HS6010-W 1. Module 1 · HS6010-W 1. Module 1 ... You can only work on one module at a time. After you pass the test for a module, ... Module 2 4.1 HS6010-W Course Menu

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HS6010-W

1. Module 1

1.1 Radiological Worker Training

1.2 Untitled Slide


1.3 HS6010-W Course

Notes:

1.4 Introduction HS6010-W Rad Worker I

Notes:


Welcome to HS6010-W, “Radiological Worker I Training.” The content of this course is very focused on lab operations, much more so than was the content in previous versions of the course. So, if you have taken the course before, the content will be somewhat different than you are used to. The course consists of 9 modules which must be taken in sequence in order to get LTRAIN credit. The course contains a number of improvements which we think you will like. However, there are some rules you must know before you start:

At the top of the tool bar is a “PDF” button which allows you to download the course material for that module.

You can only work on one module at a time. After you pass the test for a module, you will no longer have access to that module.

1.5 Introduction Continued

Notes:


If you wish to pre-test out of a module, you are allowed one opportunity. If you pass the pre-test, you will automatically advance to the next module. You are not required to pre-test if you don’t want to.

If you don’t choose to take the pre-test or don’t pass the pre-test, you are required to work through the module materials prior to taking the post-test. If you don’t pass the post-test, you can review that module before trying again.

Remember, you cannot advance to the next module until you pass either the pre-test or the post-test for the previous module.

After passing all 9 of the modules, you will be given LTRAIN credit for HS6010-W. You will not need to take a test at the end of the course to get credit.

Okay, now that you know the “rules,” you are ready to start the course. Good luck and we hope you like the changes.”

1.6 HS6010-W Course Menu


Notes:

Table of Contents

1.7 Module 1

Notes:

Welcome to HS6010-W, Radiological Worker I Training. Because the course materials are extensive, you may choose to close the course at the end of a module and return to it later. If you use the same computer, the computer will return you to the point where you left off and you can continue with your training.


1.8 Overview

Notes:

All Laboratory employees take HS6001, “General Employee Radiological Training,” every two years. If your job requires that you use non-dispersible radioactive material or operate radiation generating devices, you need to take two courses. The first course is the one you are taking right now, HS6010-W.


1.9 HS6010-P

Notes:

After you finish this course, you will be prompted to take the associated practical course, HS6010-P. The practical must be completed within 30 days of successfully completing this web-based course. When you have completed both courses, you will have Radiological Worker training that is equivalent to DOE Radiological Worker I.


1.10 Additional Training

Notes:

Depending on the type of work you need to do, you may need additional radiological training, as shown in this matrix.

For example, if you work with radiation generating devices, you need to take HS6988-W, “Radiation Generating Device Safety.” And if you work with dispersible radioactive material, you need to take HS6300-W.

If you use anti-contamination clothing, you need to take HS6340-P. You may also need more specific isotope courses, such as, tritium, uranium, or plutonium.


1.11 ES&H Vol. II Doc. 20.1

Notes:

The documents that govern the Lab’s radiation safety program are in Volume II of the ES&H Manual. Document 20.1, “Occupational Radiation Protection,” contains the elements of the program that apply to all radiological operations. Topics include:

Dose limits

Monitoring radiation doses to workers

Monitoring the workplace

The As Low As Reasonably Achievable (ALARA) Program



Notes:

Radiological requirements for work control documents

Training requirements

Responsibilities, resources, and contacts



Notes:

Document 20.2, “LLNL Radiological Safety Program for Radioactive Materials,” contains the requirements and controls for use of radioactive material, and Document 20.3, “LLNL Radiological Safety Program for Radiation Generating Devices (RGDs),” contains the requirements and controls for use of x-ray machines, accelerators, and other radiation-generating devices.


1.14 ES&H Vol. II Links

Notes:

This course largely covers the information in Document 20.1, along with some selected material from Document 20.2 so that you will be permitted to handle sealed radioactive sources after completing the course.

It is important that you read and become familiar with the portions of the ES&H Manual documents that apply to your work. You can click on the buttons below to access the table of contents for Document 20.1, 20.2, and 20.3.


1.15 Techs

Notes:

Your ES&H Team has staff specifically trained in radiation safety to assist you in planning and executing radiological work.

Health and Safety Technologists (or, H&S Techs) are trained Radiological Control Technicians who can assist you in day-to-day operations such as radiation monitoring, moving radioactive materials, and responding to spills and events. Get to know them and talk to them about any aspect of radiological work.


1.16 Tech Supervisors

Notes:

The H&S Tech Supervisors, who are also trained Radiological Control Technicians, coordinate the H&S Tech support on the ES&H Team and can provide you with additional radiological support, as needed.


1.17 Health Physicists

Notes:

Health Physicists (or HPs) are responsible for working with you to identify appropriate radiological safety controls and for helping you to get these controls in your work documents. Including your HP early in the design phase of work ensures that radiological controls are effectively designed into your operations.

HPs also review and concur on radiological work control documents such as work authorizations, work permits, integration work sheets, and various technical work documents.


1.18 Radiation Protection Functional Area

Notes:

The Radiation Protection Functional Area provides you with “behind the scene” radiological support.

LLNL Radiological Control Manager (RCM) provides the overall direction for the Radiation Safety Program. The RCM is responsible for developing policies and procedures that effectively implement the Lab’s contractual requirements. The RCM works with Laboratory management to ensure requirements are clear, understood, and executed appropriately within all of the Principal Associate Directorates.


1.19 Operational Teams

Notes:

A variety of operational groups within the Radiation Protection Functional Area to provide technical services such as calibration of radiation detectors; analysis of radiological swipes, air filters, and other samples; and monitoring of workers for internal and external radiation dose.

The Radiation Protection Functional Area supports all aspects of your radiological work and works closely with the ES&H Teams.

Let’s hear from the Laboratory’s Radiological Control Manager.


1.20 Radiological Control Manager

Notes:

“Hello, I’m Phil Worley, the Radiological Control Manager here at the Lab. I want to take this opportunity to welcome you to our Radiation Safety Training Program.

This radiological worker training is intended to familiarize you with the controls that apply to all radiological work. Additional courses will provide specific requirements associated with dispersible radioactive materials and radiation-generating devices.

I think you’ll like this course. It has been significantly modified to focus more on the Lab’s radiological controls and less on theoretical information. It is designed to align with Livermore’s work control process and to track with the requirements in ES&H Manual, Document 20.1. Hopefully you’ll find this course useful in understanding and implementing the Lab’s radiological work requirements.

In today’s highly regulated environment, it may be natural to categorize


radiological requirements as “compliance issues,” rather than “safety issues;” but while compliance is important, it’s your safety and that of your co-workers and the environment that are my primary concern. Please, never forget that the requirements identified in this training are in place to help keep you safe.

Your ES&H Team health physicist is a key contact for helping you find cost-effective ways of integrating radiological safety requirements into your operations. Be sure to contact them early in the planning phase of your work to optimize the integration of controls.

The Lab has established a Radiation Safety Committee, representing each Program, which meets regularly to oversee and deal with issues that pertain to the Radiation Safety Program. If you have issues or concerns that cannot be resolved by the ES&H Team, I urge you to get in touch with me or the Radiation Safety Committee representative, so we can work towards a sensible solution. My contact information can be obtained by clicking on the Help tab or by clicking the Resources tab above.

As the Radiological Control Manager, I want to assure you that my goal is consistent with yours: that is, to conduct the Lab’s radiological work safely and efficiently.

Thank you for your time and attention, and I hope you enjoy this course.”


1.21 Course Goal

Notes:

After completing this course and the associated practical, you will be able to safely conduct your radiological work involving non-dispersible radioactive material.


1.22 Before

Notes:

Before beginning radiological work, you need to:

Obtain radiologically controlled items and materials.

Identify the radiological hazards associated with work tasks and the controls needed for those hazards.

Recognize radiological work document requirements.

Use appropriate dosimetry.

Perform escort responsibilities in radiation and high radiation areas.


1.23 While Working

Notes:

When you actually begin working, you will need to:

Participate in documented pre-job briefings.

Enter the radiologically controlled area.

Conduct operational radiation monitoring for potential exposure.

Control external radiation dose.

Handle sealed radioactive sources and other non-dispersible radioactive materials.

Perform appropriate actions for off-normal conditions.

Exit the radiologically controlled area.


1.24 Next Steps

2. RESOURCES/PDF

2.1 Untitled Slide


3. GLOSSARY

3.1 Untitled Slide

4. Module 2



Notes:

4.2 Next Steps

Notes:


4.3 Module 2

Notes:

4.4 Overview

Notes:


You can’t begin work until you use the Lab’s process to obtain radiologically

controlled

items and materials.

This module starts with some basic concepts necessary to understand

radioactivity and

radiologically controlled items and materials.

Then you’ll learn to use the Laboratory’s procurement process to order,

receive, and

transport these materials.

You’ll then understand the need to contact the Facility Manager or Facility

Point of Contact

(also called the FPOC) so he/she knows these materials are coming into your

work facility.

4.5 The Atom

Notes:

We’ll start with some fundamental physics necessary to work safely with radiologically


controlled items and materials.

The basic unit of matter is the atom. Each atom consists of a nucleus made up of positively

charged protons and non‐charged neutrons. Orbiting the nucleus are negatively charged

electrons.

Please take a second and identify the various parts of the atom in the diagram.

4.6 Elements and Isotopes

Notes:

The element is defined by the number of protons in the nucleus and the

isotope is defined

by the total number of protons and neutrons in the nucleus. There are

several isotopes for

each element and most of these are stable (or non‐radioactive) isotopes.


4.7 Isotopes of Hydrogen

Notes:

Radioactive materials are unstable isotopes. These are also called

radioisotopes. They

contain too much energy to remain as they are, so they decay to stable

isotopes by the

release of ionizing radiation. This process is called radioactivity.

In this graphic we see the three isotopes of the element Hydrogen. H‐1 and

H‐2 are stable,

but H‐3 (also known as Tritium) is radioactive. As the unstable Tritium atom

releases its

ionizing radiation, it changes to a stable form of another element, becoming

Helium‐3.

All radioactive atoms will eventually become non‐radioactive through the

release of their

excess energy as ionizing radiation.


4.8 Radioactive Decay

Notes:

Radioactive decay is the process by which radioisotopes give off ionizing radiation as they

change (or disintegrate) to another isotope. Every radioisotope has a unique half‐life, which

is the time required for ½ of the radioactive atoms to disintegrate.

Consider this example, where a pie represents an original amount of radioactive material.

Initially, the pie is whole, but after 1 half‐life has elapsed, exactly ½ of the pie remains.

After the second half‐life, only a quarter of the pie remains. After about 10 half‐lives have

elapsed, almost none of the pie is left. Of course, with radioactive materials, the decayed

part does not disappear, it just becomes non‐radioactive.


4.9 Radiation

Notes:

Although it may seem mysterious, radiation is just energy moving through

space. Some

types of radiation, like light, are visible to the human senses, but most types

of radiation

are invisible to the human senses. Here we see a radiant heater which emits

heat as

infrared radiation and a light bulb giving off visible light.


