ML043100223
| ML043100223 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/28/2002 |
| From: | State of NY, Energy Research & Development Authority |
| To: | Leslie Fields Division of Regulatory Improvement Programs |
| Fields L, NRR/DRIP/RLEP, 415-1186 | |
| Shared Package | |
| ML043130490 | List: |
| References | |
| Download: ML043100223 (95) | |
Text
Item 58 Reports to New York State showing the types and quantities of radwaste from Units 1 & 2 (2001, 2002, 2003)
,j /1' RETURN BY MARCH 1. 2002 NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENT AUTHORITY Radioactve Waste Policy and Nuclear Coordinabon Progrin CODE (official use only)
I I I I I I 2001 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM NOTE Fleaerefer to toe hstrucioni beore orw etng tis arm. Also, see Ptlic Auttcites Lrw. Secton 1854-d(1) and Part 502 ol Chater rof Tite 27 NYCRR (Repcrng Regubbons) proided Wtr tis tam.
FOR THE PERIOD. JANUARY 1 THROUGH DECEMBER 31, 2001 PLEASE TYPE OR PRINT LEGIBLY SECTION L GENERATOR INFORMATION A I Updbud Geneeutr Informton
_Lcrsihg Apencyla lIcense No,).
New York State Depaent of Labor New York State Departonent of Health New York City Deparmerit of Health U.S. Nuclear Regulatory Cormissin Your Facility Email Address Phone No.:
(3,6) 319-Ext. A/A'
... 7 eJ.z X
70, eo, Contact g _
.7 Trtb -
Faciliy Narne 7
/
Stree Address city County ta Zip Code B
iNaeand princpal ofce of fitlity ere LLRW is generated If dilerent from A (boe)
Street address City State lZi Code 3444, Preparer's Name Title Teo ad Extension C.I7 C1,IPCI Teleor* and Eidensim D Identiy, by issuirg autority and nurrber, perrits tWat authorize transfer of your LLRW tb a hlcnsed LLRW disposal lacilty
_suuhg Authortty Dslpoal Sne Locrtion DbpoaI Stbe Use Pernt Number FL CL C
O Ac th c t
code ta best decrbe yo u X
E l FAaLfTY TYE CODE @*. /
lRefar to the inst n 'ons to detrn'ine the fity type code V-rat besl desabes yourx facBt. U e onty one code F l Briefly de e
b e acivtes. procsses, or uses of radlbve materia! a resul inLLRWgewerabon atyvur IEty.
S/Aud 4s-,
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<<F a S2.%
S
' ALT-"/4.I S f o4 VtS4
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A SIGNATURE OF PREPARER.
5,
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Z d-DATE
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- ECTION IL INFORMATION ON LLRW
' 4~sa 4
ce'4v5 A. LLRW AS GEERATED B. ON-SITE WASTE TREATMENT Wusia Waste Sorption or Dnecripion vanagerret Chemnical Form Other Hard Treatnent Solidiffirabon Eted of Post-TreatInent Code t
.Mehod Code Code Code Code Traent Volun tn')
¶23 4
5 6
?
a 32 V
0
_A_
/1a 4
3Z Xe
/
t 3 1 i7/
__/
39 e_
__r 10 40for SEC
_ION 1 of tLELRIVEA REPORTFORM CODES for SECTION Il of the 2D01 LOW-LEVEL RADIOACTIVE WASTE RE-PORT FORM Ak LIMEAS ENERATED WASE DESCRIPTION COOE (Choose the cateirtV that best describes the waste 20 Charcoa!
21 Incanerator Ash 22 Soil 23 Gas 24 0O 25 Aqueous Liquid 26 Filter Media 2?
Mechanical Filter 29 Demolition Rubble 30 Cation Ion-exchange Media 31 Anion lon -exchange Maedia 32 Mixed Bed ton-exchange Media 33 Contaminated Equipment 34 Organic Liquid (except oil) 35 Glassware or Labware 36 Sealed SourcelDevice 37 Paint of Plating 38 Evaporator Botorms, Sludges/Concentfales 39 Dry or Conpactilte t rash (paper. plastic, glass, eIc) 40 Noncomnpactible Trash (metal components.et 1 A1 Animral Carcass 42 Biological Maleria! lexcepl antrnal carcass) 43 Actvated Material 44 Materiattha wil De Incinerated 5S Other (describe) 2 WASTE 1A4AGEMENT NETHM~
Transfer to Authorized Recirrent WI 1ranster o Disposal Sile via W2 Transler to Disposal Site Directly W3 Transter - Other (describe) tnterrn Slorate WA Placed in Storage betore 2000 WS Placed in Storage during 2000 WG Shipped lor Treatment prior to Storage Storame for Decar W7 Storage ftr Decay lOnly lirilted information required See instruclionrs 3
CTERx-AL FOW CODE CI PaPer and Plaslic C2 Glass C3 Metats CA Metal Oxides CS Inorganic Salts C6 Organic Sails C7 Nucteic Acids CB Arnino Acids. Proleins.
Enzymes C9 Carbohydrates. Sugars CID Lipids. FattyAcids C1I Olher Idescribe) 4 OTHER trAA CODE HI tzgnitable H?
Corrosive H3 Toxic H4 Reactve HS Pathogenic H6 Carcinogenic H7 Other(describel H8 None B.
OSITEWASTETREATMENT TREATY IT CODE 7I Corpachion T2 Supercoropaclon T3 Evaporatiortystatizaraon T4 Fluid Bed DryringCatcinalion 15 WetOxidatlion 16 Mernbrane Separaton (ultrafittratlon. reverse osmosis)
T7 Incineration Te Scdiditicabon t9 Adsorption T10 Soning(Segregation TI I Macroencapsulation T12 Absorption 113 Deconlarninaton T14 Surlace Rerioval (scabbitng.
abrasive cleaning)
T IS Dry Chemical Packing (lme) 716 Size Reduction Isectioning, shredding. cutting) 717 SteamnRetorr 71E Catalytic Extraction Process 119 Dewalered T20 Other (descrite) 721 None SOF:r-ATMORSOW17 COOE Sorriton 60 Speed tDri 61 Celetorn 62 Ftoor DrylSuperfine 63 Hi Dri 64 Sale T Sorb 65 Sale N Dri 66 Fbrco 67 Floroo X 68 Solid A Sorb 69 ChernsiJ3 70 ChemnsO50 71 Chemsi 3030 72 Dicaperl HP200 73 DicapertHP500 74 Petroset 75 Petroset U 76 Aquasel 7 7 Aquase 11 89 Other (describe)
Sol'oilottlv 90 Cement 91 Concrete (encapsulation) 92 Biturmen 93 Virnyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required
- ECTION IL INFORMATION ON LLRW_
k LLWF?
AS GENERATED B. ON-SITE WASTE TREATMENT Wa waste Sorptlon or Describoif Managemef Chemical Form Other Hzard Treatmert Solidlficatton el"d Of Post Tretn'wnt Method Code Code Code Code T
nattrtrt Volume (rnl) 1 2
3 4
5 6
.a 3Y IV/
C' WY _
,3 3P ze,,<
3 8
C 9
CODES for SECTION ll ol the 2DD1 LOW.LEVEL RADIOACTIVE WASTE REPORT FORM k
UWR ASGEMIERATED 1WASTE DECRPTtOH COOE (loose the category that best describes Vte wasle 20 Charcoal 21 Incrneralor Ash 22 Soil 23 Gas 24 Ot 25 Aqueous Liquid 26 Fifte Media 27 mechanica Fifter 29 Derroilion Rubble 3D Cation ton-exchange Media 31 Anion Ion-exchange Media 32 Mixed Bed lon-exchange Media 33 Contarnunated Equipment 34 Organic Liquid (except oil) 35 Glasswareor Latware 36 Seated Source/Device 37 Paint or Plating 3e Evaporator BotornOs SludgesiConcentrales 39 Dry or Cornpacliblb Trash (paper. plastic, glass, etc.)
'0 Noncompactible 7rash (meta' component. et.)
41 Anrnia! Carcass 42 Biologica Malerial lexcept aninal carcass) 43 Actrated Material 44 Materiat thae will be tncinerated 59 Otner (describe) 2 WASTE AGEMENT MTHOD Tran sier lo Aunorized Recigen!
WI Transter to Disposal Site via Broker W2 Transler to Disposa! Site Directly W3 Transfer-Other (describe)
Iterren Storame WA thaced in Sbrage betore 2000 WS Placed in Storage during 2D00 W6 Shipped lot Treatrent prior to Storage Storage for Decav W7 Storage bil Decay lOnly limiled inr'iatoon lequied See instructions.)
3 CHEMCAL POWit CODE CI Paper and Plastic C2 Glass C3 Metals C4 Meta! Oxides CS Inorganic Salts C6 Organic Salts C7 Nuider Acids CB Aino Acids. Proteins.
Enzymes C9 Carbohydrates. Sugars CIO Lipids, Fatty Acids CII O.her ldescnbe) 4 OtHER R2FsD CODE HI Igniable-H2 Corrosive H3 Tox0r H54 Reactive HS Pathogenic H6 Carcinogenic H7 Other (describe)
H8 None B.
CSnTE WASTE TRWATWENT 5
TREATWNT CODE T 1 Corriason T2 Supercornpacteon T3 EvaPoMraIOrslCrystallizalon 14 Fluid Bed DryingtCalcination TS Wet Oxidation 16 Merntrane Separation (ultrafittration. reverse osrmsis)
T7 Incineration TB Soiddicatmn T9 Adsorption T10 Sorling)Segregation TII Ma1-roencapsulatlin T12 Absorption 1 13 Decontaminaten 114 Surlace Removal (scabbing.
abrasive cleaning)
T 15 Dry Chemical Packing (rime) 716 Sire Reduction Isectoning.
shredding, cutting) 117 Steamn Relorrm 11e Ca.a1yi: Extraction Process 119 Dewaaeted 120 Other (describe)
T21 None 6
SOt WATIO OR SoRPTIt5 CODE 60 Speedi Dri 61 Celelcrn 62 Floor Dry'Supertine 63 HiDri 64 Safe l Sorb 65 SaleNDri 66 Fbrco 67 Fborco X
68 Solid A Sorb 69 Chems 30 70 Chensl B0 71 Chenssil 3030 72 Dicaperl HP2D0 73 DicapertHPSOO 74 Pelrosel 75 Pelrosel II 76 Aquasel 77 Aquase ll E9 Other (describe)
Solidicaton 90 Cement 91 Concrete lencapsulatton) 92 Bitumen 93 Vinyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required
S.ECTION It. INFORMATION ON LLRW (cont.)
-,.7tA _,-: e~
C. ON-SrrE CONTAINER INFORMATION D. BROKERIPROCESSOR INFORMATION Contalner Uuismum Surface Deserklon Container Volume RWeb Levde Number of code (m)
(mSV/hr Containers Broker Code Processor Code Tratment Code 9
10 II 12 13 14 I5
/3 o
v
)'
/3 6____,_/
3
,/3
/o o
.6
/
/ % '
3/3 2&.s
/00
/
g/o A/c?,v s /3
- .'~ v v
5//
___/
6
/3
____S
_Y
/
_____/fe Is 3
0/- c/
O_
_-_/__
"s 4
t y
/g /
7 EFFECT CFYFAT&bCNT Impact of treatmernt on volume may be shown in percenlorrat.o Noleincreaseordecreaseby I or l. and describe change in chemical and physca form I
POST TREATMENTVOLUME Volume must be noted i crubic meters (n9j C.
ON-=tTE CtAWR IFORyMTS)N S
CONTAINER DESCRFTO COOE 1
Wooden Box or Crate 2
Mela! Box 3
Plastic Drum or Pai 4
Meta' Drum or Pal 5
Metal Tank or Liner 6
Concrete Tank or Liner 7
Potyetnylene I ank or Liner E
Fiberglass Tank or Liner 9
Demineraltzer 1 0 Gas Cylinder 1I Bulk, Unpackaed Wasle 1?2 Unpackaged Components 13 High-Inlegrity Container 14 Fiberboard Drum 19 Otherldescribe) 10 CONTAINER VOIME Volume must be noted m cubic meters irr(
11 l
tXP" S FACE RADIATIDN LEVEL Surlace raiation must be noted in mSvf/r 12 NLUM8ER OF COTAINE1S This information is requred for eadc %aste BRROKEROCESSOR INEOWATM~
13 BROKER CODE BCI NDL BC2 Radiac BC3 Adio BC4 Teledyne eCS US Ecology BC6 Chem-Nuclear BC7 SEG BCE Bionomics BC9 Direct transler BC1D Olhertdescribe)
BC1I None 14 PROCESSO CXE Pl GTS Duralek P2 NSS P3 DSSI P4 Clrem Nuclea', IL PS Alaron Pf Ouadrex. IN P7 Pemrafix. FL P6 AlG. IN PS ATG. WA PI Other (describe).
15 TREATUEhT COE See codes B-'
r you hays retponded 'OTHER lo any rns fewor Inlormaon, pease idenity column. Ine. and waste descripbon(fbomA I) Useaddkonalpagesas necessary
- .7, -/,v 3, V 5-,,.ib,
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, IION II. INFORKATION ON LLRW (cornt.)
C. ON.SITE CONTINJER INwORMAPON D. BROKERJPROCESSOR INFORKATION Co~sta~n~
Maxmum Surface Veicrlioii Container Volume Rac~ation Larvl Numbef of code (mn)
(mSythr)
Conlriners Broker Code PrOceSsOr CoD&
Treatirrent Code 9
20I 12 13 14 6 /0" 1'.
/
Z 3
4 I
I 12 EFFECT F TRATKNlT tmpeci of treament on votlne may be shown in percentorratio Noleincreaseoridecreaseby I or 1. and describe change in chemical and physical form P0S7TREATkENTV U
V MLE Vokjme must be noted in cubic meterS (mi)
ON-WE CONTAER IHF lTK*9 IONTAINER DESCR)ION CODOE I
rooden Box or Crste 2
WWt 1Box 3
Plastlc Drum D! Pal 4
Metal Drumor Pal 5
Metal lank or Liner 6
Concrete lank or Liner I
Polyethylene I ank o Liner E
Fiberglass lank or Liner 9
Deminera!izer 10 Gas Cylinder It Bulk. Unpakaged Waste 12 Unpa:kaged Components 13 HighIntegrty Container 14 Fiberboa-d Drum 19 Other (iescvibel tC NTAINERVOULL Volume must be noted in cubic meters I(d' k
AXIMJ SURFACE RADATY)N LEVEL Suraxe ra iauon must be noted in mSan 12 NLIlKEROFCONTAJNERS This inormabon is required br each waste trxm D.
BRAEMPROCESSOR 13 BROKERCOOE BCt NDL BZ2 Radia:
BC3 Adco BC4 Teledyne BCS US Ecology BZ6 Chem-Nuclear BC7 SEG BS3 Bionornics BCS Direci transfer BZ10 Other(descnbe)
BC1I None 4
PROCESSORCODE Pt GlS Duratek P2 NSSt P3 DSSt P4 Chem Nuclear. IL PS Alaron P6 Ouadrex. T1 P7 Permafix, FL PS ATG. TN P9 AG. WA P1D Otner Idescrite) t5 TRATIMENTCOOE See codes B 5 r you rhtne mspondedOTHER to any Fequnt for briotmilon please idenbtly column, ine. and waste descnpton (Irom A-1) Use addtronal pages as necessary en" /"'/, 2 Z
S
'S*'a/
- ECTION IL INFORMATION ON LLRW (cont)
-> z 110L.5.0 s,;,_ 1-7-- 10 -;1;7-- z:-
ZTRstcFnrePCP TRFTATFWT F. OTHFR CHARACTERISTICS CHARACTERISTIC CHARACTERISTICS Source Material U
Source Weight of Source Effed of Total PoatTrentlnent Mat"Ifil Materia Total SNM Maximujm granus SNMd in any Treartment Volume hj' code (VrMS)
SNU Code (grams) shipment frarna) 2
.,26 -3')
/0___
,,7tg 7
/Jr6-4' a
7496-i-)
776
~ 6 ~ ~ 2_
E PCGT-PROCESSOR TREATMENT 0?ERMTION 1B EFFECT OF TREAT1i'NT See mnstructons for B-7 lt T0JTALPOCT-TREATMENT VLU14 Volume must be noted in cutbi meters ir9)
F.
OTHER CTkRACTERSTlCS It SOURCE MATERIAL OWE Source Matens -
Ente, one cow ver line Use a separate line lot eact lre ol source malena' transterred N'J Natural Uranium OU Depleted Uranium UO Uranium Ores NI Nalura' Thonum T0 Thorium Ores 1i WErTt OF SOURCE PATERIA.
Weight must be noted in grams Ig) 20 SU CODE Special Nuclear Matenal earts one ot the oltlowing SNMi Plutonrum SNM2 Uraiiurn233 SNM3 Uranium enrichet in the isotope 233 or in Ihe isotope 235 SNtN Any matenra artificialy enriched by any of the foregoing 21 TOTALSNM Weight must be noted in grams(g) 22 IUXtttM GRAH6 SSZ IN AN' SHIPMENT Self-explanatory 23 CHELATE CODE CAI EDTA CA2 OTPA CA3 Carbolic Acid CA4 Hydroxy-carbolic Acids CAS Cfr;c Act CAS Gluciic Acid CA7 Other (describe) 2 4 VOLLUE OF LlRW Volurre olLLRWcontainingchelating agents t m' )
2 5 K
TOG Of ULRW Weight of LLRW cantaning chelating agents fIg) 28 WEMAT % CWIATES Weght s ss mtnan 1% need not be reported G.
2?
DPOSL AJND STORAGE ULRWWCLS Class of radioactive waste as described in sections 61.55 and 61.56 of Title 10.
Code of Federal Regulations.
as in eh'e-l on January 260 1983. art.a-hed following instructions AS Class A stable AU Class A unstable B
Class 8 C
Class C In you have reponded
'OTHER to any r*tit for Irnomadce, please identify column. ne, and waste descrpt.on ItromA-1) Use additional pages as necessary.
ITON IL INFORMATION ON LLRW (cont)
-i.i-PROCESSOR TREATUMENT I F. OTHER CHARACTERISTICS CARACTERSTIC CHARACTERISTICS Source Material SNU Source Weighit dSource 3ted of Total IPcet-Trestri-ent Uutbeds m stedaw Total SNV Maximum grams SN11 In any frostrnitnt Volume ~ii')
Code (grams)
M1 Code 1grarnt) shixment fgnams) 4-3 5
E.
P;T.PAZ6SSOt TREATW-Wt KDR~MATIZ1N Is EFFECT OFTREATU NT Seeinctruons bi r7 it TOTAL PcSTTREATWNT YOLtME Volume must be niobd in cubic melers (rr@j F.
OTHER CARXCTEICS 15 SO*CrE ATERL CODE Sowce Matenia - Enterone code.
rert ne Use a separale line hor each type ofsource ma eriat transferred NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natural Thonum 10 I horiumOres it WEtSH7 O SORCE MATEImAL height must be noted in grans (9) 20 SNM CODE Specia' NuceaS Matrenal means one o' the following SNkitl Plutornrunr SNM2 Uraniumu233 R t3 Uranium enriched rn the isotope 233 or in the isotope 235 SIOM Any maleria artificially enriched by any of the toregoing 21 TOTALSNM Weight must be roted in grarmclg) 22 MAX"M GRANS StNW ItKY SHrTM Settesxplnalory 23 CHELATE CODE CA t EtTA CAW DTPA CA3 Cartotic Acid CAA Hycroy -carbolic Acids CA5 Cdrc Acid CA6 Glucnc Acid CA7 Other ides&:ibte) 24 VOLUME OF LlRW Volume of LLRW containing chelating agents (ml")
25
% IGHTOF LU.W Weighitof U.RW conta ning chefalng agents (kg) 2t
%EtGHT% Y CHELATE5 Weights less Ih an 1 % need not be reported D6POSAL AND STORAGE 2?
UL.RWCLASS Classof rarinedtive waste as described in sections 6 1.55and61.56of Iitle 10.
Code of Federal Regutat ons.
as in effect on January 26.
1983. allached following instructrons AS Class A stable AU Oass A unstable 6
Oass '
C Ctass C It you hrfe renponded
'OTHER lo wry reruet ifor hkdoonatin. please identify column. ine. and waste cdnocnplion(from A.1I Use additional pages as necessary
./4,63 *Y rIL o4u 6,Zf At iz
- ECTION IL INFORMATION OH LLRW (conL) 4IER CHARACTERISTICS (cont) (cont G. DISPOSAL AND STORAGE INFORMATION Waste Wlth Chelktin Agent Volume and Weiht of LLRW Chelatel Weight %
Dispositon Dispoeael Sb Storage Sfta Code Volume frm)
.Wedgt0 Cbd LLtW Clan CC Codo 2 __7 s7 DS/l=
/
__Z)
_S/
X5-lX /
4-3 Zs' Z2_
H LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA ULRW Clm F.=rd Codc Volumyn (ml flBSd Radortuclk!"
.- - - IL
- 1.
t-I you ha"e responded 0TME~r to arry request for Informnation, ple~se iderntly coltinn, Ine, and vwrte descriplon (treanA-1) Use addibordpagpoisasnecessary.
21 DSPOSN CODE 0 1 Directiy to disposal D2 1 teatrment pnor to dlsposal D3 Treaomentrelumed for storage D4 lrealnenUnodisposal (decontamrinalton and feuse)
D5 Sloragelrno trea'ment D6 Hold tar decay on srte and dispose as non-radioa:lve 07 hold for decay of site D5 09 and dispose as non-radioactrve Irearrnentlfi site storage Other (describe) 2n D6SPOEALStTE DS1 Bniwet SC DS2 Clive, UT DS3 Richland. WA DS4 Other (describe) 30 STORAGZE SIE St On sne S2 Radiac S3 NOL S4 A~cD S5 Other (describe)
H.
u.RWWrTTH UHACCEPTABLE OWWAL CPrTEI~A 3 1 LL.RWCLASS See codes G.27 32 HAZARD COOE See codes B' 33 VYOtiA Volume must be noted in cubc meters (rn?
