ML19276F026
| ML19276F026 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 02/21/1979 |
| From: | Darmitzel R GENERAL ELECTRIC CO. |
| To: | Kratzke R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 12122, NUDOCS 7903270013 | |
| Download: ML19276F026 (17) | |
Text
PDAL k-M.
NUCLEAR ENERGY G c,. 3d ER AL [$ ELECTRIC t
ENGINEERING GENERAL ELECTRIC CCMPANY, P.O. BCX 460, PLEASANTON. CALIFCANIA 94566 DIVISION Feb ruary 21, 1979 s
Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
R. T. Kratzke Fuel Reprocessing and Recycle Branch
References:
1)
License SNM-960, Docket 70-754 _
- 2) Order to Show Cause, 10/24/77
- 3) Letter with attachments, R. W. Darmitzel to C. V. Smith, 11/12/77
Dear Mr. Kratske:
On November 12, 1977, the General Electric Company, Vallecitos Nuclear Center (VNC), submitted a summary of oral infor=ation given to the Commission staf f concerning operation of facilities licensed under Smi-960.
In the interim, VNC has re-examined this information and has developed i= proved source terms.
Accordingly, VNC is submitting one signed and twenty (20) conformed copies of the corrected pages to our previous submittal (Reference 3).
Sincerely,
/s/R. W. Darmitzel Manager Irradiation P ccessing Product Operation mk Att.
1.21~>~
06 7903270
GEN ER AL $)) ELECTRIC AFFIRMATION General Electric hereby submits the attached corrected pages to its submittal of Nove=ber 12, 1977, concerning activities conducted at the Vallecitos Nuclear Center under License SNM-960.
To the best of my knowledge and belief, the infor=ation contained herein is accurate.
By:
/s/R. W. Darmit el Manager Irradiation Processing Product Operation Submitted and sworn before me this day of 1979.
, Notary Public in and for the County of Alameda, State of California.
On occasion, work with other alpha emitters is also done in Cell 4.
For example, fabrication of sealed sources containing Am-241 =ay be done on a special order basis.
Similarly, sealed sources containing Cf-252 may be made in this cell.
The Cf-252 is in a californium-palladium cermet and is non-dispersable.
The An-241 is currently stored in a 2-R type container and is non-dispersable.
Only sufficient material to fabricate sources which have been ordered would be handled at any one time.
The final cell in this group is Cell 3, where the fission product separations take place.
This cell also has a high integrity, free-standing, reinforced 1/8" stainless steel enclosure with sealed penetrations. Processing in this cell is in batches based on 100 grams of U-235 which have been irradiated at less than 210 kW in the GETR for a period of 7 to 17 days.
Prior to processing, decay for 8-12 hours after discharge is allowed.
The purpose of the process is to separate Mo-99 and Xe-133 for sale for =edical uses, with iodine also being separated for control and disposal.
Chart #4 shows a su= mary of the materials which might be present in Cells 1, 2, and 5.
3cch Cells 1 and 2 may contain sub-kilogram quantities of solid encapsulated irradiated UO li ited by criti-2 cality considerations.
Cell 5 =ay contain less than 300 gm of solid fuel specimens being mounted and prepared for metallography.
In addition, Cell 1 may contain as much as 100,000 Ci of Co-60 and 10,000 to 50,000 Ci Ir-192 in the form of solid metal pellets.
Finally, sealed sources containing Antimony-124 are sometimes present.
These are reactor start-up sources which have been irradiated and are being tested for output and surface contamination.
There is no potential for release of any of these solid materials.
The principal source of release is an estimated 760 C1 of mixed fission product particulate contamination resulting from the destructive examination of reactor fuel =aterials. 1/29/79
CELLS 1, 2, 5 FUEL R0D EXAMIt!ATI0t!
760 CI MFP LOOSE CONTAMINATION (INCLUDING 0.01 CI, TRANSURANIC) 100 CI I!OBLE 6AS CO-60 HANDLING (SOLID PELLETS)
IR-192 HANDLING (SOLID PELLETS)
Sa-124 SOURCES (SEALED)
CELL 4 0.1 CURIE AS CONTAMINATION (ASSUMED TO BE ALL PU-239) 5 CURIES CF-252 AS WIRE GR PELLETS 50.
