ML20054D537
| ML20054D537 | |
| Person / Time | |
|---|---|
| Site: | 07001216 |
| Issue date: | 06/20/1980 |
| From: | Rich Smith NAVY, DEPT. OF |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20049A233 | List:
|
| References | |
| FOIA-81-428 0763, 16733, 763, NUDOCS 8204230107 | |
| Download: ML20054D537 (12) | |
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'44 2 0 JUN 1980 U.S. Nuclear Regulatory Cornission Division of Fuel Cycle and Ibterial Safety Materials Licensing Branch Washington, D.C. 20555 Gentlemen:
The attached application by the Naval,0cean Systems Center, San Diego, California to renew U.S. Nuclear Regulatory Commission Materials License No. SNM-ll54 is endorsed.
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Ihpeditious review of this applicatiori is requested to permit testing of new fuel forms.
Sines ly, if MY 11. S51Til Technical Director Radiological Affairs Support Office
Attachment:
(1) NOSC ltr WCS:rc 10330 Ser 037/25 of 9 Jun 80 Copy to:
(w/o attach)
NAVFACENGCOM (111N)
NOSC San Diego
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03AG333 16733 8204230107 811110 PDR FOIA WESTLAKE81-428 PDR
APPLICATI OR REfiEWAL OF SPECIAL fiUCLEA dTERIAL LICEtlSE Stim-ll54
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In troduc tion :
flaval Ocean Systems Center (f105C) is headquartered at Point Loma, San Diego, Cali fornia.
The mission of fiOSC is to be the principal flavy research, development, test and evaluation center for command control, communi-cations, ocean survesillance, surface and air launched undersea weapon systems, and supporting tecdologies.
fl0SC has facilitics in San Diego, California and San Clemente Island, Cali fornia.
2.
Quantities and uses of Special !!uclear Material:
The special nuclear r;aterial will be possessed and used as follows.
a.
Tieutron Source:
Pu-239-Be sealed neutron source Model flu fiEC-A - 16 A-grams.
This source was manufactured by the fluclear Materials and Equipment
~Corporation, Apollo, Pennsylvania in accordance with the specifications indicated in Attachment #1.
The source will be stored, when not in use, in its original shipping container or in a 10 foot underground, boronated water shielded,.
storage vault which is located next to Building 46 (See Attachment #2).
The dose rate at the surface of the original shipping container is approximately 10m rem /hr.
The source will be used for research and development activities and instrument calibration.
b.
Counting Standards:
Pu-239, 20 micrograms as alpha sources for counting
'C standards, research and development activities and instrument calibration.
y c.
Radioisotopic Heat Sources:
(1 )
Under the spo?sorship of the Flight Safety and Fuels Branch, Advanced fiuclear Programs Division, Department of Energy, f40SC is planning a test program to evaluate the ef fects of the ocean environment upon the physical and chemical characteristics of pure plutonium oxide, (PPO) enriched in 238Pu.
i A general objective of the program is to evaluate the consequence of the entry
'j into the ocean environment of a radioisotopic thermoelectric generator fueled i with such a heat source.
g (2) Two fuel capsules are to be tested at any one time.
Each con t
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of about 153 crams of plutonium oxide with an isotopic composition of 80%
Pu and 20; 239, 240, 241 u.
The capsules were fabricated at the los Alamos Scientific P
laboratory (LASL).
The process consisted of hot-pressing plutonium oxide granules to 85.1% of theoretical density into the shape of a cylinder 2.738 cm (diam) by 2.768 cm (height).
Each pellet is clad with iridium, equipped with_ajnt, r
and the dimensions of this product are 2.99 cm (diam) liy'3.0T cm (height).
To reduce the neutron emission rate, the oxide is depleted in I70 I8 and 0 isotopes to several hundred parts per million (ppm) and about 100 ppm, respectively.
The neutron emission rate for each capsule is 4-6 x 105 neutrons /
sec.
The beta-gamma-dose rate is 0.5 mr/h/g of plutonium oxide at 10-cm for unclad plutonium oxide.
Activation of the iridium is expected to be about 1-3 microcuries per year.
Some capsules hava undergone a safety test at LASL in which each was fired at a granite slab while at elevated temperature under such conditions as to simulate the heating and impact experienced upon r,e-entry to the ground from space.
Each source passed a leak test which allows for the detection of E n d.L t o h w
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v only several alpha-ray disintegrations per minute on surface wipes taken 24-hours after the impact test.
