ML20004E613

Safety Radiation Protection Program

ML20004E613
Person / Time
Site:	07001351
Issue date:	02/26/1980
From:	ARMY, DEPT. OF, HEADQUARTERS MATERIEL DEVELOPMENT
To:
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ML20004E608	List: ML20004E607 ML20004E612 ML20004E613
References
PROC-800226, NUDOCS 8106120393
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Text

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• CERCOM Suppl 1 to AMCR 38S-2S HEADQUARTERS D

US ARMY CO>o!UNICATIONS AND ELECTRONICS MATERIEL READINESS C0ho!AND FORT MONMOUTH, NEW JERSEY 07703 CERCOM Supplement 1 26 February 1980 to AMCR 38S-2S Safety RADIATION PROTECTION l.

Issue of further supplements to this regulation by CERCOM subordinate elements is prohibited, unless specifically approved by Commander, CERCOM, ATTN:

DRSEL-SF.

AMCR 38S-2S, 12 August 1968, is supplemented as follows:

Page 2, paragraph 2, Scope. Add the following:

This supplement applies to directorates, offices and activities of the US Army Communications and Electronics Materiel Readiness Command (CERCOM), US Army Communications Research and Development Command (CORADCOM), US Army Electronics Research and Development Command (ERADCOM), US Army Medical C-Department Activity (MEDDAC) and all other tenant activities located at Fort Monmouth concerned with the use of radioactive material and/or radiation

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producing devices.

Page 2, paragraph 3b, General. Add the following:

National Council on Radiation Protection and Measurements (NCRP) reports may also be referred to for supplemental information.

Page 3, paragraph S, Policy. Add subparagraph g after subparagraph f.

g.

Limited and special application of this supplement relative to organi ations in possession of US Nuclear Regulatory Commission (NRC) licenses and/or Department of the Army (DA) authorizations and having an independent I

radistion protection program is contaimd in appendix C.

Page 3.

Add paragraph 6-1 after paragrarih 6.

6-1 Responsibilities of CERCOM.

a.

The Chief, Safety Office (DRSEL-SF) will:

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(1) Be the CERCOM staff contact for all radiation safety matters.

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(2) Designate an Installation Radiological Protection Officer (RPO) and alternate to perform the tasks outlined in paragraph 6c(2) of the basic regulation, and provide radiation safety support to the Commanding Officer, Headquarters and Installation Support Activity (HISA).

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• This supplement supersedes ECOMR 385-9, 17 August 1973 including all changes.

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CERCOM Suppl I to AMCR 385-25 26 February 1980 Page 4, paragraph 6b, Radiation control committee. Add subparagraph (4) after subparagraph (3):

(4) The Fort Monmouth Ionizing Radiation Control Committee (IRCC) organi-zation is delineated in appendix D.

Page 7, paragraph 6.

Add subparagraph f after subparagraph e.

f.

The Chief, Supply Services Branch, Industrial Prerations Division, HISA, CERCOM, will insure prompt notification to the installation RPO of shipment or receipt of radioactive materials. Exclusive use vehicles transporting the received radioactive materials will only be released by the installation RPO or his designated representative as required by Title 49, Code of Federal Regulations, Part 173.397.

Page 18, paragraph 17c(_1). Add the following:

The installation RPO or his designated representative will be contacted for this purpose.

Page 22, paragraph 21.

Add subparagraph e after subparagraph d.

The Chief, Safety Office, CERCOM, will be infdrmed of discharges of e.

radioactive effluents at Fort Monmouth, i

Page 47.

Add appendices C and D after appendix B.

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UNITED STATES ARKl MATERIEL CO>DWD

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AMC REGULATION 10 February 1969 No.

385-25 V-CHANGE 1

SAFETY j

I RADIATION PROIECTION AMCR 385-25,12 August 1968, is changed as follows:

a.

Paracraoh 5f_ is added:

f.

The AMC Surgeon (AMCPT-H) provides Eedical guidance for the pro-tection of health of personnel in use of radiation sources."

b.

Make the following changes:

d) Paraeraphs 5d, sixth if ne: 6b(3), sixth line: 12b, fourth line; 21d, third line: 30d(1)(3), fif th line: and

_1, sixth line. Change "AMCAD-S" to "AESF. "

p/t2) Paragraoh Se, first line. Change " Division" to " Office."

Pace 48, too of nace.

Change "(AMCAD-S)" to "(AMCSF)."

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FOR Ti1E CO'B!ANDER:

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OFr CIAL:

CIARENCE J. LANG t

Major General, USA Chief of Staff

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Colonel, G I

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Chief, Administrative Office DISTRIBUTION:

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s AMC REGULATION 12 August 1968 No.

3.85-25.,

SAFETY I

RADIATION PROTECTION h

Paragraph Page j-

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1.

2 Purpose -------------------------------------------------------

Scope ---------------------------------------------------------- 24 2

General ----------- ---------------------------.-.------------- 3 2

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Definitions ------'------------------ ;------------------------ 4 2

5 2

Policy --------------------------------------------------------

6 3

Responsibilities ----------------------------------------------

AEC licenses and Department of the Army authorizations -------- 7 7

i Local control of radioactive material ------------------------- 8 7

Radioactive material ------------------------------------------ '9 10 Saf e handling of radioactive materials ------- ----------------- 10 11 Other sources of radiation ------------------------------------ 11 11 Personnel exposure -------------------------------------------- 12 12 Medical ~ examinations ------------------------------------------ 13 14 Periodic medical examinations --------------------------------- 14 14 Training and experience of personnel --- ~-------------------.;- 15 14 I

Personnel dosimetry ------------------------------------------- 16 15 Ra d ia t i on su rvey s -- -- - - ------ - - - - -- - - - -- - -- - - - - - -- - - - --- - - - --- 17 17 Radiation warning signs -------,,------------- ---------------.18 18 Co6structi~on of radiation facilities'--- ---------------------- 19 18 Operational safety procedures --------------------------------- 20 20 j

D i s p o s a l - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 21 22 Contamination levels ------------------------------------------ 22 22 ' -

Pers onn el d e contaminat ion ------------------------------------ 23 26 Equipment a.nd area decontamination ---------------------------- 24 27 S to rage ~ of radioactive mat e rial s -------- ---------------------- 25 29 On-post transportation of radioactive materials --------------- 26 30 l

Off-post transportation of radioactive materials -------------- 27 31 On-site command of emergency during transportation ----- ------ 28 31 Radiac instrumentation ---------------------------.------------ 29 31 Emergency procedures ------------------------------

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30 33 A d di t i o nal r e qu i r eme n t s ---- -- ---------- - --- - -- ---- --- ---- -- --- 31 36

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l Key eme rgen cy pe rso nne l ------------------------------ --------- 3 2 36 l.

Records -------------- ------------------------.---------------- 33 37

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l Appendix A.

Glossary of Radiation Safety Terms 38 B.

Recommended Documents for a Reference Library -----------

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This regulation establishes U.S. Army Materiel gg

, Command ( AMC) ionizins radiation protection standards.

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Scope. This regulation applies to all AMC elements procuring,

. receiving, storing, shipping, using, transporting, maintaining, or disposing of ionizing radiation-producing materials and/or equipment.

This regulation does not apply to nuclear weapons, nuclear reactor systems, or spent fuel from nuclear reactors, nor does it apply to LASER or microwave radiation.

3.

General. This regulation supplements AMCR 385-224 and is to be used in conjunction with AMCR 385-224.

Waivers of radiation safety requirements of this regulation a.

are.the same as those set forth in AMCR 385-224.

b.

National Bureau of Standards handbooks on radiation pro-tection shall be used as AMC standards in planning of facilities and local procedures except where such publications conflict with the requirements of this regulation in which case this regulation shall apply.

c.

The terms shall, will,or must indicate mandatory require-l ments. 'phe term c:ay or should is advisory.

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Definitions.

See appendix A.

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5.

Policy.

a.

Prior to the use of sources of ionizing radiation in any program or project, and prior to the incorporation of a' source of Jonizing radiation into an item of: supp,ly (issue items), the' cost effectiveness and safety of such use must be weighed against the use of alternate methods or materials to achieve project or program goals.

The radiological hazards shall be investigated and written guidance prepared before supply items containing sources of ionizing radiation are issued for field use.

(The word " radiation" will be used in this regulation for "f onizing radiation.")

b.

Without proper controls, radiation can be hazardous to health f

and property. Consequently, proposals to obtain, use, store, t ran spo rt,

j maintain, or uispose of items which are, or contain, scurces of ionizing pe f

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Adequate procedures, facilities, equipment, and trained t {,.; -

personnel will be provided to assure the safe use of materials or c.

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equipment capable of producing radiation. Failure to meet this require-ment will result in cessation of operations or delay in start-up.

se d.

Commanders of separate activities tenented upon an instal-C lation will be guided by the installation radiation protection stand-ards. Local radiation protection standards will not be 1ess restrictive i ",c.

than those standards established by Federal, Army, or AMC regulations.

6 Should a separate activity's mission be hampered or restricted by the installation requirementa, and the difficulty cannot be resolved l

at local level, the problem will be forwarded to the Commanding General, 1

AMC, ATTN: eMCADg AMC#,

Ofkei Headquarters, AMC Safety Divicip, developes and directs e.

the AMC Radiation Protection (health physics) Program.

6.

R pensibilities.

a.

Installations and activities.

Commanders ef installations and activities that procure, receive, store, ship, use, transport, maintain, or dispose of sources of radiation will:

(1) Establish a formal, written radiation safety program.

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(2) Appoint a radiation control committee.

y (3) Appoint a quali.fie,d individual as radio'ogical pro-te'ction officer (AR 40-14) and an alternare tu provide continuity of operations.

(4) Assure compliance with Federal, State, and local regulations.

f Radiation control committee. The committee will consist i

of the'cocrander or his designated representative, the radiological l

protection officer, medical officer (where the establishment has a medical facility), the snfety director, and other persons who are know-l ledgeable in the safe use of radiation, as are deemed necessary.

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. (1) Rasponsibilities of this committee will includa:

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(a)

Recommending to the commander policies on the

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(b) Reviewing the radiation safety aspects of pro-posals for the procurement and use of sources of radiation, the modifi-cation of existing radiological operations and operating procedures,

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e and providing recommendations to the commander for appropriate action.

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(c) Reviewing applications for Atomic Energy Commis-sion (AEC) licenses or Department of the Army authorizations.

(d) Reviewing and approving the qualifications of users of radiation.

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(e), Reviewing reports of radiation accidents and in-cidents to determine the cause and recommending appropriate action to the commander.

4 (2) The radiation control committee should not exercise the functio.ns of a clinical committee on radioisotopes in a medical facility, or of a reactor safeguards committee. However, handling, receiving, shipping, storage, transport, or disposal of radioisotopes beyond the control of the immediate medical or teactor staff is subject to the review of the radiation control committee.

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(3) The committee membership will be kept up-to-date.

Training and experience rdsumds for each member of the committde will be kept on file by the radiologica,1-protection officer.

In those cases where the. committee membership list and rd*umds are on file at the AEC,

, the AEC will be advised of membership changes by letter forwarded through the Commanding General, AMC, ATTN: ??C?S Sw (See AMCR 385-9.)

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Radiological protection officer (RPO). The training and experience of the radiological protection officer and his alternate must be commensurate with the type and hazard of the radiation source (s) for which they will be responsible. As a minimum, the formal training of the radiolog' cal protection officer and his alternate will be suc-l cessful completion of the U.S. Public Health Service Occupational l

Radiation Protection Course or equival,ent.

Organizationally, he should i

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(1)

In_ cases involving more than 100 millicuries of unsealed sources and more than 10 curies of sealed sources', the radiological pro-tection officer should be an individual other than a radiation user.

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(2) Responsibilities of the radiological protection officer 7I 'r will include:

"U (a) Providing the commander, radiation control coc:mit-(%

tee, and radiation users with advice and assistance on a11 matters per-taining to radiation safety. ( Advice includes in'structing and. training of i.

-- worker _s and visitors in the safe use of protective equipment and proce-dures.)

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(b) Implementing the radiation protecTfon safety program.

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l (c) Reviewing radiological operations to determine compliance 'with regulations and approved procedures.

'I (d) Maintaining an accurate record of the inventory of sources of radiation possessed by the installation or activity in accord-ance with AR 700-52. The record for each item should include: Federal stock number and nomenclature, manufacturer's model number, description

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j and serial number, the isotope, source ra,dioactivity and date radioactiv-

's ity was determined, chemical and physical form, whether sealed or unsealed, date received, and using organization and location.

L (e) Maintaining radiation protection records.

(f) Performing radiation surveys and leak tests, or causing such surveys and tests to be performed. The accuracy of tests and N

surveys if performed by others remains the responsibility of the radio-

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logical protection officer.

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(g) Evaluating the hazard potential and adequacy of

_l protective measures for existing and proposed operations.

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.l (h) Reviewing standing operating procedures (SOP's) for l

operations involving sources of radiation prior to review by the radiation l

control committee.

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(i) Investigating radiation accidents and incidents.

(j) Reporting the findings of investigations (para

-j 30)~ in accordance with AMCR 385-3.

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.[AMCR385-25 q-(k) Assuring that radiation dattetion instrum:nts ara L '

properly calibrated and are available to radiation workers.

b' (1) Monitoring incidents wherein unusual levels of

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• radiation or contamination are suspected.

3 (m) Prior to being relieved of his duties, the radio-logical protection officer will take the following action with regard to T '-

radioactive materials and equipment for which he is responsible:

1_. Secure all material and equipment in such a

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manner as to preclude use or removal during the period for.which there is

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'no radiological protection officer appointed; or

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Turn over to a properly qualified and authori-zed individual, all materials and records for which he is responsible.

1 Such an authorized individual will have_ the qualifications and training

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d.

Supervisors of radiation workers or radiological projects will be responsible for:

(1) Maintaining a current inventory of all sources of radia-tion for which they are responsible.

r (2) Knowing the exact location of all sources of radiation for which they are' responsible.

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(3) Posting appropriate warning signs and notices..

(4) Assuring 6.at tHe'ir ' personnel have received adequate

-instruction and experience prior to using or being exposed to radiation.

l (5) Controlling contamination.

(6) Assuring sources are secured against unauthorized use.

(7) Controlling personnel exposures.

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(8) Preparing, prior to the start of any operation involving radioactive material or possible exposure to radiation, an adequate SOP i

j for review by the Radiological Protection Officer and the Radiation l.

Control Committee prior to final approval in accordance with paragraph 1625,AMCR 385-224.

The SOP will contain,is a minimum, responsibilities, maximum permissible levels of radiation in the areas concerned, storage of

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sources, procedures regarding dosimetry, decontamination, and emergencies.

(This SOP is mandatory for operatic'ns in which there is 'a reasonable proba-bility of exposure beyond established limits.)

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(10) Reporting to the radiological protection officer, any accident, unusual incident, personnel injury, however slight, suspected

-l overexposure, and/or suspected internal exposure, as soon as possible k

af ter occurrence.

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,.'A-(11) Prior to being relieved of his duties, each radiation

[]j(,', j supervisor will take the following action with regard to all radioactive materials and equipment for which he is responsible:

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'(a)

Secure all material and equipment,in such a manner

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• as to preclude use or removal while not under the immediate' suaervision 4,

. Sill of a qualified and authorized individual; or gas.3, (b) Turn over to a properly qualified and authorized q

individual, all materials and equipment for which he is responsible.

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the safe handling of the materials involved.

i e.

Radiation workers will be responsible for:

(1) Knowing and following SOP's, rules, and special instruc-l tions.

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Using safety equipment properly.

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,fts-dent; personal injury, however slight; suspected overexposure and/or sus-

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pected internal exposure; as soon as possible af ter the occurrence.

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AEC licenses and Department of' the Army authorizations. AMCR 385-9 furnishes guidance for installations and activities for obtaining AEC licenses and Department of the Army (DA) authorizations required by AR 700-52.

8.

Local control of radioactive material.

a.

Activity and instal-

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lation commanders will establish internal procedures to control the

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procurement, receipt, shipping, transport, use, maintenance, storage, I

an'd/or disposal of the following radiation sources:

' "I (1) Radioactive solids in excess of 1 microcurie or with a specific radioactivity exceeding 0.002 microcuries per gram or emitting a 56se rate of 0.1 millirad /hr at contact.

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AMCR 3S5-25 (2) AEC-controllstd materials in excess of tha quantities

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listed in Title 10, Code of Federal Regulations, Section 31.100.

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q (3) Machines which produce radiation; e.g., X-ray devices, accelerators, electron microscopes, etc.

1 (4) Radioactive gases or liquids of concentrations in excess

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of the values listed in Table II, Appendix B, Title 10, Code of Federal 2, - 9 Regulations, Part 20.

(See para,19 and 20 for disposal and release requirements.)

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(5) Items activated in nuclear reactors (including Army re-actors), by accelerators or by nuclear weapons.

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b.

