ML20053B130

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Application for Renewal of License SNM-244 Authorizing Possession & Use of Enriched U in Neutron Detectors & Pu in Pu-Beryllium Sources,Neutron Filters & Alpha Source Stds
ML20053B130
Person / Time
Site: 07000263
Issue date: 02/26/1982
From:
ARMY, DEPT. OF, HEADQUARTERS MATERIEL DEVELOPMENT
To:
Shared Package
ML20053B127 List:
References
20663, NUDOCS 8205280094
Download: ML20053B130 (44)
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!D APPLIC ATION FOR RENEWAL OF SPECI AL NUCLEAR MATERI AL LiCEN SE NO.

SNM -244 26 February 1982 Army Materials and Mechanics Research Center Watertown, Massachusetts 02172

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90- % 3 APPLICATION FOR 'lllE RENEWAL OF SPECIAL NUCLEAR-MATERIAL LICENSE NO. SNM-244 In accordance with the U.S. Nuclear Regulatory Commission (USNRC), Code of Federal Regulations, Title 10, Part;70, request that license SNM-244 pres-ently held by the Anny Materials and Mcchanics Research Center (Abt!RC) to possess and use special nuclear material be renewed as described herein.

The following information is provided in accordance with 10 CFR, ' Part 70, as required by the indicated sections:

Sec. 70.22(a)(1) Army Materials and Mechanics'Research Center Arsenal Street Watertown, Massachusetts 02172 Sec. 70.22(a)(2) Uranium, enriched in U-235 isotope is used in neutron detectors, which are associated either with the AhtlRC nuclear reactor control system, or neutron experiments at other Abt!RC laboratories.

Plutonium, fabricated into two (2) 5 curie Pu-Be neutron sources, is used to calibrate neutron detectors, neutron survey meters, and foils used in AMMRC laboratories.

fabricated into four (4) neutron filters, is used in neutron Plutonium, experiments associated with the Mf!RC nucicar reactor and associated a.,paratus.

j Plutonium is also to be used in a maximum of four (4) alpha source standards.

Sec. 70.22(a)(3) The 'icense is requested for the same period as presently j

issued.

I Sec. 70.22 (a)(4) Applicant proposes to use and possess up to eight (8)

I grams of uranium enriched up to 90i, in isotope U-235.

The uranium will be i

utilized in the chemical forms of U 0, and UO.

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Applicant also proposes to use and possess up to one hundred and sixty l

(160). grams of pluton ium-239.

The plutonium is mixed with beryllium and is contained in two stainless steel cylinders,- each 3.2" long and 1.3" in diameter.

i Applicant further proposes to use and possess up to thirty-two (32) grams.

l of plutonium-239, fabricated into four pieces, approximately 2" X 2'? X 0.005",

4 cach sealed in an aluminum can 3" in diameter by approximately 0.050", to be used as neutron filters, and up to 0.16 micrograms of plutonium-239 to be used in four (4) alpha source standards.

Sec. 70.22(a)(5) Deleted effective April 14, 1967.

Sec. 70.22(a)(6) AMMRC personnel involved in the use and handling of special nuclear materials are listed below. The technical qualifications, including training and experience of each individual user, are included in Appendix 1 of this application.

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i NAME POSITION Dr. John J. Antal Supervisory Research Physicist l

Mr. Forrest C. Bums Research Chemist 1

William A. Lorenzen IIcalth Physicist / Radiological Protection Officer Mr. Cha rles E. Dady Chemist / Radiological Protection Officer, Alt ernat e John F. Vining Superviso.ry Safety Engineer / Radiological Protection Officer, Alternate Dr. Laurence D. Jennings Research Physicist

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ILT Louis J. Farese Member, X-Ray and Neutron Analysis Group Dr. James W. McCauley Chief, Materials Characterization Division i

Robert Fitzpatrick Research Materials Engineer i

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NOTE: Use and handling of material under this license will be carried out by the individuals named above or under their direct supervisor.

1 Sec. 70.22(a)(7) 1.

The facilities and work areas which will be used at 4

AMMRC in conjunction with special nuclear materials are as follows:

f a.

Reactor.

(Reference USNRC Docket 50-47) The reactor is currently in standby status.

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b.

Building 97.

This building is joined to the reactor shell by an air-lock and contains laboratories for use in the experimental programs using a 14 Mov generator, and two Californium-252 sources (approximately 2.6 curies total on 31 October 1976).

Floors are covered with vinyl tile and walls and ceiling painted with acid resistant paint.

Personnel decontamination facilities' are provided.

Walls of all rooms are solid concrete block or poured concrete, (6 inches thick).

c.

Calibration Laboratory.

This laboratory is attached to Building 97, but is accessible only from outside the building. The two Pu-Be sources and i

the four neutron filters are stored in the ' source storage area of this lab.

Entrance into the source storage area, as well as the Calibration Lab itself, is strictly controlled. The Pu-Be sources are used in the Calibration Lab for calibrating neutron survey instruments.

2.

Ilandling Devices. Mobile glove boxes are available for use if ever required.

Long-handled tongs and magnets are also availabic and complete machine-shop fac-

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ilities are available for fabrication of special-handling equipment.

3.

Shiciding.

Large quantities of lead bricks, solid concrete blocks, and paraffin are readily available for shielding.

Facilities, including a foundry, are available for fabricating storage containers.

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Measuring and Monitoring Inst rum,ents. A complete list of radiation measur-a ing and monitoring instrument s presently at this Ccnter, is included in Appen-dix 2 of this application.

Sec. 70.22(a)(8)

Safety Procedures and Monitoring.

Special nuclear mat-b j

erials will be handled in a manner which is consistent with the radiation safety i

regulations prescribed in AMMRC Memorandum 385-4, " Radiation Protection Policy.

f and Program", dated 22 Phrch 1978. A copy of this regulation is included as Appendix 3 of this application.

Criticality. Uranium and plutonium in the amounts requested in this app-lication present no criticality problem.

Waste Disporal.

Plutonium presents no' waste disposal problem as it will I

be used indefinitely. The sources will be returned to the vendor for repair l

if leaks develop at any time. The uranium referenced in this application will i

be returned to the USERDA when it is no longer useful to this Center.

Leak Testing. The procedure for leak testing scaled plutonium sources is 1

i as follows:

Each plutonium source shall be tested for leakage every three (3) a.

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months.

In the absence of a certificate from a transferor indicating that a 1

test has been made within three (3) months prior to the transfer, the sealed source shall not be put into use until tested.

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b.

The test shall be capable of detecting the presence of 0.005 microcurie l

of alpha contamination on the test sample. The test sample shall be taken from 1

the source or from appropriate accessible surfaces of the device in which the scaled source is permanently or semipermanently mounted or stored.

Records of I

leak test results shall be kept in tmits of microcuries and maintained for inspec-tion by the USNRC.

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c.

If the test reveals the presence of 0.005 microcurie or more of remov-able alpha contaminat ion, the source shall be immediately withdrawn from use and be decontaninated and repaired or be disposed of in accordance with NRC 10, CFR 20.

Within five (5) days after determining t hat any source has 1 caked, AhMRC will file a report with t he Director, of Nuclear Material Safety and Safeguards, U. S. Nuclear Regulatory Commission, Washington, D.C.

20555, describing the source, the test resu lt s, t he extent of contaminat ion and the corrective action taken.

A copy of t he report shall be sent to the Director of the nearest USNRC Regional Compliance Office listed in Appendix D, NRC 10 CFR 20.

d.

The periodic leak test does not apply to scaled sources that are stored and not heing used.

