ML20206P518
| ML20206P518 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/31/1986 |
| From: | Breiner E, Peddicord K, Schlapper G TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608270229 | |
| Download: ML20206P518 (12) | |
Text
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, ANNUAL OPERATING REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRA!NING REACTOR NRC LICENSE R-23 JUNE 1,1985 - MAY 31,1966 l
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l DEPARTMENT OF NUCLEAR ENGINEERING TEXAS A&M UNIVERSITY Cotiege Station, Texas 77843 L
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ANNUAL OPERATING REPORT
. of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23
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JUNE 1,1985 - MAY 31,1986 Prepared by:
/ N Evelyn K{. Breine'r Reactor Operator Reviewed by:
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] Gerald A. Schlappe'r'
]. Acting Reactor Superisor Approved by:
62an*Y Nb ca h i
K[nneth L. Peddicord, Head Nuclear Engineering Dept.
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DEPARTMENTOFNUCLEAR ENGINEERING
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TEXAS A&M UNIVERSITY College Station, Texas 77843 4
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- 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 1985 to 31 May 1986.
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 licence R-23.
- The utilization of this facility continues to be similar to - that of r
previous years. The general categories of utilization for this past year '
were support of Nuclear Engineering courses, operator training, and preventive maintenance. Nuclear Engineering courses supported during the past year were:
NUEN 405 Nuclear Engineering Reactor Experiments NUEN 606 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 i
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advorsely affcct the safo operation of this facility.
A facility modification was performed this year. It involved removing the original float water level detector and rsplacing it with a new float and magnetic reed switch assembly. The change was reviewed and approved by the Reactor Safety Board. This modification is 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 SURVE!LLANCE MEASUREMENTS DATE REACTIVITY WORTH VALUE 16 JAN 86 SAFETY ROD #1 1.'171% Ak/k 16 JAN 86 SAFETY ROD #2 1.155% Ak/k 16 JAN 86 COARSE CONTROL ROD ' 123% Ak/k 16 JAN 86 FINE CONTROL FOD 0.351% Ak/k 4
ROD DROP TIMES 24 FEB 86 SAFETY ROD #1 108 msec 24 FEB 86 SAFETY ROD #2 143 msec
. 24 FEB 86 COARSE CONTROL ROD 125 msec REACTIVITY INSERTION RATES 13 JAN 86 SAFETY ROD #1 0.044% Ak/k/sec 13 JAN 86 . SAFETY ROD #2 0.045% Ak/k/sec 13 JAN 86 COARSE CONTROL ROD 0.037% Ak/k/sec 13 JAN 86 FINE CONTROL ROD 0.011% Ak/k/sec TOTAL EXCESS REACTIVITY 16 JAN 86 TOTAL EXCESS REACTIVITY 0.275% Ak/k CORRECTED TO 20 C
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- 2. OPERATIONAL
SUMMARY
1 UTILIZATION BY CATEGORY: HOURS (a) Support of Nuclear Engineering Courses 34.05 (b) Operator Training 10.02 (c) Preventive / Corrective Maintenance 03.37 Total Ooeratino Hours: 47.43 Total Hours Critical: 33.62 Total Watt-hours of Ooeration: 25.51
. Averaae Power Level of Ooeration (Wattsk 00.73
. Number of Reactor Startuos: 85
- 3. UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION 17 JUN 85 - Scram Hi Level Operator Trainee Reinstruct Student Channel 3 Error in Switching Operator Ranges 24 OCT 85 Low Level Failure of Water Added Filtering to Shield Water Level Detector Circuit interlock Integrated Circuit 29 OCT 85 Low Level Failure of Water ~ Changed Power Source Shield Water Level Detector to independant Supply
, Interlock Integrated Circuit
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19 NOV 85 Low Leval Failuro of Water Changed Detector Shield Water Level Datoctor Design to Magnetic interlock - . Integrated Circuit Reed Switch / Float 06 Feb 86 Scram Hi Level Operator Trainee Reinstruct Student Channel 3 Error in Switching Operator Ranges 11 FEB 86 Low Level Operator Trainee Reinstruct Student Channel 3 Error in Switching Operator Interlock Ranges 27 FEB 86 Scram Hi Level Operator Trainee Reinstruct Student Channel 3 Error in Switching Operator Ranges j
03 APR 86 _ Scram Hi Level Operator Error in Operator Counseled Channel 3' Switching Ranges 10 APR 86 Rod Drop Safety Frobable Cause is Restricted rpm to Rod 2 Vibration from . Prevent Reoccurence i-Motor on Oscil-l lator (Occurred at about 2000 rpm)
- 4. MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE i
(a) 17 OCT 85 The existing water level detector float assembly was removed.
(b) 01 NOV 85 During testing of the new water level detector, Safety rod #2 jammed at its upper limit while on the test stand, and binding of the rod caused the motor to fail. The rod and the carriage were mechanically unjammed, and the motor was replaced. The failure
- was attributed to the rod top limit switch (replaced 11/14/85.)
(c) 08 NOV 85 While operating all of the rods on the test stand, it was
. noted that Safety Rod # 2 started inserting l itself automatically as soon as Safety Rod #1' top limit l , switch made contact. Found that Safety Rod #2's
in-hold-out switch contacts were failed in the "in" direction. Replaced the switch with another of the same type.
