ML20151A105
| ML20151A105 | |
| Person / Time | |
|---|---|
| Site: | 07109218 |
| Issue date: | 09/30/1981 |
| From: | Clements T EG&G IDAHO, INC. |
| To: | |
| References | |
| WM-F1-81-015, WM-F1-81-15, NUDOCS 8804060279 | |
| Download: ML20151A105 (135) | |
Text
.
=, - _ _ =., _ _ _ _ _.
_ _ _ _,m m u.._;.._
-.--,.._.-_~.__.._;_m_;_2.
t h h
WP.- F1 015 bbEb idaho, Inc.
Report No.
September 1951 Date:
9 PA"h" C_EA RED L
INTERNAL TECHNICAL REPORT IDAHO NATIONAL ENGINEERING LABORATORY STORED
.U' TRANSURANIC WASTE CHARACTE;IZATION:
NONRADIOLOGICAL HAZARDS IDENTIFICATION Organi:ation:
Waste Programs Division j
Courtesy re!e se to Se public on request.
This document was prepored primarily for Irternal use. Citatten oc quoh : ion of this document or hs contents is inoppropr' te.
o T. L. Clements, Jr.
.muthor:
/
Sy:, N A;creved By:
s/ W 'W Che:Ke
/-
8804060279 010930 PDR ADOCK 071*****
/AIMT CLEARED ammunnimumman
._n..,.
,,., c,, = =.= :.
1-
-. d m
.m_
m
. =,
w.._=
,w
-.n=-
,.=
i
\\
O*
PA"ENT C_EARD
"-71-82-o1=
. IDAHO NATIONAL ENGINEERING LA60xATORY STORED TRANSURANIC WASTE CnARACTERIZATION:
NONRADIOLOGICAL HAZARDS IDEdTIFICATION Prepared by:
Thomas L. Clements, Jr.
'aaste Programs Branch Waste Programs Division Septemoer 1981 Courtesy releese to the pub'ic on requ<st This document was prepared yimarily for internal use. CHotien or quotation of this document or its contents is inoppropriota.
Prepared for:
NUC EAR FUE
'YC'.E DIVII:0N U.S. Ce:ar: en: of Energy 1cano V:eratiens Office MTET CLEARED
l r
1 ABSTRAC T
'o This report summari:es tne available.information concerning j
icentification of potential nonradiological hazarcs incluced in transuranic (TRU) contamilated wastes stored at the Icaho National Engineering Lacoratory (INEL). Waste cnaracterization information incluces process cescriptions, type of waste generated, anc waste management practices.
This report covers botn offsite-and sita-generated wastes.
i ine generic types of nonraciological nazarcs found in :ne stored wastes include inorganic and organic enemicals, biulogical wastes, and mecnanical ha:aros.
These types of waste may nave an impact on future management alternatives for transuranic wastes storec at tne INit.
l I
i i
l y
l 4
.s' t
CONTENTS ABSTRACT.............................................................
11 1.
INTRODUCTION....................................................
1 2.
ESTABLISHING CONTACTS AND 06TAINING DATA........................
3 2.1 Initial Contact...........................................
3 3
2.2 formal Contac:............................................
2.3 Visitation................................................
3 4
2.4 Repor
3.
OFFSITi-GENERATED WASTES........................................
5 l
[
j 3.1 Mound Laboratory..........................................
5
)
l 3.1.1 Plutonium Processing Builaing.....................
5 3.1.1.1 P ro c u c t i o n..............................
6 3.1.1.2 Plutonium Recovery......................
7 3.1.1.3 Analytical..............................
8 3.1.1.4 Waste Salicification....................
g 3.1.1.5 Decontamination anc Oecommissioning.........................
10 l
l 3.1.2 Researen Building...'..............................
13 3.1.3 Waste Discosal Suilcing...........................
14 3.1.4 W as te Management Pr ac 1ces........................
16 3.1.4.1 Waste Drums.............................
17 3.1.4.2 Waste Boxes.............................
19 3.1.5 Nonraciological Hazaros...........................
20 3.1.5.1 Mercury.................................
20 3.1.5.2 deryllium..............................
22 3.1.5.3 Pressurizea Drums......................
2?
3.1.5.4 Gas Generation..........................
22 J.1.5.5 Ion Exenange Resins.....................
22 3.1.5.6 Asces:os................................
23 3.1.5.7 Organic Wastes..........................
23 3.1.5.3 Otner...................................
23 3.2 Battelle Cuium:us Laboratories............................
24 3.2.1 Plu:enium Lacoratory..............................
24 3.2.1.1 Oc:entamination anc Dec:mmissioning.....
25 iii
~
f 1
3.2.2 Waste Management Practices........................
27 3.2.2.1 Waste Containers........................
28 3.2.2.2 Content Coce Description................
29 3.2.3 Nonr aciologic al Haz arcs...........................
29 i
3.2.3.1 Polycnlorinatec Biphenyls...............
29 3-3.2.3.2 Other...................................
30 30 3.3 Settis Atomic Power Laboratory............................
3.3.1 Fuel Manuf acturing Facility (L-Building)..........
31 3.3.2 Experimental Physics ano TRX Facilities (C-Area).........................................
31 3.3.3 invironmental anc Raciochemistry Analyses (N-Building).......................................
31-3.3.4 Analytical Chemistry (L-6uilding).................
32 3.3.5 Waste Management Practices........................
32 3.3.5.1 Waste Packaging Metnoas.................
32 3.3.5.2 Absorced Liquids........................
33 34 3.3.6 Nunraciological nazarcs...........................
34 3.3.o.1 Acies...................................
3.3.5.2 Oils................................
3.,
34
~
3.3.6.3 Carbo Wax 6000 (Polyethylene Glycol)....
34 3.3.6.4 Otner...................................
34 3.4 Argonn e N at ion al L acor atory-E as t..........................
34 3.4.1 Chemical, Engineering Division.....................
35 3.4.1.1 Decentamination anc Deccomissioning.....
36 c
3.4.1.2 An alyti c al Chemi s try....................
37 3.4.2 Material Science Division (Suiloing 212)..........
38 3.4.3 Scecial Macerials Divisien (Suilcing 212).........
38 3.4.a Building 350......................................
39 3.4.4.1 New Brunswick L acor atory................
39 3.4.4.2 Dec:ntamination anc Decommissiening.....
29 l
3.4.5 Cnemistry Division (Suilcing 200).................
42 3.4.6 was e Managemen: Practices........................
43 3.4.6.1 Reclamation Group.......................
43 3.4.6.2 Waste Description.......................
44 I
iv 1
l l
4
s t
3.4.7 Nonradiological Hazarcs...........................
45 3.4.7.1 Beryllium...............................
4E 3.4.7.2 urganic Wastes..........................
45 3.4.7.3 Ion Exenange Resins.....................
46 3.4.7.4 Otner...................................
46 3.5 Rocxy Fiats Plant.........................................
46 3.5.1 Plutonium Operations..............................
48
- 3. 5.1.1 Plutonium Faorication Facilities........
48 3.5.1.2 fire waste..............................
50 3.5.1.3 Plutonium Analytical Lacoratory.........
56 3.5.1.4 Chemical and Metallurgical Researen and Development.........................
56 3.5.1.5 General Lacoratory......................
58 3.5.1.6 Critical ity Researen.................... ' 58
]
3.5.1.7 Process Chemistry anc Engineering Researen and Develcoment................
58 3.5.1.8 Molten Salt Extraction..................
59 3.5.2 Plutonium Recovery Facility.......................
59 3.5.2.1 Soecial Recovery Operations.............
59 3.5.2.2 P reauction Recovery Operations..........
60 3.5.3 Aqueous kaste Treatment Facility..................
61 3.5.3.1 First Stage Sluege (Content Cece 1).....
61 3.5.3.2 Secenc 5tage Sluege (Centent Code 2)....
62 3.5.3.3 Comoined Slueges (Centent Coce 1).......
62 3.5.3.4 Solicifiec Organics (Content Coce 3)....
66 3.5.3.5 Special Set-Ups (Content Coce 4)........
68 3.5.3.5 Evaporator Salts (Centent Cece s).......
68
)
3.5.3.7 New Aqueous Waste Treatment Facility....
68 3.5.4 Nontransuranic Operations.........................
71 J.5.4.1 Builaing 444/447........................
71 4.5.4.2 duilcing 083............................
73 3.5.4.3 Builcing 365............................
73 I
i 3.5.5 Was*e Management Prac* ices........................
73 l
1 i
i J.O..I
, Waste Drums.............................
./
- i
.,as*e doxes.............................
s:
l 3.0.0.2 n
S.5.5.3 Centent Coce Description................
75
)
l i
3.5.6 Nenraciological Ha: arcs...........................
85
]
3.5.6.1 Bielegical Waste........................
85 1
3.5.6.2 Gas Cylincers...........................
85 1
4 d
v 1
. - - - ~. -... -
J J.5.6.J AsDestos................................
86 l
l S.5.6.4 Polycnlorinated signenyls...............
86 i
3.5.6.s Beryllium...............................
87 3.5.6.6 Nitratec Wastes.........................
87 i
3.5.5.7 Batteries...............................
88 3.5.6.8 0:ner Cnemical aastes...................
88 i
3.5.o.9 Hycrogen Generation.....................
89 3.s.6.10 Drum Pressuri:ation.....................
89 1
1 3.5.6.11 Pyrophories.............................
89 i
I 4
l 4.
10AHO NAi!0NAL ENGINEERING LABORATORY-GENERATED WASTES..........
91 4.1 Test Area North (TAN).....................................
92 4.2 Chemical Processing Plant (CPP)...........................
92 4.3 Argonne National Laboratory-West (ANL-W)..................
93 i
4 4.4 Naval Reactor Facility (NRr)..............................
93 4.5
.T e s t R e a cto r A r e a ' ( TRA)...................................
94 4.6 Nonraciological Hazaros...................................
94 l
5.
SUMMAAY.........................................................
95 5.1 scuno.acoratory..........................................
97 1
97 1
5.1.1 Mercury...........................................
1 e.l.2 ceryllium.........................................
97 5.1.3 Pressuri:ed Drums.................................
97 5.1.4 Gas Generation....................................
97 5.1.5 Ion Exenange Resins..........................;....
98 5.1.6 Ascestos..........................................
98 i
a 5.2 Battelle Columbus Lacoratories............................
98
'(
5.2.1 Polycnicrinated Sienenyl (PC3)....................
98 i
i I
5.3 Bettis Atomic Pcaer Laboratory............................
98
)
5.3.1 Carco Wax 6000 (Polyetnylene Glycol)..............
98 i
5.4 Argonne Natienal Lacoratory-East..........................
99 i
3 5.a.1 Seryllium.........................................
99 1
- .4.2 Urganic Wastes....................................
99 5.5.3 len Exenange Resins...............................
99
)
i 5.5 Rocxy Flats Plant......................................... 100 i
)
Stolo9 cal Wastes................................. 100 i
5.5.1 5.5.2 G as Cy l i n c e r s..................................... 100 vi i
l i
s i
5.5.3 Assestos.......................................... 101 5.5.4 Polychlorinated Bipnenyls (PCS)................... 101 5.5.5 Beryllium......................................... 101 5.5.6 Nitratec Wastes................................... 101 5.5.7 Batteries......................................... 102 5.5.8 other Chemical Wastes............................. 102 5.5.9 Hycrogen Generation............................... 103 5.5.10 Drum Pressurization............................... 103 5.5.11 Pyrophories.....................................:. 103 5.6 Idaho National Engineering Lacoratory..................... 103 5.6.1 Seryllium......................................... 103 6.
R EF ER E N C E S...................................................... 104 APPENDIXES AP P END IX A--WASTE QUESTIONNAIRE E XAM.PL E.............................. 105 APPENDIX S--MOUND SLUDGE ANALYSES.................................... 113 APPENDIX C--ROCKY FLATS SLUDGE ANALYSES.............................. 117 FIGURd5 1.
F irs: Stage Sluege P ack aging Me:ncas............................
63 2.
Secenc Stage Sluege Packaging Methods...........................
64 t
3.
Cc cined 51uege Packaging Me:nce................................
65 4
dolicifiec Organic Waste Pacxaging Methocs......................
67 5.
Special Set-Ups Packaging Metnocs...............................
59 5.
EvaPerator Sal: Packaging Me:nocs...............................
70 IABLES 1.
Ha:srecus materials inclucea in storea TRU wastes...............
96 vii
s s
IDAHO NATIONAL EhdINEERING LaeURATORY STOREO WASTi CHARACTERIZATION:
NONRADIOLOGICAL HAZARDS 10ENTIFICATION 1.
INTRODUCTION The Radioactive Waste Management Complex (RhMC) encompasses approximately 144 acres in the soutnwestern corner of the Icano National 3
Engineering Lacoratory (INEL). The RWMC was establisned in 1952 as a controlled area for burial of solid radioactive, wastes generated by INEL cperations.
In 1954, tne burial ground was cesignated as a solid transuranic (TRU) waste cisposal site. Until 1970, all TRU waste was buriec celow grace at the R'aMC.
In Novemoer 1970, the Transuranic Storage area (TSA) was estaolisnea for retrievacle storage of waste contamina:ec aitn greater inan 10 nLi of transuranic activity per gram of waste.
The waste is stored aoove-ground on asphalt pads at tne TSA.' After a section of a pac nas been filled witn waste containers, successive layt:rs of plywocc, nylon-reinforced polyvinyl sneeting, and approximately 3 feet or soil is pla:eo over tne waste containers.
Transuranic wastes storea at TSA are generatec cy operations egncuctec f:r the U.S. Atomic Energy CO. mission and its successor agencies, new tne U.S. Department of Energy (00E).
The following facilities nave generateo ne majerity Of TRU aastes placed in s:crage at T5A:
Mound La:cratory, Miamiscurg, Chic; Ba::elle Columeus La:cratories, Columeus, Onio; =ettis A::mic Power Lacoratory, West Mifflin, Pennsylvania; Argonne National Lacoratory-East, Argonne, Illinois; anc :ne Rocky Fia:s Plant, Golcen, Coloraco.
Small volumes of TRU wastes nave also :een genera ac by INEL
- erations.
In accition, the INEL Initial Drum Retrieval (ICR) and Early a'aste Retrieval (EWR) projects nave contributec wastes pia:ed in s:Orage at j
TSA.
Ine total volume of TRU waste placec on TSA from Novem:er 1970 l
- nreugn Decem:er 1930 was 1,:95,560.9 f:*.
Ine purpose of :nis report is to icentify ;c:ential nenraciolcgical nazar:s inclucec in transuranic wastes s:: rec a: :ne INEL-ISA.
i 1
i
)
Nonradiological ha: ares may include inorganic anc organic cnemicals.
[
oiological wastes, and mec'nanical ha: arcs (pressuri:ec gas cylincers, etc.). Tnese materials not only are raciologically contaminated out also j
represent a nonradiological ha:ard cue to associated enemical, oiological, f
or meenanical properties.
Availaole INEL waste snipment recorcs are not
-complete in listing potentially ha:ardous materials in storea TRU wastes.
f Icentification of potential ha:arcous materials will assist in ensuring personnel anc environmental protection tnrough acequate engineering design of retrieval, processing, ano snipping facilities usec in future stored Tau l
waste management alternatives, i
During the course of :nis project, icentification of nonradiological ha: arcs recu1 rec an understarling of each waste generator's operations.
[
I processes, type of waste generatec, material usage, waste management I
practices, anc any significant enanges occurring since storage of TRU wastes oegan. This waste enaracteri:ation information is incluced in :nis report to assist reacers in gaining a more complete uncerstanding of tne f
cifferent types of operations tnat generate TRU wastes snipped to tne INEL l
i for storage.
i j
F i
l l
1
)
3 l
i i
1 i
l l
l l
i l
2 i
f i
_ ~ _-._._._. __
2.
ESTABLISr;NG CONTACTS Aa0 06TAlaiNG DATA 2.1 Initial Centact Initial contact was estaclisnec witn eacn offsi;e waste generator by letter from ne Waste Progrtms Division, EG&3 Icano, Inc.
The letter oriefly explained tne purpose of :ne study and requesteo :na a contact incivioual be designated from each offsite waste generator. ine contact incivicual was to assist in characteri:ation of s:crea =aste and icentification of potential nonraciological na: arcs inclucec in :ne was:e.
2.2 Formal Contact Fo* mal contact was estaclisnec by telepnene witn :ne contact incivicual icentified my offsite generaters responcing to tne initial letter.
Tne purpose of the study was explainec in greater cetail to tne contact incivicual, and attempts were mace to determine the availacility of informatien c:ncerning wastes snippeo to tne INdL. m waste questionnaire p;pencix A) was cesignec to provice a general format for systematically enaracter1:ing :ne waste.
IndL waste generators aere contac ec cirectly f:r informa:icn concerning waste placea in s:Orage at TSA.
2.3 Visita:icn A personal visit was mace to eacn offsite waste generating facility, except for :ne Se: tis Atomic Poner Lacciratory. Permission ;c visit ne 5e::is facility aas ceniec by DOE-Pittssurgn Operations Office.
During visits to :ne c:ner was;e genera:ces, availacie recorcs ce: ailing waste sni;ments anc f acility operatiens were reviewec.
Personnel naving (nc*lecge of c;erations, processes, ex;eriments, aaste nancling procecures, etc., were interviewec to cetain information concerning nonraciolcgical na: arcs :nat may exis in s:Orec TRU as:es.
s 3
s' 2.4 Ae: ort The information centainec in eacn section of :nis reocrt, concerning
.aste characterization and icentification of nonradiological nazarcs, nas revienee by tne appropriate waste generating f acility.
This review nas cencuctec to ensure tne completeness ano accuracy of the characteri:ation information.
I I
i
~
o 1
3.
OFFSITE-GdNERATED WASidS 3.1 Mound Laboratory 1
The Mounc Lacoratory is operated oy the Monsanto Research Corppration for tne 0.5. Department of Energy.
The function of tnis facility is to manufacture components for use in the weapons program ano produce plutonium i
cioxide (23dPu0 ) heat sources for commercial and military j
2 applications. Transuranic (TRU) wastes sent from tne Mound Facility to tne 230 INEL are generated oy Pu heat source operations only. Waste
]
originating from manufacture of weapons components ano associated researen and all <10 nC1/g waste from plutonium areas are disposed at comercial and otner government disposal sites. Heat source programs nave generated transuranic wastes from enemical purification, f aorication, recovery, analytical activities, decontamination and decommissioning (MD) activities, and waste treatment facilities. Mound waste shipments to the INEL began in February, 1975. ine yearly volumes and numoer of waste l
containers received were as follows:
vear Volume (m )
Volume (f:3)
Druns
- lo xe s i
3 l
1975 604.4 21,344.4 2207 48 4
1876 193.8 6,844.0 931 1977 310.9 10.979.4 762.
46 1975 180.7 6,381.4 d68 li79 394.1 13,917.6 1352 32 1950 19z.3 6,791.1 318 43 TOTALd:
1876.2 66,267.9 6438 16 1 1
1 ine following indivicuals proviced information concerning wastes i
snippec to tne INEL:
R. K. Slauvelt, D. R. Hopkins, R. L. Deaton, j
A. B. Cones, A. R. Campoell, R. Goss, T. Elswick, anc 0. R. Ficler.
i 3.1.1 Plutonium Precessine Builcine The Plutonium Processing (PC) Suiicing at tne Mound Lacoratory processes '3"^PuA receivec from tne Savannan River Plant (SRP) anc 1
23S i
fa:ricates py neat sources for comer:ial anc military aoplications.
o
Heat sources f aericated at Mound nave beer useo in tne Acollo lunar project, planet Mars Viking program, Pioneer spacecraft program, carciac paceina(ers, milliwatt generators, ana multihuncrec aatt sources for space co r:unication satellites. An estimated 70% of Mouno-generated TRU waste originates frcm tne PP :luiluing.
3.1.1.1 Freduction. Prior to 1979, 238Pu0 receivec frem SRP was 2
enemically purified oy dissolution in a mixture of nitric /hyurofluoric (HNO /HF) acid and tnen precipitated with amnonium nycroxide (NH;0H) 3 forming plutonium hydroxide (Pu(VH)4).
ine Pu(OH), self-calcined to pug and was grounc to var'ious particle sizes, depencing on program 3
particles were sintered ano tnen requirements. After grinding, tne Puu2 sent to a heat source faorication line.
The ratio of isotopes in :ne final proauct was as follows:
807. 238P u, i bi. 2 hPu,3%2%y, 0.5.-
Pu, and 0.2% 242Pu.
In the glovecox fabrication lines, :ne particles aere either coated with a metal, usually molyocenum, or pressed intu seneres or aiscs anc tnen triple encapsulateo.
Encapsulation materials incluced iricium, graonite, Hastelley, tantalum, and titanium.
Solic wastes generated oy product'.on efforts includeo paper, rags, plastics (polyethylec,e, polyprooylene), carton cie parts, hano tools, glass, lera-linec gloves, some ascestos gloves, molyedenum anc tantalum foils, graonite, anc metals (iron, stainless steel, aluminum, iricium, etc.).
Small in-line generated wastes aere placeo in 1/2-gallon (metal) or 1-gallon (plastic coatec careboard) cartons; tne carton aas then placeo in a polyetnylene Dag anc transferred to tne assaying station. Any cartons 238 f"
containing recoveracle amounts of 3u02 " 5'"I IO "'CU**P7 processin;. Car: ens containing beloa-ciscaro amounts of '35Pu02**"*
caggec out of :ne glovecox into polye:nylene ":uce" bags (several cartcns/ tag) and placec in 17C 55-gallon crums.
Esen crum naa a 90-m11 polyliner and a plastic mag lining :ne polyliner.
ine cartons aere segregatec into ecmoustible anc nonccmousticle fractions. Larger waste l
items (:cols, motors, etc.) aere cocole-containec in colyetnf ene cercre placement in crums or ooxes, cepending on size.
ine crums aere sent tu i cuilcing for assaying by segmented ga,ma scan.
doxes are assayed oy gaana scan a: :ne P? iuilding, o
Since 1979, 238Pu0 has been receivec from SRP in a purified, 2
encapsula ec form.
decause enemical purification is no longer required, the volume of wastes generated by procuction efforts nas oeen greatly recuced.
in accition, heat source procuction operations nave been gracually pnased out since 1978. Currently, most of tne prouuction lines are uncergoing DJ.
Several encapsulation and assemoly lines are still in 4
operation.
3.1.1.2 Plutonium Recovery. Recovery operations servec to recover O
and purify Pu0 frem aeove-ciscarc-level wastes (term means tne 2
waste is contaminated witn recoverable amounts of special nuclear material) generatec ey procuction, research (R Building), and analytical programs.
Recovery operations at Mounc ceased in late 1975.
Since tnen, wastes 20 contaminated with recoveraole amounts of Pu0 hava een sent : SRP l
2 for processing. Solid wastes generated by recovery operations were inclucec in early Mound waste snipments to INEL. Liquic wastes were i
j orocessec at tne Waste Solicificatien (WS) facility in :ne PP Building.
J j
Plutonium was recovered frem waste items ey several processes tnat I
incluceo incineration, fiuerination, anc fusion. Ine resulting resicues were processec ey dissolution, leacning, concentratien of :ne leacna:e, ion excnange, anc precipitation of plutonium nitrate (Pu(ft0,)2) *ith
- 1I*
(n C 0 ) acid. Chemicals used in recovery operations incluced nitric 3g4 anc nycrofluoric acies, nycroxylamine nitrate, socium carbonate, ferrous sulfamate, and socium nycroxice.I Listed below are recovery me:nocs usea for various waste items:
Cor:ent Coce Material he:noc i
l 501 rags, paper incineration, followec ey cis-solution 302 glovecox gloves, leacn j'
ruecer 303 metals, ecuipment, leacn j
pipes 30c plastics, tygon leacn 205 asbestos filters leacn i
610 glass, flasks leacn 513 glass filters anc hF fluorination ficerglass 7
Ar:er processing, tne remaining resicue (gloves, glass, filters, metals, slucge, etc.) was criec anc packaged as solic was:e. Mos: of tnese wastes were pacxaged in cartons (as previously cescricec), lacellec for conte,1t, reassayed, segregated into comoustible and noncomoustible fracticns, anc placeo in aaste crums. Evaoorator anc cissolver slucge (content cooe Sil) was generated from processing various wastes. The slucge contained 248 pug, iron (Fe), calcium (Ca), socium (Na), chromium (Cr), and otner 2
enemical residues from recovery efforts. Two-hundred-and-twenty-one 1/2-gallon (metal) cartons of sluage were incluced in waste snigments.
Spent ion exchange resins (Oow series) were also included in early waste snipments. Tne resins were packaged in cartons (28 total) anc lacellcd as content coce 812.
3.1.1.3 An alytic al.
Tne analytical lacoratories at Mounc sup or:
prouuction, recovery, ana waste trea: ment operations ano participate in :ne Safeguarcs Analytical Lacoratory ixcnange (SALE) program.
Tne purpose of
- ne SALE program is to verify racioisotope inventory anc stancara analytical :echniques used by o:ner labortories. Tne analytical lauuratories perludically participate in aeapon components surveillance pregrams.
The volume of waste generated oy analytical operations is small.
2 Solid wastes (glass, paper, plastic) are contaminated witn Pu,
~ ~~P u, 2 ~"~U, 2 "*U, an d t eryl l ium ( Se ). Beryllium-contaminated wastes (glass, gioves, pa:er, and sample precipitates) originate frcm analyses of weapon comoonents. Approximately one to nree 1-gallon cartons of Ee-c:ntaminatec aastes are generatec esen year.
Samole precipitates are la:elle: as content coce Sil. Each car:en contains <0.05 g (estima:ec) of de. All cartons are lace 11ec as containing Se.
C:ntaminatec elemental ercury (ng) has also oeen generated oy analytical operaticns. Tne Hg is centainec in plastic oc::les (precaoly pin si:e) insice 1/2-gallen (metal) cartons.
Six:y-one car: ens of ng aere inclucec in waste sni;ments anc were laaelled as c:n:en: c:ce 832.
in-line generatea licuic aastes are ;recessec ey tne n's facility.
.ca-l ev e l alsna-c:ntaminated licuics are processed at :ne Waste Disposal (au) ou11cing.
U
,l J
3.1.1.4 Waste Solilification.
The Waste Solidification (WS) facility processes contaminated acia and caustic liquid wastes generated primarily ey production, recovery, and analytical operations.- Trace amounts of liquic wastes are generated by cleaning neat source nardware anc research Prior to 1979, procuction operations generated hNO /hF wastes 3
programs.
from tne cissolution of Pu(N0 )2 and hycroxide filtrates from 4
precipitation of Pu(N0 )2 Recovery operations, wnien enced in late 4
1975, generatec HNO, HF, and oxalic acic wastes.
Solutions of 3
hydroxylamine nitrate, sodium caroonate, socium hycroxice, anc ferrous sulfamate were also generated by recovery operations.
