ML20003D545
| ML20003D545 | |
| Person / Time | |
|---|---|
| Site: | 07001207 |
| Issue date: | 05/23/1979 |
| From: | NAVY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20003D536 | List: |
| References | |
| NUDOCS 8103270644 | |
| Download: ML20003D545 (46) | |
Text
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O APPLICATION FOR REf1ENAL OF SiiM-1147 TABLE OF CONTENTS Licensea's Name:
Address:
A.
Use B.
Location of use C.
Sources and SNM description and handling procedures D.
Storage and security E.
Period of time renewal requeste,d F., ihme, amount and spectficaiton of SI'M required l
G.
Technical qualifications of users H.
Types of radiation instruments I.
Procedures to protect health and minimize danger to life ur property J.
Leak testing procedures
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K.
Additional information "
L.
Radiation protection program l.
Radiation User Staff j
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2.
Organizational and Administrative Procedures l
3.
Transfer of radioactive material t
t 4
General radiological safety procedures
.f.
5.
Special precaution 6.
' Monitoring 7.
Emergency action s103 270 GW
_._....__..,m g-
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a APPLICATION FOR RENEWAL OF SNM-1147 1.
Licensee's Name:
US Department of the Navy 2.
Licensee's Address:
Naval Surface Weapons Center White Oak, Silver Spring, Maryland 20910 3.
License No.: SNM-1147 4.
Docket No.:
70-1207 5.
Expiration Date: July 31, 1979 6.
Materials:
a.
Plutonium b.
Uranium 233 c.
Uranium enriched in the U-235 isotope d.
Thorium and natural and/or depleted uranium e.
Plutonium 238 f.
Uranium 235 s
7.
Maximum quantity of material which licensee may possess at any time under tnis license; a.
1-Pu: 3.3 milligrams Pu 239 as resin deposited sources; 180 grams Pu 239 encapsulated as Pu-Be neutron sources; 20 grams Pu 239 as contained oxide; and 21 grams Pu 238 in any form.
2-Pu:.760 grams Pu 239 in any form.
pup neutron source 4
b.
U-233: 10 grams as" nitrate a
c.
U-235: 50 grams as oxide or foil d.
Thorium and natural and/or depleted uranium 150 pounds
-e.
Pu-238: 3.3 milligrams f.
U-235: 60 grams in any form 8.
Authorized use A.
Authorization is requested to receive, possess and store the materials listed below in Item 7 as follows:
- 1) 3.3 milligrams Pu-239 as resi'n deposited sources 20 grams Pu-239 as contained oxide; and 21 grams 2), Pu 238 in any form.
10 grams U-?.33 as nitra e
- 3) 50 grams U-235 as oxide of foil
- 4) 10 grams of U-235 in any form B.
Authorization is requested to receive, possess and use 1
f2 Page 1
e tt.e materials listed below:
- 1) 130 grams Pu-239 enc',psulated as Pu-Be neutron sources
- 2) 760 grams Pu-23a in any forv pup
- 3) Pu 4 neutron source 233-3.3 milligrams
- 4) U-235: 50 grams in any form
- 5) 1.,0 lbs. Urantam depleted in the J-235 isotope
9.
Authorized places of use Su' siding 70, Room 121; Building 71, Environmental Laboratory; Buildings 321 and 343; and Trailer N-9 at the NAVSNC/ White Oak Facility, Maryland.
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APPLICATION FOR RENEWAL OF SNM-ll47 LICENSEE'S NAME:
Department of the Navy ADDRESS:
Naval Surfac'e Weapons Center White Oak, Silver Spring, Maryland 20910 A.
USE The 239 Pu-Be sources are used for calibration of radiation 2
detection instruments.
The 760-gram Pu 39F4 is also used for this purpose and for shiciding measurement, studies and instrument development research.
(See Sketch A)
The special nuclear material such as uranium enriched and the isotope U-235 will be used for radiation in nuclear reactors, linear accelerators, cyclotrons, and Van de Graaff machines.
The special nuclear raterial will be irradiated with neutrons, thus causing fission of the uranium-235 isotope.
Max. mum amount of special nuclear material per sapple for irradiatlo: is about 50 milligrams of the enriched uranium-235 isotope.
The irradiated samples of uranium-235 will be used for counting measurements.
Radiochemical analysis will also be performed on the irradiated uranium samples.
The 238 plutonium dioxide in j
the fcrm of microspheres in a prior use was subjected to a sea-water environment in an exposure chamber where the effect of the ocean could be determined by observation and measurement.
Further use is not definite.
Uranium depleted in the U-235 isotope in microgram to gram i
amounts is to be used as follows:
- 1) standard source l
- 2) fragmentation studies l
- 3) radiochemistry
- 4) Van de Graaff targets for investigating the stop-ping power of heavy particles In addition, small amaunts of d'pleted uranium are to be used e
in investigation of metallurgy and stress corrosion cracking tests.
The uranium in cylinder form will be used while mounted under ten-l sion in an environmental chamber operated under control conditions.
i of temperature, moisture and ' effluent direction.
Thorium is utilized in compounds of metals with metalloids for experiments measuring their magnetic and non-magnetic prop-erties. Thorium is also used in making or compounds.
B.
LOCATION OF USE:
The plutonium sources are used in Building 70. Room 141 and in Building Experimental, Laboratories.
Page 2' 1 of 7
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55 OAL. DRUM FILLED WITH CONCRETE TEST SPECIMEN..
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- AN/PDR-70 Neutron Detector'
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INS $RUMENTATION.
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SOURCE STAND 760 gm. PuF 4
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TEST SET-UP Shiciding measurement studies i'
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The uranium-235 is used in Building 343 Radiochemistry lab-oratories, Building 4 (' 'n de Graaff) and other licensed author-i:ed places of use.
The depleted uranium is used principally in the environmental laboratory in Building 20.
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Pu-238 microspheres project is used in Radiochemistry lab-oratories in Building 343.
C.
SOURCES AND SNM DESCRIPTION AND HANDLING PROCEDURES The 760-gram Pu23)i soutca is four inches long by four inches g
in diameter.
It is welded and sealed within a doublewalled en-capsulated aluminum cylinder.
When not in use, the source is stored within a 15" diameter x 15" long paraffin lined metal D0D M-6 container.
An aluminum plug over the top of the source provides the same amount of shielding as the para fin surrounding the source.
In preparation for use, the source will be transferred into a concentrically arranged five-inch diameter by 22-inch long steel pipe embedded within the concrete-filled. drum.*
The alum-inum shfelding plug is then inserted into the pipe.
The total four-pi emission rate of the source is 6 x 106 n/sec (fast).
A tissue equivalent dose rate reading at a one meter distance from the source in the exposed condition is 13.5 mrem /hr.
Measurements taken at contact with the surface of the storage container both at the side and top of the container with an AN/PDR-70 survey meter revealed. readings of 23 mrem /hr.
Six-foot tongs are used in transferring the source to and from the storage container.
The source is always returned to its storage container when not in use.
The storage container is equipped with a bar-type lock to prevent unauthorized removal of the source.
The 55-gallon experimental drum is also provided with a safety screw and lock.
Equipment necessary for experimental operations is set up prior to exposing the source in order to minimize source expo-sure time.
Personnel working with the source are positioned approximately 15 feet behind the detector (see Sketch A) during source exposure in radiation levels generally of less than 1 mrem /hr.
.7 Handling of the source is under the direct supervision of authorized personnel.
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- Concrete density of 150 lbs/cu ft.
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STORAGE AND SECURITi The sources. are stored. and 1ccked within their storage contain-ers in Buildings 70, 71, and 321 (SNM storage area) when not in use.
The laboratories in which the sources are used and stored (temporary)
I ar: kept locked during use as well as non-use.
Only designated per-sonnel have keys to the sourc's and laboratories.
These areas are e
aise.mder 24-hour surveillance by the security force.
When a source is not in use for extended periods. of time, the sodrce is stored in the central isotope storage building, blown as Euilding 321.
This building is ender the direct supervision and control of the Health Physics Division.
E.~
PERIOD OF TIME RENEWAL REQUESTED:
5 y. ears.
F.
NAME, AMOUNT AND SPECIFICATIONS OF SNM REQUIRED,.See page 1. (142).
G.
