ML20009A189: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 138: | Line 138: | ||
- L' SCALE hir..= 100 f t. | - L' SCALE hir..= 100 f t. | ||
k | k | ||
.1 am..m T | .1 am..m T | ||
i w | i w | ||
Latest revision as of 12:17, 17 February 2020
| ML20009A189 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 02/28/1980 |
| From: | Kirkland R Neely Research Reactor, ATLANTA, GA |
| To: | |
| Shared Package | |
| ML20009A185 | List: |
| References | |
| NUDOCS 8107090166 | |
| Download: ML20009A189 (7) | |
Text
r ~ - _ . . . , . . . . . . ._, . . . _ . . _ .
/
GEORGI A INSTITUTE OF TECHNOLOGY SCHOOL OF NUCLEAR ENGINEERING ATL ANT A. GEORGI A 30332 FH AN g H, h4 E LV N tJC LE A H H ESE ANCH C EN T E R TLLEPHONE. (404l 394 3600 s
February 28, 1933 U.S. I'uclear Regulatory Cocr.insicn, Region II 101 bhrietta Street , N.W. 1 Atlaria, Geortla 30303 Refemnce: Do &et 50-160; License R-97 Gentlemen:
Parsuent to section 6.7a of the Technical Specificatf orc fer the Georgia Tech Research Reactor (license R-97), the co lla.:Irc an-nual report is subnitted. The reporting period is J:enuar/ 1,1979 through Decerter 31,1979 (calender yea" 1979). Tre designation of the paragraphs follow the title and order of Section 6.7a of our Technical Specifications.
- 1. Operations Sunr:nry
- a. Chanres in Facility Ibsien here wem no reportable changes in facility design d tring this reporting period.
- b. Perfornnnce Characteristics During the reporting period, the reactor was operated at power levels up to 5000 kd(t) using a 17 elecent core. Fuel perforrance has continued to be natisfactor*/
with no known problems.
- c. Chances in Operating Procedures (Safety Palated)
I Were were no reportable changes in operating procedurec during the reporting period.
- d. Pesults of Surveillance Tests and Inspections The surveillance tests and inspections of the facility required by the Technical Specifications were performed.
Results of each of these tests and inspections are avail-able at the site for review.
8107090166 810630 DR ADOCK 05000160 t
- c. .
U.S. Nuclear Regulatory Comission, Region II Page 2 February 28, 1980
- e. Changes, Tests and Experinents Approved by USNRC i
Bere were no changes, tests or experinents that required the approval of USNRC pursuant to 10CFR 50.59 (a).
- f. Changes in Plant Staff and Corrnittee Membership he curmnt plant operating staff is as follows:
Dr. M.V. Ihvis, Director, Nuclear Research Center Mr. R.S. Kirkland, Associate Director and Reactor Supervisor Mr. R.S. Kirkland, Acting Reactor Engineer Mr. R.M. Boyd, Radiological Safety Officer he current organization of the Nuclear Safeguards Caxtittee is as follows:
Fr. R.M. Boyd Dr. R.N. FacDonald Dr. M.V. Davis Dr. D.W. Fartin Dr. B. Kahn Dr. J.H. Russell Mr. R.S. Kirkland Dr. J.W. Poston
- 2. Power Generation Fbr the period January 1,1979 throu@ Decenter 31, 1979, the total power generation of the reactor was 837 megawatt hours.
3 ShutdowTis During the reporting period, there were 24 unscheduled shutdowns of the reactor. Rese are tabulated in Table I as to the cause and pmventive action taken.
- 4. Fhintenance 6afety-related systems and components)
In July and in November, repairs were made to the regulating rod drive mechanism. he repairs included replacenent of the right-angle gear drive and replacenent of a broken shaft key.
In Septenber, mpairs were made to the TRA-D1 mcorder. A broken lead was replaced and a lead length adjust potentiometer was cleaned.
In October, the purification pump FD-4 failed due to excessive bearing wear. In Decenber, companion pump FD-3 failed for similar reasons. New bearings and a replacement rotor were installed in MD-4 and the unit returned to service.
In November, the motor and bearings for the Kanne circulating punp were mplaced fouowing failure of the unit.
. , - .. - . - ,r- -
c,e -. - y , . - - , - . , , ,, ,-.,..,y -
~ , , ~ , - . . , , , - - - - -
o . . . . . . _
U.S. Nuclear Eegulatory Comission, Region II Page 3 February 28, 1980 In December, the uncompensated bn cha2er position H-18 was removed in an effort to locate the source of the many Ion Chamber Voltage Scrams. Evidence was found of loose or broken pin connections at the high temperature cable /
. chad er connection. A replacenent chamber was installed ard the high temperature cables were re-worked.
