ML19320D553

Annual Operations Rept of Tx A&M Univ AGN-201M Training Reactor, for June 1979-May 1980

ML19320D553
Person / Time
Site:	Texas A&M University
Issue date:	07/11/1980
From:	Cochran R, Zgliczynski J TEXAS A&M UNIV., COLLEGE STATION, TX
To:
Shared Package
ML19320D549	List: ML19320D548 ML19320D553
References
NUDOCS 8007210512
Download: ML19320D553 (9)

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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 J. B. Gglieffriski A -

l I

Reactor Supervisor I l

l Approved by: l Ori.Tir.c3 Signed By hbert G. Cochran R. G. Cochran, Head Nuclear Engineering Department

'DEFARTMENT OF NUCLEAR ENGINEERING

-Texas A&M University College Station, Texas 77843 i

l i

L.

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 l 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.

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 2/22/80 Fine Control Rod Reactivity Worth 0.35%

2f 2/18/80 Coarse Control Red Reactivity Worth 1.18% $f 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 2/18/80 Safety Rod #2 Reactivity Worth 1.16%

$f-1/17/80 Safety Rod #2 Rod Drop Time 150 msee 4/21/80 Total Excess Reactivity G20 C 0.29%

Sh

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

3

3. UNSCHEDULED SHUTDOWNS Corrective Date' . Type Cause Action 8/1/79 -Chan. #3 High Level Scram Operator Error in Switching None Meter Scales 2/5/80 Chan. #2 High Level Scram Drift of Trip Setpoint Readjust to Lower Setting Trip Setpoint 2/7/80 Lost Magn (t Current Dirty Contacts on Cleaned Shield Water Level Interlock Contacts 2/7/80 Chan. #3 High Level Scram Operator Error in None Switching Meter Scales 2/7/80 Chan. #3 Low Level Operator Error in None Interlock Switching Meter Scales 2/8/80 Lost Magnet Current DLrty contacts on Shield Water Cleaned Level Interlock Contacts 2/8/80 Chan. #3 High Level Scram Operator Error in None Switchine Meter Scales 2/12/80 Petiod Scram Instrument Noise None 2/12/80 Period Scram Instrument Noise None l

2/13/80 Chan. #3 High Level Scram Instrument Noise when None Switching Meter Scales 2/19/80. Period Scram Instrument Noise None Summary (a) Instrument Scrams 7 sb) Operator Error 4 Total Unscheduled Shutdowns 11 l 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 l

4 (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 3

replaced 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.

l

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.

w .-

6 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.

. x

. - -a. .

I a

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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