Activity or installation approval of proposed procurement, "i

receipt, use, transport, storage, maintenance,and/or disposal of radio-acti' e material will be based upon the following considerations:

v (1) Organizational element responsible for the proposed op-

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' eration.

(2) Purpose for which the materials will be used, including the desired initiation date and estimated duration of the project.

(3) Materials desired, including:

(a) Isotopes and maximu:t activities to be used and 4

possessed at any one time.

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(b) W ether sealed or unsealed.

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(c) Chemical and physical form.

.- -1 (4) Qualifications and experience of persons who will directly supervise the operation and of the Radiological Protection Officer.

(5) Qualifications and experience of persons who will use or handle the material.

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(6) Locations where sources will be used or stored (building

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number, room,and/or area number).

I (7), Radiac instrumentation available to support the opera-

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( I (8) Adequacy of facilities and equipment, storage contain-4 ers, exhaust hoods, handling equipment,and protective equipment available.

_-j"j (9) Adequacy of operational procedures, including procedures to be followed for collection and disposal of contaminated waste materials.

.-j (10) Adequacy of* radiation protection procedures to include s...e

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• safeguards to preclude emergencies, and actions to be taken should an T.

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emergency occur.

(11) Estimated exposure of operational and nearby non-

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operational personnel.

• ?"1 (12) Authority and conditions established in the AEC license c.

or DA authorization issued to the installation or activity.

Activity or installation approval for programs involving c.

machines which produce radiation will be based on the following information:

(1) Type of device.

(a) Function.

(b) Manufacturer and model number.

(c) Radiation output.

4 (d) Anticipated workload (hours / month).

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-c' (e) Whether fixed or mobile operation is anticipated.

t (f) Whether single or multiposition exposure head is to be.used. _

(g) Pulse duration and anticipated workload.

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(h) Target.

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(i) Calibration procedure and frequency.

(j) For accelerators, the curie level of the target, the l

j mode of operation (positive or negati,ve), energy of accelerator particles, the. procedures for exchange of targets,apd the available ventilation will

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(2) Safeguards.

l (a) Shielding.

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Interlock provisions and console locations.

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(c) Estimated exposure based on seven consecutive day operations modified by the planned workicad.

(Exposures of operational and nonoperational personnel must be considered.)

(d) Occupied locations nearby.

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(e) Boundaries of testricted area.

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(3) Training and experience of operators.

.d.

Approval of the commander should be withheld until the-radiation control committee has determined that:

J (1) The proposed operation complies with regulations, cur-rent standards, and conditions contained in applicable licenses and/or DA authorizations.

i (2) The operation will not present undue personnel exposure damage to property.

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(3) Personnel are adequately trained.

(4) Facilities, equipment, locations, and procedures are adequate to assure safe operation.

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) i (5) Necessary conditions and controls are provided.

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9.

Radioactive material, a.

Unsealed radioactive material should not be used where sealed sources ca'n pierform the desired function.. Un-

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sealed radioactive material may result in the contamination of personnel and equipment if not properly handled.

b.

The least hazardous chemical and physical form should be selected.

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storage or use of eating, drinking, chewing, smoking, and c.

cosmetic materials will be prohibited in tFe immediate areas containing radioactive materials.

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Radioactive solutions will',not be pipetted by mouth.

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workers in areas containing unsealed radioactive materials. Properly A-marked receptacles will be provided for the disposal of such materials.

f.

Operations.and facilities involving radioactive materials should be planned to limit the spread of radioactive material.

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(1) Work areas will be designated, marked,and monitored..

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K (2) Movement of personnel and unsealed radioactive material

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Ventilating systems will be designed so as to preclude the

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spread of radioactive mat'erials.

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In the case of sealed sources, the capsule enclosing the l

radioactive material and the physical form of the radioisotope will be I

chosen to minimize the possibility of dispersion, inhalation,and ingestion of the material. The capsule and container should be resistant to fire and corrosion.

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1.

Operations using remote-control devices to control sealed sources of radiation should be designed to prevent leakage or rupture of the source capsules; to provide a positive means of containment of con-tamination in case of leakage, rupture or other damage to the capsule; a positive means of control of the sources from " safe" to " exposed" position; 3-and an interlock, visual or audible alarm system to prevent entry of per-(_

sonnel into the radiation field while the sources are in the " exposed" position. Compressed gas systems are considered to be the least likely type of system :o meet these requirements,.

j. TB MED 232 provides guidance concerning storage and mainte-nance of self-luminous devices.

10.

Safe handling of radioactive mat *erials.

Additional guidance on the safe handling of radioactive materials is available in National Bureau of Standards Handbook 92.

11.

Other sources of radiation.

a.

Guidance for design of facilities and preparation of operating procedures for other sources of radiation, l

such as X-ray units, accelerators, an,d electron microscopes, can be found in National Bureau of Standards Handbooks 50, 55, 63, 66, 74 and 97, or replacement documents, available from the Superintendent of Documents, U.S.

t Government Printing Office, Washington, D.C.

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Enzards associated with tha high voltage, secondary bsam, n'

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scattered radiation and activated material must also be considered. Venti-lation, interlock provisions, shielding design, remote control,and handl-ing procedures are essential considerations.

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-J Prior to oleration,X-ray, accelerator,and similar facilities i

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should be surveyed by a competent individual for radiological safety haz,

ards in construction and operation. The services of the U.S. Army.

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Environmental Hygiene Agency are available for these surveys (AMCR 385-7).

In' order to avoid modification' of or

• delay in operation of these facilities, the construction plans should be reviewed by a competent person.

12.

Personnel exposure. The radiation exposure standards contained in this section are applicable to all personnel. Exposures incurred dur-ing examination or treatment for medical or dental purposes are not to be q

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included in calculations for compliance with this section.

However, medical exposures should be considered in the. programing occupational ex-posures.

Exposure of personnel will not exceed the following values:

a.

(1) Personnel 19 years of age and over who are occuoationally exposed to radiation:

(a) Accumulated dose to the whole body, head and trunk, active blood-forming organs, gonads, or lens of the eye will not exceed:

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3 rem in any calendar quarter, or

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2,. 5(N-18) rem total lifetime dose where N equals the present age in years.

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(b) Accumulateddosetotbeskinofthewholebodyor the thyroid will not exceed "I% rem in any calendar quarter or 30 rem in any calendar year.

(c) Accumulated dose of radiation to the hands and fore-arms and to the feet and ankles will not exc'eed 18 3/4 rem in any calendar l

quarter or 7,5, rem in any calendar year.

(2) Members of the general public, personnel not occupa-tionally exposed,and persons who are less than 19 years of age will not be exposed in any calendar quarter in exchss of 0.125 rem or in excess of 0.500 rem in any calendar year. Pregnant

• women will not be exposed to ionizing radiation for other than medical reasons (AR 40-5). At the first j

indication of pregnancy, women should notify their supervisor.

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excess of the limits in a(1) above, the installation or, activity will

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b.

Before permitting any individual to receive an exposure in forward a request through channels, to the Commanding General, AMC, ATTN:

Y. g q [."."Cl> % for review and coordination.

In addition to the information re-quired in Title 10, Code of Federal Regulations, Section 20.102, the proposal must cor_ain complete justification and describe the means for 4 -

assuring that the higher levels requested will not be exceeded.

Personnel exposure will be kept as low as practicable. The t

c.

necessity for exposure must be weighed against the benefi.ts expected.

d.

When an individual has received exposure in excess of the amount established for a calendar quarter, he shall be removed from duties i

involving exposures to radiation until subsequent exposure limitations are I

established through consultation with competent medical authority. When an individual has received exposure in excess of that established.for a calendar year,he shall be removed from duties involving further,, exposure urtil his exposure records have been evaluated by Headquarters, AMC, and subsequent exposure limitations are established. When an individual has received an accumulated dose of radiation in excess of 5(N-18) rem, he shall be removed from duties involving occupational exposure to ionizing radiation until his exposure record has been evaluated by The Surgeon General-Headquarters, DA, and subsequent exposure limitations are established.

1 Radiation workers may be exposed to the limits establisi"d in

-Q e.

a(1) above, when warranted. However, personnel exposure will j

k be kep't as ' low as practical. The necessity of exposure must be weighed

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j against the benefits expected. Should an individual receive exposure in excess of the limits listed belo' withe circumstances involved will be re-j corded in the radiation protection records a;.d the affected individual's i

DD Form 1141.

(1) 0.3 rem in any seven consecutive days, or (2) 1.0 rem in any calendar month.

f.

Should an individual be exposed to external radiation as well I

as internal radiation,his total exposure must. be considered and recorded.

I For example, should an individual's thyroid receive eight rem in a calendar I

quarter as a result of a radioiodine spill, that exposure should be added to,h,is whole body exposure to determine t,he total dose received by the thyroid.

g.

Additional guidance concerning maximum permissible concentra-i tion and control of internal radiation hazards are contained in Title 10, Code of Federal Regulation, Part 20, and National Bureau of Standards Handbook 69.

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AMCR 385-25 13.

Medical examinetions.

a.

Radiation workers should b.m given a preemployment examination which includes medical history, radiation exposure history, physical examination, and a complete blood count.

j Personnel who are to be occupationally exposed to neutrons will be given ml a slit-lamp test prior to exposure. If radiation workers are to be ex-

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posed to unsealed radiation sources, appropriate bio-assay should be

c-taken to establish base lines.

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b.

Any abnormalities wIll he recorded and carefully considered

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prior to exposure or continued exposure.

c.

If a similar examination has been conducted within the past 6 months, those portions of the examination need not be repeated for wh'ich results are entered in the individual's record.-

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Jisitors and personnel on temporary duty for less than 30

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days do not require a medical examination provided they will not be ex-

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posed to radiation in excess of the levels established in paragraph 12a(1),

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to radioactive concentration in excess of those given in Title 10, or Code of Federal Regulations, Part 20, Appendix B, Table II.

14.

Periodic medical examinations.

a.

Radiation workers should Il be given a medical examination at least once every 3 years. Dependent upon the work involved, the medical officer may desire to repeat the examination more frequently.

b.

Upon termination of the occupitional exposure, the individual

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should be given a medical examination.

C c.

In the event of an overexposure, a medical examination may be necessary.

15.

Trainine and experience of personnel, a.

Personnel, including visitors, who will be exposed to radiation and/or radioactive materials will be informed of the following information prior to exposure:

(1) The presence of radiation or radioactive material.

(2) Health hazards associated with exposure to sych materials and/or radiation.

I (3) Procedures and precautions to minimize exposures.

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(4) Applicable provisions of AEC licenses, DA authorizations,

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if regulations,and standing operating procedures.

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(5) Emergency procedures.

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~ Right to receive'a repert of his exposure incurred.' '

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-- [g, (7) Proper use of protective equipment and clothing.

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b.

Radiation workers will receive the instruction in a above.

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In addition they will be instructed in the following, areas:

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(1) Maximum exposure and contamination levels.

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(2) Safe methods of performing work.,(The use of protective

't equipment and the operational steps involved will be demonstrated.)

6 (3) Procedures to minimize contamination and to secure

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4 sources of radiation from unauthorized use.

-L Before an individual uses or supervises the use of sources of

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radiation, the radiation control committee should determine that his train-

' ng'and experience are sufficient t.o enable him to deal safely with mate-i r

l rials involved.

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d.

An individual whose training and experience is not adequate will be required to work under the direct sup'ervision of a person known to

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i be qualified until such time that the individual can demonstrate his ability on the job.

In the event such training is not available locally, inquiry should be made into the possibility of the employee receiving the required training and experience at another AMC installation or activity.

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l Emergency and security personnel will be trained and equippec e.

j to cope'with radiological hazards that may be encountered in the perform-l ance of their duties. Training will be sufficient to enable such person-

.l nel to function without waiting for the guidance of the radiological pro-tection officer, or other individuals not part of their immediate group.

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Such persons will be informed of the existence of situations that might g:

become hazardous during special or dnusual circumstances.

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f.

A record of training will be recorded on DA Form 750 (Record I

l of Training') and placed in each employee's official personnel folder.

I Dosimetry requirements contained in l

16. Personnel dosimetry.

a.

'j this paragraph are not applicable to persons exposed while being examined l

or treated for medical or dental purposes.

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b.

Knowledge of the radiation exposure received by personnel is q

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necessary to prevent future overexposurc and possible injury.

The Army J

s fila badge packet described in SB 11-206 will be used as the primary device to officially determine personnel exposure.

Film badges will be worn by each individual who is likely to c.

be exposed to radiation or radioactive materials. This requirement applies to visitors as well as installation or activity personnel.

d.

Pocket chambers or self-reading pocket dosimeters may be used to. supplement the film badge dosimeter. Such devices are useful when worn in areas in which an individual is likely to receive"five or more millirem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

In areas in which an individual is likely to receive 100 milli-tem or more of radiation in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, personnel will wear self-reading pocket i

dosimeters in addition to the film badge.

e.

The type of film badge (range and type of radiation detected),

the part of the. body upon which the badge is to be worn (lapel, belt, wrist, hand, etc.) and the need for additional dosimetric devices must be determined by taking into account the type of radiation exposures to be experienced.

f.

In the event of failure or loss of dosimetric devices, per-1

- sonne exposure will be calculated or estimated from past exposure histories, results of ra~diation survey, the exposures of other personnel under similar circumstances, breath samplins, bio-assay, techniques, and whole body counting and scanning.

g.

AMC personnel who may-be: expo, sed to radiation at no'n-Army sites will wear film badges obtained from the radiological protection officer of their home installation / activity. On-site film badges may be worn in addition to the Army badges, but not as substitutes for the Army g

badges. AMC personnel who may be exposed to radiation while on travel status will furnish the radiological prote'etion officer with a copy of any

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reports of exposure received for inclusion in the DD Form 1141 (Record of

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l Occupational Exposure to Ionizing Radiation) and the appropriate radiation protection records. In the event differences between the reading of on-site film badges and Army film badges cann~ot be resolved, the Army reading will oe recorded in the individual's health record.

h.

Procedures will be established for the centralized issue and conbrol of dosimetric devices:

i (1) Personnel will be instructed not to tamper with dosi-f metric devices, either physically, or by causing them to indicate readings that are not indicative of the personnel exposure.

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(2)' ' Facilities will ba provided 'for the storage of dosi.

j metric devices when the devices are not-being worn. These storage facil-ities should be located so that the dosimeters will not be exposed to y

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= i radiation, or excesses of heat or light. Each film badge dosimeter storage. facility will be equipped with a control badge, in accordance with d

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SB 11-206.

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(3) Because of the possibility of being lost, or, forgotten or

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the possibility of recording a faulty exposure, dosimetric devices must be-i stored in a designated receptacle wh'en not being worn.

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(4) Personnel on 'IDY will store their badges in such a i

manner that they will not be exposed to radiation when not being worn.

e However, personnel on TDY will wear film badges whenever they are exposed

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to radiation, whether or not during normal duty hours.

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17. Radiation surveys. Surveys should be made under representative conditions. The following describes certain types of radiation surveys.

a.

Initial surveys. An initial survey will be made by the

-radiological protection officer of sites and areas where sources of radia--

tion will be used and/or stored before 'an operation involving radiation is initiated or operational changes are approved, or upon installation of a i

device which produces ionizing radiation.

l b.

Routine surveys.

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'7 (1) Surveys of each area in which scurces of radiation are used and/or stored shall be performed by or under the direction of the

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radiological protection officer at least once each month. The radiation hazards incident to the product'idn,'use, release, disposal,or presence of l

radioactive materials or'other sources of radiation will be evaluated.

Such an evaluation includes a physical survey of the location of materials and equipment, measurements of levels of radiation and/or concentrations of radioactive material in and around the site. Conditions of stable storage may be exempted from monthly surveys at the discretion of the local l

radiation control committee. However, the intervals of surveys of storage areas will not exceed 3 months.

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-(2) The area survey will be performed using suitable in-k*ork struments, and, when appropriate, smear and air sampling techniques.

habits of personn(1 should be observ'ed to obtain data regarding additional i

si,t,es _ to be monitored or areas of imp' rov,ement for the operational proce-dures. Locations of the monitoring points with the results, state.,ent of l

the hazard, and any recommendations as to decontamination, shielding, l

procedural changes, etc., will be recorded and filed.

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c.

In cdditien to tha curv4ys in a and b abova, sp:cici surysys *

.cra rzquirad in ths event of the following occurrences:

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(1)

Shipment or receipt of radioactive materials. Packages

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s and the unloaded vehicles must be surveyed.

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(2) Termination of a project involving radioactive materials.

A survey is required to determine that no contamination exists and that

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sources of radiation are properly stored or have been disposed of properly.

(3) Unplanned events. Loss of control, spill, overexposure, 4

or any unplanned event which could adversely or did advergely affect the safety of the operation must be monitored. Control must be re-established

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to prevent the hazard from increasing.

(4) Hazardous operations. Particularly hazardous operations, such as decontamination, encapsulation, or smelting of radioactive materials, as authorized by AEC license or DA authorization, must be ' continually monitored.

d.