Tne volume of.liquic waste contrioutec ey tne analytical laboratories is small and consists of HNO, W H SO, and nCl. Overall, an estimatec 95% of tne acicic 3
2 4 waste was HNO witn trace amounts of HF, hcl, H 3U4 ""d 0**IIC 3
2 acies. The primary source of caustic liquic waste is the corrosive vapor scruceer system.
This system is enarged witn a caustic solution (socium nydroxice) to scrub acidic fumes from all PP operations. Procuction operations generated small volumes of caustic waste (hycroxice filtrates) from ne precipitation of Pu(N0 )2 with NH 0H.
4 4
Prior to Decemoer 1975, the acicic (content coce 834) anc caustic (content coce 335) liquic wastes were processec in separate systems.
After recovery operatiens encea in late 1975, tne volume of acicic liquic waste was greatly recucac, and separate processing systems were no longer requirec. Since Decemoer 197o, any acicic liquic wastes nave even comuineu w1:n caustic liquid wastas for processing. Almost all licuia processac since nen snoulc ce easic. A program was initiatec in Decemoer 1979 to ensure that all liquias were easic cefore processing.
Setore prucessing, eacn liquid baten is sampled for analytical cetermination of normality anc m'"Pu content. All solutions were required to contain less nan 2O 0.012 mg/mi of Pu until 1979 wnen :ne limit was raised to O.025 mg/ml. After tne analytical results are cotainec, :ne liquic is transferrec to a nolcing tank. The nolding tank is vacuum or air "spargec" to ensure suspension of :ne plutonium :nrougnou
- ne liquid baten. After soarging,10 gallon aliquets are transferrec into a calioratec tanx anc gravity-fed into a 17C 55-gallon crum, witn a 90-mil polyetnylene crum liner anc a plastic Dag lining :ne 90-mil crum liner, fillec witn 150 lbs.
9
of cia:omaceous eartn particles (Floricin Company proauct fierco) to absoro tne licuid. After being fillec, tne crums are sept unoer negative pressure for a minimum or lo hours for off-gassing cefore sealing tne c% a Acicic waste crums have been snipped to :ne INEL since Iv7o.
Inese crums were generateo during 1974-1975 but were storec at Mounc for repackaging due to pressuri:ation.
Drum pressurization problems occurred from the use of a ciato..iaceous eerth absoroent (tracename Auto-0ri anc/or Dri-Rite) that contained calcium caroonate (CaCU ),
eaction between 3
CACO and tne acidic IWuic was:c resultec in the procuction of caroon 3
cioxice (CO ).
After tne pressuri:ation problem was icentifiec, use of 2
Auto-Ori and/or Ori-Rite was suspended anc use of Florco, wnich coes not contain CACO, began in July, 1975.
Drums suspected of ceing pressuri:ea 3
were repackaged by dividing :ne contents of a crum in:o two crums, storing ne crums for approximately 3 montns, rechecxing for pressuri:ation, anc civicing :ne drum contents again if necessary. Tne last acid crums (content code 334) were snippec to INEL in veceinoer 1980. An estimat.ea 20 acio crums may nave been snippec to INdL (s1975) cefore tne pressuri:ation proclem aas icentifiec. Inese crums may be pressuri:ec.
i
'1.1.1. o vecentamination anc Dec;mmissionine.
Dec:ntamina:icn anc cec:=missioning (D&D) of PP recovery, analytir.al, anc procucticn glovecox lines cegan in late 1977.
Since then, most of :ne solio waste generated of PP Suilcing nas been from D&D cper3tions. At present, one analytical laceratory ano several neat source assemoly lines are still in operation, out :ne volume of waste generated oy nese coerations is small.
Sefere a C&D o;;eration begins in a section of tne PP Suilding, all non-glovebox line associatec items (furniture, electronic ecuipment, etc.)
i are re. moved. All small, loose in-line ecui;: men: (flasks, nanc tools, i
i pacer, rags, etc.) are placed in plastic bags anc :nen into 1/2-gallon i
metal er 1-gallen car:boarc car: ens, assayec, anc caggec ou cf :ne j
glovecox in coucle plastic bags. Larger pieces of equipmer,t, suen as tan <s, are cissassemolec, if p0ssiole, oaggec out of :ne glovecox in coucle Elastic cass, and placed in crums or stancarc si:e aste ocxes.
Enernal piping and service lines into ne glovecox are removec ano paccagec.
After l
10 i
l
\\
all ecuipment nas oeen removec from :ne glovecox, tne glovecox interior is coateo witn approximately 2-3/4 in of polyurethane foam to "fix" :ne l
contamination.
Tne glovebox is then cutup, or if poss1 ole, uncoltee from Ine glovecox line.
If the glovecox was cut from tne main line, a piece of 16-gauge sneet metal is sealeo to tne exposeo end of the glovecox witn ruecer cement (trace name RTV) and tape. Each glovecox is usually wrapped in one or more layers of plastic before placement into a stancarc or over-sized waste cox.
Polyurethane foam is useo for snoring. No waste items are placed inside ne glovecoxes. The following information concerning equipment ano materials removed curing PP Suiloing D&D operations was proviceo:
ele linear feet of stainless steel glovecoxes, 7 ft nign oy J f:
o wice; removec in sections e
30 linear feet of fiberglass glovecoxes, 4 ft hign by 3 ft wice; removeo in sections 1
o Plexiglas winoows frem tne glovecoxes i
t o
Stainless steel fume neocs l
r F
l o
One macnining latne, 2 ft nign by 3 ft long I
{
o f antalu:n tanks (evaporators, cissolvers, precipitators) l o
Polyetnylene tanks (1 to S gal)
]
]
o Stainless steel tanks (3 to 40 gal) a Acproximately 20 large (132 to 160 gal) stainless steel tanxs u
l 1
J o
Six resistance furnaces, IS-in. ciameter oy 18-1n. nign o
Small amounts of ficer;1 ass anc ascestos insulation from j
furnaces, et:.
1 11
o Two vacuum puma presses; eacn press nas o large senerical enameer mace of 1-in. :nic< stainless steel; oil was drainec from eacn press.
o Tnree stainless steel diffusion pumps, largest pump is 3 ft long by 10-in, ciameter; oil was craineo trem eacn pump.
o Numerous Welsn puntos; oil was ortined from each pump, o
Manipulators and manipulator boots o
Leac-lined glovecox gloves and seme ascestos gloves o
Glassware o
Wrenenes and c:ner hand-tccls o
Grapnite molcs ano crucibles o
Duct acr<
o Small amounts of lead shot o
Pa:er, rags, plastic o
S: sinless steel anc black iron piping, 3/5-in. o 1-in. ciameter o
Weloing ecuipmen: (electroces,caoles) o Cencui o
Concrete, fl:or tile o
A: proximately 900 linear ff;et of fieergiuss conveycr system, 2 f:
aioe ey 3 f: nign, aill ce sent curing FY-d2.
12 u
i a
3.1.2 Researen euiloina 4
TheResearen(R)Buildingsupportedproductionoperationsconoucted.at l
tne PP duilcing.
The R Builcing was responsible for developing process 238 technology for ne fabrication of Pu0 heat sources.- These i
2 processes incluced heat source coatings, encapsulation researen, snaping and pressing heat sources, anc otner metallurgical researen.
i l
Decontamination and decomissioning of most R duilding laboratories (glovebox lines) began in 1978.
I Solid wastes generated by ne research programs (1975-1978) were similar to wastes generated by PP Builcing procuction operations. Tne aastes consisted of paper, rags, plastic, leac-lined gloves, graonite, molybcenum and tantalum foils, glassware, and metals.
Small in-line generated was:es were placed in 1/2-gallon (metal) or 1-gallon (cardcoarc) 1 cartons, then caggec out of :ne glovecox into a plastic cag, and taken to 1
pP Builcing for assay. Any wastas containing recoveraole amounts of 238
]
Pu0 were processed at :ne PP Building.
Larger waste items were 2
contained in at least two plastic bags. Low-level alpna-contaminated l
I liquic wastes aere processed at the WO Builoing.
1 Seven R Building laboratories will eventually be cecorrrnissioned. A:
present, four laceratories nave been completec.
The procecures used for l
D&D opera' ions are similar to tnose used in D&D operations at the t
79 Suilcing. Tne following information concerning OLD aste from 1
A Evilcing was previded:
i I
o alc linear feet of stainless steel glovecoxes, a f: nign ey 3 ft j
q
. ice
}
o Vacuum neat cress, partially dismantlec; cress containec a I
scr.eric.sl cha-:,er, 3 f t ciameter witn ac;roximately 1-in. : nick stainless steel walls o
inree stainless steel ciffusion pumos, larges pump is 3 f: nign oy 18-in. ciameter; oil aas crainec frem eacn pump 13 i
o Numerous helsn vacuum pumps, 18-1n. ciameter ey 22 in. long; oil was crainee from each pump o
One macnining latne, 2 ft nign by 3 ft long o
Several stainless steel tanks o
Two fumenocos, 4 ft nign oy 3 ft long, mace of 1/2-1n. tnicz stainless steel
{
f e
Cooper ano stainless steel piping
[
o Hot plates, nand tools f
o Glassware (flasks, beakers) o Crucibles (grapnite and tantalum) l l
o Leac-linec gloveDox glCves o
Plastic, paper, rags, etc.
l 3.1.3 Waste Discosal Builcing i
i The waste Disposal (WD) Building processes all low-level f
al:na-contaminatec liouid wastes from tne PP, R, ri (launcry), anc au Euildings. The felicwing materials make up tne culk of licule waste f
influent to 'a0 5uilcing:I j
I o
Snower aater ano soap o
Decontamination water o
Cooling aater o
Detergents 14
P t
Alconols--trace amounts of metnanol, etnanol, propanol o
t l
4 o
Acids--HNO, H 50, MF, hcl, etc.
3 2 4 i
i o
Caustic--primarily NH 0H l
4 l
o Janitorial wastas--wax, wax stripper, bew1 cleaner, etc.
t o
Paint j
4 o
S awcust, 4
)
o Acetone, trienioroetnylene--trace amcunts, j
Trace amounts of solid enemical aastes are incluceo in :n liquic waste.
[
j Ine following estimated quantities of enemical wastes are incluceo yearly in tne liquio waste stream:I Chemical Quantity (Ins.)
[
1 t
Potassium carocnate (K M0 4.0 Potassium sulfate (K 50 )3) 1.0 i
2 4 j
Copper sulfate (Cus0 )
1.0 4
Calcium caroonate (CACO )
3.0 i
~
l 0xalic acid (H C 04) 1.0 22 uithium enlorica (LiC1) 2.0 l
j Zircenium oxice (Ir09) 2.5 i
4 Socium caroonate (ita00 )
0.25 3
Caustic soca anc lime 60.0 Petusium bremice (Kar) 2 2 5)
Potassium pyrosulfite 'K 3 0 5.0 j
2.5 Nickel sulfate (NiSO )
4.0 4
As:estes ficer 1.0
)
)
Metnylene clue 1.0 l
l Mercury (ng), Leac (Po)
- race Beryllium (Be), cyanices Trace l
a All licuic wastes are collecteo in four 20,000-ga11cn interc:nnecteo influen: tanks. Tne aater is sampleo fer racioactivity anc ;reparea for 2#3 i
treatmen:. ine ;rimary contaminant is
/u, aitn trace amounts of j
'**U, *3Np, and 241 2
Am. Ine trace nuclices originate from j
- enen-scale & pr Jects en prccessing liquic wastes ::ntamina:ec wita j
4 I6
~
o:ner radionuclices. Inis acrk is concycted by WD cevelcoment grou:s.
After :ne analytical results are octainec, treatment enemicals are accec to the influent tank. An average treatment c:nsists of 7 to 10 cags (100 lb eacn) of calcium enlorice (CaCl ) ano 2 to 4 :ags M lo eacn) of 3
amorpneus car:cn ano socium nycroxice (novN) for pri acjus: ment.
ine treated aaste water is pumpec into a clariflocculator wnere tne major portion of radionuclices are removec by c0 precipitation and aosorption.
Tne precipitate is collected from :ne bottom of the clar1tiocculator as a sludge.
Tne supernatant water overflows tne clariflocculator ano passes I
througn sand filters for removal of any remaining particulates or precipitate.
Tne sand filter effluent water flows tnrougn a cone cnar aaserotion column and a micropolishing filter and is collectea in one of four interconnec:ec 30,000-ga11,on tanks. The water is sampled prior to ciscnarge.
If :ne water does not meet cischarge requirements, it is recycled nrough :ne treatment process, l
The clarificcculator sludge, whicn cor.tains ne racionuclices anc resicual treatment chemicals, is pumped to nolcing tan <s.
For general f
I slucge properties see Appencix S.
The sludge is dewaterec and sa plea 238 for *. solics (range = 25-30s) anc Pu content. After sampling, tne slucge is preparea for cisposal oy solicification.
approximately I
au gallons of sluese is hemogenously mixed witn 2 to 2-1/2 bags of Portlano cement in 17C :ii-gallen crums (with a 90-mil polyetnylene crum liner).
ine 1
1 slucge/ cement mixture (content c:ce c3o) is cureo for 24 nours befvre tne crum is sealed. Inis waste categcry represents approximately 5C% of all Mounc-genera:ec aaste crums.
l 3.1.; Waste Manacement Practices l
Operations anc O&O personnel are rescensible for packaging all aste items.
'nformation snee:s are fillec Out on eacn aaste c:ntainer. ine information incluces the container icentification numser, container c:ntent, fissile centent, etc.
ine c ntainer information sneets are transferrec from c:erations to Nuclear Accountaoiit:y/,aste Managemen for rec:re keeping our:cses and final Ore:aration of the waste centainer for snipping. Tne Nuclear Materials Assurance Grouo' encucts periccic ccm liance aucits of all waste management ;racuces.
le
3.1. t. 1 aaste urums.
All waste crums usec ey Mounc are 17C 55-9allon crums with a 90 mil polyetnyiene crum liner. All 90 mil liners, exceo: for tne sluege/ cement drums (content coce S26), are linec with a plastic (polyetnylene) cag.
Solic waste items are contained in at least two layers of plastic (polyetnylene) cefore placement in a waste container.
Small in-line generated wastes (rags, paper, glass, filters, etc.) are containea in ct.rtons and each carton is coucle containea in plastic cefore placement in a waste drum. Very little polyvinyl enloride (PVC) plastic is useo at Mound.
Mound storec waste drums are lacelled witn ~a unique crum icentifica:icn numoer, aaste cesignator coce, anc year of manuf acture of
- ne crum (example:
12602 C3 74).
The following ciscussion accresses tne Easte cesignator :oces.
1.
Cannea Drum (CD):
This coce represents a crum containing small in-line seneratea wastes containea in 1/2-gallen (metal) or 1-gallon (plastic coated careboard) cartons.
Eacn carton is lacelleo for content, placeo in a polyetnylene cag, anc sealea witn tape.
ine following content coces are used for labelling eacn car:en:
uomousticle Non cmousticle Cen tat.*, Loce 2escriction Centent Coce Oescriction 501 Rags, caper, acco 503 Metal 502 Dry cox gioves, 505 Ascestos <ilters 0-rings 304 Plastic Tygen, etc.
5 10 Glass, flasks, etc.
512 Ion exenange resin 511 Evacorator ano cissolve-sluege 513 Glass filters 514 3racnite c25 nust, ficer sweepings 532 Contam, mercury ine lace 11e: cartons are assayec anc segregate: into :ctous-icle anc ncncamousticle fractions.
Eacn :ar on is taggeo Out of :ne 17
glovesox into a polyetnylene tuce ta; lup to 5 c.rtens per eag);
tne tuce bag is cui., sealed with tace, anc placed in a CD waste crum. The content coce assignec to eacn crum (801, etc.) oy I
Nuclear Accountaollity represents the major portion of cartons in
[
the crum lacellec witn tne same content coce.
For example, a j
arum labelled as content coce 803 will contain a majority of cartons labellac tne same, out otner cartons containing noncomoustible wastes (content coce 805, 310, etc.) will also ev incluced. Several content coces (612, rec) ou not appear in It<EL l
records due to the small numeer of cartens generated in tnese weste categories, bince 1977, all content coce 501 wastes nave been incinerated and tne asn sent to SRP for processing.
ine following information concerning the total numoer of cartons was provicea for tne period of Feorwary 1975 to Feeruary 1980:I Total i
Content Cece Descriotion Cartens i
1 801 Paper, rags, etc.
147 802 Gloves anc 0-rings 136i S03 Metal 1325 504 Plastics 2077 305 Aseestos filters ilus 310 Glass 7eo 311 Evap, anc cissolver sluege al 48 312 Spent ien exenange resin 313 Glass filters h3 S14 Graonite 3
d26 Floor swps/ rust 3*
51 332 Centam. mercury tm 2.
acic/ Caustic (AC) Grums: This coce re; resents ac!cic (centent coce 834) or caustic (content coce 835) licuid wistes aoseroec on Florce, as previously cascricec.
ine crum cesignator cace aas recently enanged to CA, and cescrites caustic aastes only.
Acicic waste crums are no lenger generatec by Mourc, 1
1 l
18 i
\\
3.
Equipment (Eg) Drums:
The EQ designator coce represents urumi containing small equipment items (content coce 525).
ine equipment waste incluces small tanxs, presses, piping, etc.
Tne waste crums contain mostly noncombusticle items. A small percentage of tne crums contain ecmoustiole wastes, une equipment crum snippec in 1976 containec americium sources.
ine sources were placed in a metal can, ane ne can =as placed in the micole of a crum filled witn Florco.
4 Compacted (LD) Drums:
The LD cesignater coce represents crums containing compacted comoustible wastes centaminated with
<100 nC1/g (content cece 347). A large percentage of tne c:moustiole waste is large pieces of polye:nylene plastic usec in D&D coerations. A smaller percentage or :ne waste incluces wet ano cry rags, sheecovers, and ruceer gioves.
ine compaction ratio is approaimately 4: 1.
Florco (5-10 les) is placed in :ne bottom of eacn drum for aoscrption of any tree liquies.
5.
Nonccmpactec (L5) Drums:
The LS cesignator represents crums c:ntaining c:moustible waste (c:ntent coce 547) or ncncomous:iole waste (c:ntent c:ce 548) contamina:ec wi:n <100 nC1/g.
inese crums are not compactec. Florco (5-10 les) is placed in tne cett:m of each crum for acsorptien of any free liquics.
5.
Sludge (SL) Drums: The SL designator is used for :ne sluege/ cement (conten: coce S26) crums.
Tne sluege is procucec ey treatment of all low-level alona c ntaminated liquid wastes.
The slucge is solicifiec witn Portlanc cement, as previously cescrieec.
3.1.c.2 paste 5 exes. 5:ancard and eversi:e te es are usec for cacxaging lar;er waste items.
All cxes are coatec wi:n ficerglass reinforcec pol ester (FTtP).
S:ancarc FAP coxes (4 oy a ey 7 ft) are usec
/
for cacxaving equi: ment (centen: c:ce 524), sucn as vacuu.n :resses, :anas, manicula:crs, fumenoces, etc. ine -aste items are centainec in a leas:
tao layers of plastic.
Stancarc coxes are also useo for pacxaging 19
contaminateo soil (content coce Sc2).
The soil ts packaged in smaller (2 cy 3-1/2 by 3 f t) boxes and sealec, and then four smaller ooxes are l
placed in eacn stanchre box.
iignteen stancare coxes were identified as containing 3:i-gallon crums (up to 5 per oox), see Section 3.1.5.4 The crums ere placea in coxes UO because of nign Pu content or because tne drum or crum liner was rejected by quality assurance. ine content of tnese crams mignt represent any waste category.
f Oversi:e FRP coxes 2re generally used for pac (aging glovecox sec fons or large e:uipment (content coce 324) tna; aill not fit into stancarc
- oxes. Four oifferent si:ec ecxes are usec.
ine cimensions are as folions:
Oversize Box Tyce Wictn Heient Lenetn 5 ft 11-1/2 in.
9 ft 11 ft 4-1/2 in.
111 5 f: 1/2 in.
8 f: 5-1/2 in.
9 ft 1/2 in.
IV 4ft i ft 6 in.
8 ft V
5 ft 1/2 in.
5 f: 2-1/8 in.
S ft 7-1/2 in.
l l
Oca:le neignt gicvecoxes are packaged in Type I or III oxes. T,pe ly coxes are usec to package glovecox sections f rem R Builcing.
5:ancarc si:ec glovecoxes en stancs are packaged in Type V toxes. Glovecoxes are constructec of stainless steel or ficerglass witn plexiglas ninco s, as previously cescricec. ine interior of :ne glovecox is cuatec itn approximately 2-3/4 in, of polyure:nane foam to fix Int contamina:1on.
Eacn glovecox is centainec in two layers of polye:nylene plastic.
Polyure:nane foam is sprayec into :ne corners of each :ox to provice snoring f:r :ne glovesex.
3.1.5 Nun *aciolo:1 cal ma: ares 3.1.5.1 Mercurv.
Sixty-one cartons of con:sminates elemental mercury t
(Hg) nave teen incluce: in wa::e sni? men s.
The mercury is con:Ainec in pias-ic so;;1es (precaoly pint si:e) insice of 1/2-ga11on me:al car;:ns.
It all pin; co :les.ere filleo witn mercury (s;ecifics are unn,ncon), ;nis 1
i-f i
I
.culo represent a maximum of 7.e3 gallons or 864 los of mercury.
ine INc,L l
Transuranic Contaminatec Waste Container Information System (TCWIS) l incicates tnat two S5-gallon cruins of Hg were placeo in storage.
j Information provided by Mound indicates tnat tnese crums, lacelled as i
I content coue ela, actually contain cartons of grapnite waste. A recoro searen cenducted by Mound located the 61 cartons of mercury (centent f
coce 832) in the following crums:
9 Drum levntification Numoer Ho Cartons /Orum Shioment Numoer i
13714 CD 76 2
36 l
13593 1
l 13594 2
13s97 2
j.
13601 3
i 13e03 2
l l
13610 3
13615 1
l I'
13o20 5
i 13637 5
1 l
13579 CD 76 6
29 i
j 13632 1
137c6 1
i 137c6 3
l 13767 2
t 1
13791 CD 76 1
42 l
i 137c4 1
14756 1
l Lievo 1
137c0 CD 76 2
43 l
l I25!!
l 13cco o
i lf i
1360s CD 76 3
46 13631 1
l 13720 3
l 13910 CD 76 1
49 13914 1
i I
13990 CD 76 1
57 4
TOTAL:
iT l
t i
]
Mouno is currently cetermining a metnoo to solicify waste mercury.
i l
scomising soliotftcation metnod is amalgamation witn Icac. A;;roximately l
4 i
i I
i I
i r
I 21 l
i 50 lbs of waste mercury will be precessec after a final solicification
)
metnoc has been determinec. Any mercury contaminates ith <10 nCi/g.ill te disposed of at tne nevaca Tes: Site.
3.1.5.2 Seryllium.
Small amounts of ceryllium (Se) contaminatec wastes have teen snippec to INEL. One to tnree l-gallen cart:ns or' de aste are generatec ey analytical operations each year, ine.eignt of se in eacn carton is estimated to be <0.0b grams.
3.1.5.3 Pressuri:ec Ort ms. An estimated 20 crums of aoscr:ec acicic
.astes (centent coce 834) snippec to INCL (s1975) may ee pressurized, as previously cescricec in Section 3.1.1.4 3.1.5.4 Gas Generatien. Raciolytic pr:cuction of nycrogen gas may occur in certain.aste crums.
Suspect crums.ould ce in-line generatec c:meusticle astes (centent ceces 501, Su2, 404 anc 312) anc
<100 nCi/g com:usticle waste crums (content coce 547 anc 9 8).I
$1nce 1976, all comoustible.aste crums have been requirec to centain <1 g
- N.
I
-w A total of 74 55-gallen : rums :nat exceec tne 1 9 timit of ' 7 u nave ceen sni;;ed to INEL (shipment num:ers 37 and 28).
ine crums.ere l
packagec in 18 stancard size coxes (uo to 5 crums/ box). The crums contain I
cartons of c:moustible anc noncom:usticle (unsegregated) in-line generaten
[
wastes.
Ine crams.ere pac 4 aged before :ne 1 g limi: as estaclisnec in 1v75.
I f
3.1.5.5 I:n Exenange Resins.
Twenty-eign: cartons of s;ent ion exenan;e resins fr:m recovery c:erations have teen sn1;;ec to IML.
ine l
resin is an or;anic-basec polymer ;rcoucec ey Oc. Cnemical Wmpany.
During recovery Operatiens, :ne resins are exposec :o various c:ncentrations of n1tric acid. Nitratec resins may Dec:me nignly flammacie anc/or explesive it :ne resin is alic ec :o cry.
l It is :elievec all resin as:e (content coce 312) inclucec in.Meunc
.aste sni; ents.as.asnec.itn ater :efore pacxaging.
1; is n; cnc n l
l 22
now completely tne resins were cenitratec. As a safety precaution, the following containers were icentified as containing resin waste:
Sniement Numoer Container Icentification Resin Cartons / Container 34 Orum 13eo7 CO 76 9
36 Drum 13562 CD 76 1
Urum 13689 CD 76 1
37 Box 76 4
Box 109 2
35 Sox 113 9
43 Orum 13856 CD 76 1
4v Orum 13965 CO 76
_1, TOTAL:
28 Drum 13667 CD 76 (snipment 34) was mista<enly lacellec as content coce 501. The drum containea only :ne resin waste.
The content cooe snoulc ce cnanged to 512.
3.1.5.6 Asbestos.
As of Feeruary 1980, 1108 cart:ns of ascestos filters (c'entent coce 805) nave oeen incluceo in waste snisments. The fil:ers are usually eacxaged in cartons, and tne cartons are ccuole-c:ntainec in plastic.
In accition, some as:es:cs gloves nave been incluce: in aaste sni;ments.
3.1.5.7 Oceanic Wastes. All organic aastes, sucn as oil removec from etui; ment curing 0&J operaticns anc scintillation vials, are storec at Mounc. Scme of :ne cils are contamina:ec with ;olycnlorina:ec bi;nenyl (PCd). At present, a 1.etnoc for processing tne organic.aste nas not :een ceterminec.