Sou rces removed from storage shall be tested for leakage prior to any use or transfer, unless they have been leak tested within three (3) months prior to the date of use or transfer.

II. S. WRIGiff Director 1

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Dr. John J. Antal 1957-Present Research Physicist, Army Materials and Mechanics Research Center, Watertown, MA 1952-1957 Guest Associate Physicist, Solid State Physics Section, Brookhaven National Laboratory 1952 Physicist, Watertown Arsenal Laboratory, Wa te r town, MA Education and Training 1948 B.S., Physics, University of Scranton 1949 M.S., Physics, St. Louis University 1952 Ph.D., St. Louis University During graduate school, he held a Graduate Fellowship, and was Instructor in Electronics for an Air Force program.

Pertinent Experience Pertinent areas of competence include:

neutron scattering by solids, radiation damage in solids, neutron spectrometry, neutron facility design, computer-experiment interface design, low temperature experimentation, neutron radiography, and radiation detection.

lias published numerous papers on various topics of neutron scattering, solid state physics, and research instrumentation.

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Mr. Forrest C.15 urns 1961 - Present Research Chemist, Army Materials and Mechanics Research Center, Watertown, MA 1958-1961 Employed by NASA at Cleveland, OH from 1958-1961.

After training at Oak Ridge National Laboratory for one year in radio-chemistry and activation analysis techniques, he was placed in charge of the NASA Plumbrook Reactor Radio-Chemistry Laborato ries.

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Education and Training 1956 A.B., Chemistry, Berea College, Berea, KY 1958 M.S., Chemistry, University of Kentucky L

Pertinent Experience llaa used the M.I.T.

and Army reactors 1

for activation analysis'research and has also-donc considerable work on radiochemical separations to determine low level amounts of contamination in germanium, silicon, sea.

water, and Arctic ice samples.

He is currently carrying out our research on 1

neutron radiography using reactors and accelerator-produced 14 MeV neutrons, and building a facility for thermaneutron radiography for the examination of defects in munitions.

Has over 21 publications in the field of nucleonics.

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Mr. William A. Lorenzen 3/81 - Present Ilealth Physicist, Army bhterials and Mechanics Research Center, Watertown, MA 10/80 - 3/81 Safety Technician, Army Materials and Mechanics Research Center, Watertonw, MA 1975 - 1980 Civil Engineering Technician, US Dept of Co-op Work Program Army, Corps of Engineers, Waltham, MA Education and Training 1978 A.S., Civil Engineering, Wentworth Insti-tute of Technology, Boston, FR 1980 BSET, Civil Engineering Technology, Went-worth Institute of Technology, Boston, MA 1981 Radiological Safety Course, 7K-F3, US Army Chemical School, Fort McClellan, Alabama Pertinent Experience As llealth Physicist, responsible for:

Organizing and administrating the AMMRC Rsdiological Safety Program; Providing technical advice and assistance to AMMRC pertaining to the development and imple-mentation of policies for minimizing or eliminating radiation hazards; Developing and maintain g NRC licenses applications, standing opei ting procedures for the hand-ling and use of isotopes; conducting opera-tional radiological safety surveys and I

determining degree of exposure, adequacy of protective measures, controls, and conformance with pertinent regulations; Developing and conducting a radiological safety training program, for both class-room, on-the-job, including procurement, transportation, storage, handling, use and disposal of radioactive materials, special nuclear material, Byproduct material, l

source material, and devices that produce ionizing radiation.

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Mr. Charles E. Dady 1970 - Present Chemist, Army Materials and Mechanics Research Center, Watertown, MA.

i 1962 - 1970 Chief, Radiological Safety Office, Army i

obterials Agency, Watertown, MA 1959 - 1962 Chief, Radiological Safety Orrice, Ordnance Materials Research Office (OMRO, Water-town, MA 1957 - 1959 Physical Chemist,. Atomic Energy Division, OMR0; on detached duty at Oak Ridge National Laboratory.

1954 - 1957 Analytical Chemist, Analytical Chemistry i

Branch, Watertown Arsenal Laboratories.

1952 - 1954 Employed as chemist in Industry.

Nducation 1952 B.A., Chemistry, Boston University i

1954 - 1957 Graduate courses in Chemistry, Boston College i

1957 - 1958 Vanderbilt University, Graduate School, I

USAEC courses in radiological physics I

1958 - 1959 Attended Oak Ridge School of Reactor Technology (ORSORT).

All prescribed courses, except engineering, were taken.

Pertinent Experience 1958 (Summer)

Field work in IIcalth Physics Division, Oak Ridge National Laboratory (ORNL).

1958 - 1959 Assigned to IIcalth Physics Division, ORNL.

1959 (Summer)

ORNL Reactor Division for reactor opera-tions training.

1969 Certified as IIcalth Physicist 1970 - 1978 Alternate Radiological Protection Officer 4

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Mr. John F. Vining 111 Positions held and pertinent experience 6/81 - Present Safety Engineer, and Acting Chief, Occu-pational' Safety and llealth Office, Army obterials and Mechanics Research Center,.

Watertown, MA 9/80 - 12/80 Personal service contractor for research and drafting of hazardous waste regula-tions, Commonwealth of bbss., Dept of Environmental Quality Engineering.

1973 - 1980 Engineer Director (Captain), US Public Ilealth Service, NIOSil, Morgantown, W.VA 1970 - 1973 Senior Engineer (Commander), US Public llealth Service, (NIOSil), Cincinatti, Oli i

1957 - 1968 US Army Sanitary Engineer- (Lt and Captain),

several tours with the Army Environmental liygiene Agency, Edgewood Arsenal, 50. CBR Officer on Okinawa for Medical Center.

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1955 - 1957 Army enlisted 1,

1954 - 1955 Chemical supervisor, Dupont, NJ Education l

1949 - 1954 B.S., Chemical Engineering, Northeastern University, Boston, hR 1959 - 1960 M.S., University Pittsburgh School of Public IIcalth.

I 1968 - 1969 liarvard School of Public (Radiological j

IIcalth).

Several short courses in IIcalth Physics by Public Ilealth Service and Army.

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Dr. Laurence D. Jennings 1959 - Present Research Physicist, Army Materials and Mechanics Research Center, Watertown, MA 1955-1959 Assistant Professor, Ohio State University Education and Training 1955 Ph.D., Physics,M.I.T.

1950 S.B.,

Physics, M.I.T.

Pertinent Experience Radio distribution functions in amphorous metals; x-ray diffraction physics; hard permanent magnets; calorimetry; magnetic equation of state at low temperatures.

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Farese flember, X-ray and Neutron Analysis Present Group, Materials Charactetization Division, Army Materials and Mechanics Research Center, Watertown, MA 1981-1982 Chief, Radiological Division, Professional Training Department, Directorate of Training and Doctrine, U.S. Army Chemical School, Ft. McClellan, AL 1978-1981 Instructor, Radiological Division, U.S.

Army Ordnance and Chemical Center and School, Aberdeen Proving Ground, MD.

Education and Training 1973 H.S., Biology, Providence College 1978 Radiological Safety Course, U.S. Army Ordaance and Chemical Center, and School, Aberdeen Proving Ground, MD 1979 Laser-Microwave llazards Course, U.S. Army Environmental Hygiene Agency Edgewood Arsenal, MD Pertinent Experience Was responsible for operation of the Radiological Training Laboratory at the U.S. Army Chemical School, providing instruction in the areas of radiological safety and radiological laboratory procedures, and certifying personnel as Radiological Protection Officers (RPO).

