ML20080D680
| ML20080D680 | |
| Person / Time | |
|---|---|
| Site: | 05000406 |
| Issue date: | 08/09/1983 |
| From: | Payton B TUSKEGEE INSTITUTE, TUSKEGEE, AL |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20080D672 | List: |
| References | |
| NUDOCS 8308300546 | |
| Download: ML20080D680 (8) | |
Text
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- c"R*"" " '" ' ' ' ' " " l Buskegee 3nstitute
_W . _E R _ T_ P _E, 7sau,, 's E "d FOUNDED BY BCCKER T. WASHINGTON.1881 yE,"[ Q7, A EDWARD ALLINSON MRS MADOLYN A RADNEY DeOhDORNE SERMELET JR THOMAS REED m" YE,',Ev' OFFICE OF THE PRESIDENT 7,50'j"Rf 7 A O GASTON WILUAM J SC>eEFFELsN m EARL G GRAVES WAVNF. TEAGLA ELK, TNE TUSKEGEE INSTITUTE JAseER F W'i uAus wiluELasmJR ALAflA M OAvo J uAMONEv 36068 HONORANT TRUSTEES ARTHUR P COON MELVsN A GLASSER FR D MTTERSON JAMES A fv0CHE WILUAM ROSENWALQ August 9, 1983 Mr. Darrell E. Eisenhut Director of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20545
Dear Me. Eisenhut:
Re: Docket 50-406 In accordance with 10CFR50.30, as the duly authorized legal officer (President) of Tuskegee Institute, I formally request authorization to both dismantle and 'ispose of our AGN-201 reactor components and also for tu mination of our operating license R-122.
Dr. Vascar G. Harris, Dean of Engineering and Architecture, has the formal responsibility of seeing to it that conditions for the above request are met, but if I can be of assistance, please contact me at this office.
Sincerely, W
8308300546 830809 PDR ADOCK 03000406 Ben amin F. Payton W PDR President BFP:t STATE OF ALABAMA )
l COUNTY OF MACON )
Sworn to and subocribed before me this 9th day of August, 1983, at Tuskegee Institute, Alabama.
A wb . o '
s '
Pauline W. Punch Notary Public Commission expires 10/20/84 DorWin F. Peyton, ProeJWent L. A. Williams, trice President for Sus / ness Attairs k.
s o e
- TUSKEGEE INSTITUTE RADIATION SAFETY COMMITTEE Radiation Survey and Contamination Swipe Tests for the Tuskegee Institute AGN-201 Reactor (Operating License R-122)
In accordance with the provisions of Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors",
a comprehensive radiation survey has been made of the Tuskegee .
Institute AGN-201 Reactor (Operating License R-122). {
The reactor was shipped to Tuskegee Institute in 1973 after having been located at Oklahoma State University of Agriculture and Applied Science for a number of years. The reactor was never operated at Tuskegee Institute but was held in a pre-operational state. Since it was never operated, it was nct expected that any residual contamination would be found for the unit. None war found by either a radiation survey utilizing an Eberline Protable Beta-Gamma Geiger Counter or analysis of contamination swipes using a Nuclear Measurements Corporation Proportional Counter or e Packard Liquid Scintilla-tion Counter. All the results as recorded in detail on the accompanying tables indicate that there is no residual contamina-tion associated with the reactor components. Contamination swipes in scme cases, were made over areas larger than 100 cm2 ;
with the intention of breaking up the swipe into smaller 100 cm2 areas if contamination was found. None was found so this was deemed unnecessary.
All the analysis was done looking for gross alpha-and beta-gamma counts fully expecting to try to identify the radionuclide source of contamination if any radiation near the limits of Table 1 in Regulatory Guide 1.86 was found. None was found so that it was deemed unnecessary to do this. Activity in dpm was calculated for each component based on the calibration of the instrument with a. calibrated check source.
All counts were made and documented between May 11, 1983 and June 17, 1983 No effort was made to further reduce radiation contamina-tion on any reactor component since the levels were already background levels.
A sketch of the Tuskegee Institute Engineering Nuclear Facility, where the AGN-201 reactor is located, is included in order to identify the premises for those reviewing this report.
NOMENCLATURE Abd-201 REACTOR COMPONENTS Component Description Standard Check Sources for Comparison Component Source Radio- Activity Form Identity Identity isotope
- c. Outside reactor skirt q. C-14 .00077 uCi Disc
- e. Outside control rod hat t. Cl-36 848 DPS-11/70 "
cover
- f. Inside control rod housings u. Cl-36 1.06x10-5 mci-1/73'"
- g. Inside glory hole v. U-238 Check "
- h. Inside top shield tank w. Am-241 5555 apm* "
- 1. Shield. tank space above x. Pu-239 Check "
reactor J. Fuel tank space
- k. Inside Fuel tank
- 1. Outside Fuel tank Experiments Ports - 4 mt Temperature Gauge Side m3 Staircase Side Control Rods -
Safety rod #1 Light orange USR1 Safety rod #2 dark red USR2 DCR Coarse rod reddish orange DFR Rine rod yellow I Based on 2 n geometry J
Instruments Used:
- a. Survey Meter - Open Window (Engineering Nuclear Facility)
Eberline Instrument Corp.
