MICHAEL E. DEBAKEY VA MEDICAL CENTER

RADIATION SAFETY HANDBOOK

RESEARCH SUPPLEMENT

A quick reference guide to radiation safety

questions and problems commonly encountered

in the laboratory

Prepared by: Jeffrey G. Triebel

Radiation Safety Officer

November 1991

Revised: 9/8/04 by Stan Bravenec, Asst. RSO

TABLE OF CONTENTS

Section Page

I. Radiation Physics

A. The atom 1

B. Radioactivity 1

C. Interaction of radiation with matter 2

D. Activity, Exposure, and Dose 2

II\. Radiation Safety

A. Radiation Effects and Risks, ALARA, and Pregnancy Concerns 4

B. Reducing Exposure 6

C. Posting Signs and Storing Material 7

D. Ordering and Receiving Radioactive Materials 7

\- Package receipt and delivery

\- Transferring radioactive material

E. Laboratory Monitoring 8

F. Emergency Procedures and Decontamination 10

G. Waste Disposal\--how to package and label waste 11

H. Personnel Dosimetry 12

I. Bioassays 13

J. Miscellaneous Procedures 14

1\. Protocol approval by the Radiation Safety Committee

2\. Starting new employees

3\. Discontinuing radioactive material work in a lab

K. Radiation Safety Phone Numbers 14

III\. Licenses, Rights, and Responsibilities 15

APPENDIX\-- Sample Dosimetry Report

Radioisotope Pick up Procedures

Waste Pick up Procedures

Collection and distribution of Radiation Monitoring Badges

Reporting Radiation Safety concerns to outside agencies

ABBREVIATIONS: RAM Radioactive material(s)

RSC Radiation Safety Committee

RSM Radiation Safety Manual (Medical Center Memorandum No. 237)

RSO Radiation Safety Officer

NRC Nuclear Regulatory Commission

NHPP National Health Physics Program

**I. Basic Radiation Physics**

**A. The atom**

One way of picturing the atom is the Bohr model. In this model, the atom
is pictured as a small solar system with the nucleus in the center and
the electrons like planets orbiting around it.

The nucleus is composed of protons and neutrons. The number of protons
in the nucleus is called the Atomic Number or Z. It determines the name
of the element that the nucleus represents. For example, the element
with Z = 6 is carbon. In a neutral atom, Z also equals the number of
electrons.

The number of neutrons is N. The Atomic Mass or A equals Z + N. To
symbolize various nuclei, the name of the element (representing Z) is
followed by the Atomic Mass, A. For example, P-32 refers to a phosphorus
nucleus (Z = 15) with A = 32. N is therefore A - Z or 17.

Nuclei with equal numbers of protons but differing numbers of neutrons
(and therefore different A) are called isotopes. For example, carbon has
several isotopes: C-9, C-10, C-11, C-12, C-13, C-14, C-15 and C-16.
While all of these have the same Z and therefore are all carbon nuclei,
the number of neutrons ranges from 3 for C-9 to 10 for C-16. Some
isotopes are stable: for example C-12 and C-13. Other isotopes are
radioactive and are therefore called radioisotopes.

NOTE: Two other terms that are used in radiation physics are \"nuclide\"
and \"radionuclide\". For our purposes, the terms are synonymous with
\"nucleus\" and \"radioisotope\" respectively.

NOTE: [Scientific Notation]{.underline}\--Many numbers in this handbook
are written in a short-hand form of scientific notation. For example, 37
billion is written as 3.7E10, where \"E10\" means to multiply 3.7 by 10
to the 10th power. Thus, 3.7E10 = 37,000,000,000 and 3.7E-4 = 0.00037,
etc.

**B. Radioactivity**

**1. Instability of nuclei**

It is important to remember that the nucleus is responsible for
radioactivity. For the time being, the electrons orbiting the nucleus
may be forgotten as we consider what makes a nucleus radioactive.

Nuclei, like any physical system, want to reach the lowest possible
energy state. It\'s like dropping a ball\--the ball falls down in order
to lose the potential energy it had while you were holding it.

The numbers of protons and neutrons in a nucleus influence its
stability, i.e. whether or not it is in a high energy state. Nuclei have
an ideal neutron-proton ratio depending on their size and when an
isotope has too many or too few neutrons for the number of protons, it
decays to adjust itself to a better n-p ratio.

**2. Electron volt\--**The energy given off during radioactive
transitions is measured in electron volts. One electron volt is the
amount of energy gained by an electron when falling through a potential
(voltage) of 1 volt. The units normally encountered are the keV (1000
eV) and the MeV (one million eV).

**3. Beta minus decay\--**excess neutrons: Neutron → Proton + Beta
minus + Neutrino (most nuclei also emit gamma and/or x-rays). H-3, C-14,
P-32, S-35, Fe-59, Rb-86 use beta minus decay.

Example: C-14 → N-14 + beta minus + neutrino / Energy given off = 156.5
keV.

6p 7p

8n 7n

In beta minus decay, a neutron decays to a proton and a beta minus
particle and a neutrino. A beta minus is an electron that originates in
the nucleus. A neutrino is a very small particle emitted in the decay,
but not of concern with respect to radiation safety. The energy lost in
the decay process is shared between the beta minus and the neutrino. The
average energy a beta receives is often listed along with other
information about the isotope. Sometimes the beta receives all the
energy**\--**this is known as the maximum beta energy and is also often
listed. If no gamma or x-rays are emitted, shield for the maximum beta
energy. Sections 7 and 8 explain the origins of gamma and x-rays.

**4. Beta plus decay\--**excess protons: Proton → Neutron + Beta plus +
Neutrino (most nuclei also emit gamma and/or x-rays)

Example: Na-22 → Ne-22 + beta plus + neutrino / Energy given off = 545.5
keV.

11p 10p

11n 12n

In beta plus decay, a proton decays to a neutron and a beta plus
particle and a neutrino. A beta plus is identical to a beta minus or an
electron except that it is positively charged. Similar to beta minus
decay, the energy is shared between the beta plus and the neutrino.
Also, when the beta plus meets an electron, they annihilate each other
to produce two 511 keV gamma rays.

**5. Electron capture decay\--**excess protons: Proton + Electron →
Neutron + Neutrino (most nuclei also emit gamma and/or x-rays). Na-22,
Se-75, I-125 use electron capture decay.

Example: Na-22 + electron → Ne-22 + neutrino

11p 10p

11n 12n

Here, a proton in the nucleus combines with an electron orbiting around
the nucleus to produce a neutron and a neutrino. As implied in the
example, there is often competition between beta plus decay and electron
capture. Na-22 can use either means to lose energy.

