ML20151M624
| ML20151M624 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/31/1988 |
| From: | Breiner E, Poston J TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8808050259 | |
| Download: ML20151M624 (10) | |
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ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 JUNE 1,1987 - MAY 31,1988 i
DEPARTMENTOF NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77843 0
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ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR i
NRC LICENSE R-23 JUNE 1,1987 - MAY 31,1988 DEPARTMENTOF NUCLEAR ENGINEERING -
TEXAS A&M UNIVERSITY College Station, Texas 77843
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i, ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN 201M TRAINING REACTOR t
NRC LICENSE R-23 JUNE 1,1987 - MAY 31,1988 Prepared by:
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'Evelyn 6. Breiner Reactor Supervisor Approved by:
$h hn'W. P6ston, Head Nuclear Engi.neering Department s
DEPARTMENTOF NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77843
- 1.
SUMMARY
This report details the pertinent activities related to the Texas A&M University AGN-201M training facility operated by the Department of Nuclear Engineering during the period of- 1 June 1987 to 31 May 1988.
Furthermore, it is intended that the contents of this report comply with 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:
. NUEN 402 Radiation. Counting Laboratory.
NUEN 405 Nuclear Engineering Reactor Experiments 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.
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The results of all major parameter surveillance tests are shown in Table 1.
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, TABLE 1 REACTOR PARAMETERS SURVEILLANCE MEASUREMENTS DAT.E REACTIVITY WORTH VALUE 08 JAN 88 SAFETY ROD #1 1.181% Ak/k 5
08 JAN 88 SAFETY ROD #2 1.197% Ak/k 08 JAN 88 COARSE CONTROL ROD 1.171% Ak/k 08 JAN 88 FINE CONTROL ROD 0.339% Ak/k ROD DROP TIMES 06 JAN 88- SAFETY ROD #1 107 msec
, 06 JAN 88 SAFETY ROD #2 137 msec 06 JAN 88 COARSE CONTRCC ROD 130 msec REACTIVITY INSERTION RATES 08 JAN 88 SAFETY ROD #1 0.0471% Ak/k/sec 08 JAN 88 SAFETY ROD #2 0.0453% Ak/k/sec .
08 JAN 88 COARSE CONTROL ROD 0.0434% Ak/k/sec 08 JAN 88 FINE CONTROL ROD 0.0121% Ak/k/sec TOTAL EXCESS REACTIVITY 08 JAN 88 TOTAL EXCESS REACTIVITY 0.245%Ak/k COnRECTED TO 20 C
- 2. OPERATIONAL
SUMMARY
UTILIZATION BY CATEGORY: ,
F_Q)RS (a) Support of Nuclear Engineering Courses 19.93 (b) Operator Training /Requalification 08.80 (c) Preventive / Corrective Maintenance 06.79 (d) Research Projects 51.64 Total Ooeratina Hours: 87.16 Total Hours Critical: 69.54 Total Watt-hours of Ooeration: 35.67 Averaae Power Level of Ooeration (Watts): 00.69 Number of Reactor Startuos: 114
- 3. UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION G-9-87 Period Scram Sample moved too Experimentors rapidly counseled on proper procedure 7-14-87 High Level Drift in setpoint Performed C2HT to Channel #2 reset trip setpoint 9-26-87 High Level Operator error in Trainee counseled Channel #3 switching scales 3-3-88 Period Scram Spurious scram No correctivo action indicated
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- d. MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE (a) 6-29-87 Replaced a 1 A slow blow fuse in the 28 V power supply.
(b) 6-30-87 Replaced the 1 A slow blow fuses F10, F11, and F13 -
associated with the rod drive motors. The cause of the fuse failure was determined to be slack in the rod drive chain.
(c) 7-14-87 Drift in the high trip set point on Channel #2 resulted in an unscheduled shutdown during operation at 5 W.
The trip set point was readjusted according to standard maintainance procedures.
(d) 8-10-87 Replaced tubes V17 and V14 in Channel #2 with identical replacements.
(e) 1-13-88 Replaced the 10-7 calibration potentiometer on Channel
- 2 with an equivalent potentiometer.
- 5. (a) FACILITY CHANGES On 11-23-87, Channels #2 and #3 power supplies were replaced with variable voltage power supplies with regulated voltage output of 0-3000 VOC. The power suppUes are considered to be an upgrade over the previously used set' voltage power supplies. This- facility change was reviewed and approved by the Reactor Safety Board on 1-29-88.
(b) CHANGES TO PLANS AND PROCEDURES The facility Security Plan was updated to reflect the completion of several projects which had not been completed at the time of the previous version of the Security Plan. In addition, the preventive n1aintenance procedures EPEX and EVAC which test the Emergency Plan were updated to reference the most recent version of the Emergency Plan, and the preventive maintenance procedures CH1P, CH2P, and CH3P were char.ged to l
incorporate the facility change indicated in section 5(a).
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, ' (c) NEW EXPERI'MENTS OR TESTS No new experiments or tests were performed during this reporting period.
- 6.
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.
- 7.
SUMMARY
OF RADIOACTIVE EFFLUENTS RELEASED No liquid or solid radioactive waste was released during this reporting period.
- 8. ENVIRONMENTAL RADIOLOGICAL SURVEYS No environmental radiological surveys were performed outside the facility during this reporting period.
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, 9. RADIATION EXPOSURE l
No radiation exposures greater than 0.100 Rem were reported during the calendar year 1987.
- 10. MISCELLANEOUS The following personnel participated satisfactorily in the AGN requalification program.
l Robert Berry SOP-43374 Evelyn Breiner SOP-43242 Gerald Schlapper SOP-4210 l
Luis Pocaterra OP-42172 l
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o TEXAS A&M UNIVERSITY COLLEGE OF ENGINEERING COLLEGE STATION TEXA5 77843 3133 4^
OEPARTMENT OF NUCLEAR ENGINEERING (4091845 410t 28 July 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
REFERENCE:
License R-23, Docket 50-59
Dear Sir:
Please find enclosed one copy of the most recently completed annual operating report dated 1 June 1987 to 31 May 1988 for the AGN-20lM reactor, Docket 50-59.
If you have any questions concerning this report please contact Dr. Gerald Schlapper at (409)845-4161.
, Sincerely, b<4:m. L Evelyn M. Breiner Reactor Supervisor l
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COLLEGE OF EN0iNitMING : TEACHING + MtStancu . EXTENSION
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