ML20155H830

Forwards Rev 4 to Security Plan for Alchemie Facility 1-CPDF.Rev Withheld (Ref 10CFR2.790(d))

ML20155H830
Person / Time
Site:	05000603
Issue date:	09/16/1988
From:	Smelser J ALL CHEMICAL ISOTOPE ENRICHMENT, INC.
To:	Thompson H NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
24757, NUDOCS 8810240240
Download: ML20155H830 (1)

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Septerrber 14, 1988 GEN-1270  ;

t U.S. Nuclear latory Ccrimission Medical, c, and Ccunercial Use [

Safety Branch (Mail Stop OMN-6H3)

ATIN: Mr. Michael Lamastra Washington, D.C. 20555

Subject:

Control No. 019643; Subnittal of an Expanded Appendix 5.0 to General Atcmics' Application for License to Distribute Irradiated 'Ibpaz

Reference:

A ^1th E. Asnussen letter GEN-1266 to U.S. NRC Medical, Acadanic, and Ccmten::ial Use Safety Branch, ATIN: Mr.

Michael La:mstra, dated Septarber 9,1988

Dear Mr. Lamastra:

As you know, General Atcmics (GA) recently subnitted the referenced application for a license authorizing the distribution of irradiated topaz to prsons exertpt frcm regulation. Mtile we were finalizing that subs.ttai, we were also nearing the ccepletion of a test nm of our system for assaying large sanples of ger. stones. his system was described in Appendix 5.0 to our application. Inportant results frcm this test nm have just teccne available.

In order to zmke the infonstion contained in our acplication as ccnplete as possible, we have expanded AppendLx 5.0 to include a sunreary and discussion of these results. ne Appendix 5.0 subnitted with our referenced application should be replaced by the e criplete expanded version which is erciosed.

W apologi:e for the inconvenience caused by this late change to Appendix 5.0.

If you should have any questions or neert any additional infonmtion, please do not hesitate ;,., contact me at (619) 455-2823 or Drs.

Mtitterocre or Pa:Vi at (619) 455-3277.

Verf truly yours, mus%-

Keith E. Asnussen, R1 nager Licensing, Safety and g Nuclear Ccnp11ance

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APPENDIX 5.0  !

i Assay of Iarge Satples of Ganstones Using Hi@ Resolution hirv=virtor Detector ne Ge(Li) (or equivalent HpGe) high resolution detector used in the determination of radionuclide concentrations in irradiated gemtonen is mounted on a vertical cryostat. ne available detectors have gama sensi-tivities ranging between 5 and 20 percent. n e diameters of the outer con-a tainer will vary between 2.75 inches and 3.0 inches.

n e design of a holder for the assay of a large number of garstones in Step K1 (Figure 1 of Application) (eg., ~501-gram stones) is based on ex-perimental measurements made with a specially assa: bled source containing approx 1rately 0.08 pci cs-13.7 (662 key) and 0.13 pci co-60 (1173,1333 kev). ne source holder for these measuranents was a urall polyethylene cap with irside diaceter of about 8 m and about one-half millfreter th!.ekness betwen the source and the geratone holder. A curvey was rode in four quadrants and at various heights to arrive at the curvature shown in Figure 1.

The relative sensitivity as a function of positu n is 44% of the censi-tivity for a single stone placed in the usual locatlon used for measure-cents on a single stone. ne value (44%) is an aver tge at each location of the sensitivities for the gantna rays frcra cesium and cobalt.

A test run for 44 gerrstor.es weighing about 50 grams was made using the large sanple holder. Tables 1 and 2 present the pertinent ce(Li) data. In addition to the routine isotope callouts (Table 1) ths esectrosecpist pro-vided results of his inspection and adiitional calculations that also iden-tified weak co-6u and 2n-65 ccrponents (Table 2). no absence of addf-tional gwma lines for Eu-154 yd se-75 allowed the spectroscopist to line out these possibilities. A sunnary of the results was derived by the spectroscopist fran Tables 1 and 2 and is given telcw Nuclide nCi/g 10 CFR30.70 Ratios Limits (nCi/g)

Ta-182 50 x 10-3 0.40 0.125 Sc-46 2.7 x 10-3 0.40 0.0068 Mn-54 3.5 x 10-3 1.0 0.0035 Co-60 0.7 x 10-3 0.50 0.0014 Zn-65 1.7 x 10-3 1.0 0.0017 C ',-134 2.3 x 10-3 0.09 0.026 Na-22 2.7 x 10-3 (1.0)* 0.0027 l

• Seu discussion below.