**6. Alpha decay\--**large nuclei, e.g. radium, uranium. These nuclei
emit an alpha particle, which is a single particle consisting of 2
protons and 2 neutrons. It is the same as a helium nucleus. Most nuclei
also emit gamma and/or x-rays

Example: Ra-226 → Rn-222 + alpha

88p 86p 2p

138n 136n 2n

**7. Origin of gamma rays\--**Gamma rays are electromagnetic radiation
(similar to light and microwaves) which originate in the nucleus. After
one of the above decays, the daughter nucleus is not always in its most
stable (lowest energy) configuration and so it releases this extra
energy in the form of gamma rays.

**8. Origin of x-rays\--** X-rays are also electromagnetic radiation,
but they originate outside of the nucleus. Electrons are sometimes
knocked out of orbit as a result of the above decay processes. The
resulting vacancy in the electron orbit or shell is filled by an
electron coming from an outer shell. The difference in energy between
the two shells is given off in the form of x-rays.

There is another method of producing x-rays which is important in
shielding considerations. When beta particles encounter heavy nuclei
such as lead, x-rays are given off. This is why PLASTIC shielding is
preferred over lead for high energy \"pure\" beta emitters (no gammas or
x-rays) such as P‑32.

**C. Interaction of radiation with matter**

Particles, gamma rays, and x-rays traveling through matter cause
electrons to be knocked out of atoms in the matter. This is known as
ionization. In water and therefore in living systems, this can lead to
the creation of chemical species foreign to the living system. Some of
these chemicals are hazardous to the system. In some cases, the
radiation directly ionizes and causes changes in biological molecules
such as DNA.

**D. Activity, Exposure, and Dose**

> **1. Activity\--**The number of nuclei decaying per unit time. The
> older, but more common unit is the Curie, which equals 37 billion
> disintegrations or nuclear transformations per second. To write it
> another way, 1 Curie = 3.7E10 dps. The newer unit of activity is the
> Becquerel = 1 dps.

1 Curie (Ci) = 3.7E10 dps = 3.7E10 Bq = 37 GBq

1 millicurie (mCi) = 3.7E7 dps = 3.7E7 Bq = 37 MBq

1 microcurie (μCi) = 3.7E4 dps = 3.7E4 Bq = 37 kBq

**2. Specific activity\--**the activity per unit volume or mass. The
units are Ci/gram, Ci/ml, etc.

> **3. Radioactive decay\--**Half-life is the time required for one-half
> of the nuclei in a sample to decay. Each isotope has its own
> half-life. The activity at any time may be calculated using either of
> the following formula:

A1 = A0 \* e^(-0.693\ \*\ t\ /\ T)^, where

A1 is the unknown activity at time = t1

A0 is the known activity at time = t0

t is the elapsed time which equals t1 - t0, and

T is the half-life. T and t must be expressed in the same units, e.g.
days.

> NOTE: For calculating the activity at a later time (post-calibration),
> t1 \> t0 and t is positive. For calculating the activity at an earlier
> time (pre-calibration), t1 \< t0 and t is negative. The formula works
> in either case.
>
> **4. Exposure\--**The amount of ionization in air (expressed as
> electric charge) caused by the passage of radiation.
>
> Units: Roentgen = 2.58E-4 coulombs/kg. Usually expressed as an
> exposure rate, e.g. milliroentgen/hour = mR/hr.
>
> Use: Radiation surveys, e.g. mR/hr. However, see NOTE below.
>
> **5. Dose\--**The amount of energy absorbed by *any* material as a
> result of the passage of radiation.
>
> Units: Rad = 100 ergs/gram of material. The new unit is the Gray = 100
> rad = 1 joule/kg.
>
> Use: Expressing the dose to organs of the body from internally
> deposited RAM, whether accidentally or intentionally ingested, inhaled
> or injected.
>
> **6. Dose equivalent\--**The dose multiplied by the biological
> effectiveness of the particular type of radiation one is exposed to.
>
> Units: Rem = Rad \* Q. Q is called the quality factor and is a measure
> of biological effectiveness. For beta particles, gamma rays, and
> x-rays, Q = 1. For alpha particles, Q = 20. The new unit of dose
> equivalent is the Sievert = 100 rem = 1 joule/kg.
>
> Use: Personnel dosimetry, e.g. millirem = mrem or milliSievert = mSv.
>
> **7. Note concerning the use of mR/hr\--**Under NRC regulations
> effective January 1, 1994 the unit mR/hr is no longer recognized.
> Instead, the unit mrem/hr is to be used for radiation surveys. However
> since this change would require hundreds of licensees to change their
> forms and survey meter scales, the use of mR/hr is still permitted as
> long as the conversion between mR/hr and mrem/hr is communicated to
> radiation workers. For our purposes, **[1 mR/hr = 1
> mrem/hr]{.underline}**. Therefore we will continue using mR/hr in
> surveys with this understanding.

**II. Radiation Safety**

**A. Radiation Effects and Risks, ALARA, and Pregnancy Concerns**

**1. Natural background = approx. 300 mrem/year**

> **2. Effects of acute exposure** (not seen in the research setting
> unless someone is [extremely]{.underline} careless)

[Dose]{.underline} [Biological Effect]{.underline}

\<25 rem whole body (WB) Probably none

25 rem WB Observable blood change

100 rem WB Probable nausea

350-450 rem WB Death to half within 30 days

200-500 rem to ovaries Sterilization

500-700 rem to testes Sterilization

10,000 rem to WB CNS death

**3. Effects of chronic exposure** (possible in the research
setting\--see paragraph 6 also)

10 rem/day to WB Death within months

1 rem/day to WB Death probable within a few years

0.2 rem/day Unknown\--possibly cataracts, changes in skin, anemia,
leukemia (after a latent period)

0.1 rem/week Probably none (occupational exposure limit: 0.1\*50 =5.0
rem/year)

**4. Maximum permissible dose (MPD)**

MPD\'s have been designated to minimize the number of radiation effects
in both radiation workers and the general public. They are intended as
definite upper limits to radiation exposure and therefore we try to keep
exposures as far below these as possible (see ALARA). There have been no
observable radiation effects at these levels.

> MAXIMUM PERMISSIBLE DOSES\*\--OCCUPATIONAL EXPOSURE
>
> Organ(s) Yearly Quarterly Monthly Where listed on dose report
>
> (rem) (mrem) (mrem)
>
> Whole body \*\* 5 1250 417 *Deep* reading
>
> **or \*\*\***
>
> Whole body(organ) 50 12500 4167
>
> Lens of the eye 15 3750 1250 *Eye* reading
>
> Skin 50 12500 4167 *Shallow* reading
>
> Extremities 50 12500 4167 *Shallow* or *Shallow extremity*
>
> \* If necessary these consist of a summation of internal and external
> doses.
>
> \*\* *Whole body* means the head, trunk, arms above the elbows, and
> legs above the knees.
>
> \*\*\* Whole body limit is 5 rem to the whole body or 50 rem to any
> organ, whichever is less.

