ML20235G145
| ML20235G145 | |
| Person / Time | |
|---|---|
| Site: | 07000263 |
| Issue date: | 05/22/1987 |
| From: | Wright E ARMY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20235G045 | List: |
| References | |
| 107403, NUDOCS 8709290463 | |
| Download: ML20235G145 (49) | |
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APPLICATION FOR RENEWAL OF.SPECIAL NUCLEAR MATERIAL i
LICENSE NO. SNM-244~
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2 enIs"E$UtE!v LABORATORY l
I 22 May 1987
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U.S. Army Materials Technology Laboratory Watertown, Massachusetts 02172-0001 h
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AWROVED BY OMB to C F R 30. 32,33. 34 316& O120 nede APPUCATION FOR MATERIAL LICENSE EP-
$3m INSTRUCTIONS: SEE THE APPROPRI ATE LICENSE APPLICATION GUIDE FOR DET AILED INSTRUCTIONS FOR COMPLETING APPLICATION SEND TWO COP!ES OF THE ENTIRE COMPLETED APPLICATION TO THE NRC OFFICE SPECIFIED BELOW AMLICATIONS FOR DISTRIBUTION OF EXENIPT PRODUCTS FILE APPLICATIONS WITH IF YOU ARE LOCATED IN U S NUCLE AR REGULATORY COMMfS$10N ILLINOIS INDI AN A IOW A. MICHIG AN, MINNESOT A. MISSOURI. OHlo, OR DtvtSION OF FUEL CYCLE AND MATERIAL SAFETY NMSS WISCONSIN. $END APPUCATIONS TO WASHINGTON. DC 20566 U $ NUCLE AR REGULATom y COMMIS$ TON REGION Itt ALL OTHER PERSONS FILE APPLICATIONS AS FOLLOWS. IF YOU ARE MATE Rt ALS LiCEN$rNG SECTION LOCATEDIN 799 ROOSEN E LT RO AD j
GLEN E LLYN. lL 60137 CONNECTICUT DELAWARE. Ol8TRICT OF COLUMBIA. MAINE. MARYLAND, MASSACHUSETTS. NEW HAMPSHIRE. NEW JE RSEY. NEW YORK. PENNSYLVANIA A ARK ANSAS. COLOR ADO, IDAHO. K ANSA $. LOutsl AN A. MONT AN A. N E BR A$K A f.HODE ISLAND, OR VE RMONT, SEND APPLICATIONS TO NEW MEXICO. NORTH DAKOTA, OK LAHOMA, SOUTH DAKOT A. TEXAS, UT AM.
U S NUCLEAR REGULATORY COMMisslON. REGION I NUCLE AR MATERlALS SAFETY SECTION 8 U $ NUCLE AR REGULATORY COMMISSION. REGION ly 331 PARK AVENUE MATERI AL R ADI ATION PROTECTION 5EC fiON KING OF PRUS$1A. PA 19406 011 RY AN PLAZA DRIVE, SUITE 1000 ALAB AM A. FLORIDA. GEOftGI A. KENT'JCK V MIS $1SSIPPl. NORTH CAROLIN A P'UE ATO RICO. SOUTH CAROLINA. TENNESSE E. VIRGINIA, VIRGIN ISLANDS. OR ALASKA, ARIZONA, CAltFORNIA HAWAll, NEVADA OREGON. WASHINGTON, WEST VIRGINIA. SEND APPLICATIONS TO AND U.S. TERRITORIES AND POSSESSIONS IN THE PACIFIC, $END APPLICATIONS U S NUCLE AR REGULATORY COMMISSION, REGION ll NUCEAR MATERIALS SAFETY SECTION U S NUCLEAR REGULATORY COMMISSION. REGION V tot MARIETTA STREET. SUITE 2900 NUCLEAR MATER 6ALS SAFETY SECTION ATLANT A, GA 30323 1 A50 MARIA LANE. SUITE 210 WALNUT CREEK, CA 94506 s
FET. SONS LOCATED IN AGREEMENT ST ATES SEND APPLICATIONS TO THE U S NUCLEAR REGULATORY COMMIS$10N ONLY IF THEY WlSH TO POSSESS ANO USE UCENSED MATERIAL IN STATE 5 5UBJECT TO U.S. NUCLE AR RE GULATOR Y COMMISSION JURISDICTION THIS l$ AN APPLICATION FOR ICaeca scoroanere, rem >
2 N AME AND M AILING ADDRESS OF APPLICANT IIncludele Covel Department Of the Army A NEW uCENSE U.S. Army Materials TechnO10gy Laboratory e AMENOMENT TO UCENSE NUMBER
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C RENEWAL OF uCENSE NuMetR SNM-244 WatertOwn, Massachusetts 02172-0001 3 ADDRES$tES) WHERE LICE NSED M ATERI AL WILL BE UEE D OR POSSE S5tU Same as Item 2 4 NAME OF PERSON TO BE CONTACTED ABQUT THIS APPLICATION TE LEPHONE NvMe F P Charles E.
Dady (617) 923-5139
$U3MIT ITEMS 6 THROUGH 11 ON Si = 11" PAPE R TME T)PE AND SCOPE OF INFORMATION TO BE PRoviDED 15 DESCR4 BED IN THE LICENSE APPLICATION GUIDE 6 R ADIOACTivE MATE PI AL e E +emeal end mess numhee, b caem and o on ue' tem and e men,m.sm amove 6 PURPOSE tS) F OR WHICH LICENSED MATERI AL WILL BE USE D v
whech will be possessed at say one time 8 TFI AINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED ARE AS RAN A
ER E CE 9 F ACILITIE3 AND EQUIPMENT
- 10. R ADI ATION SAF ET Y PROGR AM 12 LsCENSE E F E E5 t5ee 10 CFR I/O sod Section 1/0 3 0 11 W A$TE MAN AGEMENT, rAMOUNT FEE C ATEGORY N/A l E NC LOSE D S 13 CE R TIFIC ATION IMust ce comp <ered er appocean THE APPLICANT UNDE RST ANDS TH A T A LL ST AT EMENTS AND FIE PRESEN T ATIONS M ADE IN TMe$ APPLICATION ARE BINDING UPON TwE APPLIC ANT THE APPLICANT AND ANY OF FiCiAL EX ECUTING TMIS CERTIFIC ATION ON BEH ALF OF THE APPLICANT, N AMED IN ITEM 2 CERTIF v TH AT THl$ APPLICATION IS PREP AR ED IN CONFORMITY WITM TIT LE 10 CODE OF F EDER AL REGUL Af TONS PARTS 30. 32. 33,34. 35. AND 40 AND TM AT ALi INFORMATION CONT AINE D wE R EtN.
18 TRUE AND CORRECT TO THE BEST OF THEtR KNOWLEDGE AND BELIEF W ARNING 18 U S C BE CTION 1001 ACT OF JUNE 2'i 1948 62 ST AT 749 M AK ES IT A CR!M!N AL OFFENSE TO M AKE A WILLFULLY F ALSE ST ATEMENT OR REPRESENT ATION TO ANY DEPARTMENT OR AGENCY OF THE UNITED ST ATES AS TO ANY MATTER WITHIN ITS JURISDICTION 51GN ATURE -CE RTIF YtNG OF F ICER TvPEO PRINTED N AME T IT L F DATE Edward S. Wright Director 7 May 1987 94 % O i V N 7 A SIy 6 Q N C M CCAtA a ANNm (m PIEE,P a p NyMBt F4 UF E MNO Y E E S # 7 ors' fo' a WOv uD Y OU BE Wi L L tNG T O F UR NiSM COS T IN F ORM A T SON Qo"er eno'or ste" aovm
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l APPLICATION FOR THE 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 Army Materials Technology Laboratory (MTL) 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) US Army Materials Technology Lnboratory 405 Arsenal Street Watertown, Massachusetts 02172 Sec. 70.22 (a)(2) Uranium, enriched in U-235 isotope, is used in neutron detectors to be used with neutron experiments at MTL laboratories.