CURIES AM-241 STORED IN A 2-R TYPE CONTAINER CHART 14 1/29/79
Chart #4 also covers Cell 4 This cell used to contain sub-kilogram quantities of solid, encapsulated, irradiated, mixed oxide fuel rod segments limited by criticality considerations (all M0 r ds have been removed from the cell). The 0.1 Curie 2
of loose contamination in cell was estimated from an analysis of smear surveys taken on 11/10/77, and is considered in the source term. No other loose radioactive materials are in Cell 4.
Before discussing the inventory in Cell 3, it is necessary to explain in broad terms the processing which takes place. As mentioned earlier, the object of the processing is to recover fission product Mo-99 and Xe-133.
In order to do this, a reactor target which contains fully enriched U-235 in a metallic aluminum matrix is processed.
The process begins by dissolving the aluminum structure in NaOH.
During this step, essentially all of the noble gases are vented, recovered in a vacuum system, and trarped in a cryogenic cold trap.
From this point en, the noble gases are always maintained either on cold traps or in sealed containers. The dissolution of the target material also results in molybdenum and iodine going into solution.
- However, uranium and the other fission products do not dissolve. The next step in the process is filtration of the resulting slurry through a sintered, stainless steel filter of a nominal 2 =1cron pore size.
This results in essentially all the uranium and insoluble fission products being trapped. The filter, which is in a heavy stainless steel case, is then i= mediately sealed with 1/29/79 postulated ground acceleration, but he is less sure about Cells 6 and 11.
Furthermore, while he has not made an analytical approach :o the ef fect of surf ace f aulting, his opinion is that larger cells would move with ground dis-place =ent or even bridge a gap created by ground displace-ment. Therefore, it is our feeling that even considerations of surface faulting would not greatly change this analysis.
D.
Radiological Consecuences Considering that the cells after the seismic event would be still standing but severed frem power, coc=unication, and services to include external ventilation lines, and in-cell enclosurer (Cells 3, 9, and 10) with integral filters are intact, an analysis was made of the potential driving forces for dispersion of activity.
In the case of fission product separations at Cell 3, if seismic damage were to occur during the process, both radioactive decay heat and procat: 'aat are available to cause convection currents in the cell which car.
rasuspend and transport material.
If liquids a: e spilled inside the cell, over a period of time they wile evaporate and some of the radioactive naterial can then b, dispersed from the cell.
For gases, it is assumed that cnce free they will completely escape of diffusion.
Even this assumption is conservative, particularly for high moleculi.r weight not ).e gases. External, atmospheric cir movement may also cause some Laternal movement of air and transport of material.
Finally, criticality considerations were analy zed.
It is concluded that in no case is there a possibill:v of an accidental criticality as a result of a seism:.c event, therefore, energy from criticality is not cocaidered a credible driving force for release of radioactive material.
1/29/79 Next, based on these driving forces and the =echanics of the situation, an analysis was made of the fractions of radioactive material which =ight be released.
The factors resulting are in several categories.
For noble gases, 100*. was assumed to be released, while for halogens the fraction was estimated to be 0.1%.
For powders where both resuspension and diffusion through openings must be accomplished, the factor is 10'.
For liquids where evaporation must precede resuspension and diffusion, the
-5 factor is 10 For powders and liquids inside intact cell enclosures with filtration systems, the factors are 10- and
-8 10
, respectively.
For solids which do not require cooling, the release factor is zero.
Using these release factors and the quantities of radioactive materials discussed earlier, the source terms were calculated.
This is a conservative basis since the quantities represent sealed containers of material, except for Cells 1, 2, 4, and 5 where they represent loose contamination.
Chart (/8 su=marizes the resulting calculation.
Releases from Cell 3 dominate the results, but recall that for Cell 3, conservatism in all categories of release has already been poin?.ad out.
It is unrealistic to assu=e all of the noble gas from three processes can be released since at times other than the dissolution, noble cases are eain-tained in a sealed vacuum system or in one of several cryogenic traps.