TECHNICAL' QUALIFICATIONS OF USERS-See Supplemental Sheet,-Resumes pages #21,22,25,26,27,28,29 4 30 Charles Christianson
'L.E. Murray Gordon. Riel William Neall-H.
TYPES OF RADIATION INSTRUMENTATION
.See supplemental sheet, p. age
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I.
PROCEDURES TO PRCTECT HEALTH AND MINIMIZE DANGER TO LIFE OR PROPERT'.
Se's Radiatibn' Prot'ection Progr'an (Supplemedtal Sheet), page 7' A
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J.
LEAK TESTING PROCEDURES l
See Radiation Protection Program and supplemental sheet, -
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ADDITIONAL INFORMATION l
Caution signs, labels, and ' signals; records of surveys, radia-tion monitoring, and disposal; reports of theft or loss of licensed l
materi.al; notification.of incidents; Posting and labelina l
l Ref. NOL Instruction PS100.5A Radiological Safety Manual Addendum No.1 '
l Item III A, B,'D, G, P and,R.
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PROCEDURES TO PROTECT LIFE AND MINIMIZE DAIIGERS TO LIFE OR PROPERTY 1.-
Criticality Precautions-Special precautions are required to assure that the inadvertent accumulation of a sufficient quantity of special nuclear materials (U 38, U 35, pq239, er oth'er fission-2 2
able material) necessary to create a critical mass with an attendant nuclear chain reaction won't 'nappen.
Requirements are as follows:
2.
Safety Recuirement(s):
Radiation Safety Instruments:
Operating personnel shall have available at all times at least one neutron survey radiac (AN/PDR70 or equivalent) and one alpha survey radiac (AN/PDR-56 or equivalent).
Operating personnel and authorized visitors shall wear neutron and/or ga=ma radiation dosimeters of type (s) to be specified and supplied by Health Physics Sec-tion (Code X31).
The Radiation Instrumentation branch (Code R41) shall maintain a log of operations with sources.
This log will list names of operator personnel and visitors, applicable dates, exposure times, dosimeter types and dumbers, and such other infor-mation as shall be required by Codes R41 and X31.
3.
Procedure:
Neutron source (s):
When a neutron source is to be used in' air, the operator (s) shall first calculate the maximum projected-exposure rate and dose based on planned operating time.
The maximum projected exposure rate shall be confirmed by radiac measuremen; which the exposed operator (s) shall obtain from Charles Christianson for conducting further work.
The neutron source (s) shall be handled with the tongs provided and in no case shall the source (s) be manipulated directly by an operator's bare hands.
The procedures to be used will empha-size the use of suitable warning signs 'on all doors, the wearing of radiation dosimeters by operating personnel and visitors, and
' keeping a log of radiation source use and operation.
4.
Se~aled Sources:
The " sealed source" configuration must meet the criteria-established in TID-7016, " Nuclear _ Safety Guide" for
- subscriticality by virtue of quihtity, size; volume or dimension before procurement or use in the laboratory.
In addition, the basic configur,ation of the sealed source shall not be altered
-in-any way during use.
Additional quantities.cf special nuclear caterials shall not be used or stored in the same or-in adjacent rooms.
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LEAK TESTING PROCEDURES r
1.
All sealed sources will be leak tested by the Health Physics Section as described below:
Alpha sources at three (3) month intervals; Gamma sources at six (6) month intervals a.
Technioues Employed (1) Filter paper wetted with alcohol (or other suitable solvent), or ry, will be zubbed over the source or the appropri'ately accessible surface of the storage container.
.(2) Cotton-tipped wooden applicator swabs, either wet or dry will be rubbed over the scarce or the appropriately accessibic surface of the storage container.
b.
Counting Methods (1) Each wipe or specimen will be counted.for alpha and beta-gamma in equipment of sufficient senitivity to perform the test. A list of the detection instruments is part of this attachment.
- (2) If any leak test reveals the presence of removable radioactivity in excess of 10% of the limit of 0.005 microcuries (i.e., 5 x 10~4 microcuries) the source shall be imediately withdrawn from use and will be decontaminated or disposed of according to regulations. The following' calculation is used in making these determinations:
cpm ( bserved) - background Efficiency =
dpm of standard
.3969 cp - O cpm
=
Efficiency =.
1.39 x 104 dpm
% Efficiency.= Eff'. x 100
.3969 x.100 = 39.69%
Net epm (of sample) '
dpm =
efficiency 100.78 dpm dpa =
=
396 r
ff00 r dpm (of sample) x (4. 51 x 10~7) microcuries =
pei
-5 6
C 54 x 10 uci or 2
0 100.78 x (4.51 x 10- ) = 4.54 x 10 pei
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The.NRC will be notified within five days of any leakage in excess,of 0.005 microcuries
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K-Additional Information:
Pi toniu::r hafety Recuirements There are three main hazards involved in the use of plutonium: criticality, pyrophoricity, and high toxicity.
1.
Criticality (i.e., 235, g3}U,ticg}gtyistheconditionwhenfissionablematerial U
Pu, etc.) is capable of sustaining a chain reaction.
2.
Pyrophoricity Plutonium metal, hydrides and metallic alloys especially in a finely divided state, are capable of spontanecas ignition.
This property of plutonium requires the installation of an automatic fire smothering system.
3.
Toxicity Plutonium is one of the most dangerously toxic radioactive elements known today.
The long effective half-life and its alpha emissions have been known to produce neoplastic growth in the bone tissue of lower animals.
In man, the recommended permissible body burden f'or the bone is 0.04 uCi which is 2.5 times more restrictive than radium.
The easiest method of entry into the human body is via contaminated air.
Proper design of experimental apparatus and good housekeeping are the first steps toward aerosol control.
After a project has been initiated, air and surface monitoring should be performed regularly.
All solutions of plutonium must be covered when not in use.
Another method of entry is via contaminated wounds or breaks in the skin.
Once the material is present in the subcutaneous tissue, plutonium will slowly but continuously be released into the blood stream, liver, and bone.
Therefore, all open wounds should be covered before starting work.
Any contact with plutonium should be followed by alpha monitoring and decontamination, as necessary.
Operations involving plutonium solutions should be performed in a glove box (unless specifically exempted in an SOP approved by the Health Physics.Scction.
Insofar as possible, the glove box should be,a completely closed system.
It is imperative that no. leakage of plutonium from the glove box be tolerated since an escape into the laboratory may contaminate the entire building and the building ventilation system.
In the event of such contamination, the building must be evacuated and will remain unoccupied until satisfactory decontamination can b'e completed.
9 (From Radiological Safety Manual Naval Surface Weapons Center Instruction P5100.5A Addendum Mo. 1)
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RADIATIO 1 PROTECTION PRCGR/44 1.
RADIATION USER STAFF Dr. J. S. di Rende, Head of the Research & Technology Depart.ent has the respcnsibility for work performed by this grcup under this license. M r. P. P..
Wessel, Head of the Radiation. Divisicn directly supervises cperaticns.
2.
ORGANIZATIONAL AND ADMINISTRAT!VJ PROCEDURES a.
General - The Radiation Safety Comitee is responsible for reviewing and approving radiatien safety policies for the Center as well as requests for use of Nuclear Regulatory Ccc ission (IIRC) license material.
Primary responsibility for radiation safety control at the Center is assigned to the Head, Health Physics Section, Occupational Health Branch.
Health Physics is res;cnsible for the prcmulgation and enforcement of recuired safety prac-tices pertaining to the u're of radioactive materials and radiation sources.
Users of radioactive materials and radiation sources at the Center must cc ply with the radiatica safety requirecents of the Radiological Safety Manual (currently being updated) and the Standard Operating Procedure (see Ifea 15 Attachement D-b) which pertains to the use of specific radioactive mater-tal or radiation sources.
b.
Radiological Safety Officer - The Radiolcgical Safety Officer (RS0) has the overall respcnsibility for the Center's radio-logical safety program which includes the Radiation Protecticn Program for the UCM-5X Neutren Calibrator. The Head of the Health Physics Section is the RSO for the Center.
c.
Health Physics Section - The Health Physics Section is an organized part of tne Occupational Health Branch, Safety t
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Division, Ccer.and Support Department of the Center.
It consists of the following personnel.
j (a)RadiologicalsafetyOfficer i
William G'.' Neall, Health Physicist Phone: 41785(Work) 932-5918 (residence)
(b) Staff:
Alphonse Douyon, Safety Engineer Phone 41842 (work) 439-5108 (residence)
- For resume's of RSO see page h, for staff members see page(>
Page 3 1 of.