3.1.5.3 C:ner, No <no.n mecnanical or tiological nacarcs exist in Mounc =aste sni;ments.
Any gas cylincers feca D&D opera:*:ns are cepressuri:ec Defere placemen; in.aste cantainers.
l l
l l
1 i
l l
33 I
3.2 Battelle Columous Lacoratories 1
ine dattelle Columous Lacoratories (BCL), a part of tne Battelle Memorial Institute, is a not-for-profit organization tnat concacts contract j
research and development. At present, all transuranic contaminatec wastes snipped to INEL nave been generated by decontamination.and oecommissioning (D&D) of tne SCL Plutonium Lacoratory only. Researcn operations in tne Plutonium Laboratory ceased in late 1977, and D&D operations began in early 1978. The following volumes of waste and numcer of waste containers have been receivec:
Year Volume (m )
Volume (ft )
Drums
$1ns 1973 16.82 558.7 7o 24 1979 81.5o zebu.3 1v80 40.78 1440.2 12 138.lo 4879.2 76 36 Information concerning transuranic wastes shipped to INEL for storage was proviced by:
D. G. Freas, T. R. Emswiler, H. M. Foust, and D. McCarty.
3.2.1 Plutonium Laboratory 1
Researen projects conducted by the Plutonium Lacoratory incluced fuel 9to procuction and special properties meas"rements, f aerication of '~"Pu02 heat scurces, and enemistry/ metallurgy operations supporting the lacoratory.
A majority of projects concucted at tne Plutonium Lacoratory involvec 250 manuf acturing anc testing enricnec 2~^~:U/ ~~Pu fuel pins as part of ne aavanced alternative fuels program for breecer reactors. Tne fuel was processec oy weigning out specific quantities of eacn metallic ruel and melting anc alloying tne fuels. The alicyed fuel was crusneo into small pieces, nyarated, nitratec, and recuceo to the nitrice form (UN, ?uN).
Ine nitrice fuel was pressec into pellets, sized, weigneo, anc loaced into fuel pins. Tne fuel pins were tnen analy:ec for cimensions, nitrice content, etc.
I I
2a
l ine Plutonium Laboratory was also involved in commercial development of pug neat sources for carciac pacemakers ano develcoment of 2
bu0 Purifiec 2 *'8 larger sources for use in tne space program.
ID pressec into pellets and sintered in the presence of 0 for recuction g
of neutron raciation. Tne pellets were encapsulated witn tantalum-tungsten ano riastelley C.
Chemis.try and metallurgical operations servec to support various l
Plutonium Lacoratory projects. Operational support incluced enemical analyses, destructive and noncestructive assay of procucts, and periodic support to tne weapons program (component analyses). A variety of plutonium and uranium isotopes was usec by support operations.
3.2.1.1 Decontamination anc Decomissionine.
Decontamination and deccmissioning of glovecox lines in :ne Plutonium Laceratory began in 1978. All TRU contaminated wastes presently snippec to INEL have oeen generatec by O&D activities only. All racionuclice contaminants snould be in tne oxice form.
Before a D&D operation begins, a nylon-reinforcea polyetnylene (a-mil nicx) plastic tent is constructed around several glovecoxes for contamination control.
Initial u&D operations involve removal of all loose unneecea i:rms (glass, tools, crucibles, etc.-) in :ne gloveboxes. Tnese waste items are baggea out of :ne giovecox into 14-mil
- nick polyvinyl enlorice (PVC) plastic bags.
Sharp cojects, such as glass anc :cols, are placec in 1/2-gallon metal cans anc eagged uut of the glovesox into a PVC bag.
The PVC cag containing :ne waste is cut ano sealed witn tape.
Each PVC bag is then placed in two more PVC bags seacn cay is sealeo witn tape), or is wrappec in two layers of nylon-reinforcea polyetnylene plastic Defore placement in a waste container.
ine estima:ec percentage of plastic usage is 50% polyetnylene ano 20% PVC.
After all unneecea items nave seen removec, :ne interior of :ne glovecox is aasnea tnree times to remove loose contamination. The wasn solution (water anc cetergent) is collectec and processed oy solicification. After :ne glovecox nas cried, :nree coats of polyure:nane paint are aoplied Oc tne in:erior to "fix" remaining contamination.
The glovecox plexiglas wincows are removec, anc tne glovebox is usua:iy cut up 25
into sinali pieces. Tne average estimated weignt of a metal piece is 100 lbs. Several waste bins contain half-sections of glovecoxes. After tne glovebox nas oeen removec, any equipment insice tne glovecox (latnes, furnaces, etc.) is cisassemoled or cut up..if possible. Macnining ana luoricating oil is crainec from all equipment.
Sharp or jaggec eages on waste items are taped. All waste items are smeared for cetermination of fissile content. Large waste items, such as glovebox pieces, parts of latnes, etc., are triple-contained in nylon-reinforcec colyethylene plastic. Eacn waste item is weigned oefore placement in a waste container. The following information concerning OLO wastes is intended to give a general idea of tne waste content:
o Approximately c0 stainless steel glovecoxes o
Plexiglas wincows o
Small equipment, tools, anc materials,- sucn as tongs, copper crucibles, hot plates, glassware, molyucenum ana tantalum foil, etc.
o.
One Leolonce machining latne, disassembled o
une small Soutncena lathe, cisassemoled o
One Western sintering and pelleti:ing cress, partially cisassemoled o
Tao vacuum hign-temperature presses, not disassemolec. Eacn cress was 5 f t nign by 3 f t wide anc contained a 3-f t-ciameter stainless steel tank.
o inree small Carver presses, disassemolec One nycraulic press, disassemolec except for tne stainless steel o
nycraulic cylincer.
ine cylincer neignec cetaeen 500-c00 los.
26
Five vacuum / controlled atmospnere furnaces; several of :ne o
furnaces were not disassemoled o
One arc-melt furnace, otsassemoled o
One centerless grincer o
Nine-inen-diameter sneet metal cucting, cut to 4 ft lengths Filter housings (4 by 4 by 3 ft) and 24 in. square aosolute o
(nEPA) filters Numerous 7-in, diameter by 7-in. tall inline absolute filters o
o Approximately 20 12-volt lantern catteries o
Lead bricks used for snielding o
Copper piping and valves o
Stainless steel piping and valves o
Approximately 30 to 35 steel Maxitrol valves; eacn valve neigneo sl50 los D&D wastes include nylon-reinforced polyetnylene tent str'uctures, o
4 by 4 in, wooo supports, plastic suits, cooties, air nose, ruocer gloves, wrenenes, nammers, saw blaces, etc.
3uture wastes generated oy 060 activities will incluce sancolasting grit, oricks, cir, and sections of sneet metal walls from final D&D effor:s.
3.2.2 aaste Manacement Practices O&D opera icns eersennel are responsicle fur packaging easte items.
Except for content coce 203 (paper, glass, metal), all was:es are 27
~
~
segregatec into noncomoustiole and comousticle frac 1cns. Quali;y assurance and safety procecures do'not allow inclusion of liquia or eneinical aastes in waste centainers. All wastes are triple-contained ~in plastic before placement in waste containers (crums or bins). coaoing travelers are filled out for eacn waste container.
Tne traveler contains information concerning each waste package, sucn as type of w3ste (glass, metal, etc.), incivicual package weignt, and smear count. The travelers are transferred from O&D to Nuclear Materials Accountability anc Nuclear Packaging and Transportation for record Keeping purposes and final preparation of the waste containers for snipment to INEL.
3.2.2.1
'aaste Containers.
All waste crums snippea to INEL are 17C l
55-gallon crums with a 90-mil polyetnylene liner.
Except for a few drums in early waste snipments, polye:nylene cags are not used to line the insice f
j of the 90-mil drum liner.
I a
l l
All waste eins used by SCL are M-III type metal bins.
The bins are usea to centain large pieces of noncemousticle items (glovecox pieces, presses, furnaces, etc.) and ccmousticle wastes generated by D&D ac-ivities. Eacn bin cen;ains a plywood box (1/2-in.
nicx, plywced)
- nat serves as a ein liner. Waste is placec insice tne plywood oox.
Tne box is not removaole.
At present, waste crums have not been packaged in waste eins. A future (FY-81) aaste snipment will incluce four M-III bins containing a total of 32 55-gallon waste cruns (8 crums/cin).
Twenty-two naste crums are 17H waste crums :na: co not meet presen: INEL waste container criteria.
Tne 17H drums contain a mixture of.noncomous:iole anc
)
comoustiole wastes generated by fuel facrication projects.
Scme of :ne crums were packagec five years ago. Tne centents of :nese drums are celievec to incluce paper, rags, plastic, graonite and cocoer crucioles, f oil (aluminum, tantalum, molyocenum, etc.), tools, ana otner wastes associatec witn fuel faorica icn. Ali fissile material snould ce in the oxice form.
It is not believeo any na:arcous wastes were inclucea in :nese crums.
Soecific information on :ne con en: of :nese crums is not availaole. Tne remaining 10 crums will ce :ne'17C type con aining l
C&v aastes.
Inese crums will De usea to fill vuic scaces in :ne oins.
23
3.2.2.2 Content Coce Descriotion.
The following content cooe cescriptions are provicec:
1.
Content code 200 (americium sources):
Based on BCL records, no americium sources have been incluced in waste snipments to INEL.
2.
Content coce 201 (noncomoustible solids):
Noncomoustiole wastes are packaged in crums and eins.
These wastes include tools, crucibles, piping, valves, pieces of equipment (gloveboxes, latnes, furnaces, etc.), leac oricks, plexiglas, etc.
3.
Content code 202 (comoustible solids):
Comoustiole waste items are packageo in crums and bins.
The wastes incluce nylon-reinforced tent structures, wooa, plastic suits, snoe covers, rueber gloves, air nose, etc.
4.
Content code 203 (paper, glass, metal):
Wastes are packaged in crums and eins. Waste containers will contain a mixture of comoustible and noncomoustible wastes.
5.
Content coce 204 (solicified solutions):
Solutions (water and cetergent) from wasning tne interior of glovecoxes were solicifiea in 55-gallon crums. Approximately 30 gallons of liquid waste was placed in a drum; tnen 250 lbs. of patching cement was acced and mixec wi:n a stick. after mixing, :ne cement mixture was allowea to cure for 2 to 3 days. After i
curing, tne stick was cut off ana :ne crum was sealea.
3.2.3 Nonraciolacical Hazarcs i
2 3.2.J.1 Polycr.lorinatec Bionenyls (PCS).
Oils removec frcm various ecuipment pieces (latnes, presses, etc.) curing D&D coerations were assoroec in Oil-Dri in 1-gallon metal cans. Tne oils may oe contamina:eo w1:n PC3s of unknown concentrations. An estimatec 20 metal cans will contain the aosorced oil. The cans were placed in content coce 203 waste i
containers.
j 29
3.2.3.2 Otner.
No mecnanical (gas cylinoers, etc.) or utological nazarcs were incluced in waste snipments to INEL.
3.3 Settis Atomic Pcwer Lacoratory Information concerning wastes generated by :ne Bettis Atomic Power Lacoratory (SAPL) was supplied to EG&b loano, Inc. in Westingnouse Electric Corporation report WAPD-OLO(FO)E-150, July 13, 1981.
ine enaracterization study was conoucteo oy BAPL because permission for EG&G Idano, Inc.
cersonnel to visit dAPL for tne purpose of waste characterization was cenied. The following information was proviced in tne report.
The SAPL, operated for :ne U.S. Department of Energy by Westingnouse Electric Corporation, cesigns and cevelops nuclear reactors for tne Naval Nuclear Pr'opulsion Program anc for central power stations. All researen and develooment. ograms concucted at BAPL are performed under tne cirection of tne 00E Division of Naval Reactors.
BAPL waste snipments to tne INil begain in 1973. The yearly volumes anc numoer of waste containers received were as folicws:
Year Volume (m )
yoju=, ;f 3) 3 urums 1973 23.67 1,189.1 119 1974 92.56 3,279.3 44o 1975 122.40 4,322.5 588 1976 113.1 3,994.1 543 1977 8.745 308.8 42 1978 8.121 286.8 39 1979 11.66 411.8 66 1980 31.65 1.117.7 89 TOTAL 422.15 14,910.1 1922 Transuranic wastes snippec to :ne INEL were generated by -the following f acilities: Fuel Manufacturing Facility (L-Builcing), Excerimentai ?nysics
/acility anc IRX Facility (C-Area), invironmental and Raciocnemistry Analyses (N-3uilcing), and Analytical Chemistry (L-3uilding).
30
1h 4
-e.
.M.-.J.2<
a 3.3.1 Fuel Manuf acturinc f acility (L-Builcing)
The Fuel Manuf acturing Facility manuf actures anc assemoles fuel roos.
processes performed by this facility include mixing fuel powders ano sintering of fuel into pellets, loading fuel into fuel rocs, ano sealing the roos by welding. Materials associated witn manuf acturing operations include UO, Th0,
UO 'IhU all ys, 235U0,
UO, Zr0 '
23 2
2 2
2 2
2 2
Ca0, Carbo Wax 6000 (polyetnylene glycol), zirconium, caroon-steel, stainless steel, etc. Wastes generated by manuf acturing operations incluce contaminated comousticles suen as gloves, plastic, paper, filters, oil asseroed witn "Absorcal" (diatomaceous eartn), Caroo Wax, etc.
Noncomoustiole wastes incluce contaminated metal scrap (carbon and stainless steel), zirconium tuoing, sludge from grincing and polisning coerations, etc. An estimated 85% of waste snippec to tne INEL was generatec ey manufacturing operations.
3.3.2 Excerimenta'l Physics and TRX Facilities (C-Area)
The function of tne Experimental Physics group was to evaluate the nuclear physics characteristics of fuel rocs.
Wastes generated by this i
233 group consisted of UO and Th0 contaminatec comsustiole, (rags, 2
2 gloves, paper, filters, and plastic) and noncomoustible (metal scrap, glassware, cinary scrap pcwder, and fuel rocs anc pellets) wastes.
During 1980, 77 mocifiec 6M 100-gallon crums anc 12 6M 55-gallon crums containing kilorocs (uritical facility fuel rocs) were snippec to ne INEL from ne Tri-Regional Experimental (TRX) Facility. An estimatec 8% of waste snipped to tne INEL was generatec ey tne Experimental Pnysics anc TRX Facilities.
3.3.3 Environmental and Raciocnemistry Analyses !N-Builcing)
Environmental ano Radiccnemistry concuctec isotopic and isotopic cilution analyses of nuclear fuels. Materials associatec.itn analytical operations inclucea fuel samoles, acias, and normal enemical lacoratury ecui: ment.
The type of acics usec in fuel analyses were sulfuric (n 50 ) anc pnospneric (H.P0 ).
Was,tes generatec ey analytical 2 g a 3 coeratiens aere contaminatec with g ~ ~'UO, 2 ~~*UO, c e o l e t ea an o g
2 31
i normal V, ano Tn0. Comoustible wastes inclucea rags, paper, filters, 2
gloves, poly, rubber, etc. NoncomoustiDie wastes incluaed glassware, metal, neutralized enemical solutiens, anc enemical resicues, an estimatea
- 37. of BAPL waste was generatea ey tnese operations.
3.3.4 Analytical Chemistry (L-Building)
The Analytical Chemistry laboratory performed enemical analyses of fuel mixtures for verification of content. Analytical operations incluced dissolution of fuel samples in acid (ri 50, H PO ) as part of tne 2 4 3 4 procecure. Wastes generated oy the operations were similar to wastes 233 cescribec in buesection 3.3.3, and were contaminated with U0 ana 2
Th0. An estimated 4*.' of SAPL, waste was generated by analytical 2
enemistry operations.
3.3.5 Waste Management practices The content code assigned to a waste crum was selectec on the easis of the major type of waste containeo within :ne crum.
Drums can be expecteo to contain limitec amounts of materials otner than :ne assigneo content coae inoicates. For example, a comoustiole waste crum may contaisi noncomoustible wastes. However, crums lacellea as content code a0, solia sinary scrap pcwcer (fuel mixture pcwcer), usually ce not contain wastes frem another content coce.
3.3.5.1 Waste packaging Metnods. Wastes genera:ec by SAPL f acilities aere utaally pacxaged as follows:
1.
Content coce 10 (comoustibles):
Small waste items were wrapped in plastic and placeo into a 3-1/4 inen diameter by 7-inch nign tin plated steel can with a screw-on lid.
This can was :nen placed in a "juice can" and tne juice can top was sealec to tne can witn a roll seam.
l H
Larger aas:e items were wra: ped in plastic and placea into a a-3/8 inen ciameter by eitner 20- or 2c-inenes-nign tin-plated 32 j
j
steel can. After the can was loaced, tne can top was placed on,...
and the entire can was wrapped in plastic before placement in a type 17C or tim waste crum witn etner cans of waste.-
2.
Content code 20 (noncomoressible, noncomoustiole):
$mt.ll and larger waste items that would fit into cans were packaged as described for comoustible wastes. Larger metal wastes tnat woul'd not fit into tne cans were wrapped in plastic before placement into a type 17C waste crum.
3.
Content code 30 (solidified grindino sludge): Grincing sluage, wnich was generated by fuel manufacturing grinding and polisning operations, was cried in a CO.g (caroon dioxide) atmospnere at a temperature of 950*C, coolec, anc pacxaged int'o 3-1/4 inch ciameter by 7-inen hign tin-plated steel cans.
Tne cans were then wrappec in plastic before placement in a waste crum.
4.
Centent coce 40 (solid binary scrao oowcer):
dinary scrap powoer was pacxagea in 3-1/4 inch diameter by 7-incn nign tin-plated steel cans or 4-3/8 inen diameter by eitner 20- or 24-inen-hign tin-plateo steel cans.
The cans were wrapped in plastic cefore placement into type 6M waste drums.
Kilorods (critical f acility fuel rocs) were placed into a plastic-lined 5-inen ciameter pipe installed witnin a type 6M drum with either 55-or 100-gallon capacity.
Polyetnylene anc PVC plastic was usec for packaging aste items. An estimatec 90% of :ne plastic used for packaging was polyetnylene, anu 10%
was PVC. Two layers of plastic were usually used to wrap tne cans containing waste items before placement in a' waste crum.
3.3.5.2 Aoseroed Licuies.
Liquic waste, sucn as oil, water, ano neutralizec enemical solutions, was aosoroeo on "Aosorcal" (ciatomaceous e ar tn ).
xcioic wastes (H 50, H PO ) were neutrali:ec to a pH of 5 g 4 3 4
- o S witn eitner soaium nyoroxice (Na0H) or hycrated lime (Ca0). Acics 33 m
neutralizec with Na0H were mixea witn Absorcal containea in polyetnylene bottles.
Tne cottles were packaged.in metal cans, ano eacn can was wrapped in polyethylene before placement in a waste crum. Acics neutralizec witn nyarated lime were mixed in a metal can to form a neutralizec solic.
The can was sealea anc wrappea in plastic Defore placement in a aaste crum.
I daste oil was mixed with Aescroal and packagea in metal cans before placement in waste drums.
Containers of aoseroea liquid wastes were placed in waste crums labelled as centent coce 10 (ccmoustioles) or content coce 20 t
(noncomoustibles).
3.3.6 Nonraciolo;ical Hazarcs 3.3.6.1 Acies.
All acioic wastes were neutralized and aosoreec prior to snipment to tne INEL ano snoula not represent a hazard. The volume of l
this waste is unknown.
3.3.6.2 Oils.
It is believed any aosorbed oils, sucn as hycraulic oil, grincing oil, etc., inclucec in waste shipments will not centain chlorinatea nycrocaroons, sucn as PCos. Tne volume of cil.inclucec in waste snipments is unknown.
3.3.6.3 Caroo Wax 6000 (polyetnylene Glycol).
Caroo ' wax in tna form of solic powcer or flakes was packagea in metal cans before placement in waste crums. Metal cans containing tnis material were placeo in ccmoustiole (content coce 10) anc ncncemoustiole (content coce 20) waste crums. Tne volume of ma erial incluceo in waste sniements is unknown.
3 3.5.4 0:ner.
It is believec nu mecnanical or oiological aastes i
were incluced in waste snipments to tne INEL.
3.4 Ar;cnne National caooratory-iast Tne Argonne National Laboratory-East ( ANL-E) is coera so by tne University of Chicago and tne Argonne Universities Association ter the U.S.
l 4
i jd
)
Department or Energy.
Ine ANL-E is involved in a oroaa range of programs including funcamental researen in tne pnysical, oiomedical, ano environmental sciencet, and also serves as a major energy research ano aevelopment (nuclear and nonnuclear) centar. Radioactive wastes shipped to INEL frca ANL-i 1.1cluce beta-gamma, intermediate level transuranic, anc low-level transuranic wastes. Cnaracteri:ation of ANL-E generatea wastes was conducted for stored (low-level) transuranic wastes only. Transuranic waste snipments to t<e INEL began in September, 1974 The yearly volumes and numoer of waste containers received were as follows:
3 Year Volume (m )
Volume (ft )
Drums Bins 48 1974 163.1
-5,759.9 3o 1975 118.9 4,198.9 1976 147.2 5,198.4 c0 42 1977 125.7 4,439.1 20 36 1978 107.6 3,799.9 50 30
$4 1979 183.5 e,d80.3 1980 210.1 7,419.7 29 c0 TOTALS:
1,056.1 37,29e.2 149 300 ine following incivicuals proviced information concerning transuranic wastes snipped to tne INEL:
C. L. Cneever, L. F. Coleman, E. R. Taylor, W. M. Kline, J. R. McCreary, C. E. Pietri, C. C. Jierree, R. A. Mason, M. K. Hollanc H. J. Hcward, R. G. Dam, W. H. Livernasn, R. R. Heinrien, and O. R. Senmitt.
3.4.1 Chemical Encineerine Division (duildino 205) t Transuranic contamina.ed wastes generatec ey tne Chemical Engineering Divisien (CEN) originate primarily from decontamination ano cecommissioning i
)
l a.
Volumes incluce wastes placea in storage at tne INdL Intermediate Level Transuranic Storage facility (ILTSF).
35 i
(0&D) of tne plutonium laboratory. Plutonium laboratory operaticas ceasea in 1972 after a nydrogen explosion occurreo in the glovecox line. Tne plutonium lacoratory concucted a variety of researen projects (cnemical purification and processing) using various plutonium compounas, sucn as oxices, caroices, etc.
Small volumes of TRU wastes are also generated oy Building 205 analytical enemistry groups.
J.4.1.1 Decontamination and decomissionino.
Initial v&D of tne plutonium laooratory began :n 1972. At,oresent, cleanup of tne lacoratory is near completion, All 0&D operations are concuctea oy tne xeclamation gruup. uuring init'al U&D of a glovecox line, all unneeded items, such as teols, crucibles, and equipment,.are removed.
The waste items.are caggea cut of tne glovecox into a 20-mil-thick PVC cay, ann tne bag is cielectrically (neati sealed.
Sharp ocjects, sucn as glassaare, are placeu in polyetnylene cattles or tapec before tagging out of the glovecox. heavy aaste items are couole contained in PVC bags. Most of :ne equipmen removed frem tne glovecoxes fits into unlined 17h 55-gallon drums.
Machining and luoricating oil is crained from all equipment.
After all unneeded items have been removed, the interior of tne glovecox is aasnec :nree times to remove loose contamination.
The wasn sole: ion (water and detergent) is collected and aosorbed on sermiculite containec in couole polyetnylene cags.
After tne glovecox nas criec, four to five coats of latex (dater-based) paint are applied to tne interior to fix remaining contaminatien. Tne glovecox aincows (safety glass) anc necorene glovecox gloves are removed, and tne glovecox is reacy for si:e-reduction. Eacn wincow is placea in a polyetnylene bag, anc tnen t o windows are placec insice a PVC cag and dielectrically sealec. x glovecox is recuct:c in size to fi: eitner a full size ply
- cod cox (53 oy aa oy 72 in.) or a nalf size box (53 oy 44 by 36 in.).
Tne coxes, i
.nien are construe:ec witn 3/c-in. plywood, are placea in M-111 aaste j
sins. One full-si:e cox, or two nalf-size coxes will fit into a waste i
cin. Depencing on contamina:icn levels, :ne glovecoxes will be wracped in ene or more layers of polyetnylene plastic. Other wastes generatec Oy D&D activities ere placea insice a glovebox for scace utili:ation.
Segregation of comousticle and noncomoustible wastes began in 1974 The following information concerning D&D *astes gives a general icea of :ne waste content:
30 i
o Approximately 11 caroon steel glovecox lines o
Glovecox safety glass wincows o
Equipment such as scales, not plates, nand presses, etc.
o Glassware o
Crucibles (Be, Th, and graphite) o Four stainless steel sintering furnaces o
Three centrifuges o
One small macnining la:ne o
Copper, aluminum, ano stainless steel piping o
vacuum pumps o
Approximately four small gas cylincers; eacn cylincer was depressurized o
Cinderblock and asphal: floor tile o
O&D wastes include paper, rags (cry and camo), polyetnylene tent s tructures, plastic suits, latex gloves, etc.
3.4.1.2 Analy ical Cnemistry.
Tne analytical enemistry group succor s CEN and c;ner ANL-E projects. Cnemical operations incluce irraciatec anc nenirradiated actinide separations, enemical purification, isotoce icentification (mass spectrometry), anc c:ner racicmetric ceterminations. Tne volume of transuranic centaminatec solia aastes generatec cy analytical enemistry operations is small. Mos or the waste is glassaare (pioettes, ceaxers, etc.) and pacerwipes. Occasionally metal wastes, suen as no: plates, ano spen: ion exenange resins are inciucea.
.l l
37
Tne resins are usually rinsed witn water or a ci'ute mixture of HC1/HF acta before disoosal. Wastes generated in fumenocas are disposed of in unlined 5-gallon paint cans (PC5). Wastes generated by glovecox operatiens are caggee out of tne glovecox into a PVC bag. Tne PVC cag is heat sealed ana placed in a PC5. After a PC5 is filled, tne metal lid is crimpeo on, anu tne can is collected by tne Reclamation group. All liquid wastes, such as mineral acies, enemical wastes, and caustic scruocer solutions, are collected and processed by tne-Reclamation group.
3.4.2 Materials science Division (Suiloing 212)
The Mat'erials Science Division plutonium laooratories are multi-purpose lacoratories cesigned for concucting research witn a variety of special nuclear materfals sucn as plutonium and uranium. Tne laceratories are ecuipped for f acrication (melting, casting, ana macnining), metallograpnic examinations, pnysical and mecnanical procerties measurements, passivatio1, x-ray analysis, and concucting neat treatment anc corresson tests supocrting reactor-relateo projects.
Tne volume of transuranic waste generated by this facility is small.
All fissile material snould be in :ne oxide form. Wastes generated oy tne plutonium facility incluce ;acer wipes, neoprene glovebox gloves, and metal wasto (aluminum, stainless steel, brass, etc.). Wastes are placea in aluminum cans P-in. ciameter ey 8-in. leng:n) and cagged out of ne glovecox into a 20-mil : nick PVC bag. The bag is a1 electrically sealeo ana placed in a 17H is-gallon crum.
Since 1974, pericoic O&D wort nas oeen condue:ec ey tne reclamation group. Tne OLD wastes incluce approximately i
six glovecoxes, sacuum pumps, equipment, paper, rags, anc plast 1.
1 J.a.3 Soecial Materials Division (Suilcing 212)
The Special Materials Division (SPM) is responsiole for managing all special nuclear (Pu, U, in, etc.) materials for Atu.-E.