Only a small portion could be released if the seismic event interrupted the collection of the gas, but no halogens could be released at this point.
Further= ore, the particulates have been assu=ed to be in liquid form and available for release even though this situation is also only true for one process during the dissolution step, when the halogens are not available for release.
Furthermore, a process change has been under evaluation for several =enths and is very near to t=plementation. This change would involve a chemical 1/29/79
SCURCE TEF.MS NOBLE CAS HALOGENS PARTICULATES ACTINIDES CELLS 1, 2, 4 & 5 100 C1
.076 C1 11.
c ai CELL 3 20,000 C1 19 Ci
.0008 Ci
.72 uCi CELL 6
.0015 C1 CELL 9
.012 C1 CELL 10/11
.0004 C1 20,100 Ci 19 Ci
.0907 C1 12 p Ci Chart #8 1/29/79
means of tying up the halogens as a silver salt. This step would take place i==ediately after the dissolution, but before filtration. Thus, the precipitated silver salts would be trapped on the filter and would be effectively precluded from being re-leased at any stage of the process.
Using the calculation methods outlined later. the source terms just described (assuming a uniform release over 2 hr.), and atmospheric conditions in Regulatory Guide 1.4, the 50 year dose commitment resulting from a two hour exposure of an individual at the site boundary was calculated. The whole body dose result is 1;6 Rem compared to the guide in 10CFR100 of 25 Res.
The dose to the thyroid is calculated to be 11 Rem (or 7.6 Rem if the halogens are in insoluble form) compared to the regulatory guide limit of 300 Rem.
Therefore based on these calculations. we conclude that the effects at the site boundary due to activities in the radioactive material laboratory are well within regulatory guidelines, even in the extreme event of the unrealistic seismic assumptions made by the NRC Staff.
In reviewing the Table 1 Source Terms, several errors in the Table as presented to the NRC staff on October 28 1977 were discovered. The Table i submitted here has been correcced. The errors primarily were associated with the listed inventories for Cell 9 - Glove Box and for Cell 9.
Most of the inventories originally listed with Cell 9 are now correctly listed with Cell 9 - Glove Box.
Sulfur-30 and iron-55 originally listed in powder form with cell 9 Glove Box are now correctly listed as solution in Cell 9 - Glove Box.
Further, mercury-197 originally listed in Cell 9 is now correctly listed in Cell 6.
These changes do not materially affect the previcus determined site boundary radiological impact. 1/29/79
Additionally, the halogen and mixed fissica product inventories originally listed for Cell 3 were based on three separate processes.
As discussed under the cell 3 section of Table 1, this was an unrealistic approach and these inventories have been corrected accordingly.
Finally analysis of Cell 4 s= eat-taken on 11/10/77, indicated a smearable contamination inventory in the stainless steel liner of not more than 0.1 C1 (assumed to be all Pu-239). No other loose radioactive materials are in Cell 4. 1/29/79
TABLE 1 SCURCE TERMS Cells 1, 2, 4, and 5 Total Inventory Physical States Release Release Inventory Isotooe Curies and Forms Fraction Curies 0.461x10[f
-0 0.461x100 Powder 1.00 x 10 Ce-141 Ce-144 1.274 x 10' 1.274 x 10,~
Ru-103 0.488 x 10, 0.483 x 10-Ru-106 1.057 x 10; 1.057 x 10_2 Cs-137 2.710 x 10'1 2.710 x 10 '
Cs-134 8.672 x 10 8.672 x 10-Zr-95 5.149 x 10 5.149x10f 0
Nb-95 5.420 x 100 5.420 x 10 7 Eu-154 9.214 x 100 9.214 x 10_'2 Pr-144 1.463 x 10' 1.463 x 10,
0 Co-60 0.486 x 10_
0.486x10[{
Alpha (Pu-239) 1.1 x 10 v
v 1.1 x 10 Halogen Gas 1.00,
Kr-85 1.00 x 10' Gas 1.00 1.00 x 10' The above values are based on data appearing in RP&S Log Book 820. Three assumptions are made in arriving at the above inventories: (1) The isotopic mix reported in Log Book 820 for Cell 2 is representative of Cells 1, 2, and 5; (2) The pre-cleaning values are a factor of 1,000 higher than the reported post-cleaning values; and (3) The assumed contaminated surf ace 2
areas are as follcws: Cells 1, 2, and 4--221 ft and Cell 5-100 f t Cell 6 and Storage Cave Total Inventory Physical States Release Release Inventory Isotooe Curies and Forms Fraction Curies
-5 5.00x10[6 Ba-135m 0.50 x 10 S luci n 1.00 x 10 0
Te-123m 0.10 x 10 1.00 x 10,
3.00x10[}
Hg-203 3.00 x 10 Ba-133 1.00 x 10 1.00 x 10.