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i Dr. James'W. McCauley 1981 - Present Chief, Materials Characterization' Division, Army Materials and Mechanics l-Research Center, Watertown, MA 1974-1981 Group leader, synthesis and characterl-zation, Ceramics Research Division, Army Materials and Mechanics Research Center, Watertown, MA 1968-1974 Research Scientist, Ceramics Research Division, Army Materials and Mechanics Research Center, Watertown, MA 1966-1968 Research Assistant in solid state science, Materials Research Laboratory The Pennsylvania State University, University Park, PA e

Education and Training 1961 U.S., Geology, St. Joseph's College (Ind) 1965 M.S., Minerology, Pennsylvania State

{Jniversity 1968 Ph.D., Solid State Science, The Pennsylvania State University Pertinent Experience Pertinent areas of competence include:

almost all aspects of materials characterization specializing in x-ray crystallography and optical a

microscopy; material synthesis; pow t -

technology; instrumental analysis.

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Robert Fitzpatrick 1955 - Present Research Materials Engines-AMMRC Watertown, MA WAL Watertown, MA Education and Ttaining B.S., ME, Northeastern University Registered Professional Engineer, MA Pertinent Experience Pertinent areas of competence include:

Directed engery protection including laser hardening and microwave, special purpose armor, KE penetrators, and protective arming link materials.

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r APPENDIX 2 TYPE OF INSTRUMENTS l

Radiation Survey Instruments:

No. Avail Detected Sensitivity Range 1

G. M. Survey Meter, Nucicar S

Beta-Gamma 0.1,.3,1,3,10,30 l

100 mr/hr Chicago, Model 2650

" Juno", Technical Assoc.

6 Alpha and 0-50,500,5,000 Models SRJ-6 and SRI-7 Beta-Gamma mr/hr Low Energy Survey Meter, 5

Alpha and 0-3,10,30,100,300 Victorcen, Model 440 Beta-Gamma mr/hr Low Energy Survey meter, 1

Alpha and 0.3,1,3,10,30 Victorcen, Model 440 B Beta-Gamma mr/hr G. M. Survey Meter, Eberline 2

Beta-Gamma 0.2,2,20,200,2,000 l

mr/hr i

Model E-500-B G. M. Survey, Eberline 1

Bota-Gamma 0.2,2,20,200 i

mr/hr Model E-500-A Ionization Chamber 1

Beta-Gamma 0-10,100,1,000 Victorcen, Model 592 B mr/hr Neutron Detector, 2

Neutrons 0-50,50-5K mrem /hr.

Model PNR-4, Eberline Ionization Chamber 1

Beta-Gamma 0-1,3,10 mr/hr Victorcen, Model 471 Ionization Chamber 1

Beta-Gamma 0-30,100,300 mr/hr Victorcen, Model 0-75,250,750,}/sec 5K, BF Neutron Survey Meter, 2

Neutrons 3

7.5K,25K n/cm Nucicar Chicago, Model 2671

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Victorcen Condensor R-met er 1

Gamma 0-250 R l

Laboratory Moniters:

Remote Area bbniter, 6

Gamma 0.1-100 mr/hr-Tracerlah TA-6 probes lland and Shoe Moniter 3

Beta-Gamma Tracerlah Ratemeters 5

Alpha and 0- 100,200,500,1 K,2 K Beta-Gamma 5K,10K,20K cpm t

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Alpha and 0-500,5K,50K mr/hr Beta-Gamma Counting Systems:

Thermoluminescence Dosimetery 1

Beta-Gamma Reader System Nuclear Data 2000 2

Gamma Gamma Spectrometer 1NC 256 Channel Spectrometer 1

Gamma Searle Gas Proportional 1

Alpha and Beta-Gamma Counting System Tracerlab Gas Proportional 1

Alpha and Counting System Beta-Gamma e

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APPENDIX 3

  • AMMRCR 385-4 DI!PARTMENT OF Tile ARMY ARMY MATl!RI ALS AND MECilANICS RiiSliARCll Cl!NTER Watertown, Massachusetts 02172 AM1RC REGULATION 22 March 1978 No.

385-4 Safety RADIATION PROTECTION - POLICY S PROGRAM Paragraph 1

Purpose----------------------------------------------------

2 Scope ------------------------------ -------------------------

3 Policy --------------------- ---------------------------------

4 Responsibilities ------------------------------------ --------

Cont ro l o f Radioact ive Mate ri al ------------------------------

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Personnel Dosimetry ---------------- ---------------- --------

7 Pe rsonne l E xpo sure Lim i t s - ----- --- --------------- --------

Exposures Associated with Accidents or Emergencies -- --------

8 Medical Examinations -----------------------------------------

9 10 Tra i n i n g o f Pe rs onne l -- ----- ---- ---- ------ ----- ------ -------

General Procedures for Restricted Areas ----------------- ----

11 Radiation Surveys - --------------------------------- --------

12 Ca l ib ra t i on o f Me te rs --- ---------- -- -------------------- ----

13 Pu rch a s e o f Me t e rs - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - -- -- - - - --- - -

14 15 Waste Disposal ------------ ----------------------------- ----

NRC Licenses and Department of Army Authorizations -----------

16 N41RC Authorizations to Ilse Radioactive Materials ------------

17 Purchase Requests involving Radioactive Materials or Equipment Producing Ionizing Radiation ----------------

18 19 Key Emergency Personnel ------------------------ -------------

On-Post Transportation of Radioactive Materials --------------

20 bbximum Permissible Contamination of Inanimate Objects -------

Table I Relative Biological Effectiveness Values of Various Types of Radiation for Tot al Body Chronic Exposure -------------

Table II Neutron Flux Dose Equivalents - --- ------------ -------------

Table III Caution Si gn and Signal Devi ce Requirements ------------------

Table IV De f i n i t i o n s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Appendix 1.

PURPOSE. This regulation prescribes the Army Materials and Mechanics Research Center (NetRC) policy and program pertaining to the protection of personnel and property from unwarranted radiation exposure.

This regulation pertains to the requirements for procuring, 2.

SCOPE.

a.

receiving, storing, shipping, using, transporting, maintaining, or disposing of material and/or equipment which produces ionizing radiation.

  • This Regulation supersedes AMMRC Memorandum 385-4, dtd 13 March 1973.

1 AMMRCR 385-4 22 March 1978 t

b.

The provisions of this regulation apply to all organizations and i

. cmployees of AH4RC, guest scientists and personnel on detail to AMMRC from other organizations.

3.

P9LICY. All operations involving ionizing radiation-producing material and equipment will be conducted in such a manner as to maintain radiation exposures to personnel as low as reasonably achievable (AI. ARA). Operations involving ionizing radiation shall be planned so that the limits established i

j hy NRC, DA, DARCOM, OSilA, and ASNRC regulations are not exceeded.

4.

RESP 0.'!SIBILITIES.

a.

The Chief, Radiation and Occupational Safety Branch (RGOSB), is responsible for all aspects of the AMMRC Occupational i

Safety and licalth (OSil) Program.

b.

The Radiation Protection Officer (RPO), as a staff member of the RGOSB, will perform, as an integral part of the overall AMMRC OS!! Program, the actions required to establish and maintain preventive measures to safe-i guard personnel and equipment from harmful effects of ionizing radiation.

Responsibilities of the RPO are delineated in DARCOM-R 385-25.

Radiation Control Committee (RCC) advises the Commander on policy c.

and actions necessary to insure the safe use of material and equipment which i produces ionizing radiation.

Responsibilities of the RCC are outlined in AhNRC Memoranduia 15-2.

d.

