ML20010B968
| ML20010B968 | |
| Person / Time | |
|---|---|
| Site: | 07000756 |
| Issue date: | 07/23/1981 |
| From: | Coogan J ENVIRONMENTAL PROTECTION AGENCY |
| To: | |
| Shared Package | |
| ML20010B963 | List: |
| References | |
| 19424, NUDOCS 8108180544 | |
| Download: ML20010B968 (33) | |
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E FORM NRC-313 l U.S. NUCLE AR REGULATORY COMMISSION
- 1. APPLICATION FOR:
(3 80)
(Check rnd/or complete as appropriate) 10 CF R 30 APPLICATION FOR BYPRODUCT MATERIAL LICENSE l
INDUSTRIAL I a. NEW LICENSE See nttachelinstructions for details.
- b. AMENDMENT TO:
LICENSE NUMBER Completed applications are filed in duplicate with the Division of Fuel Cycle and Material Safety, Office of Nuclear Material Safety, and Safeguards, U.S. Nuclear Regulatory Commission' Washington, DC 205S5 or applications may be filed in person at the Commission's office at
- c. RENEWAL OF)gga g,egugg nu, 1717 H Street, NW Washington, D. C. or 791b Eastern Avenue, Silver Spring, Maryland.
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- 2. APPLICANT'S NAME (Institution, firm, person, etc.)
- 3. NAME AND TITLE OF PERSCN TO BE CONTACTED REGARDING THIS APPLICATION Environmental Protection Agency J.S. Coogan, Radiation Safety Officer TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION FTS 545-2200 FTS 545-2538
- 4. APPLICANT'S MAILING ADDRESS (includelip Codel
- 5. STREET ADDRESS WHERE LICENSED MATERIAL WILL dE USED (Address to which NRC correspondence,,otices, bulletins, etc.,
(Include Zip Code) should be sen t.)
EMSL-LV P.O. Box 15027 Same as 4.
Las Vegas, NV 89114 (IF MORE SPACE IS NEEDED FOR ANY ITEM, USE ADDITIONAL PROPERLY KEYED PAGES.)
- 6. INDIVIDUAL (S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL (see items 16 and 17 for required training and experience of each individual named below)
FULL NAME TITLE Loren E. Thor.1pson Research Chemist Earl L. Whittaker Chief, Monitoring Guidelines & Standardi-b.
tai.iun Sud.iva
- c. Robert G. Patzer Biophysicist
- 7. RADIATION PROTECTION OFFICER l A ttach a resume of person's traming and experience as outtmed in items l 16 and 17 and describe his responsibihties under item 15.
J.S. Coogan
- 8. LICENST.D MATERIAL L
ELEMENT CHEMICAL NAME OF MANUFACTURER MAXLMUM NUMBER OF I
AND AND/OR AND MILLICURIES AND/OR SEALED N
MASS NUMBER PHYSICAL FORM MODEL NUMBER SOURCES AND MAXIMUM ACTI-E (If Sealed Source)
VITY PER SOURCE WHICH WILL BE POSSESSED AT ANY ONE TIME N O.
A _
249
- 2Jd, B
C D
("
Plutonium Any 20 milligrams m
Chromium 233 Any 1 gram tal Chromium 235 Any 1 gram 236 (4)
Pu Any 5 microcuries 240 (5)
Pu Any 5 microcuries 241 (6)
Pu Any 5 microcuries 242 (7)
Pu Any 5 microcuries (4) 8108180544 810724 h PDR ADOCK 07000
r 1
i
- 9. STORAGE OF SEALED SOURCES Y
CONTAINER AND/OR DEVICE IN WHICH EACH SEALED NAME OF MANUFACTURER MODEL NUMBER N
SOURCE WILL BE STORED OR USED.
NO.
A.
B.
C.
(1)
(2)
(3)
(4)
- 10. RADIATION DETECTION INSTRUMENTS TYPE M ANU F ACTU R E R'S MODEL NUMBER R ADI ATION SENSITIVITY
{
OF NAME NUMBER AVAsLABLE DETECTED RANGE N
INST RUMENT (alpha, bets, (milliroentgens/ hour E
9'* *"'"*"I
- ' ' ""'#l*5""l 9O, A
B C
D E
F (1)
(2)
(3)
(4)
- 11. CALIBRATION OF INSTRUMENTS LISTED IN ITEM 10 Ca. CAllBRATED BY SERVICE COMPANY
@b. CAllBRATED BY APPLICANT NAME, ADDRESS, AND FREQUENCY A ttach a separate sheet describing method, frequency and standards used for calibrating instruments.
Attachment #1
- 12. PERSONNEL MONITORING DEVICES (check and/or compi$te as appropriate.)
(serv ce c$any)
EMHMGE WEQUENCY C
A B
N(1) FILM DADGE
- 11. Reynolds Electric & Engineering x-)uONTHey Co., Inc. - DOE contractor QC l2) THE RMOLUMINESCE NCE
- 12. EPA EMSL-LV O QUARTERLY b
DOSIMETER (TLD)
L)s (33 OTHe R (sp,c,fy;,
Whole Body
- 13. EPA EMSL-LV o 07H e R (sp,c,,,;,
_Countinq FaCilitv
- 13. FACILITIES AND EQUIPMENT (Check were appropriate and attach annotated sketch (es) and description (s).
@ a. L ABOH ATOR Y F ACILITIES. PLANT F ACILITIES, FUME HOODS (/nclude te/tration, if any), ETC.
@ b. STOR AGE F ACILITIES CONTAINE RS. SPECI AL SHIELDING (fixed and/or temporary), ETC.
Q c. REMOTE H ANDLING TOOLS OR EQUIPMENT, ETC.
Q d. RESPIRATORY PROTECTIVE EQUIPMENT, ETC.
- 14. WASTE DISPOSAL
- a. NAME OF COMMERCI AL WASTE DISPOSAL SERVICE EMPLOYED Department of Energy, Nevada Test Site Disposal Site.
