are extremely expensive to dispose of and, in some cases,
impossible. Some examples of difficult wastes are radioactive materials mixed
with any:
• flammable liquids (e.g., xylene)
• corrosive liquids (pH less than 2 or greater than 2.5)
• reactives (e.g., peroxides)
• toxics (e.g., mercury)
9.2. Labeling and Record Keeping Requirements
Radioactive waste should be completely labeled at all times, from the time it is deposited into
a container until final disposal. The Authorized staff should keep a notebook for logging the
volume and type of radioactive waste when placed into a numbered container. When the
container is full, a tag must be completely filled out with the following information and
attached to the container:
a) Radionuclide/Radioisotope present
b) Physical/Chemical form
c) Total volume
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d) Brief description of items in container (ex. Used gloves, paper towels, etc)
e) Total Activity (MBq)
f) Date activity was measured
g) Other relevant information (chemical hazard, if any)
h) Method of Disposal
i) Origin (Organizational unit/Authorized Staff responsible)
Due to the problems in radioactive waste management and legal requirements, no radioactive
waste may be removed from the laboratory without the complete information on the tag.
Chronic failure to thoroughly manifest radioactive waste is considered a violation and may
result in the imposition of appropriate sanction on the Authorized Staff as well as the
Principal Investigator.
9.3. Quantifying Levels of Radioactivity in Waste
In order to accurately list levels of radioactivity on the tags, it is necessary to assess the levels
which are disposed in both liquid and solid waste. Suggestions on methods for quantifying
the waste are:
9.3.1 During a given experiment it is known that a certain quantity of radionuclide is used.
At the end of each of several similar experiments, take a sample of liquid waste and count it
with the appropriate counting equipment. The activity in the sample per unit volume is then
multiplied by the total volume of the liquid waste generated. For the solid waste, the quantity
of radioactivity in the liquid is subtracted from the total quantity used in the experiment, and
the remainder is then the quantity in the solid waste.
Example: Wastes collected from use of dCTP (alpha P-32) in Southern Blotting
Concentration of starting material : 0.37 MBq/ml
Volume used per experiment : 5 ul
Total Used per experiment : 1.85 MBq
Total Liquid Waste Volume : 3040 ml
Activity in Liquid Waste Sample : 1200 dpm/ml = 1.85E-05MBq/ml
Liquid Waste Total Activity : 1.85E-05MBq/ml X 3040 ml. = 0.0592 MBq in liquid
waste
Solid Waste Total Activity : 1.85 MBq- 0.0592 MBq =1.7908 MBq in solid waste
9.3.2 After the first few experiments, or when the waste carboy is full, take a sample of
the pooled liquid waste, and count it as above. Multiply the activity of the sample per unit
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volume by the total volume in the carboy to obtain the total activity in the carboy.
Quantify the solid waste as above by subtracting the liquid waste activity
9.4. Interim Storage of Radioactive Wastes
Because of limited space in some of the radioisotope laboratories and in consideration of
safety and regulatory issues, radioactive wastes awaiting further conditioning or disposal are
stored temporarily in a designated on-site radioactive waste storage facility. Solids and
liquids are stored in separate compartments. Within each compartment, wastes with long-
lived nuclides (half-life >65 days; ex. H-3, C-14) are placed in the innermost or at the back of
the room while those with short-lived nuclides (half-life<65 days; ex. P-32, P-33) are place at
the front side. Short-lived wastes are held for decay in storage until while long-lived wastes
are temporarily stored for proper disposal to PNRI at a later date. The Authorized Staff
should take responsibility for the container and its contents, transporting them from the
laboratory to the storage facility and finally, for proper disposal depending on the type and
activity of the nuclide.
The following guidelines should be observed:
a) The Authorized Staff should inform and seek approval of RSO prior to transfer of
waste to storage area.
b) Wastes should be properly segregated, and containers sealed and labeled as
described in previous sections in this manual.
c) Transport of radioactive wastes to the storage facility should be in accordance
with conditions described in previous section on Transport of RAM within IRRI.
d) Records of wastes transferred should be maintained by the Authorized Staff and
copies submitted to the RSO.
e) The radioactive waste storage rooms should be locked when unattended and the
keys returned to RSO (or designated assistant) for safekeeping.
f) The Authorized Staff should take charge of the disposal of wastes in a timely and
appropriate manner. Interim storage of unconditioned wastes shall be as short as
possible and should not exceed five (5) years.
