ML19246A522
| ML19246A522 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 06/21/1979 |
| From: | Cochran R TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19246A523 | List: |
| References | |
| NUDOCS 7907030247 | |
| Download: ML19246A522 (1) | |
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T E X A.,
A&M U N I V E ll S IT Y
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COLLEGE OF ENGINEERING uw,t o m,os u..s 7,e43 i
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- --- - J ciran tvent or s u c t is p i s cir c rair a June 21, 1979 713 - E 4 5 -- 4161 Mr. Robert W. Reid, Chie f Operating Reactors Branch #4 Division of Operating Reactors Nuclear Regulatory Commission Washington, D. C. 20555 Re: License R-23
Dear Mr. Reid:
Attached are three (3) copies of our 1978-79 Operations Report for the AGS-201M Training heactor - License R-23.
If additional information is needed, please advise.
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'f <_. (f!C, R. G. Cochran, Head Nuclear Engineering Department Texas AD1 University College Station, Texas 77843 Enclosures 274 128c 24
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ANNUAL OPERATIONS REPORT of the TEXAS Afst UNIVERSITY AGN-20lM TRAINING REACTOR NRC LICENSE R-23 J ale 1, 1978
'hy 31, 1979 274 130 7a0703ngy7 g
I ANNUAL OPERATIONS REPORT of the TEXAS Afd! UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 June 1, 1978 - bby 31, 1979 Prepared by:
k-f J. B. ZgMczyn&V Reactor Supervisor Approved By:
W R. G. Cochran, Heaci Nuclear Engineering Department DEPARThENT OF NUCLEA' ENGINEERING Texas AliM University College Station, Texas 77843 4 ** **
1 1.
S M L\\RY This report details the pertinent activities related to the Texas ASM University AGN-201M training reactor facility operated by the Department of Nuclear Engineering during the period June 1, 1978 to May 31, 1979.
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 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 perfomed 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 perfomed 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 perfomed during this reporting period were nominal. A summary of various reactor parameter surveillance measurements are shown in Table I.
TABLE I.
REACTOR PARMITER SURVEILLANCE FL\\SUREMENTS Date Paraueter Value sk 2/8/79 Fine Control Rod Reactivity h' orth 0.38% j 2/7/79 Coarse Control Rod Reactivity h' orth 1.20%
1/18/79 Coarse Control Rod Drop Tiue 140 msec h
2/7/79 Safety Rod #1 Reactivity Worth 1.18%
1/18/75 Safety Rod #1 Rod Drop Time 150 msec 2/7/79 Safety Rod #2 Reactivity h' orth 1.18%
1/18/79 Safety Rod #2 Rod Drop Time 140 msec 4/30/79 Total Excess Reactivity @20 C 0.34%
2.
OPERATIONAL SUbM\\RY Utilization by Category:
(a)
Support of Nuclear Engineering Cources 77.20 hrs.
(b) Operator Training
.98 hrs.
(c)
Preventive Maintenance 16.73 hrs.
Total Operating flours 94.91 Total h'att - Hours of Operation 97.44 watt-hrs.
Average Power Level of Operation 1.03 watts Number of Reactor Startups 114 i
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3 3.
UNSOIEDULED SillRD0hNS J
Date Type Cause Corrective Action 6/16/73 Period Scram Signal Noise None 6/16/78 Lost Magnet Current Dirty Contacts on Shield Cleaned Water Level Interlock Contacts 1/12/79 Lost Magnet Current Dirty Contacts on Shield Cleaned Water Level Interlock Contacts 2/13/79 Chan. #3 liigh Level Operator Error in Scram Switching Meter Scales None 2/16/79 Chan. #3 liigh 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 liigh Level Operator Error in Scram Switching Meter Scales None Sumary (a)
Instnnnent Scrams 4
(b) Operator Error 3
Total thischeduled Shutdowns 7 4.
CCRRECTIVE MAINTENANCE AND COMPONENT REPLACEMENT Corrective maintenance and component replacement perfomed as normal maintenance of the Texas ASM University AGN-201M reactor and instrumentation 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 normal control rod inspection.
