ML20052A943
| ML20052A943 | |
| Person / Time | |
|---|---|
| Site: | 07001216 |
| Issue date: | 02/04/1975 |
| From: | Vehar M NAVY, DEPT. OF |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20049A233 | List:
|
| References | |
| FOIA-81-428 NUDOCS 8204290446 | |
| Download: ML20052A943 (12) | |
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DEPARTMENT OF THE NAVY
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NAVAL UNDERSEA CENTER j
SAN DIEGO, CALIFORNIA 92132 IN REPLY REFER TO:
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$p) 1104/ALS:cc j
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10330 jg Ser: 1104-6 g
4 FEB 1975 M
From: Commander, Naval Undersea Center d
To:
Chief, Materials Branch, Directorate of Licensing, 2
U. S. Atomic Energy Commission, Washington, D. C.
20545 y
Via:
Ccmmander, Naval Facilities Engineering Command (042) g Subj: Special Nuclear Material License No. 1154; request for
[
renewal of
'L Ref:
(a) AEC ltr Program Code 22120 of 2 January 1975
' Encl:
(1) Application for Special Nuclear Material License 1.
In accordance with reference (a) an application for renewal of Special
_h Nuclear Material License No. SNM-1154 is submitted as enclosure (1).
2-M. E. VEHAR By direction
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STANDARD AND CUSTOM PU239-BE NEUTRON SOURCE 3
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Soecification and Price List Plutonium beryllium neutron sources are used where a relatively constant neutron strength
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with a low associated gamma radiation dose is desired over a long life period. NUMEC y
m standard Pu239-Be sources are an alloy of
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'a** 'ana'r =
....~ commercial-grade plutonium and -berylliudt. in -
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which the plutonium is approximately 92 per cent Pu239 The nominal neutron efficiency y.
"12."$i%, s 6e,.,.a w-
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..... ww of.these sources is-1.8 x 10 neutrons per-l)i
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- . ;.;gydpN.~.
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'9 p
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."l.""'."'o<
second per curi.e. The dat..a presen..ted i. n
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the diagram at the right and Table 1 below s
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describe the standard NUMEC Pu239-Be sources.
mW f'".17. '.".."..'.*'.:."* e e,o-2 mis-3 y;
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e Table 1 presents critical specification and N
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purchase price data for NUMEC sources. De-livery is normally made immediately from
'"**'"*'as "da
.... stock.;.fo.r...s,ources in sho.r.t su.pply, two.
Stondord NUMEC Plut0niurn-DeryttiOrn-Neutron Source
..:to. four..wceks delivery is. usually.provi ca.
. Table 1 Standard NUMEC Pu 239 Se Neutron Sources (Specifications and Purchase Prices)
Catster Plutoniurn Conte.t Diarcter Length Ap;rosituate Price (2)
J Designation
. Curies Crams
. Cylinger (11(In.)
Cytincer (1) (In.)
Strengt!n (f.PS)
(U.S. Dallars)
Sources with 0.250* cap and 10/32 tapped hole:
t4GMEC A 1
16 1.020 1.445 1.8 x 10*
5 665 ilu M EC.D 2
32 1.020 2.190 3.6 x 10' 765 t4 U M EC-C 2
32 1.310 1.510 3.6 x 10*
765 HUMEC M 3
48 1.020 2.935 5.4 x 10' 865 N U M EC.D 3
48 1.310 1.915 5.4 x 10' E65 N U M EC..
3 48 1.550 1.505 5.4 x 10*
E65 ti U M EC.N '
4 64 - -
1.020 -
3.680 7.2 x 10*
965
- 4 U M E C.F 4
64 1.310 2.320 7.2 x 10*
965 N U M E C.G 4
.64 1.550 1.775 7.2 x 10' 965 N U M EC-P 5
E0 1.020 4.425 9.0 x 10*
1065 j
N U M EC.H 5
80 1.310 2.720 9.0 x 10*
1065 l
N U M EC.I 5
60 1.550 2.045 9.0 x 10*
1C65 fiU M ECrj 7
112 1.(50 2.585 1.2 x 10' 1250 N U M E C.K 10 160 1 550 3 360 1.8 v 10' 1550 l
Sources with 0.100* cap and no tapped hole:
NU M E C. AT 1
16 1.020 1.295 1.8x10*
665 i
NU M EC.BT 2
32 1.020 2.040 3.6 x 10*
765 N U M EC.M T 3
48 1.020 2.785 5.4 x 10*
865 N U M EC.NT 4
64 1.020 3.530 7.2 x 10*
965 N Uu t C.PT 5
80 1 020 4 775 90m10*
1065 PrecistoA long counter source:
N U M EC-S35 l
0.073 l
1.19 l
0.498 l
0.498 l
1.0 x 10' l
450 (1) All dimensions are 0.002 Inches.