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TRANSFER OF RADIOACTIVE MATERIAL No radioactive material will be moved within the Laboratoty without' prior approval and documentation by the Health Physicist in accordance with this license application.
o 4
GENERAL RADIOLOGICAL SAFETY PROCEDURES i
L The control procedure for use of radioactive material requires the pre-l paration of a Standard Operating Procedure (SOP) as described in the NAVSUC Safety Manual P5100.5A by the responsible supervisor within his assigned j
The 50P is reviewed by the appropriate Division Head, and if approved area.
is fonvarded to the Health Physicist for general review and consideration as to the adequacy of safety requirements. After review and Safety's approval, the S0P will be fonvarded to the investigator's cognizant Department Head for final review and approval.
The Health Physics,section of the' Center is responsible for the protection of labor.atory personnel and the environment i
from radiological hazards.
This includes ad. equate radiological i
safety measures for all laboratory personnel who work in spaces l
where radioactive material is ussd and/or stored.
I Special monitoring'is performed on a case basis or when requested where any experimental or maintenance operation may j
involve an unusual radiological hazard.
These services include special monitoring of film badges, pocket docimeters, and ap-
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propriate radioclinical examinations for. evaluation of internal contamination.. (These. examinations will be done at the National l
Naval Medical Center, Beth'esda, Maryland, when required._ A supply of calibrated portable monitoring instruments, adequate to measure all types of radiation, are provided by the Naval Electronic Systems. Command, Washington Navy Yard, Washington, 6
D.C.,
203SO, for the' Health' Physi'es section, and for use by inve'stigators for 'self-monitoring purposes.
The Environmental Laboratory in Building 71, and Room 141, Building 70, are designated as restr'icted areas and as such l3 l
are provided with nece'ssary lockd and interlock systems and.
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l are posted with appropriate warning siigns.
The words " Caution -
l High Radiation Area" and' other identifying information are con-spicuously posted.
All personnel who work in the area when L
radioactive material is utilized are required to follow ra-
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dialogical safety procedure &.
Film badges are worn by all per-sonnel.. Monitoring by investigators of themselves and work kj
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areas with. portable instruments are carried out freque.tly.
3 Pocket dosimeters are utilized by investi~gators whe~never they could receive an exposure to radiation of 100 mrem / week or more..
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v Whenever a dosimeter goes off scale (over 200 mr) the person will stop work and notify the Health Physics Division immediately.
It is not anticipated that the use of the listed sources will produce radioactive aerosol or waste.
Radiochemistry operations with'small quantities of SNM material will provide a medium amount of radioacative waste.
However, in the event of a leak from a sealed source, any quantity of radioactive waste generated as well as the waste from its subsequent decontamination will be placed in specially marked solid and/or liquid radioactive waste containers for all radioactive wastes.
Disposal would be to a licensed contractor.
Air sanples will be collected should the possibility of generating a radioactive aerosol be likely to occur.
A Victoreen " Vamp" Automatic Gamma Alarm or a similar area monitor will be provided within a distance of 20 feet from the experimental setup with large quantities (1 Curie or more) of sealed sources.
This instrument is equipped with both an audible and visible alarm to indicate any increase in radiation background level.
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5-SPECTAL PRECAUTIONS Although the Pu239F source with its containment has been deemed nuclear safe, the following additional precautions will be followed:
1.
Experiments involving this special nuclear material will be isolated from other such experiments.
To confor= to the above, no other special nuclear =aterial will be used or stored in these facilities (Environmental Laboratory - Bldg. 71, or Room 141, Bldg. 70) during use or stcrage of this nuclear material.
A buffer distance of at least 12 feet will be required between other possible neutron source.s within other areas of Buildings 70 and 71.
2.
The basic configuration of the source shall not be altered in any way during use.
6'. MONITORIUG In order to assure that adecuate safety procedures are being followed in experiments with radioactive =aterial, the-use is checked by Health Physics Division personnel.
Monitoring consists'of surveys for radiation dnd contamination levels with portable radiation detection instruments and by the swiping of working areas for evidence of removable activity.
All sources will be leak tested upon receipt, prior to issue, and when in use at three (3) month: intervals.
Leak tests will be made by the Health Physics Section-personnel. - This is accomplished by saturating a filter paper with alcohol and wiping the appropriate accessible surfaces of the device in which the sealed source is stored.
This will be accomplished by the use of long tongs and portable shields ii.
required.
Wipes will be counted in an appropriate detector.
If any '3eak test reveals the presence of an activ#.ty of 5 x 10-microcuries or more, the source shall b( i=:ediately withdrawn from use and decontaminated or disposed of in accord-ance with Nuclear Regulatory Co= mission regulations (Title 10 CFR 70.201) and the " license condition for leak testing."
Air sampling is also conducted if there is a possibility of airborne activity.
A routine monitoring progcfm will be conducted in spaces where radioactive materials are"used and stored.
Areas immediately surrounding these spaces will also be surveyed to determine any egress of radioactive =aterials.
Periodic check surveys by the responsible Eealth Physicist will be conducted to determine radiatier. and centamination levels in his areas of respcnsibility.
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Emergency Action:
In the event of an Emergency such as: Soure.e positioner Jamming; container hang up; fire in rocm involving the source (s);' loss of power, the following ix.ediate action must be taken:
a.
Evacuate all personnel from the icmediate area to an area in which the Radiation levels are less than 2 milliroetgen per hour (rR/hr)-
b.
Secure area and post someone to prevent unknown and none>t'.arized entry.
Erect sign stating nature of hazard and operator's name and extension.
c.
Contact Health Physicist immediately at 41785 or 933-5918 (hece),
appropriate personnel as the situation deemed necessary.
Fire Department: x41333 Sources Custodian:
x41566 498-2804 (home)
(Charles Christianson)
(CL Guard) - Security x41712
-Safety Office - x43530
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lidliiAT10N 1ANAGT10iblI.} Tit lHibilk'.'s 11; U:.;::, bY Tils; it?.ALTil 8'l!Y i1CG DIV1310N AT KOL Il1CLUDE Ti!E FOM.0W1ilG i.
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c NUMIiER JtADIATION SEK3ITit!1TY WINDOt.' TylCKNLTJU ei INSTRt! MET AND TYPE.
- AVAILABLE DETECTED RANGE
' (mi/cm )
U.9E AN/ PDM 27()
p-y 0-500cr/hr 4-5 Dooo Rate and End tlindow GM Contamination Monitoring -
3 Encloced GM i
B:rksley 2750-1 2
p-Y O-20 mr/hr 1-4 Doso Rate and Contamination Monitoring N'berlinoEll2B 1'.
p-Y 0-20mr/hr 0-50 Donc Dato and I
Sido Vlindow CM Contamination Monitpring El-Tronics CP3-D/Cutio Pio d'
p-y 0-10 r/hr O.25 mil Doce Rato Monitoring Ionization Chambor.
8 1
0 -1,0.00-,p.oo Pm -
a Radipa,qtivity Monitoring Baird-Atomi.. -
c --
c s.
s.
Seidti11ato'r T M I-e so Victorcen 440 1
p-g -
. O-300 mr/hr 1
Doso Rate Monitoring M-Ionization Chamber
'l Nucicar Roscarch.Coc. 3., 2
- r-D' O.1-50mR/hr 30 cst.
