ML20137J845
| ML20137J845 | |
| Person / Time | |
|---|---|
| Site: | 07002873 |
| Issue date: | 06/06/1978 |
| From: | PUERTO RICO, UNIV. OF, MAYAGUEZ, PR |
| To: | |
| Shared Package | |
| ML20136E113 | List: |
| References | |
| NUDOCS 8512030055 | |
| Download: ML20137J845 (85) | |
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l APPLICATION IUR LICENSE for i
SPECIAL NUCLEAR MATERIAL for UNIVERSITY OF PUERTO RICO Mayaguez Campus 4
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0512030055 851007 REG 2 L IC70 SNM-1836 PDff
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N.2 INDEX i
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1.
Applicant 1
2.
Principal Official 1
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3.
Activities for Which Special Nuclear Material Intended 1
4.
Technical Qualification of Personnel 3
5.
Description of Facilities, Equipment and Instrumentation 8
6.
Instrument Calibration Provisions 25 7.
Renote Handling Devices 30 8.
Storage Containers and Facilities 30 9.
Radiation Safety Responsibilities and Duties 31 10.
Personnel bbnitoring 39 11.
Radiation Survey Program 41 12.
Acceptable Limits 42 13.
Record Management 43 14.
Material Contml Provision 43 15.
Waste Disposal 48 16.
Leak Test Provision 50 17.
Emergency and Decontamination Program 51 18.
Procedure for Training Personnel 62 19.
Appendix (A) Health Physics Foms 20.
Appendix (B) Calibration Records of Pu-Be Sources and Alpha Sources v
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Applicant i
k Name: University of Puerto Rico, Mayaguez Campus Address: College Station,.Mayaguez, Puerto Rico 00708 State Where Incorporated: Puerto Rico 2.
Principal Official Name: Rafael Pietri Ons
Title:
Chancellor, Recinto Universitario Mayaguez Address: College Station, Mayaguez, Puerto Rico 00708 3.
Activities for hhich Special Nuclear Material Intended Application is made for license for three (3) Pu-Be Sources as follows:
1.
Pu-Be sealed source Manufacturer; Grams of Pu : 15.05 g Lbnsanto Research Corp.
(Pu-239, Pu-240, Pu-241, Americium) bbunt Laboratory Miamisburg, Ohio Grams of Be : 7.43g bbdel No: M-157 Activity in Ci : 41p C1 (1.51 x 106 n/sec)
No record of dose-contributing contaminants 2.
Pu-Be sealed source Manufacturer:
Grams of Pu : 14.90 g bbnsanto Research Corp.
(Pu-239, Pu-240, Pu-241 Americium) bbunt Laboratory Miamisburg, Ohio Grams of Be : Not available hbdel No: M-158 Activity in Ci :
41 6 n/sec) p C1 (1.53 x 10 No record of dose - contributing contaminants
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Pu-Be scaled source Manufacturer:
Grams of Pu : 14.99 g Monsanto Research Corp.
-(Pu-239,Pu-240,Pu-241, Americium)
Mount Laboratory Miamisburg, Ohio Grams of Be : 7.45 g Model No: M-159 42gCi Activity in Ci :
(1.55 x 106 n/sec)
No reconi of dose - contributing' contaminants.
Calibration records of these sourtes, supplied by the manufacturer, are attached. (See Appendix B)
Source #1 is used as a startup source in a 10-watt training reactor.
It is never physically removed from the reactor containment vessel.
Reactor Manufacturer:
Atomics International North American Rockwell P.O. Box 309 Canoga Park, California 91304 Reactor Model: L-77 Laboratory Reactor.
Sources #1 and #2 are used in the Nuclear Engineering Laboratory for T_- pile and subcritical pile experiments. When not in use, the sources are stored in special containers in the storage facility. These are described in Sections SD and 8.
4.
Additionally four (4)
Manufacturer:
Plutonium Alpha Standants Eberline Instrument Corp.
as shown in Appendix B P.O.. Box 2108 Santa Fe, New Mexico (Serial No: P1694, P1738, P610 and P1900)
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T^chnic 1 Qualific~tioni of Pc.rronn71 4.1 Radiation Protection Officer Training and Experience Nimia E. Irizarry Duration of Type of Training Where Trained Training On the Job Formal Course c.
Principles and practices of radiation protection...
1.
Seminar in radiological Center for Energy and Environment 5 months Yes (No)
(Yes) No health Research (CEER), (Formerly Puerto ggg 2.
Radiation hazards and Rico Nuclear Center), in coordination 5 months protection with Medical Sciences Campus U.P.R.
3.
Laws and regulations in Rio Piedras, Puerto Rico.
5 months radiological health 4.
Safety in reactor operations 5 months 5.
Field practice 2 months b.
Radioactivity measurement standardization and monitoring Same as above Yes (No)
(Yes) No techniques and instruments...
1.
Radiation detection 5 months 2.
Radiation dosimetry 5 months 3.
Decontamination and waste management 5 months 4.
Radioactivity of the llh environment 5 months c.
Mathematics and calculations basic to the use and measurement Same as above Yes (No)
(Yes) No of radioactivity...
1.
Radiation physics 5 months 2.
Radiation chemistry 5 months d.
Biological effects of radiation...
Same as above Yes (No)
(Yes) No 1.
Radiation effects in mammals jf o
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-Additional Experience:
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Total of 8 years working with radioisotopes.
I Four years as Research Assistant I ~to III. Working in neutron j
activation and spectrometric analysis of samples..
i Four years as Radiological Safety Officer, 3 of which have t
been as Head, Health and Safety Division, Center for Energy and 1
l Environment Rescatrh (formerly Puerto Rico Nuclear Center).
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T^chnical Qualific* tion, of P rronnr1 4.1 Radiation Protection Officer Experience with Radiation Nimia E. Irizarry
' Isotope Maximum Amount Where Experience was Gained Duration of Experience Type of Use CD-60 16413 Ci Puerto Rico Nuclear Center 4 years Gamma irr.
Ra-226 21.6 mg Puerto Rico Nuclear Center 4 years Instr. and film cal.
Cs-137 20 Ci Puerto Rico Nuclear Center 4 years Instr. and film cal.
Pu Be 15 g Pu Puerto Rico Nuclear Center 4 years Instr. and film cal.
TRIGA FLIP reactor 2 MW Puerto Rico Nuclear Center 4 years Radiation Protection Officer O
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Page 6 4.2 Supervisory Personnel 4.2.1 Senior Reactor Operator and Professor Knud B. Pedersen Senior Reactor Operator Professor blechanical and Nuclear Engineering Department RlBI, University of Puerto Rico, h!ayaguez Education B.S.ht.E.
- Iowa State College -
1958 bl.S. 6 Ph.D.
- Nuclear Engineering Iowa State University - 1964 - 1967 respectively Experience Experience in handling radioactive materials include the laboratory courses that are part of the nuclear engineer-ing degrees. Calculations w11ch are basic to the use and measurement of radioactivity are included in these and other courses, as are the biological effects of radiation.
Practical experience includes four years laboratory work at Ames Laboratory, Ames, Iowa. Considerable time was spent on the mechanical properties of natural uranium at elevated temperatures.
Further practical experience includes reading of reactor laboratory course and nocicar measurement course at the University of Puerto Rico, h!ayaguez.
Additional experience has been the supervision of five theses involving neutron activation analysis, involving the handling of radioactive materials in various physical forms and different, strengths.
Iko summer courses at h!IT on nuclear reactor safety,1972 and 1974.
1 Three months at Oak Ridge National Laboraton working on Environmental Statements of nucicar reactors - 1973.
Three months at Johnson Space Center, NASA, working on radiation effects on materials and space crew - 1976.
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Reactor operator and reactor supervisor TRIGA and L-77 reactors, Puerto Pico Nuclear Center - July,1976.
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4.2 Supervisory Personnel 4.2.2 Senior Reactor Operator and Professor Richard Brown Campos
. Senior Reactor Operator j
Assoc. Professor, hbchanical Engineering Mechanical and Nuclear Engineering Department RIN, University of Puerto Rico, Mayaguez, Puerto Rico Education B.S.M.E.
- University _of Puerto Rico - 1958 ORINS Radioisotope Training Course - Sumer 1958 m
This course. included.~ principles of physics of radiation, detection and measurements of radiation, probability and statistics, laboratory techniques, practice and experi-ments using radioisotopes.
ORNL Reactor Supervisor Training Course:
A 16 month on-the-job: training covering all phases of reactor operations including nuclear and reactor physics, instrumentation and control, shielding, cooling systems, and radiation protection.
l Sumer course in reactor experiments Gainesville,. Florida.
h5 Nuclear Technology University of Puerto Rico - 1962 Courses in this curriculum included atomic and nuclear i
g physics and laboratory, radiological health and radio-
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logical instrumentation.
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3 5.
Description of Facilities, Equipment and Instrumentation 5.1 Facilities and Equipment The Nuclear and Radiation Laboratory of the University of e Puerto Rico, Mayaguez Campus, is located within the compound of the Center for Energy and Environment Rescatrh (CEER) which is operated by the University of. Puerto Rico for the U.S. Department of Energy, and which stands on a 8.6 ha tract of land that ad-joins the University of Puerto Rico's Mayaguez Campus as shown in Fig. 1.