4.10 Two Types of Radiation

Notes:

All radiation comes in one of two types, either non-ionizing or ionizing.

Non-ionizing radiation covers the low energy radiations ranging from electric power to ultraviolet light. This electromagnetic spectrum chart helps illustrate the various types of non-ionizing radiation. In general, non-ionizing radiation presents a minimal hazard to human beings.

On the other hand, ionizing radiation, which can be produced by radioactive materials and radiation generating devices, is much more energetic, so much so that, when it interacts with an atom, it can eject an electron from the atom.


4.11 Ionization

Notes:

This ionization creates an “ion pair,” a free electron and a positively charged ion, which causes chemical changes in materials and could be harmful if the materials happen to be human tissue.


4.12 Ionizing Radiation Cell Damage

Notes:

Ionizing radiation damages human tissue at the cellular level. It damages the cell by directly or indirectly damaging the cell’s DNA. There are three possible outcomes for this damage. First, the DNA is repaired perfectly and the cell becomes viable again. Second, the damaged DNA is repaired but not perfectly. The DNA is mutated and may lead to negative health consequences. Lastly, the DNA damage is so great that the cell dies. All of the safeguards we put in place are meant to keep ionized radiation out of human tissue.


4.13 Radioactive Contamination

Notes:

One of the keys to safety with radioactive materials is keeping them under proper control.

If loose radioactive materials are found in an unwanted location, it is called radioactive

contamination.

In this image, we see a small radioactive materials work area viewed in normal room light.

No contamination can be seen in this picture.

If we then view the same area with UV light, you now can clearly see the glowing simulated

contamination.


4.14 Alpha Particle

Notes:

There are 4 basic types of ionizing radiation found here at the Lab. Each type has special

properties that affect its hazards and the necessary controls for those hazards.

First is the alpha particle. Alphas are massive particles with a positive charge and are very

energetic. These properties make the alpha particle likely to ionize any atom it interacts

with. Because it is interacts so readily, it has a very short range (less than an inch in air) and

will give up all its energy in the dead outer layer of human skin. Even a piece of paper acts

as a shield for alphas. Therefore, alphas do not present an external radiation hazard.

However, if alpha emitting contamination becomes deposited in the body (called an

internal radiation hazard), the alphas can cause harm by depositing large amounts of

energy in a small amount of human tissue.


4.15 Beta Particle

Notes:

Our second type of radiation is the beta particle. Betas are energetic

electrons with a very

small mass and a minus charge. Depending on their energy, betas can

present an external

skin and eye exposure hazard as well as an internal exposure hazard for

deposited beta

contamination. Beta range in materials is a function of their energy; for

instance, low

energy betas travel less than an inch in air, whereas some high energy betas

travel more

than 20 feet in air. Most betas can be shielded with about 0.8 inches of

plastic or glass.

Be aware that intense beta fields, if improperly shielded, may interact with

matter to create

another type of radiation (X‐rays).


4.16 Gamma Particles & X-Rays

Notes:

Our third type of ionizing radiation is gamma rays and X‐rays. We will discuss

these

together because they have very similar properties. Both of these are

electromagnetic

waves, meaning they have no mass or charge and are pure energy. They can

penetrate

most materials including the human body, so they present both an external

and internal

radiation hazard. Shielding these rays requires very dense materials like lead,

tungsten,

water or concrete.


4.17 Neutrons

Notes:

Our last ionizing radiation type is a free neutron ejected from the nucleus.

Neutrons have

substantial mass but no charge and they are normally quite energetic with

long ranges in

materials. Neutrons have enormous ability to cause ionizations and they

present primarily

an external radiation hazard.

They are shielded differently from gammas or x‐rays. We use materials rich

in hydrogen as

shielding for neutrons; so water, concrete and plastics are good choices.


4.18 Types of Ionizing Radiation

Notes:

A specific radioactive material will give off one or more of the 4 types, so it is important to

understand what radiations are emitted by radioisotopes you are using.


4.19 Records, Radioactivity & Units

Notes:

You must maintain records of the isotopes and radioactivity you receive, store and use. This

requires you to have an understanding of radioactivity units.

Radioactivity (sometimes just called activity) is measured not by weight or volume but by

the number of atoms disintegrating per unit of time.

An example is the disintegrations per minute (or dpm). One disintegration per second (or

dps) is called a Becquerel (or Bq). A Curie (or Ci) is defined as 2.22 x 1012 dpm

(2,220,000,000,000 dpm).


4.20 Bq and Ci

Notes:

Since the Bq is very small and the Ci is very big, we often use special prefixes to simply express values. Here are some examples of common prefixes and how they are used with radioactivity units.

4.21 Roentgen, Rad, Rem


Notes:

Measurements of radiation fields are expressed in several different units. It is important to

understand the units and their meaning to allow you to make and interpret measurements.

We start with the Roentgen (or R), which is used to measure external radiation exposure. It

applies only to gamma and x‐ray fields and indicates the number of ions formed in a gas

volume.

Our second unit is the rad (radiation absorbed dose) where dose is the amount of energy

deposited in any material by any kind of ionizing radiation. The rad is useful in radiation

protection, but it does not account for biological effects from different types of radiation.

The third unit is the rem (radiation equivalent man), which is the unit of dose equivalence.

The rem applies to all types of ionizing radiation but only describes the biological

effectiveness in human tissue. This is the unit used in radiation protection to describe

human radiation doses.

To determine the rem, we multiply the rad by a radiation weighting factor that depends on

the radiation type and energy.


4.22 Roentgen, Rad, Rem

Notes:

The most common unit you will encounter is the millirem.

4.23 Dose Rate


Notes:

Radiation dose is not the same as the dose rate. The dose rate is the dose per unit of time.

To determine the dose ‐ you have to multiply the dose rate by the time of exposure.

In our first example, we will assume a low dose rate of 10 mrem/hour. If you are in such a

field for 3 hours, that would equal 3 times 10 or a total dose of 30 mrem.

In our second example, assume a much higher dose rate of 900 mrem/hour. If you are in

the field for 2 minute (which is 1/30th of an hour), that would equal 900 times 0.0333 or a

total dose of 30 mrem.

These example dose rates were extremely different, yet the difference in the time of

exposure resulted in exactly the same total dose. These examples help to show the

importance that exposure time has in controlling radiation dose.

4.24 Dose Rate Control - Part 1


Notes:

Controlling the time you are exposed can help to limit the radiation dose received. Time (in

combination with distance and shielding) is an important factor to consider in controlling

radiation dose.

4.25 Dose Rate Control - Part 2

Notes:

Take a minute and use your mouse to move the slider control back and forth to see the

dramatic effect exposure time can have on the total dose received.


4.26 The LLNL Radiation Protection Program

Notes:

Now that we have discussed some basics concepts like the atom, radiation types,

radioactivity, and radiation units, we need to move on to the details of the LLNL radiation

protection program.

The requirements for LLNL radioactive materials program can be found in the LLNL ES&H

Manual Document 20.2. We’ll start by discussing the document guidance on how you can

obtain radioactive materials and items.


4.27 Obtaining Radioactive Materials

Notes:

You will find the specific requirements for obtaining radioactive materials and items in the

LLNL ES&H Manual, Document 20.2, Section 5.2, Acquisition of Radioactive Material. We

urge you to coordinate with your H&S Tech for additional details and assistance in meeting

the requirements.


4.28 Process for Obtaining Radioactive Materials

Notes:

This flow chart shows the steps to follow when ordering radioactive materials and devices.

Your Technical Release Representative (or TRR) will assist you in the ordering process. Keep

in mind that the Radiological Control Manager has to approve most requests to obtain

radioactive materials or items. This is true whether you purchase, borrow, or get them

loaned from someone outside the Lab.

The Radiological Control Manager approval may be documented either by using the Lab’s

procurement requisition process or by an e‐mail. Details can be reviewed by clicking on the

indicated link.


4.29 Acquisition of Radioactive Material

Notes:

You can find the requirements for receipt of radioactive material transported from outside

the Lab in Document 20.2, Section 5.2.2, Receipt of Radioactive Material from Offsite

Transportation.

4.30 Receiving Non-Lab Owned Materials


Notes:

You can find the requirements for receipt of non‐Lab owned radioactive material in

Document 20.2, Section 5.2.3, Radioactive Material Owned by Non‐LLNL Organizations.

4.31 Controlling Non-Lab Owned Materials

Notes:

Non‐Lab radioactive sources left at LLNL beyond the time of the visit must be

controlled

consistent with LLNL requirements.

The non‐Lab owner must follow applicable DOT regulations while

transporting the material

offsite but is not required to process the radioactive material through the

Materials

Management Section.


4.32 Isotopes and Individual Facilities

Notes:

Individual facilities must control radioactive material to assure radioisotope specific limits

are not violated. The limits vary with the nature of the facility and work being performed

there. Violation of these limits is a serious matter that may be reportable to the

Department of Energy (DOE).

To make sure the limits are not violated, you must contact the Facility Manager or FPOC to

obtain permission to bring radioactive material into your facility.


4.33 Module 2 Summary

Notes:

This module has covered some basic physics, the Laboratory’s procurement process to

order, receive, and transport radioactive materials and the need to inform the Facility

Manager or FPOC about materials coming into your work facility.

You may choose to review any topics you feel unsure about at this time by using the menu

on the left to select a topic. When you are finished reviewing, select the last topic on the

menu, Module 2 Summary, and click on the quiz button.

You may also wish to refer to the glossary if you have any questions about the terms used

in the module. The glossary tab is on the top right of the screen.

You must take and pass the quiz for this module before advancing to module 3. When you

are ready, click the quiz button to take the quiz.


5. GLOSSARY

5.1 Untitled Slide

6. RESOURCES/PDF

6.1 Untitled Slide


7. Module 3


7.2 Next Steps


7.3

7.4 Overview

Notes:

After completing this module, you will be able to identify and control the radiological


hazards associated with your work tasks.

You will be able to explain the basic concepts of radiation biology, since radiological hazards are connected to the potential for a biological effect.

Next, you will relate the radiation dose to the potential for the radiation effect.

This means you will need to determine both the properties of the radiological material and the resulting dose rates.

This information will then enable you to determine and apply appropriate radiological controls.

It’s also important that you are able to recognize the requirements for radiological work documents.

7.5 The 5 Factors and Bioeffects

Notes:

The potential for a radiation biological effect (also called a bioeffect) is connected to one or more of five factors.

Proper understanding and control of these factors allows us to limit the potential for a biological effect.


(Paul, can we move last sentence to next slide?)

The first factor is the total radiation dose received. Limiting the total dose to any human tissue is our primary goal in radiation protection.

7.6

Notes:

The first factor is the total radiation dose received. Limiting the total dose to any human tissue is our primary goal in radiation protection.


7.7 Factor 2: Duration of Dose

Notes:

The second factor is how long it takes for the dose to be delivered to the tissue.

The dose is either “chronic”, defined as a low level dose rate received over a long period of time or “acute”, defined as a high level dose rate received over a short period of time.

