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REPLY TO ATTENTION OF:

NGGU-CST

MEMORANDUM FOR RECORD:

SUBJECT: Executive Summary of CST Actions Taken

1. This memorandum provides a summary of actions taken during the Alert, Deployment and Response phases of CST operations. The information is captured in this memo and appropriate Tabs.

2. Summary of Alert Actions:

a. Timeline: TIME 94thCST-WMD SITREP

18JUN12 1359 LTC Limtiaco received a call from GHS, Mr. Leo Expia informing

of an unaccounted 2401 Troxler Soil Moisture Gauge. Requested for technical assistance to dispose the equipment. LTC Limtiaco advised to talk to Guam EPA and consult with UNITEK Environmental, civilian contractor.

20JUN12 1945 Initial call of Request for Assistance and Meeting

21JUN12 0800 Meeting at Guam Homeland Security with civil authorities 1130 94th CST receives authorization from the TAG to deploy for

22Jun2012 @J 0930hrs 22JUN12

0805 GU-JOC notified of situation via email SITREP 0924 Strike team deploys from Home Station to DPW 0937 LTC Limtiaco links up with Incident Commander (IC) Edward

Flores, GFD Captain 0940 PMT Conducted. Footprint ready for occupation. 1030 IEP brief conducted and approved by IC 1045 Team makes en!ry into HZ 1118 Team finds readings above background with AN-PDR 77 Alpha

Probe with 132 CPM. US DOE determines that a possible leak will be detected when readings more than 100 CPM above Back Ground. Back Ground Readings from 0-1 0 CPM.

1142 1st Entry completes. 1155 Debrief conducted and 2"0 Entry Brief. 2"0 Entry is joint 94m CST

andGFD.

SDMS DOCID# 1138585

1210 2"0 Entry team makes entry into container to mitigate and over pack. Gauges.

1220 Overpacking completed and no readings above Back Ground. 1225 2"0 Entry mission complete 1225 All Objectives completed.

b. Situation:

Guam Environment Protection Agency (GEP A) Air Safety Administrator, Mr. Peter Cruz and Guam Department of Public Works, Mr. Carl Dominguez and Mr. Ricky Iglesias requested through Homeland Security to have 94th CST to provide analytical and technical support on 200800JUN2012. The 94th was activated to determine ifthere is a leak in a wooden box filled with a Troxler 2401 Nuclear Gauge that utilizes Compton scattering and photoelectric absorption of gamma protons to measure the total or wet density of materials being tested. The instrument has two methods of measuring densities, the backscatter method and the direct method. Second, 94th CST will mitigate the situation as necessary if there is a leak in the wooden box and Troxler device. Upon the findings, 94th CST will provide recommendations or disposition of wooden container and device. 94th CST members will provide technical and operation support to determine leaks and provide swipe tests samples for GEP A to disposition for further testing.

On 5March20 12, representatives from Guam EPA tested the outside of the wooden box and Container No.8 using a BNC SAM 940. SAM 940 is portable radioisotope identification (RIID) system that detects and identifies multiple nuclides, providing quantified results using real time and MCA analysis. An e-copy of the results was transmitted to Mr. Sam Poppell, USEPA Radiological Response Team Commander, for his advised and recommendation. The recommendations are as follows: • Secure the source and prevent entry to the area (Complete) • Department of Public Works-Guam to account for the radiation source and other radiation sources in the facility • IfDPW-Guam cannot account for the radiation source, recommend Guam Homeland Security Office of Civil Defense be notified to active the 94th Civil Support Team The wooden box that was found in Container No.8 with a radioactive label indicates Radium 226, Beryllium. Additional markings on the box with label verses below: • Special Form Type "A" Radioactive Material Sealed Source USA DOT 7A • Model2401 Gauge, Surface Moisture Density, Troxler Laboratories, Raleigh, North California, USA

94th CST deployed the ADVONIMED/Survey Section to link up IC with GFD CPT Flores. IC objectives were to conduct leak detection/contamination, check box integrity, mitigate if necessary, provide recommendations for disposition (GEPA). Mission complete.

2

b. IC's Objectives:

• Conduct leak detection to determine the extent of contamination (Complete) • Field Screening of the Gauge for contamination (Complete) • Conduct wipe test on Gauge (Complete) • Mitigate by overpacking (Complete)

3. Substance Identification and Analysis:

CHEMICAL 0 Substances [gl No substances detected

BIOLOGICAL 0 Substances detected [gl No substances detected

RADIOLOGICAL [gl Substances detected: Particulate readings of 132 CPM 0 No substances detected

OTHER THREATS 0 Substances detected [gl No substances detected

4. Summary of Other Services Provided: (communications support, medical support, technical reachback, modeling, decontamination)

[ J Communications Support Summary

~ Medical Support Summary [gl Technical Reach-back Summary

0 Decontamination Support Summary [ J Hazard Plume Modeling Support Summary

0 Other Support Provided (describe}

5. Law Enforcement Sensitive Information: N/A

6. Recommendations to the Incident Commander: (checked items)

0 Scene presents a continued threat to the public

[gl Additional local, state, and/or federal assistance is recommended to process this scene (consult state HAZMA T I WMD Response Plan for phone #s) The IC was advised that a local HAZMA T contractor should be contacted regarding disposal of the underground storage container and potential soil contamination from the contents within the container.

[gl Additional medical treatment is not required.

0 Other recommendations pertinent to this scene Notes:

3

7. Contact Information: a. Primary Contact: LTC Joseph S.B. Limtiaco 671-898-9641 (c) b. Alternate Contact: Capt Victor P. Balajadia 671-898-0848 (c) c. FAX 671-735-4201 d. Address: 94th CST, 430 Army Drive, BLDG 500 Barrigada, GU 96913-4421

8. Approval Verification:

ared by: Capt Victor P. Balajadia, 94th CST Operations Officer

~~--~----~-----------Date: ..:2..?-:t'~c---<- ..?01?-

Approved by: LTC Joseph S.B. Limtiaco, 94th CST Commander

~ Date: 2-Z- JqA) Z<?IZ.

4

1. Incident Name 2. Operational Period (Date/Time) UNIT LOG Dept. Of Public Works Soil Density Gauge From: 22JUN/0900 To: ICS 214-0S

3. Unit Name/Designators 4. Unit Leader (Name and ICS Position) Survey Team, 94th CST (WMD) Fire Captain Edward Flores

5. Personnel Assigned

NAME ICS POSITION HOME BASE

LTC Limtiaco, Joseph Commander, 94th CST

MAJ Tajalle, Ray PA, 94th CST

CPT Balajadia, Victor OPSO, 94th CST

SFC Meno, Bruce OPS NCO/HAlMA T Modeler, 94th CST

SSG Cruz, Anthony Survey Team Leader, Acting

TSgt Martinez, Lance CBRN NCO

SGT Valdes, Tanny CBRNNCO

SGT Quitugua, Matthew CBRN NCO

SSgt Eclavea, Christine CBNRNCO

SSG Caasi, Nixon DE CON

SFC Esteves, Fred MED NCO, 94th CST

Air Consumption Log: SCBA_ BG-4_ M-40 M-95 _M-53 -Call Sign I Starting PSI Starting Time 20m 40m 60m 80m 100m 120m

Entry Team:

TSgt Martinez, Lance

SGT Quitugua, Matthew

Backup Team: B Team

SGT Valdes, Tanny

SSgt Eclavea, Christine

6. Activity Log (Continue on Reverse)

TIME MAJOR EVENTS

18 June/1359 LTC Limtiaco received a call from GHS, Mr. Leo Expia informing us of the unaccounted 2401 TROXLER Soil Moisture Gauge. He requested for technical assistance to dispose the equipment. LTC advised to talk to Guam EPA and consult with a UNITEK Environmental Guam, civilian contractor.

20 June/1900 LTC Limtiaco received a call to attend a meeting at GHS.

21 June/0800 Attended a meeting at GHS. Present for the meeting was LTC Limtiaco, SFC Meno, CPT Balajadia (94th CST), DPW Deputy Director and Safety Officer, Public Health Rep., GFD Fire chief, Homeland Security Guam and Guam EPA Rep. Conference call with US DOE Tom Gorman and Sarah. Request was made to CST to conduct the following: 1. Conduct RAD screening for possible particulate contamination. 2. Assist GFD with Over-packing should there be a leak.

22 June/0924 Strike Team Deploys with 11 PAX and 4 Vehicles

0937 Team arrives at DPW and links up with IC

0940 PMT conducted and clears area to occupy

1030 IEP Conducted and approved by IC

1045 Team makes entry into HZ

1046 Team opens container and makes entry

1047 First reading is 600 uR/hr and 12.6 CPM on floor

7. Prepared by: Date/Time

SFC Bruce R. Meno

UNIT LOG June 2000 ICS 214-0S

1. Incident Name 2. Operational Period (Date/Time) UNIT LOG (CONT.) From: To: ICS 214-0S

6. Activity Log (Continue on Reverse)

TIME MAJOR EVENTS

1050 Gauge container is badly dilapidated. Need to place all items into a over pack container

1053 1.23 mR!hr when box is opened an gauge is exposed.

1054 7.50 CPM A Probe from PDR 77/17mR!hr

1057 13 CPM 2" from Gauge

1100 1 ft away receiving 78 uR!hr/Gauge is all the way upon the safe position

1106 Taking out Gauge from container.

1110 Conducting 10 with ldentifinder for 5 minutes

1114 Conducting wipe test

1118 Conducting monitoring under the Gauge. 10 mR/hrwith ldentifinder and 132 CPM with PDR 77. Above 1 00 CPM above background is the determination of possible leak. Therefore, Overpacking is necessary.