All places, equipment, persons, and animals suspected or known to have been in con' tact with radioactive material will be monitored for centamination. Personnel must be monitored before eating, smoking, chew-f og, drinking, or leaving the area in which radioactive materials are located.

e.

Environmental mon.itoring. Environmental monitoring will be performed whenever radiological operations.are such that they might have an adverse impact upon the surrounding environment.

Ideally, such monitor-

,_s ing should be done prior to the inception of radiological operations at an installation and periodically thereaf ter.

The results of such' environ-men,tal monitoring should be used.to determine the need to modify controls and/or operations.

18.

Radiation warning signs.

a.

Areas, buildings, inclosures, pack-ages, and containers will be conspicuously posted with radiation warning signs as required by AR 385-30; AR 55-55; Title 10 of the Code of Federal Regulations, Part 20; and Title 49 of the Code of Federal Regulations.

b.

Additional instructional or precautionary information may be posted as desired, but not substituted for the signs required in a above.

19.

Construction of radiation facilities, a.-

Selection of a radiation facility site will include consideration of the following factors:

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i (1) Impact cf surrcunding opsrstions uport tha pioposed facility:

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(a) Radiation background.

(b) Effluents from nearby operations.

(c) Fire and explosive hazard.

(d) Capability of, controlling access.

(e) Possibility of expanding i.. e facility or of using 9-larger sources.

(2) Impact of proposed facility upon operations in surround-ing areas and in areas downwind and downstream of the proposed site,:.

I (a) Increased radiation background.

E (b) Effect of effluent discharge.

!I, (c) Impact of most severe plausible radiation incident.

J (3) Possibility of flood or land movement.

l (4) Waste disposal. A separate piping syst:m =ay be desir-

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abic for the disposal of liquid waste.

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b.

A radiation facility should be a single story structure with-t out a basement, and of noncombustible construction.

Floors, walls, sur-faces,and equipment should be nonporpus and easy to clean.

Fire fighting 4'

in radiation controlled areas presents pr'oble'ms that must be considered before any installation of fire fighting devices. While the containment and extinguishment of fires is desirable, the installation of fire fighting devices mus' be such that will not result in the contamination of drainage pystems due to runoff; that will not result in the spread of contamination; or increase the hazard to personnel.

In many ins tances, " fog" and " foam" type devices meet these requirements. Where practical, an automatic fire alarm system, reporting directly to the fire department, should be installed.

Ventilation systems must be planned carefully:

c.

l (1) Recirculation of ai'r, should not be permitted within bul,1, dings containing radioactive materials.

(2) Air intakes will be located to prevent the entrance of j

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radioactive effluent from the same or nearby buildings. into the ventila-l (ton system.

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i AMCR 385-25 (3). Air flow will ba from nonsctiva to " hot" areas, through filters, to the discharge. " Hot" areas should be maintained at a negative

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' pressure to reduce the spread of contamination. Blowers should be posi-tioned downstream from the filter so that the air is sucked rather than

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pushed through the filter.

(4) Hoods will be interlocked or designed to prevent reverse flow when all of the hoods are not operating at the same time. The air-

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flow rate through openings of-the hood, should be at least 100 linear feet per minute. (See NBS Handbook No. 92.)

(5) Hoods, dry boxes, and traps are use'ful laboratory tools for minimizing contamination. Dry boxes may not be used for storing or han'dling radioactive.' materials involving explosives or flammable solvents unless designed to function as operational shields for the quantities of explosives or flammables involved.

d.

Buildings in which unsealed radioactive materials are handled should be equipped with shower and monitoring facilities.

Two separate locker rooms separated by a wash and shower room should be provided. The one locker room is for storage of the worker's street clothing; the other, for his work clothing.

20., Operational' safety procedures, a.

High radiation areas should l

be interlocked to halt the irradiation upon the entry of personnel to the prea, or otherwise to alert workers of Jhe entry of personnel into i.

the area during irradiation. The alarm system should be of a fail-safe design of such type that in case of primary alarm circuit failure the

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secondary alarm circuit is set off. High radiation areas that' exist for more than 30 days will be equipped. wit automatic alarms and' devices .as required by Title 10, Code of Federal Regulations, Part 20. In high radiation areas that exist for less than 30 days, appropriate protective measures, such as close supervision to prevent unauthorized entry and exposure, will be taken. i t i b. Work areas will be designated at d marked. Radiation levels should be measured,and marked where practical. Process control devices, such as thickness, gages and moisture c. ~ gages, involving radioactive sources,will be designed to protect the ' source (s) against mechanical damage and to limit the exposure of operators l and maintenance personnel to limits established for the general public. i The device will be conspicuously and permanently marked with a radiation warning sign. d. Each AMC installation or activity having radiation counting facilities should perform surveys for smearable contamination on outdoor surfaces. l l 20 g b B 1 _ +. -

AMCR 385-25 N, (1) Lsvals of rrdietion'aufficiently high to ba significtne _( may r sult from various sourcza, such as poor radioactiva wasta dispesal _s practices, radiation incidents,and nuclear weapons testing. %s ] (2) If significant levels of radioactive material are j deposited out of doors, this contamination, if not detected, can be tracked into " clean" areas and sensitive " low level" laboratories. . "] e. Emergency exits, passageways, and doorways must be planned to 3 enable safe movement of personnel in the event of an emergency. f. " Hot" drains and tanks should be planned on the assumption that they will leak and will require maintenance. Unles's criticality re- ~ quirements prohibit, " hot" drains should empty into hold up tanks in order, that samples can be analyzed to effect proper disposal. ~ g. Whenever a high radiation area is not mechanically secured to prevent unauthorized entry, a guard will be posted. ~ h. Secure, centralized storage facilities will be provided for radioac'.ive materials not required in the immediate work areas.

i. Before initiation of an operation or modifying an operation involving radiation, the operating and emergency procedures should be prac-ticed,u, sing a dummy source or other non-radioactive material.

j J. Explosives, propellants, and. excessive flammables will be ex-cluded from areas in which radioactive materials are used or stored unless _.,,_s ( specifically approved in a DA authorization or AEC license. i k. Personnel with open; ski.n wounds will not be permitted to work , with unsealed radioactive material without an adequate waterproof cover-ing on the wound and the approval of the medical officer. 1. Containers of radioactive liquids should be provided with secondary containment. Except in an emergency, anti-contamination equipment and m. clothing will be worn in radiation controlled areas only. Each item of equipment being released from a " hot" area to a n. " clean" area will be monitored,and decontaminated if necessary, and certi-fied by the monitor to have contamination levels below those listed in table 1. / o. Maintenance that must be performed in a radiation controlled area will be cleared with the radiological protection officer and area supervisor prior to initiation. ( 21 O* O w 4 FF m

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M:CA 385-25 4 at least once every 6 months (alpha sources every 3 month p. - } ' \\w T

• after any suspected or actual damage. shipments; suspect sources

)) I' Unless required otherwise by Army directives, sealed sources containing less than 10 microcuries of activity or containing only natural uranium, natural thorium, or depleted uranium need not be tested. Leak test results will be recorded in terms of micro-curies. khe quantity of radioactive material stored within a workin q. area should be limited to the smallest reasonable quantity consistent with operational requirements. by the radiological protection officer and sill be marked in acc -i r.

• ?;

with TM 3-261. i 21. Disposal. a. of in accordance with AR 755-15 (Disposal of Unwanted Radioact rial). b. j tion. Radioactive material will not be buried on any AMC installa-j c: Disposal of radioactive effluents (liquids or gases) into unrestricted areas will be in accordance with. Title 10, Code of Federal Regulations, Sections 20.106 and 20.303, provided local governments do not prohibit such disposal. --s Compliance with concentration levels established in Appendix B, Title 10, Code of Federal Regulations, Part 20, will be determined by averaging concentrations on a monthly basis instead of an annual. basis. The total quantity of radioactive effluents discharged at any installation will not exceed the amount authorized a single licensee under Title 10, Code of Federal Regulations, Part 20. At ins tallations where more than one licensee desires to discharge radioactive effluents ,the com=ander will apportion the atounts to b'e authorized each licensee. 1 i i d. as specifically authorized by prior approval of Headquarters, AM UJ::'.A0 A //MC M. 22. _ Contamination levels. Maximum permissible contamination Icvels and indicated actions are contained in tables 1, 2, and 3 below. lowing notes and definitions will apply to the use of tables 1, 2, and 3: The fol-( the same counting time, gives a count which is not different"None" s a. from the 22 e ,(- e - f

j' AMCR 385-25 bsckground count. (Sas Nationni Bureau of Standards Handbook No. 80, ,( Section 2.5.3, para 2'.) j ( ~ b. No allowance shall be made for particle size or for the use _I of protective clothing or equipment for determining whether an individual is exposed to radioactive concentrations in excess of the levels specified in this regulation. Items which cannot be decontaminated will be marked and c. tagged to indicate their condition, and will be removed from use pending further decontamination or disposal. 's d. Contamination should be kept at a minimum at all times. The publication of maximum permissible contamination levels should not be used as a license for unwarranted relaxation of controls. ? ' ~ Abbreviations used in table,s 1, 2, aiid 3 have the following, ~ e. meaning: .. I dpm = disintegration per minute 2 = square centimeter cm MFC = Maximum Permissible Concentration. See Title 10, Code of_ Federal Regulations, Part 20, and National Bureau of Standards Handbook 69 for Maximum Permissible Concentrations of Radionuclides in j Air. f t.. ~ t h 9 l l f i 23 l ~~ em - i, f m

l c I.-- -) fg g1 / i . i I Table 1. Maxirum permissible contamination on inanimate objects. t CONTAMINATION LEVEL Alpha Beta-Cansna Item and Corrective Action Fixed (F) or d'pm/100 cm2 dpm/100 cm2 mrad /hr Removable (R) Instrument Smear at 1 in, dpm/100 cm2 M Yo 1. Fersonal clothing, including shoes. y Replace, decontaminate or store for F 200 0.2 y decay,if above: R None None ~ 2. Protective clothing, incl. shoes. l 6 a. General. Should be replaced or F 1,000 0.5 j decontaminated,if above: R 200 1,000 h b. Laundry. Do not re. lease to pablic F-200 0.4 / ~ laundry,if aboye R 50 200 c. Respirators ,F 200 0.06. {t None None

i I

3. Laboratories and worls areas: e a. Uncontrolled ar'eas. Require F 200 0.25 n' controls and posting or decontaminate. R $0 100 2 if above: i

• b.

Controlled areas. Decontaminate, F 1,000 2.0 or it impossible, fix with periodic R 200 1,000 i check on fixation,1f above:

• . 1- *

} g 4. Vehicles: a. Use in controlled areas. Decon-F 1,000 2.0 taminate or if impossibic, fix, R 300 1,000 if above: b. Use in uncontrolled areas. Decon-F 500 0.4 caminate,1f above: R - 30 500 1 5. Tools, equipment and containers.. Prior to, *F 200 0.25 non-radioactive use, decon if above: R 50 100 Shipping containers, outUde surfaces, l 6. F 500 0.25 decon if above: R None None i b -t - U. v

AMCR 385-25 4 cC Table 2. Airborne contamination levels. - g -l Alpha Beta Required respiratory protection Concentration Concentraticn ~ IHalf f ace mask with filter or 1 MPC 1 MPC ~ canister respirator. Supplied air or'self-contained ~~ 5 MFC 10 MPC air supply with full face mask. -s .l 4 IFor operations under the control of an'AEC license, specific approval of i the AEC must be obtained before making any allowance for use of respira-i tory equipment. ? Table 3. Maximum permissible personnel contamination. Alpha or Beta-Gamma C Area and action 1. Skin. Contact medical officer if contaminated on face or'oVer . Any detectable level'above t major area of the body. Continue background. decontamination, if above: -~ 2. Hands. Continue decontamination, Any detectable level'above background. if above; i e l l l = 25 [ e e e. w.,,_, l .{ 9 + [, N r-,-- n- ,.--,w r,e .. -,-w----+ --g-,---. 7y- - -. - - -, -, -.. -,. - -, -

AMCR 385-25 ~ 23. Personnel decontamination. a. Thorough washing with non-()) (~ g abrasive soap and lukewarm water is the best general method of decon- .. ' g _. tamination of the hands and other parts of the body regardless of the

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contaminan t. If the contaminant is localized, it is of ten more prac-4 tical to mask off the affected area and cleanse with swabs, ratner than '.~ ' risk the danger of spreading the contaminant by general washing. Or-ganic solvents must be avoided as decontamination agents because they -q may increase the probability of the radioactive materials entering the body through skin absorption. Special. attention must be given to the areas between the fingers and around the nails. The outer edges of the hands are readily contaminated and often neglected in the washing. ~ b. After repeated washings, the skin may tend to chap. To avoid this, apply lanolin or hand cream and then continue to wash. If repeated washing with soap and water is unsuccessful in decontamination, the indi-vidual should be referred to the local medical officer for application of the more drastic chemical decontamination procedures listed in the National Bureau of Standards Handbook No. 48. c. If it is suspected that any person, by inhalation, ingestion, or by any other manner, has introduced radioactive materials into his body, the local medical officer vill be notified immediately so that medi-t cal procedures can be initiated to facilitate the elimination of such material. Contamination over a large area of his body or his face will be the basis for suspecting that the person 'is internally con-taminated. ( d. In the event an individual is contaminated on a large portion of his body, the following decontamination procedure is recommended: i (1) Place the individual under a lukewarm shower. -(2) Using a mild toilet soap, individual will cover his entire body with lather. (3) While still covered with lather, the individual will step out of the shower. An assistant will then cover the individual with a heavy coat of mild soap flakes. (The purpose of the lather is to cause the soap flakes to adhere to the person.) (4) Using his hands, the contaminated individual will rub the soap flakes on his body into a pastg. (5) Individual will then return to shower and attempt to rinse off the soap by starting at the top and working his way down. (Note. It will be necessary for the individual to rub body surfaces with his hands while rinsing, in order to remove soap paste.) Soap paste will remain in 26 9 7 v m Y"* w-1 r a ~ ' - t' ' ~, = 3, w p, 4 s . +,,

[g AMCR 385-25 those areas that have not been thoroughly rinsed. Although a soft cloth (~(} may be used, a brush may not. Particular attention should be given the a \\ s' hairy portions'of the body. 'd (6) When the individual has rinsed himself to the point that - j he no longer feels slimy and while still under the shower, he will ba ex-amined by an assistant for traces of soap. The presence of soap will indicate which areas of the body have not been decontaminated. -e

J x (7) After removing all traces of soap, the individual will leave the shower and dry himself.

(8) Af ter drying off, the individual will be monitored. If the individual is still contaminated, procedures outlined above will be repeated. d. In all cases of personnel contamination, the raclological protection officer will be consulted. All water used in the washing and rinsing described above -1 e. will be contaminated and its disposal should be conditioned by this fact. i Eculpment and area decontamination. a. General methods. - :2 24. (1) Care must be taken during the decontamination process to '~ avoid further spread of the contaminant which can be accomplished by: i c l \\_ (a) Always taking precautions to contain the contamina- ]{]) tion by the use of monitoring, protective clothing, and shoe covers. (b) Always workin, g from the areas of least contamina-tion toward the area (s) of the heaviest contamination. (c) Using a minimum amount of decontamination liquids and being aware that the runoff solutions, mops, rags, and brushes will all be contaminated. l ( 2) The methods listed below should be tried in the follow-Ing sequence: (a) Damp moppine. The area is wiped with a damp rag. l The wiping surface of the rag is changed repeatedly to ".inimize spreading of.the contaminant. l (b) Water and detergent. The area is wetted with a i minimum amount of detergent solution. The area is then wiped dry with l j absorbent gauze or cloth. (; 2, l (- +% ,p.,., A s* 1 see m

AMCR 385-25 '\\ {]g (c) Steam cleaning. ) (d). Cleaning with solvents other than water. N (e) Surface removal by use of chemicals, abrasives, sand blasting, grindine, etc. (3) Vacuum cleaners. Only vacuum cleaners which are equipped ^ -l with absolute filters and which have been tested for filtration efficiency may be used. The filtration efficiency will be tested after each replace-ment of the filter and each time contents are emptied. b. Soecific methods. If the above methods (a above) do not work,_, the following s,pecific methods may',be trli'ed: . (1) Metals. "a) Remove any oil from the surface with organic ~ solvents. (b) Soak in a solution of citric acid prepared by addi-tion of one pound of citric acid to one gallon of water. . (c) Soak in a s'olution of diluted hydrochloric acid prepared'by carefully adding one part of commercial grade concentrated hydrochloric acid to four parts of water. Hydrochloric acid should not be used on stainless steel because of the etchir.g which will take place and ( ) destroy the smooth surface of the metal. (d) Use metal polish. (2) Plastics. Cican with ammonium citrate, dilute acids,or organic solvents (,f a type not injurious to the plastics). (3) Glass and porcelain. Clean with detergent solution. If this method fails, soak in concentrated nitric acid or chromic acid cleaning solution. ~ ~ ~ (4) Painted surfaces. Use paint remover, or, in cases where surfaces were coated with a strippable paint, peel the paint from surface. (5) Rubber, including respirators and gas masks. Wash with detergent and water or with a warm 20 per cent (by weight) water solution of sodium citrate, c. Decontamination of clothing. 28 q d 7 .V --~------q- ~- = ? /.- ~ A ~. - s m E

m AMCR'385-25 (\\ /~ (1) Determine extent of contamination using an AN/PDR-27, or 7 } equivalent, with the beta shield removed, and with the AN/PDR-60, or equivalent. (2) Wash in special laundry facility (home type or other washer and dryer kept in the facility for washing " hot" clothing only). Use the following steps: (a)' Soak overnight in water solution of laundry i detergent. (b) Drain. ~ f Wash for full cycle with hot water and laundry. (c)

• A detergent.