The site is bound on the north by "Los Perros Trail", on the west by State Road #108 and on the east and south by the Experiment Station as shown in Fig. 2.
The main facilities located at CEER are:
offices,.
- a.
Laboratory building containing classrooms and chemistry and physics laboratories. This building.
,contains a gama pool where two high level gama sources.
are operated (Fig. 2),
b.
Administration building with office space, warehouse and a lecture room-lunch room area.
c.
Shop build ng with office space, machine shop, electronics shop'and tool room areas.
d.
Chemistry annex building with two chemistry laboratories and one instmment 1aboratory,
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- e.. A 100,000-ga11on elevated water tower.
f.
Plant house and service room.
g.
Annex building with office space, classroom areas, nuclear '
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engineering laboratories, a neutron generator room and a reactor llaboratoly where a subcritical graphite pile and a 10-watt aqueous homogeneous reactor are located. (Fig. 3). -
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Flamable and radicactive waste storage shacks.
The site is surrounded on all sides by a 2.44 m cyclone wire fence with'one entrance gate leading to State Road #108.
This gate is kept locked during off-duty hours. Normal work-
'ing hours are from 7:30 N61 to 6:00 PM Mondays through Fridays.
Four licensable installations and the laboratories for licensable materials are described:
A.
Wo cobalt-60 gamma irradiation source in the Gama Pool Irradiation Facility.
B.
A graphite subcritical pile.
C.
A 10-watt homogeneous reactor (L-77).
D.
Laboratories and calibration facility.
A.
Gama Pool Irradiation Facility The gama pool irradiation facility is located on the first floor of the laboratory building (Figs. 2, 4 and 5). The build-ing is provided with a once-through-type central air condition-ing system. The' irradiation facility consists of two irradiators, an 800 curie' cobalt-60 variable geometry irradiator and a 10.5 kilo-curie cobalt-60 fixed geometry irradiator.
Variable Geometry Irradiator
'Ihe gamma source for the variable geomatry irradiator is contained in twelve pencil-type capsules,. 6.4 m diameter by 25.4 cm high, each containing approximately 66 curies. The cap-sules' are inserted in the variable geometry.irradiator (VGI)
-(Fig. 5). The VGI is remotely and continuously adjustable to "fom a hollow cylinder from 12.7 cm to 50 cm in diameter. A symetrical field is obtained by using 3, 6 or 12 capsules.
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Page 10 Fixed Geometry Irradiator The fixed geometry irradiator (FGI) consists of an altninta plate with three concentric circular holders into which a gama source consisting of 12 strips, 22 mm wide by 33 cm long, may lL be loaded. - The concentric holders are 20 cm, 40 cm and 56 cm.in diameter for three different dose ranges.
Pool:
A pool 2.7 m x 2 m x 4.4 m deep, located in room 121A, con -
tains the variabic geometry irradiator and the fixed geometry irra--
l diator. A dry well. is adjacent to one end of the pool with an i
1 aluminta plate separating the two sides. Covers provide suitable l
scattered radiation protection on top of the dry well.
i A wel1~ with a lead cover is located 'at the bottom of the pool for source storage during pool repair or maintenance.
A 10 ga11on per minute ptnp and. filter system continuously circulates the water for purification purposes. ~ A one-gallon per minute side stream is circulated through a mixedbed ion
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exchange column' to continuously demineralize.the' water'. Pump i
inlet and outlet pipes are kept near the pool surface to prevent accidental' pool drainage. Water: mixing is attained by pointing the~ outlet water jet down into the pool. Sma11' evaporation losses are made up manually with tap water.
'A portable steel bridge across the top of the poo1~ serves as the base' for the' operator conducting irradiations.
A platfonn, _1.2 m x 2.4 m, is ' located ten' feet' below the~ water-i in the pool. This platform serves as an operating; base for the var--
inble geometry irradiator; it has ~12' cylindrical containers to hold' 9
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Pool the pencil-type capsules. Re-fixed geometry irradiator is located on the bottom of the pool approximately 2.1 m away (center to center) from the variable geometry irradiator.
A radiation monitor with visual-and audibic alarm is preset' at.20 mr per hour. The probe is attached to the underside of the b' ridge.above the area where the. irradiations are conducted.-
Room The gansna pool. irradiation facility (GPIF),is housed J
0 This room h,'s a double' in room-121A in.the laboratory building.
a door to-the rear corridor and one ~ single door.to room 103.
The doo~r to room 103 is secured at all times with a breakable seal. ne room'has a ' cabinet for storing accessory equipment and. survey meters. iOxygen, nitrogen and conpressed' air may be provided accordin'g -to the' needs of an experiment.
Safety Provisions 1.
Water Loss Water:may:be lost from the pool in three ways:
- a. Evaporation, b. Pumping or c. an earthquake cracking 5'
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' Evaporation 7 osslwill be compensated by manual, periodic 1
' addition ~of water from a water.line adjacent;to the' pool.
All-pennanent connections to -and !from the; pump are not-more than 30.cm below :the nonnal. level of the water; therefore,.
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.it is impo's'ible to' drain-the pool below that level.
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The counting room located in Room 114 in the main laboratory building (Fig. 2) is an L-shaped room whose main demensions are 6.7 m by 4.3 m.
This room is equipped with a multichannel analyzer connected to a shielded GE(Li) detector which is used by the Radiation Safety Division, as.well as by university students.
o Ventilation and temperature contml is provided by a window-type air conditioner' installed in the wall. No hoods i
i are provided in this room.
3.
A third laboratory is presently used for the pre-
^
paration of samples which do not' involve the use of licensable materials. This laboratory is 7 m'by 7.3 m and is located in k-Room 123 in the main laboratory building- (Fig. 2).
'Ihis room is' equipped with a hood and is ventilated by the main ventilation system. This system is-only operated-i during working hours and therefore no counting or detection lcquipment can be kept there.
Licensabic radioactive sources, when they are not i
in use or if they are not part of a piece of equipment, are stored in the storage shed(Fig.2), which is under the' adminis-
.trative control of the Radiation Protection Officer.
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4.
The calibration ' facility is a 4 m by 4 m room' located j
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in the annex building (Fig. 3)~.
Item S, page.21, Calibration-Provisions,-describes the facilities located in this room. There are no provisions-for: ventilation, altlough air conditioning
'canbeinstalledinanexisting-openinglinthbwall.
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' Safety Provisions Only in the event that the pool is to be deliberately drained will a temporary connection be used so that the water may be completely pumped out. This connection is to -
be removed after refilling the pool.
If an earthquake of sufficient magnitude to crack the reinforced concrete walls should occur, resulting in a loss of water, the area will be vacated. Health Physics will be netified and the necessary remedial action taken. As an example, the source might be covered with sand or dirt to provide temporary shielding. Specific remedies will depend on circumstances.
2.
Power Failure The operation of the' GPIF is entirely manual with the exception of the alarm systems and lights. A battery-opera-ted portable light is available.
In the event of electrical failure, all experiments will be stopped and no samples will be removed from or inserted into the irradiators.
B, Graphite Subcritical Pile A graphite subcritical pile.is housed. in the reactor _ lab-oratory of the Annex Building (Figs _2 and 3). The building is a cement block structure with a concrete slab floor and a built-up roof. Ventilation for the temperature and humidity control is provided by' window-type air conditioners Since no hazardous gases (radioactive or otherwise) are produced during the operation g*
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-of either facility, no special ventilation or hoods are provided.
I The subcritical' pile is made up of graphite stringers 10 cm on a side fonning a block 1.53 m x 1.73 m x 2.34 m with horizontal channels for the placement of irradiation-foils.
~
The fuel loading consists of 844 slugs containing 1408 kilograms of natural uranium. The slugs are clad in aluminum and are 2.54 cm in diameter by 15.24 cm long. The pile is driven by a 1 curie Pu-Be source which can be placed at various locations on a horizontal channel provided for this purpose.
The pile can be covered on all sides by aluminum-clad cadmium sheets. The front and rear covers are removable for loading and unloading operations.
When not in the pile, the fuel is stored in a padlocked steel cage in a corner of the laboratory adjacent to the pile.
When not in use the' Pu-Be source is' stored in its shielded container in the radioactive storage area.
No permanently installed nuclear safety-related'instru-mentation is provided. Health Physics coverage is requested during fuel unloading and loading operations, or while handling
.the netron source.-
C.
L-77 Reactor General
Description:
The L-77 reactor'is ' located. in the same laboratory of the Nuclear Engineering Annex Building as the subcritical pile.
It is a solution-type? reactor using light water as modera-
. tor and. enriched uranyl sulfate as fuel. A cutaway of the core-r-
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shield assembly is shown in Fig. 6.
The design thennal-power level of this reactor is 10 watts. Because of the j
low power level, no cooling system is required.
A spherical stainless steel core contains the fuel
. solution.
In the event of a major power excursion, the large throat area above the core permits rapid expulsion of expanding fuel solution into the overflow assembly, which is an annular holdup volume within the canopy. A gas recombiner located in the canopy serves to catalytically recombine the hydrogen and oxygen generated by decomposition of the moderator in the fission process. The core and canopy assembly is completely surrounded by three solid shield regions, a water shield, and the reactor shield tank.
The reactor is equipped with two control-safety rods.