1120 Conducting wipe test on bottom

1133 Team completes objectives, conducting DECON

1134 Guam EPA informs Sarah Hartson from US EPA

1142 Team completes mission and overpacks PPE

1210 2nd Team Makes entry into HZ

1215 Team begins mitigation and overpacking procdures

1220 Mitigation complete and no readings over back ground

1225 2nd Entry completes entry mission complete

1300 Site and HAZWASTE transferred to IC

7. Prepared by: Date/Time

SFC Meno, Bruce R. 22Ju n 12/1300

UNIT LOG June 2000 ICS 214-0S

HAZMAT TERMINATION CHECKLIST

0 Mark over-pack containers accordingly

0 Use Clean monitoring equipment (survey) to monitor recovery personnel

0 Remove PPE from recovery personnel.

0 Seal bag and leave in place, tag accordingly

FINAL HAZMAT TERMINATION CERTIFIED BY:

ACKNOWLEDGE: ACCEPT I EC E RESPONSIBILITY FOR HAZW ASTE

DATE

§ Sampling

Testing

Mitigation § Sampling

Testing

Mitigation

Soil Moisture Density Gauge. The wooden box has hazardous labels indicating Radium 226 and Beryllium. The lwr,nrl~>n box contains a Troxler Gauge Device that was purchased in the mid-late 1970's. The last leak wipe test was conducted in

Ra226 is a Alpha, Beta, and Gamma emitter.

5 Dry 5 Hasty 221006JUN2012

Sechon VII. Srte Map

Site Map:

-11 , Safety Officer

LTC IN Commandin

Parking Lot Evacuation Area: GUAM

WATERWORKS

A wooden box was found in Container No.8. A Radioactive Label was placed on the outside of the box.

On March 5, 2012, representatives from Guam EPA tested the outside of the wooden box and Container No. 8 using a BNC SAM 940. SAM 940 is a portable radio-isotope identification (RIID) system that detects and identifies multiple nuclides, providing quantified results using real time and MCA analysis. An e-copy of the results was transmitted to Mr. Sam Poppell, USEPA Radiological Response Team Commander, for his advised and recommendations. A copy of this report is also attached.

1. Secure the source and prevent entry to the area;

2. DPW to account for the radiation source and other radiation sources in the facility; and

3. IfDPW cannot account for the radiation source, the 94 Civil Support Team should be activated.

The Radioactive Label indicates Radium 226, Beryllium

Photo No. 11 and No. 12 content of Storage Container No.8 Recommendations:

1. Storage Container No. 8 be secured to prevent entry; 2. Records be reviewed to determine the content of the wooden box; 3. If no records are available, we recommend that Guam Homeland Security/Office

of Civil Defense be notified to activate the Guam National Guard, 94 Civil Support Team.

10 ACTiVE MATERIAL SEALED SOURCE

USA DOT lA

Additional marking on the wooden box

Additional marking on the wooden box - Model 2401 Gauge, Surface Moisture Density, TROXLER Laboratories, Raleigh, North Carolina, USA

Photo No. 12 and No. 13 content of Storage Container No. 8. The 2401 nuclear gauge utilizes Compton scattering and photoelectric absorption of gamma protons to measure the total or wet density of materials being tested . The instrument has two methods of measuring densities, the backscatter method and the direct transmission method {see figure 1). A copy of th is information is attached and EPA's information Moisture and Density "Nuclear" Gauges Used in Road Construction. http://www.epa.gov/radtown/gauges.html.

2012-Mar-05 18:39

723

Troxler Electronic

--- ---"'\ I I ___ --J

FIGURE 1

9195490761

SAFE POSITION FOR STORAGE AND STANDARD COUNTS

BACKSCATTER, AIR GAP, AND MOISTURE POSITION

2 INCH POSITION

DIRECT TRANSMISSION POSITIONS

8 INCH POSITION

0

0

INDEX ROD POSITIONS

4

118

2012-Mar-05 18:39 Troxler Electronic 9195490761

or:

The latter equation is sometimes referred to as tha working fo~ula and onv~nient fox use on desk calculators. The deviation obtained is root-mean-square (RMS) error of the individual measurements £~om the

of the RMS deviation to the predicted deviation should fall een .8 and 1.25. Ratios outside of .7 and 1.4 defin~tely indicate a ctive system vrhile ratios between the$e values indicate possible cts and the test should be repeated.

Tb.e gauge stability over a w·orking day should be such that the drift in sta dard count is less than tha~ required to cause an error in excess o£ one standard deviation. For the 2400 Series gauges this m~imum dif erence is 0.5% for the density standard count and 1% for the moisture st dard count. These values were picked at 120 PCF density and 15 PCF

content.

The long term drift of the standard count is difficult to set a m~imum forJ since it is dependent on the source o£ the drift. Detectors display an ging which is temperature dependent and this type of drift is compen ated for by the standard count procedure. A gradual shift of even 10% ay be of no concern if it has occurred over a long period o£ time; how er, any sudden shift in excess of 2 to 3% may indicate a mechanical shi t in the gauge geometry and the calibration should be checked against a own reference.

XII. RAD OLOGICAL SAFETY lNFORMATION

A. GENERAL

The quantities of radioactive material contained in Troxler moistuxe and density gauges are quite small, and an operator may safely use a gauge day after day without receiving any bodily damage due to radia~ tion. In addition, each radioactive source is doubly sealed to afford even greater p~otection for the operator. However, all radioactive sources, no matter how small, should be handled with care.

The purpose of this appendix is to acquaint the operator with the tyPes and characteristics of radiations he will be working withJ and to describe the routine handling procedures and precautions which should be followed in order to obtain safe and efficient op~~ation of 'rro:s:ler gauges.

37 723

2/8

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723

B. RADIATION CHARACTERISTICS

1. Types of r~diation

The radioactive materials in Troxler gauges emit four types of radiation which the operator should knov7 about: alpha patticles 1

beta particles~ gamma rays, ~nd neutrons. Of these four, I the alpha and beta particles are completely stopped by the walls of the source container; therefore, only the characteristics of the gamma rays and neutrons need to be discussed in detail.

Gamma rays (~omet~es called photons) are a ~orm of elect omagnetic radiation, soaewhat similar to radio waves and r ys of light. TI1ey travel in straight lines with the speed of l"ght, and are electrically neutral. However, unlike light rays, gamma rays are extremely penetrating, and may pass through sev-ral inches of lead or concrete without being deflected. The energy of a gamma ray is usually expressed in units of m1llions of electron volts, or MeV. This need not be discussed any urther except to state that, in general, the higher the energy, l the more penetrating the gamma ray will be.

When a gamma ray (photon) enters a slab of material, any of three things may happen. First, the photon may be a~sorbed (s opped) by the material. Second, the photon may be deflected or 11scattered11 in the material, and come out of the materia 1i1ith a different direction and lo~er energy than when it entere • (Of course, sometimes the photon is scattered several times efore being absorbed or coming ou-t; of the mate~1al.) Third, t e photon may pass through the material without being s.cattered or absorbed.

It is impossible to accurately predict what will happen o a single gamma ray entering a certain material. However, "£ a beam of photons is directed at the material~ it is possible £ calculate the percentages of the beam that will be abso~bed, scattered or transmitted. The percentage of photons that will pa s through a m~terial depends mostly on the energy of the photons d the density of the material. For example, if a beam of 1.~ MeV photons were directed at a concrete block 11.2 inches ~~ick, 10% o£ the beam would be transmitted. Ho~rever, only 1. 73 iq.ches of lead would be required to cut this same beam down to 10%, because lead is much heavier than concrete. I Neutrons, instead of being rays, are extremely small, v ry dense particles. They are electrically neutral and quite pen trating. Unlike gamma rays, the penetrating power of neutrons th·ough a material does not depend on the density of the materialt but on , the material composition. Neutrons are slowed down mos effec- 1

tively by a material con·t:aining hydrogen atoms (such as water or -i· polyethylene). For this reason, neutrons are used to asu~e the ~ moisture content of soils or other materials. ~-

38

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r ' ·~.· ._, < ·· ·:

) . __ TROXlER The Leader .n CorstructiOf1 Test rg Equiprner.t

Gauge model : 2401

Transferred on: 16-Dec-1974

Transfer Data :

Transferee

License: N/A

Company:

Address:

Sealed Source Data:

Radionucllde Activity Serial No.

RA-226:BE 0.074GBq 16-4004 (2.000 mCi)

Notes:

Gauge Certificate (with transfer data)

Serial no: 2818 SS&D registry:

Sales order: 5842 Date Printed: 05-Mar-2012

Certification Date

16-Dec-1974

Transferor

032-0182-01

Troxler Electronic Laboratories, Inc.

3008 Cornwallis Rd

RTP, NC 27709

USA

Assay Date Leak Test Troxler Date Drawing

16-Dec-1974 100280

Special Form ANSI Certificate Class

GB:SFC.112 C64444

1. Certification Date: The most recent date the source was inspected and tested as meeting stringent quality control standards for source integrity.

2. Assay Date:

3. Leak Test Date:

The date the source activity was determined and the reference date for calculation of the current source activity.

The date the source was leak tested and found to have removable activity of less than 185 Bq (0.005 microcuries).

You should permanently retain this document as a record of gauge receipt.

723

0/C

3. Radiation Units

Although there are several units·of radiation measurernen~, there are only two with which the operator o£ a Troxler gauge needs to be familiar. These are the curie and the rem.

I

The curie is defined as the quantity of any radioactive katerial gi~ing 3.i x 1010 disintegrations per second (dps). Th is, in a curie of radium., 3. 7 x 1010 atoms would decay each sec nd.

The strength o£ sources used in Troxler gauges is usual expressed in millicuries (one millicurie is one-thousandt of a curie, or 3:7 x 107 dps). Therefore, a 3 millicurie Ra ium source would yield (3) (3.7 ~ 107) = 11.1 x 107 dps, or 111 million dps.

In order to calculate the amount of radiation absorbed ~y a human being, a unit called the ~em is used. Because th~ amount o£ absorbed radiation is usually small, doses are usual~y expressed in millirem (thousandths of a rem). The millir<f.n is actually a measure of the effectiveness of the body in ~bsorbing radiation, and depends on the type and energy of the ra~iation,

4. Exposure Limitations

Jn order to protect personnel from o~erexposure to radi the Atomic Energy Commis~ion and the Federal Radiation have established exposure limits for radiation workers. limits, expressed in millirems1 are reproduced in the f table.

