ML20126L178

Revised Application for Amend to License SNM-1067 Authorizing Temporary Possession of Certain U & Thorium Waste Matls for Packaging & Transfer to Commercial Disposal Facility

ML20126L178
Person / Time
Site:	07001100
Issue date:	05/01/1981
From:	Lichtenberger ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
19963, DDH-81-145, NUDOCS 8106010565
Download: ML20126L178 (35)

Text

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d-pDQ C E Power Systems Tel 203/688 191i Combusbon Engineeong.. Inc.

Teler 99297 1000 Prospect Hill Road

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y U.S. Nuclear Regulatcry Ccmnission b

Washington, D.C.

20555 222 R

w en ATIN: Mr. R.G. Page, Chief

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Uranium Fuel Licensing Branch h5 8

Division of Fuel Cycle and Material Safety g

REF:

(A) C-E Letter, DDH-80-086, dated November 10, 1980, Request for Amendment to License S21-1067 Gentlemen:

1 By Reference (A) it was requested that license SRf-1067 be amended to authorize temporary possession of certain uranium and thorium waste materials for packaging and transfer to a ccanercial disposal facility. This letter forwards additional infomation in the form of a revised application in s"pport of the original request for an amendment. This additional information has been incorporated into the criteria and demonstration sections; Attachment A and B, respectfully; and should resolve ccmaents sad /or questions presented by members of your staff.

Attachments A and B included herein supersede and therefore should replace Actachments A and B forwarded by Reference (A).

It remains our intent to package and dispose of the material within nine months af ter approval of the amendment, therefore the request that the amendment be effective for that period of time is unchanged.

If there should be any further questions concerning this application, please contact Mr. P.R. Rosenthal of my staff on extension 3366.

Very truly ~vours, c 71 9/f)&

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H.V. Lichtenberger,

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DDll-81-145 Page 1 Attachment A - StM License Anendment Criteria 1.

This attachment establishes the criteria to be used te package and transfer certain uranium and thorium bearing waste materials and all contaminated soil described below from Canbustion Engineering's Windsor, Connecticut site to a ecmnercial disposal facility. The material, consisting of the residue from burning scrap metal con-taining 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 property as shown in Attact:nen:s (B-1 and B-2).

A staging area shall be established within the clearing for packaging and repackaging of the material, soil, used waste drums, and other contaminated equipment to be discarded.. After packaging in new containers, the packages shall be transferred to an outdoor storage area (see Attachment B-1) where it shall remain until subsequently released to a Carrier for transport to a ecmercial disposal facility. Both the area where the nuterial is now located and the latter storage area shall be established as restricted areas in accordance with 10 CFR 20. Specific dimensions of the contaminated restricted area and general arrangement of tools and equipnent to be used during repackaging of the materials is shown in A m chment (B-3). The storage area shall be maintained as a conti Tation free area: less 2

2 than 100 dpm/100 cm alpha and less than 200 dpm/100 cm beta gamna activity. To ensure ecmpliance this area shall be surveyed weekly.

ddditionally, both areas shall be maintained as restricted areas until acceptance criteria for unconditional release of the areas has been met and confinned by the NRC.

e v

DDil-81-145 Page 2 3.

It has been detennined (see Attachment B-4 thru B-10) that the material, j

which is predcminantly zirconium oxides, contains radioisotopes j

4 of both uranium hnd thorium. Based upon the sampling procedure l

and analysis described in Attactuent B-11 and B-12, this criteria includes authorization to process 4kg of total uranium enriched in the isotop U-235 to 93% and 10kg of. thorium.

. 4.