The rods pass through thimbles which penetrate the core and canopy assembly vertically. Steel tapes attached to the upper end of each rod are used to lift the rods. The rod drive mech-anisms, located on the top of the shield tank, utilize electro-magnetic clutches to engage the rod drive.
Operation of the reactor is observed and controlled from a desk-type console. The console displays pertinent operating information, such as control-rod positions and neutron-flux levels.
' Reactor instnamentation consists, essentially, of two neutron channels, a pressure-monitoring system, and the electri-cal interlocking circuitry.
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Page 16 The experimental facilities include four small-diameter exposure tubes and a larger diameter exposure tube, all of which completely penetrate the core and terminate at opposite sides of the water-filled shield tank; two beam tubes which extend from the shield tank wall to the external periphery of the core; and two of the four instrumentation thimbles (the other two contain ion chambers).
In all of the experimental facilities, adequate shield plugs, which are stepped as necessary, are utilized to prevent radiation streaming when the facilities are not in use.
The L-77 reactor is operated according to NRC regulations and the following applicable documents:
1.
Hazard Sumary Report 2.
Technical Specification 3.
Operating Procedures d.
Laboratories and Calibration Facility Two laboratory rooms will be used for all licensable sources at the Nuclear and Radiation Laboratory; these are the nuclear engineering laboratory located in the annex (Fig. 3), and the counting room located in the main laboratory b'uilding (Fig. 2).
1.
The nuclear engineering laboratory is a' counting lab-oratory, measuring 7.4 m by 4.6 m, equipped with several' scalers and a nultichannel analyzer connected.to one of two-shielded NaI detectors.
Approximately 9.5 m of counter top, equipped with one sink, is available for student experiments.
Ventilation and temperature control is provided by a -
- window-type air conditioner installed in the' wall. No.other ventilation is provided, and no hoods are presently installed.
5.2 R1 diction Detection In:truments Type of Instrument Number Radiation Sensitivity Range Window Thickness Use 2
Available Detected (mr/hr)
(mg/cm )
Trapole (Snoopy) NP-2 Serial No.
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0-2000
.N/A Surveying 5093 Proportional probe.
Ludlum (Ludlum Measurement Inc.)
2 Sy 0-Surveying lll Model 3 Ludlum (Ludlum Measurement Inc.)
2 a
0-Surveying Model 2 Ray-D-Tech (American Nuclear 3
By 0-100 mr/hr Surveying Corp.) AMC-100XL Ray-D-Tech (American Nuclear 3
By 0-1000 mr/hr Surveying Corp.) Model cpm-X-1000 ORNL Model Q-2092A - IRI (GM) 1 Sy Surveying Teletector Total (Eberline Instr.
3 By 0.1 mr/hr to Surveying Corp.) Model 6112 1000 mr/hr (4 ranges Vamp. Voctorcen Model 808 B 1
Sy Monitoring Nuclear Measurement Corp.
2 Constmut Air Monitor Model AM-3D 1
Sy 50-50000 5.6 mg/cm Monitoring cpm Log Eberline Instrument Corp.
1 By 0-200 mr/hr Surveying Model Fm-li Gas Flow Proportional Counter 2
aSy N/A N/A Measuring (Nuclear Measurement Corp.)
Model PCC-11T-DS-1T Combination
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5.2 Radiation D: taction Instrumints Cont.
Type of Instrument Number Radiation Sensitivity Range WindowThigkness Use Available Detected (mr/hr)
(mg/cm )
GeLi Detection System (Camberra 1
N/A' Measuring Ind.) Model No. 7229 2
Decade Scaler (Nuclear Chicago) 2 N/A 1.4-20 mg/cm Measuring (l)
Models No. DS-1T, DS-2 Eberline Air Monitor Model AIM-3 1
0-1500 cpm N/A Monitoring O
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Location of the University of Puerto Rico and the Center for Energy and Environment Research in Mayaguez, Puerto'Rico, l
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'g B - Greenhouse (Plant House)
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C - Agro-Bio-Science Laboratory arking Lot k
D - Marine Biology Iaboratory 4
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G - Reactor Building l
N H - Shop Building I - Shop Storage Area f-r J - Administration Building
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M - Agricultural Shed
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Sand Fill LR Laille-es Room M
- Ments l 'om Neutron L
L-77 Ikeactor Generator C
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- Calil,r.ition Room C
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- Decontamination Room A-11
- Stora<re Room e
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'o N-10-B Classroom N-10 M
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M Laboratory Laboratory i
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h Lab Office g
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Office Office Office Office Office M
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Instrument Calibration Provisions -(Methods, Frequency 4 Standards) 6.1 Methods and' Procedures of Calibration Different calibration sources are used as follows:
6.1.1 Co-60 93.96 mci, this source is loca'ted'inside a_well 4.54 m deep as shown in Fig. 1.
It is tied to a ribbon that is connected'in a motor assembly. The source is moved out.by means of a motor (A). This source is used only for calibrating high ranges of the instruments and for high doses in the film badges. On calibrating the instruments, the probe is placed on top of the well (B)
'and the source is raised to a known distance. The film badges are placed in a wooden assembly (C), the source
~
is raised and the-technician leaves the room after turning the warning lights on.
6.1.2 Ra-226,- two sources,. 0.918 mg of Ra and 21.6 mg of Ra used for calibrating instruments and films. These two sources are stored in two different portable lead shield-ings and are used in the assembly shown in Fig. 2 as follows:
The 0.918 mg source is normally stored in the lead shielding E.
Using a pair of tweezers, the source is
- taken from the shielding and placed at A_.
The instnt-ment is placed at B.
The' distance from B and A_
corresponding to the different exposure rates (10 mR/hr, etc.)ismarkedon7,ameterstick. The stand F_.that holds the source moves to the right or to th'e left according to the. desired exposure rate. The' technician 5
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Page 26 calibrating the instruments stands in front of G and is protected from the source by D a lead brick wall. hhen exposure rates higher than 20 mR/hr are being calibrated the 21.6 mg source is placed at A.
This source is normally in'another Pb pig located in the same room.
6.1.3 Pu-Be sources approx. 15 mg Pu, M-158. The Pb bricks are reinforced using paraffin blocks in front of the source placed at A_.
The correspond-ing calibrating distances are also marked in the meter stick and the source is moved accordingly.
For neutron film calibration the films are placed at different distances from the source and for the corresponding time period. The technician is-protected using paraffin blocks.
6.1.4 Monitoring Instmments:
6.1.4.1 The constant air monitor has a built-in Ra-226 check source and it is adjusted to the level specified in the instruction manual.
6.1.4.2 The.others are calibrated using the 0.918 mg Ra source and Sr-90 calibrating sources.
6.1.5 ' Measuring' Instmments:
l.
Measuring instruments are calibrated using exempt Ra DE, Co-60, Cs-137 and C-14 calibrating sources. The l-
< S., y and a operating voltages of the gas flow pro-portional counters are checked using Ra DE sources.
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Calibration assembly using Co-60 source.
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The Ge(Li) system is calibrated using Co-60, Cs-137 -
.and other calibration sources-to obtain a curve rela-ting isotope energy with channel number.
6.2 Calibration Frequency 6.2.1 Surveying Instruments:
6.2.1.1 All surveying instruments are checked on a monthly basis. If the measured exposure rate is more than 10% off the tme exposure rate the instrument is calibrated.
6.2.1.2 All instruments are calibrated after repair.
and whenever abnormal readings are noticed.
6.2.2~ Monitoring Instruments:
6.2.2.1 Constant. Air Monitors are calibrated weekly.
6.2.2.2 Others are calibrated monthly or more frequent-ly if-abnomal readings are noticed.
-6.2.3 Measuring Instmments:
6.2.3.1-The gas flow proportional counters' plateaus are checked every three months using Ra DE.
- calibrat' ion sources.
6.2.3.2 The Ge(Li) detector is connected to a Nuclear Data Computer System and it-is calibrated every time'the whole' system is turned on i.e., when the whole system' is turned,off, the' programs
'in the ~ computer are erased, and it has to be.
calibrated in or' der'to be used' again.
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6.3 Methods and Procedures of. Calibration 6.3.1 Surveying Instruments:
All surveying instruments are calibrated adjust-ing the variable resistors in the instrument so that.the meter reading agrees with the known exposure rate.. Usually, the exposure rates used are 1'mR/hr, 20 mR/hr, 50 mR/hr,100 mR/hr 500 mR/hr and the corresponding Co-60' highest exposure rate for the mosth when 'the range of the instrument requires it..
s-7.
Remote Haiidling Devices Two handling devices are useu for rapid transfer of 4
either of the two sealed Pu-Be sources.
1) 1 scissor type tong, 2 ft. long-
~
2) 1 tweezer type,.1 ft. long 8.
Containers for Storage of Pu-Be Sources The containers in which the two movable sources are stored in the storage shed are two 30-gallon drums filled with paraffin. A source is placed in a slot in the bottom of a tube which fits inside another tube
. imbedded in the paraffin. The tube with the' source can be lifted 'after removing' the cap of the embedded
-u tube.,There is one source in each drum. The activity at the surface of a container is a maximum of:
15 mrem /hr neutron
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5 mrem /hr gamma ~
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Page 31 Two portable paraffin containers
- 1. 23 cm x 23 cm x 25 cm rectangular container
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- 2. 25 cm diameter square cylinder container The maximum activity at the surface of a portable container is 20 mrem /hr neutron j
5 mrem /hr gama Additionally there are 20 blocks of auxiliary shield-ing consisting of paraffin each measuring 48 cm x 30 cm x 2.54 cm.