Plutonium, fabricated into a 5 curie Pu-Be neutron source is used te calibrate neutron detectors and neutron survey w.eters.
Plutonium, fabricated into four (4) neutron filters is used in neutron experiments at MTL.
Plutonium is also to be used in a maximum of four (4) alpha source standards Sec. 70.22 (a)(3) The license is requested for the same period as presently issued.
Sec. 70.22 (a)(4) Applicant proposed to use and possess up to eight (8) grams of uranium enriched up to 90% in isotope U-235.
The uranium will be utilized in the chemical forms of U 0, and UO -
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Applicant also proposes to use and posseus up to eighty (80) grams of plutonium-239. The plutonium is mixed with beryllium and is contained in a stainless steel cylinder, 3.2" long and 1.3" in diameter.
Applicant further proposes to use and possess up to thirty-two (32) grams of plutonium-239, fabricated into four pieces, approximately 2" X 2" X 0.005",
each 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 (*)(6) MTL personnel involved in the use and handling of special nuclear materials are listed below. The technical qualifications, including training and experience of each iudividual user, are included in Appendix 1 cf this application.
NAME POSITION Dr. John Antal Supervisory Research Physicist Mr. Forrest Burns Research Chemist Mr. Charles Dady Analytical Chemist / Acting Radiological Protection Of ficer
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I Mr. Alfred Broz Chief, Materials Testing and Evaluation Division /
l Acting Radiological Protection Officer l
i Dr. Laurence D. Jennings Research Physicist I
Mr. Louis J.
Farese Member, X-Ray and Neutron Analysis Group Dr. James W. McCauley Chie f, Materials Characterization Division Mr. 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.
Sec. 70.22 (a)(7) 1.
The facilities and. work areas which will be used at MILin conjunction with special nuclear materials are as follows:
a.
Reactor Containment Shell.
(Reference USNRC Docket 50-47) The reactor is currently in standby status, 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 Mev generator and two Californium-252 sources (approximately 2.6 curies total on 31 October 1976).
Floors are covered with vinyl tiles 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 Pu-Be source and 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, i
is strictly controlled. The Pu-Be source is used in the Calibration Lab fe
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calibrating neutron survey instruments.
2.
Handling Devices. Mobile glove boxes are available for use if ever required, 1
Long-handled tongs and magnets are also available and complete machine-shop l
facilities are available for fabrication of special-handling equipment.
3.
Shielding. Large quantities of lead bricks, solid concrete blocks, and paraf fin are readily available for shielding.
Facilities, including a foundry,
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1 are available for fabricating storage containers.
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4.
Measuring and Monitoring Instruments. A complete list of radiation measuring and monitoring instruments presently at this Laboratory, is included in Appendix 2 l
of this application.
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Sec. 70.22 (a)(8)_ Safety Procedures and Monitoring.
will be handled in a manner which is consistent with the radiation safety regulations l
prescribed in AMHRC Memorandum' 385-4, " Radiation Protection Policy and Program,"
l dated 12 May 1983. A copy of this regulation is included as Appendix 3 of this l
l application.
Criticality. Uranium and plutonium in the amounts requested in this application present no criticality problem.
Waste Disposal.
Plutonium presents no waste disposal problem as it will be used indefinitely. The sources will be returned to the vendor for repair if leaks develop at any time. The uranium referenced in this application will be returned to the USERDA when it is no longer useful to this Laboratory.
[epk Testing. The procedure for leak testing sealed plutonium sources is as follows:
a.
Each plutonium source shall be tested for leakage every three (3) months.
In the absence of a certificate from a transferor indicating that a test has been made within three (3) months prior to the transfer, the sealed source shall not be put into use until tested, b.
The test shall be capable of detecting the presence of 0.005 microcurie of alpha contamination on the test sample.
The test sample shall be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is permanently or semi-permanently mounted or stored.
Records of leak test results shall be kept in units of microcuries and maintained for inspection by the USNRC.
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c.
If the test reveals the presence of 0.005 microcurie or more of removable alpha contamination, the source shall be immediately withdrawn from use and be decontaminated and repaired or be disposed of in accordance with NRC 10, CFR 20.
Within five (5) days af ter determining that any source has leaked, AMMRC will file a report with the Director of Nuclear Materials Safety and Safeguards, U. S. Nuclear Regulatory Commission, Washington, DC 20555, describing the source, the test results, the extent of contamination and the corrective action taken. A copy of this 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 sealed sources that are stored and not being used.
Sources 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 of transfer.
4 E. S. URIGHT Director I
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APPENDIX I
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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, Watertown, MA Education and Training 1948 B.S.,
Physics, University of Scranton 1949 M.S.,
Physics, St. Louis University 1
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 j
detection.
Has published numerous papers j
on various topics of neutron scattering, solid state physics, and research instrumentation.
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s Mr. Forrest C. Burns 1961 --Present Research Chemist, Army Materials and Mechanics Rasearch Center, Watertown, MA 1958-1961 Employed by NASA at Cleveland, OH from
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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 Laboratories.
Education and Training 1956 A.B.,
Chemistry, Berea College, Berea, KY 1958 M.S.,
Chemistry, University of Kentucky Pertinent Experience Has used the M.I.T.
and Army reactors for activatica analysis research and has also done 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 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. CHARLES DADY 1987 - Present Acting Radiological Protection Officer, Materials t
Technology Laboratory, Watertown, MA 1981 - Present Leader, Analytical Chemistry Team,, Materials Char-
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acterization Division, MTL, Watertown', MA 1970 + 1981 Chemist Army Materials and Mechanics Research Center Watertcwn, MA 1962 - 1970 Chief Radiological Safety Office, Army Materials Agency, Watertown MA 1959 - 1962 Chief, Radiological Safety Office, Ordnance Materials Research Office (OMRO, Watertown, MA) 1957 - 1959
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Physical Chemist Atomic Energy Division, OMRO: on t
detached duty at Oak Ridge National Laboratory.
1954 - 1957 Analytical. Chemist Analytical Chemistry Branch.
Watertown Arsenal Laboratories 1952 - 1954 Employed as a chemist in Industry Education 1952 B.A.,
Chemistry Boston University 1954 - 1957 Graduate courses in Chemistry, Boston College 1957 - 1958 Vanderbilt University. Graduate School j
USAEC courses in radiological physics 1958 - 1959 Attended Oak Ridge School of Reactor Technology (ORSORT). All prescribed courses except engineering, were taken.
Pe rtinen t __ Experience 1958 (Summer)
Field work in Health Physics Division, Oak Ridge National Laboratory (ORNL) 1958 - 1959 Assigned to Health Physics Division, ORNL
.1959 (Summer)
ORNL Reactor Division for reactor operations training 1969 Certified as Health Physicist
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1970 - 1978 Alternate Radiological Protection Of ficer 3
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D_R. ALFRED BR0Z O
O 1987 - Present Acting Radiological Protection Officer, MTL 1987 - Present Chief, Materials Testing & Evaluation Division. MIL
' Chief, Nondestructive EvaluatIorrBranch 1982 to 1987,
(NDEB), Army Materials and Mechacies Research Center, Watertown, MA 1980 to 1982 Physicist, NDEB, Army Materials and Mechanics Research Center, Watertown, MA l
1974 to 1980 Physical Scientist, Aberdeen Proving i
Ground, MD l
l Education and Training 1965 B.S.,
Physics, College of St. Thomas, St.
Paul,MN 1968 M.S., Physics, SD School of Mines & Tech.
