CESO

Engineer Manual

385-1-80

Department of the ArmyU.S. Army Corps of Engineers

Washington, DC 20314-1000

EM 385-1-80

30 May 1997

Safety

RADIATION PROTECTION MANUAL

Distribution Restriction StatementApproved for public release; distribution is

unlimited.

i

DEPARTMENT OF THE ARMY EM 385-1-80U.S. Army Corps of Engineers

CESO Washington, D.C. 20314-1000

Manual 30 May 1997No. 385-1-80

SafetyRADIATION PROTECTION MANUAL

Table of Contents

Subject Para. Page Subject Para. Page

Chapter 1. Organization of USACERadiation Protection Program.

Purpose 1-1 1-1

Applicability 1-2 1-1

Policy 1-3 1-1

Management Commitment,Involvement, andLeadership 1-4 1-2

Scope 1-5 1-2

Overview of thisManual 1-6 1-3

Chapter 2. USACE PersonnelResponsibilities and Qualifications.

The Chief, Safety andOccupational HealthOffice, HQUSACE 2-1 2-1

Radiation ProtectionStaff Officer 2-2 2-1

USACE Commanders 2-3 2-2

Radiation ProtectionOfficer 2-4 2-3

Laser Safety Officer 2-5 2-4

Qualified HealthPhysics Personnel 2-6 2-5

Authorized Users 2-7 2-5

Authorized Users’Assistants 2-8 2-7

Site Supervisors 2-9 2-7

Project/Plan/ProcedureOriginators andReviewers 2-10 2-8

Radiation ProtectionCommittee 2-11 2-9

Hazardous, Toxic andRadioactive Waste(HTRW), Center ofExpertise 2-12 2-9 Refresher Training 2-13 2-10

Additional Training/Special Applications 2-14 2-10

All Personnel includingVisitors at a RadiationSite 2-15 2-10

Chapter 3. Introduction toRadiation.

Atomic Structure 3-1 3-1

Radioactive Decay 3-2 3-1

Activity 3-3 3-2

Decay Law 3-4 3-3

Types of IonizingRadiation 3-5 3-4

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Interaction ofRadiation With Matter 3-6 3-6

Human Health Effects 3-7 3-8

Determinants of Dose 3-8 3-9

Background Radiation 3-9 3-11

Radiation Quantities 3-10 3-12

Biological Effectsof Ionizing Radiation 3-11 3-16

Ways to MinimizeExposure 3-12 3-18

Standing OperatingProcedures 3-13 3-21

Monitoring andSurveying Equipment 3-14 3-21

Chapter 4. Licensing.

Overview ofRegulatory Agencies 4-1 4-1

Types of NRCRadioactive MaterialLicenses 4-2 4-1

'Storage Only'Licensing 4-3 4-4

Radiation GeneratingDevices 4-4 4-4

ReciprocityRequirements 4-5 4-4

Army RadiationAuthorization 4-6 4-5

Army Radiation Permitsand Other ServiceInstallation Permits 4-7 4-5

Applying for an NRCLicense 4-8 4-7

Applying for an ARA 4-9 4-9

Amendment Requests 4-10 4-9

Renewing Licenses orARAs 4-11 4-10

Transfer of RadioactiveMaterials 4-12 4-10

Terminating aRadioactive MaterialLicense or ARAs 4-13 4-11

Information Flowthrough ApplicableUSACE Channels 4-14 4-11

Chapter 5. Dose Limits and ALARA.

Occupational DoseLimit Structure 5-1 5-1

USACE Dose Limits 5-2 5-1

NRC and Agreement StateDose Limits 5-3 5-3

OSHA Dose Limits 5-4 5-4

Monitoring requirements 5-5 5-4

Doses to the Public 5-6 5-4

Chapter 6. Working with Radiation.

Caution Signs andLabels 6-1 6-1

Airborne Radioactivity 6-2 6-3

Rooms/Areas in WhichRadioactive Material isNo Longer Usedor Stored 6-3 6-3

Receiving RadioactiveMaterial 6-4 6-3

Radioactive Materialand RadiationGenerating DeviceInventory 6-5 6-6

Storing RadioactiveMaterial 6-6 6-6

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Contamination Control 6-7 6-7

Wipe Tests 6-8 6-8

Leak Testing 6-9 6-9

Exposure Rate Surveys 6-10 6-10

Accident/IncidentResponse 6-11 6-11

Accident/IncidentReporting 6-12 6-11

Audits and Reviews 6-13 6-13

Chapter 7. Personnel Monitoring.

External Monitoring 7-1 7-1

Internal Monitoring 7-2 7-2

Advanced Monitoring 7-3 7-4

Exposure Reporting 7-4 7-5

Chapter 8. Transportation ofRadioactive Material.

Purpose 8-1 8-1

Applicability 8-2 8-1

Regulations 8-3 8-1

Procedures 8-4 8-2

Packaging 8-5 8-2

Marking 8-6 8-3

Labeling 8-7 8-4

Placarding 8-8 8-5

Manifesting 8-9 8-5

Hazardous WasteManifesting 8-10 8-6

Emergency ResponseInformation 8-11 8-7

Hazmat EmployeeTraining 8-12 8-7

Exceptions 8-13 8-8

Chapter 9. Waste Management.

Regulation ofRadioactive Wastes 9-1 9-1

Low Level RadioactiveWaste (LLRW) 9-2 9-2

Elements of a WasteManagement Program 9-3 9-4

Material Tracking 9-4 9-4

Waste Minimization 9-5 9-4

Waste Recycling 9-6 9-4

Waste Storage 9-7 9-5

Waste Disposal 9-8 9-5

RadionuclideConcentrations 9-9 9-7

Chapter 10. Laser Safety.

Classifications ofLasers 10-1 10-1

Safety features andLabeling Requirements 10-2 10-1

Laser ProtectionProgram 10-3 10-2

OSHA Standards 10-4 10-3

USACE Standards 10-5 10-3

Protective Eyewear 10-6 10-3

Chapter 11. Radio Frequency (RF) andMicrowave Safety.

DA Limits 11-1 11-1

USACE Limits 11-2 11-1

OSHA Regulations 11-3 11-1

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General Guidance 11-4 11-1

Warning Signs 11-5 11-2

RF Safety Training 11-6 11-2

Appendix A.

References A-1

Appendix B.

Definitions B-1

Appendix C.

Sample Standing OperatingProcedures C-1

Appendix D.

X-Ray Fluorescence Lead AnalysisDevices D-1

Appendix E.

Rules of Thumb and Conversions E-1

Appendix F.

Signs, Labels and Postings F-1

Appendix G.

Radon G-1

Appendix H.

Applications and License Examples,Applicable Forms and Statements H-1

Appendix I.

USACHPPM Survey ProtocolChecklist I-1

Appendix J.

Acronyms Used in this EM J-1

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Chapter 1. Organization ofUSACE Radiation ProtectionProgram.

1-1. Purpose.

This guidance manual prescribesthe requirements of theRadiation Protection Program ofthe US Army Corps of Engineers(USACE) contained in EngineerRegulation (ER) 385-1-80,Ionizing Radiation Protection,and Engineer Manual (EM)385-1-1, Safety and HealthRequirements Manual. It is tobe used when activities utilizeor handle radioactive material(which includes radioactivewastes) or a radiationgenerating device. Radiationgenerating devices include X-ray equipment, accelerators,lasers, radio-frequency ande l e c t r o m a g n e t i c f i e l dgenerators. Authoritativeguidance and regulations arecontained in 10 CFR (Energy)and the NRC Regulatory Guides,29 CFR (Labor) 1910 and 1926OSHA regulations, and 40 CFR( P r o t e c t i o n o f t h eEnvironment). This manual isintended to assist USACECommands in integratingessent ia l requ i rementscontained in Federal, DA andUSACE radiation protectionregulations to ensure that thesafety and health requirementsof all agencies are met.

1-2. Applicability.

This manual is applicable toUSACE personnel and visitors toa worksite under thejurisdiction of USACE whereradioactive material or aradiation generating device maybe present. It shall be usedin conjunction with ER 385-1-80and EM 385-1-1. Contractorrequirements concerningionizing and non-ionizingradiation protection issues arecontained in EM 385-1-1 .

1-3. Policy.

a. USACE will work toensure that all personnelradiation exposure is kept aslow as is reasonably achievable(ALARA) taking technologicaland socioeconomic factors intoaccount. Radiation exposure toUSACE personnel, visitors andcontractors, as well as to thegeneral public, will be con-trolled so that exposures areheld well below regulatorylimits. There shall be noradiation exposure without acommensurate benefit.

b. All personnel involvedwith ionizing radiation work ofany kind will be knowledgeableof the programs, policies, andprocedures contained in ER 385-1-80 and this manual. Personnelworking with non-ionizingr a d i a t i o n s h o u l d b eknowledgeable of the specificinformation concerning thesetopics presented in thismanual. They shoulddemonstrate responsibility and

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accountability through aninformed, disciplined, andcautious attitude towardradiation and radioactivity.

c. Continuing improvementin radiation (ionizing and non-ionizing) protection isessential to USACE operationsinvolving radiation. Allpersonnel working withradiation are expected to lookfor ways to improve radiationprotection and make USACEprojects more efficient.

1-4. Management Commitment,Involvement, and Leadership.

S u p e r i o r , c o n s i s t e n tperformance is achieved whenqualified personnel useapproved procedures and whenmanagement actively monitorsthe work place and assessesongoing activities. To achievesuch performance requiresconstant review, informedinvolvement and leadership bysenior management. All levelsof management must emphasizethe need for high standards ofradiation safety through directc o m m u n i c a t i o n , c l e a rinstruction, and frequentinspections of the work area.

1-5. Scope.

a. This manual fullydescribes policies andprocedures for the safe use ofradioactive material andradiation generating devices atall USACE sites. It should beused to evaluate the

acceptability of health andsafety practices by USACEpersonnel and contractors onUSACE controlled sites.

b. The manual is alsointended to be consistent withall Federal (NRC, OSHA, EPA,DOE, and DOT) DA, USACE, State,and local statutes andregulations (that is,“applicable regulations”), andintegrate the variousregulations into one coherentpublication for USACEoperations. It will be revisedwhenever necessary to achieveconsistency with statutes andregulations.

c. For all contracts andactivities that requireFederal, State, or locallicensure or permitting, suchlicenses or permits shall besecured, and all license orpermit conditions shall beadhered to. If the statedlicense or permit conditionsvary from applicable sectionsof this manual, such license orpermit conditions prevail.Contractors will be required tosecure proper licensure orpermitting (for activities thatrequire it) within specifiedtime frames and before the datethat they are scheduled tobegin the work. All USACECommands and contractors usingArmy radioactive materialswill meet requirements of

Nuclear Regulatory Commission(NRC) licenses and ArmyRadiation Authorizations (ARAs)

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issued to USACE and the US ArmyMateriel Command, and ofapplicable Army technicalpublications.

e. Alternatives toprocedures addressed in thismanual may be acceptableprovided the alternativesachieve the same, or higher,level of radiation protection.Alternative procedures must beapproved by the RadiationProtection Officer, or LaserSafety Officer, as appropriate,and for specific conditions,higher level authorities priorto implementation.

1-6. Overview of this Manual.

This manual is designed toaddress all health and safetyaspects of work with radiationwithin USACE. Most personnelwithin USACE will not need theentire manual but will need toselect the chapters andsections applicable to theirwork requirements. Somegeneric classifications ofradiation work are listed inTable 1-1 with reference to theapplicable chapters of thismanual. It is recommended thatall personnel working withradioactive material andradiation generating devicesread Chapters 1, 2 and 3 ofthis manual. Depending on thetype of work being performed,portions of other chapters maybe applicable.

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USACE Radiation ProtectionProgram and the record keepingrequirements for work withradioactive material andradiation generating devices.

(5) a working knowledgeof US Nuclear RegulatoryCommission (NRC), USEnvironmental Protection Agency(EPA), US Department of Energy(DOE), US Department ofTransportation (DOT), and USDepartment of Labor (DOL) whichis the responsible for the USOccupational Safety and HealthAdministration (OSHA), and USArmy regulations pertaining toradioactive material andradiation generating devices.

b. Duties of the RPSO areas follows:

(1) Serve as the primaryliaison between USACE, DA andNRC in matters concerningradioactive materials orradiation generating devices.

(2) All NRC licenseactions will be submittedthrough, reviewed, and acceptedby the RPSO.

(3) Provide a copy of allcorrespondence relating to NRCapplications to DA as required.The RPSO will retain copies ofall NRC radioactive materiallicenses and correspondence(originals will be retained by

the licensee).

(4) Ensure that each USACE

Command possessing an NRCradioactive material license isaudited at least triennially toensure compliance with theUSACE Radiation ProtectionProgram. The RPSO, ordesignee, will check forcompliance with the USACERadiation Protection Programand the NRC radioactivematerial license. The RPSO, orhis designee will document allinspection findings and submitthem to the audited USACECommand for review and action.

2-3. USACE Commanders.

USACE Commanders shall:

a. Ensure a RadiationProtection Committee (RPC)shall be formed when theCommand possesses an NRClicense with a conditionstating that the licensee shallhave a RPC, or if the Commanderconsiders an RPC necessary.The RPC will consist ofpersonnel and duties describedin subparagraph 2-11.

b. Designate, in writing,a qualified person to serve asUSACE Radiation ProtectionOfficer (RPO) when any of thefollowing is true:

(1) an NRC License, ArmyReactor Permit, ARA ora p p l i c a b l e t e c h n i c a lpublication requires it,

(2) personnel are requiredto wear dosimetry,

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(3) personnel are requiredto participate in a bioassayprogram.

c. Fund, maintain andsupport the RPO and theRadiation Protection Program.The RPO shall meet thequalifications and provide theservices described in paragraph2-4.

d. Fund, maintain andsupport the Laser SafetyOfficer (LSO) and the LaserSafety Program when a USACECommand operates, maintains orservices a non-type-classifiedclass IIIb or class IV lasersystem as defined in section1.3, ANSI Z136.1. The RPO maybe designated as the LSO. TheLSO shall meet thequalifications and provide theservices described in paragraph2-5.

2-4. Radiation ProtectionOfficer (RPO).

a. The RPO (also known asa Radiation Safety Officer(RSO) in other documents) is aperson, designated by the USACECommand, and tasked with thesupervision of the USACERadiation Protection Programfor that command. The RPOshall have direct access tothe Commander for radiationprotection purposes. The RPOensures compliance with current

directives (AR’s, ER 385-1-80,EM 385-1-1, etc.) for radiationprotection and with this

manual. The RPO may limit orcease operations within theirCommand where there is aneminent and legitimateradiation safety issue.

b. The RPO shall beresponsible for:

(1) Establishing writtenpolicies and procedures toassure compliance withapplicable Federal, DOD, andArmy radiation protectionregulations and directives.These documents will includeemergency reaction plans asnecessary and procedures forinvestigating and reportingradiation accidents, incidents,and overexposures.

(2) Assuring that allpersonnel occupationallyexposed to radiation receivea p p r o p r i a t e r a d i a t i o np r o t e c t i o n t r a i n i n gcommensurate with potentialhazards from radiation sourcesthey may encounter.

(3) Maintaining aninventory of radiation sourcesas higher headquarters directsand IAW with requirements ofNRC licenses, Army reactorpermits, ARAs, and technicalpublications.

(4) Approving and filingrecords noting all AuthorizedUsers, Authorized Users’

Assistants and site supervisorsworking with radioactivematerials or radiation

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generating devices within theCommand.

(6) Providing or securingan acceptable source for allrequired initial and annualrefresher training for allindividuals within the Command.

c. The RPO will reviewthe USACE Radiation ProtectionProgram for their Commandannually for content andimplementation. The RPO willassure that the quality andtimeliness of the program meetthe radiation safety standardsoutlined in this manual. TheRPO will review work withradiation within the Command.The RPO will write and/orreview Standing OperatingProcedures to ensure thesafety, ti meliness, andcompatibility with existingradiation regulations.

d. The RPO will betechnically qualified, meetingthe experience, training, andeducation requirements listedbelow:

(1) A working knowledgeof NRC, EPA, DOE, DOT, and USArmy regulations pertaining toradioactive material, radiationg e n e r a t i n g d e v i c e s ,radioactive and mixed wasteused within their Command.

(2) Forty hours of formal

training covering:

(a) the physics of

rad ia t ion , rad ia t ion 'sinteraction with matter, andthe mathematics necessary tounderstand the above subjects;

(b) the biologi cal effectsof radiation;

(c) the instrumentationnecessary to detect, monitor,and survey radiation, and theuse of such instrumentation;and

(d) radiation safetytechniques and procedures.This training will include theuse of time, distance,sh ie ld ing , eng ineer ingcontrols, and PPE to reduceexposure to radiation.

(3) Practical, hands-onexperience using radiationinstrumentation, procedures,and theory.

(4) A working knowledgeof the Army RadiationProtection Program and theUSACE Radiation ProtectionProgram, and the record keepingrequirements for work withradioactive material andradiation generating devicesused within their Command.

2-5. Laser Safety Officer(LSO).

a. The LSO is a persondesignated by the USACE Command

tasked with the supervision ofthe Laser Sections of the USACERadiation Protection Program

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for that command. The LSOensures compliance with currentdirectives for laser safety (EM385-1-1, TB MED 524, ANSIZ136.1, etc.) and with thismanual.

b. The LSO will reviewthe USACE Laser Safety Programfor their Command annually forcontent and implementation.The LSO will assure that thequality and timeliness of theprogram meet the laser safetystandards outlined in thismanual. The LSO will write andreview Standing OperatingProcedures to ensure thesafety, ti meliness, andcompatibility with existinglaser regulations.

c. The LSO will betechnically qualified, meetingthe experience, training, andeducation requirements listedbelow:

(1) A working k nowledge ofapp l icab le regu la t ionspertaining to lasers usedwithin their Command.

(2) Practical, hands-onexperience using lasers, laserprocedures, and laser theory.

(3) A working k nowledge ofthe Army Radiation ProtectionProgram and the USACE RadiationProtection Program, and therecord keeping requirements for

work with lasers within theirCommand.

2-6. Qualified Health PhysicsPersonnel.

A qualified Health Physicist(HP) is responsible forassisting the RPO with theirUSACE Command RadiationProtection Program, andreviewing Scopes of Work, WorkPlans, and/or Site Safety andHealth Plans for all workinvolving radiation. QualifiedHPs are personnel:

a. Meeting the Office ofPersonnel Management Standardsfor the HP Series, GS-1306, andhaving three years experiencein work with radiation; or

b. Certified as a HealthPhysicist by the American Boardof Health Physics, or certifiedby the American Board ofIndustrial Hygiene (CertifiedIndustrial Hygienist) and oneyear experience working withradiation; or

c. Identified as being aqualified HP by the Director ofArmy Radiation Protection, ArmySafety Office, or the ArmySurgeon General, and havingthree years experience in workwith radiation.

2-7. Authorized Users (AUs).

AUs are individuals who, bytheir training and experience,are allowed to work,

unsupervised, with radioactivematerial or radiationgenerating devices. AUs may

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also direc tly superviseAuthorized Users Assistantsworking with radioactivematerial. All AUs must beapproved by the facility RPC,if one exists. If the facilitydoes not require an RPC, theAUs must be approved by theRPO. All AUs must meet thefollowing training andexperience requirements:

a. A working knowledge ofapp l icab le regu la t ionspertaining to radioactivematerial, radiation generatingdevices, and radioactive andmixed waste with which they maybe working;

b. Unless differentrequirements are stated in thelicense, authorization orpermit conditions, eight clockhours of formal trainingcovering:

(1) the physics ofrad ia t ion , rad ia t ion 'sinteraction with matter, andthe mathematics necessary tounderstand the above subjects;

(2) the biologicaleffects of radiation;

(3) the instrumentationnecessary to detect, monitor,and survey radiation, and theuse of such instrumentation;and

(4) radiation safetytechniques and procedures.This training will include the

use of time, distance,sh ie ld ing , eng ineer ingcontrols, and PPE to reduceexposure to radiation.

c. Practical, hands-onexperience using radiationinstrumentation and procedures.The level of training will becommensurate with the hazardpresented by the radioactivematerial or radiationgenerating device; and

d. A working knowledge ofthe USACE and his or her USACECommand Radiation ProtectionProgram, and the record keepingrequirements for theradioactive material andradiation generating devicesused in their work.

e. Instruction in theirr i g h t s a n d t h e i rresponsibilities under theUSACE Command NRC license, orArmy Radiation Authorization(ARA). This includes:

(1) the employe r’s duty toprovide safe workingconditions;

(2) a report of allradiation exposure to theindividual;

(3) the individual'sresponsibility to adhere to theNRC’s regulations and theCommands's radiation material

license, or ARA; and

(4) the individual's

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responsibility to report anyviolation or other occurrenceto the RPO.

f. Authorized users ofportable gauges will alsoreceive 8 hours training in thesafety and use of the gaugefrom the manufacturer.

2-8. Authorized Users’Assistants (AUAs).

AUAs are individuals allowed towork with radioactive materialonly under the directsupervision of an AU (that is,in the physical presence of theAU). All AUAs must benominated by the AU andapproved by the RPO. AUAs willhave the training andexperience described below:

a. A total of at leastfour hours instruction in thefollowing:

(1) the health effectsassociated with exposure to theradioactive material orradiation they work with;

(2) ways to minimizeexposure;

(3) the purpose and use ofprotective equipment used intheir work; and

(4) the applicableregulations to their work.

b. Practical, hands-onexperience using radiationinstrumentation and procedures.

c. Instruction in theirr i g h t s a n d t h e i rresponsibilities under theUSACE Command NRC license, orARA. This includes:

(1) the employe r’s duty toprovide safe workingconditions;

(2) a report of allradiation exposure to theindividual;

(3) the individual'sresponsibility to adhere to theNRC’s regulations and theCommand's radioactive materiallicense, or ARA; and

(4) the individual'sresponsibility to report anyviolation or other occurrenceto the RPO.

2-9. Site Supervisors/Construction Quality AssurancePersonnel.

a. Individuals working ass i t e s u p e r v i s o r s o rconstruction quality assurancerepresentatives on projectsinvolving radioactive materialor radiation generating devicesmust be knowledgeable of: theprinciples of radiationpro tec t ion ; app l i cab leregulations pertaining toradioactive material andradiation generating devices,

and the application of theseprinciples and regulations toworker and public health andsafety at project sites.

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b. Individuals whosupervise work or act asconstruction quality assurancerepresentatives at sitesinvolving radioactive materialor radiation generating deviceswill have a minimum of eighthours of radiation safetytraining covering thefollowing:

(1) physics of radiation,radiation's interaction withmatter, and the mathematicsnecessary to understand theabove subjects;

(2) biological effects ofradiation;

(3) instrumentat ionnecessary to detect, monitor,and survey radiation, and theuse of such instrumentation;and

(4) radiation safetytechniques and procedures.This training will include theuse of time, distance,sh ie ld ing , eng ineer ingcontrols, and PPE to reduceexposure to radiation.

2-10. Project/Plan/ProcedureOriginators and Reviewers .

a. Individuals whooriginate or review projects,plans, or procedures involving

radioactive material orradiation generating devicesmust be knowledgeable of theprinciples of radiationprotection, the applicable

regulations pertaining toradioactive material andradiation generating devices,and the application of theseprinciples and regulations toworker and public health andsafety.

b. Originators andreviewers of plans, projects orprocedures for work at sitesusing radioactive material orradiation generating deviceswill have a minimum of eighthours of radiation safetytraining covering thefollowing:

(1) physics of radiation,radiation's interaction withmatter, and the mathematicsnecessary to understand theabove subjects;

(2) biological effects ofradiation;

(3) instrumentat ionnecessary to detect, monitor,and survey radiation, and theuse of such instrumentation;and

(4) radiation safetytechniques and procedures.This training will include theuse of time, distance,sh ie ld ing , eng ineer ingcontrols, and PPE to reduceexposure to radiation.

2-11. Radiation ProtectionCommittee (RPC).

a. Each Command possessingan NRC license or an ARA with a

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condition stating that thelicensee shall have an RPC, orwhere the Commander deemsnecessary, shall form an RPC.At a minimum, the RPC willconsist of:

(1) The Command ing Officer(CO) or deputy;

(2) The RPO, who will actas recorder for all meetings;

(3) The Chief; Safety andOccupational Health Office; and

(4) A representativeAuthorized User from each groupusing radioactive material orradiation generating devices inthe Command.

b. The RPC is accountableto its USACE Commander. The COor his/her deputy chairs theRPC. The RPC will meet at leastonce each six-month period andat the call of the chair. TheRPC will continually evaluateradiological work activities,and make recommendations to theRPO and management. Ina d d i t i o n t o i t sresponsibilities establishedin the Army RadiationProtection Program, the RPCr e s p o n s i b i l i t i e sinclude:

(1) Annual review of USACECommand personnel exposure

records;

(2) Establishing criteriafor determining the appropriatelevel of review and

authorization for workinvolving radiation exposure;and,

(3) Evaluating health andsafety aspects of theconstruction and design offacilities and systems andplanned major modifications orwork activities involvingradioactive material orradiation generating devices.

c. The RPO will furnishthe installation commander andRPSO with copies of theminutes of all RPC meetings,within 30 days of the meeting.

2-12. Hazardous, Toxic andRadioactive Waste (HTRW),Center of Expertise (CX).

a. The HTRW-CX providestechnical assistance to USACEheadquarters, and designdistricts as requested on allareas of HTRW and environmentalremediation. The CX has a staffthat includes Technical LiaisonManagers (TLMs), Chemists,Regulatory Special ists,Geotechnical, Process, and CostEngineers, Risk Assessment,Industrial Hygiene and HealthPhysics personnel.

b. The HTRW-CX can providetechnical assistance to theRPSO as requested, including:

(1) licensing,

(2) inspecting,

(3) product development,

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(4) and advice andguidance on radiation safetyand protection issues.

c. The HTRW-CX can providesupport to other Commands onradiation safety issues,including radon, X-rayfluorescence devices for leadmonitoring, etc.

2-13. Refresher Training.

USACE personnel who havecompleted their initialtraining, shall receive annualrefresher training on thematerial described for eachperson in this chapter. Therefresher training may becomprised of an update of SOPs,review of dosimetry results,changes in standards orguidance, equipment changes,and any other pertinentradiation safety informationthat needs review. The lengthof this training is dependenton the specific material beingcovered, it does not have toequal the time requirementsneeded for initial training.Personnel who have completedtheir initial training and anysubsequent refresher training,but currently are not and willnot be assigned to workinvolving radiation, are notrequired to be up-to-date

regarding the refreshert r a i n i n g r e q u i r e m e n t .Personnel whose refreshertraining has lapsed may notwork with radiation until aftercompletion of refresher

training. Personnel who havenot received refresher trainingfor over two years may berequired, at the RPO’sdiscretion, to repeat theirinitial training.

2-14. Additional Training -Special Applications.

Additional training may berequired for work involvingspecial applications (forexample , plutonium, fissileuranium, tritium, and accelera-tor facilities). Personnelworking with specialapplications should consultwith the HTRW-CX for additionaltraining requirements.

2-15. All Personnel includingVisitors, at a Radiation Site.

a. Regulations requirethat all individuals who arelikely to receive 100 mremabove background in one yearshall be kept informed of thepresence of radioactivematerial or radiation in thearea and shall be instructedannually in the following:

(1) The health effectsassociated with exposure to theradioactive material orradiation;

(2) Ways to minimizeexposure;

(3) The purpose and use ofprotective equipment and surveyinstruments used in the area;

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(4) The regulationsapplicable to the area.

b. The extent of

instruct ion shal l becommensurate with the extent ofthe hazard in the area.

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Chapter 3. Introduction toRadiation.

3-1. Atomic Structure.

a. The atom, which hasbeen referred to as the"fundamental building block ofmatter," is itself composed ofthree primary particles: theproton, the neutron, and theelectron. Protons and neutronsare relatively massive comparedto electrons and occupy thedense core of the atom known asthe nucleus. Protons arepositively charged whileneutrons are neutral. Thenegatively charged electronsare found in a cloudsurrounding the nucleus.

b. The number of protonswithin the nucleus defines theatomic number, designated bythe symbol Z. In anelectrically neutral atom (thatis, one with equal numbers ofprotons and electrons), Z alsoindicates the number ofelectrons within the atom. Thenumber of protons plus neutronsin the nucleus is termed theatomic mass, symbol A.

c. The atomic number of anatom designates its specificelemental identity. Forexample, an atom with a Z=l ishydrogen, an atom with Z=2 ishelium, and Z=3 identifies anatom of lithium. Atomscharacterized by a particularatomic number and atomic massare called nuclides. A

specific nuclide is representedby its chemical symbol with theatomic mass in a superscript(for example, H, C, U) or3 14 238

by spelling out the chemicalsymbol and using a dash toindicate atomic mass (forexample, radium-222, uranium-238). Nuclides with the samenumber of protons (that is,same Z) but different number ofneutrons (that is, different A)are called isotopes. Isotopesof a particular element havenearly identical chemicalproperties, but may have vastlydifferent radiologicalproperties.

3-2. Radioactive Decay.

a. Depending upon theratio of neutrons to protonswithin its nucleus, an isotopeof a particular element may bestable or unstable. Over time,the nuclei of unstable isotopesspontaneously disintegrate ortransform in a process known asradioactive decay orradioactivity. As part of thisprocess, various types ofionizing radiation may beemitted from the nucleus.Nuclides which undergoradioactive decay are calledradionuclides. This is ageneral term as opposed to theterm radioisotope which is usedto describe an isotopicrelationship. For example, H,3

C, and I are radionuclides.14 125

Tritium ( H), on the other3

hand, is a radioisotope ofhydrogen.