J. (d) Rinse, dry and remonitor. (3) Water utilized for washing, rinsing or soaking contaul-nated clothing will be contaminated as a result of such usage and its disposal should be conditioned by this fact. Laundry equipment may be-come contaminated also. 4 d. Monitoring technique. Check crevices and.nside corners of areas,' tools,and equipment. Special attention should be given to oily and greasy surfaces such as those on automotive equipment. 25. Storage of radioactive materials. a. Areas will be set aside for the secure storage of radioactive materials. These areas will be used to store only radioactive'mdterialss The storage area will be free from the danger of flooding and outside the danger radius of flammables or explosives. Physical security standards for storing radioactive mate-rials are contained in appendix A, AMCR 190-3. b. Each storage and shipping container will be marked as required by AR 55-55 and AR 385-30, whether or not the radioactive material is under the license control of the AEC. Laboratory containers such as flasks and t&st tubes need not be marked as long as the user is continuously present. Radioisotopes will not be stored in glass containers unless c. secondary containment is provided. d. Radioisotopes should not be transferred from one storage con-tainer to another within the storage area. A system will be provided to control and record the " check in" and " check out" and monitoring of radio-I active materials. 29 C i Cs -*""N . en m -o=_ p p 's d a p gge=, ~

x AMCR 385-25 2 s o. Storaga aters will bs adaquetely vsntilated es datermined by }) Ese RPO if gaseous sources are being stored. A;- m ~~ '1 f. All sources and' containers will be labeled. The areas will be monitored periodically to assure adequate shielding and to detect any . ;r cont.'mina tion. '] g. Dose rates of a shipping container should not exceed 200 . +m 3 mrem /hr at the surface nor 10 mrem /hr.at 3 feet from,any surface of the container. ,1:- ~ '/- h. Operating officials will keep a current recor'd of all stored rad,ioactive material, and a copy of this record will be forwarded to the RPO. The RPO-will conduct a phy.sical inventory every,6 mon'ths. [ _, l x.. ;z:

jgu

~ '26. On-post tra'nsportation of radioactive materials. Within an in-sta11ation, it is usually not convenient to package and transport radio-active materials in the manner required for off-post shipments. However, 4. the following precautions will be~ observed: a. In loading the vehicles: (1) Keep within the weight limitations. (2) Limit or arrange cargo to keep radiation levels, to ~ '~ which personnel (including the driver) will,be exposed during trqnsporta - tion *,1as low as possible. Maximum permissible dose rate in occupied areas C.) of the vehicle will depend upon the time required to transport the mate-rial. The driver will wear a film badge and will not be exposed to ionizing radiation in excess of the.li.mits indicated in paragraph 12a. (3) Keep the containers avay from the cab of the vehicle. b. Do not haul loose radioactive materials. Tail gates should be closed to minimize the chance of cargo loss. c. Containers should be sturdily constructed, scaled air-tight, i and be free of removable contamination. Each container must hcve a com-pleted DA Label 15 (Caution: Radioactive Mater'ials) unless specifically. exempt by military specification M-19590C. d. The route used should be p'lanned to avoid areas in which ex-plos$yes are stored or handled and in which there is heavy traffic or per-l sonnel activity. The fire departrent, guard force,and safety director should be informed of the exact route and time of movement in sufficient time to allow implementation of any special protective measures required. 'l + 30 l.. m ,W r') g; Wke - + TrI 25'4 e

• ~

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AMCR 385-25 i e. A suitsblo vshicle should be ussd. Vdhiclos that ara dif- { ficult to decon'taminate, and privately-owned automobiles should not bc g ~) used., f. Unless emergency personnel (guard force and fire department) ) have demonstrated a capability to cope with a radiological emergency, a technically trained person should accompany the movement to be able to .d advise in the event of an emergen'y. i s,c:

Y~ ~

.Off-post' transport tion of radioactive materials. a. Radio-27. active material will be transported in accordance with AR 55-55 and ~

i applicable Federal and State regulations.

..3..f-b. Radioactive material should not be forwarded through the U.S. r. , -4,73 ~.',y mail channels except in an emergency. Should transmission by mail be necessary, shipment will comply with Part 125.24, U.S. Postal Manual, and will be registered. 3 Containers should be secured by blocking or tie down, when c. -y appropriate. g 9' d. Msterials shipped will be properly addressed to insure delivery to the proper installation and section within the installation. Personnel who will transport and/or escort radioactive ship-e. ments ' ill be briefed as to potential hazards, methods to minimize hazards w .and emergency precedures. In addition tio. the briefing, personnel engaged to transport the radioactive material will be given a completed DD Form 836 (Special Instructions for Motor Veh_cle Drivers) supplemented with written c emergency procedures. Written information will be provided as to the means ~' for obtaining assistance of radiological, emergency teams off-post. f. Consignees will be notified in advance of impending shipments in order that consignees may assure that they have the capability to re-N ceive and handle the materials being shipped. 28. On-site command of emergency during transportation. The ranking person accompanying the shipment will take immediate steps to clear the area and request assistance. He retains command at the accident site pending the arrival of the commander of the nearest military installation or his representative. The designated Army area representative assumes responsibility upon his arrival. 29. Radiac instrumentation.

a. 'Sofficient radiac instruments will be available to properly support the use of radiation sources. The instruments will be capable of detecting the types and levels of radiation-i involved and any possible resulting contamination.

31 ( y ..a

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-7 ~ e i - M $' D..-, ' ~ / ). R +. -4 ^ " ' ' [.~ '~ i -,, - -. - ~,

,CC.< 355-25 ~ ~^ b. Parsonn)1 monitoring davices will be immediately evcilable ]

• ~

in areas in which radioactive materials are handled. c. All instruments used for radiation protection will be cali-brated at least every 3 months, and af ter each maintenance or battery J.j change. More frequent calibration will be necessary for instruments which .j receive heavy use. Dosimeters need to be calibrated only at 6-month intervals. Dose rate instruments used to determine time of stay and expo- ~ sure estimates should be calibrated at a minimum c.f two points on each A . instrument scale. The instruments will be labeled with DA Label SO (U.S. Army Calibration System) to show the d' ate of the last calibration, source or method used for calibration, and the initials of the calibrator. c; ,g ,d. Faulty, instruments will be tagged with DA Form 2417 (Unservice-w able. '"est Instrument or Standard) to prevent their being used before having -N1 been repaired. ~ .c e. Each instrument used for radiation protection should be pro-vided with a check source or test sample. _i f. Pocket dosimeters should be calibrated every 6 months. At 7j the time of calibration, the correction factor for the dosimeter should be determined. Dosimeters which leak more than 5 percent of full scale af ter 24 hours in a radiation free area or which have an error of more than 10 percent should be repaired. Dosimeters should be calibrated by exposing..them to known sources of an energy level comparable to that which a ' the dosimeter will be exposed during use. Each dosimeter will bear a label showing the correction factor and the-date of calibration. The cor-rection factor is determined by dividing the actual level of radiation s ) by the indicated level. 'f ~ g. Dosimeters are used to~give thd wearer an estimate of his exposure while receiving the dose, in order that he may limit himself to permissible levels. Disagreement between dosimeter and film badge measure- ~ .ments is to be expected. The film badge reading will be used as the offi- ~ cial dose for record purposes unless the ba,dge is proven to have recorded an incorrect exposu:.u i h. Instrumentction must be selected based on the type and level l of radioactive material and/or radiation to be encountered. In high radia- '? tion

• areas, it is desirable to have a high-range survey meter in addition

~' to a low-range meter, in order to cover the range of dose rates likely to l be encountered. t

i. If funds parmit, duplicate rad'iation protection instruments e

should be available. The duplicate instruments will avoid the necessity of shutting down a radiological operation until an instrument can be re-l9, paired or replaced. \\ t 32 q l l lq l [' - ~ ~~ ' ~ ~ " ']." ~~ } 'E e .1 L__ j ~

., ~, - ~ AMCR 385-25 \\.7 30. Emergency procedures. a. In view of the complicating factors ,., ['?t, ~ ,[ that may arise in an emergency, it is impossible to establish simple - ' J '" rules of procedure to cover all situations of a radiation emergency. However, in any emergency, the primary concern must always be the protec-3-j tion of personnel from radiation hazards. Confinement of the contamina-tion to the immediate environment of the accident should be a secondary conce rn. Copies of the investigation report, relative to exposures - (5 .. _'. 4_ received by the personnel involved, will be given to each individual in-volved in that emergency. (([ .3 b. Emergencies will probably be of the following types: y2;j (1) Spill of radioactive material. (2) Explosion. ._._4 (3) Fire. ..r> g.a. (4) Overexposure. (5) Injury to personnel. {.,.) (6) L6ss of radioactive source. (7) Vehicular accident involving radioactive material. j ,. - Il 74 c. The medical officer of each AMC element having radiation ...'v-ds! sources shall establish written medical procedures for radiation casualties. g -j d. Emergency procedureI'w'111 be preplanned and rehea'rsed at least '-h once each year. In the event of an emergency, the following action will be w taken: s (1) Spills or uncontrolled spread of contamination. (a) Notify all persons not involved with the spill to [ vacate the area at once. I (b) If the spill is liquid and the hands and clothing are protected, right the container and take steps to contain the spillage. (c) If the spill 'is on the skin, flush thoroughly. m (_ l ~~..~ l. (d) If the spill is on the clothing, discard outer or ' 1,, protective clothing at once. .a .if (e) Notify the local radiological protection officer. l l- ) k 33- ,' h ~- ~ 1 5 3 e ~ [ --7--r------- j--- 7--- j _ g., g----- -~- l

ANCR 385-25 ~ (f) Decontaminate personnel. } ,q (g) Decontaminate the area. .a L4 (h) Mon'*ot all persons involved in the spill and clean-bcf ing operation to determine'at'squacy of decontamination. ~/ $ (i) ' Permit no person to resume work in the area until an " area survey is made and the area is cleared by the radiological protection ..E1 , officer. .d. HG7 (j) Prepare a complete history of the incident and decon-tamination operation related thereto for.the facility or area records. The sf ~ history will include a statement of the corrective actions taken to prevent 2-1 a recurrence. Forward within 2 weeks of the accident, an information copy to the Commanding General, EC,' ANN: M2.'.F-5[ /7McM - - { (2) Accidents involving radioactive dusts, mists, fumes, organic vapors,and gases.

.L

,.J (a) Notify all personnel not directly involved with the f incident to vacate the area immediately. (b) Hold breath, and switch off any air circulating devices ; 'e.g., fans, air conditioners, blowers, etc. g-3 (c) Vacate the area to a predesignated region, and allow r? no person to leave until monitored. -4 ' 1'3 (d) Close and de'ai all eqtrances into the area and post

• I; conspicuous warning signs or guards to prevent doors from being opened ac-cidentally.

l ~~ (e) ~ Notify the RPO. i l (f) Immediately report all known or suspected inhala-i tions of radioactive materials to the local RPO and the medical officer. ~ (g) Evaluata the hazards and the safety devices required for safe re-entry and apply the "two man rule." i

5~ 1 ;

(h) Deteraine cause of c*ontamination and rectify the con-l_'ij dition. ,,7, yc (i) Decontaminate the area.

- ?-

l 34 .g l = l ~ i .3,, k*. ~~~~# .y, ~~ i=' ~"-Q,

e \\, AMCR 385-25 ,r (j) Perform an area survsy (including air sampling) of the area before resuming normal operations. 4 'S (k) Monitor all persons suspected of contamination.

-;],

,_l (1) Prepare a complete history of the accident and . f*7 subsequent activity related thereto for the facility records. Forward, -;1 within 2 weeks of the incident, an information copy to the Commanding ii F General, AMC, ATT5:' AMCAii-S. ' ~ ~ " (3). Injuries to personnel involving radiation. .,. f, (a) Wash minor wounds immediately under running water ~ while spreading the edges of the wound. f -m .. e (b) Contaminated p'ersonnel who are in jured. In any radiological accident involving injured personnel, the local medical offi-cer will be notified immediately. Unless an emergency medical reason re-quires that the injured person be removed immediately, the injured person will not be transported until a litter or ambulance is available. If, however, other emergencies exist (e.g., fire or possible explosion), good coceon judgment should be used. Moving of the patient'may become impera-tive. ~.6 (c) Personnel with minor wounds will be monitored and If decontaminated, if necessary, before leaving the radiation facility. ,j the wounds are of a serious nature, the injured individual will be wrapped ~ .' b.-) in a blanket to prevent the further spread of contamination, and immediately f,,; be removed to the nearest medical facility. Persons accompanying the in- ~ dividual will warn the medical. personnel,that there is a possibility that ,a the injured is contaminated. ~ l (d) Report all radiation accidents (overexposure, wounds, ingestion, inhalation) to the personnel involved, to the medical officer, and to the RPO. (e) Permit no person involved in radiation injury to return to work without the approval of the attending physician and the RPO. (f) Prepare a complete history of the accident and subsequent ectivity related thereto'for the radiation facility records. The history will include a statement of.the corrective actions taken to prevent a recurrence. Forward, within 2 weeks of the occurrence, an in-formation copy to the Commanding General, AMC, A'TTN: AMCAD-S'. ~ 35 ( L_.- l _..Y.R- -.n. .; * :.) t-R

-r r-

.\\ AMCR 385-25 (4) Fires end other maior emergencies. } ./ (a) Notify all persons not directly involved with the incident who are in the area. 1 h* (b) Notify the fire department and other emergenc-j per-sonnel. a. (c) Attempt extinguishment of fires using readily d available first-aid type extinguishers if a radiation hazard is not im- ( mediately present. Efforts should be made to prevent water or fire fight-ing chemical from coming in contact with the radiation sourt:e. Attempt to c control runoff, preventing it from entering sewers or drainage systems until it has been monitored. (d) Notify the RPO. (e) The RPO will advise and assist the emergency per-sonnel. (f) Following the emergency, monitor the area and determine the protective devices necessary for safe decontamination. i (g) Decontaminate. r (h) Monitor all persons who were in the emergency area and t'hore who were involved in combating the~ emergency. (i) Monitor downwind, delineate all contaminated areas, -l and restrict access as necessary.,.., l

31. Additional requirements. The above reporting requirements are in addition to the requirements of AR 385-40; AMCR 385-2; AMCR 385-3; and in addition to Title 10, Code of Federal Regulations, Sections 20.401,.402

- and.403, when AEC-licensed material is involved. Information copies of reports to the AEC will be forwarded (AMCR 385-9) immediately, through channels, to the Commanding General, AMC, ATTN: ?."C.'.0 % #MCSX 32. Key emergency personnel. Key emergency personnel, such as Provost Marshal, Fire Chief, Medical Officer, and Safety Officer will be kept currently informed of the receipt, storage, use, disposal, or transfer of radiation sources and will be sufficiently trained and equipped to cope with, radiological emergencies independent o,f the presence of the RPO. 36 O L._ .-w-a

• w+---=

,{ .g ..m ~ ~ A. ~ ..5- ~-

AMCR 385-25 ,N (

33. Records. Records will be maintained to docum:nt all cspzeta of the radiation protection effort. Included are:

5 l Licenses, authorizations, and suppe. ting applications. a. ~ 5 b. Receipts, transfers and shipment records, notification of movement,,and instructions to drivers. I,, Inv-ntory and'1eak test,re. cords. c. Instrument and souree calibration records and certificates. d. y Utilization logs 'a'nd' ra'diation work permits'. e. J e f. Radiation' survey records which include description of each use, operation or work performed; radiation lavels and personnel exposure rates encountered; airborne and smearable contamination detected; hazards and corrective action, estimated personnel exposure; and disposition of radiation sources. i g. Environmental monitoring records. f ~ h. Vaste disposal records. r i. Records of training, plans of instruction, experience and certification of radiation workers.

j. Standing operating procedures.

k. Records of special studies, investigations. .. -^ t 1. Copies of reports originated and received. Inspection reports and related papers. m. n. Radiation analysis files. Miryutes of committee meetings. o. Directives and interpretation of regulations, l p. q. Personnel occupational exposure records. AR 40-14 requires l the custodian of the medical records to prepare and maintain DD Form 1141 foi each person occupationally exposed t o ionizing radiation. For ad-l ministrative control purposes, it is recommended that the Radiological Protection Officer maintain forms AEC-4 and AEC-5 also, where AEC licenses These forms are available at the U.S. Atomic Energy Com-are involved. mission, Division of Materials Licensing, Washington, D.C. 20545,, and may be reproduced locally. 37, ( V e= h

