ML20236P262
| ML20236P262 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/31/1987 |
| From: | Breiner E, Peddicord K TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8708120277 | |
| Download: ML20236P262 (11) | |
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ANNUAL OPERATING REPORT-of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR l
NRC LICENSE R-23
~ JUNE .1,1986 - MAY 31,1987 I
l DEPARTMENTOF NUCLEAR ENGINEERING ;
TEXAS A&M UNIVERSITY College Station, Texas 77843 -
B700120277 979533 kDR ADOCK 05000059 PDR 1Ek 1
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I' ANNUAL OPERATING REPORT !
of the .
TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 JUNE 1,1986 - MAY 31,1987 I Prepared by:
N-Evelyn M. Breiner -
l Reactor Supervisor Approved by: I
/A W l Khrfheth L. Peddicord[ Head Nuclear Engineering Department DEPARTMENTOF NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77843
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SUMMARY
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This report details the pertinent activities related to the Texas A&M University AGN-201M training facility operated by the Department of l 1
Nuclear Engineering during the period of 1 June 1986 to 31 May 1987.
Furthermore, it is intended that the contents of this report comply- with I the requirements- of 10 CFR 50. section 50.59 (b), and Appendix A, Technical Specifications, of license R-23. ,
The utilization of this facility continues to be similar to that of previous years. The general categories of utilization for this past year were support of Nuclear Engineering courses, operator training, research, and preventive maintenance. Nuclear Engineering courses supported during the past year were:
ENGR 102 Introduction to Nuclear Engineering NUEN 402 Radiation Counting Laboratory NUEN 405 Nuclear Engineering Reactor Experiments NUEN 602 Nuclear Reactor Analysis Components replaced as part of preventive and corrective
maintenance are. detailed in Section 4. Components replaced during this period do not involve unreviewed safety questions and are not expected to adversely affect the safe operation 'of this facility.
The results of all major parameter surveillance tests are shown in Table 1.
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' TABLE 1_ REACTOR PARAMETERS SURVEILLANCE MEASUREMENTS I
DATE REACTIVITY WORTH VALUE' 03 MAR 87 SAFETY ROD #1 1.175% Ak/k 03 MAR 87 ' SAFETY ROD #2 1.172% Ak/k 03 MAR 87 COARSE CONTROLROD 1.185% Ak/k 03 MAR 87- FINE CONTROL ROD 0.354% Ak/k ROD DROP TIMES 1'7 MAR 87 SAFETY ROD #1 130 msec 17 MAR 87 SAFETY ROD #2 140 msec 17 MAR 87 COARSE CONTROL ROD 135 msec REACTIVITY INSERTION RATES 11 MAR 87 SAFETY ROD #1 0.0461% Ak/k/sec 11 MAR 87 SAFETY ROD #2 0.0487% Ak/k/sec 11 MAR 87 COARSE CONTROL ROD 0.0382% Ak/k/sec 11 MAR 87 FINE CONTROL ROD 0.0106% Ak/k/sec TOTAL EXCESS REACTIVITY 12 MAR 87 TOTAL EXCESS REACTIVITY 0.296%Ak/k CORRECTED TO 20 C l
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- 2. OPERATIONAL
SUMMARY
UTILIZA-[lON BY CATEGORY: HOURS (a) Support of Nuclear Engineering Courses 32.60 (b) Operator Training 08.77 4
(c) Preventive / Corrective Maintenance 05.43 (d) Research Projects 09.50 Total Ooeratina Hours: 56.30 Total Hours Critical: 37.88 Total Watt-hours of Ooeration: 38.92 Averaae Power Level of Ooeration (Watts): 01.03 Number of Reactor Startuos: 101
- 3. UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION 20 NOV 86 Scram High No cause found. No action taken.
Level Channel 2 03 MAR 87 Low Level Student Operator Student operator l Channel 3 error in switching counseled. l channels. j 09 APR 87 Period Scram Sample with large Experimenter was negative reactivity counseled.
removed too quickly from reactor
(~-0.4% Ak/k).
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- . 4. MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE 1
(a) 12 AUG 86- At 0257, the AGN-201 evacuation horn went off. The Radiological Safety Officer determined that no radiological. hazard existed. The incident was attributed to a voltage spike. At 1420, the AGN-201 evacuation horn went off, again. After the Radiological Safety Officer determined that no radiciogical hazard existed, the control rods were removed from the reactor to ensure subcriticality, and the skirt mr nitor was removed from the console for maintenance.
(b) 14 AUG 86 Replaced a bad 0.01 F capacitor in the skirt monitor unit. Removed the Geiger-Mueller detector (GM) from the reactor skirt.
(c) 19 AUG 86 Replaced several transistors in the skirt monitor.
Noted that the GM detector had a defective seal and was not functioning properly due to loss of its fill gas.
- (d) 28 AUG 86 Replaced the GM detector with one of equivalent '
manufacture.
(e) 29 AUG 86 Replaced Relays C and D in the skirt relay box with ones of equivalent manufacture.
(f) 11 SEP 86 The AGN-201 evacuation horn went off. The Radiological Safety Officer determined that no radiological hazard existed. The reactor console was deenergized for investigation.