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b. Many radionuclides suchas radium-226, potassium-40,thorium-232 and uranium-238occur naturally in theenvironment while others suchas phosphorus-32 or sodium-22are primarily produced innuclear reactors or particleaccelerators. Any materialwhich contains measurableamounts of one or moreradionuclides is referred to asa radioactive material. As anyhandful of soil or plantmaterial will contain somemeasurable amount ofradionuclides, we mustdistinguish between backgroundradioactive materials and man-made or enhanced concentrationsof radioactive materials.

c. Uranium, thorium andtheir progeny, including radiumand radon are NaturallyOccurring Radioactive Materials(NORM). Along with an isotopeof potassium (K-40) these makeup the majority of NORMmaterials and are found in mostall soil and water, and areeven found in significantquantities within the humanbody.

d. Another group ofradionuclides are referred toas transuranics. These aremerely elements with Z numbersgreater than that of uranium(92). All transuranics areradioactive. Transuranics areproduced in spent fuelreprocessing facilities andnuclear weapons detonations.

3-3. Activity.

a. The quantity whichexpresses the degree ofradioactivity or radiationproducing potential of a givenamount of radioactive materialis activity. The activity maybe considered the rate at whicha number of atoms of a materialdisintegrate, or transform fromone isotope to another which isaccompanied by the emission ofradiation. The most commonlyused unit of activity is thecurie (Ci) which was originallydefined as that amount of anyradioactive material whichdisintegrates at the same rateas one gram of pure radium.That is, 3.7 x 1010

disintegrations per second(dps). A millicurie (mCi) =3.7 x 10 dps. A microcurie7

(µCi) = 3.7 x 10 dps. A4

picocurie (pCi) = 3.7 x 10-2

dps.

b . T h e S y s t e m eInternationale (SI) unit ofactivity is the becquerel (Bq)which equals 1 dps. SystemeInternationale units, such asmeters and grams, are in usethroughout the rest of theworld. Only the United Statesstill uses units of curies foractivity.

c. The activity of a givenamount of radioactive materialis not directly related to themass of the material. Forexample, two one-curie sourcescontaining cesium-137 might

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have very different masses,depending upon the relativeproportion of non-radioactiveatoms present in each source.for example, 1 curie of purecesium-137 would weigh 87grams, and 50 billion kilograms(100 million tons) of seawaterwould contain about 1 curie ofCs-137 from fallout.

3-4. Decay Law.

a. The rate at which aquantity of radioactivematerial decays is proportionalto the number of radioactiveatoms present. This can beexpressed by the equation(Eq.):

N=N e Eq. 1o-þt

Where N equals the number ofatoms present at time t, N iso

the initial number ofradioactive atoms present attime 0, þ is the decay constantfor the radionuclide present,(this can be calculated fromthe half-life of the materialas shown below),and e is thebase of the natural logarithms.Table 3-1 indicates half-livesand other characteristics ofseveral common radionuclides.

b. Since activity A isproportional to N, the equationis often expressed as:

A = A e Eq. 2o-þt

Table 3-1. Characteristics of Selected Radionuclides

Radionuclide Half-life (Type and max. energy in MeV)

hydrogen-3 12.3 years þ, 0.0186 carbon-14 5370 years þ, 0.155 phosphorus-32 14.3 days þ, 1.71 sulfur-35 87.2 days þ, 0.167 potassium-40 1.3E09 years þ, 1.310 iodine-125 59.7 days þ/X, 0.035 cesium-137 30.2 years þ/X, 0.51/.662thorium-232 1.4E10 years þ/X, 4.081uranium-238 4.4E09 years þ/X, 4.147americium-241 432 years þ/X, 5.49/.059

þ-alpha particle, þ-beta particle, X-gamma or X-ray

c. Half-life. When halfof the radioactive atoms in agiven quantity of radioactivematerial have decayed, theactivity is also decreased by

half. The time required for theactivity of a quantity of aparticular radionuclide todecrease to half its originalvalue is called the half-life

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Eq. 3

(T ) for the radionuclide. 1/2

d. It can be shown

mathematically that thehalf-life (T ) of a particular1/2

radionuclide is related to thedecay constant (þ) as follows:

Substituting this value of þinto Equation 2, one gets:

e. Example 1: You have 5mCi of phosphorus-32 (T =1/2

14.3 days). How much activitywill remain after 10 days?

A = ?

A = 5 mCio

t = 10 d

þ = .693 14.3 d A = A eo

-þt

A = 3.1 mCi

f. An alternative method

of determining the activity ofa radionuclide remaining aftera given time is through the useof the equation:

f = (½) Eq. 4 n

where f equals the fraction ofthe initial activity remainingafter time t and n equals thenumber of half-lives which haveelapsed. In Example 1 above,

n = t/T1/2

n = 10/14.3

= 0.69

f = (½)0.69

= 0.62

A = fAo

= (0.62)(5)

= 3.10 mCi

Both methods may be used tocalculate activities at a priordate, that is "t" in theequations may be negative.

g. The activity of anyradionuclide is reduced to lessthan 1% after 7 half-lives andless than 0.1% after 10 half-lives.

3-5. Types of IonizingRadiation.

a. Ionizing radiation maybe electromagnetic or may

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consist of high speed subatomicparticles of various masses andcharges.

(1) Alpha Particles.

Certain radionuclides of highatomic mass (for example,,Ra-226, U-238, Pu-239) decay bythe emission of alphaparticles. These are tightlybound units of two neutrons andtwo protons each (a heliumnucleus). Emission of an alphaparticle results in a decreaseof two units of atomic number(Z) and four units of atomicmass (A). Alpha particles areemitted with discrete energiescharacteristic of theparticular transformation fromwhich they originate.

(2) Beta Particles.

A nucleus with a slightlyunstable ratio of neutrons toprotons may decay by changing aneutron into a proton, or aproton into a neutron throughthe emission of either a highspeed electron or positroncalled a beta particle. Thisresults in a net change of oneunit of atomic number (Z), upone for a beta minus and downone for a beta plus. The betaparticles emitted by a specificradionuclide range in energyfrom near zero to up to amaximum value characteristic ofthe particular transformation.

(3) Gamma-rays.

(a) A nucleus which hasdisintegrated is left in anexcited state with more energythan it can contain. Thisexcited nucleus may emit one ormore photons (that is,particles of electromagneticradiation) of discrete energiesto rid itself of this energy.The emission of these gamma-rays does not alter the numberof protons or neutrons in thenucleus but instead has theeffect of moving the nucleusfrom a higher to a lower energystate. Gamma-ray emissionfrequently follows beta decay,alpha decay, and other nucleardecay processes.

(b) X-rays and gamma-raysare electromagnetic radiation,as is visible light. Thefrequencies of X- and gammarays are much higher than thatof visible light and so eachcarries much more energy.Gamma- and X-rays cannot becompletely shielded. They canbe attenuated by shielding butnot stopped completely. A gammaemitting nuclide may yieldmultiple gamma- and X-rays,each with its own discreteenergy. It is possible toidentify a gamma emittingnuclide by its spectrum.

(4) X-rays.

X-rays are also part of theelectromagnetic spectrum andare indistinguishable from

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gamma-rays. The onlydifference is their source(that is, orbital electronsrather than the nucleus). X-rays are emitted with discreteenergies by electrons as theyshift orbits and lose energyfollowing certain types ofnuclear excitement or decayprocesses.

(5) Bremsstrahlungradiation.

When a charged particle passesnear the nucleus of an atom,it deviates from its originalpath and is slowed down by thecoulombic interaction with thenucleus. When this occurs, thecharged particle will emit aphoton to balance the energy.These photons are calledbremsstrahlung radiation.Bremsstrahlung radiation onlybecomes a significant source ofexposure from high energy betaparticles. The amount ofbremsstrahlung radiationemitted is proportional to theZ number of the nucleus thebeta interacted with, and theenergy of the beta particle.

(6) Neutrons.

(a) Neutrons are unchargedparticles released duringfission of heavy atoms(uranium) or released from somenon-radioactive material afterbombardment by alpha particles(americium-beryllium [Am-Be]sources). Because neutrons areuncharged particles, they

travel further in matter. Whenneutrons are sufficientlyslowed down in matter(thermalized) they are absorbedby matter with an accompanyingburst of gamma radiation. Thenature of production of theneutron determines whether itis emitted in a spectrum (as infission) or at a discreteenergy (as from Am-Be sources).

(b) A single radioactivedecay event may generate alarge number of radiations asillustrated in Table 3-2, forexample:

Table 3-2 I-125 Radiations RADIATION ENERGY(keV) DECAY%Gamma 35 6.7 Ka X-ray 27.4 114 Kb X-ray 31 25.6 L X-ray 3.9 12 K Conv. Elec. 3.7 80 L Conv. Elec. 31 11.8 M+ Conv. Elec. 35 2.5 K Auger Elec. 23 20 L Auger Elec. 3-4 160

KeV: kiloelectron volt

3-6. Interaction of RadiationWith Matter.

a. Excitation/Ionization.

The various types of radiation(for example, alpha particles,

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beta particles, and gamma-rays) impart their energy tomatter primarily throughexcitation and ionization oforbital electrons. The term"excitation" is used todescribe an interaction whereelectrons acquire energy from apassing charged particle butare not removed completely fromtheir atom. Excited electronsmay subsequently emit energy inthe form of X-rays during theprocess of returning to a lowerenergy state. The term"ionization" refers to thecomplete removal of an electronfrom an atom following thetransfer of energy from apassing charged particle. Anytype of radiation havingsufficient energy to causeionization is referred to asionizing radiation. Indescribing the intensity ofionization, the term "specificionization" is often used.This is defined as the numberof ion pairs formed per unitpath length for a given type ofradiation.

b. Characteristics ofDifferent Types of IonizingRadiation.

(1) Alpha particles have ahigh specific ionization and arelatively short range. Alphaparticles are massive and carrya double positive charge. Thiscombination allows alphaparticles to carry a largeamount of energy but to easilytransfer that energy and be

stopped. In air, alphaparticles travel only a fewcentimeters, while in tissue,only fractions of a millimeter.For example, an alpha particlecannot penetrate the dead celllayer of human skin.

(2) Beta particles have amuch lower specific ionizationthan alpha particles and aconsiderably longer range. Therelatively energetic beta'sfrom P-32 have a range of 6meters in air or 8 millimetersin tissue. The low-energybeta's from H-3, on the otherhand, are stopped by only 6millimeters of air or 5micrometers of tissue.

(3) Gamma- and X-rays arereferred to as indirectlyionizing radiation since,having no charge, they do notdirectly apply impulses toorbital electrons as do alphaand beta particles. A gamma-ray or X-ray instead proceedsthrough matter until itundergoes a chance interactionwith a particle. If theparticle is an electron, it mayreceive enough energy to beionized whereupon it causesfurther ionization by directinteractions with otherelectrons. The net result isthat indirectly ionizingparticles liberate directlyionizing particles deep insidea medium, much deeper than thedirectly ionizing particlescould reach from the outside.Because gamma rays and X-rays

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undergo only chance encounterswith matter, they do not have afinite range. In other words,a given gamma ray has adefinite probability of passingthrough any medium of anydepth.

(4) Neutrons are alsoindirectly ionizing. Whenstriking massive particlessuch as the nuclei of atoms,the neutron undergoes elasticscattering losing very littleenergy to the target nucleus.But when a neutron strikes anhydrogen nuclei (a singleproton, about the same mass asa neutron) the energy is sharednearly equally between theneutron and the protonresulting in a loss of abouthalf of the neutron's energybefore the interaction. Theproton now is a charged,directly ionizing particlemoving through matter until allof its energy is transferred tothe matter.

3-7. Human Health Effects.

The effects of ionizingradiation described at thelevel of the human organism canbe divided broadly into twocategories: stochastic (effectsthat occur by chance) ordeterministic (non-stochastic)effects (characterized by athreshold dose below whicheffects do not occur).

a. Stochastic Effects.

Stochastic effects are thosethat occur by chance.Stochastic effects caused byionizing radiation consistprimarily of genetic effectsand cancer. As the dose to anindividual increases, theprobability that cancer or agenetic effect will occur alsoincreases. However, at notime, even for high doses, isit certain that cancer orgenetic damage will result.Similarly, for stochasticeffects, there is no thresholddose below which it isrelatively certain that anadverse effect cannot occur.In addition, because stochasticeffects can occur in unexposedindividuals, one can never becertain that the occurrence ofcancer or genetic damage in anexposed individual is due toradiation.

b . D e t e r m i n i s t i c(Non-Stochastic) Effects.

(1) Unlike stochasticeffects, deterministic effectsare characterized by athreshold dose below which theydo not occur. In addition, themagnitude of the effect isdirectly proportional to thesize of the dose. Furthermore,for deterministic effects,there is a clear causalrelationship between radiationexposure and the effect.Examples of deterministiceffects include sterility,erythema (skin reddening), andcataract formation. Each of

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these effects differs from theother in both its thresholddose and in the time over whichthis dose must be received tocause the effect (that is acutevs. chronic exposure).

(2) The range ofdeterministic effects resultingfrom an acute exposure toradiation is collectivelytermed "radiation syndrome."This syndrome may be subdividedas follows:

(a) hemopoietic syndrome -characterized by depression ordestruction of bone marrowactivity with resultant anemiaand susceptibility to infection(whole body dose of about 200rads);

(b) gastrointestinalsyndrome - characterized bydestruction of the intestinalepithelium with resultantnausea, vomiting, and diarrhea(whole body dose of about 1000rads); and

(c) central nervous systemsyndrome - direct damage tonervous system with loss ofconsciousness within minutes(whole body doses in excess of2000 rads).

(3) The LD (that is, dose5O

that would cause death in halfof the exposed population) foracute whole body exposure toradiation in humans is about450 rads.

3-8. Determinants of Dose.

The effect of ionizingradiation upon humans or otherorganisms is directly dependentupon the size of the dosereceived and the rate at whichthe dose is received (forexample, 100 mrem in an hourversus 100 mrem in a year).The dose, in turn, is dependentupon a number of factorsincluding the strength of thesource, the distance from thesource to the affected tissue,and the time over which thetissue is irradiated. Themanner in which these factorsoperate to determine the dosefrom a given exposure differssignificantly for exposureswhich are "external" (that is,resulting from a radiationsource located outside thebody) and those which are"internal" (that is, resultingfrom a radiation source locatedwithin the body).

a. External Exposures.

(1) Exposure to sources ofradiation located outside thebody are of concern primarilyfor sources emitting gamma-rays, X-rays, or high energybeta particles. Externalexposures from radioactivesources which emit alpha orbeta particles with energiesless than 70 keV are notsignificant since theseradiations do not penetrate thedead outer cell layer of theskin.

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(2) As with all radiationexposures, the size of the doseresulting from an externalexposure is a function of:

(a) the strength of thesource;

(b) the distance from thesource to the tissue beingirradiated; and

(c) the duration of theexposure.

In contrast to the situationfor internal exposures,however, these factors can bealtered (either intentionallyor inadvertently) for aparticular external exposuresituation, changing the dosereceived.

(3) The effectiveness of agiven dose of externalradiation in causing biologicaldamage is dependent upon theportion of the body irradiated.For example, because ofdif f e rences in theradiosensitivity of constituenttissues, the hand is far lesslikely to suffer biologicaldamage from a given dose ofradiation than are the gonads.Similarly, a given dose to thewhole body has a greaterpotential for causing adversehealth effects than does thesame dose to only a portion ofthe body.

b. Internal Exposures.

(1) Exposure to ionizingradiation from sources locatedwithin the body are of concernfor sources emitting any andall types of ionizingradiation. Of particularconcern are internally emittedalpha particles which causesignificant damage to tissuewhen depositing their energyalong highly localized paths.

(2) In contrast to thesituation for externalexposures, the source-to-tissuedistance, exposure duration,and source strength cannot bealtered for internal radiationsources. Instead, once aquantity of radioactivematerial is taken up by thebody (for example, byinhalation, ingestion, orabsorption) an individual is"committed" to the dose whichwill result from the quantitieso f t h e p a r t i c u l a rradionuclide(s) involved. Somemedical treatments areavailable to increase excretionrates of certain radionuclidesin some circumstances andthereby reduce the committedeffective dose equivalent.

(3) In general,radionuclides taken up by thebody do not distribute equallythroughout the body's tissues.Often, a radionuclideconcentrates in an organ. Forexample, I-131 and I-125, bothisotopes of iodine, concentratein the thyroid, radium andplutonium in the bone, and

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uranium in the kidney.

(4) The dose committed toa particular organ or portionof the body depends, in part,upon the time over which theseareas of the body areirradiated by the radionuclide.This, in turn, is determined bythe radionuclide's physical andbiological half-lives (that is,the effective half-life). Thebiological half-life of aradionuclide is defined as thetime required for one half of agiven amount of radionuclide tobe removed from the body bynormal biological turnover (inurine, feces, sweat).

3-9. Background Radiation.

a. All individuals arecontinuously exposed toionizing radiation from variousnatural sources. These sourcesinclude cosmic radiation andn a t u r a l l y o c c u r r i n gradionuclides within theenvironment and within thehuman body. The radiationlevels resulting from naturalsources are collectivelyreferred to as "naturalbackground". Naturallyoccurring radioactive material(NORM) can be detected invirtually everything. Naturalpotassium contains about 0.01%potassium-40, a powerful betaemitter with an associatedgamma ray. Uranium, thoriumand their associated decayproducts, which are alsoradioactive, are common trace

elements found in soilsthroughout the world. Naturalbackground and the associateddose it imparts variesconsiderably from one locationto another in the U.S. andranges from 5 to 80microroentgens per hour. It isestimated that the averagetotal effective dose equivalentfrom natural background in theU.S. is about 250mrem/person/year. This doseequivalent is composed of about166 mrem/person/year fromradon, 34 mrem/person/year fromnatural radioactive materialwithin the body, 25mrem/person/year from cosmicr a d i a t i o n , a n d 2 5mrem/person/year fromterrestrial radiation.

b. The primary source ofman-made non-occupationalexposures is medicalirradiation, particularlydiagnostic procedures (forexample, X-ray and nuclearmedicine examinations). Suchprocedures, on average,contribute an additional 100mrem/person/year in the U.S.All other sources of man-made,non-occupational exposures suchas nuclear weapons fallout,nuclear power plant operations,and the use of radiationsources in industry anduniversities contribute anaverage of less than onemrem/person/year in the U.S.

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3-10. Radiation Quantities.

a. Exposure (roentgen). Exposure is a measure of thestrength of a radiation fieldat some point. It is usuallydefined as the amount of charge(that is, sum of all ions ofone sign) produced in a unitmass of air when theinteracting photons arecompletely absorbed in thatmass. The most commonly usedunit of exposure is theroentgen (R) which is definedas that amount of X or gammaradiation which produces 2.58E-4 coulombs per kilogram (C/kg)of dry air. In cases whereexposure is to be expressed asa rate, the unit would beroentgens per hour (R/hr) ormore commonly, milliroentgenper hour (mR/hr). A roentgenrefers only to the ability ofPHOTONS to ionize AIR.Roentgens are very limited intheir use. They apply only tophotons, only in air, and onlywith an energy under 3 mega-electron-volts (MeV). Becauseof their limited use, no newunit in the SI system has beenchosen to replace it.

b. Absorbed Dose (rad).

Whereas exposure is defined forair, the absorbed dose is theamount of energy imparted byradiation to a given mass ofany material. The most commonunit of absorbed dose is therad (Radiation Absorbed Dose)

which is defined as a dose of0.01 joule per kilogram of thematerial in question. Onecommon conversion factor isfrom roentgens (in air) to radsin tissue. An exposure of 1 Rtypically gives an absorbeddose of 0.97 rad to tissue.Absorbed dose may also beexpressed as a rate with unitsof rad/hr or millirad/hr. TheSI unit of absorbed dose is thegray (Gy) which is equal to 1joule/kg which is equal to 100rads.

c. Dose Equivalent (rem).

(1) Although thebiological effects of radiationare dependent upon the absorbeddose, some types of particlesproduce greater effects thanothers for the same amount ofenergy imparted. For example,for equal absorbed doses, alphaparticles may be 20 times asdamaging as beta particles. Inorder to account for thesevariations when describinghuman health risk fromradiation exposure, thequantity, dose equivalent, isused. This is the absorbeddose multiplied by certain"quality" and "modifying"factors (Q) indicative of therelative biological-damagepotential of the particulartype of radiation. The unit ofdose equivalent is the rem(Radiation Equivalent in Man)or, more commonly, millirem.For beta, gamma- or X-rayexposures, the numerical value

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of the rem is essentially equalto that of the rad. The SIUnit of dose equivalent is thesievert (Sv) which is equal to:1 Gy X Q; where Q is thequality factor. Q values arelisted in Table 3-3 (Note thatthere is quite a bit ofdiscrepancy between differentagency's values).

Table 3-3Q Values

Radiation Type NRC ICRU NCRPX & Gamma Rays 1 1 1Beta Particles (Except H) 1 1 13

Tritium Betas 1 2 1Thermal Neutrons 2 - 5Fast Neutrons 10 25 20Alpha particles 20 25 20

(2) Example: An individualworking at a Corps lab with I-125 measures the exposure at awork station as 2 mR/hr. TheNRC licenses and regulates thelab. What is the doseequivalent to a person sittingat the work station for sixhours?

DE = Exposure x 0.97 rad/R x Q

Exposure = Exposure Rate xTime

Q for gamma-radiation = 1

DE = Rate x Time x 0.97 x Q

DE = 2 mR/hr x 6 hr X 0.97rad/R x 1 = 11.64 mrem.

d. Deep Dose Equivalent

(DDE).

(1) The DDE is the dose tothe whole body tissue at 1centimeter (cm) beneath theskin surface from externalradiation. The DDE can beconsidered to be thecontribution to the totaleffective dose equivalent(TEDE) from external radiation.

(2) Example: A worker isexposed to 2 R of penetratinggamma radiation. What ishis/her DDE?

DDE = exposure x 0.97 rad/R x QQ for gamma radiation = 1DDE = 2 R x 0.97 rad/R x 1 =1.94 rem.

e. Effective DoseEquivalent (EDE).

(1) Multiplying the doseequivalent by a weightingfactor that relates to theradiosensitivity of each organand summing these weighted doseequivalents produces theeffective dose equivalent.Weighting Factors are shown inTable 3-4. The EDE is used indosimetry to account fordifferent organs havingdifferent sensitivities toradiation.

Table 3-4 Weighting Factors

Gonads 0.25Breast 0.15Lung 0.12Thyroid 0.03

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Bone 0.03Marrow 0.12Remainder 0.30

(2) Example: A person isexposed to 3 mR/hr of gamma-radiation to the whole body forsix hours. What is theeffective dose equivalent toeach organ and to the wholebody?

EDE = þ (DE x WF) DE = R x Q R = Rate x Time Q for gamma = 1 R = 3 mR/hr x 6 hrs. = 18 mR 18 mR x 0.97 mrad/mR = 17 mrad DE = 17 mrad x 1 = 17 mrem EDE for:Gonads = 17 mrem x 0.25 =4.25 mrem

Breast = 17 mrem x 0.15 = 2.55 mremLung = 17 mrem x 0.12 = 2.04 mremThyroid = 17 mrem x 0.03 =0.51 mrem

Bone = 17 mrem x 0.03 =0.51 mrem

Marrow = 17 mrem x 0.12 =2.04 mrem

Remainder = 17 mrem x 0.30 =5.10 mrem

--------- EDE for whole body: 17 mrem. (note that the weightingfactor for the whole body isone)

f. Committed DoseEquivalent (CDE).

(1) The CDE is the doseequivalent to organs from the

intake of a radionuclide overthe 50-year period followingthe intake. Radioactivematerial inside the body willact according to its chemicalform and be deposited in thebody, emitting radiation overthe entire time they are in thebody. For purposes of doserecording, the entire doseequivalent organs will receiveover the 50-years following theintake of the radionuclides isassigned to the individualduring the year that theradionuclide intake took place.The CDE is usually derived froma table or computer program, asthe value is dependent upon theradionuclide, its chemicalform, the distribution of thatchemical within the body, themass of the organs and thebiological clearance time forthe chemical. Two commondatabases are MIRD and DOSEFACTthat contain CDEs for variousradionuclides. The CDE can becalculated from the data in 10CFR 20 Appendix B, or from theEPA Federal Guidance Report #11if there is only one targetorgan, otherwise the dose mustbe calculated from thecontribution of theradionuclide in every organ tothe organ of interest.

(2) Example: An individualingests 40 microcuries of I-131. What is the CDE? Becausethe dose to the thyroid fromiodine-131 is 100 times greaterthan the dose to any otherorgan we can assume that the

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thyroid is the only organreceiving a significant doseand can use the 10 CFR 20approach, from 10 CFR 20,Appendix B. The non-stochastic(deterministic) Annual Limit ofIntake (ALI) is 30 µCi. A non-stochastic ALI is the activityof a radionuclide that, ifingested or inhaled, will givethe organ a committed doseequivalent of 50 rem.DE/ALI x 50 rem = committeddose equivalent to the organ.40 µCi/30 µCi x 50 rem = 67rem.

(3) An example of the CDEderived from a table ispresented in Table 3-5 forinhalation of Co-60.

g. Committed EffectiveDose Equivalent (CEDE).

(1) Multiplying thecommitted dose equivalent by aweighting factor that relatesto the radiosensitivity of eachorgan and summing theseweighted dose equivalentsproduces the committedeffective dose equivalent. TheCEDE can be considered to bethe contribution from internalradionuclides to the TEDE.

(2) Example: A male workerinhales 10 µCi Co-60. What ishis CEDE?

Using the CDE above for Co-60,and the weighting factorsabove, we get the following:EDE for:

Gonads = 10 µCi x 6.29E+00mrem/µCi x 0.25 = 15.73 mrem

Table 3-5Inhalation Coefficients (H ) in mrem/µCi50,T

Co-60 (T = 5.271 year) Class Y F1 = 5.0E-02 AMAD = 1.0 µm½

organ (H ) organ (H ) 50,T 50,T

-----------------------------------------------------------------Adrenals 1.11E+02 Lungs 1.27E+03Bladder Wall 1.09E+01 Ovaries 1.76E+01Bone surface 4.99E+01 Pancreas 1.17E+02Breast 6.80E+01 Red Marrow 6.36E+01Stomach Wall 1.01E+02 Skin 3.77E+01Small Intestine 2.60E+01 Spleen 9.99E+01Up lg Intestine 3.59E+01 Testes 6.29E+00Lw lg intestine 2.93E+01 Thymus 2.12E+02Kidneys 5.77E+01 Thyroid 5.99E+01Liver 1.23E+02 Uterus 1.70E+01-----------------------------------------------------------------H = 1.33E+02 H = 2.19E+02rem,50 E,50

ICRP 30 ALI = 30 µCi

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Breast= 10 µCi x 6.80E+01mrem/µCi x 0.15 = 102.00 mrem

Lung = 10 µCi x 1.27E+03mrem/µCi x 0.12 = 1524.00 mrem

Thyroid= 10 µCi x 5.99E+01mrem/µCi x 0.03 = 17.97 mrem

Bone = 10 µCi x 4.99E+01mrem/µCi x 0.03 = 14.97 mrem

Marrow = 10 µCi x 6.36E+01mrem/µCi x 0.12 = 76.32 mrem

Remainder = 10 µCi x 1.33E+02mrem/µCi x 0.30 = 399.00 mrem ----------- CEDE for whole body: 2149 mrem

h. Total Effective DoseEquivalent (TEDE).

(1) The sum of the DDE andthe CEDE. Dose from internalradiation is no different fromdose from external radiation.Regulations are designed tolimit TEDE to the whole body to5 rem per year, and to limitthe sum of the DDE and the CDEto any one organ to 50 rem peryear.

(2) Example: The personworking in example d. alsoinhales 10 µCi Co-60 as inexample g. What is his or herTEDE?

TEDE = DDE + CEDEFrom Example d his DDE is 1.74rem = 1,740.00 mremFrom example g his CEDE is 2,149.00 mrem -------------TEDE 3,889.00 mrem

3-11. Biological Effects ofIonizing Radiation.

Biological effects of radiationhave been studied at differentlevels; the effects on cells,the effects on tissues (groupsof cells), the effects onorganisms, and the effects onhumans. Some of the majorpoints are reviewed below.

a. Cellular Effects.

(1) The energy depositedby ionizing radiation as itinteracts with matter mayresult in the breaking ofchemical bonds. If theirradiated matter is livingtissue, such chemical changesmay result in altered structureor function of constituentcells.

(2) Because the cell iscomposed mostly of water, lessthan 20% of the energydeposited by ionizing radiationis absorbed directly bymacromolecules (for example,Deoxyribonucleic Acid (DNA).More than 80% of the energydeposited in the cell isabsorbed by water moleculeswhere it may form highlyreactive free radicals.

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(3) These radicals andtheir products (for example,hydrogen peroxide) may initiatenumerous chemical reactionswhich can result in damage tomacromolecules and/orcorresponding damage to cells.Damage produced within a cellby the radiation inducedformation of free radicals isdescribed as being by indirectaction of radiation.