Responsioilities include receiving, storing, snipping, scrao recovery, incineration of pyropnoric fissile materials, and ac:ountacility.
Recoveraole amounts of fissile material are processec at otner government facilities. Wastes 38
generated by SPM operations incluoe various sizes of metal cans, plastic, glass vials and cottles, paper wipes, anc small pieces of equipment (tools, calances, etc.). Most of tne waste is packaged in aluminum cans, as previously described, and baggec out of the glovecox into a PVC cog.
Tne cag is cielectrically sealea anc placed in a 17H 55-gallon crum. Larger waste items are containec in at least double PVC bags before placement in a waste crum. Sharp or jagged edges are taped. The wastes are not segregated.
3.4.4 Builcino 350 3.4.4.1 New Brunswick Lacoratory. The New Brunswick Laboratory (NBL), operatec ey :ne U.S. Department of Energy, conducts a variety of enemical analyses for DOE and the Nuclear Regulatory Commission (NRC).
Transuranic contaminated wastes are generated by :ne NSL plutonium lacoratories. These laboratories supoort tne U.S. Nuclear Safeguarcs Program, witn some involvement in the nuclear fuel cycle anc weapons programs.
Analytical operations conoucted by tne p uconium lacoratories incluce sample oissolutions, enemical purification oy ion excnange, plutunium and uranium assay, iso pe identification, isotope abundance cetermination, etc.
Solio wastes generated oy analytical operations incluce paper wipes, i
latex gloves, polyetnylene pipettes and bc:tles, small plastic ion excnange columns b5 mL resin / column), glassware, HE?A filters witn steel frames, anc tools.
Snarp oojects, suen as glassware, are packagec in 1/2-gallon metal cans.
Ion exchange resins are washed with cilute HC1/HF acid and packaged in metal cans. All waste items in :ne glovecox lines are contained in two polyethylene cags.
Tne polye:nylene cags are saggee out of tne glovecox into a PVC sleeve bag.
After filling, :ne PVC bag is cielectrically sealed anc placed in a 17H 55-gallon waste crum (uo to is PVC bags / drum). All liquic and enemical aastes are processed oy :ne Reclamation gr:up.
3.a.4.2 Decontamination anc Decommissioninc.
Dec:ntamination ano cecommissioning of :ne ANL Plutonium Faoricatten Facility (PFF) oegan in 39
i l
1974 to provide space for tne NBL. Tne PFF was involved witn f abrication 239 235 of mixed Pu/
0 fuel elements (metallic, oxice, and carsice forms) supoorting ANL reactor researen programs. Fissile material used for fuel i
procuction aio not require enemical purification, j
l Small volumes of waste generated by production operations may have been included in early ANL-E waste shipments to tne INEL.
The wastes woulo j
inctude glass tuces, grapnite and magnesium oxide (Mg0) crucioles, scrap oluminu:n, polyetnylene plastic, paper wipes, neoprene glovecox gloves, and empty tin cans usea for transporting fissile material. Most of :ne waste l
was packagec in small steel cans and sealec (similar to a fruit or vegetaole can). Tne cans were caggec out of tne glovecox into a PVC cag and :ne Dag was cielectrically sealed.
Tne sealed PVC bags aere placed in 1-gallon metal cans, sealec, anc placed in 17H 55-gallon crums.
Larger waste items were couole-cagged in PVC anc placec in waste drums.
Decontamination and decoranissioning operations, wnicn initially began in 1974, are conducted by the Reclamation group. During a D&D operation all unneeced items, sucn as tools, balances, overnead hoists, furnaces, presses, vacuum systems, piping, HEPA filters, etc., are removed from tne glovebox. Wastes are baggec out of tne glovebox into a PVC cag and ne bag is cielectrically sealed. Waste items are generally placed in either full-or nalf-si:e plyaced boxes, and the plywood boxes are placed in M-III Dins. After tne waste items have been removed, the glovebox is wasned anc
- ne interior is paintec (two to :nree coats) to fix remaining contamination, as previously cescriceo. A section of glovecox is cisconnectec anc moved to a 0&D tent for si:e recuction. bloveccxes are reduceo in si:e to fi a ply
- cod oox.
Approximately 8% of tne waste generated by Builcing 250 C&D efforts is placed in nalf-s1:e ;iy coc coxes ano 2 3 in full-si:e boxes. All small and large waste items placec in plyacoc coxes are containec in at least one layer of plastic (PVC or colye:nylene). Machining and luoricating oil is crainee frem pumos ano otner eculpment and aosorcec on vermiculite containec in small me:al cans.
Tne following information concerning D&D wastes was provicec:
40 1
Approximately 400 linear feet of aluminum glovecoxes, 4 ft wiae o
by 6 f t nign o
Plastic glovecox wincows o
Neoprene glovecox gloves o
Three vacuum furnaces, each 30-in. diameter by 36-in..hign One heavy-duty resistance tube furnace, 2 ft diameter by 6 ft o
length o'
Two Stanat rolling mills o
One Hardinge Tool-Makers latne, 5 f t long oy 3 f t nigh o
One 250-ton capacity vertical press o
One 50-ton capacity cutton-oreaking press, 30-in. square by 30-in. hign o
One Heald milling macnine o
One foil snear o
One Cincinnati snear witn 6 ft wice 31 aces o
One call mill o
Two swaging macnines o
One Sutton 600-ton capacity extrusion cress; :ne press may not come to INEL ce:encing on c:ntamination levels o
Numerous vacuum pumos i
41
L o
Copper tuoing ano condui:
i l
iring o
a t
i o
Several small 1-ton capacity hoists and steel rails t
.t l-o Grapnite insulating olocks and crucibles t
L o
Small nandtools and equipment (wrenches, scales, etc.)
l f
i o
Plastic, paper, net and cry rags, etc.
[
3.4.5 Cnemis:rv Division (cuildino 200) j l
l The Cnemistry Division conducts a variety or analytical ana researen
)
6 anc cevelopment programs using small (<mg) quantities or various
(
transuranic 1sotopes.
Projects include 11guia-Ticuid extraction j
experiments, hign pressure enromatograpny, laser isotope separations, laser j
spectral ceterminations, ion excnange resin experiments, and racionuclice fi migration and leacn tests.
1 l
Mos of :ne waste generated oy enemistry operations consists of f
paperwipes, latex gloves, ana glassware.
Otner wastes incluce small j
pl:stic ion exenange columns (10-15 mL resin / column); cried sample preclaitates contaminatec with transuranics in tne form of fluorices, enlorices, and nitrates; and rocx samples frem leacn tests.
len exenange resins (Dow-X series organic polymer) are rinsec witn oxalic acid to remove I
fissile material and ceni: rate :ne resin. Recoveraole amoun:s of fissile j
material are processec ey :ne Soecial Materials Division.
Samole
{
precici:ates are rackaged in 1-quar; polyetnylene bottles. All solia l
wastes are cacsajec in unlinec 3-gallon or 5-gallon paint cans (PC3 or j
/ t.s ). After a can is full, :ne metal lic is crim:ec on, anu :ne cans are pac < aged in 17H :o-gallon waste crums.
Segregation of solio wastes into ccm:usticle and ncncemoustible fractions began in late 1973.
l l
i I
42 l
Acueous licuid wastes are aosorced on vermiculite contained in 1-gallon polye:nylene cattles and allowea to cry.
Until January 1961, organic scintillation liquias were also aosorcea on vermiculite ano alle ed to cry, inis practice ceased Decause of concern that peroxice formation could occur from cecomposition or etner-casec scintillation liquics.
oottles containing aosorced liquias were segregatea trom otner wastes.
Tne sealec bottle was placed in a PC3, ano tnen tne can was filled w1:n vermiculite sealed, and placed in a 17H 55-gallon weste crum (several g
cans /uruin).
It is uelieved any waste crums containing aosarced chemical wastes were so lace 11ec. Currently, all TRU-contaminatec organics are stored a: ANL-E for future processing by incirnestion. All mineral acia wastes and solid enemical wastes are processed by tne Reclamation group.
3.4.6 Waste Manacement Practices 3.4.6.1 Reclamation Grouo. Tne Reclamation group, wnicn recorts to the Waste Operations Manager, is currently responsible for management of all racioactive wastes. Organizational enanges were recently made to ensure compliance witn INEL waste acceptance criteria.
Reclamation responsibilities incluce waste collection, final preparation of waste con ainers for snipment, recorc keeping, D&D activities, and processing enemical ano liquid wastes.
Operations and D&D personnel in eacn waste generating area are j
resconsiole for segregating anc pacxaging was e items.
n'astes are pacnaged in 3 ano 5-gallon paint cans, 17H 55-gallon crums, ano plywooo coxes.
inese aeste containers are placec in M-III bins for snipment to :ne InEL oy tne waste generators or tne declamation group.
because or :ne cliterence in waste packaging, tne M-III cins snoulc ce consicerec as :ne secenc level of containment. Transuranic was es are assayec by segmentec gamma scan oy
- ne Special Materials Division anc tne Heal:n Pnysics Division (U&D wastes only).
Information snee:s are preparea for eacn was e container oy :n=
waste generator.
The snee:s incluce informa: ion concerning radia:icn i
level, fissile content, waste conten (comousticle or noncomousticle),
etc.
Segrega:icn of wastes into c:moustible anc ncncomousticle fractions generally eegan in 197a.
Several sas e-generating areas ce no: se;regate l
ddstch uue tu tne low volume of waste generatec.
The information sneels anc waste c:ntainers are transferreu to the Reclamation group tur processing anc preparation or :ne waste for snipping.
Transuranic contaminated liquid wastes, sucn as mineral acias and spent caustic scruocer solutions, are processec by neutrali:ation and assorption on vermiculite. The liquias are analy:ea for fissile conten and collected in a nolding tank. The liquid waste is mace basic with soaium hycroxide (Na0H) to a pH of 8 to 10.
A 17 gallon aliquot of liquia adSte is then ansurbed on vermiculite contained in a 17C 66-gallon drum
- Ith d 90-mil polyethyldne liner. The first snipment of absorbed 11guio wastes (content coce 102) was sent to INit in 1980.
Empty bottles (glass anc polje:nylene) usea to transpor liquid wastes are filleo at:n vermiculite ana pacxec in 17C 50-gallon waste crums, witn a 90-mil polyetnylene liner, ano the crum is filled witn vermiculite (content coce 106).
Prior to January 1981, other liquid wastes, sucn as aqueous solutions, macnining and pump oils, and e ner crganic wastes (scintillation liquias, etc.) were aosorced on vermiculite contained in various size metal cans ana polye:nylene be::les. Inese wastes ere generally processed oy :ne aaste generating area.
Curren:1y, all licuid wastes are processec ey :ne Reclamation group. Organic wastes, such as scintillation liquics, are storea for future processing oy incineratien.
3.c.6.2.
Was e Descriotion. All wastes generatea oy ANL-E, including NBL, are snipsec to tne INEL in M-11I cirs. Currently, NSL liquid wastes are ceing segregated from ANL-E wastes for future snipment to the Nevaca Tes: Site. The 4aste sins snipoec to :ne INEL contain either nalf-or full-size plywooa coxes or 17H 55-gallen crums anc me:al paint cans (?C5,
?C;).
Tne M-111 ein snoulo be consicered as tne secona level of containment.
Tne following conten coce descriotions aere provicec:
Content coce 100 (General clan waste):
M-III cins con:cin wastes in 17n id-gallen crums anc metal paint cans.
The was:ss are genera:ea cy various ANL-E Ouilcings as previou;1y cescrioec.
degregation of 44
wastes into comousticle anc noncomoustible fractions began in 1974, except for several low-volume generators tnat co not segregate tne waste.
Content coce 101 (Cut-co alovecoxes): Generally, tne M-III c1ns contain nalf-or full-size plywood ooxes.
Tne boxes contain glovecox sections and other equipment generated by D&D activities.
Content code 102 (Aosorcea licuios):
The 17C sb-gallon crums containing absorbed liquias, as previoutly aescrioed, are snippea to inEL in M-111 oins.
The drums are unloaaed at tne Racioactive Waste Management Complex (RWMC), and the sins are returnec to ANL-E.
Content coce 104 (Alona hot-cell wastel:
Alpna not-cell wastes are packagec in 17u SU-gallon crums and snipped to tne INEL in leaa-snielaec casks.
Tne crums are unloaced at the RWMC anc placea in storage at the Intermediate Level Transuranic Storage f acility (ILTSF). The wastes include nonccmbusticle and ccmbustible waste items generated by post-irraciation fuel examinations.
Content coce 105 (Emety oottles):
Emoty glass and polyetnylene cottles used to transport liquid wastes to tne Reclamation group are packagec in 17C 55-gallon crums as previously cescribec.
The crums are snipped to tne IhEL in M-III cins ana unloacea at tne AWMC.
3.4.7 Nonraciological Hazarcs 3.4.7.1 deryllium.
Small amounts of beryllium in tne form of crucioles, roos, etc. nave been snipced to tne INEu.
Inese was as aere removed frem glovecox lines curing D&D operations.
ine volume of ceryllium is unxnonn.
2.4.7.2 Urganic aastes. Organic wastes aoscroed on vermicuitte containec in metal cans anc polyetnylene octtles have oeen inclucec in waste snipments. Tne organic wastes incluce scintillation licuics, alconols, anc macnining and pumo oils.
Informaticn provicea oy ANL-E a5
personnel inoicates tnat some of tne scintillation licuics ccntainec etner. The scintillation liquics aere aoscroea on vermiculite ana allowea tu urj.
ine etners, upon standing, may f or:n peroxiues and avula represent a potential explosion nazard. Tne numoer or vulume of cans or octtles containing assoroed scintillation liquics inclucea in weste snigments is Cnemical bottles containing low-carbon aliphatic (generally unnnown.
butyl) alcunols ere tillea with vermiculite oy D&D personnel.
Tne alcohols wera. usea oy Building 350 for reacting waste souium (Wa) used in fuel pin tacrication.
No unreactea sccium was inclucec in waste snipments to Init.
Macnining, lubricating, anc pump oils ;enerated curing D&D operations aere aoscroec on vermiculite contained in metal cans anc coljetnyiene buttles.
It is unknown it any of :ne oils contained polycnlurinated Disnenyls (PLS).
I 3.4.7.3 Ion Exenance Resins.
Small plastic ion excnange coluums, containing o to 15 mL of organic-easea resin, are usec ey several ANL-t areas for isotuce separation anc recovery experiments.
Tne resins are exposeo to various concentrations of nitric ac1c.
Tne resins are usually i
rinsed witn eitner oxalic acia or a mixture of hcl /hr~ actes cefore i
cisposal.
Informatiun provicec cy anL-E personnel indicates :nat. tne resins rinsed witn oxalic acid snould not represent a na:aro. Vxalic acic denitrates the resin and removes most of the fissile material. Resins rinsec wi:n r;C1/kF may oe in tne nitrate form. Nitrated organic resins, it cry, may represent a flammaoility anc/or exolosion na: ara.
Ine overall volume of ion excnange resins generatec ey ANL-E operations is believea to oe small.
Soecific informaticn is not availaole.
3.4.7.4 0:ner.
No <nown mecnanical or oiologi:al na: arcs were inclucec in ANL-E transuranic waste snioments to tne !Nf L.
J.5 Rocxv Flats Plant Ine <ccxy Flats ? lent (s?/) is coerated of tne xockaell International inergy bystems Scoup for tne U.S. Department of inergy.
ine function of 46
this facility is to faoricate plutonium anc otner components for use in tne Racicactive wastes generateo ey RFP operations originate weapons program.
primarily from founcry operations, component f aorication, plutonium recovery and purificatioil coerations, analytical research and development activities, anc waste treatment facilities.
In accition :o wastes originating from these operations, wastes from tne f aorication f acility fire in May 1969 have been incluced with other kFP storea wastes.
Storage of dip transuranic wastes began in Novemoer, 1970.
The yearly volumes ano numuer of waste containers received were as follows:
A Volume (ft )
gums coxes Year Volume (m ).
1970 1,420.0 50,147.3 J,676 196 1971 7,142.0 252,219.7 19,336 900 1372 5,944.0 209,912.4 17,598 729 Iv73 5,775.u 203,944.1 9,165 1221 1974 3,778.0 123,773.2 6,042 792 1975 2,538.0 89,629.5 4,723 488 1976 647.6 22,370.0 2,34d 16 1977 2,Ia4.0 75,715.a 2,2-0
- db 1 t/ S 662.1 23,382.i 2,584 38 1979 2,605.0 91,995.6 2,369 673 1900 1.778.0 62,790.1 1.9eg a31 Totals 34,44.7 1,21o,379.4 74,c41 6,077 1
Prior to isovemoer 1979, waste coxes were not entereo on tne INEL Weste a.Mane w.ient Information System CaMIS) until tne ocxes aere placeo in their final storage location. Inis is tne reas n for fluctuations in tne nucoer ut ooxes anc volume of waste storec On a yearly Dasis.
4 i
a7
Information concerning racioactive wastes sni; pea to Indu was uctaineu in three visits tu RFP curing FY-00 anc one visit in FY-el.
The visits were extencea over nis time oue to tne complexity of cnaracter1:1ng </9 generated wastes.
Information containea in this report, for storea waste unly, was cotainea curing tne FY-dl visit and f rom fu&u xeport WM-F2-SI-001, Waste Cnaracterization of Rocxy flats Plant daste Sniocea to luano National Encineerine uacoratory 1954-1980, G. K. varnell.
T. L. Clements, Jr., ano R. R. Wrignt, unpuo ishea.
Informatien, sucn as l
fire wastes ano nonradiological nazarcs, ceveloped in tne referencea report is usea, where applicaole, in the stored waste cnaracterization for RFP.
The ubjective is tu compile, in this cocument, information necessary to icentify nonradiological ha: arcs in ali TRU =aste snipped tu the taHC for retrievable storage. ine following incivicuals provicec information concerning wastes curing :ne FY-81 visit to R/P:
J. A. Hayaen, U. dtransfeld, T. E. Soya, R. L. Kocnen, M. d. Killion, R. uiebel,
- 3. E. Grif fin, A. E. Mocges 111, W. deneuerman, H. L. Wells, R. P. DeGrazio, D. L. Saaso, R. G. Leebel, W.' N. James, P. i. Gocesiacois,
/. A. Guerrieri, G. Tuck, K. J. Grossaint, L. DiGia11onarco, i. Sutton,
- d. ncover, anc J. Da11arosa.
3.5.1 Pluconium Queraticns 3.5.1.1 Plutenium Faorication Facilities.
The piutonium faorication f acilities are locatec in Builcings 707 ane 77e/777 (a ecmcinec comclex).
Inese facilities c:ntain founcry, rolling / forming, machining, storage, inspection, noncestructive testing and assemoly o;erations.
Plutonium feea material, in tne form of scrap, but:ons, anc ori uettes, is melted in a tantalum cruciole in a vacuum incuction furnace and poured tnrougn a tantalum funnel in:o a :ca:ea gra: nite molo to form an ingo: of tne requirec snace anc alley content.
Metallurgical c:erations incluce
- asting, rolling, blanking, forming, anc nea: treating :ne ingots.
engine satnes, Jig :orers, anc numerical c:n:rol macnines are useo in macnining coerations. Hycraulic oil is used as macnining ecoiant. Plutonium par:s (c:::enents), tools, g?cvss, anc macnines are cegreasea ni:n car:en tetracnlori:e (CC1 ).
Finisnec plu: nium car:s are further cleanec, 3
o inspo;;ea, ano assemoleo witn c:ner comconents.-
i 4
Two general types of waste ara procuced oy plutonium f acrication facilities:
line-generatec ano nonline-generated wastes. Line-generated wastes consist of any materials exposeo to plutonium in tne glovecox lines. Examples of this type of waste include paperwipes, rags, plastic, ruocer, tantalum crucibles anc funnels, empty small glass vials wrappea 3
with lead tape, lead-lined glovecox gloves, latex glovos, filters (HdPA,
D CWS, Ful-Flo), insulation, grapnite molds, oil filters, aluminum foil, tools (stainless steel and aluminum), gloveboxes, and equipment sucn as furnaces, latnes, drill presses, etc.
Nonline-generated wastes consist of materials :nat are not in tne l
1 i
glovecox line ano are not in contact witn plutonium.
Because tnese t
materials are in a plutonium processing area, tney are ;reatec as transuranic (TRU) waste. Examples of nonline-generatea wastes include office equipment, waste paper, rougning filters on ventilation inlets, electronic equipment, leaa snieloing, lead glass, Benelex snielaing, cincerolocxs, sneetrock, c' tiling panels, electrical cords, structural I
metal, and conduit.
Oeoencing on si:e, wastes are packaged in eitner S$-gallon crums or stancarc si:e (4 cy 4 cy 7 ft) ooxes. Line-generated ano nonline-generatec
.astes in 55-gallon waste crums'are sent to Building 771 for noncestructive assay. Any crums containing fissile material aoove tne econcmic ciscard level are retainea for plutonium recovery. Tne eLonomic discaro level, anien is :ne level at anien it is cetermined to be aconomically acceptacle to discard plutonium, varies cepending on :ne type of waste. Drums containing fissile material celow ciscare levels are sent to Waste donagement (Suilding 776) for final preparation for snipping. Large.aste items (totn line-generatec anc nenline-generatec) are pacxagea ano sent cirectly to Waste Management for assay, wasning, size recuction, anc final preparation for snipping.
a.
nign ifficiency P rticulate Air t
o.
Chemical aarfare Service
- 9
Liquio wastes, sucn as macnining oils and cegreesing solvents, are prucessec at :ne Acueous waste Treatment Facility (w if), su11 ding 774 J.b.l.2 Fire daste. on May 11, 19e9, a fire oc a
tne plutonium production area of bu11cing 776.
fne fire star u u In a can or plutonium enips storea in tne founcry area ano progressea enrougn-:ne conveyor glovtoox lines. A total of 2600 linear feet or glovecoxes, inclucing macnining and f abrication stations, was externally contaminated or camaged oy the fire. Some of the Plexiglas wincows anu Senelex snielcing (2-inen tr.ick, nign-density reawood masonite) on the glovecoxes A total meltec or ourneo, allowing escape of contaminants to the builcing.
of 230,000 f t# of floor space, including areas of Suilding 777, was contaminatea by :ne release.
In accition to gross contamination of tne procuction f acility, tne heat from tne fire warceo seine vertical structural columns and overnead beams. The fire cleanup resultec in removal of all equiement, macninery, gloveboxes, piping, HVAC cucting, wiring, concuit, tools, parts of :ne roof, ano some walls and structural components.
Most of tne fire cleanup operation was concucted by Roczy flats personnel.
The final cleanup operation was concucted oy Swinerton
& Walterg (S&W), tne maintenance contractor fer RFP. Generally, all fire was:es were centained in coucle layers of plastic (polyetnylene ano Pyy, tapea closec, anc placed in waste crums or ooxes.
Waste coxes were usually oy 4 cy 7 ft, al:nougn larger anc smaller ooxes aere useo anen neeceo.
4 Wuoden snuring and cracing were used to support heavy items in approximately 10". of :ne waste ooxes.
Large quantities of aosorcent t:racename Oil-Ori) were placed in glovecoxes anc en macnines to aosoro free licuies.
ine total volume of fire cleanuo aaste snippec :o :ne INEu aos 3
approximately 200,000 ft. An unknown volume of tnis waste was placed in st: rage at :ne RAMO sy direct sni; ment from AFP anc fr:m :ne IML Initial Drum Retrieval (ICR) project. Tne following information concerning :ne eculpment anc materiais removec curing cleanuo c;eratiens gives a general icea of :ne aaste content anc waste packaging me nod, as remescerec Of acr(ers involvec witn cleanuo Operations.
20
t
'ouncry Area Sixteen steel vacuum incuction furnaces, 6 ft ciameter ey 2 ft o
oeep eacn.
Tne furnaces were cut in nalf for a total of 32 pieces and put in 4 by 4 by 7 ft woocen aaste coxes for aisposal.
Eignt vacuum pumps, neavy cast iron wich motor, pu11ey3, anc oil o
were packed in boxes.
Eacn pump had an exterior glovebox wnicn was cut up ano placea in 4 by 4 by 7 ft boxes.
une Marform press, 60 f t hign by 10 by 10 f t on tne case, with a o
3-ft ciameter nycraulic cylinder.
Tne press was constructec or cast iron ano steel anc we1gned nuncrecs of tens. uil was craines from tne unit.
Tne press was cut up ano put in 4 of 4 1
wy 7 ft boxes..
l One Hydroform press 4 by 4 by 10 ft nign, plus pcwer pac. Cut I
2 o
up and placed in 4 by 4 by 7 ft boxes j
l j
u One nPM press, 4 cy 4 cy 20 ft hign. Cut up and placea in 4 cy 4 cy 7 ft boxes One 4-nign rolling mill, 8 by 8 cy 10 f t hign with two lu-in. and l
i o
two 30-in. ciameter narcened steel rolls, eacn 54-in. long.
The macnine nac a large separate drive (gearoox and motor) unit.
Tne rollers were tne heaviest single components ano ere recucea in j
si:e to meet tne 5000 le/:ox limit. Tne rollers were exceecingly i
i I
nard anc tcok several cays to cut tnrougn.
Many saw claues nere i
consumec curing eacn wor <ing snift.
i o
One 2-n1gn rolling mill, 5 oy 2 of e ft nign ni n two narcenec steel rolls 2 -in ciameter, 3 ft long.
Tne rolling mill may not l
nave seen cut up Out was partially oisassemolec.
6ne mill as partially containec in a glovecox. Tne glovecox was inciuceo in tne neste.
i I
f i
j 51
p-4 une inear, 6 by 6 Dy b f t high, not cut up One circle snear, a cy 7 oy b ft hign in glovecox, not cu-_up v
o Too small vacuum inouc. tion turnscet in giovecoxes. dacu glovecox was 3 oy 3 by 6 f t.
l-0 Neutron shields constructea of 2-inen tinick ownelex.
Tne snielcs were in tne form of a fence (approximately 30 cy 40~ of a f t nign) j ano surrounaec casting furnaces.
Tne snieles were cismantled ano placea in waste boxes curing early cleanup operations.
i Macninino Area A large numoer of glovecoxes cont e ning machining ecuipment anc o
tools were cisconnected from tne main conveyor glovecox line and boxec anole for shipment.
The dimensions of the waste boxes vartec, cepencing on the size anc weignt of the glovecox and associateo equipment. All visible plutonium was removec from eksily accessiole locations on :ne macnines, no.ever, since tne macnines aere not cismantlec, tnere were niccen poc<ets of plutonium enips in seme macnines, possioly kilogram quantities.
ine general opinion of RFP personnel was tnat no pieces of plutonium larger nan macnining enios or lathe turnings woule ce founc.