(g) 18 Sep 86 Changed the printed e!. cult board and meter face on the i skirt monitor with equivalent models obtained from an identical Nuclear Model L Count Rate Meter.
(h) 09 OCT 86 The AGN-201 evacuation horn went off. The Radiological Safety Officer determined that no radiological hazard existed.
(i) 14 OCT 86 Discovered that the skirt monitor had been plugged into line AC where the circuit diagrams for the console indicated regulated AC. Removed the control and safety rods from the core to ensure subcriticality, and
., l. .. .disablad tho ovacuation horn while leaving the skirt monitor in place.
(j) 15 OCT 86 Discovered that the skirt monitor had tripped. Removed the unit from the console and discovered a short on the printed circuit board.
(k) 28 OCT 86 Replaced the skirt monitor into the reactor console.
(1) 13 NOV 86 Enabled evacuation horn, and replaced control and safety rods into the reactor.
. (m). 03 DEC'86 During a shutdown configuration, Channel #2 read about 10 9 Amps, approximately 100 times the normal !
observed shutdown reading. Noted that Channels #1 and 3 indicated normal shutdown readings. Subsequently, replaced tubes V17 and V15.
(n) 03 DEC 86 During a prestartup check, Channel #2 Low Level Interlock failed.
(o) 12 DEC 86 Replaced transistor O1, silicon control rectifier SCR1, and diode D1 in the API Optical Meter Relay control module for Channel #2.
(p) 16 DEC 86 Replaced original transistor Q1, and replaced silicon control rectifier SCR1, resistor R6, and capacitor C3 in the API Optical Meter Relay control module for Channel
- 2. The trip was verified to be operable by shorting the two pins B and C from the output of the meter. This indicated that the optical trip on the meter face had failed.
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(q) 18 DEC 86 Deenergized the reactor console.
(r) 20 JAN 87 Reenergized the reactor console, and noted that a Low i Level Channel #1 Interlock was obtained. Ensured that the startup source was incerted in the reactor by i checking the power level reading.
(s) 29 JAN 87 Verified that the optical source for the optical trip on Channel #1 had failed.
(t) 06 FEB 87 Replaced Channel #1 meter with a Ludlum CM Contactless Meter, range 0-100 A DC, one low limit 1
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,/_, trip obtained optically. This meter is an equivalent
. replacement.
(u) 20 FEB 87- Replace Channel #2 Log Amp meter with an identical replacement: API Optical Trip Meter Model 503L, 200 A DC full scale.
(v) 27 FEB 87 During a prestartup check, the evacuation alarm failed to activate. The console was deenergized and the skirt monitor unit was examined. Discovered that a silicon control rectifier .that governed the operation of the relays had failed. Replaced SCR 2N3525 with an identical replacement.
(w) 17 MAR 87 Noted that the check infinity switch on the Channel #2 Period meter no longer performed in a momentary contact mode. The switch was replaced with a momentary contact switch of equivalent manufacture.
- 5. (a) FACILITY CHANGES No facility changes were made during this reporting period.
(b) CHANGES TO PLANS AND PROCEDURES No changes to plans or procedures were made during this reporting period.
i (c) NEW EXPERIMENTS OR TESTS No new experiments or tests were performed during this reporting period, l
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SUMMARY
OF SAFETY EVALUATIONS No changes, tests, or experiments were performed during this reporting period which meet the criteria of 10 CFR 50 paragraph 50.59 requiring a safety evaluation.
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SUMMARY
OF RADIOACTIVE EFFLUENTS RELEASED i
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No liquid or solid radioactive waste was roloased during this reporting period.
- 8. ENVIRONMENTAL RADIOLOGICAL SURVEYS No environmental radiological surveys were performed outside the facility during this report ng period.
- 9. RADIATION EXPOSURE Eight ir:dividuals received radiation exposures between 0.100 and 0.250 Rems for the calendar year 1986.
- 10. MISCELLANEOUS The following personnel participated satisfactorily in the AGN requalification program.
Evc'yn Breiner SOP-43242 David Carpenter SOP-43243 Gerald Schiapper SOP-4210 Robert Gerry OP-42171 Luis Pocaterra OP-42172 Evelyn Breiner was named Reactor Supervisor for the AGN-201M facility effective 15 September 1986.
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TEXAS. A&M NIVERSITY COLLEGE OF ENGINEERING COLLEGE STATION TEXAS 7784i-3133
' DLPARTMENT Of NUCLEAR ENGINEERING (409) 645-4161 3 August 1987 j" 2 @ $ 0W2 l'3 i ' ii i.;)
Robert Martin Ab - O !OEI 1i Regional Administrator "
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U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arilington, TX 76011
Dear Mr. Martin:
Please find enclosed the original and three copies of the most recently completed annual operating report dated 1 June 1986 to 31 May 1987 for the AGN 201M, docket no. 50-59.
If you have any questions concerning the report please call me or Dr. Gerald Schlapper at (409) 845-4161.
Sincerely, Evelyn M. B einer Reactor Supervisor, AGN-201M Nuclear Engineering Department e
COLLEGE Of ENGINEERING : TEACHING RESEARCH ~ EXTENSION
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