(4) The cell nucleus isthe major site of radiationdamage leading to cell death.This is due to theimportance

of the DNA within the nucleusin controlling all cellularfunction. Damage to the DNAmolecule may prevent it fromproviding the proper templatefor the production ofadditional DNA or RibonucleicAcid (RNA). In general, it hasbeen found that cellradiosensitivity is directlyproportional to reproductivecapacity and inverselyproportional to the degree ofcell differentiation. Table 3-6 presents a list of cellswhich generally follow thisprinciple.

Table 3-6. List of Cells in Order of Decreasing Radiosensitivity

Veryradiosensitive

Moderatelyradiosensitive

Relativelyradioresistant

Vegetativeintermitotic cells,mature lymphocytes,erythroblasts andspermatogonia,basal cells,endothelial cells.

Blood vessels andinterconnective tissue, osteoblasts,granulocytes andosteocytes, sperm erythrocytes.

Fixed postmitoticcells, fibrocytes,chondrocytes,muscle and nervecells.

(5) The considerablev a r i a t i o n i n t h eradiosensitivities of varioustissues is due, in part, to thedif f e rences in thesensitivities of the cells thatcompose the tissues. Alsoimportant in determining tissuesensitivity are such factors asthe state of nourishment of thecells, interactions betweenvarious cell types within thetissue, and the ability of thetissue to repair itself.

(6) The relatively highradiosensitivity of tissuesconsisting of undifferentiated,rapidly dividing cells suggestthat, at the level of the humanorganism, a greater potentialexists for damage to the fetusor young child than to an adultfor a given dose. This has, infact, been observed in the formof increased birth defectsfollowing irradiation of thefetus and an increasedincidence of certain cancers in

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individuals who were irradiatedas children.

3-12. Ways to MinimizeExposure.

a. There are three factorsused to minimize externalexposure to radiation; time,distance, and shielding.Projects involving the use ofradioactive material orradiation generating devicesneed to be designed so as tominimize exposure to externalradiation, and accomplish theproject. A proper balance ofways to minimize exposure andthe needs of the project needto be considered from theearliest design stages. Forexample, if a lead apronprotects a worker from theradiation, but slows him or herdown so that it requires threetimes as many hours to completethe job, the exposure is notminimized. Additionally,placing a worker in fullprotective equipment andsubjecting the worker to theaccompanying physical stressesto prevent a total exposure ofa few millirems does not servethe needs of the project or ofthe worker.

(1) Time.

Dose is directly proportionalto the time a individual isexposed to the radiation. Lesstime of exposure means lessdose. Time spent around asource of radiation can be

minimized by good design,planning the operation,performing dry-runs to practicethe operation, and contentiouswork practices.

(2) Distance.

Dose is inversely proportionalto the distance from theradiation source. The furtheraway, the less dose received.Dose is related to distance bythe equation:

Where: I = Intensity at Distance 1, 1

D = Distance 1, 1

I = Intensity at Distance 2,2

D = Distance 2.2

Doubling the distance from asource will quarter the dose(see Figure 3-1).

Figure 3-1.

Distance from a radiationsource can be maximized by good

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design, planning the operation,using extended handling toolsor remote handling tools asn e c e s s a r y , a n d b yconscienscious work practices.

(3) Shielding

(a) Dose can be reduced bythe use of shielding. Virtuallyany material will shieldagainst radiation but itsshielding effectiveness dependson many factors. These factorsinclude material density,material thickness and type,the radiation energy, and thegeometry of the radiation beingshielded. Consult a qualifiedexpert to determine shieldingrequirements.

Cost considerations often comeinto play. The shieldingprovided by a few centimetersof lead may be equaled by theshielding provided by a fewinches of concrete, and theprice may be lower for theconcrete. Table 3-7 lists half-value layers for severalmaterials at different gammaray energies.

(b) Shielding can be usedto reduce dose by placingradiation sources in shieldswhen not in use, placingshielding between the sourceand yourself, good design ofthe operation, and contentiouswork practices.

Table 3-7Half-value layers (cm) for gamma rays

-----------------------------------------------------------------E (MeV) Lead Concrete Water Iron Airþ

-----------------------------------------------------------------0.1 0.4 3.0 7.0 0.3 36220.5 0.7 7.0 15.0 1.6 61751.0 1.2 8.5 17.0 2.0 84281.5 1.3 10.0 18.5 2.2 10389-----------------------------------------------------------------

b. Personnel ProtectiveEquipment (PPE).

PPE is a last resort method forradiation exposure control.When engineering controls usingtime, distance, shielding, dustsuppression, or contaminationcontrol cannot adequately lowerthe exposure to ionizingradiation or radioactivematerial, PPE may be used. PPE

may include such items as:

(1) full-face, air-purifying respirators (APRs)with appropriate cartridges;

(2) self-containedbreathing apparatus (SCBA);

(3) supplied air; and

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(4) shielded gloves,aprons, and other clothing.

c. Selection of PPE isbased on unique conditions ateach job site. The PPE may berequired in the followingcircumstances:

(1) when handlingcontaminated materials withremovable contamination;

(2) when working inc o n t a m i n a t i o n , h i g hcontamination, and AirborneRadioactivity Areas; or

(3) when required by anNRC license or ARA.

d. Specific PPErequirements for each job siteshould be obtained from USACEor a USACE contractor HP orindustrial hygienist.Respirator use must meet therequirements of 29 CFR 1910 or1926 and USACE respiratoryprotection requirements of EM385-1-1. The respiratoryprotection factors fordifferent types of respiratorsare listed in 10 CFR 20,Appendix A.

*NOTE* Half-face APRs will notbe used for any USACE workinvolving radioactive material,unless there is no otherpractical solution. Anyspecial use of half-face APRswill first be approved by theRPO.

e. Cartridges forradionuclides must be selectedwith consideration for theradionuclide's chemical form.Respirator filters approved foruse under 30 CFR 11 may stillbe used until July 1998. Bythat time, all respiratorcartridges must be classifiedaccording to the new NationalInstitute of OccupationalSafety and Health (NIOSH)modular approach described in42 CFR 84. With the newmodular approach to respiratorcertification, cartridgesapproved by NIOSH, will nolonger be labeled fordusts/mists/fumes/radioactivedusts. The color coding hasalso changed. Dust/mist/fumefilters will now be labeled asN95, N99, N100, R95, R99, R100,P95, P99, and P100. The numberrelates to the filteringefficiency, and the letterrelates to the type of aerosol,with P100 being the mostprotective over the widestrange of aerosol types.Dust/mist and dust/mist/fumecartridges do not provide anyprotection against radioactivevapors or radioactive noblegases. Consider the use ofcombination cartridges tocontrol dust and vapors, andactivated charcoal cartridgesto control noble gasses. Whenselecting APRs, consider thebuildup of radioactive materialin the cartridges. A highconcentration of gammaradiation-emitting particles orvapor in cartridges may produce

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a radiation field positionedvery close to the face andchest of the person wearing theAPR.

f. Any PPE will slow downthe working speed of personnel,and extend the time needed forentry and exit. The increasein dose due to the increasedtime in the radiation fieldmust be weighed against theradiation dose reduction causedby the use of PPE. The use ofwhole body personal protectiveequipment, particularly theimpermeable type can cause heatstress problems. A heat stressmonitoring program shall beimplemented to evaluate andcontrol heat stress hazardswhenever PPE is used.

3-13. Standing OperatingProcedures.

Where a project or operationuses radiation in a method thatis amenable to written standingoperating procedures (SOPs),the RPO overseeing theoperations shall assist in thepreparation of SOPs. Mostmanufacturers of instrumentsand articles containingradioactive material or thatgenerate ionizing radiation,include SOPs in their operatingmanuals. The RPO shall reviewthese SOPs and ensure that theymeet USACE safety guidelinesoutlined in this manual and therequirements of ER 385-1-80 andEM 385-1-1 before use.

3-14. Monitoring and SurveyingEquipment.

a. Anytime personnel areworking with radioactivematerial or radiationgenerating devices, radiationmonitoring procedures will beused. Equipment needs to beselected that can detect theradiation or radiations inquestion. Table 3-8 is ageneral guide to types ofdetectors and the range andtypes of radiations theydetect. Some radiations areextremely difficult to detectin the field. Weak betaemitters such as tritium(maximum beta energy of 18.6kilo-electron volts (keV) andweak gamma emitters such asiodine-125 present monitoringproblems. Prior to workinvolving radioactivematerials, consult the RPO andHP to select appropriateinstruments and procedures fort h e d e t e c t i o n a n dquantification of the specificradiation in question.

b. Radiation MonitoringInstruments.

(1) Gas-filled Detectors.

Gas-filled detectors consist ofa gas-filled chamber with avoltage applied such that acentral wire becomes the anodeand the chamber wall thecathode. Any ion pairsproduced by radiationinteracting with the chamber

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move to the electrodes wherethey are collected to form anelectronic pulse which can bemeasured and quantified.Depending upon the voltageapplied to the chamber, thedetector may be considered anionization chamber, aproportional counter or aGeiger-Muller (GM) detector.

(a) An ionization chamberis a gas-filled chambercontaining an anode and acathode. As radiation passesthrough the gas it ionizes someof the gas molecules. Theseion pairs are attracted to theanode and cathode and create anelectrical pulse. The pulsesare counted and integrated anddisplayed on the meter face inroentgens per hour. Because ofits design, an ionizationchamber has a very linearresponse to radiations ofdifferent energies. For thisreason, an ionization chamberis the preferred instrument forquantifying personnel externalradiation exposures.

(b) Because of itsversatility and dependability,the GM detector is the mostwidely used portable surveyinstrument. A GM detector witha thin window can detect alpha,beta and gamma radiation. Itis particularly sensitive tomedium-to-high energy betaparticles (for example, as fromP-32) and X-and gamma-rays aswell. The GM detector isfairly insensitive to low

energy X or gamma rays; that isbelow 50 keV, to low energybeta particles such as thoseemitted by S-35 and C-14, andcannot detect the weak betasfrom H-3 at all. Unlike theionization chamber, the GMdetector does not actually"measure" exposure rate. Itinstead "detects" the number ofparticles interacting in itssensitive volume per unit time.The GM should thus read-out incounts per minute (cpm)although it can be calibratedto approximate mR/hr forcertain situations. With theseadvantages and limitations aGeiger-Muller detector on arugged survey meter is theinstrument of choice forinitial entry and survey ofradiation sources andradioactive contamination inthe field.

(2) ScintillationDetectors.

(a) Scintillationdetectors are based upon theuse of various phosphors (orscintillators) which emit lightin proportion to the quantityand energy of the radiationthey absorb. The light flashesare converted to photoelectrons which are multipliedin a series of diodes (that is,a photomultiplier) to produce alarge electrical pulse.Because the light output andresultant electrical pulse froma scintillator is proportionalto the amount of energy

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deposited by the radiation,scintillators are useful inidentifying the amount ofspecific radionuclides present(that is, scintillationspectrometry).

(b) Portable scintillationdetectors are widely used forconducting various types ofradiation surveys. Ofparticular use to workersworking with low energy gammaradiation, as from radioiodine,is the thin crystal sodiumiodide (NaI) detector which iscapable of detecting theemissions from I-125 withefficiencies nearing 20% (a GMdetector is less than 1%efficient for I-125).

c. Assaying Instruments.

(1) The most common meansof quantifying the presence ofbeta-emitting radionuclides isthrough the use of liquidscintillation counting. Inthese systems, the sample andphosphor are combined in asolvent within the countingvial. The vial is then loweredinto a well between twophotomultiplier tubes forcounting.

(2) Solid scintillationdetectors are particularlyuseful in identifying andquantifying gamma-emittingradionuclides. The common gammawell-counter employs a large(for example, 2" x 2" or 3" x3") crystal of NaI within alead shielded well. The samplevial is lowered directly into ahollow chamber within thecrystal for counting. Suchsystems are extremely sensitivebut do not have the resolutionof more recently developedsemiconductor counting systems,such as high-purity germaniumdetectors.

d. Neutron detectors,sometimes called 'neutronballs' or 'rem balls' are usedfor detection of neutrons.Neutron detectors use ahydrogenous moderator to slowdown the neutrons which willallow the neutrons to interactwith charged particles. Thesecharged particles then aredetected using a conventionalradiation detector. Borontrifluoride (BF ) is a common3

detector gas used for neutrondetection.

e. Semiconductor diodedetectors or solid state

Table 3-8Radiation Detection Instruments

Detector type RadiationDetected

DetectionLimit

Comments

GM-thick walled þ >50 keV 100 dpm Limited use.

GM-thin window ß >35 keVþ >35 keV

100 dpm Good for detectingcontamination, not goodfor quantifying.

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Detector type RadiationDetected

DetectionLimit

Comments

3-24

NaI- 2" x 2"crystal

þ >50 keV 500 dpm Good for detection andquantification.

NaI-thincrystal

ß >50 keVþ >25 keV

500 dpm Good for detecting low-energy gamma radiation.

IonizationChamber

ß >50 keVþ >50 keV

0.2 mR/hr Most accurate forexposure measurement.

PressurizedIonizationChamber

þ >50 keV .01 mR/hr Good for environmentalsurveys.

Micro R meter þ >50 keV .01 mR/hr Good for environmentalsurveys.

HPGe þ >40 keV variable Lab equipment, canquantify trace amounts.Field models available.

LiquidScintillation

þ, ß, þ variable Lab equipment, canquantify trace amounts.Field models available.

GasProportional

þ, ß, þ variable Lab equipment, canquantify trace amountsfield models available.

detectors use a solid materialwith a charge applied to it todetect the energy deposited byradiation. These detectors canbe designed to provide gooddetection of most allradiation, but particular typesof radiation and energy ranges,each call for a differentconfiguration.

f. One type of solid statedetector that is finding

widespread use is the highpurity germanium detector(HPGe). The HPGe, like itspredecessor the germanium-lithium (GE(Li)) detector, hasexcellent energy resolution andis commonly used inlaboratories for identificationand quantification of gammaemitting radionuclides. Aprimary drawback of the HPGedetector is the requirement tosupercool the detector. This

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is done by attaching a Dewarflask containing liquidnitrogen to the detector. HPGesystems are being made that arefield portable, using smallDewar flasks and laptopcomputers, and can providelaboratory quality analysis inthe field.

g. Energy proportionaldetectors such as scintillationdetectors, semiconductor diodedetectors and HPGe detectorsare often coupled with a multi-channel analyzer (MCA) to allowfor determination of the energyof the radiation detected, andthrough reference, to determinethe radioisotope that emittedthe radiation and the quantityof that isotope in the samplemeasured. Most modern MCAs areused in conjunction withcomputers which process theinformation, contain thelibrary of radionuclidesreferenced by energy ofradiation, and display softwarefor digital and graphic output.

h. Instrument Calibration.

(1) Radiation surveymeters are calibrated with aradioactive source and anelectronic pulser. When anelectronic calibration isperformed, the instrument ischecked for response to aradioactive source. In mostsituations, survey meters mustbe calibrated at least annuallyand after servicing. (Batterychanges are not considered

"servicing".)

(2) Survey meters will befunction tested with a checksource or other dedicatedsource before each use. If thesurvey meter is not respondingproperly, it may not be usedfor surveys until it isrepaired. There is no need tokeep a record of the functionchecks, but a record must bekept of the discovery of theimproper response and theservice of the meter to correctthe problem, as well as of therecalibration of the meter.

I. Quality Control.

Q u a l i t y control ofinstrumentation is essential ina radiation protection program.All instruments used formonitoring safety and healthshould be subjected to aquality control (QC) program.Two tracking/trending methodsare commonly used in instrumentQC. The general principle isapplicable to both field andlab instruments. The twomethods are background trendingand check source trending.

(1) Background trending isdone by plotting the dailybackground reading versus dayssince last calibration.Background trending canindicate when instrument probesbecome contaminated, by showinga rise in the background rate.Care must be taken in measuringthe background daily to assure

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that the instrument is inapproximately the same locationand that the location iscontaminant free.

(2) Check-source trackingis a method of assuring thatthe instrument is respondingproperly, and remaining incalibration. Check-sourcetracking is performed byplotting a daily check source

reading of a dedicated checksource against the days sincecalibration. Check-sourcetracking can indicate damage tothe instrument or probe,variance of the electronics orchanges in the meter response.Figure 3-2 is an example ofbackground tracking and check-source tracking.

x-background count

Figure 3-2

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Chapter 4. Licensing.

4-1. Overview of RegulatoryAgencies.

a. Nuclear RegulatoryCommission (NRC).

(1) The Atomic Energy Actof 1954 charges the NRC withthe responsibility of writingand enforcing regulationsconcerning the use ofradioactive material. Alicense is required forpossession of source, byproductor special nuclear material andlicense holders are inspectedby NRC to determine ifregulations are being followedby the licensee. If serious orrepeated violations occur, alicense may be revoked and ther a d i o a c t i v e m a t e r i a lconfiscated. Table 4-1 listsNRC regional offices, NRC Form3, attached at Appendix H,indicates what NRC regionstates fall under.

(2) Although the NRC isthe federal agency responsiblefor adopting and enforcingrules and regulations thatapply to users of radioactivematerial, broad administrativeresponsibilities have beentransferred to some stategovernments. In 1959 the NRCwas permitted to makeagreements with those statesthat could operate a suitableradiological health program forthe radioactive material usersin their states. States that

have such agreements with theNRC are called AgreementStates. Table 4-2 lists theAgreement States and eachstate's radiological healthprogram office and emergencyphone numbers.

b. Agreement States.

Agreement states have their ownstate regulations and theyprovide personnel to licenseand inspect users ofradioactive material.Agreement state regulationsmust be as stringent as NRCregulations and, usually, aremore stringent. The primarydifference in most Agreementstate regulations is theinclusion of NORM and Naturallyoccurring and Acceleratorproduced Radioactive Material(NARM) materials (such asradium, thorium, and cobalt-57)as well as source, byproductand special nuclear material asregulated materials. The NRCdoes not regulate NORM or NARM(only source, byproduct, andspecial nuclear material).Agreement states do not issuelicenses to Federal agencies,including the US Army; only theNRC may do so.

c . E n v i r o n m e n t a lProtection Agency (EPA).

The Atomic Energy Act andReorganization Plan No. 3authorized the EPA to establish

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standards to protect humanhealth and the environment fromthe effects of radiation. TheEPA does not licenseradioactive materials, butregulates their release to theenvironment and the exposure ofthe public to radiation.

d. Occupational Safety andHealth Administration (OSHA). OSHA is authorized to protectworker health and safety. OSHAdoes not license radioactivematerials, but regulates theiruse in the workplace. Toprotect workers from radiation,OSHA, in 1984, adopted the NRCregulations specified in 10 CFR20, as it stood in 1984. 10 CFR20 was amended by the NRC in1994. Consequently, there aretwo sets of regulationsgoverning Authorized Users’Assistants with NRC licensablematerials; the NRC regulationsand OSHA regulations. This isexplained more thoroughly inChapter 5; Dose Limits andALARA.

4-2. Types of NRC RadioactiveMaterial Licenses. NuclearRegulatory Commission licensesfor radioactive material are oftwo types: general andspecific.

a. General Licenses.

(1) NRC general licensesare provided in 10 CFR 31 andare effective withoutsubmitting an application and

without receiving a licensingdocument. Generally licenseddevices usually contain littleactivity and pose minimal riskto the user. Devices which maybe generally licensed include:static eliminators, somecalibration sources, somemeasuring, gauging andcontrolling devices and self-luminous exit signs. Generallylicensed material stillrequires compliance with 10 CFR19 and 10 CFR 20 requirementsfor worker instructions andnotices, and radiationprotection standards.Additionally, for manygenerally licensed items, thereare requirements for semi-annual leak testing andinventories, as well asprohibitions on transfer ordisposal except for return tothe manufacturer or transfer tothe holder of a specificlicense for that radioactiveitem.

(2) Example: ABC Co. has aspecific license to manufactureand to distribute a gaschromatograph (GC) containing a50 mCi Ni-63 sealed source togeneral licensees. A USACE lab(the general licensee) maypurchase the GC withoutapplying for an NRC specificlicense. In the instructionmanual for the GC areprocedures for performing leaktests on the source at 6- monthintervals, and keeping awritten inventory of the deviceupdated at 6-month intervals.

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Additionally, the manualincludes a statement that theGC may not be transferred orsold to anyone who does nothave a specific license topossess 50 mCi of Ni-63, andthat the GC can only bedisposed of by shipping it backto the manufacturer.

b. Specific Licenses.

(1) Specific licensesrequire the submission of anapplication (either to the NRCor an Agreement State dependingupon who has jurisdiction) andthe issuance of licensingdocuments from the regulatoryagency. It is illegal totransfer (sell or give)licensed radioactive materialto another person orinstitution unless therecipient has a license topossess the material.Consequently, radionuclidesupply companies requireinformation about a customer’slicense before they will fillan order. Devices which may bespecifically licensed include:g a s c h r o m a t o g r a p h s ,moisture/density gauges, andindustrial radiography cameras.

(2) Example: A districthas a specific license topossess and use up to 100 mCiof Ni-63 in sealed sources. Thedistrict may have two 50 mCisources at one time.Additionally, the specificlicense may contain conditionssuch as:

The sealed sources will beleak tested at 3-monthintervals.

The source shall be used onlyby persons who have completedtraining as described in thelicense application.

An example of an NRCradioactive material license isincluded at Appendix H.

c. Exempt Quantities.

(1) A list of exemptquantities, that is, the amountof a particular radionuclidethat can be obtained without ageneral or specific license canbe found in 10 CFR 30.71,Schedule B. These NRCregulations also list exemptconcentrations, that is, theconcentration of a particularradionuclide in a product thatcan be obtained without ageneral or specific license.Additionally, NRC and AgreementState regulations contain alisting of exempt items, thatis, items containingradioactive material that canbe obtained without a generalor specific license. If youare unsure of the licensingrequirements for a device youwish to use, contact theCommand RPO.

(2) *NOTE*: As previouslymentioned, there is someradioactive material that isnot regulated by the NRC, but is regulated by Agreement

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States. Most Department ofDefense (DOD) sites areexclusive Federal property andso are regulated by the NRC,but some bases and someportions of bases may be stateproperty and may be regulatedby the state. Always check todetermine if the site you areon is Agreement Stateregulated. This is normallydone through the Command RealEstate function and the Officeof Counsel.

4-3. 'Storage Only' Licensing.

The NRC allows licensedradioactive material that isnot being used to be licensedfor storage only. This methodof licensing is less expensivethan a possession and uselicense. The sealed sourcewipe testing requirements aregreatly reduced (usually, onceper 10 years, prior to storage,and when removed from storage).The license may require a semi-annual inventory of allradioactive material.

4-4. Radiation GeneratingDevices.

The NRC does not licenseradiation generating (X-ray)devices since they do notcontain radioactive material.Most states, however, requireregistration and/or licensingof radiation generatingdevices. States do not haveauthority to regulate devicesused only on exclusive Federal

jurisdiction facilities, butmany states request that theybe notified of all radioactivematerials and devices locatedwithin their boundary.Facilities located on non-exclusive federal jurisdiction,may be subject to stateregulation. USACE requiresthat most ionizing radiationgenerating devices have an ARA(see paragraph 4-6). Table 4-2lists the state radiologicalhealth program offices tocontact for registration and/orlicensing of radiationgenerating devices.

4-5. Reciprocity Requirements.

a. The NRC and AgreementStates reciprocally recognizeeach other’s radioactivematerial licenses. That is, anAgreement State licensedcompany can perform work in NRCjurisdiction under thecompany’s Agreement Statelicense. Likewise, an NRClicensed company can performwork in an Agreement State’sjurisdiction under thecompany’s NRC license.

b. When a state-licensedcontractor desires to performwork in an “NRC-state,” thecontractor must first begranted reciprocity by the NRC.The contractor must provide theNRC with a copy of its stateradioactive material licenseand inform the NRC of its workintentions using NRC Form 241.There is a fee for filing NRC

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Form 241 which may range from$200.00 to $1000.00 or moredepending on the type oflicense and work to beperformed.

c. When a state-licensedcontractor desires to work inanother Agreement State, thecontractor must notify theAgreement State using theappropriate state form.

d. An NRC licensedcontractor performing work on asite under an Agreement State'sjurisdiction must notify theAgreement State using theappropriate state form. SomeAgreement States also charge afee for reciprocity.

4-6. Army RadiationAuthorization (ARA).

a. ARAs are issued byMajor Army Commands (MACOM)(including the Corps ofEngineers). An ARA is requiredfor a USACE Command to receive,possess, use, or transferradioactive material that isnot licensed by the NRC, thatis, NORM or NARM material or anionizing radiation generatingdevice. An ARA is not requiredfor radioactive material thatis covered by another MACOM’ssimilar authorization.

b. An ARA is not requiredfor:

(1) NRC license exempt orgenerally licensed materials,

(2) less than 1.0microcurie of NORM or NARM,

(3) less than 0.1microcurie of radium-226,

(4) electron tubescontaining less than 10 µCi(370 kBq) of any NARMradioisotope,

(5) machine-producedionizing radiation sources notcapable of producing a high orvery high radiation area, and

(6) Army nuclear reactorsand Army reactor-produced RAMthat remains at the reactorsite. The Army Reactor Officeissues Army reactor permits forthese sources (see AR 50-7).

4-7. Army Radiation Permits(ARP) and Other ServiceInstallation Permits.

a. An ARP is required fora non-Army agency (includingcivilian contractors) to use,store, or possess ionizingradiation sources on an Armyinstallation, facility, orproject, or at a U.S. ArmyReserve Center. Non-US AirForce (USAF) organizations onUSAF property are required toobtain a USAF permit for use ofNRC licensed material, NORM orNARM, or radiation generatingdevices. Concurrence of the AirForce or Navy installationcommander, and/or RPO isrequired to obtain a basepermit. “Ionizing radiation

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source” means any source that,if held or owned by an Armyagency, would require a generalor specific NRC license or anARA.

b. The non-Army applicantwill apply by letter withsupporting documentationthrough the appropriate tenantcommander to the installationcommander.

c. The ARP applicationwill specify start and stopdates for the ARP and describefor what uses the applicantneeds the ARP. Theinstallation commander willapprove the application only ifthe applicant provides evidenceto show that one of thefollowing is true:

(1) The applicantpossesses a valid NRC licenseor Department of Energy (DOE)radiological work permit thatallows the applicant to use thesource as specified in the ARPapplication.

(2) The applicantpossesses a valid agreementstate license that allows theapplicant to use RAM asspecified in the ARPapplication, and the applicanthas filed NRC Form-241, Reportof Proposed Activities in Non-Agreement States,(attached atAppendix H) with the NRC inaccordance with 10 CFR 150.20.An ARP issued under thesecircumstances will be valid for

no more than 180 days in anycalendar year.

(3) For NARM and machine-produced ionizing radiationsources, the applicant has anappropriate state authorizationthat allows the applicant touse the source as specified inthe ARP application or has inplace a radiation protectionprogram that complies with Armyregulations.

(4) For overseasinstallations, the applicanthas an appropriate host-nationauthorization as necessary thatallows the applicant to use thesource as specified in the ARPapplication and has in place aradiation protection programthat complies with Armyregulations.

d. All ARPs will requireapplicants to remove allpermitted sources from Armyproperty by the end of thepermitted time.

e. Disposal of RAM bynon-Army agencies on Armyproperty is prohibited.However, the installationcommander may authorizeradioactive releases to theatmosphere or to the sanitarysewerage system that are incompliance with all applicableFederal, DOD, and Armyregulations.

f. *NOTE* Moisture/densitygauges, X-ray fluorescence

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4-7

analyzers, and other similardevices require an Army or USAFradiation permit or exemption.

g. *NOTE* Any ARP shouldbe written to allow sufficientflexibility and be as genericin nature as is possible. Oncea permit is approved, thedetails listed MUST be adheredto with no variations allowed.

h. Installation permitsneed to be applied for at least45 days prior to the start ofthe intended use of thematerials and must be securedbefore radioactive material arebrought onto a base.

I. An NRC licensed companymust notify the RPO beforebringing radioactive materialonto a Navy base. A statelicensed company must notifythe RPO and, provide the RPOwith an NRC Form 241 and a copyof the company's stateradioactive material licensebefore bringing radioactivematerial onto the Navy base.

4-8. Applying for an NRCLicense.

If it is determined that aCommand needs to ownradioactive material, thefollowing steps should befollowed:

a. Check with the CO toensure that the Command willsupport the license and all theaccompanying costs and

responsibilities.

b. Find the source offunding for paying licensing,maintenance and training costs.The license alone will costbetween $500 and $4000 peryear. Maintaining and meetingthe license conditions willdepend on the type and extentof the license and can easilyreach $2000 a year. AuthorizedUsers, Authorized Users’Assistants, RPOs, etc. willrequire initial and annualrefresher training.

c. Contact the RPSO andcoordinate the licensing.

d. Obtain a copy of theNRC Form 313 “Application forByproduct Material Usage”(attached at Appendix H). Alsoobtain the appropriateregulatory guide (this willdepend on what radioactivematerial you desire and yourintended use). The regulatoryguide will provide good step-by-step instructions forfilling out the form.

e. An example licenseapplication is included atAppendix H. Note that theapplication will include a copyof the Command’s RadiationProtection Program, and thatthe license will include acondition (condition #19 in theexample at Appendix H) statingthat the application and allaccompanying documentation willbecome a part of the license.

