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1 Radiation Safety Policy and Procedure Manual
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Radiation Safety Policy and Procedure Manual
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TABLE OF CONTENTS
Section Title Page
1.0 Organizational Structure……………………………………………………………………………………………………………… 3
2.0 Emergency Procedures……………………………………………………………………………………………………………….. 7
3.0 Posting Requirements…………………………………………………………………………………………………………………. 8
4.0 Radioactive Spill Procedures……………………………………………………………………………………………………….. 9
5.0 Procedure for Decontamination of Personnel…………………………………………………………………………….. 9
6.0 Evaluation of Users and Uses of Radioactive Materials……………………………………………………………….. 10
7.0 Laboratory Classification & Equipment Required………………………………………………………………………… 11
8.0 Training for Radiation Workers …………………………………………………………………………………………………… 12
9.0 Safe Use of Radioactive Materials ……………………………………………………………………………………………….. 13
10.0 Radiation Exposure of the Fertile Woman and the Embryo /Fetus………………………………………………. 14
11.0 Ordering of Radioactive Material………………………………………………………………………………………………….. 16
12.0 Receipt of Radioactive Materials………………………………………………………………………………………………….. 16
13.0 Opening Packages Containing Radioactive Materials……………………………………………………………………. 17
14.0 Radioactive Material Shipping Labels…………………………………………………………………………………………… 19
15.0 Radiation Producing Machines (X-ray)…………………………………………………………………………………………. 19
16.0 Tracking of Radioactive Materials………………………………………………………………………………………………… 21
17.0 Inventory of Radioactive Material………………………………………………………………………………………………… 21
18.0 Waste and Transfer of Radioactive Material………………………………………………………………………………… 21
19.0 Personnel Monitoring………………………………………………………………………………………………………………….. 22
20.0 Information of Personnel Wearing Personal Dosimeters…………………………………………………………….. 23
21.0 Radiations Safety Surveys…………………………………………………………………………………………………………….. 24
22.0 Wipe and Leak Tests…………………………………………………………………………………………………………………….. 25
23.0 Bioassays………………………………………………………………………………………………………………………………………. 25
24.0 Procedure for use of Survey Meters…………………………………………………………………………………………….. 26
25.0 As Low As Reasonably Achievable (ALARA) Policy………………………………………………………………………… 27
26.0 Audits…………………………………………………………………………………………………………………………………………… 28
27.0 Weekly Wipe Test Instructions…………………………………………………………………………………………………….. 29
Appendix
A Spill Report Form…………………………………………………………………………………………………………………………. 31
B Application for Authorized User Non-Human Use of Radioactive Material…………………………………. 32
C Application for Authorized Non-Human Use of Radioactive Material…………………………………………. 34
D X-ray Safety Information……………………………………………………………………………………………………………... 41
E Radiation Safety Inspection Form……………………………………………………………………………………………….. 43
F Cabinet X-Ray Inspection Form……………………………………………………………………………………………………. 46
G Radioactive Material Shipment Receipt Form……………………………………………………………………………… 47
H Radioactive Materials Tracking Form…………………………………………………………………………………………… 48
I Quarterly Inventory of Sealed Sources Form……………………………………………………………………………….. 49
J Radioactive Waste Disposal Form………………………………………………………………………………………………… 50
K Application for Personal Dosimetery…………………………………………………………………………………………… 51
L Daily Radiation Survey Form………………………………………………………………………………………………………… 52
M Weekly Wipe Test Form……………………………………………………………………………………………………………….. 53
N Bioassay Form………………………………………………………………………………………………………………………………. 54
O Declaration of Pregnancy Form…………………………………………………………………………………………………….. 55
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Issued By: University Environmental Health & Safety Office
Effective Date: August 15, 2003
Revision Date: December 24, 2003; September 16, 2004; June 1, 2011, December 5, 2011, June 2012,
March 2013, June 2014, August 2014
POLICY:
USM RADIATION SAFETY POLICY AND PROCEDURE MANUAL
1.0 Organizational Structure
1. Organization: The Radiation Safety Committee (RSC) will be responsible for evaluation of proposed
uses and users of radiation and for the overall management of radiation safety under the broad scope
license. The RSC will report to the Provost. The Radiation Safety Officer (RSO) will act as the
executive agent for the RSC, and will utilize members of the Radiation Safety Staff to carry out specific
responsibilities. An organizational chart is shown below which details the reporting relationships. The
chair of the RSC will be appointed by the President or Provost of the University. The remaining
members of the RSC will be appointed by the President or Provost upon written delegation by the
President, at the recommendation of the Chair.
RADIATION SAFETY ORGANIZATIONAL CHART
PRESIDENT OF THE UNIVERSITY
PROVOST
RADIATION SAFETY COMMITTEE
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2. Radiation Safety Committee (RSC)
a) Membership: The Radiation Safety Committee will consist of the Radiation Safety Officer
(RSO), the Director of the University Environmental Health and Safety office, a representative
of management, and at least one authorized user. Members may be replaced or deleted and
additional members may be appointed as needed. Appointment duration is typically two to three
years. Appointment renewals are automatic unless an individual elects to stop participation or the
RSC decides through a majority vote to terminate the appointment.
b) Frequency of Meetings: The Committee will meet as often as necessary to conduct business, but
not less than two times during the calendar year. A quorum will consist of at least one-half the
members of the committee including the RSO and at least one representative of the Office of
Research Integrity and Outreach. Minutes of each meeting will be maintained on file, and a copy
sent to each member. The minutes will include the date of the meeting; the members present; the
members absent; a summary of deliberations and discussions; recommended actions; numerical
results of all ballots and documentation of any safety reviews.
c) Responsibilities: The Radiation Safety Committee will have the responsibility to:
i. Conduct radiation safety evaluations of proposed users and uses based procedures and
criteria described in this manual.
ii. Develop procedures and criteria for training and testing each category of worker.
iii. Establish methods for maintaining records of the Committee's proceedings and radiation
safety evaluations of proposed users and uses of radioactive materials.
iv. Develop radiation safety manuals as necessary to ensure proper program implementation
and good health physics practices.
v. Maintain a list of current committee members and their training and experience.
vi. Establish a table of investigational levels for occupational dose that, when exceeded, will
initiate investigations and considerations of action by the RSO.
vii. Monitor the institutional program to maintain occupational doses as low as reasonably
achievable (ALARA).
viii. Review on the basis of safety:
With regard to the training and experience standards for individuals as required by
the regulations of the State of Maine, will approve or disapprove any individual
proposed as an authorized user or the RSO.
Approve or disapprove each proposed location of receipt, storage or use of
radioactive material.
Approve or disapprove each proposed method of use of radioactive material.
Approve or disapprove procedure and radiation safety program changes.
ii. Review occupational radiation exposure records of all personnel working with
radioactive materials.
iii. Review all incidents involving radioactive material with respect to cause and subsequent
actions taken.
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iv. Review and audit the Radiation Safety Program and devote sufficient time, along with the
RSO and the University Environmental Health and Safety office staff, to evaluate
records, reports from the RSO, results of inspections, written safety procedures and RSO
audits to ensure adequacy of the institution's management control systems. These
reviews may be conducted by an independent auditor, but this does not relieve the RSC
of the responsibility to ensure that the reviews are conducted in accordance with
regulations.
v. Review protocol or user permits issued by the RSC at intervals not to exceed 2 years.
vi. Review letters of agreement with offsite emergency response agencies.
vii. Review procedures for controlling and maintaining inventories, procurement of
radioactive material, individual user and institutional cumulative possession limits,
transfer of radioactive material within the institution, and transfer of radioactive material
to other persons or licensees.
viii. Review safety manuals for adequacy and completeness.
3. Radiation Safety Officer (RSO)
a) Requirements: The radiation safety officer (RSO) must be a faculty member or staff employee
of USM, must possess a four year degree in the physical or biological sciences or engineering; or
Be board certified in an appropriate field, or
Have received 200 hours of classroom and laboratory training in radiation physics and
instrumentation, radiation protection, mathematics pertaining to the use and measurement of
radioactivity, radiation biology and radiopharmaceutical chemistry, and one year of full time
experience in radiation safety at an academic organization under the supervision of an RSO, or
Be an authorized user for those radioactive material uses that come within the RSO's
responsibilities, or have considerable (typically 5 years or more) professional experience in
managing a radiation safety program similar to the program at USM. In the event that no suitable
faculty or staff member is available, a consultant who otherwise meets the requirements may
hold the position
b) Authority: The RSO will report directly to the RSC and have access to all levels of the
University and have the authority to immediately terminate any activities that are found to be a
threat to public health, safety or property.
c) Responsibilities
The RSO will have the responsibility to:
i. Maintain surveillance of all activities involving radioactive material, including
monitoring and surveys of all areas in which radioactive material is used.
ii. Determine compliance with rules and regulations, license conditions, and the conditions
of project approvals authorized by the Radiation Safety Committee.
iii. Attend periodic training to stay current with State and Federal regulations and radiation
safety practices.
iv. Provide necessary information on all aspects of radiation protection to personnel.
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v. Oversee proper delivery, receipt, and radiation surveys of all shipments of radioactive
material arriving at the institution, as well as packaging, labeling and surveys of all
radioactive material leaving the institution.
vi. Distribute and process personnel radiation monitors, determine the need for and evaluate
bioassays, monitor personnel radiation exposure and bioassay records for trends and high
exposures, notify individuals and their supervisors of radiation exposures approaching
maximum permissible amounts, and recommend appropriate remedial action.
vii. Conduct training programs and otherwise instruct personnel in the proper procedures for
the use of radioactive material prior to use, at periodic intervals (refresher training), and
as required by changes in procedures, equipment, regulations, etc.
viii. Supervise and coordinate the radioactive waste disposal program, including effluent
monitoring and record keeping on waste storage and disposal records.
ix. Provide storage for radioactive materials not in current use, including wastes.
x. Perform or arrange for leak tests on all sealed sources and calibration of radiation survey
instruments.
xi. Maintain an inventory of all radioisotopes at the institution and limit the quantity of
radionuclides at the institution to the amounts authorized by the license.
xii. Immediately terminate any activity that is found to be a threat to public health, safety or
property.
xiii. Supervise decontamination and recovery operations.
xiv. Maintain other records specified in the State of Maine Rules Relating to Radiation
Protection
xv. Hold periodic meetings with and provide reports to the Radiation Safety Committee.
4. Radiation Safety Staff
Under the supervision of the RSO, The University Radiation Technician will perform required
measurements (surveys, etc.), maintain and calibrate survey and monitoring instruments, train technical
and ancillary staff, and perform other duties as required on a day-to-day basis.
