ML20112E088

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Responds to 711005 Request for Info on Radioactivity Released in Effluents of Georgia Tech Research Reactor
ML20112E088
Person / Time
Site: Neely Research Reactor
Issue date: 12/29/1971
From: Kirkland R
Neely Research Reactor, ATLANTA, GA
To: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20112E009 List:
References
NUDOCS 9606050144
Download: ML20112E088 (5)
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' (404) 8734211 l Muolear and Biological l Boiences Division #

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Mr. Donald J. Skovholt, Assistant Director  %

i Division of Reactor Licensing U. S. Atomic Energy Coonnission

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Washington, D. C. 20545 Wi -

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Reference:

Docket 50-160, License R-97 D:iar Mr. Skovholt:

This letter is in response to your request dated October 5, 1971 requesting l cartain information on the radioactivity released in the effluents of the GeorSia l Tsch desearch Reactor. The information is presented below; the numbers refer to l tha specific questions in your original letter.

1. a.

Gaseous radioactive effluent released to unrestricted areas:

An average, annual release for the 6 years 1966 through 1971 has been l

t 445 curies per year, p l

b. Liquid radioactive affluent released to unrestricted areas:

The average annual release has' increased from 274 Ci per year in 1966 to an estimated 6708 pCi per year for 1971 (through December 1). This y

-increase reflects the continuing increase in facility usage.

_ c. Solid radioactive effluent released to unrestricted areas

i There has been no release to unrestricted areas. All of our solid radio-l active waste is shipped to a licensed burial site.'

! 2 {

a. . The only radionuclide we have detected in the gaseous effluent is argon 41.
b. The principal radionuclides'in the liquid affluents we have i the past 6 years are noted below: O N Sc 58 pC1 32 P 4233 pCi & 00NC u

i 110 24 " 'l l Ag 25 pCi -

Na 123 pCi 'p #M 3 1972 ' 2 i Tb 20 pCi 3 H 2500 pci M[ M nr 90 131 c3 occni ct!M ' '

i Y 345 pCi Da 539 u,ci

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% b The majority of our radioactive liquid effluent. contains unidentified 4 and y emitting nuclides. No alpha emitting isotopes have been released {

to unrestricted arcas. The GTRR and the laboratories of the Nuclear

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' Research Center chare a comunon liquid waste handling system; therefore*

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the above list includes some releases which are not associated with thej

reactor.

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9606050144 960524 i PDR ADOCK 05000160

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l 3. a. The maximum measured direct radiaticr. onposure to an unrestricted area due to direct radiation from the containment building is 20 mrem per l year. This occurs at two monitoring stations located on the restricted area fence. One station'(#3) is south of the facility and the other

(#12) is east of the facility. The attached map shows the location of the various monitoring stations.

b. The maximum measured radiatica exposure to an unrestricted area due to the direct rediation from the effluent from the building (argon 41) is 40 mrem per year. This occurs at station #12. The average bachground in p l our area is 140 mrem per year. ,,
4. A reasonably extensive environmental monitoring program has been routinely j conducted since the reactor began operating in 1965. Briefly it can be '

l described as follows: '

(. a. Onsite Monitoring I

(1) There are 10 beta-gamma area monitors located throughout the containment building. The data from ea'ch monitor is recorded in the reactor control room.

1 i

(2) The containment building exhaust duct is monitored by three differ-ent systems. One of these systems is ahead of the roughing and high-efficiency filter bank complex. The other two are located at the base of the stach. One of these monitors the duct for gaseous activity and the other for particulate activity. The readout from all three systems are recorded in the reactor control room.

(3) There are 6 film badges sensitive to beta, gansaa and neutron radiation located within the reactor containment building. These film badges are changed on a inonthly schedule (4) Inside the exhaust stack at an elevction of approximately 25 feet above grade there are 2 film badges and 2 LiF thermoluminescent dosimeters (TLD's). The film badges are changed every month and the ELD's are changed every.three months.

(5) Throughout the containment building there are 10 criticality l dosimeters.

l (6) There are 4 particulate air sampics systems continuously operating at the facility. These are portabic systems; generally there is one inside the containment building'and three outside the building but within the restricted area. The filters on these systemp are changed and counted on a daily schedulo.