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Everything that the applicantcommits to in the applicationand subsequent correspondencewill be binding in the license.Some tips which may helpcomplete the form are asfollows:

(1) In Item 5a, list eachradionuclide that will be used.

(2) In Item 5b, if usingsealed sources, the chemicaland/or physical form is “sealeds o u r c e . ” L i s t t h emanufacturer’s name and themodel number of each source.Do not give serial numbers;allow flexibility.

(3) In Item 5c, give themaximum amount of eachradionuclide that will bepossessed at any given time,including all material instorage and waste.

(4) In Item 6, describethe uses in very broad terms.For example: “To be used inTroxler Model 3440 gauge tomeasure soil parameters attemporary job locations withinthe United States.”

(5) In Item 7, list nomore than one individual, and,if necessary, one alternate. The individual(s) must meet thetraining requirements describedin Chapter 2.

(6) In Item 9, be surethat the instruments listedwill detect the type of

radiation emitted by theradionuclides listed. Include adiagram of the work site andthe radioactive materialstorage location when it is notin use.

(7) In Item 10, eachlicensee is required to have awritten, site-specific,Radiation Protection Program.One method of developing thisprogram would be to lift theapplicable sections of thisguidance and incorporate thosesections into a manual, addingsite specific emergency plans,points of contact and personnellists.

(8) In Item 11, for sealedsources, state that "No wastewill be generated. Sealedsources will be returned to themanufacturer for disposal.” Ifusing unsealed sources,coordinate with an HP or theRPO to determine a wastedisposal plan.

(9) Photocopy and keep acopy of the application and allsubmittals as these documentswill probably be “tied down” onthe license. When a documentis “tied down,” it isspecifically identified on thelicense and the regulatoryagency can inspect against it,that is, the applicant mustabide by all commitments madein those documents.

(10) Submit theapplication and any license fee

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to the RPSO.

(11) The RPSO will reviewthe application, edit asneeded, and forward theapplication and fee to the NRCin the appropriate region.

(12) Radioactive materialmay not be ordered until theapplicant has a copy of theradioactive material license inhand.

4-9. Applying for an ARA.

a. If it is determinedthat an activity needs NORM,NARM or an ionizing radiationgenerating device, thefollowing steps should befollowed:

(1) Check with the CO toensure that the unit willsupport the permit and all theaccompanying costs andresponsibilities.

(2) Find the source offunding for paying maintenanceand training costs. All usersof the radioactive materialwill require initial and annualrefresher training.

(3) Contact the RPSO andcoordinate the licensing.

(4) Obtain DA Form 3337"Application for Department oft h e Army RadiationAuthorization or Permit” and"Instructions for preparing DAForm 3337" from your local

forms manager. Theinstructions are self-explanatory. The tips inparagraph 4-8, “Applying for anNRC License” apply equally toArmy permits. Copies areattached at Appendix H.

b. The application for anARA is made by submitting DAForm 3337 to the USACE RPSO.The Form does not get sent tothe address listed in the“Instructions for preparing DAForm 3337”. The applicationwill include a list of all NRClicenses and other ARAs held bythe Command. Renewals oramendments will be submitted inthe same manner as an originalapplication. Requests shouldbe submitted at least 120 daysprior to expiration date. Arenewal request received priorto the expiration date isconsidered active until therenewal approval is received.

4-10. Amendment Requests.

a. An amendment to an NRCor Agreement State radioactivematerial license or an ARA isnecessary anytime:

( 1 ) a d d i t i o n a lradionuclides or radioactivematerial of another chemical orphysical form is desired;

(2) the use of radioactivematerial changes from thecurrently authorized use;

(3) the Radiation

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Protection Program or wastedisposal method will changesubstantially; and

(4) if the RPO is listedon the license by name, and anew RPO is then appointed.

b. Amendment requests aresubmitted in the same way asnew licenses or permits.Licensees may not procurerequested radionuclides orquantities until the amendmenthas been approved.

4-11. Renewing Licenses orARA’s.

a. Radioactive materiallicenses are issued for fiveyears and must be renewed tostay in effect. The NRC willsend a notice (approximately 90days in advance) stating thatthe license is about to expire.It will also send the necessaryforms to renew the license.License renewal requests mustbe submitted to the RPSO forreview and forwarding at least60 days prior to the expirationdate. If sufficient time isnot available to prepare therenewal request, the applicantmay ask the NRC (in writing) toextend the expiration date forup to 90 days.

b. License renewalrequests that are received bythe NRC thirty days prior tothe expiration date will bedeemed “timely filed.” The NRCwill send a “timely filed

letter”. With this letter, thelicensee may continue operatingunder the old license untilthey issue the renewed license.If material is needed, thesupplier may ask to see this“timely filed letter.”

c. If a license is notrenewed in a timely manner, allradionuclide use must cease onthe date of expiration. Atthis point, the NRC may requiresubmission of a new licenseapplication.

d. ARAs also must berenewed every five years. TheRPSO will send a notice,approximately 90 days inadvance, to permit holdersinforming them that their ARAis about to expire.

4-12. Transfer of RadioactiveMaterials.

a. Should a Command wishto transfer radioactivematerial to another Command, aRequest for Authorization toTransfer Radioactive Materials(ENG Form 4790-R) must becompleted and submitted to theRPSO through command channels.A copy of ENG Form 4790-R isincluded at Appendix H.

b. The RPSO will reviewthe request, and the receivingCommand’s radioactive licenseor ARA to ensure that allregulations, license or ARAconditions are met, thenapprove the transfer.

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c. When the Commandreceives authorization totransfer the materials, the RPOshall ensure that theradioactive materials arepackaged and shipped accordingto DOT and NRC regulations (seeChapter 8).

d. The RPO shall prepare aCertificate of Disposal ofMaterials (NRC Form 314) andforward the original to theRPSO. The RPSO will review thecertificate and record thetransfer in the USACE radio-active materials inventory. Ifthe radioactive materials arelisted on an NRC license, theRPSO will submit thecertificate to the NRC.

4-13. Terminating a RadioactiveMaterial License or ARA.

a. When a Command nolonger wishes to possess or uselicensed or permittedradioactive material, thelicense or ARA must beterminated. License or ARAtermination involves disposalof all radioactive material, asurvey of the premises forr a d i o a c t i v e m a t e r i a lcontamination (a “close-outsurvey”), submission ofdisposal documentation and theclose-out survey results, and awritten request for terminationof the license or ARA submittedto the RPSO. The RPSO willreview the request and submitit to the proper regulatoryagency or DA official for

acceptance. The close-outsurvey must be performed in allareas that may possibly becontaminated with radioactivematerial. Sealed sources, thathave passed semi-annual wipetests pose little hazard ofcontamination and a survey ofthe main storage area would besufficient. Where unsealedforms of radionuclides havebeen used, the survey should beconducted following NRCguidance. Nuclear RegulatoryCommission NUREGs and Reg.Guides explain the requiredsampling and monitoringstrategy for different sitetypes, gridding methods forsurveys, sample analysis, datainterpretation techniques, anddocumentation requirements fortermination surveys.

b. The license isconsidered formally terminatedonly upon receipt of the letterof termination from the NRC tothe RPSO.

4-14. Information Flow throughapplicable USACE Channels.

a. All NRC license or ARAapplications, approvals,amendments, submittals,terminations, etc., must berouted through all Safety andOccupational Health Officechannels (that is, “throughchannels”), prior to beingreceived for action by theHQUSACE RPSO. For example: arequest to obtain an NRClicense amendment would flow

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from the local RPO, through thelocal SOHO, through theDivision SOHO, to the RPSO foraction. Actions would beforwarded from the RPSO inreverse order.

b. Failure to follow theinformation flow process is aviolation of the USACEdelegation requirementsspecified by the DA. Technicalconsultations between NRCOffices and license holders atUSACE Commands may take place,though notification of the RPSOof such communications isrecommended.

TABLE 4-1NRC Regional Offices

REGION LOCATION TELEPHONE NO.

Region I King of Prussia, PA 610-337-5000

Region II Atlanta, GA 404-331-4503

Region III Lisle, IL 708-829-9500

Region IV Arlington, TX 817-860-8100

TABLE 4-2State Radiological Health Program Office and 24-Hour Phone Nos.

†Agreement State

STATE OFFICE PHONE NO. 24-HOUR PHONE NO.

Alabama† 205-613-5391 205-242-4378

Alaska 907-465-3019 907-789-9858

Arizona† 602-255-4845 602-223-2212

Arkansas† 501-661-2301 501-661-2136

California† 916-322-3482 916-391-7716

Colorado† 303-692-3030 303-771-8517

Connecticut 203-424-3029 203-566-3333

Delaware 302-739-3787 302-678-9111

District of Columbia 202-727-7190 202-727-1010

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STATE OFFICE PHONE NO. 24-HOUR PHONE NO.

4-13

Florida† 904-487-1004 407-297-2095

Georgia† 404-362-2675 800-241-4113

Hawaii 808-586-4701 808-733-4300

Idaho 208-334-2235 800-632-2235

Illinois† 217-785-9868 217-785-9900

Indiana 317-383-6152 317-383-6154

Iowa† 515-281-3478 515-993-5386

Kansas† 913-296-1562 913-296-3176

Kentucky† 502-564-3700 502-564-7815

Louisiana† 504-765-1060 504-765-0160

Maine† 207-287-5686 207-624-7000

Maryland† 410-631-3300 410-922-7609

Massachusetts† 617-727-6214 617-727-9710

Michigan 517-335-8200 517-336-6100

Minnesota 621-627-5039 612-649-5451

Mississippi† 601-354-6657 601-856-5256

Missouri 314-751-6102 314-635-4964

Montana 406-444-3671 406-442-7491

Nebraska† 402-471-2168 402-471-4545

Nevada† 702-687-5394 702-687-5300

New Hampshire† 603-271-4588 603-271-3636

New Jersey 609-987-6389 609-292-7172

New Mexico† 505-827-4300 505-351-4651

New York† 518-458-6461 518-457-2200

North Carolina† 919-571-4141 919-733-3861

North Dakota† 701-328-5188 701-328-2121

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STATE OFFICE PHONE NO. 24-HOUR PHONE NO.

4-14

Ohio 614-644-2727 614-644-1909

Oklahoma 405-271-7484 800-522-0206

Oregon† 503-731-4014 503-731-4014

Pennsylvania 717-787-2480 717-783-8150

Rhode Island† 401-227-2438 401-621-1600

South Carolina† 803-737-7400 803-253-6488

South Dakota 605-773-3364 605-224-7888

Tennessee† 615-532-0360 615-741-0001

Texas† 512-834-6688 512-458-7460

Utah† 801-536-4250 801-533-4097

Vermont 802-865-7730 802-244-8727

Virginia 804-786-5932 804-674-2400

Washington† 360-586-8949 360-786-8001

West Virginia 304-588-3526 304-558-5380

Wisconsin 608-267-4782 800-943-0003

Wyoming 307-777-7574 Not available

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Chapter 5. Dose Limits andALARA.

5-1. Occupational Dose Limitstructure.

As described in Chapter 4,doses to Authorized Users’Assistants are regulated by theNRC or Agreement State, OSHA,and DA and USACE regulations.To ensure compliance with allregulatory agencies, USACE hasestablished a three tieredapproach to worker dose limits.Tier 1 is the NRC regulatorydose limits which are never tobe exceeded. Tier 2 is theUSACE dose limits which areeffectively 10% of the NRClimits. The USACE limits willensure that USACE workers willbe in compliance with OSHAregulations and Agreement Stateregulations. Tier 3 is projectspecific dose goals which willbe set below the USACE doselimits. Project specific dosegoals are used to promote theconcept of ALARA; keeping thedose as low as is reasonablyachievable, taking social,technical and financialconsiderations into account.Army and NRC regulationsrequire a radiation protectionprogram that promotes ALARA.Descriptions and examples ofthe technical definitions ofthe various dose items areexplained in paragraph 3-5 ofthis manual. Table 5-1highlights the dose limits putforth in the three-tieredapproach.

5-2. USACE Dose Limits.

a. Tier 1; NRC doselimits. Each user ofradioactive material orradiation generating devicesshall limit occupational dosesto individuals to the followinglimits:

(1) An annual limit whichis the more limiting of:

(a) 5 rems (5000 millirem(mrem)(0.05 sieverts (Sv))TEDE,

(b) The sum of the deepdose equivalent and thecommitted dose equivalent toany individual organ or tissueof 50 rems (50000 mrem)(0.5Sv),

(c) 15 rems (15000mrem)(0.15 Sv) to the lens ofthe eye, or

(d) 50 rems (50000mrem)(0.5 Sv) shallow doseequivalent to the skin, or anyextremity.

(2) The TEDE to the fetusof a declared pregnant workerwill be kept below 0.5 rem(500 mrem)(0.005 Sv) during theentire gestation period.Should the worker declarepregnancy after the fetus hasreceived 0.5 rem, the fetuswill be limited to no more thanan additional 0.05 rem for theremaining gestation period, asper 10 CFR 20.1208.

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b. Tier 2 USACE annualdose limits. Without thewritten approval of the RPSOthe annual occupational doseshall not exceed the morelimiting of:

(1) 0.5 rems (500 mrem)(0.005 sieverts (Sv)) TEDE,

(2) The sum of the deepdose equivalent and thecommitted dose equivalent toany individual organ or tissueof 5 rems (5000 mrem)(0.05 Sv),

(3) 1.5 rems (1500mrem)(0.015 Sv) to the lens ofthe eye,

(4) 5 rems (5000 mrem)(0.05 Sv) shallow doseequivalent to the skin, or anyextremity, or

(5) The TEDE to the fetusof a declared pregnant workerwill be kept below 0.5 rem(500 mrem)(0.005 Sv) during theentire gestation period.Should the worker declarepregnancy after the fetus hasreceived 0.5 rem, the fetuswill be limited to no more thanan additional 0.05 rem for theremaining gestation period.

c. Tier 3 projectspecific dose goals. To keepdoses ALARA, the user shall setadministrative action levelsbelow the USACE annual doselimits. The ALARA actionlevels shall be realistic andattainable. ALARA action levelscan be set at any level, butneed to take the particulars ofeach project into account.Example action levels for asmall project involving littleradioactive material could be:

(1)Shall not exceed themore limiting of:

(a) 0.1 rems (0.001sieverts (Sv)) TEDE,

(b) The sum of the deepdose equivalent and thecommitted dose equivalent toany individual organ or tissueof 0.5 rems (0.005 Sv),

(c) 0.15 rems (0.0015 Sv)to the lens of the eye, or

(d) 0.5 rems (0.005 Sv)shallow dose equivalent to theskin, or any extremity.

Table 5-1Dose Limits

Body PartNRC AnnualLimits

USACE AnnualLimits

ExampleAnnual ALARALimits

Whole Body 5 rem 0.5 rem 0.1 rem

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Body PartNRC AnnualLimits

USACE AnnualLimits

ExampleAnnual ALARALimits

5-3

Individual Organ 50 rem 5.0 rem 0.5 rem

Lens of eye 15 rem 1.5 rem 0.15 rem

Skin 50 rem 5.0 rem 0.5 rem

d. Planned specialexposures (see definitions)shall not be used without thewritten consent of the RPSO.

e. Persons under the ageof 18 shall not be allowedoccupational exposure toradiation on USACE sites.

f. Because theembryo/fetus is veryradiosensitive, the NRC has setlower dose limits. The dose toan embryo/fetus shall notexceed 0.5 rem (0.005 Sv)during the entire gestationperiod. To accomplish this, andto ensure privacy and workingrights, the NRC has definedregulations for the control ofdoses to a Declared PregnantWorker (DPW).

(1) A declared pregnantworker means a women who hasvoluntarily informed heremployer, in writing, of herpregnancy and the estimateddate of conception.

(2) A declared pregnantworker will be provided with adeclaration of pregnancy formwhich the RPO will use to

calculate the dose receivedfrom the date of conceptionuntil the date of declaration.Exposure limits for theremaining allowable dose willbe set at that time. Adeclared pregnant worker may“un-declare” at any time.

(3) The RPO will give theDPW a copy of the DPW statement(see Appendix H for an example(if Social Security Number isused, ensure proper privacy actstatement is included)), a copyof NRC Regulatory Guide 8.13,and enroll the DPW in a fetalmonitoring program (See chapter7).

5-3. NRC and Agreement StateDose Limits.

a. NRC dose limits are theTier 1 limits. NRC regulatesonly NRC licensed source,byproduct or special nuclearmaterials. Most AgreementStates have the same doselimits as the NRC, but mostinclude regulation of NORM andNARM materials and radiationgenerating devices.

b. Under NRC regulations,

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each user of licensedradioactive material shalllimit occupational doses toindividuals as stated inparagraph 5-2a.

c. Note that compliancewith the USACE dose limits willcomply with the NRC andAgreement State dose limits.

5-4. OSHA Dose Limits.

a. OSHA adopted the NRCdose limits as they werewritten before the new 10 CFR20 was issued in 1991. Notethat OSHA regulations apply toall radioactive materialsincluding NORM and NARM, aswell as radiation generatingdevices such as X-ray machines.

b. No employer shall useradioactive materials orradiation generating devices ina manner which would cause anyindividual to receive a doseduring one calendar quarter inexcess of:

(1) 1.25 rem to the wholebody; head and trunk; activeblood forming organs; lens ofeyes or gonads.

(2) 18.75 rem to the handsand forearms; feet and ankles.

(3) 7.5 rem to the skin ofthe whole body.

Note that compliance with theUSACE dose limits will meetthis requirement.

5-5. Monitoring Requirements.

Both OSHA and NRC haverequirements to monitor dose toindividuals who can reasonablybe expected to receive a dosegreater than 10% of the maximumpermissible dose. Compliancewith USACE Tier 2 dose limitswill keep workers at dosesbelow 10% of the maximumpermissible doses. The RPO willi s s u e dosimetry tooccupationally exposedindividuals as deemed necessaryto demonstrate compliance withFederal, Army and USACEregulations, and to ensure thatdoses are kept ALARA.

5-6. Doses to the Public.

a. NRC and AgreementStates presently require that alicensee restrict dose to thepublic to 100 mrem/year TEDEfrom licensed activities. TheEDE in any unrestricted areamay not exceed 2 mrem in anyone hour. The maximum allowabledose to the public fromeffluents from a licensedfacility is 50 mrem/year andlisted in Appendix B of 10 CFR20 as a calculatedconcentration for each specificradionuclide yielding 50mrem/year. For decontaminatedand decommissioned facilitiesto be released withoutrestrictions, the dose fromresidual contamination must bebelow 25 mrem/year to thepublic.

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b. The EPA has standardsfor radioactivity in communitydrinking water systems. Thepresent standards are 5picocuries per liter (pCi/l) ofRa-226 plus Ra-228, and 15pCi/l of gross alpha particleactivity, including Ra-226 butexcluding uranium and radon.The present dose limits are 4mrem/year from beta/gamma-emitting radionuclides to thewhole body or any organ.

c. There are proposedrules from both the NRC and theEPA to limit dose to the publicfrom radiation to 15 mrem/year.Note that this value is so farbelow natural background levelsas to be unmeasurable by anyinstrumentation and onlycalculable through dosemodeling.

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Chapter 6. Working withradiation.

6-1. Caution Signs and Labels.

a. Appropriate warningsare required in all areas,rooms, and on all containers inwhich significant amounts ofradiation or radioactivematerial may be found.Warnings consist of postingsand labelings. In general,areas or rooms are “posted”with signs whereas containers,devices, equipment, etc. are“labeled.” The specificwarning to be used depends onthe type and degree of hazardpresent. The RPO will postrooms, hoods, work areas, etc.The AU is responsible forappropriate labeling.

(1) Posting Caution Signs.

(a) USACE policy is thatany room or area in whichradioactive material, coveredby an NRC license, an AgreementState license, or an ARA isused or stored shall be posted“Caution, RadioactiveMaterial”.

(b) A room or area inwhich radioactive material isused or stored may requireadditional posting if the doserate in the room or area islikely to exceed 5 mrem in anyone hour at 30 cm from thesource or source container.Table 6-1 specifies when a roomor area must be posted as aRadiation Area, a HighRadiation Area, or a Very HighRadiation Area.

Table 6-1Caution Sign Posting Requirements

Dose Rate Distance FromSource

Posting Required

1. 5 mrem inany onehour.

1.30 cm

1. “Caution,RadiationArea”

2. 100 mrem inany onehour.

2.30 cm

2. “Caution,HighRadiationArea”

3. 500 rad inany onehour.

3.1 m

3. “GraveDanger, VeryHighRadiationArea”

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(2) NRC Required Labeling.

(a) When a container has aquantity of radioactivematerial equal to or greaterthan that listed in 10 CFR 20Appendix C, a "Caution,Radioactive Material" labelwill be affixed to the outsideof the container. Most gaugesand instruments containingradioactive material, such assoil density gauges, electroncapture sections of gaschromatographs, or sedimentdensity probes will requirethis label. The label should belarge enough to be conspicuous.Standard labels are roughly 4"x 3.5".

(b) Each AU shall, priorto disposal of anyuncontaminated empty containerto an unrestricted area, removeor deface the label orotherwise clearly indicate thatthe container no longercontains radioactive material.

(c) Be advised that thislabeling requirement isseparate from the labelingrequirements of DOT. A packageof radioactive materialprepared for transportation mayalso need DOT labels asdescribed in Chapter 8 -Transportation of RadioactiveMaterial.

(d) An AU is not requiredto label containers when they

are attended by an individualwho takes the precautionsnecessary to prevent theexposure of any individual toradiation or radioactivematerial in excess of thelimits when they are intransport and packaged andlabeled in accordance with DOTregulations, or c o n t a i n e r swhich are accessible only toindividuals authorized tohandle or use them or to workin the vicinity thereof,provided that the contents areidentified to such individualsby a readily available writtenrecord.

b. Signs and labels shallhave a yellow background with amagenta or black standardradiation symbol. Letteringshall be magenta or black, butmagenta is the preferred color.

c. Regulations requirethat the following informationbe posted in a prominentlocation, in sufficient numbersto be accessible to all whowork in, or frequent, areaswhere radioactive material isused:

(1) A copy of the licenseo r permit, conditions,references and amendments.This is usually accomplished byposting a notice of where thelicense, license conditions,referenced documents andamendments are kept. For

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example, "NRC License documentsare kept in the District SafetyOffice and may be viewed byanyone upon request."

(2) Applicable operatingprocedures for the prescribeduse of radioactive material.

(3) All notices ofviolations involving workingconditions, civil penalties, ororder, and the response fromthe licensee. These noticesmust be posted within twoworking days of their receiptand must be posted for aminimum of five working days oruntil the violation has beencorrected whichever is later.

(4) NRC Form 3, "Notice toEmployees" most recent version(rev. Jan 96 as of thisprinting), or Agreement Stateequivalent. (NRC Form-3included at Appendix H.)

6-2. Airborne Radioactivity.

a. If the activities youare engaged in are suspected tocreate airborne radioactivity(for example, vapors oraerosols), the RPO or HP canconduct the appropriate surveysand calculations to determineif posting the area isrequired. If necessary, theseareas will be posted with a" C a u t i o n , A i r b o r n eRadioactivity Area".

b. The RPO will arrange atime to conduct the posting of

each authorized use locationprior to approving thatlocation for radioactivematerial use. A facilityposting checklist is utilizedto document postings.

6-3. Rooms/Areas in WhichRadioactive Material is NoLonger Used or Stored.

The AU is responsible fornotifying the RPO by memo whenradioactive material usage in aroom or area has ceased. TheRPO will perform a close-outsurvey of the area to ensure noresidual contamination, removeall signs and postings,document the survey and, ifnecessary, apply to amend orterminate all applicable NRCLicenses and/or ARAs.

6-4. Receiving RadioactiveMaterial.

a. NRC regulations requirethat written instructions forreceiving and opening packagesbe maintained and followed byall personnel receivingradioactive material. Refer to10 CFR 20.1906 for completeguidance. The following writteninstructions meet the NRCrequirements.

b. When a package isreceived it will be inspectedas follows:

(1) A visual check is madeto see if the package isdamaged (wet or crushed). If

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there is evidence ofdegradation of packageintegrity, the package will bewipe tested for radioactivecontamination and radiationlevels.

(2) Wipe test the externalsurfaces of a labeled package(a package labeled with aRadioactive White I, Yellow II,or Yellow III label asspecified in DOT regulations,49 CFR 172) for radioactivecontamination unless thepackage contains onlyradioactive material in theform of gas or in special formas defined in 10 CFR 20 or anypackage that appears damaged,or if the wipe test resultsfrom the shipper are notdocumented.

(3) Survey the externalsurfaces of a labeled packagefor radiation levels unless thepackage contains quantities ofradioactive material that areless than or equal to the A2

quantity listed in 10 CFR 71Appendix A, and the radioactivematerial is in the form of agas or in special form. Tables6-2 and 6-3 list some of thecommon A1 (special (sealedsource) form) and A2 (normal,unsealed form) values. All theA1 and A2 values can be foundin 49 CFR 173.35. Surveying andwipe testing shall be performedas soon as practicable afterreceipt of the package, but notlater than three hours afterthe package is received if it

is received during normalworking hours, or not laterthan 3 hours from the beginningof the next working day if itis received after normalworking hours.

(4) The receiver willimmediately notify the finaldelivery carrier and, bytelephone and telegram,mailgram, or facsimile, theRPSO, and the NRC whenremovable radioactive surfacecontamination exceeds 2200 disintegrations per minute(dpm)/100 cm beta, gamma or2

220 dpm/100 cm alpha or if the2

external radiation levelexceeds 200 mrem per hour atany point on the externalsurface of the package or 10mrem per hour at 1 meter fromthe package.

(5) When a radioactivematerial package is received,there is a chance theradioactive material has leakedout of the inner container.One could receive a radiationexposure if a contaminatedpackage is opened withouttaking proper precautions.Always assume a radioactivematerial package iscontaminated until provenotherwise.

c. SOPs for openingpackages should be developedfor each site receiving andopening radioactive materialpackages. The followingguidance may assist in

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preparing the procedure:

(1) wear gloves.

(2) check to be sure thecontents match the packingslip.

(3) remove and wipe testthe inner container ifcontamination is suspected. Donot release the contents untilthe wipe test results have beenobtained.

(4) if contamination isnot found, store theradioactive material in asecure storage area that isconspicuously posted for

radioactive material, asrequired above.

(5) if contamination isfound, dispose of allcontaminated shipping materialas radioactive waste. If theradioactive material is stillusable, clean the outside ofthe container, and store in anarea posted as necessary, forradioactive material. Surveythe receipt area forcontamination.

(6) deface or remove alllabels on the uncontaminatedshipping box and dispose of asnormal trash.

Table 6-2Typical A Quantities in Special (sealed source) Form: 1

H-3 . . . . . . . . . 1000 CiC-14 . . . . . . . . 1000 CiNa-22 . . . . . . . . . . 8 CiP-32 . . . . . . . . . 30 CiS-35 . . . . . . . . 1000 CiCo-57 . . . . . . . . . 90 CiFe-59 . . . . . . . . . 10 CiCo-60 . . . . . . . . . 7 CiNi-63 . . . . . . . . 1000 CiSr-90 . . . . . . . . . 10 CiI-125 . . . . . . . . 1000 Ci

Ba-133 . . . . . . . . 40 CiCs-137 . . . . . . . . 30 CiPm-147 . . . . . . . 1000 CiTl-204 . . . . . . . . 300 CiPo-210 . . . . . . . . 200 CiRa-226 . . . . . . . . 10 CiTh-232 . . . . . . unlimitedU-238 . . . . . . . unlimitedAm-241 . . . . . . . . . 8 CiCf-252 . . . . . . . . . 2 Ci

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Table 6-3Typical A Quantities in Normal(unsealed) Form:2

H-3 . . . . . . . . . . 20 CiC-14 . . . . . . . . . 60 CiNa-22 . . . . . . . . . . 8 CiP-32 . . . . . . . . . 30 CiS-35 . . . . . . . . . 60 CiCo-57 . . . . . . . . . 90 CiFe-59 . . . . . . . . . 10 CiCo-60 . . . . . . . . . 7 CiNi-63 . . . . . . . . 100 CiSr-90 . . . . . . . . . 0.4 CiI-125 . . . . . . . . . 70 Ci

6-5. Radioactive Material and Radiation Generating DeviceInventory.

a. The RPO for each USACECommand is responsible for allradioactive material andradiation generating devicesowned or possessed by theCommand, regardless of whetherthe material and radiationgenerating device is authorizedunder a general license, aspecific license, or ARA. Inorder to ensure control of allradioactive material andradiation generating devices,the RPO shall maintain awritten inventory of allradioactive material andradiation generating devices within the Command. Inventoryshould be categorized into NRCspecifically licensedmaterials, NRC generallylicensed materials, ARAauthorized materials, andradiation generating devices.

Cf-252 . . . . . . . 0.009 CiBa-133 . . . . . . . . 10 CiCs-137 . . . . . . . . 10 CiPm-147 . . . . . . . . 25 CiTl-204 . . . . . . . . 10 CiPo-210 . . . . . . . . 0.2 CiRa-226 . . . . . . . 0.05 CiTh-232 . . . . . . unlimitedU-238 . . . . . . . unlimitedAm-241 . . . . . . . 0.008 Ci

The inventory shall be kept onENG Form 3309-R “Record ofRadioactive Material”. A copyof this form is attached atAppendix H.

b. The RPO for each Commandowning or possessingradioactive material orradiation generating devicesshall physically inventory eachitem at least semi-annually,and more often if their licenserequires it. This will usuallybe accomplished along with thesemi-annual wipe test. Forremote sources, such as thoseassigned to dredges, the RPOmay have an AU perform thephysical inventory of theitem(s).