Duties include but are not limited to, weekly surveys, specifically Geiger counts and Micro-beta counter
wipe tests, and cleaning of the radiation core facility in accordance with University policy and procedure
as adopted by the Radiation Safety Committee. Other tasks include: monitoring radiation core facility
for safety compliance; attendance at Radiation Safety Committee meetings; meeting with Radiation
Safety Officer, monitoring and ordering of supplies for the radiation core facility; and meeting and
consulting with radiation core facility users. Note: The Radiation Technician position is currently
suspended. The RSO performs these duties.
2.0 Emergency Procedures
1. Radiation Emergency Response Team
The Radiation Emergency Response Team shall include:
John R. Reed - RSO, cell: (207) 420-4831 & home: 787-8831
Hong Xie Ph.D. - Chair, Radiation Safety Committee, 228-8067
Doug Murphy - XRF Factory Trained Operator (FTO), 780-4126
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2. On-Call Radiation Safety Personnel
Situations occasionally arise at night or on weekends when the assistance of Radiation Safety personnel
is required. Examples of such situations include: arrival of a damaged package of radioactive material
or removal of radioactive trash from a laboratory by Environmental Services personnel.
If assistance from the University Environmental Health and Safety office is required, contact names and
numbers are posted on the Core Facility laboratory doors. In addition, these numbers will always be
available through the USM Campus Police.
3. Response to Fire in Areas Where Radioactive Materials Are Used and/or Stored
Fires in areas where radioactive material is stored and/or used should be handled without regard for the
radioactivity in the area.
Once the fire is extinguished, an evaluation of radioactive contamination of the area and any persons
entering the area should be made, and decontamination performed if necessary.
4. Loss of Radioactive Material
All radioactive material entering or leaving any USM site must be accounted for and have a written
record maintained.
In the event that any quantity of radioactive material is lost or otherwise unaccounted for, the Radiation
Safety Officer must be immediately notified.
The RSO will initiate efforts to recover lost material and if necessary utilize personnel from the Campus
Police as well as from the effected laboratory.
The RSO will if appropriate notify the chairman of the radiation safety committee, USM administration,
and regulatory authorities.
3.0 Posting Requirements
1. Warning Signs
All areas in which radioactive material may be stored or used, including waste storage areas, will be
posted with the standard, “Caution – Radioactive Material” sign. An example is shown below.
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In the event there is an area in which radiation produced by electronic means is present but no
radioactive materials are present, a similar sign with the words, “Caution – Radiation Area” shall be
used.
2. Emergency Numbers: The entrance to each area in which radiation may be found shall be posted with
the names and numbers of persons to contact in case of an emergency.
3. Notice to Employees: The standard Notice to Employees (State of Maine form HHS-845) shall be
posted conspicuously in one or more places frequented by employees.
4. Violation Notices: Notices of inspections and violations issued by the State shall be conspicuously
posted where they may be seen both by employees and by the general public.
4.0 Radioactive Spill Procedures
The procedures given below must be followed if there is a spill of radioactive material:
1. Notify all persons in the area that a spill has occurred. Prevent all possibly contaminated persons from
leaving the area. If personnel are contaminated, refer to Procedure for Decontamination of Personnel
below.
2. Notify the Radiation Safety Officer.
a) If the magnitude of the spill is large (volume or activity), secure the area and wait for instructions
from the RSO.
b) If necessary, call the Public Safety Department (780-5211 or 911 on a campus telephone) for
assistance in securing the area.
3. For small spills or when directed by the Radiation Safety Officer:
a) Put on gloves and prevent the spread of contamination by covering the spill with absorbent
paper. Use enough paper to absorb all the liquid.
b) Place masking tape around the spill area.
c) Carefully fold the absorbent paper with the clean side out and place in a plastic bag.
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d) Wash the contaminated area with detergent. Wash the area just inside the tape first and work
toward the center. This will limit the spread of contamination.
e) Once the area is thoroughly washed, perform a wipe test on a 10 x 10 cm area (100 cm2) within
the tape. Wipe this area with an alcohol swipe and place in a vial. Place another alcohol swipe
in a vial to use as a background swipe.
f) The wipe test results must be recorded in DPM/100 cm2 (disintegrations per minute per 100
cm2). Record this value in the spill log.
g) For I-125, I-131, I-123, In-111, Co-57, Co-58 and P-32 the wipe test results must be less than 20
DPM/100 cm2 for an unrestricted area, or less than 200 DPM/100 cm2 for a restricted area. For
all other isotopes, the wipe test results must be less than 20 DPM/100 cm2 for an unrestricted
area, or less than 200 DPM/100 cm2 for a restricted area. If the measured wipe test activity
exceeds the limits, the area must undergo further decontamination and be retested. Contact the
Radiation Safety Officer if you have any questions.
h) Remove the tape and dispose of any contaminated absorbent paper, gloves, and other material in
the same manner as radioactive waste.
i) Complete a radioactive spill report form and contact the Radiation Safety Officer (see Appendix
A, Forms).
4. If necessary the Radiation Safety Officer will notify staff, USM administration and external authorities.
5.0 Procedure for Decontamination of Personnel
If personnel are contaminated with radioactive material, the procedures given below must be followed:
1. Injured Personnel: Persons who are injured as well as contaminated, and who require immediate
medical attention, should receive medical care without regard for the contamination. The University
policy for response to persons injured within the facility should be followed. Persons caring for the
injured, contaminated person should use universal precautions to minimize the effects and spread of
contamination. When the injured person is stable, an evaluation of the contamination should be made
and decontamination efforts initiated.
2. Contaminated Skin
a) Go immediately to a sink and wash the contaminated area gently with cool water, using a mild
soap solution or a commercial cleanser such as Radiacwash. Do not use warm or hot water since
that will cause the pores in the skin to open. Wash gently for five to ten minutes. Avoid
abrasion of the skin. Abrasion of the skin increases the difficulty of removing the radioactive
material.
b) Emergency eye washes are available and can be used to flush the eyes thoroughly. The RSO
must be informed immediately if radioactive material contaminates an individual's eyes.
c) Survey the contaminated area with Geiger Counter or NaI detector.
d) Continue washing and surveying the area until you observe background radiation levels.
e) Record all actions taken on a Radioactive Spill Report form (see Appendix A,). The completed
form should be given to the University Environmental Health and Safety office.
3. Contaminated Clothing
a) Any clothing that is contaminated should be removed and placed in a plastic bag. Label this bag
with your initials, the name of the radioactive material spilled, the location of the radioactive
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material on the clothing, and approximately how much radioactive material was spilled on the
clothing.
b) Keep this bag in a secure location and notify University Environmental Health and Safety office
for decontamination or disposal.
6.0 Evaluation of Users and Uses of Radioactive Materials
Proposals to add new users and/or new uses of radioactive material must be submitted on specified forms and
will be evaluated by the Radiation Safety Committee. The action of the committee will be noted in the minutes,
and a letter will be sent to the applicant indicating approval or disapproval of the proposal. If the proposal is
denied, an explanation of the reasons for denial will be provided.
The following subjects will be evaluated:
1. Types of isotopes, their activities and the forms desired.
2. Adequacy of the facilities and equipment to maintain exposures to radiation workers, other workers and
the general public below regulatory limits and ALARA principles. Included in this area are the
following:
a) Ordering procedures, inventory control, and security
b) Storage facilities
c) Procedures for handling and other operations
d) Procedures for handling radioactive waste
e) Types of instruments used for assay and survey purposes
f) Personnel monitoring
g) Bioassay instrumentation and procedures
h) Air sampling instrumentation and procedures
i) Special requirements (use of animals, etc.)
3. Previous training and experience of persons who will be responsible for the use of material.
4. Training that will be provided to radiation workers in the areas of use and to other personnel who may
come into contact with radioactive material.
5. When a proposal is approved, a numbered permit will be issued specifying the types of isotopes
allowed; the activities; the locations of use; the approved users; any restrictions; and the beginning and
expiration dates of the permit. Permits will normally be issued for a period of two years, renewable
upon reapplication and satisfactory performance.
6. The Maine State Radiation Control Program will have the sole authority to add or delete an
Authorized User (AU).
7. Once a new user is approved by the RSC and the State, an amendment request will be sent to the
Maine State Radiation Control Program for amendment of the Limited Scope license.
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7.0 Laboratory Classification & Equipment Required
1. Laboratories are classified in accordance with the radiotoxicity and quantity of the radioisotopes used
within the laboratory.
a) Type A Laboratory: Specially designed for handling large quantities of highly radioactive
materials.
b) Type B Laboratory: Specially designed radioisotope laboratory.
c) Type C Laboratory: Good quality chemical laboratory
RADIOTOXICITY
OF
RADIONUCLIDES
TYPE OF LABORATORY REQUIRED
TYPE A TYPE B TYPE C
VERY HIGH ≥ 10 mCi 10 uCi - 10 mCi < 10 uCi
HIGH ≥100 mCi 100 uCi - 100 mCi < 100 uCi
MODERATE ≥1 Ci 1 mCi - 1 Ci < 1 mCi
LOW ≥10 Ci 10 mCi - 10 Ci < 10 mCi
RELATIVE RADIOTOXICITY OF RADIONUCLIDES
VERY HIGH HIGH MODERATE LOW
Am-243 Ac-228 Au-198 Co-58m
Cf-249 Bi-207 Be-7 Cs-125
Cm-244 Ce-144 C-14 Ge-71
Pa-231 Cl-36 Cr-51 H-3
Pb-210 Co-56 Gd-153 Kr-85
Po-210 Co-60 La-140 Nb-97
Pu-238 Hf-181 Na-24 O-15
Ra-226 I-125 P-32 Os-191m
Ra-228 I-131 Ru-103 Rb-87
Th-227 Ir-192 S-35 Rh-103m
Th-232 Na-22 Sc-48 Tc-99m
U-238 Sb-125 Sr-91 Xe-131m
etc. Zr-95 Te-125m etc.
Cs - 137 V-48
etc. W-187
Y-90
Zn-65
Zn-69m
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For each class of laboratory, the following table lists the facilities and equipment required.
FACILITIES AND
EQUIPMENT
REQUIRED
TYPE OF LABORATORY
TYPE A TYPE B TYPE C
Low-level survey
meter
YES YES YES
High level survey
meter
YES YES NO
Wipe test counting
instrument
YES YES YES
Shielded isotope
storage areas or
containers
YES YES YES
Shielded waste
areas
YES YES (*)
Shielded L-blocks YES YES NO
Fume Hood YES (**) YES (**) NO
Caution signs YES YES YES
Personnel
monitoring
YES YES YES
(*) Depends upon type of emissions (alpha, beta or gamma)
(**) Depends on use of volatile materials such as H-3, I-125 and I-131
8.0 Training for Radiation Workers
All employees who may come into contact with radioactive materials in the course of their work will be trained
in radiation safety at a level commensurate with their risk. The training will be given upon initial employment
and whenever methods or procedures change or are modified. The type of training will vary depending on the
level of exposure to employees.