Handling and packaginp, of the material shall be performed in accordance.with written procedures approved by C-E's Manager of 1

-Health Physics. The procedures shall be impicmented by a

{

i Radiation Work Permit (RWP), see Attachment (B-13).

ll f

5. ' All personnel who physically handle the material in the course of packaging shall wear protective clothing, shoe covers, gloves, and other apparel as specified by the Manager of Health Physics. All personnel who enter the restricted areas as defined in Condition 2, above, shall wear personnel dosimeters. A breathing zone lapel' air sampler shall be used 100% of the time by each individual handling l

unpackaged material or material which is not contained. The B/Z 1apel

{

1 samplers shall be' counted and results reviewed on a daily basis. An action i

limit of 50% of that allowed by 10 CFR 20.103 will be established, j

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Upon reaching the action limit all work shall be stopped until a review of'the packaging procedures can be made by the Manager of Health Physics to determine that 10 CFR 20 limits shall not be exceeded. Al1 l

a personnel, material, and equipment shall be surveyed prior to leaving 2

'the restricted area. A release limit of 100 dpn/100 cm alpha and 2

200 dpn/100 cm beta /ganma activity shall be cbserved for materials and equipnent. Personnel shall be surveyed for alpha and beta /ganma activity.

4 Release limit for personnel shall not exceed background.

Background accur-racy shalli e acceptable if within two standard deviations of the established background' level.

5

i DDll-81-145 Page 3 It has been determined (see Attachment B-15 and B-16) that the fissile content 6.

of the nbterial is well below the criticality 1Lnit. Thorofore criticality controls are not needed during packaging of the material.

Based upon the same detennination, noterial packaged in 55 gallon drums (Specification 1711 drums) can be stored in any array and maintained at a high degree of subcriticality.

Druns shall not be stacked greater than two high.

It is planned that small samples of material will be transferred to the Development Laboratory, Building #5, for analysis. This building is presently licensed for mass limit controls under license SK4-1067.

For the purpose of mass limit control, each sanple taken to the laboratory shall be assumed to have the highest concentration of U-235 based upon previous analysis until it has been. determined-by garra spectroscopy that no uranium is present or until it has been determined by chemical assay or mass spectroscopy that the U-235 content is less than that originally assumed. None of the material shall be transferred to Buildings

1. 17 or #21 at any time.

The sampling plan presented in Attachment (B-17) shall be used for 7.

determining the quantity and enrichment of uranian to be transferred to the disposal facility.

The material shall be packaged and released to a carrier for transport 8.

to a disposal facility in accordance with applicable provisions of 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 of l

10 CFR 71, 49 CFR Parts 100 through 199, or the disposal site criteria shall be repackaged so as to comply with the applicable requirements.

4

DDil-81-145 Page 4 I l i

It has been detennined by laboratory tests that the radioactive mater-9.

ials are in the insolubic fann (see Attachment B-18) therefore migration To ensure that fran scepage or surface water runoff is insignificant.

resuspension of the material does not occur during packaging, continuous air monitoring shall be performed in close proximity (within six (6) feet) to the loading hopper (see Attachment B-3).

In addition, air sampling shall be perfonned at the perimeter of the restricted area both up wind and down wind. An action limit of 25% MPCa in accordance with 10 CFR 20 will be established.

Upon reaching the action limit, all work shall be stopped until a review of packaging procedures and activities is made by the Manager of Health Physics to determine that 10 CFR 20 limits shall not be exceeded.

Based upon results of radioactivity measured in stratification soil samples (see Attachment B-19) it is estimated that 4 to 6 inches of loose waste material will have to Most of this material is in the form of resolidified be removed.

scrap metal oxides which have " capped" the surface 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 l

direct radiation dose rate will be measured at each grid For a diffuse source area (an area greater than 25' x

,4 area.

25') the gauina dose rate in air one meter above the ground should not exceed 10 ur/hr. above background.

For a dis-crete area (an area smaller than 25' x 25') the ganina dose rate in air one meter above the ground should not exceed

'18 ur/hr. above background.

4

)

DDll-81-145 Page 5 b.

Representative soil samples shall be taken fran each grid area and analyzed for the concentration of nuclides in dry soil. The soil shall be acceptabic for unrestricted use if the dose from the sum of the major radionuclides does not contribute to a total lung dose greater than 10 mrem / year, based on calculations using the conversion factors presented in Attachment B-21 and B-22.