6-6. Storing RadioactiveMaterial.

The AU is responsible forassuring that all radioactivematerial is stored in a secure

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manner when not in use. Sealedsources used in the field maybe locked in their storagecontainers. Sealed sourcesstored in a building may belocked in a storage room orstorage cabinet. Unsealedsources may be locked in astorage container, cabinet,drawer, refrigerator, orfreezer. Labs where unsealedsources are used shall belocked whenever the lab isunattended. Sealed sources infixed use locations may besecured in their work position.The AU must ensure that whereever radioactive sources arestored, proper labeling andposting, as per paragraph 6-1is used.

6-7. Contamination Control.

a. Depending upon thetypes and quantities ofradioactive material in use,contamination surveys may bemade directly with portablesurvey instruments orindirectly (removablecontamination survey, wipe orswipe survey) by wipingsurfaces (approximately 100cm ) with a filter paper and2

counting the wipes.

A direct contamination surveyis performed using a meter anddetector appropriate to thenuclides in use in the area.For example, if surveying forP-32 contamination, one woulduse a GM detector (probe); forI-125, one would use a thin

window NaI scintillationdetector (probe). Anionization chamber would not beappropriate for a contaminationsurvey. At the beginning ofeach day of use, aninstrument’s operability shouldbe checked with a suitablecheck source. Each meter hasan integrator circuit and itwill take time for it toproperly respond. It is highlysuggested that meters beequipped with audio circuits soa surveyor can hear a change in'click' rates and resurveysuspected 'hot spots'.

b. Removable contaminationconsisting of low energy betao r a l p h a e m i t t i n gradionuclides, such as H-3,C-14, or Pu-239, is bestdetected through the use ofwipes and liquid scintillationcounting since the betaemissions from theseradionuclides have insufficientenergy to be efficientlydetected by portable surveyinstruments, and the alphaemissions have of too short ofa range in air to be easilydetected. Wipes may also beappropriate when attempting todetect contamination in areaswith higher than backgroundradiation levels. For example,the use of a GM survey meter todetect contamination would notbe practical if radiationlevels in an area are alreadyelevated from radioactivematerial stored within thearea. In this situation, a

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wipe test could be performedand the wipe counted at alocation away from theradiation field.

c. When radiation levelsin an area are normalbackground, portable surveyinstruments can be quiteeffective in detecting certaintypes of radioactivecontamination. Most GM meterscan detect P-32 withefficiencies exceeding 20%.I-125 can be detected atefficiencies nearing 20% with at h i n crystal (NaI)scintillation probe. Allsurvey instruments are only asgood as their maintenance. Aportable survey meter, in mostcases must be calibrated atleast once every year andoperability verified each dayof use with a check source.

6-8. Wipe Tests.

a. A wipe test, alsocalled a ‘smear’ or ‘swipe’test, is collected usingvarious materials. The mostcommon material is a filterpaper type material designedspecifically for this purpose.This material can be used wetor dry but dry wipe tests arepreferred. Dry tests arepreferred if the chemical formof the radionuclide is notknown. If it is not watersoluble, a wipe with a wet swabwill not collect as much of thecontaminant as a dry swab.Conversely, if a swab is wetted

with an oil based solvent,water soluble contaminants willnot be collected asefficiently. Additionally,many solvents are hazardousmaterials, and shouldradioactive contamination befound, the swab may become amixed or commingled waste. Thewipe test is performed byphysically wiping the area tobe checked.

b. If water is used tomoisten the material, cautionmust be used to not saturatethe material and to allow thematerial to dry prior tomeasurement. Water willattenuate alpha emitters andallow for false readings whenread with a survey meter orsome counting systems. The NSNfor a box of 500 wipe testersis 6665-01-198-7573 (a 2-inchdiameter Whatman filter paperworks well also). Anothercommon method for small spacesis the use of cotton swabs,similar to ‘Q-tips.’ A NSN fora package of these is 6515-00-890-1475.

c. Wipe testing isperformed by using the wipe orfilter paper or cotton swab andwiping it over an areaapproximately 100 squarecentimeters. Wipe tests areperformed using normal fingerpressure on a dry filter paperor swab and wiping in an "S"shape for a distance of 50centimeters and wiping again ina backwards "S" shape at right

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angles to the first one foranother 50 centimeters. Thewipe is then analyzed on siteor packaged in an envelope andsent to a lab for analysis. Ifan item is too small orirregularly shaped for thisprocedure, then wipe the entiresurface area of small items oran accessible 100 squarecentimeter area of irregularshaped items.

d. Suggested limits forremovable contamination arelisted in Table 6-4. Wheneverradioactive contamination isfound, reasonable effortsshould be made to remove allcontamination.

6-9. Leak Testing.

a. Many sealed sources arerequired by license orauthorization conditions to beleak tested periodically. Leaktests are typically requiredevery six months. But somelicense conditions may requiremore frequent testing. A leaktest is performed in a mannersimilar to a wipe test. Theprimary difference is that mostsealed sources emit much moreradiation than mostcontamination, and for ALARApurposes it is best to keep asmuch distance between thesource and the personperforming the leak test. Thisis done by using long handledcotton swabs or forceps to holdthe filter paper swab,increasing the distance between

the source and the hand. Thewipe, or swab should then beplaced in its own plastic bagor glycine envelope to avoidpotentially contaminating otherwipes or areas. Since manyCommands do not have theinstrumentation available todetermine the amount ofcontamination from a leak test,most leak test wipes are sentto a lab for analysis. USACEleak tests shall be sent toUSAIRDC for analysis.

b. The limits forcontamination of sealed sourcesis 0.005 µCi per wipe.

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Table 6-4Acceptable Surface Contamination Levels

NUCLIDE a AVERAGE b c

dpm/100 cm2MAXIMUM b d

dpm/100 cm2REMOVABLE b e

dpm/100 cm2

U-nat, U-235, U-238 andassociated decay products

5,000 þ 15,000 þ 1,000 þ

Transuranics, Ra-226, Ra-228,Th-230, Th-228, Pa-231, Ac-227, I-125, I-129

100 300 20

Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133

1,000 3,000 200

Beta-gamma emitters (nuclideswith decay modes other thanalpha emission or spontaneousfission) except Sr-90 andothers noted above.

5000 ß-þ 15,000 ß-þ 1,000 ß-þ

Where surface contamination by both alpha- and beta-gamma-emitting nuclidesa

exists, the limits established for alpha- and beta-gamma-emitting nuclidesshould apply independently.

As used in this table, dpm (disintegrations per minute) means the rate ofb

emission by radioactive material as determined by correcting the counts perminute observed by an appropriate detector for background, efficiency, andgeometric factors associated with the instrumentation.

Measurements of average contaminant should not be averaged over more than 1c

square meter. For objects of less surface area, the average should be derivedfor each object.

The maximum contamination level applies to an area of not more than 100 cm . d 2

The amount of removable radioactive material per 100 cm of surface areae 2

should be determined by wiping that area with dry filter or soft absorbentpaper, applying moderate pressure, and assessing the amount of radioactivematerial on the wipe with an appropriate instrument of known efficiency. Whenremovable contamination on objects of less surface area is determined, thepertinent levels should be reduced proportionally and the entire surfaceshould be wiped.

6-10. Exposure Rate Surveys.

In addition to contaminationmonitoring, it is alsoimportant to assess exposurerates resulting from the

storage and use of relativelylarge quantities of high energybeta or gamma emitters. Thisinformation is important inplanning and evaluating thecontrol of time, distance, and

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shielding in order to minimizepersonnel exposure. In somesituations, a GM metercalibrated at or near theenergy of the radiationmeasured, can give a reasonableestimate of the exposure rate.An ionization chamber will givethe most accurate estimate ofexposure and should be usedwhenever measuring exposures todetermine posting requirements,measuring the transport index(TI) of a package, or whenexposures are more than a fewmillirems.

6-11. Accident/IncidentResponse.

a. There is always apossibility of an accidentinvolving radiation orradioactive material. USACEwill strive for a zero accidenttolerance level. This can beaccomplished using StandingOperating Procedures,conscientious work practices,and having and practicing anAccident / Emergency ResponsePlan. The plan, required forall HTRW sites, must provideguidance for response to fire,natural disasters, radioactivematerial spill, and inadvertentradiation exposure. The planwill address the followingprocedures:

(1) Evacuation of thebuilding/area;

(2) Treatment of injuredpersonnel;

*NOTE* Never delay treatment ofan injured person because ofactual or potential radioactivecontamination.

(3) Firefighting;

(4) Spill response;

( 5 ) P e r s o n n e ldecontamination; and

(6) Any additional sitespecific requirements.

6-12. Accident/IncidentReporting.

a. Any individualsuspecting or knowing of anaccident, incident, loss ortheft involving radioactivematerial or radiation willnotify the RPO as soon aspossible. The RPO will notifythe RPSO immediately of anyaccident, incident, loss ortheft that requires reportingto the NRC or other regulatoryagency. The RPO will notifythe NRC, OSHA or otherregulatory agency in therequired time frame, of allaccidents, incidents, losses orthefts that require reporting.The RPSO will notify HQDA(DACS-SF) of all NRC, OSHA orother agency notificationswithin the same time frame asrequired by the agency. TheRPSO will also notify DASG-PSPof all exposures exceeding Tier1 dose limits or OSHA doselimits and submit copies ofreports to other agencies to

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DASG-PSP as required by theArmy Radiation ProtectionProgram. All telephone reportswill be followed up by awritten report within 30 days.

b. All written reportswill address the followingitems:

(1) A description of thematerial involved, includingthe kind, quantity and chemicaland physical form of thematerial,

(2) A description of thecircumstances surrounding theincident,

(3) A statement of thedisposition, or probabledisposition of the materialinvolved,

(4) An estimate of dosesreceived by any individuals,and the circumstances of theexposure,

(5) Actions taken, and

(6) Procedures or measuresproposed or adopted to preventrecurrence.

c. The following are someof the reportable accidents/incidents, and the requiredreporting times:

(1) Theft or loss of 1000times the 10 CFR 20, Appendix Cquantity of a radioactivematerial must be reported

immediately;

(2) Theft or loss of 10times the 10 CFR 20, Appendix Cquantity of a radioactivematerial must be reportedwithin 30 days;

(3) Incidents that causeor threaten to cause anindividual to receive 25 remTEDE, 75 rem EDE, or 250 remShallow Dose Equivalent (SDE),must be reported immediately;

(4) A release ofradioactive material, eitherinside or outside a restrictedarea, that could possiblyresult in a 24-hour dose ofgreater than five times theannual limits must be reportedimmediately;

(5) Incidents that causeor threaten to cause anindividual to receive 5 remTEDE, 5 rem EDE, or 50 rem SDE,must be reported within 24hours;

(6) Release of radioactivematerial, either inside oroutside a restricted area, thatcould possibly result in a 24hour dose of greater than theannual limits must be reportedwithin 24 hours.

(7) Incidents that causean occupational worker, memberof the public, a minor or anembryo/fetus of a declaredpregnant woman to receive adose in excess of the

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appropriate regulatory dose,must be reported within 30days;

(8) A release ofradioactive material, inside arestricted area, greater thanthe license limits must bereported within 30 days;

(9) A release ofradioactive material, outside arestricted area, greater than10 times any license limit,regardless of any exposure toan individual, must be reportedwithin 30 days.

d. Reports must includethe information required in 10CFR 20 Subpart M, or asrequired by other regulatoryagencies.

6-13. Audits and Reviews.

a. The RPSO, or theirdesignee, will audit eachCommand that possesses aradioactive material license orARA tri-annually. The audit isto ensure personnel safety andcompliance with regulatoryrequirements. The audit mayconsist of a records review,facility inspection, interviewswith the RPO and AUs, and anexit interview with the RPC orthe Commander, depending on theactivity at the Command. Theaudit will be documented and acopy furnished to the Commanderand the RPO.

b. The RPO will review

their Radiation ProtectionProgram annually for contentand implementation. The RPOwill assure that the qualityand timeliness of their programmeet the radiation safetyguidelines outlined in thismanual. The RPO will reviewall work with radiation withinhis/her Command. The RPO willperform the annual review withthe purpose of anticipating theneeds of the program in thecoming year. The review willbe documented and a copyforwarded to the RPSO.

c. Additional audits andreviews may be performed asdeemed beneficial to theCommand by the RPSO, the RPO,or the Commander.

d. Documentation Audits.Documentation audits may beperformed by the RPSO or theirdesignee for Commands with anNRC license or ARA where littlehealth risk is posed byradiation. A document auditwill consist of a review of theradioactive materials licenseor ARA, the inventory,personnel dose histories,receipt, transfer, and disposalrecords, and leak test results.Deficiencies may includeincomplete or inaccuratedocumentation. Significant ormultiple deficiencies mayinitiate a field audit.

e. Field Audits. Fieldaudits will be performed by theRPSO or their designee for

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Commands where the use ofradioactive materials orradiation generating deviceshas the potential to presentgreater health risks to USACEpersonnel or the public. Afield audit will consist of adocumentation audit and an on-site inspection. The inspectionwill concentrate on proactiveradiation protection proceduresand processes. These mayinclude:

(1) ensuring properposting and labeling,

(2) ensuring proper use ofdosimetry,

(3) ensuring proper andsecure storage of radioactivematerials,

(4) ensuring thatradiation monitoring equipment

is of the proper type for theradiation used; that theinstruments have beencalibrated in a timely manner;and that personnel know thecorrect methods of surveyingf o r r a d i a t i o n a n dcontamination,

(5) ensuring that anytransportation of radioactivematerials complies with NRC andDOT regulations.

f. U.S. Army Center forHealth Promotion and PreventiveMedicine (USACHPPM) Surveys.Presently, USACHPPM surveysUSACE Commands annually. USACHPPM surveys follow asample protocol/checklistpresented at Appendix I.

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Chapter 7. PersonnelMonitoring.

7-1. External Monitoring.

a. To indicate the amountof radiation to which a personhas been externally exposed, anindividual monitoring devicemay be used. NRC regulationsdefine an “individualmonitoring device” as a devicedesigned to be worn by a singleindividual for the assessmentof dose equivalent. Examples ofdosimeters include film badges,thermoluminescent dosimeters(TLDs), pocket ionizationchambers (“pencils”), alarmrate meters, track etchdosimeters, and neutronsensitive film. NRC and OSHAregulations require that eachlicensee monitor occupationalexposure to radiation andsupply and require the use ofdosimeters by:

(1) Adults likely toreceive in one year fromsources external to the body adose in excess of 10 per centof the limits specified inChapter 4;

(2) Declared pregnantwomen likely to receive duringthe pregnancy, from sourcesexternal to the body a dose inexcess of 10 per cent of thelimits in Chapter 4; and

(3) An individual enteringa high or very high radiationarea.

b. Most individuals whowork in radiation areas neverapproach values which requirepersonnel monitoring.Statistical evaluations ofmonitoring results have shownthat 70% of all monitoredAuthorized Users’ Assistantsreceive no measurable exposureand another 20% receive lessthan 100 mrem per year.Exposure histories havedocumented the fact thatusually only those individualswho work in radiology,radiography, and other fieldsusing high activity sources arerequired to be monitored.

c. Within USACE, the RPOwill determine which USACEpersonnel should weardosimeters. USACE personnelare among the aforementionedlarge percentage of individualswhich are not likely to receivea measurable dose. Dosimetryis issued, in most cases, todocument low exposures.

d. The RPO will instructpersonnel in the proper use ofdosimeters, will issuedosimeters, will collectdosimeters and submit them foranalysis, and will review theanalysis results. Dosimeters(except direct and indirectreading pocket ionizationchambers) will be processed bya laboratory which holdscurrent accreditation from theNational Voluntary LaboratoryAccreditation Program (NVLAP)of the National Institute of

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Standards and Technology(NIST).

e. Most contractors usevendor supplied services. USACEpersonnel will use the US ArmyIonizing Radiation DosimetryCenter (USAIRDC) for dosimetryservices. Exposures shall bereported and recorded.Exposures shall be recordedusing the computer generatedprintout generated by USAIRDCor NRC Form 5 (a copy forreference of the USAIRDCversion of NRC Form 5 isattached at Appendix H). Theprogram is administered fromRedstone Arsenal and may becontacted at the following:

US Army Missile CommandAttn: AMSMI-TMDE-SR-DRedstone Arsenal, AL 35898-5400commercial phone number:(205)876-1858.

f. The four chip TLD isthe standard US Army whole bodydosimeter.

g. Personnel should notexpose their dosimeter tosecurity X-ray devices,excessive heat, or medicalsources of radiation. Shouldjob conditions dictate,dosimeters may be removed froma job site as part of anemployee’s routine travel toand from work. At sites wheredosimeter use is routine, andthere is a responsibleindividual to manage thedosimeters, the personal

dosimeters should be stored atsite and not taken home eachnight. A dosimeter shall bereturned to the RPO if anemployee will not be physicallypresent at the job site for aperiod of one month or greater.

h. A person whosedosimeter is lost, damaged, orcontaminated while working willimmediately exit the radiationcontrol area and report theoccurrence to the RPO. Reentryof the person into theradiation control area will notbe permitted without RPOapproval. Dosimeters will notbe utilized by USACE personnelfor operations at locationsother than USACE sites.

7-2. Internal Monitoring.

a. NRC regulations alsorequire that each licenseemonitor the occupational intakeof radioactive material by andassess the committed effectivedose equivalent to:

(1) Adults likely toreceive in one year an intakein excess of 10 percent of theapplicable ALI; and

(2) Declared pregnantwomen likely to receive duringthe pregnancy, a committedeffective dose equivalent inexcess of 50 mrem.

b. If a licensee isrequired to monitor bothexternal and internal

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exposures, then the externaland internal doses must besummed to demonstratecompliance with the dose limitsspecified in Chapter 5.

c. Internal monitoring canbe achieved via bioassay. Abioassay is a determination ofthe kind, quantity, orconcentration and location ofradioactive material in thebody. A direct (in vivo)bioassay measurement may bemade by whole body counting(that is, counting the gamma-rays emanating from aradionuclide in a given organ).An indirect (in vitro) bioassaymeasurement may be made byassessing the quantity of aspecific radionuclide insamples that are excreted (forexample, urine, feces, orblood). There are four types ofbioassays:

(1) Baseline: Prior topotential exposure;

(2) Routine: At aspecified frequency (forexample, quarterly);

(3) Postoperational:Within two weeks of the lastpossible exposure whenoperations are beingdiscontinued or when the workeris terminating duties withexposure to radioisotopes; and

(4) Diagnostic: Follow-upbioassay performed within twoweeks of any measurement

exceeding the action level.This will confirm the precedingmeasurement and allow anestimate of effective half-life.

d. Within USACE, personnelshall participate in a bioassayprogram when they are likely toreceive an intake that mayresult in a committed effectivedose equivalent of 100 mrem ormore, or, when an intake ofradiation is suspected for anyreason. Specific bioassayrequirements will be determinedby the RPO for each job site.Bioassay procedures, supplies,lab analysis and doseassessment may be obtained on acost reimbursable basis fromthe US Army Center HealthPromotion and PreventiveM e d i c i n e ( U S A C H P P M ) ,Radiochemistry and AnalysisProgram (RAP), commercialphone,(410) 671-3983.

e. Personnel shall benotified promptly of positivebioassay results, as well asthe results of dose assessmentsand subsequent refinements.Dose assessment results shallbe provided in terms of mrem tothe organ(s) and whole body.

f. Personnel shouldparticipate in diagnostic(follow-up) bioassay monitoringwhen their routine bioassayresults indicate an intake inthe current year with acommitted effective doseequivalent of

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100 mrem or more.

g. Management shouldrequire a post-operationalbioassay when a person whoparticipated in the bioassayprogram terminates employmentor concludes work involving thepotential for internalexposure.

7-3. Advanced Monitoring.

a. Multiple dosimeters maybe issued to personnel toassess whole-body exposure innonuniform radiation fields oras required in radiation workplans. Nonuniform radiationfields exist when the dose to aportion of the whole body willexceed the dose to the primarydosimeter by more than 50percent, and, the anticipatedwhole-body dose is greater than100 mrem.

b. The use of an alarmrate meter is encouraged forentry into a high radiationarea or when a planned dose ofgreater than 100 mrem in oneweek is expected. An alarmrate meter provides an earlywarning of elevated exposurethrough the use of a presetdose rate or an integrateddose. A direct reading(pencil) dosimeter may be usedin place of an alarm ratemeter. A pencil dosimeter withthe lowest range applicable(typically 0-200 mR) should beselected. The alarm rate meteror the pencil dosimeter should

be worn simultaneously with theprimary dosimeter. The alarmrate meter or pencil dosimetershould not be allowed to exceed75 per cent of full scale.

c. The establishment andmaintenance of a comprehensivearea monitoring program mayminimize the number of areasrequiring the issuance ofpersonnel dosimeters, and,demonstrate that doses outsideradiation work areas arenegligible. Minimizing thenumber of personnel dosimetersissued lowers the costs ofoperating the dosimetry programand reduces costs associatedwith maintaining personnel withenhanced training andqualifications.

d. Area-monitoringdosimeters should be used incontrolled areas to supplementexisting monitoring programs,and to provide data in theevent of an emergency. Area-monitoring dosimeters should beused to record and documentradiation levels in routinelyoccupied areas that areadjacent to areas where radia-tion, or operations withradiation exist. Area-monitoring dosimeter resultscould be used to supportdosimetry investigations ifpersonnel express concernsabout their work environmentsand possible exposure toionizing radiation.

e. Any pregnant worker who

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wishes to voluntarily enroll inthe fetal monitoring programneeds to contact the RPO.

(1) The worker will beprovided with a declaration ofpregnancy statement which theRPO will use to calculate thedose received from the date ofconception until the date ofdeclaration. An example of thisstatement is included atAppendix H (if Social SecurityNumber is used ensure properprivacy act statement isprovided). Exposure limits forthe remaining allowable dosewill be set at that time.

(2) A copy of thecompleted declaration ofpregnancy statement, NRCRegulatory Guide 8.13, and afetal monitoring dosimeter willbe provided to the declaredpregnant worker as soon aspractical. The fetalmonitoring dosimeter is to beworn at waist level versus thestandard whole body dosimeterwhich is worn at the collar.If a lead apron is utilized,the fetal dosimeter is wornunder the apron and the wholebody dosimeter outside theapron.

(3) The exposure levelsfor fetal monitoring dosimeterswill be closely evaluatedthroughout the entire gestationperiod by the RPO. A fetalALARA level has been set by theRPSO at an exposure of 40mrem/month. Should this level

be exceeded, the declaredpregnant worker will receiveimmediate notification, andactions will be taken to reduceany further exposure.

(4) At the end of thepregnancy, or if the workerrescinds her pregnancydeclaration and wishes to ceasefetal monitoring, the declaredpregnant woman should contactthe RPO to discontinue thefetal monitoring dosimeter. Afetal exposure final reportwill be generated.

7-4. Exposure Reporting.

a. The RPO will furnisheach worker annually with awritten report of the worker’sdose.

b. At the request of aworker who is terminatingemployment, the RPO willprovide (within 30 days of therequest) a termination reportregarding the radiation dosereceived by that worker for thecurrent year or fractionthereof. If the most recentresults are not available atthat time, a written estimateof the dose will be providedwith a clear indication thatthis is an estimate. The RPOcan obtain this informationfrom USAIRDC.

c. It is each individual’sresponsibility to notify theRPO when they terminate workinvolving radiation exposure.

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d. A worker formerlyengaged in activitiescontrolled by USACE, mayrequest a written report ofhis/her exposure to sources ofradiation for each year thathe/she was monitored. Thereport will be prepared by theRPO, will cover the period oftime that the worker’sactivities involved exposure toradiation, will include thedates and locations of work,and will be furnished to theworker within 30 days of therequest. The RPO can obtainthis information from USAIRDC.The RPO can provide a detailedinterpretation of a monitoringreport form. Information whichmay be useful when reading amonitoring report is asfollows:

(1) A HARD exposurerelates to the whole bodyexposure (DDE);

(2) A SOFT exposurerelates to a skin exposure(SDE);

(3) An EYE exposurerelates to an exposure to thelens of the eye (Lens DoseEquivalent); and

(4) A dose of 000.000 or'M' indicates a minimumreading. This means the dosefor the monitoring period wasbelow the minimum measurablequantity for the type ofdosimeter used. Usual minimum

values are as follows:

(a) Whole Body Badge - 10mrem for X-and gamma-radiation,40 mrem for energetic betaradiation; and

(b) Ring Badge - 10 mremfor X- and gamma-radiation, 30mrem for energetic betaradiation.

e. Each RPO hasinformation relevant toenrolling in the program. A DDForm 1952 (available throughthe local forms manager) mustbe completed and forwarded tothe RPO.

f. All individuals mustprovide a dose history to theRPO if they are likely to havereceived in excess of 10% ofany applicable annual limit.Additionally, any individualwho had been monitored atanother facility during thecurrent calendar year mustprovide the RPO with pertinentexposure data. This exposuredata will allow adjustments tobe made so that the annual doselimits are not exceeded. Bothof these are required prior toenrolling in the dosimetryprogram.

g. All personnel requiringbioassays will be sent a copyof their bioassay results on anannual basis. An individualmay request the result of anybioassay at any time.

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Chapter 8. Transportation ofRadioactive Material.

8-1. Purpose.

This chapter is intended tointroduce containment, control,and communication requirementswhen transporting radioactivematerial. This chapter is notan exhaustive review of allregulatory requirements whichpertain to shipping radioactivematerial.

8-2. Applicability.

This chapter applies to allpersonnel who ship or transportradioactive material and allpersonnel who superviseoperations which involveshipments or transportation ofradioactive material.

8-3. Regulations.

a. The transportation ofradioactive material isregulated jointly at theFederal level by the DOT andthe NRC. The division ofresponsibilities between DOTand NRC is specified in amemorandum of understanding.DOT regulates shippers,carriers, Type A packages andLOW SPECIFIC ACTIVITY (LSA)packages, and it issuesCertificates of CompetentAuthority for InternationalShipments. Relevant DOTregulations may be found in 49CFR 170-189.

b. NRC regulates Type Band fissile packages; it isresponsible for transportationsafeguards; it investigatesaccidents/incidents, and it isa technical advisor to DOT.Relevant NRC regulations may befound in 10 CFR 71. It isworth noting that 10 CFR 71.5requires NRC licensees tocomply with 49 CFR 170-189.

c. DOE controls andregulates shipments of U.S.Government program relatednuclear materials. DOErequires shippers and carriersof non-weapons under theirauthority to conform to DOT andNRC regulations.

d. U.S. Postal Service(USPS) regulations for mailableradioactive material may befound in USPS Publication 6,latest edition (March 1990)-“Radioactive Material.”Mailable packages are limitedto those meeting DOTrequirements in 49 CFR 173.421and 173.422 for LimitedQuantities and Instruments andArticles EXCEPT THAT theradioactivity content in thepackage is further limited toone-tenth of DOT limits inTable 7, 49 CFR 173.423.

e. For purposes oftransportation, radioactivematerial is defined as anymaterial which has a specificactivity greater than 0.002µCi/g (70 Bq/gm) [49 CFR173.403 and 10 CFR 71.10(a)].

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f. Hazardous material isdefined by DOT as anysubstance, including mixturesand solutions of substances,which the Secretary ofTransportation has determinedto be capable of posing anunreasonable risk to health,safety and property whentransported in commerce (49 CFR171.8). Radioactive materialis considered hazardousmaterial by DOT’s definition.

8-4. Procedures.

a. Nuclear transportationregulations ensure safety byeffective containment of thematerial; effective control ofthe radiation emitted from thep a c k a g e ; p r e v e n t i n g -criticality for fissileradioactive material; andadequate dissipation of anyheat generated in a package.Primarily, safety in transportis accomplished by properpackaging of the radioactivematerial and by accuratelycommunicating any associatedhazards.

b. Hazard communication isachieved through correctmarking, labeling, placarding,manifesting, and emergencyresponse information.

8-5. Packaging.

a. In general, there arefour types of packages used totransport radioactive material:

(1) Strong, tightcontainers (STC);

(2) Industrial packagings(IP-1, IP-2, and IP-3);

(3) Type A packages; and

(4) Type B packages.

b. The package requiredfor a particular shipment ofradioactive material isdetermined by the activity orquantity of the shipment. DOTcategorizes quantities ofradioactive material into fivesubtypes:

(1) EXCEPTED QUANTITIESwhich includes:

(a) Limited Quantities(173.421), must be in a STC;

(b) Instruments andArticles (173.424), must be ina STC;

(c) Manufactured Articlesof U, DU, or Th (173.426), mustbe in a STC; and

(d) Empty Packages(173.428), must be in a STC.

