ML20147D239
| ML20147D239 | |
| Person / Time | |
|---|---|
| Site: | 07000709 |
| Issue date: | 09/29/1978 |
| From: | Trabant E DELAWARE, UNIV. OF, NEWARK, DE |
| To: | |
| References | |
| NUDOCS 7810130268 | |
| Download: ML20147D239 (56) | |
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r,ECEWED September 29, 1978 1l 04 Radioisotope Licensing Branch i
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Division of Fuel Cycle 6 Material Safety J'3 (f t n
Of fice of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission n
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Washington, D.C.
20555 Re:
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ZEZ Centlemen:
The intiversity of Delaware. Newark, Delaware hereby makes application for renewal of Special Nuclear Material License Number SNM-656.
The following information is submitted in seven(7) copies in fulfillment of Section 70:22, Title 10, Code o f Fede ral Regula tions, Part 70 "Special Nuclear Material" and in accordance with U.S. Nuclear Regulatory Commission Regulatory Guide 10.3, Sections 4 and 6.
1.'
Specification of Applicant The University of Delaware, Newark, Delaware was made a Land-Grant College by act of the Delaware General Assembly in 1857.
It is thus organized in and by the State of Delaware.
The principal of fice of the University is located in Hullihen llall, University o f Delawa re, Newark, Delaware 19711.
The principal of ficers of the University are:
Name Title Address Citizenship Edward A. Trabant President 47 Kent Way United States Newark, DE 19711 L. Leon Campbell Provost 6 Vice 76 Polly Drummond Rd.
United States P re s iden t for Newark, DE 19711 Academic Af fairs There is no foreign control or ownership exercised over the applicant by any alien, foreign corporation, or foreign government.
2.
Specification of Activities a.
One Pu-Be neutron source M233 will continue to be held in storage by the Department of Electrical Engineering in Room 241 of P.S.
duPont llall Laboratory, Main Campus, or used as a calibration source for neutron detection instruments.
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One Pu-Be neut ron source N800118 will continue to be used in the Nuclear Physics Laboratory of Sharp Laboratory, Main Campus.
The source will be used for educational instructional purposes.
It will be used in the two specific experiments in the second half of the one year senior laboratory course PS 617/618.
- 1) n-gamma discrimination A liquid scintillator NE-213 will be placed near the howitzer's side port to detect the neut rons and t;amma photons.
Standard pulse shape discrimination technique will be applied for distinguishing neutrons f rom gamma counts.
The student will be sitting in the control room of the accelerator laboratory with the electronic console.
The signals f rom the liquid scintillator are sent through a conduit under ground via coax Lal cables.
- 2) neutron activation analysis A short-lived isotope like Mn-56 will be produced by irradiating Manganese powder in plastic pouches.
The pouches will be placed in the lucite sample-holding rod of the howitzer. The rod is then slid into the vicinity of the source inside the howitzer for Irradiation. Af ter irradiation' the rod can be pulled out and the activity will be counted in standard gamma photon counting set-up in the nearby laboratory reserved for the PS 617/618 course.
1 In both experiments the Pu-Be source shall remain inside the howitzer and the howitzer will be kept inside the accelerator vault.
j 3.
Specification of Special Nuclear Material The University of Delaware possesses two(2) Plutonium-Beryllium sources totaling approximately 96 grams of Plutonium in source Nos., M233 and N800Il8 given In Grant Number MG--179-73 RIS:ZEZ to the University of Delaware by the Laboratory Relations Branch, Division of Nuclear Education and Training, USAEC, on February 13, 1973. This grant replaced Loan Agreement R2 (1958) and 62-6.
a Source No. M233 of approximately 16 grams of Plutonium and one(1)
Curie of activity was manufactured by Monsanto Research Corporation, Mound Labo ratory, Miamisburg, Ohio.
The source is stored and secured by lock and key in its original shipping container which is a 15-gallon drum filled with paraf fin.
The shipping container has a 15-inch diameter.
The source is described as 15.93 grams Plutonium contained in Tantalum and stainless steel having dimensions of 1.06" 0.D. x 1.58" H, 10-32 thread.
b.
Source No. N800I18 of approximately 80 grams Plutonium and 5 Curies of activity was fabricated by Nuclear Materials and Equipment Corporation, Apollo, Pennsylvania.
The source is stored, used, and secured when stored by lock and key in a neutron howitzer model NR-2 manuf actured by U.S. Nuclear Corporation, P.O. Box 208, Burbank, Cali fo rnia. A print of the details and dimensions of this howitzer were enclosed with the University's previous applicatton dated October 10, 1962.
This print is U.S. Nuclear drawing number E-0050.
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d a.
The source is desc ribed as 74.42 grams Plutonium contained in -
Tantalum and stainless steel having dimensions of 1.63" 0.D. x 2 " 11,
c.
This renewal application requested a possession limit of ninety-six (96) grams of Plutonium encapsulated as two(2)
Pu-Be neutron sources.
4.
Technical Qualifications of Personnel 1
Course Ins t ruc to rs
-.i Cheng-Ming Fou, PhD., Associate Professor o f Physics 1956 B.Sc. National Taiwan University, Taiwan China 1961 Dipl. Phys.
Universit!!t Mllachen, Munich, Germany 1965 PhD.
University of Pennsylvania, Philadelphia, Pa.
1965-68 Research Associate, Univ. of Penn., Tandem Accele rato r Laboratory 1968 Assistant Professor of Physics, University of Delaware 1972 Associate Professor of Physics, University of Delaware Recent Publications Investigation of B and Be Levels in Kinematically Complete B(p,pn) Be, J.M. Chou, C. M. Fo u, C. S. 1 in, Y. C. Liu, P.S. Sung, and M. Wen, Journal of Physical Society of Japan, 44, 1 (1978).
Characteristics of the First Exci ted S tate o f 112-5, C.M. Fo u, Y. C. L i u, C.C. Ilsu, and S.L. Iluang, J. Phys. G. 1_1_ 847 (1976).
Study of Multi-particle Final State Interac tion with a Pulsed Beam, J.C. Chou, C.M. Fou, C.S. Lin, Y.C.Liu, P.S. Sung, and M. Wen, Nucl. Instr. Methods 130, 157 (1975).
The Characteristics of the Third Excited State o f Li-6,11. Schwartz and C.M. Fou.
J. of Phys. G7,, L57 (1975).
The Excitation Energy of the First Excited State of Be, C.M. Fou and P.T. Wu, Canadian J. Phys. (1975).
The Characteristics of the First Excited State of Li, R.M. Gagne nad C.M. Fou, Journal de Physique 3f, 759 (19 75).
t Dr. Fou has served on the Radiation Safety Committee of the University of Delaware since 1976 and served as chairperson of that committee during the 1977-1978 academic year. lie is also an authorized permit supervisor under the Univers Lty's Broad "A" NRC license #07-01579-19.
C.B. Cooper, PhD., Pro fesso r o f Physics 1950 PhD., Physics, University of Maryland 1944-46, Technical Supervisor, Hanhat tan Project, Oak Itidge, Tenn.
1946-49, Instructor, Physics, University of Delaware 1951-52, Assistant Professor of Physics, University of Maryland 1952-58, Vice-President, Tageraf t Corporation 1958-65, Associate Pro fessor o f Physics, University of Delaware 1965 Professor of Physics, University of Delaware 1968-69 Acting Chairperson, Dept. of Physics, University of Delaware
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l Recent Publications l
Analysis of Pb-azide Thin Films by Rutherford Backscattering, H.M. Windawi, C. B. Cooper, and F.E. Wili tams, J. Appl. Phys., 4], 3418 (1976).
AES Depth Profiling with N,,+ Ion Sput tering, ll.M. Windawi, J.R. Katzer, and C.B. Cooper, Phys. Lett.
(Neth.), 59A, 62 (1976)
A Combined UlIV Ion 9cattering and Secondary Ion Mass Spectrometer Utilizing a Magnetic Sector Magnet, L.L. Tongson and C.B. Cooper, J. Phys. E., 10, 12 4 5 (19 7 7).
Dr. Cooper has been active in the field of surf ace physics for about thirteen years.
He has in addition to the above publications about 35 others.
Dr. Cooper served as Radiation Safety Of ficer for the University during 1963-1965 and has been supervisor of NRC license #SNM-656 for a numbet of years.
Radiological Safe ty Jenny M. Johansen, M.S., Safety Coordinato r/ Radiation Safety Of ficer j
1965 B. A. Concordia College, bbo rhead, Minnesota 1969 H.S. Radiological Health Physics, North Dakota State University, Fargo, N.D.
1969-70 Research Assistant, Radia tion Safety Of ficer, Virology and Tissue Culture l
Lab., Tuf ts Medical School, Brockton V. A. Hospi tal, Brockton, Mass.
1970-71 Health Physicist / Chemist, Radiation Safety Of ficer, Division of Nuclear Medicine, Peter Bent Brigham Hospital, Boston, MA.
j 1970-74 Health Physicist, Assistant Radiation Safety Of ficer, Joint Center for Radiation Therapy, Boston. FM.
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1974 -
Radiation Safety Of ficer, University of Delaware.
1975-Appointed Instructor, College of Craduate Studies, University of Delaware 1976 - Safety coordinator / Radiation Safety Of ficer, University of Delaware.
Ms. Johansen has extensive experience with handling, storage, and safe use 4
of the various radioactive nuclides used in Nuclear Medicine, Radiation Therapy, and Resea rch.
In addition, she is the Radiation Safety Of ficer of record under the University's NRC Broad"A" license 07-01579-19 and serves as Executive Secretary of the Radiation Safety Committee.
Complete list of radionuclides Ms Johansen i
has used listed in the University's application for Broad "A" license dated December 3, 1974.
Ms. Johansen also teaches a course on safe handling of l
radionuclides to graduate students who are going to use radionuclides in research.
Supervisor Source #M233 (in storage)
Bruce C. Lutz, Ph.D., Professor of Electrical ingineering 1942 B.A. Physics University of Western Ontario 1944 M.A. Physics 1954 Ph.D. Physics, Johns Hopkins University i
19 'e 4-45 Instructor, Lieutenanc RCNUR 1945-47 Lecturer in Physics, University of Manitoba 1947-55 Instructor in Physics, Unive rsity of Delaware 1955-57 Assistant Professor of Physics, University of Delaware i
1957-62 Associate Professor of Physics, Electrical Engineering, University of Delaware 1962 Professor of Electrical Engineering, University of Delaware
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1 Dr. Lutz has served as supervisor of NRC License R-043 covering the AGN-201 nuclear reactor from 1958 until May, 1978. License R-043 has been terminated by the 1
NRC as the reactor was defueled and decommissioned in December of 1977.
Before the time of the defueling, the Pu-Be neutron source M233 previously covered by R-043 was transferred to NRC License #SNM-656 by Amendment #3 dated October 17, 1977 and requested by letter dated _ September 23, 1977.
Dr. Lutz has held a Senior Operator's License # SOP-313 and supervised NRC (AEC) license 07-01579-02 before its termination in 1975.
Dr. Lutz has served on the Radiation Safety Committee since it was formed in 1957 and was chairperson during the 1975-76 academic year.
5.
Description of Equipment, Facilities and Inst rumentation a.' Remote handling tools Source No. N800L18 has a two foot long handling tool supplied by U.S. Nuclear Corporation.
1 Source No. M233 has a two foot long handling tool which is attaened to it.
b.
S torage containe rs, facilities and instrumentation
- 1) Storage containers are previously described under items 3a and 3b, and provide adequate shielding of the neutron sources.
In addition, source No. N800118 in its howitzer is stored inside the van de Graff accelerator vault which i
is located in the basement of Sharp Laboratory.
The vault is surrounded on all sides by high density concrete 90 cm thick.
Signal cables are pulled through underground con-L dults and the entrance to the vault is shielded by a concrete maze.
The door to the maze contains 2 cm thick lead.
The door to rooms 014C, D, E, which is the accelerator complex is kept locked when an authorized person f rom the Department of Physics is not in the immediate area.
A diagram of Sharp Lab basement is attached to this application.
2)
Source No. M233 is stored in a small room within Room 241, P.S. duPont llall.
This snnll room formerly contained a 250 Kev x-ray unit which has been removed.
In the walls, i
doors, ceiling and floor o f this small room is 1/4" lead shielding.
The door to Room 241 is kept locked unless used by an authorized person from the bepartment of Electrical Engineering. These persons do not enter or use the small x-ray room.