- b. IF COMMERCI AL WASTE OlSPOSAL SERVICE IS NOT EMPLOYED, SUBMIT A DETAILED DESCRIPTION OF METHODS V,ritCN WILL BE USED FOR DISPOSING UF R ADIOACTIVE WASTES AND ESTIMATES OF THE TYPE AND AMOUNT OF ACTIVITY INVOLVED. IF THF APPLICATION IS FOR SE ALED SOURCES AND DEVICES AND THEY WILL BE RETURNED TO THE M ANUFACTURER,SO STATE.
FORM NRC-3131 (3 80) h J
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lNFORMATION REQUIRED FOR ITEMS 15,16 AND 17 Describe in detail the information required for items 15,16 and 17. Begin each iterr, on a separate page and key to the application as follows:
15.
RADIATION PROTECTION PROGRAM. Describe the radiation protection program as appropriate for the material to be used including the duties and responsibilities of the Radiation Protection Officer, control measures, bioassay procedures (if needed), day-to-day general safety instruction to be followed, etc. If the application is for sealed source's also submit leak testing procedures, or if leak testing will be performed using a leak test kit, specify manufacturer and model number of the leak test kit.
16.
FORMAL TRAINING IN RADIATION SAFETY. Attach a resume for each individual named in items 6 and 7.
Describe individual's formal training in the following areas where 6pplicable, include the name of person or institution providing the training, duration of training, when training was received, etc.
- a. Principles and practices of radiation protection.
- b. Radioactivity measurement standardization and monitoring techniques and instruments.
- c. Mathematics and calculations basic to the use and measurement of radioactivity,
- d. Bio;ogical effects of radiation.
17.
EXPERIENCE. Attach a resume for each individual named in items 6 and 7.
Describe individual's work experience with radiation, including where experience was obtained. Work experience or on-the-job training should be commensurate with the proposed use. include list of radioisotopes and maximum activity of each used.
- 18. CERTIFICATE (This item must be completed by applicant)
The apolicant and any official executing this certificate on behalf of the applicant named in item 2, certify that this application is prepared in conformity with Title 10. Code of Federal Regulations.
Part 30, and that a!! informat.on contained herein, including any supplements attached hereto, is true and ccrrect to the best of our knowledge and belief.
WARNING.-18 U.S.C., Section 1001: Act of June 25,1948; 62 Stat. 749; makes it a criminal offense to make a willfully falso statement or representation to any department or agency of the United States as to any matter within its jurisdiction,
- a. LICENSE FEE REQUIRED
- b. CERTIFYING OFFICI AL (Signature)
(See Sectinn 170,31 10 CFR 170)
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- c. N$MG ifType or prmt)
/ J.S. Coogan (1) LICENSE FEE CATEGORY:
Radiation Safety Officer e.DATE (2) LICENSE FEE ENCLOSED: $
July 23, 1981 FORM NRC 313 i G80)
'4, CONTENTS OF APPLICATION 1.
The correct address is:
Environmental Protection A gency Environmental Monitoring Systems Laboratory-Las Vegas 944 E. Harmon Avenue Las Vegas, NV 89114 2.
Formula as listed equally less than 1
<1 1 gr U-235 + 1 gm U-233 +.135 gm Pu
=
350 200 200 Sealed Plutonium Sources for Instrument Calibration Eberline Sealed Pu Source Set (5) Serial #P-1005 Disintegration / minute 2H 820 3,770 4
23,300 210,100 2,913,700 Eberline Sealed Pu Source Set (1) Model S-94-1 2 microcuries Eberline Alpha Standards for Alpha 3 Air Samplers (2)
Model DNS-16 26,000 disintegrations per minute 4H 26,000 disintegrations per minute 4H Plutonium 0xide (poly-disperse particulars) 238 239 Pu and Pu 280/1 mass ratio 238 239 Pu and Pu 9.3/1 mass ratio mci g3[
i 238 Pu 70.4 4.09 i
239 Pu 6.6 107.5 71.0 111.59
S.
. 3.
Attachment #2 ives a resume of training and experience of the Radiation 3
Safety Committee members. Members require a protocol prior to initiation of an experiment for review.
One or more members are present during the conduct of an experiment.
RADIATION SAFETY PROGRAM The Radiation Safety Program is structured along the same lines as the Health and Safety Program. Mr. John S. Coogan is the Radiation Safety Officer.
The Laboratory has a Radiation Safety Committee which consists of the following:
Richard L. Douglas Chairman John S. Coogan Radiation Safety Officer Maxwell E. Kaye, M.D.
Medical Officer Wayne Bliss Member Joseph Hans Member James Payne Member Jack Thrall Member Earl Whittaker Member When a research scientist plans an experiment that includes radioisotopes, he first writes a protocol which is submitted to the Radiation Safety Officer.
He makes sure that our Byproduct Material License allows us to possess this particular isotope and in the quantities the scientist wishes to use.
Each month the Radiation Safety Committee meets and studies and discusses any protocols that have been submitted. After it has been approved, Health Physics assistance is assigned to the project, provision is made for bioassays, samples and whole body counting of the people involved, and radiation monitors are assigned.
For day-to-day radiation safety in the labs, we have a Radiation Safety Manual that is available in each lab for the use of the personnel.
A routine inspection of the laboratory is performed with smear samples of the entire facility taken on u monthly basis.
All radioactive source material is received in the Radiation Safety Office, i
numbered and an isotopic inventory is maintained by computer program through our Laboratory.
Dosimetry records, bioassays results and whole body counts are performed on routine intervals and results maintained in the Radiation Safety Office.
o,
. LABORATORY BUILDINGS The Envirormental Monitoring Systems Laboratory-Las Vegas (EMSL-LV) has a present operation at 944 East Harmon Avenue. Consisting of five modern structures expressly designed to meet its specific requirements, four of the buildings are single story and used for research,-development and analysis in the fields of chemistry, physics and biology. An experimental farm and laboratory complex is located at Energy Research and Development Administration's Nevada Test Site in Mercury, Nevada.