Area'm.onitoring
.c BZ--216/UD GM "ictorcen-740 4
p-y 0-10 r/hr b Ionization Chamber 0.25 mil Doso Rate Monitorin6 s
.Polyethylono Ionization Chamber' Polyethylene Bota Shield
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,e ATTACllMENT ;B i
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ItADIATION DETECTION Il10Tlu)'1EI1TS IN USE BY Tile IIMALTil PJIY3IC" ' DIVISION AT WOL INCLUIE Tile POLLOWIifG m
44 WIN 00'.-l TilICXNESS
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f J_?iSTHU'h:1:T AMD TYPE AVAILABLE DETECTED RA?,'CE (me/cm2)
USE All/PD31M113A
,3 py 0-20 mr/nr 0 50 Monitorinc End Window GM AN/PDR 56 6
3 a
0-10. cpm 1
Cont. amination Scintillator Honitoring Dosimeters IM-9E/PD 3
Y 0-200 mr/hr Pocitet Chambor (Direct Reading)
Pornonnel V
Donitrctry i
Dosimotor Charger - Kole! cot 1
Charginc Percbnnel Dattery Operated Douimet.cro Air Sampler 7
a-D-y _
~25 CFM Staplex High Volumo Acronol Samplo Collector a
Film badco,
ac nooded p-y
'. 0 01 - 10 0 0 irtem -
,.- Mcutron,I}cta Q Gammata Nat. Ilaval Medical Centor (Type 6'3()*
n-0.02-20 rem Personnel Docimetry 39 -
Daird-Atomic-M-135 41 p-y 0-1,000,000 cpm' 1 Air-Water Wipe I
Scaler w/cnd Window GM Samplo Counting j
linmner NS-11 Scalcr 1
a 0-999,999 cpm
'l Air-Unter Wipo Scintillation Counter Somplo Counting
. g Victorcon 440 RF 1
p-Y 0-300 mr/hr 1
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Icnization Chamber Doso Rato Monitoring UNILUX-IIA - Liquid 1
p-a up to Liquid Scintillation Scintillation Counter 99,000 counta Counting
- Type /~hasonlybota-cammadetec'tioncapability; Typo A has qcutron,uradigti.on..,,.j g._,
t detcetion capability.
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HADIATION DETECTION II'GTRUMHitTS IN USE 'BY TilR !!EALTil PilYSICO DIVISION AT WOL-I!1CLUDE.Ti!E FOLLOWJNG 4,
O n
d
..<iNDO'.f TilICKNESS IN.9TfiUMEF.T Atb TYPN AVAILAllLE DETECTED RANGP.
(ma/cm ).
U.lE 2
y
'l
/J up to OKn
- Laboratory t
1 Air '.later Wipo a
Radiation Detector j
sepa atc" 1,000,000 counts.
.' Sample Counting l
crystal AN/PDR-70 (Snoopy) 1 Neutrons 0-2,000 mr/hr Decicned to inencure thu
. biological doce rate of O.
neutrono rancing in enorcy i
from thermal to 15 Mif/.
s Victorcon Neutron
.1 Neutrons With cadraium Doce Rate Monitoring Survey Moter'488A
& polyethyleno,
moderators 800,000 cpm 3
Gl Victorcen Neutron 1-Neutrons a
n Doso aato; Monitoring t.o Uurvey Motor 48,8
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- ;: u 1.c.
.g CF-95A 1
Y 0-600 R Reading DT-60 Docirr.etero
) O. DT-60' 20 y
0-600 R Perconnel Monitorinc I
IM-153 Porconnol Monitoring 2
Y 0-1,000 R
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- RADIATION DETECTION IUCTRUMrMTS IU USE DY TI!E HEALTH PHYSICS DIVISION AT EOL-INCLUDE TIIS.FOLLOWING 44o s
WI.NDOW TilICIC ESS 2
IMSTRUMTC ' A TYPE AVAILICLE DETECTED RANGE (mg/cm )
USE p
y -p 0-500 n/hr
'4-6 Range AN/PDR-433-
. Monitoring Indication Shipboard isN/PDR-G5 1
7 0-10,000 r/hr Monitoring q.
Monitoring 0-500 r/hr 72/PDa-18 1
.y,
Gamma & X-Radi.a-Victorean R Meters 2
0.250-1000 R
- y tion Exposures with 2 Ch:anbcrs Quart: Pibro Dosinctors
);
IM-101 19
,Y 0-1 R f3' n!-9P 17 7
0-200 MR Y"
0-5 R IM-135-7 y
0-600 R IM-143 11 y
PP-4276 Charger for abovo Pocket Dor,imeters 1
h'ide Data II Planchot 1
p 0.1 to 2,000,000 cpm 500 Air-Wat'cr wipe 2,
Counting Syctcm Gas Flow pgm/cm samplo counting up to 999,999 Photunulti-Air-Water wipe sac-4 1
a Scintillation plier Tubo samplo counting 2" dia, 10 Phosphor stago, S11 re-sponso, end window l
l 4
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t j-1'ETHOD, FREOUSNCY, AMD STAEDARDS USED IN CALIBRATING II STRU::ESTS
. Radiation detection instruments are serviced on a recular
./j periodic basis, or as required (instrument. failure, etc.)'.
The electronic conponents are checked quarterly and each instrucent is calibrated at six month intervals or every other tine it is sdrviced.
In addit $cr., caen ic.strunent is checked immediately I
before use with e, small radipactlye test standard containin;-
l' mieregram quantities of Ra22c, Coco, or natural Thorium.
Instru-ments taken froc storage are checked and calibrated prior to use.
I Electronic and calibration services for portable instru-ments are perforned at the local Eadice Repair Facility, Naval Electronic Systems Co= mand, Navy Yard, 'dashinr: ton, D. C.
Each instrument is calibrated in accordance with the conditions of 3
the:Radiac Ecpair Facility's AEC License Humber 03-03179-02.
l I
Counter-scaler sys' tens a're checked (and repaired) for i
l electronic performance by instrur.ent technicians at MOL.
Count-ing systers are calibrated by Health Physics personnel for operating plateaus and are checked daily with calibrated standards,. e.g.
Radionuclide Activit.v (dom) 2 An 41 1580 f
Am2N1
~
1.11 x 104 I
90' 4
Sr 2 51 x 10
~
N l
Sr90
- 1.11 x O
=.
i 110 4-Ag 5.87 x 10 60 2.85 x 104 Co 60
[
Co 1,11 x 105 60
' 1,11 x ac6
-Co
-Cs 37
,1.11 x 105 1
Cs 37
'1.11 x 106 1
~
5-p, g I..t i x 10 Page 4 5 of 6
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--:- -. ~. - -,. - = = -
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Radionuclide Activity d '.
1N 5
1.11 x 104 C
dpm 2
, I 1
Ba 33 1,11 x 105 dpc
. t. -
Ba133 1.11 x 106 dpd
~
U 38 2
.l 4.44 x 103 dom j
Pu239' 7,3 x 10 epa 4
s' l
2 Pu 39 1'.8 x 103 dpa 3
Tc99 9 54 x 104 dpa 1
Id 9.0 x 105 dpn for instrument perfor ance.
N a
t Air samples are checked prior to use and occasionally thereafter or as reo.uired to deternir.e the air fica.
s 1.
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L-m
WILLIAM G. NEALL FORMAL EDUCATION
- 1.. Degree in Bachelor of Science with major in Chemical e
Engineering, Acadia University, 1942 2.
Elementary Nuclear Physics, NAVPERS 10775 Navy Training Course, 1952.
3.
Interaction of Energy with Matter Parts I and II, NRDL Orientation Course, 1951-1952.
4.
Radiological Defense and Atomic Medicine Practice, Naval Medical School, Nat. Naval Med. Ctr. Training Course, 1954.
5". ' Introduction to Nuclear and Atomic Physics x 410 ABC, U. California (extension), 1962.
6.
Nuclear Defense Construction Engineering Course No. 44, Navy Training School, Civil Engineers Corps, 1968.
7.
' Basic Radiological Health, Bureau of Radiological Health Public Health Service, HEW, Rockville, Maryland, June 1970.
i
~
8.
Nuclear Emergency Team Exercise Facility, Field Command Defense Atomic Support Agency, Sandia Base, Albuquerque, New Mexico, 1970.
9.
Health Physics Society Meeting, Workshop in Neutron Personnel Dosimetry, and Some Aspects of 14C Released to the Atmosphere, Atlanta, Georgia, July 1977
- 10. New ICRP Recommendations For Internal Dosimetry, Bethesda,
- Maryland, August 1977.
I PROFESSIONAL EXPERIENCE t
l 1.
Radiological Protection Officer, Naval Surface Weapons Center, White 9ak, Silver Spring, Maryland, 1969-1979.
2.
Assistant Head, Health Phy. sics Division and Industrial Safety Specialist-Navel 3adiological Defense Laboratory
.(NRDL), 1963-1969
~
3.
Senior Investigator, Health ' Physics Division for Chemica]
!~
Technology and Bio-Med' Divisions, NRDL, 1953-1963.
l
[
i r
Page 5 10f 7 4
S Mw v
v
1 3
Area and Cc;.cinehtal U. g Field Projects in Pacific Test Radiation S;fety, Officer 4.
