ML20148M549

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Requests Amend to License SNM-1067,authorizing Temporary Possession of U & thorium-bearing Waste Matls for Packaging & Transfer to Commercial Disposal Facility.Criteria, Supportive Info & License Amend Fee Encl
ML20148M549
Person / Time
Site: 07001100
Issue date: 11/10/1980
From: Lichtenberger
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, EMVC-EPS
To: Crow W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
17839, DDH-80-086, DDH-80-86, NUDOCS 8012180493
Download: ML20148M549 (26)
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POVIER La i SYSTEMS Noven ber 10, 1980 y

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U.S. Nuclear Regulatory Commission

-S Washington, DC 20555 W

d Attention: Mr. W. T. Crow, Section Leader Uranium Process Licensing Section

-3 Uranium Fuel Licensing Branch y

2 Division of Fuel Cycle and Material Safety Gentlemen:

It is requested that License St:M-1067 be amended to authorize tem-parary possession of certain material described in Attechment A for packaging and transfer to a commercial disposal facility.

The criteria to be used during packaging and transfer uf the material are contained in Attachment A.

Information in support of the stated criteria is presented in Attachment 3.

It is our intent to package the material as soon as possible and transfer it for disposal within six months after approval of the amend-ment. However, due to the uncertainty of weather and the inability of the disposal sites to accept all the material at one time, it is requested that the amandment be effective for a nine-month period.

Enclosed please find a check in thr! amount of 31,400 to cover the amendment fee in accordance with 10 CFR 170.31.

If you have any questions concerning this application, clease con-tact Mr. P. R. Rosenthal or my staf f on extension 3366.

Very t..iy yours, i

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,w'db, /},/g[.. t( c tb:,vd/'b V H. V. Lichtenberger Vice President - Nuclear Fuel Nuclear Power Systems HVL/PRR/amb 1

I Attachments cc:

W. P. Chernock gr-cog THIS DOCUMENT CONTAINS ad" POOR QUAUTY PAGES 801218063 O

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l Attachment A - SNM License Amendment Criteria 1.

This attachment establishes the criteria to be used to package and transfer certain uranioni and tharium bearing waste materials described below from Combustion Engineering's Windsor, Connecticut site to a comirercial disposal f acility.

The material, consisting of the residue from burninn scrap metal containing alloys of zirconium and thorium, was generated as part of a former U.S. Navy program.

The material has been present in place for at least 20 years.

2.

There are approximately 167 55-gallon drums containing this material and an additional estimated 1100 cubic feet of loose material.

The material is located within a clearing in a wooded area on the Company prcperty as shown in Attachment 8-1.

A staging area will be established within the clearing for packaging and repackaging of the material.

After packagina in new containers, the material will be transferred t.o an outdoor storage area (see Attachment B-1) where it will remain until subsequently released to a Carrier for transport to a commercial disposal facility.

Both the area where the material is now located and the latter storace area will be established as restrict 2d areas in accordance wt th 10 CFR 20.

Additionally, the stnrage area will be maintained as a 2

contamination free area:

less than 100 dpm/100 CM alpha and less than 2

200 dpm/100 CM beta activity.

3.

It has been determined (see Attachment B-2) that the material, v.hich is predominantly zircontum oxides, contains radioisotopes of bnth uranium and thorium.

The material has been estimated, based on sampling (see Attachment B-3) to contain approv.imately 2 kg total of uranium (including a conservatively high estimate of 860 grams of l

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U-235) in low concentration and 1pproximately 7.3 kg of thorium,

-also in low concentration.

It has been determined (see Attachment 8-4) that the uranium enrichment varies among samples from less than 1% U-235 to between 80 and 90% U-235.

4.

Handling and packaging of the material will be performed in accordance with written procedures approved by C-E's Manager of Health Physics.

5.

All personnel who physically handle the material in the course of packaging will wear protective clothing as specified by the health physics technician.

A breathing zone larcl air sampler will be used 100% of the time by each individual working in this area.

An action limit of 50% of that allowed by 10 CFR 20.103 will be established.

Upon reaching the action limit all work will be stopped until a review of packaging procedures can be made by the radiological engineer and the Manager of Health Physics to determine that 10 CFR 20 limits will not bc exceeded. All personnel, equipment, and material will be surveyed prior to leaving the restricted area.

A release limit of 100 2

2 dpm/100 CM alpha and 200 dpm/100 CM beta activity will be observed.

A health physics technician will be assigned to monitor packaging opera-tions at all times.

G.

It has been determined (see Attachment B-5) that the fissile content of the material is well below the criticality limit.

Therefore criticality controls are not needed during packaging of the material.

Based upon the same determination, material packaged in 55-gallon drums (Specification 17 H drums) can be stored in any array and maintained at a high degree of subcriticality.