Chronic dose allows time to perform biological repair of any injury, so we always favor chronic over acute dose conditions.


7.8 Factor 3: What Type of Radiation?

Notes:

The third factor is the radiation weighting factor which was covered in Module 2 when we learned about radiation types.

Since some radiation types cause more damage in tissue than other types, if we know the types of radiation present, it helps us know when and how to apply radiation controls.


7.9 Category 2: Radiation-Induced Cataracts

Notes:

The second category is the potential for formation of radiation-induced cataracts.

A cataract is a clouding in the lens of the eye that obscures human vision.

Radiation cataracts normally result from beta or low energy x-ray dose to the lens of the eye exceeding 200 rad.


7.10 Category 3: Radiation Systemic Effects

Notes:

The final category is radiation systemic effects.

Systemic effects vary and can be much more serious than the other two categories. Let’s discuss some examples of systemic effects.

A whole body dose of about 25 rad is required to induce temporary clinical changes to blood by suppressing the function of the bone marrow.

The person does not feel this effect and it can only be detected by analysis of blood samples.


7.11 Category 3: Radiation Systemic Effects

Notes:

A whole body dose of 100 rad or more can induce an additional effect known as acute radiation syndrome (or ARS).

ARS is characterized by prolonged severe flu-like symptoms including diarrhea, vomiting and dehydration.

Healthy individuals will usually recover within 30 to 60 days, but may have an increased likely hood of developing various cancers over their life expectancy.


7.12 As Low As Reasonably Achievable (ALARA)

Notes:

Because of the dominance of limiting doses under the ALARA concept, the dose limits are somewhat less important than they were in the past.

These days we always try to reduce doses well below the dose limits by using ALARA.


7.13 Performing Radiological Design & Operational ALARA Reviews

Notes:

Identifying controls to limit radiation doses requires an evaluation of the radiation environment. This is called an ALARA Review.

This formal review covers both operations and facility design and is described in Document 20.1, Appendix G.


7.14 Performing Radiological Design & Operational ALARA Reviews

Notes:

The LLNL Authorizing Organization has certain responsibilities which are normally delegated to a Responsible Individual (or RI).

It is important that the Team HP be involved early in the work planning process.

This includes providing drawings and designs to the HP with sufficient time for review.

After the review, be sure to either incorporate the HP’s recommendations, or otherwise address in writing any issues that are raised.

Be sure to retain all records of radiological reviews conducted in accordance with the procedure.


7.15 The Administrative Control Level (ACL)

Notes:

One part of the ALARA review is an evaluation of past doses and determination of how to limit future doses.

This process results in determination of the Administrative Control Level or ACL.

The ACL results from agreement between the Responsible Individual (RI) and the Team HP.

No ACL is required if the dose is unlikely to exceed 100 mrem per year.

An ACL is required for any individual whose dose is likely to exceed 100 mrem in a given year.

In addition, a formal ALARA evaluation is required if the ACL is more than 500 mrem per year.

Finally, increasing levels of management authority are required to approve any ACL which exceeds 1000 mrem.


7.16 Radiological Work Control Documents

Notes:

Like all work at the Laboratory, radiological work must be planned, authorized, approved and released prior to beginning the work.

This requires a written work authorization, usually an Integration Work Sheet or IWS.

The written authorization documents radiation protection measures that cover both existing and potential hazards inherent in the work.


7.17 Written Work Authorization

Notes:

A written work authorization is required:

If you are working with Class I or greater quantities of radioactive materials. NOTE: for dispersible Transuranics then the activity drops to 1 nCi or more.

If the work is likely to generate radioactive contamination above certain thresholds.

If you need to control entry into or perform work within Radiological Areas (we will discuss Radiological Areas in detail later in this course).


7.18 Written Work Authorization and Safety Plan

Notes:

A written authorization and a safety plan is required:

If you work in Type III workplaces with Type III quantities of radioactive material.

If you use Class IV sealed radioactive sources.

If you handle, storage, or transport significant quantities of fissionable material.

Or if you use RGDs.


7.19 The Integration Work Sheet (IWS)

Notes:

The Integration Work Sheet (or IWS) describes all work hazards and controls required for the use of radioactive materials or items.

You are required to read, understand and comply with all requirements of the IWS.

Your H&S Tech can assist you in complying with requirements established in the IWS.


7.20 Radiological Work Reviews

Notes:

Formal radiological reviews are performed by the Authorizing organization in coordination with the Team HP.

These reviews provide the basis for the content of written authorizations and technical work documents.

Formal radiological reviews must be conducted prior to conducting planned, non-routine or complex work activities.

Formal radiological review must be based on existing radiological conditions or conditions expected and done prior to implementation of engineering and administrative controls.


7.21 Technical Work Documents

Notes:

Technical work documents, such as procedures, work packages, or job or research plans, must be used to control hands-on work with radioactive materials.

Such documents are provided by the authorizing organization.

The Team HP will then review the documents and provide feedback.

HP concurrence on Technical work documents is required prior to incorporation into written work authorizations.

Technical work documents provided must be clear and accurate.


7.22 Radiological Controls – Containment and Posting

Notes:

Radiological operations must be properly contained and posted to prevent loss of control over the radioactive material.

Containment and posting - both during storage and use - are primary controls that must be considered at all times.

Containment needs are a function of the radioactive material being used, its physical and chemical form, and the work process being used.

The work authorization will clearly identify all work controls.


7.23 Radiological Controls – Containment and Posting

Notes:

Understanding the types of radiation emitted from the radioactive material or items is essential in designing shielding and other work controls.

For example, use of beta emitters requires very different shielding than is required for shielding gamma emitters.

Your Health & Safety Tech can answer questions regarding radiations emitted from various radioisotopes.

Your Team HP can give you advice on shielding.


7.24 Limiting Radioactivity in the Workspace

Notes:

Radiological hazards are tied directly to the activity of the radioactive material present.

This activity is sometimes referred to as the source term.

The source term should be limited to the minimum activity required to perform the work.

Any additional activity in your inventory should remain shielded or otherwise contained to limit radiation doses.


7.25 Specific Activity

Notes:

It is important to understand the relationship between the size (or mass) of a given radioactive material and the radioactivity of that mass.

This concept is called the specific activity.

Specific activity can vary dramatically between two or more radioisotopes.

So the size (or mass) of a radiation source is never a good indicator of its relative radiological hazard.

The hazard can only be understood by knowing the dose rate.

For example, some physically very small gamma emitting sources are extremely dangerous, while a cubic meter of another isotope may present little or no hazard.


7.26 Determining Dose Rates

Notes:

To understand the radiological hazard, it is necessary to determine the dose rate from the radioactive material.

This may be accomplished either by measurement with radiation survey instruments (which is most common) or by use of calculations.

Once the dose rate is known at a given distance, the dose rate at other distances can be easily calculated.

We will discuss the proper use of radiation survey instruments later on in this course.

If you need to calculate the dose rate, please contact your H&S Tech or your Team HP for assistance.


7.27 Module 3 - Summary

Notes:

This module has covered some basic radiation biology as well as how radiological hazards are connected to the potential for a biological effect.

We also discussed the radiological material’s properties and the need to properly determine dose rates.

Lastly, we focused on applying radiological controls, including the requirements for work documents.

You may choose to review any topics you feel unsure about at this time by using the menu on the left to select a topic.

When you are finished reviewing, select the topic on the menu and click on the quiz button.

You may also wish to refer to the glossary if you have any questions about the terms used in the


module.

You must take and pass the quiz for this module before advancing to module 4. When you are ready, click the quiz button to take the quiz.

7.28 Draw from Factors affecting bioeffects

Draw 2 questions randomly from Factors affecting bioeffects

7.29 Draw from Risk, Dose and ALARA

Draw 2 questions randomly from Risk, Dose and ALARA

7.30 Draw from ALARA Reviews and Responsibilities

Draw 3 questions randomly from ALARA Reviews and Responsibilities

7.31 Draw from Radioactive sources and specific activity

Draw 3 questions randomly from Radioactive sources and specific activity

7.32 Results Slide

(Results Slide, 0 points, 1 attempt permitted)


Results for

7.28 Draw from Factors affecting bioeffects

7.29 Draw from Risk, Dose and ALARA

7.30 Draw from ALARA Reviews and Responsibilities

7.31 Draw from Radioactive sources and specific activity

Result slide properties

Passing Score 80%


Success (Slide Layer)

Failure (Slide Layer)


8. GLOSSARY

8.1 Untitled Slide

9. RESOURCES/PDF

9.1 Untitled Slide


10. Module 4


10.2 Next Steps

Notes:


10.3

10.4 Objectives

Notes:


An essential part of any radiation protection program is proper use of radiation dosimetry. A radiation dosimeter is a device used to measure your external radiation dose. Radiation dosimeters used at LLNL are Thermo-luminescent dosimeters - often called TLDs for short.

After completing this module, you will be able to use the appropriate type of dosimeter for the job assignment. This includes:

Identifying the dosimeter type you need.

Wearing the dosimeter properly.

Exchanging your dosimeter on a prescribed schedule

Identifying and using supplemental dosimeters for entry into high radiation areas.

Responding appropriately if your dosimeter is contaminated, lost or damaged, and

Interpreting your individual dosimetry report.

Let’s start by determining where radiation dosimeters are required.

10.5 Dosimeters - Where required?

Notes:


Anyone employed at the lab must wear their assigned LLNL dosimeter while at the lab (unless the Radiological Control Manager specifically directs them not to).

Persons other than employees must wear an assigned LLNL dosimeter while at the Lab if they enter an area posted with the radiation trefoil symbol. The issued dosimeter must be in the in the dosimeter holder with the plastic flap bearing the LLNL logo.

The dosimeter must be worn facing out on the upper part of the body and not be covered by other materials (like plastic cards). However, dosimeters may need to be worn under anti-contamination (anti-C) clothing.

Assigned LLNL dosimeters may only be worn at LLNL and by the person to whom it was issued.

10.6 Dosimeter - Types

Notes:

There are several different types of radiation dosimeters used at LLNL. The blue slide 802 and black slide 810 dosimeter types pictured are the most common types used at LLNL.


The type you need really depends on the type of work you do. Be aware that you may require more than one dosimeter depending on the type of work you do.

Your Team HP will determine the type of dosimeter you should wear and once that is determined, you must wear the assigned radiation dosimeter(s).

If you have questions or feel your dosimeter type is wrong, contact your Team HP as soon as possible.

10.7 Dosimeter - Outside of LLNL

Notes:

You must not wear your LLNL dosimeter at other facilities unless authorized by the Radiological Control Manager. If a dosimeter is needed at other facilities, that facility is responsible for supplying the dosimeter and providing your dose records to LLNL.

The RCM must authorize:

Any alternate uses of dosimeters (e.g., for tour groups, etc.)

Not wearing a dosimeter (for instance if you have received medical radioactive materials)


Using LLNL dosimeters at other sites

10.8 Dosimeter - Non-US facilities

Notes:

LLNL must ensure that workers are appropriately monitored . Therefore, in some situations, LLNL may supplement the monitoring provided by the host facility, this most often applies in non-U.S. facilities

Document 20.1, Section 3.3.2 contains additional details on use of dosimeters outside of the Lab.