J. Facilities,!!RDL, 1954, 1957,
.1959, 1961, and 1964-1969.
5.
Engineer, Radiological Safety Branch, !!RDL, 1951-1954.
~
b.
Head, Health Engineering Unit, NRDL, 1948-1951.
PUBLICATIONS AND LABORATORY REPORTS 1.
Three Keys to Radiological Safety and Your Guide to Radiological Safety, 1949, (joint author).
2 Ha zarc bom Industrial Operations on Surface Contaminated with RaJioactivity,1949, USNRDL AD-14 4(H) (Joint Author)
. 3.
Performance of a Vacuum Blasting Equipment in Removing Low Level Contamination,19 51, USU?IL AD-301 (E).
4.
Radiological Safety Hydra I, David Taylor Model Basin, 19 60, USNRDL TR-42 3.
' 5.
Radiological Safety for Land Reclaimation Measures at a Fi' eld Facility,196 S, USNRDL R EL-S 7-13.
MISCELLAMEOUS J
1.
Ccctified Health Physicist, American Board of Health Physicists, 19 50.
' \\_
- 4
~
. Page 5 2 of 2
'\\
.1
. I.,
Alphonse Douyon
\\
RESUME Education:
Bachelor degree in Sciences: University of Sciences, Haiti, W.I.
Major : Mathematics.
1956-1960 Physics-English-Mathematics : Oregon Instute of Technology, Klamath Falls, Oregon Sept. 1964-Sept. 1965.
i-Bachelor in S'ciences in Civil Engineering: Chicago Tech. College Major: Structural. Chicago, Illinois. 1968-1972
...s Review Engineering courses for P E. licence-University of Illinois Spring 1972. Chicago, Illinois.
Mas.ter degree in Sciences courses : Catholic University.
Maj or : Radiation. Washington D.C. September 1978 to present.
Experience:
Civil Engineer-Daniggelis Associate Engineers. Chicago, Illinois 1968-1974 Civil Engineer-Design 4 6onstruction, University of Maryland Collyge Park, Maryland. Jan. l'977-Feb.1978.
Safety Engineer-Naval Surface Weapons Center, White Oak Maryland.
March 1978 to present.
Training:
(
en job)
.Non Ionizing Radiation, Laser Microwave Hazards. Dept. of'the Army Aberdeen Proving Ground. Maryland. 21-25 Aug. 1978.
General Safety training. Courses. Federr.1 Cafety 6 Health Council NSWC. (20 classroom hours). Feb. to April 1977 Ge[eralSafetytrainingCourses: Federal Safety 5 Health Council NSWC
( 20 classrooms' hours) Feb. to April 1978 Safety Professional Development. University of Maryland, College j
Park, Maryland. 13-19'Oct. 1978 I
Safety Programming. Univer,sity of Maryland, College Park, Maryland 29-30 Nov. 1977.
ir, High Energy Laser System Design.
NSWC.Dahlgren, Virginia Oct. 30 to Nov. 3, 1978.
1 i
Pace 6 1 of 2
- - ~.
e Training:
(on tne job)
Health Physics Branch NSh'C White Oak, Maryland January 1979 to present.
- 1) Primary responsabilities and duties are assisting -
~
Health Physicist in the preparation of licences applicatio for Nuclear Regulation of Sources in expericent by the Labo.ratory Staff, and writing th'e Safety procedures, for.
the Users.
~
~
. 2) Provide direct assistance to the Health Physicist in supplying Radiation services to the various Radioactive materials, and X-Rays Radiation users throughout NSWC.
~
e
- 3) Maintain Radiatich-Detection equipment in a response readiness status, periorning voltage and pulse plateaus and nino~r repairs to the equipment.
- 4) Maintain the performance of the Radiation Detecti~en equipment consisting of : instrument background counting
- results, Radiation Standard counts and the calculated efficiency for each instrument in use.
- 5) Make. Mechanical sketches of special equipment used in '
Radiation Experiments, and layouts of Building locations.
s /,
3 Page a 2 or :
=..
r
~
Name. Education Gordon Riel: BChE,1956, MS, flue.1961,' PhD,1967:
Licensed Professional Engineer, State of Md., Nuclear T'
and Chemical, since 1970: Various short courses in-
]1 cluding training as a meember of the Navy's Nuclear Emergency Team (HET) for five years.
J3]8 D: tails of Education and Experience:
j m'
~ Graduate study at the University of Maryland included operation df both the large
- ]
C9-60 radiation facility and nuclear reactor.
Reactor experience included safe i
handling of experiments retrived from the core and beam tubes, and monotoring and disposal of the water clean up ion exchange resin.
Training with the~ nuclear emergency team (NET) involved exercises with radio-isotopes at NAVSWC and field facilities.. Once each year, the team was trained at the DASA NET training facility in New Mexico. This involved a week's work in both classrocm and field. The above exercises included wearing protective clothing, using respirators, measurement of various types of radiation, plotting radiation contours, establishing stay times, monitoring and cleanup of personnel and gear returning from the contaminated site, and computation of individual and group ra-
. diation dose.
r The past four years et NAVSWC have been involved in both research and in use of i
neutron monitoring equipment. These include the Navy's AN-PDR-70 (A Neutron REM reter, based on the design of Anderson and Braum), the Hankins 9" Sphere rem meter (and it's companion 3" Cd covered sphere), the LiFTLD Albedo nuetron pe.sonnel cosimater, an area monitor based on the LiFTLD, a neutron spectrometer using liquid scintillator with multi-parameter analysis (of energy and time) to seperate neutren and gamma spectra, and the multipshere neutron spectrometer described by Bonner, using matrix solution developed here (after Schofield, Gold), for the response functions calculated by Sanna.,
Usa of this equipment has included. routine measurements of dose equivalent rate,.
i computation of quarterly dose to personrel, and evaluation of errors in REM meter Alb:do TLD, and Area Monitor indicated.oae equivalent caused by field radiation spectra which differ from the calibration spectrum.
Ressarch has led. to the design of a new area inonitor and a new neutron cal-r 2
ibrator with better than an order of magnitude reduction in dose to personnel.
l
.(This calibrator requires the sources s,pecified in this license).
{
h Modification of the old calibrator resulted in a 7 fold reduction in dose
!q N
l to personnel.
Field installation of this modification as well as calibra-3 tion, measurements on our fast neutron rang.e,"' have involved handling the M
5 Ci PuSe neutron source.
03 l
O 1
l
- 4 Page 7
=
.. n
.e
L. E. MURRAY Experience with Radiation For the past ten years I have been employed as an Electronics Technician in a test and evaluation section of the Nuclear Physics Branch of NSWC.
In this capacity first article tests are perfomed on radiacs. This involves checking their response in a known radiated field. Often problems arise that are not related to radiacs but are indiger.aus to nuclear physics, such as measuring exit doses of weaponry and 'npping containers.
I have also served four years on the Nuclear Emergency Team and was also a member of the Rad Safe Committee for one year.
(Calibration of all Radiacs were my responsibility as well as maintenance on field exercises.)
For t'he most part I was trained in all asoects of Item 8 while on the job.
Additionally, several short courses offered by the Health Physics Section of NSWC were attended and for approximately 10 days each year while a meaber of Nuclear Emergency Team, I received additional training.
s Subjects of the Instructions Accident Response System Emergency Team Nuclear Physics Review Operating Procedures Alpha, Beta, Gama Detecti 7 Instrument Safe Handling of Radiosotopes Air Sampling Technics Protective Equipment Radiological Accidents l
Cs 37 112.64 ci NSWC, on the job 1 yr Dosimetry and Radiac Response Csl37 83.2 ci Csl37 20.4 ci Csl37
'80 ci Pu23s 5
ci 2 yr Co60' 300 ci 6 mo Co60 3.8 ci 6 mo
~
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Page S
_1.__..
__ ~
~.
RESQ!E CHARLES CHRISTIANSON A.
For=al Education 1.
Degree in Bachelor of Science in Electronics Engineer with =ajor in both Physics a=d Mathematics. Manhattan College, New York 1952 2.
Graduate Courses in advanced Nuclear Instrumentation and Nuclear Reactor Engineering. 'New York University and Pratt Institute 3.