It is planned that i

small samples of material will be transferred to the Development f :

e laboratory, Bu11dinci #5, for analysis.

This building is presently

' licensed for mass limit controls under license SNM-1067.

For the purpose j

l of mass limit control, each sample taken to the laboratory will be assumed to have the highest concentration of U-235 based upon previous analyses until it has been determined by pamma spectroscopy that no uranium is present or until it has been determined by che.:11 cal assay or mass spectroscopy that the U-235 content is less than that originally assumed.

None of the material will be transferred to Buildings 17 or 21 at any time.

7.

The sampling plan presented in Attachment B-6 will be used for determining the quantity and enrichment of uranium to be transferred to the disposal facility.

8.

The material will be packaged and released to a carrier for transport to a disposal facility in accordance with applicable provisions o' 10 CFR 71 and 49 CFR Parts 100 through 199. Any package determined to have a quantity and/or enrichment of uranium exceeding the limits af 10 CFR 71, 49 CFR Parts 100 through 199, or the disposal site criteria will be repackaged so as to comply with the applicable requirements.

9.

It has been determined by laboratory tests that the radioactive mater-ials are in the insoluble form (See Attachment 3-7) therefore migration from seepage or surface water runoff is insignificant.

To ensure that resuspension of the material does not occur during packaging, air sampling will be performed at the perimeter of the restricted area l

both up wind and down wind.

An action limit of 50% MPCa in accordance with 10 CfR 20 will be established.

Upon reaching the action limit, all work would he stopped until a review of par.kaging procedures and i

cu nqineer and the Manager of Health activities is made by the rad Physics to determine that 10 CFR 201:mits will not he exceeded.

Based upon results of radioactivity measured in stratifica

.n soil samples (see Attachment B-8) it is estimatcd that 4 to 6 inches of loose waste material will have to be removed.

Most of this material is in the form of resolidified scrap metal oxides which have " capped" the surf ace of the soil.

10. The following target criteria will be used for the release of the land comprising the restricted areas for unrestricted use:

A square grid system measuring 25' x 25' will be established a.

over the restricted area after clean-up operations.

The direct radiation dose rate will be measured at each grid area.

For a diffuse source area (an area greater than 25' x 25') the gamma dose rate in air one meter above the grcund should not exceed 10 pr/hr. above background.

For a di s-crete area (an a ea smaller than 25' x 25') the gamma doce rate in air one meter above the ground should not exceed 18 pr/hr. above background.

b.

Representative soil samples will be taken fro"1 each grid area and analyzed for the concentration of nuclides in dry soil. The soil will be acceptable for unrestricted use if the dose from the sum of the major radionuclides does not contribu.e to a total lung dose greater than 10 mrem / year, based on calculations using the conversion f actors presented in Attachment B-9.

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_ - -.. ~ [. DDil-80-00d . htta<lampt U-3 Exhibit l_ There eniats 167 55 gallon druma of wasto material. Of this total 96 drunr. have Lcen surveyed using a mult-channel analyzer with the following resulta: l Nuator of D.r_wr.s. Radioactive CC. "fents 3 i 25 Uranitet only 35 Thorium only 23 Uranium and Thorian 13 No detectable activity t Total 96 Seventy cne of the rums have not been surveyed at the present timo because they are in the inner revs of drums and are inaccessible until the cuter drunc have been renoved. Assuming that the material in the unsurveyed drums is of l the same nature and type as the surveyed drurs, it is estimated that for the f total cf 167 drums the following w uld result: t Nunicr of Druns Podioactive Contents 43 Uranium only 61 Thorium only 40 Uranium and Therit.m J 23 No detectable radioactivity j i [ Total 167 k All of the.TA scans which indicated the preconce of uranium warc reviewod to determine which camples exhibited the highest activity per unit weight of material. Seven camplec were conservatively celected and sent to a cutcontractor i L for nu.43 spoetroucope analysis. The resulta are shcen in attac! ment B-4. j Using the resulta from attachment B-4 and an average acasured nutorial dannity, I the total quantityof uranium and U-235 was determine: I E t .m, -,m-

) Dull-80-006 littJchnen t B-3 (con ' t. ) Sample PPM CC./ Drum Total Density Total U U-235 I!unter U U C.C. U granu/c.c. U-235 Kg. Granc 1-11 285.00 60.527 717.25 1.5 75.41 1.076 811.41 1-25-2 8.20 1.741 20.64 1.5 82.73 0.031 25.60 1-27 1.90 0.421 4.98 1.5 64.47 0.007 4.52 1-28-2 4.50 0.956 11.:' l.5 26.06 0.017 4.43 1-45-2 146.00 31.007 366.81 1.5 1.02 0.550 5.61 2-15-2 105.00 22.299 253.76 1.5 1.45 0.381 5.52 2-17-2 1.16 0.246 2.92 1.5 64.00 0.004 2.80 Total 2.066 859.93 The quantity cf thorium ias esti.Tated by using a measured density for thcrium of 0.936 grrs/c.c. anc! assuming " hat the material was hcTcgeneous in de 61 drums projected to contain only thorium. One half this value was used to estimate the th;rium content of the druirs which indicate presence of :'rth thorium and uranium. All MCA gantra spcctrum recults of icose material indicata the presence of only therium ad therefcro all 1100f t. cf locco :raterial is assumcd to Le thorium. The follcwing is a suirmary of the total quantity of thorium precent: 61 druns thorium only 1.916 Kg. 40 drturs thorium and uranium 0.628 Kg. 1100 ft 3 thorium only 4.756 Kg. loose material 7.300 i:g.

