ML20245J323
| ML20245J323 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 12/31/1988 |
| From: | Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 8905040097 | |
| Download: ML20245J323 (12) | |
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I February 14, 1989 I
1
'IABLE I l
1988 GAS & PARTICULATE EFFIDENTS JULY 1,1988, 'HIROUGH DECEMBER 31, 1988 i
Measurement Emission Release Point Basis
- Effluent (Curies)
H'IGR Fuel Fabrication (1) (3) (4)
U-235 (93% enriched),
3.58 x 10-6 i
Facility (SV-A) thorium-232 & daughters SV-B (1) (3) (4)
U-235 (93% enriched),
1.31 x 10-6 depleted uranium, thorium-232 & daughters s
'IRIGA Fuel Fab Facility (1) (3) (4)
U-235 1.35 x 10-5 Hot Cell (1) (3) (4)
Mixed fission products 2.48 x 10-5 (1) (3) (4)
I-131 3.22 x 10-6 (2)
H-3 1.90 x 10-2 (1)
Kr-85m 2.14 x 10-5 (1)
Kr-85 1.985 x 10-2 (1)
Kr-87 4.70 x 10-5 (1)
Kr-88 1.40 x 10-4 (1)
Xe-133 3.70 x 10-6 (1)
Xe-135 2.67 x 10-5 Experimental Area (2)
H-3 1.5 x 10-5 Building (EA-1)
(2)
C-14 1 x 10-5 (2)
Mixed fission products 1 x 10-5 (2)
Mixed activation products 1 x 10-5 (2)
U-235 4.0 x 10-8 (2)
Th-232 2 x 10-8 (1)
Kr-85 1.00 x 10-3 Experimental Area (1)
Sr-90/Y-90 1.60 x 10-7 Building - Bunker (EA-1 Bunker) i TRIGA Reactor Facility (1)
Ar-41 Mark I & Mark F 8.25 x 10-1 (3) (4)
Mixed fission products 2.51 x 10-6 TRIGA Fuel Developmnt (2)
Kr-85 0
Research Iabs (no work (2)
Xe-133 0
F$6 with unencapsulated (2)
Mixed fission products 0
Q radioactive material (other than Xe-133 &
during this period)
Kr-85) mn CO Sorrento Electronics (1)
Kr-85 0
gg 10240 and 10247 (1)
Xe-133 0
oo Flanders Drive oo?
nom SQ
- (1) Measured.
(2) Estimated.
(3) This value includes both measured values and values that were below our lintits of detection which is an overest (4) From gross alpha plus gross beta results.
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'mBIE I' (Cont-imwi)
February'14, 1989 Measurement Emission Release Point Basis
- Effluent' (Curies)
Waste Processing (1)
Radionuclides Z=1-103 1.31 x 10-6 Facility Science laboratories (2)
U-235 1.2 x 10-7 (2)
Th-232 0
(2)
H-3 0
(2)
U-238 1.2 x 10 Building 10 (1)
H-3 2.00 x 10 (Calibration Facility)
Test Tower (2).
Mixed fission products 5.0 x 10-6 (2)
Mixed activation products 5.0 x 10-6 l
- (1) Measured.
(2) Estimated.
(3) This value includes both measured values and values that were below our limits of detection which is an overestimate.
i (4) From gross alpha plus gross beta results.
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February 14, 1989
'DMEE II 1988 IJQUID EFFIDENTS JUIX 1,1988, 'HIROUGH 1mrneER 31, 1988 Effluent
. Emission Release Point, Radionuclides (Curies)
IIIGR Fuel Fabrication Facility U-235, thorium 2.06 x 10-6
-(Building 37, Sorrento Valley)
Main Site idonuclides Z=1-103 5.321 x 10-3
'IUTAL 5.323 x 10-3
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s' February 14, 1989 l
'mBIE III 1988 NCN-RADIGOGICAL EFFIDEtff DMA JULY 1,1988, 'lHROUGH nmFNBER 31, 1988 A.
Suspended Particulate Particulate Date of No. of Concentration Arithmetic Sample Collection Samples Range (pg M )
Mean (Mg M )
12/5/88 - 12/12/88 16 17 to 121*
56 B.
No sanples 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 sanples. This constriction is not related to GA activities.
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LABORATORY
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TMEE I
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1988 GAS & PARTICULATE rn JULY 1,1988, 'DIROUGI mnFNBER 1," 95825 Measurement Emission Release Point Basis
- Effluent (Curies) l H'IGR Fuel Fabrication (1) (3) (4)
U-235 (93% enriched),
3.58 x 10-6 Facility (SV-A) thorium-232 & daughters SV-B (1) (3) (4)
U-235 (93% enriched),
1.31 x 10-6 depleted uranium, thorium-232 & daughters TRIGA Fuel Fab Facility (1) (3) (4)
U-235 1.35 x 10-5 Hot Cell (1) (3)'(4)
Mixed fission products 2.48 x 10-5 (1) (3) (4).
I-131 3.22 x 10-6 (2)
H-3 1.90 x 10 (1)
'Kr-85m 2.14 x 10-5
~
'(1)
Kr-85' 1.985 x 10-2
- (1)
Kr-87 4.70 x 10-5 (1)
Kr-88 1.40 x 10-4 (1)
Xe-133 3.70 x 10-6 (1)
Xe-135 2.67 x 10-5 Experimental Area (2)
H-3 1.5 x 10-5 Building (EA-1)
(2)
C-14 1 x 10-5 (2)
Mixed fission products 1 x 10-5 (2)
Mixed activation products 1 x 10-5 (2)
U-235 4.0 x 10-8 (2)
Th-232 2 x 10-8 (1)
Kr-85 1.00 x 10-3 Experimental Area (1)
Sr-90/Y-90 1.60 x 10-7 Building - Bunker (EA-1 Bunker)
TRIGA Reactor Facility (1)
Ar-41 Mark I & Mark F 8.25 x 10-1 (3) (4)
Mixed fission products 2.51 x 10-6 TRIGA Fuel Develegnent (2)
Kr-85 0
Research Labs (no work (2)
Xe-133 0
with unencapsulated (2)
Mixed fission products 0
radioactive material (other than Xe-133 &
during this period)
Sorrento Electronics (1)
Kr-85 0
10240 and 10247 (1)
Xe-133 0
Flanders Drive
- (1) Measured.