Navy human factors, Washington, DC 1963 - Introduction to Ccoputers, NASL, January 1963, System Eff ectiveness, NASL, November 1963.
3.
Professiona1 Experience 1.
Previous positions held in fields related to current position:
a.
Electronic Engineer (GS-13) from 2 September 1973 to Present at Naval Surface Weapons Center, White Cak, Maryland. Principal investigator of Fleet's Tritium Monitoring Equipment Improvenent Program. As designated Program Leader, supervised the work of one Physicist GS-13, one Electronic engineer, GS-12, and two technicians in the cenduct of the Research, Development, Test and Evaluation of criti:al radiation monitoring equipments for the nuclear e-d FEM fledts. This problem was the secchd most recurrent equipment failure problem in the FF21 fleet.
This program required extensive interface with the sponsor (NAVELEX), the end user (the cperatin;; Navy) and venders and manufacturers.
The major task of the program has been successfully completed and the fleets requiresents for effective and reliable monitors are being met.
b.
Supervisory Electronics Engineer (G) (GS-13), from 3 September 1961 to 20 December 1964 at US Naval Applied Science Laboratory. As Senior Task Leader in the Nucleonics Branch of the Physical Sciances Livision, directed a group of 7 to 10 scientific and engineering personnel (grades GS-9 to GS-12) in nucleonics R&D projects.
c.
Supervisory Electronics Engineer (G) (GS-12), from 27 November 1960 to 3 September 1961 and Supervisory Physicist (NP) CS-12), frem 6 March to 27 November 1960, at the Material Laboratory. As Unic Head of the Equipment
. Development Unit of the Nuclear Instrumentation Development Section, directed a group of six Electronic Engineers and Physicists in R&D Naval Radiac Equipments.
d.
Supervisory Electronic Scientist (GS-12), from 9 March 1958 to 6 March 1960 at thd Material Laboratory. As Unit Head of Radiation Monitoring Unit, directed a group of six Electronic Engineers and Phys. cists in R&D of nucleanic techniques, procedures, and instrumentation for specialized nonitoring problems associated with operation of Nuclear Powered Submarines.
2.
Previous Research Experience r
a.
From 6 July 1970 to 2 September 1973 Senior investigator, Electronic Engineer, GS-12.
Condu:ted basic and applied research on high sensitivity GM tubes, rr.dicactive standard sources, counting techniques for accident dosi=eters, standard light sources f cr thermoluminescent dosimetry systems.
Such research directly related to current work.
Page 9 1 of 4
=
s b.
Frc= 1 July 1963 to 1 June 1970, Task Leader, Electrcnic Engineer G S-12.
Conducted basic and applied research on the Effects cf Ther=al Radiation frc= Nuclear Weapons en Ships' Radiacs and Cther Ship's Structures and the Develop =en: of Hardening Techniques.
c.
Frc= 6 Dece=ber 19c4 to 1 July 1963, Task Leader and Specialist, Electronic Engineer, GS-12.
Conducted EDT5E in Radiation Hazards Progran.
Pri=arily concerned with applied research and develep=ent of Prctectic: Devices f c-- Personnel f ree: Mierevave and RF Radiation Hacards.
d.
Frc= 6 Nove=ber 1953 to 20 Dece=ber 1964.
Cendue:ed applied research in Nucleenics and Radiac Pr:gra=s. This verk has resul:ed in the R53 of a c:x:plete 3 eta Ceu= ting Syste= for the radiolcgical c;pnitcring of the envire==ents of nuclear povered ships. This verk required the deter =inatien of the beta and ga==a sensitivity of GM detecters to a spectru: cf radioise cpes in various gec=e: ries to deter =ine basic counting efficiencies. The counting efficiencies deter =ined for the gaseous radioisc:cpes Argen-41 a d Xenon-133 w ee a unique and criginal effer: in the field. As Senicr Tas'c Laader and Uni:
Hesd, the incu= ben directed the tech =ical efferts and provided regular revie and guidance for frc= 7 to 10 scientific and engineering persennel.
His ass.
- ents were broad in nature as to technical require =ents and he received a =ini=u=
cf technical guidance frc= the 3 ranch Chief. During this peried of verk, he devised nev techniques and procedures for counting radicactive sa=ples and developed acvel apprcaches to carry cut tasks and resolve proble=s of critical nonprecefen: natur e.
J C.
Professienal Standing 1.
Societies Sig=a Pi Sig=a, Physict Ecucr Scciety Nevten Mathe=atics Society Albertus Magnus Guild 2.
Heners and A ards s.
- a.. Outstanding Perfer=acce Award (October 1974 to Sep:e=ber 1975) for Progra= Leadership of Fleet's Tritiu= Mcnitoring Equip =ent I=prevement Progra=. QSI of December 1975.
b.
No=inee for Naval Applied Science Labora: cry Director's Award for Scientific Achieve =ent for the Year 1962.
c.
Ten letters of ce==e.dation fcr varicus accc=plish=ents, such, as Outsta ding Werk Perfer=ance, Unique R&D Effort, Paten: Diclosures, etc.
d.
Three 3eneficial Sugges:r#cu Awards.
~
~
e.
20 years, Length of Service Award.
1-Page 9 2 cf 4
4 3.
Consultation services as technical specialist and advisory authority on:
a.
Problem areas in Navy Rad Haz Program (Radiation Hazards to Personnel from Microwave and RF sources) to NAVSEC, BuSanda, BUMED, US Army and Air Force, FAA, RCA, and BASA, 1964 to 1968.
b.
Precedural and developmental probleme in nuclear instrumentation to BuShips, BuUeps, BUMED and Surgery, BuSanda, Nat'l Bureau of Standards,
,RCAF, RCA, Vic toreen, Raytheon, Reactor Test Sites, Knolls Atomic Power Laboratory, Code 1500 (BuShips) and various nuclear powered submarines and surface ships, 1960- 1964.
D.
Scientific Contributions 1.
Reports and Papers a.
Author of NAVSHIPS 93393, A&B, " Counting Ta
.s, Procedures and Instrumentation for Measuring Radioactive Samples Al.rd Nuclear Powered Ships," January 1959, June 1960 November 1963, in excess of 1000 copies dis tributed.
" Filament Wound Plastic RF l'igh Voltage Insulator Link for Ships' Cranes, " published by NAVSHIPS Tech. Journal, September 1967.
b.
Over fif ty laboratory reports,e many issued as ASTIA documents such as:
" Development of Techniques and Procedures for Measuring Beta-Activity of Water for Use on USS Nautilus, SSN 571." Lab. Proj. 5470, Pt. 5, Final Report, October 1954.
" Portable Survey Meter for Measurement of X-ray Hazards Associated with ' Radar (X-Ray Hazard Meter.)" Lcb Proj 5115-42 Pt 12, P.R. 4 of June 1963.
" Effects of Thermal Radiation on Radome Materials (U)," NOLTR 71-135 of 9 Aug 1971 (SECRET).
l 2.
Conf erences, Consultations, Presentations l
l a.
Presentation in February 1974 of Program Plan Package for
" Ships Radionuclide Radiation Safety Program" to Admiral J.11. Nicholson (Ships 04) - in attandance, NAVSHIPSCOM, NAVELEX, NAVSEC, NAVSliIP, NAVSQRFWPNCEN.
l b.
Presentation in October 1976 of Tritium Minitors Improvement.
l Program, Overview and Status to NAVSWC Management, Department, Division and Branch Heads in Attendance.
Conference and Consultation' with Tri-Service Radiological Working c.
Group in December 1976 on Radiac Cal'fbration Handb'ook at NAVSWC.
In attendance NAVELEX, ARM'f, AIR FORCE.
d.
Analysis of Gas Fill in 7840 Type GM Tube"," presented at Tri-Service Conference on GM Tube Technology, OCD, Washington, DC Jan 1971.
3.
Patents a.
Eleven Patents issued for Radiological Detection, Monitoring and ~
Processing Methods, Equipments and Devices. Many of these equipments are in extensive use in the Fleet aboard nuclear powered ships. Other inventions-Page 9 3 of 4
are in the,araa of Personnel Safety devices for Detection of X-rays from s
Radar Tubes and Shielding from RF Radiations.
b.
Examples: " Concentration Unit for Radioactive Solutions "
- 3, 109,099 of 29 Oct 1963.