(b) 7/13/78 - Coarse Control Rod " carriage down" microswitch found defective and was replaced during nonnal control rod inspection.
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4 (c) 7/20/78 - Coarse Control Rod drive switch noise suppression capacitor failed and was replaced.
J (d) 7/24/78 - Channel #2, Log N Channel, vacuum tubes V-5, V-6, and V-14 replaced.
(c) 9/11/78 - Safety Rod #1 " rod down" microswitch found defective and was replaced.
(f) 12/24/78 - Channel #2, Log N Channel, chassis power transfomer burned out. Subsequent investigation showed that a cathode to filament short in vacuum tube V-12 (6Bh'4) probably caused a high current in the chassis power transformer filament windings leading to overheating and burn out of the trans fomer. On 1/5/79 - vacuum tube V-12 and the chassis power transformer were replaced.
(g) 1/5/79 - Clumnel #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 h'ater 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 S G NIM bin replaced with equivalent Tennelec NIM bin power supply.
274 134
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 description of the facility as submitted in the license application and amendments thereto.
5.
(a) REACTOR FDDIFICATIONS Modifications of the Texas Afpl University A(N-201M reactor and instrument-ation perfor.'ed 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 AGN drawing 2-000 474 - A as revised.
This modification was made to decrease ripple in the D.C. outputs and to modernize the D.C. power chassis. Tests of the power supply after modifi-cation showed significant ripple reduction and much better stability under load.
This modification was presented to the Reactor Safety Board on 9/18/78 and has no safety impact.
(2) 7/13/'8 - The " rod up" microswitch mechanisms on Safety Rod fl, 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 activateo earlier, thereby preventing the rod drive carriage from jaming into the mechanical stop. Tests of this modification showed that the microswitch mechanisms operated smoothly and that the rod drive carriages coasted gently against tne stops.
This modification was presented to the Reactor Safety Board on 9/18/79 274 US
6 and has no safety impact.
(3) 10/17/78 - Leeds 6 Northrup recorder capillary pens replaced with 4
disposable marker pens. This modification has no safety impact.
Reactor modifications performed 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 amendrents thereto.
5.
(b) OIANGES TO PROCEIURES No changes to procedures were made during this reporting period.
5.
(c) NEW EXPERDIEVfS OR TESTS No new experiments or tests were perfomed during this reporting period.
6.
SU'fl\\RY OF SAFETi EVALUATIONS No changes, tests, or experiments were performed subsequent to 10 CFR 50 paragraph 50.59, during this reporting period; therefore, no safety evaluations were required.
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7.
SU?f4\\RY OF RADIOACTIVE EFFIIIE. f RELEASE V
No liquid or solid radioactive waste was released during this reporting period.
8.
ENVIRO.N?IE?TTAL RADIOLOGICAL SURVEYS No environmental radiological surveys were performed 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.
274 136
7 10.
REACFOR SAFLTY BOARD ACTIONS 9/11/78 - Dr. F. Sicilio of the Reactor Safety Board audited the AGN-201M 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.
I
- 11. MISCELLANEOUS The NRC Region IV Office of Inspection and Enforcement inspected the AGN-201M Reactor Facility on 11/7/78 with regard to physical and administrative security. No items of noncompliance were found.
The NRC Region IV office of Inspection and Enforcement made a general inspection of the AGN-201M Reactor Facility on 1/9/79 and 1/10/79. No items of noncompliance were found.
The AGN-201M reactor license, R-23, with revised Technical Specifications, was renewed by the NRC on 4/25/79 for a period of 20 years.
T 274 137
NUCLE AR REGULATORY COMMISSION IN THE M ATTER OF:
DUKE PCNER CO)DA2PI (Oconee-McGuire)
Dccket No. 70-2623 Charlotte, North Carolina Place -
Wednesday, 20 June 1979 382 - 692 pag,,
Teiecnone:
(202)347-3700
.h ACE - FEDERAL REPORTERS,INC. 2 [ f j } g Og Of>icialReporters 444 Nor+h Capitel Street Washingten. D.C. 20001 g
NATIONWIDE COVERAGE - DAILY 7907030
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