0 Cd-109 1.00 x 10 1.00 x 10 3 2.00x10[]
Fe-59 2.00 x 10 Ag-110m 2.00 x 10 2.00 x 10 -
2.00x10f 2.00x10[#
Sr-85 t
Co-58 5.00 x 10 5.00 x 10.
0 2n-65 4.00 x 10 4.00 x 10 ?
Sn-ll3 1.00 x 10 1.00 x 10 7 1
Yb-169 2.50 x 10 2.50 x 10 7 1
Se-75 6.00 x 10 6.00 x 10 7 Cr-51 1.00 x 10 1.00 x 10 7 0
5.00 x 10 '
Hg-197 5.00 x 10 v
, 1/29/79
TA3LE 1 SOURCE TERMS (continued)
Cell 9--Glove Box Total Inventory Physical States Ralease Release Inventory Isotoon Curies and Forms Fraction Curies S-35 1.20 x 10 Liquid 1.00 x 10[f 1.00 x 10,3 2
~
C-la 1.00 x 10' Powder 1.00 x 10 1.00 x 10 7 Liquid 1.00x10[5 1.00x10_]
1.00xlof
~
Fe-55 Ni-63 1.50 x 10 Solution 1.00 x 10 -
1.50 x 10 Ca-45 2.00 x 10 1.00 x 10 3 2.00 x 10 $
~
~
1.00x10[j 2.00x10["
~
Cl-36 2.00 x 10 T1-204 1.00 x 10 1 1.00 x 10 1.00 x 10 ;
-5
-6 C4-4 7 2.00 y 10 1.00 x 10 2.00 x 10 0
-5
-5 Sn-119n 2.00 x 10 y
1.00 x 10 2.00 x 10 Cell 9 Total I=ventory Physical States Ralease Release Inventory
_,Ipocoon Curies and Forms Frae:1on Curies 0
~0 1.00x10[6 M.-54 1.00 x 10 Solution 1.00 x 10 k-32 2.00 x 10' l
- l 2.00 x 10 1
~7 P-33 2.00 x 10 v-2.00 x 10 Radiochemis erv Radiochenistry routinely handles up to 8 C1 of Mo-99, 0.04 Ci of P-32 and 100 agm of low burnup nixed oxide fuel solutions.
The activities are considered insignificant for this study.
Plutonium Analvtical Laboratorv The PAL is restricted te < 200 g=s of plutonium. Most is handled as ?UO2 or PU(NO3)2. The a=ount of plutonium transported to the site boundary is considered in a separate study.
Call 3 Total Inventory Physical States Release Release Inventory Iso toee Curies and Forms Fraction Curies 4
4 Noble Cas 1.98 x 10 Gas 1.00 1.98 x 10 4
,3 1
Halogens 1.37 x 10, Cas 1.00 x 10 1.37 x 10,
~0 Mix Fission 8.10 x 10*
Solution 1.00 x 10 8.10 x 10 '
~
Produc t Particulate
,3
,7 Acti=1 des 7.18 x 10 Solution 1.00 x 10 7.18 x 10
Cell 3 (continued)
The Cell 3 noble gas inventory is assumed to consist of the noble gas activity generated by the irradiation of 6 fission product moly capsules irradiated for 7 days at 35 kW each, and decayed for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, plus the noble gases from another 6 capsule batch decayed for 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br />, plus the noble gases frcm another 6 capsules decayed for 178 hours0.00206 days <br />0.0494 hours <br />2.943122e-4 weeks <br />6.7729e-5 months <br /> minus 1,200 curies of Xenon-133 (shipped as product).