" RAD HAZ Eye Protection Device," #3,325,825 of 10 i
Jun 1967.
9 G
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6 Page 9 4_ cf 4 '-
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d
~ M SPECIAL REQUIREMENTS GOVERNING THE PURCHASING, RECEIV'ING, 9
AND SHIPPING OF RADIOACTIVE MATERIAL M
o li-PURCHASING ~
A
- 1. Authori=bd user determines the need for a.particular radioactive source.
- 2. User consults with Health' Physics personnel with ' regard to radia-tion safety requirements and submits a Standard Operating Proce-dure (SOP) to Health Physics for approval.
- 3. SOP is ' thdn' submitted to Safet'y Division for docket' control num'-
ber and to the user'_s Division Head for approval.
- 4. Upon approval of the SOP, the ' user submits a purchase request through Health Physics.
Thereques't must be initialed as approved by Health Physics pric-Lo procurement.
RECEIVING.
i
- 1. Nuclear Regulatory Commission and Department of Transportation "
l Regulations require that radioactive ~ shipments be provided 'with l
special labeling as prescribed in Title '32,S.:172.403' (a), (by, f
(c) and (d) yellow-I, yellow-II and yellow-III labels, to denote the kind and quantity of material contained.
The receiving in-l voice should also contain information stating the quantity and j
kind of material received.
- 2. If the container is not labeled, the ' shipping ~ papers woul'd no're -
.5; the fact that labeling is not required in accordance~of specifica
' h.if tion 173.391 (Limited quantities of radioac'tive materials'and W-
,t?;;
radioactive deyices) or 173.392 (Low specific activity radio-j active material).
k,-l When incoming-shipments arrive, Receiving Branch personne5 w' ll
.l i
3.
notify the Health Physics. Section immediately uhenever it is
,)
determined that a shipment contains or may contain radioact.tvc material.
Posters entitled " PROCEDURES TO'BE FOLLONED UPON L.
RECEIPT OF PARCELS CONTAINING RADIOACTIVE MATERIAL" a're conspic-i uously posted within the receiving dock,.
s-I
__._12a_
1_. o f 6 1
~
SPECIAL REQUIREMENTS G'0VERNING THE PURCHASIMG, RECEIVING, AND SHIPPING.0F RADIOACTIVE MATERIAL (cont'd)
The Health Physics Branch is responsible for assuring that any handling of radioactive shipments,uill not present a radiation hazard so Shipping Branch personnel.
The assigned Health Physi-cist will monitor throughout the packaging and shipment processes ?
to prevent exposure of any individual froh exceeding acceptable radiation dosage' limits.
Film badges S TLDsare previded-as needed.
Radioactive material shipments. will be monitored by the Health Physics ' Branch for radiation emission, prior to release from the laboratory', including possible radioactive contamination.
on the shipping container.
Shipping documants will be. checked to
' assure that the appropriate information is given as required by URC and DOT regulations.
Shipping papers will contain the following information:. -
u.
1)
The name of the~ radionuclide and' the form, or a.
description of the physical and chemical form if the material is not in special form.
2)- The' activity contained (in curies, millicuries or microcuries).
.3)
The gross neight of the container, if oven 110 lbs.
~
4)
The requirement for the trahsporting vehicle to be placarded.
5)
If the package is one which has been approved by the U. S. Energy Research and Devel'opment Admin.
(ERDA) or the Muclear Regulatory Commission (NRC),
a notation of the package ident1fication as ERDA or NRC prescribes.
6)
.The type of packaging required by.t. bgDgType B Qty.
artment of Transportation..or Type A Qty or.
~7)
The category of the label to be applied:
RADI0 ACTIVE WHITE-I:
if measures 0.5 r311irem or less per-hour on external surface and is not a "large quantity"*
RADIOACTIVE YELLOW-II:
if measures more than
.0.5. but less than 50 millirem per hour on surface and not exceeding.1.0 millirem per
' [,-
hour at three feet from any point on the external surface of package.
RADIOACTIVE. YELLOW-III:
if measures -more tha'n 50 millirem per hour on external surface or exceeds 1.'.0 millirem par hour at three feet from any surface of the package, and does not exceed 200 millirem per hour at the surface and 10 millirca per hour at three feet from.
the external surface of the package, or the package contains a "large quantity"$ of radioactive matcrial.
~
SHIPPING
- 1. Shipping Branch, Supply Department, is responsible for final packaging and shipment of radioactive material.
m
- 2. When special packag2.ng 3.s necessary to comply with regulata.ons p
governing shipping of radioactive materials, Health Physics Sec-p:-
tion will advise and assist as necessary to satisfy the require-
)%
j
- 4 ment;s.
ihl
- 3. The' radioactive material user will be responsible for transfer to the Shipping Branch of outgoing parcels containing radioactive materials.
The Health Physics Section will advise and assist-in these matters and must approve final transfer of the material for
~
shipping.
Il 4;. All shipping paper, marking and labeling shall' meet the 1
the requirement as specified in DOT Reg. Title. 49 parts: Type A QtyJ 4 172-200 thru. 172-204.; 172-300 thru 172-330.; 172-400 thru 172-446 and all packaging as specified in Reg. 173-391 thru 173.446.
1
-5..All shipping of Type B Quantities
- shall meet the requirements j
o,f-Title 10 CFR Part 71.
~
i i
t i
1 Type A Type B Transport Grp.
(Quantity in curies)
I 0.001 20.
II 0.05 20 III 3
200
.IV e
20 200 V
20 5 000 3
VI & VII 1000
~
50,000 I
Special form 20#
5,000..
5
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N
}
- except 252 Cf,. limit is 2.
\\ic g-W
~
5.
9 m
m
l Ceneral pachging and shipment reouirements:
Unless otherwise specified, all shipments of radioactive materials must maet all requirements of. this section, and must be packaged as follows:
a.
The outsido of each package must incorporate a feature such as a seal, which is not readily breakable and which while intact, will be evidence that the package has not been illicitly opened.
b.- The sma11ost outside dimension of any package must be 4 inches or greater.
c.
Each radioactive material must.be packaged in a packaging which has been designed to maintain shielding efficiency and leak tightness, so that under' conditions-normally incident to. transportation, there will be no release of radioactive material. If necessary, additional suitable inside packaging must Be usedi Each package must be capable of meeting the standards according to specification 173-398 (b) and 173.24.
F.- lo-m. M/F vQt, I' 2 5ii!e-Ff :rT vnnrse-
- d.. Internal bracing or cushioning, where used must be adequate to assure that, under the conditions normally incident to transportation, the distance from the inner container or radioactive material to the outside wall of the package remains within the limits for which the package design was based, and the radiation dose rate external to the package does not exceed the transport index number shown on the label.
Int 4-shield closures must be positively secured to prevent loss of the content..
e.
The packaging must be designed, ~ constructed and loaded so that during transport:
(1) The heat generated within the package because of the radioactive materials present will not, at any time during transportation, affect the efficiency of the package under the conditions normally incident to transportation, and (2) The temperature of the accessible external surfaces of the~
packr.ge will not exceed 1220F in the shade when fully loaded, assuming still air at rabient temperature.
If the package is transported in a transport. vehicle,
contigned for the sole use of the consignor, the maximum accessible external surftce temperature shall be 1800F.
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19 A
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When packages antaining " Fissile radioactive raterial" means the following materials: Ur aium-233, Uranium-235, Plutonium-233 or any material containing any of the foregoing materials. The following materials are not classified as fissile r:dioactis e materials are exempted frem this section and cust instead be packaged in accordance with the other provisions of this subpart, as appropraate:
a.
Not more than 15 grams of fissile material; b.
Thorium, or uranica containing not = ore than 0.72 percent by weight of fissile =aterial; c.
Uranium compounds or other than metal, and aqueous solutions of uranium, in which the toal amount of uranius-233 and plutoniua present does not exceed 1.0 percent by weight of the uranium-235 content, and the total uranit:2 content; d.
HomoZencus. hydrogenous solutions or nixtures containing not nore than; (1) 500 grass of any fissile caterial, provided the arcaic ratio of hydrogen to fissile material is greatern than 7,600 or (2) S00 grams of uranium-235, if the ato=ic ratio of hydrogen to fissile material is greater than 5,200 and the centent of other fissile =aterial is not more than 1.0 percent by weight of the total uraniua-235 content of (3) 500 grams of uranium-233 and urar.i.ua-235 if the atomic ratio of hydrogen to fissile _ material is greater than 5,200 and the content of plutonica is not more than 1.0 percent by weight of the total uranius-233 and uraniu:2-235 content.