Rapid City, South Dakota 1973 Physics,.Phd., Notre Dame, IN 1979 Radiological Safety Course, USA 0CCS, APC, MD 1974 Industrial and Flash X-Ray Operations Training, APG, MD Partinent Experience 1974 to 1980 Responsible for industrial and Flash X-Ray Operations, Materiel Testing directorate, APG, MD.
1979'to 1980 Radiation Protection Off.icer, Materiel Testing Directorate, APG, MD. Dutys included monitoring of depleted uranium projectile firings.
1979 to 1980 Appointed Alternate Radiation Protection Officer, Member and 1st Vice Chairperson Radiation Protection Committee, Aberdeen Proving Ground, Maryland.
1980 to Present As Chief, NDE Branch, responsible for direction of Industrial X-Ray Facility (2.0 Mev), CS-137 Radiographic Facility, Industrial X-Ray Units (100 kv to 3 mv).
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l' DR. LAURENCE D. JENNINt,5 1
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'1981 - Present Deputy Chief, Materials Characterization Division 1
1959 - 1981 Research Physicist, Army Materials and l
Mechanics Research Center,' Water *,nwn, MA 1955-1959 Assistant Professor, Ohio State University i
j I
l Education and Training 1955 Ph.D., Physics,M.I.T.
1950 S.B.,
Physics, M.I.T.
1 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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Mr. Louis J. Farese Present Member, X-ray and Neutron Analysis Group, Materials Characterization 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 1975 B.S.,
Biology, Providence College 1978 Radiological Saf ety Course, U.S. Army Ordnance and Chemical Center, and School, Aberdeen Proving Ground, FD 1979 Laser-Microwave Hazards 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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l Dr. James W. McCauley 1981 - Present Chief, Materials Characterization Division, Army Materials and Mechanics Research Center, Watertown, MA.
1974-1981 Group leader, synthesis and characteri-zation, Ceramics Research Division, Army Materials and Mechanics Research Center, Watertown, FUL 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 Education and Training 1961-B.S., Geology, St. Joseph's College (Ind) 1965 M.S., Minerology, Pennsylvania State University
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1968 Ph.D., Solid State Science, The Pennsylvania State University
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l Pertinent Experience Pertinent areas of competence include:
almost all aspects of materials characterization specializing in x-ray crystallography and optical microscopy; material synthesis; powder
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technology; instrumental analysis.
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m Robert Fitzpatrick 1955 - Present Research Materials Engineer AMMRC Watertown, MA WAL Watertown, MA Education and Training 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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APPENDIX II
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O APPENDIX II l
TYPE OF INSTRUMENTS Radiation l
Survey Instruments:
No. Avail Detect'ed Sensitivity Range G. M. Survey Meter,-Nuclear 3
Beta-Gamma 0.1,3,1,3,10,30 Chicago, Model 2650 100 mr/hr Low Energy Survey Meter,-
4 Alpha and 0-1,10,30,100,300 Victoreen, Model 440 Beta-Gamma mr/hr Low Energy Survey meter, 1
Alpha and 0.3,1,3,10,30 Victoreen, Model 440 B Beta-Gamma mr/hr G. M. Survey Meter, Eberline 1
Beta-Camma 0.2,2,20,200,2,000 Model E-500-B mr/hr Ionization Chamber 1
Beta-Gamma 0-10,100,1,000 Victoreen, Model 592 B mr/hr Neutron Detector, 2
Neutrons 0-50,50-5K Model PNR-4, Eberline mrem /hr Ionization Chamber 1
Beta-Gamma 0-1,3,10 mr/hr Victoreen, Model 471 Ionization Chamber 1
Beta-Gamma 0-30,100,300 Victoreen, Model 470 A mr/hr BF Neutr n Survey Meter, 2
Neutrons 0-75,250,750,7,5K, 3
Nuclear Chicago, Model 2671 7.5K,25K n/cm /sec Victoreen Condensor R-meter 1
Gamma 0-250 R G. M. Neutron Ratemeter 1
Alph-Beta 0-500,0-5,000 Ludlum, Model 15 (5 probes)
Gamma-0-50,000, Neutrons 0-500,000 cpm Digi / Master, Ratemeter 1
Beta-Gamma 0-100 mr/hr Reactor Experiments 0-100 r/hr Ionization Chamber 1
Beta-Gamma 0-5,0-50,0-500 Eberline, Model R0-2 0-5,000 mr/hr 1
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APPENDIX II (cont 'd)'
Radiation Laboratory Moniters:
No. Avail Detected Sensitivity Range Tracerlab Ratemeters 3
Alpha and 0-100,200,500,1K,2K Beta-Camma SK,10K,20K cpm Technical Associates 4
Alpha and 0-500,0-5,000 Radiation Monitor Beta-Gamma 0-50,000,0-500,000 Model SML-2 cpm Area Monitor 1
Beta-Gamma 0-100 mr (Audible)
Dosimeter Corp.
Model 3000 Area Alarm Meter 1
Gamma 0-1,000 mr/hr Ludlum, Model 300 (2 Probes)
Area Alarm Meter Ludlum, Model 3005 1
Fast Neurton 0-1,000 Mrem /hr 3
Tritium Sniffer 1
> 1 pCi/T Johnson Assoc., E S-E-1036-17 Personnel Audable Units:
i Radiation Detector 1
Beta-Gamma 0.2,1-2,10-20 i
(' ariable alarm) l v
Solar Electronics Digital 1 Exprosure Meter 1
Beta-Gamma 0-1,000 nr Xetex, Model 409A (variable alarm)
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Radiation Alert Solar Electronics, " Mini" Model Counting Systems:
Tracerlab Propor-1 Alpha, Beta Variable tional Counter with Automatic Sampic Changer Searle Analytic 1
Alpha, Beta Variable Proportional Counter, Model ll52B, with Automatic Sample Changer
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Nuclear Data 4410 2
Gamma Variable Multi Channel Gamma Spectrometer i
TMC 256 Channel Spectro-1 Gamma Variable
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APPENDIX III-N
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O APPENDIX III DEPARTMEh? 0F THE ARMY ARMY M'ATERIAIS AND MECHANICS RESEARCH CENTER
-Watertown, Massachusetts 02172 a
AMMRC REGULATION 12 May 1983 No.
385-4*
Safety RADIATION PROTECTION - POLICY 6 PROGRAM 1
l Paragraph Purpose ----------------------------------------------------------
1 l
Scope ------------------------------------------------------------
2 Policy -----------------------------------------------------------
3 Responsibilities -------------------------------------------------
4 Control of Radioactive Material -----'----------------------------
5 Personnel Dosimetry -------------------- ----------------------- -
6 Personnel Exposure Limits ----------------------------------------
7 Exposures Associated with Accidents or Emergencies - -------------
8 Medical Examinations ---------------------------------------------
9 Training of Personnel --------------------------------------------
10 General Procedures for Re stricted Areas --------------------------
11 R a d i a t i o n Su rv e y s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
12 Calibration of Meters --------------------------------------------
13 Pu r c ha s e o f Me t e r s - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
14 Waste Disposal ---------------------------------------------------
15 NRC Licenses and Department of Army Authorizations ---------------
16 AMMRC Authorizations to Use Radioactive Materials ----------------
17 Purchase requests Involving Radioactive Materials or Equipment Producing Ionizing Radiation --------------------
18 Ke y 'Eme rg en cy P e r sonn e l - - - - - - - -- - - - - - - - - - -- -- - - - - - - - - - - -- - - - - - - -
19 On-Post Transportation of Radioactive Materials ------------------
20 Maximum Permissible Contamination of Inanimate Obj ects -----------
Table I Relative Biological Effectiveness Values of Various Types of Radiation for Total Body Chronic Exposures ----------------
Table II Neu tron Flux Do s e Equ ivalent s ---------- -------------------------
Table III Caution Sign and Signal Device Requirement s ----------------------
Table IV Definitions------------------------------------------------------
Appendix 1.