Each of the five buildings in the complex is separately connected to a public sewer system. The estimated effluent discharge from the buildings is as follows:
Exposure Assessment Annex 10 - 20 GPM Exposure Assessment Laboratory 40 - 50 GPM Monitoring Systems Laboratory 15 - 25 GPM Executive Center 15 - 25 GPM Chemistry Laboratory 40 - 50 GPM All laboratory buildings are provided with acid neutralizing and cleanout traps.
AIR CONDITIONING SYSTEM The air conditioning system in all buildings is a conventional-ducted, air-type operating from a central fan room. Approximately 65% of the air is recirculated to all areas. All buildings are divided into zoned areas for the purpose of control. With few exceptions, the return from all zones is common to all zones.
The intakes to the air handling equipment are located on the sides of the buildings with the exception of the Exposure Assessment Annex whose intake is located on the roof. All of the intakes are fitted with louvers which are oriented downward. All the air handling equipment is fitted with paper-type filtration equipment which eliminates extremely small particle sizes. The filters are inspected and changed about once a month.
All laboratory buildings are provided with Permablab constant velocity fume hoods with make-up air supply.
These hoods are vented through the roof, through common exhaust fans in the Chemistry Lv, oratory and through separate exhaust fans in the Exposure Assessment Laboratory where perchloric acids might be used. The exhaust fans are mounted on the rcof and are surrounded by a solid plywood fence. There is no danger from cross-contamination between hood exhaust and buildings air conditioning intakes.
. LABORATORY FURNITURE All laboratory furniture is constructed of steel with baked enamel finish as manufactured by Pennalab Furniture.
Bench tops are of synthetic stone.
BUILDING FINISH MATERIALS Flooring is either asphalt tile on a concrete slab or epoxy paint on concrete.
Wall finish is painted plaster. Stripable epoxy paint is available when decontamination considerations warrant.
USE OF RADIONUCLIDES For operational purposes, laboratory use of isotopes is limited to a maximum of 100 microcuries of activity for a single nuclide at any one time in a laboratory at Las Vegas. When working levels above this activity are required a special hot lab area facility is provided in a laboratory under control of the Radiation Safety Officer. Similarly, h:gh level activity storage facilities are also provided in the hot lab area.
In excess of 90% of the isotopes required by EPA operations are consumed in the use process. Of the remainder requiring disposal, either the decay procedure or transfer to the disposal area of the ERDA located on the Nevada Test Site is the method used. Only rarely is an isotope discarded by sewage disposal procedures.
The EMSL-LV Laboratory has the responsibility for environmental radiation mon-itoring for DOE /NV for the area surrounding the Nevada Test Site.
This area is primarily defined as the twenty western states.
EPA work includes monitor-ing radiation emitting from uranium mills, tailing piles and other environmental radiation sources.
MONITORING EQUIPMENT INVENTORY 14 ea 400 Channel Pulse Height Analyzer Systems.
Used for isotopic identifi-cation.
59 ea Scintillators, Ludlum, Baird-Atomic.
Range background to 3 mR/hr.
Used for low-level Gama detection.
18E ea G-M (E500-B), Eberline.
Range.01 mR/hr - 2 R/hr.
Used for Gama detection. Also in emergency can be used to identify high energy Beta radiation.
68 ea Radectors, Jordan & Victoreen. Range 1 mR/hr to 50 R/hr.
Used for the detection of Gamma radiation and can be used for high-energy Beta radiation.
17 ea PAC ISA Alpha instruments, Eberline.
15 ea EPA-modified Alpha instruments, portable.
v.
. 7 ea RM-3 Laboratory monitors, Eberline.
Range 0-50,000 counts per minute. Measures Alpha-Beta-Gamma.
80 ca Background radiation monitors, Lear Siegler.
Range.004 to 40 mR/hr.
3 ea Alpha air monitors, Eberline, Nuclear Measurement Corp.
Used to detect Alpha particles in air.
2 ea Fidler, Eberline. Range 0-500,000 counts per minute.
Used for the detection of low energy radiation (% 17 to 60 kev).
1 ea Complete Whole Body Counting facility.
1 ea Phoswich Detector System.
Used to identify and quantize low energy isotopes.
Attachment #3 jndicates portable instrument calibration techniques.
Sealed Sources used in calibration are listed under NRC License 27-05861-02, expira-tion date January 31, 1982.
WHOLE BODY COUNTING FACILITY A comprehensive surveillance program for monitoring employees is implemented primarily through the whole body counting program.
The whole body counting facility consists of four primary components: 1) a whole body counter utilizing an ll"x4" crystall used for y rays with energies greater than 50 kev, 2) a whole body scanner, 3) a phoswich detector assembly used for gamma rays with energies less than 65 kev, and 4) a data collection and analvsis system consisting of two multichannel analysers, a magaetic tape transport and a programmable cal-culator with plot capabilities.
The whole body counting facility has been operational at its present location since 1966 and human counting has been performed at this Laboratory since 1963.
Low energy counting was started in 1974 specifically to monitor Pu burdens.
Prior to and after completion of an experiment whole body counting information 4
is obtained.
In addition, if there is any reason to suspect possible uptake of radionuclides during the course of an experiment, whole blood, urine and fecal samples are obtained if the nature of the particular experiment warrants it.
Calibration of the whole body counter is made on a continuous basis to ensure proper operation of the equipment, reproducability of the results and comparison of results with standard radionuclide sources.
The calibration is performed with the use of several types of phantoms, point sources and liquid simple configurations.
The whole body counting program is administered by a physician and is in egrated into the overall industrial safety program for the Laboratory.
. RADIATION SAFETY COMMITTEE RfSPONSIBILITIES
~
The Radiation Safety Committee established within EPA facilities shall have jurisdiction over all radiation sources and activities in areas under their
-control.
Functions of this committee include, but are not limited to, the following:
a.