E = 64 x 10 3 gCi C = 0.167 (( 1.00 9

These data dmonstrate that for this batch, the "sum of ratics" is less than unity, with a total specific activity of 0.064 nCi/g. It is also apparent that stones with this sane distribution of radioactive caponents could have spcific activity as large as 0.383 nC1/g and still satisfy the release cri-teria - i.e.,

-h?h-x0.064=0.383nci/q This noximum specific activity 1,. c lled % as used in Equations 5 and 6 on pge 27 of the 14 plication.

no assay nethodology using a large holder with approxirately 50-gram sm ples of geestones for the Ge(Li) count (Step K1) hat inproved the sensi-tivity of detection level for the minor radioactive cmponents in the

stones, sinultaneously, this has increased the possibility of identifying isotopes (at these very low levels of concentrations) not previously found  :

in assays of one-gram sanples. Furthernere, this increases the likelihood of finding an revmional isotope not included in schedule A of 10Cm30.70. ,

The "catchall level of 10-6 pC1/ gram is considered inappropriate for this f application because it is arbitrarily small. Consider the case of Na-22 [

which is an isotope not listed in schedule A and found at a level of 2.7 I picoeurle/ gram in the reported data. In the following we illustrate a suitable approach for handling this and similar cases that may arise in the future.

i In the particular case of Na-22, it is cmitted frca Schedule A even I i though it can be produced by nuclear reactors. This is well known to  !

workers experienced with sodium cooled reactors. Its threshold for (n, 2n) production is about 12.5 Mev with the cross section as a function of neu-tron energy given in B E-325 (1). We fraction of all fast neutrons frca a l

reactor fueled with U-235 above about 13 Hev is 1.103 x 10-4 (2). Si.ce I the fast flux at the location of the gemstone irradiation is about 1012 ny, i the portion of this fut flux suitable for this (n, 2n) reaction is about I i

, i t

j p (E > 13 Hev) = 1.1 x 108 n *, l t

l An activation of 2.7 x 10-3 nci/ grams corresponds to an activation of (

j ' 5.0 dps for the 50 gram sanple of stones: ,

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! 0.693t/  :

) Act=(16)p(1-e T1/2],,,,,,,,,{g) r j

where Act = activation of Na-23 to produce Na-22,  !

, (tu) is the nunber of atcms of Na-23 in the 50 gram l sanple of stones, and cr is the effective (n, 2n) [

cross section, i

4- - ----------,-,----.---..-r--- ,-,,3---- ------,c---,---- -- --- - . +-~-

a = 1.1 x 108 ny, and t = 4 weeks or 0.077 yr.

T 1/2 = 2.6 yr.

Frcm equation (1) we see that (M7) = 2.24 x 10-6 m-2 ,

If the average cross section above 12.5 MeV were as small as 1 millibarn, then N = 2.24 x 1021 atoms of Na-23 (~ 90 milligrarra). A more reasonable average cross section might be as large as 10 millibarns, for which the mass of Na-23 would be only 9 milligrams. 'Ib find such a small adnixture of Na-23 (9-90 milligrams) in a 50 gram saple of stones cannot be consid-ered unreasonable, although it'is unusual frcm all past experience.

'Ite question new arises on how to arrive at a reasonable 100R30.70 limit for the Na-22 isotcpe. As demonstrated above, Na-22 can be prMM by reactors frcn Na-23 and the' afore, should be listed in Schedule A. 'Ib arrive at a suitable limit fr this application, we have ccr: pared its gama and beta racitation with other isotopes present and which may have similar half lives and/or ernissions. These are ccrrpared in the following listing:

Isotope T1/2 g Energies frax 30.70 Limits (kev) (M) nCi/g Ta-182 0.32 yr 59, 67, 1121 0.522 0.40 1189, 1221 Sb-125 2.8 yr 176, 428, 601, 0.612 1.0 636 Zn-65 243.8d 1116 7 0.325 1.0 Sc-46 83.3d 889, 1120 0.357 0.4 Na-22 2.6 yr 511, 1275 7 0.545 --

For the case of Na-22 we first note that it cannot be ingested or in-haled because it resides within the empletely insoluble topaz crystal.

Next, we note frcan the above listing that on the basis of half li.fe, Na-22

most nearly matches Sb-125 with a release limit of 1.0. we also note that the 1275 kev line of Na-22 raatches the 1116 kev line of Zn-65 which also haa a release limit of 1.0. Further, the range for positrors with Emax of 545 kev that are snitted by Na-22 is very much the same as the betas frcan

the far nore prevalent isotope, Ta-182, as well as sb-125. In other words, even the smallest stones are infinitely thick for the Na-22 positrons.

Because of the similarities in the half lives and anitted radiations between Na-22 and Sb-125, we believe a reasonable release limit for this minor caponent can be taken as that for Sb-125, i.e.,1.0 nCi/g.