**General public** (non-occupational exposure): 100 mrem per year.

**Unborn child**: 500 mrem during the 9 months of gestation (for
declared pregnant worker).

**5. ALARA\--the basis of radiation safety guidelines**

For maximum safety, it is assumed that any amount of radiation no matter
how small is harmful. Therefore, we work to keep exposures As Low As
Reasonably Achievable (ALARA). All employees are expected to actively
seek ways to reduce exposures. Sometimes minor procedural changes can
significantly reduce exposures.

Part of our NRC license is a formalized ALARA program. The RSO reviews
film badge records and reports to the RSC quarterly exposures which are
greater than 10% of any of the quarterly MPD\'s. The RSC reviews the
exposures and determines whether or not an investigation should be
conducted.

It is rare for research personnel to have exposures even approaching the
level requiring investigation. Occasionally, hand and skin exposures
exceed the 10% mark when large amounts of beta emitters are handled.

**6. Risk factors\--What risk are you being exposed to?**

The probability of getting cancer following a 1 rem exposure has been
estimated to be 3 in 10,000 or 0.03%. In other words, if 10,000 people
received a 1 rem exposure, 3 cancers above normal incidence would be
expected on the average.

Since the normal probability of getting cancer is 25% the added risk
from small amounts of radiation is not measurable. Still, it is assumed
that any amount of radiation exposure entails some risk and so it should
be minimized.

Genetic effects (passed from one generation to another) due to radiation
probably occur very rarely. They have not been observed even in
populations exposed to significant amounts of radiation.

As has been mentioned, very few research personnel even approach 10% of
the MPD and most film badge readings are \<10 mrem. Thus, there is very
little risk associated with exposures you receive. Nevertheless, we want
to minimize the risk wherever possible.

**7. Pregnancy and the radiation worker**

As a radiation worker you have the option of whether or not to
\"declare\" your pregnancy. Declaration of pregnancy is made by
informing the RSO, in writing, of your pregnancy and the estimated date
of conception. The declaration may be made at any time during the
pregnancy and the pregnancy does not have to be medically confirmed.

If you declare your pregnancy the facility has an obligation to limit
the exposure to your unborn child to 500 millirem during the entire
pregnancy. We are also required to make efforts to insure that radiation
exposure is received at a uniform rate without substantial variation
from month to month. For these reasons the RSO will monitor film badge
results very closely during the course of the pregnancy.

If you choose not to declare your pregnancy the facility will still
strive to keep your exposures as low as possible, but cannot prevent you
from working in high exposure situations simply on the basis of
pregnancy. You may also \"undeclare\" your pregnancy anytime after it
has been declared. This does not have to made in writing, but that is
preferred.

Should you continue working with radiation during pregnancy? The RSO has
materials to assist you in assessing the hazard to your unborn child and
in making this decision. There are usually several options that may be
pursued and these should be discussed with your supervisor and the RSO.
In most cases, work may continue as long as some additional precautions
are observed. Examples are: having others perform tasks that involve the
highest potential exposures, wearing a pocket dosimeter, and using
additional lead shielding. In addition, the usual practices of using
time, distance and shielding to limit external exposures and following
safety rules to limit internal exposures must be exploited to their
fullest extent.

It is important that everything be done to keep exposures to the unborn
child as low as is reasonably achievable (ALARA). Since a woman may not
know she is pregnant for some time after conception, she must at all
times exercise extreme care so as not to unintentionally harm a
developing child.

Concerning the risk to the unborn child, it is important to keep in mind
that many common activities such as smoking are known to be hazardous
and may be more hazardous than any radiation received at work. The risk
to the fetus from external exposure is very small. The greatest
radiation hazard to the unborn child is ingestion or inhalation of RAM
by the mother. This is a very real hazard and one that is not measurable
with film badges. Extra care must be taken so as not to contaminate
one\'s hands or face or get any material in a cut. Again, safety rules
are designed to help with this.

**B. Reducing Exposure**

**1. Two types of exposure\--internal and external**

Internal exposure is caused by ingestion or inhalation of RAM. H-3 and
C-14 cause essentially no external exposure, but can cause internal
exposure by transfer from contaminated skin to mouth. This can also
occur when using any other isotope.

I-125 and other volatile isotopes may be inhaled. Use fume hoods. I-125
is particularly dangerous because it is concentrated in the thyroid
(fetal thyroid too after 12 weeks).

Since internal exposure can be detected ONLY by bioassay, make sure you
schedule the appropriate bioassays (see Section II. I.).

External exposure is caused by high energy betas, gammas and x-rays. It
is measured with film and ring badges.

**2. Reducing internal exposure\--laboratory safety rules**

> • There must be **[NO]{.underline}** eating, drinking, smoking or
> applying of cosmetics in areas where RAM are used. This includes gum,
> mints, and soda.
>
> • Refrigerators designated for RAM must not contain any food or food
> containers.
>
> • Protective clothing, such as laboratory coats, gloves, etc., shall
> be worn by personnel whenever handling RAM. Keep the lab coat
> buttoned.
>
> • Wear protective goggles if there is a danger of RAM splashing into
> the eyes.
>
> • Never pipet by mouth.
>
> • Carry out the work on plastic-backed absorbent material.
>
> • All work involving the possibility of airborne contamination must be
> done in a hood providing a uniform air flow of at least 100 cubic
> feet/minute with the sash one-half open.
>
> • Remove gloves before touching any object not being used in the
> experiment. This includes phones, pens, light switches, calculators
> etc. Don\'t answer the phone with gloves on.
>
> • Wash hands thoroughly after working with RAM.
>
> • Monitor yourself, your lab coat and the area after finishing your
> work.
>
> • Some special precautions for P-32: If you are using \>1 mCi, ring
> badges and eye goggles are required. Be careful with P-32 since it can
> be easily incorporated into DNA.

**3. Reducing external exposure\--Time**

For external exposures, the dose is directly proportional to the
exposure time. Thus, reduce this time as much as possible. One method is
to carefully plan each experiment and then perform a dry run without
radioactivity to get all the bugs out.

**4. Reducing external exposure\--Distance**

Locate storage and use areas as far from occupied areas as possible. Use
long handling tools for handling \>100 μCi of gamma or high-energy beta
emitters.

For a point source, the exposure rate is inversely proportional to the
square of the distance. For example, 10 mR/hr at 4 feet is 2.5 mR/hr at
8 feet. The distance is doubled so the exposure rate is reduced by a
factor of 4. To calculate exposure rate at any distance use the
following formula, which works both for getting farther from and closer
to a source.

(Current distance)2

New mR/hr = Current mR/hr \*
\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

(New distance)2

**5. Reducing external exposure\--Shielding**

Betas are stopped very effectively by plastic and wood. A 1 cm thickness
of Plexiglas is sufficient for almost all betas. Lead is not to be used
for high energy betas because x-rays are produced when the betas are
slowed down by the lead.