EXPOSURE L~ITS FOR RADIATION WORKERS

tion, ouncil

These llowing

Type of Exposure Millirem Limit for

Sensitive Regions (whole body, eyes, gonads, skull)

Kidneys, spleenJ lungs, liver

Skin of whol'e body

Hands, arms, feet, ankles

13 w~ek.s 1- eek rate

1,250

s,ooo

7,500

96

385

577

1,442

These limits are intended to be highly conservative, a d do not represent the absolute maximum exposure a person could receive without becoming ill or suffering radiation damage. H wever, it

40

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2012-Mar-05 18:47 Troxler Electronic 9195490761

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is advisable to remain under the l~its whenever possible. This can be done quite easily with Troxler gauges, by following established handling precautions.

Shielding

There are ~110 basic ~11ays in which a person can protect himself from a radioactive source: distance and the interposition of shie14ing material.

As a person moves a~vay from a source, the amount o£ radiation which he is receiving from the source falls off sharply. In fact, radiation obeys the •rinver.se square•r law which states that the radiation intensity falls as the inverse square of the distance from the center of the source to the •rtarget'r. For example, if a person standing one foot from a source were receiving forty millirem per hour, moving back another foot l~ould cut the intensity to ten millirem per hour. By moving back, the person represents a small 11 target area11 to the source.

The other method of shielding is obtained by placing matter beb11een the source and the target. To a reasonable approximation, it makes no difference where the shielding material is placed between the source and the target, as long as the thickness of the material remains · the same. As was mentioned ea~lier, dense material provides the best shielding against gamma radiationJ while hydrogeneous (hydrogen-containing) material affords good protection against neutrons. The type of shielding in general use is as follows for the ~arious encapsulated source materials:

RA226 Csl37

Ra226 + Be Am241 + 'Be

LING PROCEDURES

Heavy material Heavy material Heavy material and hydrogeneous material Hydrogeneous material

lthough Tro~ler gauges can be operated quite safely, the following eneral precautions should be obs erved:

Do not operate or attempt to operate a gauge unless you have been au·thorized to do so.

Keep the gauge in the 11 SAFE11 or storage position \-Then not in use.

Wear a film badge or other radiation measurement device at all times while operating or transporting a gauge.

Keep unauthorized persons away from the gauge.

Be su~e that the gauge is locked up or othe~se secured when it is not in use.

41 723

6/8

Rl I.

'"D.

6. Follow established operating p~ocedures when using t~e gauge.

7. Insure that the gauge is leak tested at proper inte~ls.

8. When i1;1 doubt, ASK.

ACCIDENTS AND INCIDENTS ~ In case a gauge is lost or stolen, or involved in an acc·dent which might cause physical damage to the source, notify your dialogical Safety Officer, IMMEDIATELY. He will notify the proper. uthorities.

XIII. SHIPPING

723

A. GENERAL

Shipping p~ocedures for 2400-Series gauges are governed 9Y applicable Department of Transportation Regul ations for 1

Shipment of Radioactive materials. These regulations are contained in Title 49, Code of Federal Regulations.

B. PACKAGING

2400-Series gauges are shipped from the factory in shipp~ns cases which contain the proper labeling. This labeling l consists of a Radioactive Yellow-II label on either side of the package. DO NOT REMOVE THESE LABELS. Information o these labels include:

a. Type of mate~ial b. Number of curies c. Transport Index (This is the highest reading ·in

mr/h~ at one meter from any part of the package •

These original shipping cases should be used whenever it is necessary to ship the gauges an~ihere. If it is desired to ship empty shipping cases, an 11EMPTY" label must be aff · ed to the package~ instead of placing tape over the radioa ive labels.

Each package should have a seal (such as banding or a 1 which, while intact, lvil1 be evidence that the package not been illicitly opened.

Since the 2400-Series gauges contain sealed sources whi meet ''SPECIAL FOID111 requirements, the shipping cases are des· gued to meet u.s. DOT Specification 7A for Type A packaging. A lapel must be affixed to the container which states:

DOT 7A Type A SPECIAL FORM Radioactive Material

The sealed source has Competent Authority Approval Cert ficate GB-SFC 112.

42

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SU!lfl\CE I METER FROM S!JM'ACE FRONT 2.5 0,3

BACJ< 9 0 .5 SIDE 7 0.4

TOP 0.7 0.2.

BOTTOM 6 0.4 HANDLE - -

FRONT 1.1 0.3 BACK 5 0,4

l'fOTE• SICc,BACI< A.'JD FROrff ME~Sl.flEIIENT TAKEN B L~CH ES UP FROM BOTIGM SURFACE ,

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TROXLER ELfCTRONIC LABORATORIES, INC.

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Dose Rates are mrem/hr

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2400 SERIES RADlATION PROFILES

........... """ 'SIIU: I at' I ..... _

""'· C-100806 A

J~TIOXl!R~ The leader <n Cor.st~Jction Testing Equipment

Gauge model: 2401

Transferred on: 16-Dec-1974

Transfer Data:

Transferee

License: N/A

Company:

Address:

Sealed Source Data:

Radionuclide Activity Serial No.

RA-226:BE 0.074 GBq 16-4004 (2.000 mCi)

Notes:

Gauge Certificate (with transfer data)

Serial no: 2818 SS&D registry:

Sales order: 5842 Date Printed: 05-Mar-2012

Certification Date

16-Dec-1974

Transferor

032-0182-01

Troxler Electronic Laboratories, Inc.

3008 Cornwallis Rd

RTP, NC 27709

USA

Assay Date Leak Test Troxler Date Drawing

16-Dec-1974 100280

Special Form ANSI Certificate Class

GB:SFC.112 C64444

1. Certification Date: The most recent date the source was inspected and tested as meeting stringent quality control standards for source integrity.

2. Assay Date:

3. Leak Test Date:

The date the source activity was determined and the reference date for calculation of the current source activity.

The date the source was leak tested and found to have removable activity of less than 185 Bq (0.005 microcuries).

You should permanently retain this document as a record of gauge receipt.

I

Roll Call: o Entry Team Members o Back up Team oDeconLine oGPDRep oHSRep o Ops Officer

o Safety officer oCommo o Deputy Commander oGFDRep o Med Section oCommander

Introduction: I am the_ of the 94th Civil Support Team and I will give you this brief Initial entry brief

LsrruAS??~~ ~ \ T R-c \) Gltt~cW .

A The date and time is now: ru ~ l" ~ IJ 'L-Q \ U

C. Incident Name: () ~~c*- ~ (\\--.'\' r ox.\~ ( D?W )

D. IncidentCommander: f1 ft (Jbe,~ SOC'C\ IJ\d 6oS ur &o f1Pre..5

E. Incident D=ripti= tl-olc}_ • 0c-h m-- bow. -\u c , ~ 1. Casualties:

(a) Number: rJ (b) Location: fJ

F. THREAT

Known Agents:

Dispersion Method:

Secondary Devices:

G. IDGHER and SUPPORT.IN'G AGENCIES:

JOC ________________ GFD __________ GPD __________ __

H. Weather: (filled in by modeler)

I. Temperature: i f).-a r 2. Humidity I Precipitation: ~ L\ %:>

3. Barometric Pressure (Trend =Rise'Fall) ~q , ~ S"' It

4 . Wind speed: \\, _M.? t\

5. Wind Direction: '0<-o ""'- 't:" CA-~ T A-18

Entry Team: 1. Mo~"'k ~ \.-J>.., '"!.....

Back up Team:2. \I a~.\,Jt-1\ T, -Work time down range will be 40-50 minutes or if air allows.

Back up Team will be located at staging area near decon line

Entry Teams Key Tasks: L ~('f. v...-V fl'v'l J G 2. ________ _ 3. ______ __ _

Entry Teams Additional Tasks: L ________ _ 2. ________ _ 3. ________ _

PPE Level: \')\ ' IJ "-1 ~ J•·'\a.,dY- J ~ ~· r: --~~--~--~~--~~~-+.~~~~~--~~~~~

Desired End state: To conduct mission to complete IC request without any injury to the team or harm to the equipment 3. EXECUTION This is how I want the operation done

Orientate Team to Map: ________________________________ _

MOVEMENT ROUTE TO INCIDENT SITE

Route: Describe how to move down range and what to do

Staging Area: \) ~ vJ ~ w\' ~ v-.1" lot ':'\\) - l'J

Entry!Exit:_-u=-=J'--W _ __ M____.;.Ov_,,_\-__ e=_,-\tv_\Y_....:..o~..:._i\1\..__;;_v~_·

SafeRefugeArea: DvvJ \J~~v\~ ~\.U,"t /~LJfi Emergency Evacuation Rte: t fl •,J ~ ~~ ~~' ~\lv\¥·o..v-Y.~

A-19

I

Equipment taken downrange: We will take all equipment stated on our check list and to include:

l. u~\;JJJ~ 4. _____ _

2.~n~, l1 C~\~4) 3 .. __ _ 5. 6 .. _____ _

7. _____ _ 8. 9 .. _____ _ 10. ____ _ 11. 12 .. _____ _ 13. _ _ _ __ _ 14 15 .. _____ _

Abort Criteria/fum: ~ I. Team Member sustains Serious Injury

2. Armed Combatant is encountered 3. Tom Suit or other life support equipment becomes inoperable 4. Gross contamination 5. Explosion or fire

i 6. Loss of communication of more than 5 minutes (Backup team will go in if time expires) Note: if all right come back out to last know com spot and give report or use hand signal for ok

7. Team member becomes safety risk 8. SCBA Air level@ Il40 PSI

i.9. RAD dose of .25 cGy is met (total dose is I cGy) 10. 02 reading of over 23.5% indoors and 25% Outdoors 11. LEL readings of> 10% indoors and 20 % outdoors 12. Uncleared secondary devices (Do not use radio until you have cleared the BWG) 13. OEG: .25cGy for dose rate, 1. cGy Total Dose

Report back criteria: 1. 02 readings of <19.5% 2. Double background reading of:---:-:-:--.,----,-3. Any elevated RAD reading of (2milirem/l Omilirem) 4. AnyVOCReading 5. AnyToxReading 6. Sampling Start and End procedures 7 . Returning to decon line

COORDINATING INS1RUCTIONS:

Man Down procedures: Code word real world: Man Down/ Code word Training: Exercise Man Down

(Back up team will suit up and assist down team member, bring him directly to emergency decon line for process. Next, entry team member will process followed by Back up team with lowest man on air going through first

4. SERVICE SUPPORT: At this time I would like to call up: _____ _

NMSO:- -------,,---..,--..,.---, SAFETY OFFICER: F \ --( \ ~\-cfWt\~ PHYSICIANS ASSISTANT: ___ _

COMMO:. _______ _ MEDOPS: _______ _ CDR: _____ __ _

DECON: ----------OPS: ________ _

5. COMMAND AND SIGNAL Command: SSL and CBRN NCOIC will be located at the Survey Staging Area Succession of Command: SSL, CBRN NCOIC, ATC, BTC 1BEN Alphabetically after that

Signal: (1) Channel3A Survey/Decon line (all others must stay off of this channel) (2) lA OPS

Review some hand and arm signals: 1. Out of air 2. Tripwire 3. Aircheck 4. In Trouble

A-20

5. Cutmeout

,.;.:du··ct''.B kB'ef:···.-;:· · ......... : · . . ·: ,,,.- ; ·, .... .-,:.- .···: . ·: .... :.· . · · ' \....Un ac n. ', • ('II,,!, 'J , '• : .~ ., , -~·,, ,'-•,"' ' <0(:•',\~• ' ~••'• ... '.!"•t'•(t,'• :., ~·~· . ... . C".·:··· ... :;, ,-;-. ,-,!·I .... ::~1•.V'. . . . . . ·. t,,·,.-.,..,. .· ' " ',!·~···· · . ·-i·""'l· · ... !"ro.:;· ...... ...z ;;.· .. _,:. ~ ·, .•.