A diagram of P.S. duPont llall is attached to this applica;1on.
I 3)
Radiation detection instruments The following radiation protection instrumentation is available for Source No. N800I18:
Instrument & Manufacturer Radiation Detected l
i Alpha Survey Meter, Nuclear-Chicago Alpha l
Corporation, Model 2672 Neutron Survey Meter, Nuclear-Chicago Fast & thermal neutrons Model 2671
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Description of the above instruments:
4 Nuclear-Chicago Corporation Alpha Survey Meter, Fbdel 2672 -
This instrument consists of a count rate nonitoring unit, and an alpha probe that houses a thin w(ndow air proportional detector with a high gain pre-amplifier. The probe has a window with 80 cm2 of sensitive area.
Sensitivity to a point source at the center of the window averages 90% of maximum.
The ef ficiency is approximately 12% for alpha particles f rom
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rad + E or Uranium oxide (for 2n geome try). The efficiency for betas and gammas is 0.1%.
The maximum background is 5 cpm, or about 0.0833 counts /second.
Nucicar-Chicago Model 2671 transistorized neutron portable sur-vey meter.
This instrument consists of a Nuclear-Chicago Model 2646 Neutron detector and Model 2673 neutron portable count ra te me t e r. The instrument is intended for general survey work for detection of fast neutrons.
By removal of the wax moderator and cadmium shield from the detector tube, the Model 2671 may be used for detection of thermal neutons.
Gamma discrimination for the Model 2671 is such that a negligible j
response is produced in a gamma flux of 5 roentgans per hour j
from radium.
The Fbdel 2646 Neutron Detector has a sensitivity for neutrons such that approximately 1 count per second is produced in a flux of 10 neutrons per square centimeter per second from a radium-beryllium neutron source.
The sensitivity for thermal neutrons without the wax moderator and cadmium shield is approximately 3 counts per second produced in a flux of 10 neutrons per square centimeter per second.
The moderator is approximately one inch of wax.
A 20 mil cadmium shield extends along the length of the tube, but the end is left open.
The detector tube is a BF3 gas filled chamber for proportional counting having a pressure of 30 centimeters of mercury. The detector is not sensitive te alpha, beta or gamma radiation fields of high intensity.
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In addition the Radiation Safety Office has on hand the following instruments available to use for both neutron sources:
Radiation Window Instrument & Manufacturer Detected Sensitivity mg/cm2 Use J
Victoreen-490 with 0-80,000 cpm 489-35 probe a,
6, y 0-20 mR/hr 1.4 Survey 489-4 probe 6, y 0-80,000 cpm 30 Survey 0-20 mR/hr 489-50 probe y
0-200 mR/hr NaI(TI) 1x1" Survey Victoreen-440 S, y 0-300 mR/hr 3.0 without Survey Measuring cap Vic to reen-444 a,
6, y 0-300 mR/hr 1.5 Survey Monito ring Victoreen Radector III S, y 0.1 mr/hr-1 Kr/hr Monitoring Eberline PAC-40-3 Survey 0-500,000 cpm 0.85 Measurement with AC21 probe a
i Survey AC21B probe 6
0-500,000 cpm 0.85 Measurement Survey TP-L probe 6
0-500,000 cpm Windowless Measurement Survey Eberline PNR-4 q
0-5,000 MREM Measurement
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Assaying Eberline MS-2 with u, S 0-500,000 cpm Windowless Measuring proportional gas flow FC-1 detector i
Calibration of Survey Meters n-Detection instruments will be calibrated at various distances in air against the 1 Ci Pu-Be neutron source #M233 which has a reported flux of 1.86 x 106 n/sec (1962).
We will assume an average neutron energy for Pu-Be of 3.4 MeV (NBS publication 456 " Measurement for the Safe Use of Radiation, andaconversionfactorofapproximately28x10g.89,1976) n/cm2 = 1 Rem f
(General Dynamics Health Physics Handbook, p. 163, 1963). The assumed radiation flux relation to source strength for point 2
& = S / (4nR ) where & is n/cm2/sec, s is n/sec and i
sources is F.is distance in cm.
Relationship of 41 = 42(R /R )2 is used.
2 1 The source was given to the University by AEC, traceable to NBS is assumed.
Concrete shielding is placed on three sides of i
the Pu-Be source for protection. Detection chambers and survey
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l meter are separated by a 36" cable.
PuBe source has a tolerance l
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-distance in air of 22 inches giving 55 n/cm/sec which is i
equivalent to 0.3 Rem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> exposure.
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i Alpha detection instruments and probes are calibrated against 4-Eberline certified Pu-239 sources traceable to NBS within a 0.2% agreement.
The sources are of 0.0003 uCi SN#7418, 0.0030 uCi SN#7419, 0.0337 uCi SN#7420, and 0.3731 uCi SN#7421, giving disintegration rates of 690 + 15, 6,700 + 130, 74,700 1,500, 827,400 1 16,500 assuming 1.5% backscatter of alpha particles from the surface of the disk and 2n geometry in the source holder in which the source is recessed by 1 mm.
The instruments are calibrated on 2 scales compatible to sources instruments with the probe at a distance of 1 mm f rom the surf ace of the a source, will be adjusted to read within 10% of source values.
Beta detection instruments and probes are calibrated against 4-Eberline Certified Tc-99 sources traceable to NBS within a 0.2% agreement. The sources are o f 0.0002 uC1 SN#7415, 0.0025 uCi SN#7416, 0.0256 uC1 SN#7417, and 0.2289 uC1 SN#139/71, olving disintegration rates of 550 + 15, 5,650 + 170, 56,820 + 1710 and 507,S00 + 15,200 assuming 25% backscatter of beta particles i
f rom surf ace of the disk and 2n geometry in the source holder in which che source is recessed by 1 mm.
The instruments are calibrated on 2 scales compatible to the source with the probe at a distance of 1 mm f rom surface of the source, instruments will be adjusted to read within i 10% of source values.
Gamma detecting instruments and probes are calibrated against a 100 mci CS-137 USN type 375, SN F171 source mounted in a JLS Series 10 Calibrator, SN 598 as is directly traceable to NBS, having an output of 100 mR/hr at 50 cm and a 200 beam port.
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The instruments and probes are calibrated at certain distances in air along the center of the beam port which will give a 1/2 scale reading at 2 scale settings on the instrument.
The distance from the source for 1/2 scale reading is first calculated.
With the port of calibrator closed, the instrument is placed in line with the calibration port at the distance calculated and measured. The scale on the instrument is placed so it can be seen from behind the calibrator. The calibration port is then opened and the exposure rate on the instrument is read. The port is closed and adjustments made to the instrument if necessary to bring the reading f
to +10% of exposure rate calculated for the distance.
The process is repeated until the adjustment to 110% is reached. The person performing the calibration is always behind the calibrator when the beam is open.
The port is opened with a remote handling tool.
If the instrument cannot be placed so the scale is readable, a mirror is'placed so that the scale can be seen from behind the calibrator.
Binoculars are also available so that the scale can be seen with greater accuracy f rom behind the calibrator.
Calibrations are performed by either one of the course instructors or the Radiation Safety Of ficer at six month intervals at the location of the Pu-Be source in duPont Hall or the basement of the Radiation Safety Of fice.
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J 6.
Procedures to protect Health and Minimize Danger The very first lecture of the PS 617/618 course using Source No. N800I18 will be on radiation safety in whtch the relevant paragraphs of the University of Delaware Radiation Safety danual (UDRSM) will be explained, The use of radiation monitors and survey meters wl:1 be shown.
Throughout the semester at each laboratory session, the area i
which the students occupy while the experiment is in progress will be surveyed to ascertain the radiation levels.
Each student will carry a personalized pocket dosimeter.
The readings of these dosimeters will be recorded before and af ter the laboratory session.
For the experiments described, the students are near the neutron howitzer for approximately ten (10) minutes in order to either adjust the position of the liquid scintillator or to slide the sampic in or out for irradiation. An estimated total accumulated exposure of 0.2 mrem /hr for the one (1) hour laboratory session can be expected.
This exposure is well below 25% of MPD values stated in 10 CFR-20 and conform to "ALARA" philosophy.
The sealed source is not removed from,the howitzer at any time during the laboratory sessions, periodic surveying of the radiation level around the howitzer immediately outside the port with and without the port plug in place will be carried out and results posted near the howitzer to inform the students coming in to do the experiment.
At the end of each day of use, the howitzer will be surveyed to determine if the neutron source is in the storage position.
When not in use the neutron Source No. N800118 will be stored in the storage position of the U.S. Nuclear NR-2 howitzer. The side ports and top closure port will be locked at all times, with the key available only to the laboratory instructors, chairperson of the Physics Department and Radiation Safety Officer.
For Source No. M233 which shall remain in storage, the key for the lock is controlled by Dr. Bruce C. Lutz of the Department of Electrical Engineering and available to the Radiation Safety Of ficer for calibration purposes, Specification of Radiation Safety Responsibilities and Duties a.
Although written for NRC License 07-01579019, the University of Delaware Radiation Safety Manual covers all NRC licensed activities at the University of Delaware. The purpose, organization and responsibilities of the University Radiation Safety Committee are outlined in Sections 1.1, 1.2 and 1.3 and of the Radiation Safety Officer in Sections 2.1 and 2.2.
Qualifications of the Radiation Safety Of ficer are stated under Section 4 of this application.
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b.
Personnel Monitoring j
1 Students in PS 617/618 will wear Bendix Model 884 fast neutron - y tissue equivalent dosimeters having a detection range of 0-200 mrem for measurement of whole body exposure.
Other personnel monitoring requirements are covered by Section 3.8 U DRSM.
Film badges for whole body fast neutron - y are supplied by R. S. Landauer, J r., 6 Company, Glenwood, Illinois on a bi-weekly.
basis.
c.
Radiation Safety Program Surveys to be carried out during the PS 617/618 course are I
, described in the paragraphs under item 6.
In addition the Radiation Safety Officer surveys the howitzer and storage con-j tuiner of the two Pu-Be sources on a quarterly basis during leak testing procedures for ri, y radiation levels.
d.
Record Management Log of surveys conducted during student experiments will be kept by the course instructor. All other records pertaining to the Pu-Be sources are kept by the Radiation Safety Officer with copies in the Departments of Physics and Electrical Enginee ring,
c.
Scaled Source Leak Testing All leak testing is performed by the Radiation Safety Officer or the Health Physics Technologist under direction of Radiation Safety Officer.
Qualifications of Radiation Safety Officer are i
stated under item 4.
Leak testing is carried out by smearing the surface of the sources with a cloth smear attachec to an 18" f o rceps.
Smears are counted on an Eberline Model F-1 windowless gas flow detector attached to Eberline Model MS-2 miniscaler rate meter.
Each smear is evaluated by comparison to count rate received on alpha plateau of proportional counter of an Eberline Serial #7422 Pu-239 disk source of 0.0046 uci i 2% traceable to NBS.
Pu-Be sources are leak tested on a quarterly basis.
f.
General Safety Instructions A copy of the UDRSM is submitted with this application.
Sections 3.3 and 3.5.2 apply.
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Emergency and Decontamination Procedures These are listed in Section 4.0 of UDSkM and the call list in Section 4.7 is posted in the lab rooms where the Pu-Be sources a re ke p t.
The Radiation Saf ety Of ficer would supervise any problem such as a source rupture which would require decontami-nation.
h.
Procedures for Training of Personnel L) A description of the training for students taking PS 617/618 is described in the paragraphs under Item 6.
2)
Source No. M233 is in storage and will be used only for cali-bration purposes in the foreseeable future, but should a project be proposed for its use, the persons who may be involved in or associated with the use ut this source must fulfill the requirements of the Radiation Safety Committee for authorization as outlined by the UDRSM, Sec tions 3.1, 3.2, pages 5-9.
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Persons not fulfilling these, requirements may be trained on the job under the direction of Dr. Lutz, this on-the-job training to cover items listed ou the Instruction Check-Off List found in Appendix A of UDRSM.
Persons trained on the job must pass a written examination covering the radioisotope or radiation device for which they are requesting authorization to use.
Also the Radiation Safely Committee may require persons not fulfilling the requirements to complete the one semester, three credit hour formal course, "Sa f e llandling of Radioisotopes,"
j U-675, taught by the Radiation Safety Officer. This course covers items outlined on NRC (AEC) Form 313, Section 8.
In addition an amendment to License SN'-656 for the specific
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purpose would be cent to the NRC for approval to use Source No, M233 for the project p ro po sed.