1. Ancillary Employees
Ancillary employees are employees who don’t actually work with radioactive materials or radiation
producing equipment but work in the vicinity of where this type of work is conducted. Examples of
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Ancillary employees are individuals who work with environmental services, police, engineering,
materials management and others who only have occasional contact with areas where radioactive
materials are used or stored.
The purpose of the training is to familiarize personnel with radiation, radioactive materials, or radiation
producing instruments, the hazards of exposure to radiation, and the safeguards recommended to prevent
or minimize exposure at this university. The University Environmental Health and Safety office and
RSO will provided this instruction.
Periodic refresher training for these groups will be conducted by the University Environmental Health
and Safety office.
2. Radiation Workers
In addition to the training received by ancillary personnel, radiation workers receive additional training
specific to the materials used and tasks performed. Particular emphasis is placed on recognition of
hazards and methods for individual employees to protect themselves, other workers and the general
public.
Radiation workers also receive hands-on training prior to actually working with radioactive materials or
radiation producing equipment or whenever there is a significant change in the laboratory protocols
specific to the research being conducted. The training is provided by the authorized user or the
authorized user’s designee.
All training is documented. Documentation includes the names of individuals receiving training, date
and location of training, topics copied and signature of trainer. Records of training are maintained by
the University Environmental Health and Safety office. The authorized user also maintains a copy of
this documentation which is available for inspection in or near the laboratory where the work takes
place.
9.0 Safe Use of Radioactive Materials
1. Adherence to regulations
The University of Southern Maine will conduct its operations involving radioactive materials in
accordance with statements made in license applications, provisions of licenses granted by the State of
Maine and regulations promulgated by the State of Maine and other appropriate regulatory bodies.
2. Personal radiation safety: Each person handling radioactive material shall be responsible for conducting
work in a manner that will keep radiation exposure to a minimum, for the worker, fellow workers,
patients and the general public. The radiation protection rules given below must be followed:
a) Wear laboratory coats or other protective clothing at all times in areas where radioactive
materials are used.
b) Wear disposable gloves at all times while handling radioactive materials. While wearing gloves,
do not touch objects such as the telephone, doorknobs, etc. Gloves should be changed when you
leave the immediate local area of radioactivity.
c) All radioactive solutions and materials must be properly labeled.
d) Never pipette radioactive materials by mouth.
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e) Prevent the spread of contamination by handling all radioactive materials on a disposable,
absorbent pad.
f) Do not eat, drink, smoke, or apply cosmetics in any area where radioactive material is used or
stored.
g) Do not store food, drink, or personal effects in areas where radioactive material is used or stored.
h) Wear personal radiation monitors (PRM) at all times while in areas where radioactive materials
are used or stored. These devices should be worn as prescribed by the Radiation Safety Officer.
When not being worn to monitor occupational exposures, PRM should be stored in the work
place in a low background area.
i) Dispose of radioactive waste only in designated, labeled, and properly shielded receptacles. Any
glassware or other object that has been in contact with radioactive materials shall be disposed of
with other radioactive waste or decontaminated.
j) Notify the University Environmental Health and Safety office (X 5406) if any of the following
occurs.
i. Spill of radioactive material
ii. Known or suspected external or internal over-exposure to radiation
iii. Known or suspected contamination of work areas
10.0 Radiation Exposure of the Fertile Woman and the Embryo/Fetus
1. Introduction
The University of Southern Maine recognizes the fact that female radiation workers who are pregnant or
who plan to become pregnant in the future are concerned about the effects of radiation on their fetus.
For this reason, it is felt that a statement of policy concerning the duties and continued employment of
such employees is advisable. The purpose of this policy is to provide maximum protection to the fetus
without placing undue burdens on fellow employees.
2. Estimate of Risk
The National Council of Radiation Protection (NCRP) reviewed the studies and literature concerning
hazards to the fetus from radiation exposure, and published its findings as NCRP Report #53 (Review of
NCRP Radiation Dose Limit for Embryo and Fetus in occupationally-exposed Women – March, 1977).
Similar findings were reported by the National Academy of Science and the Committee on the
Biological Effects of Ionizing Radiations (BEIR) in the 1990 Beir V Report.
The NCRP found that there is no direct evidence of increased birth defects or childhood leukemia or other
cancers at the exposure levels normally encountered in university laboratory facilities. Some estimates
may be obtained by means of extrapolation of high-dose data, or from animal studies, but it must be
realized that such extrapolations are subject to considerable uncertainty. Using “worst-case” data obtained
from several studies, the NCRP found the following:
a) Birth Defects: The natural incidence of birth defects is about 40,000 cases per 1,000,000
pregnancies. If all 1,000,000 women were given a dose of 0.5 rem to the fetus, an additional 10
cases would be expected (for a total of 40,010).
b) Childhood Leukemia: The natural incidence of childhood leukemia (during the first 10 years of
life) is about 1,000 cases per 1,000,000 pregnancies. If all 1,000,000 women were given a dose of
0.5 rem to the fetus, an additional 35 cases would be expected (for a total of 1,035).
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It should be emphasized that these numbers represent “worst-case” estimates, and the actual risk is
probably much less.
It should also be noted that these estimates are based on a dose of 0.5 rem to the fetus. Because of
attenuation due to the tissue between the mother’s skin and the fetus, the surface dose required to deliver
0.5 rem to the fetus will be higher. In the case of laboratory personnel, the surface dose would have to be
on the order of 2-3 rem. The surface dose is what is recorded by the employee’s personal dosimeter.
3. Current Exposure Levels
Due to improvements in radiation safety practices, the average annual dose to radiation workers at the
University of Southern Maine is expected to be well below 0.5 rem.
The NCRP recommends, and the State of Maine requires in its regulations, that the annual whole body
dose to radiation workers not exceed 5 rem. However, it is USM’s policy to take action if the annual
dose is likely to exceed one-tenth of that amount, or 0.5 rem.
The State of Maine also requires that the total dose to the embryo/fetus not exceed 0.5 rem during the
entire period of gestation from occupational exposure of a declared pregnant woman. In addition, all
efforts should be made to avoid month-to-month variation in the dose.
3. Radiation Safety Practices
In order to keep personal exposure as low as reasonably achievable (ALARA), each radiation worker
should practice these radiation protection measures:
a) Time – Keep the time during which you are actually exposed to ionizing radiation to a minimum.
b) Distance – Maintain the maximum distance possible between yourself and the source of the
ionizing radiation.
c) Shielding – Protect yourself with shielding when you are in a radiation area. Remember, the
shielding should be placed between the source of the radiation and your body.
4. Declaration of Pregnancy
The policy of the University of Southern Maine regarding occupational exposure of pregnant
women is as follows:
a) A pregnant radiation worker may declare her pregnancy and estimated conception date in writing to
the RSO (See Appendix O). She should meet with the RSO to discuss her exposure history and
protective measures. This information will remain confidential. The RSO will keep a separate record
of the radiation exposure to the pregnant employee.
b) During the gestation period, the dose to the fetus should not exceed 0.5 rem, and the dose should not
exceed 0.05 rem in any one month.
c) In order to help achieve this goal, it is mandatory for all personnel to use appropriate protective
devices and follow accepted good laboratory practices.
d) Pregnant radiation workers will not be excused from performing their normal duties since experience
indicates that occupational exposures from these procedures do not represent any demonstrable
hazard to the fetus. Conversely, pregnant radiation workers will not be routinely assigned to non-
occupationally exposed areas against their will (for example, a forced transfer to clerical duties).
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e) A pregnant employee who feels that her fetus is in jeopardy despite all the measures taken to protect
it, and despite all of the scientific information available as outlined above, may resign or be considered
for a leave of absence in accordance with USM Human Resources Policies.
f) The declaration of pregnancy remains in effect until the declared pregnant woman withdraws the
declaration in writing, or is no longer pregnant.
11.0 Ordering of Radioactive Material
1. All orders for radioactive materials will only be placed by persons authorized in writing by the RSO to
do so.
2. Completion and submittal of Appendix B (Application for Authorised User – Non Human Use of
Radioactive Materials) and Appendix C (Application for Non Human Use of Radioactive Materials)
must be received and approved by the RSO and Radiation Safety Committee prior to ordering of any
radioactive materials.
3. Orders for radioactive materials to be used for in-vitro clinical or any research purposes may only be
made for purposes approved by the Radiation Safety Committee.
4. Orders will not be placed until it is verified that the activity of the received material will not cause
appropriate possession limits to be exceeded.
5. Approved orders for radioactive materials will be placed by the University Environmental Health and
Safety office following current USM purchasing policies and will be billed to the requesting department.
12.0 Receipt of Radioactive Materials
1. Once an order is placed the University Environmental Health & Safety office will notify the PI and
Research Administration Office of the details of the order and the estimated shipping date and carrier.
Research Administration will contact the carrier and confirm the shipping and tracking information to
ensure that the carrier has the correct delivery information, details, and arrange to have staff available to
receive the shipment at the time specified by the carrier and in accordance with the order delivery
specifications.
2. Packages will only be accepted during normal working hours (8:00 AM to 4:30 PM, Monday through
Friday) at the Science Building new wing loading dock designated as 70 Falmouth Street, Portland, ME
04104.
3. All packages with radioactive material warning labels shall be inspected and, if undamaged, delivered
directly to the Radioisotope Core Facility. If a trained person with access to the Radioisotope Core
Facility is not immediately available the undamaged package will be placed in the deliveries lock box
located in room 178 of the new wing of the Science Building. Once a trained person with access to the
Radioisotope Core Facility is located, that person will retrieve the lock box key from the Radioisotope
Core Facility, retrieve the package and transport the package to the Facility. The lock box will be
surveyed each time it has been used to house a radiation labeled package, or at any time there is
suspicion that contamination may have occurred. Each survey will be properly documented. (See
Appendix G)
17
4. If at the time of delivery an inspection reveals damage to the package or if the package is wet the
package and the delivery person will be kept at the loading dock until the package has been scanned and
is shown to be safe. If the scan reveals that there is radiation present above limits specified by law,
regulation or policy, the standard radiation spill procedures will be followed and documented (See
Appendix A).