PURPOSE.
This regulation prescribes the Army Materials and Mechanics Re-search Center (AMMRC) policy and programpetaining to the protection of per-sonnel and property from unwarranted radiation exposure.
2.
SCOPE.
A.
This regulation pertains to the requirements for procuring, receiving, storing, shipping, using, transporting, maintaining, or disposing of material and/or equipment which produces ionizing radiation.
- This Regulation supersedes AbNRC Regulation 385-4, dtd 22 March 1978.
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12 May 1983 AhNRCR 385-4 b.
The provisions of this regulation apply to all organizations and em-ployees of AhNRC, guest scientists and personnel on detail to AbNRC from other organizations.
3.
POLICY. All operations involving ionizing radiation-producing material and equipment will be conducted in such a manner as to maintain radiation ex-posures to ' personnel as low as reasonable achievable (ALARA).
Operations in-volvine ionizing radiation shall be planned so that the limits established by i
NRC, DA, DARCOM, OSi!A, and AhNRC regulations are not exceeded, t
4.
RESPONSIBILITIES.
a.
The Chief, Safety Office, is responsible for all l
aspects of the AhWRC Occupational Safety and llealth (OSil) Program.
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b.
The Radiation Protection Officer (RPO), as a staff member of the Safety Office, will perform, as an integral part of the overall AhNRC Safety Program, the actions required to establish and maintain preventive measures to safegaurd personnel and equipment from harmful effects of ionizing radia-
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tion.
Responsibilities of the RPO are delineated in DARCOM-R 385-25.
1 Radiation Control Committee (RCC) advises the Director on policy and c.
actions necessary to insure the safe use of material and equipment which pro-duces ionizing radiation.
Responsibilities of the RCC are outlined in AhNRC Memorandum 15-2.
j i
d.
Reactor Safeguards Committee (RSC) reviews, evaluates, and approves all aspects of maintenance and radiological safety for the former nuclear reactor which is in standby status.
Responsibilities of the RSC are outlined in AhWRC Memorandum 15-1.
The MEDDAC Health Clinic at AhNRC is responsible for providing medi-e.
cal examinations in support of the Safety Program as required by higher autho-rity within the provisions of this regulation.
f.
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 established in this regulation. The responsibilities of an organizational chief include:
(1)
Complying with and enforcing the radiological safety requirements prescribed in this regulation, and radiation safety requirements applicabic 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.
2 a
O O
12 May 1983 AMMRC 385-4 (3) Assuring that all equipment and facilities are operated in accordance with established procedures to minimize radiation hazards to personnel and con-tamination of equipment.
(4) Assuring that prior to the start of any operation involving radio-active 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 RPO.
(5) Assuring that an AMMRC Procedure is prepared covering work which is performed at a frequency which makes the completion of RWP's impractical.
Such procedures will be submitted to the Safety Office for review and appro-val by the Radiation Control Committee, i
(6)
Providing necessary space and facilities for the Safety Office to l
carry out prescribed monitoring programs in his/her area.
g.
Supervisors of radiation workers or radiological proj ects are respon-sibic 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 Health Roster (OHR), XMR Form 245, Figure 1, of all personnel under his/her control who are likely to receive an accumulated dose of radi.ation in excess of 5 percent of the appli-cabic quarterly limit.
(3) Assuring that his personnel are instructed in requirement s for working with radioactive materials or radiation equipment and compliance with applicable rules and regulations governing radiological safety.
(4) Assuring that required monitoring devices, protective clothing and equipment, and contamination control methods are used.
(5) Assuring that all equipment and facilities are operated in accordance with established procedure to minimize radiation exposure to personnel and contamination of equipment.
(6) Notifying the Safety Office in advance of any scheduled maintenance or repair work which may involve radiation exposure or the release of radioac-tive materials not covered by an approved standing operating procedure (SOP).
(7) Obtaining recommendations of the Safety Officcin nonroutine oper-ations 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.
3
O O-AMMRCR 385-4 12.May 1983 (9)
Posting NRC Form 3 in the immediate work area and pos' ting the fol-lowing documents or the location where they may be found:
(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 21 (f) 10 CFR Part 30 (By-Product Material Only)
(g)- 10 CFR Part 40 (Source Material Only)
(h) 10 CFR Part 50 (Nuclear Reactor Only)
(i) 10 CFR Part 70 (Special Nuclear Material Only)
(j )
Section 206 of the Energy Reorganization Act of 1974 (k) Copy of the regulation (1) Copy of AMMRC procedures pertinent to operations in the area per-taining to radiation (m)
DA authorization applicable to the area (n)
AMMRC Memorandum 385-15 (10)
Limiting working times so as to control the total radiation expo-sures of personnel within prescribed limits.
(11)
Keeping informed on the radiation exposure status of personnel under his control.
(12) Maintaining control of visitors.
(13)
Reporting to the chief of the operational organization any viola-tion of these regulations or failure to follow prescribed procedures by any individual in his area.
(14)
Ensuring that radiological ~ safety surveys are conducted at least weekly reporting any abnormal results to the RPO, and maintaining permanent records of these surveys.
(15)
Inform the Safety Office by telephone (ext. 5225 or 5605) as soon as he/she knows that an individual on the Occupational Health Roster is to separate from employment, complete XMR Form 245, and forward i t to the 4
O O
v v
AMMRCR-385-4L 12 May 1983 Safety Office,for processing, h.
The ind_ividual'is responsible for:
(1) ' Completing Form NRC-4 and/or DD Form 1952 upon request by the Safety
_ Form NRC-4 'and DD Form 1152 are furnished by the Safety Office.
Office.
(2)
Keeping his daily exposures to radiation as low as practicable.
i (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.
l (8) Reporting wounds, ingestion accidents, and other incidents involving radioactive material promptly to his supervisor. Safety Office, and MEDDAC Health Clinic.
(9)
Being familiar with the radiological safety requirements prescribed in this regulation and SOP covering his operation.
(10) Roping off working 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.
L 1
(12) Cleaning up any contamination he generates following prescribed procedures.
(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 per-tinent NRC, DA, DARCOM, OSHA, and AMMRC regulations or posting their location.
5.
CONTROL OF RADIOACTIVE MATERIAL IN AMMRC.
a.
Procurement of radioactive material.
All requests for procurement of radioactive materials will receive the concurrence of the Safety Office before being forwarded to the Procurement Office.
b.
Receiving and Shipping. All radioactive material being shipped to or from AMMRC will be c1 cared by the RPO in accordance with AR 385-11.
5 l
O.
O 12 Mex 1983 AMMRCR 385-4 c.
Internal Transfer of Radioactive Materials.
Internal' transfer of radioactive material will be made only between authorized users.
Each such j
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 RP0 will be responsible for j
insuring that radioactive materials are disposed of in accordance with AR 385-11.
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 and under the direction of the RPO.
6.
PERSONNEL DOSIMETER, a.
Personnel who are likely to receive an accumu-lated dose of radiation in excess of 5 percent of that tabulated in paragraph 7.a will be placed on the OHR for ionizing radiation.
Personnel on the OHR will be issued film badges and/or thermoluminescent dosimeters (TLD), and will be subject to periodic medical examinations in accordance with paragraph 9.
I 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 mrem per year, may be issued film badges (XMR Form 406), Figure 2, without being placed on the OHR.
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.
c.
Personnel on the OllR who receive medical exposure (other than routine 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 RPO will forward applicable exposure information to the Medical Officer for inclusion in their DD-1141 Form.
d.
AhNRC personnel who may be occupationally exposed to ionizing radia-tion outside of AMMRC will wear film badges issued by the Safety Office, e.
Personnel on the OllR may request a copy of their radiation exposure to date from the MEDDAC llealth Clinic at ASNRC.