Review and act on all applications for use of radionuclides, including review and approval of the qualification of users, prospective users, facilities, procedures and equipment involved.
b.
Receive and review periodic reports from the RSO on monitoring, contamination and personnel exposure.
Rf.01ATIONSAFETYOFFICER The Radiation Safety Officer derives his authority from the Director and it the Director's authorized representative regarding measures concerning radiation protection.
INDIVIDUAL RESPONSIBILITY FOR RADIATION PROTECTION Each individual who is designated to participate in a study where radioactive material is being used is responsible for:
a.
Keeping this exposure to radiation as low as practicable, and speci-fically below the Radiation Protection Standards for External and Internal Exposures as listed.
REMS PER CALENDAR QUARTER Whole body; head and trunk, gonads; lens of the eye; red bone marrow active blood forming organs 3
Unlimited area os the skin (except hands and forearms); other organs; tissues and organ systems (except bone)............
5 Bone
............................10 Hands and Feet........................
25
- b. Wearing the prescribed personnel monitoring equipment such as TLDs, film badges and pocket dosimeters.
- c. Each individual user shall utilize all appropriate protective measures, including the following:
. Shall wear protective clothing required by the RSO.
Example: Protective coveralls, boots and impervious gloves shall be worn when han41;ng drums of radioactive waste.
2.
Shall be fitted for respiratory protection by REECo Environmental Sciences Department prior to the start of a study involving radioactivity.
Respiratory protection will be worn during operation when deemed necessary.
by the RSO.
3.
Shall maintain good personal hygiene and report to the RSO any skin cut or abrasions prior to handling radioactive material.
4.
Investigator shall subrait background biological samples and whole body count either sodium iodide or phoswich detector as appropriate prior to each experiment or on a frequency _ determined by the RSO.
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Attachment #1
.r0RTABLE INSTRUMENT C,$LIBRATION Attached is a working draft of Instrument Calibration Procedures as utilized at EMSL-LV.
Calibration of portable instruments is on a thirty-day schedule. Equipment used in experiments are calibrated immediately prior to use and thirty lays later or at the termination of the experiment, whichever is shorte..
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DO N7P ADJUST 1..
(gg,3 29........................X10 RV4,.... (X10)
X.1 pot. on 10........
20.......................X100 RV3.... (X100)
Brown Scintillad ggq,4 tor t:,
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14 3 6.'}.
16.....................'.. X. 01 A.01 20........
2 15..................'.....X0.1 X.10 I~&S.O 100........
15.......................XI.0 XI.0 g 2. g. g 100........
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200........
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15........................X10 X10
.},1 15.......................X100 X100.......... Small Range,
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,4........................ Low 1 mR/hr 10........
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.04....................... Low Check Point 100........*
40.......................High 10 mR/hr 39,y
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4........................High g4g,3 Check Point J~ -
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RADECTOR 100........
72p.o... 0.5....................XmR/hr Lower Right 100........
50.....................XmR/hr Upper Right
. 2-W, 72,0 200........
50......................XR/hr Lower Left
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2 R/h:*................. XR/hr Upper Left f, y f g, 3
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t.1 RADECTOR CALIBRATION PROCEDURE
. NOTE: The Radector uses an ion chamber as its detector. These ion chambers take at least 5 minutes to stabilize at any radiation level (rate) less than 50 mR/hr.
Care MUST be taken to allow enough time i
for the ion charaber to stabilize.
1.
Turn on all of the Radectors that are to be calibrated to the mR/hr scale.
Allow 5 to 10 ninutes for stabilization.
t 2.
Put ONLY one Radector on the range cart at a time. Move 'he t
range cart togo,o em from the 100 mci source and adjust the lower I;
right hand pot. until the meter indicates 0.5.
Allow at least one I, -
minute for the adjustment to stabilize.
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3.
Move the range cart to 72,0cm from the 100 mci source and adjust the upper right hand pot. until the meter indicates 50.
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b.
If you had to adjust the upper right hcnd pot., then go back jf 4.
a.
and repeat steps 2 ahd 3 until no more adjusting is necessary.
b.
If either pot. is at maximum and if the meter is NOT calibrated, then the bucking resistor will have to be replaced.
(Rej ect the meter indicating that the low end will not adjust.
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5.
If you manage to complete step 4a, then set the range cart to
((6.0 cm from the 200 mci source. Select the R/hr scale and adjust the j
lower left hand screw until the meter indicates.05.
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CAUTION:
In this part of the procedure, relatively high levels of radia-tw.
tion exist.
Before moving the range cart to -
cm from the 200 mci source, put a screwdriver in the upper left hand well AND make sure the i-screwdriver is in the screw slot of the pot.
' )d 6.
Nove the range cart to l$.3 cm from the 200 mci source. Select the R/hr scale and adjust the upper left hand scale and adjust the upper t '.
left hand pot. until the meter indicates 2 (R/Hr). Stand as far away as is practicable from the source.
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7.
If you had to adjust the upper left hand pot. then repeat steps 5 and 6.
NOTE:
If the meter will not calibrate.fter repeating steps t1 5 and 6, then forget about calibrating that particular meter.
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Refer to step 4b.
If the same conditions exist then reject the
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neter and indicate the high end will not adjust.
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2 INTERNAL SOURCE CALIBRATION:
This calibration must be checked and adjusted if ne Select the mR/hr scale.
a.
Push the CALIB. SOURCE to the ON-position.
After the meter has had time to stabilize, it should indicate 50.
b.
The meter should indicate.05.With the calib. source still in th scale.
the ion chamber, both the mR/hr and R/hr scale will ind c.
low or too high respectively.
er to d.
screw from the source chamber.If the interbal source needs to be moved Use an allen wrench to move the source f
to the proper distance.
Recheck by using steps 1 and 2.
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Replace the set screw so it sets snugly against the source e.
f.
The meter is now completely calibrated and ready for issue
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MODIFIED PAC-4G CALIBRATION PROCEDURE i
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A.