3 4 ACThtlY Altrvdy must be reponed mn Meogaecqueiets (iA6q) 35 RAD ESXUDCS As applcable lo H-3
, I)ON IL INFORMATION ON LLRYW (cnt.)
I CHARACTERISTICS (cont) (cord G. DISPOSAL AND STORAGE INFORYATION lste Wh Cbelbtn Apert Volume and Weight of LLRW j
j bet!Welght Y.
Dhpoeltifon Dispozt Site Storag Site bde Volume tr_)
we____
LIRW Class Co
-Codecode
_/
,49-/ Z A5 Jdr 4
/
E 5 6
H LLRW HOT KEETING D(SPOSAL FACILIIY ACCEPTANCE CRITERUA LLRW Cin Hard Code Vohme (ms) p(Bql Radonudidk I
I I__
V Wyou bum taponded 0THER toany reqLeetfoe linformatlon. please idenhify cclurrn, I nee. &nd wiade descrpboni(frtwm A-)
UserAdditiorrolpaginac necessay.
28 0SP Tr)ONCODE D I Dirctt to dsaoSal 02 I reatmenli prior to dtsposa!
D)3 TreatmenL'returned to-storage 4
Treatmentuno disposal ldecontamination and reuse)
DS Storazelne trea ment D6 Hold for decay on site and dispose as non.
rad.oa:tnre r7 Hold otI decay oil slte and dispose as non-radioactive D6 TrearmenVolttste storage D9 Otner (describe) 29 DOCGALSrrE 05 Banmvex SC DS2 Dye. UI DS3 Richland. Wt DS4 Other (describe) 30 s01RfAMs WE SI On siv S?
Radia:
S3 NOL SA Arico SS Otnei diescribe)
R ULRWVMiH LIMCCEPTARTE cxs1cSAL C8OTEtRA 3 1 LLRW CLASS See coocs G il 32 HAZARD COOE See codes 614 33 VOLLRE Volume must be noted in cubc meters Imr) 34 ATMITY Actvity must be reported Ni MegaBecquerets (MBa) 3 A RADpItCHDES As eppykacs e Lc H 3
CTION 11. INFORMATION ON LLRW (cont.)
. Ch'WT EJRSWITH SURFACE RADAT OH LEVELS GPEATER TAhN2mSvhrln r(mAIt U
as Volume on_)
_A_________ud
__(lq)
- CTION Ill. LLRW
SUMMARY
4 4So
,1r.~~
e~"724Z A. 2X1 DISPciALTOTALS D twpowed at Bmw all. SC I D*ostod d: tOlva, UT l~"
>s R:lddi, WrA I
Claa..e Clsa A olu t
AL. fty.
Vdume At')
E (MJ%
Vme On) t D
S7UTarALS BY CLASS Via Brokeu/
1 -7 ;7) 27
/ *3LS)
Vdolume-A AdM+y.A Via Brokert Vdurnt 4 Adtyu 4 Processor Direl Transle_
Via BrmkerJ Vduimet Aceyhy-C ProCe55ar Direct 7 ransfer TALALCLASSES TorAs ACT 1 7"?'4TFZll I
=
St Cas T
VTAl bn a____
Act" Vdume On Ste Ol.Site OnSte A
t 3
6 5
.5__
a ss c V___meC AdMty_-_C
-_e lM vI St S -
3 0366)I 707AL ALL CLASSES
CTION 11. INFORMATION ON LLRW (contQ MCONTAINERS WiTH StRFACE RADIATKtN LEVELS GREATER TWNi 2mSykh, (2COmR1ht t
r a
Vciumelby)
L-I Youm n)kieby Rf ud)de (M3a)
CT1ON EL, LLRW
SUMMARY
K n1MDSPOSALTOTALS I
lhnosd at ERam tdl SC I bso ed ad?
UT I Dtwosod ts:RFslmm WA rlats..
z __
- --I a"s A Vdvume
)
Acoy (VW VOlume bw)
A
(
me TOq SMOTALS BY CMASS Via Brokerl Vdt0*
AA b Yr A
-A Psocem or
__3_
D~fcI Transier
.__9_____/,
CIM Via Brokver Vdusrre.C Acffty.-
Processor Direct Tra tstef TOTALS V
r'
.z9
)
2 2.P
/.63 (s) r l
TOTALAL CLASEMSUW O n S t e tDG Ste CUss C Vokimec.C Adhty.C TtlT S Ls 11 arr SO~lte
__________Mr 70TALALI CLASSES I
ECTION IV. RADIONUCLIDE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED TE Radonucddes mean eacn indvidua; radionudide if knovwn. o, at a minimnum, a!I radionucddes Mnaf have been or would have to be idenbtfd on disposal ste manifests H-3. C-14, Tc-99, and 1-129 must be Identified where present A.1 List he radonucides contained in the LLRW disposed of during 2001 (see response to Secton III-A)
Use additional sheds as necessary.
Padionucllde Act Y (IB Radlonulkie Actlytty (MqN Radonudide Actftty (VBqo 14- /{
Z Zt21142 S)
/3/t 6 i'/ 6 v )
2 7.9 9 S
z 7 A - '
3 I.s9-
,a'4) 6G--
6) 4-6 9-69(6 )
A--,23_?
_2_
/4//- 59 3
)Z, L/3)
/%-23f9
__2_
/0_
All 3
/)
Total achity for all radionuclides listed above Tota! ac tyshould equal bta flor LLRW disposed of, as reported in Secton III-A TOTAL ACTIVIT
-.?,
-/ P e, -,. I I, any od t radionudides l;sed in Table A-1 have half-ffves of less than 90 days, please explain v-y mese are not being held for decay and eventual dsposaf as A
I non-radioative wasle lolV&t 8.1 I
Ut t radionucdde contaned in the LLRW being held In sto2ag for ~e on shte as of December 31. 20)01 Lise *ddttona sheets as rrecissay.
Rad~lonuctlde Racliorudidie Radionveilde Radionuclide Rxdonuciki, RadlonueCkid
./V 6 '
t_
EI 2ILst6
- ,ul contained in the LLRW benq held In storsve for decy Tstte asof Decemnbe 31,2D01 Use addlional sheels a inecssary.
Radloonucllde Radionucilde Radlonuclide Radionuclide Radlonudlide Rdonuclclde A ' 4 1 1 V_
C.1 A On see - List radonudides conti-ied in LLRW in knterbt cto2Z on ske as o' Decenber 31. 2001 Use addttional sheeft as MY.
FRdlonuclide Actlytty (lIk Radionudide Acettvy (Bq Radionudcie AdMV (Il84 AL-3 SA~z-)
,-,3 Ja-6)
S
.6 (3'
__3
_90_
// c K1z) 3
/*66z)
- sL;1
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/ 'et3
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6?-/W S vo s')
('- Gc
/1,0
- 36)
/? -. ;?A'
>?36 Ia) )
-__9 I,$ FZefz) 6~-
2
/.96v)
)
To~al actvity for a1 radionuclides listed above:
Tola aizlly should equa toal for LLRW stored on site, as reported.
TOTAL ACTIVITY
-:b3
- 1) mq C2 Off s0te - List icanuddes contined in LLRW in kftetm s*torage off he as of DeoaT6e 31, 20D1 lstdde lona he as necry.
Radionucide Adty PIBS Radlonicle ktmt fMBq Rdonudcde ActV PI84 1,0/A1&
R Total ativity for all radionudides listed above:
Total acivity should equal total for LLRW being stored off site, as reported TOTAL ACTIYITY MBq l I any of te radiontdides Isted in Table C., or C-2 have haff-lves of less tan 90 days, please explain why tese are no, being held for decay and eventual C5 drsposal as romadtoadlpe waste 4/ 6A/d
SECTIONV. STORAGE FACILITY INFORMATION NC">=: I your facility manages LLRW by storage for decay only, you only need to corrmete the Condensed Form for Decay in II
,e Only.
ONSTE STORAGE FACILITIES
.1 Bnefly describe your on-site LLRW storage facilites. Include falities you have for storage of speal LLRW forms such as freezers, shielded areas for hgh-radiatbon-level wastes or bermed storage areas for liquid wastes, and estmate the storage capacity for each
~
A-At7 rc
- <n o/{
o>l wzs c-a zO~o
,c<Z 4*v S
r /
,Avl tc i
___ia A-/ r
< zrZ.
&',o'r S
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4 z
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f' 2 20t /&
,5 A2 Total Storage Capaity: '/-49 rrr' A3 Estimated maxirmum volume of LLRW hed in storage for decay al any one bme:
C; m3 mD No. Skipto C.
B Do you have any plans for increasing your on-site storage capacity?
C' m
Yes. Complete this secdon.
Describe such plans and indicate your expected new storage capaty.
l OFF-SrE STORAGE FACILITIES I Of-ste storage facility ntorrmabon. Use additional pages ir necessary.
4 47 PRease indicate if of-site strage is for strage for decay or interim storage 0] Stbage for decay 0] Intenim storage Name of fatity.
Address Contat and prlone number NOTE. Please answer the following question btsod on LLRW requfring disposal at kensed LLRW dspogl fWcilles, n LLW held h torgfor decy. Do OT USE DEsDrS ETERWs S
AS uM-rrEn CONlri OR EIT ESTlIIAED STORAGE TIME FOR LLRW REQUIRING DISPOSAL D
Based on your anticied LLRW generaion rate and your articipated capacity lo store waste as of NOTE: Answer mcmlbe In moths December 31, 200,1 HOW MANY MONTHS could you continue to produce and store LLRW on ste it access 1o icensed LLRW disposa facilities were no boner available?
2____
mrttS
SECTN)N V1 FUTURE LLRW GENERATION URE LLRW GENERATION THAT VMLL REQUIRE DISPOSAL Ywj l C-2 AcIttvty (UBq)
Volume (m j
Radlonudide, 2002 A
_ _ )
_ g B
.<g t-y6,-6e,,s
^ r/.-63s -S
- 7.
S99 C
tS 23 e* 1 /W
/
2Y 23 A
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vs Sv'o2 B
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- 7.
&f/g 2003 A
Yoa3 B
C Eo
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, D7 t
p 200 A
/4 B
St t5
-6')
C TciW
('
TA0 Packaaes Greater than 2 mSv at Contact 2001 Package Number 99-001 99-002 99-003 99-004 99-005 99-006 99-007 99-008 Waste Class A
A
-A A
A A
A A
Volume (m3) 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 WeIght (kg) 63 93 100 91 91 95 95 60 Dose Rate (mSv) 4 4
20 3
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CODE (o ficial use only) 2002 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM RETURN BY MARCH 1, 2003 NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENrT AUTHORITY Radioactive Waste Policy and Nudear Coordination Program NOTE Please refer to the Instuctions before completing ttis fan. Also, see Public Authorties Law, Section 1854-dl1) a.d Part 502 of Chapter )a of Tite 21 NYCRR (Reporting Regulations) provided with this form.
FOR THE PERIOD: JANUARY 1 THROUGH DECEMBER 31, 2002 Please Type or Print Legibly
-Place mailing label from front in tne space to the right.
- Mark any corrections in the table below.
Place Mailing Label Here SECTION L GENERATOR INFORMATION A I Updated Generator Information Licensing Agencylies License No(s)
New York State Depatrtent of Labor New York State Department of Health New York City Depattment of Health U.S. Nuclear Regulatory Commission DPR-63 Your Facility Email Address Phone No.:
(315) 349-4982 Ext Skip.Taylor@nmp.cn.com Contact Skip Taylor Tie Supervisor-Radwaste Unit 1 FacilityName Nine Mile Point Nucler Station Unit 1 StreetAddress 348 Lake Road City Oswego County Oswego State NY lZipCode 13126 B I Name and pnncipal citoce of fadity where LLRW is generated If different from A (above)
Street address City County State lZpCode IPrepare s Tim Carroll e Technician C Telephone and Extension D Identify, by issuing acuhoity and nurnber, permits that authorize transfer of your LLRW to a lcensed LLRW disposal faWVty.
Issuing Authority Disposal Site Location Disposal Shte Use Permit Number South Carolina DHEC Barnwell, SC 0004-31-02-X FACILITY TYPE CODE Al Refer to the instrctions to determine the f typ pe code thV best describes your faciy. Use only one code n
4-4-
T-F I Briefly describe the ativities, processes, or uses of radioaive rnateriat that resut in LLRW generation a' your faclity. FrI VLsIgI WVdE VVCdtCL I I I U-U::
I in plant systems. Dry active waste from operation and maintenance activities and plant modifications.
SIGNATURE OF PREPARER:
DATE:
I
SECTION 11. INFORMATION ON LLRW A. LLRW AS GENERATED B. ON-SITE WASTE TREATMENT Waste Waste Sorption or Description Management Chemical Form Other Hazard Treatment Solidification Effect of Code Method Code Code Code Code Treatment Waste Volume (m3) 2 3
4 S
6 7
e 132 WI C4 H8 T19 None 38.5 2
3 3
39 W2 C4 H8 T21 3 39 WI C4 H8 T21 40 Wi C4 H8 T21 s
32 WI C4 H8 T21 6
24 WI C4 H8 T21 7
38 Wi C4 H8 T21 a
32 W5 C4 H8 T19 None 11.0 9
32 W5 C4 H8 T19 None 5.5 10 CODES for SECTION 11 of the 2002 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM A
LLRWASGENERATED WASTE DESCRPT0N CODE Choose the category that best describes the waste 20 Charcoal 21 Incinerator Ash 22 Soil 23 Gas 24 ai 25 Aqueous Liquid 26 Filter Media 27 Mechanical Filler 29 Demolition Rubble 30 Cation ton-exchange Media 31 Anion ton-exchange Media 32 Mixed Bed ton-exchange Media 33 Contaminated Equipment 34 Organic Liquid (except oil) 35 Glassware or Lsbw are 36 Sealed SourceJDevice 37 Paint or Plating 38 Evaporator Bottors?
Sludges/Concentrates 39 Dry or Compactible Trash (paper, plastic, glass. etc.)
40 Noncornpactible Trash (metal comtponents, etc.)
41 Animal Carcass 42 Biolorgica! Material (except anirma carcass) 43 Activated Material 44 Material that wil tbe Incinerated 59 Other (describe) 2 WASTEMANAGEMENT METHOO Transfer to Authorized Recipient W1 Transfer to Disposal Site via Broker V;2 Transfer to Disposal Site Directly W3 Transfer - Other (describe)
Interim Storaqe W4 Placed in Storage betore 2002 W5 Placed in Storage during 2002 W6 Shipped for Treatment prior to Storage Storaqe for Decay W7 Storage for Decay (Skip to hem G30) 3 CHEMICAL FORM CODE C1 Pape, and Plastic C2 Glass C3 Metals C4 Metal Oxides CS Inorganic Salts CB Organic Salts C7 Nucleic Acids CB Amino Acids, Proteins.
Enzymes C9 Carbohydrates. Sugars C10 Upids. Fatty Acids C11 Other (describe) 4 OTHER HAZARD CODE Hi Ignitable H2 Corrosive H3 Toxic H4 Reactive H5 Pathogenic H6 Carcinogenic H7 Other (describe)
HS None B.
ON-SITE WASTE TREATMEKT 5
TREATMIENT CODE T1 Corrpaction 72 Supercompacthon T3 Evaporation/Crystallization T4 Fluid Bed Drying/Calcination T5 Wet Oxidation T6 Membrane Separation (ultrafiltration, reverse osmosis)
T7 Incineration T8 Solidification 79 Adsorprion T10 SortingrSegregation T1 1 Macroencapsulalion 712 Absorption 713 Decontamination 714 Surface Remova' scabbing.
abrasive cleaning)
T15 Dry Chemical Packing (lime) 716 Size Reduction (sectioning, shredding, cutting) 717 Stean Reform T18 Catalytic Extraction Process T19 Dewatered 720 Othe! Idescribe)
T21 None 6
SOLDtFCATiON OR SORN CODE Sorptlion 60 Speedi Dri 61 Celetom 62 Flor Dry.'Superfine 63 Hi Dri 64 Safe 7 Sorb 65 Safe N Dri 66 Florco 67 Florco X 68 Solid A Sorb 69 Chemsit 30 70 Chemsi! 50 71 ChemsDl 3030 72 Dicaperl HP200 73 Dicapert HP500 74 Petroset 75 Petroset it 76 Aquaset 77 Aquaset li 89 Other (describe)
Solidficalion 90 Cement 91 Concrete (encapsulabon) 62 Eiturnen 93 Vinyl Chloride 94 Vinyl Ester Slyrene 99 Other (describe) 100 None Required
SECTION II. INFORMATION ON LLRW (cont)
C. ON-SITE CONTAINER INFORMATION D. BROKERIPROCESSOR INFORMATION Container Maximum Surface Description Container Volume Radiation Level Number of Code (MI)
(mSvlhr)
Containers Broker Code Processor Code Treatment Code 9
10 11 12 t3 1I i5 13 5.5 80 7
BC10 P10 T17 2
13 5.5 20 1
BC11 T21 3
2 36.2 1.5 4
BC10 P1 T7 2
36.2 3.0 3
BC-10 P1 T13 5
13 5.5 400 1
BC10 P10 T17 6
2 2.7 0.001 6
BC10 P1 T7 4
0.2 25 14 BC-10 P1 T2 13 5.5 700 2
BC11 T21 13 5.5 20 1
BC1I T21 10 11 7
EFFECT OFTREATMENT Impact of treatment on volume may be shown in percent or ratio. Note increase or decrease by l or I, and describe change in chemical and physica! form.
POsT.TREATuENTVOLuME Volume must be noted in cubic meters (nrj.
C.
ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE 1
Wooden Box or Crate 2
Metal Box 3
Plastic Drum or Pail 4
Metal Drum or Pail S
Metal Tank or Liner 6
Concrete Tank or Liner 7
Polyethylene Tank or Liner 8
Fiberglass Tank or Liner 9
Demineralizer 10 Gas Cylinder 11 Bulkh Unpackaged Waste 12 Unpackaged Components 13 High-Inlegrity Container 14 Fiberboard Drum 19 Other (describe) 10 CONTAINERVOLUME Volume must be noted in cubic meters (n93.
11 MUIrMUM SURFACE RADiATION LEVEL Surlace radvation must be noted in mSvlhr.
12 NUMBEROFCONTAINERS This information is required for each waste fom D.
R WFRMATi)ON 13 BROKERCODE BC1 NDL BC2 Radiac BC3 Adco EC4 Teledyne BC5 US Ecology BC6 Chem-Nuctear BC7 SEG BCE Bionomics B^9 Direct transfer BC10 Other (describe)
BC11 None 14 PROCESSOR CODE P1 GTS Duralek P2 NSS P3 DSS P4 Chern Nuclear, IL PS Alaron P6 Ouadrex. TN P7 Permafix, FL PS ATG, TN P9 ATG,WA P10 Other (describe) 15 TREATMENTCODE See codes B-S.
If you have responded OTHER to any request for Informnaion, please identify column. line, and waste description (from A-1). Use additional pages as neessary.
Col 13 Line 1,5 Studsvik Cot 13 Line 3,4.6,7 GTS Duralek Col 14 Line 1,5 Studsvik
SECTION II. INFORMATION ON LLRW (conL)
E. POST-PROCESSOR TREATMENT F. OTHER CHARACTERISTICS Source Material SNM Source Weight of Source Effect of Total Post-Treatment Material Material Total SNM Maximum grams SNM in any Treatment Volume (m')
Code (grams)
SNM Code (granms) shipment (grams)
_ _17
___ ___1___
- 7. 1 6:11 6.5 None 0
None 0
0 2
5.5 None 0
SNM1 1.73E-3 1.73E-3 3
None 0
SNM1 8.74E-5 6.64E-5 None 0
SNM1 4.50E-6 1.62E-6 s
7:14 0.8 None 0
SNM1 1.22E-3 1.22E-3 6
/00 0.16 None 0
None 0
0 7
None 0
SNM1 8.52E-5 8.52E-5 e
11.0 None 0
SNM1 5.04E-3 2.96E-3 5.5 None 0
None 0
0 11 PfOST4-ROCESSOR TREATMENT NFORUATON 16 EFFECTOFTREATMENT See instructions for f-7.
17 TOTALfPOST-TREATMENT VOWME Volume must be noted in cubic meters (in).
F.
OTHER CHARACTEPZTICS 1
SOURCEMATERIALCOOE Source Material - Enter one code per line Use a separate line for each IyPe of source rratena!
transferred NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natura Thorium TO Thorium Ores 19 WEIGHT Of SOURCE MATERIAL Weight must be noted in grams (g).
20 SNM CODE Special Nuclear Materia! means one of the following:
SNM1 Plutonium SNM2 Uranium-233 SrJM3 Uranium enriched in Ile isotope 233 or in the isotope 235 SrAu Anymaleriatardificiafly enriched by any of the foregoing 21 TOTALSNM Weight must be noted in grarnslg).
22 MAXIMUM GRAMS SHM IN ANY SHIPMENT Self-explanatory.
23 CHELATE CODE CAI EDTA CA2 DTPA CA3 Carbolic Acid CA4 Hydroxy-carbolic Acids CA5 Citric Acid CA5 GflucinkAcid CA7 Other (describe) 24 VOWMEOFLLRW Volume of LLRW containing chelating agents (rrt I.
25 WEIGHT OF LLRW Weight of LLRW conlaining chelating agents (kg).
26 WEIGHT % CHELATES Weights less than 1% need not be reported.
G.
