IRRI RADIATION SAFETY MANUAL RL-RSM00-R01asl.irri.org/lims/downloads/IRRI Radiation Safety Manual - final_2011.… · Topics included in the Radiation Safety Course.....17 4.3. Radioactivity

IRRI

International Rice Research Institute

Analytical Service

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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

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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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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)


• 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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• 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.


• 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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• 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%


• 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)


• 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)


• 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]


• 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


• 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;


4.7.2.3. 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;


4.7.3.4. 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


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


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


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

forms for posting\NRLSD 008A.xls


forms for posting\RIL 2a_open sources.xls


forms for posting\RIL 2b_sealed sources.xls

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forms for posting\RIL 3_research proposal.doc


forms for posting\RIL 4a_proposed authorized users.xls


forms for posting\RIL 4b_list of persons working in or frequenting restricted area.xls


forms for posting\RIL 5_survey equipment.xls

10.4 Appendix 4. - Code of PNRI Regulations (CPR Part 4), “Rules and

Regulations for the Safe Transport of Radioactive Materials”

L:\ALLin\_LabSection\RL\CPRPart4.pdf

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

(END OF DOCUMENT)

Documents

IRRI RADIATION SAFETY MANUAL RL-RSM00-R01asl.irri.org/lims/downloads/IRRI Radiation Safety Manual - final_2011.… · Topics included in the Radiation Safety Course.....17 4.3. Radioactivity