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1 7.
Period o f 1,1 cense Renewal of this license is requested for a five, ear period.
Sincerelv, l
Edw. d A. 'I rab a n t,
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President
, Application Approved
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'I ' t Department of Physics /.
Cheng-Mitig Fou, Ph.D.
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Associate Pro fessor o f Physics A
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'NdF Charles B. Cooper, Ph.D.[
Profesuor of Physics Application Approved jf '
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Department of Electrical 4L-<.< c -a 1
Engineering Bruce C.
Lutz, Ph.D.
P rofe< 10 r of Elect rleal Engineering Application prepa red b and Approved for the j
Radiation Safety
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.1nny M. [nanser
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E E
E RADI ATION SAFETY r
h MANUAL 9a l
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I UNIVERSITY OF DELAWARE g
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I UNIVERSITY OF DELAWARE I
RADIATION SAFETY MANUAL References to AEC in this Manual should be changed to NRC Prepared and Written by:
Jenny M. Johansen, M. S.
Radiation Safety Officer 1
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\\N b'w (
f Approvec! by Racliation Safe b Committee I
Date:
INfc d db ilN I
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Approved for the Univerr/igy Administration by the Associate Provost of Research Date:
/? / '2 l7L/
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I
- I From its first organization as the Conmiittee on Atomic Energy Activities on August 2, 1957, the Radiation Safety Committee has
'I continued to serve the University of Delaware community in solving problems l
i of radiation safety in research.
From the " grass roots" conunittee o f five to its present membership of ten, the committee represents the disciplines of the University engaged in research and development.
In the past, several members have served not only as a member of the faculty but also as the Radiation Safety Officer.
To those members listed below, the Radiation Safety Conmtittee dedicates this Radiation Safety Manual as a token of our appreciation for their services to the I
University and the Radiation Safety Connaittee.
1957 - 1963 Dr. John II. McClendon i
1963 - 1965 Dr. C.
Burleigh Cooper 1965 - 1967 Dr. Conrad N. Trumbore 1967 - 1971 Dr. Richard B.
Murray 1971 - 1973 Dr. Robert L. Salsbury I
1973 - 1974 Dr. Robert Gagne I
Members of the Radiation Safety Comctittee - 1974 I
Dr. Robert L. Salsbury, Agriculture, Chairman Dr. Olaf P. Bergelin, Coordinator of Research Dr. C. Burleigh Coopur, Physics Mrs. Sheila Cushing, Nursing I
Miss Jenny M. Johanten, Radiation Safety Officer, Executive 6ecretary Dr. Bruce C. Lutz, Ilectrical Engineering Mr. M. D. Machnovitz, Safety jl Dr. Jonathan H. Shat p, Marine Studies l5 Dr. G. Fred Somers, Biological Sciences Dr. Conrad N. Trumbore, Chemistry I
1 l
I 1
RADIATION SAFETY MANUAL l
Table of Contents Section Title Page 1.0.
The Radiation Safety Committee 1
E 1.1.
Purpose of Committee 1
1.2.
Organization of Committee 1
1.3.
Responsibilities of Committee 2
1.4.
Appeal of Committee Actions 3
2.0.
The Radiation Safety Of ficer 3
2.1.
Authority of the Officer 3
2.2.
Responsibilities of the Of ficer 3
3.0.
University Regulations Governing the Use of Radioactive 5
Materials 3.1.
Procurement of Radioactive Material 5
I 3.1.1.
Approval of Request for Authorization to Use Radioactive Materials or Radiation Producing Devices 5
3.2.
Responsibilities of Project Supervisor 7
3.3.
Responsibilities of All Users 8
3.4.
Classification of Areas 3.4.1.
Unrestricted Areas 9
3.4.2.
Restricted Areas 9
3.5.
Procedures for Using Radioactive Materials 10 3.5.1.
Unsealed Sources 3.5.2.
Scaled sources 11 3.6 Transfer of Radioactive Materials 13 3.L.1 On-campus Transfers 13 3.6.2.
Off-Campus Transfers 13 3.7.
Disposal of Radioactive Waste 13 l
3.7.1.
General Considerations 13 3.7.2.
Dry Wastes 13 t
I CONTENTS Section Title.
Page 3.7.3 Liquid Waste 14 3.7.4 Gaseous and Airborne Wastes 15 3.7.5.
Biological Wastes 15 3.8.
Pe rsonnel Monito ring 15 3.8.1.
Exte rnal' Monitoring 15 3.8.2.
Internal Personnel Monitoring 17 4.0.
Radiation Emergency Procedures 18 4.1.
Minor Spills 18 4.2.
Major Spills 19 4.3.
Accidents 19 4.4.
Injuries to Personnel 19 4.5.
Ove r-Exposure or Ingestion 20 4.6.
Fires 20 4.7.
Call List for Radiation Emergencies 20 4
Appendix Contents 21 I
I I
I
l<0.
THE RADIATION SAFETY COMMITTEE 1.1.
PURPOSE OF Tile RADIATION SAFETY COMMITTEE The purpose of the Radiation Saf ety Committee of the University of Delaware is the promotion of the best practice in safe handling and use of radioisotopes and radiation producing devices throughout the University campus, reg;ional campuses, affiliated institutions and properties throughout the State of Delaware.
The establishment of a Radiation Safe ty Committee is required by the federal government before an institutional program for the use of radioisotopes in research and development under a broad scope will be licensed.
Federal and state government regulations concerning radioisotopes shall be implemented by the action of the committee in association with individual radioisotope users, department heads and the admini-stration of the University.
Radia t ion, as used herein, includes x-rays, gamma rays, alpha and beta particles, high speed electrons, neutrons, protons, and other nuclear particles; but not sound or radio waves, o r visible, infrared and ultraviolet light.
1.2.
ORGANIZATION OF Till: RADIATION SAFETY COMMITTEE 4
The Radiation Safety Committee shall be appointed by the Provost or the Associate Provost for Research.
Membership shall consist of faculty or professional staff experienced in handling radioisotopes, the use of radiation producing devices, the practice of radiation protection, or those who have a desire to institute practices of safety in regard to radiation.
These members should include the areas of Agriculture, Life and llealth Sciences, Chemistry, Engineering, Marine Studies, Nursing, Physics, Safety and the Radiation Safety Officer.
J The activities of the committee are directed by the chairperson, who is E
appointed by the Provejl or AsSoClate Provost [o r Research upon recommenda-tion of the committee.
The business of the committee is administered through the Radiation Safety Of fice which is directed by the Radiation Safety Of ficer.
The Radiation Safety Of ficer is a full-time professional staf f member f rom the Division of Safety, appointed by the Associate Vice President for Personnel and Employee Relations, upon recommendation of the Radiation Safety Committee on the basis of the person's experience, education, and qualifications in J
the area of radiation safety.
The Radiation Safety Of ficer serves as 3
executive secretary to the Radiation Safety Committee. _
...l
1 I
Meetings of the committee shall be called by the chairman at his discretion, not less than once per quarter (calendar year) or on petition by any member of the committee.
A quorum of the committee to conduct business shall consist of at least three members plus the Radiation Safety Officer.
I The Radiation Safety Officer and the chairman shall conduct the interim business of the committee subject to the approval of the committee at the next scheduled meeting.
1.3.
RESPONSIBILITIES OF THE RADIATION SAFETY COMMITTEE 1.3.1.
Assume the responsibility for the radia tion safety aspects for I
all University programs involving radioisotopes or radiation producing devices.
I 1.3.2.
Review and grant permission for, or disapprove the use of, radio-isotopes in any amount or radiation producing devices within the University from the standpoint of radiation safety.
A simple majority of the committee is required for approval.
1.3.3.
Review and prescribe special conditions, requirements and re-strictions that may be necessary for safe handling or radioisotopes including additional training of personnel and physical examinations (e. g. blood test, urine specimens, e tc. ) be fore commencing worte with radioisotopes, designation of limited areas of use, proper I
disposal methods, and procedures to be followed after spills or other radiation accidents.
The commi.ttee must approve any project involving radioisotopes or radiation producing devices before it can be initiated.
1.3.4.
Serve as the University's sole liaison with the Delaware State Board of llealth and the United States Atomic Energy Commission in matters of registration, licensing, and radiation safety.
1.3.5.
Receive and review periodic and/or urgent reports from the Radiation Safety Of ficer regarding:
a.
Results of area monitoring, b.
Personnel exposures as ueasured by suitable dosimeters.
c.
Accidents in handling, s torage or use of radioisotopes.
d.
Loss or thef t of any amount of radioisotopes.
Records of radioisotope procurement and disposal.
c.
1.3.6 Recommend remedial action if safe procedures are not being observed where ionizing radiation hazards exist or if these procedures are not in compliance with government regulations.
I l I
l
!I l
l 1.3.7.
Pass judgment in advance of construction of new bu tidings or 55 remodeling of existing buildings in which the use of radioisotopes j
or radiation producing devices is contemplatH.
Nritten approval i
is needed f rom the committee of the proposed btilding plans.
l l
1.3.8.
Keep department chairmen and radioisotope users tdvised of current rules and recommendations of various government agencies concerned with radiation safety and the safe use of radioisotopes.
/
i 1.3.9.
Keep a written record of actions taken in approving or disapproving ig the use of radioisotopes and radiation producing devices and other jg t rans ac t io ns, communicati.ons and reports involved in the work of the committee.
j 1.4.
APPEAL OF COMMITTEE ACTIONS Actions taken by the University Radiation Safety Committee may be appealed lI by the s taf f member or department concerned to the Associate Provost of Research, with the prior knowledge of the Department Chairman and Dean of the College.
i 2.0.
THE RADIAT t0N SAFETY OFFICER i
2.1 AUTHORITY OF THE RADIATION SAFETY OFFICER i
ig The Radiation Safety Officer derives his authority from the Vice-I E President for Employee Relations, Office for Safe ty Coordina tion and the Radiation Safety Committee. The Radiation Safety Officer is a j g.
member, m.d the authorized representative, of the Radiation Safety jg Committee regarding measures to implement radiation protection and control within the University.
I The Radiation Safety Officer, or his authorized representative, has the authority to stop all operations with radioisotopes or radiation j
producing devices where a potential hazard or violation exists, jg Resumption of operations may take place only upon authorization
}g from the Radiation Safety Committee.
I i E 2.2.
RESPONSIBILITIES OF TIIE RADIATION SAFETY OFFICER
- E l
The Radiation Safety Of ficer will have the responsibility for ensuring jl adherence to all regulations issued by or subscribed to by the Radiation l
Safe ty Committee and will advise and assis t the Radiation Safety lm Committee with regard to the current applicable regula tions of the l
United States Atomic Energy Commission, the United States Public jg Ilealth Services, state and local agencies, and all similar codes and
- a regulations.
i l
2.2.1.
Implement the organization, administration and management of the l
Radiation Safety Program of the University of Delaware.
i l
i 2.2.2.
Interpret regulations which govern the use of sources of ionizing i
radiation and disseminate information on radiation safety.
I
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ll I
ig 2.2.3.
Develop and keep up-to-date a manual of Radiation Safety regulations jg and procedures for the University of Delaware.
i l
2.2.4.
Supervise all radiation protection programs and develop and maintain these programs.
I 2.2.5.
Coordinate the dosimetry service, maintain personnel exposure jl l
records, and give timely notification of exposures to super-
)W visors as well as individuals exposed.
!lg 2.2.6 Review all requests for procurement of radioisotopes to assure jg compliance with limitations for possession and use.
1 j
2.2.7.
Procure, receive and arrange delivery and shipment of all radioactive materials coming to or leaving the University, i
2.2.8.
Maintain records of procurement and receipt of radioactive Ig ma te r i al s, including non-AEC regulated isotopes and radiation 3
producing devices and machines.
2.2.9.
Supervise the radioactive waste disposal program, l
I l
2.2.10.
Instruct groups of employees on proper procedures for handling radioactive materials.
2.2.11.
Maintain radioisotope disposal records and records of transfer of any radiation producing equipment.
j j
2.2.12.
Conduct periodic radiation surveys and wipe tests in laboratories l
and storage areas; leak tests on significant sources, i
2.2.13.
Conduct alpha scintillation meter surveys when applicable (e. g.
radium storage areas) and provide instrumentation for overseeing the decontamination of alpha-contaminated areas or equipment.
2.2.14.
Conduct surveys on and register all radiation producing equip-1 ment other than those used to calibrate instruments.
2.2.15.