Fissile radioactive materials packages are classified according to the controls
-needed to provide nuclear criticality safety during transportation as follows:
a.
Fissile' Class I - Packages which may be transported in unlimited number-and in any arrangement, and which require no nuclear criticality safety control, a transport.index is not assigned to Fissile Class I packages.: However, the external ' radiation levels may require a transport index number.
b.
Fissile-Class II - Packages which may be transported together in any arrangement but in numbers which do not exceed an aggregate transport
'index of 50. For purposes of nuclear criticality safety control, individual
[.
packages may have a transport index of not less than 0.1 and no more than 10.
However, the external radiation levels may require a higher transport index number but not to exceed 10.
Such shipments require n'o nuclear criticality safety control by the shipper during transportation._
c.
Fissile Class III.- Shipments of packages which.do not meet the lequirements of Fissile Class I or II and which. are. controlled to provide nuclear criticality safety in transportation by special arran'gements between the shipper and the carrier.
a e
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g
. Definitions.
(a)"Large quantity" means a quanticy of radioactive material, the aggregate of which exceeds any one of-,
the following:
For transport groups as defined in paragraph (b) below:
~
Group I or II radionuclides:20 curies; Group III or IV radionuclides:200 curies; Group V radionuclides: 5000..ctiries ;
Group 'VI"or VII sadionuclides:,'5 0,0 0 0. curies.;.
/
For special ~forn naterial as defined in pai-a -r -
~
graph ~(c) below: 5,000 duries.
.. -(b)STran' yurt group" neans anyjE5 'o...f ' s even ' gfoup s ' ........
s into which radionuclides in normal forn are
~
classified,'according to their toxicity and -
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~
their relative potential haca--d in transport.
For further infernation as to classification >
see' Code of Federal Reg's Title.10,-CCFR-10).
-Par,t 71:4 E Appendix C.
(c)".Special form" means any of the following physical forns of licr.nsed naterial of any transport.,.
group:.
- 1) The material is,in' solid foi n having no dinension les's than 0.5 r.illimeter or at Itast one'
~
dinension greater than 5 nillimeters; does not.nelt,.
,' subline, or ignite in air ~at a tenperature of 1,0000F; will not shatter.or crumble if.' subjected-to -
the' piercussion test d,escribed in CFR 10 Part' 21.
Appendix D'; and is not -dissolved or converted into
'~
dispe9sible form to the extent:of more than 0.005 %
by weight' by innersion for 1 week in water. at' 580F.
'......... ~4 or-in al.r.at.S ~o~; ;or
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- 2) The material is securely contained -in a ca.
~
having no dinesnion less than 0.5 =illinstdr or psule.
at least one dinension greater than 5 millimeters, which -
will retain, its contents if subje'eted to the tests prescribed in Appendix D (CFR 10 Part 71); an'd which-is, constructed of materials uhich do not melt, subH ~
or ignite in. air. at 1,475 F., and.do not dissolve or -
coitv ::rt into dispersible form to the e,xtent of nore than 0.005 % by weight by in=ersion for.I week in~
water at 680F. or in, air at 8SOF.
~
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PROCEDURES FOR ISSUANCE M'D PROCESSING OF FILM 3AOGES Film Badcas
~
1.
New films will be furnished on a routine monthly frequency by the Health Physics Division.
2..
Each film badge has the e=ployee's name and identifying nu=bers.
Only the person indicated may wear that film badge.
3.
Each film badge is dated to show the period covered.
4.
Control badges, not to be worn, are maintained at each rack lccation.
These centrol badges are developed monthly.
5.
Film is purchased thicugh~DASA Centract, DASA 120-71-D-3594.
Prccessing of the film is provided by the Naval Medical Center in Bethesda, MD.
The~results are' reported to this activity, and are reviewed by the RSO to determine the necessary aCicn required.
~
_i 6.
The Rad.ioicgic'al S5fety officer will review all repo'rts and I-check for any high or unusual results.
The individual involved
.and his supervi~ or will be informed of film badge findings.
s 1
{-
7.
The Radiological Safety Officer will be respcasible for maintaining a file on all film badge results~ received.
Duplicate records are maintained on a computer generated Form DD-ll41.
~
8.
Personnel working in Zone 4 areas (High Radiation Area) and/or any other place that a person.cculd receive a whole body exposure of 100 mr/hr are required-to wear two pocket-dosimeters in addLtion to fL1m badges.
9.
Radiographic personnel shall' b.e re=cved fr,om exposure' t.o.
radiation when.necessary to keep their individual dosages frc exceeding 100 mrem per week.
- 10. Lithium Fluoride Thermoluminescent Dosimeters sh'ould be used also for neutron monitoring. (see,'page 2 of Page 12b).
12b 1 of 3
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- iiT$IC1 FWCRIDE TdER'!OLTtINESCENT DOSDtETRY:
Each individual vill be issued by Health Physics section a lithina fluoride thermoluminescent dosi;aeter (LIF TLD). These LIF TW will be forwarded for reading and dose dete=ination, every 2 months (not to exceed 90 days) to the Radiological Safety Service, National Naval Medical Center, Bethesda, Maryland 20014.
.r Each LIF TOLD will bear the employee's.name and identifying numbers.
Caly the oarson indicated may wear that LIF TLD.
Each LIF TLD will be numbered
~
and lo2ged on a ' separated sheet of paper to show the period covered.
Control 15F TLD (which are not to be worn) are maintained at each rack location.
These Control (LIF TLD) are also developed every two months.
LTD Program-
.?
.... The LIF TLD 'is capable of detecting gam =a,'X-ray an'd neutron radiation.
The LIP TLD will be issued to monitor personnel for. gamma and/or neutron radiation. The LIF TLD contains. two lithic:a fluoride chips; one has been (nriched with lithium: six which will respond to gamma radiation and ther=al neutron radiation, while chip number two has been enriched with lithium seven which will only respond to ga:cna radiation.
00.00S to 1 x 10* Rea for ga=ma radiation.and 00.030 to 1 x 10TherangeofthegIFTLDis Rem for neutron radiation.
CoIIection:
~
The LIF TLD's in their holders, shall be nailed to the Radiological Safety Service, National Naval Medical Center, Bethesda, Maryland 20014, within three working "
days' following ecliection. The dosimeters shall be arranged in the same order as they appear on the ifAWlED 6470/3... The dosimeters and NAW1ED 6470/3 shall be' shipped in a mailing container,.such as box NSN 8115-00-782-3939,. (7 1/2" x 4 3/8")
cr box NSN 8115-00-782-3940 (7 1/2" x 7 x 3 3/8") that will prevent damage to the dosimeters.
Because of the cost of the LIF TLD cards 'they shall be mailed using traceable means to prevent loss.
12b 2 of 3
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The Modal L-70 has the Gamma and X-Ray sensitivity supressed so the reading s
- Ys 200 mRes full scale for thermal neutron only. Diameter 1/2" Length 1 1/2".
Model L-81 is an X and gn=ma ray chamber for 2r full scale range.
It is nor= ally worn with an open adjustable finger ring to protect the hands of isotope workers. Dianete-1/2" Length 1.1/2".
1!cdal L-60 Charcer_ reader for charging and reading above neters It uses the rugged type quartz fiber volt =eters. Batteries are easily replaced.
They consist of one 1 1/2 volt size D cell to provide light for the microscope field and si.: 22.1/2 volt.No. 412 minimax batteries. ~ heir life is at least-two years (shelf-life). The scale is markedclearly so that all the afore centioned meters can be read without interpolation. (Ref Johnson 5 Associates Catalog).
Dosi::teter: DT-518/PD Non self-indicating dosimeter capable of detecting and recording fast -
~
neutron exposure frca 10 to 50,000 rem and g::m ray doses froa 1 to 10,000 rem. This is done by means of sulfur tablets for neutron dose and thermo-luminescent powder for gama and x-t af dose: Size 1.1" x 5" x 5";.017 pounds.
Sulfur tablets are ' processed after exposure and counted. The therno-luminescent powder 2.s placed in a Victoreen 2300 =cdel unit S read.
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