(21 Price covers source fabrication. all USAEC use and loss charges during fabrication. Catsbration of source against standard NUMEC source, and insurance during transit within continental Uniteo States; a $50 handieng charge is added to each nondomestic order.
Proces are subject to change without notice.
Shipping containers can be purchased for customer storage use or returned to NUMEC for deposit refund.
2-Supplement (2)
Enclosure (1)
APPLICAT 9M FOR SPECIAL NUCLEAR I;IATrRIAL LICENSE 1.' Introduction Naval Undersea Center (NUC) is headquartered at Point Loma, San Diego, California.
In addition to San Diego, NUC programs are conducted at 6 other sites.
Supplement (1) to this enclosure describes the mission, major programs and major facilities of the
- Center.
All special nuclear materials will be used by UUC at its San Diego and San Clemente Island sites.
2.
References Information submittcd in previous applications, cited.in
~
this enclosure, is contained in the following letter references.
a.
NUC ltr 703/ALS:lvp 10330 Ser 70-92 of 15 Dec 1969 b.
NUC ltr 703/ALS:vh 10330 Ser 703-1 of 27 Mar 1970 c.
NUC ltr 1104/ALS:vh 10330 Ser 1104-31 of 3 Nov 1972 d.
NUC ltr 1104/ALS:vt 10330 Ser 1104-34 of 26 Dec 19737 '
e.
NUC ltr 1104/ALS:vt 10330 Ser 1104-33 of 11 Nov 1974 vf.
NUC ltr 1104/ALS:vt 10330 Ser 1104-35 of 5 Dec 1974 Hig v,W2,-n 7
3.
Types and Quantities of Special Nuclear Materials The special nuclear material will be possessed and used as follows.
a.
Pu-239-Be Sealed Neutron Source-16 grams.
This source was manufactured by the Nuclear Materials and Equipment Corp.,
Apollo, Pennsylvania in accordance with the specifications indicated in Supplement (2) to this enclosure.
The source will The dose rate at the surface of this. container pping container.
be stored, when not in use, it its original shi 1s of the order of 10 rxem/hr'.
The source will be used for calibration purposes.
It may be used as a fast n'entron source in a free-air, 3600 configuration or as a thermal neutron source in a moderating medium.
b.
120 grams as metal foil.
The program utilizing,
the material is described in letter reference 2a.
c.
20 micrograms as alpha sources for counting standards.
The use of these materials is described in letter reference 2b.
d.
40 grams plutonium (principle isotope Pu-238) as two oxide pellets.
The program utilizing the material is,
described in letter reference 2c.
e.
91 grams plutonium (principle isotope Pu-238) as three clad oxide pellets.
The program utilizing the material is described in letter references 2d, 2c, and 2f.
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Enclosure (1)
I g'n 4.
Using Personnel Qualifications of personnel conducting programs in which special nuclear materials are used.
- a. h iard J.
WESLEY, Head, Radiation Physics Division, Undersea Surveillance and Ocean Sciences Department.
Education:
B.
S.
in E.
E.,
University of California - 1948 Experience:
Head, Radiation Physics Division, NUC, 1969 to present.
Electronics Engineer and Engineering Supervisor in design and development of nuclear radiation measuring instrumentation for gamma, beta, alpha and neutrons at NRDL, San Francisco, 1948-1969.
Ten to fifteen years experience with 100 curie level Co-60 and Cs-137 and 5 curie PuBe sources used in instrument calibration.
Have used many other gamma, beta, and alpha calabration sources ranging from microcurie to curie level.
Publications 1.
Wesley, E.