Perform leak tests on scaled sources, i;g 2.2.16.
Maintain running inventory of radioisotopes, sealed sources, g
and radiation producing equipment at the University.
l 2.2.17.
Assume the responsibility for storage of sources and materials not in current use.
l 2.2.18.
Assume the responsibility for calibration of monitoring and surveying equipment.
2.2.19.
Verify and report to appropriate authorities any radiation l
incident which may have resulted in injury to, or contamination I
of, personnel or damage to property.
2.2.20.
Note and take steps in order to correct nuclear and radiation safety problems as well as general laboratory safety problems.
2.2.21.
Perform other duties related or similar to the type described above.
I.
L 3.0.
UNIVERSITY REGULATIONS COVERNING Tile USE OF RADI0 ACTIVE MATERIALS
(
3.1.
PROCUREMENT OF RADIOACTIVE MATERIAL All radioactive materials for all University facilities (incitling Regional Campuses, Research Farms and other of f-campus locatiot.s and properties) shall be procured through the Office of the Radiation Safety Officer.
This includes the so-called " license exempt" radioactive materials.
An instruction sheet and the Radioactive Material Requisition
(
(Form RSO-1) can be obtained f rom the Radiation Safety Of fice.
Examples of this form and sheet are included in Appendix A.
~
3.1.1.
APPROVAL OF REQUEST FOR AUTHORIZATION TO USE RADI0 ACTIVE MAfERIALS OR RADIATION PRODUCING DEVICES Approval of an applicant using the request form (RSO Form APFT)
[
will be granted by the Radiation Safety Committee on the basis of the applicant's experience and training; proposed use, type, and level of material to be used; facility where the material will be used and the personnel involved.
Request fo rms (RSO Fo rm APFT) can be obtained f rom the Radia tion
~
Safety Officer and should be submitted to the Radiation Safety Officer who will circulate requests to the Radiation Safety Committee.
An example of the RSO Form APFT is included in Appendix A.
The procedure for obtaining approval is:
3.1.1.1.
Submit RSO Fo rm APFT.
(This should normally be sub-mitted by the principal investigator who will be the designated License Permit Supe rviso r. )
3.1.1.2.
Upon receipt of RSO Form APFT, the Radiation Safety Officer will review and evaluate the information given.
The information and recommendations of the Radiation Safety Of ficer are then distributed to the committee.
For all approvals whether temporary or permanent, the committee reviews RSO Form APFT using the f ollowing paramete rs :
a.
Authorization of Personnel, RSO Form AFFT, Pages 1, 2, and 6.
[
Both the designated License Permit Supervisor and other personnel on the project (users) are classified into the following categories based on their training and experience:
Class A. - Adequate training and extensive experience; has held or could hold specific NRC license.
[-
Class B. - Adequate training and experience.
Class C. - Adequate training and some experience or some training and adequate experience.
Class D. - Some training or experience.
Class E. - No previous training or experience.
E 1)
License Permit _ Supervisor - is usually a prof essional staff or faculty
[
membe r having rank of instructor or above or the 3 individuals L
deemed qualified by the Radiation Safety Committet.
In order to supervise users of a Class D or E category, a License Permit Supervisor must have a Class A or B rank.
a)
A License Permit Supervisor will generally be required to meet a minimum of the following requirements:
a college
{
degree at bachelor's level (or equivalent) in science or engineerint; and at least 40 clock hours of training and experience in safe handling of radioisotopes, the characteristics
[-
o f ionizing radiation, quant ities and units of radiation dose and L
biological hazards of radiation exposure.
2)
Authorized Users - are the other personnel working on a project or with a device as designated on RSO Form APFT.
They are usually students (t;raduate or undergraduate) or employees (post-doctoral fellows, resea rch technicians, etc.).
They may be working on the
~
p roj ec t of the License Permit Superviso r o r carryint; out independent research ior an academic degree under general supervision of the License Permit Supervisor.
3)
Other Personnel Specifications -
a)
Persons categorized as Class E users can hold that status onl y for one (1) month af ter issuance of a temporary permit under the supervision of a Class A or B License Permit Supervisor.
b)
The License Permit Supervisor (Class A or B) must he present and give direct supervision when a Class E user is handling radioisotopes or radiation devices.
c)
The License Permit Supervisor (Class A or B)shall give I
inst ruction to the Class C user not registered for the formal course during his/her month at that status in safe handling of radioisotopes used, rules and regulations of 10 CFR-19, 10 CFR-20 and the University Radiation Saf ety Manual or I
request Radia tion Saf ety Of fice assiutance in giving instruction.
Also, any other users in categories C and D shall be instructed if specified by Radiation Safety Committee.
I d)
Ce r t i f ica ti on that instruction has been given will be sent to i
the Radiation Safety Officer via the " check-off list" which
,I can be obtained f rom the Radiation Safety Of fice.
The Radiation Safety Officer will verify instruction through examinat10n.
f e)
Upon successful examination the Class E user will be promoted to Class D status allowing the person to handle radioisotopes l
independent of the License Permit Supervisor's presence, but still under the License Permit Supervisor's general direction.
[
f)
Persons successfully completing the formal course on Safe I
Handling of_ Radioisoto_pjes will be promoted to Class B or C users or can be License Permit Supervisors i.f approved by the l
Radiation Safety Committee.
.I
-Sa-lL
The License Permit Supervisor and other personnel (users) are granted authorization by following the preceding parameters and that the designated License Permit Supervisor's knowledge and ability are commensurate with the project to be carried out, hazards involved, agree to follow all University regula-tions governing the use of radioactive materials and radiation producing devices, and, upon request of the committee, submit a history of past occupational and medical exposure or any other special medical requirements (e.g. record of recent
[
complete blood test).
b.
Authorization of Project RSO Form APF1; Pages 3 and 4 Project for which radioisotopes are requested shall be reviewed by the Radiation Safety Officer and the Radiation Safety
~
Committee for feasibility based on the information given on pages 3 and 4 of RSO Form APFT.
c.
Authorization of Facility
[
Radioactive materials are to be used only in those facilities
~
which have been approved by the Radiation Safety Officer and the Radiation Safety Committee.
Due to size of laboratories, benches or portions of benches within laboratories may be designated as radioisotope use areas and nonuse areas. Use areas ruust be properly designated with a Radio-active Material sign or tape around the dimensions of the area.
The g; ranting of the use - nonuse area designation will be based on the laboratory classification.
1)
~
Laboratories will be classified as Type A (lligh Level), Type B (Intermediate Level), Type C (Low Level) and Type D (Very Low Level) according to the type and level of material to be used and the type of usage.
(See Appendix B, Tables 1-3; General Requirements for each type of laboratory are listed in Appendix B, Table 4.)
2)
Monitoring Instruments: Unless specifically exempted by the committee or Radiation Safety Of ficer, each laboratory in which radioactive materials or radiation producing devices are used shall have on hand or readily available in operating condition
~
a properly calibrated survey or monitoring instrument appro-priate to the type and level of ionizing radiation used.
3)
Other Radiation Safety Equipment: The Radiation Safety Committet may require the use of other special equipment or devices that it may determine to be necessary to ensure the safe use of radioisotopes in a given situation.
This includes special shielding, handling tools or tongs, alarms and warning devices, air sampling equipment and other such apparatus.
4)
Radioactive waste containers are required as specified in 3.7.
5) llandling and usage of 50 millicurie amounts of H-3 (organic compounds) and millicurie amounts of I-125 and I-313 (non-contained compounds) shall be confined in a' fume hood having i
a flow rate of at least 100 linear feet per minute.
1
3.1.1.3.
ISSUANCE OF AUTHORIZED PERMIT If there are no objections within ten days by the Radiation Safety
~
Committee Members to the information given on RSO Form APFT and the Radiation Safety Of ficer's recomendations distributed, a temporary permit and number are issued by the Radiation Safety Officer.
This temporary permit has a number which will be used on all radioisotope re qu e s t s.
A pe rmanent permit " Authorization Permit for Use of Radioisotopes and Radiation Producing Devices" (RSO Form LP) is issued af ter review and final approval at,the quarterly or special meeting of the full committee. The temporary number will be changed to a permanent one at that time.
~
3.1.1.4.
AMENDMENT (S) TO AUTHORIZED PERMITS Amendments will be granted on the same basis as original requests for authorization but only the pages of RSO Form APFT concerned with the change need be submitted.
a.
Examples of pages to fill out if change applies to :
1)
New isotopes, same project : Pages 1 - 2
~
2)
Initial isotopes requested, different project: Pages 3 - 4 3)
Change in facility location of usage:
Page 5 4)
Same isotopes, project and f acility, new personnel:
Page 6 3.1.1.5.
RENEWAL OF AUTHORIZATION Authorizations will be granted for >ne (1) year.
One month before the expiration date the permit holder is requested to submit pages 1 and 2 of RSO Forn; APFT and any of the other pages needed if amendments to the original application are involved.
[
3.2. RESPONSIBILITIES OF LICENSE PERMIT SUPERVISOR Those persons who have been issued permits by the Radiation Safety Committee to use radioisotopes are responsible for the safe use of radioisotopes and radiation sources by individuals under their super-vision.
They are also responsible for:
a.
Compliance with University regulations for safe handling of radioactive materials and NRC regulations 10-CFR-19 and 10-CFR-20.
b.
Instruction of students and employees under their supervision in the use of safety devices and procedures (e.g., wearing of film badges, surveying hands and clothing, submit urine or blood samples as re-
[
quired by committee, etc.).
To instruct Class E users during the one month duration as outlined in section 3.1.1.2. 3) a) through f),
and instruct all users in rules and regulations outlined in point a of this section.
r l
c.
Proper planning of an experiment or procedure to ensure that
{
adequate safety precautions are observed.
d.
Communication to the Radiation Safety Officer of all pertinent
~
information regarding changes in their permits.
(e.g., employee, operational and procedures changes, alteration of physical plant, etc.)
Limiting the use of radioisotopes under their permits to authorized e.
users.
f.
Maintaining required records of receipts, use, storage and disposal of radioisotopes.
~
g.
Preparing an inventory of radioisotopes on hand every May.
h.
Maintain security of radioisotopes in use and in storage.
1.
Receive instruction in radiation safety as determined by the Radiation Safety Officer.
~
3.3.
RESPONSIBILITIES OF ALL USERS Each person who has contact with radioisotopes has a responsibility to:
a.
Ref rain from smoking, eating, drinking, food preparing and applying cosme tics in radiolsotope laborato ries.
b.
Survey hands, shoes, body and clothing for radioactivity and remove all contamination before leaving the laboratory.
~
c.
Check work areas periodically for contamination and keep a written reco rd of results.
Periodically means experiments involving use of radioisotopes continuously over a period of time - survey for con-tamination daily.
Experiments involving irregular use of radioisotopes
[
at irregular intervals - survey for contamination on day of initial use and daily while use continues.
[
Written record of results will be inspected by the Radiation Safety Office.
~
d.
Conduct decontamination procedures when necessary, e.
Report immediately to the Radiation Safety Officer the details of spills or other accidents involving radioactivity.
f.
Wear the recommended personnel radiation detectors such as film badges and/or pocket ionization dosimeters and/or thermoluminescent dosimeters (TLD).
g.
Use all recommended protective measures such as protective
[
clothing, respiratory protection, remote pipetting devices, L
vent.ilated and shielded glove boxes and hoods.
L -
a
['
h.
Keep personal exposure to radiation at the lowest possible level specifically below the maximum permissible does (mpd) levels as
[
stated in 10-CFR-20.101.
- i. Maintain good housekeeping practices in the laboratories.
[
- j. Label radiation equipment and segregate radioactive waste and equipment to avoid cross contamination.
k.
Maintain security of radioisotopes in use and in storage.
3.4.
CLASSIFICATION OF AREAS 3.4.1.
UNRESTRICTED AREAS An area is unrestricted and does not require control measures if:
a.
An individual, continually present in the area, cannot receive more than 2 mrem in any one (1) hour, or one hundred (100) mrem in any seven consecutive days, to any portion of the body.
b.
When allowance is made for expected occupancy and time variat;as in dose rate, no individual is likely to receive mo re than 500 mrem it. a calendar year.
{
3.4. 2.
RESTRICTED AREAS All areas within the University in which dose levels do not a.
conform to the standards for unrestricted areas shall be
[
restricted and shall be under control of the Radiation Safety Officer for radiation saf ety purposes.
b.