HIGH VOLTAGE ADJUSTMENT 1.
Remove the instrument from its case.
2 Connect an electrostatic voltmeter to the high voltage terminal and ground.
3.
Adjust the high voltage pot. until the eiectrostatic voltmeter indicates 1600 Volts.
B.
CALIBRATION 1.
Disconnect the probe and cable from the case.
2.
Connect the cable to the Eberline adapter.
Connect the adapter to the high voltage terminals of the meter. -
3.
Place the Irrobe on the Pu 1,150 cpm source WITH the screen cov 4.
the source.
Adjust R2 until the BLACK needle indicates 250 on the GRAY scale.
5.
Place the probe on the Pu 14,700 cpm source WITH the screen c the source.
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Adjust R3 until the BLACK needle indicates 3.3 on the t
BLACK scale.
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6.
Repeat steps 4 and 5 until no further adj'usting is necessary e
7.
Place the probe on the Pu 14,700 cpm source WITHOITT the screen covering the cource.
on the ORANGE scale. Adjust R4 until the RED needle indicates 10K
'. +
8.
Place the probe on the Pu 1,686,000 rpm source WITH the screen covering the source.
385K on the MAROON scale,Adjdst R5 until the RED needle indicates 9.
Repeat steps 7 and 8 until no further adjusting is necessary.
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.:s 10.
Reconnect the probe and cable to the case.
Replace the meter in 7.;
the case.
Put the probe in its holder and check that the meter
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indicates the approximate cpm as written on the side of the case
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A.
Discriminator Control Adjust 1.
Be sure that the plastic probe cover is on securely.
2.
Select the X1 scale.
t-5 L 3.
Adjust the DISCR pot. until the meter indicates 50 counts per
,!i minute.
I B.
. Light Leaks in Probe Face 1.
Take the meter into sunlight.
2.
Remove the plastic probe cover.
3.
Select the X1 scale and expose the probe face to direct sunlight.
4.
If the meter indicates any count rate greater than 50 cpm, then the Mylar facing must be either replaced or the pin holes covered with, BLACK LACQUER.
3 If more than 10% of the active Mylar face area is covered with the
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5.
L-black lacquer then the Mylar facing MUST be replaced.
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C.
Calibration
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. l 1.
Remove the probe and cable from the instrument case. Attach the i
probe and cable to the Eberline adapter and connect the adapter j
to the high voltage terminals.
r 2.
Put the probe on the 1,435,000 cpm Pu source. Place a weight on the front end of the probe so that the entire probe touches the
-t.
Select the X1K scale and adjust the X1K pot. until the
}Q source.
meter indicates 1,435.
3.
Place the probe on the 103,500 cpm Pu source. Select the X100 scale and adjust the X100 pot. until the meter indicates 1,035.
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Place the probe on the 11,500 cpm Pu source.
Sel ct the X10
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scale and adjust the X10 pot. until the meter indicates 1,150.
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Place the probe on the 410 cpm Pu source.
Select the X1 scale
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and adjust the X1 pot. until the meter indicates 410.
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Place the probe on the 1,860 cpm source.
Use the XI scale to i '. d check the linearity of the meter.
It should indicate 1,860.
[ j, DO NOT adjust any pot.
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The instrument is now calibrated and ready for issue.
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LSI CALIBRATION PROCEDURE
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PRE-CnLIBRATION CflECKS l
1.
Check to see that the needle of the Rustrak recorder is properly zeroed.
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2.
Check to see that the chart paper is taped on the take-up reel.
3.
Check to see that there is at least one-half of a roll of chart.
paper.
4.
Turn the I.SI on and allow it to run off of the batteries.for 10 minutes.
CALIBRATION 1.
Put the LSI on the range cart.
Plug an A.C. power cord into the receptacle and listen for the relay to click.
2.
Be sure the carrying case handle is up.
- s 3.
Move the range cart todM/ Y cm from the 10 mci source.
Allow 'a few minutes for the Rustrak recorder to change scales.
If the recorder does not change over, then adjust the 1 mR/hr pot, and wait to see if you adjusted correctly.
An audible click from the recorder will indicate c. scale change over.
4.
Move the range cart to Nf,[r em from the 10 mci source.
Allow a few minutes for the recorder to stabilize at.04 mR plus background. '
DO, NOT adjust either pot.
s S.
Move the range cart to 77// cm from the 100 mci source.
Allow a few minutes for the recorder to stabilize at 40 mR/hr.
Adjust the 10 mR/hr pot. if necessary.
.i 6.
Move the range cart to)S/M cm from the 100 mci source.
Allow a fet< minutes for the recorder to stabilize at 4 mR/hr.
DO NOT
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adj,ust either pot.
7.
Nove the range cart to7 783 cm from the '100 mci source.
Allow a few minutes for the recorder to subi1.ize at.4 mR/hr.
DO NOT adjust either pot.
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P'ut a brown desiccant bag in the electronic well.
8.
Put the cover
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on and secure it.
9.
Put a blue desiccant bag on top of the cover.
Be sure there are two (2) takeup spools in the recorder.
10.
Mark on the cart paper the calibration date and your initials.
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E-500 CALIBRATION PROCEDURE 1.
Do not put more than three (3) E-500's on the range cart.
2.
Make sure all of the probes are closed,.i.e., the G.M. tube should not be showing.
,4 3.
Move the range cart to 436 7 cm from the 10 mci source.
Select the X.01 scale and adjust the X.01 pot. until the meter indicates 16.
LO.i 4.
Move the range cart to j37,0 cm from the 10 mci source.
Select the X.1 scale and adjust the X.1 pot until the meter indicates 15.
......s 5.
Move the range cart to /28 7 cm from the 100 mci source.
Select the X1 scale and adjust the X1 pot. until the meter indicates 15.
,1 6.
Move the range cart to 4/.c em from the 100 mci source.
- ::,y Select the X10 scale and adjust the X10 pot. until the meter indicates 15.
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.;. ;q 7.
