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ANNUAL OPERATIONS REPORT
of the
TEXAS-A&M UNIVERSITY AGN-20lM TRAINING REACTOR"
NRC LICENSE R-23,
June 1, 1979 - May 31, 1980
.~
i
Prepared by:
Afb f A -
|J. B. Gglieffriski I
Reactor Supervisor I|
|Approved by: |
Ori.Tir.c3 Signed Byhbert G. Cochran
R. G. Cochran, HeadNuclear Engineering Department
'DEFARTMENT OF NUCLEAR ENGINEERING
-Texas A&M UniversityCollege Station, Texas 77843
i
|i
L.
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l .- SUMMARY
This report details the pertinent activities related to the Texas A&M
University AGN-20lM training reactor facility operated by the Depa'rtment of
Nuclear Engineering during the period June 1, 1979 to May 31, 1980. Futhermore,
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:
ENGR 101 Engineering Analysis |
NL 405 Nuclear Engineering Experiments !-
l
NE -679 Practical Applications of Radiological Safety I..
Several modifications of facility hardware were made during this reporting
perica to improve system performance. 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 normal 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 .
ofthishacility.
.
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2.
.
The results of all major surveillance tests and inspections performed
during this reporting period were nominal. A summary of various reactor
parameter surveillance measurements are shown in Table I.
TABLE'I. REACTOR PARAAETER SURVEILLANCE MEA 9UREMENTS
Date Parameter Value
2f2/22/80 Fine Control Rod Reactivity Worth 0.35%
$f2/18/80 Coarse Control Red Reactivity Worth 1.18%
1/18/80 Coarse Control Rod Drop Time 140 msee
2/18/80 Safety Rod #1 Reactivity Worth 1.16% S
1/17/80 Safety Rod #1 Rod Drop Time 140 msee
$f-2/18/80 Safety Rod #2 Reactivity Worth 1.16%-
1/17/80 Safety Rod #2 Rod Drop Time 150 msee
Sh4/21/80 Total Excess Reactivity G20 C 0.29%
2. OPERATIONAL SUMMARY
Utilization by Category:
(a) Support of Nuclear Engineering Courses 61.93 hrs.
(b) Operator Training .77 hrs.
(c) Preventive Maintenance 8.69 Hrs.
Total Operating Hours 71.39 Hrs.
, Total Watt - Hours of Operation 61.24 watt-hrs.
Ayerage Power' Level of Operation .86 watts
Number of Reactor Startups 102
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3. UNSCHEDULED SHUTDOWNS
CorrectiveDate' . Type Cause Action
8/1/79 -Chan. #3 High Level Scram Operator Error in Switching NoneMeter Scales
2/5/80 Chan. #2 High Level Scram Drift of Trip Setpoint Readjustto Lower Setting Trip Setpoint
2/7/80 Lost Magn (t Current Dirty Contacts on CleanedShield Water Level Interlock Contacts
2/7/80 Chan. #3 High Level Scram Operator Error in NoneSwitching Meter Scales
2/7/80 Chan. #3 Low Level Operator Error in NoneInterlock Switching Meter Scales
2/8/80 Lost Magnet Current DLrty contacts on Shield Water CleanedLevel Interlock Contacts
2/8/80 Chan. #3 High Level Scram Operator Error in NoneSwitchine Meter Scales
2/12/80 Petiod Scram Instrument Noise None
2/12/80 Period Scram Instrument Noise None|
2/13/80 Chan. #3 High Level Scram Instrument Noise when NoneSwitching Meter Scales
2/19/80. Period Scram Instrument Noise None
Summary
(a) Instrument Scrams 7
sb) Operator Error 4
Total Unscheduled Shutdowns 11 |1
l
-4 CORRECTIVE MAINTENANCE AND COMPONENT REPLACEMENT
Corrective maintenance and component replacement performed as normal
maintenance of the Texas A&M University AGN-20.111 reactor and instrumentation
during this reporting period are summarized as follows:
I
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_ - _ - _ . _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
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.
(a) 7/2/79. - Channel #2,' Log' N Channel, vacuum tubes V 4(6CB6), V-5
(6CB6), and V-ll.(6C4) replaced.
(b) 7/5/79'- Channel #1, High voltage _ power supply failed. High
voltage' power supply replaced with equivalent unit. .
(c)- 7/26/79 - Replaced " Rod Down" microswitches on safety rods #1
and #2 and coarse control rod with equivalent items.
(d) 8/6/79 -Channel #1, Log count rate channel, high voltage power supply
failed.- High voltage power supply replaced with equivalent unit.
