ML20009A186
| ML20009A186 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 03/13/1981 |
| From: | Kirkland R Neely Research Reactor, ATLANTA, GA |
| To: | |
| Shared Package | |
| ML20009A185 | List: |
| References | |
| NUDOCS 8107090163 | |
| Download: ML20009A186 (8) | |
Text
i GEORGI A INSTITUTE OF TECHNOLOGY SCHOOL OF NUCLE AR ENGINEERING ATL ANT A. GEORGI A 30332 March 13, 1981 FRANgH,NEELY guCLL AR RESE ARCH CENTE R TEL4 PHONE: 4404) See 3600 U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W.
Atlanta, Georgia 30303
Reference:
Docket 50-160; License R-97 Gentlemen:
Pursuant to section 6.7a of the Technical Specifications for the Gerogia Tech Research RePator (License R-97), the following annual report is submitted.
The reporting period is January 1, 1980 through December 31,1980 (calendc r year 1980). The designation of the sections below follow the title and order of Section 6.7a of our Technical Specifications.
- 1. Operations Summary
- a. Changes in Facility Design There were no reportable changes in facility design during the reportir.g period.
- b. Performance Characteristics During the reporting period the reactor was operated at power levels up to 5000 kw(t) using a 17-element core. Fuel per-formance has continued to be satisfactory with no known problems.
- c. Changes in Operating Procedures There were no reportable changes in operating procedures during the
.eporting period.
- d. Results of Surveillance Tests and Inspections The surveillance tests and inspections of the facility required by the Technical Specifications were performed. Documentation of each of the tests and inspections are available at the site for review.
- e. Changes, Tests and Experiments Approved by USNRC There were no changes, tests or experiments that required the approval of the USNRC pursuant to 10CFR 50.59 (a).
r2107090163 810630 DR ADOCK 05000160 PDR
U.S. Nuclear Regulatory Commission, Region II Page 2 Nbrch 13, 1981
- f. Changes in Plant Staff and Committee Membership The current plant operating staff is as follows:
Dr. J.L. Russell, Director, Nuclear Research Center Mr. R.S. Kirkland, Associate Director and Reactor Supervisor Mr. R.S. Kirkland, Acting Reactor Engineer 2
Mr. R.M. Boyd, Radiological Safety Officer The current organization of the Nuclear Safeguards Committee is as follows:
Mr. R.M. Boyd Dr. R.N. MacDonald Dr. M.V. Davis Dr. D.W. Martin Dr. B. Kahn Dr. J.L. Russell Mr. R.S. Kirkland Dr. J.W. Poston
- 2. Power Generation For the period January 1,1980 through December 31, 1980, the total power generation of this reactor was 1007 megawatt hours.
! 3. Shetdowns During the reporting period there were thirty-six (36) unscheduled shutdowns of the reactor. These are tabulated in Table I as to the i cause and preventive action taken.
I
- 4. Maintenance (Safety-related systems and components)
- a. In March and April, gasket f ailure in heat exchanger HX-D1 caused 4
partial tube blockage in downstream heat exchanger HX-D2. A new gasket was installed.
- b. In March and April, a series of spurious power trip scrams led to the replacement of an uncompensated ion chamber in one of the high flux monitor channels.
- c. In April, following a containment building pressure test, the gasket of the inner personnel air lock' ruptured. A new gasket was installed and tested.
- d. In July, a reactor outlet isolation valve failed to close duringThea test because a failed retainer ring impeded the closing mechanism.
' valve operator mechanism was overhauled and tested.
i f e. In August and again in December, a leak developed in the containment building truck door gasket. Repairs and testing were done each time.
l The gasket is scheduled for replacement in spring 1981.