Set the SMALL RANGE cart at 217 cm from the 200 mci source.
-i Remove the instrument from its case. Select the X100 scale and
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adjust the X100 pot. until the meter indicates 15. The E-S00 is
'i now calibrated and ready for issue.
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YELLOW SCINTILLATOR CALIBRATION PROCEDURE l
1.
Turn the meter on two (2) hours for stabilization.
2.
After 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, adjust the stabilizer pot, RV 1, so the needle is
.e within i 10% of the RED line.
Be sure there are no sources out.
3.
Put the styrofoam block between the meter case and the meter assembly.
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4.
Put the meter at 3f&t/ cm from the 1 mci source. Select the XL
.4 scale and adjust RV S until the meter indicates 30.
Move the meter to /f4.5 cm from the 1 mci source.
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S.
Select the
- q X10 scale and adjust RV 4 until the meter indicates 20.
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6.
Move the meter to /lf,[p cm from the 10 mci source. Select the X100 scale an,d adjust RV 3 until the meter indicates 20.
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- e The meter is now calibrated and ready for issue.
7.
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LUDLUM (BROWN) SCINTILLATOR CALIBRATION PROCEDURE
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c NOTE:
No stabilizar'.on time is required.
'h 1.
Put one Ludium at a time on the range cart. Move the carc to 3(#f cm from the 1 mci source.
Select the XI scale and adjust
- ' ".b the XI pot. until the meter indicates 30.
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2.
Move the cart to f(3 6 cm from the 1 mci source'.
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Select the X10
- I.
scale and adjust the X10 pot. until the meter indicates 20.
Move the cart to //f, (, cm from the 10 mci source.
. - ::93 3.
Select the '
- Y X100 scale and adjust the X100 pot. until the meter indicates 20.
.. '..M 4.
D0_ NOT adjust the X.1 pot.
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-i Resume of Health' Physics-Related Training and Experience as of June 1981 James C. Payne, Jr., Program Management Officer Of fice of Program Management and Support 1.
TRAINING A.
University-Level 1962 B.S. degree, Agricultural Engineering, Michigan State University 1963 3 credits, Atomic & Nuclear Physics, University of Nevada, Southern Division 1963 3 credits (audit), Nuclear Engineering, University of Nevada, Southern Division 1967 M.S. degree, Radiological Health, Rutgers University B.
USPHS Courses 1963 Alpha-Monitoring Basic Radiological Health Management of Nuclear Emergencies 1966 Measurement of Airborne Radioactivity 1969 Radionuclide Analysis by Camma Spectroscopy Occupational Radiation Protection C.
0ther Cources
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1968 Radiation Monitor Certification Program, Southwestern Radiological Health Laboratory, USPHS (and annual updates thereof) 1969 Medical Self-Help Training, Department of Civil Defense 1969 Badiological Emergency Operations, Radiological Sciences Depart-ment, REECo 1979 Cardiopulmonary Resuscitation, Las Vegas Fire Department (and update 1981, Sunrise Hospital)
II.
EXPERIENCE (all with USPHS and EPA) 1962-1964 Developed and tested ground and aerial sampling equipment for the collection of radioactive aerosols released at the Nevada Test Site. Part-time Radiation Monitor for Off-Site Radiological Safety-Program at the NTS.
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2 1964-1966 Coordinated field research projects in conjunction with nuclear cratering tests at the NTS, including respon-sibility for radiation safety or personnel.
Radiation Monitor.
1967-1978 Program radiation safety adviser. Assist Laboratory Radiation Safety 6f ficer with experiments at the NTS.
Radiation Monitor.
Radiation Sa fety Commit tee Member, EMSL-LV.
Radiological Assistance Team Member, EMSL-LV.
1975-Present Radiological Assistance Team Member, USERDA and U.S.
Department of Energy.
Radiation Monitor.
Radiation Safety Committee Member, EMSL-LV.
Radiological Assistance Team Member, MELS-LV.
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JOHN S.
COOGAN Resume of Training & Experience in the Use
& Handling of Radioisotopes Formal Training BS~ degree from University of New Mexico plus a number of graduate courses with emphasis on health physics, physics and nuclear physics.
Several short courses on radiological health given by PHS at R.A. Taft Sanitary Engineering Center covering aspects of general radiological health, counting and radiochemis-try, environmental surveillance, x-rays and reactors.
Job Experience 1952-1953 General Electric Corporation Involved in research design of beryllium windows and other portable and fixed Radiac instrumentation.
1956-1961 Reynolds Electrical & Engineering Corapany, Inc.
Responsible for the health physics program at the Nevada Test Site for the prime contractor.
Involvement primarily in the weatpons testing program with some work in unshielded reactors used as rocket engines for the space program.
Work involved protection of workers for the prime ccntractors, conducting field surveys and laboratory analysis of samples for the National Laboratory as well as D00.
While employed by REECo', I was involved with all types of radiation including some x-ray work. During this period I was familiar wity all types of survey in-l struments such as gas flow proportional counting systems, ion chambers using a vibrating reed electrometer, scintillation detector with _ ingle channel analyzer and mutlichannel analyzer instrumentation.
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. 1961-1970 Southwestern Radiological Health Laboratory, USPHS For approximately seven years was responsible for the off-site monitoring and surveillance program around the Nevada Test Site. This program was designed to protect the civilian population surrounding the Nevada Test Site from radiation emanating from the nuclear weapons testing program and the nuclear reactor testing.
I Program consisted of an air sampling network, dosimetry program, human surveillance program (whole-body counting of off-site residents); field monitoring for alpha and beta-gamma contamination.
For the balance of this period assigned to the Programs and Plans Division reviewing data and plans for experimental design and safety.
1970 - Present Environmental Monitoring System Laboratory-Las Vegas, EPA Safety Officer including Radiation Safety for the Laboratory which consists of approximately 450 people with many disciplines.