9.
Radiation Safety Responsibilities and Duties Radiation Protection Program
- The University of Puerto Rico, Mayaguez Campus (hereinafter called the. College).is authorized by the Nuclear Regulatory Comission-(NRC) to procure and use radioactive materials and to' operate certain sources of high energy radiation. The valid-ity of this. authorization is contingent upon the existence of a
-safety organization. This document is designed to establish guidelines 'for the effective functioning of the safety organi-zation within the College.
9.1 Safety' Organization
'Ihe Chancellor of the College has the ultimate r,espon-sibility and authority for all activities related.
I
- Note - Certain portions of these documents may'be~ revised by.the
~
Radiation Safety Committee'without prior notification of the.NRC~ staff.
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9 to radiation safety.
It is recognized that radiation safety is a line responsibility. The Chancellor will issue under conpetent advice, regulations governing the.use of radioactive materials within the area i
controlled by the College.
A campus-wide Radiation Protection Organization will
.be developed at the College, consisting of a Radiation Protection Officer (RPO) and a Radiation Safety Com-mittee (hereinafter called the comittee). The Chan-cellor has the responsibility of maintaining this
-organization with qualified personnel and in compliance with NRC and local applicable regulations.
. 9.2 Radiation Safety Comittee-Charter
9.2.1 Scope
To assure that all operations and experiments involving the'use of radioisotopes are conducted in a safe manner.
9.2.2 Chairman
The chairman shall be appointed by the Chancellor. The chaiman shall chair. the meetings of the Committee and i
enter into discussions, but shall not vote on any issue
~
before the' Committee, except in the case of a tie vote.
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9.2.3 ', Secretary:
The secretary of the Comittee is appointed by the chairman and does not need to be a member of the Comittee.
9.2.4 Membership
i Membership is selected from different' disciplines.
The chairman, with the approval of the Chancellor, chooses the members of the Comittee. At the present time, the membership is as follows:
Mortimer Kay
- Chemist i
~ Richard Brown
- Mechanical Eng.
i Knud Pedersen
- Mechan. 4 Nucl. Eng. (Chairman)
Ferdinand Rosa
- Mechan. S Nucl. Eng.
j.
Nimia Irizarry
- Health Physics 9.2.5-Requirements:
Each member should be trained and experienced in the
_ use.of radioactive materials, should have keen Inter-est :in the' business of the Comittee, and be-compe-l l
tent in his1. field.
-~
l 9.2.6! Duties:
- a. -Review and ev tiuate,'all proposals _ and experiments l
L involving _the purchase and use of radioisotopes.
s i
l b.
Provide ~ technical. assistance to.the radiological safety-officer whenever requested to do so.
- c. Provide advice to the Chancellor on matters related to radiation safety.
'd.; Approve guidelines.for_ the safe :use of radioisotopes
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in laboratories.
e.
Review incidents related to the use of radio-isotopes and propose corrective actions if x.
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f.- Establish, and periodically revise, procedures for the procurement,} storage and disposal of
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9.2.7
-Quonim and. Requirements for. Holding Meetings:
s bbre than half of the members of the Comittee shall be considered quorum. The meetings are restricted to the secretary and the members of the Committee.
However, when necessary, other persons related to 1
, the topics in the agenda may be invited. The Com-i mittee shall meet no less than twice.a year or as frequent as the chairman considers necessary.-
9.2.8 Reporting
A report of the minutes of the meetings.shall be submitted to the Chancellor. Also,.a copy of all materials, i.e., reports, procedures, etc., evaluated, i
revised or' reviewed in the ' meetings shall be equally submitted. - A copy of these documents shall be kept y
by the secretary of the Comittee.
9.3
-Radiation Protection Officer -
9.3.1 Responsibilities
a.
The Radiation Protection Officer has operational
' responsibility for all matters related to the q
t safe use of radioisotopes.-
b.
Is responsible. for conducting' the radiation safety s,
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'Page 35
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hbst have full authority to stop without consultation, any procedure deemed unsafe.
d.
Represents the Chancellor in all matters related to radiation safety.
e.
Can authorize repeats of experiments previously approved by the Radiation Safety Committee.
9.3.2 Duties
4 a.
The general surveillance of all activities pertaining to radiation safety including the acquisition, use and disposition of all radio-active materials and radiation sources'.
b.
Furnishing consultation services to perscnnel at all levels' and -all aspects of radiation protection.
c.
Receiving, opening,-delivering,' shipping, storing, transferring, and disposing of all' radioactive materials arriving'at the' College.-
d.
Maintaining and operating a personne1'and area monitoring service suitable-for the radioactive materials being used, maintaining dose records,
'and issuing exposure record notices to the radia-tion workers.
e.
Maintaining a calibration facility for all survey'
.i instruments and-monitoring devices in use.
f.
Perfonning periodical surveys in all areas where radioisotopes are being used.
g.
Maintaining an iventory of all radioactive materials i
Page 36 under the College control.
- h. Perfonning Icak tests on all scaled ' sources under the College control.
- i. Supervising decontamination procedures in cases of accidents involving radioactive -
4
-contamination,
- j. Notifying individual _s and the proper. author-ities whenever a radiation exposure reaches reportable levels as prescribed in NRC regula-tions.
- k. Coordinating indoctrination courses for personnel,
- 1. Enforcing all NRC and local authority applicable regulations.
~
- m. Maintaining all required records and forms.
- n. Referring.to the Radiation Safety Coninittee matters requiring its review and approval.
9.4 Individual _EmployeeUsinERadioisotopes.
J
- Each. employee is responsible for:
Using radioisotopes in sudh a manner ~ as-to Mini-a.
mize all chances of undue radiation expostire.or injury.
b.
Wearing the prescribed' monitoring device such as'
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film badge or pocketcdosimeter andEleaving it
- after working hours in the. place'provided for that purpose.
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Properly labeling radioactive materials and materials i
' that have been used with them.
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- d.. Keeping areas where radioisotopes areLbeing used ~
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Refraining from smoking, drinking, eating or using cosmetics in any place where radioisotopes are being used.
f.
Never, under any circumstances, pipetting any radioactive solution by mouth.
g.-
Wearing clothing appropriate to the task being
- performed and protective devices whenever required.
h.
Keeping custody of the radioactive materials in his possession. These materials shall not be lent
. given', or'otherwise transferred'without prior approval by the; Radiation Protection Officer.
~
~
- i. Reporting promptly to the supervisor and the Radia-tion Protection Officer any accident.
- j. Taking prompt action to prevent the spread of any
. released or spilled radioactive materials.
-i k.~ Carrying out' decontamination procedures under the f
direction of a competent authority approved by the Radiation Protection Officer..
'1. ;Never, under any circumstances, working'with radio-1 active solutions while having an exposed wound.
2 4
m.
In.the case of female personnel,-reporting. pregnancy,
~
as soon as it -is confirmed, to the supervisor and to the Radiation. Protection Officer.
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Prior to separation, leaving the working area in a clean, safe, and neat condition.
o.
Making use of those techniques' that will prevent a spill or other accident.
9.5 Supervisory Personnel
. Supervisory personnel shall insure that individuals under their direction handle radioactive materials in a safe manner and shall further be responsible for:
Adequate planning of procedures and experiments a.
involving the use of radioactive materials.'
b.
Notifying the Radiation and Safety Committee at least four weeks in advance of any new experiments or procedures involving the use of radioactive materials and providing the infonnation required in HPO FORM-004. Making themselves available in-case the committee needs any infonnation related to their proposals.
.c.
Requesting the issuance of film badges or any other monitoring device for new radioisotopes users under their supervision, and notifying the Radiation Protection Officer within two weeks of the users' departure.
d.
Procuring, using and disposing of radioactive Mate-rials in accordance with these regulations.
e.
Notifying the Radiation Protection Officer of any accidents involving radioactive' materials within their supervision.
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- f.. Obtaining clearance from the Radiation Protection Officer before.any. equipment that may be contami-nated' is sent from a' working area :for cleaning,.
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repair, or modification, -to surplus, or to ulti-i mate disposal.
e g.
Obtaining approval from the Radiation Protection f
Officer fo'r the procurement of radioactive Mate-rials.
h.
Notifying the Radiation Protection Officer,before any service or maintenance work is done on plumb-d ing, ventilation,orothercomponenthinanyarea where rad oact ve mater als have been used.
i i
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Instructing those personnel for whom they are L.
responsible in the techniquesnecessaryfto maximize safety.
- j. Making all new employees;available for any indoctri-c1D nation that may be; sponsored' by;the' Radiation Protec-o tion Officer.
r
.k.- iPrior 'to separation, leaving working areas in a clean, safe, and uncontaminated 1 condition'.
- 10. Personne11.fonitoring C-10.1 Personnel Monitoring Devices:
10.1.1J Film Badge or TLD Badges" 4
.10.1.1.1. A film badge'or TLD ba'dgesimust'be~wornIby'all
- personnel working' in a.',' Restricted; Area". where.a whole-body " exposure of 10 millirems or more is. likely'
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-to occur in 'any calendar quarter.
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se 4o 10.1.1.2 The supervisors. shall request a badge for any employee or student prior to date of arrival.
