ML20151S206

Forwards Annual Operating Rept for June 1987 - May 1988

ML20151S206
Person / Time
Site:	Texas A&M University
Issue date:	07/28/1988
From:	Breiner E TEXAS A&M UNIV., COLLEGE STATION, TX
To:	Chaney H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 8808150102
Download: ML20151S206 (1)

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$ @ M DW LE TEXAS A&M UNIVERSITY COLLEGE OF ENGINEERING E 2 19 %

COLLEGE STATION TEXAS 7 843 3133 p OEPARTVENT 0.~ NVCLEAR ENGINE (RoNG H09,1845 4161 28 July 1988 Harold Chaney U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arilington, TX 76011

REFERENCE:

License R-23, Docket 50-59

Dear Mr. Chaney:

Please find enclosed one copy of the most recently completed annual operating report dated 1 June 1987 to 31 May 1988 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.

1 Sincerely,

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Evelyn M. Breiner Reactor Supervisor, AGN 201M l Nuclear Engineering Department l l

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1 ANNUAL OPERATING REPORT l

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TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR  ;

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l NRC LICENSE R-23 JUNE 1,1987 - M AY 31,1988 DEPARTMENT OF. NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY -

College Station, Texas 77843 4

ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 JUNE 1,1987 - MAY 31,1988 1

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DEPARTMENTOFNUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77843

ANNUALOPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 JUNE 1,1987 - MAY 31,1988 Prepared by:

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'Evelyn . Breiner Reactor Supervisor Approved by:

~'ms hn W. P6ston, Head Nuclear Engineering Department DEPARTMENTOFNUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77843 ,.

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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. l l

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, i and preven'ive t maintenance. Nuclear Engineering courses supported during i

4 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 1

DATE REACTIVITY WORTH VALUE I

08 JAN 88 SAFETY ROD #1 1.181% Ak/k '

08 JAN 88 SAFETY ROD #2 1.197% Ak/k l 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 CONTROL 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 l

08 JAN 88 FINE CONTROL ROD 0.0121% Ak/k/sec TOTAL EXCESS REACTIVITY l

08 JAN 88 TOTAL EXCESS REACTIVITY 0.245%Ak/k CORRECTED TO 20 C

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2. OPERATIONAL

SUMMARY

UTILIZATION BY CATEGORY: .

HOURS i 1

(a) Support of Nuclear Engineering Courses 19.93 i

(b) Operator Training /Requalification 08.80 (c) Preventive / Corrective Maintenance 06.79 1

I (d) Research Projects 51.64 l

i Total Ooeratina Hours: 87.16 l

Total Hours Critical: 69.54 i

Total Watt-hours of Ooeration: 35.67 Averaae Power Level of Ooeration (Wattsk 00.69 1

Number of Reactor Startuos: 114

3. UNSCHEDULED SHUTDOWNS DATEi TYPE CAUSE. CORRECTIVE ACTION 6-9-87 Period Scram Sample moved too- Experimentors

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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 corrective action I indicated

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.. 4. 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

1. 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 VDC. The power supplies 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 additlen, the preventive naintenance 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 changed to incorporate the facility change indicated in section 5(a).

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-(c) NEW EXPERIMENTS OR TESTS No new experiments or tests were performed during this reporting period. ,

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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 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.

9. RADIATION EXPOSURE 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.

Robert Berry SOP-43374 Evelyn Breiner SOP-43242 Gerald Schiapper SOP-4210 '

Luis Pocaterra OP-42172 l l

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