This Laboratory is involved in radiation research, advanced monitoring techniques for a number of pollutants as well as air and water surveillance program. Work is perfonned for a number of agencies including DOE, 000, States and other EPA Regions.
Radiation program consists of the Off-Site Monitoring and Surveillance Program and the Radiation Research Program which is primarily engaged in animal and plant research.
I have the added responsibility of Radiation Safety Officer for the Environmental Protection Agency.
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t Earl L. Whittaker, Radiation Safety Committee Member, EMSL-LV Resume of experience Fonmal Training BS degree from Northwestern University plus a number of graduate courses in evening school with emphasis on Chemistry, Physics, and Mathematics, including a year cours in nuclear physics.
Job Experience 1955 - 1957 Nuclear Chicago Corporation Responsible for designing and f abricating sealed sources up to several Curie levels of activities including making chemical separations to purify specified activities.
Responsible for some special projects such as the pro-duction of Hg-198 from Au-197 by in-pile irradiation of the Au-197 followed separation of the Hg-198 from the Au-197.
Used Geiger tube and ion chamber types of counting systems.
Performed calibrations and standardizations with the above-named instruments.
1957-1958 isotope Chemical Company Responsible for setting up taborstory operations for the production of radioisotope labeled organic compounds (C-14, S-35, P-32 and H-3).
Responsible for obtaining AEC license for the use of by-product materials, License No.
12-2904-1. Used gas flow proportional and liquid scintillation types of counting systems.
Performed calibrations and standardizations with the above-named instruments.
1958-1959 Minnesota Department of Health Responsible for obtaining AEC license for the use of by-product materials, License No. 22-4589-l(A-61).
Responsible for setting up laboratory procedures for separating and measuring radioisotopes in environmental and food type samples. Used gas flow proportional low background beta counting system.
Performed calibrations and standardizations with the above-named counting system.
1959-1961 Reynolds Electrical and Engineering Company Responsible for development of laboratory procedm as for radiochemical analyses of health physics type n' 5c.1ples (environmental and bioassay samples such as air, weier, and urine samples.)
I used the following detection instruments at REECo.
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. Earl L. Whittaker All types of survey instruments.
Laboratory instruments such as gas flow proportional counting system, ion chamber used with a vibrating reed electrometer, scintillation detector with single channel analyzer instrumentation and with multichannel analyzer instrumentation, and autoradiagraphic track counting instrumentation.
Performed calib.ations and standardizations with the above-named instruments.
1961-1972 Southwestern Radiological Health Laboratory, USPHS For approximately five years was responsible for the safe operation of the Cockcrof t-Walton type neutron generator (safety with respect to occupational and non-occupational exposures.
Conducting research and development in air sampling techniques and systems and analytical methods of stable and radiochemistry.
Used the following laboratory radiation detection instruments:
Scintillation detectors with single er winel and with multi-channel instrumentation. Gas flow pi
.rtional counting system used with a gas chromatograph.
Spiral orbit spectrometer (beta spectrometer)
Beta-gamma coincidence instrumentation.
Perform calibrations and standardizations with the above-named instrumentation.
1972-Present As Chief, Monitoring Guidelines and Standardization Section, Quality Assurance Branch, Monitoring Systems and Development Program, Environmental Monitoring Systems Laboratory-Las Vegas, Environmental Protection Agency.
Responsible for the evaluation, selection, and collaborative testing of methods for the purpose of establishing standard reference methods for monitoring of radioactive pollutants in the environment.
Use the following radiation detection instruments:
Liquid scintillation systems Gamma spectrometers Alpha spectrometers Beta-Gamma Coincidence instrumentation Gas flow proportional counting systems.
Alpha and beta scintillation detection systems.
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. Earl L. Whittaker i
Other Experience 1949-1951 Allied Mills, Incorporated Performed routing analyses for quality control purposes.
1951-1955 The Miner Laboratories Performed evaluations of analytical methods (approximately 3 years) and research in the uses of glycerine and in identification of aldehydes. occurring in cigarette burning (approximately 2 years).
1942-1944 Military Service Trained as a surcical technician.
(There was a very helpful carryover from surgical techniques to techniques in handling radioisotopes. )
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RESUME OF EXPERIENCE MAXWELL E. KAYE, M.D.
Training 1 Sept.1950
" Introduction to Nuclear Effects," U.S. Naval Air Station, Naragansett, RI.
- 2. Feb.1952 - Disaster Relief Course, U.S. Naval School, Port Hueneme, CA.
- 3. Aug.1954
" Mass Casualty Course," Brooke Army Medical Center, San Antonio, TX.
- 4. Nov.-Dec.1958
" Mass Casualty Course," Brooke Anny Medical Center, San Antonio, TX
- 5. Aug.1958 - Medical Symposium for Officers of Armed Forces - Con-cerning current special weapons, their effects, the application of nuclear energy other than weapons which present medical problems (accidents involving nuclear fission and radioactive contamination)
- 6. Feb.-Mar.1959, Advanced Course in Radiobiology for Medical Offic'rs (Field Course, Reed College) at:
t 1.
NTS, Camp Mercury, NV 2.
Anned Forces Special Weapons Prcdect, Sandia Base, Albuquer-que, NM.
3.
Los Alamos, NM.
- 7. May-June 1959 - ABC Defense Course for Senior Medical Officers, U..S. Naval Base, Treasure Island, San Francisco, CA.
- 8. May 1961 - Chemical, Biological and Radiological Weapons Orientation Course (Effects), U.S. Anny Chemical Corps Proving Ground, Dugway, UT.
Experience with Radiation g
- 1. Hold M.D. and Dr. of Public Health Degrees.
- 2. Merrber of Radiation Safety Committee at EMSL-LV since Nov.1970
- 3. June 1958-Aug.1961 - Served at DASA as Senior Medical Officer at Lake Mead Base, NV, during which time also taught ABC Casualty Training at NTS and wrote ABC (Atomic, Bacteriolop,1 cal and Chemical)
Handbook.