For shielding gamma and x-rays use lead. For our purposes, a two-inch
thickness (equal to a lead brick) is sufficient. For work with **mixed
beta and gamma**, place the plastic shield closest to the source(s) and
the lead one outside of that.

**C. Posting Signs and Storing Materials**

1\. Put this sign in areas where RAM is used or stored. Examples are
doors to rooms where materials are used, waste containers,
refrigerators, freezers, hoods, and shields. Remember not to store any
food in labeled refrigerators.

2\. Also place the sign on containers of RAM such as beakers, flasks of
stock solutions and lead pigs. Add sufficient information to the label
to allow others to take proper precautions. Information such as the
isotope, activity, date, chemical form and the initials of the person
making up the solution should be included. If multiple containers are to
be used it\'s a good idea to label them before the procedure is started
so you don\'t lose track of which one is which.

**3. Storage of radioactive materials**

Sources of radiation (including radioactive waste) must be secured
against unauthorized removal from the place of use or storage. Safeguard
RAM like you do your equipment**\--**be alert and lock doors when you
will be gone for more than a few minutes and at night. THIS IS A Nuclear
Regulatory Commission (NRC)/VA National Health Physics Program
REQUIREMENT.

Properly and conspicuously label waste containers so they are not
mistaken for regular trash. Radioactive waste containers should also not
be located near regular trash. Disposal of RAM in the ordinary trash is
prohibited.

Waste containers should be covered when not in active use. In some
cases, they may need to be shielded as well. Use the results of your
surveys as a guide.

**D. Ordering and receiving RAM**

All requisitions for RAM must be signed by the RSO or his designee. A
list of all authorized users of RAM, the isotopes they are permitted to
purchase and their maximum possession limits is on file in the Radiation
Safety Office.

All packages must be delivered to Radiation Safety, Room 1C-369,
Building 100, where they are logged in and checked for contamination.
You will be notified when the package is ready for pickup.

Each laboratory must have an inventory logbook showing receipt, use,
transfer and disposal of all RAM. A utilization log accompanies each
package.

It is IMPERATIVE that all shipping containers and packing materials be
surveyed before discarding. If there is no contamination, remove or
deface any radiation labels before discarding. If any material is
contaminated, notify the RSO.

**Transferring RAM\--**Giving ownership of material to another
investigator.

> **Within the facility:** Material may be transferred to another user
> PROVIDED: (1) the user is authorized for it, (2) receipt of the
> material will not exceed the user\'s possession limit, and (3)
> permission is obtained from Radiation Safety before transferring the
> material. Fill out the bottom portion of the utilization log and give
> one copy of the log to the lab receiving the material.
>
> **Outside the facility:** Transfers outside the hospital (including
> Baylor) may be done only under special circumstances. Contact the RSO
> for further information.
>
> **NOTE: The lab receiving the material must start a new inventory
> sheet for that material.**

**E. Laboratory monitoring**

**1. Definition**: The measurement and evaluation of radioactive
contamination and radiation exposure levels in the lab. It consists of
survey meter readings and wipe tests taken on bench tops, hoods, door
knobs, etc. From these measurements, steps may be taken to decontaminate
or to determine better handling and storage methods.

**2. Survey meters\--requirements**

Each lab must have available a calibrated survey meter that can detect
the isotopes in use. The only exception is those labs using only H-3 and
C-14.

A check source must be available for each survey meter. A check source
reading is taken immediately after calibration and must be recorded on
the meter. As long as subsequent check source readings are within ±20%
of the original one, the instrument calibration is still good.

Once each day before using a survey meter:

> 1\) Perform a battery check. If this fails, change the batteries. Do
> [not]{.underline} use a meter with low batteries.
>
> 2\) Read the check source. If the reading is within +/- 20% of the
> check source reading listed on the calibration sticker, the meter may
> be used. Otherwise, do [not]{.underline} use the meter and call the
> RSO.

Survey meters must be calibrated yearly and after major repair.
Radiation Safety will provide for the calibration of each meter and can
give you a loaner meter during calibration. [Be sure to indicate the
correct meter on your survey log when you are using a
loaner]{.underline}.

**3. Survey meters\--theory**

Geiger counter\--detects radiation by means of the ionizations produced
in the probe. Each ionization is registered as a count and/or a
\"click\".

Ionization chamber\--Also detects radiation by means of the ionizations
produced, but reads directly in mR/hr. It is much less energy-dependent
than the Geiger counter.

Scintillation counter**\--**Uses a solid crystal to detect beta or gamma
radiation by means of the flashes of light (scintillations) produced in
the crystal. Measures in counts/minute which may be converted to
activity. It is extremely sensitive.

**4. Survey meters\--selection and use**

Tritium is not detectable with normal survey meters because its energy
is too low**\--**wipe test only. For Carbon-14 and low energy betas use
an end-window or pancake Geiger. You must remove the end cap and get
very close to the source. A beta scintillation probe may also be used.

For high energy betas and gammas use Geiger, ion or scintillation
meters. A special scintillation probe is available for I-125.

Use the \"clicks\" as an indicator of hazard. This is easier than
looking at the meter and gives a faster response than the meter reading.

Be sure to move the probe slowly over the area being surveyed. Even when
listening to the \"clicks\", low contamination levels can be missed if
you survey too quickly.

**5. Wipe tests\--the most sensitive measure of removable
contamination**

Wet a cotton swab or piece of filter paper and wipe an area of 100 sq cm
(approximately 4 x 4 inches).

Place swab in a test tube or vial, add cocktail if appropriate, and
place it in a counter used to count the isotope being tested for.

The activity is not necessarily equal to the counts per minute obtained
from the counter. You must therefore convert from cpm to activity
(disintegrations per minute or dpm) using the following formula:

dpm = cpm / efficiency.

For example, if the efficiency is 70% divide the cpm by 0.70 to obtain
dpm.

**6. Trigger levels\--action levels**: Survey meter readings or wipe
test results requiring corrective action such as decontamination, adding
shielding or rearranging the lab. Corrective action is required when:

> • An area exhibits an exposure rate above 0.1 mR/hr.
>
> • A surface suspected of being contaminated exhibits an exposure rate
> above 0.1 mR/hr at a distance of 1 inch.
>
> • Wipe tests of a surface detect: \>2000 dpm/100 sq cm of either H-3
> or C-14
>
> \>200 dpm/100 sq cm of any other isotope

If trigger levels are exceeded record the initial reading in the
logbook, notify your lab\'s radiation safety supervisor or the RSO, take
appropriate corrective action, record the action taken, and record the
final survey result.