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-. L v a.. 9 Q 6-e-m n p h V be" EYa Cd 50 VAN Curitn AvtNut WEOTWOOO NT W Jf ritty 01615 (201) fA4 7010 f CLC s 13-44 / 4 i PAGE 1 TELEDY!!E ISOTOPt:S RON DATE 03/26/80 REPORT OF A::ALYSIs f.n U l1 G R A '! E S 9 t:52-510 COM!USTIC" E ': C I" E S ?. I !: G I'I C P O'.' U R STS, TUELC S MATLS D07 1000 P::0;NCT UILL 3D 0G095 VIHUSCP. CT E037. 03D00 tlU"CER C U S'IO M S R P.O. NUMDC3 DATE-DSOVD DELIV-CATE 08/10/80 08/29/00 3-2952 NUCLE A3 FDEL '0234 U235 U236 U220 TOTAL UFFn 285 .772 75.4C9.379 23.440 735 t> 2 1-11 8.2 .994 82.725.416 15.914 r3543 1-25-2 1.98 .724 64.473 330 34.uc5 F3544 1-27 4.50 .294 26.0(1 137 73.503 P3545 1-20-2 146 .0032 1.020 LT.001 93.972 P3546 1-35-2 105 015 1.454 LT.001 98.531 F3047 2 2 1.1G .63G G3.995 322 35.047 F3548 2

  • 7-2 LAST PAGC 07 BEFOUT APPROVED BY L.CASAD01\\

CU/26/UD N A!! AGER M M '.i SPEC GOVICES ST!t D 1 COPICO 70 COS83S Ma W n r,0.VE0 '3452-510 1 G/A . f'l / f 4<<-,j *U 6 b'

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lill01OIfico Con espondenco Athwhw ot. u c n:li i ts i +_1 C >lT-] POV!!ill L.1-iUf) SYUl E{iiS f, ,( Y l, R. /. Kl o't:. J To: P. R. Rosenthal (A) cc: R. ,a.. Harding (C f({ hf' Pl10 -CO-132 W. A. Goodwin (C Octoher 30, 19G0 Criticality Evaluation of Was te Drums The fissile contents of the samples analyzed by teledyne have becq comparcJ to the limits in AN5 N16.1 and all samples including F3542 which has the highest concen'. ration of U-235, are well belcu the criticality limit. The degree of subcriticality can best be shown by tal;ing the U-235 concentration in the above sample and assuming it is mixed with water in this sa"e concentration. The resul ting concen-tratico is still a factor of 37 below the uniform Acuenus Solution limits in ANS N16.1, Of course, the other materials in the swples will act as a poisco and furt;ur reduce t" cri tic al i ty sa fety f : tor.. Again m arn making the above ccncluniont cn the highest rvasur"d cen-centration v.hich is over a factor of 30 higher than the next highest measu > ed concentra ticn. RJK:ajm i 9 4

t)! O-on-Mn c l l , Attach-ent C-H Enhibit 1 _Sa.".elina Plan A 15 C.C. canple will to obtained from each new 55 gallen drum an it is An attetpt will be nnde to obtain a representative sangle by packagcd. taking 5 C.C. of material when the drum is 1/3 full, 5 C.C. of materf.al Cach 15 C.C. when the dru:n la 2/3 full arvi 5 C.C. when the drum ic full. sample will be transferred to the Developacnt Departnent laboratory for gama spectroscopy. If rer.ults of the gantna spectrum scan indicates the presenca of thoriun only, the drum will be considered to be homogeneous containina Wcrium at a measured density. If results of the ganna specJum indicate the presence of uranium er uranium mixed with thorium, a portion of the 15 C.C. sample will be sent to an in-depen: lent latcratory for acaay to determine radioistopo concentratica r,d U-235 The quantity of the radioactive material and the enricl=ent in cnrichnent. the dr rn will be calculated using the method outlined in attachment B-3, Exhibit 1. T [ e b i I l l i l