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- 4. 1961 Lecturer and Consultant on Nuclear Matters at the U.S. Naval Anmunitions Base, Guam, Marianna Islands.
1 5.1970 to Present - Coordinator for MLON organization (Medical Liaison Officer Network), treatment and diagnosis of radiologi-cal accidents covering the U.S. and its possessions.
6.1970 to Present - Consultant for DOE in relation ta claims against the U.S. Government far alleged off-site radiation exposure.
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08584
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e RESUME OF EXPERIENCE Richard L. Douglas Health Physics Training
- 1. " Engineering Aspects of Radiological Health," a 9-week course given by PHS at R.A. Taft Sanitary Engineering Center - taken duririg Summer of 1961.
Course covered general radiological health, counting and radiochemistry, er.vironmental surveillance, x-rays and reactors.
The last week was spent at ORNL.
- 2. Attended graduate Rad Health program at Rutgers - 1964-65.
Received M.S. in Radiation Science in October 1965.
Course and laboratory work included electronics, radio-chemistry, radiation biology, physics and shielding, en-vironmental science, radiation detection instruments, epidemiology and health physics. Special problems in-cluded: survey of hospital radiology department, collec-tion and analysis of environmental samples, survey of Van deGraaff accelerator and survey of radiopharmaceutical plant. During the summer, I took the health physics course at Brookhaven.
This program emphasized the practical aspects of nearly all phases of health physics.
Practical Experience I have been employed by USPHS/USEPA at Las Vegas since July 1961, except for the periods mentioned above.
Experience includes:
Monitoring and surveillance around Nevada Test Site Development and calibration of air samplers, field monitor-ing for alpha and beta-gamma contamination; radiobiology research, facility Radiation Safety Officer; Chief, Field Studies Branch, ORP-LVF.
Certification Certified by the American Board of Health Physics - March 1969.
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RESUME OF EXPERIENCE JOSEPH M. HANS, JR, Training B.S. Degree-Physics-West Liberty State College, W. Va.
1 yr. graduate training-University of Rochester, Rochester, NY Radiation Biology 3 months-On-the-job training-Brookhaven National Laboratory Health Physics M.S. degree-Nuclear Engineering-Georgia Tecn, Atlanta, GA 3 months-On-the-job training Georgia Tech Reactor Health Physics Certified Health Physicist t'
Experience 1959-1962 - PHS assignee to the Georgia State Radiolcgical Health Program-Environmental Surveillance, x-ray and radium management and decontamination activities.
1962-1965 - PHS Headquarters - Air sampling, accelerator health physics, decontamination activities and radium management 1965-1972 - PHS Radiological Health Laboratory.
Training in all aspects of radiological health and microwave and laser safety.
1972-Present - PHS-EPA-Nuclear accident management, uranium mines and mills surveys, phosphates, decontamination of uranium mill site.
CS584
d Resume of Health Physics-Related Training Wayne Allen Bliss Formal Training in Radiation Safety -
Northwestern Oklahoma State University - M.Sans & P.H.
8-6-65 Oklahoma University Other formal training has been completed through short courses as follows:
Radionuclide Analysis by Gamma Spectroscopy offered by U.S. Public Health Service 2/27 to 3/10/67 Introduction to ADP Systems offered at the U.S. Public Health Service 10/14 to 10/18/68 Occupational Radiation Protection offered by the U.S. Public Health Service 1/3 to 1/24/69 Laser Instrumentation and Survey Techniques offered by U.S. Public Health Service 11/9 to 11/13/70 Statistics and Computer Programming of fered by University of Nevada - Las Vegas in 1973 Experience Nov. 10, 1980 to Present - Project Officer for Office of Radiation Programs, U..S. Environmental Protection Agency.
Plans, develops, schedules and conducts field and literature studies, coordinates these with State and Federal Agencies, and supervises and coordinates activities of personnel detailed to participate in projects. Prepares reports evaluating project l
data.
Provides consultation and direct assistance to State and Federal Agencies.
Participates in field studies conducted by other programs and branches in ORP.
Distributed over the period of 1970 to 1980, I participated as Radiation Safety Committee member and alternate RS0 on metabclism studies using both small and large animals.
The isotopes used were principally transuranics in varying levels up to tens of millicuries per cnimal.
Not included in the above, I have also participated in the health physics programs of Operation Morning Light; the joint Canada /U.S. recovery of the nuclear-powered USSR satellite Cosmos-954 and the incident at Three Mile Island, both initially and during the purge of the contaminant building.
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4 RESUME OF HEALTH PHYSICS-RELATED TRAINING AND EXPERIENCE
-Loren E. Thompson Quality Assurance Division Education',
Portland State College 1962 - 1965 Biology (Major)
Chemistry (Minor Oregon State University 1965-1967 Chemistry (Major)
B.S.
1967 Work U.S. Atomic Energy Conmission 1968 - 1973 Chemist Primary responsibility Strontium 90 & 89 Analysis in all media U.S. Environmental Protection Agency 1973 - Present
. Chemist Preparation, calibration and shipment of radionuclide standards l
Resume of Experience JACK E. TIIRALL Training 1.
1956-1963 U.S.
A. E. C.
Idaho Operations Office Idaho Falls, Idaho On the job training as follows:
a.
Principle and practice of Radiological Health related to men and animals.
b.
Techniques of decontamination of military instal-lations.
c.
Nuclear devise radiation on blast effects on structures, animals and electronic equipment.
d.
The design and use of field and laboratory instru-ments to detect and measure radiation.
2.
1963 U.N.L.V. Formal course in Basic Atomic Physics.
Experience with Radiation 1.
U.S.
A.E.C.
Idaho Operations Office a.
1956-1963 Field monitoring of Nevada Test Site and National Reactor Testing Station b.
Laboratory-Standardization and Celibration of Electronic Instruments 2.
1963-1976 U.S. PilS - U.S. EPA, Las Vegas, NV a.
Field monitoring of Nevada Test Site b.
Calibration and Stat.dardization of electronic instruments b
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