J.,
" Radiation Instrumentation for the Classi-fication of Nuclear Explosions at Sea," USNRDL-TR 525, 7 Sep 1961.
2.
Wesley,.E.
J.,
- Cole, R.,
Olson, M.
A.,
Joseph, W.
F.,
Aerial Survey of the Surface Radioactivity Remaining After an Underwater Nuclear Detonation," (U) USNRDL-TR-626, 4 Mar 1963, (SECRET).
3.
- Wesley, E.
J.,
- Hopton, R.
L.,
" Radiological Search Instru-mentation," USNRDL-TR-805; also appeared in Nuclear Instru-ments and Methods 37 281-287, 1965.
4.
- Wesley, E.
J.,
" Gamma Radiation Background in an Airborne Detection System," (U) USNRDL-TR-67-13, 27 Jan 1976 (CONF).
5.
- Wesley, E.
J.,
" Neutron Surveillance Measurements Sept 25-27, 1968," Oct. 1968 (SECRET).
6.
Wesley, E.
J.,
" Gamma Ra lation Over a Nuclear Submarine,"
(U) USNRDL-LR-67-12, 5 May 1967 (SECRET) 7.
- Wesley, E.
J.,
" Submarine Reactor Detection," (U) USNRDL-TR-in print, (SECRET).
PATENTS 1.
Radiac Alarm Dosimeter 3,019,339 2.
Recycling Radiation Ratemeter 3,050,625 3.
High Speed Digital Register-Counter 3,120,925 2
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- b. /"*erberM_ WEISS _,
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H escarch Chemist, Chemistry and
. Environmefftal Sciences Division, Biosystems Research Department.
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Education:
Ph.D. in Chemistry, University of Cincinnati,1952.
Experience with Radioactivity:
Use of radionuclides to develop analytical procedures, !!eutron irradiation of materials for elemental analysis by activation.
NUC, 1969 to present.
Supervisory radiochemist, flaval Radiological Defense Laboratory, San Francisco, California,1956 to 1969.
Work at t!UC and NRDL included tracer and fission product studies with a wide variety of radionuclides, including byproduct materials, radium and transuranic elements in the millicurie ranges of quantities.
Publications (partial list):
1.
- Gong, J., Cohn, S., Shipman, W. H., Weiss, H. V.,
Uptake of neutron induced activities and mixed fission products by.
the clam.
Proc. Soc. Exptl. Biol. Med. M, 451 (1957).
.2.
Weiss, H. V., Cohn, S. H.,
Residual contamination of plants animals soil and water of the Marshall Islands two years af ter Operation CASTLE.
The Shorter Term Biological Hazards of a Fallout Field, p. 205 USAEC-D0D (1958) 3.
Weiss, H. V., Reed, J.
The determination of cobalt in seawater.
J. Marine Research 18, 185 (1960).
4.
Weiss, H. V., Lai, M. G.,
The determination of radium in urine.
Anal. Chem. 33, 39 (1961).
5.
Weiss, H.
V., Shipman, W. H.,
The determination of plutonium in urine. Anal. Chem. 33, 37 (1961).
6.
Weiss, H.
V., Lai, M. G.,
The cocrystallization of ultramicroquantities of various elements with alpha-nitroso-beta-napthol.
Determination of uranium in seawa ter.
Anal. Chim. Acta. 2_5 550 (1961).
7.
Lai, M. G., Weiss, H. V.,
The cocrystallization of ultramicroquantities of elements with thionalid.
Determination of silver in seawater. Anal. Chem. 34 1012 (1962).
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8.
Weiss, H. V., Lai, M.
G.,
The cocrystallization of ultramicroquantities of elements with 2-mercaptobenzimidazole.
Determination of gold in seawater.. Anal. Chim.
Acta g, 242 (1963).
3
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(d'
'9.
- Weiss, H.
V.,
Near-Symmetric-fission - Identification and yield of Cd-121.
~
Phys. Rev. 139 No. 2B 304 (1965) 10.
Weiss, H.
V.,
Reichert, W.,
Pd-115 yield in thermal neutron fission of U-235. J. Inorg.
Nucl. Chem. 28 2067 (1966) 11.
Weiss, H.