• • u"

-~ g--gm=e= w,. .m g e-T*;.. 2- = 1 e " w. ,a. . -. =. -

~~~ AMCR 365-25 ~ ~~ ~~~~' AppIndix A ]) CL, OSSA,RY OF RADIATION SAFETY TERMS, 9 APPROVAL. Official certification of compliance with the provisions of this regulation and with instructions and directives as issued by Headquarters, AMC, or with those of other appro,ving agencies specifically referred to'in this regulation. BACKGROUND RADIATION. Radiation crising from radioactive material other than the one directly under consideration. Background radiation due to cosmic rays and natural radioactivity is always present. There may also be background radiacion due to the presence of radioactive substances in other parts of the building, in the' building material itself, etc. CONTAMINATION (RADIOACTIVE). Deposition of radioactive material in any place where it is not desired, and particularly in any place where its i presence can be harmful. The harm may be in invalidating an experiment or a procedure, or in actually being a source of danger to persons. A unit of activity defined as the quantity of any radioactlyg CURIE. nuclide.in which the number of disintegrations per second is 3.700 X 10 7 - millicurie - One-thousandth of a curie (3.700 X 10 dis-integratTons per second). ~ r. ( _ - microcurie - One-millionth of a curie (3.700 X 10' dis-integrations per second). DOSE. . 1 ^ 1. Absorbed Dose. When ionizing radiation passes through matter, some of its energy is imparted to the matter. The amount absorbed per unit mass of irradiated material at the place of interest is called the absorbed dose and is measured in rads, where 1 rad = 100 erg /gm = 1/100 joule /kg. The rad unit is applicable to any type of ionizing radiation, but in report-ing dose, the type, as well as irradiated material (for instance, tissue), and the place of interest must be speci,fied. Without the above three factors, a statement of absorbed dose received is incomplete and probably useless, since the same dess of "fferent kinds of radiation, even delivered I to the ;ame place, can produce entirely cifferent effects. I r. I 38 = e I l

' \\, ' AMCR 385-25 [~ ( 2. Exposure Dose. See EXPOSURE. ~ . s_. 3. Biological Dose. The radiation dose absorbed in biological mate- ] rial. It is measured in rems. DOSE EQUIVALENT. The term "RBE" dose has been used in the past in both radiobiology and radiation safety. It is now recommended that the term RBE be used in radiobiology only and that another term be used for purposes ej of radiation safety. The linear-energy-transfer factor is multiplied by the absorbed dose, Da, to obtain a quantity that expresses on a common scale the irradiation received by persons exposed to all ionizing radia- - f tions. The name recommended for the linear-energy-transfer-dependent factor ~ is quality factor, QF. Other factors must also be considered for the pur-poses of radiation safety. A distribution factor, DF, is used to express the modification of the biological effect of radiation due to a nonuniform distribution of isotopes in the body. The distribution factor, like the quality factor, also affects the absorbed dose when radiation safety is being considered. It is recommended by the International Commission on Radiological Units and Measurements that the final calculated dose received by an individual af ter the absorbed dose is modified by the above-mentioned factors, plus any other factors that may effect the incom-ing radiation, be called the dose equivalent, DE'. If the only apparent , modif 1ng factors are QF and DF, then: 4 DE = Da (QF) (DF).

.(

( If other factors must be considered and are defined, then: DE = Da (Q F) (D F).......' t where the dots take into account the product of these other factors. The unit of dose equivalent, DE is the rem. The unit of absorbed dose, Da, is the rad. (Compare definitions of Ren and Rad.) Although the above defini '- tion of dose equivalent does not cover a number of theoretical aspects (in particular the physical dimensions of some of the quantities) it fulfills the immediate requirement for an unequivocal specification of a scale that may be used for numerical expression in radiarian safety. EXPOSURE. The term " Exposure Dose" is obsolete. E.gosure is a term adopted by the International Commiss, ion on Radiological Units and Measure-ments in 1962 to replace the term "esposure dose" introduced in their 1956 report. The quantity is used for X-and gamma radiation. Exposure is the measure at a certain place of radiation which has the ability to produce ionization. The unit of exposure is the roentgen, R, where IR equals 2.58 X 10-4 coulombs / kilogram. The definition thus corresponds to the terms roentgen dose and air dose. 39 (^ gW

• 6 e

m.. -= e ---m. m. m., ,e-, .rm v 7--% y

e e N. AMCR 385-25 EXPOSURE, OCCUPATIONAL. Exposure to ionizing radiation that is incurred as ) a result of an individual's employment or duties which are in support of j .-j facilities which use materials or machinery capable of producing ionizing Q radiation. Exposure of an individual to ionizing radiation for medical or dental diagnosis or therapy shall not be deemed as occupational exposure. J FAIL-SAFE. A design characteristic of the hardware, co=ponent or system which, in the event of a malfunction,,will not result in a degradation of ,~, safety. FILM EADCE. A pack ~of appropriate photographic film and filters used to determine radiation exposure. HAZARD. RADIATION. See RADIATION HAZARD. INTLRLOCK. A device, usually electrical and/or mechanical in nature, to prevent activation of a control until a preliminary condition has been met or to prevent hazardous operations. Its purpose usually is safety of per-sonnel or equipment. For example, it may be used to warn responsible per-sonnel of an unsafe condition or unauthorized entry of personnel. IONIZING RADIATION. See RADIATION. I LEAK TEST. A determination of the integrity of a scaled source encapsula-tion by detection of leakage or escape of radioactive contamination. i 1 (3 NUCLEAR REACTOR SYSTEM. Any equipment or device, except a nuclear weapon, (. capable of neutron multiplication through fission of special nuclear mate-rial. This definition includes nuclear reactors and subcritical assemblies 4 of special nuclear material and clie'su* porting equipment or device (if any) p -associated with them. ( RAD. The rad is defined as the unit of absorbed dose of any nuclear (or ionizing) radiation which is accompanied by,the liberation of 100 ergs of energy per gram of absorbing material. Or, one rad is approximately equal to absorbed dose delivered *when soft tissue is exposed to one roentgen of medium voltage X-radiation. The rad is to be used solely with absorh d dese. l rad = 100 erg / gram = 1/100 joule /kg. RADIATION. Energy propagated through s*p, ace. As used in this regulation, the t,erm refers to two kinds of ionizing ra,diation: 1. Electromagnetic waves (X-rays, gamma rays), and. 2. Corpuscular emissions from radioactive substances or other sources (alpha and beta particles, etc.). Ionizing radiation is any electromagnetic or particulate radiation capable of producing ions, directly or indirectly, in its passage through matter. ~ G .a _g 4,, em .s me 4 M*= ~* s -n =

AnLR 3G5-15 .\\ s RADIATION CONTROLLED AREAS. Any area, whosa recess or occuptncy 10 con-- <l trolled for. the purposa of protection of individus1.s from exposure to ionizing radiation and radioactive materials. 7 ] RADIATION CONTROL COMMITTEE. A group of persons appointed by the commander to advise him on policy and actions necessary to ensure safety of person-nel and property from hazards of radiation. Synonymous with " Isotope Committee," " Radiological Health and Safety Committee," " Rad?.ation Protec. 1 tion Committee,',' and other similar titles of committees with the same O purpose. 3 RADIATION HAZARD. A condition under which persons might receive radiation i ? - in excess of the applicable maximum permissible dose, of where radiation damage might be caused to materials or personnel. RADIATION _ SOURCES. Materials, equipment or devices which generate or are capable of generating ionizing radiation, including: (1) naturally occurring radioactive materials, (2) by-product materials, (3) source materials, (4) special nuclear materials, (5) fission products, (6) mate-rials containing induced or deposited radioactivity, (7) nuclear reactors, (8) radiographic and fluoroscopic equipment, (9) particle generators and accelerators, and (10) radio frequency generators such as klystrons and magnetrons which produce X-rays. RADIAIION WORKER. Any person occupationally exposed to ionizing radiation and/or raEcactive materials. (Job descriptions of radiation workers should reflect that the individual is potentially exposed to ionizing radiation.) (j RADIOACTIVE MATERIAL. Any substance which undergoes spontaneous disinte-gration in which energy is liberated, generally resulting in the formation of new nuclides (a species of atom characterized by the constitution of its nucleus). The process is accompanied by the emission of one or more types of ionizing radiation. Included are materials possessing artificial, in-duced and natural radioactivity. 1. Ev-product materials. Any radioactive material (except special nuclear material) yielded in or made radicactive by exposure to radiation incident to the process of producing or utilizing special nuclear material. 2. Source material. Uranium or thorium or a ecmbination thereof, in one-twentieth any physical or chemical form or ores which contain by weight, of one per cent (0.05 per cent) or more of uranium, thorium or any combina-tion thereof. Source material does not include special nuclear material. 3. Special nuclear material. Plutonium, uranium 233, uranium en-riched in the isotope 233 or in the isotope 233, or any other material which the U. S. Atomic Energy Commission pursuant to the provisions of section 51 of the Atomic Energy Act of 1954, 42 USC section 2071, determines to be S 41 JE s_ _ g ,,, ~ _

c4R 355-25 'z { spscici nuclorr matsrials, but doza not includa sourcs matarial; cr any [ matsrial crtifically enrichzd by cny cf th2 foregoing but does not in- ) clude source material. { 4. Naturally occurring radioactive material. Substances which are radioactive in the natural state, such as radium and thorium and their dec.ty products, except those defined as source and special nuclear mate-rial. RADIOLOGTCAL PROTECTION OFFICER. An individual designated by the comander to provide consultation and on the degree of hazards associated with ionizing radiation and the effectiveness of measures to control these haz-ards. This individual shall be technically qualified by virtue of educa-tion, military training,' and/or professional experience to assure a capa-bility commensurate with the assignment. The term " Radiological Protec-7 - i tion Officer" is a functional title and is not intended to denote a com-missioned status or job classification within the Armed Forces. RBE. (Relative Biological Effectiveness.) The RBE of a given radiation is defined as the ratio of the absorbed dose in rads of gamma radiation (of a specific energy) to the absorbed dose in rads of the given radiation hav-ing the same biological effect. (See Dose Equivalent.) REM (Roentgen Equivalent Mamal). One rem is the quantity of ionizing radiation of any type which, when absorbed by man or other mammal produces a physi 6Iogical effect equivalent to that produced by the absorption of one roentgen of X-ray or gamma radiation. Dose in rems equals RBE times ~ dose in rads. The rem provides an indication of the extent of biological (*l injury (of a given type) that would result from the absorption of nuclear C radiation. Thus, the rem is a dose unit of biological effect, whereas the rad is a unit of absorbed energy, dose, and the roentgen (for X-ray and gamcfa rays only) is one of exposure. 'The rem can also be defined as the unit of dose equivalent. ne dose equivalent is numerically equal to the dose in rads, multiplied by the appropriate modifying factors. The quantity of gamma or X-radiation which will give rise to the ROENTGEN. formation of 2.08 X 10 ion pairs per cubic centimeter of dry air, STP (O C, 1 atm). H is is equivalent to the release of 87.7 ergs of energy when one gram of dry air under STP conditions is exposed to one roentgen of radiation. The roentgen is to be used solely as the unit for exposure. 1 R = 2.58 X 10-4 coulombs /kg. SEALED SOURCE. Radioactive material th'at is encased in and is to be used in a container in a manner to prevent laakage or escape of the radioactive material. i e 42 .3 V /. l ,pe e y ,%m ~er wwwe

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AMCR 385-25 s. UNSEALED SOURCE. A diserats Enount of rtdioactiva material thst is not 4 encapsulated in a container to prevent leakage'or escape of the radioactive j material. _j _ i USER. The activity, section, division or other organizational unit which has been assigned responsibility for the use, handling, operadon or storage '~ of radiation sources. 6 4 a e - ** i e S 4 g 4 %8 1 Q. t 9* 8 i l l b 1 43 p L. i___.._..__._.____..__ -r,+ -v-- yy ,-..v-,.--.,,e-3-,, yy w

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AMCR 305-25 N Appendix B [, RECOMMENDED DOCUMENTS FOR A REFERENCE LIBRARY l-o 1. Army regulations. AR's 40-4, 40-5, 40-14, 40-37, 40-501, 55-55, --J 55-355, 385-10, 385-12, 385-30, 385-32, 385-40, 385-80, 700-25, 700-52, 700-63, 700-64, and 755-15. , 2. AMC regulations. AMCR's 190-3, 385-1, 385-3, 385-7, 385-9, 385-13, and 385-15. '4.. 3. Field manual. FM 3-15. 1

• 4.

Table of allowances. TA 50-914. j 5. Supply bulletin. SB 11-206. 6. Technical bulletins. TB's CML 52, CML 53, CML 63, 3-6665-200-12, J 3-6665-201-12, 3-6665-202-12, 3-6665-203-12, 3-6665-204-12, MED 62, MED 223, MED 232, MED 249, "IG 226-8, SIG 226-9, TC 7, and 5-6600-227-15/1. 7. Technical manuals. TM's 3-220, 3-260, 3-261, 3-6665-214-15, t 11-5514, 11-5314A. 11-5543 11-6665-204-12, 11-6665-206-12, t i 11-6665-208-15, 11-6665-209-15, 11-6665-216-15. 11-6665-221-15, 11-6665-224-15, 38-250, 38-750, 39-20-3, 39-20-6, 39-35-15, 39-N-11. 8. Military standards and~ specifications.1 a. MIL-STD-129 Marking for Shipment and Storage. b. MIL-M-3o35A Mark'6rs', Self-Luminous. c. MIL-C-10436 Compasses, Lensatic, Luminous Dial. d. MIL-M-19590 Marking of Commodities and Containers to Indicate Radioactive Material, e. MIL-STD-450 Radiation Hazard Symbol Contaminated Areas. 9. Miscellaneous. a. DOD 4160.21-M,' Defense Disposal Manual. b. Title 10, Code of Federal Regulations. - Atomic Energy.2 Title 14, Part 49 of Code of Federal Regulations.2 c. 2 d. Title 46, Part 146 of Code of Federal Regulations Title 44, Parts 171 through 178 of Code of Federal Regulations.2 3 e.. f. U.S. Postal Manual, Chapter 1, Sections 124.24 and 125.24.4 {234See footnot'es on page 47. p 44, j 4-e -e= -g-

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9 .\\ AMCR 385-25 h, Education and Welfare. gal Health Handbook, U.S. Department of Heal g. Radiologi e j 7, 'j 10. U.S. Department of Commerce, National Bureau of Standards Hand-books. 48 - Control and Removal of Radioactive Contamination in Labora- ': ^3, tories. 1 49 - Recommendations for Waste Disposal of Phosphorus 32 and i Iodine 131 for Medical Users. 51 - Radiological Monitoring Methods and Instruments. 53 - Recommendations for the Disposal for Carbon-14. t 55 - Protection Against Betatron-Synchrotron Radiations up to 100 Million Electron Volts. y 57 - Photographic Dosimetry of X-and Gamma Rays. 58 - Radioactive Waste Disposal in the Ocean. 59 - Permissible Dose for External Sourr's of Ionizing Radiation. .c i 63 - Protection Against Neutroa Eadiation up to 30 Million i Electron Volts. i 65 - Safe Handling of Bodies Containing Radioactive Isotopes.

-* 1 66 - Safe Design and Use of Industrial Beta-Ray Sources.

69 - Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure. 72 - Measurement of Neutron Flux and Spectra for Physical and . Biological Applications. 73 - Protection Against Radiation from Sealed Gamma Sources. 75 - Measurement of Absorbed Doses of Neutrons and of Mixtures of Neutrons and Gamma Rays. 76 - Medical X-ray Protection up to 3 Million Volts. 78 - Report of International Commission on Radiological Units. and Measurements 80 - A Manual of Radioactivity Proc,edures. 4See footno'tes on page 47. {1 6- = =. - - e y . +, >e- -,.y --,,,,-y = -p e.s-,-

'l AMCR 385 ! '1 84 - Radiation Quantities and Unite (ICRU Report 10a). 1 3 85 - Physical Aspects of Irradiation (ICRU Report 10b). V 86 - Radioactivity (ICRU Report 10c). 87 - Clinical Dosimetry (ICRU Report 10d). "j 88 - Radiobiological Dosimetry (ICRU Report 10e). 89 - Methods of Evaluating Radiological Equipment and Materials (ICRU Report 10f). _3 92 - Safe. Handling of Radioactive Materials. g - 93 - Safety Standard for Non-Medical X-ray and Sealed Gamma Ray j Sources: Part I. General. 4 11. Federal Radiation Council Reports No.1 - Background Material for the' Development of Radiation Protection Standards. 1 No. 2 - Background Material for the Development of Radiation Protection Standards. ,12. Internatienal Atomic Energy Agency Regulations 5 Safety Series No. 1 - Safe Handling of Radioisotopes. Safety Series No. 2 - Safr Handling of Radioisotopes: liealth Physics Addendum. Safety Series No. 3 - Safe Handling of, Radioisotopes: Medical ~ Addendum. Safety Series No. 4 - Safe Operation of Critical Assemblies and Research Reactors. Safety Series No. 6 - Regulations 'for the Safe Transport of Radio-active Materials. l Safety Series No. 7 - Regulations for the Safe Transport of Radio-l active Materials. Notes on Certain Aspects of the Regulations. l Safety Series No. 8 - The Use of Film Badges for Personnel Monitoring. See footnotes on page 47. [ 4S 46 ,] s L ~ - - * ~ * * * ". ~~~ ~ ~ ~ ~ .{ ,m ,,,m., = = -