6. Objectives: 7. Downrange Plan:

8. AbortCrireria: --------------------9. Current Situation: --------------------10. Decon Solution: --------------------11. Loss of Commo Plan: -----------------

Date: 2--2 -J'k .v' I 2 Print Name: f_pw 1\-t'Y? pt.-A V2-f£. ..S r ~ FO t!R'r 1 "',!:(___

A-21

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Radium, Radioactive (alias of Radium Radioactive)

WMD Response Guidelines

Nuclear {Radiological) Materials Guide 14

SIGNS AND SYMPTOMS • Short-Term:

o Nausea

o Burns

INDICATORS • Overt Threats

• Groups Taking Credit for Incident

• Specialized Packaging Near the Scene

• Radiological Placards on Vehicles

• Radiological Labels of Items

ROUTES OF EXPOSURE • Inhalation

• Absorption

• Ingestion

• Injection

EMERGENCY RESPONSE • Approach from Upwind, Uphill, or Upstream (if there is potential for dissemination of nuclear material or particulate matter)

• Isolate Immediate Area in all directions distance of at least 80-160 feet

• Keep Unauthorized Persons Away

• Consider Immediate Downwind Evacuation Distance of 330 feet at night

• Consider Immediate All Direction Evacuation Distance of 1000 feet during the day

• Stay Upwind

• Make Notifications

• Obtain immediate medical evaluation for all exposed or potentially exposed personnel

TYPE OF HARM • Radiological

• Possible Chemical

• Possible Thermal

PERSONAL PROTECTION • Time: Keep Exposure and Product Contact to Minimum

• Distance: Stay at least 300 feet away on Upwind Side Until Agent is Identified

• Shielding: Chemical Protective Clothing

Content reproduced for WISER with permission from the Louisiana State University and A&M College, National Center for Biomedical Research and Training, Academy of Counter-Terrorist Education. WMD Response Guidebook © . Further reproduction prohibited.

Printed by (Version 4.3.4401, Database Version 4.4.20) HHS/ NIH, National Library of Medicine

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Protective Equip./Ciothing

Protective screens made from lead or concrete should be provided to reduce emissions of gamma-radiation. The thickness of the screen will depend on the level of radiation emitted .... remote manipulation devices should be employed wherever possible.

Operations that routinely produce airborne contamination should use engineered containment and ventilation systems to prevent exposures to individuals from air borne releases to the environment .... Appropriate personal respiratory protective devices may be used .. . but only in abnormal situations or when effective engineering controls are not feasible ... For radiation safety, the primary functions of a ventilation system are to move airborne contamination away from occupied work areas (and the potentially exposed workers) and to provide a mechanism for the "recontainment" of the airborne radioactive material that was released. To meet these objectives, the ventilation system must have acceptable pressure differentials between work areas and the outside environment. High-efficiency particulate air (HEPA) filtration or other appropriate filtration may be needed, but the radiation exposure of individuals from the radioactive materials retained on the filter should be evaluated. A pressure differential system should be used to control the flow of airborne contamination. In the system design, a pressure gradient should be established, with the lowest pressure and collection points in areas with the highest potential for release of dispersible material. The flow should always be from clean areas to contaminated areas.

Shielding may be necessary to reduce the potential for exposures to workers and visitors at the facility and to the public in the vicinity of the facility .... Vvarious materials can be used for shielding, depending on the type of radiation, its energy and intensity, and the attenuation required. Typically medium and high atomic number materials such as iron and lead are effective for shielding X and gamma rays. For moderating fast neutrons a material with a high hydrogen content, such as water or polyethylene, must be included in the deign. When thermal neutrons are captured in hydrogen, cadmium or other elements, high-energy gamma rays are emitted and must be considered in the shield design. Concrete is suitable for shielding both photons and neutrons and is a cost-effective material of choice when space is available. Earth is also an effective and inexpensive material that is widely used as shielding in various types of facilities. In addition to meeting radiation protection goals, the selection of shielding material is dependent upon engineering factors such as weight, cost, structural stability and compatibility.

In most /emergency/ situations, respiratory protection that is designed to protect responders against chemical or biological agents is likely to offer some degree of respiratory protection in a radiological attack. Concerns about the presence of chemical or biological contaminants will influence the selection of respiratory protection. If used properly, simple face masks provide reasonably good protection against inhaling particulates, and allow sufficient air transfer for working at high breathing rates. If available, high-efficiency particulate air filter masks provide even better protection.

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~.¥ri9..tl!. Priyac'!':, Acce_ssibllity U.S. National Library of 11-ledicine, 8600 Rockville Pike, Bethesda, MD 20894

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Health Effects

0.2.1 SUMMARY OF EXPOSURE

0.2.1.1 ACUTE EXPOSURE A) The two immediate concerns in radioactive contamination are (

1) treatment of life-threatening injuries and ( 2) decontamination procedures. Initial care should focus on managing the airway and ensuring adequate ventilation and hemodynamic stability. The two most radiosensitive organ systems in the body are the hematopoietic and the gastrointestinal systems.

B) ACUTE RADIATION SYNDROME- This is a symptom complex following whole body irradiation (> 1 gray (Gy)). It varies in nature and severity, depending upon:

(a) dose measured in gray (Gy) (radiation absorbed dose, 1 Gy = 1 joule per kilogram of absorbed energy of any type of radiation in any tissue), (b) dose rate, (c) dose distribution, and (d) individual susceptibility. Whole-body radiation doses can be divided into potentially lethal (2 to 10 Gy), sublethal (less than 2 Gy), and supra lethal (greater than 10 Gy) doses. Acute radiation syndrome has four clinical phases: prodrome, latent, manifest illness, and recovery. An older unit for radiation absorbed dose is the "rad", where 1 rad = 100 ergs of energy absorbed per gram of irradiated tissue. 1 Gy = 100 rads.

C) PRODROME -This is an initial toxic period beginning minutes to hours after exposure; its onset and severity are dose-dependent. Minimum dose is unknown, but the prodrome may occur with doses as low as 1 Gy and always with exposure to greater than 4 Gy. At doses less than 4 Gy, the symptoms begin within 24 to 48 hours; at doses greater than 6 Gy, symptoms begin within two hours.

1) PRODROMAL phase occurs in the first 48 to 72 hours and is characterized by nausea, vomiting, diarrhea, intestinal cramps, salivation, and dehydration. Fatigue, weakness, apathy, fever, and hypotension are the result of neurovascular dysfunction. At doses below about 5 Gy it lasts 2 to 4 days.

D) LATENT period follows the prodromal phase and lasts for approximately 1 to 2 and 1/2 weeks. During this time critical cell populations (leukocytes, platelets) are decreasing as a result of bone marrow insult. The time interval decreases as the dose increases. It is generally a dose-dependent phase of well being.

1) The latent phase is longest preceding bone marrow depression of the hematopoietic syndrome (varies between 2 and 6 weeks). Prior to the gastrointestinal syndrome, the latent period lasts from a few days to a week. Preceding the neurovascular syndrome, the latent period is shortest, lasting only a few hours. These times are exceedingly variable and may be modified by the presence of other disease or injury.

E) MANIFEST ILLNESS phase is a period when overt illness develops. This phase presents with the clinical symptoms associated with the major organ system injured (bone marrow, intestinal, neurovascular). F) RECOVERY phase or death - recovery may take weeks or months. G) Within the acute radiation syndrome is included: CNS syndrome, hematopoietic syndrome, gastrointestinal syndrome, skin, and trauma injuries. H) TRAUMA, MULTIPLE- The combination of even benign-appearing trauma and radiation exposure will produce synergistic effects. Mortality is increased because of bleeding diathesis complications, prolonged wound healing, and increased risk of sepsis.

0.2.3 VITAL SIGNS0.2.5 CARDIOVASCULAR

0.2.5.1 ACUTE EXPOSURE A) Hypotension may occur following the neurovascular stage or due to hypovolemia.

0.2.6 RESPIRATORY

0.2.6.1 ACUTE EXPOSURE A) Pulmonary radiation injury may result in radiation pneumonitis and radiation pulmonary fibrosis.

0.2.7 NEUROLOGIC

0.2.7.1 ACUTE EXPOSURE A) Supralethal radiation doses may result in headache, acute brain syndrome, alterations in mental status including coma, and (rarely) seizures within minutes of exposure.

0.2.8 GASTROINTESTINAL

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0.2.8.1 ACUTE EXPOSURE A) Gastrointestinal syndrome (nausea/vomiting) commonly occurs after doses of 9 to 20 Gy and may occur following doses as low as 5 Gy. Initial vomiting is followed by persistent diarrhea, wh ich may be bloody.