7.
PERSONNEL EXPOSURE LIMITS.
The radiation exposure standards contained in this paragraph are applicable to all personnel.
Exposures incurred dur-ing examination or treatment for medical or dental purposes are not to be in-cluded in calculations for compliance with this paragraph.
a.
In order to be permitted to receive the maximum exposures listed in the following table, the individual must (1) be at least 18 years of age; (2) be occupationally erposed; (3) have on file with the MEDDAC llealth Clinic 6
O O
AFNRCR 385-4 12 May 1983 a complete NRC-4 Form, DD Form 1952 or equivalent and (4) meet the restric-tions of Section b of this paragraph.
~
TYPE OF EXPOSURE PERIOD OF EXPOSURE DOSE (REM) f h' hole body, hand and accumulated
- 5 (N-18) trunk, active blood-calendar qtr 3
l forming organs, gonads or lens of eye.
Hand 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 Note:
Beta radiation should be counted as skin dose.
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 re-ceived the maximum allowable 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 ren total for first three quarters.
(4) 5 rem for the year, c.
Members of the general public, personnel not occupationally exposed 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.
e.
When an individual has received an exposure in excess of the quarter-ly limit, he shall be removed from duties involving radiation exposures until subsequent exposure limit s are established through consultation with the medical officer.
When an individual exceeds a yearly limit, he will be re-moved from duties involving radiation exposure until his records are reviewed by Headquarters, DARCOM, and subsequent limits established.
When an indivi-dual exceed the 5(N-18) dose, he will be renoved from duties involving ra-diation exposures until his records are myiewed by the DA, Surgeon General, and subsequent limit s established.
7
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AMMRCR 385-4 12 May 1983 8.
EXPOSURES ASSOCIATED WITH ACCIDENTS OR EMERGENCIES.
It is recognized that i
there may be accidents or emergencies' in which an overexposure should be ac-cepted in order to prevent serious body injury or property damage.
a.
In " planned emercency" a ct ion. i.e. action which is taken following some' preparation, twenty-five (25) rem should be considered the maximum allow-able dose.
l I
b.
To prevent serious body injury or death of an individual, the maximum considered dose should not exceed 100 rem.
i 9.
MEDICAL EXAMINATIONS, a.
Radiation workers on the OHR will be given a pre-employment examination.
Personnel who are to be occupationally exposed to neutrons will be given a slit-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 radiation 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 OHR will be given medical examinations at least yearly.
XbR Form 245 will be used for initial and termination examinations.
XMR Fonn 265, Figure 3, will be used for periodic examinations, d.
Upon termination of employment or removal from the OHR the individual will be given a medical examination.
10.
TRAINING OF PERSONNEL.
Personnel, -including guest scientists, who will 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 and placed in each employce's of ficial personnel folder. The Safety Office will arrange for required training in conjunction with the Training Officer.
11.
GENERAL PROCEDURES FOR RADIATION CONTROLLED AREAS.
These rules consti-tute the basic techniques and procedures to be followed in restricted area:
a.
Smoking, drinking and eating are prohibited in airborne radioactivity areas and contamination areas.
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 radio-active waste.
c.
Protective clothing and monitoring devices will be worn when required.
f.
No one shall work with radioactive material with open or uncovered 8
O O
MNRCR 385-4 12 MaY 1983 wounds.
Appropriate gloves, bandages, or coverings are allowed if approved by the RPO.
g.
Custodial personnel will only wet-mop and vacuum-clean areas where tvdioactive contamination may be present.
Dusting and sweeping will not be al? owed.
Vacuum cleaners used in radiation areas will be approved by the RPO.
12.
RADIAfION SURVEYS.
The Safety Office is responsible for performing radia-tion 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 radiation is initiated or changes approved, or upon in-sta11ation of a device which produces ionizing radiation, b.
Routine Surveys by the Safety Office.
Surveys of each area in which sources of radiation are used and/or stored shall be performed by the Safety Office at least once each month.
Areas of static storage shall be surveyed at least once every three months.
The radiation hazards incident to the produc-tion, use, release, disposal, or presence of evaluation includes a physical survey of the location of materials and equipment, measurements of IcVels of radiation and/or concentrations of radioactive material in and around the site.
Locations of the monitoring points with the results, statement of the hazard, and any recommendations as to decontamination, shielding, procedural changes, et c., will be recorded.
c.
Operational Surveys.
Operating organizations will survey their areas at least weekly to insure that their operations are within the limit s pre-scribed by this regulation.
d.
Special Surveys.
The RPO is responsible for performing the following special surveys:
(1) Non-routine operations involving radioactive materials or radiation producing equipment where there is a resonable probability of any individual being exposed in excess of 2 mrem in one hour.
(2)
Receipt or shipment of radioactive materials.
Packages of radio-active materials for shipment will be checked for external radiation icvel, leakage probabilit y, contaminat ion, and proper labeling. Packages of radio-act ive materials received at AMMRC will be surveyed by the RPO prior to their delivery to the individual who is reponsible for their use.
(3)
Termination of a proj ect involving radioactive materials.
A survey will be performed to determine that no contamination exists and that sources 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 operat ion will be investigat ed by the RPO.
9
I 1
g\\ /
O-12 May 1983 AMMRCR 385-4 (5) Hazardous operations. Particularly hazardous operatidns will be con-tinuously monitored.
(6) Leak Tests.
Leak tests of sealed sources vLll be performed at least once every 6 months except for alpha sealed sources that are not in storage which will be performed at least every 3 months.
13.
CALIBRATION OF METERS.
The Safety Office is responsible for the calibra-tion of all portable radiation survey meters.
All portable radiation survey meters, unless labeled CBU, will be cali-a.
brated at least every 3 months and af ter each maintenance or battery charge.
Instruments will be calibrated at a minimum of 2 points on each scale.
b.
Pencil dosimeters assigned to individuals will be calibrated at 6 l
month intervals.
Others will be CBU, 14.
EURCHASE OF METERS.
The Safety Office should be consulted prior to the
. purchase of survey meters or other metera to be used for radiation protection in order that the type and variety of meters at /JURC can be kept to a minimum This procedure is adopted to minimize spare parts requirements as well as to facilitate the maintenance and calibration of meters.
15.
WASTE DISPOSAL.
a.
The Safety Office is responsible for insuring that i
unwanted radioactive materials are disposed of.in accordance with AR 385-11.
1
)
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, Table II, is not exceeded at the point of release unless otherwise authorized by the U.S. Nuclear Regulatory Commission.
I c.
The concentration of liquid waste released to the environment shall l
I conform to 10 CFR 20.
d.
Storage areas and containers for radioactive materials will be approved by the Safety Office.
16.
NRC LICENSES AND DEPARTMENT OF THE ARMY AUTHORIZATIONS. AMMRC will be guided by the procedures in AR 385-11 when applying for NRCLicenses and Department of the Army Authorizations.
l
)
17.
AMMRC AUTHORIZATION 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 Reg-ulations 15-2 for details.
18.
PURCHASE 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 sub-l mitted to the RPO for approval.
I 10 l
l L
O o
AMMRCR 385-4 12 May 1983 19.
KEY EMERGENCY' PERSONNEL.
Key emergency personnel will be kept currently informed of the receipt, storage, uso disposal, or transfer of radiation sources and will be sufficiently trained and equipped to cope with radiological emergencies independent of the presence of the RPO.
The Intelligence and Security Office will maintain a current listing of personnel to be called in on emergencies.
20.
ON-POST TRANSPORTATION OF RADI0 ACTIVE MATERIALS.
Within an installation, it is usually not convenient to package and transport radioactive materials in the manner required for off-post shipment.
However, the following precautions will be observed:
In loading the vehicles:
a.