It was believec all plutonium snoulc ce in :ne oxice form. However, it is possible that small amounts of unoxict:ec I
(metallic) plutonium or plutonium sucoxices may be founo trappeu in :ne macntne cooling oil, sucn as in :ne vacuum pots connectec j
to each machining station.
l o
T.enty Monaren engine lathes, 5-ft nign neacstock, 15-in,swind, 7-it latne cec, ana 10-f t overall lengtn. All tools, Jigs, enucks, fixtures, motors, coolant pumps, and exterier glovecoxes 52
were incluceo in the waste.
facn glovebox was approximately a by 14 cy 8 ft nign. During initial cleanup operations, waste boxes were constructeo arouno the latnes ano exterior glovecoxes. During later cleanup operations, tne latnes ano glovecoxes were recuceo in size to fit 4 by 4 oy 7 waste coxes.
Eacn 14tne weigheo approximately 4.25 tons. Generally, luericating oil was not draineo from tne latne gearboxes. Tnere may be 4 to 8 gallons of oil in each machine. Large quantities of Oil-Dri were placed in the glovecoxes ano on the machines to rosoro free liquics.
Four racius generators, 6 by 3 by 5 f t dign, inclucing exterior o
glovecox.
Two generators were cut up to fit 4 of 4 cy 7 *t ooxes, o
One Jig borer, 3 oy 4 oy 7 f: nign, plus etterior glovecox
'l o
One two-spinele automatic la ne, 7 cy 4 cy 5 f: nign, plus exterior glovebox One four-spincle autcmatic lathe, 8 oy 5 oy 7 ft nign, plus o
exterior glovccox, dismantleo oefore snipping i
T o Excello : ace macnines, 6 by 5 oy 7 ft nign, plus ex erior 1
o glovecoxes, not Cut up I
o One dricgepor mill with 7 oy 6 by 7 ft nign glovecox, cut up to i
fit waste oox l
h o
Two 16-in. optical ceccarators, 3 oy 3 oy 4 ft, witn e,xterior glovecoxes o
One coucle-spincie benen crill press, 2 cy 2 oy a f: h1gn, witn j
exterior giovat.
~ut u7 to fi: waste box l
4
une lapping macnine, 4 by 4 cy 3 ft nign, *in exterior glovecox o
o Eacn of tne 3 Dove macnines (macnining area only) was equippec with a vacuum pot and pump unit, dacn unit was 2 cy 3 by 2 ft hign and was separate frem :ne glovecox.
Tne vacuum puts contained a mixture of hignly contaminated macnining oil, caroon tetracnlorice, ano slucge generatea by eacn ucctiining station.
These units were not crainec esfore shipment tu tne InEL.
A prox'mately 300 linear feet of elevatea (on legs) conveyor line o
glovecoxes, approximately 4 ft nign by 3 ft wice III' o
Eacn macnining station was equippec with a CO2 extinguisner. The fire extinguisners aere incluced in wastes sent to the INEL.
It is celieved all extinguisners were c(pressurited orier to sniement; nc-ever, tnis cannot be c nfirmec.
o One 25-ton bridge crane, 20-f t span, plus rails o
Several 24-anc 14-in. aice riange beams, recucec in size o
Numerous electric motors and pumps o
Large quantities of sneetrock ano en1pcoarc Large quantities of lignt gauge cuct ork, smasnec anc placea in o
a oy a by 7 f t waste boxes o
Approximately 10 coxes of Senecule 120 nycraulic oicing, 3-inen ciameter u
Two large arc eleers 54
~
five 2 oy 4 cy 7 ft uoxes of ccncrete witn :/8-in, recar, o
concrete cut to 1 ft tnick pieces o
Most of tne outicing root, 240 oy 520 f t witn 1/e-in. outyl sneet cover and 4-to 5-in. thick fiberglass insulation. A total of 40 to 50 coxes were snipped.
o Dirt and asphalt.
o Transite (asbestos-cement) wall and steel supports. Aporoximately 12 boxes were snipped ouring 1972.
anole tool boxes, instruments, gauges, micrometers, jigs, crills, o
wrenenes, etc.
Packagec in 4 by 4 oy 7 ft waste boxes.
fire Cleanuo aastes i
The fire cleanup operation required tne use of size-recuction equipment to perform cutting ano equipment removal operations.
Ine tools, ecuiement, anc materials used in :nese operations cecame part of tne waste uio are listeo :elow.
o One 54-in. ciameter Trennieger saw; assumec to have oern cut up at end of cleanup cperatiens j
o Six Fein nanc-neld reciprocating saws o
nuncrecs of saw claces o
Movie anc still :ameras i
j o
Two power-lift scaffolcs i
j l
i a
.,...l
o Thousands of sets of anticentamination clotning o
Large cuantities ("acres") of polyetnylene snee: plastic 1
o One 4000-lb capacity for< lift wi:n catteries; it is not (nown wne:ner tne forklif aas recuced in si:e before snipping.
3.5.1.3 Plutonium Analytical Laboratory.
Tne Piutonium Analytical Lacoratory (Suilding 559) concucts enemical analysa.s suppor:1ng various RFP tr.insuran1c operations (tabrication, recovery, was:e treatment, e:c.).
Analjtical capacili:1es incluce measuring clutonium content, impurities, ano alloys in metals, liquics, and exices, anc performing analyses of gases and liquias laqueous anc non-aqueous) by mass spectometry, gas l
cnrematograpny, infrarec spectroscopy, anc :nermal tecnniques.
l l
Solid wastes generated by laboratory operations include paperwipes, I
rags, plastic, ruceer gloves, ion excnange resins, glassware, metal waste
(:cols, files, etc.), anc ceramic (Leco) crucibles. Depending on :ne lacera:Ory area, line-generated waste items are either single-containec in j
a large PVC cag or couole-contained in a polyethylene and PVC bag befcre placement in aaste crums.
Snarp ocjects sucn as glassaare are taceo or placea in polyethylene cottles.
Ion excnange resins are eitner processed of Plu:cnium Recovery (Builcing 771) or currec in :ne laborstory. All
\\
waste drums are sent to Builcing 771 for noncestructive assay.
'J rums containing fissile ma:erial acove :ne ciscarc-level are retainec for plu:enium recovery.
Selvw-ciscarc-level crums are sent to Waste Managemenc l
(duilcing 77c) fue inspection anc final preparation f or snipment..
l De;encing on plutenium content, all licuic aastes are processea :nrougn l
ei:ner :ne Pia:cnium Recovery Facill:y guilcing 7/1) or :ne acueous aaste 1
1 Treatmen: Facility (AWTF), Builcing 774 l
1 1
3.5.1.4 Cnemical anc hetalluccical Researen an: Deveicoment.
A veriety of researen and cevelopment programs in :ne enemical anc metallurgical fielcs are c:ncuctec in duilcing 779.
nase programs inciuce
~
1 I
se
evaluation of fiele return units, cetermining processes for recovering anc purifyi..g transuranic element: from waste streams, imoroving processes for recovering and purifying plutonium ey enemical, pyrocnemical, anu nyoricing tecnniques, beryllium machining researen, prouuct integrity surveillance.
anu r..etallurgical (metallograpny, x-ray cefraction, etc.) examinations.
Solid wastes generated by Building 779 operations nave inclucea paperwipes, rags, plastic, glassware, lead-lined glovecox gloves, latex gloves,miscellaneouslaooratoryequipment(ringstands, tools,etc.),
1-gallon metal containers of nalice salt mixtures, sucn as LaCl '
2 Incl, kcl, NaC1, and MgC1, from pyrocnemical (cirect oxice recuction, 2
2 pyrorecox, electrorefining, salt cleanup, ctc.) recovery researen, tantalum crucioles and stirring rocs, hign-density magnesium oxice crucibles, sancoaper, anc small amounts of ceryllium contaminated aastes. Generally, all waste items are couole-contained in plastic (polyetnylene anc PVC) ana segregated oy content coce before placement in waste crums.
14cnline-generateu comoustible wastes (laceratory trasn, etc.) are compac ea in aaste crums. All waste crums are sent to Building 771 for noncestructive assay. Any crums containing fissile materihl acove tne ciscard level are retainec for plutonium recovery.
- ielow-ciscarc-level liquic aastes are processec at tne An'if.
Acove-ciscarc-level liquia aastes are processed by plutonium recovery.
- n bril 1973, an inacverten; tritium (3 ) release occurrec in a ri gle ecox line located in :ne Plutonium Hy: ricing Lacoratory. The cleanup jperationgenera:ecaccroximately15to20crumsofnignlycentamina:ec
~h aastes.
Ine was:es incluce vacuum pumes, plastic, paperwipes, tools, noses, cocoer tuoing, ano small me:al con:ainers of acueous solutions solicifiec in Por:lanc cement.
It is believec all aastes were at least triple-containec in polyetnylene or PVC plastic cefore ciacment in :ne aaste crums. All crums aere lacellec as containing #H.
l 57
i 3.5.1.5 General Lacoratory.
The General Lacoratory in butic.ing u l conouc;s a variety of trace contamination analyses supporting RU l
cperations.
Small volumes of wastes contaminateo itn lon-level transuranic isotopes are generated by tnese operations. Wastes include
(
papffrwloes', process paper Idtex gloves, plastics, glassware, small f
iun-exchange columns, stainless steel planenets, soil and evaporator salt semples, and lauvratory equipment such as not plates, etc. All waste items i
l are contained in a polyethylene bag before packaging in a waste container.
Comoustiole wastes are packaged in waste crums ano sent to Waste Management f
anere the crum contents are emptied into a 4 by 4 by 7 ft waste eux, Noncomoustiole waste items are packaged in 4 by 4 cy 7 ft waste ooxes and sent to Waste Management for inspection anc final preparation for snipment l
to tne INdL.
{
f r
o.a.1.o Criticality Researen.
Small volumes of waste are genera:eo f
oy the critical mass laevratory in Building 88b. Criticality stuotes nave 2M 235 ceen concucted with metallic Pu ano low-and nign-enrieneo g
compounds. Wastes generated by criticality stucies incluced paperwipes, rags, latex gloves, experiment handling tools, jigs, and fixtures. Wastes are packaged in crums and occassionally, boxes. Waste crums are sent to Builcing 771 for noncestructive assay. Drums containing >10 nCi/g i
fissile material are sent to Waste Management wnere tne wastes are removeo l
from tne crum and repackaged in 4 by 4 by 7 f t waste coxes for shipme!)t to
- ne INEL.
3.5.l.7 Process Chemistry anc Encineerine Researen anu Deveicoment.
}
Tne Process Cnemistry inc Engineering is&D Division conoucts special-orcer l
acr< anc component faerication supporting weapon tests programs..astes genera:ec ty tnese orograms are contaminateo with a variety of special 231d, 237,p, 2al.nn, 2 2Pu, ano un, Wastes 264..
{
isotopes inclucing a
contamina:ec with special isotopes are not processeo ey plutonium recovery f
cperations. These wastes are not segregated cue to :ne Ica volume of waste
[
genera:eo oy A&D efforts.
l l
e 68
O 3.S.I.8 solten Salt Extraction.
The molten salt extraction process 24I (Builaing 776) separates americium (primarily Am) from plutonium metal. A halide salt mixture (Nacl, kcl, and MgCl ) is usec to extract 2
americium trum molten plutonium, ine salt residue is processeu for recovery of americium anc plutonium.
Small amounts of celow-ciscarc-level salt resicue have been shipped to INEL. The salt resicue is packagec in 55-gallon waste crums.
3.o.2 Plutonium Recovery Facility The Plu 9nium Recovery Facility (Suilding 771) receives and processes plutonium-contaminatec residues from various RFP operations and some resicue from other Department of Energy f acilities. Tne majority of RFP resicues processed in this facility originates from plutonium foundry and 1
macnining operations (Suildings 707 and 776/777).
Tne purpose of :ne recovery facility is to extract plutonium from tne resicue material so enat j
tne final waste procuct will contain plutonium at or below tne economic l
uiscaro level and to procuce aeapon and researen-grace plutenium metal.
i Plutonium-contamina:ec solic resicues (crums only) generatec by l
varicus A/P operations are sent to cuilcing 771 for nenuestructive assay l
for cetermination of fissile content.
If tne waste contains fissile j
material celow tne economic ciscaro level, the aste is sent to aaste Management (Suilcing 775) for inspection, repacksging if necessary, and final preparation of :ne wasta for shipment to the INEL.
Drums of residue containing fissile material acove the economic ciscarc level are retainec a: Suilcing 771 for processing. Any RFP-generatee liquic.astes containing acove-ciscarc-level amounts of plutonium are also processed.' Recovery operations are civiceo into two separate processes:
special recovery anc procuction recovery operations.
j 3.5.2.1 Soecial Recove*y Ocerations.
Special recovery coerations I
process plutonium resicues :nat can not be processed oy procuction i
recovery.These resicues are contaminatec with uranium or otner l
4 69
_m.,
l racienuclices wnien would interfere witn produe:1on plutuntum recovery l
processes. A tributyi pnosphate (ISP) solvent extraction process is usec to remove the racionuclice contaminants. Waste resicue generatec cy special recovery operations includes paperwipes, rags, plastics, HEPa l
filters, polypropylene filters, glassware, metal waste sucn as stainless steel, aluminum, etc., lead-lined glovebox gloves, iun exchange resins, and f
I equipment (notplates, furnaces, etc.). Most of tne resicue is tnen processed by production recovery operations. Large waste items are sent to
/aste Management (5uilcing 776) for wasning ano size reduction.
3.0.2.2 Production Recovery Doerations.
Production recovery operations are civicea into two categories called "slow" ano "fast" recovery. Slow recovery operations process residues containing hign and low concentrations of plutonium out require extensive precessing anc ourification to octain a suitaole plutonium nitrate solution. Fast recovery operations process plutonium residues that are relatively pure anu recuire a minimum of processing to produce a plutonium nitrate solution.
i Pure plutonium metal is extracted from fast ano slow nitrate solutions oy furtner processing.2 i
Procuction recovery operations currently process 81 cifferent categories of plutonium-contaminated materials. Inese materials incluce l
paper, rags, plastic, ruocer, glass, grapnite molds, tantalum crucioles l
anc funnels, metal, filters, insula:icn, molten salt anc electrorefining residues, spent ion-exenange resins, impure plutonium, anc laceratory solutions. Examples of slew recovery tecnnicues incluce incineratien of cumousticle wastes, scracing or grinding graonite anc tantalum weste to remove acnerec plutonium, dissolu icn of various resicues (incinerated asn,
)
grincings, filter media, etc.) wi n nitric acid to remove tne slutonium, j
anu lon-exenange procacures to purify plutonium nitre:e solutions.
Durifiec plutonium nitrate solutions from slow anc fas recovery operations are concentratec anc precipita:ec to form plutenium peroxice. Plu;cnium peroxice is calcinec to plutonium oxice anc nyorofluorinatec to form plutonium ta:rafluorice.
Plutonium tetrafluorice is reducec witn calcium
b u
to plutonium metal.
Solid wastes generatec by recovery operations are reassayec to ensure tne waste meets plutonium ciscarc requirements. Any j
wastes rat meetirg discara requirements are reprocessed. Wastes sucn as
[
inciner ator ash neela, grapnite heel, insulatien neel, anc filter slucge are packaged in 1-gallon polyetnylene oc::les. Glass, grapnite molcs, etc.
dre packageo in 2-or 5-gallon size fioerpaks (caraboard cartons).
Some j
i wastes are wet or camp wnen packagec. Waste pacxages are oaggeo out of Wastes are glovecox lines into a PVC bag before placement in a waste drum.
segregated into specific content coces.
Liquia effluents frem recovery operations are analyzed to determine fissile content. ecove-ciscarc-level f
l
[
effluents are reprocessec.
Below-ciscaro-level effluents are sent to tne Aqueous waste Treatment Facility for processing.
J r
present plutonium recovery operations will be transferreo in tne j
future to tne new plutonium facility (5uilding 371) currently uncer l
c construe:icn.
3.5.3 Acueous Waste Treatme,nt Facility i
ine Acueous Waste Treatment Facility (AhTF), Builcing 77c, treats all j
liquic process aastes from :ne Plutenium Recovery Facility (Suiletng 771) l j
and all other plant liquid aastes tna: co not meet RFP cnsite impouncment t
)
requirements. Tne following information concerning treatec aastes was j
i provicec.
I 3.5.3.1 First Stace Slud:e (Conten: Coce 1).
First stage slucge i
(prefix 741) is generatec ey processing licuic wastes, suen as ion-excnange 4
column effluent, ;istilla:es, caustic scruo solutions, etc., from plutonium recovery operations in Builcing 771. Ine liquic wastes are mace easic and comoinec, and tne racioactive elements, sucn as plutonium anc americium,
{
are enemically precipitatec frcm the licuic waste.
Trea: men: cnemicals j
usec are ferric sulfate, calcium enlorice, magnesium sulfate, ano l
2 i
i 4.
neel is :ne remaining waste resicue after :ne leacning ;:rocess.
l 3
i l
il
.T.
cua9aluting agents. Tne resulting precipitate, or sluc3e, is filterec anc packaged in 55-gallon was:e crums.
See Figure i for sluage pacxaging metnocs. First stage slucge crums nave periccically seen leac-1inec, anen necessary, to reduce radiation levels to or Delew the 200mA/n limit.
Increasec raciation levels are usually associated witn nign americium concentrations in the sludge. Prior to 1972, fully leac-linec crums (top, tottom, anc sides) were usec. A leac-lined crum aould centain 1/lo-inen
- nick lead sheeting. After use of :ne 90-mil polyethylene drum liner Degan in 19/'4, leac sheeting could not be used and was replaced with approximately 5-mil thick lead tape. After a drum is fillec witn sludge anc tne 90-mil drum liner is sealed, :ne crum is invertec and pullec off of
- ne liner. The liner is wrapped with lead tape and :ne crum is :nen placed oac< over :ne liner.
3.5.3.2 Seconc Stace 51ucce (Content Coce 21 Second stage sluege (prefix 742) is procuceo from treatment of all c:ner plan: liquic astes l
recuiring treatment anc furtner treatment of :ne first stage effluent.
Tne 1
sec:na stage treatment peccess uses ne same enemiculs usec in :ne first 1
stage treatment. dee Figure 2 for sluoge packaging me:nocs.
5eccnc stage sluege urums pacxaged oefore 1973 may contain otner waste items suen as electric m ::rs, glass or polye:hylene oc::les of enemical (usually liquic) wastes, mercury and litnium eatteries, and small amounts of c:ntaminatec mercury in pin bottles.
S pecifie. information concerning
- ne type or volume of enemical aastes incluceo in seconc stage sluege crums l
1s not availa:le. P.acicactive sources have also teen periccically inclucec l
in sec:nc stage slucge crums nreugn 1979.
3.5.2.3 Sm:inec Slu:;es (Content C:ce 1).
Since :ne fall of iv79,
- ne first anc sec:nc stage slucges nave :een comoinec to recuce :ne l
caciation levels associa:ec *1:n firs stage slucge.
Tne sluege mix ure (prefix 7t.12) is snippeo to :ne N L as c:ntent coce i siucge.
See l
Figure 3 ter slucge pacxaging me:noc.
Tne as:er ccntent ci slu ge aste (c:ntent coce 1 anc c) ranges frem
- 0 to 70% Oy weign. The slueges ::ntain a variety of resicual :nemicals l
i O t.
l
1970 1972:
C d
J'.b},* ;. _ _
.--- 5 lb cement h',.* *..,*,I,'..
,' l, l l. n
'*w..
'1
)
~ - Crum
- Dlastic Cag
!,1 Sludge.
A i /
==
- 0. ring tag
/
'/
,/ /
i I
e
> u.s.:i., ::.e::. s..u. n:.;%-we Pen,ena e.nnt
.n.
,Q_.x :.. m., y t
- 3 s te. Pwlana r.;';i..;*.'.':[.'l.N. _.4.. W f f. w
- .m JamenLIaYet NCte: Rutter Surgical SICves were ;erioclut'ly,; Jeef..h trie DCtten cf t!16 crum tefore fillinq with Stuc;e.
1 W72 1979: In 1972. use of tne 90 mil pojtthy.ene t', rem : leer te;tn.
I
/t _ _
W A) LM of so.mit acty liner G-cii.on I
3 5 te. Portlane cement-
- i..y,
.\\p-so.~,a :ety uner f'~
/'
- p,33,i, 3 3,
/
[
~
- '.-o.nn; tag
\\
Slucce y i 1
1 1
//
f.' fff...9,7.~.:. I..,?.][i :.R; '
l
.g.;b. Porttanc :.eneU 3
~-
w}:-
....* 2 *.4]y-3 5 te. Pentano
.f e
3 cur,in'nayer INE' 4 te '63 i
Figure 1.
First stage slucce pacxaging me:r.ccs.
i 53
.,., J.. a ;
y
1970 1972:
P L
J 4.'*. %-.
...:...9-Dru m -
.' Y.
. i
.i..*
3 5 lb. Portlanc cement
... a. *... i. :. -l '
.?.... :
{
l Siucge
.:::..:. ;.a..;7.*.:.' :..* :'?, );i. * 'TU-
"'" * *=
l..n.:.:..:....Slucge.... :.,...:.... ::
i Siuege l
- .
- ...cs.:.;:.;.l...'-l~;s:...?.q i
c t
Slucge i
':::.-l4.:". ;;.. a..l *:.~:.' '. i ? ' '
i Stucge i
t
.ny..............:
Stucge
- ..... _... s. )
3 5 lb. Portlanc l
y.... ;,....
w :,. '
cement / layer
..,5f
,,,i......;.
j
(.'; e.....*: ;..:...........
3 t
t 1972 1979: In 1972. use of the 90 mil polyethylene drum liner began.
l P
/
\\
Oil.On -
N
")ru m 90 mil poly liner j
3 5 te Fertlanc :ement
...../....
A-'i
- ;.i :%::;.. :.l.!.v.~ i: -.
-Pfastic tag i
\\
'... :. e ;. Sludge
- r. *n. ?;...s e r i st; l
Slucge 1
.. * ::. ; ??:. :.......... t ;...
Stucge i
...,... u. :.... '... s': :.....
i
?
Stucge Slucge s
1
- .. * ?; *; : *.'." *:.....;.
,t M
3 5 !b. Portlanc
- .G.h,, h %^ _"
- , + '.
cement!!ayer
[
(-
_J i
j Nois. Siucre cNrMS :ac%3;ec cnct to 1973 may 00ntain othcr wastes such as Oattenes, i:c.ttts of vttad:.it westas, etc. Racloactive sources h:'e atso teen clacec in stucce
[
j uums tur:ngn 1919.
mt' us tu l
I i
1 i
-19 w e e.,
Seconc stage sludge pac <agine methoes, i
4 i
6*.
I a
1979 Present: Since 1979, the first stage and second stage stucces have'been combined, b
\\
/
Dru m Oil Dri -
4N\\
3 510. Pertland cement _
,, $ ' ^
-90 mil poly liner f
- Plastic bag 0 nng bag Stuc;e
/
/
1
/..../..//
301e. Per. land cement
~. -
....., '?.... V ** '. ' *. ; :, :
. ;,'j;.
, h'
- f*..
-3 5 lb. Portland
(
h :;.y.*:::W [J cemen11layer INEL A 19 246 Figure 3.
Cem:inec siuege cackaging methed.
from licuic wastes generatea oy tne processing plant.
Analytical reporss concerning slucge properties were proviced oy R/P anc are incluceo in Appenuix C.
a.c.3.4 Solicifiec Oceanics (Content Coce 3).
Solicified organics (prefix 743) are procucea frem treatment of liquic organic aastes generatec ey various plutonium and non-plutonium operations. Organic wastes sucn as aegressing agents, lathe coolant (machining oil and caroon tetracnlorice),
and hyuraulic oils are generated primarily by plutonium faorication operations. Organic aastes incluce trienloroetnane; caroon tetracnlorice; trieniorce:nylene; tetracnloroethylene; hydraulic, gearoox, ano spincle oils; and trace concentratiens of miscellaneous organic (organopnespha es, nitrecen:ene, etc.) laboratory wastes.
In accition, unknown volumes of oil containing polycnlarinated~cionenyls (PCB) were processee ni:n otner organic wastes until 1979. Oegreasing solvents genera:ec of Suilcing cae c;erations are contaminated with ceryllium.
Licuid organic westes are collected by pipeltne for processing in a c:mmon t ank or are receivec in catcn quantities centainec in cottles or crums. ine liquics are processeo my blending appecximately 3v gallons of Organic wastes aitn 100 lbs. of calcium silicate (Junns-Manville procuct Microcel i) in a continuous mixer to form a solid-li<e paste or "grease".
See figure 4 ter.aste pacnaging metnoas.
Tne follo.ing information concerning major organic liquies anc quantities processeo eacn mon:n was J
provicec ey RFP:
Urcanic Licuic Gallens/Mentn
% of Total Latne ::alant--50% Texaco 700 47 Regal oil, 20% caroen te:racnlorice Trichlor:e:nane 150 10 i
Miscellanecus--nveraulic oil, : ear:cx 550 43 oli, spincie oil", freon,'iarsol, etc.
Total 1500 100%
66
e 1970 1972: In mest waste crums, accroximately 10 20 lbs. of Oll.ori was mixed in w6th the Crganic wastes and Calcium sillCate.
cit,0n,it necessary Plast c bag
\\'
Solicified organic waste
\\
Y
/ ///"4/// //////Mb
- 41b. Oil On/ layer
, < // l////Q u / /// //QA
/
?
(//jf f f////
///// isis/
3 1972 Pesent Use of tBe 90. mil polythytene crum ist'er began, The inner clastic tag was replaced with an O.nng tag. Oll Ori is usually mixed in with the waste.
3 On.On x
ei N
...t,...g m
=
4.nngcag Solicitied 4
organic waste 4 tt. Oil 0"MY
w c, c
-s..s Figure 4 Solicifie: crganic waste gacsaging ee: noes, e7
i l
3.6.J 5 Soecial 5
-Ues tContent Coce 4).
Liquia astes :na ai e not compatible witn enemical precipitation treatments are trea ec separatelj cue to tne plutonium complexir.g nature of tne aaste.
Lumplextag enemicals incluce some alconols, organic acics, anc Versenes (trauemarx for a series of cnelating agents casec on ethylenediaminetetraacetic acic tivrM.
Tne liquid waste is processec by blending two bags of Portlanu cement anc one j
cag of insulation or otner a:scrcing material in a waste crum, ano tne liquid waste is tnen acced to ne mixture ano allowec to set up.
bee Figure b for aaste packaging metnoas.
3.5.3.e Evaooration Salts (Content Code 5).
Liquid effluent from the l
- secene stage treatment process and otner RFP-generatec liquio nastes not requiring treatment are concentrated in solar evaporation p;ncs.
The concentrated licuics are pum;ec from :ne conos to tne Building 714
(
eva;crator. Tne evapora:cr concentrates and dries tne licuic waste, f orming a salt resicue.
The a: proximate enemical makeuc cf :ne sal; is 60% sodium nitrate (NANO ), 30% potassium nitrate (KNU ), anc 1
3 3
107. miscellaneous.