A caution sign - CAUTION RADIATION AREA - shall be prominently displayed at the entrance to each restricted area and the individual who has been issued a license permit for work
{
with radioisotopes in each such area shall be responsible for controlling access to this area.
3.4.2.1.
POSTING OF AREAS AND OTilER LABELING REQUIREMENIS Signs are required by law to denote areas or containers with icvels of radiation or radioactivity specified in the following
[
sections.
a.
C_AUTION RADIATION AREA - Any area accessible to individuals
{
in which there exists ionizing radiation at such levels that a i
major portion of the body of such individuals could receive an absorbed dose greater than 100 mrem in any five consecutive days.
b.
CAUTION llIGil RADIATION AREA - Any area accessible to individuals in which there exists ionizing radiation at such levels that a major portion of the body could receive an absorbed dose greater I
than 100 mrem in one hour.
Iw
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i'I i
! E c.
CAUTION RADIOACTIVE MATERI ALS - Although federal regulations g
exempt certain containers, rooms, etc., containing radioactive materials less than amounts specified as per 10-CFR-20,203 (c), (f) and 10-CFR-20 Appendix C, for the p urposes of this t
manual, all containers, rooms, refrigerators, etc., containing any radioactive materials should have a Caution Radioactive Materials sign, also indication of isotope and amount when j
necessary, in order that all persons are aware of the j
presence of radioactive materials, d.
Only signs of the design specified in 10-CFR-20 shall be used.
l 3.5.
PROCEDURES FOR USING RADIOACTIVE MATERIALS 3.5.1.
UNSEALED SOURCES 3.5.1.1.
PROTECTIVE RULES FOR PREVENTING PERSONAL CONTAMINATION I
Extreme personal cleanliness and careful techniques are the primary means of preventing contamination and protecting against I
ingestion of radioactive materials.
In order to minimize contamination and prevent entrance of radioactive materials.
into the body,the following rules shall be observed in laboratories where unsealed sourc are used.
a.
Eating, drinking, food preparation, food storage, application of cosmetics and smoking shall not be permitted in laboratories where radioactive materials are stored or used.
b.
Storage of food and beverages is not permitted in the same storage lo ca t io n (refrigerator, etc.) as radioactive materials.
c.
The use of milk bottles or other food containers for handling or storing radioactive materials is forbidden, d.
Pipetting of radioactive solutions by mouth shall not be permitted.
Remote devices are available and shall be used for such applications, e.
No experiments with radioisotopes should be undertaken I
until trial runs, complete in every de tail, are made with nonradioactive materials.
Such runs should be made until the procedure is reproducible, and improvements incorporated as needed, f.
Any work with materials susceptible to atmospheric distribution (e.g. vaporizing, spillage, dusting, effervescence of solution, I
or other releases of radioactive gas) shall be confined in a suitable hood or glove box.
I g.
Personnel shall not be permitted to work with radioisotopes if there are open cuts or abrasions on the body.
Extreme precaution must be taken to avoid cuts or puncture wounds, especially when working with materials of high activity or of a high hazard.
I I
!lI 4
l!E h.
Care must be exercised when using organic solvents to avoid
'5 skin contact with radioactive materiats-(Sotvents may make i
the skin more permeable.) Appropriate gloves should be i
worn for handling radioisotopes.
'I i.
Monitoring of hands, feet and clothing is recommended
,i especially where large amounts of radioactive materials are
- l being used.
Protective garments should be left in the lab-E oratory when work is completed or until monitored and found i
free of contamination.
l 3
j 3.5.1.2.
PPs0TECTIVE RULES FOR CONTROLLING CONTA'11 NATION OF LABORATORY FACILITIES AND EQUIP > LENT ll a.
Auxiliary containers, blotters, and covers shall always be
]=
used where danger of spills and contamination of the person or equipment is possibic, b.
Contaminated equipment, or equipment that has been used and j
is suspected of contamination, shall be isolated in designated areas in the laboratory or in suitable storage spaces.
c.
Tools, equipment and apparatus uhen used in handling radioactive material, should be placed in non-porous metal trays or pans
- I which are lined with absorbent disposable paper. This paper should be monitored and changed frequently.
lI d.
Care should be taken that equipment, not immediately necessary to the operations being performed, is not brought into the working area, c.
Equipment and tools shall be routinely monitored following their use.
No equipment shall be returned to stock unless It is known to be comple tely free of contamination inside and out.
f.
Contamination shall not be allowed to remain on working
,I surfaces or floor unless appropriately shielded. (For purposes of this rule contami. nation is taken to mean amounts of beta-gamma activity greater than 100 dpm or alpha activity greater than 20 dpm as determined by standard I
2 smear test on a surface of 100 cm,)
l 3.5.2.
SEALED SOURCES
)
3.5.2.1.
DEFINITION
'g A scaled source is one in which radioactive material is g
permanently encapsulated (in stainless steel, plastic, glass, lacquer or other material) to prevent leakage, and in which the intent is to utilize the radiation emitted rather than the material itself.
l 3.5.2.2.
IlANDLING PRECAUTIONS a.
Scaled sources should not be handled directly with the hands.
The use of remote handling tools for sources of high activity is essential to minimize both whole body and I
hand exposure..
i i
l b.
Users of scaled sources should monitor themselves routinely I
during periods of work with the sources to assure that j
source rupture or leakage has not occurred.
I c.
Under no circumstances should a user attempt to repair a ruptured or leaking source.
,g d.
In case of devices containing sealed sources, users may use
!3 the device only as recommended by the manufacturer.
Sources may not be removed f rom such devices except in those cases a
where the devices are specifically designed for usage of the source outside of the device.
ll e.
Repair of devices containing radioactive sources is normally l
not permitted when such repair involves those parts of the l5 device containing the source.
The Radiation Safety Of ficer j
should be consulted to determine the conditions under which lg minor repairs or corrections may be authorized.
!g i
3.5.2.3.
LEAK TESTING Unless otherwise exempted by A.E.C.
regulations because of low activity, periodic leak tests are required on all sealed l
sources.
a.
Such tests will be carried out at intervals not to exceed six months (preferably every three months), except in cases where the A.E.C. has specified otherwise, i
i b.
Such leak tests,as are required, will be performed by the Radiation Safety Officer or his authorized representative.
jl Users are required to make their sealed sources available
}W for such tests at the necessary intervals.
i
!E c.
hhenever eak tests reveal the presence of 0.005 microcuries i5 or more of removabic contamination on a sealed source, the source must be immediately removed from further use and steps must be taken to prevent and control the spread of contamination.
l d.
Leaking sources mus t ei ther be disposed of as radioactive waste or returned to the nanufacturer for repairs, i
1 3.5.2.4.
CAUTION SIGNS, LABELS AND TAGS FOR SEALED SOURCES i
{
a.
Any scaled source containing by-product material (as defined by A.E.C.) which is used outside o f its shielded container shall be labeled with an attached tag not less than one square inch in size bearing the radiation symbol and words
" Caution Radioactive Material -- Do Not llandle -- Notify Civil Authorities if Found."
Colors shall be magenta and yellow.
I b.
Sealed sources mounted in devices or shields shall be tagged on the device or shield with Caution Radioactive Material.
Also the nuclide and date of assay shall be included.
Colors shall be magenta and yellow.
I 12-t w
7_ _ _ __
i t
3.6.
TRANSFER OF RADICACTIVE MATERIALS I
3.6.1.
ON-CAMPUS TRANSFERS 3.6.1.1.
Radioactive materials shall not be transferred from one department or laboratory to another without approval by the Radiation Safety Officer, since approval for the use of the materials is given only for the original working area.
3.6.1.2.
All trans fers between laboratories, or from storage areas to 4
working areas, shall be done in such a manner as to minimize l
the probability of spillage or breakage.
Double containers should be used, including suitabic shielding, for such transfers.
3.6.2.
OFF-CAMPUS TRANSFERS i
3.4.2.1.
Radioactive material shall not be shipped or transferred to or g
iE fr m the Univeraity wi.thout approval of the Radiation Safety Officer.
Approved shipments mus t be packaged and labeled in accordance with D.O.T.
regulations, the A.E.C.
regulations or j
the U.S. postal regulations, whichever is applicable.
j 3.7.
DISPOSAL OF RADIDACTIVE WASTE 3.7.1.
GENERAL CONSIDERATIONS l
i 3.7.1.1.
Except as specifically authorized by the Radiation Safety Committee, l
no rad ioac t ive materin!s ahall be disposed of directly into the l
sanitary sewage s) 4 t.m, into the atmosphere, or into cold trash ll baskets (non-radioactive waste).
All radioactive wastes must
?
i be collected by the user in suitable contai.ners for processing j
'W and disposal by the Radiation Safety Of ficer, j
- g 3.7.l.2.
Any accidental releases of activity into the environment must
!g be reported immediately to the Radiation Safety Of ficer.
3.7.1.3.
When unusual problems o f disposal arise, the Radiation Safety Officer must be consulted to eatablish a satisfactory procedure.
4 j
3.7.1.4.
The Rad iation saf e ty Of ficer '7i11 collect all dry and liquid radicactive taste periodically.
3.7.1.5.
All types of waste should be separated by half-life, short lI (less than 30 days ), and long (more than 30 days).
3.7.2.
DRY WASTE 3.7.2.1.
CONTAINERS 1
1 Waste contai.ners for disposal of dry contaminated was tes are to il be available in aLi 1aboratories usine unsealed radioisotopes.
,5 Normally these should be a matai vaste container with a step-pedal operated tid and p1astic bag liner.
Waste cans should be conspicuously labeled with a caution Radioactive Materials sign.
I iI 3.7.2.2.
SEGREGATION BY llALF-LIFE Dry waste, contaminated with short-lived radioactivity (half-life is less than 30 days) should be cellected in a separate container f rom dry waste contaminated with long half-life I
(greater than 30 days) material.
Normally the chort-lived material will be held for 10 half-life I
periods and the- 'isposed of, according to procedures of the Radiation Safet, 2ficer, as non-radioactive was te.
3.7.2.3.
LABELING OF WASTE FOR PICK-UP BY RADIATION SAFETY OFFICER All dry radioactive waste for pick-up by the Radiation Safety Officer shall be sealed and properly labeled with a standard I
radioactivity caution label and should bear the following additional information:
a.
User's nane, department and account code number b.
Isotope (s) c.
Approximate criantity of activity J.'
d.
Date I
3.7.3.
LIQUID WASTE 3.7.3.1.
CONTAINERS Containers for liquid waste should be 5 gation plastic carboys or 30 gal.lon liquid ' rums, filled with solid pak, of the type I
provided by Teledyne/ Isotopes.
3.7.3.2.
LABELING OF WASTE FOR PICK-UP BY THE RADIATION SAFETY OFFICER All liquid containers shall be properly labeled with a Caution Radioactive Material sign.
In addi. tion, liquid waste containers shall bear the following additional information:
a.
Users' names, department, and account code number b.
Iso tope (s )
c.
Approxin ate quantity of activity d.
Date lg e.
Principle solvents or reagents in container (e.g. water, acid, g
etc.) inc ludi ng anyrox ima te pII.
3.7.3.3.
STRONG ACIDS, BASES, OR OTHER SOLVENTS I
Unless special arrangements are made with the Radiation Safety Officer, the user is required to neutralize or otherwise dilute strongly acid or basic waste solutions to the point that they I
!.I
l I
!E can be reasonabix m1xed in s011difying or absorbing agents j g without causi.ng violent chemical reactions or releasing strong j
fumes and vapors or volatilization of the isotope to gaseous state.
fl In case of organic solvents, especially those which may be highly
- E volatile or otherwise reactive, appropriate precautions must be l
noted on the waste containers.
3.7.4.
CASEOUJ AND AIRBORNE WASTES In cases where the release of votatile radioactive products or
]
radioactive aerosols are anticipated, means should be provided to j
trap such materials (either by chemical or physica1 methods).
The j
tesulting product may then be handled as a liquid or dry waste which ever is appropriate.
j 3.7.5.
BIOLOGICAL WASTES The Radiation Safety Officer should be contacted regarding all i
problems that may arise in dispocal of biological wastes containing l
radioisotopes.
3.8.
PERSONNEL MONITORING 3.8.1.
EXTERNAL MONITORING 3.8.1.1.