9.5. Methods of Disposal
9.5.1. By Decay in Storage (DIS) - materials with short-lived nuclides
Short-lived material (physical half-life <65 days) may be disposed of by DIS. When
using this procedure, it is important to segregate materials according to half-life and
form/type. When the container is full, complete labeling and record keeping
requirements as described in previous section and seal the container. The container may
then be transferred to the Interim Storage area.
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a) Decay the material for at least 10 half-lives. Calculate and record the
approximate date the wastes may be safely disposed of as in-house waste.
b) Before disposal as in-house waste, monitor each container as follows:
• For liquid wastes, collect a few ml from each container and submit the
samples to ASL to confirm activity using the Liquid Scintillation Counter.
• For solids wastes, use an appropriate radiation survey meter.
� Check your survey meter for proper operation.
� Take the background reading. If possible, monitor in a low-level area
(normally 25-30 cpm).
� Remove any shielding from around the container.
� Monitor all surfaces of each individual container.
c) Discard as in-house waste only those containers that cannot be distinguished from
background. Record the disposal date, and the type of material (e.g., paper or
plastic paraphernalia, etc.). Check to be sure that no radiation labels are visible.
d) Containers that can be distinguished from background radiation levels must be
returned to the storage area for further decay.
e) Chemically hazardous wastes with radiation down to background levels must also
be properly labeled and transferred to the Hazardous Chemical Waste Storage(c/o
Safety Office) for appropriate disposal.
f) Water soluble, non-chemically hazardous liquid wastes with radiation level down
to background may be disposed of by release to the sanitary sewer. The aqueous
effluents may be discharged directly into a sink designated specifically for this
purpose inside the liquid section of the interim waste storage area. A stream of
tap water may be used to further dilute the effluents during discharge.
9.5.2. Discharge of water soluble, non-chemically or biologically hazardous liquid
wastes into sanitary sewer
Radioactive material, including long-lived nuclides such as H-3 and C-14, may be
discharged to the sewers only if each of the following conditions is satisfied:
a) The material is readily soluble or dispersible in water;
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b) The activity of radioactive material that the licensee releases into the sewer in 1
month divided by the average monthly volume of water released into the sewer
by the licensee does not exceed the concentration listed in Appendix D,
"Concentrations For Releases to Sewers";
c) If more than one radionuclide is released, the following conditions must also be
satisfied:
• The licensee shall determine the fraction of the limit in Appendix D,
"Concentrations For Releases to Sewers" represented by discharges into
sanitary sewerage by dividing the actual monthly average concentration of
each radionuclide released by the licensee into the sewer by the
concentration of that radionuclide listed in Appendix D, "Concentrations For
Releases to Sewers"; and
• The sum of the fractions for each radionuclide required by paragraph
(a)(3)(i) of this Section does not exceed unity;
• The total quantity of radioactive material that the licensee releases to the
sewers in a year does not exceed 185 GBq (5 curies) of hydrogen-3, 37 GBq
(1 curie) of Carbon-14, and 37 GBq (1 curie) of all other radioactive
materials combined.
Records must be kept of all these disposals (in GBq) and the information must be
provided to the RSO annually. The intent of this permission is to dispose of small
quantities of radioactivity contained in large volumes of fluid (>1 liter). Examples of
such solutions are rinse water and buffer solutions. Radioactive liquids discharged to
the sanitary sewer should be flushed with large amounts of running water.
9.5.3 By transfer to an authorized recipient (PNRI)
Any other radioactive material or spent source no longer suitable as originally
intended in the license, and having radioactivity levels and concentration not exempt
from regulatory control, must be disposed of by transfer to a person authorized by
PNRI to receive such wastes or by returning the sources to the original supplier.
a) PNRI provides Radioactive Waste Management Service for licensed materials
transferred there for disposal. Required fees must be paid depending on the
volume. It is therefore recommended to compact solid wastes as appropriate or to
pool similar liquid wastes together in suitable containers. Liquid scintillation
fluid wastes containing H-3 and C-14 may be pooled in used cocktail containers,
sealed, and properly labeled. Used LSC vials may also be pooled and compacted
prior to transfer.