(d) 14 NOV 85 Replaced the rod top limit switch cn Safety Rod #2 ,
and rep! aced Safety Rod #2's in-hold-out switch with
. a new double pole - double throw momentary on - off -
momentary on toggle switch. These switches satisfy the requirements of 10 CFR 50.59.
(e) 26 NOV 85 Replaced control rod cwitches for Safety Rod #1, the Coarse Control Rod, and the Fine Control Rod with switches of the same type as on Safety Rod #2 (11/14/85.)
(f) 13 DEC 85 Disconnected existing ground wire from the 120 VAC console power outlet. Then, the ground was reconnected to a 6 AWG solid copper wire running to an earth ground.
(g) 06 JAN 86 Replaced the rod top !imit switches for Safety Rod #1, the Coarse Control Rod, and the Fine Control Rod with switches of identical manufacture.
(h) 09 JAN 86 Installed new float / magnetic reed sv;Pch water level assembly. Previous replacement had proven to be incompatible with the system due to the noise voltage level on the ground bus.
(i)' 05 FEB 86 Installed an evacuation horn bypass beeper circuit in the upstairs graduate / lab area. Reviewed by the Reactor Safety Board during a quarterly audit on 6/12/86. Approved during Reactor Safety Board meeting of 7/31/86.
(j) 05 FEB 86 Channel 2 failed low during the prestartup checkout.
Performed inspection of the Channel 2 drawer and cleaned and resoldered several connections.
(k) 06 FEB 86 Cleaned and resoldered more connections on the Channel 2 drawer. Replaced the Mercury battery with a 1.4 V Mercury battery and recalibrated all set points; (I) 11 FEB 86 Installed an evacuation horn bypass beeper a
Replaced a blown 15 A-fuse on the circuit downstairs.
line input to the console. (The- reactor. was in a shutdown configuration when the fuse failed.)
(m) 12 FEB 86 When the Manual Scram button was depressed, all rod position indicator lights were lost. Found and replaced a blown 28 V,1 A fuse. (The fuse subsequently failed again on 13 FEB 86.)
} (n) 13 FEB 86 Attempted a reactor startup but could not insert Safety.
Rod #1. Found that fuses F 10, F 11, F 12, and F 13 had failed. The fuses were replaced and the rods were <
tested. These fuses failed due to the 28 V,1 A fuse failing on 12 FEB 86 and the subsequent attemots to
, drive the carriages out.
4 (o) 18 FEB 86 Found that a wire leading from the Fine Control Rod upper limit switch was shorted to ground. The wire was replaced and secured.' It was determined that this. ~
was the cause of the failure of the 28 V,1 A fuse.
- . (p) 21 FEB 86 Replaced the 28 V,1 A fuse. When the console was energized, the 5 A fuse for the Channel 2 filiment i,
supply failed. The fuse was replaced.
j (q) 12 MAR 86 Radiation survey was performed at several power
! levels. Indications show that operator exposure at the j console during full power (SW) operations remains
! within safe levels, t
(r) 17 MAR 86 Replaced Channel 2 period. meter with an identical ;
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meter from a spare drawer. ,
(s) 28 APR 86 Replaced the low adjust potentiometer for . Channel 1 -
I with a new 5 kn potentiometer.
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- 5. (a)- FACILITY CHANGES 1,
! Facility changes this year included replacing the shield tank water i
leval detector. The new water level detector consists of a proximity '
sensing magnetic reed switch with a : magnet activator attached to a. float '
{. assembly. When the magnet on the float drops more than about one inch below the reed switch, the switch opens, and a relay in the console
deenergizes causing the LOW LEVEL SHIELD WATER alarm and an interlock scram. Tne float assembly is attached to the inside wall of the shieki tank and is constructed from plexiglass for corrosion resistance.
(b) CHANGES TO PLANS AND PROCEDURES The maintenance procedure for testing the shield water level interlock was modified to reflect the design changes. These changes do not decrease the effectiveness of the procedure.
(c) NEW EXPERIMENTS 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 paragraoh 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.
- 9. RADIATION EXPOSURE Three individuals received radiation exposures between 0.100 and 0.250 Rems for the calendar year 1985.
- 10. MISCELLANEOUS The following personnel particip,ated satisfactorily in the AGN
requalification program.
Donald Anderson SOP-43203 Gerald Schiapper SOP-4210
Mr. Randall White resigned as Reactor Supervisor effective 15 May 1986.
Dr. Gerald Schlapper was named the Acting Reactor Supervisor for the AGN-201M facility effective 16 May 1986.
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c TEXAS A& Al UNIVE RSITY -
COLLEGE OF ENGINEERING COLLEGI STATION 1EXAS 7 841-1131 DEPARTMENT Of huCLEAR s 'ERtNG (409) 845-4161 19 August 1986 Cecil O. Thomas, Chief Standardization and Special Proj. Branch Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Thomas:
Please find enclosed five copies of the most recently completed annual operating report
@.ted 1 June 1985 to 31 May 1986 for the AGN-201M, docket no. 50-59.
If you have any questioas concerning the report please call me or Dr. Gerald Schlapper, Acting Reactor Supervisor, at (409) 845-4988 or (409) 845-4161.
Sincerely, 4( . _. --
Evelyn M. Breiner Reactor Operator, AGN-201M Nuclear Engineering Department 0
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COLLEGE OF ENGINEERING : TEACHING = RESEARCH . EXTENSION A