ML20057B379

From kanterella
Jump to navigation Jump to search
Forwards Semiannual Effluent Rept for Jan-June 1993, Including Data on Radiological Gaseous & Particulate Effluent Released to Unrestricted Areas & Radiological Liquid Effluents Released to Sewerage Treatment Plant
ML20057B379
Person / Time
Site: 07000734
Issue date: 09/30/1993
From: Asmussen K
GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To: Faulkenberry B, Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20057B380 List:
References
NUDOCS 9309210277
Download: ML20057B379 (3)


Text

.

c s

a k CENERAL AfDRNCE,,

i 4 *

' RECEIVED NRC t

REGl0ld V T3 AUS 31 A10:13 August 30,1993 SNM-2121 VIA OVERNIGHT EXPRESS SERVICE Mr. Bobby Faulkenberry Regional Administrator Region V

{

U.S. Nuclear Regulatory Commission l

1450 Maria Lane, Suite 210 l

Walnut Creek. CA 94596

'r

Subject:

Submittal of Semiannual Effluent Report (2 copies),

{

Reference:

GAC letter 696-677 dated 2/27/76, SNM-696, Docket 70-734

Dear Mr. Martin:

i in accordance with 10 CFR 70.59, we are transmitting the semiannual effluent report required j

for the period January 1,1993 through June 30,1993. By copy of this letter, six (6) copies of the f

f report are being forwarded to the Director, Office of Nuclear Material Safety and Safeguards, I

U.S. NRC. Additional copies are being sent to the State of Califomia, Department of Health Services.

Table I lists data on the radiological gaseous and particulate effluent released to unrestricted

[

areas from our facilities handling radioactive 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.

1 Table 11 shows the radiological liquid effluent which is released into a 100 million gallon / day

{

l regional sewerage treatment plant. Table lli contains the non radiological effluent data taken from i

our air particulate and hcl sampling points.

I i

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 j

the basis for deriving radiological effluent concentrations at the site boundary and nearby vicinity.

j

/-

l h

9309210277-930930' O

PDR ADDCK 07000734 C-PDR 3550 GENERAL ATOMICS COURT, SAN Dif GO CA B21211194 -

PO If0X 85608 SAN DIEGO. CA 921116-9784 1619)455 3000 I

Mt. Bobby Faulkenberry, U. S. NRC August 30,1993 SNM-2121 Page 2 s,

Attachments A and B provide backup information. Attachment A provides detailed information conceming liquid releases, TRIGA Ar-41 releases and Kr-85 and Xe-133 releases. Attachment B provides stack sample results over this reporting period.

We trust the information provided is satisfactory to meet the requirements for this submission.

Very truly yours, Om?b&

WL-Keith E. Asmussen, Director Licensing, Safety and Nuclear Compliance LRQ:rmk Attachments:

Figure 1 Table I-Gas & Particulate Effluents - 1/1/93 - 6/30/93 Table 11 - Liquid Effluents - 1/1/93 - 6/30/93 Table ill - Non-Radiological Effluent Data - 1/1/93 - 6/30/93 i

Attachment A & Attachment B cc :

Director (6 copies via overnight express service)

Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Mail Stop 6 E6 One White Flint North 11555 Rockville Pike Rockville MD 20802 Dr. Gerard Wong (1 copy)

State of California Department of Health Services Radiologic Health Branch P. O. Box 942732 Sacramento,, CA 94234-7320 Mr. William Watson (1 copy)

State of California Department of Health Environmental Radiation Management Unit 1449 West Temple Street, Room 222 Los Angeles, CA 90026 Mr. Kim S. Wong (1 copy)

Regional Unit Chief State of California Department of Health Services Radiologic Health Branch 1449 West Temple Street Los Angeles, CA 90026 trq w:\\rmk\\snm-2121.ftr

4 E

FACILITY 1

ADMINISTRATION Q

2 LABORATORY 4

i 9

EXPERIMENTAL Y U' 11 SERVICE ANO RECEPTION CENT ER

, f. Ep AB 13.14.15 T.O. COMPLEX

\\

21 TRIGA REACTORS 22 TRIGA FUEL FAB U

23 HOT CELLS 25 WASTE PROCESSING-MS 27 EA-1

\\

g*

"\\

30 LINAC 31 ECF 5

34 ' ' DOUBLETlil 35 TEST TOWER k

INDUSTRIAL 37 SV-A (FUEL MANUFACTURING)

I AREA 3

W-B Q

/

41 WASTE PROCESSING-SV 4

Que"

,r

.54 8

Sorrento Valley Site t

n SECURITY 22 3

CONTROL 31 STATION 3

Main Site g

~g>

s 8

k 13

)

15 e

r 0 250 500 750 1000

Ocq, SCAI.E IN FEET O

TYUNE Fig. 1.

Plan View of Sites l

-