10.9 Dosimeter - Exhange or loss of

Notes:

All individuals must exchange their dosimeter as soon as possible when a new dosimeter is received. This is typically done via internal Lab mail.

Visitors must return their dosimeter at the end of their visit or six months after it was issued, whichever is longer. Most LLNL staff are on a six-month exchange cycle, but exchange cycles may be quarterly or even monthly, depending on the work performed.

Please be careful to keep the old dosimeter separate from the new dosimeter when performing the exchange.

Notify your team HP promptly if your dosimeter is:

Exposed to non-occupational sources of radiation (e.g., airport X-ray machines, dental X-rays or medical procedures)

Exposed to excessive heat or moisture, or

Lost, damaged or contaminated.


In such cases, you must stop work, place your work in a safe condition, immediately exit the area, and report the occurrence. You will be restricted from entry into radiological areas until a review has been conducted to verify that dose limits have not been exceeded.

10.10 Dosimeter - Supplemental use part 1

Notes:

Supplementary dosimeters are required for entry into high radiation areas at LLNL.

You must also wear a supplemental dosimeter when:

A planned activity is likely to result in a dose exceeding 50 mrem or 10 percent of the ACL in a work day (whichever is greater),

Your dose is expected to be greater than 100 mrem in a work day,

Or when required by a radiological work permit or other work control document.

Supplementary dosimeters are worn in addition to the primary TLD dosimeter. The TLD normally provides the official dose (called the dose of record), unless a formal dose assessment indicates otherwise.


Supplemental dosimeters are intended to provide real-time indication of radiation exposure and assist in maintaining your dose ALARA.

10.11 Dosimeter - Supplemental use part 2

Notes:

Electronic personnel dosimeters (or EPDs) provide an early warning of elevated exposure through the use of preset alarm points. For this reason, alarming supplemental dosimeters are preferable to non-alarming supplemental dosimeters and should be used whenever feasible.

Supplemental dosimeters must be read periodically while in use.

Work must be stopped and the H&S Tech or HP must be consulted prior to continuation of work:

When a supplemental dosimeter reading indicates a total dose or rate of exposure substantially greater than planned, or


If the supplemental dosimeter is off-scale or not functioning correctly.

10.12 Dosimetry - How to modify

Notes:

If you are changing the radiological work you are doing or if you have concerns that you do not have the correct dosimeter(s), you should immediately contact your Team HP.

Your Team HP will work with you and your RI to determine if your dosimetry needs to be modified.

Always wear any dosimeters you are assigned while working at LLNL.


10.13 Dosimetry - Reports

Notes:

Dosimetry reports are how you receive your dose information. You will receive an annual dosimetry report in the Spring of each year while working at the Lab. Or, you may obtain dosimetry information at any time by contacting the ES&H Dosimetry office at 3-7902.

Additionally, any unusual doses will be investigated by the Team HP. The HP will meet with you to determine if the dose is real, and if so, how can future doses be kept ALARA.

More information about dosimetry reports can be found in Document 20.1, Section 3.3.6, “Dose Monitoring Reports.”



Notes:

This module has covered use of the appropriate type of dosimeter for the LLNL job assignment.

We specifically discussed:

Proper dosimeter choice and use,

Dosimetry exchange cycles,

The use of supplementary dosimeters,

The proper response to lost or damaged dosimeters and

Dosimetry reports

You may choose to review any topics you feel unsure about at this time by using the menu on the left to select a topic.

When you are finished reviewing, select the topic on the menu and click on the quiz button.

You may also wish to refer to the glossary if you have any questions about the terms


used in the module.

You must take and pass the quiz for this module before advancing to module . When you are ready, click the quiz button to take the quiz.

11. GLOSSARY

11.1 Untitled Slide


12. RESOURCES/PDF

12.1 Untitled Slide

13. Module 5



Notes:

13.2 Next Steps

13.3 Module 5


13.4 Objectives

Notes:

This module begins our discussion of how to safely conduct radiological work

at the Lab.

After completing this module, you will be able to:

1.Participate in Pre-job Briefings. We will also discuss how to:

Establish Type 0 and I workplaces

2.Enter radiological areas safely. This includes how to:

Identify radiological postings

Recognize controls on radiological postings

Control radiological areas in lieu of postings and

Use PPE as specified by facility or work authorization document - finally

you will learn how to:


3. Perform escort responsibilities in radiological areas

13.5 Conducting Briefings

Notes:

Pre-job briefings are an integral part of the Lab’s Integrated Safety

management system. You are re1quired to participate in all pre-job briefings

associated with your work. Formal radiological Pre-job Briefings will be held

and attendance documented prior to conducting g and radiologic work that:

requires a formal radiological review or is non-routine and could cause the

spread of radioactive contamination or result in an individual dose in excess

of 100 mrem


13.6 Radiological Postings

Notes:

Radiological Areas established for the control of radiation fields are clearly

posted with one of the following signs:

A “CAUTION Radiation Area,” where the whole body dose rate is more

than 5 mrem/h up to 100 mrem/h***

A “CAUTION High Radiation Area,” where the whole body dose rate is

more than 100 mrem/h up to 5 rem/h

Entry into a “CAUTION High Radiation Area” requires a supplemental self-

reading dosimeter and radiation monitoring as necessary to determine

exposure rates present during the access.***

Because of the severe radiological hazards involved, no entry is allowed into

either the “DANGER High Radiation Area” or the “GRAVE DANGER Very High

Radiation Area” whenever radiation is present.


13.7 ES&H Staff Manage Postings

Notes:

Posting, un-posting, or altering signs using the radiation trefoil symbol must

only be done by, or under the direction of ES&H Department staff, usually

the H&S Tech. Only postings approved by the RCM may be used. Such signs

may contain supplemental information as needed to meet operational

requirements.

It is very important to inform either your H&S Tech or your Team HP if any

radiological conditions have changed so that the posting can be updated to

meet regulatory and operational needs.


13.8 Controls in lieu of postings

Notes:

Normally all radiological hazards will be posted. Again, it’s important to

always read and obey all radiological postings you encounter.

Posting requirements may occasionally be waived for a period of less than 8

hours.

This is only allowed when the area is placed under continuous observation

and control by a assigned person.


13.9 Determining PPE Requirements

Notes:

Entry into radiological areas often requires various types of Personal

Protective Equipment (or PPE). PPE requirements for radiological work areas

vary, depending on area conditions and the work to be conducted

This PPE will be normally be provided by your authorizing organization and

shall be worn by the worker as required.

The work authorization document or facility work documents will specify the

required PPE for radiological activities as determined by the Team HP.

Basic PPE requirements include use of:

A buttoned lab coat (or equivalent)

Closed toe shoes and

Disposable gloves

NOTE: Use of safety glasses (or other eye protection) may also be required.

All PPE should be donned and secured prior to entering the radiological area.

After monitoring and determining the PPE is free of contamination, doff the


PPE immediately after leaving the radiological area.

PPE must not be worn in general office areas or public areas (e.g., rest rooms

or cafeterias) but may be worn in the hallway while going from one

radiological area to another.

13.10 Escort Responibilities

Notes:

If you escort visitors or other persons into radiological areas, you are

responsible for their safety.

Please make sure of the following:

That escorted persons receive appropriate visitor training (usually GERT)

That you keep radiation doses ALARA for any persons escorted

That escorted persons wear the required dosimeters

That they wear the appropriate PPE to enter areas AND

That they remain in your sight at all times


Also, be sure to:

Instruct them to follow directions regarding safety alarms and emergency

procedures and,

Be alert to changing/unusual conditions and hazards

Remember - you are responsible for the radiological and other safety of

persons being escorted.


Notes:

This module has covered:

1.Participate in Pre-job Briefings

2.Establish Type 0 and I workplaces


3.Enter radiological areas safely

Identify radiological postings

Recognize controls on radiological postings

Control radiological areas in lieu of postings

Use PPE as specified by facility or work authorization document

4.Perform escort responsibilities in radiological areas

You may choose to review any topics you feel unsure about at this time by

using the menu on the left to select a topic.

When you are finished reviewing, select the topic on the menu and click on

the quiz button.

You may also wish to refer to the glossary if you have any questions about

the terms used in the module.

You must take and pass the quiz for this module before advancing to module

6. When you are ready, click the quiz button to take the quiz.


14. GLOSSARY

14.1 Untitled Slide

15. RESOURCES/PDF

15.1 Untitled Slide


16. Module 6


Notes:


16.2 Next Steps

16.3 Monitoring/Controlling Dose


16.4 Module 6 Objectives

Notes:

This module continues our discussion of how to safely conduct radiological

work at the Lab.

After completing this module, you will be able to make radiation

measurements and determine the potential for radiation exposure by:

1.Conducting operational monitoring AND

2.Controlling external radiation dose

Objectives include:

Selecting survey meters for various types of radiation

Performing operational checks on meters

Monitoring work areas and personnel


Responding to survey results

Reducing time of exposure

Increasing distance from the radiation source and

Using appropriate radiation shielding

Let’s start by discussing the importance of survey meters.

16.5 Why We Need Radiation Monitors

Notes:

It is very important to conduct radiation monitoring. Why, because none of

the human senses can detect the presence of ionizing radiation.

Therefore, ionizing radiation does not have warning properties to alert you of

it’s presence.


So, radiation survey meters are essential tools required in radiation

protection.

There are many kinds of survey meters. Each has advantages (and

disadvantages) for use in various radiation environments. These limitations

can affect your decision on which meter to use.

For example, most survey instruments detect only one or two types of

ionizing radiation and may not meet all needs when measuring mixed

radiation fields.

So now let’s talk about monitoring those radiation fields.

16.6 Measuring the Radiation Field

Notes:

When we monitor for radiation we are trying to measure the dose or count


rate of that particular radiation field.

You may hear people use the words monitoring and surveying

interchangeably - but here at LLNL there one very specific difference

between the two.

Where monitoring is simply measuring a radiation field, surveying is formally

documenting that monitoring, usually on a survey map or form.

Surveys are performed only by ES&H staff, where monitoring can be

performed by all radiation workers.

So it’s important that you learn how to perform radiation monitoring!

16.7 Monitoring and Survey Differences

Notes:

Radiation Monitoring is not normally documented, unless specifically

required by a work control document.


Monitoring is often associated with control of contamination on surfaces and

personnel, but can include dose rate measurements.

Radiological workers must conduct operational monitoring of work areas

during activities that could affect radiological conditions and - before, during,

and after completing work.

The monitor must promptly notify the ES&H Team of any changes in

radiological conditions and of unplanned events.

Dose rate measurements may be taken at any distance that provides

meaningful information to the worker.

Again, radiation surveys differ from monitoring in that they are documented.

Such survey documents are then used to provide radiological information to

workers.

Surveys are only performed by the H&S Tech, ES&H Team HP or other person

designated by the Radiological Control Manager. Surveys are performed on

a periodic basis, based on the hazards of the work and other needs.