9 is i

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.DD11-81-145 Page.6 1

4

. ATTACIMENT B

' List lof Contents-B-l' Windsor. Site Building Location Plan

' B-2.

. Detail Map of Material Location B Waste Material. Staging ' Area 4

B-4 Drun Identifice' inn Plan - Ground Level' Drums -

B-5; Drum Identific.

u Plan - Upper Level Drums

- B-6 Gamma Spectrur.

um 1-2 Sample

- B-7 Ganma Spectru..

.ci1-27 Sample B-8.

Cama Spectru

'a 2-10. Sample j

B-9 Gama.Spectrt an 2-20 Sample B Ganma Spectr:.

Jil Sample 3-1 B-11

' Determination t terial Quantity

B Isotopic Analpis.'of Material' Samples e

- B-13.

Packaging Procedure and Sample RWP B-14 Criticality Evaluation.

B-15 Criticality Evaluation -' Density Method

. B-16 Sampling Plan

'aste Oxide' Leach Test W

B-17 i

B-18 Stratification Soil Sampling B-19 Stratification soil Sampling - Activity vs. Depth s

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B Release of the Land for Unrestricted Use B-21; Dose Conversion Factors to be Used for Determining Lung Burden t

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DDH 145 ~ Page 17 + Atiachment B-11 / Ehcroexists16755gallondrumsofwastematerial. Of this total 96 drums have.tcon surveyed'using a mult-channel analyzer with the following results: Radioactive Contents Number of Dnims l Uranium only .25 Thorium only 35 Uranium and Thorium 23 No detectable activity i 13 Ibtal 96 Seventy one of.the drums have not been surveyed at the present time because ~ > they are in the inner rc c of dru:rs and are inaccessible until the outer dru:rs have been renoved. Assuming that the material in-the unsurveyed drums is of the same nature and type as the surveyed drums, it is esthrated that for the total of 167 drums the folicwing would result: 4 Radioactive Contents Number of Drums 43 Uranium only 61 Thorium only Uranium ahd Thorium 40 No detectable radioactivity 23 Total 167 All of the SCA scans which indicated the presence of uranium were reviewed to determine which samples exhibited the highest activity per unit weight of material. Seven samples were conservatively selected and sent to a subcontractor for mass spectroscope analysis. The results are shown in attachment B-12. Using the results from attacharnt B-12 and an average measured notorial density, the total quantityof uranium and U-235 was determinc: 0 4 4 f l e.. .,y-,,..,,w7,-.,.gw+, .,,,,,,,y .-+-,,,,_y4mmw..,,,,-,,y,,,,_.,,.,%.-- ,,,-y.+ % w m.,,,, .,,wrru,,, ,w., ,,.,y,m.sy mw -,. ~, ~ -

DDit 145 Page 18 Atitachnent D-l 1 (con ' t. ) Sampl'c PPM CC./ Drum _. Total - Density Total U U-235 Numtcr' U U C.C. U grams /c.c.. U-235 Kg. Grants 1-11 285.00 60.527 717.25 l'. 5 75.41 1.076 811.41 1-25-2 8.20 1.741 20.64 1.5 82.73 0.031 25.65 1-27 1.98 0.421- '4.98 .l.5 64.47 0.007 4.51 1-28-2 4.50 0.956 11.33 1.5 26.06 0.017 4.43 t-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 of thorium was estimated by using a measured density for thorium of 0.986 grams /c.c. and assuming that the material was homogeneous in the 61 drums projected to contain only thorium. One half this value was used to estimate the therium content of the drums which indicate presence of both thoriumand uranium. All tCA gama spectrum results of 1cose material indicate

the presence of.only thorium and therefore all 1100f t.3 of loose material is assumed to be thorium. The folicwing is a sumary of the total quantity of thorium present:

61 drums thorium only 1.916 Kg. 4 8' 40 drums. thorium and uranium 0.628 Kg. 1100 ft.3 thorium only 4.756 Kg. loose material 7.300 Kg. e 4 -=wve-tr*+--m-to-e=---y --ee*-w---r----t-W -,,,,*r-av=--;* +e,* -erec r