Reactor Safeguards Committee (RSC) reviews, evaluates, and approves all aspects of maintenance and radiological safety for the nuclear reactor which is in standby status.

Responsibilities of the RSC are outlined in s

AFNRC Memorandum 15-1.

The MEDDAC !!calth Clinic at AMMRC is responsible for providing e.

medical examinations in support of the OSil program as required by higher i

authority within the provisions of this regulation.

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Chiefs of operating organizations utilizing radioactive materials or equipment which produces ionizing radiation are responsible to the Commander for establishing and implementing the radiological safety program in their respective organizations.

The program will be consistent with the guidelines i

established in this regulation.

The responsibilitics of an organizational j

chief include:

(1) Complying with and enforcing the radiological safety requirements prescribed in this regulat ion, and radiation safety requirements applicable to all the operations for which he/she is responsible.

(2) Assuring that his personnel are properly instructed and trained in the requirements for working with any radioactive materials or radiation producing equipment which is under his jurisdiction.

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22 March 1978 ASNRCR 385-4 (3) Assuring that all equipment and facilities are operated in accordance with established procedures to minimize radiation hazards to personnel and contamination of equipment.

(4) Assuring that prior to the start of any operation involving radioactive material or possible exposure to radiation not covered by a procedure or RCC authorization, a Radiation Work Permit (RWP) is properly completed for review and approval by the RPG.

(5) Assuring that an A5NRC Procedure is prepared covering work which is performed at a frequency which makes the completion of RWP's im-practical.

Such procedures will be submitted to the R60SL for review and approval by the Radiation Control Committee.

(6) Providing necessary space and facilities for the R60SB to carry out prescribed monitoring programs in his/her area.

g.

Supervisors of radiation workers or radiological projects are responsibic for:

(1) Being familiar with the radiological safety requirements prescribed in this regulation and radiation safety requirements applicable to all the operations for which he is responsible.

(2) Requesting placement on the Occupational IIcalth Roster (0!!R),

XMR Form 245, Figure 1, of all personnel under his/her control who are likely to roccive an accumulated dose of radiation in excess of 10 percent of the applicable quarterly limit.

(3) Assuring that his personnel are instructed in requirements for working with radioactive materials or radiation equipment and compliance with applicabic rules and regulations governing radiological safety.

(4) Assuring that required monitoring devices, protective clothing

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and equipment, and contamination control methods are used.

(5) Assuring that all equipment and facilities are operated in accordance with established procedures to minimize radiation exposure to personnel and contamination of equipment.

(6) Notifying the R60SB in advance of any scheduled maintenance or repair work which may involve radiation exposure or the release of radioactive materials not covered by an approved standing operating procedure (SOP).

(7) Obtaining recommendations of the R60SB in nonroutine operations where radiation exposure or contamination is involved.

(8)

Preparing SOP's covering the use, handling, operations and storage of ionizing radiation producing material and equipment.

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AHNfRCR 385-4 22 March 1978 1

4 (9) Posting the following in the immediate work area:

1 (a) NRC Form 3 (b) NRC license applicable to the area (c) 10 CFR Part 19 (d) 10 CFR Part 20 (e) 10 CFR Part 30 (By-Product Material Only)

(f) 10 CFR Part 40 (Source Material only)

!j' (g) 10 CFR Part 50 (Nuclear Reactor Only)

(h) 10 CFR Part 70 (Special Nuclear Material only)

(i) Copy of this regulation g

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i (j ) Copy of AMMRC procedures pertinent to operations in the area j

pertaining to radiation (k) DA authorization applicable to the area (10) Limiting working times so as to control the total radiation exposures of personnel within prescribed limits.

I (11) Keeping informed on the radiation exposure status of personnel under his control.

l (12) Maintaining control of visitors.

(13) Reporting to the chief of the operational organization any violation of these regulations or failure to follow prescribed procedures by any individual in his area.

(14) Ensuring that radiological safety surveys are conducted at 1 cast weekly reporting any abnormal results to the RPO, and maintaining permanent records of these surveys.

(15)

Inform the R60SB by telephone (ext 33225 or 33605) as soon as he

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knows that an individual on the Occupational ifcalth Roster is to separate from employment, complete XMR Form 245, and forward it to the R60SB for processing.

l h.

The individual is responsible for:

1 (1) Completing Form NRC-4 upon request by the R60SB.

Form NRC-4 is furnished by the R60SB.

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e 22 March 1978 AMMRCR 385-4 (2) Xceping his daily exposures to radiation as low as practicable.

(3) Wearing prescribed monitoring devices.

(4) Wearing prescribed protective clothing whenever contamination is possible and removing clothing before entering " clean" areas.

(5) Using respiratory protective devices when prescribed.

(6) Using prescribed techniques and facilities in operations involving radioactive materials, in accordance with organizational SOP's or RWP's.

(7) Complying with restrictions on drinking, eating and smoking.

(8) Report ing wounds, ingestion accidents, and other incidents involving radioactive material promptly to his supervisor, R60SB, and MEDDAC Health Clinic.

(9)

Being familiar with the radiological safety requirements prescribed in this regulation and any SOP covering his operation.

(10) Roping off unrking areas, posting warning signs, properly labeling waste containers, and otherwise controlling special radiation hazards for which he is responsible.

(11)

Limiting the volume of radioactive wastes.

(12) Cleaning up any contamination he generates following prescribed p rocedures.

(13) Properly storing and handling radioactive materials.

(14)

Recording data in accordance with organizational SOP's.

(15) Complying with all sections of this regulation and with posted pertinent NRC, DA, DARCOM, OSilA, and AMMRC regulations.

l S.

CONTROL OF RADIDACI'lVE MATERI AL IN AMMRC.

a.

Procurement of radioactive material.

All req' nits for procurement of radioactive materials will receive the concurrence of the R60SB before being forwarded to the Contract and Procurement Branch.

b.

Receiving and Shipping. All radioactive material being shipped to or from AMMRC will be cleared by the RPO in accordance with AR 55-55.

The RPO will complete DA Form 2701 and DA Form 836, if applicable, for each shipment of radioactive material.

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AMMRCR 385-4 22 March 1978 c.

Internal Transfer of Radioactive Materials.

Internal transfer of radioactive material will be made only between authorized users. Each such user will maintain an inventory of all radioactive material under his control and will notify the RPO prior to transferring the control of any radioactive material to other authorized users.

d.

Disposal of Radioactive Material. The RPO will be responsible for insuring that radioactive materials are disposed of in accordance with AR 755-15.

The RPO will be consulted prior to the disposal of any radioactive materials. Disposal of radioactive effluents (liquids or gases) into unrestricted areas will be carried out in accordance with 10 CFR Part 20.

6.

PERSONNEL DOSIMETER.

a.

Personnel who are likely to recieve an accumulated dose of radiation in excess of 10 percent of that tabulated in paragraph 7.a will be placed on the OllR for ionizing radiation.

Personnel on the OllR will be issued film badges and/or thermoluminescent dosimeters (TLD),

and will be subject to periode medical examinations in accordance with paragraph 9.

b.

Personnel who either because of the limited time they are required in radiation areas and/or because their exposures are expected to be less than that permitted for the population at large, i.e., 500 mren per year, may be issued film badges (XMR Form 406), Figure 2, without being placed on the OllR.

These badges will be used to obtain data on low radiation exposures which, in accordance with AR 40-14, do not require official monitoring or maintenance of radiation exposure records on DD Form 1141.

Personnel in this category will not require periodic medical examinations nor maintenance of a DD Form 1141.