0.2.12 FLUID-ELECTROLYTE

0.2.12.1 ACUTE EXPOSURE A) Fluid and electrolyte losses generally occur during the gastrointestinal syndrome.

0.2.13 HEMATOLOGIC

0.2.13.1 ACUTE EXPOSURE A) A decrease in neutrophils may reflect the degree of exposure. Leukemia may develop following significant exposures. Pancytopenia may occur and predisposes to infections and sepsis, especially in patients with concomitant t raumatic Injuries.

0.2.14 DERMATOLOGIC

0.2.14.1 ACUTE EXPOSURE A) Thermonuclear burns may occur. If erythema is produced by a penetrating radiation, serious systemic Injury is certain. B) A skin dose greater than 3 Gy results in epilation within 2 weeks. Cutaneous rad iation syndrome has produced cutaneous ulcers, dermal defects, and cutaneous fibrosis.

0.2.16 ENDOCRINE

0.2.16.1 ACUTE EXPOSURE A) Hypothyroidism or hyperthyroidism may occur. Both benign and malignant thyroid tumors have been associated with ionizing radiation exposure.

0.2.20 REPRODUCTIVE HAZARDS

A) In addition to an increased risk of cancer, exposure to ionizing radiation is known to affect human reproduction. B) Prenatal Ionizing radiation exposure may cause congenital anomalies, mental retardation, and an increased incidence of seizures.

0.2.21 CARCINOGENICITY

0.2.21.2 HUMAN OVERVIEW A) Ionizing radiation has carcinogenic effects in many tissues. B) Acute ionizing radiation exposure survivors have increased long-term cancer risks. A dose-response relationship exists between exposure to ionizing radiation and the risk for the subsequent development of cancer.

0.2.22 GENOTOXICITY

A) Ionizing radiation is genotoxic and causes breaks in the structure of DNA, resulting in mutations or chromosomal structural aberrations. Double strand breaks in the mutagenic and carcinogenic effects of radiation have been reported. Incorrectly rejoined break leads to DNA misrepair which In turn leads to DNA deletions and rearrangements. Large scale changes in DNA structure appear to be typical of most radiation-induced mutations. B) Chromosomal translocations in persons who lived in houses (up to 16 years) in Ta iwan contaminated with cobalt-60 has been reported. Compared to controls (no exposure to cobalt-60), the overall translocation yield in the residents was 5 times higher. Chromosomes 2, 4 and 12 were affected in 500 metaphases per person. The FISH method for reciprocal chromosomal translocations was used {Chen et al, 2000).

Portions of the POISINDEX® and MEDITEXT® databases have been provided here for general reference. THE COMPLETE POISINDEX® OR MEDITEXT® DATABASE SHOULD BE CONSULTED FOR ASSISTANCE IN THE DIAGNOSIS OR TREATMENT OF SPECIFIC CASES. The use of the POISINDEX® and MEDITEXT® databases is at your sole risk. The POISINDEX® and MEDITEXT® databases are provided "AS IS" and "as available" for use, without warranties of any kind, either expressed or implied. Micromedex makes no representation or warranty as to the accuracy, reliability, timeliness, usefulness or completeness of any of the information contained in the POISINDEX® and MEDITEXT® databases. ALL IMPUED WARRANTIES OF MERCHANTABIUTY AND FITNESS FOR A PARTICULAR PURPOSE OR USE ARE HEREBY EXCLUDED. Micromedex does not assume any responsibility or risk for your use of the POISINDEX® or MEDITEXT® databases. Copyright 1974-2004. Thomson MICROMEDEX. All Rights Reserved. Any duplication, replication, "downloading," sale, redistribution or other use for commercial purposes is a v iolation of Micromedex' rights and is strictly prohibited.

Find more information on this substance at: Hazardous Substances Data Bank , TOXNET, PubMed

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Treatment Overview

0.4.2 ORAL EXPOSURE

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A) Treatment is symptomatic and supportive. Prevention and treatment of infection is imperative, using broad-spectrum antibiotics with gram-negative coverage.

1) Radioactive materials of military significance include: Americium, cesium, cobalt, depleted uranium, iodine, phosphorus, plutonium, radium, strontium, tritium, and uranium.

B) Bone marrow depression should be treated with G-CSF or GM-CSF. C) Replace fluids and electrolytes as needed. D) HYPOTENSION: Infuse 10 to 20 ml/kg isotonic fluid. If hypotension persists, administer dopamine (5 to 20 meg/kg/min) or norepinephrine (ADULT: begin infusion at 0.5 to 1 meg/ min; CHILD: begin infusion at 0.1 meg/kg/min); titrate to desired response. E) SEIZURES: Administer a benzodiazepine IV; DIAZEPAM (ADULT: 5 to 10 mg, repeat every 10 to 15 min as needed . CHILD: 0.2 to 0.5 mg/kg, repeat every 5 min as needed) or LORAZEPAM (ADULT: 2 to 4 mg; CHILD: 0.05 to 0.1 mg/kg).

1) Consider phenobarbital or propofol if seizures recur after diazepam 30 mg (adults) or 10 mg (children > 5 years) . 2) Monitor for hypotension, dysrhythmias, respiratory depression, and need for endotracheal intubation. Evaluate for hypoglycemia, electrolyte disturbances, hypoxia.

0.4.3 INHALATION EXPOSURE

A) The history obtained at the scene is of great importance. The exact type of exposure, i.e., internal versus external and partial versus whole body exposure, should be obtained. B) If exposure is internal, both the route of entry (oral, inhalation, contaminated open wounds) and the specific radioactive material

(s) should be determined. Monitoring exposed patients for contamination and decontamination procedures should be started. All personnel involved in handling patients should wear disposable protective clothing. The patient should be completely undressed and given a soap and water bath or shower (if the patient's condition permits and if the facility exists).

C) Acute inhalation of radionuclides presents some difficult problems. Early bronchopulmonary lavage, in addition to chelating, blocking, and diluting agents, may be used. Chronic low-level inhalation of contaminants is more common, and long-term sequelae have been reported. D) Complete recommendations for treatment of radiation exposure by all routes is found in the DERMAL EXPOSURE section .

0.4.5 DERMAL EXPOSURE

A) OVERVIEW 1) Decontamination with soap and water should be repeated until dosimetry readings become normal; all waste should be saved in special receptacles. 2) Complete recommendations for treatment of radiation exposure by all routes is found in the ORAL/PARENTERAL EXPOSURE section.

Portions of the POISINDEX® and MEDITEXT® databases have been provided here for general reference. THE COMPLETE POISINDEX® OR MEDITEXT® DATABASE SHOULD BE CONSULTED FOR ASSISTANCE IN THE DIAGNOSIS OR TREATMENT OF SPECIFIC CASES. The use of the POISINDEX® and MEDITEXT® databases is at your sole risk. The POISINDEX® and MEDITEXT® databases are provided "AS IS" and "as available" for use, without warranties of any kind, either expressed or implied. Micromedex makes no representation or warranty as to the accuracy, reliability, timeliness, usefulness or completeness of any of the information contained in the POISINDEX® and MEDITEXT® databases. ALL IMPLIED WARRANTIES OF MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE OR USE ARE HEREBY EXCLUDED. Micromedex does not assume any responsibility or risk for your use of the POISINDEX® or MEDITEXT® databases. Copyright 1974-2004. Thomson MICROMEDEX. All Rights Reserved. Any duplication, replication, "downloading," sale, redistribution or other use for commercial purposes is a violation of Micromedex' rights and is strictly prohibited.

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DOT Emergency Guidelines

GUIDE 163 ERG2008

RADIOACTIVE MATERIALS (Low to High Level Radiation) POTENTIAL HAZARDS

HEALTH · Radiation presents minimal risk to transport workers, emergency response personnel and the public during transportation accidents. Packaging durability increases as potential hazard of radioactive content increases. · Undamaged packages are safe. Contents of damaged packages may cause higher external radiation exposure, or both external and internal radiation exposure if contents are released. · Type A packages (cartons, boxes, drums, articles, etc.) identified as "Type A" by marking on packages or by shipping papers contain non-life endangering amounts. Partial releases might be expected if ''Type A" packages are damaged in moderately severe accidents. · Type B packages, and the rarely occurring Type C packages, (large and small, usually metal) contain the most hazardous amounts. They can be identified by package markings or by shipping papers. Life threatening conditions may exist only if contents are released or package shielding fails. Because of design, evaluation and testing of packages, these conditions would be expected only for accidents of utmost severity. · The rarely occurring "Special Arrangement" shipments may be of Type A, Type B or Type C packages. Package type will be marked on packages, and shipment details will be on shipping papers. · Radioactive White-I labels indicate radiation levels outside single, isolated, undamaged packages are very low (less than 0.005 mSv/h (0.5 mrem/h)). · Radioactive Yellow-II and Yellow-III labeled packages have higher radiation levels. The transport index (TI) on the label identifies the maximum radiation level in mrem/h one meter from a single, isolated, undamaged package. · Some radioactive materials cannot be detected by commonly available instruments. · Water from cargo fire control may cause pollution.

FIRE OR EXPLOSION · Some of these materials may burn, but most do not ignite readily. · Radioactivity does not change flammability or other properties of materials. · Type B packages are designed and evaluated to withstand total engulfment in flames at temperatures of 800°C (1475°F) for a period of 30 minutes.

PUBLIC SAFETY • CALL Emergency Response Telephone Number on Shipping Paper first. If Shipping Paper not available or no answer, refer to appropriate telephone number listed on the inside back cover. • Priorities for rescue, life-saving, first aid, fire control and other hazards are higher than the priority for measuring radiation levels. · Radiation Authority must be notified of accident conditions. Radiation Authority is usually responsible for decisions about radiological consequences and closure of emergencies. · As an immediate precautionary measure, isolate spill or leak area for at least 25 meters (75 feet) in all directions. · Stay upwind. · Keep unauthorized personnel away. · Detain or isolate uninjured persons or equipment suspected to be contaminated; delay decontamination and cleanup until instructions are received from Radiation Authority.

PROTECTIVE CLOTHING · Positive pressure self-contained breathing apparatus (SCBA) and structural firefighters' protective clothing will provide adequate protection against internal radiation exposure, but not external radiation exposure.