• a se wee e-*,w

-<e-e e i- --v-me-v v.s +w-* --e'w-*

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" Attachment B-12. Page 19 9PTELEDYNE ISOTOPES DDH-81-145 60 VAN 00f t(H AvtNUC I WE$fwo00. Htw Jf ruv 01615 (7011064 7070 f(LEX 13 4414 i ~.x I PAGE 1 TELEDYllE ISOTOPES ROH DATE 00/26/80 REPORT OF Atl A LYSIS ^ 58 9 M CRAVES-9452-510 - COMEDSTICM E ?t G I!! E ER I:td I?lC FUELF S "ATLS DEV P07FR DTD, 1000 PROSPECT !!ILL RD 06095 12R0508 CT CUSTOMER P.O. NUMDER DATE-RECVD DELIV-RATE B02K 03D23 IlUMBER 08/10/80 08/29/80 3-2952 NUCLEAR F0EL 0234 U235 U236 U230 TOTAL UDFM 772

75. 4 c9.379 23.440 205 10542 1-11

.994 82.776 416 15.914 8.2 F3543 - 1 2 .724 64.473.338 34.465 1.98 Y3544 1-27 .294 26.061,137 73.508 4.50 73545 1-20-2 0082 1.020 LT.001 98.972 146 -73546 1-45-2 .015 1.454 LT.001 98.531 105 ' 73547 2 2 1.16 636 63.995.322 35.047 73548 2-17-2 LAST PAGE OP IIEPORT 08/26/80 APPROVED RY L. CASA 00'lA MMI AGER MASS SPEC DEllVICES n GRAVES 9452-G10 1 COPIES TO COG 033 na W SEND l~ L ,n e I 4 O 4 r e-, -e.--,,~>.ngw ,v-- ge-. g.n ,m+,--,*--,,-v a m- = .ra, -.n,v ,,.,-....e ne ~ ~~,,

~. 'DDil-81-J43 Pages 20 - 24 y / [, ATTACIMFNP li-l'1 .This procedure, and associated Radiation Work Permit, are sulxnitted as a demon-stration of the method to be used to ensure that the necessary radiological controls are being implemented. It should be recognized that, due to the nature of the task,. changes to the procedure may be required and that charges nay be made without prior notification of the NRC stal~f. these changes, however, will not violate the conditions of Attaclanent A, nor reduce the effectiveness of the procedure, DEVELODOT ~ DEPAR'DET URN 1ILM NTD TriORIlDI DEMlING WASTE PACKAGING PROCEDURE I PROCEDURE FE DER: DDH-S1-142 t NA 4 O"O I Prepared by: Date: ~ li 78/ e Date: Approved by: Original Issue: 4/8/81 Revision: d Date: e 9. f e a 8 8 9 9 O 9 8 e S ., -, - +,, r~..v. r -,,vv---.<,-,,,,.a. - +,. - -,e <r,~,--,w ,,vn,. ~, ~.,,,.. - - -. - e-.. . - ~ ~ -

DDii-81-142 1 s' ,1 %l 1.0 SCOPE ~ his procedurc covers 'the work required to package uranium 1.1 bearing wastes for disposal.. j 1 2.0_ PRalEOUISITES_ An amendment to License Stef-1067 has-been approved to autho possession'of the low level waste material. 2 '.1 ) 2.2 ' All personnel working in accordance with this procedure a i as radiation workers. 2;3. he area to be worked in is posted and maintained as 'a res area. A Radiation Work Permit is issued to cover the work performed u 2.4 this procedure. ifying 2.5 Prior to l'eading,new and old drums have been marked with a lable. llect 2.6 The area surrounding the loading station has been covered to co any spillage. 3.0 EQUIP >ENT- -3.1 Alpha friskers 3.2 -Beta friskers 3.3 ' Alpha / Beta smear counting equipnent 1-3.4 Continuous air monitor 3.5 Breathing zone air samplers i j. Survey instruments capable of monitoring areas and equipment - 3.6 existing radiation levels. ' 3.7 Special loading hopper SPECIAL PRECAlIFIONS 4.0 Work will not be perfonned,if it is raining or if there is a threa l ity as measured at Bradley Airport 4.1 if the wind ve oc of precipitation, if the Manager - Health Physics detennines the exceeds 30 mph or weather conditions to be unfavorable. lh Data Sheet #1 must be canpleted, reviewed and approved by Physics personnel for each repackaged drun, prior to that 4.2 being released for disposal. 0 4 4 - w w. --r- .,,,c 6._, y.,u,, ,n-.. ,,.r--..ie.,

