ML19241A711
| ML19241A711 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/31/1979 |
| From: | Zgliczynski J TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | |
| Shared Package | |
| ML19241A708 | List: |
| References | |
| NUDOCS 7907090317 | |
| Download: ML19241A711 (9) | |
Text
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ANNUAL OPERATIONS REPORT of the TEXAS ASM UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 June 1, 1978 - hhy 31, 1979 Prepared by:
Ad-fW' J. B. ZgMc::ynsky Reactor Supervisor Approved By:
,I u R. G..Cochran, Head Nuclear Engineering Department DEPARTMENT OF NUCLEAR ENGINEERING Texas A6M University College Station, Texas 77843 309 099 7907090 3/7 ?
/a '
1
- 1. SU5f4\RY This report details the pertinent activities related to the Texas Afd!
University AGN-20DI training reactor facility operated by the Department of Nuclear Engineering during the period June 1,1978 to May 31,1979. Furthemore, it is intended that the contents of this report comply wich the requirements of 10 CFR 50, Section 50.59 (b) and Appendix A, Technical Specifications, of NRC 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, and preventive maintenance.
Nuclear Engineering courses supported during the past year were:
NE 402 Nuclear Detection and Isotope Technology Laboratory NE 405 Nuclear Engineering Experiments -
NE 485 Problems NE 679 Practical Applications of Radiological Safety I Several modifications of facility hardware were made during this reporting period to improve system perfomance. These modifications are described in detail in Section 5. (a.) . None of the modifications performed change the facility description or performance as described in the safety analysis report or technical specifications.
During nomal preventive maintenance, malfunctioning components were replaced as detailed in Section 4. Facility modifications and component replacement performed during this reporting period do not involve unreviewed safety questions and are not expected to adversely affect the safe operation of this facility.
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2 The results of all major surveillance tests and inspections perfonned during this reporting period were nominal. A summary of various reactor parameter curveillance measurements are shown in Table I.
TABLE I. REACTOR PARAh!ETER SURVEILLANCE >!EASURBIENTS Date Paraueter Value 2/8/79 Fine (.cntrol Rod Reactivity Worth 0.38%
h ak 2/7/79 Coarse Control Rod Reactivity North 1.20% y 1/18/79 Coarse Control Rod Drop Time 140 msec 2/7/79 Safety Rod #1 Reactivity Worth 1.18%
1/18/79 Safety Rod #1 Rod Drop Time 150 msec 2/7/79 Safety Rod #2 Reactivity Worth 1.18%
h 1/18/79 Safety Rod #2 Rod Drop Time 140 mscc
^k 4/30/79 Total Excess Reactivity @20 C 0.34% y
- 2. OPERATIONAL SLM!ARY Utili::ation by Category:
(a) Support of Nuclear Engineering Courses 77.20 hrs.
(b) Operator Training .98 hrs.
(c) Preventive >!aintenance 16.73 hrs.
Total Operating flours 94.91 Total Watt - Hours of Ooeration 97.44 watt-hrs.
Average Power Level of Oneration 1.03 watts Nt=ber of Reactor Startuos 114 309 101
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- 3. UNSOIEDULED SIUrD0hSS Date Type Cause Corrective Action 6/16/73 Period Scram Signal Noise None 6/16/78 Lost bbgnet Current Dirty Contacts on Shield Cleaned Water Level Interlock Contacts 1/12/79 Lost 3bgnet Current Dirty Contacts on Shield Cleaned Water Level Interlock Contacts 2/13/79 Chan.13 Ifigh Level Operator Error in Scram Switching Meter Scales None 2/16/79 Chan. #3 fligh Level Operator Error in Scram Switching Meter Scales None 2/28/79 Period Scram Source Driven in at Subcritical Source Level None 3/21/79 Chan. #3 fligh Level Operator Error in Scram Switching Meter Scales None Sumarv (a) Instmuent Scrams 4 (b) Operator Error 3 Total Unscheduled Shutdowns 7 4 CORRECTIVE MAI.F"\NCE NiD COMPONEST REPLACEMENT Corrective maintenance and component replacement perfomed as nomal maintenance of the Texas A6M University AGN-201M reactor and instmmentation during this reporting period are sumarized as follows:
(a) 7/11/78 - Safety Rod #2 " rod up" and " engaged" microswitches found defective and were replaced during nomal control rod inspection.
(b) 7/13/78 - Coarse Control Rod " carriage down" microswitch found defective and was replaced during nomal control rod inspection.
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4 (c) 7/20/78 - Coarse Control Rod drive switch noise suppression capacitor failed and was replaced.
(d) 7/24/78 - Channel # 2, Log N Channel, vacuum tubes V-5, V-6, and V-14 replaced.
(e) 9/11/78 - Safety Rod 81 " rod down" reicroswitch found defective and was replaced.