V.,
- Elzie, J.
L.,
Fresco, J.
M.,
Identification and yield of ll7Pd in the thermal neutron fission of 235U. Phys. Rev. 172, 126.9 (1968).
12.
Weiss, H.
V., Bertine, K.
K.,
Simultaneous determination of. manganese, cooppr, arsenic, cadmium, antimony, and mercury in glacial ice by radioactivation.
Anal. Chim. Acta. 65 (1973.) 253-259.,
~
c.
Francis K. KAWAHARA,. General Engineer, Advanced Systems' Division, Ocean Technology Department Education ~:
7 B.S.
in M.E., University of California 1950 Experience:
General Engineer, NUC, 1969 to Present Project Manager, SNS/AEC Fuel Systems Project Manager, NUC SNAP 21 Environmental Studies Project Manager, NUC Ocean Diffusion Studies General Engineer, NRDL, 1950 - 1969 Fallout studies, Operations Ferris Wheel, Sunbeam, Hardtack, Redwing, Wigwam, Castle Participated in Ship Washdown Studies and in Land Reclamation Studies utilizing radioactive tracer techniques.
5.
Administrative Controls Special nuclear materials will be used under the radiological control of the NUC Radiological Safety Officer, Albert L. Smith.
The qualifications of the Radiological Safety Officer (RSO) are as follows:
Health Physicist, Safety Office, Central Staff, NUC to present.
Head, Health Physics Division, NRDL, (U. S. Naval Radiological Defense Laboratory), San Francisco, California, 1962 to 1969.
Head, Radiological Safety Branch, Health Physics Division, NRDL, 1956 to 1962.
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Health Physicist, General Electric Corporation, Hanford Atomic Products Operation, January 1948 to October 1951.
BS in Chemical Engineering, University of Louisville, 1938.
Certified by American Board of Health Physics, December 1960.
The responsibilities of the RSO include the control and accountability of all special nuclear materials used at NUC.
Control procedures require a documented experimental plan to be submitted by an investigator for each program in which special nuclear material is used.
The RSO will investigate each proposed usage, provide rad-safety indoctrination and train-ing of each user as required and issue specific rad-safety pro-cedures to be followed.
The RSO will maintain record showing the identity, quantity, location, and disposition of all special nuclear materials.
6.
Health and Safety Measures
~
General administrative and radiological safety regulations in effect at NUC are contained in NUC Instruction 5100.3A,
" Ionizing Radiation Control Handbook", submitted as supplement 3 to this enclosure.
Contamination control measures will include use of dry boxes and/or ventilated hoods with filtered air exhaust.
Personnel will utilize appropriate protective clothing and respirator protection.
Air sampling and personnel and area monitoring will be conducted as indicated by the nature of the operation.
Specially marked liquid and solid waste containers will be pro-vided for collection of SNM contaminated waste.
Disposal will be by packaging and shipment to a licensed disposal contractor.
Radiourinalysis capable of greater then 70% recovery and less than 1 d/m sensitivity will be conducted on all personnel incurring exposure to an acrosol of any SNM in excess of the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> limit.
All shipments of SNM will be delivered, unopened, to the RSO who will open the package and conduct radiological surveys, perform any decontamination required and determine the activity content of the material.
SNM materials, when not in use, will be stored in locations under the general radiological control of the RSO, with adequate security control to prevent theft or loss.
5
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7."' Personnel-Monitoring Devices and Procedures
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The standard Navy film badge will be used for personnel moni-toring.
This badge can measure and distinguish between beta (E),
soft X-ray, and gamma (y) in the range from 20 mR (gamma) to about 1,000 R.
Neutron film will be provided for those personnel working with neutron sources, as the PuBe source.
All film processing will be by the Navy Medical Center, Bethesda, Maryland.
8.
Respiratory Protection Navy MK 5, Army MK 9,'and Army / Navy MK 17 gas masks, all with 99.9 + % efficiency for 0.7 micron particles, are available and will be used to minimize personnel exposure and to be used in the event of an accident.
We are not requesting allowance for the use of this equipment in determining the exposure of individuals to airborne concentrations.
9.
Monitoring Devices Monitoring Devices available at NUC include the following:
See next page.
