ML19308C304
| ML19308C304 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/26/1979 |
| From: | Daniel J, Garman L, Nitti D GENERAL PUBLIC UTILITIES CORP. |
| To: | GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001220673 | |
| Download: ML19308C304 (8) | |
Text
Junc 116,1989 i 3 5,, fb.% U " ?'* Gh ao 7
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bCi.dEh.-4j M W hOh 1Rt,opolitan Edison Company Three Mile Island - Unit 2 - Redioactive Wastes Cemposition and Isotopic Analysis Lo:aSon TMI Distribution 1.0 Introduction This memo serves to transmit the estimated conpositions and volumes of thethree main radioactive liq id vaste sources, namely the auxiliary building reactor coolant bleed tanks, the containment sump, and the reactor coolant system.
Table I (attached) lists the radioactive nuclides expected to be found present in each vaste source together with their respective atoont of activity, as of July 1,1979.
Table II (attached) lists the various chemical elements and co= pounds expected to be associated with each vaste water source together with their respective concentrations as of July 1,1979.
Both these tables, which correlate all the data known, theorized, and/or calculated to date, are of f ered as a first attempt to inform concerned individuals of the estimated co. position of the liquid vastes and the substances which night be encountered during the treatnent of these vastes.
Since some of the figures have been formulated f rom engineering judg-ment, it is our intent that the Data Analysis Section of the Wasie Management Group periodically update both tables as more accurate data becomes available.
A:sended tables vill be issued, as they become available, per distri-bution of
's memo and to other persons expressing an interest in this infor a tion.
2.0 Discussion In order to develop both tables, it was necessary first to, establish an estimate of the type and degree of damage the core incurred during the incident, secondly, to develop a criterla for fission product release, and thirdly, to perform material and water balances on the three vaste sources to obtain the chemical compositions.
- D']M(0'I D P 2.1 Core pamage Assessment 3
ss s
w a.
The dr. mage assessment of the core and its Zircaloy clad fuel rods was evaluated using the f ollowing:
1.
Technical report NUREG/CR-0274 (ORSLh UREC/TM-154)
- j October 1, 1978.
8 0 0.y g'ggn y3 :.
.... \\
[
a.
GoU Smi:e Cor:dinon c. a subsiivy o! G:nt-ra! Ph.*::: U:Sc3 Com: a:.on J
u-~;
,g 50 Xc, Kr.
60.
I, H2 65 Cs, Rb
~
60 Te, Se, Sb 5
j I
Sa, Sr, Mo i
I 3
i i
I:oble Metals 0.2 Rare Earths 0.2 Zr, Nb The radioactive caterial released from the core was dis tributed between
~
the contain=ent st=p, and the auxiliary the reactor coolant system, building reactor coolant bleed tanks based on the ca:pected che=f es1 behavior of each nuclide and on the available analyses of cach nuclide and on the available analyses of reactor coolant and biced tank samples.
For nuclides that have been identified in the reactor coolant and in
'the bleed holdup tanks, it was possible to esti= ate the activity in the sump by subtracting the measured amounts from the estimated release For the zeno:i and krypton nuclides which are found from the core.
primarily in containment g-a's samples, the concentration in the contain-For ment su=p was determined by assuming a Henry's I.av equilibrium.
nuclides for which no information was available, their behavior was -.
~
deduced by one of the following nethods:
1.
The nuclide was assu=ed to behave in. a like canner to another nuclide in the same che=ical f amily for which measured data was available.
2.
The nuclide was assumed to be in the form of a hydroxide or a hydrated oxide, and its chemical behavior was pre-dicted based on the co= pounds volatility and solub,ility.
2.3 Chemical Composition The chemical compositions of the various vaste sources were obtained with the aid of the following:
Eshcock and Wilcox vater inventory =emo dated May 6,1979.
1.
' Gilbert Associates Water In& lysis Su.=ary f or the Susquehanna 2.
River at Three Mile Island.
Babcock & Wilcox Boric Acid - Sodium Hydroxide Titration -
3.
Curves.
\\
4.
ORSL Chemical Analysis Primary Coolant dated May 25, 1979.
5.