No person shall start working in restricted areas without a monitoring badge.
10.1.1.3 Fom HP0 Form-005 will be used to request badges and/or notify temination of. employees or stu-dents working in restricted areas.
10.1.1.4 When badge users leave the restricted areas, the badges sliall be left in the, place provided for this purpose.
10.1.1.5' The badge shall be worn outside of all clothing on the part of the body where the greates t radia-tion exposure is anticipated.
10.1.1.6 In special cases, as recomended by the Radiation Protection Officer, the regular badge will be supple-mented with wrist or finger ring badges.
10.1.2 Pocket Ionization Chambers 10.1.2.1 Pocket ionization chambers will be provided to visitors entering restric'ted areas. These will be read daily in the appropriate electronic char-ger-reader for indirect reading dosimeters. Read-out ranges: 0 to 40 mR or 0 to 200 mR full scale.
Calibration to these will be done as specified in instruction manual, using the'.same sources described in Item 6 of this application.
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Page 41
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10.2. Frequency for Changing Dosimeters
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10.2.1 Badges: Badges will'be changed on a monthly basis i-except for secretaries, maintenance personnel, and i
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~10.'2.'2 - Pocket Ionization Chambers: These will be changed and iead: daily.
~
10.3 Organizations Furnishing Dosimeters 1
~ 10. 3.1 Badges - Either of these companies will be contracted for Dosimetry services l.
^
1601 'Irapelo Road A.
Tracerlab-l Waltham, Massachusetts 02154 Tel. (617) 894-6600 Ext. 363 i-B.
ICN Dosimetry Service ICN Pharmaceuticals, Inc.
26201 Miles Road l.
Cleveland, Ohio 44128 Tel. (216) 831-3000.
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Toledyne Isotopes 50 Van Buren Avenue-Westwood, New Jersey 07675 i
(201) 664-7070-l 10.3.2 - Pocket Ionization Chambers - These-willbe furnished i~
and maintained by personnel within the college.
10.4 Bio-assays-
~
The amount, frequency of use, and the fom of.'the byproduct material to be used do not justifyLbio-assays. The Radiation
- Safety. Committee will review all~ future proposals for the use i
of radionuclides. and will determine the need of bio-assays-In case the Comittee considers bio ' assays necessa.ry a' procedure
~
p will be; developed.
,. Radiation Survey Programs 11.
L 111.1.'. Methods ' and Frequency of' Surveys 4
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11.1.1 Direct' Survey:
'Ihe direct survey consists' of measurement' of nonremovable icontamination and' external a, 6, Y radiation levels. Working.sur-
' dacesinthelaboratorieswhereradioisotopesintheliquid'forn are being used will be scanned using appropriate survey meters.
This survey will be done monthly or bimonthly,-depending 'on the t
concentrations being handled in the laboratory.
11.1.2J'-Survey for Removable Contamination:
Standard. smear techniques, i.e. wiping. a surface of 100 cm2
- with a-filter paper, using moderate pressure and then counting the 7
activity-of the filter paper in an appropriate instrument will be used in'the survey for removable contamination.
' The survey will be performed bimonthly.
The smears will be~ counted in a gas-flow proportional counter when
.looking for high energyLBeta, Gama and ' Alfa emitters.
A' liquid scintillation counter will be,used for counting the smears taken in those areas'where C-14, H-3, P-32 and other low energy Beta emitters are'used.
12 - Acceptable-Limits
- 12.~1 Radiation Levels:
The' principle of maintaining radiation exposures. as low as=prac-
.ticable'and within the guidelines provided in 10 CFR Part 20.101 will be followed at the College.
No radiation worker must receive more than 2.5 mR/h'r or more than
~
100:mR in five~ consecutive working days or 5000 mR>in'any one calendar =
~
!yeari 12.2 -Contamination'. Limits:
ja. ; Specific cleanup is required.in any area whereLa wipe-test-
"shows:200 dpm above background.
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A level above 1000 dpm defines a contamination _ zone which will be specially restricted until decontamination is ac.complished and released by the Radiation Protection Officer.
- 13. Record-Management Th'e radiation protection officer is responsible for the records
. involving surveys, inventories of licensable materials, personnel exposures, and receipt,-use and disposal of licensable materials.
Records are reviewed on a monthly basis. The fonns used in the reconi-keeping are attached in Appendix A.
- 14. bbterial Control Provisions Acquisition and use of Radioactive Materials The following procedures are to be followed in the acquisition and use of any radioactive material. In developing these procedures every attempt has been made to achieve simplicity, while at the same time complying with all applicable regulations and requirements of '
~
radiation safety.
14.1 Authorization of Experiments and Operations 14.1.1 All experiments and operations involving the use of radioisotopes within-the College shall have a prior.
written approval from the Radiation Safety Committee.
14.1.2 ~All experiments proposed will be'submittedLto the Committee using HP0 Form-004* within no less than four I
weeks prior to expected date that the experiment will-
. start.
- NOTE - Forms used in Materials Control Program are attached in Appendix'A.
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.-14.1.3JThe Censnittee will review all proposals as.soon -
as possible and sha11' notify the results to the requisitioner"using the space provided in HPO
-Form-004.
14.1.4 Experiments that will bela repetition of a pre-viously approved'one, only need approval from'the Radiation Protection Officer.
14.1.5 The requisitioner is responsible for providing to the Comittee all the information, related to the' experiment being revised, that-the Committee con -
siders necessary for a better evaluation of it.
14.2 ' Radioactive Material from Outside the College: Purchasing
~
14.2.1 Only those. individuals who have been approved by the Committee are permitted'to acquire, by what-ever means, radioactive materials from outside the. College.
A. request for procurement is :ini-tiated by submitting two' copies ~ of HP0 Fonn-001:
~
to.the; Radiation. Protection Officer. If the.
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- appli tion is. approved, the Radiation Protection Officer. will return one. copy. of. it bearing an
, approval number; Thistndmb'er,' valid for the current e
' fiscal year, will authorize;the-procurement of the
' listed radioisotopes in the amount, 'fonn,'and for
^
the:use specified in the application.- If the pro-posed acquisition or use is Onacceptable from a safe-4
' ty; standpoini, the Radiation' Protection Officer will consult promptly with.the.originatorLto determine the
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modifications needed in order to' satisfy safety.
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Page 45 requirements. When an approved user desires to acquire radioactive material as specified on ap-
. proved HPO Form--001~, he will submit to the Radia-tion Protection Officer HP0 Form-002-in triplicate, together'with the standard College purchase requi-
-sition form. When the request is approved the Radia-tion Protection Officer will:
a.
Return one approved copy of HP0 Form-002 to the requisitioner.
- b. ' Note approval on the-purchase requisition and one copy of HPO Form-002'and-forward it through the corresponding administrative channels to the
. Procurement Office for processing. The; Procure-ment Office will not initiate procurement of any radioactive material without this approval.
- 14.2.2 All incoming radioactive materials shall be delivered to the Radiation Protection Officer. Upon receipt of a shipment, the Radiation Protection Officer will:
a.
Check the shipping data against the' amount requested.
b.
Monitor the package and any inner containers for surface contamination or breakage.
c.
Where possibic, make at least a rough check on the activity received.
d.
Fill the corresponding blanks in'HPO' Form-002.
e.
If acceptable, deliver the material promptly to the
' requisitioner..
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Q Page 46 14.2.3 Specific Responsibilities and Duties 14.2.3.1 Purchasing Department:
The purchasing department is responsible for:
- a. Withhold Processing of all requisitions or other procurement. documents related to the acquisition of Radioactive materials by any College personnel unless the acquisition is approved by the Radiation Protection Officer.
b.
Call the Radiation Protection Officer in case of any doubts about the radioactivity of any item to be purchased or acquired by members of the College.
14.2.3.-2 Property Office:
All materials, equipment, etc., purchased or acquired by members of the College staff will be delivered to the property office. For this reason, the property office plays an important role in the control of radioactive mterials arriving at the College.
The property office shall notify the Radiation Pro-tection Officer of the arrival of all radioactive materials at the College. The packages bearing " Radio-active" warning labels shall not be delivered' to any person but the Radiation Protection Officer.
14.3 Radioisotopes Transfer DOT regulations control the transport of radioactive materials. No transfer of radioactive material by air or land nost be made without.the supervision and approval:
of the Radiation Safety Officer.
1
O O
rese 47 r
14.3.1 Transfer within the College No custodian of radioactive s terials shall transfer custody within the College without the approval of the Radiation Protection Officer.
.This approval is requested by submitting lip 0 Form 003. Approval will be granted only if the receiver is an approved user of that particular material. Upon receiving approval, the radio-active material will'ae given to the Radiation Safety Officer to accomplish the actual transfer.
Such transfer will be made in compliance with all NRC,. College and local authority applicabic regulations. The above regulations apply both when radioactive materials are being transferred from one custodian to another, and from a place approved in HPO Fom-001 to another not so approved.
14.3.2 Transfer Outside the College 1
The Radiation Protection Officer must be notified by means of lipo Form-003 of any desired transfer of radioactive materials to a person outside the College. The license status of the intended
, recipient will be detemined. If the recipient is qualified, the sender will be promptly notified.