Keep within the weight limitations.
b.
Limit or arrange cargo to keep radiation levels to which personnel (including the driver) will be exposed during transportation as low as practi-cal. Maximum permissible dose rate in occupied areas of the vehicle will de-pend upon the time required to transport the material.
The driver will wear film badge, if specified by the RPO, 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.
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AMMRCR 385-4 12 May 83 TABLE II RELATIVE BIOLOGICAL EFFECTIVENESS VALUES OF VARIOUS TYPES OF RADIATION FOR TOTAL BODY CHRONIC EXPOSURE Type of Radiation RBE 10 Alpha Beta 1
X or Gamma 1
Protons 10
- Thermal Neutrons 2.5
- Fast Neutrons 10 TABLE III**
NEUTRON FLUX DOSE EQUIVALENTS Number of neutrons per square centimeter Average flux to q ivalent to a dose deliver 100 millirem Ne m on me m Mev) f l #**2 I"h0 hours (neutrons /cm )
(neutrons /cm per sec.)
Thermal 970 X 106 0.0001 720 X 10 500 6
0.005 820 X 10 570 0
0.02 400 X 10 280 0.1 120 X 10 80 6
0.5 43 X 10 30 1.0 26 X 10 18 6
2.5 29 X 10 0
6 5.0 26 X 10 18 6
7.5 24 X 10 17 0
10 24 X 10 17 6
10 to 30 14 X 10 10
- If neutron energy is known, the value in Table III may be used.
- 10 CFR 20.4(c) 13
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ARMY MATERIALS AND MECHANICS RESEARCH CENTER
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REQUEST FOR CHANGE TO OCCUPATIONAL HEALTH ROSTER (Prepare in Quintuplicate)
]
i
?
To: Safety Director From:
Prit i i Supervisor it is requested that the following actions be taken:
Add to Roster O Remove from Roster O Other O Name n te of Birth Payroll No.
a 4
Extension Social Security No.
. Job Title and Grade
' Organization Branch Ridg.
Room _.
Education:
Grammar School O High School O College O Previous r;diation exposure record; include industrial exposure and medical X-rays other than routine. (Check area of conceno loriizing 1(adiation:
Depleted Uranium O Machine-Produced Radiation O Other Radioisotopes D lleavy Metals O Beryllium O Laser O Noise O Other O Brief des.:::ption of duties involving item (s) checked:
i S!gnature Date To: Medical Officer From: Safety Director PAlt1 11 Perform physical examination for areas checked in Part I.
Beta Gamma Badge No.
Neutron Badge No.
Remarks:
?
Signature Date fo: Safety Director From: Medical Officer PAltT eli-t Acceptable, no restrictions O Acceptable, with restrictions O Rejected (state reasons)
Ikenurks:
l Signature Date To:
From: Safety Director PAlffIV Su pervisor Forwarded for your information and retention.
Signature Date l-(15)
+
l AMR I ORM 245 Code: white. R&OSD; Yellow Employee 4 Supervisor; Green Medical Officer; o I I u 73 Revisal Blue Suspense (R&OSB); Pink Suspense (Employee 4 Supervisor).
l L______-----
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,, FIGURE II
. ; ARMY MATERIAL.S A$ ) MECHANICS.RESEARCil CENTER
' REQUEST FOR FILM BADGE MONITORING FOR PERSDNNEL, NOT REQUIRED,TO BE ON THE OCCUPATIONAL HEALTH ROSTER (Prepare in Quintuplicate)
To:
From: Radiation Protection Officer (RPO), R&OSB PARTI Superv6sor.
is not required to be placed on the Occupational Health Roster (OHR) for ionizing radiation (See AMMRC Mem~orandum No. 385 4 for OHR requirements).- In the interest of monitoring low level exposures to ionizing radiation, recommend that subject employee be issued a film badge Part 11 should be completed and returned to this office 'in order that'a' film badge can be issued.
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Signature Date To: RPO,R&OSB Frem:
PART 11 3,,,,,g,,,
Employce's Name Payroll No.
Ext.
Date of Birth Social Security No.
Job Title and Grade Lab /Div Branch Building Room Previous radiation exposure record (include industrial exposure and medical X rays other than routine).
Briefly describe duties which involve possible low level radiation exposure.
I Signature Date To:
From: RPO,R&OSB PART 111 Su persinor Beta gamma film badge has been assigned to above named employee of your organization. Film badge can be picked up at R&OSB, Bldg. 37, and when not in use will be stored in the film badge rack located at Building
. Room Signature Date XMR FORM 406 Code: white R&OSH. Yellow - 1.mployee's Supervisor, Green Employee; 9 FLH 73 (16)
IHue Suspense tR&OSH); Pink Suspense (Supersimr)
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FIGURE III
..; ARMY ' MATERIAL S AND MECHANICS,RESEARCH CENTER -
PERIODIC PHYSICAL EXAMINATION OCCUPATIONAL HEALTH ROSTER (Prepare in Triplicate) :
Part 1 GENERAL INFORMATION 1
Date Name:
Payroll No.
Extension Date of Birth Social Security No.
l Job Title and Grade l
Organization Branch Blds.
Room
'Date of Last Physical Examination
~Part 2
,~.
To:
Safety Director From: Medical Officer (Check area of concern)
Ionizing Radiation:
Depleted Uranium O Machine-Produced Radiation O Other Radioisotopes. O lleavy Metals O Beryllium O laser O Noise O Chemical O Other O (Specify)
O Acceptable, no restrictions O Acceptable, with restrictions O Rejected (state reasons)
Remarkst Medical Officer Date Part 3 To:
j Supervisor From:
Safety Director O Forwarded for your information and retention.
O Employee is no longet physically qualified to work with ionizing radiation and abould return his film badge to the R&OSB immediately.
O lmployee h no longer physically quahfied to work with i
signature Date l
j CODI:: White. R&OSil Green. Medical Officer Yellow F.mployee's Supervisor XMR I ORM 265 17 i M AY 75 (hev)
.I
AMMRCR 385-4 12 May 1983 uO APPENDIX DEFINITIONS AREA DEFINITIONS:
a.
Unrestricted Area.
Any are in AMMRC, entry into which is not controlled.
b.
Restricted Area.
Any area to which access is controlled for the pur-pose of protection of individuals from exposure to radiation and radioactive materials.
c.
Controlled Area.
Any area, accessible to personnel in which there exists radiation such that special controls or conditions have been established for.the protection of individuals.
i d.
Uncontrolled Area. Any are in which no special radiation controls or conditions have been established for protection of individuals.
j
- e. Radiation Area.
Any area, accessible to personnel, in which there exits 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 ex-cess of 100 millirem.
f.
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.
g.
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 amount specified in CFR 20, Appendix B, Table I, Column I.
AUTHORIZED USER. An individual whose qualifications *o use radioisotopes and/
or equipment which produces ionizing radiation has been reviewed and approved by the AMMRC Radiation Control Committee (see AMMRCM 15-2).
BACKGROUND RADIATION.
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 radiation due to the presence of radioactive substances in other parts of the building in the building itself, etc.
]
CONTAMINATION (RADIOACTIVE).
Deposition of radioactive material in any place where it is not desired, and particularly in any place where its presence can be harmf ul, to an experiment or a procedure, or is actually being a source of danger to persons.
l CURIE.
A unit of activity defined as the quantity of any rggioactive nuclide f
in which the number of disintegrations per second is 3 X 10 l
A-1 1
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AMMRCR 385-4 12,May 1983 a.
Millicurie - One-thousandth of a curie (3 X 10 disintegrations per second).
4 b.
Microcitrie ' One-millionth of a curie (3 X 10 disintegrations per second).
DOSE:
a.
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 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 hs 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 radiat1on safety.
It is now recommended that the term RBE be used in radiobiology only and that another term be used for purpone of radiation j
safety.