Tests at LASL indicate that the average release rate from a bare Pu oxide pellet in cold seawater is 10 nCi/sec, m2 surface area of the bare pellet.
Were the capsules under consideration unciad a concentration of 3 p Ci/ml. day would be expected if the material was dispersed in only a m3 of seawater. < Clearly, a substantially lesser concentration would be anticipated for the iridium-protected pellet.
Exposure tests of. several 238Pu sources occurred near fiorth Light Harbor Pier, San Clemente Island from 1967-1978.
flaterials collected from this environment in 1979 were analyzed for their Pu content by investigators at the Lawrence Livennore Laboratory (See Attachment #3).
They accounted for 238Pu greater th'an the expected 0.10 mci from fallout 3 0.18 + 0.05 mci deposition in the surface sediment over a 3.8 km2 region surrounding the pier.
This amount approximates an estimate of the quantity mobilized from bare microspheres tested in the 1960's.
Interestingly, the total fallout plutonium (238 + 239 + 240) in surface sediments from Santa Barbara and Soledad basins is greater than the total plutonium in the surface sediments sampled at San Clemente Island.
2 Further, except for a 0.025 km area around the pier, the total plutonium in surface s' diinent is with~iiIthe range of total plutonium frc,m
~
e fallout in the Atlantic and Pacific Ocean surface sediments obtained from water column depths less than 100 m.
(3) The program will be carried out at the fiarine Environment Test Station, located on the protected (mainland) side of San Clemente Island, Cali fo rni a.
This island is located approximately 60 miles from the nearest mainland.
Attachment #4 shows the location of San Cicmente Island with respect to the Los Angeles area and the other Channel Islands.
Also shown on Attachment
- 4 is the north end of the Island where all the facilities to be used by this project are located.
(4) fl05C is a tenant at the Island, which is under the jurisdiction of the flaval Air Station, fiorth Island, San Diego, California.
Entry to the Island is restricted to personnel authorized by the flavy.
(5) The implacement area will be the shallow water just off shore of the fiarine Environment Test Site, at florth Light Harbor.
T_he waters contiguous to the florth Light Harbor are not normally used for projects other than those conducted at the fiarine Environment Test Station.
(6) The test program involves immersion of two PP0 samples placed in ocean bottom material (sand, mud, organic material) in an exposed chamber which will be implanted on the ocean bottom at about a 50 foot depth of water.
A sketch of the exposure chamber is shown in Attachment #5.
(7) At approximately 3 month intervals, the exposure chamber will be recovered, the sample visually inspected, marine biota samples recovered for plutonium analysis, and the sample reimplanted if it appears normal.
If 2
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V the sample appears abnormal, it will be returned to LASL.
The chambers will be vented to the ocean to permit convection interchange of sea water and biotic material between the chamber and the ocean.
Experience with the project to date has indicated minimal problems with currents, tides and oorms affecting the exposure chamber.
(8)
Upon receipt of the test samples a complete monitoring survey will be made, including neutron and gamma dose rates, surface and removable alpha activity and air sampling as indicated by the nature of the work.
The samples will be opened in a glove box and immediately immersed, while in the glove box, in water.
(9) Appropriate protective clothing, including gloves, coveralls and respirators as needed, will be worn during sample handling.
Personnel will be monitored for alpha contamination during and after sample handling. Thermo-luminescent dosimeters or film badges will be worn by personnel handling samples.
(10) Each time the exposure chamber is removed from the water, contamination control measures will be employed.
The exposure chamber will be placed in a plastic wading pool, monitored for direct and removable contam-ination, samples of sand, water and biological material will be collected for plutonium analysis, and an area survey made upon completion. The Radiological Safety Officer or his designate will be present for monitoring services during recovery of exposure chamber, examination and/or recovery of samples and replacement of chamber.
(11) Upon completion of the test program the samples will be packaged in accordance with Department of Transportation requirements and returned to LASL.
The exposure chamber and their contents will be decontaminated or disposed of through a licensed radioactive waste disposal contractor.
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d.
Co-crystallization Research:
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(1) 10 microcurie each Pu-237, U-237 used in a research grant to c
study the recovery of these tracers from seawater by certain precipitation and co-crystallization reactions.
v.
(2)
Pu-237 and U-237 will be prepared in nitrate or chloride solutions I
by Oak Ridge f!ational Laboratory.
The radioisotopes will be used in a laboratory
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which has as a minimum:
a fume hood, appropriate protective clothing, and remote handling devices.