(2) LSA QUANTITIES andSURFACE CONTAMINATED OBJECTS(173.427), in an industrialpackage, in a DOT Spec 7A TypeA package, or in a STC;

(3) TYPE A QUANTITIES (þ A1or A values in 173.435), must2

be in a Type A package;

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(4) TYPE B QUANTITIES (þA or A values in 173.435),1 2

must be in a Type B package;and

(5) HIGHWAY ROUTECONTROLLED QUANTITIES (3000 XA or A values in 173.435, or1 2

exceed 27,000 Ci.), must be ina Type B package.

c. When preparing ashipment, a person should firstdetermine the DOT subtypeinvolved. Then, the person candetermine the type of packagerequired either by referring tothe information and regulatorycitations given above or byreferring to column 5 of theHazardous Materials Table(172.101).

d. Each shipper of a DOTSpecification 7A package (aType A package) must maintainon file for at least one yearafter the latest shipment, andshall provide to DOT onrequest, DOT packageperformance test records [49CFR 173.415(a)].

e. Any shipper of a Type Bpackage that has been approvedby NRC in accordance with 10CFR 71 shall be registered withthe NRC as a party to theapproval and the shipment mustbe made in compliance with theapproval (49 CFR 173.471).

f. Anyone needing to shipradioactive material, but whohas little experience doing so,

should seek assistance from aqualified professional.

8-6. Marking.

a. Packages containingradioactive material must bemarked according to 49 CFR172.300. Proper markingincludes:

(1) The proper shippingname and the identificationnumber as shown in 49 CFR172.101 for packages which areless than 110 gallons;

(2) If transferred toanother carrier, the name andaddress of the shipper(consignor) or the receiver(consignee);

(3) The gross mass ifgreater than 110 pounds;

(4) “Type A” or “Type B”in ½ inch letters for thesetypes of packages;

(5) “This End Up þ” forliquids;

( 6 ) “ U S A ” f o rinternational shipments; and

(7) “RQ” for reportablequantities (172.101, App. A).

(8) Shipments where theterm “radioactive material”does not appear in the propershipping name on the manifestand shipments not requiring amanifest must be marked

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“Radioactive Material”

b. The markings must bedurable, legible, in English,and printed on or firmlyaffixed to the package. Themarkings must be displayed on abackground of a sharplycontrasting color. Markingsmust be located away from othermarkings, such as advertising,that could substantially reducethe noticeability of themarking. Markings must not becovered or obscured by labelsor attachments.

8-7. Labeling.

a. Packages containingradioactive material must belabeled according to 49 CFR172.400. DOT specifies threecategories of labels forpackages containing radioactivematerial: Radioactive White-I,Radioactive Yellow-II, andRadioactive Yellow-III. Thelabel required for a packagedepends on the radiation levelat the package surface and at 1meter from the package surface[the radiation level measuredat 1 meter, in mrem/hr, andlisted without units is alsoknown as the transport index(TI)]. Each label must includethe name of the radionuclide,the activity (in SI unitsfollowed by curie units inparentheses), and the TI(Radioactive Yellow-II and -IIIlabels only). Proper labelingincludes:

(1) Labels on two oppositesides excluding the bottom;

(2) Labels affixed nearthe markings (same side) andoriented in the same directionas the markings; and

(3) Label must be durableand able to withstand colorchange for 30 days.

b. Packages of LimitedQuantities, Instruments andArticles, and ManufacturedArticles of U, depleted uranium(DU), or Th are exempt fromlabeling requirements.EXCEPTED QUANTITIES preparedfor shipment must have a notice(as written below) enclosed inor on the package, includedwith the packing list, orotherwise forwarded with thepackage. Limited Quantitypackages and ManufacturedArticles of U, DU, or Thpackages must have the word“Radioactive” on the innerpackaging. Empty packages musthave an “Empty” label. LOWSPECIFIC ACTIVITY packages musthave a “Radioactive-LSA” label.

c. Excepted quantitiesnotice. The notice mustinclude the name of theconsignor or consignee and thestatement “This packageconforms to the conditions andlimitations specified in 49 CFR173.421 for exceptedradioactive material, limitedquantity, n.o.s., UN 2910; 49CFR 173.422 for excepted

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radioactive material,instruments and articles, UN2911; 49 CFR 173.424 forexcepted radioactive material,articles manufactured fromnatural or depleted uranium ornatural thorium UN 2909; or 40CFR 173.427 for exceptedradioactive material, emptypackages, UN 2908" asappropriate.

8-8. Placarding.

a. A vehicle transportinga package labeled RadioactiveYellow-III or a vehicletransporting exclusively LOWSPECIFIC ACTIVITY packagesand surface contaminatedobjects in accordance with173.427(b)(3) must beplacarded. The shipper mustprovide the carrier with allnecessary placards. Properplacarding includes:

(1) Placards must bedisplayed on the front, rearand both sides of the vehicle;

(2) Placards must bedurable, legible, and readilyvisible and must be at leastthree inches from othermarkings; and

(3) Placards must conformto the shape, size, color anddesign requirements specified49 CFR 172.500.

b. Placarding is alsorequired for vehiclestransporting HIGHWAY ROUTE

CONTROLLED QUANTITIES; however,the placard must be placed on asquare background.

8-9. Manifesting.

a. Persons shipping otherthan EXCEPTED QUANTITIES ofradioactive material mustdescribe the material on ashipping paper as per 49 CFR172.200.

b. A shipping paper mustcontain the following:

(1) A hazardous materialentry which must consist ofand/or appear as follows:

(a) Appear as the firstentry on the shipping paper;

(b) Be designated by an“X” in the hazardous materialcolumn (“RQ” may be used in thecase of hazardous substances);or

(c) Be highlighted orentered in a contrasting color.

(2) A shipping descriptionwhich must include:

(a) The basic description- the proper shipping name,h a z a r d c l a s s , a n didentification number (in thatorder);

(b) The total quantity;

(c) The name of eachradionuclide (abbreviations are

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authorized);

(d) Physical and chemicalform (if the material is not inspecial form);

(e) Activity per packagemeasured in SI units followedby curie units in parentheses;

(f) Category of labelapplied (for example,Radioactive White-I);

(g) TI on RadioactiveYellow-II and RadioactiveYellow-III labels;

(h) For a shipment offissile materials, see172.203(d)(7);

(I) Type B package -Certificate of Approval fromNRC or DOE, packageidentification;

( j) Import/exportshipments - U.S. Certificate ofCompetent Authority number;

(k) “Highway RouteControlled Quantity” enteredwith the basic description forsuch shipments;

(l) “Limited Quantity” or“Ltd Qty” entered with thebasic description for suchshipments;

(m) An indication that theshipment is consigned asexclusive use for suchshipments;

(n) LSA-I, LSA-II, LSA-III, SCO-I, or SCO-II for suchshipments; and

(o) An emergency responsetelephone number (see paragraph8-11c).

(3) Each entry must beseparated from the next by acomma. The shipping paper musti n c l u d e a shippingcertification statement wordedexactly as described in 49 CFR172.204(a). The certificationmust also include additionalclauses for some materials andmodes of transportation asdescribed in 49 CFR 172.204.The shipping paper must besigned by the shipper.

(4) When transported bypublic highway, a shippingpaper shall be within thedriver's immediate reach whilehe/she is restrained by the lapbelt and either readily visibleto a person entering thedriver's compartment (that is,NOT in the glove compartment)or in a holder which is mountedto the inside of the door onthe driver's side of thevehicle.

8-10. Hazardous WasteManifesting.

For a shipment of hazardouswaste, which includesradioactive waste, a hazardouswaste manifest must be preparedaccording to 40 CFR 262. TheRCRA definition of hazardous

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waste includes mixed waste butnot radioactive waste (seeChapter 9 for a definition ofmixed waste).

8-11. Emergency ResponseInformation.

a. Persons shipping otherthan EXCEPTED QUANTITIES ofradioactive material mustsupply emergency responseinformation as required in 49CFR 172.600. This emergencyinformation must contain:

(1) The basic descriptionas required by 49 CFR 172.202;

(2) The immediate healthhazards;

(3) The risk of fire orexplosion;

(4) Precautions to betaken in the event of anaccident;

(5) Methods for handlingfires;

(6) Methods for handlingspills or leaks; and

(7) First aid measures.

b. The information must bein English and be located awayfrom the package containing theradioactive material. Theinformation required must bepresented on a shipping paper,in a separate document (forexample, a material safety data

sheet), or in a guidancedocument [40 CFR 172.602(b)].The information must beaccessible to persons enteringthe vehicle.

c. A 24-hour emergencyresponse telephone number mustbe on the shipping paper. Theemergency response number mustbe manned by a person who iseither knowledgeable of theradioactive material and knowsthe proper emergency responseprocedures or has immediateaccess to someone who does.The emergency number must befor either the person makingthe radioactive materialshipment or for a companywilling to accept theresponsibility for emergencyresponse. The person makingthe shipment must ensure thatthe company is capable ofperforming the emergencyresponse necessary.

8-12. Hazmat Employee Training.

a. A hazmat employer isdefined by DOT as a person whouses one or more of itsemployees in connection with,among other things,transporting hazardousmaterials in commerce. Ahazmat employee directlyaffects hazardous materialstransportation safety. It is ah a z m a t e m p l o y e r ’ sresponsibility to ensure thateach of its hazmat employeesreceives training such thathazmat employees can recognize

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and identify hazardousmaterials, know how to respondin an emergency situation, knowself-protection measures, andknow accident preventionmethods (49 CFR 172.700).

b. Hazmat employees shallreceive the training at leastonce every two years. Trainingprovided by employers to complywith OSHA regulations (29 CFR1910.120) or EPA regulations(40 CFR 311.1) may be used tosatisfy DOT’s hazmat employeetraining requirements if thetopics specified in thepreceding paragraph arecovered.

c. Subpart I, “Radiationprotection program.” of 49 CFR172 requires that a hazmatemployee’s annual effective

dose equivalent of occupationalradiation exposure not exceed1.25 rem per three months orfive rem per 12 months (0.125rem per three months or 0.5 remper 12 months for workers underthe age of eighteen). 8-13. Exceptions.

Exceptions exist for nearly allDOT regulations. Theseexceptions are listed in Title49 near each applicable part.One major exception ofimportance is that theInternational Air TransportAssociation (IATA) DangerousGoods Regulations may be usedin place of Title 49 for anyshipment where at least one legof the shipment will be by air.IATA is similar to, but muchsimpler than, Title 49.

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Chapter 9. Waste management.

Radioactive waste management isan important part of aRadiation Protection Program.There are few options fordisposal of radioactive wasteand all are costly. A wellthought out waste managementprogram will make radiationprotection simpler and lessexpensive.

9-1. Regulation of RadioactiveWastes.

a. Oversight Agencies.

(1) The NRC regulatessource, byproduct and specialnuclear material only.Agreement States may includeNORM and NARM within theirjurisdiction. Congressmandated that states dispose ofthe radioactive waste generatedwithin their borders. Thestates formed compacts to allowconstruction of one facilityfor the disposal of waste fromall states within the compact.Compact commissions regulatethe disposal of waste withintheir compact states andcontrol the import and exportof radioactive waste to andfrom their states.

(2) The EPA regulatesradioactive material at CERCLAsites, in air emissions, and in

drinking water. Legislation isunderway to allow EPA toregulate allowable radiationexposure to the public from anyman-made source.

(3) Table 9-1 is a listingof major laws and regulationspertinent to low levelradioactive waste (LLRW) andmixed waste disposal, siteremediation, and operationalpractices. The followingparagraphs describe the variousagencies propounding thoseregulations. This chapter isnot an exhaustive descriptionor listing of all applicablelaws and regulations.Identification of applicablelaws and regulations is a site-specific determination madeonly after full consultationwith a regulatory specialistand Office of Counsel.

b. Department of Army.

(1) The U.S. ArmyIndustrial Operations Command(AIOC), AMSIO-DMW, Rock Island,IL 61299-6000, has beenappointed as the executingagent for disposal of DODradioactive waste. Theexecuting agent is responsiblefor inventorying and reportingall DOD waste disposal. Theexecuting agent also serves asthe POC for the disposalcompacts and operates two DOD

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TABLE 9-1Low Level Radioactive Waste Laws and Regulations

DOT EPA NRC OSHA DOE DOD

Regulatesinterstatetransportationof DOT definedradioactivematerials(>2000 pCi/g).Title 49

Regulatesmixed waste,air and wateremissions.Title 40

Regulatessource,byproduct, andspecialnuclearmaterial; alsoapplies DOTregulations tointrastateshipments ofradioactivematerial. Title 10

Regulatesworker healthand safety. Still appliesold 10 CFR 20regulations. Title 29

Regulatesradioactivematerial on DOEsites andnuclear weaponsmaterials.Title 10

Responsiblefor DODlicensedradioactivematerial andARA authorizedmaterials.AR 385-11

storage facilities forradioactive waste that cannotbe disposed due to compactstatus.

(2) USACE is responsiblefor remediation of radioactivewastes at formerly used defensesites (FUDS), and at thediscretion of the installationcommander, for remediation ofradioactive and mixed wastes onactive and base realignment andclosure (BRAC) listed bases. USACE is also involved withLLRW disposal during other DODinstallation environmentalrestoration actions. USACEdisposal of DOD LLRW wastemust be coordinated through theHTRW-CX. The action will thenbe coordinated with the DODexecuting agent for low-levelradioactive waste disposal.

(3) Non-DOD (for example,RCRA Corrective Action) LLRWwaste disposal will becoordinated with the HTRW-CX.

9-2. Low Level RadioactiveWaste (LLRW).

a. LLRW is defined as allradioactive waste that is nothigh level waste or uranium orthorium mill tailings. Thisdefinition was enacted forpurposes of determining methodsof disposal of LLRW and highlevel radioactive wastes. Mostradioactive waste USACE maymanage is LLRW. LLRW shouldnot be construed to present alow hazard. The hazards ofradioactive wastes aredetermined by the type andquantity of radiation emitted.

b. Mixed Waste.

Mixed waste is defined as wastecomposed of NRC regulatedradioactive materials mixedwith RCRA (ResourceConservation and Recovery Act)listed hazardous wastes, and/orRCRA characteristic hazardouswaste. The radioactivecomponents of mixed waste

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regulated by the NRC aresource, byproduct or specialnuclear material, and thehazardous component of mixedwaste is regulated by EPA. Ahazardous waste is defined in40 CFR 261 as a solid wastewhich exhibits a hazardouscharacteristic, is "listed" inthe regulations, or is amixture of hazardous and solidwastes.

c. Radioactive materialwhich is not source, byproductor special nuclear material isnot regulated by the NRC, butmay be regulated by AgreementStates, depending on the statelaws. Hazardous wastes thatare not RCRA listed orcharacteristic hazardous wastesmay be regulated by the stateas a hazardous waste understate hazardous wastemanagement laws. The statedoes not need to be RCRA-authorized to establish thisauthority. When non-NRCregulated radioactive materialis mixed with RCRA hazardouswaste, or with state listedhazardous waste, or when NRCregulated radioactive materialis mixed with state listedhazardous waste, the waste isconsidered to be combinedwaste, also called co-mingledwaste.

d. The distinction betweenmixed and combined or co-mingled waste is importantbecause the disposal optionsdiffer. There are a number of

disposal options for combinedor co-mingled waste, but only afew options for mixed waste.

e. Agreement States arelisted in Table 4-2. LLRWcompacts are shown on the maplocated in Appendix H.

f. Mixed Waste Amendment.The mixed waste amendment isfound in Section 105 of theFederal Facilities ComplianceAct of 1992. The amendmentcreated a new mixed wasteprovision within RCRA. Theamendment required DOE tosubmit a plan with schedulesfor all applicable permitapplications, constructionactivities and processing ofmixed waste at each of the DOEsites. Any USACE activitydoing work for DOE shouldverify if a plan exists for thesite and if there are anycompliance schedules or permitsin place. Examination ofcompliance schedules shouldinclude evaluating thehazardous portion regulatedunder RCRA. The RCRAcompliance schedules maycontain critical time-lines forUSACE to meet in order to stayin compliance. The mixed wasteamendment also required EPA orEPA authorized states toreceive a copy of the mixedwaste management plan forreview and approval.

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9-3. Elements of a WasteManagement Program.

There are five elements of aradioactive waste managementprogram. These elements are:

a. Material tracking;

b. Waste minimization;

c. Waste recycling;

d. Waste storage; and

e. Waste disposal.

9-4. Material Tracking.

Any project involvingradioactive material will havea radioactive material trackingprogram in effect. Thisprogram will document thearrival on site of theradioactive material, thepackage receipt procedures, anactive inventory of allmaterials and their locationsat all times, all radioactivewaste generated, and the finaldisposal of the radioactivematerial. Radioactive materialwill be tracked using theRecord of Radioactive Materialform (ENG 3309-R). On HTRWsites where there isradioactive contamination, theradioactive material will beentered into a tracking programas the contamination iscontainerized, or remediated.Each container will be labeledas described in Chapter 8, andtracked, from inception until

final disposal at the disposalsite.

9-5. Waste Minimization.

The most effective method ofdealing with radioactive wasteis to not generate it. This isoften the case when usingsealed sources. When workingwith unsealed sources or onHTRW sites this is usually notpossible. Radioactive wastedisposal costs are based on thecubic foot of waste at shallowland burial sites and by thegallon at incinerators, sothere is a financial incentiveto minimize the amount of wasteproduced and the volume ofwaste disposed. Whereradioactive waste is generatedor packaged, waste minimizationtechniques should be used.These techniques includea v o i d i n g e q u i p m e n tcontamination, limiting thespread of contamination,decontamination of items whereit is cost effective, efficientpacking of bulky items andcompaction or supercompactionwhere possible.

9-6. Waste Recycling.

A number of companies willrecycle certain radioactive andmixed wastes. Sealed sourcesare often in demand bycompanies and universities.Radioactively contaminatedmetals can be smelted and castas parts for disposalcontainers for other

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radioactive wastes. If aproject involves recyclableradioactive wastes, contact theHTRW-CX for a POC at therecycling companies.

9-7. Waste Storage.

Due to the status of some lowlevel radioactive waste statecompacts, there may be nodisposal option for someradioactive wastes. Storage onsite in most cases requires NRCor Agreement State licensing ofthe site and is generally notrecommended. If the waste is amixed waste, the RCRA timelimit for storage on-sitewithout a part B permit may bein effect. The US Army hascontracted two facilities forlong term storage ofradioactive wastes. Neitherfacility has a Part B permit,so neither can store mixed,combined or co-mingled wastes.If long term storage is needed,contact the HTRW CX to arrangefor use of the US Armyfacilities.

9-8. Waste Disposal.

a. Radioactive wastes canbe disposed of in the followingways.

(1) An NRC licensedfacility is allowed to releaselimited concentrations ofradionuclides into the air orwater. Small quantities can bedisposed of in a sanitarysewer. Concentrations that can

be disposed of by these methodsare listed in Appendix B of 10CFR 20.

(2) 10 CFR 20 also allowsdisposal of, and incinerationof liquid scintillation fluidsor animal tissue containingtritium or carbon-14 atconcentrations of 0.05microcurie per gram or lesswithout regard to theradioactivity of the medium.Many liquid scintillationcocktails contain toluene orxylene which are RCRA hazardouswastes. The liquidscintillation cocktails thatcontain these, or otherhazardous wastes, must still bedisposed of as hazardouswastes.

(3) NRC licensedradioactive material which isconsidered waste and cannot bedisposed of by the abovemethods, must be disposed of ata licensed LLRW disposalfacility.

b. A classificationsystem has been developed tosegregate LLRW by hazard fordisposal at near surfacedisposal sites. The hazard isbased on the longevity and theradiation emitted. There arecertain requirements to be metfor all classes of LLRW,intended to facilitate handlingand provide protection to thesite personnel, the nearbypublic, and potential intrudersinto the disposal facility.

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LLRW is classified as to thedegree of rigor required forthe disposal method.

(1) The acceptablephysical characteristics ofLLRW and the containers it isdisposed in are determined byconditions on the disposalsite's radioactive materiallicense. Exemptions may beapplied for and are granted ifthere is no increase in thehazards or risk to the publicand environment.

(2) Some LLRW restrictionsapplied at disposal facilitiesinclude the following:

(a) Waste may not bepackaged in cardboard orfiberboard boxes.

(b) Liquid LLRW must besolidified or packaged insufficient absorbent material.Solid LLRW containing liquidshall contain as little freenoncorrosive liquid aspossible, not to exceedone percent by volume.

(c) LLRW must not becapable of detonation,explosion, or any other violentdecomposition under ordinarydisposal unit conditions.

(d) LLRW shall not containor generate quantities of toxicfumes or gases during handling,transport, or disposal.

(e) LLRW must not be

pyrophoric; waste containingpyrophoric materials shall bestabilized or treated to becomea nonflammable waste.

(f) Gaseous LLRW must bepackaged at less than1.5 atmospheres pressure at20 degrees Celsius and eachcontainer will not contain morethan 100 Ci total.

(g) LLRW containinghazardous, biologic, pathogenicor infectious material must betreated to reduce the potentialhazard from the non-radiological materials.

(h) LLRW must possessstructural stability to avoiddegrading the containment andthe site. It will generallymaintain its physicaldimensions and form under theexpected disposal conditions.Conditions to consider inassessing structural stabilityinclude weight of overburden,presence of moisture, microbialactivity, radiation effects,and chemical changes. Thewaste form itself may providestructural stability before orafter processing; or the wastemay be placed in structurallystable containers or structuresfor disposal. Generally, onlythose stabilization media whichhave been evaluated accordingto the stability guidancerequirements of the NRC's LowLevel Licensing Branch,Technical Position on WasteForm, are considered acceptable

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media. Liquid LLRW must beconverted to a form containingas little free-standing andnoncorrosive liquid asreasonably achievable. Thevolumetric content of the LLRWpart of liquid or solid wastewill not exceed 1 percent of asingle container or 0.5 percentof the volume of wasteprocessed to a stable form.Void spaces within the wasteand between the waste and itspackage will be reduced as muchas reasonably possible.

c. Class A LLRW.

(1) Class A LLRW is wastethat does not containsufficient amounts ofradionuclides to be of concernwith respect to migration, longterm active site maintenance,and potential exposure tointruders. Class A LLRW tendsto be stable. Class A LLRW isusually segregated from otherwaste classes at the disposalsite. Class A LLRW must meetthe minimum handlingcharacteristics required anddescribed above.

(2) Class A LLRW hasconcentrations less thancolumns 1 and 4 as shown inTable 9-2, Concentration/Activity Levels for LLRWClassification.

d. Class B.

(1) Class B LLRW must meetmore rigorous standards for

stability than Class A.Class B LLRW is more highlyradioactive than Class A.

(2)Class B LLRW hasconcentrations greater thancolumn 1 and less than column 2as shown in Table 9-2.

e. Class C.

(1) Class C LLRW must meetthe most rigorous standards onwaste form stability andadditional measures at thedisposal facility to protectagainst inadvertent intrusion.

(2) Class C LLRW hasconcentrations greater thancolumn 2 and less than column3, and less than column 5 asshown in Table 9-2.

f. Greater than Class C.

(1) Waste classified asgreater than Class C is notsuitable for near surfacedisposal.

(2) Greater than Class CLLRW has concentrations greaterthan column 5.

9 - 9 . R a d i o n u c l i d eConcentrations.

Concentrations may be measureddirectly or calculated if thereis reasonable assurance ofcorrelation to directmeasurements. Indirect methodsof concentration determinationinclude inference of one

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nuclide concentration from thatof another which is directlymeasured, and materialinventory records. Concentra-

tions may be averaged by weightor by volume.

Table 9-2Concentration/activity levels for LLRW Classification

ConcentrationNuclide

Col. 1 Ci/m3

Col. 2 Ci/m3

Col. 3 Ci/m3

Col.4 Ci/m3

Col. 5 Ci/m3

C-14 0.8 8

C-14 activatedmetal

8 80

Ni-59 activatedmetal

22 220

Nb-94 activatedmetal

0.02 0.2

Tc-99 0.3 3

I-129 0 8

TRU with halflife > 5 yrs.

10nCi/g

100nCi/g

Pu-241 350nCi/g

3500nCi/g

Cm-242 2,000nCi/g

20,000nCi/g

all halflives < 5yrs.

700

H-3 40

Co-60 700

Ni-63 3.5 70 700

Ni-63 activatedmetal

35 700 7000

Sr-90 0.04 150 7000

Cs-137 1 44 4600Mixtures are determined by the sum of the fractions rule.

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Chapter 10. Laser Safety.

As stated in Chapter 2, anyCommand whose personnel areoccupationally exposed to classIIIb or class IV lasers shallhave a Laser Safety Officer(LSO). The LSO shall ensurethat personnel exposure tolaser radiation is kept withinguidelines listed in ANSIZ136.1 and ANSI Z136.3, andthat work with lasers isaccomplished in accordance withOSHA regulations as stated in29 CFR 1926.54, and USACEguidance in EM 385-1-1. Thisshall be accomplished byestablishing and ensuringcompliance with a LaserProtection Program.

10-1. Classifications oflasers.

a. Lasers are classifiedby their hazard capabilities.The ANSI Z136.1 standardaccurately defines theclassifications of lasersdepending on the power outputand light wavelength, but ingeneral the classifications areas follows:

(1) Class I - Cannotproduce hazardous radiation.These devices may contain anembedded class IIIb or class IVlaser.

(2) Class II - Continuousintrabeam exposure may damagethe eye. Momentary intrabeamexposure (<0.25 second) is not

damaging to the eye.

(3) Class III - Can damagethe eye during momentaryintrabeam exposure.

(a) - Class IIIA:intermediate power lasers (1-5mW). Only hazardous forintrabeam viewing.

(b) - Class IIIB:moderate power lasers ( 5-500mW). In general Class IIIBlasers will not be a firehazard, nor are they generallycapable of producing ahazardous diffuse reflection.

(4) Class IV - May damagethe skin as well as the eyeduring momentary intrabeamexposure or exposure to diffusereflection. These lasers may befire hazards and may producelaser generated aircontaminants(ozone) and plasmaradiation.

10-2 Safety Features andLabeling Requirements.

The Department of Health andHuman Services in 21 CFR 1000-1050, the ANSI standards, andUSACE EM 385-1-1 require thatcertain engineered safetyfeatures and labeling be usedwith the different classes oflasers. Table 10-1 cross-references the safety featuresand label requirements for eachclass of lasers. Examples oflaser labels and area postingsare included in Appendix F.

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Lasers may have additionalsafety features or labelingrequirements. Check themanufacturer’s manual for

a d d i t i o n a l l a b e l i n grequirements.

TABLE 10-1Laser Safety Features and Labeling Requirements

Safety Feature Class

Safety Features I II III IV

Protective Housing X X X X

Safety Interlock X X X X

Remote Connector X X

Key Control X X

Emission Indicator X X X

Beam attenuator X X X

Labels I II III IV

Certification and Manufacturer X X X X

Class Designation and Warning Logotype X X X

Aperture Label X X X

Radiation Output X X X

Non-interlocked Protective Housing X X X

10-3. Laser Protection Program.

A Laser Protection Program, asrequired for Commands wherepersonnel may be exposed toclass IIIa, class IIIb or classIV laser radiation shouldconsist of the followingelements:

a. A list of personnelr e s p o n s i b i l i t i e s a n dqualifications,

b. A list of trainingrequirements for operators andbystanders,

c. A description of thetypes and hazard potentials forthe types of lasers used in theCommand,

d. A description of lasersafety measures used in theCommand,

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e. A compendium ofStanding Operating Proceduresfor the lasers used within theCommand,

f. An emergency responseplan.

10-4. OSHA standards.

OSHA 29 CFR 1926.54 addressesworker exposure to non-ionizingradiation. OSHA requires that:

a. Only qualified andtrained personnel work withlaser equipment,

b. Proof of qualificationshall be carried by theoperator,

c. If the potential forexposure to direct or reflectedlaser light above the exposurelimit exists, then workers willbe furnished with acceptableeye protection,

d. Laser work areas mustbe properly posted,

e. Beam shutters and capsmust be utilized,

f. Unattended lasers shallbe shut off,

g. Only mechanical orelectrical means will be usedfor beam alignment; beamalignment will not be made byeye.

h. The beam shall not bedirected at employees,

i. Lasers shall not beused in the rain or in foggyconditions if possible,

j. Each laser shall belabeled to indicate its maximumoutput,

k. Lasers shall be usedabove the heads of personnelwhen possible; and

l. Employees shall not beexposed to light intensitiesabove the exposure limits.

10-5. USACE Standards.

The Army and USACE have adoptedthe current American Conferenceof Governmental IndustrialHygienists (ACGIH) ThresholdLimit Values (TLVs) as thelimits for employee exposure tolasers. The ACGIH TLVs areessentially the same as theANSI Z136.1 standards. TLVs aredependent upon the wavelengthof the light and the durationof exposure. Consult with theCommand Laser ProtectionOfficer to determine the TLVfor each laser used within theCommand.

10-6. Protective eyewear.

Protective goggles may berequired when using somelasers. The protection factorof goggles depends on thewavelength of the laser light

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and the amount of energy thelaser can deposit at the siteof exposure. The exact opticaldensity required for anyspecific laser use scenario maybe calculated using equationsin ANSI Z136.1, or Table 10-2may be used. Goggles must havea label listing the laser

wavelengths for which theyprovide protection, theiroptical density at thosewavelengths, and the amount ofvisible light that the gogglestransmit. The LSO shouldverify the optical densitycalculation.

Table 10-2 Optical Density Requirements

Intensity,Continuous Wave Max.Power Density(watts/cm )2

Optical Density Attenuation Factor

0.01 5 10,000

0.1 6 100,000

1.0 7 1,000,000

10.0 8 10,000,000

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Chapter 11. Radio Frequency(RF) and Microwave Safety.

11-1. DA Limits.