The linear-energy-transfer factor is multiplied by t.he absorbed dose, D
to obtain a quantity that expresses on a common scale the irradiation re-a ceived by persons exposed to all ionizing radiations. The name recommen6td for the linear-energy-transfer dependent f actor is quality factor QF.
Oth'er factors must also be considered for the purposes of radiatic-safety. A distribution factor, DF, is used to sxpress 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 offects the absorbed dose when radiation saf ety 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 factor, plus any other factors that may effect the incoming radiation, be called the dose equivalent, DE.
If the only apparent modifying factors are QF and DF then:
If other factors must be considered and are defined, then:
1 DE = D,(QF)
(DF)...............
where the dose takes into account the product of these other factors. The l
unit of dose couivalent, DE is the reu.
The unit of absorbed dose, D, is the rad.
(Compare definitions of rad and rem). Although the above [efinition of dose equivalent does not cover a number of theoretical aspects (in A-2 1
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s.
O O
ANMRCd385-4 12 May 1983
.1 particciar the physical dimensions of'some of the quantities) it fulfills the immediate' requirement for an unequivocal specification of aiscale. that may be used for numerical expression in radiation safety.
EXPOSURE. The term " Exposure Dose" is obsolete.
Exposure is a term adopted by the International Commission on Radiological Units 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 ionizgtion.
The unit of exposure is the roentgen, R, where IR equals 2.58 x 10 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 capable 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.
FILM BADCE.
A pack of appropriate photographic filn and filters used to de-te.rmine radiation exposure.
!!AZARD, RADIATION.
See' RADIATION HAZARD.
' INTERLOCK. 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 enfety of personnel or equipment.
For example, 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 sealed source encapsulation by detection of leakage or oscape of radioactive contamination.
NUCLEAR REACTOR SYSTEM. Any equipment or device, except a nuclear weapon capable of neutron multiplication through fission of special nucinar material.
This definition includes nuclear reactors and subcritical assemblies of special nuclear material and the supporting equipment or device (if any) as-sociated with them.
t 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 voltac,e X-radiation.
The rad is to be used solely with absorbed dose.
1 rad = 100 erg / gram = 1/100 joule /kg A-3 i
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AMMRCR 385-4 12 May 1983 RADIATION.
Energy propagated through space. As used in this regulation, the
. term refers to'two kinds of ionizing radiation:
a.
Electromagnetic waves (X-rays and gamma rays), and b.
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, i'
in its passage through matter.
RADIATION CONTROL COMMITTEE.
A group of persons appointed by the Director to advise him on policy and actions necessary to ensure safety of personnel and property from hazards of radiation.
Synonymous with " Isotope Committee,"
" Radiological Health and Safety Committee," " Radiation Protection Committee,"
and other similar titles of committees with the same purpose.
RADIATION HAZARD. A condition under which persons might receive radiation in excess of the applicable maximum permissible dose, or where radiation damage might be caused to materials or personnel.
RADIATION SOURCES. Materials, equipment or devices which generate or are capable of generating lonizing radiation, including:
(1) naturally occurring radioactive material, (2) by-product materials, (3) scurce 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 magnetrcns which pro-duce X-rays.
RADIATION WORKER. Any person occupationally exposed to ionizing radiation and/or radioactive materials.
(Job descriptions of radiation workers should reflect that the individual is potentially exposed to ionizing radiation.)
RADI0 ACTIVE MATERIAL.
Any substance which undergoes spontaneous disintegration 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 induced and natural radioactivity.
a.
By-product materials.
Any radioactive material (except special nuclear material) yielded in or made radioactive by exposure to radiation incident to the process of producing or utilizing special nuclear material.
l b.
Source material. Uranium or thorium or a combination thereof in any 1
physical or chemical form or ores which contain by weight, one-twentieth of I
one percent (0.05 percent) or more of uranium, thorium:or any combination thereof.
Source material does not include special nuclear material.
A-4 l
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AMMRCR 385-4 12 May 1983 c.
-Special. nuclear material.
Plutonium, uranium 233, pranium enriched in the isotope 235 'or any other material which the U.S. Atomic En'ergy Com-ission pursuant to the provisions of Section 51 of the Atomic Energy Act of 1954, 42 USC Section 2071, determies to be special nuclear materials, but does not include source material: or any material artificially enriched by any of the f oregoing 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 products, except those defined as source and special nuclear material.
RADIOLOGICAL PROTECTION' 0FFICER. An individual designated by the Commander.
to provide consultation on the ' degree of hazards ass 6ciated with ionizing ra-diation 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 func-tional title and is not intended to denote a commissioned status or job classification within~ the Armed Forces.
RBE.
(Relative Biological Effectiveness.) The RBE of a given radiation is defined cn 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 having same biological effect.
(See DOSE EQUIVALENT)
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 that 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) th'at would result f rom 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 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 (0*C, 1 atm). This is equivalent to the release of 87.7 ergs of energy when one gram of dry air under STP conditious is exposed to one roentgen of radi-ation, The roentgen is to be used solely as the unit for exposure.
-0 1 R = 2.85 x 10 coulombs /kg SEALED SOURCE.
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.
A-5
/^)
(D G
<J 12 May 1983 AMMRC 385-4 I
UNSEALED SOURCE.
A ' discrete amount of radioactive material that is not en-capsulated in a container to prevent leakage or escape of the radioactive material.
(DRXMR-H)
FOR THE DIRECTOR:
GEORSE W.
SIBERT OFFICIAL:
Colonel, Infantry
'f Deputy Director / Commander bj)EROYBE
,gasa4j p
,s o
- Chief, ministrat e Office DISTRIBUTION:
B Safety (200 cys)
MEDDAC Health Clinic (2 cy) i
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18
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APPENDIX F DEPARTMENT OF THE ARMY ~
i l-ARMY MATERIALS AND bECHANICS RESEARCH CENTER l
Watertown. Massachusetts 02172 AMMRC SAFETY PROCEDURE 11 May 1983 NO.
385-3*
STANDING OPERATING PROCEDURE CALIBRATION LAB, BUILDING 97 t
Paragraph Purpose----------------------------------------------------
1 Scope -------------------------------------------------------
2 General -----------------------------------------------------
3 Gamma Source Facility-Operating Inst ructions ----------------
4 Ra d i at ion Warn i ng Si gn s --- -- -- -- -- ---- ------ ---- -- ---- -- ----
5 Em e r g en c y P l an - - - - -- -- - - -- - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - -- - -
6 1.
PURPOSE. To prescribe operating rules pertaining to use of the Calibra-tion Lab, Building 97.
2.
SCOPE.
The provisions.of this procedure apply to all personnel whose assigned duties require their presence in the Calibration Lab.
3.
GENERAL.
Personnel who are required to enter the Calibration Lab as a part of their assigned duties will adhere to the following general requirements:
a.
The Safety Office, Ext. 5225, will be notified prior to entrance in-to Lab. Access will be restricted only to personnel authorized by the Radia-tion Protection Officer (RPO).
b.
Personnel entering the Calibration Lab must be accompanied by a mem-ber of the Safety Office.
c.
Personnel using the Calibration Lab are required to wear whole body film badges and/or self-reading pocket dosimeters.
d.
During operations such as calibration of survey instruments, calibra-tions of radiation sources, Icak testing of sealed sources, physical inventory of sources, and other similar functions which require radioactive sources to be exposed, all persons present will wear whole body film badges and self-reading pocket dosimeters.
Wrist badges will be worn when exposure to the hands is expected to be significantly greater than to the whole body.
4.
GAMMA SOURCE FACILITY-0PERATING INSTRUCTIONS.
a.
Before entering the source elevator room, an operating beta-gamma survey meter should be obtained.
Area should be surveyed to insure that sour e has not been moved or left in a raised position.