5 Changes, Tests and Er.periments Without Prior USNRC Approval.
During the reporting period there were 69 approved experiments for the Georgia Tech Research Reactor. Each of these was evaluated prior to its approval with regaM to Section 3.4 of our Technical Specifications. RecoMs of each experiment are available at the site for review.
- 6. Radioactive Effluent Releases
- a. Gaseous Effluents:
- 1. Gross Radioactivity Released
- a. Total gross radioactivity - noble gases:
Curies of 41A (only detectable isotope) 73.01
- b. Average normal stedy state3.0 concentE. tion released out of stack. At 1 Md: X 10- pCi/cc 5 Md: 1.8 X 10-4 pCi/cc
- c. Maximum instantaneous concentration released:
~
2.1 X 10 pC1/cc or 396.69 pCi/sec
- d. Percent of technical specification limit: 67.8%
- 2. Iodine Release
- a. Total iodine radioactivity mleased: None detected.
Minimum detectable release is 400 pC1/ year.
- b. Percent of technical specification limit: 41.7%
3 Particulate Release
- a. Total gross radioactivity (B,y) released: 41pCi
- b. Gross alpha radioactivity released: 41pCi
- c. Total gross radioactivity of nuclides with half-lives greater than eight days: (19C1
- d. Percent of MPC for particulates with half-lives greater than eight days: ;:0.01%
m.
U.S. Nuclear Regulatory Cor: mission, Regicn II Page 4 February 28, 1980
- b. Liquid Effluents
- 1. ibtal gmss radioactivity (8,y) released excluding tritium and average concentration:
2 Total: 1.636 x 10 uci*
-7 Average Concentration: 3.64 x 10 pci/cc before diluticn with other Georgia ibch water.
- 2. Maxirun concentration radioactivity (8,y}6 *"** ** " "E tritium to unmstricted ama: 3.84 X 10 uCi/cc (Co-60) before dilution 3 Total alpha radioactivity released: None detected (mint::um detectability 2 ui/yr.)
8 4 Total volume of liquid waste mleased: 4.5 x 10 ,7 10 5 Total volume of dilution water: 6.750 x 10 ml
- 6. Total radioactivity and concentration released by nuclide:
103,500 uci Tritium
-4 Average concentration: 2.3 X 10 uci/cc tritium
- 7. Percent of technical specification limit for total radioactivity from site:
.01% for gross 8,y excluding tritium 9 02% for tritium I 7 Envimnrent Monitoring l
- a. through d. Envimnmental monitoring is done with 43 TLD's l
and 30 film badges. See Figum 1. " Environ-i mental Monitoring Statiom". TLD's am changpd l on a thme month basis and film badges on a one i
I r:onth bases. The film badges are at 30 of the l
sare locations as the TLD's l
TID Ibse mmm**
l Highest 11 (Station 2)
Iowest 0 (Station 2)
Highest Annual Avg.
i Radiation Iavel 2.8 (Station 2)
- The ma,jority of this is for the laboratory sinks or operations outside
' the reactor containrrent building and is not necessarily attributable to reactor operations.
- Minimum sensitivity 3 mrem
- n. n , . .. ~ ~ - - .
- U.S. Nuclcar Regulatory Cmmission, Region II Page 5 February 28, 1980
- e. Mnnn cumulative radiation dom fmm
- 1. Dimet radiation and gaseous effluent: <l5 mreWyr.
- 2. Liquid effluents: none or <1% 10CFR20 limits
- 8. Total Occupational Personnel Radiation Exposure For 1979 e
'Ihme persons received greater than 100 mrem ('Ihe highest was 1820 mmm). No persons under the age of 18 years received greater than 10 mmm.
Sincerely yours, GEORGIA INSTITLTIE OF TEC'EJOIDGY r
/faddL/
R.S. Kirkland Associate Director RSK:lm cc: Merbers, Nuclear Safeguards Comittee L.D. McDowell 1
l Sworn to and subscribed before me this Q 9 day of J.is , 1980
,( j(tt cj L'2 n & L
.y ~ v a s .. ,ou.c. c.o,,,.. si . At urge u, cemnissa,n um... u.y a. rm l
l I
.>+ .
y ' ' g -( l l!r _
'b .
m W.ik };i ,j l's(' Q
, / .