• --,*---,n-r.-wew e,e-,---w--

-e*---*.- em-y- - - - ---.---------v 4 ~* - -

DDil-B1-lu [.. 1 4 3 0' PROCEDURB 5.1 Drum P,cpackaning. 5.1.1 Place a new empty drum under the hopper '/. Transfer as many old drums to the hopper as may be 5.1.2 required to fill the new drum. Carefully fill the new drum'fran the hopper (see step 5.1.4). 5.1.3 ENSURE Tile DATA SilEET FOR Ti!E NEW DRU'l REFLECTS NOTE: Tile I.D. MUMBERS OF-Tl!E OLD DRUMS TilAT COMPRISE 1T. 5'.'1.4 - Obtain 3 sampics, approximately 50cc each, when the new drum is approximately 1/3,_2/3 sad full. Identify sample container with same I.D. number as the new drum. i When the new drum is full,. place a lid on the drum. l ~5.1.5 5.1.6 Perform a smear survey of the new drum. Decentaminate the drum as necessary for release to the storage area. Weigh the new drum and record the weight on the data sheet, 5.1.7 Transfer the new drum frcm the loading area to the 5.1.8 ' storage area. j PRIOR TO TRANSFERRING Tile NEW DRUM TO TIIE STORAGE 6 0F THE DATA SHEET MUST BE CCMPLETED f NOTE: ARCA ITEMS 1 TIIRU AND SIGNED BY THE COCMIZANT l!EALTil PHYSICS TECHNICL\\N ) IN TIIE SPACE AVAIL \\BLE. i 5.2 Loose Material Packaeing 'D0 NOT BEGIN 'IllIS SECTION OF THE PROCEDLEE LHTIL I NOTE: ALL WASTE DRUMS HAVE BEEN SUCCESSFULLY REPACKAGED. Place 2 or 3 new empty drums in a front loader. 5.2.1 l 5.2.2 Carefully transfer the loose material frcm the area to the drums. 5.2.3 Obtain 3 sampics, approximately 50cc cach, when the new drum is approxinutely 1/3, 2/3 and full. Identify sampic container with'same I.D. number on the new drum. Wlken the new drum is full, place a lid on the dmn. .5.2.4 5.2.5 Perform.a smear survey on the new drum. Decontaminate the 3 drum as necessary for release to the storage area. 5.2.6 Weigh the new drun and record the weight on the data sheet. Transfer the new drum fran the loading area to the storanc area. 5.2.7 i NOTE: PRTOR TO 'lRANSFEllRING TllE NEW DRUM TO Tile'STORACE ARl'A, l 0F Tile DATe\\ SilEl l' MllST BE Cm!'IKrED AND Sl(:Ul:D ITINS 1 TilRll (3 ,........,.,,,, u mn i.ny.m..., pm.g g gg ; g.;.;;g g;,gg 393 ; g,qg, l

Panc 3 of 3 DDil-81-142 UltAN11tf & '1110RilBI lil'ARit:0 WASTM PAGACING DATA SilEl.T . j, fute: new Drum I.D. Number: (step 5.1.3 only)

i. Fran old drums

3

4. - Sampic obtained and identified (ll.P. initial)