AMCR 385-25 .N I Safsty Sarice Ns. 9 - B: sic Safety Stand:rds for Radiation Pro-tection. " Teview' Series No.12 - The. Packaging, Transport and Related Hand- ~ j ling of Radioactive Materials. y Review Series No. 18 - Processing of Radioactive Wastes. 6

13. National Fire Protection Association Publications Fire Protection Handbook,12th Edition,1962.

N National Fire Codes - Pamphlet 801, Laboratories Handling Radioactive Material,1955. Pamphlet 802, Nuclear Reactors,1960. ni

14. USA Standards Institute Publications 7 5

ASA N6.1 - Safety Stan'dard for Operations with Fissionable Materials Outside Reactors, 1964. ASA N5.2 - Design Guide for a Radioisotope Laboratory (Type B), 1963 1 Military standards and specifications are'available from the Commanding Officer, U.S. Naval Supply Depot (NSD 103), 5801 Tabor Avenue, Philadelphia, g Pennsylvania 19120. Copies of the Code cf Federal Regulations are normally available from the 2 Post Judge Advocate. Copies can be purchased from the Superintendent of Documents, U.S. Government Printing Offiqe, Washington, D.C. 3The Interstate Commerce Commission regulations are also published as " Agent TC George's Tarif f No.19", available from the Bureau of Explosives of the American Association of Railroads, 30 Vesey Street, New York, New York. Installation Transportation Officers usually have copies of George's Tariff No. 19. 4Available from Superintendent of Documents, U.S. Gov ernment Printing Of'fice, Washington, D.C. 5 vailable from National Agency for International Publications, Inc., A 801 Third Avenue, New York, New York 10022 6Available from National Fire Protection Association, 60 Batterymarch Street, Boston, Massachusetts 02110. .~ 7Available from USA Standards Institute, 70 East 45th Street, New York, New York 10017. 47 ] C i I -1 e e e -.,2, =e

/ddCR 3S5-25 5 d W (/YPICSP) ' r 1 ['t FOR THE COMMANDER: ~f> ' t a. 1 . 's y OFFICIAL: CLARENCE J. LANG Major General, USA , Chief of Staff ~ r, Gk h Colonel, G V e Chief, Administrative Office .r.. DISTRIBUTION: A and B

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l 26 February 1980 CERCOM Suppl 1 to AMCR 385-25 Appendix C REQUIREMENTS OF ORGANIZATIONS HAVING RADIATION PROTECTION OFFICERS AND RADIATION PROTECTION PROGRAMS e The application of this supplement is limited to the following: a. To coordinate the radiation protection programs, the RPO or designated i representative of each organization radiation protection committee will serve as a member of th'e Fort Monmouth IRCC. l* b. All organizations will furnish copies of their NRC licenses and DA authorizations, including all supporting documentation associated with these j licenses and authorizations, to the IRCC. c. All organizations will furnish a radioisotope inventory report semi-annually to the IRCC. The Chief, Safety Office, CERCOM, will be notified of any change in inventory to include off-post shipments, disposals and transfers to other activities at Fort Monmouth. d. Each organi:ation RPO will submit a copy of all results of inspections and surveys conducted by higher authorities to each member of the Fort Monmouth IRCC. , ((n e. The installation RPO is responsible for radiation protection concern-3 ing shipments of radioactive material while such shipments are in the physical custody of the Chief, Supply Services Branch, Industrial Operations Division, HISA. Shipments on and off Fort Monmouth will be in accordance with paragraph 26 and 27, AMCR 385-25. All organizations will advise the installation RPO-of all outgoing shipments. l a i I I I E C-1 4.- ww-m 5 ~-----. --

'CERCOM Suppl 1 to AMCR 385-25 26 February 1980 Appendix D IONIZING RADIATION CO.VTROL COMMITTEE (IRCC) 1. Organi:ation: The IRCC will be appointed on appropriate orders of the Commanding General, CERCOM, and will consist of the following members: a. Installation RPO, Chairman. b. Health Physicist, ERADCOM, Member, or designated representative. c. Systems Safety Engineer, Safety Office, CORADCOM, Member. d. RPO, MEDDAC, Member. e. - Environmental Engineer, Environmental and Energy Control Office, HISA, Member. f. Representative of the 54th Ordnance Detachment, Explosive Ordnance Disposal, Member. g. Science Advisor, Office of the Scientific Advisor, ERADCOM, Member. h. Representative of the Commanding General, CERCOM, Member. 2. Functions: The IRCC will: a. Serve in an advisory capacity to, and act as, the authoritative body i for the Commanding General, CERCOM, on matters pertaining to ionizing radiation, coordinating with organizations and activities assigned, detached or located at Fort Monmouth. b. Formulate rules and regulations relating to the use of ionizing radiation sources and equipment. Review reports of radiological accidents and incidents, and of c. violations of appropriate regulations, recommending any required corrective action. d. Review and authenticate NRC License, DA Authorization and DA Permit applications. 3. Responsibilities: a. The Chairman of the IRCC will: (1) Call and preside at meetings of the IRCC. (2) On majority vote of the IRCC, approve proposals, authenticate applications and correspondence on behalf of the IRCC. b. Members or alternates will: ~ (, (1) Attend IRCC meetings. D-1 e e O ~ ~ e n- -,-wa---m.pq -w-w q ,r w. ~ g --~---,s+-+<>rm er e --9

26 Fetman 1980 I CERCOM Suppl I to AMCR 385-25 Appendix D--Continued (2) Review reports of IRCC officers, NRC License /DA Authori:ation applica-tions, and requests involv roni radiation sources, as required. (3) Review accident and incident reports and provide corrective action recomendations. s (DRSEL-SF) i FOR THE C0!$1ANDER: OFFICIAL

• LOUIS A. REINKEN, Jr.

Colonel, GS ff_ Chief of Staff CAMILLE JAST NSKI ILT, AGC Adjutant DISTRIBUTION: M and T plus Chief, Safety Officer .......,50 Cdr, DARCOM, ATTN: DRCSF-P ,,,,1 I 4 1 i e we HISA-FM 369-80 e-4- --y_. -..__._.,-.m .., -,,, 3 y,,,,,,.3,_.y.,.,m, ,.m.,,, ,__._,,,,.,.,,_,._em.. .y,__,,.%.-,_-.-._._-y..,, ,,_,,m._

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y-- c-TO All Elements of FROM Cmdr TSA DATE 1 Jul 80 C"1 TSA Cmdr CSTAL-Mr. Potter /jle/65292 ~~" CSTAL . ri._- Dir ETDL ;- ETDL. -a -.. - f. Dir.EWL .:_-- EWL 3. :. ~ ~ ~.:~ ' d ~-.a.:.E._ -E'=I F.El-5 5 .3 = = - -. - . _ ;;-.3.-;_ _ -..,. : u. =-. 3- _

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= ~ a. It is the policy of the.CommanderfDirectors that radiation sources be used in c fashion. which. vill protect personnel from unwarranted radiation exposure and will maintain radiation exposures at a level asElow'as reasonably achievable. ~ .. ~.

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~ rr: : =.- : 1.:2.g... .a. r. 2 _. _: m ._ =. ;; _..u-- - =L, b. - Radiation sources.will be~used with#the:iniderstanding that their procurement 'and utilization shall be in acc6rdance, lith Ra'diition Safety Procedures (copy attach-' 2 J e sd). Any~ questions concerning th'e interpretati5n of procedures will be 'orought to the ~"~~" cttention of the Radiological Protection OfficeE (RPO).for assistance ahd guidance. -=-: g- - 7 z :. ~., -- 2.. DISCUSSION.

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as-"' ~... =. - ME~ ~ ~ *= ~~i~ :} [^E ~ ~ =.a. These procedures apply to all addressee organizational units and individuals l who procure, possess, use, store, transfer,' or dispose of radiation sources, i.e., _ = = _ = + rcdioactiv material vi.th an activity ofione microcurie or greater, and ionizing '===

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. :-- ?... -2=:=[+ E:E=- - - -. __ g yA-C. m==.=% .. -. d_ ~ ,_.--s - ;= l . __ y ;' b. Responsibilitiesiand' procedures governing the radiation protection program -. ~.. - cro described in the inclosure!~~' ' {2#27-W " ' ~ ~ " 2:g;:p m,;; _ _ : = =-.c.i:E=L_-. -::E il x- = :.:.. - .x -T_- :.- e -{- - -... .2. 3. REFERENCES. 1,.7 1,=_== ~==Efe~:" ?.~O2 :/;.;:

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x: --r: =5=$:: -~; ;... " = = _ CONTENTS CHAPTER PAGE ~'_..;;. 1 Responsibilities 1 3 _ ~ _. - 2 Definitions n._..... 3 Exposure Guides 9 4 Radiological Permits 12 . =. _., - ~ 5 .~. '--~ Procuring, Shipping and r- . Receiving Radiation Sources 13 g....- ~ ~"" 6 Prevention of Radiation Hazards 14 7 Emergency Procedures for Radiation Accidents 23 z-ir;; 2 2. C.. ~~ F-*"... g._.. 55.4 [. --J.. 2.. ~~ P s p. + em .b .2":.:::.'

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? bbl * CHIPTER' l.~. ' r-' r_ :.:.... :.. Responsibilities E="..).;..; 1. The Chief, ERADCOM Safety Office is responsible for establishing an effective Radiation Protection Program in coordination with laboratory directors. For this purpose he will appoint a Radiation Protection Officer to assist him and act in an advisory capacity and coordinate safety policies = = =.. = - " and procedures among various users of radiation sources.

==. 2. The Radiation Protection Officer is responsible for: Z ~_~f. _ a. Staff supervision of the Radiation Protection Program including authority to order. temporary suspension of hazardous operations. .-----c. b. Advising the Commander TSA and L'abAratory Directors on the ~ degree of hazards' associated with ionizing radiation and the effective- - - - = ness of measures to control these hazards. [_; c. Performing inspections t insure compliance with provisions of 2.5 ~ NRC licenses and applicable Army" regulations. IZZ.~ d. Maiataining the inventory of radiation sources and radioactive r-- materials, including both materials licensed by NRC and those requiring ~ ~ ~ - ~ DA authority. ~~~~" ..J e. Coordinating purchases of radioactive material to assure compliance with NRC licenses or DA authority. _; =. y _~ _ y _ f. Representing ZRADCOM on the Ionizing Radiation Control Committee. g. CoordinatAng submittal of applications for renewal or amendment of NRC licenses and DA authorization and for issuing permits to use radiation sources. v. h. Maintaining a library of current regulations pertinent to the Radia-tion Protection Program which will be furnished on request co persons covered by this regulation. 3. The Industrial Safety Officer,is responsible for providing assistance and advice on general safety matters in relation to the radiological safety --~ l programs...' y;.-~_[. .Q ~~~7 =. ..g. 4. The Chief, Logistics Management' Division, TSA, is responsible for assur- [.~. ~ ing that all purchases for items containing radioactive material, X-rays, lasers, or other radiation sources have been cleared through the Radiation

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== CHAPTER 1 - continued c'.. 5. The Chief, Logisttes Management Division, TSA, is also responsible for prompt notification of the Radiation Protection Officer when radiation "~" sources.are recei ed. Items will be picked up by the user after check by ~-lll the ~!adiation Protection Officer. . - - ~ ~ ~ 6. Supervisors in areas where radiation sources are used are responsible

====. for: ~ a. Insuring that permits are obtained before any work with radiation sources begins. [_-],','_~. ~ b. Insuring that the purchase or use of radiation sources are coordi- _~_~._:. nated with the Radiation Protection Officer. Insuring that all requisiti2ons o7 contracts requiring radioactive _ c. material or other sources of radiation are clearly marked as " documents ~ ~ ~ - " for procurement of radiation sources" and that these requisitions-are ~"l. coordinated with the Radiation Protection Officer. ~ d. Providiv.g training of new employe s in the safe handling of radiatioa sources. 7. Eorkers in areas where radiation sources are used are responsible for strict compliance with procedures approved for the specific application. These procedures and-limitations will be contained in the application for a loi si permit. 7 :. . _p. p. 3~ 8. Aay person who notices a situation where an ionizing radiation safety _T_T' ~- hazard aight exist will report thst situation to the Radiological Protection ~Z Officer, Mr. Stanley Potter, telephone 65292, or his alternate, SP 5, Norman Iratt, at the same number.' In the event that these persons cannot be contacted the report will be made to Dr Walter McAfee, telephone 54131. ~ - ~ - l

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i-. ~ . r.u E!E_( CHAPTER 2 b.5= Definitions E.=== EEEE Accelerator A device for imparting kinetic

==

energy to charged particles, such as electrons, protons, deterons -C ---- and helium ions. Airborne radioactive material Any Radioactive material dispersed N=N-in the air in the form of dusts. -g;=. fumes, mists, vapors of gases. --]- Bioassay The determination of kinds, amounts or concentrations, and locations of J' radioactive materials in the human body, whether by in vivo counting (whole-body counting, selection organ counting, etc.) or by analysis and evaluation of materials excreted or removed from the human body. ]'l Byproduct materials Any radioactive material (except ((.' _. special nuclear material) yielded in or made radioactive by exposure to the process of producing or ~ utilizing special nuclear material. Contamination (Radioactive) Deposition of radioactive material - - " ' ~ ~ ~~C ir.'any place where it is not desired, - ~~ . tad particularly in any place where its presence can be harmful. The - + - harm may be in invalidating an experiment or a procedure, or in c.. actually being a source of danger .to persons. Controlled arca A defined area in which the exposure ~~ l of personnel to ionizing radiation ~} ~.~.. l is under the supervision of an in-l dividual in charge or radiation . :,. - s-d i . protection. . = = - Jecay, Radioactive .F~ 'The disintegration of the nucleus

===

.? of an unstable nuclide by the

r_

spontaneous emission of charged IE'~- .] particles and/or photons. l 9

i......

.w. w g .e_we . e e

"~~ r y=p::. CHAPTER 2 -- continued

== ' .~~a EEsw Decontamination Factor The ratio of the amount of undesired

=

radioactive material initially present ~..... to the amount remaining after a suit-

~=

able processing step has been com-plated. A factor referring to the i==:==:.:. reduction of the gross measurable ~~ T.. radioactivity. Dose (Dosage) The radiation delivered to a speci- = fled area or volume or to the whole ~~-" body. The dose may be specified in air, or the skin, or at some depth below the surface, but no statement of dose is complete vithout specifi- ~~~~ 2 cation of location. - Dose Equivalent (DE) This is the product of absorbed dose ' - ~ ~ (D), quality factor (QF), and other " ~ ~ " factors needed to achieve the common

==

exposure scale referred to under the EZ[ definition of Quality Facu r. It is ~~.-~' commonly expressed in rems. i Dose Rate Radiation dose delivered per unit time. ~~'~1 _,_.. ~. Dosimeter D M An instrument used to detect and ~~~ measure an accumulated dose of N--. radiation. Dpm Disintegrations per minute. - b-Ganna Ray Electromagnetic radiation emitted by 6 a nucleus as a result of a transition "1 ~ i ~ ~~ ~betseen two nuclear energy levels. l l. Ganna rays have high energies with correspondingly short wavelengths I and their ability to penetrate matter -- is high. ~ Health Physics ~ ' jax- _ A term in common use for that branch n or radiological science dealing with ---~ -l~~ F' the protection of personnel from

==" harmful effects of ionizing radiation. ~ ~ ~ ~ High radiation area Any area, accessible to personnel, in which there exists radiation at Z ~~~ such levels that a major portion of =.:, the body could receive in any one hour a dose equivalent in excess of 100 millirem. ---~ l 4 l E~5 l .., ~

zs.

-

CHAPTER 2 - continued ~ =.-- .r;.. = :....=: Ionizing Radiation Any electromagnetic or particulate radiation capable of producing ions, E-directly or indirectly, in its passage through matter. Ionizing Radiation Producing Devices Electronic devices which are capable of generati':.g ionizing radj.ation such as x-ray machines, linear accelerators, cyclocrons, radio frequency generators which use klystrons, magnetrons, or 2-~";. other tubes which produce x-rays, and

---

+

electron mierescopes. One or more nuclides having the same ~E-- Istope - = atomic number but a different mass. Z'--" Istopes of a substance have altest .:===E identical chemical properties. ~-"~" Monitoring Periodic or continuous determination ~~~I of the amount of ionizing radiation or radioactive contamination present in any occupied region or location. ..1:,;. MPC Maximum permissible concentrrtion(s). Millirad mrad._ mrem Millirea = = = -r '~_~-i~- g ~ Z~~ = 1 __ : _.- _w h elementary uncharged nuclear .C p dticle which has a ass equal to

-._ z. _.. _T.

that of a hydrogen acom. ~ L~ A quantity of electromagnetic energy ~~~ ~ Photon whose value in ergs is the product r_r e of its frequency in hertz and Planck's constant. A natural constant of proportionality Planck's Constant (h) .'t& ~ ~' ~ ~ relating the frequency of a ~ . $ _ :57N _ _ qdantum of energy to the total energy of the quantum. h=6.624x10-34 joules-sec. ~~~~ ' + =- = 1 :- _c A particle equal in mass to the l._... Positron electron and having an equal but positive charge. ..=r . - - - - = r"-~

5. 5....P

.:--=:: 5 = =.

• • -"*:*T'

=:'.. -

==.=:- m..e. aw, s m,- .s.geoe->. g-n. e-r--. ee er r 4 .e e

• -,.i'e- - -. - -

-ee ve-v e. - .,,-ar-3 .--w-- -+----y-v

• gy

-y----y-.e--c--y.-wm ,r-yy---- v-ey---~ 3= w,r-ww----*

---

's--'T w

CHAPTER 2 - contiuusd

r'.

Quality Factor (QF) This is the linear-energy-transfer- ~~ ~" dependent factor by which absorbed doses are to be multiplied to obtain, r::._:. for purposes of radiation protection,