The Radiation Protection' Officer will supervise-the packaging and shipment to insure compliance with all DUr and NRC regulations.
l
Page 48 14.4 Radioisotope Inventory
~
With the exception of certain 1ow activity sources i
which may be exempted by virtue of CFR 10 Part 30.70, 1
i all radioactive materials under the College's custody will be carried on an inventory list maintained by the Radiation Protection Officer. The officer will make inventory checks every six months in order to determine the isotopes in stock, the activities remaining, the amounts used and the amounts disposed of as waste.
It is recognized that a high accuracy cannot be achieved on some items, however, each custodian is responsible i
for making the best estimates in cases wL2re exact fig-ures are not available.
- 15. Waste Disposal Each radionuclide decays at its own characteristic rate and nothing that man can do will change this rate. For this reason, strict regulations govern the disposal of radioactive materials'. The~ Radiation Protection Officer is responsible for the ultimate disposal of all radio-active wastes. The following simplified regulations apply to all users:
15.1 No person shall discharge any radioactive waste into the city sewage system without the approval of the Radiation Protection Officer.
15.2 Under no circumstances shall radioactive material be discharged into regular waste containers or other containers which would cause contamination of the regular trash.
'I l
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i y
Page 49 15.3 Each user must' assure that there is a radioactive waste
.o can, properly identified, in the laboratory where radio-
! active materials will be used.
If there is no such can, call the Radiation Protection Officer to acquire one.
15.4 Handle' all radioactive materials over: surfaces covered with ab' sorbent paper or any other paper that absorbs any spills and can be easily disposed oI.
15.5 Keep all radioactive; wastes to the minimum volume,techni-cally possible..
15.6 Each user shall request-from the Radiation Protection Officer a container for radioactive liquid waste, and use it in an appropriate way.
15.7 Each user nust make a good estimate of the radioactive material deposited in the waste containers..The isotope, date and approximate activity of the wastes must be recor-ded in a safe place.
15.8 Wastes will be collected at regular intervals or_upon request.
15.9 The radiation Protection Officer must be notified promptly
. if there has been any accidental violation of any of the regulations in this or any other.section of the Radiation
. Protection Guide.:
15.10 The Radiation Protection (Officer will store and dispose
'of all wastes as indicated in, Item 15.
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Page 50 J
w
'16.
Leak Test Provisions 16.1 Smear Test Scope - Detect any radioactive material that can pass through a leak hole and be' deposited on the outer surfaces of the sources where it can be detected as transferable contamination.
16.1.1 Take all necessary precautions to minimize exposure of person performing the test.
16.1.2 Wipe thoroughly (no attempt shall be made to scrub) all accessible surfaces of the source using a piece of filter paper, a cotton medical applicator or other suitable material of high absorptive capacity. The material could be wet but not necessarily.
16.1.3' Count the activity in. the wiping material in the gas-flow proportional counter. Set the counter in the appropriate operating voltage according to the conta-mination expected ( a,' 6, y).
16.2 Person to perform the leak test - Ms. Nimia E. Irizarry Radiation Protection Officer, (see section 4). Experience in Leak Testing, 4 years.
16.3 Frequency of Tests Every six months.
16.4 Instrumentation used for counting wiping material 2 -; Gas Flow Propertional Counter (Nuclear Meas:.rement Corp.)
~.Model PCC-11T-DS-1T Combination
- These counters are able t'o_ detect less; than 0.005 gCi o(
activity.
4 5
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Page 51
- 17. Emergency and Decontamination Procedures 17.1
. Radioactive Material Spills Scope: Advise individuals working with radioactive materials on the proper way to respond to emergencies involving spillage of radioisotopes and prevent the spread of the contamination to other areas.
17.1.1 Minor Spills
- a. Notify all other persons in the imediate area at'once.
- b. If it is 'a liquid spill and your hands are protected, put the container in upright position.
- c. Cover the spill with absorbent paper.
- d. Limit access to the area to only those persons necessary to deal with the spill.
- e. Survey personnel in the area for possible contami-nation and decontaminate when necessary.
- f. Notify the Radiation Protection Officer as soon as possible. Tel. 832-1414 Ext. 245.
- g. Make a written report to the Radiation Protection Officer explaining the incident and the action taken.
w
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/^T-(vO Page 52 O
l
, 17.1.2 Major Spills a.
Notify all persons not involved in the spill to vacate the room at once. Limit the movement of persons to confine the spread of contamination.
b.
If. the' spill is liquid and your hands -
are protected, right the~ container, other-wise use a stick.
c.: Cover the spill with absorbent paper.
d.
Switch off all fans.
e.
Vacate the room if possible, f.
Notify or have one notify the Radiation
~
Protection Officer.
- g..If the spill is on the. skin, flush thoroughly.
h.
If the spill is on clothing, discard outer or protective clothing ~at.once.
- i. Monitor all persons involved in the spill and initiate decontamination of personnel
- as necessary.
.j.. Contaminated areas shall not be occupied and contaminated personnel shall.nct Le released until clearance by the Radiation Protection Officer is granted.
k.
hbke'a written report to the Radiation Protection Officer. with the' complete history of the-incident and the action taken.
1 a
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Page.53'
-(
- 17.2-. Fire Plan Introduction 17.2.1 The following. Fire Plan has been prepared to provide organized piutection to persons working in areas.where radiositopes'are used.
It shall not be considered as the Fire Plan for all.the' College facilities but shall be supplementary to it.
No fire, no matter how small, should be treated lightly. Prompt action is important; it is equally important to avoid panic.
The most effective Fire Plan is that one ' designed I
to prevent fires from starting. Plan all
. laboratory procedures carefully,. maintain all equipment in safe operating condition and keep the storage of flammables to the minimum, consistent with efficiency.
17.2.2 Fire in the laboratory or adjacent areas. An occasional'small-fire may occur which an individual imediately present is absolutely.
sure he can extinguish..He should'do so and.'then report the incident promptly to the: supervisor and/or the College Guard. "All other fires should be handled according~to the' regulations given here.
5 4
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i Page 54 p
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.17,2. 2.1.
First person to'see' the fire:
a.
If there is~ a fire alam box in the vicinity,
. pull it.
b.
If there is no fire alarm,' call or have some-one call the-College Guard and the City Fire Department.
c.
Disconnect or turn off electrical equipment
.and secure radioactive materials in a. safe place; provided that there.is no risk of personal danger.
d.
Inform the persons in the vicinity ' nd ask a
them to vacate the' area.
- e.. Stay'near the area ~until the College Guard
. or-the firemen _ arrive,'as long as there is no risk of. personal danger.- Advise.them ofl the presence:of radioisotopes in the area.
f.
Infome the Radiation' Protection Officer and aid'in the' survey for spills or co$taminants after, the fire has been~ contro11ed'.
~
g.
Write' a report on the incident' and-submit -it
[to the Radiation Protection Officer.
17.3 ' Radioactive Materials Handling No exposure guide or permissible dose should be1consideredL
- as an allowable outer limit which~ can be' approached with complete safety. Every practical effort must be made to keep exposures as far below the guides ~as'is consistent
- .with program efficiency and economy..The' Radiation Protection Officer andlthe Radiation' Safety Comittee will assist in J
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Page 55 detennining the laboratory ' areas in which certain operations can be~ carried out and will assist in planning procedures that will minimize personnel exposures. A continuous monitor on procedures will be.provided where this seems indicated.
17.3.1 Designation of Areas NRC regulations carefully define certain areas with respect to radiation sources.
17.3.1.1
. An unrestricted area is an area into which access is not controlled for the purpose of protecting individuals from radiation exposure.
17.3.1.2 A restricted area is an area into which access is controlled for the purpose of protecting individuals from radiation exposure.
-17.3.1.3 A radiation area is any area where an individual could receive to a major portion of his body a dose greater than 5 mrems in one hour or 100 mrems in five consecutive days. Each radiation area is conspicuously posted with a sign or signs in English and/or Spanish bearing the words:
CAUTION RADIATION AREA orPELIGR0 AREA DE RADIACiCN
17.3.1.4 A high radiation area is any area where an indivi-dual could receive, to a major. portion of his body, a dose greater than 100 mrems in one hour.
Each high radiation area is conspicuously posted with a sign or signs in English and/or Spanish bearing the words:
+
CAUTION HIGH RADIATION AREA or PELIGRO AREA DE ALTA
)
RADIATION"
.C1 O
rese se 17.3.1.5 Areas where licensed materials are stored and which contain any radioactive material exceeding 10 times the quantity of such material specified in 10 CFR Part 20 Appendix C are conspicuously posted with signs bearing the radiation caution symbol and the words in English and/or Spanish:
CAUTION "PELIGR0" or RADI0 ACTIVE MATERIALS 4!ATERIALESRADI0ACTIVOS*
17.3.2 Radiation Symbol a.
Cross-hatched area is to be magenta or purple, b.
Background is to be yellow.
c.
Words added shall be black.
17.3.3 Laboratory Practice It is not possible to present in detail all of the techniques and procedures applicable to the proper use of radioactive materials. Some of the most im-portant requirements,are given below. The Radiation Protection Officer and/or the Radiation Safety Commit-tee will review special cases and will supply detailed i
information upon request.
17.3.3.1 Each entrance into an area where radioactive materials i
i are used or stored in such a manner as to make that area l
~
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a Radiation Area,-or High Radiation Area, etc., shall be conspicuously marked with a sign identifying the area in accordance with the definitions given above.