Personnel on the O!!R who receive medical exposure (other than routine c.

chest and dental x-rays) or who receive industrial exposures under circum-stances that the exposure is not recorded on their film badges are responsible for notifying the RPO.

The RPG will forward applicable exposure information to the Medical Officer for inclusion in their DD-Il41 Form.

d.

AMMRC personnel who may be occupationally exposed to ionizing radiation outside of AMMRC wilI wear fi1m badges issued by the R40SB.

Personnel on the OllR nay request a copy of their radiation exposure e.

to date from the MEDDAC llealth Clinic at AMMRC.

7.

PERSONNEL EXPOSURE LIMITS.

The radiation exposure standards contained in this paragraph are applicable to all personnel.

Exposures incurred during examination or treatment for medical or dental purposes are not to be included in calculations for compliance with this paragraph.

In order to be permitted to receive the maximum exposures listed in n.

the following table, the individual must (1) he at least 18 years of age; (2) be occupationally exposed; (3) have on file with the MEDDAC llealth Clinic a complete NRC-4 Form or equivalent and (4) meet the restrictions of Section b of this paragraph.

6

AhNRCR 385-4 22 March 1978 TYPE OF liXPOSilRii PERim 0F I!XPOSilRI!

DOSE (REM)

Whole body, hand and accumulated

  • 5 (N-18) trunk, active blood-calendar qtr 3

forming organs, gonads or lens of eye.

Iland and forearms, calendar qtr 18 3/4 feet and ankles calendar year 75 Skin of whole body calendar qtr 7 1/2 or thyroid calendar year 30

  • N = age of individual b.

An individual who has not completed Form NRC-4, or equivalent, an individual employed at age 18 or an individual beyond age 18, who has roccived the maximum allow.ble dose shall not be exposed during ensuing year to whole body doses exceeding:

(1) 1.25 rem for first calendar quarter.

(2) 2.5 rem total for first two quarters.

(3) 3.75 rem total for first three quarters.

(4) 5 rem for the year.

Members of the general public, personnel not occupationally exposed c.

and persons who are less than 18 years of age will not be exposed in excess of.500 rem in any calendar year.

d.

An individual exposed to external and internal radiation must have his total dose considered and recorded.

When an individual has received an exposure in excess of the c.

quarterly limit, he shall be removed from duties involving radiation exposures until subsequent exposure limits are established through consultation with the medical officer. When an individual exceeds a yearly limit, he will be removed from duties involving radiation exposure until his records are reviewed by lleadquarters, 1)ARCOM, and subsequent limits established. When an individual exceed the 5 (N-18) dose, he will be removed from duties l

involving radiation exposures until his records are reviewed by the DA, Surgeon General, and subsequent limits established.

i 8.

EXPOSURES ASSOCI ATED WITil ACCIDENTS OR EMERGENCIES.

It is recognized that there may be accidents or emergencies in which an overexposure should be accepted in order to prevent serious body injury or property damage.

l 7

i l

(

l

AMMRCR 385-4 22 March 1978 In " planned emergency" action, i.e., action which is taken following a.

some preparation, twenty-five (25) rem should be considered the maximum allowable dose.

b.

To prevent serious body injury or death of an individual, the maximum considered dose should not exceed 100 rem.

9.

MEDICAL EXAMINATIONS.

a.

Radiation workers on the OllR will be given a pre-employment examination. Personnel who are to be occupationally exposed to neutrons will be given a slip-lamp test prior to assignment to duty.

b.

Visitors and personnel on temporary duty for less than 30 days do not require a medical examination provided they will not be exposed to radiatien in excess of 1.25 rem per quarter or to airborne radioactivity in excess of the limits established in 10 CFR 20, Appendix B, Table II.

c.

All personnel on the OllR will be given medical examinations at least yearly.

XMR Form 245 will be used for initial and termination examinations.

XMR Form 265, Figure 3, will be used for periodic examinations.

d.

Upon termination of employment or removal from the OllR the individual will be given a medical examination.

10.

TRAINING OF PERSONNEL. Personnel, including guest scientists, who w:ll be exposed to radiation and/or radioactive materials will be given training in accordance with the instruction prescribed in DARCOM Reg 385-25.

A record of training will be recorded on DA Form 750 (Record of Training and placed in each employee's official personnel folde. '. The RGOSB will arrange for required training in conjunction with the.' raining Officer.

11.

GENERAL PROCEDURES FOR RADIATION CONTROLLED AREAS. These rules constitute the basic techniques and procedures to be followed in restricted areas:

Smoking, drinking and cating are prohibited in airborne radioactivity a.

areas and contamination.

b.

Refrigerators will not be used to store food or beverage in airborne radioactivity areas or contamination areas.

c.

Location of radiation sources will be clearly indicated.

d.

Properly labeled and suitable containers will be available for radioactive waste.

Protective c?othing and monitoring devices will be worn when required.

e.

f.

No one shall work with radioactive material with open or uncovered wounds. Appropriate gloves, bandages, or coverings are allowed if approved by the RPO.

8

22 March 1978 AMMRCR 385-4 g.

Custodial personnel will only wet-mop and vacuum-clean areas where radioactive contamination may be present.

Dusting and sweeping will not be allowed. Vacuum cleaners used in radiation areas will be approved by the RPO.

12.

RADIATION SURVEYS. The R60SB is responsibic for performing radiation surveys and ensuring that radiation surveys are performed by others in accordance with the following:

a.

Initial Surveys. An initial survey will be made by the RPO of sites and areas where sources of radiation will be used and/or stored, before an operation ' involving radiatiou is initiated or changes approved, or upon installation of a device which produces ionizing radiation.

b.

Routine Surveys by the R60SB.

Surveys of each area in which sources of radiation are used and/or stored shall be performed by the R60SB at 1 cast once cach month.

Areas of static storage shall be surveyed at least once every three months. The radiation hazards incident to the production, use, release, disposal, or presence of 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.

Locations I

of the monitoring points with the results, statement of the hazard, and any

)

recommendations as to decontamination, shielding, procedural changes, etc.,

will be reccrded.

c.

Operational Surveys. Operating organizations will survey their areas at least weekly to insure that their operations are within the limits prescribed by this regulation.

d.

Special Surveys.

The RPG is responsible for performing the following special surveys:

4 (1) Non-routine operations involving radioactive materials or radiation producing equipment where there is a reasonable probability of any individual being exposed in excess of S mrem in one hour.

l (2)

Receipt or shipment of radioactive materials. Packages of radioactive materials for shipment will be checked for external radiation level, leckage i

probability, contamination, and proper labeling.

Packages of radioactive materials received at AMMRC will be surveyed by the RPG prior to their delivery i

to the individual who is responsible for their use.

(3) Termination of a project involving radioactive materials. A survey I

will be performed to determine that no contamination exists and that sources l

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

(4) Unplanned Events.

Loss of control, spill, overexposure, or any unplanned event which could adversely or did adversely affect the safety of the operation will be investigated by the RPO.

i 9

1,

22 March 1978 AMMRCR 385-4 (5) llazardous operations.

Particularly hazardous operations will be continuously monitored.

(6) leak Tests.

Leak tests of sealed sources will be performed at least once every 6 months except for alpha scaled sources which will be performed at least once every 3 months.

13.

CALIBRATION OF METERS. The R60SB is responsible for the calibraticn of all portable radiation survey meters.

a.

All portable radiation survey meters, unloss labled CBU, will be calibrated at least every 3 months and after each maintenance or battery ch a rge.

Instruments will be calibrated at a minimum of 2 points on each scale.

b.