27 DlSPOSALfAND STORAGE LLRW CLASS Class o0 radioactive waste as described in sections 61.55 and 61.56 of Title 10.
Code of Federal Regulations.
as in effect on Januay 26.
1983. attached following instructions.
AS Cass A stable AU Class A unstable B
Class B C
Cfass C If you have responded
- OTHER-fo any request foe Information, please identify columnn line, and waste description (from A-1). Use additional pages as necessary 4 /L 5*,., /A
SECTION II. INFORMATION ON LLRW (cont)
F. OTHER CHARACTERISTICS (cont)
G. DISPOSAL AND STORAGE INFORMATION Waste With Chelating Agents 1
Volume and Weight of LLRW Chelate Weight %
Dispos'tion Disposal S'e Storage Site Code Volume (TM)
Weight (kg)
Chelates LLRW Class Code Code Code 23 24 25 26 27 28 29 3c C
D2 DS1 2
B DI DS1 3
A D2 DS2 A
D2 DS2 B
D2 SS1 A
D2 DS2 A
02 DS1 B
D 5 Si s
A D5 Si
.,-10..
H. LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA Activity LLRW Class Hazard Code Vodume (in')
(MBq)
Radionuclides 31 32 33 34 35
.I
.I If you have responded 'OTHER7 to any request for information, please identify colunr, line, and waste desription (forom A-1). Use add tiona! pages as necessary.
2t DtSPOSmoNCODE D1 Direclly to disposal D2 Treatment prior to disposa!
D3 Treatinentireturned for storage D4 Treatmenuno disposal (decontamrination and reuse)
D5 Storagelno treatment D6 Hold for decay on site and dispose as non.
radioactive D7 Hold lor oecayofV site DE D9 and dispose as non-radroa:tive Trealzenvoi-site storage Osher (describe) 29 DSPOSA!. SJTE DS1 Barnwert SC DS2 Clive. UT DS3 Richland. WA DS4 Other (describe) 30 STORAGESITE Si On site S2 Radiac S3 NDL S4 Adc S5 Other (describe)
L LtRWWITH UNACCEPTABLE DISPOSAL CRITERIA 31 LLRW CLASS See codes G-27.
32 HAZARD CODE See codes B-t.
33 VOLUME Volume must be noted in cubic meters (rd).
34 ACTIVIT Activity must be reported in Mega~ecquerels (MBq).
35 RADIONUCLtDES As applicable to H-3.
SECTION II. INFORMATION ON LLRW (cont)
L C0~(TAJNERS WTH SURFACE RADLATION LEVELS GREATER THMmSv/r(20OmMih LLRW Class I Volumeirr')
J Activity by Radionuelide (MBq)
See Attached Spreadsheet I
I I
SECTION IlIL. LLRW
SUMMARY
l A.
2002DISPOSALT TOTALS I I Classes I Disposed at: Barnwell, SC Disposed at Clive. UT Disposed at Richland,WA Class A Volume (In')
Activity (MBq)
Volume (In')
Activity (MBq)
Volume (r'r)
Acvty (MBq)
SUBTOTALS BY CLASS Via Brokerl
~A7-A Volune -A Actyllyy-A Pr ESoessor 1.44 5.1 7E4 5.48 4.99E3VdreAA Direct Transfer Class B Via Brokerd O
.4 8 Volume -8 Activity.B Processor 0J.483C I 39 Direct Transfer 5.5 8.98E5 Class C Via Broker/
Volume -C Activity.C Processor 2
=
==
3.8EO[
Direct Transfer TOTALS 9.62 5.82E6 I
TOTALALLCLASSES VOWUE ACTrIIY B. 2002 ITERIM STORAGETOTALS Classes Placed In interim Storage during 2002 Placed In interim Storage before 2002 SUBTOTALS BY CLASS Class A Volume (rri)
Adity (MBq)
Volume (m)
Actlvity (UBq)
Volume -A Activty -A On Site 5.5 2.72E5 5.5 2.72E5 Of Ste 84.1 2.51 E5 84.1 2.51 E5 Clas B Volume - B Actiity B OnlSe 11.0 2.5OE7 11.0 2.50E7 Class C Volume -C Activty C Of She TOTALS VOLUME ACiMTy TOTAL ALL CLASSES 1 00.6 2.55E7 A
J.
SECTION I1. INFORMATION ON LLRW (cont)
L CONTAINERS WITH SURFACE RADIATION LEVELS GREATER THAN 2mSvlhr 200mRlhr)
LLRW Class Volume (ms)
I Activity by Radionuclide (MBq)
See Attached Spreadsheet 5
- 1 SECTION IlIl. LLRW
SUMMARY
A. 2002 DISPOSALTOTALS
-1 q
I Classes l Disposed at Barnwel, SC Disposed at Cive, UT Disposed at Richland, WA Class A Volume (in')
Activity (lBq)
Volume (nm!)
Activity (Maq)
Volume(ff)
Activity (MIBq)
SUBTOTALS BYCLASS Via Broke 3.39 7.96E5 Volume -A Activity -A Processor
.9.
Direct Transfer 10.31 8.53E5 Class B Via Broker/
Volume-B Activity.-
Processor DirectTransfer 5.98 2.29E6 Class C Via Broker/
Volume-C Activity-C Processor Direct Transfer 2.20 3.48E6 TOTALS 8.87 8.01E5 TOTALALLCLASSES V
VOLUME ACTIVITY (18.49 l6.62E6 B. 2002 HiTERIU STORAGE TOTALS Classes Placed In hIterim Storage during 2002 Placed In Interim Storage before 2002 SUBTOTALS BY CLASS Class A Volume (rm)
Activity (MBq)
Volume (nm)
Activity (MBq)
Volume-A Activity
- A On Ste Class B Volume -B Activity - B On Site or Ste_
Class C Volume - C Activity -C ctlSue
_I or1 Ste TOTALS VOLUME ACTTVTIY I
TOTAL ALLCLASSESI
Waste Class A
A A
B A
B Dose Rate (mSv) 80 20 30 20 10 700 mCi OXIVIMB7i mCi 1EM,'*t6; mCi
'44iWl mCi 1iM t
mCi Z;t mCi H-3 0.002+00 0106Et0d O.OOE+00 1.11o oEip.00 O.OOE200 i,0166E+Ob 3.12E+00 '
0.00E+00 J,,dQO,,t O.OOE+O0 1 0%E; C-14 4.02E+02 149EOg4 3.24E+02 2
948E+01 T5iEi3 2.81 E+0 12+01 EZ ti...
7.36E+01 s.jo4 Cr-51 O.OOE+00
__ f60E 0.0021+00 PtOb O 0.002,0.OOE+00 0.0000 O.d 0ooE+400 0~oo6 O.OOE+00 i4,%bCEO Mn-54 1.01E2+04 4.26E+03 1,Po4; 0,d 1.98E+03 zjO 1.132+03 5 4Fl4 1.15E+03 a
1:822+04 Z
Fe-55 1.42E+04 4V2;25 1.15E+04 WWZ%.Sb02~
3.36E+03.
td 1.76E+04 E
2.03E+O' 3E>
2.70E+0' Fe-59 O.OOE2400,.O'O~b, 0.00+00 O.OOE+00 i 06*O00 1.09E+02
.'"AC 4
0,3 0.OOE+OC fmObUO O.OOE+OO dObdb Co-58 0.00E+00 lE+O6 0.00E+00 gO0E~0 0.00E400
'rOtJ~pO 4.73E+01,
2.31 E+01 '
9.25E+02 FI4- ;O4 Co-60 1.012+04 jsW3t.%.
8.16E+03.
,C06 2.38E+03 3.872+03 ;,li 32d0 1.44E+03 o5 5.OOE+04 8
Ni-59 0.002400 1'0tROEtO O.OOE2400 9IOQ.Ob, O.OOE+00 <,:'tOATb O.OOE+00 O.OOE+000 bat0,0'gd O.OOE+O0.§1-0 Wod Ni-G3 1.22E+02 1FOd 9.82E201,
0'3 2.87E201 1I06E,3 2.14E+02.
1.73E+01,
2.33E+03 1XEI Zn-65 0.002+400 OVQr.d.0fl 0.OOE+00 Obdb
.002+00 ~,0YE.
O0.OOE+00 Oofd
.OOE+00 O.OOE400 Sr-90 1.14E+00 1.09E+ 00A 061 4.79E-01 i b7 2.48E+00 $
,1 2.76E-01 t~fldi 8.90E+00 Nb-94 O.OOE+00 RN0o TO 0 O.OOE+00,.of o
00E+00 6,
o.OOE+400 ad(0tjp O.OOE+00 E
B O.OOE200 Tc.99 0.00E2+00 O1~
~
.002+00 &L 6
O0.00+0 bo 00E0E0+00 00 fl0b1O 0.02 00 0 0iE4 Tc 99OOEO Bt00Stt OOEO f5&~l5d so~aWf'dt o.OOE+00
.X O.OOE+oOO,
,06 O.OOE+00 ¢B°o Ag-110m 1.15E+02 0.OOE+00 1-p0 -T O.OoE+00 O.OOE+00 t 1.43E+01 4M R
2.49E+02 Sb-124 O.OOE+00 O.OOE200 Mf l
.OOE+00 E
0.002+00 O.OOE+00 O.OOE+W00 1 J44o Cs-134 0.002E00 WThMOboE O
O O.OOE+00 tIrI 0O.OOE200 j 0.002+00 4
0.00.0OE+O00
&bO 06w 0
OOE+*.O Cs-137 1.59E+02 1.52E+02
,2 6.68E+01 3
1.13E+03 7.%Wt~b41 3.85E+01 3
5.37E+03 f 9 EM, Ce-144 0.002+00
)OQ0OO 9.872+01 ObOOO)O 4.322+01 '.Ji6O2'+Q, 1.46E+02 5'.OE+?03 2.53E+01 7.92E402,
Pu-238 O.OOE+00 eKo.:'oEj o O.OObOO,OOCb O.OOEO.OE+O
-Wb,,tO',O-OO 1.8E0 *ff*zR O.OOE+OO 'W-t#Et 2.4-1Pt~
P280.0+0$,'OOb 0020 obdo 0.002+400
- 62
~
118-1 43Y ~
00240 d1t5OM8 2.842-01 1j,5%Qpf Pu-239 O.OOE+00 N,'0%dVOb O.OOE+OO
.6tOb~
l O.OOE2400 f O',Obd 8.14E-02 O.OOE+00
..dE!i6o 1.23E-01
_b2d-;
Pu-241 0.002+00 O.OOE+O 0.0020 O.OOE 0.002C00 tOd 5.342+00 E+OC B
0.002+00.
7.952+00 t42 Am-241 0.02+00 J
O.OOE+OO4O3Oo.002R O.OOE+00 iQd~4iO 4.54E 01 Sir8E, 0.002+00 Q2002,6O 9.992-01,
2.182-02 I,8;O, 2.15E-02 9.390 i EI 1.72E201 OAd0 5.562-03,
3.142+00 E
Cm-243 0.00E+00 O bE O.OOE+00 O.OOE+O0 7.33E-02.i O.OOE+00 f&C%0 1.56E201 ;L il Total 3.52E+04 0
2.46E+04 7.95E+03 L#
t 4~
2.43E+04 $ A lO.
4.80E+03 ?
S 3.482+05 '
t
.Tld
.8+
IZIZLZZ I
B A
A A
B 400 20 10 20 500 mCI mCi
,.6I2 mCi mCi ioMlB$A mCi Jb 7.49E+00 O.OOE.O00
$ 0.OOE+00 O
.OOE+00 VVr6o09 O.OOE+00 !^#'QtJOQ 4.54E+01 Jlo~Z 8.97E+01 l
8.97E+01 5 TQO3 1.04E+02
,2V_.
3 O.OOE+00 0O.dtW O.OOE+00 _
O.OOE +o00 t5.dEt O
O.OOE+00 MOr$l 1.74E203 _
4.86E+03,V9'EO$
4.52E+02 7
6.+02
§M02 5.16E+02 2.75E+04 IMUe 3.10E+04 D,.5El;.6 1.59E+03 i8E.
3.12E+03
- 2.88E+03 2.37E+05
- 0. 6 O.OOE+400 o.ooE400 O.OOE+00 0.002+00 tiiO1Ol°.li 2.75E+03 A W.rM O.OOE+00 !
O1t 1.18E+01 m O.OOE+00 O.OOE+00 W 2.45E+03 gr=,.
2.752+04 51~E~idE 1.13E+03
+j8gb,4 2.232+03 B' 2.14E+03.
4.48E+04 2.O+0~lc~O~
~o+ofY d;:
.23E+0 b6~
.0+0
~
~
4.4E+024 2.41E+01
,21W,02 0.00E+00* #mPQUgOi O.OOE200 0,6E110 O.OOE+OO O.OOE+OO,
0.14E+02 Mf60 +E 1.37E+01 ;A W
2 2.71E+01 t
. t 2.71E+01 M
~
12.06E+03 4'
4 O.OOE+OC t o
0.002+00 O
0.002+00
, u4o6 O.OOE+00 1.140E+02-0
- 3. 16GE +OO V Wji, 'r0t02 1.GSE-01 ;'A>0,;.;E{0 3.23E-01 > gEot 3.20E-01 ;.tlS+6 1.29E+01 MMMM-12g O.OOE+0O 0 ftp00+0 IdO O
O.OOE+OO jg.ot,0 O.OOE+00 ti'0~d O.OOE+OO 1meQfp i
O.OOE+0O 1sA Ojb o 0.OE+00 dO6ET tI 0.00+00 0b6E0p O.OOE+00itEA26 O.OOE+0O 0 9~O+O\\wta.
.50E+00 MJ2o O.OOE+0O0
.ti O.OOE+OO X.t
.9E0 t$f O.OOE+00o~oOM Z40+/-
ooooac,.dt O.OOE+OO00te O.OOE+OO f.^11+00d 1t07E+02 fAVIN M O.OOE1+OO 9.,hy'WOfkoO O.OOE+OO Zom'i6bag O.OOE+OO U.PA00p O.OOE+OOfm-t6.M;".
O.OOE+O0 OVgt~Et 8.23E+03 ;~:5g 2.3t +t1 M~x 45E+01
-DM-plVSX 4.47E+01 %W-UiMtj 7.6E0 t
8 O.OOE+O0FO.
.~¢60EtOb 1.42E+01 go-Ampo 2.72E+01.oiM
.6E0 61>r~.
1.13E+03 COARR.YP,6 6.36E1-02 g§it~g OOEO
.O+Og 6,:&¢
.O+OQ
-S 4.05E-01. wi3tst 4.29E-02 3Z.ML0~592,,6 O.OOE2+OC tjDEodAfg O.OOE1+O0~JOX "gOQto O.OOE+OO Vd',
0 1.75E-01 IMtW848S~
5.8EO1,,tl~'af5S O.O+Ci;Ed,~yO O.OOE+O 40,0
¢
,0 O.OOE+O
§ 00 1.13E+1 401o 2.8-1,t,^$4toO.OOE+O00~t-'EO O.OOE+OO %OV, d,,~dOd, O.OOE+OO0 1.43E+OO R"Mitx116WE11 1.85E 0 t.t4 2.97E-'&1j0t3,a5.O-3*tt--j2 3.4E0 o.,.,t,86 4.30E 00 '...............t5w6 5.84E-0 a2j~~'%.8'o
.OO+OitoWitd O.OOE+O ~~008 PZ0-0 O.OOE+OOIW,,
O.OE+00 2.23E-01 MMY;S 7.23E+04 JW;H-s67,04 3.29E+03
,410 6.20E+03,,,%X0 5.72E+03 $*g2~t 3.28E+05 WEp
I I
A A
25 20 mci O"Wb" cl MIA-MIM
-7.0-2.77E-01 OE+00 3.10E+01 7.55E+01 0.00E+000401-001.0 O.OOF-+00 ta"Mm"'A 1.20E+02 1.07E+03 3.7OE401 2.69E-03 O.OOE+00 O.OOE+00 7.77E+00,,K40W,-,TO 0.00E+oo G.57E+021riflv5Tb4 1.90E+03,fXvf45t63 5.83E-02j.r-,,U0rTm O.COE40011*91n, 'data 1.01E+01 INI't-W1,402 2.28E+010911-02 O.OOE+00 PROM"M 0.00E+oo WIN 1.17E+00 6.74F:400 OM O.OOE+00 O.OOE400 O.OOE+00, 1.63E+01 O.OOE+00 INqd,M'O.
O.OOE+00_$=,,_LM6 I
0.00F-+Oo I M.,
9.39E+02 Wfj 6.21E402 8.69E-03&ftdV 400 Ur O.Oor-fft_%T,00
-03 JUNIN 5.19E O.OOE400 9.27E-02 d
O.OOE+00
.,b o.ooE+oo 1.37E-01
%Q0 O.OOE+00 MKia-016b 7.34E+03
SECTION IV. RADIONUCLIDE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED NOTE: Radionucides mean each individual radiontclde i known, or, at a rrninirum, all radionuclides that have been or would have to be identified on dispsa! she malffests. H-3, C-14, Tc-99, and 1-129 must be identified where present A. is! the radionuddes crntained in tie LLRW disrosed of durixo 2002 [see resmnse tI Sedin 111-A [se adfiflnnal sheetsn a nA-tcssrv Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activty (MBq)
H-3 4.01E2 Cs-137 3.65E5 C-14 3.76E4 Ce-144 9.72E3 Mn-54 7.53E5 Pu-238 6.91EO Fe-55 2.71E6 Pu-239 4.77EO Fe-59 4.03E3 Pu-241 2.16E3 Co-58 3.04E3 Am-241 2.60E1 Co-60 1.80E6 Cm-242 9.03EO Ni-59 8.92E2 Cm-243 5.OOEO Ni-63 4.22E4 Sr-90 3.40E2 Ag-11Om 5.14E3 Total activity for all radionuclides listed above:
Total acviy should equal total for LLRW disposed of, as reported in Section III-A.
TOTAL ACTIVITY I
6.62E6 If any of the radiroucides Esled in Table A-1 have haflives o' less than 90 days, please explain why these are not being held for decay and eventual disposa! as A.2 nr-radioactive waste.
None B.1 I List the rafionucdides ntained in the LLRW being held In storage for decay on shte as o! Decermber 31. 2002. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide None 1n.2 l
t eratdacie;rontained in the LLRW b2ing held in storage for dec y off sit as of December 31. 2002. Use additional shees as necessary.
Radionuclide Radionuclide Radionuc ide Radionucdide Radionuclide Radionuclide None
C.1 I On site - Lis' rasionurliies ontained in LLRW in interim storaae on site 1
nf IPmhpr 11 n
MP addfinml chn*"
Radionuclide Activity (MBq)
Radionuclide Actirty (MBq)
Radionuclide Activity (Msq)
C-14 9.36E3 Zn-65 4.22E3 Pu-241 7.12E2 Cr-51 6.44E4 Sr-90 1.06E3 Am-241 8.99E1 Mn-54 1.73E6 Ag-11Om 2.07E4 Cm-242 2.80E2 Fe-55 1.89E7 Sb-124 3.96E3 Cm-243 1.40E1 Fe-59 1.02E5 Cs-137 5.18E5 Co-58 1.25E5 Ce-144 9.41E4 Co-60 3.58E6 Pu-238 2.55E1 Ni-63 1.63E5 Pu-239 1.01E1l Total actvity for all radionuclides rfsted above:
TOTAL ACTIVITY 1
Total xcvity should equal total for LLRW stored on srte, as reported.
MBq J C.2 I Off site - Lit radionucEdes contained in LLRW in interim storuae off site as of December 31, 2002. Use additional sheets as nrzo Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Actty (MBq)
H-3 1.05E1 Sr-90 5.52E1 Am-241 9.46E-1 C-14 4.47E3 Tc-99 3.09EO Cm-242 1.47e-1 Mn-54 2.35E4 Cs-1 34 2.70E2 Cm-243 2.74E-1 Fe-55 1.08E5 Cs-137 6.74E3 Co-58 2.87E2 Ce-144 1.38E3 Co-60 1.04E5 Pu-238 3.28E-1 Ni-59 2.16EO Pu-239 1.97E-1 Ni-63 1.38E3 Pu-241 3.79eO Total activity for at radionuclides listed above:
Total activity should equa! total for LLRW being stored off site, as reported.
TOTAL ACTIVITY 2.5()E5 MBq If a.y rof the radionudides fsted in Table C-1 or C-2 have halfflives of less 1han 90 days, please explain why these are not being held for decay and eventual C.3 disposal as non-radioactive waste.
None
SECTION V. STORAGE FACILITY INFORMATION NOTE: If your facility manages LLRW by storage for decay only, you only need to complete the Condensed Form for Decay in Storage Only.
ON-SITE STORAGE FACILITIES Y
A.1 I Briefiy describe your on-she LLRW storage faclities. Indude fazTuies you have for storage of special LLRW forms such as freezers, shielded areas for high-radiation-level lwastes, or bermed storage areas for Squid wastes, and estimate the storage capacity for each.
Storage facility consists of 2 concrete pits at Unit 1 and 3 concrete rooms at Unit 2 with sufficient storage capapcity for Unitl and Unit 2 for 20 years.
A2 Total Storage Capadty
!360 M3 A.3 Estimated maximum volume of LLRW held in storage for decay at any one time: 55 m3 l i No. Skip to C.
B Do you have any plans for increasing your on-she storage capacity?
DJ Yes. Complete this section.
Descibe such plans and indicate your expected new storage capacity.
