ML20094L526
| ML20094L526 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/31/1984 |
| From: | Carpenter D, Erdman C TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8408150371 | |
| Download: ML20094L526 (10) | |
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ANNUAL OPERATIONS REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 June 1, 1983 - May 31, 1984 DEPARTMENT OF WCLEAR EMINEERIM Texas A&M University College Station, Texas 77843
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ANNUAL OPERATIONS REPORT of the TEXAS A&M UNIVERSITY AGN-201M TRAINING REACTOR NRC LICENSE R-23 June 1, 1983 - May 31, 1984 i
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Prepared by:
David C. Carpentar p
Reactor Supervisor l
Approved by:
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Carl A. Erdman, Head Nuclear Engineering Department DEPARTMENT OF WCLEAR EMINEERING Texas A8M University l
l College Station, Texas 77843 l
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1.
SupWARY-This'_ report details the pertinent activities related to the Texas A&M University AGN-201M training. reactor facility operated at the Department of
-Nuclear Engineering during the period June 1 1983 to May 31, 1984.
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 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, RSO radiation safety course, preventive maintenance, and research for a masters thesis. Nuclear Engineering courses supported during the past year were:
ENGR 101G Engineering Analysis NE 402 Nuclear Detection and Isotope Technology Laboratory NE 405 Nuclear Engineering Experiments NE 485 Problems 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 of this facility.
The results of all major parameter surveillance tests are shown in Table 1.
O
.o TABLE I.
REACTOR PARAMETER SURVEILLANCE MEASUREMENTS Date Reactivity Worth Value 10 May 1984-Safety Rod #1 1.159 % 6 k/k 10 May 1984
' Safety Rod #2 1.168 % 6 k/k
- 14 May 1984
. Course Control Rod 1.166 % 6 k/k 14 May 1984 Fine Control Rod 0.353 % 6 k/k Rod Drop Times 14 May 1984 Safety Rod #1 115 msec 14 May 1984 Safety Rod #2 140 msec 14 May 1984 Course Control Rod 125 msec Avera9e Reactivity Insertion Rates 10 May 1984 Safety Rod #1 0.0484 %6 k/k/sec 10 May 1984 Safety Rod #2 0.0498 %6 k/k/sec 10 May 1984 Course Control Rod 0.0457 %6 k/k/sec 10 May 1984 Fine Control Rod 0.ul14 %6 k/k/sec Total Excess Reactivity 16 May 1984 Total Excess Reactivity 0.297 % 6 k/k Corrected to 20*C 6
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OPERATIONAL SUP91ARY
. Utilization by Category:
(a) Support of Nuclear Lab Engineering Courses 33.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (b) Reactor Operator / Senior Reactor Operating Training 6.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (c) Preventive / Corrective Maintenance 5.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (d)'SupportofResearch 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Total Operating Hours 49.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Total Operating Hours at Power 26.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Total Watt-hours of Operation 54.4 Average Power Level of Operation 2.05 watts Number of Reactor Startups 123 3.
UNSCHEDULED SHUTDOWNS DATE TYPE CAUSE CORRECTIVE ACTION 7/19/83 Hi Level Ch #2 Trip Suspect Noise Spike None - no reoccurrence of this problem.
9/2/83 Interlock Open Suspect Noise Spike Required Readjustment of reactor shield tank level switch for condition to clear.
Did not receive low level alarm - no reoccurrence.
9/15/83 Ch #2 Period Movement of source None - caution while at low power operators about potential problem when varifying criticality at low powers 9/22/83 Low Level Ch #3 Movement oi source Counsel Operator while at low power e
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. 1/31/84 Hi Level Ch #3 Possible Noise Spike None while changing scale on Ch #3 range sw 2/1/84 Hi Level Ch #3 Student Operator Reinstruct Student error in switching Operator range sw
- 2/1/84 Lo Level Ch #3 Student Operator Reinstruct Student error.in switching Operator range sw 2/2/84 Hi Level Ch #3 Student Operator Reinstruct Student
. error in switching Operator range sw 2/2/84 Hi Level Ch #3 Student Operator Reinstruct Student L
error in switching.
0perator range sw 2/2/84 Hi Level Ch #3 Student Operator Reinstruct Student error in switching Operator range sw 2/2/84 Hi Level Ch #3 Possible noise spike None-no reoccurrence while changing scale of this problem on Ch #3. range sw 2/2/84 Hi Level Ch #3 Student Operator Reinstruct Student error in switching Operator range sw 2/3/84 Hi Level Ch #3 Student Operator Reinstruct Student i
error in switching Operator range sw 2/4/84 Lo Level CH #3 Student Operator Reinstruct Student error in switching Operator range sw 2/21/84 Hi Level CH #3 Student Operator not Reinstruct Student l
monitoring Ch #3 about need for l
properly proper eye contact of all instrumentation Summary l
(a) Scrams due to Instrument Failure or Malfunction 6
(b) Scrams due to Operator Error
- 1. Due to improper selection of CH 3 range sw 7
- 2. Other 2
TOTAL UNSCHEDULED SHUTOOWNS 15 4.