Pencil dosimeters assigned to individuals will be calibrated at 3 month intervals. Others will be CBU.

14. PURCilASE OF METERS.

' Die R60SB and Equipment Manager should be consulted prior to the purchase of survey meters or other meters to be used for radiation protection in order that the type and variety of meters at AMMRC can be kept to a minimum.

This procedure is adopted to mir.imize spare parts require-ments as well as to facilitate the maintenance and calibration of meters.

15. WAFRi DISPOSAL.

a.

The R60SB is responsible for insuring that unwanted radioactive materials are disposed of in accordance with AR 755-15.

b.

Radioactive waste may be released to the environment or unrestricted areas provided that the maximum permissible average concentration for the particular isotope or combination of isotopes given in 10 CFR 20, Appendix B, Tabic II, is not exceeded at the point of release unless otherwise authorized by the U.S. Nuclear Regulatory Commission.

c.

The concentration of liquid waste released to the environment shall con form to 10 CFR 20.

d.

Storage areas and containers for radioactive materials will be approved by the R60SB.

16. NRC LICENSES AND DEPARTMENT OF Tale ARMY AUTil0RIZATIONS.

AMMRC will be guided by the procedures in DARCOM Reg 385-9 when applying for NRC Licenses and Department of the Army Authorizations.

~

17. AmRC AUT110RIZATION TO USE RADIOACTIVE MATERIALS.

Personnel wishing to use radioactive materials at AMMRC must apply to the AMMRC Radiation Control Committee before purchasing or using radioactive material.

See AMMRC Regulation 15-2 for details.

10

l 1

22 March 1978 AMMRCR 385-4 18.

PURCilASE REQUESTS INVOLVING RADIOACTIVE MATERIALS OR EQUIPMENT PRODUCING IONIZING RADIATION. All requests for purchase of or services involving radioactive materials or equipment producing ionizing radiation shall be submitted to the RPO for approval.

19.

KEY EMERGENCY PERSONNEL.

Key emergency personnel 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 radio-logical emergencies independent of the presence of the RPO.

The Intelligence and Security Branch will maintain a current listing of personnel to be called in on emergencies.

20.

ON-POST TRANSPORTATION OF RADIOACTIVE MATERIALS. Within an installation, it is usually not convenient to package and transport radioactive materials in the manner required for off-post shipment. Ilowever, the following pre-cautions will be observed:

In loading the vehicles:

at Keep within the weight limitations.

b.

Limtc or arrange cargo to keep radiation levels to which personnel (including the driver) will be exposed during transportation as low as practical. Maximum permissibic dose rate in occupied areas of the vehicle will depend upon the time required to transport the material. The driver will wear a film badge, if specified by the RPG, and will not be exposed to ionizing radiation in excess of the limits indicated in paragraph 7.

c.

Keep the containers away from the cab of the vehicle.

11

_ ~

TABLE 1.

MAXIMLN PERMISSIBLE CONTAMINATI(N ON INANIMAlli OBJECTS

  • h' CONTAMINATION LEVEL n

Alpha Beta-Gamma

=

w 2

f.

Fixed (F) or pCi/100 cm pCi/100 cm mrad /hr item and Corrective Action Removable (R)

Instrument Smears at 1 in.

pCi/100 cm' a

1.

Personal clothing, including shoes.

Replace, decontaminate or store for F

200 0.2 None**

None *

  • l decay, if above:

R 2.

Protective clothing, incl. shoes, s.

General. Should be replaced or F

1,000 0.5 decontaminated, if above:

R 200 1,000 t

b.

Laundry. Do not release to public F

2 00 0.4 laundry, if above:

R 50 200 c.

Respirators F

200 0.06 R

None**

None *

  • J 3.

Laboratories and work areas:

a.

Uncontrolled aremi. Requirr conf.ols F

200 0.25 and posting or decontaminate, if above:

R 50 100 b.

Controlled areas. Docontaminate, " if F

1,000 2.0 impossible, fix with periodic check on R

200 1,000 fixation, if above:

4.

Vehicles:

a.

Use in controlled. areas. Decontaminate F

1,000 2.0 g

or if impossible, fix, if above:

R 300 1,000 I

b.

Use in uncontrolled areas. Decontaminate F

300 0.4 "E

if above:

R 30 500 5.

Tools, equipment and containers. Prior to F

200 0.25 j

non-radioactive use, decontaminate, if above:

R 50 100 6.

Shipping containers, outside surfaces.

F 500 0.25 l

decontaminate if above.

R N one*

  • N one *
  • i i

I

  • For depleted uranium contamination levels may be increased by a factor of 5 as determined by the RPO.
    • Less than the minimum detectable activity.

j 12 4

i e

c

22 March 1978 AMMRCR 3E3-4 TABLE II RELATIVE BIOLOGICAL EFFECTIVENESS VALUES OF VARIOUS TYPES OF RADIATION FOR TOTAL BODY CilRONIC EXPOSURE TYPE OF RADIATION RBE Alpha 10 Beta 1

X or Gamma 1

Protons 10

  • Thermal Neutrons 2.5
  • Fast Neutrons 10 TABLE III**

NEUTRON FLUX DOSE EQUIVALENTS NElfrRON ENERGY n/cm2/sec n/cm /sec 2

(Mev)

RBE (1 mrem /hr)

(100 mrem /40 hr week)

Thermal 2.5 268 670

.0001 2.0 223 582

.005 3.7 228 570

.01 5.0 215 537

.02 8.0 112 280

.1 10.0 33 83

.5 10.0 12 34 1.0 10.5 8

24 2.0 8.6 7

17 2.5 8.0 8

20 5.0 6.8 7

18 7.5 6.7 7

17

  • If neutron energy is known, the value in Table III may be used.
    • 10 CFR 20.4(c) 13

TABLE IV D.

CA!TTION SIGN AND SIGN AL DEVICE REQllREMENTS Caution f

Categories Symbol Cautioning Words Signal Devices 4-a.

Radiation Area Yes Caution Radiation Area None b.

Contamination Area Yes Contaminated Area Barriers c.

High Radiation Area Yes Caution High Radiation Area Alarms as required by 10 CFR 20 d.

Airborne Radioactivity Area Yes Caution Airborne Radioactivity None Area e.

Entrance to areas or rooms in Yes Caution None which radioactive material is Radioactive Material (s) used or stored in an amount (and, where practical, exceeding 10 times the amount describe the quantities and of radioactive material ex-kinds of radioactive materials empted by Table I - 10 CFR 20 involved) f.

Radiation Containers Yes Caution None Radioactive Material in accordana - with 10 CFR 20 g.

Radiation Yes Caution - Radiation A sign will be placed on the control (Accelerators, X-Ray This equipment produces panel near the switch which energizes i

machines, etc.)

ionizing radiation (or the tube and also at entrance to area M

X-rays) when energized f

a

r b

3 14 4

AMMRCR 385-4 FIGURE 1 22 March 1978 ARMY MATERIALS AND MECHANICS RESEARCH CENTER REQUEST FOR CHANGE TO OCCUPATIONAL HEALTH ROSTER (Prepare in Quintuplicate)

PARTI To: Safety Director From:

Supervisor it is requested that the following actions be taken:

Add to Roster O Remove from Roster O Other O Date of Birth Payroll No.

Name Extension Social Security No.

Job Title and Grade Branch Ridg.