S. Drum Smear Survey Alpha: dim /100cm ] 2 2 Beta /Caarna : DPM/100cm 6. Weight of drum: Gross Weight: lbs. Not Weight: lbs. Items 1 through 6 above have been ccmpleted Signature Date 7. Weight of sample: grams 8. Analysis results: Enrichment % U235 Total U grams Total U235 grams Specific Activity ci/ gram Isotopes W6ight of material ' Ibs. 9' Total Activity: curies i Items 7 through 9 have been ecmpleted I l i Signature Date I

10. Chemical Form:

11. Physical Form:

12. Radiation Survey:

Contact:

mr/hr 3 fect: mr/hr

13. Drum Seal Nanber:

Items 10 through 13 have been completed Signht6rc Date Date chect reviewed and drum released for dispocal w -,re-e,v,,, r, r-- vn,,,,me v., e- ,,,,w, -4n-, v ,m,, w-,

POVIER

/ SYSTEMS SMtP12 m .[4 4 $ '/ d!48 l lHN i lip, RADIATION WORK PERMIT / \\ ,1 f Hoquestor Date Start Date Expire R.W.P. No. 6/1/81 6/7/G1 111 Work Area 11 RWP is for more than one day. RWP rnust Wasto Material be initialed and dated by HP before work Date f g, 5 '" ' " ~ Staging Area Initial g e,7 r / Job Description Packaging of Uranium and 'Ihoriun waste / R.W.P. must bs initialed by all authorized personnel prior to starting work 4 Allowable Daily Allowable Exrosure Date{ Authcrized Personnel Initial Weekly (j gf Exposure Dattij Date Date Date Date Date John Doe' /$6 /CO N Jack Jones /vd IdU (7 Joe Blcw /h /M !b /7 / / ~ i 2 Radiation Levels Mrem /Hr Contamination Levels In m 1-3 mrem /hr at contact 500-2000 et \\lpha Requirements lC TLD E Full PC's O Rubber Gloves D Dosimeter O Cloth / Plastic Booties O Cotton Gloves D 8 Z Air Sampler O Cloth Hood O Plastic Suit . O Lab Coat ~ O Rubbers G Approved Procedure O Plastic Gloves d Other (Specify Below) Soccial inst'debons

1. Procedure tul-81-142 must be postec and tollowed

2. CMI must be in cperat.icn whenever work ts pertotried i

3. II.P. coverage requirect at all times Approved By Date Terminated Dy Date l

E h (') s / 6 c.e ooooni coo) ' SMIPLE i4 WD-+PP '-t-g 'qy4~-

• rpWPS.-t=+>ha+me+e t

e -ypg ,..yn y3y y.wm.+ g q w w w,,,9 ,,g..y..%w. 9,

Intorof fico Correspondence Attachment B-14 DDil-31-145 Pano 25 g POV!En @S L_aSYS1 EMS N R.' J. Kl o'tz To: P. R. Rosenthal (A) 0-M W cc: R. S. Ilarding (C)[f October 30, 1980 W. A. Goodwin (C) Criticality Evaluation of Waste Drums I The fissile contents of the samples analyzed by teledyne have beer. F3542 compared to the limits in A'lS tl16.1 and all samples, includine, which has the highest concentration of U-235, are well below the The degree of subcriticality can best te shown criticality limit. by taking the U-235 concentration in the above sample and assuming it is mixed with water in this same concentration. The resul ting 'concen-tration is still a factor of 37 below the uniform Aqueous Solution limits in Arts i!16.1. Of course, the other materials in the samples will act as a poison and further reduce the criticality safety f actor. . Again we are making the above conclusions on the highest measured con-centration which is over a factor of 30 higher than the next highest measured concentration. R y RJK:njm s' 4 'm