All contaminated solid or liquid waste will be collected and disposed of in accordance with f4AVSUP Instruction 5101.9B, of 8 December 1978 and current flRC/00T requirements.
3.
liealth and Sa fety tieasures:
a.
General administrative and radiological safety regulations in effect at tiOSC are contained in fl0SC Instruction 5100.2, " Ionizing Radiation Control Handbook", submitted as Attachment #6.
b.
Contamination control measures will include use of dry boxes and/or ventilated hoods with filtered air exhaust if appropriate.
Personnel will utilize appropriate protective clothing and respiratory protection. ~Ai r 3
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(V CN' uU sampling and personnel monitoring will be conducted as indicated by the
[ d nature of the operation.
Liquid and solid waste containers will be provided for collection of Stifi contaminated waste.
Disposal will be by packaging and shipment to a licensed disposal contractor or return to the manufacturer, Radiourinmlysis will be conducted on all personnel incurring exposure c.
to an aerosol of any radioactive material 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.
d.
All shipments of radioactive material will be delivered, unopened, to the Radiation Safety Officer, who will open the package, conduct radiological surveys and perform any decontamination required.
c.
Sliti materials, when not in use, will be stored in locations with adequate security control to prevent theft or loss.
4.
Personnel fionitoring Devices and Procedures: The standard flavy thermo-luminescent dosimeter (TLD) or film badge will be used for personnel monitoring.
All dosimeter processing will be by the flaval fiedical Center, Bethesda, fia ryl and.
And all TLD's will be exchanged at least every 7 weeks, the film badges will be exchanged on a monthly basis.
5.
Equi pment:
See Attachments 7 and 8 for a list of monitoring equipment and laboratory instrument calibration calculations.
6.
Authorized Users and Radiological Safety Officer Qualifications: Experience of the Radiation Safety Officer, Assistant Radiation Safety Officer and authorized users is provided in Attachment 9.
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,l 7.
Instrument Calibration Portable radiation detection instruments will be calibrated semi-annually at the ?laval Electronics Systems Engineering Center, San Diego, or by the manufacturer.
Laboratory counting systems will receive background and source response checks each day they are used.
Commercially available calibrated beta and alpha counting standards will be used for the source response checks and will be traceable to the flational Bureau of Standards.
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STANDARD AND CUSMM PU239-BE NEUTRCN SCURCES
, Specification and Price List
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Plu'toniun beryllium neutron sources are used
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Where a relatively constant neutron strength i
with a low associated gam.a radiation doce
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NUMEC
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"f standard Pu239-Bo sources are an alloy of g~~~*
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gh
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$. t cent Pu239 Thenominalneufronefficiency
+
h, q.... a:
...of. these sources is 1.8 x 10 neutrons per-g!! je":jP.*g.G..'...5.
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second The dat.a Presen..ted in.
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the di. P.er c.uri.e.
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agram at the right and Table 1 below r 44, ":;h./.
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hangQ describe the standard NUMEC Pu239-Bo sources.
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w Table 1 presents critical specification and purchase price data for NUMEC sources. De-
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liverf is normally made i=.ediately from stock; for sources in short supoly two i_. 7.~...'. E..74oTfous, pedks;. delivery is usualiy.p, rovided..sicaeca mm g.in.xmimewa n.u
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Table 1 e
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- Standard NUMEC Pu 239.Sc Neutron Sources (Specifications and Purch05e Prices)
Catat:t Plat..;s1s Cent.r.1.ms C.ar ste, Liegth A ;;,a...r.;t e 7:.t e.7)
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C e ntg e st.e n C o,le s C.
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"..,ces i.its 0.250 c.p nd 10/32 i.pped h.1.:
NOMEC A 1
16 1.020 1.445 3.8 s 10' 5 (C5 tiUMCC.B 2
32 1 020 2 190 3 6. IC*
745 N U M f C.C 2
32 1.330 1.510 3 6 s 30' 75 NUMCC u 3
48 1.020 2 935 S 4 a 10' H5 td u M E C.D 3
48 3.310 1 915 5 4 s 10' i.S
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48 1.550 i 505 S.4 a IC*
si5 hy,A LC N 4
64--
1 020 -
3 f.50 7.2 a 10' 565 huMECJ 4
64 1.330 2.320 7.2 a 10*
MS HUMEC G 4
.G4 1350 1.775 7.2 e 80*
WS NUMEC P 5
80 1 020 4475 90 10*
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N Uu t C.H 40 1.310 2.770 9 0 s 10*
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4 N U M C C.I CD 1.550 2 04) 9 0 m Ic*
10!5 l
NUutC J F
i12 1.* iG 2.585 1.2 a 10'
- 252 l
l N u u t C.K 10 160 1MD 33*0 3 8. IC*
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36 1.070 1 295 3 8 a 10 j i 5,,,,,,,,_
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32 1 020 2 040 3.6 a 10*
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48 1.070 2.735 54 10*
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64 _
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565 _
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s Attachment #2 RADIA TION PHYS /CS Div/SION AREA PLAN NAVAL OCEAN SYSTEMS CENTER SAN DIEGO
MONITORING EQUIPMENT O
Type of Manufacturers Model Number Radiation Instruments.