The DOD and DA, in DODI6055.11, have adopted the IEEEC95.1-1991, IEEE Standard forSafety Levels with Respect toHuman Exposure to RadioFrequency (RF) ElectromagneticFields, 3 kHz to 300 GHzmaximum permissible exposure toRF levels. The guidingprinciple is that no practiceshall be adopted or operationconducted involving plannedexposure to RF levels in excessof the applicable Permissible Exposure Limit (PEL).

11-2. USACE Limits.

USACE, in compliance with DODI6055.11, has adopted the IEEEmaximum permissible exposurelevels for a controlled area.These PELs are presented inTable 11-1. Maximum PEL’s foruncontrolled environments arepresented in Table 11-2.

11-3. OSHA Regulations.

OSHA set a radiation protectionguide for non-ionizingr a d i a t i o n , i n c l u d i n gelectromagnetic radiation. Theradiation protection guide is alevel of radiation which shouldnot be exceeded without carefulconsideration of the reasonsfor doing so. The OSHAradiation protection guide is10 mW/cm (milliwatts/square 2

centimeter) power densityaveraged over six minutes, or 1mW-hr/cm energy density2

averaged over 6 minutes. OSHA also requires that astandard radio frequencyradiation hazard sign be usedto notify employees of possibleexposure.

11-4. General Guidance.

a. As with all radiation,only personnel who have beentrained in the safe use of theequipment should work with theequipment. Similarly, onlytrained personnel, usingcalibrated instrumentation,should be used to assess,survey or evaluate non-ionizingradiation fields, personnelexposures and control measuredeterminations.

b. NOTE: Non-ionizingradiation TLVs may not protectagainst electromagneticinterference with cardiacpacemakers. Persons wearingpacemakers should check themanufacturer’s literature toensure TLVs are adequate toavoid interference.

c. The basic dosimetricparameter for RF exposure isthe Specific Absorption Rate(SAR). The SAR of 0.4 watts perkilogram has been set as themaximum exposure for humans.This is a factor of 10 belowthe level of exposuredetermined to potentially causedeleterious effects in humans.

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The PELs are listed in terms ofmeasurable field parametersthat act as a convenientcorrelation to the SAR.

d. There are exceptions tothe listed PELs for certainexposures and situations. Theseare listed in DODI 6055.

11-5. Warning Signs.

a. RF warning signs arerequired to be posted at allaccess points to areas wherelevels exceed the PELs. Postingshould be determined andmaintained by the Safety andOccupational Health Office(SOHO).

b. Where 10 times the PELsare exceeded, other warningdevices, such as flashinglights, audible signals,barriers or interlocks shouldbe used.

c. RF protective clothingshall not be used as a routinemethod of protecting personnelfrom RF levels that exceed thePELs.

11-6. RF Safety Training.

USACE personnel routinelyworking with equipment thatemits RF levels that may exceedthe PELs shall receive trainingfrom the SOHO, addressing:

a. the potential hazardsof RF,

b. procedures andrestrictions to control RFexposures, and

c. their responsibility tolimit their RF exposure.

Timely refresher training in RFsafety shall be incorporatedinto other periodic safetytraining programs.

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Table 11-1Radio Frequency/Microwave Permissible Exposure Limits for

Controlled Environments

Part A-Electromagnetic Fields(f = frequency in MHZ)

Frequency PowerDensity,S(mW/cm )2

ElectricFieldStrength(V/m)

MagneticFieldStrength(A/m)

AveragingTime E , H2 2

or S(minutes)

30 kHz-100 kHz 102, 106 614 163 6

100 kHz-3 MHZ 102,104/f2

614 16.3/f 6

3 MHZ-30 MHZ 900/f ,2

104/f21842/f 16.3/f 6

30 MHZ-100 MHZ 1.0,104/f2

61.4 16.3/f 6

100 MHZ-300 MHZ 1 61.4 0.163 6

300 MHZ-3 GHz f/300 6

3 GHz-15 GHz 10 6

15 GHz-300 GHz 10 616,000/f1.2

The exposure values in terms of electric and magnetic field strengths are the values obtained by spatially averagingvalues over an area equivalent to the vertical cross-section of the human body (projected area).

Part B-Induced and Contact Radio Frequency Currents* Maximum Current (mA)

Frequency ThroughBoth Feet

ThroughEach Foot

Contact

30 kHz-100 kHz 2000f 1000f 1000f

100 kHz-100 MHZ 200 100 100

* It should be noted that the current limits given above may not adequately protect against startle reactions andburns caused by transient discharges when contacting an energized object.

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Part C-Pulsed RF Fields

Frequency Peak ElectricField(kV/m)

Peak Power Density/ Pulsefor Pulse Durations < 100msec. (mW/cm )2

100 kHz - 300 GHz 100 (PEL)(T )/5 (pulse width)avg

Part D-Partial Body Exposures

Frequency Peak Value ofMean Squared

Field (V /m or A /m )2 2 2 2

Equivalent Power Density(mW/cm )2

100 kHz - 300 MHZ <20*E or <20*H2 2

300 MHZ - 6 GHz <20*E or <20*H2 2 <20

6 GHZ - 96 GHZ <20*E or <20*H2 2 <20(f/6000)0.25

96 GHz - 300 GHZ <20*E or <20*H2 2 40

V /m : volts squared / meter squared = E (electric field)2 2

squared.

A /m : amps squared / meter squared = H (magnetic field) squared.2 2

T : average pulse time.avg

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Table 11-2Radio Frequency/Microwave Permissible Exposure Limits for

Uncontrolled Environments

Part A-Electromagnetic Fields(f = frequency in MHZ)

Frequency PowerDensity,S(mW/cm )2

ElectricFieldStrength(V/m)

MagneticFieldStrength(A/m)

AveragingTime E , 2

H or S2

(minutes)

30 kHz-100 kHz 102, 106 614 163 6, 6

100 kHz-134 kHz 102, 104/f2

614 16.3/f 6, 6

134 kHz - 3 MHZ 180/f ,2

104/f2823.8/f 16.3/f f2/0.3, 6

3 MHZ-30 MHZ 180/f ,2

104/f2823.8/f 16.3/f 30, 6

30 MHZ-100 MHZ 0.2,9.4X105/

f3.36

27.5 158.3/f1.1668

30,0.0636f1337

100 MHZ-300 MHZ 0.2 27.5 0.0729 30, 30

300 MHZ-3 GHZ - f/1500 30, -

3 GHZ-15 GHZ - f/1500 90,000/f

15 GHZ-300 GHZ - 10 616,000/f1.2

The exposure values in terms of electric and magnetic field strengths are the values obtained by spatially averagingvalues over an area equivalent to the vertical cross-section of the human body (projected area).

Part B-Induced and Contact Radio Frequency Currents* Maximum Current (mA)

Frequency ThroughBoth Feet

ThroughEach Foot

Contact

30 kHz-100 kHz 900f 450f 450f

100 kHz-100 MHZ 90 45 45

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* It should be noted that the current limits given above may not adequately protect against startle reactions andburns caused by transient discharges when contacting an energized object

Part C-Pulsed RF Fields

Frequency Peak Electric Field(kV/m)

Peak Power Density/Pulse for PulseDurations < 100msec. (mW/cm )2

100 kHz - 300 GHZ 100 PEL)(T )/5 (pulseavg

width)

Part D-Partial Body Exposures

Frequency Peak Value of MeanSquared Field (V /m or A /m )2 2 2 2

Equivalent PowerDensity (mW/cm )2

100 kHz - 300 MHZ <20*E or <20*H2 2

300 MHZ - 6 GHZ <20*E or <20*H2 2 <4

6 GHz - 96 GHZ <20*E or <20*H2 2 f/1500

96 GHz - 300GHZ

<20*E or <20*H2 2 20

V /m : volts squared / meter squared = E (electric field)2 2

squared.

A /m : amps squared / meter squared = H (magnetic field) squared.2 2

T : average pulse time.avg

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Appendix A. References.

A-1. DA and DOD references.(Most current revisions)

DODI 6055.8 OccupationalRadiation Protection Program

DODI 6055.11 Protection of DODPersonnel from Exposure toRadio frequency Radiation andMilitary Exempt Lasers

AR 40-5 Preventive Medicine

AR 11-34 Respiratory Protection

AR 40-13 Medical Support-Nuclear/Chemical Accidents andIncidents

AR 40-14 Control and RecordingProcedures for Exposure toIonizing Radiation andRadioactive Materials

AR 50-5 Nuclear Surety

AR 50-7 Army Reactor Program

A R 200-1 EnvironmentalProtection and Enhancement

AR 385-11 Ionizing RadiationProtection

AR 385-32 Protective Clothingand Equipment

AR 385-40 Accident Reportingand Records

AR 385-80 Nuclear ReactorHealth and Safety

AR 755-15 Disposal of UnwantedRadioactive Material

EM 385-1-1 Safety and HealthRequirements Manual

ER 385-1-80 Ionizing RadiationProtection

ER 385-1-92 USACE Safety andOccupational Health Documentfor Hazardous, Toxic andRadiological Waste (HTRW)Activities

TM 3-220 C h e m i c a l ,Biological and RadiologicalDecontamination

TM 3-261 Handling and Disposalof Unwanted RadioactiveMaterials

TM 38-250 Packaging andHandling: Hazardous Materials

TM 55-315 TransportabilityGuidance for the Safe Transportof Radioactive Materials

FM 3-15 Nuclear Accident andContamination Control

USAIRDP U.S. Army IonizingRadiation Dosimetry ProgramCustomer Handbook

A-2. NRC Reg. Guides.

RG 1.86 Termination ofOperating licenses for NuclearReactors. 6/74

RG 8.7 Instructions for

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recording and ReportingOccupational Radiation ExposureData. (6/92)

RG 8.8 Information Relevant toEnsuring that OccupationalExposures at Nuclear PowerStations will be ALARA. (6/78)

RG 8.9 Acceptable Concepts,Models, Equations andAssumptions for a Bioassayprogram. 1993

RG DG-8009 Interpretation ofBioassay Measurements (5/95)

RG App X. Guidance on Complyingwith New Part 20 Requirements.1992

RG 8.10 Operating philosophyfor Maintaining OccupationalRadiation Exposure ALARA.(9/75)

RG 8.13 Instruction ConcerningPrenatal Radiation Exposure.(3/75)

RG 8.25 Air Sampling in theWorkplace. (6/92)

RG 8.29 Instruction ConcerningRisks from OccupationalRadiation Exposure. (7/81)

RG DG-8012 (Draft Revision 1 toRG 8.29) Instruction ConcerningRisks from OccupationalExposure (3/95)

RG 8.33 Quality ManagementProgram. (10/91)

RG 8.34 Monitoring Criteria andMethods to CalculateOccupational Radiation Doses.(7/92)

RG 8.36 Radiation Doses to theEmbryo/Fetus. (7/92)

RG 10.7 Guide for thePreparation of Applications forLicenses for Laboratory andIndustrial Use of SmallQuantities of ByproductMaterial. (8/79)

RG 10.8 Guide for thePreparation of Applications forMedical Use Programs. (8/87)

FC 407-4 Guide for thePreparation of Applications forLicenses for the Use of SealedSources in Portable GaugingDevices. (1/85)

A-3. NRC Information notices.

IN 80-32 Clarification ofCertain Requirements forExclusive Use Shipments ofRadioactive Materials. 1980

IN 86-54 Criminal Prosecutionof a Former RadiationProtection Officer WhoWillfully Directed anUnqualified Individual toPerform Radiography. 1986

IN 89-25 Unauthorized Transferof Ownership or Control ofLicensed Activities. 1989

IN 90-09 Extended Interim

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Storage of Low-LevelRadioactive Waste by Fuel Cycleand Materials Licensees. 1990

IN 90-35 Transportation of TypeA Quantities of Non-FissileRadioactive Materials. 1990

IN 91-03 Management of WastesContaminated with RadioactiveMaterials. 1991

IN 91-23 Accidental RadiationOverexposures to Personnel Dueto Industrial RadiographyA c c e s s o r y E q u i p m e n tMalfunctions. 1991

IN 91-49 Enforcement of SafetyRequirements for Radiographers.1991

IN 91-71 Training andSupervision of IndividualsSupervised by an AuthorizedUser. 1991

IN 93-30 NRC Requirements forEvaluation of Wipe TestResults; Calibration of CountRate Survey Instruments. 1993

IN 94-21 RegulatoryRequirements When No OperationsAre Being Performed. 1994

A-4. NRC policy and guidancedirectives.

PG 2-07 Standard Review Planfor Applications for the Use ofSealed Sources in PortableGauging Devices. 1994

A-5. Code of FederalRegulations.

Title 10 CFR ‘Energy’ Chapter1, Nuclear RegulatoryCommission

Title 21 CFR ‘Food and Drugs’ Title 29 CFR ‘Labor’

Title 40 CFR ‘Protection ofEnvironment’

Title 49 CFR ‘Transportation’

A-6. Standards and otherguidance.

ACGIH Threshold Limit Valuesand Biological Indices.

ANSI Z136.1, ‘American NationalStandard for Safe Use ofLasers’.

ANSI Z136.3, ‘Safe Use ofLasers in Health CareFacilities;’.

IEEE C95.1-1991, IEEE Standardfor Safety Levels with Respectto Human Exposure to RadioFrequency electromagneticFields, 3kHz to 300 Ghz.

IEEE C95.3-1991, ‘IEEERecommended Practice for theMeasurement of PotentiallyHazardous ElectromagneticFields-RF and Microwave’.

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Appendix B. Definitions.

ABSORBED DOSE - The amount ofenergy imparted to matter byionizing radiation per unitmass of irradiated material.(See Rad)

ABSORPTION - The phenomenon bywhich radiation imparts some orall of its energy to anymaterial through which itpasses.

ACTIVITY - The number ofnuclear disintegrationsoccurring in a given quantityof material per unit time. (Seecurie)

ALPHA PARTICLE - A stronglyionizing particle emitted fromthe nucleus during radioactivedecay having a mass and chargeequal in magnitude to a heliumnucleus, consisting of 2protons and 2 neutrons with adouble positive charge.

ALPHA RAY - A stream of fast-moving helium nuclei (alphaparticles), a strongly ionizingand weakly penetratingradiation.

ANNIHILATION (Electron) - Aninteraction between a positiveand negative electron; theirenergy, including rest energy,being converted intoelectromagnetic radiation(annihilation radiation).

ANNUAL LIMIT OF INTAKE (ALI) -Means the derived limit for the

amount of radioactive materialtaken into the body of an adultworker by inhalation oringestion a year.

ATOM - Smallest particle of anelement which is capable ofentering into a chemicalreaction.

BACKGROUND RADIATION - Ionizingradiation arising fromradioactive material other thanthe one directly underconsideration. Backgroundradiation due to cosmic raysand natural radioactivity isalways present. There may alsobe background radiation due tothe presence of radioactivesubstances in other parts ofthe building, in the buildingmaterial itself, etc.

BETA PARTICLE - Chargedparticle emitted from thenucleus of an atom, having amass and charge equal inmagnitude to that of theelectron.

BETA RAY - A stream of highspeed electrons or positrons ofnuclear origin more penetratingbut less ionizing than alpharays.

B R E M S S T R A H L U N G -Electromagnetic (x-ray)radiation associated with thedeceleration of chargedparticles passing throughmatter. Usually associatedwith energetic beta emitters(for example, phosphorus-32).

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CALIBRATION - Determination ofvariation from standard, oraccuracy, of a measuringinstrument to ascertainnecessary correction factors.

COMMITTED DOSE EQUIVALENT (CDE)- (H ) Means the doseT,50

equivalent to organs or tissuesof reference (T) that will bereceived from an intake ofradioactive material by anindividual during the 50 yearperiod following the intake.

COMMITTED EFFECTIVE DOSEEQUIVALENT (CEDE) - (H ) Isg,50

the sum of the products of theweighting factors applicable toeach of the body organs ortissues that are irradiated andthe Committed Dose Equivalentto these organs or tissues.

CONTAMINATION, RADIOACTIVE -Deposition of radioactivematerial in any place where itis not desired, andparticularly in any place wherethe presence may be harmful.

COUNT (Radiation Measurements)- The external indication of adevice designed to enumerateionizing events. It may referto a single detected event orto the total registered in agiven period of time. The termis often erroneously used todesignate a disintegration,ionizing event, or voltagepulse.

CRITICAL ORGAN - That organ ortissue, the irradiation of

which will result in thegreatest hazard to the healthof the individual or his or herdescendants.

CURIE - The quantity of anyradioactive material in whichthe number of disintegrationsis 3.700 x 10 per second.10

Abbreviated Ci.Millicurie - One-thousandthof a curie (3.7 x 107

disintegrations per second).Abbreviated mCi.Microcurie - One-millionth ofa curie (3.7 x 104

disintegrations per second).Abbreviated µCi.Picocurie - One-millionth ofa microcurie (3.7 x 10-2

disintegrations per second or2.22 disintegrations perminute). Abbreviated pCi.

DECAY, RADIOACTIVE -Disintegration of the nucleusof an unstable nuclide by thespontaneous emission of chargedparticles and/or photons.

DECLARED PREGNANT WORKER -Means a women who hasvoluntarily informed heremployer, in writing, of herpregnancy and the estimateddate of conception.

DEEP DOSE EQUIVALENT (DDE) -(H ) Which applies to externald

whole-body exposure, is thedose equivalent at a tissuedepth of 1 cm (1000 mg/cm ).2

DERIVED AIR CONCENTRATIONS(DAC) - Means the concentration

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of a given radionuclide in airwhich, if breathed by thereference man for a workingyear of 2,000 hours underconditions of light work(inhalation rate 1.2 m /hr),3

results in an intake of oneALI.

DETERMINISTIC (NON-STOCHASTICEFFECTS) - Means healtheffects, the severity of whichvaries with dose and for whicha threshold is believed toexist. Radiation-inducedcataract formation is anexample of a deterministiceffect (also called a non-stochastic effect).

DOSE - A general term denotingthe quantity of radiation orenergy absorbed in a specifiedmass. For special purposes, itmust be appropriately qualified(for example, absorbed dose).

DOSE, ABSORBED - The energyimparted to matter by ionizingradiation per unit mass ofirradiated material at theplace of interest. The unit ofabsorbed dose is the rad (orprefixed forms of the unit suchas millirad); which is100 ergs/gram. The SI unit forthe rad is the gray. 1 gray =100 rads.

DOSE, EQUIVALENT - A quantityused in radiation protectionexpressing all radiation on acommon scale for calculatingthe effective absorbed dose.The unit of dose equivalent is

the rem, which is numericallyequal to the absorbed dose inrads multiplied by certainmodifying factors such as thequality factor, thedistribution factor, etc.

EFFECTIVE DOSE EQUIVALENT (EDE)- (H ) Is the sum of theE

products of the dose equivalentto organ or tissue (H ) and theT

weighting factors (W )Tapplicable to each of the bodyorgans or tissues that areirradiated.

EFFICIENCY, INTRINSIC - Ameasure of the probability thata count will be recorded whenradiation is incident on adetector. Usage variesconsiderably so it is well tomake sure which factors(window, transmission,sensitive volume, energydependence, etc.) are includedin a given case.

EFFICIENCY, ABSOLUTE - Ameasure of the probability thata count will be recorded whenradiation is emitted by thesource. Absolute efficiencyincludes intrinsic efficiency,but also includes geometricfactors.

ELECTRON - Negatively chargedelementary particle which is aconstituent of every neutralatom. Its unit of negativeelectricity equals 4.8 x 10-19

coulombs. Its mass is 0.00549atomic mass units.

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ELECTRON CAPTURE - A mode ofradioactive decay involving thecapture of an orbital electronby its nucleus. Capture fromthe particular electron shellis designated as "K-electroncapture," "L-electron capture,"etc.

ELECTRON VOLT - A unit ofenergy equivalent to the amountof energy gained by an electronin passing through a potentialdifference of 1 volt.Abbreviated eV. Largermultiple units of the electronvolt frequently used are: keVfor thousand or kiloelectronvolts, MeV for million electronvolts and BeV for billionelectron volts.

EXPOSURE - A measure of theionization produced in air by xor gamma radiation. It is thesum of the electrical chargeson all ions of one signproduced in air when allelectrons liberated by photonsin volume element of air arecompletely stopped in air,divided by the mass of air inthe volume element. Thespecial unit of exposure is theroentgen.

EXTREMITY - Means hand, elbow,arm below the elbow, foot,knee, or leg below the knee.

EYE DOSE EQUIVALENT (LDE) -Applies to the externalexposure of the lens of the eyeand is taken as the doseequivalent at a tissue depth of

0.3 centimeter (300 mg/cm ).2

FILM BADGE - A packet ofphotographic film used for theapproximate measurement ofradiation exposure forpersonnel monitoring purposes.The badge may contain two ormore films of differingsensitivity, and it may containfilters which shield parts ofthe film from certain types ofradiation.

GAMMA RAY - Very penetratingelectromagnetic radiation ofnuclear origin. Except fororigin, identical to x-ray.

GEIGER-MUELLER (G-M) COUNTER -Highly sensitive gas-filleddetector and associatedcircuitry used for radiationdetection and measurement.

GENETIC EFFECT OF RADIATION -Inheritable changes, chieflymutations, produced by theabsorption of ionizingradiation. On the basis ofpresent knowledge these effectsare purely additive, and thereis no recovery.

HALF-LIFE, BIOLOGICAL -(B )1/2

The time required for the bodyto eliminate one-half of anadministered dose of anysubstance by the regularprocesses of elimination. Thistime is approximately the samefor both stable andradionuclides of a particularelement.

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HALF-LIFE, EFFECTIVE -(E )1/2

Time required for a radioactivenuclide in a system to bediminished 50 percent as aresult of the combined actionof radioactive decay andbiological elimination.E = (B x T )/(B + T )1/2 1/2 1/2 1/2 1/2

HALF-LIFE, RADIOACTIVE - (T )1/2

Time required for a radioactivesubstance to lose 50 percent ofits activity by decay. Eachradionuclide has a unique half-life.

HALF VALUE LAYER (Halfthickness) - The thickness ofany specified materialnecessary to reduce theintensity of an x-ray or gammaray beam to one half itsoriginal value.

HEALTH PHYSICS - The scienceconcerned with recognition,evaluation and control ofhealth hazards from ionizingand non-ionizing radiation.

HIGH RADIATION AREA - Means anarea accessible to individuals,in which radiation levels couldresult in an individualreceiving a dose equivalent inexcess of 0.1 rem (1 mSv) in 1hour at 30 centimeters from theradiation source or from anysurface that the radiationpenetrates.

INVERSE SQUARE LAW - Theintensity of radiation at anydistance from a point sourcevaries inversely as the square

of that distance. For example:If the radiation exposure is100 R/hr at 1 inch from asource, the exposure will be0.01 R/hr at 100 inches.

ION - Atomic particle, atom, orchemical radical bearing anelectrical charge, eithernegative or positive.

IONIZATION - The process bywhich a neutral atom ormolecule acquires either apositive or a negative charge.

IONIZATION CHAMBER - Aninstrument designed to measurethe quantity of ionizingradiation in terms of thecharge of electricityassociated with ions producedwithin a defined volume.

IONIZATION, SPECIFIC - Thenumber of ion pairs per unitlength of path of ionizingradiation in a medium (forexample, per centimeter of airor per micron of tissue).

IONIZING RADIATION - Anyelectromagnetic or particulateradiation capable of producingions, directly or indirectly,in its passage through matter.

ISOTOPES - Nuclides having thesame number of protons in theirnuclei, and hence having thesame atomic number, butdiffering in the number ofneutrons, and therefore in themass number. Almost identicalchemical properties exist

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between isotopes of aparticular element.

MILLIROENTGEN (mR) - Asubmultiple of the roentgenequal to one one-thousandth(1/1000th) of a roentgen.

MONITORING, RADIOLOGICAL -Periodic or continuousdetermination of the amount ofionizing radiation orradioactive contaminationpresent in an occupied regionas a safety measure forpurposes of health protection.For example, Area Monitoring:Routine monitoring of the levelof radiation or of radioactivecontamination of any particulararea, building, room orequipment. PersonnelMonitoring: Monitoring anypart of an individual, or anypart of his clothing (SeeRadiological Survey).

NEUTRON - Elementary particlewith a mass approximately thesame as that of a hydrogen atomand electrically neutral. Ithas a half-life in minutes anddecays in a free state into aproton and an electron.

NUCLIDE - A species of atomcharacterized by its massnumber, atomic number, andenergy state of its nucleus,provided that the atom iscapable of existing for ameasurable time.

OCCUPATIONAL EXPOSURE: Theexposure received by an

individual in a restricted areaor in the course of employmentin which the individual'sassigned duties involveexposure to ionizing radiationor radioactive material fromlicensed or unlicensed sourcesof radiation, whether in thepossession of the licensee oranother person. Occupationalexposure does not includeexposure to backgroundradiation, as a patient inmedical practices, fromvoluntary application inmedical programs, or as amember of the general public.

PLANNED SPECIAL EXPOSURE (PSE)- Means an infrequent exposureto radiation, separate from andin addition to the annual NRC(Tier 1)dose limit.

PROTECTIVE BARRIERS - Barrierso f radiation absorbingmaterial, such as lead,concrete, plaster, and plastic,that are used to reduceradiation exposure.Protective Barriers,Primary:Barriers sufficient toattenuate the useful beam tothe required degree.Protective Barriers, Secondary:Barriers sufficient toattenuate stray or scatteredradiation to the requireddegree.

RADIATION - 1. The emission andpropagation of energy throughspace or through a materialmedium in the form of waves;for instance, the emission and

EM 385-1-80 30 May 97

B-7

propagation of electromagneticwaves, or of sound and elasticwaves. 2. The energypropagated through a materialmedium as waves; for example,energy in the form ofelectromagnetic waves or ofelastic waves. The term"radiation" or "radiantenergy," when unqualified,u s u a l l y r e f e r s t oelectromagnetic radiation.Such radiation commonly isclassified according tofrequency as Hertzian,infrared, visible (light),ultraviolet, x-ray, and gammaray. 3. By extension,corpuscular emissions, such asalpha and beta radiation, orrays of mixed or unknown type,as cosmic radiation.

RADIATION AREA - Means an area,accessible to individuals, inwhich radiation levels couldresult in an individualreceiving a dose equivalent inexcess of 0.005 rem (0.05 mSv)in 1 hour at 30 centimeters.

RADIATION SURVEY - Evaluationof the radiation hazardsincident to the production, useor existence of radioactivematerials or other sources ofradiation under a specific setof conditions. Such evaluationcustomarily includes a physicalsurvey of the disposition ofmaterials and equipment,measurements or estimates ofthe levels of radiation thatmay be involved, and asufficient knowledge of

processes using or affectingthese materials to predicthazards resulting from expectedor possible changes inmaterials or equipment.

RADIONUCLIDE - A nuclide withan unstable ratio of neutronsto protons placing the nucleusin a state of stress. In anattempt to reorganize to a morestable state, it may undergovarious types of rearrangementthat involve the release ofradiation.

RADIOTOXICITY - Term referringto the potential of an isotopeto cause damage to livingtissue by absorption of energyfrom the disintegration of theradioactive material introducedinto the body.

R E L A T I V E B I O L O G I C A LEFFECTIVENESS (RBE) - For aparticular living organism orpart of an organism, the ratioof the absorbed dose of areference radiation thatproduces a specified biologicaleffect to the absorbed dose ofthe radiation of interest thatproduces the same biologicaleffect.

REM - The special unit of doseequivalent. The doseequivalent in rems isnumerically equal to theabsorbed dose in radsmultiplied by the qualityfactor, distribution factor,and any other necessarymodifying factors.

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B-8

ROENTGEN (R) - The amount of Xor gamma radiation below 3 MeVin energy which produces 2.58E-4 coulombs per kilogram (C/kg)of dry air. The roentgen is thespecial unit of exposure.

SCINTILLATION COUNTER - Acounter in which light flashesproduced in a scintillator byionizing radiation areconverted into electricalpulses by a photomultipliertube.

SHALLOW DOSE EQUIVALENT (SDE) -(H ) Which applies to theS

external exposure of the skinor an extremity, is taken asthe dose equivalent at a tissuedepth of 0.007 centimeters (7mg/cm ) averaged over an area2

of 1 square centimeter.Shallow Dose Equivalent, WholeBody (WB) means for purposes ofexternal exposure, head, trunk(including male gonads), armsabove the elbow or legs abovethe knee. Shallow DoseEquivalent, Maximum Extremity(ME) means for purposes ofexternal exposure, arms belowthe elbow or legs below theknee.

SHIELDING MATERIAL - Anymaterial which is used toabsorb radiation and thuseffectively reduce theintensity of radiation, and insome cases eliminate it. Lead,concrete, aluminum, water, andplastic are examples ofcommonly used shieldingmaterial.

SIEVERT - The SI unit of doseequivalent, 1 sievert (Sv)equals 100 rem.

SMEAR (Smear or Swipe Test) - Aprocedure in which a swab, forexample,, a circle of filterpaper, is rubbed on a surfaceand its radioactivity measuredto determine if the surface iscontaminated with looseradioactive material.

SPECIFIC ACTIVITY - Totalradioactivity of a givennuclide per gram of a compound,element or radioactive nuclide.

STOCHASTIC EFFECT - Meanshealth effects that occurrandomly and for which theprobability of the effectoccurring, rather than itsseverity, is assumed to be alinear function of dose withoutthreshold. Hereditary effectsand cancer incidence areexamples of stochastic effects.