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. . . , . - - - - - , , . - _ . ~ , , . , , , ~ , . , . . . - _ . . - , . . _ . , , . ~ . - . , , , . - - - . , - ,
U.S. Nuclszr Ragulatory Commission, Region II Page 3 March 13, 1981
- 5. Changes, Tests and Experiments Without Prior USNRC Approval During the reporting period there were sixty (60) approved experiments for the Georgia Tech Research Reactor. Each of these was evaluated prior to its approval with regard to Section 3.4 of our Technical Specifications. Records of each experiment are available at the '
site for review.
- 6. Radioactive Effluent Releases
- a. Gaseous Effluents:
- 1. Gross Radioactivity Released a). Total gross radic iggivity-noble gases: Curies of A (only de- 237.49 tectable noble gas) b). Average normal steady state concen- -5 3.0 X 10 tration released out of stack. At 1 MW: pC1/cc
~
5 MW: 1.8 X 10 '
LCi/cc
_4 c). Maximum instantaneous concentration re- 2.0 X 10 leased: PCi/cc or 378.00 pCi/sec d). Percent of technical specification 64.6%
limit:
None detected. Minimum detectable release is 400 pCi/ year b). Percent of technical specification s<1.7%
limit:
- 3. Particulate Release a). Total gross radioactivity (6,Y) re- (lpCi leased:
~
.,j
.-- ., m., - . -
U.S. Nuclear Regulatory Commission, Region 11 Page 4 March 13, 1981 b). Gross alpha radioactivity released: (luCi c). Total gross radioactivity of nuclides 41pci with half-lives greater than eight days:
d). Percent of MPC for particulates with half-
! 40.01%
- lives greater than eight days:
- b. Liquid Effluents
- 1. Total gross radioactivity (E,Y) released 59.3 pCi*
excluding tritium and average concentration: Total
~
Average Concentration: 2.0 X 10 uCi/cc before dilu-tion with
! other Georgia Tech water.
- 2. Maximum concentration radioactivity (2,y) -6 released excluding tritium to unrestricted area: 1.7 X 10 LCi/cc be-fore dilution None
- 3. Total alpha radioactivity released:
(minimum detectability 2 pCi/ year)
Total volume of liquid waste released: 3.2 X 10 ml 4.
10 cg 6.750 X 10
- 5. Total volume of dilution water:
e
- 6. Total radioactivity and concentration 68,920 pCi released by nuclide:
l' Tritium 2.1 X 10~
Average concentration:
PCi/cc tritium
- 7. Percent of technical specification limit for .01% for gross total radioactivity from site:
6,y excluding tritium 7.0% for tritium
- The majority of this is for the laboratory sinks or operations outside he reactor containment building and is not necessarily attributable to reactor operaticus.
U.S. Nuclear Regulatory Commission, Region II Page 5 March 13, 1981
- 7. Environmental Montoring
- a. through d. Environmental monitoring is done with 43 TLD's and 30 film L dges. See Figure 1; " Environmental Monitoring Stations". TLD's are changed on a three month basis and film badges on a one month bases.
Highest 349*** (Station 9)
Lowest 0 (Station 9)
Highest Annual Average Radi-ation Level 87 (Station 9)
- Minimum sensitivity is 3 mrem C** This dose was not from GTRR operations but rather from sealed sources used for calibration of health physics instruments.
- e. Maximum cumulative radiation dose from:
- 1. Direct radiation and gaseous effluent: 416 mrem /yr.
- 2. Liquid effluents:
no,e or 41%
10CFR20 limits
- 8. Total Occupational Personnel Radiation Exposure For 1980 Three persons received greater than 500 mrem (The highest was 1820 mrem). No persons under the age of 18 years received greater than l
10 mrem.
l GEORGIA INSTITUTE OF TECHNOLOGY
\ l36&,J
. R.S. Kirkland l Associate Director I
t RSK:1rm CC: Members, Nuclear Safeguards Committee L.D. McDowell (3) 6 Sworn to and subscribed before me this /4 day of fysu.; ,, 1981 e b . N ece) e ./ _
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TABLE I GTRR UNSCllEDULED SilUTDOWNS January 1, 1980 through December 310 1980 .