== ? a quantity that expresses on a common ~ scale for all ionizing radiations, .- n.. the effectiveness of the absorbed dose. ~ Radiation Energy propagated through space. As used in this regulation, the term refers to two kinds of ionizing radia- ~- - ^ tion: 1. Electromagnetic waves (x-rays, e-gn=mm rays) and 6--~ 2._ Corpuscular emissions from radio- ~-" [ activ.s substances or other sources '~- -(alpha and beta particles and neutrons). ~ ' - " Ionizing radiation is any electromagnetic ~ - ~ ~ or particulate radiation capable of producing ions, directly or indirectly, in its passage through matter. Radiation Absorbed Dose.(Rad) The amount of' dose imparted to matter

==

by ionizing radiation per unit mass of Z"--- irradiated material. The unit of =EE absorbed dose, the Rad, is equivalent to 10-5 Joules /ga. ?._=._=_._= C- . __~ _M-- Any area accessible to personnel in Radiation Area F ^?_i which there exists radiation at such levels that a major portion of the ~ ~ ~ " body could receive in any one hour -, ~ ~ - ~ l '~ ~ a dose equivalent in excess of 2 _ ".T ~ millirem or in any five consecutive 1 days a dose equivalent in excess of z 100 millires. .~ --.a Radiation Hazard-- '-~ - [.[ '~ --~Aiondition' under which per5ons ~ ~ If. . =. ~.~ f ~might receive radiation in excess 7 - ~'= ~ ~ ~ - ~M:-" ~ f 'the applicable==H=um permissible o l ~ ~ ~C - ~ - - - ~ ~ L dose, or where radiation damage might g.. be_causea to materials or personnel. ... ~ Radiation. Sources __... -~_ -. @ h +.-- Materials or devices which generate .q_ u -.._. c.r L=f. or are capable of generating ionizing ~ 3--. radiation, including naturally occur-ring r.:dioactive material, by-product ~ materials, source materials, special ~ g nuclear materials, fission products, "= materials containing induced or de- ~"Z_~.. posited radioactivity, radiographic [~-[ ' and fluoroscopic equipment, particle ~~~ generators and accelerators, and -~- a=2 a. h -..--n-.-~---,-n - -.,,,.......-~. -.,.,..

_.___.' ~~ ".._ " ~ ~ ~ ~ ~ ~~ CHAPTER 2 - continued " --R electronic equipment which utilizes kystrons, magnetrons, or other el'ectron tubes which produce x-rays. Radiation Work Permit A locally developed femm which is ~ completed prior to the start of any work that is to be performed in a controlled area and describes the ~ potential radiation hazards and a given job. b dioactivity Process whereby certain nuclides undergo spontaneous disintegration, liberating energy through the emission of alpha or beta particles or gamma photons or a combination of these. Radiological Survey ~~+ Evaluation of the radiation hazard incident to the production, use, or existence of radioactive materials or other sources or radiation under a specific set of conditions. Radiologicci Protection Officer An individual designated by the (RPO) commander to provide consultation and ~ ~' advice on the degree of hazards associ-ated with radiation and the effective-I. ~ i~ '~ ness of measures to control these ""~ hazards. In addition, he is tasked l ..~.1-- with the supervision of the Radiation Protection Program. This individual .m._. will be technically qualified by virtue ,,.of education, training, and professional 5 experience, to assure a capability ~C ~ _. commensurate with the assignment.- (The term " Radiological Protection- .4. Officer" is not intended to denote'a - ~~ commissioned status.) ._. g,.. Restricted area ..-[5 N.~ Any area to which access is controlled

_

.: u --ga.7 for ' purposes of protection of individ-

-_c.:._-;aj.r-uals from exposure to radiation and F---= radioactive materials. .w.uD..- l g.mu. --. ~. - - - i 7 ..u... .944 .e_ I

52Eh: 1"=.b: CHAPTER 2 -- continued .".":.~~~ Roentgen The quantity of X or gamma radiation 7.~2--. such that the associated corpuscular .~.~ 17 emission per 0.001293 gram of air . =. = = = - (lec of dry air at standard conditions)

==

produces, in air, ions carrying one ~ " ~ ' electrostatic unit or quantity of electricity of either sign. This is the radiological unit of exposure. Roentgen Equivalent Man (REM) 'Ihis is the unit of dose equivalent (DE) and is commonly referred to as the roentgen equivalent mammal. Special Work Permit.:. f.- .q A permit to assure that no work will " - - ~ ~ ' u.. commence in areas where radiation is greater than 20 mrem /hr until each Job has been properly evaluated from a radiological standpoint and has been = e- - approved by Health Physics personnel. 2. User An individual assigned to an activity, section, division, or other organiza- ~~~~ tional unit which has been deletated ~~~ the responsibility for the use, oper- ...E". ation, or storage of radiation sources. ._]

-}

-3~ _ gj -- h -,. -. .=- X-ray -===_ "__~ ~ Penetrating electromagnetic radiation .u.. _having wavelengths shorter than those l . l.~.-l ..of visible light. X-rays are similar "-~ ~ ~ ' ~ ~ rays, but originitt..inir.3 i- ~ ~" to gamma ~. l ., ~ _. ~_ the extrr -nuclear origin. ~- ~~ [.~.... .-.._7

.7

..;~~;" '~ _. - - -.. _. :..: _.. ~~'~.;-= ~ ' ' ^^2 ~ 3_ ---r -..=;. =~: --.:a ^ l .=2-W=s -

=;.

g.; . =. m= ~ r . --. =:..:-- ;..-- - = -. -=,. :::.:9...-. _.: z -

~......

_- -~~ ~ l e

• • = "*:.

i.. p..~...e.~es~ ~ 8 re. C ::;.;::..

=. - -. .o ~ i=

== ~ CHAPTER 3

===9 ~ * ~ ~ ~. EXPOSURE GUIDES

Z...."

1. Regulations. Requirements as set forth in Title 10, Parts 19 and 20,

===M~ Code of Federal Regulations, and AR 40-14 for the Control of Occupational r_ Exposure to Ionizing Radiation, will be followed. Recommendations in the National Bureau of Standards Handbooks on Radiation will be used in addition. Z:~~:: 2. Exposure of individuals in controlled areas. a. A controlled area is any area in which the exposure of personnel to radiation or radioactive materials is under the supervision of a radiation protection officer. Every effort will be made to maintain radiation doses as low as possible. Avoid all unnecessary exposura. to ionizing radiation. Radiation protection standards for the control of, ccupational exposures to ionizing radiations include the following: ,. 3 g. (1) The accumulated dose or radiation to the whole body, head and trunk, active blood-forming organs, gonads, or lens of the eye shall not exceed: (a) 1.25 rem in any calendar quarter, nor (b) 5 rem in any one calendar year, nor ]'~ (c) 5(N-18) rem total lifetime dose, where N equals the present age in years. '.5 ~ (2)~ The accumulated dose of radiation to the skin of the whole body, forearms, or the cornea of :the eya shall not exceed: - - =.. = (a) 7.5remInan[cale.ndar uarter', nor T l (b)_ 30 rem in any calendar year. ~E' - =. +. = :. (3) ~ The accumulated dose or radiation to the hands and wrists or the feet and ankles shall not exceed:4:_ 2lE '.2 i+h. ~ - :~:. :. - __..' (a)..18.75 rem in any calendar Tuarter, nor ~ . 2. - . _, W. -' ='~ ^ ~ (b) ~75 rem i fany calendar year. ~~T .. =:1_ (4). All radiation. exposure will be. maintained as low as reasonably ~ achievable. ~ ~ ' ~5: T M ---- - - m -- .C=-j =(~~] l ;.). b. Personnel not occupationally exposed, and persons who are less than 19 years of age vill 7not be' exposed in any calendar quarter in excess ~ of 0.125 rem or in excess of 0.50 rem in any calendar year. Pregnant ~ ~ ~ " - ~ women will not be exposed to occupational doses o^f ionizing radiation. ~~~- When a female employee becomes aware of her pregnancy, she will request that her duties be changed to eliminate all occupational exposure to [.. ionising radiation. ..e l .~ z'.

g...

l l l

..J ~

===

t, CHAPTER 3 -- continurd ~" c. Occupational exposure to radioactive concentrations in air or water may not exceed the limits set forth in Title 10, Part 20 of the Code of Federal Regulations. Z:"' 3. Exposure of individuals in uncontrolled areas. Radioactive materials 5 and other cources of ionizing radiation will not be possessed, used, or Z~" transferred in such a manner as to create in any uncontrolled area radiation levels which, if an individual were continuously present in the area, could result in his receiving a dose in excess of 0.5 rem in one calendar year. ~ ~ ~ ~ ~ ~ 4, Limits for contamination. When hands, body surfaces, clothing or ~ shoes become unavoidably contaminated, steps will be taken as soon as possible to remove loose contamination. Decontaminate hands and body surfaces until no detectable activity above background is observed. Some degree of fixed contamination in certain cases cannot be avoided and the ~~~~ following maximum limits are recommended for personal clothing and shoes (see Chapter 6, Pa~rha66):2 i~_ ..y c.:p. q. Alpha activity - 200 disintegrationsler minute per 100 square centimeters of area. -~ Beta-gamma activity - 0.2 millirad per hour at one centimeter. ~ 5. Concentrations of radioactive contamination surfaces, a. Loose contamination on exposed surfaces such as bench tops and floors will be ~~ removed as soon as possible. Small amounts of fixed contamination will be unavoidable at times, but the degree of such contamination should be kept as low as pracgicable. mmh =n= limits of fixed contamination:of 1000 dpm per 100 cm of alpha and 7 mrad /hr at I cm of beta-gamma are ZZ~ " 1 i recommended for controlled areas.~ Amounts of contamination in excess of the above limits will not be permitted to remain on exposed surfaces without approval of the RPO. Higher levels of contamination may be permitted for restricted surfaces, that is in areas where entry or access ~ ~ ~ ~ " ~ is controlled by procedures or special work instructions. The same standards of contamination control shall apply to tools and equipment.7 - ~ - - - - " In all cases, signs and controls for contaminated surfaces, areas, or euqipment will..be instituted to the extend necessary to prevent the l occurrence of a ' health hazard 'or the spread of contamination. In no case I will the levels result'in exposure to individuals in excess of the estab- --~ lished limits. ~ Any material or equipment jio contaminated [will be properly

-]

labeled with a contamination tag giving: =3 __T (1) Type and. level or radiation (mrad /hr) at a specified distan:e. ,. il =::==.:.:.,. 3 . ~.-=5T h

Q._.

(2) Extent of contamination on surfaces. iy- ~- l b. No contaminated equipment or material may be removed from any l area withovt prior notification and approval of the RI'O. Any equipment d'EEEL or material to be maintained or handled in a clear area must be decon-taminated according to the requirements set forth in Chapter 6, paragraph ~" 6, Table 1. EE= =.= :

• * = "

g 10

==

.3 I f

~~ z =.. CHAPTER 3 - continued {?.""".J 6. Radiation protection controls governing beta-gnama exposure. The CY following limits wi11 be observed: a. No individual without a special work permit will be permitted - ~ ~ ~ to work in a radiation controlled area where exposure levels are greater than 20 mrem /hr. b. Any radiation area where exposure levels are greater than 100 mrem /hr shall be classified as a high-radiation area. - An accurate

=

exposure record will be maintained for each individual required to work in a high-radiation area. Based on pencil dosimeter reading, the record will contaia the total cumulative exposure of the individual during the life of the special work permit. (. u_. ~~;= j~Q ~ER. c. The time during which any individual is exposed will be controlled so that exposure limits will not be exceeded. Exposure at all times will be kept as low as reasonable achievable. p 7. Radiation protection controls governing alpha exposure. External " - ~ ~ exposure to alpha radiation is negligible, since the range of the alpha particles is less than the thickness of the layer of dead skin. Fume hoods will be used in conjunction with the long-lived alpha-emitting substances or other substances presenting a similar health hazard. In handling an unsealed alpha source, gloves or forceps afford adequate l protection. Sealed alpha-neutron sources must be carefully handled to protect the integrity of the seal and prevent the spread of contamination. The prime hazard to consider is personnel contamination and the danger of ~ ingestion or inhalation of airborne contamination. Fume hoods should have ~ ~ ~ an absolute filter.. The linear flow rate should be at least.150'ft/ min. ~ ?... Airborne contamination levels will be determined as set forth in Chapter 6, paragraph 6. ~l_.. .K g ~ . = ... =.. .2 . ' ~ ?$.. ? 3 U '.. R. k= b- = ~.= E.3:f.~~~ -f.;E.;. f ---.:.=. ~ . h'.*" h* ~~ ~ ~.* ..a. . ~. :.'. 6.- -n. ~ N ? 55- ~ - - ^4.. f..~.-. ^ -"'~"; -i_i = : * - &&. '. - ~ m- .}i _ - _ -) 5 - ~ ..~ T** .Q,**.'".' j{ .a. .e t... 11 = -n. . ~._ ~ ~ ~ '~ ~ ' ' s -e--. vc .,.... - -., -,. - - -. - -., - - ~., _ _, -,..,,. -,.. -.,., _..,_.m.

l - 6* CHAPTER 5 Procuring, Shipping and Receiving of Radiation Sources 1. Procurement. All requisitions or contracts for items that contain radioactive materials will be coordinated with the Radiation Protection Officer. Each request for radiation sources will include a covering DF

---=.

stating the need for the material and citing the local radiation permit-where the sources will be used. Procurement of radioactive materials will not be initiated until propar coverage under a NRC license or DA authoriza-tion is issued. i 2. Shipping. The user (person originating.the shipment) is responsible for the a. proper packaging and labeling of radioactive materials for shipping. The user will initiate DA Form 2791-R which will then be completed by the Radiation Protection Officer. b. The user will provide the Radiation Protection Officer with a copy of the NRC License or DA authorization of the person who will receive the -~~ radioactive material. 3. Receiving. a. The Radiation Protection Officer will check all radioactive material when it arrives. He will complete all necessary shipping paperwork, then notify the user to pick up the radioactive material. Radioactive materials will only be transported in privately owned vehicles in emergency cases, and only with specific approval of the RPO. n= b. Upon receipt of radicactive material, the Radiation Protection Officer will perform a leak test, when required, and notify the user of the " - = results of the leak test. U I Q l y ~. Z :: .f 13 ..~._y d 4 I ~.

= =.

==u:usu CHAPTER 4 Radiological Permits -~~ 1. Local permits for the use of radiation sources are required. Applica-5-S tions for permission to use or store radioactive materials or sources of ionizing radiation will be submitted to the Radiation Protection Officer, - -~ DRDEL-SS-FM-H. 2. Radioactive sources. Local permits for the use er radioactive materials ~ will be issued only when an approved NRC license or DA authorization is l available. Contractors will be issued a local permit basid on an approved DA permit. 3. Application for local permits. The local permit must be obtained before procurement of the particular item (s). Each organization desiring - - ~ " ' to use a radiation source will apply for a permit. Application will be on DF addressed to Radiation Protection Officer, DRDEL-SS-Mi-H, and will include the following information: a. Organizativa. b. User personnel and qualifications (include training and experience). c. Type or radiation source. d. Physical form of the radioactive material. I_ zr-e. Number of sources required. l f. Quantity of radioactive material or power of radiation source (s). g. Planned use of radiation source. = - -. h. Radiation protection equipment.

i. Facilitiies where radiation source will be used.

j. Radiation protection program (SOP)'.

Special Work Permit ~~~ An application for a special work permit must be submitted to the RPO before working in any area'with radiation levels' greater than 20 mrem /hr when auth-orization has not been otherwise obtained. (included in local permit). -~ Radiation Work Permit (RWP) - ~ = ~ ~E Upon request from radiation area supervisors, a radiation work permit will be issued by health physics personnel for work when unusual working conditions are required as prescribed by the RPO. h.sjin l 12 . - - - ~. 1 ,m e,.m wee. ---ee-w- =#

e = = = =. .:::*:=:: CHAPTER 6 Prevention of Radiation Hazards 1.

Method, a.

This chapter contains information on the prevention of

== radiation hazards and special precautions necestary to safely work with ~~~ radioactive materials. The three methods of rad'4 tion hazard prevention are: Mechanical and chemical, medical, and monitoring. All personnel required to work in radiation hazard areas will be informed as to the function and use of each method. .___. 7 b. Some methods of radiation hazard prevention involve the proper use of fire extinguishers, roping off and posting of areas, permanent and por- ~~~ ~ ' - table shielding, and the use of area-monitoring instrumentation. Another method of radiation., hazard prevention includes the protec-c. tion of personnel by wearing some of all. oEstHelfollowidgtingmae: depending on the type of work: Disposable clothing, coveralls, plastic aprons, gloves, plastic shoe covers, and/or boots. d. Decontamination materials include such things as pthe 9hamichisuussd -~ to decontaminate personnel and laboratory equipment, waste containers, swabs ~~ ~l or Kemwipes, and paper - both absorptive and non-absorptive. e. Prevention of radiation hazards is effected by the establishment of restricted areas, time limits for stay in danger zones, and the requirements to comply with exposure limits and other rules. 2. Procedures. a. Mechanical and chemical. (1) Film badge' service will be initiated or discontinued.,by request to the RPO. An adequate supply of [_']l film badges will always be ana11able for imediate use. Staff members who l escort visitors to radiation. areas are responsible for signing badges in l and out for their visitors. (2) Each person assigned a film badge will wear only the particular badge number assigned to him. Under no circumstances will badges be ex- '-~"-' changed with another person. Film pack 2 should never be removed from the badge or tampered with in any way. (3) Personnel working in radiation areas must wear badges at all times m. while they are in such areas. These badges may be worn comfortably on the _;;m... ~ belt line or chest but they must never be covered by any other clothing or -~ carried in pockets. (4) All film badges will be kept in the assigned badge rack at the end of the work period. They will not be taken out of the building unless the -~ l outside specific duty or travel will be associated with an exposure to l radiation. "T .h ';:b:. *::. 14 4 e m ro ww,.e.-we eg-- -. - = m+e .P w e -.p- ,,w,- ,--me ,n -m er---- --wv., ,--w --w ,m = ~