This is one week's worth of activity at two processes per week. The total Cell 3 halogen and sixed fission product inventory is assumed to consist of the halogen activity generated by the irradiation of 6 fission product capsules for 7 days at 35 kW each, and decayed 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
This is one process worth of activity with no allowance for :b-99 shipments.
The MFP activity from previous processes is contained in stainless steel filters or sealed, ncn-breakable containers; the halogen inventories are fixed in basic solution and sealed in non-breakable containers.
Call 8 Cell 8 is a small shielded enclosure which is not currently in use and has no inventory of radioactive materials.
Cells 10 and 11 Total Inventory Physical States Release Release Inventory Isotooe Curies and Forms Fraction Curies Mo-99 2 x 10 Powder 1.00 x 10-2 x 10~
Tc-99m 2.2 x 10 Powder 1.00 x 10~
2.2 x 10 '
1/29/79 TABLE 2 (Rev. 3 )
StXfARY OF DOSES CALCULATED FOR Tile SNM-960 IIYPOTl!ETICAL 'EARTilQUAKE ACCIDENT AT 440 METERS DOWN WIND SollRCE TERM 2 Il0UR RADI ATION DOSE (Ri}I) FOLLOWING A 2-It0UR EXPOSURE TlHE INTERVAI.
W110LE BODY KIDNEYS 1.IV ER BONE I.UNGS TIIY ROID C I (I.I.I)
SKIN Submers.
Inhalation Suhmers.
(Sol)
(Sol)
(Sol)
(Sol)
(Sol)
(Insol)
(Sol)
(Insol)
(Sol)
(Insol)
?Ilxed Isotopes 2.01E-04 3.30E-07 3.72E-06 7. 24 E-07 9.82E-07 3.03E-05 3.07E-05 4.44E-09 1.10E-09 3.08E-04 1.55E-04 1.29E-02
'll P f rom 6 1.P. Capsules 1.03E0
- 2. 53 E-3 6.00E-4 4.91E-3 2.97E-4 5.48E-3 6.66E-3 5.84E-2 5.37E-3
- 8. 34 E-3 2.28E-3 2.34E0 to llour Decay
?tt'P from 6 3 P cdp 3"ICS 7.50E-2 2.02E-6 2.78E-8 5.70E-7 2.09E-5 1.43E-4 1.66E-4 0
0 2.68E-3 8.58E-4 2.06E-1 l
- 1. ') Day liccay I
j
?ll'P f rom 6 l'.I'. Capsules
- 1. '. Da y Dec a y 4.72E-2 1.82E-6 2.60E-8 5.77E-7 1.87E-5 1.34E-4
- 1. 54 E-4 0
0 2.53E-3 8.16E-4 1.30E-1 A. t inides f rom 3.80E-10 1.91E-12 1.09E-Il 2.90E-12 2.84E-11 3. 74 E-10 3.74E-10 0
0
- 1. 8 7 E-9 2.37E-9 7.26E-0
,, y,p, f. igm ul es
'luh t o t al 1.15E0 2.53E-3 6.04E-4 4.91E-3 3.38E-4 5.79E-3 7.01E-3 5.84E-2 5.37E-3 1.39E-2 4.llE-3 2.69E0
?Iinua 1,200 C1 L.-133
- 2. 41 E-2 0
0 0
0 0
0 0
0 0
0 6.64E-2 lotal 1.13E0 2.53E-3 6.04E-4 4.91E-3 3.38E-4 5.79E-3
- 7. ole-3
- 5. 84 E-2 5.37E-3 1.39E-2
- 4. l l E-3 2.62E0 km 1.13E0 A'Ihe halogen release inventory and downwind thyroid doses from Cell 3 processing of fission product capsules were analyzed in greater detail in the submittal package dated !! arch 1, 1978.
1/29/79
TABLE 2 (Rev. 3 )
SUtetARY OF DOSES CALCULATED FOR Tile S!01-960 IIYPOTIIETICAL EARTl! QUAKE ACCIDENT AT 440 METERS DOWN WIND SOCRCE TERM 1 YEAR RADI ATION DOSE (RDI) FOLlOWING A 2-IIOUR EXPOSURE TIME INTERVAL.