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('/91201) ~FMDC-00-000 cc: U. li. Crave".- J. ii. Lithurt Novenhcr 6,1930 A water leach test has been conducted on six ('6) was te oxide samples J The purpose collected frora storage drums by llcal th ftysics personnel.to determ ~ of the test u25 by rain later from the oxide material. The test was performed I;y placing the sanple materials in contact with At the end of j sir,.ulated rainwater for a period of fifteen (15) days. the leach period, a portion of the liquid was removed, filtar:d and ftec ults analy.Md fcr alpha and beta radioactivity and chenical uraniu per milliitte. of leach solution. A liquid pr 'sumed to be rainunter was found in the bottom of drum 2-21. This W r ' s extracted from the drun and also an::lyr-d for radicactivity i'iicto rcsuiss are lis%d in T81e i as Scr ple . contert, and t. m. No. 7 and are reportac ta.c L.illiliter o' liquid e sract. The test results show that no ci';nificant radioactive material was leachcd frrm sr? es 1, 2, 4, 5 and 6. However, $ angle '!c. 3 from drun 1-25 l !!o detectr ble indica'.as leach!ng of scne alpha and Leta radioactivity.The liquid extr?.cted frc:.. d uraniun was leachcJ fron any samole. Sample No. 7. contsined no masurable radioactivity or uraniu". in delnil in as follu'.. Simo!M.cd rai: The test ramcejuru and ' ':y sc.tura ti rc.; de:riner ;1 i: J ue t-wi th carbon diw : i .a tr :s pN e i. ga.m. 'fhe resuitant pH of this sciut: o <.es ?. T%e prcy D" d in a ^? 20 in diW ei por t ii.m o f n 9 UC t r or ' de w.il e w as psi.u la ted ra i n. ' i.c c (100 ul ) <c;.:. cefed ple.stic containce. At the end of t% '. containe: uds cappn'J and lef t ut.disturbcd for 15 days. period, a liquid smnp!e was collected ircm the supernate of cach conuiner The liquid extrac tti fron and filtered through 0.2 micron fil ter paper. Al pha and l' eta radicar. liv i ty drum 2-N was also fil tered in the same manner.of the fil tered l iquids wa Mear.urenr n t-in a low background proportional counter. liquid for 1 hr for uranium centent wer0 performed with a uranium fluorimeter. y. b = =

t . flove,t:Imr G,1 %0 Tim ininic,um detectable activities listed in Talle 1 are equ t1 to the tuo s tandard deviationn countino urcertainty or er, or and arn re;.o r t e ' ,e, I h,: re.ul t '.:ht n they a re equal t u or qr a t er t han t!u: refo.u e1 rad ioac tivi' / concen t ra t ion. The toinhuuci wn itivities lir.ted f or uroaiu:n conc. o'.ra tionr. are based up m min iar: <:: < c tam e it.hter def l ec t i on and in.trun.;n t rc<; ponce to ur.ai t.u u t s.nds.. i.'.. / / )N ,".v^... v y / ^ c.' v f. E. A. Hagel c. te in EMI/bca Attcciaant i e 0 e

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l011-30-006 l i Attrk 'mt 3-3. C:dtiMt 1 i l Three atratit'ication soil saaples were obtaitel in the apprc::u:nto locaticr. f r.dicated in attacircat 3-1, c:d11 Lit 2. Radicactivity variation with d p' h for each of the titree caaples in shown in attac!.tr.cnt B-8, e;dtibit 2. The only radicicotopo identiflo] was - thorium cr its daughtera. All'three stratification sanples wora in the for::t of resolidified scrap r:etal oxides which have " capped" the surfaca of the soil. Based upon results of thece aanples it is eatinatal that the " cap" will have to be rencved to a depth of appro:<i.mately six inches. i i e

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= _. _ _ _. j a IN 0-80 ;U0r; ~* \\ htt'acledit B '),' 1M11 bit 1 t Polnaso or tho lawl for unrrctrictol unn Since it has been deterndned that the materials are in the innoluble

form, radiation dose to man through the fccd ingesticn pathways is considered to be insignificant. The significant patliwayc of dose to e

be conaidered for' unreatrictcd release oC the land are from external direct radiation (whola - Indy) and frcm inhalation of particulates (lung burden) due to long term resuspencion of radienuclides from the soil. The target criteria to ' c used for release of the land for unrestricted use c is presented in Attachment A. The dose conversion facters to be used to deter:nine lung burden are shcun in Attachmsnt E-9, Exhibit 2. I i l-

Attsuima ut I;-9 1;rdubit 2 Lbse Cenversion F;rt r: Car Lung Parlioner:lixle [hte Crnversion Factor (Rc:r/p Ci inhaled) U-233 390 U-235 420 U-234 450 Th-232 590 Th-220 440 Th-22S 1310 Ra-228 1100 Pu-239 400 Pu-233 510 Ph-210 370 = These dcse conversica facters are basel en a "Y" cc".tcu:.d with an IMO of 1.0 un. vv0 -}}

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