(2) Estimated.
(3) This value includes both measured values and values that were below our limits of detection which is an overestimate.
.(4) From gross alpha plus gross beta results.
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'BB[E I. (Nimd)
' February 14, 1989-l j
Measurement Emission Release Point' Basis
- Effluent (Curies) l Waste Processing (1)
Radionuclides Z=1-103 1.31'x 10 l Facility-Science Laboratories-
'(2)
U-235-
'1.2 x 10 (2)
Th-232 0
q (2)
H-3 0
g (2).
U-238 1.2 x 10-7 l
Building 10 (1)
'2.00 x 10-7 (Calibration Facility) i Test Tower (2)
Mixed fission products 5.0 x 10-6 (2)
Mixed activation products 5.0 x 10-6 l
(1) Measured.
(2) Estimated.
(3) This value includes both measured values and values that were below our lhuits of detection which is an overestimate.
-(4)' Fran gross alpha plus gross beta results.
= _ - -
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February 14, 1989 i
'DUEE II 1988 LIQUID EFFLUENTS JULY 1,1988, 'IHROUGEI MN 31, 1988 Effluent Emission Release Point Radionuclides (Curies)
HIGR Fuel Fabrication Facility U-235,. thorium 2.06 x 10-6 (Building 37, Sorrento Valley)
Main Site Radionuclides Z=1-103 5.321 x 10-3
'IUIAL 5.323 x 10-3 l
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February 14, 1989
'JAME III 1988 NN-RADIGDGICAL EITIDEtE DMA JULY 1,1988, 'IEROUGH mr'FNBER 31, 1988 l
A.
Susperzled Particulate Particulate l
I Date of No. of Concentration Arithmetic Sanple Collection
~ Samples Range (uq M )
Mean (uq M )
12/5/88.- 12/12/88 16 17 to 121*
56 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 sanples. This construction is not related to GA activities, i
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FActLITY
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2 LABORATORY 9
EXPERIMENTAL i
11 SERVfCE AND RECEPTION CENTER
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$ EpAM 13,14,15 T.O. COMPLEX 7 $$"UEL FAB
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2 23 HOT CELLS u.
25 WASTE PROCESSING-MS 27 EM1 g
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30 LINAC 31. ECF 33 ' ' OOUBLETlil 35 TESTTOWER h
INDUSTRIAL 37 SV-A (FUEL MANUFACTURING)
AREA PROCESSING-SV
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Sorrento Valley Site SECURITY
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CONTROL 31 STATION 3
21 Main Site y
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6/88 O
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Fig. 1 - Plan View of Sites
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~~ 21 P12 : 25 February 14, 1989 696-1348 j
j Mr. John B. Martin Regional Administrator Region V U.S. Nuclear Regulatory Conmission 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596
Subject:
Subnittal of Semiannual Effluent Report (2 copies)
Reference:
GAC letter 696-677 dated 2/27/76, SNM-696, Docket 70-734
Dear Mr. Martin:
In accordance with 10 CFR 70.59, we are transmitting the semiannual effluent report required for the period July 1, 1988, through December 31, 1988.
By copy of this letter, six (6) copies of the report are
.being forwarded to the Director, Office of Inspection and Enforcement, NRC, and one (1) copy is being sent to the State of California, Department of Radiological Health, Sacramento.
Table I lists data on the radiological gaseous and particulate effluent released to unrestricted areas fram our facilities handling special nuclear material. The release point descriptions are keyed to the facility names whose relative locations are shown on Figure 1, a plan view of the site.
Table II shows the radiological liquid effluent which is released into a 100 million gallon / day regional sewerage treatnent plant.
Table III contains the non-radiological effluent data taken fram our air particulate and hcl sampling points.
The dispersion meteorology of the site was discussed in our first effluent report, referenced above.
Certain Table I data used in conjunction with the above referenced meteorology provide the basis for deriving radiological effluent concentrations at the site boundary and nearby vicinity.
We remain hopeful the information provided is satisfactory to meet the requirements for the now recurrent submission.
Very truly yours, I
\\
Keith E. Asmussen, Manager
!/
Licensing, Safety and l
Nuclear Cm pliance i
10955 JOHN JAY HOPKINS DRIVE. SAN OtEGO, CA 92121 1194 PO. BOX 85608. SAN DIEGO. CA 92138-5608 (619) 455-3000 s
'A n
,n, L.)
V s'
. KEA/nk Attachments:
Table I
- 1988 Gas & Particulate Effluents - 7/1/88-12/31/88 Table II - 1988 Gas & Particulate Effluents - 7/1/88-12/31/88 Table III - 1988 Non-radiological Effluent Data - 7/1/88-12/31/88 Fig. 1 - Plan View of Site (6/88) cc: Mr. James M. Taylor (6 copies)
Deputy Executive Director Office of Executive Director for Operations U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Mr. J. O. Ward, Chief (1 copy)
Health & Welfare Agency Department of Health State of California Radioactive Materials Licensing 714-744 P Street Sacramento, CA 95814 1
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L____