ML20246D529

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Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor for June 1988 - May 1989
ML20246D529
Person / Time
Site: Texas A&M University
Issue date: 05/31/1989
From: Schlapper G
TEXAS A&M UNIV., COLLEGE STATION, TX
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908280172
Download: ML20246D529 (10)
v • d • e


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TEXAS A&M UNIVERSITY.

COLLEGE OF ENGINEERING )

. COLLEGE STATION TEXAS 77843 3133 - l q

DEPARTMENT OF NUCLEAR ENGINEERI.tG

(409)S4S-4169

,i 21 Aug1989 'l y U.S. Nuclear Regulatory Commission ..

. Document Control Desk -

Washington, D. C 20555 :

REFERENCE:

License R-23,- Docket #50-59 o

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Dear Sir:

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Please find enclosed one copy of the most recently' completed annual operating report dated.1 June 1988 to 31 May 1989 for the AGN-201M reactor, Docket #50-59. If you have any questions concerning this report please contact me at (409) 845-4198. j L

r Sincerely, t

[ Gerald A. Schiapper, i

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. Reactor Supervisor (AGN-201M)

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8908280172 890531 lI PDR R

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. COLLEGE OF ENGINEERING : TEACHING RESEARCH EXTENSION

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ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 JUNE 1,1988 - MAY 31,1989

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DEPARTMENT OF NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY College Station, Texas 77743-3133 l

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ANNUAL OPERATING REPORT-
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L  : TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR-o L

NRC LICENSE R-23

' JUNE 1,1988 - MAY 31,1989 C

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. - Reviewed by Reactor Supervisor WW Reviewed by Department Head DEPARTMENT OF NUCLEAR ENGINEERING

, TEXAS A&M UNIVERSITY Ll College Station, Texas 77743-3133 e

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SUMMARY

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This report details the pertinent activties related to the Texas A&M

- Universityi AGN-201M. training facility ' operated _ by the' Department of

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4 Nuclear Engineering during the period of 1 June 1988 until 31 May 1989.

The contents'. of this report are intended to comply with _ requirements: of j

'10CFR50. section 50.59(b), and ' Appendix A of the Technical Specifications for this facility _ under' license R-23.

The. main function of 'this facility:is to provide an operating nuclear, I

system to :be used as a research tool, to support the requirements of Nuclear Engineering courses and for operator training as well a's preventive maintenance. The following Nuclear Engineering courses were supported during this reporting period:

NUEN 402 Radiation Counting Laboratory _

NUEN 405 Nuclear Engineering Reactor Experiments NUEN 685 Special Problems All of the components that were replaced as part of preventive and

- corrective ~ maintenance are detailed in Section 4 of this report. All components replaced during this reporting period do not involve any

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/ unreviewed safety questions and are; not expected to adversely affect' the.

I safe operation- of this facility. The latest results of all major parameter -

surveillance tests perfo.rmed during this reporting period.are shown in  ;

- Table 1.

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' TABLE '1 R ACTCI. PARAMETERS SURVEILLANCE MEASUREMENTS i

'DATE- REACTIVITY WORTH VALUE o

11'JAN 89 SAFETY ROD #1 1.177 %- Ak/k 11 JAN 89 SAFETY ROD #2. 1.173 % - Ak/k 1.156% -' Ak/k

~ 11' JAN 89' COARSE CONTROL ROD

e .11 JAN 89 . FINE CONTROL ROD'. 'O.355 % ' Ak/k l '
ROD DROP TIMES 31 MAY 89 SAFETY ROD #1 - 120 msec I
31. MAY 89 SAFETY ROD #2 117 msec

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31 MAY 89 COARSE CONTROL ROD 130 msec REACTIVITY INSERTION RATES 31 MAY 89 SAFETY ROD #1 0.0496 % Ak/k/sec 31.MAY 89 SAFETY ROD #2 0.0517 % Ak/k/sec 31 MAY 89 COARSE CONTROL ROD 0.0432 % Ak/k/sec

31. MAY 89 - FINE CONTROL ROD 0.0129 % Ak/k/sec TOTAL EXCESS REACTIVITY 13 JAN 89 TOTAL EXCESS REACTIVITY' O.285% Ak/k

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2. OPERATIONAL

SUMMARY

9 UTILIZATION BY CATEGORY HOURS (a) Support of Nuclear Engineering Courses 19.47 (b) Operator Training /Requalification 4.96 (c) Preventive / Corrective Maintenance 4.48 (d) Reseach Projects 36.07 Total Ooeratina Hours: 64.98 Total Hours Critical: 52.07 Total Watt-Hours of Ooeration: 19.38 Averaae Power Level of Ooeration (Watts): 00.70 Number of Reactor Startuos 76

3. UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION 7-14-88 High Level Operator error in Trainee counseled Channel #3 in switching scales 7-29-88 High Level Operator error in Operator counseled Channel #3 in switching scales 9-20-88 Period Scram Personnel moved Personnel counseled detector cables 9-29-88 Period Scram Personnel removed All cable connections monitoring equipment to remote equipment cabling. were checked and connected prior to next reactor startup.

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4. MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE

, (a) 11-1-88 Replaced the foll' awing tubes in Channel #2 with identical replacements, V-4, V-5, V-6, V-11, V-14, V-17.

(b) 5-12-89 Replaced the 1 A slow blow fuses F10,F11,F12 and F13.

The cause of their failure was improper operation of Saftey#2 Rod up limit switch.

(c) 5-31-89 Replaced Safety Rod #2 Rod up limit switch with one identical to the original. When removed from Safety Rod

  1. 2, the switch was found to have a resistance of 400 ohms rather than the normal 0 ohm resistance of a properly operating switch.
5. (a) FACILITY CHANGES No changes were made to the facility during this reporting period.

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(b) CHANGES TO PLANS AND PROCEDURES All of the facility Emergency Procedures were changed to reflect the installation of a new emergency 911 system on the campus. The Reactor Emergency Procedure (RE-1) was also changed to reflect this new emergency system. All of these changes to procedures were approved by the Reactor Safety Board on 30 March 1989.

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

6.

SUMMARY

OF SAFTEY EVALUATIONS No changes, tests or experiments were performed during this reporting period which meet the criteria of 10CFR50 paragraph 50.59 j requiring a safety evaluation.

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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 this facility during this reporting period.
9. RADIATION EXPOSURE During calender year 1988 one person's exposure was reported between 0.250 - 0.500 Rem. All of the other exposures were reported to be less than 0.100 Rem.

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10. MISCELLANEOUS The following personnel participated satisfactorily in the AGN
requalification program.

Robert Berry SOP - 43374 Gerald Schiapper SOP - 4210 Luis Pocatterra OP - 42172 Dr. Gerald Schlapper assumed the position of Reactor Supervision as of 1 August 1988.

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