**7. Frequency and method of monitoring**

**NOTE: The activity *handled* is the activity contained in any stock
vial used in an experiment. For example, if 100 μCi are drawn from a
stock vial containing 1 mCi, [1 mCi]{.underline} has been handled.**

**a. Continuous surveys**: Leave a survey meter on at all times while
you are working with RAM. You will then know immediately if a spill or
some other problem has occurred. For this reason we ask that labs not
share survey meters. A meter should be in use each time an experiment is
being performed.

**b. Daily surveys**: After finishing a procedure and before leaving for
lunch, check equipment, work area, clothes and hands with a survey
meter. No records need be kept, but it is in your own personal interest
and that of coworkers and family to perform these checks. In addition,
wipe test at least your hands and clothing before leaving for the day.
**[Again note that these surveys do not have to be recorded, but they
are the backbone of a good radiation safety program.]{.underline}**

**c. Weekly surveys**: Labs handling ≥200 μCi at one time must
**[RECORD]{.underline}** surveys weekly.

**d. Monthly surveys**: All other labs must **[RECORD]{.underline}**
surveys monthly.

**e.** **Immediate surveys**: A survey must be RECORDED after any
iodination procedure and after handling ≥5 mCi of P-32 (survey meter
survey only after handling ≥1 mCi of P-32).

**f. Survey procedure**

> 1\) Have your map and sample log sheet approved by the RSO prior to
> beginning work with RAM. Areas surveyed must include work benches,
> hoods, refrigerators, other isotope storage areas, waste storage,
> floors and sinks. Recommended areas include non-radiation areas such
> as desks, phones and light switches. Remember, you are surveying for
> your own safety so choose the areas you feel are appropriate.
>
> 2\) Measure and record the mR/hr over each area in the log. This step:
> a) quickly detects any areas that are highly contaminated so
> corrective action may be taken immediately, b) measures contamination
> that may not be readily removable with a cotton swab and c) locates
> areas where sources may have been left out or the shielding needs to
> be modified.
>
> 3\) Wipe test each area and record the results in dpm.
>
> 4\) If corrective action is required, record initial reading, take the
> action, record the action taken and record final reading. Contact your
> lab\'s radiation safety supervisor or the RSO if any trigger levels
> are exceeded or if there are any questions or problems.

**F. Emergency procedures and decontamination** (See RSM for detailed
instructions)

**Minor spills\--** small amounts of liquid, small activities, minimal
personnel contamination.

NOTIFY persons in the area

PREVENT THE SPREAD**\--**cover with absorbent paper

REPORT to your supervisor and the RSO

CLEAN UP**\--**wearing gloves, carefully clean and place waste materials
in plastic bags and then in radioactive trash

SURVEY\--using survey meter and wipes, check floor, hood, hands, feet,
etc

> **Major spill\--**large amounts of liquid, large activities, personnel
> contamination, large area affected, [ANY]{.underline} spill in an
> unrestricted area or involving radioiodine.

CLEAR THE AREA**\--**all persons not involved should leave

PREVENT THE SPREAD**\--**cover with absorbent paper, but don\'t clean
yet; potentially contaminated persons must not leave the area

SHIELD THE SOURCE**\--**only if it can be done without further
contamination or increased radiation exposure

CLOSE THE ROOM**\--**leave room and lock doors to prevent entry

CALL FOR HELP\--call 911, and then notify your supervisor and the RSO
immediately

PERSONNEL DECONTAMINATION**\--**remove contaminated clothing and store
for further evaluation; clean skin areas with mild soap and lukewarm
water

**Decontamination tips:**

> • Keep the contaminated area moist**\--**it is more difficult to
> decontaminate after it has dried.
>
> • To clean, put on gloves and blot up the spill. Do not wipe since
> this tends to spread the contamination further. Next, scrub the
> surface with water and detergent or decontaminant foam. Blot again and
> check for contamination. Repeat until contamination is below trigger
> levels.
>
> • Do not clean skin roughly or with harsh detergents. This may cause
> internal contamination. Soap or decontaminant hand cleaners are best.

**G. Waste disposal**

**1. Packaging and disposal**

a\. The table below lists the most common waste types and disposal
methods. For other types of waste, including waste containing
infectious, pathogenic or large amounts of biological material (e.g.
excreta), consult Radiation Safety.

  --------------- ----------------------------- -----------------------------
  **Waste Type**  **Definition**                **Packaging**

  Solid waste     Paper, plastic, and small     Place in pails, separated by
                  amounts of glass (very small  isotope.
                  amounts of aqueous liquid     
                  also acceptable) containing   
                  any isotope. Does             
                  **[NOT]{.underline}** include 
                  scintillation vials.          

  Deregulated     Vials containing              Place in pails. Don\'t
  liquid          scintillation fluid with      overestimate activity a great
  scintillation   \<0.05 μCi/ml of C-14 and/or  deal since it\'s
  vials (LSV\'s)  H-3.                          [impossible]{.underline} to
                                                dispose of LSV\'s containing
                                                **\>**0.05 μCi/ml of C-14/H-3

  Regulated       Vials containing              Place in pails, separated by
  LSV\'s          scintillation fluid with      isotope and labeled with
                  reasonable amounts of         activity of all isotopes
                  isotopes. May also contain    present.
                  \<0.05 μCi/ml of C-14 and/or  
                  H-3.                          

  Sink disposal   Material that is readily      Use large amounts of water to
                  water soluble or readily      flush material. All disposal
                  dispersible biological        must be recorded on a sink
                  material and not otherwise    log.
                  hazardous.                    
  --------------- ----------------------------- -----------------------------

b\. Waste containers (normally 5-gallon pails) and labels are provided
by Radiation Safety. Label each container with the name (s) and total
activity of the isotope(s) present, type of waste, name of the
authorized user, building and room numbers, date and your initials.

**c. Metallic sharp objects, such as needles or scalpel blades, must be
placed in \"SHARPS\" containers and then placed in the pails provided by
Radiation Safety.**

d\. Any sink used for disposal must be registered with Radiation Safety.
There is no limit to the activity that may be poured down the drain, but
out of concern for the environment, please try to limit activity as much
as possible. One way to do this is to hold waste for decay before
pouring it out.

e\. Do not mix different waste types in the same container. For example,
don\'t throw the gloves used in an experiment into the same pail as the
liquid scintillation vials (LSV\'s). Also, LSV\'s are NOT solid waste.
They must be packaged separately. Also, separate waste by isotope since
different isotopes must be held in Radiation Safety for different
lengths of time.

f\. Remember that all waste disposal, whether collected by Radiation
Safety staff or poured down the drain, must be entered in your logbook.
All radioactivity coming into the facility must be accounted for.

> **2. Waste pickup**

a\. All waste is to be removed by Radiation Safety staff. Other
individuals may not dispose of radioactive waste or remove it from VA
premises. Please call ext. 5106 with your requests at least 1 day in
advance.

b\. All waste must be ready for pickup and all labels
[completely]{.underline} filled out at the time the request for pickup
is made. Do [not]{.underline} overfill the pails. Containers that cannot
be easily closed or those without properly filled out labels will not be
collected by Radiation Safety staff.