A.E.C. REQUIREMENTS Any person working with radioactive material under the University's A.E.C. license is required to wear a personnel desime ter whenever entering a restricted radioisotope area where he may be likely to j
receive a dose in any calendar quarter in excess of 25 percent j
of the values s tated in 10-CFR-20.101, t
Maximum Permissible Dose in Rems / calendar quarter CFR-20.101 Whole body, head & trunk active blood-forming organs lens of eyes or gonado 1.25 Rem Hands, forearms, feet & ankles 18.75 Rem j
Skin of whole body 7.5 Rem
!E
- 3. 8.1. 2.
UNIVERSITY REQUIREMENTS
.l lg In addition to the A.E.C. requirements personnel dosimeters jg required for University personnel for all the fo110 wing are j
situations except as specified in part 3.
!l5 1
a.
When worki.ng with beta emitters of an energy exceeding 0.25 MeV (i. e. excluding 3 14 35S and 43 H,
C, Ca unless specified j
by the Radiation Safety Office.)
b.
When working with x-ray and gamma emitters of any energy.
)
c.
When working ei th neutron sources of any type.
1
] -
w w-r
I d.
When working with x-ray producing devices, c.
When working with accelerators or devices used for accelerating chargol particles.
3.8.1.3.
EXEMPTIONS FROM PERSONNEL MONITORING I
Personnel dosimeters may not be required in cases where it has been definitely established by the Radiation Safety Office that external exposure will not exceed the specified limits.
Exemptions I
will depend on the intensity and energy of the radiation and working conditions involved.
3.8.1.4 DOSIMETER INFORMATION a.
The Radiation Safety Of fice issues film badges to individuals who require them.
Individuals must fill out a Request for Personnel Dosimeter form which is available in the Radia tion Safety Of fice.
I b.
The badge, when required, must be worn at all times when the individual is occupationally exposed.
It should be worn in a fashion so as to indicate whole body exposure (breast pocket, collar, or belt) except in the case of ring, wrist I
or ankle badges, c.
Badges are issued once per month in the case of beta-gamma badg;es and twice per month in the case o f neutron badges, d.
The badge is not to be worn when the individual is under-going diagnostic or therapeutic radiation exposure.
e.
When not in use the badge should be stored in a location away f rom radiation (above background), excessive heat or
- moisture, f.
Badges that are not returned to the Radiation Safety Office I
by noon of the second working day after the badge change date shall be considered 1 ATE.
The individual will be charged a late fee of $2.00 for a late badge.
Badges that are not returned to the Radiation Safety Office within two weeks I
after the film badge change date will be considered LOST.
The individual will be charged $4.00 for each lost or damaged film badge.
g.
If the film badge is lost or damaged, the maximum legal exposure must be entered on the individual's radiation exposure I
record unless the individual's Report of Missing Dosimeter shows evidence of no possible exposure.
Therefore, it will be to the individual's advantage to return " lost badges" that have been found so that his exposure may be determined.
3.8.1.5.
RECORDS AND REPOTIS I
a.
Permanent records of film badge exposures are maintained by the Radiation Safety Office.
Copies of these reports are.
distributed monthly, by department, to all departments having monitored individuals, b.
In cases where individual monthly doses exceed 100 millirem, the Rad.fation Safety Office will notify the individual
(
through a written Radiation Exposure Report.
The individual shall fill out the information requested on the report and return it to the Radiation Safety Office so that recommenda-tions can be made to prevent recurrence of exposure.
c.
The Radiation Safety Of fice will provide an individual, upon written request, a copy of his permanent occupational exposure
[
his to ry.
Records of exposure will be forwarded to new employers upon written request of the individual.
(
3.8.2.
INTERNAL MONITORING OF PERSONNEL 3.8.2.1.
ROUTINE URINE ANALYSIS License Permit Supervisors and users qualified to handle and use in an experiment millicuric amounts of H-3 (organic compounds), Iodine-125 and Iodine-131 in noncontained form, alpha emitters or such other f
materials that the committee may specify are subject to routine urine analysis in accordance with the following parameters:
Each person so qualified shall submit a urine sample to the a.
Radiation Safety Of ficer who will assay the sample. Also, each person shall upon the Radiation Safety Committee's request
[-
submit a recent record of a complete blood count and any other medical history necessary including a physical examination. Any previous radiation exposure history must be filed with the Radiation Safety Of ficer.
b.
Any person handling and using in an experiment 50 millicuries of H-3 (organic compounds) or 10 millicuries of Iodine-125 and/or
{
Iodine-131 (noncontained forms) shall notify the Radiation Safety Of ficer at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in advance of such usage and submit a urine sampic f or bioassay. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after handling and
[
using in an experiment 50 millicuries of H-3 (organic compounds),
the person shall again submit a urine sample to the Radiation Saf ety Of ficer for bicassay.
Such conditions shall apply for Iodine-125 and Iodine-131 (noncontained forms) except that a
(
urine sample will be required after handling and using in an experiment 10 millicuries within 24 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
j
{
c.
Personnel who will be handling and using in an experiment microcurie amounts which are drawn from stock supplies containing 50 m1111 curies of H-3 (organic compounds) and 10 mil 11 curies of 1-125 or I-131 (noncontained forms) on a continuous basis, shall supply a weekly urine sample to the Radiation Safety Of fice for bloassay.
L d.
Personnel using microcuric amounts of H-3 (organic compound) and I-125 and Iodine 131 (noncontained forms) will be requested to submit a urine sample for bioassay before starting and again upon
{
termination of the research project.
' ]
[
E.
Personnel using any other materials the conmiittee may specify shall have routine urine analysis at time in te rvals designated by the Radiation Safety Officer or when gross
[-
contamination levels in the laboratory they work in show incidence of improper handling.
[
3.8.2.2.
SPECIAL URINE ANALYSIS Individuals who are known or suspected to have accidentally swallowed, inhaled, absorbed, or otherwise ingested radioactive materials will be required to submit urine specimens to the Radiation Safety Of ficer for analysis.
The number and frequency of such samples will be established by the Radiation Safety Officer based on type and level of material and condition of intake.
3.8.2.3.
ANALYSIS OF OTHER EXCRETA
[
Depending on the particular radionuclude, its chemical and physical form and the mode of intake, the Radiation Safety Office is authorized to require the submission of other excreta (such as fecal samples, nose wipes, or breath samples) in addition to or in lieu of urine samples.
[
3.8.2.4.
WHOLE BODY COUNTING w
In the case of real or suspected intake of gamma emitting nuclides, whole body counting may be required in addition to or in lieu of
{
excreta samples.
The Radiation Safety Of ficer will arrange such p ro ce d u re s.
[
[e
[
[
[
r L
-17a-
- 4. r-RADI ATION EMERGEtiCY PROCEDURES l
jg Emergencies resulting from accidents in isotope laboratories may jg range from minor spills of radioactivity, involving relatively no j
personal hazard to major radiation incidents and spills, involving i
extreme hazards and possible bodily injury.
Because of the numerous jl complicating factors which may arise and because of the wide range
{
ju and variety of hazards, set rules of emergency procedure cannot be j
made to cover all possibic situations.
In any emergency, however, the primary concern must always be the protection of personnel from radiation hazards.
The secondary concern is the confinement of the contamination to the local area j
of the accident if possible.
i The following procedures are regarded as recommendations except those with asterisks (*) which are required.
j REMEMBER ALWAYS TO STATE:
TYPE OF RADIATION EMERGENCY jg YOUR NAME tg WHERE EMERGENCY ASSISTANCE IS NEEDED l
l UHEN CALLING THE RADIATION SAFETY OFFICER OR SECURITY,IF RADIATION 1
SAFETY OFFICER CAN NOT BE REACHED.
I 4.1.
MINOR SPILLS IN UNPROTECTED AREAS INVOLVING NO RADIATION HAZARD 1
TO PERSONNEL (IN ANY AMOUNT)
!I
- a.
Notify all other persons in the area immediately.
1 ll5 b.
Permit only the minimum number of persons necessary to deal with the spill into the area, i
c.
Confine the spill immediately.
I
i i
i
- d.
Notify the RADIATION SAFETY OFFICER as soon as possible.(2) t
!g
- e.
Permit no one to resume work in the area until approval of the
!E RADIATION SAFETY OFFICER is secured.
I i!g i 5 l
(1) Water may be used except when chemical reaction with water would j
generate an air contamiaant.
Oil should then be used.
(2) The RADIATION SAFETY OFFICER (or an assistant) may be reached directly
{g by using the emergency call list posted in each radioisotope laboratory.
'g Or, call the Campus Security Office number directly and they will j
locate assistance.
l5 I 2
l I
4.2.
MAJOR SPILLS - INVOLVING RADIATION IlAZARDS TO PERSONNEL
- a.
Notify all other persons in area immediately of hazard.
- b.
Request all persons not involved in the spill to vacate the room at once and notify the PADIATION SAFETY OFFICER immediately giving details of spill.(2)
I c.
Make no inanediate attempt to clean up the spill. (3)
I d.
If spill is on skin, flush thoroughly with water.
If the spill is on clothing, discard outer clothing at once.
e.
Switch off all fans.
f.
Vacate the room and prohibit entrance to contaminated area.
I
- g.
Permit no person to work in area until the approval of the RADIATION SAFETY OFFICER is secured.
I h.
Under no circumstances should an untrained person attempt to examine or clean up the radioactive material.
4.3.
ACCIDENTS - INVOLVING RADI0 ACTIVE DUSTS, MIST, FUMES, ORGANIC VAPORS I
AND GASES
- a.
Notify all other persons to vacate the room immediately, b.
Hold breath and close all windows and escape valves.
Switch off air circulating devices if time permits.
c.
Vacate the room.
- d.
Notify the RADIATION SAFETY OFFICER at once. (2) e.
Ascertain that all doors giving access to the room are closed and locked.
If necessary, post guards to prevent accidental opening of doors.
- f.
Do not reenter the room until approval of the RADIATION SAFETY OFFICER is secured.
4.4.
INJURIES TO PERSONNEL - INVOLVING RADIATION HAZARD I
a.
Wash minor wounds immediately (within 15 minutes if possible) under running water while spreading edges of gash.(Note. light tourniquet action to s top venous return btt not to restrict arterial _ flow may be desirable to stimulate bleeding.)
b.
Notify the RADIATION SAFETY OFFICER or Security for Special Medical Assistance.
(2) The RADIATION SAFETY OFFICER (or an assistant) may be reached directly I
by using the emergency call list posted in each radioisotope laboratory.
Or, call the Campus Security Office number directly and they will locate assistance.
(3)
If spill is liquid and hands are protected, right the container. -
I I
c.
Pe rm i. t-no person involved in a radia tion injury to return to work without approval of the RADIATION SAFETY OFFICER.
4.5.
OVER. EXPOSURE OR INGESTION
- a.
Any person who suspects over-exposure to radiation from any source must report inunedi ately, by phone or in person, to the I
RADIATION SAFETY OFFICER.
(Any exposure in excess or 1.25 Rem whole body delivered in a period of 13 weeks or less is regarded as an over_ exposure for purposes of these regulations. )
- b.
Any person who swallows, injects, absorbs, or otherwise ingests i
radioactive materials (excluding normal environmental contaminants and excluding medical diagnosis or therapy) must report the intake immediately to the RADIATION SAFETY OFFICER or Security.
4.6.
FIRES - INVOLVING RADIOACTIVITY I
- a.
Pull fire alarm.
b.
Attempt to put out small fires if radiation hazard is not immediately I
present.
- c.
Notify the Security Department.
- d.
Notify the RADI ATION SAFETY OFFICER.
I Govern fire fighting or other emergency activities by restrictions e.
of the RADIATION SAFETY OFFICER.
4.7.
CALL LIST FOR RADIATION EMERGENCIES The following not ice is posted in each area where radioactive materials or radiation devices are used or stored.
I I
In case of accidents, spills, loss, theft or fire involving radio.
active material, call the RADIATION SAFETY OFFICER FIRST.
IF NO ANSWER, CALL SECURITY AND TIIEY WILL FIND ASSISTANCE FOR YOU.
ALWAYS STATE:
TYPE OF RADIATION EMERGENCY YOUR NAME WilERE RADIATION EMERGENCY HAPPENED 1.
Jenny M.
6hansen Extension - 8475 110me - 737 4874 Radiation Safety Officer 2.
