ML20054D541
| ML20054D541 | |
| Person / Time | |
|---|---|
| Site: | 07001216 |
| Issue date: | 04/03/1980 |
| From: | Drayton H NAVY, DEPT. OF |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20049A233 | List:
|
| References | |
| FOIA-81-428 037-8, 37-8, NUDOCS 8204230112 | |
| Download: ML20054D541 (10) | |
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-fq4 DEPARTMENT OF THE NAVY L.
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APR 1980 From: Commander, Naval Ocean Systems Center To:
Director, Nuclear Regulatory Commission, Division of Fuel Cycle and Material Safety Licensing Management Branch, Washington, D.C.
Via:
Officer in Charge, Naval Nuclear Power Unit, Port Hueneme, CA Subj : Request for.' renewal of Special Material License No. SNM-ll54 I
Encl:
(1) Application for renewal of Special Nuclear Material License SNM-ll54 1.
An application for renewal of Special Nuclear Material License, SNM-1154 is submitted as enclosure (1).
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APPLICATO r0a aEriEwAt Or SPECIAt riUCtevMATEa> At
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Introduction :
flaval Ocean Systems Center (fl0SC) is headquartered at Point Loma, San Diego, Cali fornia.
The mission of fl0SC is to be the principal flavy research, development, test and evaluation center for command control, communi-cations, ocean surve>illance, surface and air launched undersea weapon systems, and supporting tecifbologies.
fl0SC has facilities in San Diego, California and San Clemente Island, California.
2.
Quantities and uses of Special fluclear Material:
The special nuclear material will be pcssessed and used as follows.
a.
fleutron Source:
Pu-23'9-Be sealed neutron source Model fiU 11EC-A - 16 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 10 mrem /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 star.dards, research and development activities and instrument calibration, c.
Radioisotopic Heat Sources:
(1 ) Under the sponsorship of the Flight Safety and Fuels Branch, Advanced tiuclear Programs Division, Department of Energy, fiOSC is planning a test program to evaluate the effects of the ocean environment upon the phgsical and chemical characteristics of pure plutonium oxide, (PPO) enriched in 28Pu.
A general objective of the program is to evaluate the consequence of the entry into the ocean environment of a radioisotopic thermoelectric generator fueled with such a heat source.
s-e 2F Two fuel capsules are to be tested at any one time.
Each con ts of plutonium oxide with an isotopic composition of 80% gPu of about 153 and 20% 2 Q 4, 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 a vent, and the dimensions of this product are 2.99 cm (dian) by 3.01 cm (height).
To reduce the neutron emission rate, the oxide is depleted in 170 18 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 unciad plutonium oxide.
Activation of the iridium is expected to be about 1-3 microcuries per year.
Some capsules have 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
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only several alpha-ray disintegrations per minute on surface wipes taken 24-hours after the impact test.
Tests at LASL indicate that the average rqlease rate from a z
bare Pu oxide pellet in cold seawater is 10 nCi/sec. m surface area of the bare pellet.
Were the capsules under consideration unclad 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 North Light Harbor Pier, San Clemente Island from 1967-1978. Materials collected from this environment in 1979 were analyzed for their Pu content by investigators at the Lawrence Livermore Laboratory (See Attachment #3). They accounted for 0.18 + 0.05 mci 238Pu greater than the expected 0.10 aCi from fallout 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 sediment is within the range of total plutonium from 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 Marine 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 Clemente 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 a,ll the facilities to be used by this project are located.
(4) N0SC is a tenant at the Island, which is under the jurisdiction of the Naval Air Station, North Island, San Diego, California.
Entry to the Island is restricted to personnel authorized by the Navy.
(5) The implacement area will be the shallow water just off shore of the Marine Environment Test Site, at North Light Harbor. The waters contiguous to the North Light Harbor are not normally used for projects other than those l
conducted at the Marine Environment Test Station.
(6) The test program involves immersion of two PPO 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.
l (7) At approximately 3 month intervals,.the exposure chamber will 6 l
be recovered, the sample visually inspected, marine biota samples recovered j
for plutonium analysis, and the sample reimplanted if it appears normal.
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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 storms affecting the exposure chamber.
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(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 sampics 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.
d.
Co, crystallization Research:
(1) 10 microcurie each Pu-237, U-237 used in a research grant to F
study the rccovery of these tracers from seawater by certain precipitation and co-crystallization reactions.
(2)
Pu-237 and U-237 will be prepared in nitrate or chloride solutions by Oak Ridge National Laboratory.