DDll 145 Page 26 A1 TAC 104EtTP B-15 CRITICALITl EVALUATION OF WASTE DRlltS USING TllE SURFACE DENSITl MElll0D Reference I - R.L. Stevenson and R.ll. Odegaarden " Studies of Surface Density Spacing Criteria Using KEND Calculations". Trans. Amr. Nucl. Soc. 12,890 (1969). In addition to the criticality evaluation of Attachment B-15, an evaluation was performed by the surface density method described in Reference I above. 'Results of a mass spectrum analysis performed on a representative sample.of the waste drums, see Attachment B-12, indicates the drug with the highest concentration of U-235 would contain 152.16 x 10-0 grams U-235 per c.c. One square foot of surface area in a single drum 86.4 cm. high would contain: 86.4 cm x 929.03 cm2 = 80265 c.c. 80265 c.c. x 132.16 x 10-6 grams /c.c. = 12.2 grams /ft.2 Since attachment A requests authorization to stock drums two high, the surface density for this drum with the highest concentration of U-235 would be 24.4 grams /ft. This value is over seven times below the surface 2 density limit of 175 grams U-235 per f t, specified by reference 1. This is considered to be very conservattve since the calculations are based upon a mass spectrum anal' sis for a drum containing 30 times more uranium than y the other drums sampled, l e w

DDil 145 Page 27 Attachment B-16 Samplinn Plan A 150 C.C. sampic will be obtained fran each new 55 gallon drum as it is An attempt will be node to obtain a representative sample by packaged. taking 50 C.C. of noterial when the drum is 1/3 full, 50 C.C. of nutorial Each 150 C.C. when the drum is 2/3 full and 50 C.C. when the drum is full. sample will be transferred to the Development Department Laboratory for gamna spectroscopy. If results of the gamm spectrum scan indicates the presence of thorium only, the drum will be considered to be hanogeneous containing thorium at a measured density. If results of the gamna spectrum indicate the presence of uranium or uranium mixed with thorium, a portion of the 150 C.C. sample will be'sent to in in-dependent laboratory for assay to determine radioistope concentratior, and The quantity of the radioactive noterial and the enrich-U-235 enrichment. ment in the drum will be calculated using the method outlined in Attachment B-1!, d ND e e e e. y.-,y. - - - --_. _ -.

---

v

Intoroffico Corroopondenco > ~.. Attachment G-1f_,, g / DDil-81-145 FJ,5_4 poi!!ER .;;.3L a SYSTEMS 1 E. A. Hagelstein Waste Oxide t.cach Test 1-P. R. Rosenthal 'To: (791201)' FMDC-80-000 ..-'"~" II. M. Graves cc: J. M. Limbert November 6, 1980 i . A water leach test has been condueted on six.'('6) wasto oxide samp es The purpose collected from storage drums by Heal th physics personn by rainwater from the oxide material. 4 The test was performed by placing the sample materials in contact with At the end of . simulated rainwater for a period of fifteen (15) days.the lea 1 Results analyzed for alpha and beta radioactivity and chemical uranium.td . of these anclyses are listed in Table 1 as Samples 1-6 and are repor e

D per milliliter of leach solution.

A liquid presumed to bc rainwater was found in the b and uranium content.,,These resul ts are listed 'in Table-1 as Sample No, 7 and are. reported per milliliter of liquid extract. The test results-show that no significant radioactive material was leache However, Sample "o. 3 from drum 1-35 from sampics 1, 2, 4, 5 and 6, No detectable indibates leaching of scme alpha and beta radioactivity.The liquid extracted from . uranium was leached from any sample.Sampic No. 7, contained J/ Simulated rainwater was The test procedure in. detail is as follows. prepared.by saturating domineralized water with carbon dioxide and A 50-gm The resul tant pH of this-solution was 4.8. portion of cach waste oxide sample was placed in a 3.25 in, diameter. atmospheric gases. F Simulated rainwater (100 ml) was added, and the At the end of that plastic container. container was capped and left undisturbed for 15 days.rnate of cach container h 'geriod, a liquid sample was collected from t e supeThe liquid extracted; from and filtered through 0.2 micron fil ter paper. Alpha and beta radicactivity it drum 2-24 was also fil tered in the.same manner.of _ the filtered Measurements liquid for 1.hr. in a low background proportional counter. .for uranium content were performed with a uranium fluorimeter. e 4 - a ,1 s 8 k -,,,, -,,,, _ _ _. _, ~.,.