Sabcock & Wilcox Chemical Laboratory.1.al, sis.
Babcock & Wilcox origen calculation - run nu=bers LOR-207U 6.
' $1.'.
-h
~ ~
":~'"'
. ' ' ~
-. Q.... -I.-:- L -- ).
',. '. e-h :. :.
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and LOR-2 SE3 t
N
..s; Q}g
.._..:. v _.
f
-_.z..y-.
.:..,..1,.,.
u..,...-
w,
e 2.
P.abcoch 6 Vficox r.c:-o on hydrogen release f rom r.etal-wat er N
reactions date:'. April 19, 1979 3.
-Laboratory analyses (liquid and gaseous) 4.
Estimate of temperat e profile within the reactor core during the incident The conc 1'usions arrived at are sum:narized as follows:
i 1.
Approximately 22% by weight of the Zircaloy cladding v s exposed to high enough temperatures for the elements to be converted to their respective oxides. "
The estimated te=perature profile indicates that the greatest 2.
amount of oxide for=ation occurred at the. top center line of the core and decreased with distance to the edge of the core and to a point approximately six (6) feet from the top of the core to form a damaged region which would sppear as an inverted cone.
3.
Within the conical region where significant cladding damage ~
occurred, the Zircaloy should be highly oxidized and brittle with some degree of spallation and porosity.
Outside the conical region the cladding should be essentially int. set and non-porous with an oxidation film on the surface.
2.2 Fission Product Release In order to establish representative release fractiuns for the fis-sion products within the rods, the following reference documents were employed:
1.
WASH-1400 (Vol VII).(P. VII - 3 through VII - 15) 2.
ORNL-3981 (1965) Table 6.2 3.
Babcock 6 Wilcox memo on strontium isotopic analysis dated June 6, 1979.
4.
Laboratory isotopic analyses t
5.
ORNL sample analysis memo on ricar/ coclant dated May 25, 1979 6.
Handbook of Chemistry and PhyMr s 7.
Babcock & Wilcox Origen Calculation - Printout Numbers LOR-207U and LOR-205E Using the above references in conjunction with the section on core d::2ge assess =ent, the following release values were selected:
. mo
? D qQC
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w.
th.
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l
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..-...q:. _.
,.;._.,.y.........-
.v
.._.z. - -_
-..,: 1
.. e 7.
Unit 2 Control Roo= log #3ook 8.
Table I - Attach =ent 9.
I!andbook of Chemistry and Physics.
Th'e rajority of the items on 'the table have been dis:.ributed in the ;.
three vaste sources either by cass balance or laboratory saslyses.
'- So=e of the important facts are listed as follows:
1.
Approxicately 60,000 gallons of water, presumed to be river water, entered the c'ontainment sump from an unconfirmed source.
2.
The oil and gresse figures are derived fro: knowledge of known equip = ant inventories.
'I-is expected tha,t a portion of this oil vail be enuisified (ae to the alkaline waters.
i 3.
The inert suspended and settleable solids are based on past history of su=p typs vaste waters in power plants.
In conclusion, should there be any questions relative to the contents of this remo, please direct them to John Daniel, Donald Nitti, or David Carr.an.
Prepared by Donald A. I;itti f
G,&,"Mr L. David Car =an Approved by _
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-n ACTIVITf ACT!'lIW I:3 i
IEILiltilNG ACTIVIH 11; REACTOR ACTIVin III REACT 0i C0(tai!T N
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PADI0t3UCL1DE III Cont COO!.MIT S751Eli ColiTAll;:033T SUI 3' DICED TM*45 ~
'l El.EitEtiT In Curles IngoIEnble Solushle(I) ir.aoluable Soln >le(2)
Insolnshle !>oluabl Inpcif In Curica In pel/mi Ir. Curies In pel/ml In Curtes
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X.
e.,
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3',
P romethium rm-147 3
6 6.6 x 10 550 l ',
3.3 x 10 #
9.
Pe-14Da 7.8 x 10' 156 15 0.2 re-146 1.3 x 10' 36 3
0.1 j'.';
4 Samariun S=-151 1.2 x 104 24 2
a r8.0 5 3
15 2
0.05
'd Europium Cu-154 7.5 x 10 T.'