> **3. Additional information**

a\. Occasionally monitor procedures to see that waste is not being
created unnecessarily.

b\. Minimize the I2 phase of iodine (and thus the volatility) by
maintaining a basic solution of radioactive waste. Store iodine liquids
and others having a gas phase in a hood. Consult RSO for more iodine
volatility information.

c\. If you have any questions, problems or suggestions relating to waste
disposal, please do not hesitate to contact the RSO.

**H. Personnel dosimetry**

**1. Introduction**

a\. Personnel radiation exposure is reported in units of dose equivalent
(millirem or milliSieverts). It consists of three components, deep, eye,
and shallow.

b\. Deep dose equivalent (DDE) is the amount of radiation absorbed by
the body at a depth of 1 cm below the surface of the skin. Eye dose
equivalent (LDE or lens dose equivalent) is the amount of radiation
absorbed by the lens of the eye. Shallow dose equivalent (SDE) is the
amount of radiation absorbed by the skin. The body badge records all
three dose equivalents while the ring badge records only SDE.

c\. Radiation exposures are reported quarterly. A sample report with
explanations of some of the entries is found in the Appendix.

d\. To start dosimetry service, fill out a form (available from
Radiation Safety) with your name, Social Security Number, birthdate, and
any previous employment where you were exposed to radiation.

e\. Contact Radiation Safety if you change labs, need additional badges,
need to change any information, lose a badge, etc. If you leave the VA,
be sure to return all badges to Radiation Safety.

**2. Types of badges**

**Luxel^^ badges**\--used to measure exposure to the whole body and
skin. The badges contain aluminum oxide which is read by a laser to
determine dose. Filters inside the badge are used to determine the
energy and type of the radiation. Whole body and skin doses are recorded
as deep and shallow dose, respectively.

**Thermoluminescent dosimeters (TLD\'s)\--**Radiation excites atoms in
the TLD which give off the extra energy in the form of light when the
TLD is later heated. The amount of light given off is proportional to
the dose. Some research personnel wear TLD ring badges.

**Pocket dosimeters\--**miniature ionization chambers used for special
monitoring situations such as visitors to the lab. Contact the RSO for
guidance.

**3. Rules for using badges**

> • Wear the appropriate badges EVERY time you are working with
> radiation. This is a medical center requirement that will be checked
> during radiation safety audits of your lab. Failure to comply could
> result in losing the privilege of working with RAM.
>
> • Always leave your badges at work and in a safe, radiation-free
> location.
>
> • Do not wear a badge during any medical procedures.
>
> • If a badge is lost or contaminated, contact Radiation Safety at
> extension 7188.
>
> • Turn in badges promptly at the end of each wear period.

**4. Interpreting dosimetry reports**

a\. While no level of exposure can be considered absolutely safe, a
monthly dose of 30-40 millirem received 2-3 times during the year should
not be of concern. If more dose is received or if there is consistent,
quarterly exposure, there is not necessarily any danger, but you might
want to review your handling procedures.

b\. Note from the table of MPD\'s in Section II A, that the whole-body
MPD is 1250 mrem/quarter. Even at this level, there are no
scientifically proven effects of radiation. Of course we want to keep
exposures ALARA, so procedures are examined long before the MPD is
reached.

c\. You are entitled to see and review all your monitoring results
including those from bioassays. Each lab receives a copy of the
dosimetry report and an additional copy is filed in the Radiation Safety
Office. Contact the RSO if there are ever any problems with reviewing
your results.

**I. Bioassays**

**NOTE: The activity *handled* is the activity contained in any stock
vial used in an experiment. For example, if 500 μCi are drawn from a
stock vial containing 10 mCi, [10 mCi]{.underline} have been handled.**

**1. Radioiodine:**

> a\. Bioassay **[required]{.underline}** within 6-72 hours of handling
> [\>]{.underline}10 mCi.
>
> b\. Bioassay recommended after using smaller amounts of radioiodine,
> e.g. [\>]{.underline} 1 mCi.
>
> c\. Baseline bioassay [required]{.underline} for new employees in
> radioiodine labs.

**2. Tritium:** Urine count **[required]{.underline}** when \>100 mCi is
handled in one month or at one time. Baseline bioassay also required.

**3. To obtain a bioassay:** Call extension 7188 to schedule a thyroid
count or to arrange for a tritium bioassay. The thyroid count is
performed in the Radiation Safety Office and takes about 5 minutes.

**4. Results\--**You will be notified of all bioassay results. If a
positive thyroid bioassay is obtained, you will be recounted immediately
to verify it. If the result is still positive, you will be given
recommendations based upon the level of iodine and scheduled for a
recount in a few days. If \>0.015 μCi is found, the RSO will be
notified. The RSO may give further recommendations and may notify your
supervisor and the RSC, depending on the exact level. We are required by
the NRC to perform investigations and repeat bioassays when \>0.12 μCi
of I-125 is found.

**5. Responsibilities\--**You and your investigator are responsible to
see that the required bioassays are obtained. The Radiation Safety
Office will compare isotope receipt records with bioassay records. If
required bioassays are not obtained, the RSC will be notified and you
could lose your authorization to use isotopes.

**J. Miscellaneous Procedures**

**1. Protocol approval by the Radiation Safety Committee**

a\. As part of the overall project approval process the investigator
submits to the Research Office an application to use RAM. A subcommittee
of the RSC reviews the application and, if approved, presents it to the
full RSC. Once the RSC approves the application, a sublicense is issued
and you may order RAM and begin work.

b\. **Sublicenses:** Upon approval for use of RAM, the investigator is
issued a sublicense listing approved isotopes, quantities, procedures,
and locations as well as required survey frequencies and other
information pertinent to the lab\'s radiation safety program.
**[Any]{.underline}** changes to the sublicense (e.g., new isotopes,
more activity, change of rooms) [must]{.underline} be approved by the
RSO and the Chairman, RSC [before]{.underline} they are implemented. To
request changes, submit a memo to the RSO.

**2. Starting new employees**

> a\. Arrange for training. Classes for new employees are held the third
> Tuesday of each month. Call the RSO to sign up. New workers
> **[CANNOT]{.underline}** work with RAM until they are trained at this
> facility.

b\. Request monitoring badges.

> c\. Obtain baseline bioassays if he/she will be working with
> radioiodine or large amounts of tritium.

**3. Discontinuing radioactive material work in a lab (including
remodeling)**

a\. Discard all RAM as radioactive waste or transfer it to other users.

b\. Contact the RSO for a closeout survey/wipe test.

c\. When the area is certified as uncontaminated, remove all signs and
stickers from doors, refrigerators, etc. The area may then be designated
for other uses.