OFF-SITE STORAGE FACILITIES C
Off-site storaoe facTity information. Use additiona pages i necessary Please indicate if oft-site storage is for storage for decay or interin storage.
li Storage for decay DII Interim storage N Studsvik Processing Facility GTS Duratek Address:
Erwin, TN Oak Ridge, TN ContactandplhonenuLber Dave Schlosser 423-735-6300 Dennis Hennen 865-220-1632 NOTE: Please answer the following question based on LLRW requiring disposal at licensed LLRW disposal facilities, not LLRW held in storage for decay. DONOTUSEDESCRFrrVETERMSSUCHAS UMITED, COtlONUOUS, ORfINDEFwrEX ESTIMATED STORAGE TIME FOR LLRW REQUIRING DISPOSAL D
Based on your anticpated LLRW generation rate and your ankcpated capacity to store waste as of NOTE: Answer mustbe In months.
December 31, 2002. HOW MANY MONTHS could you continue to produce and store LLRW on site i access to lensed LLRW disposal facilities were no longer available?
240 none's
SECTION VI. FUTURE LLRW GENERATION FUTURE LLRW GENERATION THAT WILL REQUIRE DISPOSAL yew c lass Acfivity (MBq) volum(M Radionucrides 200 A
1.85E7 60 H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-58, 5.55E6 5
Co-60, Ni-59, Ni-63, Sr-90, Tc-99, Ag-11 Om C
4.00E7 5
Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, ioa 6.41E7 70 Am-241, Cm-242, Cm-243.
20O4 A
1.85E6 60 Same as 2003 B
5.55E6 5
C 7.00E8 5
Tobl 7.07E8 70 2005 A
1.85E7 60 Same as 2004 B
5.55E6 5
C 4.00E7 5
Tou 6.41E7 70 200 A
1.85E6 60 Same as 2005 B
5.55E6 5
C 7.00E8 5
T&al 7.07E8 70 2007 A
1.85E7 60 Same as 2006 B
5.55E6 5
C 5.55E6 5
Total 6.41E7 70
Z,/V/
/
2ct3
. RETUR1 ANNUALLY BY MARCH 1 st TO:
NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENT AUTHORITY Radioazlive Waste Policy and Nuclear Coordination Program 17 Columbia Circle Albany. NY 12203-6399 tIrwadmin@NYSERDA.ORG NOTE: Please refer to the Instructions before completing this form.
FOR THE PERIOD: JANUARY 1st THROUGH DECEMBER 31st CODE (official use only)
I I I I I I LOW-LEVEL RADIOACTIVE WASTE REPORT FORM PLEASE TYPE OR PRINT LEGIBLY
-Place mailing label from postcard in the space to the right
- Mar. any corrections in the table below Place Mailing Label Here (Leave Blank If Submitting Electronically)
SECTION 1. GENERATOR INFORMATION A
Updated Generator Information ENTER 4-DIGIT GENERATOR ID (can be found on the mailing label on annual postcard) 0072 ENTER REPORTING YEAR 2003 Licensing Agencylies License No(s).
New York State Department of Labor New York State Department of Health New York City Department of Health U.S. Nuclear Regulatory Commission DPR-63 Your Facility Email Address Phone No.: (315)349 -2749 Ext.
Thomas.Paeno@constellation.com Contact Thomas Paeno Title Radwaste Manager Facility Name Nine Mile Point Nuclear Station Unit 1 Street Address 348 Lake Road City Oswego County Oswego State NY Zip Code 13126 B
Name and principal office of facility where LLRW is generated if different from A (above)
Street Address City County State Zip Code C
Preparer's Name Tim Carroll Title Technician C Telephone and Extension (315) 349 - 4116
D Identify, by issuing authority and number, permits that authorize transfer of your LLRW to a licensed LLRW disposal facility:
Issuing Authority Disposal Site Location Disposal Site Use Permit Number South Carolina DHEC Barnwell, SC 0004-31-03-X FACILITY TYPE CODE Type in the appropriate letter and number fo, the appropriate code OR choose one from EACH DROP-DOWN MENU BELOW. Refer to the instructions to determine the facility type code that best describes your facility. Choose only one code consisting of a letter and number.
E Choose a Letter: A. Nuclear Power Plant Choose a Number: 1. Boiling Water Reactor F
Briefly describe the activities, processes, or uses of radioactive material that result in LLRW generation at your facility.
I.
Processing waste water for reuse in plant systems. Dry active waste is generated from operation and maintenance activities and from plant modifications.
This Repori Form has been submitted by lhe preparer listed in item l(C) above. In submitting this iorm, preparer hereby cerifies DATE: 228I4 N 3' 5
that the information set forth is true to the best of the prepare.'s knowledge.
SECTION 11. INFORMATION ON LLRW A. LLRW AS GENERATED Waste Waste Chemical Form Other Hazard Description Management Code Code Code Method 1
2 3
I 4
1 321 WI C4 H8 2
32 Wi C4 HB 3
39 Wi C4 H8 4
40 WI C4 H8 5
59 Wi C4 H8 6
32 W5 C4 H8 7
10 CODES for SECTION 11 of the LOW-LEVEL RADIOACTIVE WASTE REPORT FORM Note: It you respond 'other' to any item, please provide an explanation on the Attachment Sheet provided in Section VIl.
A.
LLRWAS GENERATED 1
WASTE DESCRIPTION CODE Choose the category that best describes the waste.
20 21 22 23 24 25 26 27 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 59 Charcoa!
Incinerator Ash Soil Gas Oil Aqueous Liquid Filter Media Mechanical Filter Demolition Rubble Cation Ion-exchange Media Anion Ion-exchange Media Mixed Bed Ion-exchange Media Contaminated Equipmen:
Organic Liquid (except oil)
Glassware or Labware Sealed SourcelDevice Paint or Plating Evaporator Bottomsl Sludges.'Concentrates Dry or Compactible Trash (paper, plastic, gtass. etc.)
Noncompactible Trash (metal components. etc.)
Animal Carcass Biological Material (except animal carcass)
Activated Materia!
Material that will be Incinerated Other (describe) 2 WASTE MANAGEMENT METHOD Transfer to Authorized Recipient W1 Transfer to Disposal Site via Broker W2 Transler to Disposal Site Directly W3 Iransfer - Other (describe)
Interim Storaqe W4 Placed in Storage before current reporting year W5 Placed in Storage during current reporting year W5 Shipped for Treatment prior to Storage Storage for Decay
%%7 Storage for Decay (Only limited intormation required See instructions.)
3 CHEMICAL FORM CODE C1 Paper and Plastic C2 Glass C3 Metals C4 Meta! Oxides CS Inorganic Salts C6 Organic Salts C7 Nucleic Acids C8 Amino Acids, Proteins, Enzymes C9 Carbohydrates, Sugars C1D Lipids, FattyAcids C11 Otner (describe) 4 OTHER HAZARD CODE HI Ignitable H2 Corrosive H3 Toxic H4 Reactive H5 Pathogenic H6 Carcinogenic H7 Other (describe)
H8 None
B. ON-SITE WASTE TREATMENT Treatment Code Sorption or Solidification Code Effect of Treatment Post-Treatment Volume (M3)
S 6
7 8
T19 NONE 11.0 2
T19 NONE 6.8 3
T21 4
T21 S
T19 NONE 5.5 7
10 11I B.
ON-SITE WASTE TREATMENT 5
TREATMENT CODE T1 Compaction T2 Supercompaction T3 Evaporation/ Crystallization T4 Fluid Bed Drying/ Calcination T5 Wet Oxidation T6 Membrane Separation (ultrafiltration, reverse osmosis)
T7 Incineration TE Solidification T9 Adsorption T10 Sorting.!Segregation Ti 1 Macroencapsulation T12 Absorption T13 Decontamination T14 Surface Remova; (scabbing, abrasive cleaning)
T15 Dry Chemical Packing (lime)
T16 Sze Reduction (sectioning.
shredd~ng. cutting)
T17 Steam Refomm T18 Catalytic Extraction Process T19 Dewatered T20 Other (describe)
T21 None 6
SOLIDIFICATION OR SORPTION CODE Sorption 60 Speedi Dri 61 Celetom 62 Floor DryfSuperline 63 HiDr 64 Safe T Sorb 65 Safe N Dri 66 Florco 67 Florco X 68 Solid A Sorb 69 Chensi 30 70 ChemsO 50 72 Dicaperl HP200 73 Dicaperi HP500 74 Petroset 75 Petroset It 76 Aquaset 77 Aquaset II 89 Other (describe)
Solidification 90 Cement 91 Concrete (encapsulation) 92 Bitumen 93 Vinyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required 7
EFFECT OF TREATMENT Impact of treatment on volume may be shown in percent or ratio. Note increase or decrease by 8 or9, and describe change in chemical and physica' form.
8 POST-TREATMENT VOLUME Volume must be noted in cubic meters (').
SECTION 11. INFORMATION ON LLRW (cont.)
C. ON-SITE CONTAINER INFORMATION D
- 0. BROKERIPROCESSOR INFORMATION Container Container Volume Maximum Surface Number of Description Radiation Level Containers Broker Code Processor Code Treatment Code Code in)(mSvlhr) 1 21 rcso 9
1QCt 12 13 14 a
7 5.5 20 2
BC10 P10 J
T17 7
3.4 600 2
BC10 ]
P10 j
T17 2
72.5 1.7 7
BC-10 P1 i T7 2
36.3 0.3 3
BC10 P1 i T13 2
27.2 0.001 2
BC10 P10 T20 7
5.5 30 1
B010 P10 T17 81 1
10I i:l C.
ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE I
Wooden Box or Crate 2
Meta! Box 3
Plastic Dnurr. or Pail 4
Metal Drum or Pai:
5 Metal Tank or Liner 6
Concrete Tank or Liner 7
Polyethylene Tank or Liner E
Fiberglass Tank or Liner 9
Derninera!izer 10 Gas Cylinder 11 Bulk, Unpackaged Waste 12 Unpackaged Components 13 High-Integrity Conrainer 14 Fiberboard Drum 19 Other (describe) 10 CONTAINER VOLUME Volume must be noted in cubic meters (m').
11 MAXIMUM SURFACE RADIATION LEVEL Surlace radiation must be noted in mSvlhi.
12 NUMBER OF CONTAINERS This information is required for each waste form.
- 0.
BROKERIPROCESSOR INFORMATION 13 BROKER CODE BC1 NDL BC2 Radiac BC3 Adco BC4 Teledyne BC5 US Ecology BC6 Chem-Nuclear BC7 SEG BC8 Bionomics BC9 Direct transfer BC10 Other (describe)
BC11 None 14 PROCESSOR CODE P1 GTS Duratek P2 NSSI P3 DSSI P4 Chem Nuclear, IL P5 Alaron P6 Ouadrex. TN P7 Permafix. FL P8 ATG TN P9 ATG. WA P10 Other (describe) 15 TREATMENT CODE See codes E-5.
SECTION II. INFORMATION ON LLRW (cont.)
E. POST-PROCESSOR F. OTHER CHARACTERISTICS TREATMENT INFORMATION F TE HRCEITC Source Material SNM Effect of Total Post-Treatment Source Weight of Source Total SNM Maximum grams SNM in any Treatment Volume (in3)
Material Material SNM Code (grams) shxipment (grams)SMi n
Code (grams)
(grams) shipment (grams) 16 17 18 19 20 21 22 6:1 66.2 NONE 0
NONE 0
0 8:1 0.8 NONE 0
SNM1 4.78E-4 3.22E-4 12:
41.6 NONE 0
SNMI 5.41E-5 1.48E-5 10:
11.2 NONE 0
SNM1 5.88E-6 3.52E-6 5
NONE 0
NONE 0
0 7
NONE 0
SNM1 2.42E-5 2.42E-5 10 11 E.
POST-PROCESSOR TREATMENT INFORMATION 16 EFFECT OF TREATMENT See instructions for E-7.
17 TOTAL POST-TREATMENT VOLUME Volrne must be noted in cubic meters (m 3).
F.
OTHER CHARACTERISTICS 18 SOURCE MATERIAL CODE Source Material C Enter one code oer line. Use a separate line for each type of source material trarsferred NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natural Thorium TO Thorium Ores 20 SNM CODE Special Nuclear Matena! means one of the following:
SNIM1 Plutonium SNM2 Uranium-233 SNM3 Uranium enriched in the isotope 233 or in the isotope 235 SNM4 Any material artiricially enriched by a-y of the foregoing 21 TOTAL SNM Weight must be noted in gramsig).
22 MAXIMUM GRAMS SNM IN ANY SHIPMENT Setlf-explanatory.
19 WEIGHT OF SOURCE MATERIAL Weight must be noted in grams (g).
SECTION 11. INFORMATION ON LLRW (cont.)
F. OTHER CHARACTERISTICS (cont.)
G. DISPOSAL AND STORAGE INFORMATION Waste With Chelating Agents Chelate Volume and Weight of LLRW LLRW Disposition Disposa Site Code Storage CeteWeight
% Chelates Class CdDipslStCoe Site Code Code Volume (i')
Weight (kg) 23 24 25 26 27 26 29 3X 3.
A D2 DS2 2
A D2 DS2 3
___A D2 DS2 4
_A D2 DS2 s
D2 DS4 6
A D2 DS2 S5 7
10 i I _ _ _
3 CHELATE CODE CAI EDTA CA2 DTPA CA3 Carbolic Acid CA4 Hydroxy-carbolic Acids CA5 Citric Acid CA6 Glucinic Acid CA7 Other (describe)
G.
27 DISPOSAL AND STORAGE LLRW CLASS Class of radioactive waste as described in sections 61.55 and 61.56 of Title 10, Code of Federal Regulations, as in effect on January 26,1983, attached following instructions AS Class A stable AU Class A unstable e
Class B C
Class C 28 DISPOSITION CODE Di Directly to disposal D2 Treatment prior to disposal D3 Treatmentlretumed for storage D4 Treatmentino dsposal (decontamination and reuse)
D5 Storagelno treatment D6 Hold for decay on site and dispose as non-radioactive D7 Hold for decay off ste and dispose as non-radioactive DS Treatment/off-site storage D9 Other (describe) 29 DISPOSAL SITE DS1 Barnwet, SC DS2 Clive, UT DS3 Richland. WA DS4 Other (describe) 30 STORAGE SITE S1 Onsite S2 Radiac S3 NDL S4 Adco S5 Otrier (describe) 4 VOLUME OF LLRW Volume of LLRW containing chelating agents (m3).
5 WEIGHT OF LLRW Weight of LLRW containing chelating agents (kg).
6 WEIGHT % CHELATES Weights less than 1% need not be reported.
H. LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA LLRW Hazard Code Volume (i 3)
Activity Radionuclides Class (mBq) 34 31 32 33 34 35 H.
31 32 33 34 35 LLRW WITH UNACCEPTABLE DISPOSAL CRITERIA LLRW CLASS See codes G-27.
HAZARD CODE See codes 8-4.
VOLUME Volume must be noted in cubic meters (m3).
ACTIVITY Actfvity must be reported in MegaBe-querels (MBq).
RADIONUCLIDES As applicabe to H-3.
I I
I I
4 I
+
A __________
.1.
- 1. CONTAINERS WITH SURFACE RADIATION LEVELS GREATER THAN 2mSvlhr (200mR/hr)
LLRW Class Volume (ml)
Activity by Radionuclide (M8q) 35 37 3
See attached I
Containers > 2 mSv Waste Class A
A A
A A
Volume (m3) 5.5 5.5 3.4 3.4 5.5 Dose Rate (mSv) 10 20 250 600 30 mCI MMCI i
mCi 5m mCi MBg mCI
'Mi t
mCI C-14 6.1OE+01 -
7.55E+01.c79SX03 E+01 +01 2
2.34E.00 2.15E+01 Mn-54 7.23E+02
.:88Ef04 9.31E+02 t3;4 l 56E404 s 77S 3.15E04 k-1.60E+03,
Fe-55 2.13E+03.V$-SOV8§ 2.57E+03
'1&93E'40 1.32E+04 e 2.72E+04,
2.11 E+03 2 8 2
Co-58 2.77E-01.;
2E03 O.OOE+00 X0<E;OO 1.56E+03 17S 4 3.1I E+03
'E!T d5 2.34E+O I E
Co-60 1.52E+03 Y frts 64 1.86E103.r B;88E+/- 4 1.32E+04 2.72E404 TE&W b4, 2.56E+03 J4?E-'
NI-63 1.85E+01 -
'.854dZ 2.28E+01 1.28E+02 7
2.65E+02.
3.37E*01 5
Sr-90 5.48E+00 0.O3>02 6.71E+00 A8,¢ 2.40E-01.{88E+d 5.12E-01 O
g.i V..
5.52E-01 Ag-11Om O.OOE+00 M 0 1.36E+01 2.0S.2 2 1.08E+02 -
O4'tP3 1.26E+02 '>-4
- 8E 3
1.66E+0 1 Cs-137 7.65E+02 tm4,8041 9.35E+02 4 0. 4 3.37E+01 'S}
O3 7.21E+01 g
- 7 3 1.58E+02,
Ce-144 4.70E+02 im.s.74A04 5.30E+02 i,; i.
0 t
1.74E+01 3.72E+01 f
EW03 1.41E+01 Pu-238 0.002+00
,,,O O.OO E+0 002.00 '4..0154d 1.08E-02 0,WEI4 2.32E-02 8Ei 4
.15E-03,,54Ei Pu-239 O.OOE+00 'OEO0 0002+00.>,OO+00 9.25E-03.
1.98E-02,Sfte3y 1.43E-03 _________0 Pu-241 O.
0 00 E.
- 0O 5.74E-O1 i 2 I2E.)
1.23E+00 s4 s2.
O1 8.09E-02 EJ Am-241 O.W E+W00 f
02.64b O.OOE++00 Sd 5.26E-03 f i i95a-1 1.12E-02 r 4.58E-03 m.<<t9'61 Cm-242 9.81 E-02 3O 1
.04-01 802y8O I.87E.03 R
92j5O 3.97E-03 i
4t'OI 7.50E-03,Th,',
Cm-243 0.00E+0
,OO,*EO O.OOE+00 4OA'dDOo
- 1. 10-03 LgK4-'O'1E2 2.35E-03 $'TR tOA 1.192-03 Total 5.73E+03,-
2.12E*O 6.95E+03,.
75 4.39E+04 it;62,0 8.952+04 7
.3
.4 6.54E+03 I E,-+O
SECTION III. LLRW
SUMMARY
A. DISPOSAL TOTALS FOR THIS YEAR Classes Disposed at: Barnwell, SC Disposed at: Clive, UT Disposed at: Richland, WA SUBTOTALS BY CLASS Class A Volume Im3)
Activity (MBq)
Volume (iM3)
Activity (MBq)
V (tvy)M
)
Volume -A I
Activity -A Via Broker I
Processor 2.600 485000.000 58.300 51100D0.000 60.900 I 5595000.000 Direct Transfer 0.000 1 0.000 Class B Volume -B Activity -B Via Broker/
Processor 0.000 0.000 Direct Transfer l
l 0.000 0.000 Class C l
l Volume -C Activity -C Via Broker /
Processor
_000 Direc Transfer 0.000 0.000 TOTALS 2.600 485000.000 58.300 5110000.000 0.000 0.000 TOTAL ALL CLASSES VOLUME ACTIVITY 4
4 60.900 5595300.030 60.900 5595000000
E. INTERIM STORAGE TOTALS Classes Placed in Interim Storage during this year Placed in Interim Storage before this year SUBTOTALS BY CLASS Class A Volume (m3)
Activity (MBql Volume (m'l Activity (MBq)
Volume-A Activity. A On Site 0C003 0.000 Off Sde 5.500 242000.000 5.500 242000.000 Class B Volume. B Activity. B On Site 0.003 0oo00 Of Sne 0.000 0.000 Class C Volume C Activity. C On Site 0.000 0.000 Off Ste 0.000 0.000 TOTALS 5.500 242000.000 0 000 0.000 TOTAL ALL CLASSES 5.500 242000.000 TOTAL ALL CLASSES 5.500 242000.000
SECTION IV. RADIONUCLIDE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED NOTE: Radionuclides mean each individual radionuclide if known, or, at a minimum, all radionuclides that have been or would have to be identified on disposal site manifests. H-3, C-14, Tc-99, and 1-129 must be identified where present.
l A 1 List the radionuclides contained in the LLRW disposed of during this year (see response to Section III-A). Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (M.1Bq)
Radionuclide Activity (MBq)
H-3 3.03D C-14 55B0.000 Mn-54 1850000.000 Fe-55 1760000.000 Co-58 175000.000 Co-60 1680000.000 N-63 16300.000 Sr-90 482.000 Ag-110m 9160.000 Cs-137 69200.000 Ce-144 40200.000 Pu-238 1.490 Pu-239 1.210 Pu-241 75.100 Arn-241 1.280 Cm-242 8.040 Cm-243 0.253 I___
Total Activity in MBq 5606012.403 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW disposed of, as reported in Section Ill-A.
A.2 If any of the radionuclides listed in Table A-1 have half-lives of less than 90 days, please explain why these are not being held for decay and eventual disposal I as non-radioactive waste.
B.1 Lisi the radionuclides contained in the LLRW being held in storage for decay on site as of December31. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide B.2 I List the radionuclides contained in the LLRW being held in storage for decay off site as of December 31. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide C.1 I On s ite B List radionuclides contained in LLRW in interim storage on site as of December 31. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MVq)
I __
I _ _
Total Activity in MBq 0.000 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW stored on site, as reported.
'.2 IOff site B List radionuclides contained in LLRW in interim storage off site as of December 31. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
C-14 795.000 Mn-54 59200.000 Fe-55 78100.000 Co-58 866.000 Co-60 94700.000 N-63 1250.000 Sr-90 20.400 Ag-11Om 614.000 Cs-137 5850.000 Ce-1t4 522.000 Pu-238 0.154 Pu-239 0.052 Pu-214 0.299 Am-241 0.169 Cm-242 0.278 Cm-243 0Q.04 4 Total Activity in MBq 241919.396 otal activity for all radionuclides listed above:
- otal activity should equal total for LLRW being stored off site, as reported.