EVACUATION Large Spill · Consider initial downwind evacuation for at least 100 meters (330 feet). Fire · When a large quantity of this material is involved in a major fire, consider an initial evacuation distance of 300 meters (1000 feet) in all directions.

EMERGENCY RESPONSE Fire · Presence of radioactive material will not influence the fire control processes and should not influence selection of techniques. · Move containers from fire area if you can do it without risk. · Do not move damaged packages; move undamaged packages out of fire zone. Small Fire · Dry chemical, C02, water spray or regular foam. Large Fire · Water spray, fog (flooding amounts). · Dike fire-control water for later disposal. SPILL OR LEAK · Do not touch damaged packages or spilled material. · Damp surfaces on undamaged or slightly damaged packages are seldom an indication of packaging failure. Most packaging for liquid content have inner containers

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and/or inner absorbent materials. · Cover liquid spill with sand, earth or other non-combustible absorbent material.

FIRST AID · call 911 or emergency medical service. · Medical problems take priority over radiological concerns. · Use first aid treatment according to the nature of the injury. · Do not delay care and transport of a seriously injured person. · Give artificial respiration if victim is not breathing. · Administer oxygen if breathing is difficult. · In case of contact with substance, immediately flush skin or eyes with running water for at least 20 minutes. · Injured persons contaminated by contact with released material are not a serious hazard to health care personnel, equipment or facilities. · Ensure that medical personnel are aware of the material(s) involved, take precautions to protect themselves and prevent spread of contamination.

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Other Preventive Measures

Basic guidelines ... essential for the health and safety of radiation workers in biological labs /should include/: 1. Mouth pipetting should never be allowed ... 2. Eating and drinking, or storage of food containers in radioisotope lab should not be allowed .... 3. Untrained individuals should not work with radioisotopes unless under direct supervision & in physical presence of an experienced individual. 4. Aid should be available when large quantities of radioisotopes are being used .... 6. Where volatiles are in use, work should be done in a hood .... 9. Radiation and/or contamination surveys should be conducted as appropriate ... 10. Survey instruments should be used to check hands and clothes for contamination at end of work (if radiation is suitable for detection.

The key to an effective program is the formal delegation of authority to competent staff members. The manager of the radiation safety program ... the Radiation Safety officer should be directly responsible to the highest level of management and should have ready access to all levels of the organization . ... Management should appoint a Radiation Safety Advisory Group ... the Radiation Safety Committee. The responsibility of the RSC is to formulate institutional radiation safety policies, review and audit the effectiveness of the radiation safety program, and provide guidance to the RSC on the operational uses of radiation and radioactive materials. The RSC is responsible for advising management concerning radiation safety practices and regulations. This individual should be delegated the authority to supervise the operational radiation safety organization, develop a budget and commit expenditures that are allowed by that budget .... The RSC is responsible for periodic and special surveillance of activities such as acquiring and disposing of radioactive materials, training in radiation safety practices for facility employees and users, developing and maintaining radiation control and dosimetry records, and authorizing the use of radiation and radioactive materials within the facility. The RSC is also responsible for developing and maintaining a radiation safety manual.

The radiation safety manual should include a comprehensive statement of policy and the principal administrative and program procedures established by the RSC . .. . The radiation safety manual should include: (1) management's commitment to proper radiation safety practice (2) description of the RSC, the radiation safety staff, and the radiation safety program (3) specific policy and regulatory requirements (4) specific procedures on how to comply with these requirements.

Depending on the complexity of a particular task and the training and experience of the individuals involved, procedures for work that involves radiation or radioactive materials should include the following elements as appropriate: (1) a description of the work that is authorized (2) a description of the potential hazards that will be encountered in performing the work, including potential radiation dose rates, identification of the sources of radioactive material, potential radioactive contamination levels, and the potential for intake of radioactive material (3) the identification of individuals responsible for making sure that the work activities are conducted in accordance with the safety procedure (4) the safety controls and procedural safeguards that are necessary to prevent or limit exposure including requirements for protective clothing, respirator protection, internal and external dosimetry, radiation surveys, worker time and dose limitations, limiting conditions fore either radiation or contamination levels, health physics or radiation safety coverage that is required during the task (5) required worker qualification including any specialized training (6) actions to be followed in the event of an emergency (7) a description of contamination control requirements (8) a description of required training and tasks that should be completed before beginning the task at hand (9) a description of the method for authorizing deviations from the specified procedure (10) references to records and reports to be completed (11) a description of acceptable results and of actions to be taken in response to unsatisfactory results.

Management should ensure that there is a quality assurance program in place to provide oversight of the radiation safety program .... Area surveys and personal monitoring are significant aids for determining the adequacy of facility design, operating procedures, and worker training. A high-quality surveillance program depends on the availability fo functioning and calibrated instrumentation. The RSC should expect prompt, accurate and consistent reports of the results of routine area surveys and personal monitoring. These reports can provide an indication of serious inadequacies in the facility procedures and training .... Routine surveys and personal monitoring are usually done on a regular schedule, but may be relatively infrequent (weekly, monthly or quarterly). For this reason, it is important that supervisors understand their essential role in controlling radiation exposure and in recognizing the implications of changes in operating conditions. This is especially critical when high-dose rate radiation sources are being used.

The amount and detail of the records that the RSC should maintain has become substantial and their maintenance represents an appreciable portion of the effort of the radiation safety staff .... Included in the records that should be maintained are those that detail administrative actions that affect the program, report internal and external audits, and record deficiencies and corrective actions. Operating procedures, personal monitoring and survey records, instrument calibration records, waste management records, and records of worker training should be maintained in a readily retrievable form.

Organizations should establish radiation safety orientation and training programs that include opportunities for all workers to receive repeat training at appropriate intervals. Radiation safety policies and procedures should be integrated into the overall safety program of the organization. The depth and breadth of training needed varies with the job requirements and responsibilities of each individual. Factors that influence the depth of training include the potential for radiation exposure, complexity of tasks to be performed, degree of supervision ... , amount of previous training, and degree to which the trainees will instruct or supervise others. Workers who need specialized radiation safety skills require extensive and ongoing in-depth training .... Records of training programs presented, course curricula and attendance records should be maintained by management.



An external radiation exposure control program must be established when there is a possibility for workers to be occupationally exposed or for members of the public to receive exposure from facility operations .... The formality of the program is clearly a function of the dose level . ... Administrative dose guidelines should be established to reduce the potential for individuals to exceed the recommended dose limits .... An effective external radiation exposure control program will ensure that doses to occupationally exposed individuals are maintained within administrative dose guidelines and that individual doses are maintained ALARA fo the work performed . .. . Engineering controls should be the primary means for controlling external radiation doses. These include distance and shielding, remote handling equipment and interlocks. Administrative controls such as safety procedures, radiation work permits, and radiation monitoring and surveys should be a secondary means for controlling external doses, but are a necessary part of the program.

/In facilities where radioactive materials are handled/ Radiation surveys should be conducted in areas where the potential exists for exposure to external radiation fields in order to: (1) characterize the radiation field so that it can be properly posted and controlled , (2) provide the information required for planning work activ ities to maintain the external radiation exposures at levels ALARA, and (3) ensure the prompt discovery of changed radiation fields ...

/In facilities where radioactive materials are handled/ External radiation dose records should be maintained to demonstrate compliance with dose limits and administrative dose guidelines, and to assist in the evaluation of the effectiveness of the external dose control program ..... In addition, records should be maintained of the external radiation surveys that are performed.

/ In facilities where radioactive materials are handled/ There should be an airborne monitoring program for radioactive materials in those areas where there is a significant potential for airborne contamination. It is not appropriate to use personal monitoring devices to control internal exposures. Thus, continuously operating samplers equipped with continuous detection devices may be needed.

Although usually not a significant risk to workers, contamination of facilities, equipment or people occurs in many operations involving radioactive material. Contamination control of routine operations is normally accomplished through containment of the radioactive material in chemical hoods, gloved boxes, hot cells, or the use of area exclusion, protective clothing, etc ....

The investigation of incidents and accidents must be timely .... Incident and accident investigations should include a thorough examination of the scene, interviews with the people involved, a review of pertinent records, and a complete and accurate report of the incident or accident and subsequent investigation. The location of the event should be completely surveyed with appropriate instruments as needed to determine and document the radiation levels and the extent of radioactive contamination. Personal monitoring devices should be collected and evaluated, and bioassays should be performed as heeded. An inventory of all radioactive material and waste should be made. Any records or logs that have been maintained should be examined . Workers and others in the area should be interviewed early in t he investigation. A photographic record of the area may be important to reconstruct the incident or accident .

/For protection of the public/ Radiation fields emanating from the facility are controlled by appropriate shielding of components or equipment that are sources of radiation . The choices of control measures are highly dependent on the nature of the facility and its processes, the quantities and types of radionuclides employed or processed, and the levels and types of radiation produced. The facility management must ensure that techniques used for control of releases of radioactive materials are adequate and that they are functioning at a satisfactory level.

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Range of Toxicity

A) In man, the median lethal dose of radiation (LDS0/60) is estimated to be 3.5 Gy.

Portions of the POISINDEX® and MEDITEXT® databases have been provided here for general reference. THE COMPLETE POISINDEX® OR MEDITEXT® DATABASE SHOULD BE CONSULTED FOR ASSISTANCE IN THE DIAGNOSIS OR TREATMENT OF SPECIFIC CASES. The use of the POISINDEX® and MEDITEXT® databases is at your sole risk. The POISINDEX® and MEDITEXT® databases are provided "AS IS" and "as available" for use, without warranties of any kind, either expressed or implied. Micromedex makes no representation or warranty as to the accuracy, reliability, timeliness, usefulness or completeness of any of the information contained in the POISINDEX® and MEDITEXT® databases. ALL IMPUED WARRANTIES OF MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE OR USE ARE HEREBY EXCLUDED. Micromedex does not assume any responsibility or risk for your use of the POISINDEX® or MEDITEXT® databases. Copyright 1974-2004. Thomson MICROMEDEX. All Rights Reserved. Any duplication, replication, "downloading," sale, redistribution or other use for commercial purposes is a violation of Micromedex' rights and is strictly prohibited.