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6 I
l Oty. on Instrument Type lle nd Range Purpose
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Berkeley 2750 End Window GM 1
0-500 c/m 0-5,000 c/m 6-Y contamination 0-50,000 c/m monitoring.i Eberline Ell 2B Side Window GM 1
0-0.2 mr/hr 0-2.0 mr/hr a-y contamination 0-20 mr/hr monitoringi 1M-113 AN/PDR Side Window GM 2 2
0-0.2 mr/hr 0-2.0 mr/hr s-y contamination ll monitoring l
0-20 mr/hr Berkeley 2750 Side Window GM 2
0-500 c/m 0-5,000 c/m g,y contamination 0-50,000 c/m monitoringt AN/PDR 27J End Window GM 0-5 mr/hr 3,y dose rate and Enclosed GM 2
0-500 mr/hr contamination monitoring y
1M-218/PDR-70 BF 2
0-2 mrem /hr Total neutron dose 3
0-20 mrom/hr rate monitoring 0-200 mrem /hr 0-2,000 mrem /hr 2
Nuclear Chicago Nemo BF 1
0-10,000. n/cm /sec Fast / Thermal 3
Model 2715 Neutronmonitoringg AN/PDR-58 Scintillation 2
0-5 mrem /hr Total neutron dose 0-50 mrom/hr rate monitoring 0-500 mrem /hr Eberline PAC-3G Gas proportional 1
0-1,000 c/m Alpha 0-10,000 c/m Contamination 0-100,000 c/m monitoring Eberline PAC 1SA -
Scintill'ation 4
0-2,000 c/m Alpha
~ 0-20,000 c/m Contamination 0-200,000 c/m monitoring i
0-2,000,000 c/m
t Oty. on
- 1 Instrument
- Type, Hand Range Purpose Staples, high volume Air Sampler 3
25 cfm a-0-Y acrosol collection Schmidt, low volume Air Sampler 1
2 cfm e - /3
'y acrosol collection Gelman Air Sampler 3
2 cfm a-g-y aerosolcollecticg a-B-Y Nuclear Chicago Gas proportional 1
Counting System air, water, and wipe sample counting co O
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,_ Handling and Storage Equipment
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Handling and storage equipment available at NUC includes the following:
-(l) -3 lead shielded storage and handling containers, lead shielding 1 inch.
(2) 3 fume hoods specifically.for use of radioactive' ma terials.
(3) 3 glove boxes (4) 1 underground storage vault (S) 4 neutron source storage and shipping containers (6) 2 remote handling tools 11.
Leak Tests Sealed sources as defined by 10CFR70.4 (q) are wipe' tested
~
before being placed in use and periodically at least each six months.
Wipes will be made with filter paper moistened with alcohol wiped over all accessible surfaces of the source.
After drying,-the wipe paper will be counted for alpha (a) activity in a gas pro-portional counter.
The counting syntem available for wipe counting will detect alpha (a) activity of the order of 10 7 uc.
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NAVAL UNDERSEA RESEARCH luND DEVELOPMENT CZWER San Diggo, California 92132 NUCINST 5100.3A 1104/ALS:ec
.. 24 August 1971 NUC INSTRUCTION 5100.3A To:
Departments, Divisions, and Branches Sub).
Ionizing Radiation Control Refs (a) NAVMED P-5055, Radiation Health Protection Manual (b) Title 10, Code of Federal Regulations, Parts 30, 30, 31, and 33 Zncl:
(1) Ionizing Radiation Control Handbook Purpose. To define NUC policies governing radiological safety, to establish safety criteria governing the use of ionizing radiation sources, and'to provide a guide to users of radioactive r.aterials.
2.
Cancellation. NUCINST 5100.3.
3.
Scope. These regulations apply to ionizing radiation sources that are used within NUC for research and development, diagnostic, and industrial purposes.
Isction. NUC personnel using or supervising the use of radiation sources will conduct their operations in accordance with references (a)~
and (b) and the instructions in this handbook.
5.
Directive Responsibilitv. The Head, Central Staff, Code 11, is responsible for keeping this instruction current.
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CHARLES B. LISHOP j
Distributions C
Suppler.ent (3)
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....Enclo.sure(1)..
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