Room Organization Education:

Grammar School O liigh School O College O Previous radiation exposure record; include industrial exposure and medical X-rays other than routine. (Check area of concern) lor.izing Radiation:

Depleted Uranium O Machine-Produced Radiation O Other Radioisotopes O licavy Metals O Beryllium O Laser O Noise O Other O Brief description of duties involving item (s) checked:

Date Signature PART II To: Medical Officer From: Safety Director Perform physical examination for areas checked in Part I.

Beta Gunma Badge No-Neutron Badge No.

Remarks:

Date Signature PARTlil To: Safety Director From: Medical Officer Acceptable, no restrictions O Acceptable, with restrictions O Rejected (state reasons)

Remarks:

Date Signature PART IV To:

From: Safety Director Supervisor I

Forwarded for your information and retention.

Signature Date xMR I'ORM 24s Code: White R&OSB; Yellow - Fnployee's Supervisor; Green - Medical Officer; Blue Suspense (R&OSB); Pink Suspense (Employee's Supervisor).

9 I/E3 73 Revised

22 March 1978 FIGURE 2

.(

AhNRCR 385-4 ARMY M All RIAIS AND 41-ill ANICS R131:ARCil Cl!.NTI R REQUEST FOR FILM HADGE MONITORING FOR PERSONNEL NOT REQUIRED TO HE ON THE OCCUPATIONAL HEALTH ROSTER (Prepare in Quintuplicate)

To:

Fonn: Radulion Protection Olficer (RPO). R&OSil PART I Nugwrvever is not icquired to be placed on the Occupatiosul ifcalth Roster (OilR) for ionizing radiation (See AMMRC Menanandom No. 3M5-4 lor OllR requiremenis). In the interest of monitoring low level q

eywisures to ioni/mg radution, reconnnend that subject employee be issued a film badge. Part 11 should be completed and returned to tins oflice in order that a film badge can be iwued.

Segnit ure Date lo: RPO, R&OSil From:

PART11 s,

l'mployce's Name Payroll No.

Ext.

I) ate of Hirth Social Secunty No.

Job Title and Grade Lab /Div liianch lluildmg Room Previous radution exposure record (include industrial ey>osure and medical Erays other than routine).

lirictly desenbe duties which involve possible low level radiation exposure.

Segnat ure Date In I tom: RPO, R&OSit PART 111 suiwn..

lieta gamma hhn badge ius been awigneil to above nameti employee of your org ni/alion. Film badge can be picked up at R&OSil, Bldg. 37, and when not in use will be stored m the film hadge rack located at Building

, Room Sagitat ure thste MIR l ORM 4Hf, Ce ede :

4 I I lt 7.4 white. R&OSil; Yellow - 1:enployee's Supervisor: Green - I'mployee; lilut' sus {witW t R&(Phll)* l'esik Suspense (SuperH50F) 16

AMMRCR 385-4 FIGURE 3 22 March 1978 ARMY MATERIALS AND MECilANICS RESEARCil CENTER PERIODIC PHYSICAL EXAMINATION OCCUPATIONAL HEALTH ROSTER (Prepare in Triplicate) l' art 1 GliNI'l(Al. INI2OlBIATION Date Name:

Payroll No.

lixten sion Date of ihrth Sot ial Sct urity No.

Job Title and Grade Or gani r u ti<n ikanth _.._, ___

llids.

Room Date of I ast Physical Examinatiivi Pasi 2 In:

Saf ety Duet tor l roin:

Meda.sl Olhier lGuri arra enf asone a en) loniting Radulion liepleted liranmni i1 M.n hme l*roduted Radution il Other Radioiwtolo U licavy Met.sh 11 ltct g lhnm 16 lawr it None 11 Oiemical L1 tliber II (\\(Wil))

O At t ertable, no rentrit lionu _ _ _ _ _. _ _

[1 Acceptable, wi th restsit tiinia. _____ _

O Rejected (state reasorid. _ _._.

Rema r k g: ___.__.____.. _.

Meth. at Of ficer Date l' art I 3";

Supervisor l' rom:

Silely l)irrtlot iI l orw ardeel f or )tisar stilonn.itson.nsiel relefiliori.

I! limplatyce i% rio hunger plI% wit allb quidilled to walk willi lotil/Ilig radiation and Should return his film badge to the Rat Win innneih.ilth.

I1 l mplovce o no longs planes. ally.tuahlied lo work with Signat ur e Date t tIlli blurc H a r his d ir i'r n Aleilis al ()f feter 4 ll*

  • M l Ollgitreg t'C 's hugstr n au sf kb!N l tINkt 2h$

iMAY75INrl

22 March 1978 AMMRCR 385-4 APPENDIX DEFINITIONS ARiiA DEFINITIONS:

a.

Unrestricted Area.

Any area in MtMRC, entry into which is not controlled.

b.

Restricted Area.

Any area to which access is controlled for the purpose of protection of individuals from exposure to radiation and radio-active materials.

c.

Radiation Area.

Any arca, accessible to personnel, in which there exists radiation at such levels that a major portion of the body could receive in any hour a dose in excess of 2.0 millirem, or in 5 consecutive days a dose in excess of 100 millirem.

d.

liigh i<adiation Area.

Any area, accessible to personnel, in which there exists radiation at such level that a major portion of the body could receive in any one hour a dose in excess of 100 mrem.

c.

Airborne Radioactivity Area.

(1)

Any room enclosure, or operating area in which airborne radioactive material exist in concentrations in excess of the amounts specified in 10 CFR 20, Appendix B, Table I, Column I; or (2) any room, enclosure, or operating area in which airborne radioactive material exists in concentrations which, averaged over the number of hours in any week during which individuals are in the area, exceed 25% of the amounts specified in 10 CFR 20, Appendix B, Table I, Column I.

individual whose qualifications to use radioisotopes and/

Alml0RIZED llSER.

An or equipment which produces ionizing radiation has been reviewed and approved by the AMMRC Radiatien Control Committee (see AMMRCM 15-2).

BACKGRollND RADI ATION. Radiation arising 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 radiat ion due to the presence of radioactive substances in other parts of the building, in the building itself, etc.

CONTAMINATION (RADIDALTIVE).

Deposition of radioactive material in any place whe re it is not desired, and particularly in any place where its presence can be harmful, to an experiment or a procedure, or is actually being a source of danger to persons.

CllR I E. A unit of activity defined as the quantity of any radioactive nuclide in which the number of disintegrations per second is 3 x 1010, 7 disintegrations a.

Millicurie - One-thousandth of a curie (3 x 10 per second).

4 b.

Microcurie - One-millionth of a curie (3 x 10 disintegrations per second).

A-1

AMMRCR 385-4 22 March 1978 DOSE:

Absorbed, Dose. When ionizing radiation passes through matter, some a.

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 one rad = 100 erg /gm = 1/100 joule /kg. The rad unit is applicable to any type of ionizing radiation, but in reporting dose, the type, as well as irradiated material (for instance, tissue), and the place of interest must be specified. Without the above three factors, a statement of absorbed dose received is incomplete and probably useless, since the same dose of different kinds of radiation, even delivered to the same place, can produce entirely different effects.

b.

Exposure Dose. See EXPOSURE.

c.

Biological Dose. The radiation dose absorbed in biological material.

It is measured in rems.

DOSE EQUIVALENT. The term "RBE" dose has been used in the past in both radio-biology and radiation safety.

It is now recommended that the term RBE be used in radiobiology only and that another term be used for purpose 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 radiations.

The name recommended for the linear-energy-transfer-dependent factor is quality factor QF. Other factors must also be considered for 'he purposes 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 effects 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 after the absorbed dose is modified by the above-mentioned factor, plus any other factors that may effect the incoming radiation, be called the dose equivalent, DE.