C 3 If any of the radionuclides listed in Table C-1 or C-2 have half-lives of less than 90 days, please explain why these are not being held for decay and eventual I disDosa! as non-radioactive waste.
SECTION V. STORAGE FACILITY INFORMATION NOTE: If your facility manages LLRW by storage for decay only, you only need to complete the Condensed Form for Decay in Storage Only.
ON-SITE STORAGE FACILITIES A.1 Briefly describe your on-site LLRW storage facilities. Include facilities you have for storage of special LLRW forms such as freezers, shielded areas for high-radiation-level wastes, or bermed storage areas for liquid wastes, and estimate the storage capacity for each.
Storage facility consists of 2 concrete pits at Unit 1 and 3 concrete rooms at Unit 2 with sufficient storage for Unit 1 and 2 for 20 years.
A.2 Total Storage Capacity: 4360 m3 A.3 Estimated maximum volume of LLRW held in storage for decay at any one time: Q M3 B
l Do you have any plans for increasing your on-site storage capacity?
2 No. Skip to C.
Describe such plans and indicate your expected new storage capacity.
OFF-SITE STORAGE FACILITIES C
Off-site storage facility information. Use additional pages if necessary.
Please indicate if off-site storage is for storage for decay or interim storage.
O Storage for decay 3 Interim storage Name of facility: Studsvik Processing Facility Address: TC Runion Road Erwin, TN Contact and phone number Ron Leonard 423-735-6300 NOTE: Please answer the following question based on LLRW requiring disposal at licensed LLRW disposal facilities, not LLRW held in storage for decay. Do NOT USE DESCRIPTIVE TERMS SUCH AS UNLIMrTED, CONTINUOUS, OR INDEFINITE.
ESTIMATED STORAGE TIME FOR LLRW REQUIRING DISPOSAL D
Based on your anticipated LLRW generation rate and your anticipated capacity to store NOTE: Answer must be in months.
waste as of December 31, HOW MANY MONTHS could you continue to produce and store LLRW on site if access to licensed LLRW disposal facilities were no longer available?
240 months
SECTION VI. FUTURE LLRW GENERATION 2003 FUTURE LLRW GENERATION THAT WILL REQUIRE DISPOSAL Year Class Activity (MBq)
Volume (M3)
Radionuclides 2004 A
1850000.000 60.000 H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59, Co-S5B, Co-60, Ni-59, Ni-63, B.
5550000.000 5.000 Sr-90, Tc-99, Aq-110m, Cs-137, Ce-144, Pu-238, Pu-239, Pu-241, 700000000.000 5.000 Am-241, Cm-242, Cm-243.
Total 707400000.000 70.000 2005 A
18500000.000 60.000 Same as 2004 5550000.000 5.000 40000000.000 5.000 Total 64050000.000 70.000 2006 A
2006 1850000.000 60.000 Same as 2004 B
5550000.000 5.000 C
7000000.000 5.000 Total 707400000.000 70.000 2007 A
18500000.000 60.000 Same as 2004 B__
5550000.000 5.000 C
40000000.000 5.000 Total 64050000.000 70.000 2008 A
1850000.000 60.000 Same as 2004 B
5550000.000 5.000 C
700000000.000 5.000 Total 707400000.000 70.000
SECTION VII. ATTACHMENT SHEET FOR ANY ADDITIONAL INFORMATION (Table will automatically expand as information is entered)
Column 1, Line 5 - Sewage sediment Column 13, Lines 1,2,6 - Studsvik Processing Facility Column 13, Lines 3,4,5 - GTS Duratek Column 14, Lines 1,2,6 - Studsvik Processing Facility Column 15, Line 5 - Assayed by processor and released for burial in sanitary municipal landfill.
Column 27,29, lIne 5 - Original waste assayed by processor and disposed in sanitary municipal landfill Column 30, Line 6 - Interim storage at Studsvik awaiting processing Note: Discrepancies between total activity of waste shipped from Nine Mile Point and total activity of waste buried by processsors is due rounding errors in compiling the data.
RETURN BY MARCH 1, 2002 NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENT AUTHORITY Radioactive Waste Policy and Nuclear Coordination Program CODE official use only)
I I I I. I 2001 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM NOTE Please refer to the Instructionsbefore completing this form. Also, see Public Authorities Law, Section 1854-d(l) and Part 502 of Chapter A of Title 21 NYCRR (Reporting Regulations) provided with this form.
FOR THE PERIOD: JANUARY 1 THROUGH DECEMBER 31, 2001 PLEASE TYPE OR PRINT LEGIBLY SECTION 1. GENERATOR INFORMATION A I Updated Generator Information Licensing Agencylies License No(s).
New York State Department of Labor New York State Department of Health New York City Department of Health U.S. Nuclear Regulatory Commission NPF-69 Your Facility Email Address Phone No.:
(315) 342-5337 Ext tavlors@nimo.com nt ctTitle Sirlavlor eneral Su ervisor acilneiie
- ont LLC.
LU r2..
Street Address PO Box 63 City County State Zip Code 0swego
_Oswego NY 13903 B I Name and principal office of facility where LLRW is generated if different from A (above)
Street address P0 Box 63 City County State ZI' Code 3444Z Lycoming oswesoNY h893 Preparer's Name Title C Skip Taylor eneral Supervisor Telephone and Extension 315-349-4982 D Identify, by issuing authority and number, permits that authorize transfer of your LLRW Io a licensed LLRW disposal facility.
Issuing Authority Disposal Site Location Disposal Site Use Permit Number State Of South Carolina Barnwell. SC 0408-31-02-X E
FACILITY TYPE CODE Al Refer to the instructions to determine the facility type code that best describes your facility. Use only one code Power Generation Facility that uses Nuclear F I Briefly describe the activities, processes, or uses of radioactive material that result in LLRW generation at your facility. fuel to generate steam to generate electrictv SIGNATURE OF PREPARER: Skip Tavlor DATE:
/ I Co w
SECTION 11. INFORMATION ON LLRW A. LLRW AS GENERATED B. ON-SITE WASTE TREATMENT Waste waste Sorption or Description Management Chemical Form Other Hazard Treatment Solidification Effect of Post-Treatment Code Method Code Code Code Code Treatment Volume (M) 2 3
6 7
9 26 WI C4 H8 T21 2
33 WI C4 H8 T21 3
32 W2 C4 H4 T21 32 W3 C4 H4 T21 38 W5 C4 1H2 121 32 W5 C4 H4 T1 I 39 W3 4
H8 T21 40 W3 C4 H-8 T21 32 W4 C4 H4 T21 C0 CODES for SECTION I11 of the 2001 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM A. LLRWASGENERATED 1
WASTE DESCRIPTION CODE Choose the cateaory that best describes the waste 20 Charcoal 21 Incinerator Ash 22 Soil 23 Gas 24 Oil 25 Aqueous Liquid 26 Filter Media 27 Mechanical Filter 29 Demolition Rubble 30 Cation Ion-exchange Media 31 Anion Ion-exchange Media 32 Mixed Bed Ion-exchange Media 33 Contaminated Equipment 34 Organic Uquid (except oil) 35 Glassware or Labware 36 Sealed Source1Device 37 Paint or Plating 38 Evaporator Botlomsr SludgeslConcentrates 39 Dry or Compactible Trash (paper, plastic, glass, etc.)
40 Noncompactible Trash (metal components, etc.)
41 Animal Carcass 42 Biological Material (except animal carcass) 43 Activated Material 44 Material that will be Incinerated 59 Other (describe) 2 WASTE MANAGEMENT METHOD Transter to Authorized Peciitien WI Transfer to Disposal Site via Broker W2 Transfer to Disposal She Directly W3 Transfer - Other (describe)
Interim Storage W4 Placed In Storage before 2000 W5 Placed in Storage during 2000 W6 Shipped for Treatment prior to Storage Storane for Deca W7 Storage for Decay (Only limited information required.
See instructons.)
3 CHEMICAL FORM CODE C1 Paper and Plastic C2 Glass C3 Metals C4 Metal Oxides CS Inorganic Salts C6 Organic Salts C7 Nucleic Acids CS Amino Acids, Proteins, Enzymes C9 Carbohydrates, Sugars CID Lipids, Fatty Acids C11 Other (describe) 4 OTHER HAZARD CODE 1-11 Ignitable H2 Corrosive H3 Toxic Ht Reactive H5
, Pathogenic H6 Carcinogenic H7 Other (describe)
HB None S. ON-SITE WASTE TREATMENT 5
TREATMENT CODE Ti Compaction T2 Supercompaction T3 Evaporation/Crystallization T4 Fluid Bed DryingtCalcination T5 Wet Oxidation TB Membrane Separation (ultratiltration, reverse osmosis)
T7 Incineration TB Solidification Tg Adsorption T10 Sorting/Segregation T11 Macroencapsulation T12 Absorption T13 Decontamination T14 Surface Removal (scabbing, abrasive cleaning) t15 Dry Chemical Packing (lime)
T16 Size Reduction (sectioning, shredding, cutting)
T17 Steam Reibrm Ti B Catalytic Extraction Process T19 Dewatered T20 Other (describe)
T21 None 6
SOLIDIFICATION OR SORPTION CODE 60 SpeediDri 61 Celetom 62 Floor DrylSuperfine 63 Hi Dri 64 Safe T Sorb 65 Safe N Dri 66 Florco 67 Florco X 68 Solid A Sorb 69 Chemsil3o 70 ChemsilSO 71 Chemsil 3030 72 Dicaped HP200 73 Dicaped HP500 74 Petroset 75 Petroset 11 76 Aquaset 77 Aquaset It 89 Other (describe)
Spltidi 90 Cement 91 Concrete (encapsulation) 92 Bitumen 93 Vinyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required
SECTION 11. INFORMATION ON LLRW (cont.)
C. ON-SITE CONTAINER INFORMATION D. BROKERIPROCESSOR INFORMATION Container Maximum Surface Description Container Volume Radiation Level Number of Code (i)
(mSvlhr)
Containers Broker Code Processor Code Treatment Code 1
00,1 4
1 1.63 68500 2
BCIO Pi T_21 2
13 3.41 38 -_I CIO P1 T1 3
13 555 30.0 6
BCI I P1 121I 4
13 5.83 40.0 3
BC1I Pi 1
13
.55 1.5 1
BCI1 P1 1
13 5.83 25.0 3
BCII P1 121 13 3.41 45.0 3
BC11 P1 T21 13 5.83 25.0 6
BC11 PS 121 13 67.2 0.52 2
BCI I Pi T21 35.84 1.001 2
BCI I P8
'21 13 3.51 38.0 13903 BCII P1 1
7 EFFECT OF TREATMENT Impact of treatment on volume maybe shown in percent or ratio. Note increase or decrease by I or 1, and describe change in chemical and physical form.
8 POST-TREATMENT VOLUME Volume must be noted In cubic meters (d).
C. ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE 1
Wooden Box or Crate 2
Metal Box 3
Plastic Drum or Pail 4
Metal Drum or Pail S
Metal Tank or Liner 6
Concrete Tank or Liner 7
Polyethylene Tank or Liner 6
Fiberglass Tank or Liner 9
Dernineralizer 10 Gas Cylinder I I Bulk, Unpackaged Waste 12 Unpackaged Components 13 High-lntegrity Container 14 Fiberboard Drum 19 Other (describe) 10 CONTAINERVOLUME Volume must be noted in cubic meters (m?).
11 MAXIMUM SURFACE RADIATION LEVEL Surface radiation must be noted in mSvibr.
12 NUMBER OF CONTAINERS This information is required for each waste lorm.
D. BROKERIPROCESSOR INFORMATION 13 BROKER CODE BC1 NDL BC2 Radiac BC3 Adco BC4 Teledyne BC5 US Ecology BC6 Chem-Nuclear BC7 SEG BC8 Bionomics BC9 Direct transfer BCt0 Olher (describe)
BC11 None 14 PROCESSOR CODE pl GTS Duratek P
NSSI 2
DSSI Chem Nuclear, IL P
Alaron 5
Ouadrex, TN IT Permafix.FL P
ATG,TN 8 -
ATG. WA FPMD Other (describe) 15 TREATMENT CODE See codes E-5.
If you have responded 'OTHER' to any request for Inlormation please Identity column, line, and waste description (from A-1). Use additional pages as necessary.
col. 2 lines 3,4,5 - transfer to processor for volume reduction and disposal.
COL. 13 lines 1.2 - WMG broker, Duratek for burial
SECTION 11. INFORMATION ON LLRW (cont.)
C. ON-SITE CONTAINER INFORMATION D. BROKERIPROCESSOR INFORMATION Container Maximum Surface Description Container Volume Radiation Level Number of Code (m)
(mSvfhr)
Containers Broker Code Processor Code Treatment Code 2
35.84 1.4 1
BC1I 9
T 2
'.69 9.4 4
BC1I Pi TI 13 5.83 18.0 6
BC1I BC10 m
7 EFFECT OF TREATMENT Impact of treatment on volume maybe shown in percent or ratio. Note increase or decrease by I or 1, and describe change in chemical and physical form.
POST-TREATMENT VOLUME Volume must be noted in cubic meters (d).
C. ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE 1
Wooden Box or Crate 2
Metal Box 3
Plastic Drum or Pail 4
Metal Drum or Pail 5
Metal Tank or Liner 6
Concrete Tank or Liner 7
Polyethylene Tank or Liner 8
Fiberglass Tank or Liner 9
Dernineralizer 10 Gas Cylinder 11 Bulk. Unpackaged Waste 12 Unpackaged Components 13 High-Integrity Container 14 Fiberboard Drum 19 Other (describe) 10 CONTAINERVOLUME Volume must be noted in cubic meters (mn?).
11 MAXIMUM SURFACE RADIATION LEVEL Surtace radiation must be noted in mSvthr.
12 NUMBER OF CONTAINERS This information is required for each waste form.
D. BROKERIPROCESSOR INFORMATION 13 BROKER CODE BC1 NOL BC2 Radiac BC3 Adco BO4 Teledyne BC5 US Ecology BC6 Chem-Nuclear BC7 SEG BC8 Bionomics BCO Direct transfer BOlD Other (describe)
BC11 None 14 PROCESSOR CODE pl GTS Duratek p
NSW.
2 DSSI F
Chem Nuclear, IL P
Alaron S
Ouadrex, TN PI Permalix, FL P
ATG, TN 8
ATG WA PMO Other (describe) 15 TREATMENT CODE See codes B-S.
If you have responded 'OTHER to any request tor Information please identify column, line, and waste description (from A-1). Use additional pages as necessary.
col. i4 lines 3 - stored on site for 2001
- SECTION 11. INFORMATION ON LLRW (cont.)
E. POST-PROCESSOR TREATMENT F. OTHER CHARACTERISTICS CHARACTERISTIC CHARACTERISTICS Source Material SNM Source Weight of Source Effect of Total Post-Treatment Material Material Total SNM Maximum grams SNM in any Treatment Volume (m')
Code (grams)
SNM Code (grams) shipment (grams) 4 10.53 n/a SNM1 1.29E-03 1.254E-03 SNIV13 4.449E-02 1.582E-02 3
4
=
a
_==
=
E. POST-PROCESSOR TREATMENT INFORMATION 16 EFFECT OF TREATMENT See instructions for 5-7.
17 TOTAL POST-TREATMENT VOLUME Volume must be noted in cubic meters (m?).
F. OTHER CHARACTERISTICS iS SOURCE MATERIAL CODE Source Material - Enter one code oer line, Use e seoarate fine to each tvoe of source material transferre NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natural Thorium TO Thorium Ores 19 WEIGHTOFSOURCE MATERIAL Weight must be noted In grams (g).
20 SNMCODE Special Nuclear Material means one of the following:
SNMI Plutonium SNLt2 Uranium-233 SNIVi3 Uranium enriched in the isotope 233 or In the isotope 235 SNM4 Any material artificially enriched by any of the foregoing 21 TOTAL SNM Weight must be noted In grams(g).
22 MAXIMUM GRAMS SNM IN ANY, SHIPMENT Sell-explanatory.
23 CHELATECODE CAI EDTA CA2 DTPA CA3 CarbolicAcid CA4 Hydroxy-carbolic Acids CA5 Citric Acid CA6 Glucinic Acid CA7 Other (describe) 24 VOLUMEOFLLRW Volume of LLRW containing chelating agents (n' ).
25 WEIGHT OF LLRW Weight of LLRW containing chelating agents (kg).
26 WEIGHT % CHELATES Weights less than 1% need not be reported.
G. DISPOSAL AND STORAGE 27 LLRW CLASS Class of radioactive waste as described in sections 61.55 and 61.56 of Title 10, Code of Federal Regulations.
as In eftect on January 26, 1983. attached lollowing Instructions.
AS Class A stable AU Class A unstable B
Class B C
Class C It you have responded
'OTHER' to any request tor Informationplease identify column, line, and waste description (from A-1). Use additional pages as necessary.
Section 11 (Cont)
- 1. CONTAINERS WITH SURFACE RADIATION LEVELS GREATER THAN 2mSv/hr (200 mRlhr)
LLRW Volume (rii)
Activity (MBq)
A 5.55 3
1.13E +05 A
5.55 5.77E +04 A
5.55 2.05E +05 A
5.55 7.14E +04 A
5.83 1.44E +06 A
5.83 t 167E +05 A
5.83 7.7E +05 A
5.83 1.01 E +06 A
5.83 6.36E +05 A
3.41 3.22E +05 A
3.41 7.29E +04 A
3.41 3.26E +05 A
5.83 3.12E +05 A
5.83 2.13E +05 A
5.83 2.09E +05 A
5.83 4.33E +05 A
5.83 9.73E +05 A
5.83 9.40E +05 A
5.83 8.45E +05 A
5.83 8.45E_+05 A
5.83 2.95E +05 A
5.83 2.51 E +05 A
5.83 1.87E +05 A
5.83 1.89E +05 A
2.69 5.81 E +03 A
2.69 1.79E +03 A
3.51 1.40E +05 A
2.69 1.27E +03
SECTION 11. INFORMATION ON LLRW (cont.)
F. OTHER CHARACTERISTICS (con(cpnt G. DISPOSAL AND STORAGE INFORMATION______
Waste With Chelating Agents_________I Volume and Weight of LLRWl Chelate T
Weight %
Disposition Disposal Site Storage Site Code Volume (m) l Welght(kg)
Chelates LLRW Class Code Code Code B
Dl DSI 2
=
C Dl DSI AU D5 DS4 4
AU DI DSI
=
AU D2 DS4
.7 II
=
=-
H. LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA Activity LLRW Class Hazard Code Volume (M)
(MBq)
Radionuclides
- 4.
-0000 If you have responded OTHER to any request for information,please identify column, line, and waste description (from A-1). Use additional pages as necessary.
col 29, line 3 stored on site col 29, line 5 sent to Duratek or ATG for processing /burial 28 DISPOSITION CODE DI Directly to disposal D2 Treatment prior to disposal D3 Ttealmentfreturned for storage D4 Tteatmentfno disposal (decontamination and reuse)
D5 Storagelno treatment DS Hold Icr decay on ste and dispose as non-radioactive D7 Hold for decay out she DS 09 and dispose as non-radioscaive Trealmentlolf-she storage Other (describe) 29 DISPOSALSITE DSt Barnwell. SC DS2 Dive, UT DS3 Richland, WA.
DSt Other (describe) 30 STORAGESITE Si On ste S
Radiac 2
NOL S
Adco 3
Other (describe)
S H. LLRWWITH UNACCEPTABLE DISPOSAL CRITERIA 31 LLRW CLASS See codes G-27.
32 HAZARDCODE See codes B-4.
33 VOLUME Volume must be noted in cubic meters (r?).
34 ACTIVITY Activity must be reported in MegaBecquerels IMI3q).
35 RADIONUCLIDES As applicable to H-3.
SECTION IV. RADIONLICLI DE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED NOTE: Radionuclides mean each Individual radionuclide If known, or, at a minimum, all radionucjides that have been or would have to be identified on disposal site manifests. H-3, C-I 4, Tc,99, and 1-129 must be ldentifiedvthere present.
A.
List the radionuclides contained In the LLRIW disposed oburlng 2001 (see response to Section 111-A). Use additional sheetes necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (M Bq)
Radionuclide Activity (MBq)
Co-60 S.63E08
____________.72E03 Pu-238 9.73E02 Zn-65 S.54E05 Fe-59 3.12E03 Pu-239 1.85EOO
~Mn-54 9.96E06 Zr-9S 8.51EOO Sb-124 5.04E02 Cs-137 7.28E03 TC-99 1.18EO3______
Ce-144 9.81E01 Cr-51 3.88E04__
C-14 6.88EO4 AP-I11Om
- 1. I2E04_______________
.97E07 Pu-24 1
.25E02__
Ni-59 2.95E05 Am-241 3.7E-01 Fe-55
~
5IEO8 Cm-242 4.22E01 Sr-90 8.95EOI b-94 1.22E03__
lo-.58 1.07E05 6-243 1.37E01 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW disposedof, as reported in Section II11 -A.
TOTAL ACTIVITY 11.8E9j IIf any of the radionud ides listed In Table A-1 have hal-l-Oves of less than 90 days, please explain why these are not being held for decay and eventual disposal as A.2 non-radioactive waste.I R-A I List the radionucjlides enntained in the LLRW beino hold In storace for derav on she of Dlecember 31. 2001. Use additional sheets as neeessarv.
RaincieRadionuclide Radionuclide Radionuclide Radionuclide Radionuclide H 8.21 Lsttheradoncliescontained In the LLRW being hold In storage for ecay off she of December 3 2001. Use additional sheets as necessary.