x . November 6, 1980 The miniraum detectable activitics listed in Tabic 1 are ccplal to the two stantlard deviation counting uncertainty or error and are rer.o rt ed a'. the re', nit when they are c<pral to or qrea ter than the The niinimum.r n.i tivities r.'ea,nred r ad ioac tivi ty concentra tion. li: ted ior uranium conce:ntrationn are based unon trin iian::t det ec table ruter def Ir:c tion and in.tru:nent recpon.;c to uranihm '.,Lund6 rds. . // .sfew % !v. / V y, ,E. A. Hagelstein E/6'/bco Attach:ront (= e A e 4 l 4 e**e

• • • eeme

+ e #4 eg ,e e a y

Table 1 leach Test Results .t

l '

Sample Sample ' Alpha-Alpha Beta Beta Uraniu:a i Number Identification D/M/ml UCi/ml D/li/ml _VCi/ml.

llicrograms/al

- 1 -8 1 1-8 <0.07 ' <3.2 x 10 <0.14 1 3 x 10 .<2 6 2 1-24 0.13+0.08 5.9 x 10 <0.14 <6.3 x 10-8 -8 1 -7 -7 3 _l-35 0.28+0.09 1.3 x 10 1.03&0.09 ' 4.6 x 10 y) 4 2-1 <0.07 <3.2 x 10-8 <0.14 <6. 3 x 10-8 ' <1 s -8 .<6.3 x 10-8 <3 l 5 2-19 <0.07 <3.2 x 10 <0.14 ~ 6 2-24 <0.07 <3.2 x 10-8 < 0.14 <6.3 x 10-8 y)- 7 Extract -8 -8 j 2-24 <0.07 <3.2 x 10 <0.14 <6.3 x 10 <1 j. i \\ 1 s 1 i t

DDIl-81-145 Page 31 Attachment B-IP, Three stratification soil saniples were obtained in the approxirrate location indicated in Attachnent B-2. lbdioactivity variation with depth for each of the three saniples is shown in Atthelment B-20. .The only radioisotope identified was thorium or its daut;hters, All three stratification sarnples were in tim form of resolidified scrap metal oxides which have " capped" the surface of the soil. Based upon results oC these samples it is estimatcJ that the " cap" will have to be removed to a depth of approximately six inches. 6 e 0

DDi!-81-145 Attachtw2nt B-19 Page 32 0 m W x, Es I l-- Q LtJ Q E Z 9 i-C a H zO El f-o..

e. I E

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c vc. x N

<C l H Q<K E w w = m -. y.,= a = a. 8 - v - ; = = a = - - - - = + - g rx x x x x x x x "a <? o b i 4 4 l t I i l i l t I i l

i

.1l j l .c4l b C N =1 a Ek "0 N N (n ~ s g d d = g .) x = w i x

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8 DDIl-81.145 .o, Page 33 Attachment B-20 Polcase of the land for unrestricted use Since it han teen determincd that the materials arc in the insoluble form, radiation -::csc to man through the fccd ingcation patJraays is considered to to insignificant. The significant pativaays of dose to be considered for unrestricted release of the land are frcm external direct rediation (whole - hedy) and frcm inhalation of particulates (lung burden) due to long term resuspension of radionuclides from the soil. The target criteria to be used for release of the land for unrestricted use is presented in Attach: rent A. The dose conversion factors to be used to determine lung burden are shown in Attachment B-22. 9 4

". f httaciutent B-21 DDil-81-145 f Page 34 Dose Convercion Factors for Lung I Padiontv>) fric Dose Conversion Factor '(Rem /p Ci irhaled) U-238 390 U-235 420 U-234 450 Th-232 590 Th-230 440 Th-228 1310 Ra-228 1100 Pu-239 480 Pu-238 510 Pb-210 370 These dose conversion factors are based a "Y" ccmpcund with an M GD of 1.0 pm. 4' 12CG3 '1}}