The signs shall remain in place as long as the area conforms with the definitions. Signs will be removed by the Radiation Protection Officer only after appro-priate radiation surveys.
17.3.3.2 Containers in which radioactive materials are being sto m d or transported shall be appropriately marked with-labels or decals available from the Radiation
~ Protection Officer. Each label or decal shall -iden-tify the nuctJo, give the activity within the container, the date of the activity estimat'e and the initials of the responsible custodian. This labeling shall not be required for laboratory containers such as b5akers and
. flasks being used in laboratory procedures during the presence of the user.
- 17.3.3.3 Stock solutions or sources in use may.be kept in.a lab-oratory area inside sufficient' shielding to reduce' the exposure dose-rate at the closest access point outside the shield to 1 mR/hr. The shield should be posted as a " Radiation Area". or a' 'High Radiation' Area", as appro-priate, even 'though a major portion of a body could not
-be exposed inside the shield.
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Page-58
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f 17.3.3.4 Manipulations involving' radioactive materials
.shall be carried out inside hoods as far as 2
is practicabic.
~ 17.3.3.5 =
'As' extensive use as'possible should be made of
^
fprotective, devices such as trays, glass plates, or absorbent paper'in order to prevent contami-nation of pennanent' building structures such as
~
~
bench tops, hoods, and floors. Absorbent. paper l
should be discarded frequently to prevent the dusting off of spills that have dried.
~
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- 17.3.3.6 Each~ user of radioactive nuclides shall make periodic surveys of his area to search for contamination.
17.3.3.7.
No detectable contamination.of any basic building component can be tolerated. Consult the Radia-i tion Protection.0fficer upon discovery, or sus-picion, of contamination and follow instructions.
17.3.3.8 Equipment used with radioactive nuclides shall not be released to other workers, sent 'to 'a' shop for repairs or modifications, or to surplus,' and shall not be discarded until it is demonstrated
-by the Radiation Protection Officer to be free of contamination. Repairs or modifications that i
must be made on contaminated equipment.shall be
?
~
done under the supervision.of the Radiation Protec-l.
. tion Officer.
- 17.'3. 3. 9 No maintenance work'or repair shall be made on j _
1any laboratory sink traps or waste lines 'or on
~
any hood ducts, exhaust systems, or house vacuum i
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V lines until the areas involved have been cleared by.the Radiation Protection Officer.
17.3.3.10 ' Protective gloves of surgical rubber or dis-posable plastic and lab coats should be worn when working with radioactive materials.
17.3.3.11 Protective equipment such as laboratory coats, surgical or disposable gloves etc., should not t
be worn outside the laboratories or working area.
17.3.3.12 bbchanical pipette-filling devices'shall always be used with radioactive solutions. Never Use 1
the Mouth to pipette Radioactive Solutions.
17.3.3.13 Smoking,' eating, drinking, and use of cosmetics are forbidden in areas where radioactive nuclides are used.
17.3.3.14 Liquid radioactive wastes shall not be put into the regular. laboratory sewerage system unless they are known to conform to the' requirements specified by the Radiation Protection Officer.
17.'3.4 Decontamination Practice
'17.3.4.1 Equipment Decontamiaation When equipment has been contaminated, a decision must be made as to whether it is most advantageous to' discard,- set aside for decay, or to decontand-nate.
If to be discarded such equipment shall
]
be considered as radioactive waste and shall be turned over to the llealth and Safety Division will also assist in storing equipment during decay to nsafe levels.
Paga 60-i e
I
~It.is usually advantageous to start decon-tamination procedures promptly. Delay frequency fixes the contaminants more firmly onto surfaces. During' decontamination pro-
- cedures protective gloves shall always be worn, 4
supplemented by' protective clothing if it is indicated.
In general. the user can, choose the most effec-tive decontamination procedure from a knowledge of the properties of the contaminant. The Radiation Protection Officer will provide advice, materials and assistance in refractory cases, and will. supervise disposal of the clean-ing materials.
17.3.4.2 Personnel Decontamination hhen radioactive nuclides come in contact with.
the skin the radiation dose-rate.at the contaminated area may be very high.
In addition,'many contami-nants are in form that are readily absorbed through the intact skin, and, to a auch greater i
extent, through cuts and abrasions. Any contami-nating' event must be. considered to create'a situat. ion requiring prompt attention. Whenever there has been any. personal contamination, the Radiation' Protection Officer should be called at once to assist in the decontamination. -When large areas of the body are involved, showering may be required,-' utilizing the.special decontami-e b
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nation room.
N-
.Without waiting for Health' and' Safety Division assistance to arrive, start washing procedures at once. Locate the area of contamination
^
Ewith a survey meter. Wash thoroughly using
~
.any available soap or detergent. Washing should l
be vigorous but care should-be taken not to
~
~
K injure the skin.by too-harsh treatment. A soft britlebrushmaybeefibctive. Recheek at inter-
- a vals with a-survey meter to' note any improvement.
u If progress is negligible, -a chelating ~ agent such i-
. as EITTA :(versene) may' be used in place of the soap. JIhe Radiation Protection Officer maintains supplies of appropriate agents. ;If contamination persists, 'the Radiation Protection Officer may call-a physician to direct the use of more drastic cleans -
y~
ing agents. -
~
. If several vigorous washings do:not. sharply reduce.
the contamination of body hair, -it -should be cut-9 short,. using extreme care not to injure -the. intact skin.
Removal of the hair will pennit more effective treatment of the underlying skin.
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Solid'~ wastes b.
Liquid wastes 18.2 For Technicians, Students, Supervisory Personnel and other similar, Personnel.
18.2.1 Fundamentals of radiation a.
What is radiation?-
b.
Types of radiation.
~
- c. ;Why is radiation a health hazard?
d.
Radiation units.
t18.2.2-External exposure e
a.
Whole body irradiation.
b;. ' Source in normal form and special form,.
Precautions against external exposures, time,-
c.
, distance, shielding.
+
.18.2.3 Internal ' exposure j
a.
Entry into the body..
b.
Inhalation, ingestion, skin absorption.
18.2.4 Contamination and decontamination a.--External contamination.
b.
Internal contamination.
c, ' Decontamination procedures.
'18.2.5 Radiation protection standards a.
Personnel monitoring devices
~
b.
The exposure report - what it means; c.
Maxinum permissible levels.
d.
Restrictions ' (pregnancy, ' etc.).
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~
. a.s I. Survey 1 meters 3
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18.2.7!: Radiation protection methods-oc m.
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18.~2.8f. Radioactive waste disposal.
n, a.
Containers.-
b.
Solid wastes.
~
.c.
Liquid wastes.
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- 18.2.9 Emergency procedures y
-18.2.10.: Health protection fonns t
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APPEllDIX A HEALTH PHYSICS FORMS 5
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HPO-FORM UNIVERSITY OF PUERTO RICO - MAYAGUEZ CAMPUS Approval No.
001 APPLICATION FOR RADIOISOTOPE PROCUREMENT A.
Submit two copies to Rad 3ation Protection Officer.
B.
Each approved application is valid only for the user, radioisotope, millicurie amount, application,. location and current fiscal year.
C.
All requisitions for the purchase or procurement of radioisotopes must be ac-companied with form 002 and must be directed to the Radiation Protection Officer.
D.
All radioisotope transfers between approved users must be preceded by completion and approval of supplementary form 003.
E.
Radioactive waste will be disposed by the Radiation Protection Officer.
1.
Na.m, dept., college address and extension of applicant performing immediate sulervision of laboratory operations.
2.
Brief past experience and training of above named individual in the use of radioisotopes.
e 3.
Name, dept., college address and extension, and radioisotope experience of individuals using the produced radioisotopes under applicants supervision (if student, so state).
4.
Radioisotope 5.
Physical and chemical form
- 6. Other potential hazards 7.
Activity limits mci, maximum to be used in a single experiment mC1, estimated to be ordered per shipment mci, estimated to be ordered per fiscal year 8.
Will the radioisotope be used in humans?
Yes ( )
No ( )
(continued on reverse side) i
Q o
9.
Proposed procedures: (as detailed as possible, including concern for other hazards, rooms involved for usage or storage, etc.
If any of these rooms are not under the direct control of the applicant, please indicate).
k:
a 10.-
Monitoring instruments available in the innediate area.
a
' 1 1.
Name and address of supplier.
Radiation Protection Officer will be the recipient of all radioisotopes and will.
deliver them to the applicant after performing an appropriate survey.
12..
Signature of Applicant Date N
13.
Signature of Approval by Radiation Protection Officer Date Expiration date of this Authorization:
June 30, 19
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HPO-FORM 002~
l UNIVERSITY OF PUERTO RICO - MAYAGUEZ CAMPUS RADIOISOTOPE CONTROL
[
1.
Purchase Order No.
Approval No.
~
2.
Requisitioner Dept.
3.
Arrival Date Time Carrier 4.
'*RPO Notified Yes ()__ No ( ) Date Time 4
=5.
Person that Notified-
)
1 l
(TO BE FIT.Tyn BY SURVEYOR) r
'6..
Survey Date Time Surveyor
)
7..
Condition of Package Good ( ) ; Punctured ( )
Stained ( ) ; Crushed ( )
\\
Wet ( ); Other ( ) _
j.
8.- Radiation Level: Maximum mR/hr (
);
mR/hr on Contact (
)
mR/hr at 1 Meter (
)
9.