(f) 12/24/78 - Channel #2, Log N Channel, chassis power transfomer bumed out. Subsequent investigation showed that a cathede to filament short in vacuum tube V-12 (6BW4) probably caused a high current in the chassis power transformer filament windings leading to overheating and bum out of the trans fomer. On 1/5/79 - vacuum tube V-12 and the chassis power transformer were replaced.
(g) 1/5/79 - Channel #2, Log N Channel, vacuum tubes V-4, V-5, V-6, V-11, V-13, V-14, and V-17, replaced. ,
(h) 1/12/79 - Shield Water Level Interlock float switch contacts cleaned and contact tension readjusted.
(i) 2/5/79 - Coarse Control Rod drive switch noise suppression capacitor failed and was replaced.
(j) 2/5/79 - Coarse Control Rod drive switch contacts were found pitted.
Drive switch was rewired to use previously unused contacts on the switch. All noise suppression capacitors on all control rod drive switches were removed.
No increase in switching noise was detectable after capacitor removal.
(k) 5/24/79 - Channel #1, Log Count Rate Channel, EG G G NIM bin power supply - 12 VDC output failed. EG G G NIM bin replaced with equivalent Tennelec NIM bin power supply.
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5 The corrective maintenance and component replacement perfomed during this reporting period have no impact on the safe operation of the reactor facility and do not change the descriptien of the facility as submitted in the license application and amendments thereto.
- 5. (a) REACTOR .\0DIFICATIONS Modifications of the Texas AfJ1 University AGN-?.01M reactor and instrument-ation perfonned during this reporting period are detailed as follows:
(1) 6/27/78 - The original AGN 110 VDC control rod motor and 28 VDC control rod magnet power supplies were modified by replacing the original selenium stack rectifiers by solid state silicon diode rectifiers.
Also large filter capacitors were added to the 110 VDC and 28 VDC outputs.
All component changes were detailed on ACN drawing 2-000 474 - A as revised.
This modification was made to decrease ripple in the D.C. outputs and to modemize the D.C. power chassis. Tests of the power supply after modifi- .
cation showed significant ripple reduction and nuch better stability undel load.
This modification was presented to the Reactor Safety Board on 9/18/78 and has no safety impact.
(2) 7/13/78 - The "rai up" nicroswitch mechanisms on Safety Rod #1, Safety Rod #2, and the Coarse Control Rod were modified to be activated by the microswitch roller cam rather than by compressing the whole microswitch activating lever. This modification was made to avoid unnecessary wear to the microswitch and to allow the microswitch to be activated earlier, thereby preventhg the rod drive carriage from janning into the mechanical step. Tests of this nodification showed that the microswitch mechanisms operated smoothly and that the rod drive carriages coasted gently against the stops.
This modification was presented to the Reactor Safety Board on 9/18/79 309 104
6 and has no safety impact.
(3) 10/17/78 - Leeds 5 Northnip recorder capillary pens replaced with disposable marker pens. This modification has no safety impact.
Reactor modifications perfomed during this reporting period have no impact on the safe operation of the reactor facility and do not change the description of the facility as submitted in the license application and amend:rnts thereto.
- 5. (b) WANGES TO PROCEDURES No changes to procedures were made during this reporting period.
- 5. (c) NEW EXPERDENTS OR TESTS No new experiments or tests were perfomed during this reporting period.
- 6. SU.'IRRY OF SAFEU EVALUATIONS No changes, tests, or experiments were perfomed subsequent to 10 CFR 50 paragraph 50.59, during this reporting period; therefore, no safety evaluation,s .
were required.
- 7. SU?4MRY OF RGICACTIVE EFFLUENT RELEASE No liquid or solid radioactive waste was released during this reporting period.
- 8. ENVIRONEEE RADIOLOGICAL SrJRVEYS No environmental radiological surveys were perfomed outside the facility during this reporting period.
- 9. RADIATION EXPOSURE No reactor facility personnel or visitors received radiation exposures greater than 100 mrem (50 mrem for persons under 18 years of age) during this reporting period.
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- 10. RE1 GOR SAFLTY BOARD AGICNS 9/11/73 - Dr. F. Sicilio of the Reactor Safety Board audited the AGN-20Dt Reactor Facility with particular attention to physical and administrative security. No discrepancies were found.
9/18/78 - The Reactor Safety Board approved the revised Technical Specifications for submittal to the NRC.
- 11. tiISGLIANECUS The NRC Region IV Office of Ir - : tion and Enforcement inspected the AGi-20H1 Reactor Facility on 11/7/78 with regard to physical and administrative security. No items of nonconpliance were found.
The NRC Region IV office of Inspection and Enforcement made a general inspection of the AGN-20D1 Reactor Facility on 1/9/79 and 1/10/79. No items of noncorpliance were found.
, The AQ -20H1 reactor license, R-23, with revised Technical Specifications, was renewed by the NPC on 4/25/79 for a period of 20 years.
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