REPORT CAUSE PREVENTIVE ACTION NO. DATE PRIMARY CIRCUIT Spurious Monitor System performance 1-8-80 Period Trip - Neg. Cautioned operating staff 80-1 Operator error (trainee) 80-2 1-15-80 Period Trip - Neg.
Period Trip-Neg. Spurious-possible loose
! 80-3 1-18-80 conn. Monitor system performance ,
Spurious Monitor system performance 80-4 1-18-80 Power Level No. 1 1-21-80 Period Trip - Neg. Found loose connections in 80-5 power supply - see 80-2,3,4 Monitor system performance Low D 0 Flow Apparently spurious 80-6 1-23-80 tow D 0 Flow Slide wire contact came 80-7 2-22-80 loose Monitor, investi gate replacement of slidewire assembly Operator error Cautioned operating staff 80-8 3-3-80 No D2 0 Overflow Cautioned operating staff and Doors Open Operator error 80-9 3-3-80 students Low D2 0 Flow Casket plugging tubes-80-10 3-5-80 IlXD2 Replaced gasket in 11X-D1 Apparently spurious Monitor system performance 80-11 3-27-80 Magnet Actuator Amplifier Monitor system performance 3-27-80 Power Trip No. 2 Apparently sprulous 60-12 Apparently spurious Monitor system performance 80-13 3-27-80 Magnet Actuator Amplifier Magnet Actuator Amplifier Operator error-manual 80-14 3-2-80 sc ram Establish better communication for alarm testing l
4-10-80 Power Level No. 2 Spurious-suspect faulty 80-15 chamber Monitor system performance Power Level No. 2 Spurious-suspect faulty 80-16 4-10-80 chamber Monitor system performance Power Level No. 2 Spurious-suspect faulty 80-17 4-10-80 chamber Monitor system cerformance Power Level No. 2 Spurious-suspect faulty 80-18 4-10-80 chamber Monitor system performance Power Level No. 2 Spurious-suspect fautty 80-19 4-11-80 chamber Replace chamber Operator error cautioned operating staff and 80-20 4-23-80 Doors Open students
REPORT CAUSE PREVENT 1sE ACTION ,,
NO. DATE PRIMARY CIRCUIT
~
- Magnet Actuator Amplifier Faulty detector being 80-21 5-6-80 tested Replace detector Operator error Cautioned staff and students 80-22 5-22-80 Doors Open Monitor system performance Magnet Actuator Amplifier Apparently Spurious 80-23 6-15-80 Apparent recorder mal-80-24 6-24-80 liigh D 0 T mp rature 2 function Monitor system switch, consider replacement of the switch mechanism liigh D 20 Temperature Apparent recorder mal- Cleaned scanner switch; consider 80-25 6-25-80 function replacement of the switch mech-anism.
Apparently spurious Monitor system performance 80-26 7-23-80 Low D2 0 Flow None 9-5-80 All Power failure 80-27 Apparently spurious Monitor system performance 80-28 10-27-80 Magnet Actuator Amplifier Monitor system performance 10-27-80 Power level No. 2 Apparently spurious 80-29 Slidewire malfunction Monitor performance, replace 80-30 10-28-80 Low D2 0 Flow amplifier and possibly the slide-wire unit Slidewire malfunction Monitor performance, replace 80-31 10-28-80 Low D2 0 Flow amplifier and possibly the slide-wire unit Recorder mal function See 80-31 80-32 10-29-80 Low D 0 Flow See 80-31 10-30-80 2
Low D 0 Flow Recorder malfunction C043 Recorder malfunction See 80-31 80-34 10-31-80 Low D 0 Flow Cautioned staff and students Operator error 80-35 11-4-80 Doors Open Operator error Cautioned operation staff 80-36 12-2-80 Period Trip
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