Name Number Available Detected Range li 1
Portable GM Eberline or E500 B 4
Beta-gamma 0-20 equivalent mr/hr 14 t.
Portable Ion Victoreen or 440 1
- Alpha Beta 0-300
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Chamber Rate equivalent Garrna mr/hr Fi Meter
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. I Portable Alpha Eberline or PAC-ISA 1
Alpha 0-2M Cpm Scintillation equivalent Ion Chamber Victoreen 570 1
Gamma
.0'c5,.25 2.5, 25 R Portable U.S. Govt.
AN/PDR-2 Alpha 1MCpm
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Scintillation 56.
Portable U.S. Govt.
PDR-70 2
Neutron 0-2 rem /hr Proportional or equivalent Neutron, REM
.I Scaler Technical FS-8 1
O Associates Air Sampler Staplex TFIA 1
Lab Counter Technical STAM-2 1
Alpha Scintillation Associates 4
End Window LND, N.Y.
1 Beta 1
GM Counting System 1
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Attachment #7
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Laboratory Instrument Calibration The laboratory counting systems will receive background and counting efficiency determinations each day they are used.
Commercially available beta, gamma and alpha counting standards will be used for counting efficiency determinations.
Cou'nting standards will have certification traceable to the flational Bureau of Standards.
Formulas used for determining counter efficiency and for determining sample activities are:
Symbols:
Counts per minute - c/m '
Disintegration per minute - d/m Microcuries - pCi Counter background (c/m) = Total counts (empty planchet)
Time counted (minutes)
Standard count (c/m) - Background (c/m)
Counter efficiency =
Standard Activity (d/m)
Sample count (c/m) - Background (c/m)
Sample activity (pCi) =
Counter efficiency x d/m per pCi Limit of Detection (c/m) to 95 percent confidence level.
2K [ h ( l + -h ) ]
LD =
+
Tt where K = 1.65 for a 95 percent confidence level Tt = Total count Tb = Total background count Rb = Total background count rate Sample calculation:
210 counts Counter background =
21 c/m
=
10 minutes 16,387 c/m std. - 21 c/m bkg.
0.339
=
Counter efficiency =
48,320 d/m Cl-36 std.
Sample count = 225 counts /10 min. = 22.5 c/m Attachment #8
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NAVAL OCEAN SYSTEMS CENTER San Diego, California 92152 l
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NOSCINST 5100.2 CII-l
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48/ALS:ghe 15 MAY 1973 NOSC INSTRUCTION 5100.2 CIIANGE TRANSMITTAL 1 I
To:
Branch Heads, Project Offices, and above Subj: Ionizing Radiation Control Manual 1.
Purpose. To transmit change 1 to the subject manual.
2.
Action. Manual holders make the following changes.
a.
Chapter I, Organization and Responsibilities.
(1) In subparagraph 2.la(2) on page I-1, insert Code 48 in lieu of Code 0403.
(
(2) Insert new subparagraph 2.le on page I-2, as follows:
j "e.
Chairman. The Chairman of the IRCC is responsible to the Commander for:
(1) Arranging for and presiding at the IRCC meetings to be held semiannually or more frequently when directed by the Chairman.
Ca (2) assuring that minutes are taken and compiled for the Commander and for distribution as directed by the Committee.
(3) Insuring that the actions of the Committee are implemented.
(4) Utilizing the Committee effectively in matters pertaining to Ionizing Radiation Control."
(3) In paragraph 2.2 on page I-2, insert Code 48 in lieu of Code 0403.
i l
l b.
Chapter V, Procedures for Use of Radioactive Materials. In paragraph 6.1 on page V-2, fifth line, change Safety Staff, Code 0403, to read Safety Group, Code 48.
l 1
R. R. GAVAZZ t
Distribution:
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