It is important that any survey documents provided to you are reviewed and

used to control your radiation dose.


16.8 Survey Instrument Types

Notes:

Radiation survey meters must be selected to meet the requirements of the

radiation types and conditions being measured.

Survey parameters (linear speed of measurement, detector distance from

source and meter response time) have great importance in determining the

accuracy of measurements and will be discussed in more detail later.


16.9 Contamination Survey Meter Operation

Notes:

Our standard contamination survey meters detect several kinds of radiation

as shown in the graphic.

For alpha emitter contamination, the Ludlum Model 12 with a large area

alpha probe is used. The electronics package may be either blue or brown.

Measure by slowly moving the probe flat and parallel to the surface being

surveyed at a distance of ¼ inch or less.

Response is fairly fast and background for alpha will tend to be very low,

certainly less than 10 cpm.

For beta/gamma emitter contamination, we use the pancake probe GM

meter.

The electronics package is normally brown. Response will be fairly fast, but


low count rates may be difficult to separate from background (normally less

than 50 cpm).

Measure for contamination by slowly moving the probe flat and parallel to

the surface being surveyed at a distance of ½ inch or less.

For both types of meters, you can only detect contamination directly under

the probe, so if you see increased counts reorient the probe to capture the

greatest value before assuming where contamination is present.

16.10 Contamination Monitoring with Large Area Wipes

Notes:

Contamination can also be determined by using large area wipes.

To do this, take a clean kim-wipe and fold it to match the size of the detector.

Then, using disposable gloves, wipe the kim-wipe over the area being

monitored and then hold the wipe close to (but not touching) the detector


surface to determine if contamination is present.

16.11 Dose Rate Meters

Notes:

Our standard dose rate survey meters detect various kinds of radiation as

shown in the graphic. Dose rate measurements are usually very

straightforward.

For beta/gamma/x-ray dose rates, we use an ionization chamber. The

electronics box is usually red and yellow. Measurements should be made to

determine the whole body dose, at least 30 cm from a given object and at

waist level. Be aware of and indicate measurement locations when

communicating monitoring information to other workers (for example: the

dose rate was 1.5 mrem/h at 1 meter from the table). Background for

beta/gamma/x-ray will vary but normally will be about 0.01 mrem/h. Ion

chambers will respond very slowly at low dose rates but much faster at

higher dose rates.

For neutron dose rates, we use a neutron dose rate meter. The meter usually


has a large plastic moderator ball attached to the brown electronics package.

Measurements should be made to determine the whole body dose, at least

30 cm from a given object and at waist level. Once again, indicate

measurement locations when communicating monitoring information to

other workers . Background for neutrons will normally be close to zero.

Neutron meters tend to respond very slowly at low dose rates.

Be aware that moderate dose rates at whole body distances will be much

higher near the source because of the inverse square law. For example, a

dose of 10 mrem/h at 30 cm from the source yields 9000 mrem/h at 1 cm

distance from the same source.

NOTE: Dose rate measurements made at “contact” (the detector touching the

surface of the object) may be useful, but will NOT be accurate because of the

detector volume and implications from the inverse square law.

16.12 Meter Operational Checks

Notes:


Regardless of what survey meter you are using, it is essential to perform

operational checks to assure ensure it is functioning properly, prior to

making actual measurements.

The operational checks include:

Familiarization with the meter, readout and controls

Calibration status - does the calibration sticker indicate the unit is still in

calibration? If not, report to the H&S Tech.

Battery condition - if the battery does not indicate sufficient battery

strength, report to the H&S Tech.

Audio function operation (if applicable)

Response to a known radiation check source - if the unit does not respond,

report to the H&S Tech.

Background reading - if background is abnormally high, report to the H&S

Tech.

Operational checks that fail requirements should be investigated and

resolved before using the meter.

If the meter fails any of the operational checks, do not use the meter. Mark it

as not functional (and why) and report it to your H&S Tech as soon as

possible.


Now let’s watch a video that summarizes what we just discussed.

16.13 Operational Checks Video


16.14 Survey Meter Selection

Notes:

You need to answer some questions before you select a survey meter and

begin radiation monitoring.

First, what type of radiation are you trying to measure? - Select your meter

based on the expected radiation type.

Second, are you looking for a radiation field or for contamination on a

surface? - Select an appropriate survey meter for the task.

Third, have I completed my operational checks? - Verify the meter is

operating properly and determine the background value.

Fourth, where are the marked radiation sources in the areas where people

work? - Monitor around sources first and then other areas of interest.

Fifth, how do measurements made relate to the background value? - Are


measurements unexpectedly high?

Finally, what actions (if any) are needed?

16.15 Contamination Monitoring of Personnel

Notes:

One of the most important types of monitoring is personnel contamination monitoring .

I cannot stress enough that contamination monitoring be conducted frequently during all work activities and at the conclusion of work.

The goal is to ensure that radioactivity is being controlled so that it never leaves the controlled area unintentionally.

Always start by checking your gloved hands - monitor the surface of your disposable gloves before touching or handling the probe and before removing your gloves.

Gloves , facial areas, protective clothing and shoes should all be monitored to validate


no contamination is present. Monitor slowly and carefully.

Once PPE has been removed, perform the same monitoring checks on your skin areas and street clothing.

Often it is better to have someone else monitor for you, using a “buddy system.” PPE should not be removed prior to validating no contamination is present.

Should contamination be found, limit your movements and immediately contact the H&S Tech. Do not attempt to decontaminate yourself without the assistance of the H&S Tech.

16.16 Interpreting Results

Notes:

Once you have performed your monitoring, you need to interpret your

results.

If results are close to background (say twice background) or if results are

similar to previous monitoring with no unusual measurements, no actions


are probably required.

However, when readings appear elevated, it is essential that you immediately

report the information to the H&S Tech.

Depending on the readings, it may be necessary to stop work and prevent

access to the area where the reading are elevated.

You may need to:

Report your results to your supervisor and others working in the area

Control access to any potentially contaminated area by limiting traffic in

and out of the area

If you need to control an area because of unusual monitoring

results, consider locking doors

Use a person in constant attendance to control access until the area can

be properly posted by the H&S Tech

Limit potential doses by using time distance and shielding (more on this

later)


16.17 Controlling External Radiation Dose

Notes:

As we have discussed in previous modules, occupational radiation doses are

limited by the DOE.

Additionally, doses are further limited by the ALARA concept, so it is

imperative that you work to properly control your radiation dose.

Four factors are used to directly control external radiation dose. Many times,

multiple factors will be used to reduce radiation doses.


16.18 Limit Source Term

Notes:

The first factor is limiting the source term, that is, limiting the amount of

radioactivity in the area where you will be working.

Only use the activity needed to do the work and keep any other radioactive

material properly stored and shielded to limit potential dose.

The other three factors are:

The time of exposure

The distance from the radiation source and

The use of radiation shielding

Now, let’s discuss these in greater detail -


16.19 Limit Exposure Time

Notes:

Radiation exposure is expressed as a dose rate. A common example might

be mrem/h. Multiplying the dose rate by the time of exposure yields the dose.

This suggests that the time of exposure is a critical factor in controlling

radiation dose.

Lets take an example; say you have work to do where the radiation field is

600 mrem/h.

So if your work took one hour, you could expect to receive 600 mrem of dose.

On the other hand, if you could finish the work in 2 minutes, you would

expect to receive only 20 mrem of dose.

Reducing the time you are in the radiation field reduces your radiation dose.

Never spend unnecessary time near radiation sources and whenever

possible, perform work in low background areas.


Practice complicated or time consuming tasks in “cold” (non-radiation) areas

first to polish skills so the actual time of exposure can be reduced.

Remember - to reduce your dose, limit the time you are in the radiation field.

16.20 Increase Distance

Notes:

It is intuitive that radiation intensity reduces with distance from the source,

however it is not a linear process, instead radiation obeys the inverse square

law.

That is, when you move away from the source the radiation dose rate

decreases with the inverse square of the distance. In the graphic we see a

source (marked as s) emitting radiation through three different distances.


Each square is the same area. At the first distance (r), all of the radiation is

penetrating a single square. Lets say the dose rate is 100 mrem/h.

At the second distance (2r) the area has increased to 2 x 2 squares or 4 times

as great an area - now the same radiation is penetrating all four of the

squares, so only ¼ of the radiation is penetrating a single square. That means

the dose rate would now be reduced to 25 mrem/h.

At the third distance (3r) the area has increased to 3 x 3 squares or 9 times as

great an area - now the same radiation is penetrating all nine of the squares,

so only 1/9th of the radiation is penetrating a single square. That means the

dose rate would now be reduced to about 11 mrem/h.

This means that moving even a small distance away from a source can

dramatically reduce the radiation dose rate. Long tongs or other “stand-off”

tools can be used to increase distance when handling sources.

To reduce your radiation dose, whenever possible maintain your distance

from the source. If you need to work close to the source, use one of the

other factors (time or shielding) to reduce your dose.

Remember - to reduce your dose, maintain your distance from the radiation

source.


16.21 Use Shielding

Notes:

Ionizing radiation is energy (or energetic particles) moving through space. It

is the energy that produces radiation dose.

So, if we can absorb (or attenuate) some of that energy, we can reduce or

eliminate the radiation dose.

Radiation shielding is used to attenuate the energy of the radiation.

To shield gamma and x-rays we use dense materials like lead, steel or

concrete.

To shield beta particles we use plastics like Lucite.

To shield neutrons we use polyethylene, borated polyethylene or water.


Normally shielding requirements will be determined by the Team HP.

Shielding provided must be used as indicated to reduce radiation doses.

NOTE: Removable shielding needed to prevent access to a high radiation

area will be visibly marked: "Radiation Shielding - Do Not Remove without

permission from ES&H."


Notes:


1.How to conduct operational monitoring - and

2.How to properly control external radiation dose

We specifically discussed:

Selecting survey instruments


Performing operational instrument checks

Monitoring work areas and personnel

Responding to survey results

Reducing time of exposure

Increasing distance from the radiation source and

Using appropriate radiation shielding




the quiz button.






17. GLOSSARY

17.1 Untitled Slide

18. RESOURCES/PDF

18.1 Untitled Slide


19. Module 7


19.2 Next Steps


19.3 Module 7

19.4 Objectives

Notes:

This module discusses the safe management of sealed radioactive sources or

(SRS for short).


Our goal is to provide you with the tools to assure adequate control of each

SRS.

After completing this module, you will be able to:***

Define Class 0, I, II and III Sealed Radioactive Sources***

Explain the roles and expectations of LLNL staff using and supporting the

use of SRS***

Describe the protocol for establishing an SRS control system

19.5 Objectives

Notes:

Identify the systems for labeling, inventorying and checking SRSs in and

out***


Describe the correct way to move each class of SRSs***

Explain the protocol for recognizing, responding to and reporting a leaking,

damaged or missing SRS

Let’s start by discussing exactly what a sealed radioactive source is -

19.6 What is a Sealed Radioactive Source?

Notes:

A sealed radioactive source consists of a known quantity of radioactive

material contained within a sealed capsule, sealed between layer(s) of

nonradioactive material, or firmly fixed to a nonradioactive surface by

electroplating or other means.