Prior to Se::emcer 12, 1975, evaporator salts were packagec in si-gallon aaste crums (see figure c) anc af:er nts ca:e, in 1. :y 4 o s ' t:
/
aoocen coxes for cisposal at tne INEL.
de:neen hovemeer lW u anc Septemoer l
1972, sal; aas:es aere starec at tne INEL Transuranic Storage Area (TSA).
I se: een Se::em:er 1972 anc April 197S, sal wastes aere placed in :ne INr.L Transar4nic vis:csal Area (TDA).
Uuring :ne thel Initial Urt.m Retrieval i
(!CR) project, any crums icentifiec as containing sal: weste aere placea in t
TDA. bince Acril 1975, all salt aste nas ceen sent to :ne nevaca Tes:
ST:e (NTS) fer cisposal.4'5 3.:.3.7 New acueous Waste Treatmen: Facility.
Ccnstruction of :ne Acuecus aas:e Treatment Facility, Evilcing Ji, was recently new completec. Tne new f acility is currently processing <10nCi/g wastes, anicn are sni: cec to NTS for cis;0 sal.
The facility will :egin processing scme >10nCi/g aastes in :ne near future.
- nicrmation ccncerning new
-aste forms as no: ava11aole since m0cifi:2 icns 0 :ne trea: men processes are currently :eing incorperatec, i
l l
l l
od 1
1970 1972:
b d
[
- D rum l
- U.,:!.-
i! 1 l
3 5 lb. Portland cement 1 ' *i.
~
- .,..',;;..3;..-
p Plastic bag
',,,3'.,.,.,.,.,.'p,:,,y'c.;::._
Portland cement acced en top of waste cement
~.
- 0 ring bag until no free licuid is j
i present Cemented
/
licuid wastel
,I 3 5 lb. Perttand
.k; cemenVlayer n:..................
c *.. ' '.; :. i ; ',... ';. ;.. y.
)
l l
1972. Present: Use of the 90 mil po.y liner began in 1972.
I G
)
/
\\
-O rum 2
i necessa y
! : ::.., e: 1... ;.. j';.*..'yi
- PfastIc cag N
0 ring tag 1
i Cemented liculd wa te
)
b I
,' f.
/
k 3 010. Port!anc cemenviayer f
D INEL A 19 247 Figure 5.
Scecial set-ucs sackaging c'ethods.
69 l
1970 1975:
b d
[
1.'
C y rum
-Plastic tag Salt waste-(.
m Note: Ouring 1C2 accroximately 1000 crums were lined with a clastic tag anc a cre:e paper tag.
After this tirne, drums were lined with either one or two plastic tags.
1975 1978: In 1975, use of the 4x4x7 ft waste cor began, Af ter April 1978, salt wastes were snicped to the Nevaca Test Site for cisposal.
[
4 i]
Plywood Oox
/g,
-Carc car: liner Pastic liner gf a
(
)
Note: On occasion, Portlane cement was acce: to the salt mixture as meisture a:scr:ent.
1 INE' A 19 24a Eigurt 6.
Ev400ft*Cr $4lt Q4 kaging meth0CS.
70 j
9 3.s.4 aontransuranic Ocerations Tne prececing text has discussec tne principal plutonium operations concuctec at tne Rocky Flats Plant.
Tne following ciscussicn accresses ncn-plutonium operations tnat generate nontransuranic radioactive and nonracicactive wastes. Generally, it is belietec all RFP nontransuranic wastes were disposed of separately from transuranic wastes snipped to INdL for ciscosal. This excludes any uranium or eeryllium wastes generated by transuranic operations. Between November 1970 anc Septemeer 197't, cepletec uranium anc beryllium wastes were disposed of at ne INEL Suosurf ace Disposal Area (SDA), in Pits 10, ll, or 12. Any depleted uranium anc ceryllium wastes (crums only) in Pits 11 anc 12 were retrievec ano placed in s; rage at tne Transuranic Storage Area (T5A-1 or TSA-R) witn otner transuranic wastes retrievec curing tne INdL Initial Drum Retrieval (10' )
d croject.
In accition, uranium anc beryllium wastes retrievec.1tn transuranic wastes curing :ne Indt Early Waste Re:rieval (ind) project were placed in storage at TSA-R. Setween Septemoer 1972 ana April 1978, cepletec uranium and teryllium wastes acre placec in ene URL Transuranic Disposal Area (TUA). Since April 1978, tnese wastes nave :een sent tu NfS for cisposal.#'*
3.5.4.1
- !uilcine 444/447 Operations conductec by tnis facility incluce founcry anc macnining coerations for faerication of teryllium (se) anc cepleted uranium components. Macnining,1f otner metals sucn as stainless steel, aluminum, titanium, copper, etc., is also concuctec in sup;or cf test operations.
Tne :eryllium foundry operation generates Se and deu (ceryllium oxice) ccntamina:ec wastes in :ne ferm Of paperwipes, plastic, gracnite moles and crucicles, small tools, anc casting "sculls" (casting resicue). During procuc;1un founcry operations, it was estimatec ey founcry :erscnnel :nat tne casting process alene woulc generate 20 to 3u les./ cay of Se and Seu sculis.
Since 1970, :ne overall average procuction rate aas estimatec at id cays / year. The es:imatec average weignt of sculls genera:=c esca year 71
aculd ce 4500 to 3750 les.
Trie sculls may be in solic (Be metal) or peacer (Se0) forms.
In accition to sculls, imoure or camaged castings tna: coulo not ce salvagee aere cericcically inclucec witn otner rounury aastes.
A beryllium casting may weign up to 125 los. Beryllium aastes are usually packaged in a carcooarc container anc :nen placed in a aaste cru.a linec with two polyethylene Dags. Wastes are usually segregatec into comcustible anc nunccmoustible fractions.
dome oeryllium was:es may nove been packagec in 4 by 4 by 7 ft ooxes. Tne specific quantity of Bit or Sed snippec to tne INEw is un6ncan.
I Webtes generatec ey Be machining operations include pacerwipes, plastic, nEPA filters lacen aitn be or se0 dust, latne oil, anc uegreasing agents, sucn as tricnicreetnylene, etc. All clean ceryllium turnings ano scrap pieces are recovered anc processed for reuse or solo as scr:p.
olic aastes are contained in a polyethylene bag before placement in plastic-lined -aste crums. Vrganic liquid aste contaminatec witn de i s processed :nrougn tne AWTF (Building 774) anc cecomes part of tne solicifiec organic wastes (centent coce 3).
Ine depletec uranium founcry operation is concuctec in :ne same area as :ne de founcry cperation. Wastes generated of :nis operaticn are similar to wastes generatec ey Se founcry operaticns.
Depleted uranium casting sculls anc macnining enips, metal turnings, ano fines from macnining opera:1ons are incinerated to convert tne pyropnoric metal to a stacle oxice (V U ) P"iO" *0 5"i **"
- I"'
I'#
I"* d"'C *
- 0 33 incinerating :nis type of waste nas al ays been usec by RFP cut cues not prewluce ine possioility :na: pyropneric metal coulo ce presen; in :ne i
waste, as incicatec by :ne June 1, b70 rireD :na occurrec a; :ne rcaMu.
- ncinera ea uranium, callec roaster exice, is pacxagec in a 30-gallon crum anu sealed, :ne drum is placea insice of a 55-gallen crum, anc :ne annular scace is fillec at:n vermiculite. 0:ner solic wastes, sucn as pacer, Tetal, etc., are segregated into ccroustible anc nonccmousticle fractions.
Comousticle adstes are containeo in a polyetnylene cas, packaged in a i
55-gallon ; rum linec aitn a plastic cag, anc compar.tec.
Ncncomous iole i
72
~.
j wastes are containec in a polyetnylene cag ano packageo in 4 oy 4 by 7 rt ooxes. Licuio wastes suen as macnining oil, cuolant, anc cegreasing agents are processeo oy tne A.TF,as solicifiec organic wastes (content coce 3).
Uepleted uranium and beryllium wastes, primarily from tne founcry area, may be intermixed in the waste containers. Large machining equipment is usually decontaminated for reuse in other plant operations. All waste containers from Builcing 444/447 operations are labelled as containinc 8e or Se0 contamination.
I 3.5.4.2 Building 883.
Processing, rolling, anc forming operations l
for cepleted uranium anc ceryllium nave been concuctec in tnis facility since 1954 Beryllium operations ceased in 1973.
Solid wastes generated oy tnis f acility are similar to wastes generatec at Builoing 444/*47 and include paper, equipment, furnaces, anc fireorick. Waste-cepleted uranium
.as oxicicec prior to snisment to tne INdL.
Liquic wastes are processea cy
- ne AWTF.
)
3.5.4.3 suilding 865.
Tnis facility was construe:eo in'1970 for tne curcese of concucting metallurgical researen anc cevelopment pro,lects itn ceoleteo uranium. Waste-cepleted uranium was exici:eo prior to snipment to
- ne INEL.
3.5.5 daste Management Practices Tne ;toexy Flats Waste Management group was formec in late 1970 as an j
outge: win of tne 1969 fire.
Tne estaclisnment of nis group startec a renc toward cetter waste management practices.
During 1971, efforts to l
segregate various wastes into soecific categeries cesan.
In accition, ins;ections of all waste c:ntainers by Was;e Management personnel were i
iin iatec to ensure c:mpliance itn pacxaging regulations.
Segregation end pacxaging of :ne waste is :ne res;ensioility of personnel in eacn.aste generating area.
If insoection of a was;e c:ntainer :y Weste Management personnel reveals improper segrega:1cn, packaging, or cresence of free I
)
l 1
f 1
v liquics, the con:alner is returneo to tne aste generatur tvr correction.
Ine enanges in waste management procecures took several years to in. clement, and U": pruuuuuret. are continually ceing itnor0ved.
All crums containing line-anc nonline-generatec astes (:ransuranic cperations only) are assayec ey gamma scan f or cetennination of t1ssile content at Builcing 771. Drums containing plutonium acove the ciscarc Ivvel are retained f or processing anc plutoniurn recovery.
delow-discarc-level crums are sent to Waste Manageman: (Builcing 775) for inspection anc final preparation for snipping, varge waste items are incivicually Ine surveyeo Defore placement in a aaste cox at tne aste generating area.
cuantity of fissile material is calculated from tne survey results.
In i
ird0, a :ox counter was ouilt in Builcing c64 After a waste Oox nas seen surveyec and sealec at :ne naste generating area, it is sent to :ne cox csunter for assay (ganna anc neutron).
If any significan anomalies occur uet.een cata octained by survey and the eux counter, the uox is returnec to Waste Management, opened, and resurveyed.
Tne Waste Managemen: Si:e Recuction Facility (Suilcing 776) tegan operation curing late 1971 or early 1972.
Inis. facility recuces large aas:e items, sucn as gi ve: oxes, piping, anc latnes, in si:e to f t:
a ty a by 7 ft aste boxes.
In 1974, wasning hignly c:ntaminateo large me:a1 =astes f r plutonium rec:very :egan.
Tnese aste items are too large to :e pr:cessec ty :ne Plut nium Recovery Facility (building 771).
Since 1974 or 1973, crums of celo.-ciscarc-level c:muustible.astes nave :een repacxagec in a by a ey 7 : oxes to improve packaging uniformity.
C ntaminatec Orums are crusne: anc placed in waste toxes.
ine oss;es are int ially pacxagec in crums for assaying purposes.
3.5.5.1 waste Drums.
Seth 30- anc di-gallon si:e aeste crums nave
- een snipped to I:dL for storage. Use et :ne 30-gallon waste crums aas cisc:ntinued in :ne early 1970's.
Uuring iv72, :ne use Of a 90-mil :nic(
polye:nylene crum liner for 55-ga11on crums began.
A polye:nylene tag is
usually usea to line tne insice of tne 90-mil liner. Prior tc :ne enange to :ne 90-mil crum liner, one or two polyetnylene bags were used to line tne insice of a aste drum.
Tne levr of aste item containment varies, cepencing on the area in which tne waste is generated. Waste items generatea uy plutonium c;erations are esually coucle-contained in polyethylene anc PVC plastic eefore placement in a waste crum.
In otner areas sucn as a laboratory, a.uste item may bc cropped airectly from the glovecox into tne large polyethylene bag tnat lines tne inside of the 90-mil polyetnylene crum liner.
Since the early 1970's, approximately 5 to 7 los. of Oil-Ori (abscreen:) nas been accec on top of tne outer sealeo plastic bag of all.aste crums cefore tne 90-mil crum liner Itc is sealed.
Ine Oil-Cri is acced by Waste Management personnel after crum insrection.
3.5.5.2 waste Boxes. Prior to early 1973, 27 larger-tnan-stancarc-s1:ea (4 cy 4 by 7 f t) waste oxes were snipped to INEL f or storage.7
'arge : oxes were usually used to c:ntain large pieces 0f waste from tne 19e9 fire. Af ter tne Si:e Recuction Facility began cperatien, only
- cy 4 ty 7 ft coxes nave ceen usec to package large.aste 1:dms.
Smaller
.aste ocxes, generally 2 cy 4 ey 7 ft, were receivea :nrougn tne mic-1970's. These boxes were usec to package small, heavy waste items ano soil.
All aste coxes are c:nstructed of plywooc.
vuring 1972, procecures ter scraying waste tc2es witn a fiberglass reinforcea polyester (FKP) coating.ere estaolisnec.
Ine FR9 coxes nave a plastic anc carc:carc liner. The level of c:ntainment for incivicual aste items :efore placement in a cox may range fr:m ncne, suen as asnec metals from si:e recuction c:erations, to ceuole-c:ntainment (;olyetnylene, PVC) Of.aste items, sucn as fire astes.
3.5.5.3 Centen: Cece Descriction.
ine InEL Transuranic Contamina:ec aaste Container :nfermation System (TCWC:5), wnien icentifies a conten c:ce for eacn waste c:ntainer, cic nc: eegin until fail of 1971 cnsecuently, c:ntairer c:ntent c:ces are net availacie for RF7 wastes slacec en 75A-1 :uring tne first year of storage.
ine nuncer or.este c:n:31ners no: inclucec in :ne itaC'S is estimatec a: 42,1t; crums anc 75
6c8 ouxes.
in avuttion, h.E IS content coce 0 incluces 11 drums of.uste placea in storage from 4/P anc 16,961 arums et waste placed in storage from lNEL retrieval projects.O ine majority of ne 18,961 drums, for wnien no centent cescriptien is availacle, are celievec to contain wastes generated oy RFP operations.
Information proviced by RFP personnel anc contained in RFP waste characterization anc categori:ation reports,9,10 indicates tnat content coues are not reliaele especially curing tne years of 1971 to 1970, ine rolluding inrurmation concerning content cuue cescriptiuns aus prov1w o oj I
knowlecgeaole K/P persennel anc ava11aole reports:
o Centent coce 1 (first stage sludge):
See Secticn 3.5.3.1 o
wontent c:ce 2 (secenc stage sluege):
See section 3.5.3.2 anc 3.5.3.3 o
Centent coce 3 (organic set-up):
See Section 3.5.3.4 o
Centent coce (s;ecial set-up):
See Section 3.5.3.5 o
Centent coce 5 (eva;crator salts):
See Section 3.5.3.6 o
Content coce 90 (cirt):
Believec to ce c1rt from cleanup around Buil:1ng 776/777 after tne fire.
Snipoec during 1971 anc 1972 1
only a
Centent coce 95 (sluege): Unkno n, sni;pec cwring 197%
o centent coce 441 ( m recers sluc9e):
Lnsnc n, sni:;ec euring 1971-1973 o
Centent coce 290 (filter slucge): One crum sni;;ec in 12/1, sluege :elievec to :e resicae frcm ne incinerater crum filter 75
l Content code 2ir2 (cemented sluege):
51ucge (grease, dirt, o
scracoings, etc.) procuced from various cleanup operations sucn as filter plenums, incinerator crum filter resicue, etc.
- elow-ciscard sluege is usually packageo in 1-gallon polyetnylene
)
cottles witn cement auced as assorcent.
{
j o
Content coce 300 (grapnite molds, crucioles): Grapnite moles ano crucibles are useo ey tne plutonium founcry.
Tne grapnite is l
scraped or ground to remove adhered plutonium, wnien is callec "scarfings".
The scarfings are furtner processed oy plutonium Tne leftover grapnite molo or cruciole (celow discard recovery.
level) is croken up anc placed in 2-or 5-gallon size fioerpaks, 4
bagged-out of the glovebox, anc placed in a aste crum.
o Content code 301 (graonite cores or cases): Part of the mole used by tne founcry for casting plutonium metal. Procecure for l
l f
disposal is same as centent coce 300.
I 1
o Content coce 302 anc 4o4 (5enelex anc Plexiglas;:
Benelex (red.coc masonite) anc Plexiglas are used as neutron snielcing f
arounc glovecoxes in all plutonium areas.
o t.ontent coce 310 tgrapnite scarfings or fines /: Grapnite scarfings are usually nignly contaminatec anc are furtner j
processac ey plutonium recovery.
It is celievec nese scarfings containee ciscarc level amounts of plutonium anc ere not 1
processed (see content coce 311). Scarfing.aste as receivec in l
1 f
1972 anc 1975, j
i o
Content coce 311 (graonite neels): Graonite scarfings or fines f
are pro:assed by acie cissolution in tne plutentum recovery J
area.
After processing, tne resicue, callec graonite neels, is l'
criec anc packagec in ficerpaks cefore placement in a aste crum.
l 1
i I
l l
l 17
Content code 320 (neavy non-SS' met.al):
Muinly consists of o
used tantalum crucibles, funnels and inserts frvm casting plutonium metal. Ot.ier metals may include tungsten, platinum, l
etc. Waste originates from Pu foundry and molten salt operatior:s.
Content code 330 (dry ecmbustibles):
Dry comuusticles mainly o
consist of rags and paper generated by all plutenium areas.
I Content coce 335 (absolute filters):
Filters consist of an o
E" x 8" woocen frame witn an ascestos filter mecia. Filters are used to remove air:orne particulates in the glovecox lines ano ore generated by all plutonium areas.
(
l I
Content coce 436 (aet c mousttelesj:
ae: ccmousticles are o
l generatec ey all plutonium areas.
ine aaste consists of paper anc rags saturatec witn cecontamination solutions.
'aaste may l
also centain aosermec nitric acio.
Centent coce 337 (ncn-leaceo rut:er ano plas:1cs): ints category o
censists of clastic (ieflon, PVC, polye:nylene) items sten as l
tags, sample vials, anc snetting generated by all plu; nium areas.
Centen, code 338 and 3e0 (insulation anc Ca's filter mecia):
o aaste categcry incluces as:estos gloves, fi-e Diankets, pipe insulation. And ascestos filter mecia generatec ey all plu::nium Insulation er filter mecia containing a:ove-ciscarc-level are as.
amoun:s of ply enium is processec ey plutonium recovery (acic leacn). Tne resicue is packagec in 1-gallon si:e polje:nylene i
oci.:les :efore placement in a aas:e centainer, Content coce 339 (leacec rutcer gloves and aprens):
'a as te s o
incluce leac-linec ruccer (neoprene) glove:cx gloves, a:rons, anc ciner leacec materials generatec in cil plu:enium areas.
a.
special source material suen as urantum er plu;cnium.
l 73
o content coce 361 (insulation neel):
Insulatten neel is generatec f rom processing insulation containing acove-ciscard amounts of plut:nium ey :ne plutonium recovery operation.
Inis content coce was only used in 1972.
It is oelievec insulation heel is inclucea in aastes lace 11ec as content coce 338 or 3o0.
o Centent coce 370 (Leco crucioles):
weco crucioles are small ceramic crucibles used by the Plutonium Lacoratory for sample
- analyses, o
Content code 371 (firecricK):
Inis category consists of plutenium-contaminated fireerick used to line tne plutonium recovery incinerator and construction crick from tne 1969 fire.
ine incinerator processes comeustible wastes containing above-ciscard amounts of plutonium.
Tne firecrics is pertocically' replaced.
o Centent coce 372 (grit):
Small aerasive material, or grit, aas usec ey plutenium recovery operations to "grit-clast" non-55 metals for recovery of acnereo plutonium.
Inis me:noc is no lenger usec. Grit waste aas snippec to IriEL curing 1974 ano iv75 only.
o Centent c:ce 374 (concrete, cirt, sand, ano olacxtop):
Inis l
aaste categcry criginates frem cleanup c:erations concuctec at any plant site.
o Centent coce 375 (Oil-Dri resicue): Oil-Dri (:racename; is an a:sor:ent material usec in a majority of RFP aaste pacnages for a:sorptien of sny free liquics.
It is believec :nese waste crums contain Oil-Ori resicues tnat recuirec r: cessing in :ne plu::ntum recovery incinerator.
l l
I
{
79
Content coae J76 tcementec insulation and filter mecia):
uur ing o
1976, procecures to cement insulation and filter meofa cegan.
The procedure was estaolisned to prevent muisture and pressurization problems from occurring in waste containers.
Content code 391 (unpulverizeo sand and crucible):
'a ast e o
consists of magnesium oxide crucibles and sana generatec by tne plutonium recovery reduction furnaces wnere plutonium tetrafluoriae (Puf ) is recuced to metallic plutonium, 4
Content code 392 (unpulverized sanc, slag, anc crucible):
n'as te o
consists of sana, slag, and magnesium crucioles generated by the same operation as described for content code 391. Inis category of waste was snipped to,IeL in 1972 only, o
Content coce 393 (sand, slag, ano cruciole neel):
Sana, slag, and cruciales containing aoove-ciscars amounts of plutonium are processed by acid leaching and dissolution.
Ine remaining resiaue, termec neel, is cried and packaged in 1-gallon polye:nylene cottles before placement in a waste crum.
o Content coce a10 (molten salt):
The halice salt mixture (Naul, r.C1, MgCl2 (30%), etc.) is used to pyrocnemically remove americium from plutonium metal.
o Content code 411 (electrorefining salt):
Salt mixture is similar to content coce 410, except tnat tne MgCl CC"C8"I#'IIC" 15 3 2
(otner salt concentratiens are un<noan).
The salt is usec to pyrocnemically remove all types of impurities frem plutonium
- metal, o
Content coae 420 (virgir, incinerator asn): Comousticle estes containing aoove-ciscarc amounts of plutonium are incineratec in
- ne plutonium recovery incinerator; :ne asn is grouna and 4
50
processed oy acia dissolution.
Content coce 420 asn contains celow-ciscard level plutonium and was not furtner processec.
Tne asn was sent to INEL curing 1972 only.
o Content coce 421 (asn heel):
Asn heel is tne remaining resicue after incinerator ash nas been processed oy acia dissolution.
The asn is cried and packaged in 1-gallon polyethylene bottles cefore placement in a waste crum.
o Content coce 422 (soot): Fly ash from the plutonium recovery incinerator accumulates in the incinerator offgas system.
Tne fly ash, or soot, is generatec wnen tne offgas system is disassemoled and cleanec.
Content coce 430 (unleached ion excnange resin):
Resin waste o
originates from ion-exchange columns used to purify plutonium nitrate solutions produced from processing waste residues by plutonium recovery operations. The resin was not leacned before cisposal.
INEL recorcs indicate this waste was receivec curing 1972 only, o
Content coce 431 (leacned ion-excr nge resin):
Same as content coce 430 except the resin was leacnea witn water to recover tne plutonium.
INEL recores incicate tne waste was receivec curing 1972 only, o
Content code 432 (cemented ion-excnanye resins): During 1872, the procecure for processing resin waste aas enangea.
5ince tnen, the resins have oeen rinsec witn water ana solicifiec in 1-gallon po1yetnylene cot les witn Por lano cement oefore placement in a waste crum.
S 31
o Content coce 440 (glass, except Rascnig rings): Glassware sucn as ceakers, flasks, ana glass vessels, is generated primarily oy plutonium recovery operations. All plutonium areas generate glassware waste.
Content coce 441 (unleached Raschig rings): daschig rings are o-glass rings witn a nign boror, content.
The rings are used as a neutron poison in storage tanks containing plutonium solutions.
The rings nave not been.leachea to remove resiaual plutonium.
All plutonium areas generate this waste category.
Content coce 442 (leacnea Rasenig rings):
Same as content o
code 441 except tne rings nave been leached witn nitric acid to remove resicua' plutonium.
Content coce 460 (wasnacles, ruboer, plastics):
Information was o
not availaole.
Content coce 460 waste was sent to lhit curing 19/'d only.
o Content code 463 (drytox gloves):
This content coue nas oeen incorporateo into content coce 339 sincs 1972.
Content code 464 (Senelex anc plexiglas): Content o
code incorporated into content code 302 since 1973.
Content coae 480 (unleached lignt non-SS metal): Unleacnea lignt o
non-SS metals include iron, copper, aluminum, anc primarily stainless steel. Ine waste is generatec by all plutonium areas and has not been leached.
)
Centent code 481 (leacnec lignt non-SS metal):
dame as content o
code 480,'except tne metal waste has ceen cut into smaller pieces and wasned for plutonium recovery.
ine Size Reauction facility processes these wastes.
32
Centent coce 490 (hEPA or CWS filters):
high efficiency o
particulate air (HEPA) and enemical warfare service (CWS) filters are used in tne exnaust systems of all plutonium areas to remove airoorne particulates. From 1971 to 1975, the filters were packaged in crums anc coxes.
Since 1975, the filters have been p4ckaged in boxes only.
Content code 900 (low specific activity (thA) paper and o
plastic):
Consists of LSA paper and plast 1cs tnat have been contaminated as follows:
Uranium, thorium, or their chemical concentrates a.
Material in wnicn the activity is essentially uniformly o.
cistributed and in wnich the estimated average cuncentration per gram of contents does not exceed tne following amounts:
1.
0.0001 millicuries of Grcup I radionuclides (e.g., Am, Pu, 232 ); or 0
2.
0.005 millicuries of Group II radionuci' des (e.g.,
230g, 233g,234U, 236 ); or U
i 3.
0.3 millicuries of Group III or IV racionuclices (e.g.,
Tritium, 236U, 2 EJ, Natural U, Eu)
Nonracioactive cojects externally contaminated witn c.
racioactive material, provicec that tne raciohetive material is not reacily discersicle ano tne surface contamination,
)
wnen averaged over an area of cne scuare meter, coes not j
excesa 0.0001 millicuries per square centimeter of Group I l
racionuclices or 0.001 millicuries per scuare centimeter of otner racionuclices.
1 i
S3
These wastes were received curing 1971-1975.
o Content coae 950 (LSA metal and glass): L5A metal ana glass waste contaminated as describec for cuntent coae 900. Wastes receiveo curing 19/1-1975.
o Content code 960 (concrete and aspnalt): Concrete ano aspnalt cleaned up in areas having suspected contamination. Waste received curing 1971-1973.
o Content code 970 (wood and Benelex):
Waste consists of Benelex and wood removed from areas naving suspected contamination.