In addition to the regular film badge and dosimeter, a wrist film badge or a dosimeter attached to the wrist may be worn.
- This Safety Procedure supersedes AMMRC Procedure No. 385-3, dtd 19 April 1978.
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SP 385-3 b.
Two survey meters should be used while operating the facility.
One survey meter should. be placed near the well to show radiation field in this area and"one survey in'strument, should be available at console in order to measu're radiation' filed at this. point, c.
Turn on main switch, power and clutch switch.
d.
Check' that powerstat reads 80 and that the motor controller rheostat is at 7.5 or lower.
A setting of 7.5 is equivalent to 20 feet per minute if the travel switch, upper right on console, is in the high mode.
In the low l
mode, the travel is halved to 10 feet per minute. for the same rheostat setting o f 7. 5.
e.
The usual position for the source is at the bottom of the well.
The clutch must be reversed before movement can be made.
Place the maunal switch to re-set position, this will place source travel in proper direction.
Return to manual position and the facility is now ready for use.
f.
Press up or down button and source will move, but only when button is held down.
CAUTION - press one button at a time.
Depressing the up and down button at the same time will blow the fuse located on the front face of the console, If top or low travel switch is trinned by the source holder mechanism g.
the manual switch has to be placed in the re-set mode and then back to the manual posit ion before source movement can be made.
h.
For hand operation, the clutch switch should be off.
This will allow the hand wheel to turn more easily.
CAUfION - In manual operation upper limit swit ch does not function.
Do not raise source higher than 6.00 inches on the digital counter or damage to the microswitch may occur.
i.
When leaving the facility, the source should be driven to the bottom of well, and clutch switch, power switch and main switch turned off.
j.
If an extended measurement is made while no one is present, the con-sole should be left on so that the red lights on the console will indicate that the source is in use.
The door to the source room should be locked and signs posted at both entrances to the Calibration Lab stating that the source is in the raised position and entrance into the lab is strictly forbidden.
5.
RADIATION WARNING SIGNS.
The Calibration Lab will be conspicuously posted with radiation warning signs in compliance with all applicable regulations.
In addit ion, when a radioact ive source must be left unattended in an exposed position, signs stat ing, " RADIOACTIVE SOURCE EXPOSED - NO NOT ENTER", will be posted on t he out side of each entrance.
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APPENDIX G DEPARTMENT OF THE ARMY ARMY MATERIALS AND MECHANICS RESEARCH CENTER Watertown, Massachusetts 02172 AMMRC SAFETY PROCEDURE 18 May 1983 NO.
385-26*
STANDING OPERATING PROCEDURES CALIBRATION PROCEDURE EBERLINE PORTABLE NEUTRON REM COUNTER MODEL PNR-4 Paragraph 1
Purpose 2
Procedure -=
Appendix A 5 Curie Pu-Be Neutron Source Calibration Data
a 1.
PURPOSE.
This procedure describes the calibration procedure to be followed when calibrating the Eberline Portable Neutron REM Counter Model PNR-4.
2.
PROCEDURE.
a.
The Curie Pu-Be neutron source will be used to calibrate the neutron survey meter.
b.
Calibration values, i.e.,
distance vs. neutron flux vs. dose rate data, are listed in Appendix A.
c.
The graduated 2" x 4" calibration board, located in the calibration room, Building 97, is used for positioning the neutron survey meter from the Pu-Be source.
d.
All calibration will be performed outside the building and away from reflecting surfaces.
c.
The Pu-Be source is placed in the holder at the end of the calibration board using a remote handling device prior to start of calibration.
f.
The instrument detector is positioned with the center of the detector at the desired calibration point.
g.
Prior to calibration determine the sensitivity to gamma radiation by placing the instrument in a gamma field of 200 mr/hr. There should be no re-sponse to gamma radiation.
If the meter responds to gamma radiation, adjust the high voltage as described in paragraph 2.1 (3), of the instrument manual.
l h.
Instruments readings within plus or minus 20% are considered to be l
within acceptable limits.
- i. Calibration: Three separate steps are required to calibrate the in-strument. These are:
i Sensitivity Adjustment Calibration Adiustment High Voltage Adjustannt
- This Safety Procedure supersedes AFERC Saf ety Procedure No. 385-26, dtd 31 Dec '80.
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SP 385-26 18 May 1983 (1)
SENSITIVITY ADJUSTF[NT (see manual for location).
This adjustment is not critical since the high voltage will compensate for a wide, range of settings.
However, if set too sensitive the instrument is susceptible to noise, and if set too insensitive. linearity of.the detector operation is affected. Optimum setting is about 2 millivolts,.which can be approximated by two 36d3 counterclockwise turns from extreme clockwise rotation.
(2)
CALIBRATION ADJUSTMENT.
The PNR-4 may be calibrated directly to a neutron field if a calibrated neutron range is available.
Before calibrating, the high voltage is adjusted as outlit.ed in paragraph 2.1 (3).
(a) To calibrat4 the following procedure is used:
l_.
Turn R3 and R5 maximum clockwise.
3 Place instrument in 4 MREM /hr field and adjust R2 for 4 MREM /hr reading.
3.
Place instrument in 40 MREM /hr field adjust R3 for 40 MREM /hr reading.
4.
Place instrument in 400 MREM /hr field and adjust R4 for 90 MREM /hr reading.
This normally should be a 400 MREM /hr reading but the Pu-Be source is not of sufficient strength where reliable readings greater than 90 MREM /hr can be obtained.
5.
Place instrument in 4K MREM /hr field and adjust R5 f or 4K MREM /hr reading.
This is not applicable when using a 5 Curie Pu-Be source.
(b)
If a calibrated neutron range is not available, calibration may be accomplished by using a pulse generator.
The pulse generator must have a negative pulse at least 3 millivolts amplitude with a rise time faster than 1 microsecond with frequency variable from below 200 PPM to 200K PPM.
1.
Remove the instrument from its case and the high voltage supply f rom the instrument.
Connect the pulse generator to the spring con-nector (junction of R8 and C2).
2.
Follow the same procedure as above except adjust pulse generator frequency to correspond to the count rate from each field.
200 pulses per minutes is equal to 4 MREM /hr, and multiples thereof.
(3) HIGH VOLTAGE ADJUSTMENT (see manual f or location).
The operational threshold high voltage is located on the flat portion of the plateau, below the gamma threshold.
One method of arriving at this setting is to turn up the voltage slowly with the detector in a gamma field, until counting is observed.
This will be gamma threshold. Turn the voltage down until counting stops.
NOTE: The high voltage cames down, slowly, so be certain to wait until it is stabilized.
2
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O.
O SP 385-26 18 May 1983
.(d) A preferable method-is to calculate a plateau with the detector in a neutron field, and a second plateau with the detector in a gamma
~
field equal to the intensity of gamma it is desired to reject..From the two curves, select the optimum setting for the high voltage. Refer to manual for a typical plateau.
(b) A longer cable between the detector and counter.will cause the plateau to shif t to higher voltages because of capacitive loading effect. Therefore, the instrument should be set up with the cable with which it is to be used.
APPROVED bE
- v JCi!N F. VINING III Chief, Safety Office l
I.
D D
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' APPENDIX A i
5 C1 Pu-Be Neutron Source Calibration Data Distance (Cm)
Neutron Flux (n
- Cm"
~
- sec )
MREM /hr.
30 652 90.6 40 377 52.4 50 234 32.5 60 163 22.6 70 119.5-16.6 80 91.7 12.7 90 72.4 10.1 100 58.7 8.2 110 48.5 6.7 120 40.7 5.7 130 34.7 4.8 140 29.9 4.2 150 26.1 3.6 160 23.9 3.3 170 20.3
- 2. 8 180 18.1 2.5 1
1 I
l 0
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