19.7 Non-Dispersible sources

Notes:

Assuming the capsule remains intact, this makes the source non-dispersible,

eliminating the potential for any radioactive material contamination. Leak

tests, or using swipes to determine if contamination is present, are often

performed on SRSs to verify the capsule is intact.


19.8 SRS hazards

Notes:

However, since SRSs are designed to allow the radiation to escape, they may

still present radiation field hazards. ***

It is very important to remember that the physical size of a SRS is not directly

related to the radiation field hazard. The hazard is, instead, directly related to

the source term (the isotope and activity present).***

Some SRSs produce very low levels of radiation*** BUT others can produce

very intense radiation fields that could injure or kill a person if caution is not

used in handling the SRS.


19.9 SRS Classifications

Notes:

For this reason, we use a hazard classification system to clearly identify the

relative hazard of SRSs used at the Lab.

There are 5 SRS hazard classes, arranged in the order of their relative hazard

from Class 0 up to Class IV.***

The Class 0 SRS presents the least hazard, ***while the Class IV SRS presents

the greatest hazard.

We will discuss these Classes in more detail in a minute, but first we should

talk about the differences between dispersible and non-dispersible sources


like SRSs.

19.10 Sealed sources vs. dispersible materials

Notes:

As mentioned previously, SRSs are non-dispersible sources.*** Non

dispersible sources may also include parts machined out of radioactive

metals like Uranium.

Properly handled and controlled, the radiological hazard from a non-

dispersible source is limited to the direct radiation field. This means that

contamination control requirements are limited. ***Although not required, it

is a very good practice to use gloves when handling SRS.

This course, HS6010-W, in combination with the Integrated Radiological

Worker Practical course HS6010-P, constitutes adequate training for use of

non-dispersible sources like SRSs.***


Dispersible sources consist of radioactive materials in a gas, powder or liquid

form. In addition to the direct radiation field, these sources also present a

potential for contamination if improperly managed.***

Dispersible sources always require contamination controls of various kinds,

especially PPE.

Additionally, ventilation controls, secondary containment and physical

barriers may be required for the safe use of dispersible sources.

Use of dispersible sources requires this course plus the follow-on

Contamination Control course HS6300-W.

19.11 Classes of Sealed Radioactive Sources (SRSs)


Notes:

Now we should talk about the specific Classes of SRSs. Classes denote

relative hazard of the source.


Notes:

Class 0 and I SRSs present a minimal physical hazard and therefore, require

less controls.***

Class 0 SRSs contain 1 nCi or more of radioactivity, but less than the Class

I threshold values. ***

Class I SRSs meet a regulatory threshold for labeling as radioactive

material but are not Class II, III, or IV sealed radioactive sources and are not

commercially available items.



Notes:

Class II SRSs are SRSs that the owner chooses to administratively control

even though they are less than the Class III thresholds. They do not require

DOE accountability but they are accountable at the local level. Leak tests

may be required in accordance with the NRC license under which they were

acquired. Class II SRSs are assigned to an appropriate sealed radioactive

source custodian (or SRSC)***

Class III and IV SRSs are accountable under DOE rules. These type of sources

typically present much greater hazards than the 0, I or II SRSs. Class III, and IV

SRSs are also assigned to a SRSC.***

Class III SRSs contain at least the amount of activity specified in ES&H

Manual 20.2, Appendix E, but are not Class IV SRSs; or are SRSs that have

been acquired under an NRC specific license.***

Class IV SRSs contain 50 times the ES&H Manual 20.2, Appendix E values.


19.14 Roles and responsibilities

Notes:

Everyone involved in use of SRSs has certain responsibilities.

These responsibilities are clearly spelled out in the*** ES&H Manual Volume

20.2 Section 8. All SRS users need to read and follow this procedure.

You can access the procedure by clicking on the link and navigating to

Section 8.


19.15 Responsible Individual (RI)

Notes:

The Responsible Individual (or RI):

Assigns a SRSC for Class II, III and IV sources and

Ensures staff using SRSs receive this HS6010-W training

NOTE: Class 0 and 1 SRSs do not require a specific SRSC, but must be

included in the locally-controlled SRS program.


19.16 SRSC

Notes:

The SRSC:

Establishes and maintains the log in/log out system for SRSs that may be

temporarily removed from the local work area or used in areas not

otherwise radiologically controlled.

Maintains and periodically verifies a list of Class 0 and I SRSs under their

control.

Makes all Class II, III, and IV SRSs available to the ES&H Team so they can

conduct the semi-annual inventory and leak tests and,

Uses the “SRS Change Form” to report changes to administrative or

physical aspects of Class II, III, or IV SRS.


19.17 ES&H and Materials Management

Notes:

The Materials Management Section maintains the official inventory of all

Class II, III, and IV SRSs.

The ES&H Team conducts the SRS inventory and leak test on each Class II, III,

and IV SRS every six months.


19.18 SRS Users

Notes:

There are also some basic expectations for all workers who handle or use

SRSs.

These include:

Understanding the physical limitations of the SRS container and not using

it for purposes or in environments other than for which it was intended or

authorized.

Not carrying SRSs near the body (for example in your pocket).

Not rubbing or abrading any electroplated SRS.

Not breaching the SRS encapsulation. If any breach in an SRS is suspected,

immediately stop your work, leave the area, and call ES&H, keeping in mind

that you or your work area may be contaminated.


19.19 SRS Handler requirements

Notes:

All workers who handle or use SRSs should also:

Periodically surveying the SRS or source container for contamination. Call

the ES&H Team health and safety technician if removable activity is

detected.***

Visually inspecting the SRS prior to each use. If the SRS appears degraded

in any way, or is suspected or known to be leaking, do not use or handle the

SRS; promptly call the H&S Tech and wait for them to arrive.

Not disposing of, re-encapsulating, or handling any SRSs that are found to

be leaking. ***

Immediately informing the SRSC and the H&S Tech if a source cannot be

located. Class II, III, and IV SRS are “accountable” and suspected loss of an

SRS must be reported within certain time limits - more on this later.***


NOTE: DOE requires LLNL to report extremely low levels of contamination

found on people or in most work areas, therefore a breached or leaking SRS

(even a Class 0 SRS) can easily produce enough contamination to require an

occurrence report to the DOE.

19.20 SRS control system

Notes:

The most basic control exercised over any type of radioactive material is an

inventory. This particularly applies to SRSs, as they are the radioactive

materials most likely to be lost or misplaced.

It is extremely important that you exercise appropriate control over any SRSs

that you either use or are responsible for.***

LLNL requires the SRS Custodian (SRSC) to controlling SRSs by establishing

and using a local control system, usually a logbook based system.

Additionally, SRS users are responsible for using the control system.***


NOTE: Use of the control system is NOT OPTIONAL, it is a requirement of the

ES&H Manual. Specific requirements of the control system will be covered

later in this module.

19.21 Log-in/Log-out system

Notes:

Logbooks may either be a physical book or an electronic record system. If

electronic records are used, they must be backed-up on a regular basis to

assure their integrity.

It is important that a unique SRS reference number is assigned to each SRS

placed in the control system.

The number can be the unique manufacturer assigned serial number of the

SRS or some other unique identifier assigned by the custodian.


19.22 Logbook entry

Notes:

The logbook should contain a complete and accurate description of each SRS

being controlled. The description must be clearly associated with the

assigned reference number.

The reference number will then be used when logging the associated source

in or out of the logbook.***

Logbooks should be inspected and reconciled on a regular basis by the

SRSC.***

Logbooks must be readily available for inspection and are considered

important operational records that should be retained for at least 36

months.***

NOTE: Systems using sign-in / sign-out white boards may supplement the

logbook but do not create a record; therefore, they do not meet the record-

keeping requirement.


19.23 Logbook entries

Notes:

The following entry information should be included in the logbook for all SRS

transactions, regardless of their Class:

The name of the person checking out the SRS.

The assigned SRS reference number

The date of SRS removal.

The destination of SRS (NOTE: this is recommended, but not required).

The date of SRS return and

Any other pertinent comments you care to include (e.g., permanent

transfer)


19.24 SRS inventory control

Notes:

The SRSC should maintain a list of Class I SRSs under their control and

periodically verify the list is accurate.

Class 0 and I SRSs are included in the locally-controlled SRS program.

Class 0, I, or II SRSs must be logged in and out of the local work area.

The local work area is generally the room (or rooms) identified on a work

control document where work is conducted with the SRS.


19.25 Lost SRS (Class 0, I, and II)

Notes:

If any Class of SRS becomes lost, make a notation in the logbook, then notify

the Authorizing Individual and the ES&H Team health physicist in a timely

manner.


19.26 Lost SRS (Class III and IV)

Notes:

Specific timely actions are required should a Class III or IV SRS becomes lost.

Initially, make a note in the logbook and immediately notify the Authorizing

Individual, the Directorate Assurance Office, the Materials Management

Section, and the ES&H Team health physicist. ***

The DOE may also need to be contacted. Document 20.2, section 7.4 contains

specifics on actions required for lost Class III and IV sources.


19.27 SRS disposition and change form

Notes:

You must make an SRS logbook entry whenever removing and returning

Class III or IV SRSs from their storage location. A storage location is the

cabinet, drawer, shield, etc. used for storing the SRS - it is not the local work

area.

SRS custodians should use the SRS change form to change administrative or

physical aspects of a Class II, III, and IV SRS.

The EH&S Team conducts semi-annual inventory and leak tests of each Class

II, III, and IV SRSs, unless the SRS is removed from service, is located in an

area that is unsafe for human entry, or is otherwise inaccessible.

To remove a Class II, III, or IV SRS from service, ensure the SRS is:

Labeled as “out of service” (NOTE: Contact the ES&H Team to obtain an

“out of service” label).

Stored in a controlled location - distinct from “in use” SRSs.

Inventoried on a semi-annual basis.

Leak-tested - prior to being returned to service.


19.28 Lost SRS notifications

Notes:

Potentially lost SRS or other radioactive materials is a very serious matter.

Timely notification is an essential for requirement for compliance with the

ES&H Manual. If in doubt, always err on the side of caution in reporting

potentially lost SRS or other radioactive materials.

Notification requirements are listed in the illustrated Table 6. As you can see,

such notifications vary dramatically with the Class of SRS.

Section 7.4 of Document 20.2 provides detailed information on requirements

for reporting and other actions required should a SRS become lost.


19.29 Labeling SRSs

Notes:

Like any other radioactive material, SRSs require appropriate labeling with

the radiation trefoil symbol.

1.If the size or configuration of the SRS precludes application of a suitable

label, the label should be attached to the source container or mechanism

containing the SRS.

2. Class 0 and I SRSs have certain labeling options. Class 0 and 1 SRSs must:

a. Bear the Class 0 or 1 label provided by the ES&H Team, or

b. Be installed in (or on) other equipment (say as an instrument check

source), or

c. Be treated as dispersible radioactive material (as opposed to a SRS).