Sante Fe, New Mexico Sensitivity Scale Model E-120 Geiger Counter 0 .5 mr/hr .02 mr/hr divisions Serial No. 5325 0-5 mr/hr .2 mr/hr Most recent Calibration Date - 3/28/83 using 0-50 mr/hr 2 mr/hr divisions a Cs-137 instrument check source Background 0.02 mr/hr
- b. Liquid Scintillation Counter (LSC)
Carver Research Foundation Packard Model 2425 (1975)
Background Count: C-14 = 28 CPM; H-3 = 22 CPM 00-14 = 87.7%; n11-3 = 60.8%
- c. Proportional Counter Milbank Hall Nuclear Measurements Corp. -
Model PC-3A (Serial 55) a-6 Plateau Operating voltage = 1850 Background Count = 205 CPM aPlateau Operating voltage = 110e Dackground Count = 17 CPM
PROPORTIONAL COUNTER EFFICIENCY Source Identity a Plateau Count-Bckd. a-S Plateau Count- Beta Beta Effi-Count Rate Rate CPM E gt* Count Bckd. Activity Activity ciency CPM Rate CPM DPM ng
- q. 24 7 -
229 17 .0077 uCi 1690 1.01
- r. 37 20 - 140,035 139,810 11,900 DPS 714,000 19.6
- t. 22 5 - 27,970 27,760+ 848 DPS 50,880 54.6
- u. 2.7 10 - 13,026 12,811+ 1.06x10-3 23,500 54.5 uCi
- v. 8073 8056 - 121,860 - - -
- w. 4551 4534 81.5%* 4,586 - - -
O 1531 1514 - 1,877 - - _ _
f x.
l
(
OSource must be covered so that it can't be seen l
- Based on 27 geomet ry
+ Count must inclued some backscattering
AGN-201 G- SSURVEY Component Reactor Dose Rate Identity Date mr/hr
- a. Outside water tank 5/11/83 Background
- b. Inside water tank housing 5/11/83 Background
- c. Outside reactor skirt 5/11/83 Background
- d. Inside reactor skirt 5/11/83 Background
- e. Outside control rod hat cover 5/11/83 Background
- f. Inside control rod housings 5/11/83 Background
- g. Inside glory hole 5/11/83 Background
- h. Inside top shield tank 5/11/83 Background
- 1. Shield tank space above reactor 5/11/83 Background J. Fuel tank space 5/17/83 Background
- k. Inside Fuel tank 5/17/83 Background
- 1. Outside Fuel tank 5/17/83 Background Experiments Ports mt Temperature Gauge Side 5/17/83 Background m3 Staircase Side 5/17/83 Background Control Rods- ,
Asr1 Safety rod #1 Light orange 5/11/83 Background nar2 Safety r d #2 dark red 5/11/83 Background Der Coarse rod reddish orange 5/11/83 Background n'fr Fine rod yellow 5/11/83 Background
AGN-201 COMPONENT CONTAMINATION ACTIVITY BASED ON SWIPE TESTS Proportional Counter Licuid Scintillation Counter c_8 a-S S 8 g Reactor aPlateau aCount-Bckd. aActivity, Plateau Count- Activity + Count Count 6 Activity Component Count Rate CPM DPM Count Bckd. DPM Rate Rate- DPM Identity Rate Rate a Count- CPM Bckd.
- a. 21 4 5 232 22 40 29 1 1
- b. 16 - 0 209 4 7 32 4 5
- c. 31 14 17 229 7 13 39 11 13
- d. 16 -
0 234 29 53 28 0 0
- e. 28 11 13 204 -
0 34 6 7
- f. 13 -
0 226 21 39 29 1 1
- g. 15 -
0 197 -
0 35 7 8
- h. 33 16 20 206 -
0 16 -
0
'i. 21 4 5 216 7 13 29 1 1
- j. 26 9 11 191 -
0 33 5 6
- k. 25 8 10 206,237 10 18 29 1 1
- 1. 17 0 0 194 -
0 25 -
O mt 16 - 0 191 - 0 36 8 9 m3 16 - 0 210 5 9 40 12 14 05R1 30 13 16 223 2 4 31 3 3 nSR2 25 8 10 204 -
0 33 5 6 DCR 24 7 9 208,186 -
0 23 -
o nFR 28 11 13 203 -
0 34 6 7 a Activity (DPM) is based on Am-241 efficiency of 81.5% for 2 i geometry
+
8 Activity (DPM) is based on Cl-36 efficiency of 54.5%
O S Activity (DPM) is based on C-14 efficiency of 87.6%
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