(e) 8/6/79 - Channel #1, Log count rate channel, Hamner NB-14 Preamp,
replaced with equivalent item.
(f) 9/13/79 - Channel #1, Log count rate channel, high voltage power
supply failed. Righ voltage power supply replaced with equivalent
unit . .
(g) 12/17/79 - Channel #1, log count rate channel,high voltage power~_
supply failed and was repaired.
(h) 1/14/80 - Channel #2 - Log N channel, vacuum tube V-11(6C4) replaced.
(1) 2/1/80'- Fine control drive motor armature found to have lower
than normal resistance. Replaced fine control rod drive motor with
equivalent item.
(j) 2/7/80 - Channel #1, Log count rate channel, high voltage power
supply failed. High voltage power supply replaced with equivalent
unit.
(k) 2/7/80 - Channel #1, Log count rate channel, BF detector replaced3
with equivalent item.
(1) 2/12/80 - Channel #1, Log count rate channel, high voltage power supply'
replaced with never model unit.
'
(m). 2/12/80 - Channel #1, Log count rate channel linear amplifier
. replaced wich' equivalent item.
L.
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5
(n) 2/12/80 Reworked shield water, level switch contacts.
(o) 4/21/80 - Channel #2, Log N channel, vacuum tubes V4 (6CD6), VS(6CB6),
V7(6AV6), V10(12AU7), V14(12AX7), and V17(12AX7) replaced.
(p) 5/2/80 - Channel #2, log N channel, vacuum tube V12(6BW4) replaced.
The corrective maintenance and component replacement performed during this
reporting perioh have no impa'ct 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 MODIFICATIONS
Modifications of the Texas A&M Univers4.ty AGN-20lM reactor and instru-
mentation performed during this reporting period are detailed as follows:
(1) 7/26/79 " Rod Down" microswitch mechanisms were modified to
_activate from the siae of the control rod flange rather than
from the bottom of the flange. This modification was designed
to prevent en7 trol rod scram force from damaging the micro-
switches. -Th a modification was reviewed and approved by the
Reactor Safety Board on 7/23/79.
(2) 3/10/80 - Added "on - off' switch to channel #1 audio output
speaker.
(3) 5/22/S0 - Added 5 amp fuse to channel #2 Log N channel 6.3V
filament circuit. .This modification was designed to prevent
filament transformer overheating in the event of tube filament
short.'
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
amendments thereto.
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5.. (b). CHANGES TO PROCEDURES
(1) Revised Preventive Maintenance Procedures were approved by the
Reactor Safety Board on 10/16/79. These revised procedures
provide much more detailed instructions for performing
preventive maintenance.
(2) Revised Emergency Procedures were approved by the Reactor
Safety Board on 3/7/80. These revised procedures comply with
ANS 15.6 and NRC Regulatory Guide J.6 guidelines.
5. (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 subsequent to 10 CFR
50 paragraph 50.59, during this reporting period; therefore, no safety,
evaluations were required.
7. SUMMARY OF RADIOACTIVE EFFLUENT RELEASE
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 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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. x. - -a. .
Ia
10. REACTOR-SAFETY BOARD ACTIONS
(a) Reactor Safety Board members performed periodic audits of the
AGN-20lM Reactor Facility on 6/19/79, 9/20/79,12/20/79, and
3/27/80. No -items of non-compliance were identified.
(b) 7/23/79 - Reactor Safety Board approved " Rod Down" microswitch
modification.
(c) 10/16/79 - Reactor Safety Board approved revised AGN-20lM Preventive
Maintenance Procedures.
'(d) 1/30/80 - Reactor Safety Board reviewed AGN-20lM Reactor Facility
Security Plan.
(e) 3/7/80 - Reactor Safety Board approved revised AGN-20lM Reactor
Facility Emergency Procedures.
-- 11. MISCELLANEOUS'l
(a) 8/9 - 8/10/79 - Mr. M.B. Weinstein of American Nuclear Insurers
inspected the Texas A&M University AGN-20lM Reactor Facility. No
items of safety violation were identified.
(b) 10/2 - 10/3/79 - Mr. B. Brock , Mr. Y. Kobosi, and Mr. A. Wieder
inspected the Texas A&M University AGN-20lM Reactor Facility for
compliance with 10 CFR 70. No items of non-compliance were identified.
(c) 3/5 - 3/6/80 - Mr. G. L. Constable, Mr. S.R. Dean, and Mr. J.W. Craig
of the NRC Inspection and Enforcement staff performed a general
inspection of the Texas AEH University AGN-20lM Reactor Facility.
No. items of non-compliance were identified.
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