RaincieRadionuclide Radionuclide' Radionuclide Radionuclide Radionuclide
CA I On site -Ust radionuclides contained in LLRW in Interim storaae on siteas ol December 31. 2001. Use additional shoots as ne essary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Co-60 1.7E06 Fe-55 1.71E06 Ae-I lm 3.64E03 Zn-65
.19E05 Co-58 1.06E04 Pu-241 7A4E03 Mn-54 2.28E05 Sr-90 1.99E02 Au-1 99 2.46E-02 Cs-137 4.49E04 H-3 1.94E03 Sb-124 I.8E03 Ce-144 2.08E03 Fe-59 I.76E04 C-14 6.22E03 Sr-89 5:77E-08 Ni-63 1.22E05 Tc-99 1.78E03 Ni-59 1.1 OE04 r-51 1.89E04 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW stored on sitpas reported.
TOTAL ACTIVITY MBq A.E06 C.2 Offsie -List radionuclides contained in LLRW in interim storage off sileas of December31, 2001. Use additional sheets as necessary.
'Radionuclide Activity 4MBq)
Radionuclide Activity (M
~q Radionuclide Activity (MBq)
Total aclivity for all radionuclides listed above:
Total activity should equal total for LLRW being stored off sitpas reported.
TOTAL ACTiVITY M~q If any of the radionuclides listed in Table C-1 or C-2 have half-lives of less than 90 days, please explain why these are not being held for decay and eventual C.3 disposal as non-radioactive waste.
i-RETURN BY MARCH 1,2003 NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENT AUTHORITY Radioactive Waste Policy and Nuclear Coordination Program CODE (official use only) 2002 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM NOTE Please refer to the Instructions before completing this form. Also, see Public Authorities Law, Section 1854-d(l) and Part 502 of Chapter A of Title 21 NYCRR (Reporting Regulations) provided with this form.
FOR THE PERIOD: JANUARY 1 THROUGH DECEMBER 31, 2002 PLEASE TYPE OR PRINT LEGIBLY
-Place mailing label from front In the soace to the right
-Mark any corrections in the table below I215) `i-74:z2 NPF-Ou IIRL Ot" tU ~7_liIRT 1-0AHAN D IRECTOR OP OPERATIONS H INE lHILE POINT NUJCLCAR P.1tiER '_TATiIWI UNI W LAlr' ROAD, P.O. BO C2 LV~COHIHlG HY 13063 SECTION 1. GENERATOR INFORMATION I.
A IUpdated Generator Information Licensino Aaencv I les License No(s\\.
New York State Department of Labor New York Stale Department of Health New York City Department of Health U.S. Nuclear Regulatory Commission NPF-69 Your Facility Email Address Phone No.:
(315) 349-2749 Ext.
thomas.paeno@nunp.cn.com Contact Title Thomas Paeno Radwaste Supervisor y
Nine Mile Point Nuclear Station, LLC 2
Street Address P.O. Box 63 City County State Zip Code Lycornine Oswerwo
.NY 13093 Name and principal office of facility where LLRW is generated if different from A (above)
Street address City County State Z
2ip Code Preparer's Name Title C
Mikke Sciortino Technician C Telephone and Extension 315-349-7056 D
Identity, by issuing authority and number, permits that authorize transfer of your LLRW to a licensed LLRW disposal facility.
Issuing Authority Disposal Site Location
-Dlsposal Site Use Permit Number State of South Carolina Barnwell, SC 0408-31-03X E FACILITY TYPE CODE A
1 Refer to the instructions to determine the facility type code that best describes your facility. Use only one code F I Briefly describe the activ-ties, processes, or uses of radioactive material that result in LLRW generation at your facility.
Power Generation facility that uses Nuclear fuel to generate steam to generate electricity. Processing waste water for re-usc in plant systems. Dry active waste from operation and maintenanc activities nd riant modifications.
SIGNATURE OF PREPARER;1fN-. v 1
1 1JK IDATE:
1
-('-
I f
(C,
SECTION 11. INFORMATION ON LLRW A. LLRW AS GENERATED B. ON-SITE WASTE TREATMENT Waste waste Sorption or Description Management Chemical Form Other Hazard Treatment Solidification Effect of Post-Treatment Code Method Code Code Code Code Treatment Volume (M)
A 2
3 i
3 6
5 C
26 W2 C4 H8 T19 None 2
32 W2 C4 H8 T19 Noe-None-3 32 W3 C4 HS T21 4
20 W3 C4 H8 T21 38 W3 C4 HS T2l 6
26 W3 C4 HS T21 7
40 W2 C4 HS T21 26 W2 C4 HS T21
.39 W3 C4 H8 T21_
40 W3 C4 HS T21 40 W2 C4 H8 T21 CODES for SECTION 11 of the 2002 LOW-LEVEL RADIOACTIVE WASTE REPORT FORM A. LLRWAS GENERATED WASTE DESCRIPTION CODE Chocos the Calepory that bes$
describes the wasil 20 Charcoal 21 IncineratorAsh 22 Soil 23 Gas 24 Oil 25 Aqueous Liquid 26 Filter Media 27 Mechanical Filter 29 Demolition Rubble 30 Calion Ion-exchange Media 31 Anion Ion-exchange Media 32 Mixed Bed Ion-exchange Media 33 Contaminated Equipment 34 Organic Liquid (except oil) 35 Glassware or Labware 36 Sealed SourcelDevice 37 Paint or Plating 38 Evaporator Bottoms/
SludgeslConcentrates 39 Dry or Cmpeactble Tiash (paper, Flastick gass. etc.)
40 Noncompactible Trash (metal components, etc.)
l Animal Carcass 42 Biological Material (except animal carcass) 43 Activated Material 44 Material that will be Incinerated 59 Other (describe) 2 WASTE MANAGEMENT METHOD Transfer to Authorized Retioien W I Transfer to Disposal Site via Broker W2 Transler to Disposal Site Directly W3 Transfer - Other (describe)
Interim Storane WA Placed in Storage before 2002 WS Placed in Storage during 2002 W6 Shipped for Treatment prior to Storage Storage for Deca W7 Storage Ibr Decay (Skip to item G30) 3 CHEMICAL FORM CODE C1 Paper and Plastic C2 Glass C3 Metals C4 Metal Oxides CS Inorganic Sans C6 Organic Salts C7 Nucleic Acids Ca Amino Acids, Proteins.
Enzymes C9 Carbohydrates, Sugars C10 Lipids. Fatty Acids C11 Other (describe) 4 OTHER HAZARD CODE HI Ignitable H2 Corrosive H3 Toxic HA Reactive H5 Pathogenic H 6 Carcinogenic H7
-Other (describe)
H8 None B. ON-SITE WASTE TREATMENT TREATMENT CODE TI Compaction T2 Supercompaction T3 Evaporation/Crystallization T4 Fluid Bed Drying/Calcination T5 Wet Oxidation T6 Membrane Separation (ultrafltration, reverse osmosis)
T7 Incineration TE Solidification T9 Adsorption T10 Sorting/Segregation T 1I Macroencapsulation T12 Absorption T13 Decontamination T14 Surface Removal (scabbing.
abrasive cleaning)
T15 Dry Chemical Packing (lime)
T16 Size Reduction (sectioning, shredding, cutting)
T17 Steam Reform T1E Catalytic Extraction Process T19 Dewatered T20 Other (describe)
- T21 None 6
SOUDIFlCATION OR SORPTION CODE Sortion 60 SpeediDri 61 Celetom 62 Floor Dry/Superfine 63 Hi Dri 64 Safe T Sorb 65 Safe N Dri 66 Florco 67 Florco X 68 Solid A Sorb 69 Chemsll3o 70 Chemsil5O 71 Chernsil 3030 72 Dicaperl HP200 73 Dicapert H P500 74 Petroset 75 Petroset 11 76 Aquaset 77 Aquaset 11 89 Other (describe)
Solidificatisn 90 Cement 91 Concrete (encapsulation) 92 Bitumen 93 Vinyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required
SECTION 11. INFORMATION ON LLRW (cont.)
C. ON-SITE CONTAINER INFORMATION D. BROKERIPROCESSOR INFORMATION Container Maximum Surface Description Container Volume Radiation Level Number of Code (m3)
(mS/hr)
Containers Broker Code Processor Code Treatment Code
- n I
1 1
44 2
67.20 7
BC11 P1 T21 2
35.84 0.7 4
BC11 P1 T2 1 3
2.52 26 1
BC1l P1 T2 I 5
5.87 30 1
BC11 P1 T21 13 5.55 120 1
BC11 P1 T21 13 5.83 50 7
BC11 P1 T21 7_.
13 3.41 800 1
BC11 P1 T19 13 5.83 50 1
BC11 P1 T19 9
13 5.83 150
- 11.
BC11 Plo T21
,o,0
_=.
7 EFFECT OF TREATMENT Impact of treatment on volume maybe shown in percent or ratio. Note increase or decrease by I or 1. and describe change in chemical and physical form.
8 POST-TREATMENT VOLUME Volume must be noted in cubic meters (m3).
C. ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE 1
Wooden Box or Crate 2
Metal Box 3
Plastic Drum, or Pail 4
Metal Drum or Pail 5
Metal Tank or Liner 6
Concrete Tank or Liner 7
Polyethylene Tank or Liner 8
Fiberglass Tank or Liner 9
Dermineralizer 10 Gas Cylinder 11 Bulk. Unpackaged Waste 12 Unpackaged Components 13 High-Integrity Container 14 Fiberboard Drum 19 Other (describe) 10 CONTAINERVOLUME Volume must be noted in cubic meters (rn3.
12 NUMBER OF CONTAINERS This information is required for each waste torm.
D. BROKER I PROCESSOR INFORMATION 13 BROKER CODE BC1 NDL BC2 Radiac BC3 Adco BCt Teledyne BCS US Ecology BC6 Chem-Nuclear BC7 SEG BC8 Bionomics BC9 Direct transfer BC10 Other (describe)
BCll None 14 PROCESSOR CODE If you have responded OTHER' lo any request for Information please identify column, line, and waste description (from A-1). Use additional pages as necessary.
Co] 2, lines 3, 4. 5, 6, 9, 10: transfer to processor for Volume Reduction /
disposal.
Col 14. line 9: to Studsvik for processing.
Pi
-P2 P3 P4 P5 P6 P,7 P8 P9 P10 GTS Duralek NSSI DSSi
.Chem Nuclear. IL Alaron Quadrex. TN Penrmafix, FL ATG, TN ATG, WA Other (describe) 15 TREATMENT CODE See codes B-S.
11 MAXIMUM SURFACE RADIATION LEVEL Surface radiation must be noted in mSvhr.
SECTION 11. INFORMATION ON LLRW (cont.)
E. POST-PROCESSOR TREATMENT F. OTHER CHARACTERISTICS Source Material SNM Source Weight of Source Effect of Total Post-Treatment Material Material Total SNM Maximum grams SNM In any Treatment Volume (m3)
Code (grams)
SNM Code (grams) shipment (grams) 25.17 N/A N/A SNMI 1.95E-3 1.945E-3 14.17 N/A m1
=
E. POST-PROCESSOR TREATMENT INFORMATION 16 EFFECT OFTREATMENT See instructtons for B.7.
17 TOTAL POST-TREATMENT VOLUME Volume must be noted in cubic metess (in?).
F. OTHER CHARACTERISTICS 18 SOURCE MATERIAL CODE Source Material - Enter one code per line. Use a separate line to each type of source material transtered NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natural Thorium TO Thorium Ores 19 WEIGHTOFSOURCE MATERIAL Weight must be noted In grarrs (g).
20 SNMCODE Special Nuclear Material means one of the lotowin;:
SNMi Plutonium SNt12 Uranium-233 SNM3 Uranium enriched in the isotope 233 or in the isotope 235 SNM4 Any material artificially enriched by any of the foregoing 21 TOTAL SNM Weigh: must be noted in grsams(g).
22 MAXIMUM GRAMS SNM IN ANY SHIPMENT Sell-explanatory.
23 CHELATECODE CA1 EDTA CA2 DTPA CA3 CartaolicAcid CA4 Hydroxy-carbolic Acids CAS Citric Acid CA6 Glucinic Acid CA7 Other (describe) 24 VOLUMEOFLLRW Volume ot LLRW containing chelating agents (m3 I.
25 WEIGHT OF LLRW Weight of LLRW containing chelating agents (kg).
26 WEIGHT % CHELATES Weights less than 1%
need not be reported.
G. DISPOSAL AND STORAGE 27 LLRW CLASS Class of radioactive waste as descrIbed in sections 61.55 and 61.56 of Title 10, Code ol Federal Regulations, as in eflect on January 26, 1983. attached following instructions.
AS Class A stable AU Class A unstable B
Class B C
Class C It you have responded OTHER' to any request for Informabon please idenfly column, line, and waste description (trorn A-1). Use additional pages as necessary.
- E.1 Per processor reduction is 24 to 1.
- E.2 Per processor reduction is 4.53 to 1.
SECTION 11. INFORMATION ON LLRW (cont.)
F. OTHER CHARACTERISTICS (CONT.)
G. DISPOSAL AND STORAGE INFORMATION Waste With Chelating Agents Volume and Weight of LLRW Chelate Weight %
Disposition Disposal Site Storage Site Code Volume (m3) l Weight(kg)
Chelates LLRW Class Code Code Code
_2R 2a 30 B
DI DSI N/A
=
Au D5 DS4 N/A Au DI DS1 N/A
=
As D1 DSI N/A Au D2 DS4 N/A As D2 DS4 N/A t
=
=
_=-
H. LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA Activity LLRW Class Hazard Code Volume (rn3)
(MBq)
Radionuclides I.,
If you have responded 'OTHER to any request for Inlormationplease Identify column, line, and waste description (from A11). Use additional pages as necessary.
Col 29, line 2: Stored on site.
Col 29, Lines 5, 6: Sent to Duratekl or Studsvikl for processing I burial.
28 DISPOSITION CODE Dl Directly to disposal D2 Treatment prior to disposal D3 Treatrnent/returned tor storage D4 Treatment/no disposal (de.ontamination and reuse)
DS Storage/no treatrment D6 Hold lor decay on ste and dispose as non.
radioactive D7 Hold for decay off site D8 D9 and dispose as non-radioactive Treatnenl I eo-sile storage Other (describe) 29 DISPOSALSITE DS1 Barnwell, SC DS2 Clive, UT DS3 Richland, WA DS4 Otier (describe) 30 STORAGESITE St On she S2 Radiac S3 NDL S4 Adco S5 Other (describe)
H. LLRWWITH UNACCEPTABLE DISPOSAL CRITERIA 31 LLRW CLASS See codes G-27.
32 HAZARDOODE See codes 54.
33 VOLUME Volume must be noted in cubic meters (m3).
34 ACTIVITY Activity must be reported in MegaSecquerels (MI3q).
35 RADIONUCLIDES As applicable to H-3.
SECTION 11.1NFORMATION ON LLRW (cont.1
- l. CONTAINERS WITH SURFACE RADIATION LEVELS GREATER THAN 2mSy/hr (200mR/hr)
LLRW Class Volume (m31 Activity by Radionuclide M~ai 34 37 31 Au 5.83 1.70E+05 Au 5.83 1.29E+05 (Continued on Au 5.83 6.43E+05 supplemental pap-e)
SECTION III. LLRW
SUMMARY
A. 2002 DISPOSAL TOTALS Classes Disposed at: Barnwell, SC Disposed at: Clive, UT Disposed at: Richland, WA Class A Volume m3)
Activitv (MBo)
Volume (m3)
Activit MBM)
Volume (m3)
Activity (MBa)
SUBTOTALS BY CLASS Via Broker/
'6.05 (DK) 3.33E+6 (DK) 24.49 (DK) 1.83E+0.5 (DK)
Volume -A Activity -A Processor 1.56 (SV) 2.22E+06 (SV) 9.39 (SV) o.13E+06 (SV) n;-H T.es.-f 17.25 2.93E+6 78.74 1.683E+7 Via Broked Volume B Activity *B Processor Direet Tran sfer 3.41 1.04E+07 3.41 1.04E+07 Via
=rokerl Volume-C Activity C Processor Direct Transfer 48.27 1.89E07 33.88 8.31E06-TOTAL ALL CLASSES VOLUME ACTIVITY 82.15 2.72E+07 B. 2002 Interim Storano Toales Classes Placed in Interim storage during 2002 Place In Interim Storage Before 2002 S MtrASR' hv Clpl:
r- " A Volume (n,31 Activtv Mno)
Volume 1m3T Aetivilv IMBot Volume - A Activity. A
_i_.
50.18 1.S6E+06 50.18 1.86E+06 r-a Volume-B Activitv-B no cit1Tl C.
Volumo - C Activitv - C TOTAtS 50.18 1.86E+06 VOLUME ACTITY 50.18 I
1.86E+06 TOTAL ALL CLASSES TOTAL ALL CLASSES 50.18
SECTION 11: Information on LLRW (Continued)
- 1. Containers with surface radiation levels greter than 2mSv/hr (200 mR/hr).
(Continued)
LLRWN Volume (nm3)
Activity by Radionuclide (mBq)
(36)
(37)
(38)
As 5.83 3.37E+06 Au 5.83 3.58E+05 As 5.83 2.01E+06 As 5.83 7.48E+05 Au 5.83 3.20E+05 Au 5.83 2.21E+05 Au 5.83 4.95E+05 Au 5.87 5.86E+05 B
3.41 1.04E+07 As 5.83 7.65E+05 Au 5.83 6.72E+05 Au 5.83 3.71E+05 Au 5.83 6.73+05 Au 5.83 1.44E+05 Au 5.83 5.37E+05 As 5.55 1.58E+06 As 5.83 1.10E+06 As 5.83 1.37E+06 Au 2.52 1.27E+05
SECTION IV. RADIONUCLIDE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED NOTE: Radionuclides mean each individual radionuclide If known, or, at a minimum, all radionuclides that have been or would have lo be identified on disposal site manifests. H-3, C-14, Tc-99, and 1-129 must be identified w here present.
A.1 Lis the radionuclides contained in the LLRW disposed oburing 2002 (see response to Section 111-A). Use additional sheets necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Au-199 2.37E-31 Co-58 1.46E+05 Nb-95 9.02E+02 Co-60 6.72E+06 H-3 4.54E+02 Sb-125 2.29E+04 Zn-65 2.21E+06 Fe-59 1.07E+05 Sb-124 1.1 OE+04 Mn-54 3.10E+06 Zr-95 8.03E+02 1-129 1.1 OE+02 Cs-137 4.90E+04 Tc-99 9.57E+03 Ce-144 1.56E+03 Cr-51 8.56E+04 C-14 3.56E+04 A-1 lOim 4.97E+04 Ni-63 1.72E+05 Pu-241 7.20E+03 Ni-59 1.84E+02 Am-241 3.28E+04 Fe-55 1.44E+07 Sn-1 13 2.61E+03 Sr-90 2.52E+02 Ae-1 10 5.74E+02 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW disposed of, as reported in Section 111-A.
TOTAL ACTIVITY I
2.72E+07I If any of the radionuclides listed in Table A-1 have half-lives of less than 90 days. please explain why these are not being held for decay and eventual disposal as A.2 Inon-radioactive waste.
None.
. 1 I List the radionuclides contained in the LLRW belno hold In storaoe for decay on she of December 31. 2002. Use additional sheets is necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide N o n e_
?
2 List the radionuclides contained in the LLRW beina hold In stncle for deRcay of she of December31.2002. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide NoeNone________________
cI]
On site List radionuclides contained in LLRW in interim storaoe on site as of December 31. 2002. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (M~q)
Radionuclide Activity (MBq)
Co-60 5.30E+05 Co-58 5.76E+04 Zn-65 1.17E+05 H-3 7.16E+01 Mn-54 3.48E+05 Fe-59 4.96E+04 Cs-137 2.17E+02 Cr-51 7.74E+04 C-14 1.32E+03 A-l Om 1.75E+04 Ni-63 9.85E+03 Au-199 3.89E+02 Nb-95 2.17E+02 Sb-124 2.75E+03 Fe-55 6.76E+05 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW stored on site as reported.
TOTAL ACTIVITY l.88E+06 MBq I Offt site -List radionuclides contained in LLRW in interim storate oft site as of December 31. 2002. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq Radionuclide Activity (MBq)
None Total aclivity for all radionuclides listed above:
TOTAL ACTIVITY Total activity should equal total for LLRW being stored off site as reported.
It any of the radionucrides listed in Table C-1 or C-2 have half-lives of less than 90 days, please explain why these are not being held for decay and eventual C.3 disposal as non-radioactive waste.
None.
SECTION V. STORAGE FACILITY INFORMATION NOTE: If your facility manages LLRW by storage for decay only, you only need to complete the Condensed Form for Decay In Storage Only.
ON-SITE STORAGE FACILITIES A.1 Briefly describe your on-site LLRW storage facilities. Include facilities you have for storage of special LLRW forms such as freezers, shielded areas for high-radiation-level wastes, or bermed storage areas for liquid wastes, and estimate the storage capacity for each.
Concrete Pits at both Unit I and Unit 2 have sufficient storage capacitv for twenty (20) years at current processing rates.
A.2 Total Storage Capacity:
124Ej5 j3r A.3 Estimated maximum volume of LLRW held in storage for decay at any one lime:
22 3
_7 No. Skip to C.
B Do you have any plans for Increasing your on-site storage capacity?
No CJ Yes. Complete this section.
Describe such plans and indicate your expected new storage capacity.
OFF-SITE STORAGE FACILITIES C
=Of-site storage facility information. Use additional pages if necessary.
None Flease indicate K off-site storage is for storage for decay or interim storage.
L Storage for decay Interim storage Name of facility:
Address:
Contact and phone number.