5. Once at the facility, a trained person will perform the package opening procedure and fill out the receipt
log. The following procedure should be followed:
a) Verify that the package is addressed to USM.
b) Visually inspect the package for damage (stains, crushed corners, leakage, puncture holes, etc.).
If the package is damaged do not accept it and require the courier to remain on site until the
Office of Campus Environmental Safety and Health has been notified (x 5406). They will then
supervise the handling of the damaged package.
c) If the package is not damaged, sign for it and release the courier. Contact the research isotope
procurement coordinator within the facility to pick up the package.
d) If questions arise or in case of an emergency, contact the University Environmental Health and
Safety office.
13.0 Opening Packages Containing Radioactive Materials
The procedures to be followed for opening packages depends on whether or not the package has radioactive
material warning labels on it.
1. For Packages With Warning Labels
a) Put on gloves to prevent hand contamination. If the package contains liquids, place it on an
absorbent pad.
b) Visually inspect the package for any sign of damage (e.g., wet or crushed). If damage is noted,
stop the procedure and notify the University Environmental Health and Safety office.
c) Record the date, time, box or lot number, P.O. number, radionuclide, radiation units on label,
transport index on label, and your initials on the radioactive shipment receipt report.
d) Use a survey meter to measure the exposure rate from the package at 1 meter and at the package
surface, compare these to the acceptable levels, and record the results on the report. The action
levels depend on the label. They are (in mR/hr):
White I Yellow II Yellow III
3' from package N/A 1 10
Package surface < 0.5 50 200
Empty package Background Background Background
e) Use an alcohol pad to wipe a 300 cm2 area on the outside of the package. Assay the wipe with a
gamma counter for a gamma-emitting isotope or a beta counter for a beta-emitting isotope to
determine if there is any removable radioactivity. Compare the results with the acceptable
levels, and record the results on the report.
18
The action level for all types of labeled packages is 6,600 DPM/300cm2 (22 DPM/cm2).
If either the measured exposure rates or the amount of removable contamination exceeds
acceptable levels expected, stop and notify the University Environmental Health and Safety
office. Take precautions against the potential spread of contamination.
f) Open the package and perform the following steps:
i. Remove the packing slip.
ii. Check the user request to ensure that the material and activity received is the material and
activity that was ordered.
iii. Open the outer package following the supplier's instructions, if provided.
iv. Open the inner package and verify that the contents agree with the packing slip.
v. Check the integrity of the source containers. Look for broken seals or vials, loss of
liquid, condensation, or discoloration of the packing material.
vi. If anything is other than expected, stop and notify the Radiation Safety Office.
vii. Place the contents in a secure, appropriate storage area.
viii. Monitor all packing material and empty packages with a survey meter, before discarding
them. Record this exposure rate on the report.
ix. If contaminated, treat this material as radioactive waste.
x. If not contaminated, remove or obliterate any radiation labels before discarding as normal
trash.
2. For Packages Without Warning Labels
Open the package and perform the following steps:
a) Remove the packing slip.
b) Check the user request to ensure that the material and activity received is the material and
activity that was ordered.
c) Open the outer package following the supplier's instructions, if provided.
d) Open the inner package and verify that the contents agree with packing slip.
e) Check the integrity of the source containers. Look for broken seals or vials, loss of
liquid, condensation, or discoloration of the packing material.
f) If anything is other than expected, stop and notify the Radiation Safety Office.
g) Place the contents in a secure, appropriate storage area.
h) If contamination is suspected, perform a wipe test on the outer package. If acceptable
levels are exceeded, notify the radiation safety office. Take precautions against the
potential spread of contamination.
19
14.0 Radioactive Material Shipping Labels
15.0 Radiation Producing Machines (X-ray)
1. Acquisition and Use
Individuals requiring radiation producing machines shall obtain approval from the RSC prior to
acquisition, whether by purchase, loan or gift. A Proposal for Use must be submitted to the RSC for
review. (See Appendix B & D)
2. Proposal for Use
The proposal for use must include the following information:
a) Principal Investigator (PI) or Instructor, and the extent of experience with the particular
instrument requested.
b) The PI or primary user of the x-ray emitting equipment (i.e. Portable XRF), will be designated
the Factory Trained Operator (FTO).
i) The FTO has had specific, documented training on the x-ray emitting instrument, and radiation
worker training provided by the RSO.
c) Names of other personnel who will use the equipment.
d) Description of the instrument, proposed use, and intended use and storage location.
20
e) The FTO is responsible for the safe operation and handling of the xray emitting instrument
which includes instrument shielding, the written safety program, dosimetry (if used outside
shielded stand), and the training of other authorized users.
3. Procedure Guides
The FTO shall provide the RSO with a copy of the owner's manual for the instrument. Each individual
operating the equipment shall be trained by the FTO to insure the operator is thoroughly familiar with
the manual and all safe operating procedures.
4. Purchase/Acquisition
All purchases of radiation producing machines shall be made through the EH&S department upon
certification and approval by the RSO and Radiation Safety Committee.
5. Survey of Installation
Prior to use, installations of radiation producing machines, whether newly acquired or relocated, shall be
surveyed by the RSO in order to determine the effectiveness of shielding, interlocks, and other
engineering controls.
6. Changes in Location
The RSO must approve, in advance, any relocation of a radiation producing instrument.
7. Disposition
The RSO must be notified of any intent to dispose, abandon, salvage for parts, or give away any
radiation producing machine.
8. Caution Signs and Labels
All radiation producing machines and areas must be properly posted. Contact the RSO for signs and
labels.
9. Personal Dosimetry Badges
All individuals working with or near operating X-ray machines must wear a personal dosimetry. The
FTO will coordinate dosimetry use and record keeping.
Note: Based on the initial 12 months of exposure records, exemption from future dosimetry use
has been authorized and approved by the Radiation Safety Committee based on consultation with
Wayne Malloch from the State of Maine Radiation Control Program.
10. Lockout
Malfunctioning or improperly used radiation producing machines will be locked out by the RSO,
pending Radiation Safety Committee agreement.
11. Inventory
Current licensed xray emitting instruments used at USM are:
i. Faxitron - model # 43855D
ii. Spectro-Ametek - model # 12878
iii. Thermo Niton - model # XL3T-500
Note: The Xray emitting Faxitron and Thermo Niton shall be inspected by a State approved
“Qualified Expert” every two years. The Spectro-Ametek instrument is “exempted”.
21
16.0 Tracking of Radioactive Materials
1. All radioactive material received at any USM facility will be tracked from receipt, through use to final
disposal.
2. Radioactive material will be initially logged in on an appropriate receipt form. In addition, a
radioisotope tracking record will be initiated which lists the amount of material that is used in each
laboratory.
3. The tracking record will also list any material classified as waste, and will include final disposition of
the waste.
4. Waste stream records, including waste service contractor records, will be maintained by the University
Environmental Health and Safety office.
17.0 Inventory of Radioactive Material
1. Routine bi-annual inventories of all sources are performed at all USM facilities.
2. These inventories are performed by the RSO and reviewed by the RSC, and are examined for
compliance with appropriate possession limits. A record of total activity on hand at the time of the
inventory will be recorded. (See appendix I)
18.0 Waste and Transfer of Radioactive Material
1. Categories of Waste: All waste containing radioactive material, at any level, must be disposed of in
accordance with applicable City, State and Federal regulations. As a general rule, radioactive waste falls
into one of several categories depending on the half-life of the radioactive material and its activity:
a) Short Half-life Material
Radioactive waste containing short half-life material is usually handled by placing the waste in
storage, allowing it to decay to background, and then disposing of the remaining waste without
regard for the formerly radioactive material. If, after decay of the radioactive component, the
remaining waste is chemically and/or biologically hazardous, it must be handled appropriately.
Otherwise, it may be disposed of as normal trash. In some cases, short half-life waste may be
returned to suppliers of such material. Examples of short half-life material are Iodine-125,
Iodine-131 P-32, etc.), and associated instruments, containers and protective clothing and
coverings.
b) Medium and Long Half-life Material
Radioactive waste containing long half-life material in encapsulated sources is usually handled
by return to the manufacturer. Examples of such waste include calibration sources (Cesium-137,
Cobalt-57 and I-129). Un-encapsulated sources (Tritium, Iodine-125, Carbon-14, Sulfur-35,
etc.) may be stored for decay to background, stored for eventual shipment to a disposal site, or
stored for disposal by other means. The choice of a method to use will depend primarily on the
type and activity of the waste, and must be approved by the Radiation Safety Officer.
2. Approval of Waste Disposal: All disposal or transfer of radioactive material must be approved by the
RSO. Blanket approval may be given for well-established methods of disposal. Each area using
radioactive material must adhere to the written procedures specific to its use.
22
3. C14 contaminated liquid waste can be disposed of through the sanitary sewer provided the liquid is
biodegradable and the amount of isotope is below release limits established according to USNRC Part
20 Appendix B. The current limit is 3 x 10-4 uci/ml.
4. General information: Sharps, including pipette tips, shall be placed in appropriately marked sharps
containers. Waste must be segregated by isotope. Waste shall initially be placed in dedicated containers
in the radioisotope core facility. The appropriate log must be filled out each time material is placed in a
waste container. When the container is full, it will be transferred to the radioactive waste storage room
(Science 61B). Determination of which waste is decayed to background and which waste is transferred
via a licensed broker to an approved radioactive waste facility, will be made by the RSO with the
approval of the RSC.
5. Records: Complete records of disposal or transfer of radioactive material must be maintained and
available for review by the RSO. Such records must include the isotope, activity, disposal date and the
initials of the person preparing the waste. (See appendix J)
6. Transfer of Radioactive Material: Radioactive material may be transferred between different locations
that are part of the same facility license. If transfer takes place between physically different locations,
all requirements of the Department of Transportation (DOT) must be met, including labeling of
containers and vehicles. Transfer to other licensees may be accomplished if there is mutual agreement
between the licensees and the receiving licensee is authorized to use the type and activity of the
radioactive materials to be transferred.
19.0 Personnel Monitoring – Dosimetry Use
1. Criteria for Inclusion: All employees of USM who are likely to receive on an annual basis from external
sources an exposure in excess of 10% of the maximum permissible dose limits, shall be required to wear
a whole body dosimeter to record exposure. The maximum permissible annual dose limits are:
Area Annual Effective Dose Equivalent
Whole body 5 Rem (50 mSv)
Lens of eye 15 Rem (150 mSv)
Skin or extremity 50 Rem (500 mSv)
Any other organ 50 Rem (500 mSv)
2. The maximum permissible dose for a minor employee is 1/10 the values listed above.
3. Furthermore, a declared pregnant employee will be monitored to assure that the dose to the embryo/fetus
does not exceed 0.5 Rem (5 mSv).