Content code 976 (Suilding 776 process sludge):
Waste consists o
of sludge removed from processing tan 500 ppm. Recorcs l
concerning processing of PCB oils are not complete. The following availaole information concerning known processing of PCB oils was provicea
. by RFP personnel:
Processino Date Drum Numoer Gross Weicht (los) 5-25-76 743-13393 457 1
8-31-76 1-litre cottle of PCd oil burieo in tne miacle of one of the following i
I drums:
743-13465 to 743-13472 l
l-J1-78 743-13948 o2e i
743-13940
'z4 1
/43-13950 ele 743-13951 644 1
743-13952 e15 l
l 743-13953 641 743-13954 539 l
743-13955 537 2-14-78 743-13982 494 743-13984 473 Nold:
743-13983 snoulc nave resicual PC5 contam1 nation'.
l I
36 i
L The total numoer of PCB-contuninatea content coce 3 crums is unnnown.
Ine PCB contamination in a drum may be eitner locali:ec or cispersea througnout tne solicified organic waste matrix.
Otner solidified organic wastes include entorinated hydrocaroons (up to 50%), such as carbon tetrachloride and trienlarcetnane, and trace concentrations of miscellaneous organic laooratory wastes, such as organopnospnates, nitrobenzene, etc.
3.5.e.5 Beryllium.
Beryllium contamination exists in first and second stage slueges (content codes 1 ana 2) and in solicified organic nastes (content code 3).
The concentration of Be in first and second s: age slucges is expectec to be <1000 ppm, see Appencix B.
The source of Se in slucge waste is usually from plutonium recovery operations. Urganic cegreasing agents useo ey be macnining operations (euilaing 444) are processed with other RFP generated organic waste.
Ine concentration of be in content coae 3 waste crums is unknown.
A significant source of stored beryllium (de) wastes is from wastes retrieved during tne INfL IDR and EWR project.
In accition, small amounts l
of de 4re generatec ey R&D efforts conducted in the plutonium areas.
Ine
[
specific quantity of Se or de compounds in INEL stored wastes is un<nown.
3.5.5.6 Nitrated Wastes. Large quantities of nitric acid are used in plutonium recovery operations, and smaller quantities are used by many otner plutonium operations. Generally, no free nitric acid is present in solic aaste packages. The acid was acsorced on paperwipes, rags, or otner aoscreent material. Nitrated cellulose materials may cecome nignly fiannacle if allowed to cry.
Ccmous:1 ole wastes, suen as content coces 330 ano 336, may contain nitrated cellulose wastes.
Ion-excnange resins are usea oy procuction plutonium recovery operations to purify plutonium-oearing solutions.
ine resin is an organic-casec (styrene) polymer procucec oy the Dow Cnemical Company.
i During recovery operations, :ne resins are exposec to various 37
concentrations of nitric acid. Nitrated resins may Cecome nignly flammaole and/or explosive'if the resin is allowed to cry.
lon-excnange column resins are usually cnanged once or twice a year cepenaing on the rate or production recovery operations.
Information provided cy RFP recovery personnel indicated that each cnange, cepenaing on the numoer of columns involved, could generate between 600 to 1200 los, or more of resin waste.
Disposal practices for resin wastes were enanged several times curing 1972, based on content code changes appearing in tne INEL Transuraniq Contam1nacea waste Container Information System (TCWCi$) and information provided oy recovery personnel. During ano prior to 19/2, resin wastes were not leached for recovery of remaining plutonium and were pacxagea in clastic cags before placement in a waste crum (content code 430).
During 1972, tne proceaure was enanged to leaching the resins witn water (content coce 931) to recover tne plutonium before packaging in plastic bags.
Tne final procedure change also occurrea during 1972.
Since 1972, resin wastes nave oeen leacned with water and then solidified with Portland cement in 1-gallon polyethylene bottles before placement in a waste drum, it is believed cemented resins snould not represent a significant hazard. Any resin wastes packagec before the solidification process was establishec (including retrievec crums) may represent a flammability or explosion nazard if tne resins nave cried out wnile in storage.
Tne numoer of crums containing resin wastes that may represent a hazard is unknown.
\\
- 3. :i. e. 7 Batteries.
Pricr to 1973, mercury ano litnium catteries were i
l periccically placea in second stage sluage crums (content coce 2).
The numoer of batteries incluced in sluage crums is unknown.
ine batteries may represent a toxic and/or explosion nazaro.
3.5.6.3 Otner Cnemical Wastes.
Generally, all licuid enemical wastes generatec by various RFP operations are processea oy tne AwiF (suilcing 774) as first or secend stage slueges, solicifisc organics, special set-ups, or evaporator salts (content coces 1, 2, 3, 4, ano 5 respectively). Prior to 1973, second stage slucge crums were periccically 88
used ;o cispose of cottles or' licuid enemical wastes, small containers of elemental mercury, and batteries.
Tne volume or type or enemicals placeo in tne slucge crums is unknown.
Sludge crums (content coces 1 and 2) also contain a variety of resicual toxic neavy elements from processing various plant-generated liquid wastes. Appenaix C contains RFP analyses of 7412-series sluage drums.
3.5.6.9 Hydrocen Generation.
Recent waste characterization projects conductea by RFP for EG&G Idaho, Inc. incicate tnat hycrogen generation occurs in waste drums. During 1979 and 1980, seventy RFP-generated waste drums were retrieved from storage at tne INEL and returned to RFP for charaC eriZation. Results of the enacteriZation project revealed tna: four crums nac elevatea levels of nyarogen (6, 12, 13, and 19% of volume). Tne lower explosive limit for nyorogen in air is 4.1% by volume.
Hydrogen generation may occur from alpha-radiolysis of water anc organic or cellulosic materials.
3.5.6.10 Orur. -
. Jriz3cion.
Pressurization of waste crums may occur from gases,
oxygen, etc.) procucea oy raciolytic, 4
eac erial, and chemical actions. During 1980, a first stage sludge crum, placed in storage at tne INEL curing 1978, was oiscovered to be pressuri:ec. Analysis of :ne crum incicated the pressure t' be 19.6 psig.I3 0:ner stored waste crums,sucn as first stage sludge crums, may also be cressurizec.
p roonories.
Small amounts of unexicizec (metallic) 3.5.5.11 y
plutonium anc/or metastacle plutonium sucoxices may oe found trapped in macnining oil, sucn as in the vacuum pots tna: aere connectec :o eacn plutonium macnining station.
The pots, wnicn were removec curing C&D operations after :ne 1969 fire, containea a mixture of nignly contaminated macnining oil, caroon tetracnlorice, anc slucge.
h 59
7 Depletea uranium,,astes, primarily roaster oxice, placed in storage
~
from INEL retrieval projects, may contain some pyrconoric metal.
Generally, all pyrophoric' metal sucn as machining cnips, turnings, and fines were' incinerated prior to disposal.
However, information provioed by macnining personnel inoicates that, on occasion, larger pieces of uranium such as a damageo parts, were placed in drums containing roaster oxide f
waste.
Specific information is not availaole.
i l
i 90'
4 IDAHO NAf!ONAL ENGINEERING lad 0dATUdY-GEnidAIE0 WAsfES Sm411 volumes of transuranic contaminatec wastes generatea by InEL operations have periodically oeen placed in storage at the Transuranic Storage Area (TSA).
Stored INEL wastes nave been generated by tne following facilities: Naval Reactor Facility (NRF), Test Area North (TAN),
Test Reactor Area (TRA), Chemical Processing Plant (CPP), ana Argonne National LaDoratory-West (ANL-W).
The INEL Transuranic Contaminated Waste Container Information System (TCWCIS) recoras concerning storage of INEL-generated wastes are not complete.
In 1975, available records were incorporated into the TCWCIS.
The TCWCIS incluaes container information cencerning wastes storea at TSn ano tne Intermeciate Level Transuranic Stcrage Facility (ILTSF).
Cnaracterization of INEL wastes was conducted for TSA stored wastes only.
Tne total volume of INEL wastes storec at TSA is estimatec at 338.0 f 3 (s30 crums--assumea to be 55-gallen size, one 4 Dy 4 cy S ft box, ano one special package). The following volumes (f t ) of waste were placed un TSA:
Year Generator 1975 1976 1977 1978 1979 1980 Total 14.8 3.0 29.6 63.2 ANu-W 15.3 22.2 7.4 TAN 14.8 163.8 14.8 TRA 149.0 7.4 51.8 LPP
- 14. 4 27.0 37.0 NRF Total 224.0 0
0 51.3 25.2 27.0 338.0 4
91
e The following incivicuals proviced it. formation concerning INEL-generated astes:
R. Ponto (ANL-W), J, S. Leavitt (TAN), D. K. a'enzel (CDP), W, C. Oldsn (C,TP), T. O. Enyear (NRF), G. F. Marriott (NkF),
A, H. Clarg (TRA), J. D. Baker (TP.A), D. M. Anderson (TRA), and H. M. Sateneiqer, Jr. (NMO).
4.1 Test Area Nortn (TAN)
Wacce generated oy TAN consisted of radioactive sources used for instrument caliorations.
In 1975, two waste crums containing plutonium-beryllium neutron sources (content cuoe lo2) anc in 1979, one waste crum containing americium sources (content cooe 200) were placed in storage.
The sources were sealed in carDon steel pipes, anc eacn pipe was centered in a aaste crum.
Cement was adcec, filling tne annular space of tne drum and encapsulating :ne pipe containing the sources. ao owner
.astes were inclucac in the waste crums.
4.2 ChemicalProcessincPlant(CPPl The 1975 waste sniement from CPP consiuted of six waste crums generated frem cecontamination and removal of equipment (content coce 150) from a processing cell in Building 601. Wastes generatea of tnis operation incluceo rags, anti-contamination clotning, equipment, piping, anc aucting. Tne wastes were not segregated into comoustible and noncomoustiole fractions.
The 1960 snipment consistea of one 55-gallon waste crum.
Tne urum contains one 1-gallon me:a1 can of rac1cactive sources (content coce 150--leocratory wastes) containec in aluminum or stainless steel capsules. Tne capsules contain oxices of piutenium ana americium isotopes ana -- U. No otner nas;es were incluced in :ne waste crum.
ou 92
1 4.3 Arconne National Lacoratory-West ( ANL-w)
Wastes generated by ANL-W originates primarily from Suilaing 762 analytical lacoratory operations.
Laboratory operations include sample preparation anu raciocnemical analyses of pre-anc post-irraciated fuel s amples. Laboratory wastes (content coce 150) may include comoustible wastes sucn as empty polyethylene bottles, tuoing (PVC, Tygon, etc.),
0-rings, paper products, rags, wood, and plastics. Noncomoustible wastes may include ferrous and nonferrous metals, glassware, ceramics, and small containers of absorbed liquio waste.
The liquid waste is usually a mixture of HNO / HCL acids (aqua-regia) containing dissolved fuel samples.
Tne 3
liquic waste is aoserbed on Oil-Ori, or in the past on vermiculite, contained in 2-gallon size metal cans.
Some metal cans nave been wrapped witn leaa sheeting io reduce radiation levels. Wastes are segregated into combustiole and noncomoustible fractions.
0:ner waste generated by ANL-W includes one crum containing a "leaky" plutenium-beryllium neutron source (content coce 152).
Ine source was wrapped in plastic and placed in a paraffin-lined lo-gallon crum.
Tne crum was tnen placec insice a 55-gallon waste crum. Anotner waste crum icentified as containing a neutron source, contains a plutoniem standard, a plutonium foil, tools, ano other noncomoustible aastes.
l 4.4 Naval Reactor Facility (NRF)
Transuranic waste generated oy the NRF Expencec Core Facility was placed on TSA in 1978.
Tne waste consisted of five waste crums centaining 238 neutron scurces. Four crums (content coce 152) contain one eacn 7u-Be neutron source.
Ine sources originated from tne Settis Atomic Power wacoratory. Eacn source was contained in a SM 55-gallon crum.
The fiftn crum, icentified as containing comoustiole laceratory waste (content 2'o coce 153), contained a
~~Pu-Be neutrcn source.
The source was generally usec for calloration of reactor and monitoring instrumentation. Ine source i
1
was pac 4 aged in a type 2K container and placed insice a 30-gallon crum linea witn paraffin.
The drum was tnen placed insice a 55-gallon drum, ano wood was added to provice snoring between the crums.
4.5 Test Reactor Area (TRA)
Transuranic waste generated in 1975 originated from decontamination anc removal of equipment from the alpha-wing of Suilding 661, Yne waste consisted of one 4 cy a by 8 f t FRP box and five 55-gallon drums cuntaining TRU scrao (content code 155) and one 55-gallon crum containing sample fuel (content code 154). The box is believed to contain a clastic glovecox.
Otner equipment, such as a nyaraulic pump (oil was N - crainec), vacuum pumps, centrifuges, tools, etc., was useo to fill in. remaining space or the waste box. Materials sucn as actinide source., a racium neeale, enu small viols of samole fuel were packaged in (as waste drum (content coce 154). The eruni was filled witn cement or snielding purposes, with a cavity in the center for tne TRU materit h.
The 1979 naste shipment consi;*.-
of two waste crums (content code lob anc 154) containing experimental m xed oxide fuel capsules from tne Bett-51 program.
The capsules originated from the Aavanced Reactivity Measurement Facility ( ARif), Suiloing 660.
The capsules were packaged in 1-gallon metal containers before placement in a waste crum.
Lead shot was used for snielding arounc the containers, and ciatomaceous earth was acced for support. iio otner wastes aere incluced in the crums.
4.6 Nonraciolocical Hazarcs No nonraciological na: arcs, einer tnan tne small amounts of ceryll um containea in neutron sources, were. identified as existing in stored aastes generatea vy INdL operations.
94 A
5.
SUMMARY
All site-and offsite-generated transuranic wastes stored at the INEL-TSA have been characteri:ed.
Information obtained during the characteri:ation study indicates that nonradiological ha ardous materials such as biological wastes, inorganic and organic chemicals, have been included in stored wastes.
Generally, specific information (container identi fication, shipment date, quantity of material, etc.) concerning these ha:ardous materials is not available.
Until April 1980, information identi fying hazardous materials in waste containers was not required.
Also, waste generators do not usually keep any recorcs concerning disposal of ha:ardous materials in waste containers.
Therefore, the information contained in this report was primarily obtained by interviewing personnel familiar with ocerations, processes, material usage, and waste management practices at each waste generating facility.
Information concerning operations, process descr'ptions, etc. is contained in the text for each waste generating facility.
A sumcary discussion of hazardous materials included in wastes shipped to INEL by each waste generator is presented below.
Specific infonnation concerning ha:ardous materials is contained in the Honradiological Ha:ards section for each waste generator. Table 1 provides a summary of this i nf o rma ti on.
Evaluation of future management alternatives for stored transuranic wastes should include the environmental and operational impacts of identified ha:ardous materials.
Certain ha:ardous materials, such as nitrated ion exchange resins, may require special handling and processing procedures to ensure personnel and environ ental protection.
95
TamLE 1.
KAZsRUOUS MATERIALS INCLUDED IN STURED TRU on5TE5 Waste Generators Hazarcous Material MNO BCL SAPL ant-E RFP InEL Mercury (elemental)
X X
deryllium (compounos)
X X
X X
Asbestos X
X Nitrated Wastes X
X X
X X
Organic Wastes (mixtures or unknown)
Polycnicrinated Bipnenyl (PCB) 0 0
X Polye:nylene Glycol X
Utner Cnemical Unknown X
Gas ueneration/Pressuri:ation 0
X in aaste Containers Pressurized Vessels 0
X Siological Wastes X
Pyrounorics 0
Mound Lacoratory MNu
=
da;:elle Columous Lacoratory BCL
=
Bettis Atomic Power Lacoratory dAPL
=
Argonne National Laceratory-East ANL-d
=
Rocky Flats Plant RFP
=
idano National Engineering Laocratory INEL
=
Ha:aro identifieo as existing in stored waste X
=
Hazard icentified as pe:en:ially existing in stored aste 0
=
96
6.1 Mound Lacoratory 6.1.1 Mercury Sixty-one car:ons of contaminated elemental mercury nave oeen incluceo in waste snipments.
Tne cartons are contained in 28 55-gallon waste drums. The estimatea total quantity of' mercury inclucea in tne waste is 7.63' gallons or 864 lbs.
5.1.2 Beryllium Approximately one to tnree 1-gallon cartons of beryllium-contaminated wastes are generatea on a yearly basis by analytical operations.
ine weignt of beryllium in eacn carton is estimatec to be s2.05 grams.
5.1.3 Pressurized Drums An estimated 20 drums of aosorcea acidic wastes were snipped to INEL anc may oe pressurized due to reaction witn calcium caroonate containec in tne aosorcent agent.
5.l.c das Generation Raciolytic procuc-ion of nycrogen gas may occur in certain waste crums.
Suspect crums would oe in-line generateo comous iole wastes ana
<100 nC1/g comoustible waste drums.
Since 1975, all comous:ioie oaste 2#d cruus nave oesn requireo to contain <19 Pu.
5eventy-four 55-gallon crums, containing unsegregatec comoustiole anc 233 noncomousticle wastes :nat exceec :ne 1 g limi of
?u, nave seen snippea to tne INEL.
Ine crums a'ere packaged oefore tne I g limit was estsellsnee.
Tne crums ere packaged in 18 stancard si:e coxes for snipment to :ne !NEL.
- .1.3 ton fxcnance Resins
. Twenty-eight cartons of spent ion excnange resins from recovery operations nave Deen included in waste sn.1pments.
The cartons are containec in f1ve waste crums anc :nree waste boxes.
Tne resins were exposeo to various concentrations of nitric acic curing recovery operations. Nitroted resins may represent a f14mmable anc/or explosive hazard if the resin is allowed to cry.
It is believed all resin wastes were wasned witn water before packaging.
It is not known now completely ne resins were cenitratec.
- .1.6 Aseestos xs of February 1980, 1,108 cartons of asbestos filters ano sume as estos gloves have been includeo in weste snipments.
S.d dattelle Lo tumous Laoorator f es 5.4.1 Pulfcnlorinateo sienenyls (PC3)
Was e oils removeo from various equipment pieces (latne:, presses, etc.) curing D&D operations were absoroec witn Oil-Dri (trode name) containee in approxima'tely 201-gallon metal cans.
The absorced oils may oe ccntaminated attn PLSs of unknown concentrations.
5.3 Bettis Atomic Power Lacoratory 5.3.1 Car:o Wax 6000 (Polvetnylene Glycol)
Caroo wax in :ne form of solic powcer or flakes was pacxaged in metal
- ans cefore placement in waste crums.
Tr.e volume of material includec in waste snipments is unknown. Caroo wax may represent a slign fire na:aro anun exoosed to neat or riame.
YS.
5.c Arconne National Laboratory-Eas t 5.4.1 Beryllium Small amounts of ceryllium in :ne form of crucibles, roos, etc. nove oeen incluced in waste snipments.
These wastes were remuvec from glovecox lines curing O&D operations.
Ine volume of beryllium includeo in tne. waste is unknown.
5.4.2 Organic Wastes Organic wastes such as scintillation liquias, alcohols, and macn1ning ano pump oils, nave ceen inclucec in waste sniements.
ine wastes are aosoroec on vermiculite contained in metal cans ano polyethylene cottles.
Until January 1981, organic scintillation licuios were absorced on vermiculite and allowec to cry.
This practice ceaseo cue to concern tnat peroxide formation could occur from deccmposition of etner-based scintillation liquids.
Inis could represent a potential explosion na:ard.
Tne numcer or volume of cans or bottles containing aosorceo scintillation licuics incluced in waste snipments is unknoan.
Cnemical cottles centaining low-caroon alipnatic (generally outyl) alcohols were filled witn vermiculite ey D&D personnel, aaste machining, luoricating, and pump oils generatec curing O&O operations were also aosoroec on vermiculite containec in metal cans anc polyetnylene cuttles.
It is unkr.own if any of tne oils containec polycnlorinatec cipnenyls (PCB).
The numcer or volume of cans or bottles containing aosuroec alconuls or oil is un<nown.
- .a.3 Ion Exenan;e Resins Small plastic ion exenange columns, containing 5 to 15 mL or organic-casea resin, are usec by several AnL-E areas for isotope separation anc recovery experiments.
Ine resins are exposec to various concentrations
or nitric 4cic.
ine resins are usually rinseo witn eitner oxalic acia or a
~
)
mixture of HC1/HF acids before disposal.
Information proviceu by Aht-E persunnel incicates tnat ne resins rinsea with oxalic acia shoulo not represent a hazarc. Oxalic acid cenitrates the resin anc removes must or tne tissile material. Resins rinsed with nC1/HF may be in tne nitrate form. Nitrated organic resins, if dry, may represent a flamacility ana/or explosion nazard.
Tne overall volume of ion excnange resins generated by i
a ANL-E operations is Delieved to be small. Specific information is not i
availaole..
j 5.5 Rocky Flats Plant 5.5.1 Biological Wastes j
l i
Three stancard si:e coxes containing biological -astes, generatea of plutonium anc americium translocation exoeriments, were snippea to :ne laEL in Fe:rrutry 1978. Une cox of wasta contains numerous empty glass quart jars originally used to collect urine anc tissue samples.
The two remaining ooxes contain carcooard ooxes of tissue samples, cc3 pens, syringes, empty scintillation vials, anc feces wrappec in plastic Dogs, ao pauto9 ente or sneinical carcinogenic work oas conouttec in cunJunction with i
- nese experiments.
i 5.5.2 Gas Cylincers j
A variety of pressurized gases nave oeen used at RFP for calioration 1
i of laceratory anc monitoring instrumentation anc for use in procuction areas. After tne 1969 fire, a large numoer of contaminatec gas cylincers, f
including C0 rire extinguisners, were inclucec in waste snipments to :ne 3
iNE*..
It was pelievec most of ne gas cylinders were ceoressuri:ec orier to placemen; in waste containers. ricaever, i was spe:ulatec tr.at cer,11n j
gases may nave been nazarcous to cepret rize in :ne wor < environmen; anc j
aculd have oeen placed cirectly into waste containers.
Infccmetion concerning cne :ype of gases, cylinaer si:es, snipmen cetes, etc. was nu:
availaole.
l 100 1
5.5.3 Ascestos Large quantities (specifics unknown) of ascestos or materials containing ascestos, sucn as filters, insulation, fire olan<ets, gloves, etc., nave been incluced in waste snipments to tne INEL.
5.5.4 Polycnlarinatea aionenyls (PCB)
Transuranic-contaminated oils containing polychlorinated bipnenyls 12 were periocically processed witn otner organic wastes until 1979.
fne consentration of PC3 in tnese oils is believea to oe >c00 ppm. Recorcs concerning processing of PCd oils are not cumplete. The total numoer of PCs-cuntaminateo crums is unxnown.
5.5.5 Beryllium beryllium (Be) contamination exists in first ano second stage sluages anc in solicifiec organic wastes.
The concentration of Be in first ano seconc stage sludges is expec ec to be <1000 ppm, see Appenaix 3.
ine concentration of Se in drums of solidifiec organic waste is un<nown.
A significant source of stored Be wastes is from wastes retrievec curing tne INEL IDR and EWR projects.
In accition, small amounts of Se are genera ea ey various R&D efforts in plutonium processing areas. ine specific quantity of Se or Se compounas in INEL storea wastes is un<nown.
5.5.o Nitratec aastet Large quantities of nitric acio are usec in plu:enium recovery coerations, anc smaller quantities are usec oy many ciner clutonium cperations. Generally, no free nitric acia is present in solic waste packages.
Tne acio was absoroeo on paperwipes, rags, or otner assorcent material. Nitrated cellulose materials may cecome nignly flammacie if allOneQ to cry.
101
lon-excnanye resins are usea ey proauction plutonium recovery operations to purify plutonium-cearing solutions. During recovery operations, tne resins are exposed to various concentrations or nitric acid, Nitrated resins may oecume nignly flammaDie ana/or explosive if the ru in is alloweu to cry.
- on-excnange column resins are usually changed once or twice a jear cepencing on the rate of proauction recovery operations. Disposal practices for resin wastes ere cnanged several times during 1972, based on content code changes appearing in tne INEL Transuranic Contaminatea waste Container Information System (TGCIS) ano information provided oy recovery personnel.
Since 1972, resin wastes have oeen leached with water and then solidified with Portland cement in 1-gallon polyethylene bottles before placement in a waste crum.
It is
. believed cemented resins snould not represent a significant hazarc.
Any resin wastes packaged before tne sulidification process was estaclisned (including retrievea crums) may represent a flammaoility or explosion nazarc if tne resins have dried out wnile in storage. The numoer of drums containing resin wastes tnat may represent a nazard is unknunn.
5.5.7 datteries Prior to 1973, mercury ano litnium batteries were perlocically placed in second stage slucge crums (rontent coce 2).
Tne numoer of batteries incluJeu in sluoge crums is unknown.
The batteries may represent a toxic and/or explosion nazaro.
s.b.d 0:ner Chemical Wastes Prior to 1973, second stage sluege crums ere periccically usec to cisocse of octtles of licuic enemical wastes, small containers of elemental mercury, anc Datteries.
The volume or type of enemicals placed in :ne sludge crums is unxnown. First and secenc slucge drums also contain a variety or residual toxic heavy elements fecm processing various plant generatea liquid wastes.
Accencix C contains RFP analyses of 7 12-series sludge drums.
102
~
5.5.9 Hyurogen Generatien L
Recent waste cnaracterization projects conducted oy RFP for Eu&G Icano, Inc. incicate tna: nyorogen generation occurs in certain waste crums. During 1979 and 1980, 70 RFP-generated waste crums were retrievea from storage at the INEL and returned to RFP for cnaracterization. Results of the enaracterization project 'IO revealed tnat four crums haa elevated 9
levels of nycrogen (6, 12, 13, ana 19% oy volume).
Tne luwer explosive 4
limit for nyorogen in air is 4.1% by volume.
Hydrogen generation mdy occur frcm alpna-raciolysis of water ano organic or cellulosic materials.
c.5.10 Urum Pressurization Pressurization of waste drums may occur from gases (nycrogen, oxygen, etc.) prouuceo oy raciolytic, cacterial, and citemical actions, uuring 1980, a first stage sludge crum, placed in storage at tne IrtEL curing 1978, was ciscovered to oe pressurizea. Analysis of the urum inu1cated tne cressure to ce 19.6 psig.Id Other stored waste drums, particularly firs:
stage slucge crums, may also be pressurized.
5.5.11 Pyreenories Small amounts of unoxicized (metallic).nlutonium anc/or metastacle plutonium sucoxices may be present in vacuum pots tnat were connec:ea to plutonium macnining stations. The po:s were inclucec with otner wastes j
genera:ec by D&D operations conouc:ed after :ne 1969 fire. Anotner potential source of pyropnories includes any cepletec uranium wastes f
retrievec anc placea in storage curing INEL retrieval proje::s.
