ML20238B106
| ML20238B106 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 06/30/1987 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20238B103 | List: |
| References | |
| NUDOCS 8709010066 | |
| Download: ML20238B106 (5) | |
Text
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August 26, 1987 TABLE I 1987 GAS & PARTICULAE EFFLUENE JANUARY 1,1987 ERDEEH JUNE 30, 1987 Measurement Dnission Release Point Basis
- Effluent (Curies)
HIGR Fuel Fabrication (1) (3) (4)~
U-235 (93% enriched),
3.47 x.0-6 Facility (SV-A) thorium-232 & daughters SV-B (1) (3) (4) 0-235 (93% enriched),
3.54 x 10-6 depleted uranium, thorium-232 & daughters i
Experimental Building (1) (3) (4)
Depleted uranium and 1,67 x 10-6 thorium-232 & daughters TRIGA Fuel Fab Facility (1) (3) (4)
U-235 8.64 x 10-8 5
Hot Cell (1) (3) (4)
Mixed fission products 3.92 x 10 7 (1) (3) (4)
I-131 4.96 x 10-Experimental Area (2)
H-3 1 x 10-5 5
Building (EA-1)
(2)
C-14 1 x 10 5 (2)
Mixed fission products 1 x 10 5 (2)
Mixed activation 1 x 10-products 2x10-g-8 (2)
U-235 4.0 x l (2)
Th-232 Experimental Area (2)
Kr-85 0
Building - Bunker (2)
Xe--133 0
(EA-1 Bunker)
(2)
Mixed fission products 1.0 x 10-5 (2)
Mixed activation 1.0 x 10-5 products (1)
Sr-90/Y-90 2.42 x 10 '
TRIGA Reactor Facility (1)
Ar-41 Mark I & Mark F 5.98 x 10-1 (3) (4)
Mixed fission products 4.59 x 10-7 TRIGA Fuel Develognent (2)
Kr-85 0
Research Labs (2)
Xe-133 0
(no work with radio-(2)
Mixed fission products 0
active material during (other than Xe-133 &
this period)
Special Products (1)
Kr-85 3.06 x 10-4 (1)
Xe-133 2.20 x 10-5 8709010066 870826 PDR ADOCK 07000734 C
'IBBLE I (03tFDHD).
Measurement Emission Release Point Basis
- Effluent
~ (Curies)
Waste Processing (1)
Radionuclides Z=1-103 1.06 x'10-5 Facility Science Laboratories (2)
U-235 1.2 x 10-7 (2)
Th-232 0
(2)
Mixed fission products
'3.0 x 10-9 (2)
H-3 0
(2)
U-238 1.2 x 10-7
- (1) Measured.
(2)
Estimated.
(3) This value includes both measured values and values t' at were below our h
limits of detection which is an overestimate.
(4) Frcu gross alpha plus gross beta results.
j l
1--
i l
August 26, 1987 TABLE II 1987 LIQUID EFFTEENIS JAMRRY 1,1987, 'IBROUGE JUNE 30, 1987 Effluent anission Release Point Radionuclides
.(Curies)
IfIGR Fuel Fabrication Facility U-235, thorium 4.172 x 10-5 (Building 37, Sorrento Valley)
Main Site Radionuclides Z=1-103 3.814 x 10-2
'IUIAL 3.818 x 10-2 f
i I
i f
4
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)
i 1
August 26, 1987 TAB 2 III 1987 IM-RADIGOGICAL EEFLENT DATA l
JANUARY 1,1987, 'IHROUGH JUNE 30, 1987 i
A.
Suspended Particulate i
Particulate Date of No. of Concentration Arithmetic i
Sample Collection Samples Rance uq/M3 Mean (uq/M3).
l 6/1/ 87 - 6/8/87 15 54 to 198*
95 B.
Hydrogen Chloride in Air No samples collected; hcl furnace not in operation during this report period.
- There has been heavy construction at Scripps Hospital and in Sorrento Valley which is near the location of the air sar.ples. This construction is not related to GA activities.
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Fig. 1 - Plan View of Site I