4. In addition, any area where an adult employee is likely to receive an intake greater than ten percent of
the applicable Annual Limit on Intake (ALI), or where minors or pregnant women are likely to receive a
committed effective dose equivalent greater than 0.05 Rem (0.5 mSv) will be monitored to ensure
compliance with these limits.
5. When appropriate, the RSO may authorize monitoring of other individuals and/or groups of workers.
23
20.0 Information for Personnel Wearing Personal Dosimeters
Should the RSO determine that an employee may be exposed to radiation levels in excess of 10% of
annual dose limits described in Section 19, a whole body dosimeter will be issued at no cost to the
employee of the University of Southern Maine.
The personal dosimeter consists of two parts: the radiosensitive material and filters encased in plastic,
and a plastic clip-on holder.
The following rules must be followed to insure accurate and timely measurement of your occupational
radiation exposure:
1. Wear the dosimeter on an anterior pocket or collar with your name facing away from your body.
2. If using a lead apron, wear the dosimeter outside the apron. This is required by State of Maine
regulations.
3. When not wearing your dosimeter, store it in a place where it is not near any sources of radiation.
4. Never wear the dosimeter when you are a patient and a medial x-ray exam is performed on you. The
dosimeter is used to measure occupational radiation exposure.
5. Never intentionally exposure your dosimeter by placing it near a source of radiation. Exposing your
dosimeter “just to see what happens” will result in an invalid measurement of your occupational
radiation exposure. An investigation will be conducted by the RSO.
6. Your dosimeter will be exchanged prior to the first day of each calendar quarter with a new devise. A
representative from the EH&S office will exchange the new dosimeter for the devise used in the
previous quarter. It is imperative that the quarterly exchange occurs and that the “old” dosimeters are
returned to the vendor for analysis and reporting.
7. Please note: Individuals who make the dosimeter exchange process challenging, or frequently lose
dosimeters, can be restricted from future activity involving radioactive materials if the RSC deems this
action necessary.
8. If you lose your dosimeter, promptly contact the University Environmental Health & Safety office
(x5406). A new dosimeter will be issued to you. (See appendix K)
9. After the dosimeters are collected each quarter, they are sent for processing to the vendor (Landauer). A
report of the radiation exposure received by each individual is sent to the RSO at USM. The RSO promptly
reviews the report and posts a copy so that you can also review your readings. Copies of all reports are kept
on file in the University Environmental Health & Safety office.
10. The Maximum Permissible Dose (MPD) to the whole body allowed by the State of Maine for
occupationally exposed workers is 5000 millirem per year. The eyes, skin, extremities and other organs are
allowed higher doses. However, investigational levels for occupational radiation exposure at USM are set
at 1/10 and 3/10 the MPD and are given below.
24
11. Based on exposure records for the previous five years, advise from Wayne Malloch from the State
of Maine Radiation Control Program, and a unanimous vote from the The Radiation Safety
Committee, it was decided on 6/20/2012 that dosimetry use could be safely suspended. Should use
of more energetic isotopes be proposed in the future, resumption of dosimeter use could result
based on potential exposures and RSO / Radition Safety Committee actions.
Investigational Levels
(mrem per calendar quarter)
Level I Level II
1. Whole body (total
effective; dose
equivalent)
125
375
2. Lens of eye 375 1125
3. Skin; extremity; organs
other than the eye
1250
3750
Please remember that you are responsible for using your dosimeter correctly. The accuracy of the
exposure measurements depends on proper use of the dosimeter.
If you have any questions concerning personal dosimeters or radiation safety, please contact the
Radiation Safety Officer at 780-5406.
21.0 Radiation Safety Surveys
Surveys utilizing a survey instrument appropriate to the energy and allowable radiation levels must be
conducted in all areas on a routine basis and whenever contamination is suspected.
The frequency of surveys depends on the classification of the laboratory (see previous section,
“Laboratory Classification”).
1. Work areas in Type A laboratories must be surveyed each day of use.
2. Work areas in Type B laboratories must be surveyed weekly.
3. Work areas in Type C laboratories must be surveyed monthly.
4. Any area that is used by more than one research group must be surveyed before and after use by any
individual or research group.
5. The package receipt area must be surveyed after any package is opened.
6. The action level for any controlled area is 0.5 mR/hr. For uncontrolled areas, the level is 0.05 mR/hr.
7. All Surveys must be documented. (See appendix L)
25
22.0 Wipe and Leak Tests
Wipe tests of areas that may be contaminated with radioactive material and leak tests of sealed sources
must be assayed on instruments appropriate to the energy and allowable radiation levels. Tests must be
performed on a routine basis, as described below, and whenever contamination is suspected.
The frequency of surveys depends on the classification of the laboratory:
1. Work areas in Type A laboratories must be wipe tested daily.
2. Work areas in Type B laboratories must be wipe tested weekly.
3. Work areas in Type C laboratories must be wipe tested monthly or upon completion of work with an
isotope.
4. Any area that is used by more than one research group must be wipe tested before and after use by any
individual or research group.
5. The package receipt area must be wipe tested after any package is opened. (See appendix M)
a. All wipe test results must be documented.
b. Action levels depend on the radiotoxicity of the radionuclide. They are (in DPM/100 cm2):
RADIOTOXICITY
Action Levels – Decontaminate if wipe level meets or exceeds theses DPM limits
Very High High Moderate Low
Restricted areas 200 2000 2000 20,000
Unrestricted
areas
20 200 200 2000
23.0 Bioassays
Bioassays will be performed on all personnel who handle un-encapsulated sources of tritium (H-3), I-
125 or I-131 above specified amounts to assure that the amount of material retained by the body is
below acceptable limits. (See appendix N)
1. Tritium (H-3): Any individual who handles more than 10 mCi of tritium in a single day in unsealed,
dispersible or volatile forms will receive a bioassay. The assay must be conducted within the calendar
month in which the material was used. A liquid scintillation counter will be used to assay urine samples
provided by the employee. Any results greater than 4 uCi/l or urine must be reported immediately to the
RSO.
2. I-125 or I-131: Any individual who handles more than 1 mCi of either I-125 or I-131 in a single day in
an open room or bench, or who handles more than 10 mCi in a single day in an adequately designed
fume hood must receive a bioassay. Persons handling solid forms or sealed sources are exempt from
this requirement. For I-125, the assay must be conducted between 24 and 96 hrs after the material is
26
handled. For I-131, the assay must be conducted within 3 days after handling. The assay will be
conducted by measuring the thyroid burden in-vivo.
A scintillation detector appropriately set for the isotope in question will be used. Any results greater
than 0.12 uCi of I-125, or 0.04 uCi of I-131 must be reported to the RSO immediately. Any results in
excess of 0.5 uCi for I-125 or 0.24 uCi for I-131 will require therapeutic counter-measures.
24.0 Procedure for use of Survey Meters
All the survey meters are battery operated portable radiation detection instruments. A Geiger-Muller probe
is attached to each unit with a cable. The steps given below should be followed when making a radiation
survey:
1. Inspect the instrument for mechanical defects such as a broken dial, loose knob, or frayed cable.
2. BATTERY CHECK: Turn the range switch to "BAT". The meter needle should deflect to the "BAT.
TEST" portion of the meter scale. Contact the University Environmental Health and Safety office if the
needle does not deflect to the correct region. This may be an indication that new batteries are needed.
3. BACKGROUND MEASUREMENT: Be sure that you are in an area where only natural background
radiation is present. Turn the range switch to X0.1. Remove the probe from its holder, and hold it as far
away as possible from the check source. Read the appropriate scale on the meter and multiply the reading
by 0.1 to determine the exposure rate in mR/hr.
4. CHECK SOURCE TEST: Turn the range switch to the appropriate setting. A check source is attached to
the side of the meter. Lift the cover of the check source box, exposing the surface of the source. Remove
the probe from its holder and place the probe face directly against the check source box, making sure it is
centered. Read the meter and compare the reading with the expected value listed on the calibration sticker
on the side of the instrument. The reading on the meter and the expected value should agree to within +/-
5%. If the reading is not within this tolerance, check to see that the probe face is centered to the check
source, and that the correct range has been chosen. If the problem persists, contact the University
Environmental Health and Safety office.
5. AUDIO TEST: While the probe is still next to the check source, turn the audio switch on and check that
it functions. The audio switch may be turned off if its use to not desired.
6. MEASUREMENTS: Turn the range switch to X0.1. Remove the probe from its holder and hold the
probe face 1 cm away from the surface to be surveyed. Move the probe slowly over the entire surface
that is being surveyed. Read the appropriate scale on the meter and multiply the reading by 0.1, to
determine the exposure rate in mR/hr. (If the needle is off-scale, turn the range switch to X1 or X10 and
survey the area.)
7. When all surveys are completed and recorded, turn the audio switch and the range switch to their "OFF
positions.
a. This survey meter has a calibration label which states the date its next calibration is due. Contact
the University Environmental Health and Safety office approximately one month prior to this due
date to arrange for calibration and batter replacement.
b. Calibration is performed annually, as required by USM’s Limited Scope Materials License.
c. The procedure for use of the BETA COUNTER is posted with the instrument in the laboratory.
27
25.0 As Low As Reasonably Achievable (ALARA) Policy
The Radiation Safety Committee and RSO of USM is committed to the program described herein for
keeping individual and collective doses as low as reasonably achievable (ALARA). In accordance with
this commitment, we hereby describe an administrative organization for radiation safety and will
develop the necessary written policies, procedures and instructions to foster the ALARA concept within
USM.
1. The RSO will report the status of the radiation safety program, including ALARA considerations to the
RSC at least annually. This will include reviews of operating procedures as well as past dose records,
inspections, etc. and consultations with outside consultants.
2. Modifications to operating and maintenance procedures and to equipment and facilities will be made if
they reduce exposures unless the cost is considered to be unjustified. The RSO will be able to
demonstrate, if necessary, improvements have been sought, that modifications have been considered and
that they have been implemented when reasonable. If modifications have been proposed but not
implemented, the RSO is prepared to describe the reasons for not implementing them.
3. In addition to maintaining doses to individuals as far below the limits as is reasonably achievable, the
sum of the doses received by all exposed individuals will also be maintained at the lowest practicable
level.
4. The RSC based on advise from the RSO established the investigational levels listed below in Tables A
and B. The RSO will perform regular reviews of occupational exposures with particular attention to
instances in which the investigational levels are exceeded. The principle purposes of this review are to
assess trends in occupational exposure as an index of the ALARA program, and to decide if action is
warranted when investigational levels are exceeded.