U110LE BODY KIDNEYS LIVER BONE LUNCS TliY ROID CI(LLI)
SKIN
_Submers.
Inhalation Submers.
(Sol)
(Sol)
(Sol)
(Sol)
(Sol)
(Insol)
(Sol)
(Insol)
(Sol)
(Insol)
- 2. 01 E-04
- 1. 44 E-03 3.06E-03
'i. 06 E-0 3 6.49E-03 8.95E-03 5.32E-02 1.59E-06 3.44E-06 1.46E-03 2.14E-03 1.29E-02 Mixed Isotopes 1.03E0 1.81E-2 3.41E-2 2.67E-2 7.20E-2
- 5. 44 E-2 2.75E-1
'. 85E0 1.25E0 1.06E-2 2.36E-2 2.34E0 s les 10 llaur Decay MFP f ron 6 F.D. Capsules 7.50E-2 5.75E-3 5.36E-5 2.18 E-4 5.76E-2 3.31E-3 1.04E-1 0
0 4.66E-3 1.16E-2 2.06E-1 3.9 Day Decay Mf? frea 6 F.P. Capsules
- 4. 72 E-2
- 5. 4 0E-3 i.24E-5 2.17 E-4 5.38E-2 3.17E-3
- 9. 84 E-2 0
0 4.48E-3 1.10E-2 1.30E-1 7.4 Dav Decay Actinides from l*
6 F.P.
1.80E-10
- 4. 54 E-10 1.01E-9 4.70E-10 7.62E-9 5.66E-8 1.68E-7 0
0 2.39E-8 2.79E-8 7.26'E-10 Capsules Subtotal 1.15E0 1.07E-2 3.73E-2
- 1. 22 E-2 1.90E-1 4.98E-2
'i. 31 E-1
'. 85E0
- 1. 25 EO 2.12E-2 4.83E-2 2.69EO Minus 1,200 Ci
'. 41 E-2 0
0 0
0 0
0 0
0 0
0 6.64E-2 Xe-113 Total 1.13E0 1.07E-2 3.73E-2 3.22E-2 1.90E-1 6.98E-2 5.31E-1 4.85E0 3.25E0 2.12E-2 4.83E-2 2.62E0 k
1.16E0
- The halogen release inventory and downwind thyroid doses from Cell 3 processing of fission product capsules were analyzed in greater derall in the subiaittal packaged dated March 1,1978.
1/29/79
TABLE 2 (Rev. 3 )
e
SUMMARY
OF DOSES CALCULATED FOR Tile S10t-960 HYPOTilETICAL EARTilQUAKE ACCIDENT AT 440 METERS D0'3 WIND SOURCE TElet 50 YEAR RADI ATION DOSE (RD1) FOLI.0 WING A 2-Il0L*R EXPOSURE TlHE INTERVAL l
TilYROID G I (1.1.1 )
_ SKIN Wil0LE BODY _
KIDNEYS LIVER BONE LUNGS Submers.
Inhalation Submers.
[So))_
(Sol)
(Sol)
(Sol)
(Sol)
(Insol)
(Sol)
(Insol)
(Sol)
(Insol)
Mixed Isotopes
- 2. ole-4
- 2. 4 2 E-3 7.60E-3 L.65E-2
- 2. 68 E-2 9.02E-3 7.63E-2
- 1. 59 E-6
- 3. 44 E-6 1.46E-3 2.19E-3 1.29E-2 MFP from 6 s
' 85EO 1.25EO 1.06E-2 2.36E-2 2.34E0 F.P. Capsules 1.03E0 1.89E-2
- 3. 41 E-2 2.67E-2 1.56E-2
- 5. 44 E-2 2.76E-1 10 llour Decay HFP from 6 F.P. Capsules 7.50E-2 6.60E-3 6.36E-5 2.28E-4 6.12 E-2 1.31E-3 1.06E-1 0
0 4.66E-3 1.16E-2 2.06E-1 3.9 Day Decay
- IFP from 6 F.P. Capsules 4.72E-2 6.24E-3
- 6. 24 E-5 2.26E-4 S.75E-2 1.18 E ).96E-2 0
0 4.88E-3 1.10E-2 1.30E-1 7.4 Day Decay Act inides f rom 6 F.P.