NOTE: Please answer the following question based on LLRW requiring disposal at licensed LLRW disposal facilities, not LLRW held In storage for decay. DO NOT USE DESCRIPTIVE TERMS SUCH AS UNLIMITED, CONTINUOUS, OR INDEFINITE ESTIMATED STORAGE TIME FOR LLRW REQUIRING DISPOSAL D
Based on your anticipated LLRW generation rate and your anticipated capacity to store waste as of NOTE: Answer must be In months December 31, 2002. HOW MANY MONTHS could you continue to produce and store LLRW on she if -
access to licensed LLRW disposal facilities were no longer available?
240 months
SECTION VI. FUTURE LLRW GENERATION FUTURE LLRW GENERATION THAT WILL REOUIRE DISPOSAL I
Year T Class Activitv (Ma'l 7 Volume (m3) l Radionuclides 2003 A
3.7E7 120 Co-60. Zn-65. Mn-54. Cs-137, Ce-144. C-14, Ni-63.
1.5E7 3.71 Ni-59. Fe-55, Co-58. Sr-90. H-3. Fe-59, Sr-89. Tc-99.
C 2.22E10 1.7 A!-l lOIm. Pu-241. Am-241. Cm-242. Pu-239.
Total 2.23E10 125.41 Pu-23O. Sb-124 2004 A
3.7E7 120 Distribution of nuclides is not expected to change 1.5E7 3.71 sienificantlv.
CO. C 0 0
Total 5.2E7 123.71 Note: Numbers assume volume reduction for DAW, 2005 A
3.7E7 120 no volume reduction for Bead Resin or Powdered B
1.5E7 3.71 Resin.
C 0
0O Total 5.2E7 123.71 2006 A
3.7E9 120 Note: Volume reduction methods will be used for 1.5E7 3.71 all waste when fiscally prudent.
C 2.2E10 1.7 Total 2.23E10 125.41 2007 A
2007_._A_
3.7E7 120 B
1.5E7 3.71
, C 0
0 Total 5.2E7 123.71
Boovr &
2oc,3
.;RETURV ANNUALLY BY MARCH 1st TO:
NEW YORK STATE ENERGY RESEARCH AND DEVELOPMENT AUTHORITY Radioactive Waste Policy and Nuclear Coordination Program 17 Columbia Circle Albany, NY 12203-6399 lIrwadmin@NYSERDA.ORG NOTE: Please refer to the Instructions before completing this form.
FOR THE PERIOD: JANUARY 1st THROUGH DECEMBER 31st CODE (official use only)
I I I I I LOW-LEVEL RADIOACTIVE WASTE REPORT FORM PLEASE TYPE OR PRINT LEGIBLY
-Place mailing label from postcard In the space to the right
-Mark any correions in the tabe below Place Mailing Label Here (Leave Blank If Submitting Electronically)
SECTION 1. GENERATOR INFORMATION A
Updated Generator Information ENTER 4-DIGIT GENERATOR ID (can be found on the mailing label on annual postcard) 0352 ENTER REPORTING YEAR 2003 Licensing Agencyries License No(s).
New York State Department of Labor New York State Department of Health New York City Department of Health U.S. Nuclear Regulatory Commission NPF-3 Your Facility Email Address Phone No.: (315)349 - 2749 Ext.
Thomas.Paenoeconstellation.com Contact Thomas Paeno Title Radwaste Opertions Manager Facility Name Nine Mile Point Unit 2 Street Address 34B Lake Road City Oswego County Oswego State NY l Zip Code j
13126 B
Name and principal office of facility where LLRW is generated If different from A (above)
Street Address City County State l Zip Code Preparer's Name Tim Carroll Title Technician C Telephone and Extension C
(315)349-4116
D Identify, by issuing authority and number, permits that authorize transfer of your LLRW to a licensed LLRW disposal facility:
Issuing Authority Disposal Site Location Disposal Site Use Permit Number South Carolina DHEC Bamwell 04D8-31-03-X FACILITY TYPE CODE Type in the appropriate letter and number for the appropriate code OR choose one from EACH DROP-DOWN MENU BELOW. Refer to the instructions to determine the facility type code that best describes your facility. Choose only one code consisting of a letter and number.
E Choose a Letter: A. Nuclear Power Plant Choose a Number: 1. Boiling Water Reactor F
Briefly describe the activities, processes, or uses of radioactive material that result in LLRW generation at your facility.
Processing waste water for reuse in plant systems. Dry active waste is generated from operation and maintenance activities and from plant modifications.
This Report Form has been submitted by the preparer listed in item l(C) above. In submitting this form, preparer hereby certifies DATE: 3130104 that the information set forth is true to the best of Ihe preparer's knowledge.
I
SECTION II. INFORMATION ON LLRW A. LLRW AS GENERATED Waste Waste Chemical Form Other Hazard Descrption Management Code Code Code MethodCoeod 1
2 3
4 32 WI C4 H8 2
32 Wi C4 H8 3
39 WI C4 H8 4
32 Wi C4 H8 s
38 Wi C4 H8 6
38 WI C4 H8 7
10 11 CODES for SECTION II of the LOW-LEVEL RADIOACTIVE WASTE REPORT FORM Note: If you respond other' to any Item, please provide an explanation on the Attachment Sheet provided In Section VI.
A.
WASTE DESCRIPTION CODE Choose the cateQory that best describes the waste.
20 21 22 23 24 25 26 27 29 30 31 32
- 33 34 35 36 37 38 Charcoal Incinerator Ash Soit Gas Oil Aqueous Liquid Filler Media Mechanical Fiter Demolition Rubble Cation Ion-exchange Media Anion Ion-exchange Media Mixed Bed Ion-exchange Media Contaminated Equipment Organic Liquid (except ol)
Glassware or Labware Sealed Source/Device Paint or Plating Evaporator Bottorns/
Sludges/Concentrates Dry or Compactible Trash (paper, plastic, glass, etc.)
Noncompactible Trash (metal cornponents, etc.)
Animal Carcass Biological Material (except animal carcass)
Activated Material Material tha wil be Incinerated Other (describe) 39 40 41 42 43 44 59 2
WASTE MANAGEMENT METHOD Transfer to Authorized Recipient WI Transfer to Disposal Ste via Broker W2 Transfer to Disposal Ste Directly W3 Transfer-Other (describe)
Inierim Storaqe W4 Placed in Storage before current reporting year W5 Placed in Storage during current reporting year W6 Shipped for Treatment prior to Storage Storane for Decay W7 Storage for Decay (Only limited information required. See instructions.)
3 CHEMICAL FORM CODE C1 Paper and Plastic C2 Glass C3 Metals C4 Metal Oxides CS Inorganic Salts C6 Organic Salts C7 Nucleic Acids C8 Amino Acids, Proteins, Enzymes C9 Carbohydrates, Sugars C10 Lipids, Fatty Acids C11 Other(describe) 4 OTHER HAZARD CODE H1 Ignitable H2 Corrosive H3 Toxic H4 Reactive HS Pathogenic H6 Carcinogenic H7 Other (describe)
H8 None
B..ON-SITE WASTE TREATMENT Treatment Code Sorption or Solidification Code Effect of Treatment Post-Treatment Volume (m3) 6 7
a T19 NONE 116 2
T19 NONE 11.4 T21 NONE 145 T19 NONE 7.6 T21 NONE 17.4 6
T19 NONE 17.4 7
10 I1I B.
ON-SITE WASTE TREATMENT 5
TREATMENT CODE Ti Compaction T2 Superrornpaction T3 Evaporation/ Crystallization T4 Fluid Bed Dryingl Calcination T5 Wet Oxidation T6 Membrane Separation (utrafiltration, reverse osmosis)
T7 Incineration T8 Solidificaton T9 Adsorption T1D SortingSegregation T11 Macroencapsulation T12 Absorption T13 Decontamination T14 Surface Removal (scabbing, abrasive cleaning)
T15 Dry Chemical Packing (lime)
T16 Size Reduction (sectioning, shredding, cutting)
T17 Steam Reform T16 Catalytic Extraction Process T19 Dewatered T20 Other (describe)
T21 None 6
SOLIDIFICATION OR SORPTION CODE Sorotion 60 Speedi Dri 61 Celetom 62 Floor DrytSuperline 63 Hi Dri 64 Safe T Sorb 65 Safe N Dri 66 Florco 67 Florco X 68 Solid A Sorb 69 Chemsil 30 70 Chemsil 5O 72 Dicaperl HP200 73 Dicapert HP500 74 Petroset 75 Petroset II 76 Aquaset 77 Aquaset 11 89 Other (describe)
Solidificaton 90 Cement 91 Concrete (encapsulation) 92 Bitumen 93 Vinyl Chloride 94 Vinyl Ester Styrene 99 Other (describe) 100 None Required 7
EFFECT OF TREATMENT Impact of treatment on volume may be shown in percent or ratio. Note increase or decrease by 8 or9. and describe change in chemical and physical form.
8 POST-TREATMENT VOLUME Volume must be noted in cubic meters (m3).
3ECTION II. INFORMATION ON LLRW (cont.)
C. 6N-SITE CONTAINER INFORMATION D. BROKERJPROCESSOR INFORMATION Container Maximum Surface Description Container Volume Radiation Level Number of Broker Code Processor Code Treatment Code Code C
e(mSvlhrs g
10 1
12 13 14 1s 7
5.8 255 23 BC10 PlO T17 2
7 3.8 10 3
BC10 P10 T17 3
2 72.5 0.4 2
BC1o P1 T7 4
7 3.8 1040 2
BC10 P10 T17 7
5.8 30 3
BC10 P1 T3 6.
7 5.8 50 3
BC10 P10 T21 8
11
=.
C.
ON-SITE CONTAINER INFORMATION 9
CONTAINER DESCRIPTION CODE 1
Wooden Box or Crate 2
Metal Box 3
Plastic Drum or Pal 4
Metal Drum or Pail S
Metal Tank or Liner 6
Concrete Tank or Uner 7
Polyethylene Tank or Liner B
Fiberglass Tank or Liner 9
Demineralizer 10 Gas Cylinder 11 Bulk, Unpackaged Waste 12 Urnpackaged Components 13 HighIntegrity Container 14 Fiberboard Drum 19 Other (describe) 10 CONTAINER VOLUME Volume must be noted in cubic meters (mn).
11 MAXIMUM SURFACE RADIATION LEVEL Surface radiation must be noted in mSvjhr.
12 NUMBER OF CONTAINERS This information is required for each waste form.
D.
BROKERIPROCESSOR INFORMATION 13 BROKER CODE BC1 NDL BC2 Radiac BC3 Adco BC4 Teledyne BC5 US Ecology BC6 Cher-Nudear BC7 SEG BCB Bionomics BC9 Direct transfer BC10 Other (describe)
BC11 None 14 PROCESSOR CODE P1 GTS Duratek P2 NSSI P3 DSSI P4 Chem Nuclear, IL P5 Alaron P6 Ouadrex, TN P7 PerrnafLx. FL P8 ATG.TN P9 ATG. WA P10 Other (describe) 15 TREATMENT CODE See codes B-5.
3ECTION II. INFORMATION ON LLRW (cont.)
E. POST-PROCESSOR
- TREATMENT INFORMATION F. OTHER CHARACTERISTICS Source Material SNM Effect of Total Post-Treatment Source Weight of Source Treatment Volume (m3)
Material Material SNM Code Totam SNM Maximum grams SNM in any Code (grams)
(grams) shipment (grams) 1i t
6 1
29 20 21 22 13:
9.9 NONE 0
NONE 0
0 2
13:
0.9 NONE 0
NONE 0
0 17:
8.1 NONE 0
NONE 0
0 8:1 0.9 NONE 0
NONE 0
0 5
44:
0.4 NONE 0
NONE 0
0 6
NONE 0
NONE 0
0 7
B_
9 10 11 E.
POST-PROCESSOR TREATMENT INFORMATION 16 EFFECT OF TREATMENT See instructions for B-7, 17 TOTAL POST-TREATMENT VOLUME Volume must be noted in cubic meters (m'J.
F.
OTHER CHARACTERISTICS 18 SOURCE MATERIAL CODE Source Material c Enter one code Der line. Use a separate line for each t"e of source material transferred.
NU Natural Uranium DU Depleted Uranium UO Uranium Ores NT Natura! Thorium TO Thorium Ores 20 SNM CODE Special Nudear Material means one of the folowing:
SNM1 Plutonium SNM2 Uraniurn-233 SNM3 Uranium enriched in the isotope 233 or in the isotope 235 SNM4 Any material artificially enriched by any of the foregoing 21 TOTAL SNM Weight must be noted in grams(g).
22 MAXIMUM GRAMS SNM IN ANY SHIPMENT Self-explanatory.
19 WEIGHT OF SOURCE MATERIAL Weight must be noted In grams (g).
SECTION 11. INFORMATION ON LLRW (cont.)
F. OTHER CHARACTERISTICS (cont.)
G. DISPOSAL AND STORAGE INFORMATION Waste With Chelating Agents Chelate Volume and Weight of LLRW LLRW coSe Disposal Site Code SteCode CoeWih hlts Class CdDipalStCoe Sitoagde Code Volume (m')
Weight (kg) 23 24 2s 26 27 28 29 30
_AU D2 DS2 2
4 AU D2 DS2 3
AU D2 DS2 4
s AU D2 DS1 5
10 3
CHELATE CODE CAI EDTA CA2 DTPA CA3 Carbolic Acid CA4 Hydroxy-carbolic Acids CA5 Citric Acid CA6 Glucinic Acid CA7 Other (describe) 4 VOLUME OF LLRW Volume of LLRW containing chelating agents (m3).
5 WEIGHT OF LLRW Weight of LLRW containing chelating agents (kg).
G.
DISPOSAL AND STORAGE 27 LLRW CLASS Class of radioactive waste as described in sections 61.55 and 61.56 of Ttle 10, Code of Federal Regulations, as in effect on January 26, 1983. atached following instructions.
AS Class A stable AU Class A unstable B
Class E C
Class C 28 DISPOSITION CODE D1 Directly to disposal D2 Treatment prior to disposal D3 Treatment/returned for storage D4 Treatmentino disposal (decontamination and reuse)
D5 Storage/no treatment D6 Hold for decay on ste and dispose as non-radioactive D7 Hold for decay off ste and dispose as non-radioadtive D8 Treatment/off-site storage D9 Other (describe) 29 DISPOSAL SITE DSI Bamwell, SC DS2 Clive. UT DS3 Richland, WA DS4 Other (describe) 30 STORAGE SITE S1 Onsite S2 Radiac S3 NDL S4 Adco S5 Other (describe) 5 WEIGHT % CHELATES Weights less than 1% need not be reported.
H. LLRW NOT MEETING DISPOSAL FACILITY ACCEPTANCE CRITERIA LLRW Hazard Code.
Volume (i 3)
Activity Radionuclides Class (MBq) 31 32 33 34 3s H.
31 32 33 34 35 LLRW WITH UNACCEPTABLE DISPOSAL CRITERIA LLRW CLASS See codes G-27.
HAZARD CODE See codes B4.
VOLUME Volume must be noted in cubic meters (mi).
ACTIVITY Activity must be reported in Mlega~ecquerels (Maq).
RADIONUCLIDES As applicable to H-3.
- 1. CONTAINERS WITH SURFACE RADIATION LEVELS GREATER THAN 2mSvthr (200mRlhr)
LLRW Class Volume (m3)
Activity by Radionuclide (MBq) 36 3
36 I
See Attached Sheets II
Packages >2 mSv Waste Class A
A A
A A
A Volume (m3) 5.8 5.8 5.8 5.8 5.8 5.8 Dose Rate (mSv) 13 10 12 10 13 6
mCi MBq mCI MBq mCi Maq mCi Maq mCi MBq mCi MBq H-3 2.28E-01 8.44E+00 2.28E-01 8.44E+00 2.14E-01 7.92E+00 2.28E-01 8.44E+00 2.31E-01 8.55E+00 2.28E-01 8.44E400 C-14 4.09E+00 1.51E402 1.99E+00 7.36E+01 5.02E+00 1.86E+02 2.66E+00 9.84E+01 2.16E+00 7.99E401 1.80E+00 6.66E+01 Cr-51 1.85E+02 6.85E+03 O.OOE400 O.OOE400 9.35E201 3.46E203 5.57E+01 2.06E+03 2.92E+01 1.08E+03 7.38E+01 2.73E+03 Mn-54 1.08E+03 4.OOE+04 4.65E+02 1.72E+04 1.08E+03 4.00E+04 6.53E+02 2.42E404 4.76E+02 1.76E404 4.90E+02 4.24E+04 Fe-55 2.10E+03 7.77E+04 1.03E+03 3.81E+04 2.51 E+03 9.29E+04 1.38E+03 5.11 E+04 1.07E403 3.96E+04 9.27E+02 7.53E+04 Fe-59 1.57E+02 5.81E+03 1.62E+01 5.99E+02 6.65E401 2.46E+03 4.89E+01 1.81E+03 2.12E+01 7.84E+02 5.02E+01 1.86E+03 Co-58 1.38E+02 5.11E+03 3.702+01 1.37E+03 1.39E+02 5.14E+03 1.04E+02 3.85E+03 4.71E+01 1.74E+03 8.16E+01 8.56E+02 Co-60 1.56E+03 5.77E+04 7.62E+02 2.82E404 1.89E+03 6.99E+04 1.02E403 3.77E+04 8.10E+02 3.00E+04 6.88E+02 5.322+04 Ni-63 3.05E+01 1.13E+03 1.49E+01 5.51E+02 3.75E+01 1.39E+03 1.99E+01 7.36E+02 1.61E+01 5.96E+02 1.34E401 4.96E+02 Zn-65 3.10E+02 1.15E+04 1.94E+02 7.18E403 4.72E+02 1.75E404 2.60E+02 9.62E+03 1.85E+02 6.85E+03 1.63E+02 6.032+03 Sr-90 0.002+00 O.OOE+00 O.OOE+00 O.OOE00 O.OOE+200 0.002+00 O.OOE+00 O.OOE00 O.OOE+000 0.002400 O.OOE+00 O.OOE+00 Zr-95 O.OOE+00 O.OOE+00 O.OOE00 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE00 0.002+00 O.OOE00 O.OE+00 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 0.002400 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 0.00+00 O.OOE+00 Tc-99 O.OOE+00 O.OOE00 0.002+00 0.00E400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE200 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+OO Ag-110m 3.45E+01 1.28E403 2.03E401 7.51E402 7.20E+01 2.66E+03 3.31E+01 1.22E+03 2.66E401 9.84E+02 1.922+01 7.10E+02 Sn-113 O.OOE400 O.OOE00 0.00E00 O.OOE+00 O.OE+00 O.OOE+00 0.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-124 1.03E+01 0.00E+OO O.OOE200 O.OOE200 3.96E+00 1.47E+02 5.872+00 2.17E+02 O.OOE+00 O.OOE+00 4.20E+00 1.55E+02 Sb-125 O.OE+00 O.OOE200 O.OOE200 O.OOE+00 O.OOE+00 O.OOE200 O.OOE200 O.OOE200 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 O.OOE400 O.OOE400 0.00E+00 O.OOE+OO O.OOE+00 O.OOE200 0.002+00 O.OOE+200 0.002+00 O.OOE200 O.OOE200 O.OOE00 Cs-137 6.74E-01 2.49E+01 3.28E-01 1.212+01 8.262-01 3.06E+01 4.39E-01 1.622+01 3.54E-01 1.31E+01 2.96E-01 1.43E+03 Ce-144 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+200 0.002+00 O.OOE00 O.OOE+00 O.OOE+00 9.36E+02 Total 5.61E+03 2.08E+05 2.54E+03 9.41E404 6.37E403 2.36E+05 3.58E+03 1.33E405 2.68E+03 9.93E+04 2.51 E+03 9.30E+04
Packages >2 mSv A
A A
A A
A A
5.8 5.8 3.8 3.8 3.8 3.8 3.8 15 12 1.5 10 10 1040 255 mCI MBq mCi MBq MCI MBq mCI Mq mCi MBq mCi MBq mCi MBq 2.25E-01 8.33E+00 2.11E-01 7.81E400 1.25E-01 4.63E400 1.24E-01 4.59E+00 1.24E-01 4.59E+00 1.93E-01 7.14E400 1.79E+01 6.62E402 6.19E+00 2.29E+02 5.79E+00 2.14E+02 3.50E-01 1.30E+01 1.89E+00 6.99E+01 3.OOE+00 1.11E+02 2.49E+01 9.21E402 1.22E+01 4.512402 3.46E+01 1.28E+03 2.01E401 7.44E+02 1.12E+00 4.14E+01 9.91E+00 3.67E+02 9.52E+00 3.52E+02 O.OOE+00 O.OOE200 O.OOE+00 O.OOE200 1.36E+03 5.03E+04 1.14E+03 4.22E+04 1.12E402 4.14E+03 4.98E+02 1.84E+04 6.69E+02 2.48E+04 1.43E+04 5.29E+05 6.75E+03 2.50E205 2.96E+03 1.10E+05 2.72E+03 1.01E+05 1.68E+02 6.22E+03 8.87E+02 3.28E+04 1.41E+03 5.22E+04 3.31E+05 1.22E+07 1.62E+05 5.99E+06 6.28E+01 2.32E+03 3.80E+01 1.41E+03 2.48E+00 9.18E+01 2.06E+01 7.62E+02 1.982401 7.33E+02 O.OOE+00 O.OOE+00 0.00E+00 O.OOE400 1.26E+02 4.66E403 7.462401 2.76E403 4.54E+00 1.68E+02 3.21E+01 1.19E403 4.40E+01 1.63E+03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.28E203 8.44E404 2.111203 7.81E+04 1.29E+02 4.77E403 6.89E+02 2.55E+04 1.09E+03 4.03E+04 9.95E+04 3.68E406 4.88E+04 1.81E+06 4.622+01 1.71E+03 4.32E+01 1.60E+03 2.61E+00 9.66E+01 1.41E+01 5.22E+02 2.24E+01 8.29E+02 1.01E+03 3.74E404 4.95E+02 1.83E+04 4.11 E402 1.52E+04 3.51 E +02 1.30E404 2.56E+01 9.47E+02 8.63E+01 3.19E203 1:48E402 5.48E403 1.84E+05 6.81E+06 8.24E+04 3.05E406 O.OOE+00 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE200 0.00E4O0 0.00E+00 6.332-01 2.34E+01 3.10E-01 1.15E+01 O.OOE400 O.OOEO0 0.002+00 0.002+00 O.OOE+00 O.OOE+00 O.OOE200 0.002EOO O.OOE +00 O.OOE+00 0.00E+00 O.OOE+00 0.002+00