**K. Radiation Safety Phone Numbers**

> Radiation Safety Officer, Jeff Triebel, x7396 or x7188, pager
> 713-841-0933
>
> Assistant RSO, Stan Bravenec, x7188, pager 877-205-8348
>
> Safety Technician, Kim Henderson, x5106, pager 713-841-0304
>
> Chairman, RSC, Dr. Vij, x7114

**IV. Licenses, Rights, and Responsibilities**

**A. VA Master Materials License/Nuclear Regulatory Commission license**

Since the Houston VA is a federal facility, we are licensed by the NRC
rather than the state under a VA Master Materials License wich is
administered by the VA National Health Physics Program (VA NHPP). The
license specifies which isotopes may be used, how they may be used, and
their maximum activities and chemical forms. Each laboratory has a
nuclear materials sublicense that specifies the radionuclide, activity,
and chemical form that is authorized for each investigator.

This type of license in known as a Broad Scope license and places great
responsibility upon management, the RSC, the RSO, individual authorized
users and each technician. The NRC or NHPP inspect us approximately
yearly to make sure we are in compliance with the license.

Licensed material may be used **ONLY** at this facility. See Section II.
D.

**B. Radiation Safety Committee (RSC)\--**According to the license, RAM
may only be used by or under the supervision of individuals designated
by the RSC. The RSC, therefore, has been given direct responsibility
from management to administer the radiation safety program and meets at
least quarterly to discuss radiation safety problems, evaluate research
protocols and to see that RAM is used in a manner consistent with ALARA.

**C. Radiation Safety Officer (RSO)**

The RSO is delegated authority by the RSC to carry out the day to day
functions of the radiation safety program. These functions include
performing inspections of laboratory facilities, procedures, and
log­books; investigating abnormal radiation exposures and accidents;
recommending changes in procedures; administering the dosimetry program;
and training users.

The RSO serves as a technical consultant to the RSC and to all users of
RAM. You should contact the RSO: 1) to review personnel dosimetry
results, 2) to see regulations, license information and inspection
reports, 3) if you are pregnant, 4) if you suspect radiation safety
problems, and 5) if you have any questions about radiation or radiation
safety.

**D. Worker rights**

a\. You have a right to work in a safe environment with respect to
radiation. This includes being trained and informed of radiation hazards
in the area where you work.

b\. You are entitled to see your personnel dosimetry results. Contact
the RSO if there are any problems with this.

c\. You may report violations of NRC requirements to your supervisor,
the RSO, a member of the RSC or directly to the NRC, or the NHPP, or VA
Inspector General (Please try to resolve problems in this order). Phone
numbers for the NRC are posted in several locations on a form entitled
NOTICE TO EMPLOYEES (NRC Form 3). You CANNOT be fired or otherwise
discriminated against for reporting violations to the NRC.

**E. Worker responsibilities**

a\. Know and follow all radiation safety rules that pertain to your job.

b\. Report any violations of safety rules.

LANDAUER

Landauer, Inc. 2 Science Road Glenwood, Illinois 60425-1586 Accredited
by the National Institute of Telephone: (708)755-7000 Standards and
Technology through

NVLAP

RADIATION DOSIMETRY REPORT

<table>
<colgroup>
<col style="width: 12%" />
<col style="width: 6%" />
<col style="width: 7%" />
<col style="width: 8%" />
<col style="width: 6%" />
<col style="width: 8%" />
<col style="width: 4%" />
<col style="width: 4%" />
<col style="width: 7%" />
<col style="width: 4%" />
<col style="width: 4%" />
<col style="width: 7%" />
<col style="width: 4%" />
<col style="width: 4%" />
<col style="width: 7%" />
</colgroup>
<tbody>
<tr class="odd">
<td></td>
<td></td>
<td></td>
<td></td>
<td></td>
<td></td>
<td colspan="3">DOSE EQUIVALENT (MREM) FOR PERIODS SHOWN BELOW</td>
<td colspan="3"><p>YEAR TO DATE</p>
<p>DOSE EQUIVALENT (MREM)</p></td>
<td colspan="3"><p>LIFETIME</p>
<p>DOSE EQUIVALENT (MREM)</p></td>
</tr>
<tr class="even">
<td>NAME</td>
<td>PART. #</td>
<td>TYPE OF RECORD</td>
<td>DOSIMETER TYPE</td>
<td>NOTES</td>
<td>RADIATION QUALITY</td>
<td><strong>DEEP</strong><br />
DDE</td>
<td><strong>EYE</strong><br />
LDE</td>
<td><strong>SHALLOW</strong><br />
SDE</td>
<td><strong>DEEP</strong><br />
DDE</td>
<td><strong>EYE</strong><br />
LDE</td>
<td><strong>SHALLOW</strong><br />
SDE</td>
<td><strong>DEEP</strong><br />
DDE</td>
<td><strong>EYE</strong><br />
LDE</td>
<td><strong>SHALLOW</strong><br />
SDE</td>
</tr>
<tr class="odd">
<td colspan="2">FOR MONITORING PERIOD:</td>
<td></td>
<td></td>
<td></td>
<td></td>
<td colspan="3"><strong><br />
11/01/04 - 12/31/04</strong></td>
<td colspan="3"><strong><br />
2004</strong></td>
<td colspan="3"><strong><br />
2004</strong></td>
</tr>
<tr class="even">
<td>CONTROL<br />
<br />
ROENTGEN, W.<br />
<br />
<br />
<br />
<br />
BECQUEREL, H.<br />
<br />
<br />
CURIE, M.</td>
<td>00RAD<br />
<br />
0001<br />
<br />
<br />
<br />
<br />
0002<br />
<br />
<br />
0003</td>
<td><p>CONTROL<br />
<br />
ASSIGNED<br />
CHEST<br />
COLLAR</p>
<p>R FINGER<br />
<br />
WHL BODY<br />
R FINGER<br />
<br />
WHL BODY</p></td>
<td>G<br />
<br />
<br />
G<br />
G<br />
U<br />
<br />
G<br />
U<br />
<br />
G</td>
<td>UNUSED</td>
<td>PM</td>
<td>10<br />
<br />
100<br />
M<br />
100<br />
<br />
<br />
<br />
<br />
<br />
100</td>
<td>10<br />
<br />
100<br />
M<br />
100<br />
<br />
<br />
<br />
<br />
<br />
100</td>
<td>10<br />
<br />
100<br />
M<br />
100<br />
70<br />
<br />
<br />
120<br />
<br />
100</td>
<td>360<br />
<br />
<br />
<br />
<br />
400<br />
<br />
<br />
600</td>
<td>400<br />
<br />
<br />
<br />
<br />
410<br />
<br />
<br />
600</td>
<td>410<br />
<br />
<br />
500<br />
<br />
450<br />
560<br />
<br />
600</td>
<td>360<br />
<br />
<br />
<br />
<br />
400<br />
<br />
<br />
600</td>
<td>400<br />
<br />
<br />
<br />
<br />
410<br />
<br />
<br />
600</td>
<td>410<br />
<br />
<br />
500<br />
<br />
450<br />
560<br />
<br />
600</td>
</tr>
</tbody>
</table>