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Laboratory

A) Baseline laboratory studies should include a CBC with differential count, platelet count, and electrolyte panel. These studies should be repeated frequently in the first 48 hours postexposure. B) See the MEDICAL SURVEILLANCE/LABORATORY section in the main document for more information.

Portions of the POISINDEX® and MEDITEXT® databases have been provided here for general reference. THE COMPLETE POISINDEX® OR MEDITEXT® DATABASE SHOULD BE CONSULTED FOR ASSISTANCE IN THE DIAGNOSIS OR TREATMENT OF SPECIFIC CASES. The use of the POISINDEX® and MEDITEXT® databases is at your sole risk. The POISINDEX® and MEDITEXT® databases are provided "AS IS" and "as available" for use, without warranties of any kind, either expressed or implied . Micromedex makes no representation or warranty as to the accuracy, reliability, timeliness, usefulness or completeness of any of the information contained in the POISINDEX® and MEDITEXT® databases. ALL IMPLIED WARRANTIES OF MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE OR USE ARE HEREBY EXCLUDED. Micromedex does not assume any responsibility or risk for your use of the POISINDEX® or MEDITEXT® databases. Copyright 1974-2004. Thomson MICROMEDEX. All Rights Reserved. Any duplication, replication, "downloading," sale, redistribution or other use for commercial purposes is a violation of Micromedex' rights and is strictly prohibited.

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Carcinogen icity Evidence

There is sufficient evidence in humans that therapeutic injection of radium-224 causes bone sarcomas, There is sufficient evidence in humans that ingestion of radium-226 causes bone sarcomas and carcinomas of the paranasal sinuses and mastoid process. There is sufficient evidence in humans that ingestion of radium-228 causes bone sarcomas. /Radium-224 and radium-228/

There is sufficient evidence in experimental animals for the carcinogenicity of mixed alpha-particle emitters (radium-224, radium-226, thorium-227, thorium-228, thorium-230, thorium-232, neptunium-237, plutonium-238, plutonium-239 (together with plutonium-240), americium-241, curium-244, californium-249 and californium-252). /Radium, Plutonium, Americium, Curium, Californium/

There is sufficient evidence in experimental animals for the carcinogenicity of mixed beta-particle emitters (iodine-131, cesium-137, cerium-144 and radium-228) . / Iodine, Cesium, Cerium, Radium/

Radium-224 (224-Ra) and its decay products are carcinogenic to humans (Group 1) . Radium-226 (226-Ra) and its decay products are carcinogenic to humans (Group 1). Radium-228 (228-Ra) and its decay products are carcinogenic to humans (Group 1). /Radium-224, radium-228/


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Radiation Limits/Potential

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Of total disintegrations /of radium-226/, 94.3% occur with emission of alpha-particles having energy of 4. 78 MeV; the remaining 5.7% is accounted for in alpha particles with a lower energy ( 4.59 MeV) and gamma-quanta with energy 0.186 MeV.

Variations in radium content of drinking water may cause appreciable differences in radiation dose to skeleton and in turn, in risks of assoc carcinogenic effects. Under avg conditions, annual dose to bone ... amt to approx 6.4 mrem/yr, which represents about 6% of total dose to skeleton from ... natural background radiation ....

... Bone-seeking radionuclides ... radium-226 and radium-228 account for somewhat larger proportion of total bone dose . ... True for 2 isotopes of radium because they, or their daughters, emit high-linear-energy-transfer (LET} radiation, and because certain restricted localities have been found to have rather high concn of radium in drinking water.

Half-life 1599 years /Radium-226/

Half-life 5. 75 years /Radium-228/

Radium-226 (half-life= 1,600 years) and radium-224 (3.6 days) ...

Half-life = 5. 76 years /Radium-228/

Half-life = 1599 years / Radium-226/

Half-life = 11.43 days /Radium-223/

DECAY PATHWAY: Radium-223, half-life 11.435 days, decays via alpha emission, 5879 keV (52.6% 5716 keV; 25.7% 5607 keV; 9.2% 5540 keV), to radon-219, half-life 3.96 seconds; decays via alpha emission, 6946 keV (79.4% 6819 keV; 12.9% 6552 keV), to polonium-215, half-life 1.781 milliseconds; decays via alpha emission, 100% 7386 keV, to lead-211, half-life 36.1 minutes; decays via beta(-) emission (91.3%, 1378 maximum, 475.7 keV average energy) to bismuth-211, half-life 2.14 minutes; decays via alpha emission, 6751 keV (83.8% 6623 keV; 16.2% 6278 keV}, and gamma emission (abs intensity: 12.95% 351.1 keV) to thallium-207, half-life 4.77 minutes; decays via beta(-) emission (99.7%, 1436 maximum, 496.2 average energy) to lead -207m, half-life 0.806 seconds; decays via isomeric transition (gamma emission (abs intensity): 97.9% 569.7 keV; 88.5% 1063.7 keV) to lead-207, half-life stable.

DECAY PATHWAY: Radium-226, half-life 1600 years, decays via alpha emission, 4870 keV (94.45% 4784 keV; 5.55% 4601 keV}, to radon-222, 3.8235 days; decays via alpha emission, 99.92% 5489.5 keV, to polonium-218, half-life 3.10 minutes; decays via alpha emission, 99.998% 6002 keV, to lead-214, half-life 26.8 minutes; decays via beta(-) emission (48.9%, 670 keV maximum, 207 keV average energy; 42.2% 727.8 keV maximum, 227 keV average energy) and gamma emission (abs intensities: 37.6% 351.9 keV; 19.3% 295.2 keV} to bismuth-214, half-life 19.9 minutes; decays via beta emission (18.2%, 3275 keV maximum, 1270 keV average energy; 17.8%, 1542 keV maximum, 540 keV average energy; 17.0%, 1507 keV maximum, 526 keV average energy; 7.43%, 1894 keV maximum, 685 keV average energy) and gamma emission (abs intensities: 46.1% 609.3 keV; 15.4% 1764.5 keV; 15.1% 1120.3 keV; 5.1% 2204.2 keV) to polonium-214, half-life 164.3 microseconds; decays via alpha emission, 99.989% 7687 keV, to lead-210, half-life 22.3 years; decays via beta(-) emission (84%, 16.6 keV maximum, 4.16 keV average energy; 16%, 63.1 keV maximum, 16.16 keV average energy) to bismuth 210, half-life 5.013 days; decays via beta(-) emission (100%, 1161.5 keV maximum, 389.0 average energy) to polonium-210, half-life 138.376 days; decays via alpha emission, 100% 5304.3 keV, to lead-206, half-life stable.

DECAY PATHWAY: Radium-228, half-life 5. 75 years, decays via beta ( -) emission, ( 40%, 39.2 keV maximum, 9 .94 keV average energy; 30%, 12.8 keV maximum, 3.21 keV average energy; 20%, 25.7 keV maximum, 3.21 keV average energy; 10%, 39.6 keV maximum, 10.04 keV average energy) and gamma emission (abs intensities: 100% 13.52 keV; 45% 16.2 keV; 19% 12.75 keV; 10% 15.5 keV} to actinium-228, 6.15 hours; decays via-beta(-) emission (29.9%, 1158 keV maximum, 382.3 keV average energy; 11.66%, 1730 keV maximum, 606.9 keV average energy; 8.0%, 595.5 keV maximum, 178.7 average energy; 5.92%, 1004 keV maximum, 324.4 keV average energy) and gamma emission (abs intensities: 25.8% 911.2 keV; 15.8%968 .9 keV; 11.27% 338.2 keV; 4.99%964.7 keV; 4.4%463.0 keV; 4.25% 794 .9 keV) to thorium-228, half-life 1.912 years; decays via alpha emission, 5520 keV (72.2% 5423 keV; 27.2% 5340 keV), to radium-224, half-life 3.66 days; decays via alpha emission, 5789 keV (94.9% 5685 keV; 5.1% 5448 keV), to radon-220, half-life 55.6 seconds; decays v ia alpha emission, 99.886% 6288 keV, to polonium-216, half-life 0.145 seconds; decays via alpha emission, 99.998% 6778 keV, to lead-212, half-life 10.64 hours; decays via beta(-) emission (82.5%, 335 keV maximum, 94.8 keV average energy; 12.3%, 173 keV average energy; 5.17%, 42.3 keV average energy) and gamma emission (abs intensity: 43.3% 238.6 keV) to bismuth-212, half-life 60.55 minutes; 64% decays via alpha emission, 96.9% 11650 keV, to lead-208, half-life stable; 36% decays via alpha emission, 6207 keV (69.9% 6050 keV; 27.1% 6090 keV) to thallium 208, half-life 3.053 minutes; decays via beta(-) emission (48.7%, 1796 keV maximum, 647.4 keV average energy; 24.5%, 1285 keV maximum, 439.6 keV average energy; 21.8%, 1518 keV maximum, 533 .3 keV average energy) and gamma emission (abs intensities: 85.2% 583.2 keV; 22.8% 510.8 keV; 12.5% 860.6 keV) to lead-208, half-life

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stable.

When radionuclides have entered the bodyr cells and tissues will continue to be exposed to the emitted radiation until the radionuclide has been completely excreted or has fully decayed. Dose limits for occupational exposure are generally derived from the dose of the radionuclide integrated over SO years after the intake. The committed effective dose for occupational exposure, E(SO), is defined as the sum of the products of the committed organ or equivalent doses and the appropriate organ or tissue weighting factors, where 'SO' indicates the integration time in years after intake. In calculating the E(SO) , the dose coefficient/ i.e. the committed effective dose per unit intake/ expressed in Sv/Bq, is frequently used. The recommended upper limit for annual intake of radionuclides is based on a committed annual effective dose of 20 mSv. The annual limit on intake in becquerels can be calculated by dividing this value (0.02 Sv) by the dose coefficient.