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b) If the transfer of spent sealed source to PNRI is not possible, the spent source
should be returned to the supplier or manufacturer.
c) The regulations of CPR Part 4 “Rules and Regulations for the Safe Transport of
Radioactive Materials in the Philippines” should apply in both cases.
10. APPENDICES
10.1 Appendix 1 - Definition of Terms
Open source
A source other than a sealed (or closed) source, for example, a radioisotope kept in a vial.
Sealed source
A radioactive material that is permanently bonded or fixed in a capsule or matrix designed to
prevent release and dispersal of the radioactive material under the most severe conditions which are
likely to be encountered in normal use and handling. A device made in such a form (i.e., an outer
casing containing a radioactive material within) that accidental dispersion of the contents is
extremely unlikely; is also called a closed source.
Physical Half-Life
The physical or radioactive half-life is the time required for the activity of a given isotope
to decay to one-half of its initial value.
In evaluating the effects of radioactive substances deposited in the human system we
need to address two additional half-lifes:
Biological half-life
It is the time required for the body to eliminate one-half of the amount of a radioactive substance
internally deposited by excretion, exhalation and perspiration.
Effective half-life
It is defined as the time required for the radioactivity from a given amount of radioactive
substance deposited in the tissues or organs to diminish by 50 % as a result of the combined
action of radioactive decay and loss of the material by biological elimination. The effective half-
life is usually experimentally determined.
Range
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Distance (in air, water, shielding material, etc.) over which the particle would have given
up all of its energy
Half-Value Layer (HVL)
The half-value layer is the thickness of a substance which reduces the intensity of a beam of
radiation to one-half of its initial value. The half-value layer is a function of the energy of the
gamma and the composition of the shield or absorber.
Committed Dose Equivalent (Ht,50)
The dose equivalent calculated to be received by a tissue or organ over a 50-year period after the
intake of a radionuclide into the body. It does not include contributions from
radiation sources external to the body.
Committed Effective Dose Equivalent (He,50)
The sum of the committed dose equivalents to various tissues in the body (Ht,50), each multiplied
by the appropriate weighting factor (wT)--that is, He,50 = sum(wT*Ht,50).
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10.2 Appendix 2. Details on CPR Part 3
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\CPR 03-STANDARDS
FOR PROTECTION AGAINST RADIATION.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix A - Exemption
Levels.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix B- Radiation
Dose Quantities.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix C - Notice to
Employees Form.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix D-1 Derived
Generic Clearance Levels for Airborne Releases.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix D-2 Derived
Clearance Levels for Liquid Releases.doc
L:\ALL in\_Lab Section\RL\CPR Part 3+Appendices\Appendix D-3 Generic
Clearance Levels for Solid Waste.doc
10.3 Appendix 3. – Required forms for obtaining Authorization to Use
Radiation Sources
L:\ALL in\_Lab Section\RL\LICENSE\RAM License Renewal
Forms\license renewal forms for posting\IRRI RAM Permit Application
Form_lrm 05jan.2010.doc
L:\ALL in\_Lab Section\RL\LICENSE\RAM License Renewal Forms\license renewal
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IRRI
International Rice Research Institute
Analytical Service
Laboratory-
Radioisotope Lab
Document Control No.:
RL-RSM 00
Title: RADIATION SAFETY
MANUAL Issue Date:2011-01-31 Revision No.: 01 Page: 61 of 61
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10.4 Appendix 4. - Code of PNRI Regulations (CPR Part 4), “Rules and
Regulations for the Safe Transport of Radioactive Materials”
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11. REFERENCES
11.1. http://www.pnri.dost.gov.ph/pnri.php?pnri=nsr
11.2. Boston University Medical Center Radiation Safety Guide. Boston University.
12. IMPORTANT CONTACT NUMBERS
Lily Molina (RSO) – loc. 2388 and 2435 (office)
Tel # : 049-501-7893 (residence)
Ruffy Manuel – loc. 2419 Safety Office – loc. 2222
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