Notes:

> 1\. Control reading represents background radiation and is subtracted
> from all dosimeters in this group.
>
> 2\. Participant number 0001 wears two badges, one on the collar and
> one under the lead apron. The dose assigned to him is taken to be the
> dose to the collar badge. We are able to calculate effective dose
> based upon both the collar and chest readings and use that as the
> assigned dose if necessary.
>
> 3\. Participant number 0002 did not use his film badge during the
> month, but did use his ring badge.
>
> 4\. Participant number 0003 was exposed to medium energy x or gamma
> rays as shown by the \"PM\" under \"RADIATION QUALITY\". The back of
> the dosimetry report explains this term as well as most of the other
> items on the report.

Radioisotope Pick Up Procedures

1.  Most packages are delivered daily between the hours of 8:00am and
    9:30am. After we process your package, your Lab will be contacted.

2.  Someone from Safety will be available in building 100, room 1C --
    369 to issue packages twice a day. Safety staff will be available
    during the morning hours of 8:00am -- 10:00am, and again in the
    afternoon from 2:30pm -- 4:30pm. Hopefully, this will reduce the
    time that unclaimed packages remain in our lab and ensures that you
    will receive your package in a timelier manner.

3.  Laboratory personnel assigned to pick up packages will be required
    to sign for their package, as well as provide identification. If
    Laboratory personnel arrive without valid VA identification, they
    will not receive the package.

> 4\. If Laboratory personnel are not available to pick up packages
> during
>
> the above stated times, please contact Kimberly Henderson at
>
> x5106/Pgr: (713) 841- 0304, or Stan Bravenec at x7188/Pgr:
> 877-205-8348
>
> so other arrangements can be made.

Waste Pick Up Procedures

Radioactive waste pick up will be conducted on Mondays and Thursdays
only. Contact Kimberly Henderson at extension 5106 and arrange for
radioactive waste pick up on one of these two days.

The following information will be needed for waste pick up:

Building location

Room location

How many replacement containers are needed

Completed waste forms attached to the container

**NOTE: [If waste forms have not been completed, your waste will not be
picked up. If your waste has not been properly segregated, it will not
be picked up.]{.underline}**

Please ensure that your staff has been trained in proper waste disposal
procedures. If your staff needs additional training, contact Stan
Bravenec at extension 7188 for assistance.

Collection and Distribution of Radiation Monitoring Badges

1.  Badges will be distributed as necessary, depending if you are on the
    monthly schedule or bi-monthly schedule. Badges for researchers will
    be placed in the mailboxes located in building 110 on the last day
    of the bi-monthly wear period.

2.  **[Badge coordinators are responsible]{.underline}** for collecting
    badges and ensuring that they are delivered to Radiation Safety by
    the [Fifth Work Day]{.underline} of the new wear period for
    processing. The badge coordinator can utilize inter-office mail. Our
    mail code is 138 S. Or badges can be dropped off at building 100,
    room 1C-369, located in the Nuclear Medicine Department. If safety
    staff is not available, please leave the badges in the drop box
    located on the door of room 1C-369.

3.  If badges can not be collected and delivered by the fifth work day
    of the new wear period, an explanation needs to be provided to the
    Radiation Safety Officer, or Assistant Radiation Safety Officer.

4.  If you know that someone will be out for an extended period of time
    due to vacation, pregnancy, or illness, collect their badge
    **[before]{.underline}** they leave and notify Radiation Safety.

5.  Badge returns are a part of your laboratory/Area Radiation Safety
    Audit. The chairman of the Radiation Safety Committee and the Chief
    of Staff reviews radiation Safety Audits. If badges are lost,
    missing, or returned late, please provide an explanation to the
    Radiation Safety Office.

6.  The badge coordinator is also responsible for notifying Radiation
    Safety of arriving and departing personnel so that they can be
    processed in a timely manner. If you have any questions, please
    contact Kimberly Henderson at extension 5106, or Stan Bravenec at
    extension 7188.

Reporting Radiation Safety Concerns to Outside Agencies

  -------------------------------------------------------------------------------
  VHA workers may report radiation safety concerns to their supervisors, to their
  Radiation Safety Officer, to the [National Health Physics
  Program](http://nhpp.med.va.gov/Top/2VAspecific/1LiveDataQuery/Contacts.asp),
  to the [VA Inspector General](http://www.va.gov/oig/homepage.htm), or to the
  [Nuclear Regulatory Commission](http://www.nrc.gov/).\
  \
  Radiation Safety Officers should include information about the resources
  discussed below during routine training sessions for radiation workers and
  others who work with or around radioactive materials.\
  \
  Local medical center or facility supervisors and/or Radiation Safety Officers
  are normally the first resource for radiation workers to use to voice radiation
  safety concerns. Other local resources include the Chair, Radiation Safety
  Committee, committee members, or senior management.\
  \
  The National Health Physics Program (NHPP) is an outside resource that staff
  may contact to communicate radiation safety concerns. The NHPP is under the
  aegis of the National Radiation Safety Committee and senior headquarters-level
  management. The NHPP has established procedures to evaluate, in confidence,
  worker radiation safety concerns and/or allegations. The NHPP point of contact
  is [E. Lynn McGuire, NHPP Director](mailto:lynn.mcguire@med.va.gov), at (501)
  257-1571.\
  \
  The VA Inspector General is another outside resource that staff may contact to
  communicate radiation safety concerns. The telephone number for the [VA
  Inspector General\'s \"Hotline\"](http://www.va.gov/oig/hotline/hotline.htm) is
  (800) 488-8244.\
  \
  The Nuclear Regulatory Commission is also an outside resource that staff may
  contact to communicate radiation safety concerns. Medical centers or facilities
  with a Nuclear Regulatory Commission license are required to post the [NRC Form
  3](http://nhpp.med.va.gov/Top/1Nrc/14Safety/NRC_FORM3.pdf) with information
  about points of contact. As an example, one point of contact listed on the NRC
  Form 3 is the NRC Safety Hotline at (800) 695-7403.\
  \
  Reporting radiation safety concerns is considered a protected activity under 10
  Code of Federal Regulations [Parts
  19](http://www.nrc.gov/reading-rm/doc-collections/cfr/part019/index.html) and
  [30](http://www.nrc.gov/reading-rm/doc-collections/cfr/part030/index.html), the
  Civil Service Reform Act of 1978, and the Whistleblower Protection Act of 1989.

  -------------------------------------------------------------------------------