Environmental ' Monitoring c --cr;. q; v.y? ..**-
.. 1,1 ,
zl T ..... &.; - Stations 9 .. g .- r,y.~
..=
i y:
. 3
[m
.g, .
i
.._._T~ ,
; > - __,:- SEPTEMBER 1975 5 i: ~ - i. ! I L Il , ' -, - '
f ""- [/ .is ._lq)..l *
/ e
- L' SCALE hir..= 100 f t.
k
.1 am..m T
i w
~:.=.. ..
_q-38 n u
-l- r M?%5Y g Q
i [-27}.te*dT*i'a1 ,3Rf J I $'
%U ,) f9sg. _ . -- Y;,g,f /,
7 .- 1, i,
\ '*5 is it g ,a y , , , ,, a g, mm..
gr k' : 83 6Y 9EY ,*-4 1
) !]
4 I'I'
- "'A',"*J."["
- hy,, .f."/,'/ *2
.: y;
> v -
# " 2
ANNUAL SURFACE _ _ _ g__ ~.. .I a/] [,&.' s
\ ((IN<_~ = $_ MMr/hig -.2, %)[i*t
- I WIND ROSE a x~ l m_ m.__ _
f21 __ x\-6 9.*, d, q h< ' ' _.a_
<x. -( ~ \ -
y'g <m . . .. . s i ,
.s , r {> JJ .' 4, ' '
i ' '\s N N j uno_ %
- n reo~.is #= * = ^ = c W / '
r d4 m, _. . C' u diodwM l.? esis Y; ) *
% gco..e ur) 9 74' r- ..... st ' '
}t,l' l -
\
.(peases,.o m' caQ f * %y. , !j'. i _- ' tw s .
s l.si 97txeni 7 y * - w, I'-.- m . h L,-. ~ , ] !.
. b j .'!. ' Il j__
" 'J '
t I,s L l , c'/13***3)
> . , ,- uucau fw [ *'
1 'S, 5% 10% 15 % l T' ' 07a * '. lY' - + { soon ... T' ', ~ -- q - ' I_ . - f i eEecEnract FREQUE8eCY j srs. sew. Sea ,M i 4 ' /
/ [ /
TABLE 1
- GTPJ1 UNSCHEDULED SHUPDOWNS January 1, 1979 through Decenber 31, 1979 -
REPORT NO, DATE CIRCUPP CAUSE PREVEfffIVE ACPION S-79-1 1-25-79 Negative Period No. 2 Clutch circuit deenergized Cleaned switch and relay contacts S-79-2 2-2-79 No D2 0 Overflow Ioss of suction on MD-4 Charge additional D 20 to TD-1 S-79-3 2-2-79 No D2 0 Overflow Ioss of suction on MD 4 Charge additional D20 to TD-1 S-79-4 2-7-79 ALL Operator error-electrical Caution operating staff short S-79-5 3-26-79 High Shield Coolant Tenp operator error-TR2 recorder Caution operating staff S-79-6 6-11-79 low Ion Chamber Voltage Spurious Check for faults and monitor system perforinance S-79-7 6-14-79 low Ion Cha:rber Voltage Spurious Grck for faults and monitor system performance S-79-8 6-15-79 Iow Ion Chamber Voltage Spurious Check for faults and monitor system perforinance S-79-9 7-24-79 Manual Scram Operator Action -procedural Caution Health Physics Staff S-79-10 9-5-79 Manual Scram Operator error Caution operating Staff S-79-11 9-26-79 Doors open Electrical Power Surge None S-79-12 9-27-79 Iow D20 Flow Fault in FRA-D1 recorder Repair fault S-79-13 10-8-79 Doors Open Icaking air connector Replaced swivel connectors S-79-14 10-23-79 Doors Open Operator error Caution operating staff S-79-15 10-29-79 Doors Open Door control improperly adj. Corrected adjustnent S-79-16 11-12-79 No D20 Overf1cw Operator error Caution operation staff S-79-17 11-27-79 Low Ion Chamber Voltage Spurious Check for faults and monitor system performance S-79-18 11-29-79 low Ion Chamber Voltage Spurious Check for faults and monitor system performance S-79-19 11-29-79 Low lon Chamber Voltage Spurious Check for faults and monitor system perfornance S-79-20 11-29-79 Low Ion Chamber Voltage Spurious Check for faults and monitor system performance S-79-21 11-29-79 Low Ion Chamber VoltaEp Spurious Check for faults and monitor system perfornnnce S-79-22 11-30-79 Low Ion Chamber Voltage Spurious Check for faults and monitor system performance S-79-23 12-12-79 Power lovel Spurious Check for faults and monitor system perforinance S-79-24 12-13-79 Magnet Actuator Amplifer Spurious Check for faults and nonitor system perfotrnnee _}}