Do Packing List and Package Contents Agree?
Radionuclide (_)
Yes If No, Explain Difference Amount
. (_)
Yes Chemical Form (_)
10.
Smear Results Contaminated ( )
Not Contaminated (_)
Contamination Level dpm Where Contaminated 11.
If Package was Shipped with Dry Ice, was Dry Ice Present in Package at the Time
' of the Survey? Yes ()
No ( ) N/A ( )
12.
Final-Disposition of Package 13.
Delivered To:
Date CERTIFIED CORRECT:
Surveyor's Signature
?
Receiver's Signature
- RPO-Radiation Protection Officer I*
Original to Radiation Protection Officer; Duplicate to Requisitioner; Triplicate to Property Office.
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HPO-FORM.003
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. UNIVERSITY OF PUERTO RICO - MAYAGUEZ CAMPUS RADIOISCfrOPE TRANSFER PERMIT 1.
Requisitioner Dept.
Date
- 2.. Present Custodian Dept.
3.
New Custodian Dept.
i i
- 4..~Present-Storage Location 5.
Proposed New Storage Location 6.
. Description of Material to be transferred Quantity 7.
Description of Container 8.
. Proposed Date for transfer
- 9. ' Person to do the transfer 10.
Remarks t
The requisitioner. certifies that the new custodian is authorized by the Radiation Safety Committee to use radioisotopes in the form described above.
Date Signature (TO BE FILLED BY THE RADIATION PROTECTION OFFICER)
Permit Granted Yes (
)
No (_)
If No, state reasons Date of transfer Transferred by CERTIFIED CORRECT:
Radiation Protection Officer's Signature New Custodian's Signature Original to Radiation Protection Officer; Duplicate to Requisitioner, Triplicate to new Custodian.
HPO-FORM 004
~.
UNIVERSITY OF PUERTO RICO - MAYAGUEZ CAMPUS RADIOISOTOPE USE PROPOSAL
'~
- 1. ' Name of Person Submitting Request 2.
Date of Submission Date Experiment Will Start-3.=
Radioisotope (s) to be used Form Amount For How Long?
-4.-
Is the Radioisotope to be Purchased? Yes ( ) No. ( )
If No, Where it Comes From?
- 5. 2 Persons Involved in the Experiment
.6.
Location of Experiment 7.
Description of Experiment (To be Filled in the Radiation Safety Committee Meeting) 8.
Date of Meeting Time-
- 9.. Members Present 4
t i
2
- 10.. Experiment Approved Yes ()
No ( )
If No, State Reasons i
i 11.
Approved with Restrictions. Yes ( ). No ( )
Restrictions i
CEIEIFIED CORRECT:
I Chairman's Signature Original to. Radiation Protection Officer, Duplicate to Requisitioner, Triplicate
-+
.to Radiation Safety Committee File.
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HPO-FORM 005 n
UNI TY OF PUERTO RICO - MAYAGUEZ JUS NOTICE OF ARRIVAL AND DEPARTURE (To be Completed by Supervisor) ected Date of NAME POSITION DIVISION Arrival & Departure Supervisor:
Date (To be Filled by the Radiation Protection Officer NAME FMI NO.
MI NO.
REMARKS NOTE: If no FMI or MI is needed write under FMI and MI no. Explain under Remarks.
If Mi is needed put a check mark under FMI and MI and write film badge number assigned next to FMI.
Do the same for pocket memters.
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B D T C D R
t 0-O APPENDIX B CALIBRATION RFf0RDS OF Pu-Bo SOUPfES AND ALPilA SOURCES 6
S s
4 l
e a
b
_ _ _ _ _ _,,, _ _ _ _l
Plutonium Neutron Source Calibration Data
~
Source - M /87 Date of calibration - NM 4 /f4/
Total neutron emission (Q) - 45///4 neutrons /second Compared with. Mound Laboratory source M-977 PLC response
.andard PLC respen ( to s M e being calibrated Standard error of comparison with Mound Laboratory source is thought.to be 2 7..
)
Anisotropy #
f (O') - O,9 6(90*) - /,0(
((180*) - O, f Isotopic analysis of plutonium used in this source.
(Isotepic analysis of plutonium used in some sources is not available.)
Weight of Plutonium -
239 Pu AN Pu240 -
pM Ip 241 Nd Pu Am241,
. Date of analysis -
- determined from measurements of this source
- typical for sources of this approximate size and shape e
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Plutonium Neutron Source Calibration Data
^
d Source _ y 7g g Date of calibration - N/>r 2 4 / 9 4 2.
Total neutron emission (Q) -
/.5 3 X/d '
neutrons /second Compared with Mound Laboratory source M-977 PLC response to standard
, jgg PLC. response to source being calibrated Standard error of comparison with Mound Laboratory source is thought to be
/
- 7..
Anisotropy -
6 (0*) -
6 (90*) - /.o.s*3 cc. o/2 *
((160*)
Isotopic Analysis of plutonium used in this source.
(Isotopic analysis of plutonium used in some sources is not available.)
Weight of Plutonium -
(It has a total of I4.90 gm of Pu)
Pu Pu
- ##WM Pu241,
241,,
Am Date of Analysis
- determined from measurements of this source
- typical for sources of this size and shape
\\
U O
Plutoniun Neutron Source Calibration Data Source - M /ff Date of calibration - N4/. / /f4/
/
6 Total neutron emission (Q) - Aff#o neutrons /second Compared with Mound Laboratory source M-977 PLC reso and W PLC responpr. -tn:rsourchalibrated Standard error of comparison with Mound Laboratory source is thought to be
,2 7..
Anisotropy M f (0') - 04 6(90') - /,el
((180') - a f Isotopic analysis of plutonium used in this source.
(Isotcpic analysis of plutonium used in some sources is not available.)
Weight of Plutonium -
Pu239 _
/,
p[
pe240 g
f Pu'41 N0 Am241 _
Date of analysis -
- determined from measurements of this source
- typical for sources of this approximate size and shape O
m.
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Senior Ad=inistration Offi.cer Puerto 2 ice Nuclear Center
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w ycguez, Puerto P.ico c' LV. C "7 LI:thbt he,
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L EBERLINE INSTRUMENT CORPORATION j
PLUTONIUM ALPHA STANDARD CERTIFICATE SERIAL NO.
F1t'.94 The alpha particle emission rate from the active surface of the source is:
10 00 t
Pm Alpha particles / minute (2 P1)
The total disintegration rate is:
10 m hm Disintegrations / minute (4 P1) 1 The source was standardized by counting the alpha particles emitted from
(
the active surface with internal, proportional, standardization chamber.
The backscatter of alpha particles from the surface was assumed to be
)
1 "% in calculating the total (4 P1) disintegration rate.
l l l DATE:
c-tA m
- 1.
m:2 SIGNED:
e This certification valid for one year frorri above date.
I t
Re-standardization is advised after one year.
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EBERLDTE INSTRUMENT CORPORATION 1
PLUTONIUM ALPHA STANDARD
., t.
s' CERTIFICATE Ma 1
Ji SERIAL NO. Pl738 a:
7 1
The alpha particle emission rate from the active surface of the source is:
f M
P2 sm Alpha particles / minute (2 Pi) 500
,i -
i*
The total disintegration rate is:
$r-W,300 5
900 Disintegrations / minute (4 Pi) g.
?
The source was standardized by counting the alpha particles emitted from
?
m y
ia
~'
the active surface with internal, proportional, standardization chamber.
a 9
The backscatter of alpha particles from the surface was assumed to be i
a
" % in calculating the total (4 P1) disintegration rate.
1 DATE:
Octcber 28, 1963 SIGNED:
e This certification valid for one year froni above date.
Re-standardization is advised after one year, j
t i
r
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)
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~
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'?LATh EBERLINE INSTRUMENT CORPORATION 4:
PLUTONIUM ALPHA STANDARD CERTIFICATE P610 SERIAL NO.
The alpha particle emission rate from the active surface of the source is:
P'503 600 Alpha particles / minute (2 Pi)
The total disintegration rate is:
'+ W t
1.200 Disintegrations / minute (4 Pi)
The source was standardized by counting the alpha particles emitted from the active surface with internal, proportional, standardization chamber.
The backscatter of alpha particles from the surface was assumed to be 1 5 % in calculating the total (4 P1) disintegration rate.
DATE:
mwember 1,1p'3 SIGNED:
2 44/
/
This certification valid for one year froni above date.
Re-standardization is advised after one year.
8 i L
L d
LE' '
- EBERLINE INSTRUMENT CORPORATION J
- .b. ;
PLUTONIUM ALPHA STANDARD CERTIFICATE SERIAL NO.P W The alpha particle emission rate from the active surface of the source is:
3
'I m.gcc
_i 1, con Alpha particles / minute (2 Pi)
Tne total disintegration rate is:
2,000 Disintegrations / minute (4 P1) x ^, co':,
i The source was standardized by counting the alpha particles emitted from the active surface with internal, proportional, standardization chamber.
The backscatter of alpha particles from the surface was assumed to be 15 9, in calculating the total (4 Pi) disintegration rate.
DATE:
0 teter 28, 1563 __
SIGNED: A4-
/A l
\\
Stic L. G21ger 9
This certification valid for one year froni above date.
Re-standardization is advised after one year, k
s' 4
_