3. Class II, III and IV SRSs require proper labeling as radioactive material.

Labels should be durable and periodically inspected to assure they are


affixed properly.

4. NOTE: Certain SRSs that are accounted for in the Controlled Material

Accountability Tracking System (or COMATS) and intended to remain in

Superblock are exempted from some requirements.

19.30 Change forms

Notes:

You must use the SRS change form:

To change administrative or physical aspects of a Class II, III, and IV SRS.

To change the SRS Custodian. Note: Requires obtaining the signature of

the new SRC custodian, or attaching an e-mail noting their acceptance of

the SRS(s).

To process off-site shipments of Class II, III or IV SRS and to indicate the

return of a SRS from an off-site location


To change an on-site location of a SRS

To change the Class of a SRS

For instance, SRC custodians may request Class 0 or 1 SRSs be listed as

Class II, which includes them in the MM inventory and requires semi-annual

inventory and leak tests

SRS custodians may also request Class II SRSs be removed from the

MM inventory

To remove a Class II, III, or IV SRS from the MM inventory.

Retain copies of all SRS Change forms submitted.

NOTE: Multiple SRSs may be included on the same form - if the same change

is to be made to each SRS.

19.31 Who can move an SRS

Notes:

Any radiological worker is allowed to move Class 0, I and II sealed radioactive

sources. However, you must contact materials management to move any


Class III or IV source. NOTE: You may not use a bicycle or private vehicle to

radioactive sources.

19.32 Summary

Notes:


Definitions of Class 0, I, II and III Sealed Radioactive Sources

The roles and expectations of LLNL staff using and supporting the use of

SRS

The protocol for establishing an SRS control system

Identification of the systems for labeling, inventorying and checking SRSs in

and out


The correct way to move each class of SRSs AND

The protocol for recognizing, responding to and reporting a leaking,

damaged or missing SRS




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20. GLOSSARY

20.1 Untitled Slide

21. RESOURCES/PDF

21.1 Untitled Slide


22. Module 8


22.2 Next Steps


22.3 Module 8

22.4 Objectives

Notes:

This module discusses off-normal and emergency situations and the

appropriate responses.


After completing this module, you will be able to:

Identify indicators of off-normal conditions

Respond appropriately to off-normal conditions, including soil

contamination areas

Initiate and participate in critiques

Participate in post-job reviews, as applicable

Let’s start by discussing how an off-normal condition differs from a normal

condition -

22.5 Normal radiological conditions

Notes:

Normal radiological conditions are those where the radiological conditions


such as contamination and/or radiation levels are consistent with your

knowledge of the area and work conditions.

The work controls should be adequate because the radiological conditions

are found to be as expected to be during planning activities. ***

Such operations are planned and executed so that radiation doses are

ALARA and the spread of contamination is controlled.

22.6 Obviously unusual radiological indicators

Notes:

But what if something unusual or unexpected happens?

What if you saw an overturned drum with the contents spilled across the

floor when you enter a work area or what if you heard a continuous air

monitor alarming as you opened the door to a room?

These two conditions would be pretty dramatic and you would instantly


know to stop and exit.

22.7 Subtle unusual radiological indicators

Notes:

But what if the conditions were not as dramatic? What if you were to

monitor an area and detect 20 mrem/h where your work package limited the

allowable dose rate to 10 mrem/hr?

What if you were to see a small puddle of liquid on the floor near your work

area without an obvious source? What do you need to do in these instances?

Such events could indicate the development of an off-normal condition - one

that might create either unsafe or problematic radiological conditions.

So what exactly is an off-normal condition?


22.8 Off-normal Conditions

Notes:

Off-normal radiological conditions are conditions created when the scope of

activities fall outside of the appropriate work controls.

Upon recognition of an off-normal condition, it is necessary to;

First - know what actions to take AND

Second - act quickly to assure your radiation dose and that of co-workers is

minimized and ensure the unexpected radiological conditions are properly

addressed.

Failure to respond appropriately could result in unnecessary exposure, skin

contamination, a spread of radioactive contamination, unfavorable attention

by regulators and unwanted coverage by mass media.


22.9 Indicators for Off-normal Conditions

Notes:

There can be many different indicators of potential off-normal radiological

conditions.

Sometimes, it’s a subtle thing - something just doesn’t look right - maybe you

see an overturned container or notice a spill of liquid - these type of things

need to be investigated and actions taken as needed

To be vigilant to such things, you need to maintain an ongoing awareness of

the radiological and other conditions in the work area.

On the other hand, some conditions are more obvious, these are:

An elevated or alarming supplemental dosimeter reading

Unexpected radiation readings or contamination levels


Activation of a radiological alarm AND***

An emergency condition extending beyond the work area

We should discuss these in more detail…..

22.10 Dosimeter Readings

Notes:

One indicator of an off-normal condition is an elevated or alarming

supplemental dosimeter.***

As we discussed in a previous module, supplemental dosimeters are

required for entry into “CAUTION - High Radiation Areas.”

While in the area, the supplemental dosimeter must be read periodically.

However, if a supplemental dosimeter reading indicates a total dose or rate

of exposure substantially greater than planned OR*** if the supplemental


dosimeter is off-scale or not functioning correctly, take the following actions:

Stop work immediately,

Leave the high radiation area

Notify your supervisor of the condition and

Inform and consult with your Team HP prior to continuing work

22.11 Survey Meter Readings

Notes:

Another indicator of an off-normal condition are unexpected radiation

readings or contamination levels.

Radiation readings well above expected levels may be an indication of:

Misplaced radiation sources

Unexpected shielding changes

Contamination from a leaking SRS


Immediately report to your H&S Tech any readings well above expected

levels.

Warn others of the situation and control access to the area until the issue

can be resolved.

22.12 Potential consequences

Notes:

Off normal conditions do NOT need to be spectacular events to create real

problems.

A word of caution is appropriate regarding “small” activity check sources

which are often thought of as being inconsequential. ***(arrow callout)


Take as an example the Pu-239 check sources attached to our alpha survey

instruments.

These contain less than 10,000 dpm of activity electroplated onto a metal

disc.

Now assume some metal object was allowed to scrape hard across the

electroplating, breaching the source and liberating perhaps 2000 dpm of the

activity as alpha contamination.

The allowed surface contamination value for Plutonium is only 20 dpm/100

cm2, so this “small” event could:

Spread alpha contamination in an uncontrolled area AND

Create the potential for personnel contamination and potential internal

radiation dose.


22.13 Radiological Alarms

Notes:

A third indicator of an off-normal condition is activation of a radiological

alarm.

Radiation Area Monitors (RAMs) (sometimes called Area Radiation Monitors

(ARMs)) are radiation detector systems used to monitor ambient radiation

dose rates in an area.

They are often used in facilities with Radiation Generating Devices as well as

facilities with large activity SRSs, like calibration facilities.

They are normally preset to alarm with both an audio and visual indicator

when an increased dose rate is detected.

Should a RAM alarm while you are in the area, the appropriate response is

to:

Immediately leave the room or area - move quickly and safely to a low

background area


Contact your H&S Tech immediately to report the alarm

You are not allowed to disregard any radiological alarm - never assume a

false alarm - always evacuate the area when you hear the alarm.

There are severe consequences possible for disregarding radiological alarms.

These include:

• Possible excessive radiation dose

• Unnecessary spread of contamination

• Unnecessary personal contamination

• Disciplinary action

Remember to report all ALARMs to your H&S Tech immediately.

22.14 Area Emergencies

Notes:

The last indicator of an off-normal condition is an emergency condition


extending beyond the work area.

Circumstances can develop that affect large areas and potentially create off-

normal radiological conditions.

These include (but are not limited to):

Fires

Earthquakes

Adverse Weather Conditions (tornado, flood, etc.)

Possible Civil Unrest or Terrorist Attacks

Such conditions will be communicated to staff by use of the building paging

systems.

If evacuation of the building is ordered, leave and move immediately to your

assembly point.

If evacuation is not ordered, but an area emergency is in progress,

immediately place work in a safe condition and follow directions provided.

Now we need to talk about how to respond to an off-normal condition.


22.15 Off-Normal Response

Notes:

When responding to off-normal conditions, do not panic - determine what is

happening and then respond appropriately.

There are three basic levels of response -

Implementing a “Safety Pause” condition

Implementing “Stop Work” procedures

Determining that an evacuation is required

You are fully authorized and expected to activate the appropriate response

depending on the off-normal condition you observe.

Let’s first talk about use of the “Safety Pause.” Details on Safety Pause

procedures can be found the ES&H Manual Document 2.1.

A “Safety Pause” refers to stopping work on a temporary basis because of a

potentially unsafe condition that can be corrected by the worker with


minimal effort and time.

For example:

To remind workers to put on their safety glasses, lab coats or other

radiological PPE. NOTE: A safety pause to remind people of PPE is

appropriate only if the work hasn’t started. If the work has started and the

appropriate PPE is not being used…it moves to a stop work.

Discussing the expected consequences/actions of a step about to be

performed (for instance, is monitoring required prior to moving this source).

***(safety pause photo)

Safety Pauses can be called by any worker, any time, whenever they believe a

job cannot be performed safely.

If there is need for additional corrective action(s), then the situation is

elevated to a formal “Stop Work.”

Once all affected personnel agree there is no unsafe condition, the pause is

terminated and the work can be resume.

Do not be concerned that such actions would be viewed in a negative light by

Lab management.

Lab management has stated in writing that “We will NEVER allow negative

consequences against employees for calling a Safety Pause or a Stop Work,”

so don’t be afraid to act when needed.

Your quick action limiting the extent of the problem will help us to get back

to work faster and more safely.”


22.16 Stop Work Initiation

Notes:

Stop Work refers to work stopped because of a problem that is “not readily

fixable.”

If it is determined that the work’s operating limits or controls are not being

followed, or when common sense indicates that people, property, or the

environment are in imminent or substantial danger, the activity shall be

stopped or suspended by any worker until appropriate remedial actions are

taken.

When you become aware of an unsafe condition, you are authorized to do

the following:

Stop the unsafe work activities and that of any other individuals in the

area who may be affected by the situation.

Clear all at-risk personnel from the area, and post personnel to warn

others trying to enter the area.

Inform all affected personnel of the reason for the work stoppage,

including the RI and/or work supervisor.


Inform your supervisor or manager, if they are different from the work

supervisor.

22.17 Stop Work Rules

Notes:

Once again, you have the authority to stop work when appropriate. Of

course there are some rules to apply:

1. Stop work authority must be exercised in a justifiable and responsible

manner.

2. Resumption of radiological work stopped because it is “imminently

dangerous” or “substantially dangerous” requires the written approval of the

AI and the concurrence of the RCM.

3. You must stop work activities for:

a. Inadequate radiological controls

b. Radiological controls not being implemented

c. Radiological control hold point not being satisfied

4. Once radiological work has been stopped, it must not be resumed until

proper radiological control has been reestablished. Resumption of work


requires the concurrence of the Authorizing Organization and the Team HP.

NOTE: Section 6 of Document 20.1 contains details on the radiological use of

“Stop Work Authority.”