1.80E-10 L. 07 L-9 4.55E-9 5.33E-9 L.91E-8 5.68E-8 1.91E-7 0
0 2.39E-8
- 2. 79 E-8 7.26E-10 Capsules Subtotal 1.15E0 1.42E-2 4.18E-2
'. 3 7 E-2
- 1. 21 E-1
'i.99E-2
>. 58 E-1
'. 85E0 1.25E0 2.16E-2 4.84E-2 2.69EO Minus 1,200 Ci
- 2. 41 E-2 0
0 0
0 0
0 0
0 0
0 6.64E-2 Xe-133 Total I.13E0 1.42E-2 4.18E-2
'. 37E-2 2.21E-1
[3. 99 E-2 i.58E-1
. 85E0 1.25E0 2.16E-2 4.84E-2 2.62E0 k
1.16EO
- The halogen release inventory and downwind thyroid doses from Cell 3 processing of fission product capsules were analyzed in greater detail in the submittal package dated March 1,1978.
1/29/79
APPEFDIX 1 TO TABLE 1 SOURCE TERMS PHYSICAL FORM OF RADI0 ACTIVE MATERIALS The source terms which were calculated, in general, are based on inventory quantities of radioisotopes prepared for shipment, except for Cells 1, 2, 4, and 5 where estimates of surface contamination
.te made.
This contamination is assumed to be in powder form and since Cel.s 1, 2, and 5 are the only cells in which no enclosure is used, the highest release factor was associated with them.
Cell 4, although having an internal enclosure, has a single EEPA filter system serving both the enclosure and the cell proper.
Therefore, Cell 4 is assigned the same release factor as Cells 1, 2, and 5.
The figures shown for Cell 6 and the storage cave are based on an accumulation inventory which is unlikely to be exceeded.
Cell 6 itself is cleaned after each processing so the source of material release would be the storage cave.
The inventory is stored as a liquid solution in a sealed glass bottle. The
-5 release fraction of 10 assumes that all of the bottles have been broken and all of the liquid is spilled within the shielded enclosure.
The Cell 9 glove box is a storage location for the materials listed there.
This inventory is stored as liquid or powder in sealed plastic or glass containers. Cell 9 itself is used for processing of the beta emitters and storage of the product inventory as liquid in sealed plastic bottles.
In Cells 10 and 11, the inventory of 2,000 Ci has been shown as powder form.
In reality, it exists as powder only for a short time during the initial stages of processing.
As was pointed out in Par. III B, the molybdenun trioxide is diasolved in a caustic solution within the enclosure in Cell 10.
Mo/Tc-99 is then present only in solutions in sealed plastic bottles which may remain in Cell 11 for a time before being shipped to customers.
1/29/79 atmospheric winds.
Since no fire is postulated, volatile solids will re=ain solids.
For this analysis, the individual fractons used for determining a total release fraction are:
Powders: Using a high resuspension factor of 10~
-1 cm yields a conservative airborne fraction in a typical cell = 10~
Liquid to Powder:
The evaporation and suspension of a particulate from a radioactive liquid is taken to be 10* of that for a powder, or a fraction of the total activity which is suspended = 10~
Unfiltered Cell The fraction of suspended particulate which to Atmosphere:
migrates out of a cell by natural draft air current is assumed to be = 10~
Filtered Enclosure The fraction of suspended particulate which is to Unfiltered Cell: drawn out of a HEPA filtered enclosure is con-servatively taken as the fraction passing through a 99.9" efficient filter.
Fraction escaping = 10~
Combining these fractions for the various cases in Building 102 gives the following total particulate release fractions (as a fraction of the total cell powder or liquid inventory):
Powder from an unfiltered cell = 10~
Liquid to powder from an unfiltered cell = 10 Liquid from Cells 3, 9, 10, & 11 with filtered enclosure = 10~
Powders from Cells 3, 9, 10, & 11 with filtered enclosure = 10 1/29/79