5. The RSO will also perform monthy radiation surveys.
6. The Radiation Safety Committee will audit the RSO activities at least annually.
TABLE A
INVESTIGATIONAL LEVELS - GENERAL
AREA MPD INVESTIGATIONAL LEVELS
(mrem/year) I (mrem/qtr) II (mrem/qtr)
Whole Body (Deep) 5,000 125 375
Eye 15,000 375 1125
Skin and Extremities
(Shallow)
50,000 1250 3750
7. The RSO will schedule briefings and educational sessions to inform workers of ALARA program
efforts.
28
8. The RSO will ensure that authorized users, workers and ancillary personnel who may be exposed to
radiation will be instructed in the ALARA philosophy and informed that management and the RSO are
committed to implementing the ALARA concept.
9. Radiation workers will be given an opportunity to participate in formulating the procedures they will be
required to follow. The RSO will keep in close contact with users and workers and will receive and
evaluate suggestions of individual workers concerning ALARA.
10. Results of personnel monitoring will be compared to the investigational levels established in Tables A
above.
a) If an individual’s dose is less than Investigational Level I, no action will be taken.
b) If an individual’s dose is higher than Investigational Level I, but less than Investigational Level
II, the RSO will compare the dose to that of other workers in the same category, and will
investigate possible causes and corrective actions for the higher level.
c) If an individual’s dose is higher than Investigational Level II, the RSO will investigate in a
timely manner the cause of the reading and will take corrective action.
d) In cases where a worker's or group of workers' doses need to exceed an investigational level, a
new, higher investigational level may be established, provided it is consistent with good ALARA
practices. Justification for establishment of a new level will be documented.
26.0 Audits
1. Radiation Safety Officer (RSO): The RSO will perform audits at least biannually to insure compliance
with all applicable policies, procedures and regulations. Additional special audits may be performed
when circumstances require them. Inspections may be unannounced. Facilities will be inspected at a
level consistent with the risk of the operations. At a minimum, the following areas will be examined:
a) Review of inventory.
b) Review of user surveys.
c) Review of handling of waste.
d) Review of safety procedures and policies.
e) Evaluation of user and technician.
f) Independent survey of radiation levels in area.
g) Evaluation of compliance with any limitations listed in RSC permits.
The RSO will report the findings to the Radiation Safety Committee during committee meetings and
following any special inspections that may be required.
2. Radiation Safety Committee (RSC): The RSC will review the Radiation Safety Officer’s audits.
29
27.0 Wipe Test Instructions
1. Purpose: To detect/prevent the spread of radioactive contamination in laboratory and working areas.
(See appendix M)
2. Equipment and Materials:
a) Geiger Counter
b) Surfactant
c) 8 – 4ml scintillation counter vials.
d) 8 – Cotton swabs, 6”
3. Reagents:
a) Scintillation fluid
b) 50 mm
4. Wipe Test Procedure:
a) Place 8 scintillation counter vials in the white scintillation vial holder (#1450-117 4ML TUBE).
Use the layout below (STD may be found in the refrigerator and will be added later).
b) Use Geiger counter to survey every tested area prior to wipe testing.
c) Use a small amount of surfactant over area to be tested (4in. x 4in. square).
d) Swab area uncovered by template with cotton tipped applicators.
e) Place swab scintillation vial.
f) Break swab off just above cotton tip to permit closure of tube.
g) Add 3.0 ml of scintillation fluid to each vial.
h) Place properly labeled/numbered cap on each vial.
i) Obtain uranyl acetate standard and scintillation fluid reference from refrigerator and place in
scintillation holder.
This End Enters Microbeta
B1
6
B2
5
7
1
8
2 3
STD
4
30
j) To make: Add 2.8 ml of scintillation fluid to 4 ml vial. Carefully add 700 uL of 50 mM UAC to
4mL scintillation vial to create 10mM standard.
k) Place the black tube-block over scintillation vials positioned in the vial holder.
5. Areas to be tested: (see attached lab maps):
a) B1: Background 1, Q-tip surfactant in 3.0 mL scintillation fluid.
b) B2: Background 2, Q-tip with surfactant in 3.0 mL scintillation fluid.
c) Door handle from hallway into prep lab.
d) Door handle from prep lab into hallway.
e) Inside the fume hood in prep lab.
f) Door handle from prep lab to tissue culture.
g) Door handle from tissue culture to prep lab.
h) Inside BSC reserved for radioactive substances.
i) 10ul pipette for radio chemical use (where tip is put on).
j) 200ul pipette for radio chemical use (where tip is put on).
k) 1000ul pipette for radio chemical use (where tip is put on).
l) Pipetboy#6
m) Mixer.
n) Centrifuge.
o) Side of outer door (where you place your hand to open door) of incubator #7.
p) Wall in the hallway (in area known to be free of isotope migration).
q) Supplemental areas may be tested that are deemed necessary by the tester at time of testing.
6. Operating Scintillation Counter:
a) Turn on scintillation counter (switch in back of machine). If machine is not already on, wait
until READY appears in the lower right hand corner of the Microbeta window.
b) Place scintillation counter holder in scintillation counter at position 1.
c) Make sure the end with two holes is facing in toward the machine.
d) Put STOP plate in next available slot.
e) Click on PROTOCOLS icon on taskbar.
f) Select GENERL and click OPEN.
g) Another window will open and select SWIPE TEST.
h) Check PLATE MAP making sure all 12 spots and stand spot are labeled and click START.
i) A manual start window will open and click START again.
j) A live action window will open and the machine will start counting your samples.
k) If machine does not start counting your samples or is acting strange, remove the scintillation
holder, turn off scintillation counter and then turn it back on. Once READY appears in the lower
right hand corner of the software application window, try counting again.
l) Record CPM on wipe-test record sheet.
m) Locate wipe-test conversion spreadsheet at Common Drive: Protocols\Instructions\Wipetest
Conversion Spreadsheet.
n) Enter CPM values in Excel Wipe Test Spreadsheet. Spreadsheet automatically calculates Net
CPM, Dpm & Efficiency. Record these values on the wipe test record sheet. Report any
negative numbers as ZERO.
o) Repeat testing for above action levels. Clean area with RadCon and Wypall paper towels,
repeat test, record test results.
i. Action Level for U-238 is greater than 20 Dpm
p) Report wipe tests 5X above action levels. i. 5X action level for U-238 is greater than 100 Dpm
31
Appendix A
UNIVERSITY OF SOUTHERN MAINE
PORTLAND MAINE
SPILL REPORT
Date: ______________Time:___________Location:______________________________
Personnel Present: ________________________________________________________
Radioisotope: _________________Activity:________________uCi
Give a brief description of the circumstances of the spill:
_______________________________________________________________________
_______________________________________________________________________
Briefly describe clean-up actions taken:
_______________________________________________________________________
_______________________________________________________________________
Wipe Test Results
Counter Used/SN: ____________________________Counter efficiency: ______________
Results of wipe tests in DPM for all tests done: __________________________________
_______________________________________________________________________
_______________________________________________________________________
Describe any follow-up actions taken to prevent recurrence:
_______________________________________________________________________
_______________________________________________________________________
Name: _____________________________ Date: ______________________________
Use additional pages as needed.
Send form to University Environmental Health and Safety office
32
Appendix B
UNIVERSITY OF SOUTHERN MAINE PORTLAND, MAINE
RADIATION SAFETY COMMITTEE
APPLICATION FOR AUTHORIZED USER
NON-HUMAN USE OF RADIOACTIVE MATERIAL
Please type or print.
PURPOSE OF APPLICATION: ____ New application
____ Amend Existing Authorization
DATE: ______________
PERSONAL DATA
Name: ___________________________ Phone/Beeper #:______________
Department: _____________________ Phone in usage area #: _____________
Requirements for training and experience vary depending on the types, amounts and usages of radioactive
material. Current requirements are listed in the State of Maine Rules Relating to Radiation Protection (10-144A
CMR 220). A summary of the requirements as of the date of preparation of this guide is given below.
Applicants should verify the details of the requirements, and determine that they meet the current version at the
time of their application.
I. BASIC RESEARCH (INCLUDING IN-VITRO AND IN-VIVO RESEARCH) (10-144A CMR
220.A.2.A(122)
A. College degree at the bachelor level, or equivalent training and experience, in the physical or
biological sciences or engineering
AND
B. Training and experience in the safe handling of radioactive material, and in the characteristics of
ionizing radiation, units of radiation dose and quantities, radiation detection instrumentation, and
biological hazards of exposure to radiation appropriate to the type and forms of radioactive
material to be used. The amount of this training and experience shall be commensurate with the
risk associated with the material to be used.
33
Appendix B
II. NOTES
A. The requirements given above may be assumed to have been met if the applicant can provide
evidence of being a named user with the privileges requested on another current NRC or
agreement state license,
B. Training and experience shall have been obtained within the five years prior to the date of
application or the applicant shall have had continuing applicable experience since the required
training and experience was completed.
[] Please indicate here if you are a named user on a current NRC or agreement state license issued to
another facility. Enclose documentation.
[] Please indicate here if you are not a named user on a current license. Complete the enclosed State of
Maine form and include documentation to support the training and experience listed on the form. If you
have questions, please call the Radiation Safety Officer prior to completing the forms.
Signature of Applicant: ________________________________________
University of Southern Maine
Portland, Maine
34
Appendix C
UNIVERSITY OF SOUTHERN MAINE PORTLAND, MAINE
RADIATION SAFETY COMMITTEE
APPLICATION FOR AUTHORIZED
NON-HUMAN USE OF RADIOACTIVE MATERIAL
Please type or print.
PURPOSE OF APPLICATION: ____ New or renewal application
____ Amend Existing RSC Authorization # ___
DATE:___________
1. Authorized User - Person who will be responsible for all aspects of use and possession of radioactive
material used under this authorization.
Name: __________________________ Phone/Beeper #:________________
Department: _____________________ Phone in usage area: __________
Cost Center: ____________________
2. Approval is requested for use of the following radioactive material:
TABLE I
Radionuclide
Chemical
and/or Physical
Form
Max. Amt. per
Experiment
Max. Amt.
Ordered
Max.
Waste
Stored
Total
Possession
Limit
3. Purpose: ______________________________________________________
_______________________________________________________________
35
Appendix C
4. List each
individual who will be working with radioactive material under this authorization.
TABLE II
NAME
SSN
DOB
TITLE/JOB
CLASSIFICA-
TION
TRAINING
RECEIVED
Will radiation badge monitoring be needed for the above personnel?