Security Extension - 2222 I
I
-20 I
II ilI 1
4 l
APPENDIX A j
FORMS FOR RADIOISOTOPE WOIE -
i RSO Form APFT:
" Request for Authorization to Use Radioactive Materials or Radiation Producing Devices" i
f
" Project Proposal for Use of Radioactive Materials"
" Facility Approval"
" Statement of Training and Experience" RSO Form LP:
- I
" Authorization Permit for Use of Radioisotopes and Radiation Producing Devices" i
j l
Form RSO-1:
" Radioactive Material Requisition" Personnel Forms :
4 Request for Personnel Dosimeter Radiation Exposure Report l
Report of Missing Dosimeter I
1 Exposure IIis tory Reques t l
Exposure !!istory Release Instruction Check-off List Form RSO-2:
'I
" Radiation Exposure Record" I
I I l
IUNJVERSITYOFDELAWARE RADIATION SAFETY OFFICE RSO Form - APFT I
REQUEST FOR AUT110RIZATION TO USE RADIDACTIVE MATERI ALS OR RADIATION PRODUCING DEVICES
-FOR USE BY RADIATION SAFETY COMMITTEE-1 Approved b Not Approved b Date User Classification License Permit No.
Temporary License Permit No.
Renewal C New Amendment Remarks 1
Signed for Radiation Safety Committee and Date E
1.
Name of Applicant (Please Type or Print Clearly)
I2.
Social Security Number 3.
Department 3a. Previous Permit or License #
4.
Radioactive Materials for which approval is requested: (Indicate radioisotope (s), chemical, or physical form (s), Maximum Activity desired; or specify device. )
I I
I 5.
Type of Use:
1 I
New Project I
I Previously approved Project Fill out project proposal and attach any significant literature for new projects or change in previously approved project.
6 Facility to be used:
I I
Facility approval requested I
I Previously approved facility I
. Building Room Attach Facility Approval for all new facilities or changes in previously approved facilities.
7.
Participating personnel indicate s tatus (staf f or student) - User Classification.*
1.
2.
3.
4.
5.
I Fill out page 6 for each participating person.
- 1f Primary application; this does not apply. If renewal, insert User Classification.
RSO Form - APFT I 4
8.
Statement of Request and Agreement:
The applicait named and participating personnel hereby request authorization to work with radioisotopes and/or radiation devices as specified herein and set forth in I
associated supportive documents which may be attached.
These individuals by virtue or their signatures below, signify that they have read and are willing to abide by the University regulations governing the use of radioisotopes and other sources of ionizing radiation. The undersigned agree to comply strictly with the rules and I
regulations and hereby agree to notify the Radiation Safety Office two weeks before any termination (sabbatical leave, etc.) of personnel in order that l
radioactive materials may be disposed of, transferred, or stored and that working areas may be surveyed.
Date Signed Date Signed 1
Date Signed Date Signed Date Signed Date Signed I
I I
.I I
I l
- RSO l'o rm - APFT I
PROJECT PROPOSAL FOR USE OF RADIDACTIVE MATERI ALS Date:
~
Ne, Project Renewal e
Amendment 1.
Applicant Department Phone 2.
Nuclide (a) a.
b.
3.
Chemical / physical form (s) a, b.
c.
d.
c.
c._
d.
e.
I4.
Position o f label where applicablo a, b,
c.
d.
e.
Amount por experiment 5b. Amount per shipment 5c. Amount on Hand at any one time
- ISa, (millicuries)
(millicuries)
(Millicuries)
I Det11ne 6
the purpose and me thod o f your projec t.
(Give sufficient detail concerning the problem and methods of use of the radioactive material to provide a basis for an evaluation I'
of health hazards and contamination potential.)
State frequency of contamination checks which you will recoru.
I I7.
Identify all procedures (e.g. purification procedure, synthesis plant studies, etc.) which may cause particular problems and evaluate any radiation hazard f rom (a) the quantity o f radioactivity in starting materal, (b) the volatile, liquid and solid wastes, and (c) other contaminated iteras.
I
. 8.
Note the ins trumentation or rtethods used to ascertain the radiation level present due to item a,b, and c in question 7.
(List acke, model, and range for radiation raonitors. )
I 9.
Indicate storage conditions for the material, including location and type of contamination.
(Specify design thickness and type of shielding material which will be used when applicable)
Y
I
-4 Indicate storage conditions for the material, including location and type of possible contamination. (Specify design thickness and type of shielding material which will be i
used when applicable)
I Specify the precautions and procedures that will be taken during your possession of the nuclide to:
I (a)
Prevent unauthorized removal of radioactive material.
I (b)
Prevent contamination and excessive levels of radiation in work or adjacent areas.
I
- If nuclide is to be used in plants or animals please answer item 11 thru 16 inclusive, Plant or animal to be used:
- 12. Avg. weight of animals:
l
- 3. Number of plants or animals to be used:
- 14. Amount of isotope per plant or animal:
]
Route of administration:
I.Doyouanticipatethatradioactivitywillbecontainedintheexhaledair?
Yes No;
{
Urine?
Yes No; Feces?
Yes No; Carcass?
Yes No; Roots?
Yes No; Le aves?
Yes No; Stem?
Yes No.
1
'<If any of the above answered yes, please describe in detail the procedures and methods you
{
will employ to control and/or prevent the spread of contamination.
1 I
I I
Iapproval Recommended:
Date:
University Radiation Safety Officer l'iproved:
Chairman, Radiation Saf ety Committee
l RSO Porm - APFT FACILITY APPROVAL I
1.
Department 2.Buikding 3.
Room 4.
Sketch of Facility:
I 5.
Type of flooring:
6.
Walls and ceiling: (Paint or coating) 7.
Bench top material:
8.
Hood (s) Single ducted?
Yes No: Flow rate sash linear ft/mir 9.
Number of persons normally working in area:
1 10.
Education level of persons in area under-grad /
grad /
technician /
postdoct/
or faculty?
Are other personnel approved radioisotope workers ?
Yes No.
Is this area also used for study / office area for research personnel?
11.
Monitoring device in facility:
Yes No.
(If yes and haven't listed device in project proposal list make, model, type, range.)
I I
12.
Special handling facilities (shielding, glove boxes, etc.)
13.
Staff member in charge of laboratory:
L4.
Individual submitting this request:
Date I
1I Approved:
Date:
Radiation Safety Officer l
l
l
- RSO Form - APFT STATEMENT OF TRAINING AND EXPERIEtICE 1.
Name
- 2. Social Security No.
3.
Type oj Training (Circle Yes or No in Columns I and II.
If "Yes" is indicated in either column, complete items III and IV)
TYPE
{ggg ON THE JOB WHERE TRAINED DURgION TRAINING (A)
Principles and Practices l Circ le On_c]
l Circle Onel of Radiation Protection Yes No Yes No i
(B) Radioactivity Measurement l Circle Uncl
);ircle Onel
+
monitoring techniques, and instruments.
Yes No Yes No (C) Mathematics and calculations
=
Nircle Onel (Ci rc l_e Uncl basic to the use and meas-urement or radioactivity.
Yes No Yes No (D) Biological effects of fjircle Onej
[ Circle _ons radiation.
Yes No Yes No i
4.
Formal Courses (If "Yes" circled in column 1 for any of items above, complete this item, listing all courses pertaining to use of radiation or radioactive materials, atomic and nuclear structurc-radiochemistry, radiation biology, nuclear engineering, etc.)
i =
litle of Course Where Trafned Course Content (A)
(B) s (C)
(D)
.I i
5.
Experience (List actual use of radioactive mater 1. is, de tails o f formal laboratory courses or on the job training.)
4 Isotope Max imum knount Where experience Duration Type of use 6
Was film badging required in experience situations?
Yes No 7.
Additional Comments or Remarks:
I
UNIVERSITY OF DELAWARE AUTil0RIZATION PERMIT FOR USE OF RADIOISOTOPES AND RADIATION PRODUCING DEVICES License Permit Number:
Licensee:
Date issued:
Expiration Date:
NOTE:
License Permit number must be shown on all radioisotope orders in space provided for License Number.
I In accordance with statements and representations made in your Request for Author-ization to use Radioactive Materials or Radiation Producing Devices, dated approval is hereby granted authorizing the below named individuals to order, possess and the materials or items designated below in accordance with University regulations and use such other conditions as are herein specified.
1.
AUT110RIZED USERS:
J l
Name l
Donartmont l
Status l
2.
LOCATION (S) 0F USE:
Butidinn l
Room l
Comments
,I l
I 3,
AUTHORT7.ED RADIOTSOTOPES OR TTFMS:
Maximum Acitvity Limits l
Nuclido or T tem Per Experirnen t l
Per Order l
Possession (Storage) l 4.
AUTHORIZED USE
,l 5.
C0tIDITIOllS :
4 i
Laboratory Monitors:
Film Badges:
)
Other Dosimeters:
Caution Signs:
,l l5 Waste Containers:
l Personnel Restrictions:
l I
i Special Precautions or Requirements:
i I
I Approved:
Date:
Chairman, Radiation Safety Committee I
I I
I I
I
'I
{
~
i
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l Tills FORM USED FOR ONI,V l'()lf R FORMS OF SAME NUCl.lDE C0utf0I RADIOACTIVE MATERIAL REQUISITION University of Delaware N "-
Note: Complete a separate requisition for each different Nuclide; retain top sheet and forward Fonn RSO l remaining form to Radiation Safety Officer at 417 Academy Street.
Department User Phone
~
g Project, Account or Grant Number I.icensee License Number
{
Quantity (mci)
Catalog No.
Nuclide and Form Specific Act.
Est. Price 1.
1.
1.
1.
1.
2.
2.
2.
2.
2.
W 3.
3.
3.
3.
3.
l 4, 4.
4.
4.
4.
To tal 1 endor Suggested Dates Desired l Remarks I
l Requested by lluilding Date of this Request Approved by (Department head or authorized agent)
Date I
Do not write below this line-Approved by R.S.O.
Date Comments 1
(To be completed when order received)
P.O. Number Date Received User Notified
[] A.M.
[] P.M.
l Assay Information llealth Physics Survey Billing IQuantity (mci) l l
Exposure Rate. unshielded l
i Cost of Nuclides C
l l
h onc. (mci /ml) i Vendor llandling l
Exposure Rate. shielded IVol. or Wt.
f reight, postage, etc.
f
. Act.
Sp i
i l
Other charges Time of Assay Surface Contamination ITotal Solids l
alpha:
i Normality l
f
{
f betamamma:
Total Purity f
l l
Other precautions Date Billed Lot No.
l l
l i.
Billing Prepared by:
i Ser. No. (scaled source) {
f f
{
l l
l l
J urnal Voucher No.
l Other I
I 1
I i
WReceived By:
Date
I UNIVERSITY OF DELAWARE RADIATION SAFETY OFFICE REQUEST FOR PERSONNEL DOSIMETER Badge No.
I All of the information requested below is required by the Atomic Energy Commission.
If this requisition is not complete, it will be returned.
No badge will be issued without a completed requisition.
g
- 1. Name
- 2. Maiden Name 4
' g Last, First, Middle (Please Print)
- 3. Sex
- 4. Social Security No.
- 5. Birthday I
- 6. University Location Department Building Course Work Employee I
f Faculty, Staff, Student
- 8. Will you be working with x-rays; radioisotopes; other?
If other circle one:
accelerator ;
reactor ;
gamma irradiator ;
neutron source?
I
~
- 9. Have you previously been associated through employment or course work with an employer or University etc. where you ware required to wear a dosimeter (film I
badge, TLD, pocket ionization chamber,etc.).
Do not include any diagnostic
)
or therapeutic radiation exposure.
List most recent ettployer first.
Employer & Address Started Terminated I
^-
c.
i D.
I Signature of Requester Signature of Radiation Safety Officer
I UNIVERSITY OF DELAWARE RADIATION SAFETY OFFICE I
RADIATION EXPOSURE REPORT I
Date It has been reported by the personnel dosimetry service that the dosimeter worn by
, dosimeter number for has received a total dose of millirems.
The dosimetry service additionally reported I
- 1) Reason for exposure - check appropriate reason (s):
Exposure due to x-rays or radioisotopes.
I I
Adequate protection devices not available.
I I
I Failure to use protection devices.
Q Badge exposed while it was not being worn.
l!
Badge partially destroyed by heat, water, light, or time.
None of the above, explain below.
Unknown.
2)
Explain all reasons checked in Item 1.
I I
I Recommendation of Radiation Safety Officer to prevent recurrence of exposure; I
I Signature of Employee Signature of Radiation Safety Officer I
i l
I UNIVERSITY OF DEIAWARE FADIATION SAFETY OFFICE I
I REPORT OF MISSING DOSIMETER I
Date Name Badge #
Date of Missing Badge I
The dosime ter described above has not been re turned to the Radiation Safety Office.