Es,-155 3.1 x 10' 62 5
0.1 3
0.01 if Eir-156 4.8 x 10 1
0.1
~0
!$ Uranium U-235 3.945 2.5 x 10-6 0
2.5 x 10~7 0
2.5 x 10 0
9 U-236 27.1A 1.2 x 10~5 0
i 2 x Ig &
O -
1.1 x 10"I O
3 0
.0 x 10~'
O 4.3 x 10-5 0
- f.t Plutonium Fu-239 8612.
4.3 x 10~3 1.7 x 10~'
O
- 1. 7 x 3 0-5 0
Y.8. 'j' Pir-240 2495.
1.7 x 10~
0 667 1067,.
95
/ TOTAL n
&n(.
3.
P-PJ' ~'.,
g C
? NOTESI (1) Daned on 85,000 gallone 3,
%gi g
(2) ansed on 540,000 nallons W
y.
(3) ansed on 240,000 an11ona
- 9 b th Y
- Indicatee Lens Than 1 lw1/mi I
r e
- h. M N
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.l tj t
r-5 s.
4
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yratr.lF-Ins u amor.%-
e (1) E !.CTOR (2) CO2.TU!!?SNT (3) FJ.ACIOR TEM C^?L/2;T SC? IN C 007..*0iT EYF 3.M PPM 31.EED T/dW.S IN IN TP:!
PPM 7.' Il2NT/CO:5'0UND:
'ed.i tn(As Na) 220 1215 220'
.i thiu= (As Li) 0.1 0.5 0.1
'siciu= (As Ca) 20 65 15
,'S;,nesiu: (As Mg) 5 15 2
'ron (As Fe) 3 6
4
~ :sssiu: (As K) 1 3
2 To:a1 Other Cstions 2
4 3
~:.ron ( As B) 3180 1650 610 Jilies (As SiO )
1 4
2 2
'ulfstes (As SO )
5 18 10 4
~ ic s.rbona t es (As HCO )
20 75 20 3
- hlorides (8.s C1) 10 15 17 stal other Anions 2
5 3
. ISSION PRODUCT ELEMENTS:
- sit = '(As Cs) 1.8 7.1, 1.0
'ubidium (As Eb) 0.7 0.9 0.3
' rontium (As,Sr) 0.6 0.2 0.1
.alybdenum (As } o) 2.0 0.5 0.1
'irconite (/.s Zr) 0.1 0.2 0.1
~
3dina (As I) 0.1 0.4 0.1 3.riu= (As Sa) 0.8 3.6 0.5
'211uriu=
(As.Te)
O.2 0'. 4 0.1 To:e1 Others ~ ~ ~ " - " ~ ~ ~ - ~ ~ -~ 2. 0
' ' ~ ~ ~ ~ '
- 1. 0 0. 8
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7H 8.0 8.8 S.O e
9' MlE
% DI 'UNOS D Tt*]D e j
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TABLE II (cont ' d.)
-3 (3) F.UCTOP.
(2) CCNTAiNYe.NT C0O', nit (1) PIACTOR SD:? IN COOLANT BLEi.D TA'T:~5 PPM
'.7.jj SYSTEM IN PPM IN PPM 4 C. EASE:
3 65 0.1 1
- Flecting 15 0.1
'.sified
^^INDED SOLT.DS:
25 35
- (Dirt, Dust, Etc.)
1 0.1 0.3 5
.ical (Colloidal,
- 'recipitates, e tc.)
LEAELE SOLIDS:
24 13 rconiu= 0xide (As Zr0 )
1585 1.7 2
U.9 109 0.003 2niun Oxide (As UO )
0.002 2
0.25 0.3
- w - Oxide (As FuG )
0.5 2
17 10 21 Other Orides 35 2rts (Dust, Dirt, Grit, Etc.)
2
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(1) Sesed en 85,000 galicas
" - ~
(2) E: sed en 540,000 gallons gallensincluding intact cladding, assu ad to be in reactor core.
(3) Ecsed on 240,000 c
(4) P,alanc e of r. ass,
h 6eI sf J SJJt!! m W
i
.