~
l i
5.6 103r.o National Engineerinc Lacoratory l
1 6.5.1 seryllium i
Small amounts of ceryliium c:ntainec in ne;;ron sources were scentifiec as existing in s:orec wastes generatec Dy INEL coerations.
103
diFidEdCE5 1.
- 4. K. Slauvelt, "TRU Waste Certification Analysis," Monsanto desearen Lurporation--Mound Facility, uctooer 17, 19o0.
2.
U.S. Department of Energy, Final Environmental imoact Statement--docky Flats Plant dite, LUE/ tid-vuo4, npril 1960.
3.
C. E. Wicklano letter to R. M. 5cnletter, 81-R/-Ve/6 (Rocxy Flats Plant), "Adottional information for Autnurization of Non-stancard aaste snipments," May 11, 1981.
4 Teleonone conversation witn H. M. datchelder, July 6, 1981.
5.
Personal communication witu 4. R. bisnoff, July 6, 1961.
6.
B. C. Anderson ano d. M. Senletter, A History of the Racioactive 'aaste Manacement Complex at the Idaho Nationas engineerina Lacoratory, WM-F 1-61-003, Maren 198I.
1.
Letter, H. M. Satenelder to T. G. Hedani, "Large Boxes on TSA-1,"
kMS-02-01, July 9, 1981.
3.
Letter, H. M. Batenelaer to G. R. Darnell, "Stored Containers Not Inclucea in :ne TCWCIS," HMS-01-81, June 12, 1981.
9.
L. L. Luckett and P. T. Fraccini, Characterization and Catecorization 5:ucy of Txu Waste for EdsG (Transmittec by J.
K. 61snoir, wkb-le-eu),
hoc <weil internationei Pliot Plant Development Group, koexy Flats PI:n:, no cate.
10.
L. L. Lucxett, Characterization and Categorization Study of Idu Waste for EG&G, C56-Bi-004:, nocxweli international nocxy Fia:s Pian:,
spell 10, 1931.
11.
L. L. Luckett, et al., Rocxy Flats Waste Stream History Recor:
(Craf t), IRV Waste Cert 171ca:1on Analysis ?rogram deport--F f-81, Rock ell international nocxy fiats Piant, uanuary i3. 19el.
12.
Letter, I. L. Clements, Jr. to K. B. McKinley, "PCB Contaminated aastes at :ne AWMC," TLC-7-81, April 27, 1981.
13.
T. h. Smi:n, "Minutes of Meeting on Gas Generation--Rocxy Fia:s slant," *H5-25-e0, July 17, 1980.
IU*
APPENDIX A EXMPLE : WASTE Q'JESTIONNAIRE FOR SETTIS ATOMIC POWER LABORATORY G
e I
105
o APPENDIX A STORLJ TRANSURN11C WASTE CHARACTER 12AT10N FCR BETTIS ATOMIC POWER LABORATORY I.
The INEL Waste Management Information System (Form ID-135) and the Transuranic Contamina!'
"aste Container Information System (Form 10-137 or equiv.
.) indicates the following waste information:
A.
VOLUME OF STORED TRANSURANIC WASTE:
Vol ume Vol ume Year (m )
(ft )
Drums Boxes Bins 1973 33.67 1,189.1 119 1974 92.86 3,279.3 44 6 1975 122.40 4,322.5 588 1976 113.1 3,994.1 543 1977 8.745 308.8 42 1978 8.121 286.8 39 1979 11.66 411.8 56 1980 31.65 1.117.7 89 TOTALS
- 22.15 14,910.1 1,922 B.
STORED TRANSURMlIC WASTE CONTENT CODES:
Centent Code Descrietion Drums Boxes Bins 10 Comoustibies (rags, gloves, 912 poly) 20 Noncompress, noncombustible 792 30 Solidi fied grinding sludge,
15 et:.
106
40 Solid binary scrap powder, 172 etc.
NOTE :
Totals may not be consistent due to use of separate information systems.
II. Facility Information A.
What is the overall function or purpose of Bettis Atomis Pcwer Labora toc /7 B.
What areas, facilities, sites, laboratories, etc., within Bettis Atomic Power Laboratory generate transuranic wastes that are shipped to INEL for storage?
C.
For each fac'ility, area, etc., that generates waste shipped to INEL:
1.
What is the function of that facility?
2.
What type of processes, operations, etc., are er have been conducted within each facility since waste shipments to INEL began?
3.
What type of materials, themical pi ecesses, etc., are associated with operation of this facility?
4 What type of wastas are generated?
5.
What physical form is the wasta in?
a.
Sol id b.
Liquid 107
c.
Sludge d.
O the r.
6.
What is the major radionuclide contaminant?
7.
What percentage of the waste shipped to INEL is generated by each facility?
III. Waste Information A.
How are the wastes generated from each facility handled?
3.
How are 2e different types of waste packaged or prepared for sni; ment?
i 1.
Wrapped in plastic 2.
Use of special containers f
3.
Solidification of liquids f
4 Waste treatment (evaporation, etc.)
5.
Volume reduction t
6.
Oth er.
C.
What type of plastic is used for packaging?
1.
Polyethyl ene 2.
Polyvinyl chlorice (PVC) f 2.
Other, please speci f ty.
i 108
,a---
D.
If several types of plastic are used, wnat percentage of each is used?
E.
How many layers of plastic are used?
F.
Are any unsolidified liquids included in the waste (examples:
~
scintille. tion vials, chemical bottles, etc.)?
G.
Are any absorbents, such as Oil-Ori, vermiculite, etc., used in packaging the wastes?
H.
Is the waste segregated as to content codes used for shipping
)
info rma ti on?,
I.
Is additional information available concerning the description of the content codes?
1.
Physical cescription 2.
Chemical characteristics, such as analysis of sludges, etc.
J.
TWTF 11 formation requirements appear as Attachment 1.
1 IV.
Nonradiological Ha:ards This section concerns identification of potential nonradiological ha:ards that may exist in the stored transuranic waste.
Nonradiological hazards may include inorganic and organic chemicals, biological agents, and mechanical ha:ards (ga ; cylinders, etc. ).
These wastes are not only radiologically contaminated, but may repeclent a nonradiological ha:ard due to associated enemical, biological, or necnanical prccerties.
f lBR
A.
Chemical Waste:
1 1.
Were elemental chemicals or chemical compounds utili:ed in research experiments, production operations or processes, etc., in facilities generating waste shipoed to INEL?
2.
Were any chemicals included in waste shipments to INEL?
i 3.
If chemicals or chemical wastas were included in waste shipments, what content code (s) were used?
4 What physical form is the chemical waste in?
1 a.
Gas (cylinders) b.
Liquids i
(
c.
Solid or particulate d.
Sludge e.
Other.
5.
What chemical classification?
i I
Inorganic--please detail speci fics, including a.
]
pyrolhorics i
b.
Organic--please detail speci fics.
l S.
Is the volume of each disposed ch(mical waste known?
7.
How was the waste packaged?
i 8.
Was the chemical waste stabili:ed prior to sn4ccent?
If so, j
wnat stabiltration nethod was used?
J 110
)
i 8.
Biological Wa'ste:
1.
Were any biological wastes (animal carcasses, feces, microbes, etc.) in wastes shipped to INEL?
2.
If so, what type of experiments, etc., were conducted?
a.
Radiological b.
Military agent c.
Carcinogenic or toxic d.
Viral or bacteriological.
3.
What type of wastes?
a.
Carcass i
b.
Feces c.
Mi crobes d.
Other.
4 What type of animals or microbes were incluced in waste shi pments?
5.
How large is the volume of animal waste?
6.
How was the waste prepared for snipping?
7.
Are any resicual ha arcs associatec with this waste?
l 1}
4 e C. Mechanical Hazards and Other 1. Have any potential ha:ards, such as pressuri:ed or partially pressuri:ed gas cylinders, batteries, explosives or explosive mixtures, initiating devices or dispersing a devices, enter any wastes shipped to INEL for storage? If
- o, please detail.
2. Have any of the facilities generating wastes shipped to INEL conducted experiments, research, testing, or production of chemical or biological agents for or under the direction of -any military or defense agency? If so, please detail. 112
APPENDIX 3 MOUND SLUDGE ANALYSES G 113
r 9 4 Y. RAD 10ACT!YC SOLUTIC lS FRU.1 DEVELCPMErii GROUPS !!i il!E WD CU!!.DifiG TO IfiFLUEriT TA:lKS: l 1. Trace amounts of U-223, flp-237, Am-241', and Pu-233 2. Trace amounts of radicactivity discarded directly to the liquid sludge in the past. Co-60, Cs-137, Sr-90 tiow it is added directly to cement. 3. Solutions added directly to the sludge without treatment in the WD Bldg.,. Sodium Carbcnate, Sedium Chloride with trace amounts of Pu-238 frem incinerator (developmnt). Estir.:ated 200 sallens over a 3-month period. 1 4 Other sludge frem WD production type incincrator WD Building. 15% fly ash in itaCL Solid. Years 1974 through 1976:flone due to cold testin9 GALLO?!S TYPE TREATMEtiT 1977 350 sludge none 1978 425 1979 162 1980 Jan-June 81 5, Incinerator scrubber solutien to WC influent tank. Contents: Water nearly saturated with flaCl and'other salts, plus various ar. cunts of suspended solids. VOLUME !!! GALLO!!S 1974 ficne 1975 150 1975 300 1977 1600 1978 1900 1979 500 1900 Jan - June tienu at that time 1900 Oct 1 Incinerator to start daily operatient m .....,/... .. ~........ ~...... _.....
f .o I After each ef fluent tank is filled, the treated waste water is sampicd for pH and alpha in the WO and a sample is sent to the Analytical Department .for specific ;21utonium-238, u-234, and H-3. When a specific plutenium-238 count of 1.0 d/m/ml or less and all other discharge str.ndards are met, the waste water is discharged. Effluent waste water that d:;cs not meet discharge standards is reprocessed through the waste disposal system. Sludge Sampling and Spacifications ) A sampic of sludge is tden frem the sludge storage tank and submitted for % solids and Pu-233.-'.ci/kg. In past years, the percentage of solids was 17-20% 3 when a large ar.. cwt of iren was used in treatment, but new with less f ren in the process the relids are in the 25-30% range. An analysis of a recent sludge batch is as, felic,;s: l Moisture 10.5 to 11.5 58.3 wt% pH range = Velatiles 14.3 7.2 Carbon 20.2 ) ~ Ash Emission spec. analysis in % of a dried sample are: I Si,P,AL Fe .6 = .6 Mg Ca Sr = .01 Co,B,Ir = THESE ELEMENTSFO'JND TO BE IN THE 0.6 Na = SLUOGE DUE TO PRECIPITATICN l Cr 0.08 ) = OR ADSORPTION. j Ni 0.08 = 0.09 i Cu = V 0.05 = Ti 0.05 = j Mn . 0.03 = l Pb 0.01 = 0.01 Sn = Density' 1.lgms/cc = 15*. 1 The felicwing Table 4 list the amount of iniiuent, chemicals used, drums of sludge produced, end the mciPu-238 since 1974 115 i
s TABLE 4 INFLUENT CHEMICAL ORUMS OF - Pu-238=:i/ D rum GALLOMS Yl.^ 0. USED/LCS. SLUDGE RAN00M BATC:!ES 915 400' estimated 250mei 1974 10,000 C = 5775 Ca = 2900 Te = 3 renth period 1975 3,204 C 9020 1588 Batch - 19 = 250 mei w 26400 39 = 180 Ca e Fe = 17200 . 73 = 110 1976 2,250 C .= 4000 427 Batch - 89 = 38 mei Ca = 48700 92 = S2 Fe 9500 = 1077 2552 C 7000 200 I B6tch - 94 = 120 inci = Ca = 59300 .99 = 50 Fe = 11200 1978 2514 C
12300 455 Batch -101
71 m:i Ca = 63400 Fe 8020 = 1979 2544 C 8'00 373 estimated ave. = 30 mei = Ca = 71900 Fe 2400 = 1980 952 C 3325 Si esticated ave. = 40 m:i = Jan - June Ca = 30900 Fe 1500 = lis e f%
o o APPENDIX C ROO(Y FLAIS 7412-SLUDGE ANALYSES 1 l l e d
77f>%dbe .w 0 61'4 7 2 -O L L ABOR ATORY SAMPLE RESULTS 'DATE 01/25/30 'I osce fr 59PLE-ID 30-008395 OJC hU"gEa e7c330co ENTRY 0175 11-01-74 AC COUNT C HioG EO o,o 3 7 4, CO*PLETION DATE 01-25-50 BUILDING 550 CLASS SSol C U S T O N.E R ?. T. 300ES A!301S ( /
- ATC"I: ABSORPTION SPECTRC*ETRY RESULTS t'
CA 86612. PPM (W) FE 61597 PPMtWi K 6162 PP"tW) NA 65501. PoMtW}c SI 3650 PPM (W)
- D LU TON !UM C H EM ISTRY LABORATORY RESULTS C
CL(-) 0.16
- (W)
CC3= 0.36
- 7. t W 1 I
F(-) 57 PPM (W) H2O 61.0
- 7. ( V )
C NO3
- 4. 2 A(W)
PO4 0.0025 ?. ( W ) SO4 0.035 P. ( V ) ic l
- SEi!-00ANTATIVE E*.ISS ION S P EC RESULTS AG 53.
PPM (W) i t. 20000 PPM (W)c AS 53. PP"(W) R 100. PD*(W) Sa 133. o"(V) RE 50. PP*(W) BI 53. P3M(W) CA 200000. P 0 * ( W ;t.- CD 1))O. P8"(W) CF 500. PD*(W1 CO 53. P D F. ( W ) Co 500. PP"tW) CS 103). P:"(W) CU 4000. PPM (Wis. FE 50))). P ' ". ( W ) GE 10. PP*(W) HG 10. P D." ( W ) K 40000. 8P*(V) LI 1000. P8"(W)
- G 10000.
P9*(WW MN 5)). 78"(W) "C 500. Po*(WS. I NA 50033. PP=(W) NB SC. PPM (V) i NI 22)). PDM (W) P 1000
- "(W:C PS 5).
PP"(V) 79 500. P2*(W) S3 53. cS"(W) 100000. PPH=> SN 10. P'"(W) SR 10000. PCMtWlc l TA $3. P o.* ( W ) TE 100. PC=(V) TH 53). D'*tW) TI SCO. co"(W) TL 53). PP"(W) U 500.
- D*(v:0 V
5. PP"(W) W 1000. PP"(W) ZN 532. DDM(k) ZP SC.
- Pvt 41 5:
\\ 1
- R13!! chi"ISTRY L A30Rar:1Y DE SULTS l
AM 0.0003317 G/G i t' ' L, ' ils t e
'w, * ~# '061472-01 LAB 0QATORY S AM.PL E RESULTS DATE CL/25/ (? DSGE ~ SAMPLE-10 00-009305 C
- A3 i OC HE MI 5 TRY LAeCRATORY P E SUL T S (CCNT!NUE01
( PU 0.00C0223 G/G U C.0017 G/G [ AUTHORIZED SIGNATURE l / / 49 i -C C e t ~ C l!c l% 1 C t C i O t i C t k C i
- C C
C l O ~ 119 L L-
- [
/ 051 72-01 L%BORATORY SA.*PLE DESUL O aT E 01/25/*0 s 0: GE MD SAMPLE-in 03-009396 OJ O NU"S E 9 Q7038000 ENTRY DATE 11-01-79 aCCCUNT CwAoGED 3037 e CCMPLETICN CATE 31-25-20 9UILDING 550 CLASS S501 'e C US T O.M E 4 P. T. GCSE S AI3OIS 4
- 173*.!: A SSORPTICN SPECTROMETRY DESULTS CA 194597.
PPM (W) PE 47915 PDM (W) MG 95S1. PD9(WI NA 105060. PPM ( Wi e SI 153. PP"(W)
- P L 'J T O N I U M CHEMISTRY LABCRATORY RESULTS C L (-)
3.15
- (W)
C03= 0.74 ?. ( v ) F(-) 101. PP"(V) H2O 55.0
- f. ( v )
e NO3
- .0
- f. ( W )
PC4 0.0025 %(d) 504 0.006
- (W) is
- S E M I-0 U A N T A T IV E E.". I S S IO N SPEC RESULTS
'G 13. POM(V) a t. 10000. PP9(V)'O AS 53. PPw(W) B 100. 92*( W I 34 5?3. Pow (W) BP 1000. P*M(V) SI 53. Pa=(w) CS 200000. PPM ( w)
- CD 1330.
PP"(W) CD 504. c?"(V) CO 53. PPM (WI Cp 500. PPMt w) PD..(W)* CS 133). P P " ( 'a l Cu 500. S PE 5033). PPM (w) GP 10. opM(W) HG 13. PPM (W) K 40000. Do"(V) LI 1300. PDM (V) MG 50000. P e.". ( V ) 'e .9 N 533. PP".(v) FC 200.
- (W)
NA 50333. Po*(W) H0 50.
- P"(WI NI 1333.
CPM (w) D' 1000. P D N ( W ) i> PS 53. PP"(V) PU 100. PPM (V) R3 503. PDM (w) 53 50.
- P"(W)
PP".(V) SN 10. PPw(W)'O SI 130300. SR 10303. PDM (V) T 50. PP*(W1 TE 10). PD*(W) TH $00. PPw(W). TI 533. P:M(W) TL 500. 20 *( N ) 9 U 53). CP"(V) V P'M( W) W 1000. ppd (V) ZN $00. PPM (W) ZR 53. PP*(W) G O 4 9 120 w
061472-01 LABORATORY SAMPLE RESULTS D ATE OL/29/ 9' shGE q, S AMP L E-! O 00 003396 = - - - - - - 6-------------..--.--------------=
- tA3IC 459ISTRY LABCRATORY R E SL't T 5 O
AM 0.00 00054 6 G/G PU O.0000350 G/G U 0.000193 G/G AUTHott2ED SIGN ATUGE O MN O O O O O . O O O O O 4 S O O c w 1 h
- / / *f yd C 614 7 3-01 LaBURATORY SAMPL6 RESULTS af g O L / 2 5 / ?-)
s s PAGE 1* SAMPLE-ID 03-009397 DJC NUMBER 97033009 5.N T R Y CATE 11-01-70 ACCCUNT CHARGEO 8037 e CC97LET!CN OaTE 01-25
- O BUILDING 559 CLASS 5581 CUSTO.uER 8
T. 3CO E S aI SC IS
- iT31!C aBSCRPTICN SPECTROMEToY 'ESULTS Ca 1216 6 L.
PPM (W) FE 49236. P DM( W ). - MG 18377. PPM (W) Na 100l70 P P 9 t V ) 4b SI 217. PP"(W)
- 8 LUTGN !UM C H EM I STRY LAB 02aTooy RESULTS ib CL(-)
1.5 ?. ( W ) CC0= 0.59 7-(W) F(-) 143. PD*(Wl H P.0 60.2
- 7. t V )
Ob NO3 3.1
- (V)
PO4 0.0025
- 7. ( W )
SO4 0.14
- (v)
,e
- S E9 I-0V ANia T IVE EMISS ICN S PEC RESULTS AG
- 40333, PP"(W) at 10000.
P o
- t W I ND as 53.
PPM (W) 8 100. PPM (W) Ba 53. PDM 4V1 BE 1000. 8P"(W) SI 53. PPM (W) CA 200000. PoM( W )
- CD 133J.
CD"(W) CF 500. 8*(W) CD 53. P**(W) Co 500. Po"tW1 CS 133). PP"(W) CU 1000. PDM (V)N8 FE 50333. PPw(W) GF 19. 7 ". t v ) HG 13. PP"(W) K 40000. epg(W) L! 1300. 8P"(W) MG 100000. PoM(Vl'* MN 133.
- PM(W)
"O 200. DM(W) Na 60303. PPw(W) NB 50. PDM (W), NI 533. POM(W) P 1000. P8*tW1# P3 53. PPX(V) 8U 100. P: F. t w i R3 533. P**tWI SE 50. Pc"(V) 51 100J3). PPMtWI SN 10. P C M I W ) h> SR 10))). 'PM(WI Ta 50. Po*(V) TE 13J. PDM (W) TH 500. P "(V) TI 30). 82M(W) TL 500. CP=(W)'e V 5J3. PCM(W) V 5. PP"(v) W 1333. DD*(V) IN
- 500, c o w ( 'i l Z D.
53. P?*(W) 5 4 \\ l i W 122 tp
0 42 Cbl672-OL LABORATORY S AMPL E RESULTS DATE 01/29/91 pace e Sa9PLE-10, 00-003307 f, ) .v
- 113 t C0 4E MI S TRY LABCRATORY RESULTS e
AM 0.000525 M0/C PU O.000004.21 G/G U C.000ft1 G/G AUTHORIZED TIGNATU2E ' e { O hk O O f C 'e b b 4 6 w h Q 123 f.
i 61472-OL LAB 09AT RY SA*PLE RESULTs O&T E 04/12/ "q i. FaGE ,I ' 'AM2L.ic 01-0033c3 DJ 0 NU* *f t 97030000 g .T1T DAT! 02-20-30 ACC OUNT C HARCEO 9037 i .;'* s t. E T I C ' D A T e co-12-83 S UI L O !'a G 550 .ST0 ER GODESIAB0!S I ATC"!: iBSORATICN S o EC TR C.* E T P Y RESULTS CA 77000. Po*(wl FE 52000. PP=(Vig CA 49. ?catw) K 65000. PP=.tvl fia C0000. 7;*(WI St 900. PP=(w) LUTO'lIUM CHEMISTRY LA30RATORY GESULTS C t.2
- (V)
Ct.(-) 0.7A P. ( W ) e C 3= 10 f.(W) F(-) 0.042 ?. ( v ) H 1.2 ?. ( w I H2O 49.C P. ( V 1 .l03 4.1 ?. t v ) t. 2.0 P.(W) p' 3C4 3.2 ?. ( W ) Se e 0.15 .i t w ) U
- 445, pc*(w)
- $ 5#I-0V ANT ATIV E E MIS S I ON S Pfic R ! $ULTS AG P:=(w)
At 5000. P P * ( V (. As 50. P8M(w) B 1 D P *. ( W F EA ! *.: J. P:*(WI flF 500. PP*.(w1 EI 50.
- Prt(w)
(. A 1:0000. PP"(wi. CO ( 1 j00. P:M(W) CF
- 500, 8P*( w)c, C*
55.
- tw) rc 200.
P8*(VI CS 1000 FF"(W) L:u 1000 DPw(wi FE !.0 9 ). P:(w) ti a 1000. CP*('*)e GE l '.). 7: M(V) 110 10 8P"(W) K 10000].
- 'M(v)
LI 1U00 PPw(W)C M.
- 130000, 87M(w)
MN 1
- 7 " t
- F-MO 100.
P;".(wI '1 A 50006 P8*(V) NB $0. P;M(W) NI 700. PS*(Vic P ( 1033. PPmtwl oR 5000. P?"( W F PU 103. 7: M(w1 RB 500. P8"Idi 53 $1 8PM(W) SI 50000.
- P*tWI,
s't 5,;.. P :.". t w l 59 5000. 8 7 * ( v 1-T 50.
- P=(a)
TE 100. SP"(W) TH 503 PP.~(W) TI 10. PS9(Wi TL f g.s. P P = t '. ) y 500. 7: S ( W )g v f.
- (wt W
1000. P 3 * ( 'a l 2N $ 0 *>. Po=(w) 2R 50. PP*tw'g 9 C.' 124 U ..... =..
a s 06L472-01 LA30RATORf SANPLE Rf5 ULT 3 cats 09/12/0 C PAGE . { S a. 00_003303 , __ _"*LE-ID
- RA0!"CHEMISTRY LABORATORY RESULTS I
0.000665 MG/G AM PU 0.0000226 0/G I AUTHOR!Ze0 SIGNATURE C -l flPr h i 1 '6 C F g n ( ~ s 125 (.
s .s C61472-01 LABORATORY SA*PLE RESULTS D aT E 0 9 /12/ E"'. ' PAGE 1 S1"ALE-10 00-008300 DJO NU*BER 47038000 (- E Tay 0175 02-20
- 0 ACCOUNT CHA'GEO 9037 C C."P L E T I: 4 CATE 04-12-80 BUIL0thG 550 CUSTO:'E2 5
000ESISSCIS
- ATC.S.IC AS SORPTION S P E C T R C.". E T R Y P. E S UL T S PPM (W P P ". ( W )p~
CA 75000. PPM (w1 PE 47000. GA 150. PP"(W) K 12000. NA 100000. PPM (WI SI 290. PPM (W) n 81. UTC N I U S CHEMISTRY LABORAT09Y R E S U(. TS C 11.1 P. ( V ) CL(-) 0.23
- 7. ( W )
C CC3= 1.4
- (w) 5(-l 0.032
?. ( v ) H 2.5 P. ( V ) H2O 57.5
- 7. ( W I N
3.4 P. ( V ) NU3 6.3 P. ( V ) c 0.36
- 7. ( V )
P04 6.C (w) 30'. U 346. SPw(9) C" S E M I- 0 U A 't ! A T I V E E.". ! S ! ! ON SPEC RESULTS AG 8.
- Pw(W)
AL 5000. P r * ( W 'c AS 50. Pcw(W) 0 1. P P " ( 'a l-2% 103. 87*(w) BE 100. Po*(W) P'*(V1 BI 90. PP*(W) CA 150000. C0 1900. ?:"(w) CE 500.
- Pw(w)C C:
51 PP"(W) CR 200. PG"(W) CS 1000. PE*(WI CU 1000. P P S ( W fc Pi S0003. P *(=) GA 1000. PDM (W) GE .1 0. PS*(W) HG 10. P84tW) K $O007. P P.* ( '4 1 (. ! 1000.
- (W)
PP"(W)p NG 1)OOOO. PE*(W) MN 1 ,C l 'm. P:"(W) NA 50003 PP*(ii Po"(Vi N3 50. P:*(W) NI 700. P o * ( W )g, P 1000. P : ( '= ) PB 100.
- U 100.
PPS(WI RB 500. D?*tw)
- P*(w$
53 55 P t '. ( w ) SI 50000. SM 2J. P : ". t v ) 58 5000. PP"(v)p Ta 50. P*(W) TF 100. P:".(V) TH $31 3JM(VI T1 10. PP*(w' TL S p.i. 8:*tW) U 500. P *(wt V 5. 37*(4) W 1000. 78*(W) I '. SD?. PA*(V) Z: 50
- "(wig C
L 126 0
. = _ _ e ,o 061'72-01 LA30RATCRY SA"PLE RESULTS DATE 09/12/3 + C PAGE C. - S a."8 L E-Io 00 83 49 _- - - -- - - cd C
- RADICCHEi!STRY LABCRATCRY RESULTS b
0.000619 "G/G A9 FU 0.00003363 G/G C AUTHORIZED SIGPl&TURE l C C e
- C i
? i 1 -l l 1 C 4 I l t {' i c i, i L' ~ j G 8 127 i i {. .}}