22.18 Evacuation Response

Notes:

The highest level of response is calling for an evacuation.

This might be triggered by a radiological alarm condition, a fire or some

other situation where remaining in the affected area could present harm to

employees.

When an evacuation is called, all persons must exit the area and be

accounted for.

NOTE: You may place work in a safe condition prior to evacuating the facility,

but only if the task can be performed without endangering persons.


Remember to report all injuries, accidents, and illnesses to your RI or

supervisor.

22.19 Off-Normal Condition: Soil Contamination

Notes:

If you identify contamination in soil, respond by implementing standard off-

normal controls for a contamination area.

Be careful not to disturb the soil, this minimizes the chance of contamination

dispersal.


22.20 How to respond in an emergency situation

Notes:

During an emergency situation you might think you have to enter a posted

radiation area to

Save a life

Protect large populations of people

Protect valuable property

There are written guidelines that specify:

Who can authorize you to enter these

areas

The conditions and or dose under

which you are allowed to enter

these areas

These guidelines can be found in

ES&H Manual, Document 22.6.


22.21 Evaluating Off-Normal Responses

Notes:

The creation of any off-normal condition is an indicator of one or more

weakness in the safety system.

Therefore, an evaluation of the off-normal condition and response is usually

appropriate.

Quite often, an informal or formal critique may be called by one or more

departments who are involved.

You should attend any critique where you were involved or have information

that may help in assessing the off-normal condition or response.


22.22 Critiques

Notes:

A critique is a special meeting of knowledgeable individuals to identify and

document pertinent facts either;

Following an unusual radiological situation or

at the satisfactory conclusion of a new or unusual operation involving

radiological controls.

The purpose of the critique is to establish and record the facts associated

with the event and to develop and disseminate lessons learned.

1. The Authorizing Organization must utilize the ES&H Manual, Document 4.7,

Analysis Methods.


22.23 When to hold critiques

Notes:

a. Critiques should be conducted for successes and abnormal events.

Management should hold critiques for other conditions that generate

concerns about radiological controls or conditions, as needed. Evaluation of

complex evolutions or events may require multiple critiques.

b. The RCM must be invited to participate in critiques related to radiological

operations, conditions, and controls. The RCM may choose to participate

directly, send an alternate, or not participate.

c. At a minimum, critiques must be held for the following events or

conditions;

Contamination above the Document 20.2 Appendix D thresholds is

detected outside of an RCA.

Radioactive contamination is tracked off-site.

Identification of an uncontrolled high radiation area.

Detection of a failed interlock associated with a radiological enclosure.


An unplanned external whole body dose exceeding 100 mrem occurs.

Planned special exposure provisions (as specified in Section 3.2.5) are

used.

As directed by the Authorizing Organization or the RCM.(RCM directing)

22.24 Post-job Reviews

Notes:

Sometimes, post-job reviews are used by departments in lieu of critiques, to

review and analyze performance at the completion of non-routine

radiological job.

At a minimum, a post-job review must be conducted if:

a. A stop-work order is issued for radiological purposes.

b. A worker unexpectedly exceeds their Administrative Control Level.

c. The pre-job dose estimate is exceeded by 100 mrem.

d. Operations result in the issuance of an Occurrence Report related to

radiological operations.


e. Significant radiological lessons learned are identified OR if

f. Indicated by the Authorizing Organization or ES&H.

The post-job review must involve the workers, the ES&H Team, and any other

individuals that may have impacted or been affected by the situation.

As appropriate, the post-job review should include reviews of:

a. Doses compared to the pre-job estimates.

b. The effectiveness of the radiological controls.

c. Any adverse events occurring during the work, such as skin

contaminations, unexpectedly high individual exposures, etc.

d. Conflicts between radiological safety requirements and other safety

requirements.

e. Opportunities to improve performance during repeated or similar work.

f. Significant differences between expected and actual radiological

conditions.

g. Worker input regarding possible improvements in radiological safety

practices.


22.25 Post-job Review Content

Notes:

As appropriate, the post-job review should include reviews of:

a. Doses compared to the pre-job estimates.

b. The effectiveness of the radiological controls.

c. Any adverse events occurring during the work, such as skin

contaminations, unexpectedly high individual exposures, etc.

d. Conflicts between radiological safety requirements and other safety

requirements.

e. Opportunities to improve performance during repeated or similar work.

f. Significant differences between expected and actual radiological

conditions.

g. Worker input regarding possible improvements in radiological safety

practices.


22.26 Summary

Notes:


Identifying indicators of off-normal conditions

Responding appropriately to off-normal conditions

Initiating and participating in critiques AND

Participating in post-job reviews




the quiz button.






-

23. GLOSSARY

23.1 Untitled Slide


24. RESOURCES/PDF

24.1 Untitled Slide

25. Module 9



25.2 Next Steps

25.3 Module 9


25.4 Objectives

Notes:

This module concludes our discussion of how to safely conduct radiological

work at the Lab.

After completing this module, you will be able to safely conclude work and

exit radiological areas by:

1.Ensuring the radiological workplace is maintained in a “safe” condition

2.Ensuring radiological conditions are properly identified and posted

3.Removing PPE safely in accordance with LLNL and other facility instructions

Topics will include:

Ensuring radioactive materials are properly identified and stored

Identifying actions that affect radiological conditions

Determining when to contact your ES&H Team or work supervisor


Removing radiological PPE properly

Let’s start by discussing the importance of creating a “safe” radiological area.

25.5 Safe radiological condition

Notes:

A “safe” radiological condition is normally characterized by all radiation

sources (e.g., drums/containers, RGDs, sealed sources) being properly

controlled, identified and shielded.

Lab policies require that radioactive materials and radiation generating

devices be kept properly secured to prevent inadvertent exposures from

occurring.

This, by itself, may not be sufficient because a number of radiological

workers could be authorized to enter the controlled area.


We need to ensure that the area is safe to enter for all those persons who

have access.

Radiological areas must always be placed in a proper “safe” condition before

leaving the area.

So what would constitute an “unsafe” radiological condition?

25.6 What makes a work area unsafe?

Notes:

An unsafe radiological work area is characterized by one or more of the

following:

An improperly secured radiological area.

Persons being unaware of existing radiological conditions when entering

the area.


Sources of radiation not being properly controlled or contained.

Radiation sources and hazards that are not properly identified.

Improperly shielded radiation sources.

25.7 Unsafe radiological work area

Notes:

Since radiation workers are taught that radiological hazards will be properly

controlled and marked, any of these conditions could result in inadvertent

radiation exposures.

A few examples of actions that could create an “unsafe” radiological work

area include:

1.Leaving a radioactive material area open or unsecure while using the

restroom.

2.Failing to post the entry to a radiological area after any substantial changes

in radiation levels from using a Radiation Generating Device.

3.Leaving a Class IV SRS outside of it’s storage shield when it is not being


used.

Maintaining a “safe” radiological work area is an LLNL operational

requirement.

25.8 Actions to make a work area safe

Notes:

As indicated before, a “safe” radiological condition is characterized by all

radiation sources being properly controlled, identified and shielded.

SRS inventory controls, proper marking/labeling of sources and proper

facility monitoring are elements required to ensure the safety of the area.

But, perhaps the most important factor, is the human factor - maintaining

situational awareness of the radiological environment.


25.9 Actions that make a work area safe

Notes:

Ask yourself these type of questions before leaving the radiological area:

1.Are all the sources properly inventoried, stored and shielded?

2.Did I monitor ensure the radiological conditions I started with have not

changed?

3.If the radiological conditions have changed, have I made the appropriate

notifications?

4.Do I need to place a note on the door to the facility with special information

on any changes?

5.Have I checked myself for contamination (as applicable)?

6.Is the facility properly secured?

These tasks are not difficult and should not take long to complete.

Being “too busy” to perform these tasks could result in all sorts of problems


later on, say if an accountable SRS becomes lost because it was not properly

stored or inventoried.

Let’s talk about notifications required if an unsafe condition were to develop.

25.10 When to contact ES&H and your supervisor

Notes:

Always notify your supervisor and ES&H immediately if:

1.There are unexpected levels of contamination are found on surfaces or if

personnel contamination is detected.

2.A Class I, II, III or IV SRS cannot be located .


3.Of any spills, changes in radiological conditions or unplanned events are

discovered during monitoring

4.Of any other incidents or conditions that may warrant attention AND

5.Changes in the workplace that might increase worker dose or affect

radiological postings (remember that only ES&H Staff can make changes to

postings).

In general, if you are not sure whether or not to make a notification - err on

the side of caution and make the notification anyway.

It can’t hurt anything and at the very least you will learn from the experience

- always better to be safe than sorry!

25.11 Minimum PPE required

Notes:


As stated previously, minimal PPE for radiological work normally consists of

lab coat, disposable gloves and closed toed shoes.

Radiological PPE required for work must be properly removed (or doffed)

when leaving the radiological area. Generally, do not wear radiological PPE

outside of radiological areas.

The only exception to this rule is when you are moving immediately and

directly to another radiological work area that requires the minimal level of

PPE (NOTE: other levels of PPE, like anti-contamination coveralls, cannot be

worn to another radiological area).

25.12 Proper removal of PPE

Notes:

The steps involved are as follows:


1.Determine if radioactive contamination is present on the PPE by

monitoring your disposable gloves first, before touching the survey meter

probe or anything else.

2.If your gloves are contaminated, slowly and carefully remove your gloves,

rolling them inside out and disposing of them properly in the radioactive

waste.

3.Monitor your hands to ensure they are not contaminated, then continue to

monitor all your other PPE, verifying it is not contaminated and disposing of

them properly.

4.If you are using a cloth or other non-disposable lab coat, ensure it is

uncontaminated before storing it for the next use.

5.Finally monitor yourself and your clothing thoroughly to ensure your

person is not contaminated.

6.Contaminated PPE must be handled carefully with clean disposable gloves,

so as to prevent the spread of contamination - always report contamination

found on PPE to your H&S Tech as soon as possible.

7.Be sure that any contaminated PPE or other items are properly bagged and

marked as radioactive material. Your H&S Tech will help you with this.

8.If you do find contamination on your person, immediately stop the process

and have someone else call your H&S Tech to respond and assist you in

become decontaminated.

Only leave when you are confident that no contamination is present that

could be spread from the facility.


25.13 Summary

Notes:

This module discussed how to safely conclude work and exit radiological

areas by:

1.Ensuring the radiological workplace is maintained in a “safe” condition

2.Ensuring radiological conditions are properly identified and posted

3.Removing PPE safely in accordance with LLNL and other facility instructions

Topics covered included:

Ensuring radioactive materials are properly identified and stored

Identifying actions that affect radiological conditions

Determining when to contact your ES&H Team or work supervisor

Removing radiological PPE properly

This module concludes our discussion of how to safely conduct radiological


work at the Lab.




the quiz button.



You must take and pass the quiz for this module to complete the course and

get credit for HS6010-W.

When you are ready, click the quiz button to take the quiz.

IMPORTANT - remember that after you complete this course, your will still

need to take HS6010-P “Integrated Radiological Practical” to complete your

radiological worker training