(7) There are two fixed-location criticality monitoring stations.

One is located near the fresh fuct storage _ vault and the other over the spent fuel storage pool. The readout from both systems is recorded,

b. Offsite Monitoring (1) At the present time film badges are routinely placed at 25

. locations on or outside the restricted area fence of the facility.

l Seven of those are neutron sensitive badges located on the facility i fence. They have never. indicated any exposure due to neutron radiation. These badges are not tabulated in Table 1 or shown -

on the aernched map. h rmoluminnecant dnstmotors are l oc ated

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, , at 34 stations. Five of these etetions era used for control and background determination and cro all locsted 0 or more miles away from the . f ncility. The locations of the reactor monitoring l TLD's are shown on the attached map. The film badges are changed j every month and the TLD's are changed overy three months. '

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5. The sumary of the data collected by the environmental monitoring program I is presented in Tabic 1. Station locations referred to in the table arc shown on the attached map. . Note that this data is a sununary only of data l from the film hadges and TLD's located in the exhaust stack and at or outsido the restricted area of the f acility. Background data was obtained from 5 TLD's located at points 3 or more miles from the facility. The Qg average background radiation icyc1 for the Atlanta ares has been measured as 140 mrom por year. All of the data in the table is reported as average hM

, radiation exposure in mrom per year above a background of 140 mrom por year clcM Station #13 ~ shows an abnormally high dose rate. It is estimated that 70 mrom per year of the total average of 90 mrom per year is due to the 9 intermittent use of .an isotope handling hood located in the south-east g corner of the laboratory building.

a. There are a total of 37 sample locations that are in the exhaust stack, on the restricted area fence or within 500 foot of the stack. An additional 5 sample locations are all over 0 miles from the facility,
b. For the 2-year period beginning January 1, 1970, data has been tabu-lated for 720 Beta-gnmma film badges,192 Beta-gmuna-neutron film badges and 240 thermoluminescent dosimeters. The film badges are changed every conth *nd the TLD's are 3 hanged every 3 months.
c. The only radionuclide we have detected in the gascous effluent from the stack has boon argon 41. It was assumed therefore that argon 41 was the primary radionuclide responsibic for the exposure at each of the stations.

d.. The minimum level of scusitivity of the monitoring systems is j tabulated below:

(1) LiF thermoluminescent dosimeters: 5 mrom (2) Film Badges: 10 mrem '

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- The above information represents our best available data on the radio-active effluent releases to unrestricted creas around the Georgia Tech acsearch 2cactor. Ghould you have any ouestions regarding the material, please contact me. The telephone system at Georgia Tech has been recently changed. My new number is 404-% 4-3502.

Sincercly yours, Original Signed by R. S. KIRK Robert S. L(AND r!d and, Reactor Supervisor cc: Nuclear 3sfcguards Jommittec .

Prof. F. W. Chambers Mr. H. L. 3-kor Encis. Table 1 Site Map i

FI; F":'.': ;'. :1..:.~;I i.00M TA3LE )

' j . . , - ,, . . . . . , M ,2 9. W Film Badga & TLD Environmental Date. - Georgia "lr.ch .2cacerch Acactor +

Exposure in mrom per yoar abovo a fait.P..o,round of 143 mrem per year.,,\\

NO. TYPE 3ADIATION LOCATICH 1973 1971 DETECTED FILM TLD FILM TLD 40 F Y In Otsck 140 -

533 -

Gee note 1 40 F 3+Y "

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lb .T T 9*Y "

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'. 250 457 2 T/F Y,F Gee Map M 6 M 21 P. + Y, T 3 " " n r; 22 M 22 4 ' "

M 39' M 22 5 "

!! 54 M 13 6 n

" M 31 gg 13 7 "

" M S M 20 3 " "

_, M 41 M 13 9 " "

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N 12 M 13 M 15 M 13 11 "

20 22 M 13 12 - " "

30 76 M 25 l 13

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M 31 M 13 17 " "

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M M liOTE3 1. F = Film 3adge T = TLD j

M = Minimum sensitivity: Film badge,10 rarem; TLD, 5 mrem.

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2. See response to question 5 relative to station fr13,
3. Stations '.ViS, IMM, etc. cro located 3 or taore miles from the facility.

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