W p CHAPTER 6 - continued (5) Film badges will be collected for exchange of film each month on the day specified on the assigned badge rack. ~ ~ ~ ~

== (6) Pocket dosimeters will be recharged as required. Additional pocket dhutmaemm will be maintained for visitors or persons whose routine does not require a permanently assigned film badge. These dosimeters will be signed for in a log, the dose will be recorded, and a notation will be made that the person wearing it was a visitor. (7) All persons entering radiation areas will wear a dosimeter or a film badge. People who are unfamiH ar with the facility will be accompanied by responsible. personnel acquainted with the facility. All persons entering a high radiation area will wear a film badge and a dosimeter. (8) Fire extinguishers will be placed in conspicuous places in radia-tion areas and clearly marked. They will be periodically checked and maintained by the Area Fire Captain. Any extinguisher that is used will not be returned to its rack but will be reported to the Fire Captain _as soon as ~'"" possible. All personnel will familiarize themselves with the location and use of these extinguishers throughout the building so that in the event of an emergency they will be brought into use as sc,n as possible. (9) Radiation signs and tags are posted for the safety of every employee and must be respected. The Radiological Protection Officer will post and remove radiation warning signs. When radiation levels exceed permissible - -~ levels, the area will be posted with appropriate signs. These signs will indicate' the nature of the radiation and/or contamination, the date of post-ing, the radiation level at a specified distance, and any other appropriate data. l. b. Medical. (1) Each person working with radiation will be required i to undergo a complete medical examination at the start of employment and at l one-year intervals thereafter. This initial = = 4n= tion will include a complete medical history and physical erm=4 nation. The history will include a notation of previous work with ionizing radiation. A copy of each medical record will be kept 'ori file by the preventative-medicine facility. The entering examination will include a complete blood count, urinalysis, and a chest x-ray. = (2) Special checkups will be made at any time as determined necessary by the Radiation Protection Officer and/or. Preventive Medicine Officer. ..z .~. ~ c. Monitoring.- (1) Personnel monitoring will be accomplished by the ? use of film badges and dosimeters with resulting data recorded. Special monitoring due to exposure or contamination may be required. Cases of ~~~ overexposure or contamination may require a special ma. dical checkup. 1 ) l 5::1 15 ....am.a e44--- /I

c 4 CHAPTER 6 - continued

( =;;;

i=;g:-- (2) If an individual receives a dose of ionizing radiation in an amount exceeding 1.25 rem per calendar quarter, he will be removed from d.U-duties involving occupational exposure to ionizing radiation until subse- =#- quent exposure limitations are established in consultation with competent medical' authority. Should an individual receive an accumulated dose of ionizing radiation in excess of 5(N-18) rem, he will be removed from duties involving occupational exposure to ionizing radiation until his exposure record has been evaluated by the Surgeon General of the Army and subsequent ~~~" exposure limitations are established as necessary. (3) The frequency of area monitoring will depend upon the radiation levels of the usual work in the area, the frequency of the use of the area u. and other conditions specific for each area. The radiation area supervisor will assure radiation levels are determined prior to working in a radiation ~*"~ control area, on a daily basis (4) The general radiation background in the area will be first recorded. Successive readings in representative work areas will be taken and noted. f If any locations are noted where the dose rate is greater than the maximum permissible, the area will be posted immediately. Where additional shielding vill correct the situation, this will be done as soon as possible. (5) The RPO will ensure that each radiation facility is surveyed at ~ ( least monthly. As each area is surveyed, a check will be made to detect - - - ~ - - - j any existing or potential hazard and to rectify it. (6) "Special surveys will be made by the RPO at any ti: c upon specific request of an individual or before unrestricted entry is permitted to a previously contaminated area.. q - - = -. (7) Sufficient instrumentation is available to the RPO to properly ~~:~ "~: support all special radiation surveys. All instrumentation used for radia-y--- tion protection will be calibrated at least every three (3) months, and after each maintenance or battery change. Dosimeters will be calibrated at least every six (6) months. ~ __._.u 3. Periodic checkups. a. From time ^to time, inspections will be made to insure that personnel are complying with procedures in radiation areas. Periodic checks will also insure that any modifications to the basic operat-ing procedures are being followed correctly so as to minimize radiation ~ hazards. F b. Constant inspections are necessary to avoid a dulled alertness on N the part of personnel.'^ It cannot be overemphasized that while working with radiation can be safe, mistakes may be very dangerous and possibly fatal. l The checkups, are for the safety of personnel. ..e.e e.us.. 16 l .na="x.. l

=i~?i:i:,

=

CHAPTER 6 -- continued "~### The efficiency of all warning devices will be determined at intervals c. ZZ~ not grerter than one month; this is in addition to the complete maintenance

==

check which will be made at any time on all locks, etc. If at any time there

=

is a failure in any remote monitors, work will be halted immediately and the g.;,. approval of the Radiation Protection Officer Will be required before normal operating procedure is resumed. 4. Access to radiation areas. a. Access to areas where there is a poten-tial radiation hazard will be limited to minimum personnel required to safely, efficiently, and most readily carry out the required procedures. All persons t := entering an area classified as a Radiation Control Area or a High Radiation P:= Area must wear a film Badge. A pocket dosimeter may also be required in certain areas. All visitors to radiation areas are required to be accompanied by personnel assigned to the area. A " visitor" is considered to anyone not _ _ _.- ~" directly connected with the work being conducted. All visitors must be advised of the potential hazards prior to being allowed into a radiation area. I b. Anyone discovering an area of hazardous radiation will evacuate the area and call the RPO who will accurately survey the area and post it. Only the RPO has the authority to remove any signs once they are posted. 5. Radiation hazard signs. These signs are in the form of labels, tags, ~~ and signs for posting areas and equipment and identifying radiation areas . ; =. and items which may be radioactive or contaminated. They incorporate the standard magenta and yellow color, the three bladed radiation symbol, and appropriate working, such as " Caution," " Danger", " Contamination", " Radiation Area", and "High Radiation Area." 'Where such signs and tags are used, additional information may be added to them by the RPO to further - ~ ~ identify the nature of the hazard.. The information will contain the nature of the substance causing t'ae hazard, its dose rate at a specified distance, the date, and other peetinent information. 6. Decontamination and wast.: disposal. a. In order to prevent the possibility of contamination, the following regulations will be observed: (1) There will be'no smoking, drinking, or eating in radiation control areas. (2) In cases of skin contamination, no eating, smoking or application of cosmetics will be permitted until all removable radioactivity has been taken from the skin and the person is released by the RPO. (3) Organic solvents, highly alkaline soaps, or abrasives should not be used for decontamination at any time, since they increase the possibility

== " of skin injury and serious contamination. Levels of radiation beyond which ~~1 areas are considered to be contaminated radiation areas are outlined in Chapter 3. Any incident or accident which causes an area to be contaminated must be reported immediately to the RPO. The use of any decontaminates other than mild soap and water should only be done under the supervision of medical personnel. - - =.

==

p.. ..e.. -r v. -,.e rw,- .--+------w--w

---

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e as.. =EF + h_~~b::A CHAPTER 6 - continued .E. b~ b. The RPO will be responsible for establishing procedures control-I2.7 ling the spread of contamination. These procedures will include emer-gency ventilation control, controlled step-off areas, controlled passage-E~ ways, personnel monitoring, decontamination procedures, etc. -.=: =: c. All persons selected by the RPO to work on monitoring and de-contamination will be equipped with protective clot.hing, suitable gloves and other equipment required by the level of work. d. In the event of airborne contamination the RPO will determine through the use of fixes or portable air sampling monitors the extent of the contamination. The RPO will specify the madmum levels for personnel access to airborne contamination areas. These limits will not sxceed: Alpha Beta = = ' ' For Personnel Wearing Concentrations Concentrations No respiratory protection 1 MPC* 1 MPC* l M-17 full face respirator 5 MPC* 10 MPC* ~ Supplied air or self-contained ~ air supply with full face mask 50 MPC* 50 MPC* iEE"

• Maximum, permissible concentration e.

When there is a possibility of conramination or radiation hazard,

== all ducts and vents leading from the building, whether they are for water, air, gas, or electrical conduit, will be marked so that maintenance or repairmen will be aware of the potential hazard. Where these tags exist, the RPO will be notified to survey the area before any work is ~~" l started. If the need for shielding is indicated by monitoring procedures, ~ the supervisor or the project leader will provide the shields before work j in this area can resume. - _r. f. Personnel decontamination methods depend upon the nature of the contaminating material and the size of contaminated skin area. No detectable contamination level above background is allowed to remain o.t hands or skin after decontamination. The following procedures will he ~~~7 used itunediately: n.. 1 _. (1) First notify the RPO. 'All~ materials needed for decontamisation 8 will be furnished by the RPO and will be located where they will be most convenient for use. .===. (2) Thorough vashing with soap and water and rinsing with large 3.;[ quantities of water is the best general decontamination method for the

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hands and other parts of the body, regardless of the nature of the radio-

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active contaminant. If, however, the contamination is well localized, 18 555

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CHAPTER 6 - continued EEE n=== =.=.-=::.

==

it is recommended that the area be cleaned immediately with sam 11 swabs

-~2 and later, if necessary, by'a general washing. Spread of contamination EEE i

to other skin areas is thus avoided. g. If the contamination is widespread, a general washing or shower i should be taken and other more specific measures outlined below should be followed under medical supervision and the RPO. ~~ ~ 4 (1) For general washing: Wash the hands for two to three minutes 'T l ~ in tepid water using a mild soap, with special attention to finger folds, 27... outer edges of.the hands and fingernails. Rinse thoroughly and repeat EE.Es a maximum of four times. If the required degree of decontamination is not reached, proceed with step (2), (2) Using a soft ' brush, wash and rinse contaminated areas three 2.'. times in eight minutes of which no less than six minutes are spent in ~ ~ ~ ~ scrubbing. Use pressure light enough not to abrade the skin. Rinse thoroughly and monitor. If the desired level is not reached after several trials, c.hemical decontamination may be attempted as outlined in step (3). (3) Apply a paste of titanium dioxide thirty and work it in [1.- over the contaminated areas for a minimum of two minutes. Use water i..... sparingly, only enough to keep the paste moist. Rinse with warm water and follow with soap, brush and water, being extremely cautious to e __. remove all paste about the nails. Monitor. Repeat process if necessary. If three successive trials fail to remove all contamination to the pre-scribed level, follow step (4). Note: Do not use near face or other -~~ 4 body openings. M Daub over the contaminated area a saturated solution of potassium T permangenate for not more than two minutes. Wash with soap and water i and rinse. Next, apply a solution of sodium bisulfite to remove the j dark permanganate stain. The procedure may be repeated but since the permanganate is caustic to the' skin," care should be taken to follow the ( prescribed times closely. Hand cream should be used as a final step EE to prevent chapping. Note: Do not use near face or other body openings. h. Persons with cuts or wounds will not be permitted to work in a contaminated area or radioisotope laboratory unless specific approval is obtained from the RPO. Any wounds, cuts or abrasions received while working with, in, or near radioactive materials should be flushed with ___EE = ? water.immediately. Any such accidents should be referred to the RPO immediately so that specific measures can be taken. FE' E 1.- The RPO will assist in and monitor the decontaminat. ion of materials

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and equipment. He will supervise the disposal or radioactive waste and [_[ other work connected with radiation hazards.

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CHAPTER 6 - continued j. In the event of contaminated clothing, the contaminated articles "~~~ will be removed imnediately. Skin areas underneath the clothing will be cleansed as soon as possible and the contaminated clothing placed in plastic' bag so that it may be properly laundered and recovered.

== k. In order to prevent the gross contamination of laundered items, two separate laundry systems are employed. All contaminated laundry ~- generated in radiation areas is laundered in a specially equipped laundry. 1. Contaminated materials will be disposed of in suitable dry radio-active waste or liquid radioactive waste containers. At no time should dry radioactive and liquid radioactive wastes be mixed. C~ntainersic: .t a for radioactive waste containers will be stored in the radioactive storage vault. m. The RPO will aid in_the problem of evaluating contaminated equipment. If it is not practical to decontaminate the equipment, it will be handled as dry radioactive waste. In some cases, it may be possible to store such equipment for future use when radiation levels have decayed to acceptable levels. Equipment properly marked and shielded will be stored in the radiation storage vault. n. The following methods can be used to decontaminate equipment; 75 the decision as to the actual and most practical method will be determined by the RPO. (1) Equipment may be washed with a hot, strong detergent solution, rinsed, and procedure repeated until the desired decontamination is ' - - ' ~ reached. Chemicals that may be used include chromic acid, nitric acid, anunonium citrate, trisodium phosphate, and ammonium bifluoride. In selecting decontamination materials, the nature of the surface and extend of contamination must be considered. For all practical purposes, decon-tamination effectiveness of a solution is considered complete at the end of the second repetition of any one process. If the desired level is not reached at this time, other methods should be considered. (2) Before any decont==inated equipment or articles can be moved or transported to a " clear area" the RPO will determine the extent of "~ contamination of the particular item. Limitsofcontgminationforitems to be admitted to a clear area on the basis of 100 cm area are as follows: Loose couramination detectable by smear Alpha (DPM) 50 - ;c-Beta-Gamma (DPM) 100

=

MmM== fixed contamination Alpha (DPM) 200 ~ ~ ~ ~ ~ ~ Beta-Gamma (m Rad /hr) 0.25 = =.. 20 --:n-5=5E i

=... :: g CHAPTER 6 - continued _ _.I.. --== In the case of area contamination, the method of decontamination will depend upon the nature of the surface. These methods are vacuuming. ="" I physical removal of surfaces, covering of short-lived materials with impervious materials, detergents, and chemicals. When practical, areas which are contaminated will be isolated until radioactive decay permits safe entry.

=.--

o. All area's which are contaminated by accidents or spills will be evacuated immediately. If certain safety precautions can be instituted (such as placing absorbent paper on a spill to prevent spread of the ~~ - ~ contaminant) without endangering one's safety before leaving, it should be done. The RPO will monitor the contaminated area and determine the most practical methods of decontamination. ~ ~~.^.:..

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