The radioisotopes will be used in a laboratory 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 NAVSUP Instruction 5101.9B, of 8 December 1978 and current NRC/ DOT requirements.
3.
Health and Safety Measures:
a.
General administrative and radiological safety regulations in effect at N0SC are contained in N0SC 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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o 22.5 c/m - 21.0 c/m bkg.
2.0 x 10-6 pCi Sample activity =
=
.338 x 2.22 x 10 Limit of detection =
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+ 2 x 1.65 [21.0 c/m (), 210 ) 3
= 1.7 c/m 225 counts 210 225 e
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Radiation Safety Officer Training and Experience c.
i RADIATION SAFETY OFFICER: CHARLES F. BOURDON l
Safety Manager EDUCATION AND TRAINING:
BS in Safety Engineering, Texas State Technical Institute,1971.
Enrolled in MS degree in Safety & Health Science, California State University, Los Angles, California.
Radiological Monitoring Traini,g Course, Office of Civil Defense, El Cajon, California, 1967.
Radiological Safety Course given in conjunction with Industrial Safety Course, Mesa College, San Diego, California,1963.
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Radiation Safe'ty Officer Course, Naval Nuclear Power Unit, Port Hueneme.
California, 1978.
EXPERIENCE:
Safety Manager, Naval Electronics Laboratory Center,1951 to 1977 and Naval Ocean Systems Center, San Diego, California,1977 to present (1980).
Twenty-nine years of industrial safety experience.
Registered State of California Professional Engineers (P.E.) in Safety Engineering, Certificate No.1594 dated 10 August 1977.
Certified Hazard Control Manager, Certificate No. 808 dated December 1977.
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Attachment # 9 1 of 14
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j;5h.k,I(3 DEPARTMENT OF THE NAVY I
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SAN DIEGO, CALIFORNIA 92152 eN REPLY REFER TO:
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9 JUN 1980 From: Commander, Naval Ocean Systems Center To:
Officer in Charge, Naval Nuclear Power Unit. Port Hueneme, 6
California Subj : Nuclear Regulatory Commission Materials License No, SNM-1154 Ref:
(a) NNPU ltr 43:WJM:lm 3253,8B Ser 0581 of 7 May 1980 Encl:
(1) NOSC ltr WCS:rc 10330 Ser 037/8 of 3 April 1980 1.
Reference (a) noted certain discrepancies in the Naval Ocean Systems Center's request for renewal of Special Material License No, SNM-1154 The discrepancies have been corrected and the renewal request is return-T-
ed as enclosure (1),
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JUti 1980 From: Commander, tiaval Ocean Systems Center To:
Officer in Charge, flaval ttuclear Power Unit, Port Hueneme, California Subj: fluclear Regulatory Commission Materials License flo. Sf4M-1154 Ref:
(a) NNPU ltr 43:WJM:lm 3253.8B Ser 0581 of 7 May 1980 Encl:
(1) N0SC ltr WCS:rc 10330 Ser 037/8 of 3 April 1980 1.
Reference (a) noted certain discrepancies in the flaval Ocean Systems Center's request for renewal of Special Material License tio. SNM-1154 The discrepancies have been corrected and the renewal request is return-ed as enclosure (1),
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LAWRENCE LIVE ORE LABORATORY g.
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March 17 1989 M:. FrarA Kawahara, code 5214
!!.i.al Octar. Systems Center San Diego, CA 92152
Dear Trara.:
Enclosed is the final version of our report. being sent off to Health Physics.
I hope it will be of some help for your discussions with NRC.
Sincerely, Yi f.4:-
Victc1 C. teahl.in, I t.. D.
Sectfer. Icaci ;r 1.y.tte Scieneas S.etion V '.;. c.. >
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Unirarsity of Chhto*nis P.O. Pos 808 Livermore, California 94',50 7e:cphone (415)4221100 u Tws 310 335 8339 UCLL LVMR
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fiuclear Regulatory Commission Materials License flo. SilM-1154 Ref:
(a) fiflPU ltr 43:WJM:lm 3253.88 Ser 0581 of 7 May 1980 Encl:
(1) fl0SC ltr WCS:rc 10330 Ser 037/8.of 3 April 1980 l
1 Reference (a) noted certain discrepancies in the flaval pcean Systems M'.
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Center's request for renewal of Special Material License flo, SilM-1154 The discrepancies have been corrected and the renewal request is return-ed as enclosure (1),
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