1 i

References:

I l 1. Neutron Cross Sections, BNL-325, Vol.1, Suppl. 2, Second Edition 4

(May, 1964).

2. H. Etherington, Ed., Nuclear Engineering HancDxck, First Edition (1958), p. 7-91.

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mis surface of revolution hum 3tes about 50 1 grain stones. For this bolder the detector has about 44% of the sensitivity for a single stone -

placed at the usual (7.5 mn) position. Measured ,

sensitivies are shown.

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TABLE 1

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PPOGRAM VERS!QN: GRIT-109 (4-22-C2) C4TECTOR: QE(LI)C2 ,

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!EHSITIV!TV: 15 TOTAL CPM: 1944.

CALCULATICN MCCE; Al LIE 4ARY IE.aacy: 4 CMNMEL Af+CE; t+ - $1?2 # Or pgAgg pyywn;  ;

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'O m U.S. NUCL E A:1 REGULAfoRY COMMissl0N

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16 846 MATERIALS LICENSE j' I

Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 438).and Title 10, I Code of Federal Regulations. Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in re d fb d 'g j, source, heretofore made and special nuclear bydesignated material the licensee, below; to use such alicense material for the ispurpose hereby (s) and atissued the place (s) authonzing designated below;to I

delner or transfer such material to persons authorized to recene it in accordance with the regulations of the apphcable Part(st This I

license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 19$4, as amended, and is I

i subject to all apphcable rules, regulations and orders of the Nuclear Regulatory Comm conditions specified below.

Ucensee A P

3. Ueense number 04 14395-02E

1. General Atomics '

P. O. Box 85608 .

San Diego, California 92138

4. Esp!rstion date October 31, 1993 ' t, I 5. Docket or

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I Reference No.

030-29179

7. Chemical and/or physical 8. Muimum amount that licensee 't j 6. Byproduct, source, and/or ~ 'may possess at any one time l I speelal nuclear material form

, under this license j

.)

1 I A. Any byproduct rnaterial A. Irradiated processed A. Not applicable j l with atomic numbers tcpaz j

- j between 1-83 j i I

t 9. Authorized use .I I

A. In accordance with Section 32.11, 10 CFR Part 32, distribution of processed topaz containin byproduct material to persons exempt from licensing pursuant to j'i l Section 3 .14, 10 CFR Part 30 or equivalent regulations,of any Agreement State. j I

1 s.

l

} CONDITIONS 1 -

f, I

I I 10. Licensed material shall be distributed only from the licensee's facilities M l1 I located at 10955 John Jay Hopkins Drive, San Diego, California. 'P I I

11. Licensed material shall be distributed by, or under the supervision of f; Dr. Junaid Razvi or Dr. William Whittemore. l q 1 I'

12. This license does not authorize possession or use of licensed material. 1 l .

l i

! 13. A. The licensee shall file periodic reports as specified in Section 32.12, 10 CFR Part 32.

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f B. The licensee shall file a report by November 1, 1989 and a new report at l

Intervals not to exceed 14 months, listing the narnes and license numbers of all specific licensees to which the licensee has transferred irradiated

gems pursuant to Section 30.41 of 10 CFR Part 30.

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! MATERIALS LICENSE he meterehb4b02L--- f I SUPPLEMENTARY $HE ET 'i 030-291Z9 i

I I

I I

CONDITIOFS l

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I I

I 14. Notwithstanding the requirements of Section 32.11(c) of 10 CFR Part 32, the licensee may use the approach described in Appendix 5.0 "Assay of Large l Samples of Gemstones, Using High Resolution Semiconductor Detector" g

g contained in its September 14, 1988 letter, to assign maximum concentration I- values for isotopes not included in Schedule A of 10 CFR 30.70, except for I Na-22 which shall be 0.4 nanocurie per gram.

l

15. Notwithstanding the requirements of Section 32.11(c) of 10 CFR Part 32, the l licensee may distribute processed topaz for the purpose of being worn by human g

beings.

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I I 16. Except as specifically provided otherwise in this license,l the licensee shall I; conduct its program in accordance with the statements, representations, and procedures contained in the docarents including any enclosures, listed below.

li i The Nuclear Regulatory Comission's regufations shall govern unless the gl statements, representations, and procedures in the licensee's application and l' correspondence are more restrictive than the regulations. ,

il I; A. Application dated September 9, 1988.

B. Letter dated September 14, 1988.- .

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l FOR THE U.S. NUCLEAR REGULATORY COMMISSION Il 4l .

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Medical, Academic, and Corrrnercial Use Safety Branch Division of Industriti and Medical Nuclear Safety, NHSS

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Washington, D. C. 20555 I!

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