TOTAL EFFECTIVE DOSE EQUIVALENT(TEDE) - Means the sum of theDeep Dose Equivalent (forexternal exposures) and theCommitted Effective DoseEquivalent (for internalexposures).

TOTAL ORGAN DOSE EQUIVALENT(TODE) - Means the sum of theDeep Dose Equivalent (H ) andd

the Committed Dose Equivalent(H ) to any individual organT,50

or tissue, other than the lensof the eye, being equal to 50rems (0.5 Sv).

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B-9

THERMOLUMINESCENT DOSIMETER - Adosimeter made of certaincrystalline material which iscapable of both storing afraction of absorbed ionizingradiation and releasing thisenergy in the form of visiblephotons when heated. Theamount of light released can beused as a measure of radiationexposure to these crystals.

VERY HIGH RADIATION AREA -Means an area, accessible toindividuals, in which radiationlevels could result in anindividual receiving anabsorbed dose in excess of 500rads (5 grays) in 1 hour at ameter from a radiation sourceor from any surface that theradiation penetrates.

WEIGHTING FACTORS (W ) - For anT

organ or tissue (T) is theproportion or the risk of

stochastic effect resultingfrom irradiation of that organor tissue of the total risk ofstochastic effect when thewhole body is irradiateduniformly.

X-RAYS - Penetratingelectromagnetic radiationshaving wave lengths shorterthan those of visible light.They are usually produced bybombarding a metallic targetwith fast electrons in a highvacuum. In nuclear reactionsit is customary to refer tophotons originating in thenucleus as gamma rays, andthose originating in theextranuclear part of the atomas x-rays. These rays aresometimes called roentgen raysafter their discoverer, W.C.Roentgen.

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C-1

Appendix C. Sample StandingOperating Procedure (SOP) forUsing a Portable Gauge onLocation.

OPERATOR CHECKLIST

Completed use log (Checked-out)? _____

O p e r a t o r t r a i n i n gcurrent?___

Wearing dosimetry? ____

Licenses, permits, orderscomplete? ____

EQUIPMENT CHECKLIST

Equipment in proper carryingcase? _____

Operating Instructions incase? _____

Copy of license in case? _____

Copy of source certificate incase? _____

Emergency Procedures incase? _____

Copy of latest leak test incase? _____

Survey meter? _____

Survey meter operability andbatteries checked? _____

Area signs? _____

TRANSPORTATION CHECKLIST

Shipping papers next todriver? _____

Emergency procedures next todriver? _____

Packaging correct? _____

Type A package certificate incase? _____

Shipping labels?

White-I (<0.5 mR/hr onsurface) _____

Yellow-II(TI < 1 mR/hr ata meter & 0.5 to 50 mR/hr onsurface) _____

Yellow-III (TI > 1 mR/hr &< 50 mR/hr on surface) _____

Markings? _____

Placards? _____

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C-2

SOP

. Ensure all necessaryequipment is assembled, inworking order, with up-to-date calibrations, leaktests etc.

. Ensure all paperwork fortransport and use of theequipment at the projectsite is complete.

. Package and load theequipment for shipment tothe site. Ensure thatequipment is secure in thetransport vehicle.

. Ship equipment to thesite.

. Upon arrival at the site,inventory equipment toensure no loss.

. Source should be lockedin case when not in use.

. Shipping case should be ina locked storage location

when not under the directphysical surveillance ofthe authorized user.

. Mark off and postrestricted zone(s) whereequipment will be used.

. Perform gauge test.

. Pack up equipment.

. Perform operational checkof survey meter with checksource.

. Perform sweep with surveymeter to ensure no loss ofradioactive material.

. Move to next test locationon site.

. Package and load theequipment for shipmenthome.

. Upon return inventoryequipment to ensure noloss, and secure equipment.

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D-1

Appendix D. X-Ray FluorescenceLead Analysis Devices.

D-1. Description.

X-ray fluorescence analysis isan acceptable method formeasuring the lead content inpainted surfaces. It is aclean, non-destructive testingtechnique which providesimmediate results. X-rayfluorescence analysis devices(XRFs) employ a sealed sourceof radioactive material.Unfortunately, the regulationof XRFs is permeated withinconsistencies. For example,many models of XRFs contain asealed NARM source which is notregulated by the U.S. NuclearRegulatory Commission (NRC) butwhich may be regulated by anAgreement State (AS).Additionally, XRFs may be

either generally licensed (G),specifically licensed (S), orboth (B) (which, actually,means either generally licensedor specifically licensed - thisis left to the discretion ofthe licensing agency which hasjurisdiction). Prior topurchasing or renting an XRF,the agency which hasjurisdiction in the proposeduse location (either the NRC oran AS) should be contacted tod e t e r m i n e r e g u l a t o r yrequirements.

D-2. Dose Potential.

a. Most persons are notaware that radiation dose-ratesfrom XRFs can be significant.Dose-rates, with the shutteropen and in the unattenuatedbeam, for selected XRFs aregiven in Table D-1.

Table D-1XRF Instruments

DEVICE(Model)

ISOTOPE ACTIVITY(mCi)

SURFACE(mR/hr)

@ 12 INCHES(mR/hr)

WarringtonMicrolead I (G) Cobalt-57 10.8 180 6.0

Niton XLModel 309 (S) Cadmium-109 10 (Not available) 10.44

Texas NuclearMetallurgist (B)

Iron-55Cadmium-109

455

2900232

5050

Scitec FA1C (S)Cobalt-57 40 (Not available) 29.3

Texas NuclearProducts Model

9290 (B)

Iron-55Cadmium-109

Americium-241Curium-244

1001010100

375,00013,0001,0009,600

188141

10

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D-2

b. According to theRegistry of Radioactive SealedSources and Devices, the doserate on the surface of theWarrington Microlead I (adevice which may be generallylicensed) is 5 mR/hr with theshutter closed. The need forextremity monitoring (that is,finger or wrist TLDs) should beevaluated for users of XRFs.

D-3. NRC Requirements.

a. Whether an XRF isg e n e r a l l y l i c e n s e d ,specifically licensed or evenif the device is rented, eachuser of an XRF has distinctresponsibilities. Pursuant toNRC and AS regulations, anyperson who uses an XRF:

(1) shall assure that alllabels on the device aremaintained;

(2) shall assure that itis tested for leakage ofradioactive material atrequired intervals;

(3) shall assure properoperation of the on-offmechanism, if any;

(4) shall suspendoperation of the XRF uponoccurrence of (or an indicationof) failure or damage to theshielding or the on-offmechanism;

(5) shall suspendoperation of the XRF upon

detection of 0.005 microcuriesor more of removableradioactive material;

(6) shall neither abandonnor export the XRF;

(7) shall not transfer theXRF to a general licenseeexcept where the device remainsin use at a particular locationand, when in storage, is in theoriginal shipping container;and,

(8) shall report radiationincidents, theft, or loss.

D-4. Specific Licensees.

a. An XRF specificlicensee, or a person who rentsa specifically licensed XRF,will have to fulfill radiationsafety and XRF operationtraining requirements. Aneight hour course will satisfymost regulatory agencies. Thecourse may be provided by theXRF manufacturer, a consultant,or you may contact the HTRW-CXto discuss training needs.

b. There may be notraining requirements for anXRF general licensee. In thissituation, it is stronglyrecommended that XRF operatorsare at least made aware of therudiments of radiation safetyand XRF operation in order toensure that occupational dosesand doses to the general publicare kept ALARA.

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D-3

D-5. Safety mechanisms.

a. The engineering safetymechanisms differ significantlyfrom device to device. Forexample, both the Scitec FA1Cand the Texas NuclearMetallurgist must be manuallyoperated to place the source inthe open and closed positions.Neither requires a sample to bein place to expose the source.

b. Conversely, theWarrington Microlead I, theNiton XL Model 309, and theRadiation Monitoring Devices,Inc. Model LPA-1 require theface plate of the probe to bepressed against a hard surface

before the source can beexposed. The RadiationMonitoring Devices, Inc. ModelLPA-1 also has two independentcircuits which must indicatethe same shutter positionstatus for the system tooperate.

c. Users of XRFs must beaware that these devices havevarying safety mechanisms.Prior to use, a person shouldknow how the shutter operates,whether the device has anyalarms and what those alarmsindicate, and what steps totake in the event of a powerfailure.

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E-1

Appendix E. Rules of Thumb andConversions.

E-1. Rules of Thumb.

Alpha particle cannot penetratea piece of paper or the deadlayer of skin.

Beta particle can not penetratea book.

Beta particle Average Energy E=1/3 E .max

Beta particle dose rate isabout 300 R/hr per mCi.

Gamma exposure at 1 foot isabout 6*Ci*E, where E is inMeV.

Gamma exposure is reduced to1/4 by doubling the distancefrom the source.

The activity of a nuclide isreduced to less than 1% after 7Half lives.

The activity of a nuclide isreduced to less than 0.1% after10 Half lives.

1 gram of Radium-226 emits 1 Ci(3.7E10 dps) of radiation.

The half value layer for Lead

for 1 MeV photons is about 1cm.

The half value layer for Leadfor 1 MeV photons is about 1cm.

E-2. Conversions.

1 in = 6.4516 cm2 2

1 ft = 0.0929 m2 2

1 eV = 1.6021 x 10 joules-19

(absolute)

1 erg = joules (absolute)10-7

1 ft = 0.3048 m

1 lb = 453.952 gm

1 Ci = 3.7 x 10 becquerel10

1 Ci = 3.7 x 1010

disintegration/sec

1 R = 2.58 x 10 C/kg of air-4

1 rad = 0.01 J/kg

1 dpm = 4.505 x 10 mCi.-10

1 ft = 2.832 x 10-2 m3 3

1 ft = 7.481 gal3

55 gal = 7.35 ft3

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F-1

Appendix F. Signs, Labels and Postings.

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F-2

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G-1

Appendix G. Radon.

G-1. What is Radon?

Radon-222 (or “radon”) is anaturally-occurring, chemicallyinert, radioactive gas. It isodorless, invisible, andwithout taste; thus, it cannotbe detected with the humansenses. Radon can move easilythrough very small spaces (suchas those between particles ofsoil and rock) and it ismoderately soluble in water.

Radon is produced from theradioactive decay of theelement radium. Radium is adecay product of the naturallyoccurring elements uranium andthorium. Radon has a half-lifeof 3.8 days and, therefore, hasenough time to diffuse throughdry, porous soils or to betransported in water for aconsiderable distance before itdecays.

The health hazard associatedwith radon itself is smallsince the majority of the radonthat is inhaled is alsoexhaled. Radon decays,however, into four daughterproducts which can attachthemselves to dust particles inthe air. When these dustparticles are inhaled, they maybe trapped in the lungs andirradiate the lung tissue.Lung cancer is the only knownhealth hazard associated withexposure to elevated levels of

radon gas.

G-2. EPA’s Action Level.

In December 1984, the Watra’shome in Pennsylvania drewnational attention when it wasaccidentally discovered to havea radon level of > 2000picocuries per liter of air(pCi/l). Scientistsinvestigating the homedetermined that naturallyoccurring radon in the soilresulted in the extremely highindoor radon level. Soon afterthis discovery, EPA effortswere underway to researchindoor radon levels nationwide.In 1986, EPA issued “ACitizen’s Guide to Radon: WhatIt Is and What to do About It.”In this guide, EPA recommendsthat the annual average radonconcentration in lived-in areasof a home be þ 4 pCi/l. Thatis, EPA’s recommended “actionlevel” is 4 pCi/l.

G-3. Radon MeasurementTechniques.

EPA has issued numerous reportsdescribing radon measurementtechniques and strategies.Briefly, EPA protocols specifythat a short-term, screeningmeasurement be initiallyperformed on the lowest levelof a structure with the testdevice placed in the ‘breathingzone’ (for example, on a table)and away from sources of humidity such as showers. The

EM 385-1-8030 May 97

G-2

screening measurement should beconducted under “closed-house”conditions (that is, windowsand doors closed except fornormal entry and exit). Airexchange systems, such as atticfans, should not be operating.The test should be postponed ifsevere storms with high windsare expected during the testperiod.

T e s t i n g u n d e r t h eaforementioned conditions isconsidered a “worst case”scenario. If the screeningmeasurement indicates thepotential for an elevated radonconcentration, a long-termfollow-up measurement isperformed.

It should be noted that EPA’stesting protocols areapplicable for typicalresidential dwellings. It isrecommended that an HP beconsulted before testing othertypes of structures.

Short-term measurements may bemade utilizing a charcoalcanister (a 2 to 7 day test) oran alpha-track detector(usually, a 3-month test).Long-term measurements may alsobe made with an alpha trackdetector (a 12-month test).

Radon measurement devicesshould be analyzed by alaboratory which has beendetermined proficient by the USEPA Radon MeasurementProficiency Program.

G-4. Radon MitigationTechniques.

Radon enters a structure at arate determined by theavailability of radon at theexterior, the number and sizeof entry routes, and thepressure differential betweenindoors and outdoors.Mitigation techniques canprevent radon entry intooccupied spaces by manipulatingpressure relationships and/orby closing entry routes.

Soil depressurization involvesthe creation of a negativepressure field in the soiloutside the structure so thatthe direction of airflow isfrom the interior to exterior.This is typically accomplishedby using sub-slab suction.

Entry routes may be sealed bycovering exposed earth (sumps,drain areas, etc.) and sealingcracks in floors or walls whereradon can enter (utility pipeopenings, holes in top row ofconcrete blocks, floor drains,etc.). G-5. DA and USACE RadonPrograms.

Both DA and USACE have adoptedEPA’s recommended action levelas an indoor radon standard.AR 200-1, Chapter 11establishes a program formeasuring indoor radon inexisting buildings on Armyinstallations and in buildings

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G-3

owned or leased by the Army.The USACE Radon Program,developed in conjunction with,and a mirror of AR 200-1,Chapter 11, can be found inMemorandum, Subject: Guidancefor Radon Assessment andMitigation for the U.S. ArmyCorps of Engineers (USACE)Civil, Research and Developmentand Military Missions.

G-6. Agreement Staterequirements.

Many Agreement States havepromulgated regulations whichpertain to radon measurementprofessionals/businesses andr a d o n m i t i g a t i o nprofessionals/businesses. Itis recommended that, iftesting/mitigation is to bedone on property determined tobe under state jurisdiction, itbe determined whether there arestate regulations with whichUSACE must comply.

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H-1

Appendix H. Applications andLicense Examples, ApplicableForms and Statements.

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H-2

Example Application for NRC License.

Application for a Radioactive Material License US Army Corps of Engineers, Omaha District

(An example of a completed NRC Form 313 is enclosed)

Item 5. RADIOACTIVE MATERIAL. Max. Activity

Radionuclide Sealed Source Per Source

A. Cs-137 ABC Corp. Model C1 10 millicuries

B. Am-241:Be ABC Corp. Model A1 50 millicuries

Possession Limit CommitmentWe will confine our possession of licensed material to quantities

such that we will not exceed the applicable limits in 10 CFR30.35(d).

Data on Registration CertificatesManufacturer/Distributor Registry Number Model Number

ABC Corp. AA-NNN-A-NNN-A Models C1, A1(sources)

ABC Corp. AA-NNN-A-NNN-A Model J (device)

Item 6. PURPOSE(S) FOR WHICH LICENSED MATERIAL WILL BE USED

Authorized UseA. & B. For use in ABC Model J gauge to measure soil parameters ata depth < 3 ft at temporary job locations within the United Statessubject to NRC’s regulatory authority.

Item 7. INDIVIDUAL(S) RESPONSIBLE FOR RADIATION PROTECTION PROGRAMAND THEIR TRAINING EXPERIENCE.

The Omaha District Radiation Protection Officer (RPO) is JoeAresso (false names used in this example). He will be responsiblefor the Radiation Protection Program and he will report directly tothe District Commander. The duties and responsibilities of the RPOare described in ER 385-1-80, Ionizing Radiation Protection and EM385-1-80, Radiation Protection Manual (both attached). It is the

EM 385-1-80 30 May 97

H-3

RPO’s responsibility to ensure that all radiation work is performedsafely and within regulatory constraints. The RPO has beendelegated, by the District Commander, the authority to stop anoperation if he believes that radiation safety concerns exist. TheRPO has met the training and experience requirements listed inChapter 2 of the USACE Radiation Protection Manual. Joe Aresso hasattended the 40-Hour RPO training class offered by ABC Corp., hehas attended ABC Corp.’s 8 hour user training course, and he hasworked with nuclear gauges for 5 years (certificates of trainingattached.

Item 8. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTINGRESTRICTED AREAS.

Individuals working in or frequenting restricted areas willreceive training as outlined in Chapter 2 of the USACE RadiationProtection Program (attached). Authorized Users (AUs) will haveattended ABC Corp.’s 8-hour training course, will be instructed inUSACE’s operating and emergency procedures (copy attached), andwill be approved in writing by the RPO prior to use of a nucleargauge.

The RPO will be responsible for supplying annual refreshertraining to all individuals. Topics which will be covered include:operating and emergency procedures, DOT requirements, changes inregulations or license conditions, and deficiencies identifiedduring annual audits.

Item 9. FACILITIES AND EQUIPMENT.

Nuclear gauges will be packaged and transported in accordancewith applicable DOT regulations (copy maintained at the USACEwarehouse). A copy of the radioactive material license and USACE’soperating and emergency procedures will be in each gauge carryingcase at all times. When not under constant surveillance at atemporary job site, the nuclear gauge will be locked in itscarrying case and securely chained in the bed of the truck orlocked in the equipment trailer. Access to the truck or trailerwill be limited to the AU, the RPO and the Site Safety and HealthOfficer. When not at a temporary job site, the nuclear gauge willbe locked in its carrying case and the case locked in a closetwithin the equipment storage room of the existing USACE warehouse.Access to the closet will be limited to the AUs and the RPO. Thedoor of the closet will be posted “Caution, Radioactive Material.”When the gauge is in storage, the radiation level does not exceed

EM 385-1-8030 May 97

H-4

background in the equipment storage room. A diagram of the USACEwarehouse is shown in Figure 1.

A Ludlum Model 3 survey meter and a Ludlum Model 44-9 thin windowpancake probe will be present at each job site for use by the AU.This instrument can measure from 0.01 mR/hr to 100 mR/hr. Theinstrument is calibrated annually by the US Army TMDE calibrationfacility. The instrument has a check source attached to the metercase and the response of the meter is checked each time the meteris turned on. If the response is more or less than 10% of normal,the instrument will be removed from service. A replacement meteror timely access to a replacement meter will be obtained beforeoperations will resume. The sources will be leak tested by the RPOas described in Chapter 5 of the USACE Radiation Protection Manualat 6-month intervals. The RPO will conduct an inventory every sixmonths to account for all sealed sources and devices received andpossessed. All maintenance by the RPO or an AU will be conductedwith the source in its shielded position following ABC Corp.’srecommendations.

Item 10. RADIATION PROTECTION PROGRAM. The USACE Radiation Protection Program is attached. The District

Commander will assure that the radiation Protection Program isaudited annually by an internal (for example, by the RPO or localacting IG) or external (for example, by the Surgeon General or anRPO from another command) agent or agency. The results of anyaudit will be promptly reviewed by the District Commander. Auditrecords will be maintained for 3 years.

Item 11. WASTE MANAGEMENT.

No waste will be generated. Sealed sources will be returned tothe manufacturer for disposal.

Diagram of the USACE warehouse located at 9901 John J. PershingDrive, Omaha, NE. Nuclear gauges will be stored in a closet(designated “Radioactive storage” on the diagram) within theequipment room.

EM 385-1-80 30 May 97

H-5

Figure 1.

EM 385-l-8030 May 97

E M 3 8 5 - l - 8 0

3 0 M a y 9 7

F o r m s / S t a t e m e n t s / I n f o r m a t i o n

D D 1 9 5 2

D A F o r m 3 3 3 7

N R C F o r m 3 ( F o r R e f e r e n c e o n l y , n o t t o f u l l s c a l e a s r e q u i r e d ( 1 6 "b y 1 1 " )

U S A I R D C C o m p u t e r G e n e r a t e d V e r s i o n o f N R C F o r m 5

N R C F o r m 2 4 1

N R C F o r m 3 1 3

N R C F o r m 3 1 4

E n g F o r m 3 3 0 9 - R

E n g F o r m 4 7 9 0 - R

D e c l a r a t i o n o f P r e g n a n c y S t a t e m e n t

L L R W C o m p a c t I n f o r m a t i o n M a p

H - 7

EM 385-l-8030 May 97

H-8

EM 385-l-8030 May 97

GENERAL INSTRUCTIONS

H-9

H-14

EM 385-l-8030 May 97

.

H-15

EM 385-l-8030 May 97

8. OTHER DATA .

H-16

EM 385-l-8030 May 97

I

.

H-17

EM 385-l-8030 May 97

INITIAL

-

.

H-18

-

OATE

Date: I

H-20

H-21

EM 385-l-8030 May 97

Appendix I. Sample USACHPPM Survey Protocol/Checklist.

I-l

EM 385-l-8030 May 97

United States Army Center for Health Promotion and Preventive Medicine (USACHPPM) Auditbased on the Nuclear Regulatory Commission (NRC) Field Notes for Inspection of Industrial.Academic, and Research Facilities

References: Title 10 Code of Federal Regulation (CFR), Chapter I - NRC. Parts 19, 20, 20, 61, & 71Energy; Title 49 CFR Parts (170-l 89), Transportation: and Title 40 CFR Parts (1500- 1508),Protection of Environment

1. INSPECTION HISTORY ( ) N/A - Initial Inspection

A. Violations were identified during any of the lasttwo inspections or two years, whichever is longer ( )Yes ( )No

B. Response letter(s) or 591(s) datedC. Open violations from previous inspections:

StatusRequirement Violation Corrective Action Taken (Yes/No) Open/Closed

D. Explain any previous violation(s) not corrected or repeated ( ) N/A

2. ORGANIZATION AND SCOPE OF PROGRAM

A. Organizational Structure

EM 385-l-8030 May 97

1. Meets license conditions (L/C) or requirements [L/C] ( ) Yes ( ) No2. Multiple authorized locations of use and/or laboratories ( ) Yes ( ) No

If yes, may us ATTACHMENT A as a guide for location(s) orlab(s) inspected and note lab numbers where violations are found

3. Briefly describe scope of activities, including types and quantitiesof use involving byproduct material, frequency of use, staff. size, etc.

B. Radiation Safety Committee (RSC) required L/C]

1. R-SC fulfills license requirements [L/C]2. Records maintained [L/C]

C. Radiation Safety Officer (RSO)

-Remarks:

3. TRAINING. RETRAINING, AND INSTRUCTIONS TO WORKERS

A. Instructions to workers/students per [ 10 CFR 19.12]B. Training program required [L/C]

1. If so, briefly describe training program:

2. Training program implemented3. Periodic training program required4. Periodic training program implemented5. Records maintained

( )Yes ( )N0

USACHPPM-2

I - 3

EM 385-l-8030 May 97

D. Revised Part 20

Workers cognizant of requirements for:

1. Radiation Safety Program [20.1101]2. Annual dose limits [20.1301,1302]3. New forms 4 and 54. 10% monitoring threshold [20.1502]5. Dose limits to embryo/fetus and declared

pregnant worker [20.1208]6. Grave Danger Posting [20.1902]7. Procedures for opening packages [20.1906]8. Sewer disposal limits [20.2003]

A. Audits are required [L/C]B. Audits or inspections are conducted

(1) Audits conducted by(2) Frequency

USACHPPM3

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EM 385-l-8030 May 97

5. FACILITIES

Remarks:

6. MATERIALS

Remarks:

I-5

A. Instruments and equipment:

B. Briefly describe area survey requirements [30.1501(a). L!C]: ,

C. Performed as required [20.1501(a), L/C]:

1. Contamination found2. Corrective action taken and documented

D. Records maintained [20.2103, L/C]E. Protection of members of the public

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EM 385-l-8030 May 97

A. Disposal

1. Decay-in-storage

.

-

-

C. Waste Management

EM 385-l-8030 May 97

-

D. Records of surveys and material accountability aremaintained [20.2 IO?, 2 1081

Remarks:

9. RECEIPT ANI3 TRANSFER OF RADIOACTIVE MATERIAL

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EM 385-l-8030 May 97

A. Licensee shipments are:

I

EM 385-l-8030 May 97

( ) N/A

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I

-

E. Reports

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F. Who performed planned special exposures (PSEs) at thisfacility (number of people involved and doses received)

EM 385-l-8030 May 97

Remarks:

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EM 385-l-8030 May 97

Remarks:

Remarks:

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EM 385-l-8030 May 97

17. BULLETINS AND INFORMATION NOTICES

A. Bulletins, Information Notices, NMSS Newsletters, etc.,received by the Licensee

Remarks:

A. Special license conditions or issues to be reviewed:

( ) N/A

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EM 385-l-8030 May 97

21. PERFORMANCE EVALUATION FACTORS (PEFs)

Licensee (name & location) InspectorInspection Date

D. Radiation Safety Committee fails to meet or functionsinadequately

EM 385-1-80 30 May 97

J-1

APPENDIX J. ACRONYMS.

µCi MICROCURIE

ALARA AS LOW AS IS REASONABLY ACHIEVABLE

ALI ANNUAL LIMIT OF INTAKE

Am-Be AMERICIUM-BERYLLIUM

APR AIR-PURIFYING RESPIRATOR

ARA ARMY RADIATION AUTHORIZATION

AS AGREEMENT STATE

AU AUTHORIZED USER

AUA AUTHORIZED USER’S ASSISTANT

BF BORON TRIFLUORIDE3

Bq BECQUEREL

C/kg COULOMBS PER KILOGRAM

CDE COMMITTED DOSE EQUIVALENT

COE CHIEF OF ENGINEERS

CEDE COMMITTED EFFECTIVE DOSE EQUIVALENT

CERCLA COMPREHENSIVE ENVIRONMENTAL RESPONSE,

COMPENSATION AND LIABILITY ACT

“SUPERFUND”

CO COMMANDING OFFICER

cpm COUNTS PER MINUTE

DA US DEPARTMENT OF THE ARMY

DDE DEEP DOSE EQUIVALENT

DOD US DEPARTMENT OF DEFENSE

DOE US DEPARTMENT OF ENERGY

DOT US DEPARTMENT OF TRANSPORTATION

dpm DISINTEGRATIONS PER MINUTE

dps DISINTEGRATIONS PER SECOND

EDE EFFECTIVE DOSE EQUIVALENT

EPA ENVIRONMENTAL PROTECTION AGENCY

EMF ELECTROMAGNETIC FIELDS

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EQ EQUATION

FOA FIELD OPERATING ACTIVITY

FUDS FORMERLY USED DEFENSE SITES

Ge(Li) GERMANIUM-LITHIUM DOPED

GM GEIGER-MEULLER

Gy GRAY

HP HEALTH PHYSICIST

HPGe HIGH PURITY GERMANIUM

HTRW CX HAZARDOUS, TOXIC AND RADIOACTIVE WASTE CENTER OF EXPERTISE

IATA INTERNATIONAL AIR TRANSPORT ASSOCIATION

ICRU INTERNATIONAL COMMITTEE FOR

RADIATION UNITS

keV KILO-ELECTRON VOLTS

LLRW LOW LEVEL RADIOACTIVE WASTE

LSA LOW SPECIFIC ACTIVITY

LSO LASER SAFETY OFFICER

MACOM MAJOR ARMY COMMAND

MCA MULTI-CHANNEL ANALYZER

mCi MILLICURIE

MeV MEGA-ELECTRON- VOLTS

mR/hr MILLIROENTGEN PER HOUR

mR MILLIROENTGEN

MW MIXED WASTE

NaI SODIUM IODIDE

NARM NATURALLY OCCURRING OR ACCELERATOR PRODUCED

RADIOACTIVE MATERIAL

NCRP NATIONAL COUNCIL ON RADIATION

PROTECTION AND MEASUREMENTS

NIST NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

NORM NATURALLY OCCURRING RADIOACTIVE MATERIAL

NRC US NUCLEAR REGULATORY COMMISSION

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NVLAP NATIONAL VOLUNTARY LABORATORY

ACCREDITATION PROGRAM

pCi PICOCURIE

PEL PERMISSIBLE EXPOSURE LIMIT

PPE PERSONNEL PROTECTIVE EQUIPMENT

Q QUALITY FACTOR

R/hr ROENTGENS PER HOUR

R ROENTGEN

rad RADIATION ABSORBED DOSE

RAM RADIOACTIVE MATERIAL

RCRA RESOURCE CONSERVATION AND RECOVERY ACT

rem ROENTGEN EQUIVALENT MAN

RF RADIO FREQUENCY

RPC RADIATION PROTECTION

COMMITTEE

RPO RADIATION PROTECTION OFFICER

RPSO RADIATION PROTECTION STAFF OFFICER

SAR SPECIFIC ABSORPTION RATE

SDE SHALLOW DOSE EQUIVALENT

SOP STANDING OPERATING PROCEDURE

STC STRONG, TIGHT CONTAINER

Sv SIEVERT

T HALF-LIFE1/2

TEDE TOTAL EFFECTIVE DOSE EQUIVALENT

TI TRANSPORT INDEX

USACE US ARMY CORPS OF ENGINEERS

USAIRDC US ARMY IONIZING RADIATION DOSIMETRY CENTER

USAF US AIR FORCE

USPS US POSTAL SERVICE