QUANTITIES OF NRC LICENSED MATERIAL REQUIRING LABELING

I RADIONUCLIDE II QUANTITY (uCi)

IRadium-223 llo.1

IRadium-224 llo.1

IRadium-225 llo.1

IRadium-226 llo.1

IRadium-227 111/000

IRadium-228 llo.1

ALI values have been established for individual radionuclides and are presented in Table 1 in Appendix B to PART 20.1001-20.2401. The ALI values for inhalation/ presented in Column 2 in Table 11 correspond to a committed effective dose equivalent of 5 rems (0.05 Sv) or a committed dose equivalent of SO rems (0.5 Sv) to any individual organ or tissue, whichever is more limiting. If the ALI value presented in Table 1 is limited by the 50-rem committed dose equivalent, the controlling organ is listed directly below the ALI valuer and the stochastic ALI va lue based on the 5-rem committed effective dose equivalent is listed in parentheses directly below the organ name. If a stochastic ALI is listed in parentheses, that value should be used to calculate the committed effective dose equivalent.

OCCUPATIONAL VALUES FOR RADIUM RADIONUCLIDES (All compounds Class W)

I RADIONUCLIDE II ORAL Ingestion ALI (uCi) II INHALATION ALI (uCi} II INHALATION DAC (uCi/mL}

IRadium-223 llsE+O (Bone Surf) (9E+O) II7E-1 113E-10

IRadium-224 118E+O (Bone Surf) (2E+ 1) 112E+O 117E-10

IRadium-225 118E+O (Bone Surf) (2E+ 1) 117E- 1 113E-10

IRadium-226 112E+O (Bone Surf) (SE+O) 116E-1 113E-10

IRadium-227 112E+4 (Bone Surf) (2E+4) 111E+4 (Bone Surf) (2E+4) 116E-6

IRadium-228 112E+O (Bone Surf) (4E+O) 111E+O llsE-10

EFFLUENT CONCENTRATIONS ESTABLISHED BY THE NRC FOR SOME RADIUM COMPOUNDS

I RADIONUCLIDE II EFFLUENT CONCENTRATIONS: Air (uCi/mL) II EFFLUENT CONCENTRATIONS: Water (uCi/mL) I IRadium-223 119E-13 lilE-7

IRadium-224 112E-12 I12E-7

IRadium-225 119E-13 I12E-7

IRadium-226 119E-13 116E-8

IRadium-227 113E-8 I13E-4

IRadium-228 116E-8 1[6E-7


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Exposure Summary

Radium is a naturally occurring element and is ubiquitous in the environment. It occurs in very low concentrations (about one part per trillion) in the earth's crust, mainly as radium-226. Of the 25 known isotopes of radium only two, radium-226 and radium-228, have half-lives greater than one year. All isotopes of radium are radioactive. Four isotopes are naturally occurring: radium-223, radium-224, radium-226, and radium-228. Radium is present in all uranium and thorium minerals. Radium would not exist in its elemental form under environmental conditions. Commonly occurring radium salts are those of bromide, chloride, carbonate, and sulfate. The concentration of radium in uranium ores is about one part radium to 3 million parts uranium. Radium is a major uranium decay product. Thermal waters contain some natural radioactivity that can be attributed to the elements from the uranium and thorium natural decay series, such as radium-226 and radium-228. High concentrations of radium are associated with natural phosphates of sedimentary origin. The former use of radium to make self-luminous paints for watches, clocks, and other instruments, may have resulted in the release of radium compounds to the environment through various waste streams. Radium is used in brachytherapy to treat cancer; brachytherapy is radiation treatment where a sealed source is used to deliver a radiation dose to a tumor. The only radium isotope with commercial uses is radium-226. Radium is a major contaminant in mine and milling wastes, such as uranium mill tailings, and is present in radioactive wastes associated with past uranium processing activities. Wastes from phosphate ore processing contain radium-226. Data from a study of soil from a field adjacent to a ventilation shaft of a uranium mine showed that there was increased activity concentrations due to various radionuclides, including radium-226 and radium-228. Radium is found in natural phosphates, which are processed for chemical fertilizers. In turn radium is widely found on agricultural lands and eventually is leached by rain water into lake and river sediments. The most important route for the release of radium to air is the combustion of coal; annual releases of total radium in the US are estimated at 2.2 Ci. Global releases of radium-226 are estimated at 150 Ci/year from the coal combustion. If released to air, radium compounds would exist solely in the particulate phase in the ambient atmosphere since they are ionic and would not be volatile. Particulate-phase radium compounds will be removed from the atmosphere by wet and dry deposition. Radium adheres to soil particles and is generally less mobile in clay soils than in sandy soils. Volatilization from moist or dry soil surfaces is not expected since ionic radium compounds would be nonvolatile. In water radium occurs as radium 2+ ion. Radium can interact with sediments and dissolved solids in water. When release to groundwater, dissolved radium sorbs quickly to solids and does not migrate far from its place of release. Radium behaves similarly to barium and insoluble compounds of barium are the same as for radium. Volatilization from water surfaces is not expected since radium compounds are ionic. Bioconcentration is not expected to be an important fate process due to the ionic nature of radium compounds. As a member of the alkaline earth metal group radium would not be expected to undergo oxidation-reduction reactions under environmental conditions, and would exist in its 2+ oxidation state either in compounds or as dissolved ions. Radium(II) ions may undergo precipitation or ligand exchange reactions in the environment. Occupational exposure to radium compounds may occur through inhalation at workplaces where radium compounds are produced or used. As radium occurs in soil, rocks, surface water, groundwater, plants, and animals at low concentrations on the order of 1 parts per trillion or 1 pCi/g, the general population will be exposed radium compounds via inhalation of ambient air and ingestion of food and water. (SRC)

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Environmental Fate

AQUATIC FATE: Uranium, thorium, radium, radon, lead, and polonium radionuclide concentrations in ground waters from the Hanford Site indicate that uranium, thorium, and radium are highly sorbed. Relative to radon, these radionuclides are low by factors of lxlO( -3) to lxlO( -6). Uranium sorption is likely due to its reduction from the hexavalent state, where it is introduced via surface waters, to the tetravalent state found in the confined aquifers. The distribution of radionuclides is very similar in all of the confined aquifers and significantly different from the distribution observed in the unconfined and surface waters. Barium correlates well with radium over three orders of magnitude, indicating that stable element analogs may be useful for inferring the behavior of radioactive waste radionuclides in this candidate geologic repository.

AQUATIC FATE: In water radium occurs as radium 2+ ion(l). Radium behaves similarly to barium and insoluble compounds of barium are the same as for radium(l). Radium-226 was found to exist primarily in the dissolved phase of estuary water in studies of the cycling of three radionuclides in the Tagus estuary (Portugal)(2). Radium can interact with sediments and dissolved solids in water(3). When released to groundwater, dissolved radium sorbs quickly to solids and does not migrate far from its place of release(4). Volatilization from water surfaces is not expected since radium compounds are ionic(SRC). Bioconcentration is not expected to be an important fate due to the ionic nature of rad ium compounds(SRC).

ATMOSPHERIC FATE: Radium compounds would exist solely in the particulate phase in the ambient atmosphere since they are ionic and would not be volatile. Particulate-phase radium compounds will be removed from the atmosphere by wet and dry deposition. (SRC)

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Volatilization

Volatilization from moist or dry soil or from water surfaces is not expected since ionic radium compounds would be nonvolatile. (SRC)


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WMD Response Guidelines

Nuclear (Radiological) Materials

SIGNS AND SYMPTOMS • Short-Term:

o Nausea

o Burns

INDICATORS • Overt Threats

• Groups Taking Credit for Incident

• Specialized Packaging Near the Scene

• Radiological Placards on Vehicles

• Radiological Labels of Items

ROUTES OF EXPOSURE • Inhalation

• Absorption

• Ingestion

• Injection

EMERGENCY RESPONSE

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Guide 14

• Approach from Upwind, Uphill, or Upstream (if there is potential for dissemination of nuclear material or particulate matter)

• Isolate Immediate Area in all directions distance of at least 80-160 feet

• Keep Unauthorized Persons Away

• Consider Immediate Downwind Evacuation Distance of 330 feet at night

• Consider Immediate All Direction Evacuation Distance of 1000 feet during the day

• Stay Upwind

• Make Notifications

• Obtain immediate medical evaluation for all exposed or potentially exposed personnel

TYPE OF HARM • Radiological

• Possible Chemical

• Possible Thermal

PERSONAL PROTECTION • Time: Keep Exposure and Product Contact to Minimum

• Distance: Stay at least 300 feet away on Upwind Side Until Agent is Identified

• Shielding: Chemical Protective Clothing

Content reproduced for WISER with permission from the Louisiana State University and A&M College, National Center for Biomedical Research and Training, Academy of Counter-Terrorist Education. WMD Response Guidebook© . Further reproduction prohibited.

Printed by (Version 4.3.4401, Database Version 4.4.20) HHS/NIH, National Library of Medicine


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Threshold Limit Values

The Physical Agents TLV Committee accepts the occupational exposure guidance of the International Commission on Radiological Protection (ICRP) . .. . ICRP Guidelines for Exposure to Ionizing Radiation: Effective Dose (a) in any single year, SO mSv, (b) averaged over 5 years, 20 mSv per year. Annual Equivalent Dose to: (a) lens of the eye, 150 mSv, (b) skin, 500 mSv, (c) hands and feet, 500 mSv. Embryo-Fetus exposures once the pregnancy is known- monthly equivalent dose 0.5 mSv- dose to the surface of women's abdomen (lower trunk) 2 mSv for the remainder of the pregnancy - intake of radionucl ide one twentieth of Annual Limit on Intake (ALI).

The Physical Agents TLV Committee accepts the occupational exposure guidance of the International Commission on Radiological Protection (ICRP). Ionizing radiation includes particulate radiation (e.g., alpha particles and beta particles emitted from radioactive materials, and neutrons from nuclear reactors and accelerators) and electromagnetic radiation (e.g., gamma rays emitted from radioactive materials and X-rays from electron accelerators and X-ray machines) with energy greater than 12.4 electron-volts (eV) .. . The guiding principle of radiation protection is to avoid all unnecessary exposures. ICRP has established principles of radiological protection. There are (1) the justification of a work practice: No work practice involving exposure to ionizing radiation should be adopted unless it produces sufficient benefit to the exposed individuals or the society to offset the detriment it causes. (2) The optimization of a workpractice: All radiation exposures must be kept as low as reasonably achievable (ALARA), economic and social factors being taken into account. (3) The individual dose limits: The radiation dose from all relevant sources should not exceed the / ICRP/ prescribed dose limits.


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