.O0E+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+200 0.002+00 O.OOE00 5.80E-01 2.15E+01 O.OOE400 O.OOE+00 O.OOE+00 O.OOE200 0.002+00 O.OOE+00 O.OOE0+0 O.ooE+00 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE2400 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.07E201 2.25E+03 5.17E+01 1.912+03 5.64E+00 2.09E+02 1.51E+01 5.59E+02 2.89E+01 1.07E+03 8.06E+02 2.98E+04 2.98E+02 1.10E+04 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.002+0 O.OOE+00 O.OOE+00 O.OOE2400 0.00+00 0.002+00 O.OOE400 O.OOE+00 O.OOE+00 5.84E400 2.16E+02 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 2.65E+00 9.81E+01 1.89E+00 6.99E+01 O.OOE200 O.OOE 200 O.OOE+00 O.OOE02 O.OOE00 O.OOE+00 O.OOE00
.OOE+O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE200 1.01E+00 3.74E+01 9.47E-01 3.50E+01 5.73E-02 2.12E+00 3.08E-01 1.14E+01 4.91E-01 1.82E+01 5.42E+00 2.012+02 2.66E+00 9.84E+01 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.56E-01 1.32E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.35E+03 2.72E+05 6.56E+03 2.43E+05 4.52E+02 1.67E+04 2.26E+03 8.35E+04 3.45E+03 1.28E+05 6.31E+05 2.33E+07 3.01E+05 1.11E407
Packages >2 mSv A
A A
A A
A A
55.8
.8 5.8
' 5.8 5.8 5.8 5.8 106) 78 105 101 10 255 30 mCi MBq mCi M~q mCi MBq mCi MBq mCI MBq mCi MBq mCi MBq 4.50E-01 1.67E2.01 3.73E-01 1.38E401 4.49E-01 1.66E+01 4.53E-01 1.68E+01 4.46E-01 1.65E401 4.50E-01 1.67E+01 1.91E+01 7.07E+02 4.04E+01 1.49E+03 5.11E+01 1.89E403 8.68E401 3.21E+03 2.35E+01 8.70E402 1.77E+00 6.55E+01 8.96E+01 3,32E+03 O.OOE400 O.OOE*00 O.OOE+00 0.002+00
.OOE00400 O.OOE+00 0.0E4OO O
.OOE+ 00
.OOE+
- 00. 0 O.OOE+00 O.OOE+00 O.OOE400 9.74E-01 3.60E+01 O.OOE400 O.OOE+00 2.83E403 1.05E405 6.01E403 2.22E405 9.30E403 3.44E+05 2.94E+03 1.09E205 2.54E+02 9.40E403 1.14E+04 4.22E+05 4.66E402 1.72E+04 2.02E+04 7.47E+05 2.55E+04 9.44E*05 4.30E404 1.59E406 1.21E404 4.482405 8.47E+02 3.13E404 4.47E+04 1.65E4.06 4.68E403 1.73E2405 O.OOE+00 O.OOE+00 O.OOE400 O.OOE00 O.OOE-00 O.OOE+00 3.87E401 1.43E+03 2.10E400 7.77E+01 1.23E+02 4.55E+03 9.19E-01 3.40E+01 1.13E402 4.18E+03 1.40E*02 5.18E403 2.64E*02 9.77E403 1.18E402 4.37E203 1.09E+01 4.03E402 3.56E402 1.32E204 1.82E400 6.73E401 1.52E+04 5.62E+05 1.92E+04 7.10E405 3.26E+04 1.21E+06 9.OOE+03 3.33E+05 6.53E+02 2.42E204 3.372+04 1.25E+06 1.23E+03 4.55E404 3.01E+02 1.11E+04 3.82E+02 1.41E+04 6.48E+02 2.40E+04 1.76E+02 6.51E+03 1.32E+01 4.88E+02 6.69E+02 2.48E+04 6.52E401 2.41E+03 1.26E*04 4.66E+05 3.37E+03 1.25E+05 6.25E403 2.31E+05 1.84E203 6.81E+04 9.05E+01 3.35E+03 5.95E403 2.20E405 1.34E402 4.96E403 O.OOE400 O.OOE400 O.OOE400 O.OOE200 0.OOE400 O.OOE+00 O.OOE00 O.OOE400 O.OOE+OO O.OOE*00 O.OOE+00 O.OOE+OO 0.OOE+00 O.OOE+oo O.OOE+00 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE00 O.OOE400 O.OOE+00 O.OOE+00 O.O+00 O.OOE400 O.OOE400 O.OOE200 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE+00 O.OOE400 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEE00 O.OOE400 O.OOE200 O.OOE+000 0.00E400 O.OOEOO O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE+OO O.OOEOO O.OOE+00 4.99E401 1.85E403 6.43E401 2.38E+03 1.01E+02 3.74E+03 8.86E201 3.28E+03 O.OOE+00 O.OOE+00 2.19E202 8.10E203 O.OOE400 O.OOE+00 O.OOE+00 O.OOE400 O.OOE00 O.OOE+0200 0.002400 O.OOEO00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 0.002400 O.OOE+00 O.OOE400 O.OOE400 O.0E0200 O.OOE+00 O.OOE+00 O.OOE+00 0.002E00 O.OOE+00 O.OOE+00 O.OOE+00 0.002400 O.OOE+00 1.932-01 7.14E+00 O.OOE400 O.OOE400 O.OOE400 O.OOE0 0..OOE+000 O.OOE+00 0.0000 0.002+001 0.0012400 O.OOE+00 1.13E+02 4.18E+03 1.60E401 5.92E202 O.OOE400 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE200 O.OOE400 O.OOE200 O.OOE400 O.OOE400 O.OOE400 O.OOE400 6.63E+00 2.45E+02 8.40E+00 3.11E+02 1.43E+01 5.29E+02 3.88E+00 1.44E+02 2.90E-01 1.07E+01 1.47E+01 5.44E402 4.29E200 1.59E+02 O.OOE+00 0.002400 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 0.00E+00 O.OOE400 O.OOE+00 O.OOE400 O.OOE+00 5.13E+04 1.90E206 5.47E+04 2.02E+06 9.23E204 3.41E+06 2.63Et04 9.74E+05 1.87E+03 6.93E+04 9.73E404 3.60E+06 6.62E+03 2.45E+05
Packages >2 mSv A
A A
A A
A Al 5.8 5.8 5.8 5.8 5.8 5.8 5.8 30 30 30 40 30 15 25 mCi MBq mCi MBq mCi MBq mCi MBq mCi MBq mCI MBq mCi MBq 2.21E*01 8.18E+02 2.21E401 8.18E+02 2.18E-01 8.07E+00 4.53E-01 1.68E+01 4.07E-01 1.51E401 4.48E-ol 1.66E401 4.53E-01 1.68E401 O.OOE400 O.OOE400 O.OOE00 O.OOE400 5.13E400 1.90E+02 1.53E+01 5.66E402 8.66E*00 3.20E202 1.49E+01 5.51E+02 1.89E+00 6.99E+01 O.OOE400 O.OOE+00 0.0012*00 0.002O0 1.24E-01 4.59E+00 3.28E402 1.21E+04 5.73E+00 2.12E402 5.42E+01 2.01E+03 O.OOE+00 O.OOE+00 5.38E+02 1.99E404 5.32E202 1.97E+04 6.64E+02 2.46E+04 2.99E+03 1.11E+05 2.40E+03 8.88E+04 1.99E+03 7.36E404 3.23E402 1.20E404 5.41E+03 2.00E*05 5.40E403 2.00E+05 2.13E+03 7.88E404 7.84E+03 2.90E*05 1.00E404 3.70E405 7.31E+03 2.70E+05 9.70E+02 3.59E+04 1.03E+00 3.81E+01 9.55E-01 3.53E+01 1.61E+00 5.96E+01 3.53E+02 1.31E+04 1.62E402 5.99E403 1.05E+02 3.89E+03 6.67E200 2.47E+02 2.07E+00 7.66E401 1.97E+00 7.29E+01 1.41E+01 5.22E+02 2.05E.02 7.59E403 1.18E+02 4.37E+03 9.13E401 3.38E403 3.29E401 1.22E403 1.42E403 5.25E+04 1.42E+03 5.25E+04 1.76E+03 6.51E+04 5.84E+03 2.16E+05 5.95E+03 2.20E+05 5.55E203 2.05E+05 7.22E+02 2.67E+04 7.56E+01 2.80E.03 7.55E+01 2.792403 3.81E*01 1.412E03 1.14E+02 4.22E203 6.38E+01
- 2.36E+03 1.11E+02 4.11E+03 1.41E+01 5.22E+02 1.541+02 5.70E403 1.52E+02 5.62E+03 2.15E+02 7.96E+03 6.84E+02 2.53E+04 9.89E402 3.66E+04 9.56E+02 3.54E+04 1.93E202 7.14E403 O.OOE200 O.OOE+00 O.OOE+00 O.OOEE00 O.OE'00 0.00E400 0.0021+00 O.OOE400 O.OOE400 O.OOE200 O.OOE00 O.OOE*00 O.OOE*00 O.OOE+00 O.OOE400 O.OOE+00 O.OOE400 O.OOE+00 O.OOE400 O.OOE+00 1.24E+01 4.59E202 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E4OO O.OOE400 O.OOE200 O.OOE+00 O.OOE+00 O.OOE+00 4.49E+00 1.66E+02 0.00E+00 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.0E0+00 O.OOE+00 O.OOE+OO 0.002+00 O.OOE+00 O.OOE+00 O.OOE2400 0.00E00 0
C O.0+0
.OOE +00 O.OOE200 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE2400 0.00400 O.OOE00 3.73E+01 1.38E+03 3.06E401 1.13E+03 2.84E+01 1.05E+03 4.22E+01 1.56E203 1.78E+00 6.59E+01 O.OOE00 O.OOE400 O.OOE200 O.OOE+00 O.OOE+00 O.OOE400 1.12E401 4.14E402 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.18E-01 8.07E+00 2.062-01 7.62E+00 3.03E-01 1.12E401 1.762401 6.51E+02 2.84E401 1.05E403 7.68E+00 2.84E+02 O.OOE400 O.OE400 1.85E+01 6.85E+02 1.84E+01 6.81E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.28E+00 4.74E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.0OE+00 O.OOE+00 O.OOE200 O.OOE+00 O.OOE400 O.OOE400 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00
.0.00E+00 4.97E+00 1.84E+02 4.97E+00 1.84E+02 8.30E-01 3.07E+01 2.52E+00 9.32E+01 3.09E401 1.14E+03 2.44E+00 9.03E+01 3.11E-01 1.15E401 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE200 O.OOE+00 O.OOE+00 O.OOE400 O.OOE400 7.65E+03 2.83E+05 7.63E+03 2.822+05 4.87E#03 1.80E205 1.84E+04 6.83E+05 1.98E+04 7.32E+05 1.62E+04 6.012+05 2.27E+03 8.382404
Packages >2 mSv A
A A
A 5.8 5.8 5.8 5.8 s0 25 50 50 mCi MBq MCI MBq MO MBq mCi MBq 4.07E-01 1.51E401 4.07E-01 1.51E+01 4.07E-01 1.51E+01 3.05E-01 1.13E+01 6.30E+00 2.33E402 4.87E400 1.80E#02 3.77E+00 1.39E+02 4.70E+00 1.74E+02 O.OOE00 O.OOE400 O.OOE200 O.OOE0O O.OOE00 O.OE+00 O.OOE+000 O.OOE+00 1.40E+03 5.18E404 1.27E+03 4.70E*04 9.26E*02 3.43E+04 9.83E202 3.64E+04 7.33E+03 2.71Ei05 5.66E+03 2.09E+05 4.37E+03 1.62E+05 5.42E+03 2.01E+05 4.23E+01 1.57E+03 4.62E+01 1.71E+03 3.58E+01 1.32E+03 1.95E+01 7.22E+02 6.68E401 2.47E403 7.54E+01 2.79E403 4.85E401 1.79E403 2.90E+01 1.07E+03 4.34E*03 1.61E+05 3.35E+03 1.24E+05 2.59E+03 9.58E+04 3.22E+03 1.19E+05 4.64E+01 1.72E403 3.59E401 1.33E+03 2.78E201 1.03E+03 3.46E+01 1.28E+03 1.44E+03 5.33E+04 1.35E+03 5.00E+04 9.91E+02 3.67E+04 8.45E+02 3.13E+04 O.OOE+00 O.OOE200 O.OOE+40 O.OE+00 O.OOE400 O.OOE00 O.OOE+00 O.OOE+00 O.OOE200 O.OOE200 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE400 O.OOE+00 O.OOE00 O.OOE*00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE400 O.OOE+00 O.OOE+00 O.OOE0+0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE0+0 O.OOE+00 4.16E401 1.54E+03 4.47E+01 1.65E203 3.55E+01 1.31E+03 2.95E401 1.09E+03 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.0E0+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
, O.OOE+00 O.OE+00 O.OE0+0 O.
0 E00+00 1.33E+00 4.92E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00
.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 0.OE+00 2.25E+01 8.33E202 1.74E+01 6.44E+02 1.34E+01 4.96E+02 1.682+01 6.22E+02 O.00E+00 O.OOE+00 O.OOE200 O.OE+00 O.OOE+00 O.OOE+0 0.002+00 O.OOE+00 1.47E+04 5A52+05 1.19E+04 4.39E+05 9.04E+03
- 3.35E405 1.06E+04
... 3.92E+05
SECTION IlIl. LLRW
SUMMARY
A. DISPOSAL TOTALS FOR THIS YEAR Classes Disposed at Barnwell, SC Disposed at Clive, UT Disposed at: Richland, WA SUBTOTALS BY CLASS Class A Volume (in')
Activity (M~q)
Volume (m0)
Activity (M8q)
Volume (m')
Activity (MBq)
Volume -A Activity -A Via Broker/
49981900.00 Processor 0.900 33600000.000 19.360 16381900.000 20.260 0
Direct Transfer 0.000 0.000 Class B Volume-B Activity -B Via Broker/
Processor 0.000 0.000 Direct Transfer 0.000 0.000 Class C Volume -C Activity -C Via Broked Processor 0.000 0.000 Direct Transfer o.ooo 0.000 TOTALS 0.900 33600000.000 19.360 16381900.000 0.000 0.000 TOTAL ALL CLASSES VOLUME ACTIVITY 20.260 49981900.00 0
B. INTERIM STORAGE TOTALS Classes Placed in Interim Storage during this year Placed In Interim Storage before this year SUBTOTALS BY CLASS Class A Volume (m')
Activity (MBq)
Volume (m')
Activity (MBq)
Volume - A Activity -A On Ste 0.000 0.000 Oft She 17.400 1170000.000 17.400 1170000.000 Class B Volume
- B Activity B On Ste 0.000 0.000 OH Ste 0.000 0.000 Class C Volume
- C Activity -C On Site 0.000 0.000 Onr Ste 0.000 0.000 TOTALS 17.400 1170000.000 0.000 0.000 TOTAL ALL CLASSES 17.400 1 1700DO.000
SECTION IV. RADIONUCLIDE INFORMATION FOR WASTE DISPOSED, HELD FOR DECAY, AND STORED NOTE: Radionuclides mean each individual radionuclide if known, or, at a minimum, all radionuclides that have been or would have to be identified on disposal site manifests. H-3, C-14, Tc-99, and 1-129 must be identified where present.
List the radionuclides contained in the LLRW disposed of during this year (see response to Section Ill-A). Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
H-3 3280.000 C-14 15400.000 Cr-51 34300.000 Mn-54 2730000.000 Fe-55 26200000.000 Fe-59 50300.000 Co-58 85500.000 Co-60 11100000.000 Ni-63 169000.000 Zn-65 9500000.000 Sr-90 34.900 Zr-95 471.000 Nb-95 204.000 Ag-1Orm 80500.000 Sn-1 13 428.000 Sb-124 2960.000 Sb-125 6250.000 Cs-137 6440.000 Ce-144 957.000 Total Activity in MBq 49986024.900 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW disposed of, as reported in Section III-A.
A.2 l If any of the radionuclides listed in Table A-1 have half-ives of less than 90 days, please explain why these are not being held for decay and eventual disposal
- I as non-radioactive waste.
All waste disposed of consists of mixed fission products. Radionuclides with half-lives less than 90 days can not be separated from the waste, and aare disposed of with the other mixed fission products.
I B.1 I List the radionuclides contained in the LLRW being held in storage for decay on site as of December 31. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide 8.2 U
Lis? the radionuclides contained in the LLRW being held In storage for decay off site as of December 31. Use additional sheets as necessary.
Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide Radionuclide CJ1 IOn site B
List radionudides contained in LLRW in Interim storage on site as of December 31. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Total Activity in MBq 0.000 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW stored on site, as reported.
C.2 lOff site B List radionuclides contained in LLRW in interim storage off site as of December 31. Use additional sheets as necessary.
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
Radionuclide Activity (MBq)
H3 41.400 C-14 494.000 Mn-54 118000.000 Fe-55 572000.000 Fe-59 3760.000 Co-SB 5560.000 Co-60 339000.000 Ni-63 3640.000 Zn-65 118000.000 Ao-1 10m 4060.000 Cs-137 1760.000 Total Activity in MBq 1166415.400 Total activity for all radionuclides listed above:
Total activity should equal total for LLRW being stored off site, as reported.
C.3 l If any of the radionuclides listed in Table C-1 or C-2 have half-lives of less than 90 days, please explain why these are not being held for decay and eventual I disposal as non-radioactive waste.
SECTION V. STORAGE FACILITY INFORMATION NOTE: If your facility manages LLRW by storage for decay only, you only need to complete the Condensed Form for Decay in Storage Only.
ON-SITE STORAGE FACILITIES A.1 Briefly describe your on-site LLRW storage facilities. Include facilities you have for storage of special LLRW forms such as freezers, shielded areas for high-radiation-level wastes, or bermed storage areas for liquid wastes, and estimate the storage capacity for each.
Storage facility consists of 2 concrete pits at Unit 1 and 3 concrete rooms at Unit 2 with sufficient storage capacity for Unit 1 and 2 for 20 years A.2 Total Storage Capacity: 4360 m3 A.3 Estimated maximum volume of LLRW held in storage for decay at any one time: f m3 B
Do you have any plans for increasing your on-site storage capacity?
El No. Skip lto C.
I
~Ii[ Yes. Complete this section.
Describe such plans and indicate your expected new storage capacity.
OFF-SITE STORAGE FACILITIES C
Off-site storage facility information. Use additional pages if necessary.
Please indicate if off-site storage is for storage for decay or interim storage.
j Storage for decay A
Interim storage Name of facility Studsvik Processing Facility Address: TC Runion Road Erwin, TN Contact and phone number: Ron Leonard 423-735.6300 NOTE: Please answer the following question based on LLRW requiring disposal at licensed LLRW disposal facilities, not LLRW held in storage for decay. Do NOT USE DESCRIPTIVE TERMS SUCH AS UNLIMrrED, CONTINUOUS, OR INDEFINITE.
ESTIMATED STORAGE TIME FOR LLRW REQUIRING DISPOSAL D
Based on your anticipated LLRW generation rate and your anticipated capacity to store NOTE: Answer must be in months.
waste as of December 31, HOW MANY MONTHS could you continue to produce and store LLRW on site if access to licensed LLRW disposal facilities were no longer available?
240 months
SECTION VI. FUTURE LLRW GENERATION 2003 FUTURE LLRW GENERATION THAT WILL REQUIRE DISPOSAL Year Class Activity (MBq)
Volume (m')
Radionuclides 2004 A
37000000.000 120.000 Co-60, Zn-65, Mn-54, Cs-137, Ce-144, C-14, Ni-63, Ni-59, Fe-55, B
15000000.000 3.710 Fe-59, Co-58, Sr-90, H-3, Sr-89, Sr-90, Tc-99, Ao-1IOm.
C.
Total 52000000.000 123.710 2005 A
37000000.000 120.000 Same as above B
15000000.000 3.710
- C Total 52000000.000 123.710 2006 A
3700000000.000 120.000 Same as above B
15000000.000 3.710 C
Total 3715000000.000 123.710 2007 A
37000000.000 120.000 Same as above B
15000000.000 3.710 C
Total 52000000.000 123.710 2008 A
37000000.000 120.000 Same as above B
15000000.000 3.710 C
Total 52000000.000 123.710
SECTION VII. ATTACHMENT SHEET FOR ANY ADDITIONAL INFORMATION (Table will automatically expand as information is entered)
Section lIc Rows 1, 2,4 Column 13 Studsvik Processing Facility Section Hlc Rows 3, 5 Column 13 GTS Duratek Section lIc Rows 1, 2, 4 Column 14 Studsvik Processing Facility Section llf Row 6 Column 28 Not processed by year's end - In interim storage awaiting processing in 2004 Section Ilf Row 6 Column 29 Studsvik Porcessing Facility