If the only apparent modi fying factors are QF and DF, then:

DE = D (QF) (DF) a If other factors must be considered and are defined, then:

DE = D,(t!F)

(DF)........

where the dose takes into account th ' product of these other factors. The unit of dose equivalent, DE is the ren..

The unit of absorbed dose, D, is the rad.

(Compare definitions of rad and rem).

Although the above d$finition 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 radiation safety.

A-2

1 AMMRCR 385-4 22 March 1978 EXPOSURE. The term " Exposure Dose" is obsolete.

Exposure is a term adopted by the international Commission on Radiological ilnits and Measurements in 1962 to replace the term " exposure 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 roentgens dose and air dose.

EXPOSURE OCCUPATIONAL.

Exposure to ionizing radiation that is incurred as a result of an individual's employment or duties which are in support of facilities which use materials or machinery capabic of producing ionizing radiation.

Exposure of an individual to ionizing radiation for medical or dental diagnosis or therapy shall not be deemed as occupational exposure.

FAIL-SAFE. A design characteristic of the hardware, component or system which, in the event of a malfunction, will not result in a degradation of safety.

Filli BADGE. A pack of appropriate photographic film and filters used to determine radiation exposure.

IIAZARD, RADIATION.

See RADI ATION IIAZARD.

INTERLOCK.

A device, usually cicctrical and/or mechanical in nature, to prevent activation of a control until a prelir'..ary condition has been met or to prevent hazardous operations.

Its purpose usually is safety of personnel or equipment.

For exampic, it may be used to warn responsible personnel of an unsafe condition or unauthorized entry of personnel.

IONIZING RADIATION. See RADIATION.

LEAK TEST.

A determination of the integrity of a scaled source encapsulation by detection of leakage or escape of radioactive contamination.

NilCLE AR REACTOR SYSTEM.

Any equipment or device, except a nuclear weapon capabic of neutron multiplication through fission of special nuclear material.

This definition includes nuclear reactors and subcritical assemblies of special nucicar material and the supporting equipment or device (if any) associated with them.

RAD.

'Ihe rad is defined as the unit of absorbed dose of any nuclear (or ioniz ing) 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 sof t tissue is exposed to one roentgen of medium voltage X-radiation. The rad is to be used solely with absorbed dose.

I rad = 100 crg/ gram = 1/100 joule /kg RADIATION.

Energy propagated through space. As used in this regulation, the term refers to two kinds of ionizing radiation:

A-3

)

4 AMMRCR 385-4 22 March 1978 i

Electromagnetic waves (X-rays and gamma rays), and a.

b.

Corpuscular emissions - from radioactive substances or other sources (alpha and beta particles, etc.).

Ionizing radiation is any electromagnetic or particulate radiation,capabic of producing ions, directly or indirectly, in its passage through matter.

RADI ATION CONTROL C04tITTEE.

A group of persons appointed by the Commander to advise him on policy and actions necessary to ensure safety of personnel j

and property from hazards of radiation.

Synonymous with " Isotope Committee,"

" Radiological llealth and Safety Committee," " Radiation Protection Committee,"

and other siailar titles of committees.with the same purpose.

RADIATION llAZARD. A condition under which persons might receive radiation in excess of the applicable maximum permissibic dose, or where radiation damage j

. might be caused to materials or personnel.

RADI ATION SOURCliS.. Materials, equipment or devices which generate or are l

capable of generating ionizing radiation, including:

(1) naturally occurring radioactive material, (2) by-product materials, (3) source materials, (4) Special nuclear materials, (5) fission products, (6) materials 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.

t RADIATION WORKER. Any person occupationally expesed to ionizing radiation and/or radioactive materials.

(Job descriptions of radiation workers sh,ould i

reflect that the individual is potentially exposed to ionizing radiation.)

i l

RADIDACTIVE PIATERI Al.,

Any substance which undergoes spontaneous disintegration in which energy is liberated, generally resulting in the formation of new.

l nuclides (a species of atom characterized by the constitution of its. nucleus).

l The process is accompanied by the emission of one or more types of ionizing radiation.

Included are materials possessing artificial induced-and natural radioactivity.

By-product materials.

Any radicactive material (except! special nucicar I

a.

material) yicided in or made radioactive by exposure to radiation. incident to the process of producing or utilizing special nuclear material.

b.

Source material. Uranium or thorium or a combination thereof,in any physical or chemical form or ores which contain by weight, one-twentieth of one percent (0.05 percent) or more of uranium, thorium or any combination l

thereof. Source material does not include special' nuclear material.

Special nu_ clear material.

Plutonium, uranium 233, uranium enriched c.

in the isotope 235 or any other material which the U.S. Atomic Energy Comm-ission pursuant to the provisions of Section 51 of: the Atomic Energy Act. of 1954, 42 IISC Section 2071, determines to be special nuclear materials, but does not include source material: or any material artificially enriched by any A-4 i

3

_ _ _ _ _ _, _. _. _,. _,.. _. ~ _. -... _. - - -. _.

4 22 March 1978 AMMRCR 385-4 of the foregoing but does not include source material.

d.

Naturally occurring radioactive ' material. Substances which are radioactive in the natural state, such as radium and thorium and their decay I

products, except those defined as source and special nuclear material.

RADIOLOGICAL PROTliCTION OFFICER.

An individual' designated by the Commander to provide consultation on the degree of hazards associated with ionizing radiatior and the effectiveness of measures to control these hazards. This individual shall be technically qualified by virtue of education, military training, and/or professional experience to assure a capability commensurate with the assignment. The term " Radiological Protection Officer" is a functional title and is not intended to denote a commissioned status or job classification within the Armed Forces.

t RBE.

(Relative Biological Effectivene_ss.) The RBE of a given radiation is l

defined as the ratio of the absorbed dose in rads of gamma radiation (of a j

specific energy) to the absorbed dose in rads of the given radiation having j

the same biological effect.

(See DOSE EQUIVALENT)

I REM.

(Roentgen Equivalent Mammal.)

One rem is the quantity of ionizing -

radiation of any type which, when absorbed by man or other mammal produces a physiological effect equivalent to the produced by the absorption of one roentgen of X-ray or gamma radiation.

Dose in rems equal RBE times dose in rads. The rem provides an indication of the extent of biological injury (of a given type) that would result from the absorption of nuclear 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 gamma rays only) is one of exposure. The rem can also be defined as the unit of dose equivalent.

The dose equivalent is numerically equal to the~ dose in rads, multiplied by 2

the appropriate modifying factors.

I ROENTGEN.

The quantity of gamma or X-radiation which will give rise to' the formation of 2.08 x 10D ion pairs per cubic centimeter of dry air, STP (0*C, I atm). This is equivalent to the release of 87.7 ergs of energy when i

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.

i I

1 R = 2. 85 x 10-4 coulombs /kg SEALED SOURCI!.

Radioactive material that is encased in and is to be used in a container in a manner to prevent leakage or escape of the radioactive. material.

~

UNSEALED SOURCli.

A discrete amount of radioactive material that is not encapsulated in a container to prevent leakage or escape of the radioactive material.

t i

I A-5 3

+, - _., - - - -

22 March 1978 ASNRCR 385-4 (DRXMR-AR)

FOR T11E DIRECTOR:

OFFICIAL:

W. R. BENOIT CO L, TC Commander / Deputy Director PETER W. LICitTEh8ERGER

,CPT, QMC Adjutant

-f DISTRIBllTION:

B R60SB (200 cys)

MEDDAC IIcalth Clinic (2 cy)

I b

4 a

18

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