No _______ Yes __________
5. List each physical place where radioactive material will be used and stored under this authorization.
TABLE III
BUILDING ROOM NUMBER
ROOM USE (i.e. storage, walk-in
refrigerator, iodination counting, etc.
RSC USE ONLY
Approved ________ Renewed___________ Amendment________
RSC Authorization # _________________ Expires _________
_____________________________________ Date: ___________
RSC Approval
36
Appendix C
6. Attach a simple drawing of the storage and usage area(s) described above. Note the following:
approximate dimensions, adjacent areas (i.e. hallway, office, etc.), radioactive material storage,
radioactive waste storage, shielding, counters, safety equipment (i.e. hoods, survey meters, etc.)
7. Describe individually your proposed procedure or experimental design of each chemical/physical form
listed in item #2 of this application. Include a description of any special procedures that you and/or your
staff will follow to ensure the safe use of the radioactive material requested. If a written protocol exists
this may be supplied instead.
8. Do you intend to transfer any radioactive material to other Authorized Users?
_____ Yes _____ No
If yes, list each recipient:
________________________________________________________________
________________________________________________________________
9. Will radioactive material be administered to animals?
_____ Yes _____ No
If yes, complete the following:
A. Type, total number, and average weight of animals to be used:
____________________________________________________________
B. Maximum activity (mCi) per animal: _________________________
____________________________________________________________
C. Has written approval been received by the Animal Care Committee? _____ Yes
_____ No
D. If animals will not be sacrificed immediately, indicate:
Where animals will be housed: ______________________________
Who will provide animal care: ______________________________
Attach written instructions that you will provide to animal care personnel for the safe handling of
radioactive animals, radioactive animal waste, and animal carcasses.
10. Will this project involve tritium (H-3) or radioiodinated material that equals or exceeds the amounts in
TABLE IV?
_____ Yes _____ No
37
Appendix C
TABLE IV
Type of Use Radioiodine Volatile
Unsealed Form
Radioiodine Bound to
Non-Volatile Agent
H-3
Any Form
Open Room or Bench 1 mCi 10 mCi 10 mCi
Approved Fume Hood 10 mCi 100 mCi 100 mCi
If YES, attach your bioassay procedure for ensuring the safety of individuals who will conduct these
activities in accordance with the guidelines established by the State of Maine.
11. List each commercially available sealed source to be used under this authorization. Be sure to include
sealed sources that are used as “check” or calibration sources for scintillation counters.
TABLE V
RADIONUCLIDE ACTIVITY
(mCi)
MANUFACTURER
& MODEL #
CALIBRATION
DATE
LOCATION
12. GENERAL RADIATION SAFETY PROGRAM - confirm the following to ensure optimum radiation
safety practices and that exposures to all concerned are As Low As Reasonably Achievable (ALARA).
A. All required documents and notices will be posted
(Include State of Maine Materials License, State of Maine Notice to Employees)
_____ Yes _____ No
B. Operating procedures are posted or can be easily referenced by lab personnel (Include General
Radiation Safety Procedures, Emergency Spill Procedures, Procedure for ordering and receiving
radioactive materials, Waste Disposal procedure, Laboratory or experiment protocols)
_____ Yes _____ No
38
Appendix C
C. Personnel monitoring will be provided as required and dosimetry reports are posted
_____ Yes _____ No
D. Radiation survey procedures will be performed and documented for review (Include day of use
operational checks of survey meters, area surveys and contamination wipe tests, wipe test
frequency, and area survey frequency)
_____ Yes _____ No
E. Documentation is maintained of current radionuclide inventory at all times (Include records of
receipt, radionuclide dispersement and radionuclides disposed or held for decay)
_____ Yes _____ No
13. RADIOACTIVE WASTE DISPOSAL - Indicate the anticipated waste categories to be produced from
your procedures. Include volumes and activities.
TABLE VI
TYPE OF
WASTE
VOLUME
(FT3) OR (ml)
ACTIVITY
(mCi)
PER MONTH PER YEAR PER MONTH PER YEAR
Solid __YES __ NO
Aqueous
Liquid
__YES __ NO
LSC Vials __YES __ NO
Animal
Carcasses
__YES __ NO
Gaseous or
Volatile
__YES __ NO
NOTE: Space for radioactive waste both institutionally and nationally is at a premium. Make
every attempt to reduce all volumes of waste to a minimum via compaction and/or
disposal of only those items that are confirmed radioactive!!
39
Appendix C
14. INSTRUMENTATION - List all instrumentation that will be used to implement your radiation safety
program, such as survey meters, scintillation counters, etc.
TABLE VII
INSTRUMENT TYPE
(GM, Ion Chamber, NaI, etc.)
MANUFACTURER & MODEL # CALIBRATION
SCHEDULE
15. ALARA (As Low As Reasonably Achievable) Responsibility:
A. The Authorized User will consult with, and receive the approval of the RSO and/or RSC during
the planning stage before using radioactive materials for a new procedure.
B. The Authorized User will evaluate all procedures before using radioactive materials to ensure
that exposures will be kept ALARA. This may be enhanced through the application of trial runs.
C. The Authorized User will explain the ALARA concept and his/her commitment to maintain
exposures ALARA to all of those he/she supervises.
D. The Authorized User will ensure that those under his/her supervision who are subject to
occupational radiation exposure are trained and educated in good health physics practices and in
maintaining exposures ALARA.
16. Any changes, deletions, additions, moves and/or discontinuances of usage of radioactive materials
within this institution other than what is represented above must be submitted to the Radiation Safety
Committee for review and approval. It is your responsibility as the Authorized User of radioactive
material to fulfill this requirement. By your signature below, you hereby confirm and accept this
responsibility, and you attest that the information is accurate and correct.
40
Appendix C
I have read, understand, and agree to comply with the contents of the current Radiation Safety Program.
This project and application was reviewed and approved by the Division/Department Director.
Signature of Authorized User: ________________________________________
Signature of Division/Department Chairman: ___________________________
University of Southern Maine
Portland, Maine
41
Appendix D
X-ray Safety Information
X-RAY CONCERNS AND PRECAUTIONS
There are several properties of X rays that make this type of radiation particularly dangerous to use in
the laboratory. X-Ray radiation cannot be sensed by humans, but some people can feel the presence of a kind of
"tingling sensation" which arises from charged air particles produced by the interaction of the ionizing X rays
with air. X-Ray radiation is also hazardous because it can appear to "bounce" off surfaces and to "bend" around
corners. This makes it important to survey each instrument for leaks after any modifications to the instrument.
At the University of Southern Maine, these checks are conducted by the campus Radiation Safety Officer.
Although X-ray instruments have the potential to be dangerous, when used improperly, modern diffraction X-
ray instruments pose few risks to careful users. The manufacture and use of analytical X-ray instruments is
regulated by both the federal and state governments. Current regulations require a variety of safety devices
be built into X-ray instruments that make it very difficult for anyone to even accidentally expose themselves to
the dangerous incident X-ray beam. The design of the instruments limits even accidental exposures to the hands,
arms and facial areas. Also, the types of radiation used in diffraction instruments (primarily Mo, Cu, and Kα
radiation) are considered "soft" radiation. These types of soft radiation generally will not penetrate more than 2-
4 cm into the body.
Possible Health Effects
To date there have been few accidental exposures in X-ray diffraction labs, and the physical ailments from these
accidents have been relatively minor. Because of the soft nature of radiation used in a diffraction lab, accidental
exposure to X-ray radiation will usually cause damage only to the skin and possibly bones near the surface of
the body. Depending on the nature and extent of exposure some or all of the following medical problems may
ensue.
Often at the time of exposure, little or no pain is felt. However, 1-3 hours later, a first- degree burn forms on the
skin and a dull pain settles in all exposed tissues. Sometimes this is followed by swelling that turns into blisters
that finally open and do not seem to heal over. In extreme cases, skin grafts and/or amputation are required.
Exposure of soft X rays to the eyes may cause permanent cataracts to form. Because of the possibility of
cataracts forming, it is recommended that glasses be worn in an X-ray diffraction lab whenever instruments are
modified or aligned.
As with all types of ionizing radiation, X Rays cause the most damage to rapidly growing,
undifferentiated cells. Thus, women that are pregnant or suspect that they are pregnant, should take special
care to protect their fetus, especially during the first trimester. Women that are pregnant or suspect that
they are pregnant and wish to avoid exposure should contact the lab director in order to make arrangements to
get data collected by someone else during the course of their pregnancy.
42
Electrical Hazard
Another serious hazard from an X-ray diffraction instrument is electrical shock. The X- ray generator is a highly
regulated DC power supply that operates at applied voltages of 40 to 60 kV in order to achieve an optimum flux
of X rays. Also, the power supply that feeds the detector operates at about 1 kV. These power supplies should
only be serviced by trained electrical engineers. Also note that the X-ray generator has several large capacitors.
Even when the instrument is turned off, these capacitors store sufficient power to injure and possibly kill a
person. All work on any X-ray generator should be done only by personnel trained in high-voltage electronics.
Safety Procedures
1. All users of x-ray producing equipment must first become "authorized users" by completing the
requirements of the USM Radiation Safety Program. They must also read the safety information above
and agree to abide by the following rules.
2. No unauthorized personnel may defeat or override any safety features on the X- ray generators, the
safety enclosures, or the goniometers including the collimators, tube shields and shutters.
a) No user may employ any power or hand tool on any part of the goniometer, detector, or low
temperature device without express instructions from the lab director. The single exception to
this rule involves the use of specific wrenches to adjust the position of the sample on the
goniometer head and to adjust the position of the video camera to view the sample.
b) All actual or suspected X-ray exposures of any person should be handled in the following
manner.
3. Medical emergencies must be treated according to the Workers Compensation Program
requirements. Call 911 for emergency transport.
4. If the exposure was due to a malfunction of the instrument, depress the red "X-RAY OFF” button on the
either side of the generator before leaving the lab. If time permits tape a message to the front of the
instrument noting "INSTRUMENT PROBLEM" and include your name, the date and your telephone
number.
5. Report the incident to the University of Southern Maine Radiation Safety Officer at 780-5406 and to the
X-ray device owner. If medical treatment is required, notify the chairman of your department.
Small electrical fires may be put out by using fire extinguishers located in the lab.
Larger fires and medical emergencies should be handled as described in your department's safety meetings. In
the case of large room fires or major water leaks, be sure to turn off the X rays by pressing the red "X-RAY
OFF" button on the front of all X-ray generators. Be sure to contact the lab director for any lab-related
problems.