In order to keep adequate radiation exposure records as required by the Atomic Energy Commission and the State of Delaware, the badge must be returned to the Radiation Safety Office.
If the dosimeter is available, return it with this form to the Radiation Safety Office.
If the dosimeter is not available, answer the following questions and return this form irmuediately to the Radiation Safety Office.
I
- 1) Reason dosimeter was not returned.
I l
- 2) Type of radiation to which you were exposed during the month in question.
If 5
you were working with radionuclides, please list them.
I
- 3) Vacations during the month in question.
Give dates.
- 4) Any unusual known radiation exposure during the month in question.
I I
Signature of Dosimeter Wearer ACTIONS OF THE RADIATION SAFETY OFFICE I
I Date Signature of Radiation Safety Officer.
. ~.
I UNIVERSITY OF DELAWARE NEWARK. DELAWARE 19711 I
O FFICE FO R S A F E T Y COO RDIN A TION 417 A C A D E M Y STREET PHONE: 302.738 8475 I
Radiation Safety Officer I
Dear Sir:
I
, Social Security Number birth date
, has indicated that he/she was associated with your institution in a capacity which required radiation monitoring.
This association existed from to We would appreciate receiving a summary of those occupational exposures to add to our records.
Thank you.
I I
Jenny M. Johansen, M.S.
Ilealth Physicist iI Radiation Safety Officer University of Delaware STATEMENT Under the provisions of 10 CFR 20.404, I authorize the release of and request that all my radiation exposure records be furnished to the Radiation Safety Office.
I Signature Date 1
I UNIVERSITY OF DELAWARE NEWARK, DELAWARE I9711 O F FICE FO R S AF E T Y COO NDIN A TION 417 A C A DE M Y $ T R E E T P HON E: 30 2 738.6 4 J 5 I
Radiation Safety Of ficer I
Dear Sir:
I The radiation exposure information you requested on Social Security Number
, birthday is as follows (readings given in mrem):
Year Type of First Second Third Fourth To tal for Radiation Quarter Quarter Quarter
- Quarter, Year i
I I
I l
This report is furnished to you under the provisions of the Atomic Energy Commission regulations entitled " Standards for Protecticn Against Radiation" (10 CFR-Part 20).
You should preserve this report for future reference.
Sincerely, I
Jenny M. Johansen, M.S.
I Ilealth Physicist Radiation Safety Officer University of Delaware I
l
I I
RAD 1ATION SAFETY 0FFICE Instruction Check-off List This is to certify I have instructed:
l l Graduate Student l
l Undergraduate Student l
l Employee I
in the proper procedures of handling radioisotopes that he/she will be using; that this instruction included:
l J Storage areas for radioisotopes in my lab.
l l Areas of my lab where radioisotopes can be used.
l l Type (s) of radiation f rom isotope (s) used.
l l Energy of radiation f rom isotope (s).
l l External and internal hazards f rom isotope (s).
l l Special problems of handling the iso tope (s).
l l Review of Federal Regulations 10 CFR-19.12, 19.13.
l
] Discussion o f Federal Regulations 10 CFR-20.
l
.] Sections 3 and 4 o f University Radiation Safety Manual, pages 5-20 and Appendix.
I l
l Security measures to be used when using radioisotopes or storing them.
I Upon successful completion of examination by the Radiation Safety Office, I request a Class "D" user status for this pe rson.
I Permit S upe rviso r I
I Re tu rn to :
Radiation Sately Of fice, 417 Academy Street within one (1) month of receipt.
I
i I
Form R50-2 UNIVE RSITY OF del.!AWA R E RADIATION EXPOSURE RECORD BAOGE NUMBE R lNAME (L A S T, ri n S T, M !.)
( Y A I O_E N N A M E l STATUS DEPARTMENT IOATE OF SOCI AL (flR TH lOATE 94TE SE Cu ral T V NO IST ADTED TERMIN A TED WHOLE BODY GAMMA J< X RAY MREM l}'
O NEUTRON l
BETA OR LOW X-RA), MREM IEAR z
y W
YEARLY QUAR TERS YEARLY Cumutalve YE ARLY QUARTERS YEARLY Cumula tive ist 2nd 3rd 4th 1st P ri d bd 4 tri
_c,.
go.
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PREVIOUS RADI ATION EXPOSURE PERIOD COVE R EO PERICO COVE 9EO ATURE OF WORK I;M"'
N A T U R E O F' WORK YE" E r,wtO Y E R IDORESS l
ADOPESS I
l OT AL C XOOSU RE (M REM) - Gamm 3 & x H
T O r m. h >- P OSU R E 'M F4 E Y)
Gamma & =
0
'cniOO COvcnr0 nERion covenro ATURE OF WOAK NATURE OF WQuK EM DLO't E 4 EMPLOYER E
') CRESS ACORE55 t,
iOTAL EXPOSURE (MREM) - C a m m-t t x B
T O T A L F. /DO5U RE (M REM)
Ga mma L x 8
i I\\TURE OF WORK RIOD COVEREO PE R IOD C OVt. R E D l
N A T u r< E O r vv0Rg ltPLOYER F M D'. 7 Y E R A D O R F.S S ITAL EXPOSURC (MREM) -
- j. TO T AL E xpeSU RE wnEM)
C.imma & 4 a
l Gamma & n D
COMMENTS I
I I
APPENDIX B EXPLANATIONS OF TABLES I, II, III AND IV Laboratories are classified based on three factors: (1) radio-I toxicity hazard of nuclides in use; (2) maximum amounts of activity stored or used in the area; and (3) type of use in terms of relative hazard of the handling procedures.
I l
In Table I, radioisotopes are classified as to their relative radiotoxic hazard in relation to internal dose.
The hazard of a radio-isotope depends on the ef fective half-life of the nuclide in the body I
or organ, the type and energy of the emitted radiation, the physical and chemical form of the material, and the organ of maximum concentration.
For normal usage, laboratories are classified according to the total activity of the various classes of nuclides present in the lab.
Table II gives the four laboratory classifications (high, intermediate, I
low, and very low) based on the hazard group and activity present.
In cases of more than one nuclide in use in a laboratory,the classification will be determined by a summing of the constituent nuclides.
The amount of nuclide permitted in a given class laboratory may be increased or decreased according to type of usage.
With high accident risk operations, the amount permitted within the classification is decreased.
For simple, relatively safe operations, the amount in a given classification may be increased.
As a guide, the modifying factors in Table III are used to determine the amount by which the permitted activity should be increased or decreased.
The Radiation Safety Committee does not have rigid specifications on design requirements for various classes or radioisotope laboratories.
I As guidelines, however, the design criteria set forth in Table IV may be used.
In designing new areas the researcher should consult the Radiation Safety Officer to discuss requirements for a particular facility.
I EXPLANATION OF TABLE V
,I As per section 3.7.1.1., specific authorizations can be given for disposal of waste via sanitary sewer.
In Table V, the federal guide-l lines are stated to insure that, based on the University water flow rate, concentrations of trace amounts or radioactivity released to the sanitary
'I sewer under a specific authorization from the Radiation Safety Committec would not exceed the guidelines as s tated in 10-CFR-20.
I I
lI
i
!I
,i i
APPENDIX B Table I l
Suggested Radioisotope Classification (Unseated Sources) i j
Class Description Examples
II Iligh llazard Ca-45, I-131 i
III Moderate llazard P-32, S-35, Co-60, Rb-86, Cs-137 IV Low flazard H-3, C-14 j
- Radiation Safety Officer has a more complete lis t of examples.
j Table II Suggested Laboratory Classification (Considering Table IV 6 I) i Radioisotope Lab Grade f
A (liigh)
B (Inter)
C (Low)
D (Very Low)
- 88 J
i 1
1 mci up to 1 mci up to 10 uCi up to 0.1 uCi II 10 mci 10 mci 100 uCi 1 uCi l
III 100 mCL 100 mCL 1 mci 10 uCi i
IV 1000 mci 1000 mci 10 mci 100 uCi til
'lE Table III Modification Factors for Laboratory Classification (Table II) iE
'E use ractor 4
. E Storage only x 100
' E Simpic wet Operation (e.g. prepartng stock solutions) x 10 Normal Chemical Operation (e.g. analysis)
X1 i
Complex Chemical Operation with 111gh Risk of Spill X 0.1 Simple Dry operations (e.g. work with volatile compounds)
X 0.1 Dry Dusty Operations (e. g. grinding)
X 0.01
- I i l
- I
M M
M M
M M
M M
M M
M M
M M
TABLE IV SUGGESTED GENERAL DESIGN SPECIFICATIONS FOR LABORATORIES USING RADIOISOTOPES Lab Classi fication A
B C
D Floor Smooth, non-porous Same as A Smooth non-Any Easily removable absorbent i
Protective underlayer i
No cracks Walls Smooth, non-porous Same as A Painted; smooth Any Strippable if possible Work Benches Smooth, nonabsorbent Same as A.
Smooth sealed Any - cover with Removable covering coating - Cover absorbent paper (as absorbent paper) with absorbent paper.
Venti 11ation No recirculated air Room under net Room under net Any Absolute filters in negative press-negative pressure.
exhaust Air room under ure-Ab s olu te fil-net negative pressure ter recommended a
fHoods Singularly ducted Same as A Singularly ducted Any Absolute filter Filters optional Flow rate: 100 +
Flow rate: 100 linear feet per minute linear feet per minute i
fOther Consider: Build in shields Same as A Portable, localized Special Handling Devices shielding as needed
(
Glove Boxes i
E Detailed considerations found in:
l 1.
NBS Handbook 92 " Safe Handling of Radioactive Materials," United States Government Printing Office, Washington (1964).
i I
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1
!I l
l APPENDIX B l
TABLE V Factors for granting authorization to dispose of radioactive materials via sanitary sewer
'I f5 As per A.E.C. regulations: No licensed material shall be discharged into sanitary sewerage unless it is:
- 1) Solubic 2)
If diluted by water flow rate to sewer, concentration of material does i
not exceed that stated in Appendix B, Table I, Column 2 of 10-CFR-20 or;
- 3) Ten times the quantity of material stated in Appendix C or; j
- 4) GROSS QUANTITY OF ALL LICENSED MATERIAL RELEASED TO SEWERAGE DOES NOT l
EXCEED 1.0 CURIE PER YEAR.
!I l
University water flow rates from July 16, 1973 to July 15, 1974 equaled 3
ft / year.
l 31,094,030 Equaled 85,189.12 ft3/ day /90 buildings 6n :ded by 3.53 x 10-5 3
ft /ml===
i 26,813,000 ml/ day / building.
,I Example of Soluble Material Appendix B Appendix C i
3-ilydrogen 1 x 10-l ci/ml 1,000uci u
14-Carbon 2 x 10-2uci/mi 100uci
,I 35 - Sul fur 2 x 10-3uci/mi 100uci i
32-Phosphorus 5 x 10-4 ci/mi 10uci u
109-Cadmium 5 x 10-3 ci/ml 10uci u
- I
.I il I
I
I REFERENCES 1
1.
LICENSING GUIDE FOR TYFE A LICENSES OF BROAD SCOPE FOR RESEARCH AND DEVELOPMENT.
U. S. Atomic Energy Commission, Directorate of Licensing Materials Branch, Washington, D.C.-February, 1973.
1 2.
RULES AND REGULATIONS - TITLE 10, CHAPTER 1, CODE OF FEDERAL REGULATIONS, Part 20, 30, 31 and 33.
U. S. Atomic Energy Commission.
I 3.
NBS ItANDBOOK #73.
" Protection Against Radiation From Scaled Sources" -
July, 1960.
4.
NBS IIANDBOOK #53.
" Recommendations for the Disposal of Carbon-14 Wastes"-
January, 1957.
5.
NBS ILANDBOOK #48.
" Control and Removal of Radioactive Contamination in Laboratories" - January, 1957.
6.
NCRP REPORT No. 39.
" Basic Radiation Protection Criteria," January, 1971.
7.
" RADIATION SAFETY MANUALS'.'
Auburn University - April, 1972.
Harvard University - June, 1972.
New England Deaconess llospital - 1973.
Peter I
Bent Brigham Hospital -January, 1969.
Iowa S tate University - March,1969.
North Dakota State University - April, 1962.
Ohio State University - 1967.
Purdue University - January, 1972.
8.
NBS IIANDBOOK #92.
" Safe Handling of Radioactive Materials" - March, 1964.
I I
I I
I I
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