43
Appendix E
Radiation Safety Inspection
Radiation Safety Officer
Date:
License:
Radiation Safety Committee:
Radiation Safety Training:
General and Radiation Worker training provided:
Exposure Review:
Badges Reviewed Exposures in excess of 10% of limit Exposures in excess of 25% of limit
Note:
Surveys conducted:
Yes/No Issues
Wipe tests performed weekly
Radiation surveys performed
Survey meters available:
Locations Inspected (Science Building, USM @ Portland):
1. Radioactive Core Facility
2. Radioactive Waste Room
3. Duboise Laboratory
4. Wise Laboratory
44
Appendix E
Safety Features Observed - YES/NO
Facility Core Facility Radwaste Room Duboise Lab Wise Lab
Radioisotope/s: P-32/C-14/U-238 All used Uranium Uranium
Posting available
Radmat labeled
Lab Coat available
Gloves available
Safety glasses
available
Shielding available
Survey meter
available
Absorbent pads
available
Fume hood available
Radwaste Containers
available
No food/beverage
Radioactive material
secure
Inventory:
Radioactive Core Facility - Contents
Refrigerator Wise Lab
Duboise Lab
Moore Lab
Freezer Moore Lab
Fume hood
Waste
45
Appendix E
Radioactive Waste Storage Room - Contents
Survey of Facility:
Survey Instrument: Model 14C Ludlum Geiger counter Serial number:
Results:
____________________
Radiation Safety Officer
Date: _________
Facility Location Dose rate (mr/hr) < 0.1
Background
Core Facility Beta counter and countertop (Area A)
Sink (Area B)
Work area (Area C)
Receiving area (Area D)
Freezer
Refrigerator
Hood (at window) and below hood
Faxitron x-ray unit
Gamma counter
Red Bag waste
Normal trash
P-32 trash can (at side of can)
Notes:
46
Appendix F
CABINET X-RAY INSPECTION FORM
Location: Manufacturer: Model:
Serial #: State License #: Date:
ITEM # YES / NO INSPECTION ITEM 1 Permanent Floor
2 Exclusion of Any Part of the Human Body
3 Presence of Safety Interlocks
First Interlock: Independent Switch on Door
Second Interlock: Independent Switch on Door
4 Need to Reset Control After Interruption
5 Beam-On Indicators
First Indicator: Light on Control Panel
Second Indicator: Timer Operation
6 Presence of Key Operated Control
7 Warning Label (Caution: X-Rays Produced When Energized)
8
Port Warning Label (Caution: Do Not Insert Any Part of The
Body When System Is Energized – X-Ray Hazard)
9 Presence of Manufacturer’s Operating (and Installation) Manual
10 Presence of Manufacturer’s Suggested Maintenance Schedule
11 Evidence of Operator Competence
12 Use of Personal Monitoring and Maintenance of Records
Corrective Actions Needed
ENVIRONMENTAL MEASUREMENTS Operating Conditions: 130kVp, 5mA Limit 0.5 mR/hr at 5 cm from surface
Survey Instrument: Manufacturer
Model
Serial #
Last Calibration Date
Check Source Reading
Survey Location: Reading (mR/hr) Comments Background
Cabinet/Control Unit
Seam
All Other Surfaces
Location of Inspection Date Individual Conducting Inspection - Printed
47
Appendix G
UNIVERSITY OF SOUTHERN MAINE
PORTLAND, MAINE RADIOACTIVE SHIPMENT RECEIPT FORM
DATE: TIME:
BOX/LOT NUMBER: P.O. NUMBER:
RADIONUCLIDE: SURVEYOR:
CONDITION OF PACKAGE: O.K. PUNCTURED CRUSHED WET
RADIATION UNITS ON LABEL: WHITE-I YELLOW-II YELLOW-III
TRANSPORT INDEX (TI):
MEASURED LEVELS: (CHECK ACTION LEVELS BELOW)
SURVEY METER MANUF: M/N: S/N:
BACKGROUND: mr/hr CHECK SOURCE: mr/hr 3' FROM SURFACE: mr/hr SURFACE: mr/hr
COMPARISON OF PACKING SLIP AND CONTENTS
RADIONUCLIDE: OK OTHER:
AMOUNT: OK OTHER:
CHEMICAL FORM: OK OTHER:
WIPE TEST (AREA WIPED = 300 cm2)(CHECK ACTION LEVELS BELOW)
INSTRUMENT MANUF: M/N: S/N:
BGND: CPM SAMPLE: CPM NET: CPM
COUNTER EFFICIENCY: ACTIVITY: DPM
SURVEY OF EMPTY PACKAGING MATERIAL: mR/hr
ACTION LEVELS
WHITE I YELLOW II YELLOW III
3’ FROM PACKAGE SURFACE (TI) N/A 1 mR/hr 10 mR/hr
PACKAGE SURFACE <0.5 mR/hr 50 mR/hr 200 mR/hr
WIPE TEST 22 dpm/cm2 22 dpm/cm2 22 dpm/cm2
48
Appendix H
UNIVERSITY OF SOUTHERN MAINE PORTLAND, MAINE
RADIOACTIVE MATERIALS TRACKING FORM
Laboratory:___________________________________________________________
Authorized User:_______________________________________________________
DATE Amount Used (uCi)
Amount Placed in
Waste (uCi)
Initials Notes/Comments
Record Reconciled by:__________________________________________________ (signature)
49
Appendix I
UNIVERSITY OF SOUTHERN MAINE PORTLAND, MAINE
QUARTERLY INVENTORY OF SEALED SOURCES
DATE: _________________
PERFORMED BY: _______________________
NUCLIDE ACTIVITY CALIB. DATE
FORM MODEL SERIAL LOCATION PRESENT
NOTES: RSO: _____________________________ Date: __________________
50
Appendix J
UNIVERSITY OF SOUTHERN MAINE
PORTLAND, MAINE
RADIOACTIVE WASTE DISPOSAL FORM
Approx Qty
mg/uci
DATE PLACED
IN STORAGE
DATE REMOVED
FROM STORAGE
Type of Waste
Liq./Solid
BKGRD (mR/hr)
Actual READING (mR/hr)
FINAL DISPOSAL
TO:
Survey Meter make:_______________________
Serial #: ________________________
51
Appendix K
UNIVERSITY OF SOUTHERN MAINE PORTLAND, MAINE
APPLICATION FOR PERSONAL DOSIMETER
1. Name:______________________________________________________________ 2. Birthdate: _________________ 3. Social Security #: ___________________ 4. Department/Supervisor: _______________________________________________ 5. Check the statement that applies to you: _____ I will be working directly with radioactive materials. _____ I will be working in situations where I will be present in a room while radioactive
materials are being used. 6. Please check either A or B. (A) ____ I have never been issued a film badge or personal dosimeter by any previous place of
employment. (B) ____ My occupational radiation exposure history may be obtained from: NAME & MAILING ADDRESS: DATES EMPLOYED ________________________________________________________________ ________________________________________________________________ ________________________________________________________________ 7. If you completed Part B in #6, please sign the authorization at the bottom of this page so that
your previous radiation exposure can be obtained and added to your exposure history at USM. 8. Please send this application to: Radiation Safety Officer University Environmental Health and Safety Department University of Southern Maine PO Box 9300 Portland, ME 04104
AUTHORIZATION FOR RELEASE OF PREVIOUS RADIATION EXPOSURE HISTORY I hereby authorize the release of information concerning my past radiation exposure to the Radiation Safety Officer, University of Southern Maine, PO Box 9300, Portland, ME 04104. Signature:______________________________ SS#:_______________Date:__________
UNIVERSITY OF SOUTHERN MAINE
Appendix L - RADIATION SURVEY FORM
52
MONTH: _______________ YEAR: _______ INSTRUMENT: _______________________________
TRIGGER LEVELS: Restricted areas >0.5 mR/hr – Unrestricted areas >0.05 mR/hr (Use Wipe Location Map)
DATE S/N BKG CHK 1 2 3 4 5 6 7 8 9 10 11 INIT.
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
Appendix M
53
UNIVERSITY OF SOUTHERN MAINE
PORTLAND, MAINE
MONTHLY WIPE TEST FORM
INSTRUMENT: _______________________ S/N__________________
ACTION LEVELS
RESTRICTED AREAS: 200 DPM/100 cm2 UNRESTRICTED AREAS: 20 DPM/100 cm2
Wipe locations (Use Wipe Location Map)
DATE BKG BKG STD 1 2 3 4 5 6 7 8
CPM
NET --- ---
DPM/100 cm2 --- ---
CPM
NET --- ---
DPM/100 cm2 --- ---
CPM
NET --- ---
DPM/100 cm2 --- ---
CPM
NET --- ---
DPM/100 cm2 --- ---
CPM
NET --- ---
DPM/100 cm2 --- ---
CPM
NET --- ---
DPM/100 cm2 --- ---
54
Wipe Location Map
(Use for numbering wipe locations)
Date of Wipe test: ____________________
Performed by: _______________________
Sink Frig A
Fume Hood Frig B
Door A
Door B
Core Lab
A C B
Faxitron
Detector
55
Appendix N
UNIVERSITY OF SOUTHERN MAINE
PORTLAND, MAINE
BIOASSAY FORM
NAME:________________________________ DATE:__________________________ INSTRUMENT:______________________ S/N:_______________ EFF:____________
A ROOM
BACKGROUND (CPM)
B SUBJECT
BACKGROUND (CPM)
C SUBJECT THYROID
(CPM)
D NET
COUNT (CPM)
E NET
DISINTEGRATIONS (DPM)
F NET
ACTIVITY (uCi)
If B is more than twice A, notify RSO D = C – B E = D/Eff. F = E/( 2.22 x 106 ) NOTES:
RSO: ______________________________ Date: ____________________
56
Appendix O
UNIVERSITY of SOUTHERN MAINE ENVIRONMENTAL HEALTH & SAFETY
Declaration of Pregnancy
In accordance with NRC regulations in 10CFR20.1003 and 20.1208, a pregnant woman who wishes to control radiation dose to the fetus/embryo resulting from occupational exposure, must voluntarily and, in writing, declare her pregnancy to her employer, so that the employer may apply the fetal dose limits set forth in 20.1208. The Nuclear Regulatory Commission requires that the estimated date of conception be provided to allow the employer to calculate the cumulative fetal dose.
In accordance with 10CFR20.1003 and 20.1208, I am declaring my pregnancy. The estimated date of
conception is .
Signature Date (PLEASE PRINT) Name
Social Security Number
Department
Supervisor
Email address
Phone
Are you occupationally exposed to sources of radiation at a place of work other than the University of
Southern Maine? Yes No
If yes, please provide the name and address of any other places of work:
Return by campus mail to: University Environmental Health & Safety Office, 88 Bedford St., Abromson Center,
Portland, ME 04104