CORRECTIVE MAINTENANCE AM) COMPONENT REPLACEMENT 6
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t Corrective maintenance and component replacement performed as normal' maintenance of' the Texas A&M ' University AGN-201M reactor during ~this reporting period are-summarized 'as follows-(a) 7/11/83. - Soldered " Borderline". connections on rod drive mechanisms -as part:of normal preventative maintenance.
(b) 7/27/83. - In preparation for -inspection of shield water tank (SWTI-12), movement of manhole. cover jarred level controller.. Movement caused actuator arm which appeared corroded to fall. into tank.
Level controller activator repaired and tested satisfactorily by standard
. procedure on 7/28/83.
(c) 9/29/83 - ~ Performed evacuation exercise under - supervision of RSB
~ member Dr. Hart.. Satisfactory. evaluation. Details of test on file.
(d) 11/7/83 - After ' repeated low ' level trips on CH #2 and subsequent period trips, performed check. of channel 2 electronics by approved procedure C2TC-6.. Replaced tubes V4, VS, V6, VIO, V11, V12, V14, V17.
Also replaced V15(0A2) and V16(0G3).
(e) 1/24/84,- Reoccurring spikes on CH #2 level and period instruments.
Again performed C2TC-6. Replaced V10 and V4.
(f) 2/4/84 - Sight glass.on thermal column broke loose.
All water that was above the lower sight glass connection was drained to reactor room floor.
Visual inspection verified no equipment damage and that approximately 3 feet of water still existed in thermal column.
.i (g) 3/7/84 Replaced tall thermal column with smaller one.
Placed concrete discs above reactor to seal off access port above reactor..
j The corrective maintenance and component replacement 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.
.5.
(a) REACTOR MODIFICATIONS No modifications were made to the Texas A&M University AGN-201M reactor during this reporting period.
(b) CHANGES TO PLANS AND PROCEDURES 4'
Revised C3LT-3 and C3HT-3 to reflect a more satisfactory compliance check.
It was possible to set CH #3 -high trip or low trip at a setting j
that would be offscale on the meter.
Procedure changed so that high trip could be no greater than 95% full scale on the meter. The low trip was set l
so that it would be no less than 5% full scale.
i Upon verification of how thermal column interlock interacts with rod control system, it was found to be in possible violation of amendment #5 to O
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license R-23.
By this _ amendment, if the thermal column were removed, the scram magnets were to be deenergized.
In: actuality, removal of the thermal-
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column opens the +110 VDC line to the rod drive. motors thus inducing a rod
. hold situation' as' the-annunciatori states. -
Mr.' Hal Bernard of USNRC l was informed of situation by Dr. Erdman. NE Department internal memo. prohibits criticalityL experiment RXEP-10. to be performed until matter reviewed by
'USNRC.
Revision 'of facility operating procedures that included several minor-text changes.and a complete rewrite of. section 3.2 -(Operational
. Information) and 3.3 ~(Checkout Procedure). _.First page of operations log was completely. revised to reflect a better order. of performance.
Additional steps; added which deal with the ~ testing of all alarms in the facility. Skirt monitor: checks and a test. of the rod interlock sytem were
- added ' to better document performance based on results of facility inspection of June 25, 1982.
. l Corrections to and changes in - performance frequency of preventative
- maintenance procedures.- To -reflect technical specifications, most of the PM procedures were performed on a quarterly or semiannual basis although by technical specifications they only needed to be performed annually.
(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 RADI0 ACTIVE EFFLUENT RELEASES 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 l
No' reactor ' facility personnel or visitors received radiation exposures i
greater than 100 mrem (50 mrem for persons under 18 years of age) during this reporting period.
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- 10. REACTOR SAFETY BOARD MEETINGS
.(a) 25 July 83 - Review of RSB audit.
Audits to be added to quarterly maintenance.
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l(b)'~ 28' October '83
. Review RSB audits conduc'ted 8 March,12 ' July and
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29 September 83. L Approval of changes in facility operating procedures'.
Approval : of change in --performance. frequency of preventive maintenance.
Notified 'of discrepancy in operation of. thermal. column interlock.
.(c) 30. January 83 - Annual review of security plan.
(d) 20 April 84 - Approval of modifications-to Reactor Facility subject to restrictions stated in ' memo. dated 20 April' 84.
Modifications consist of building new walls in Room.61'and rewiring of reactor console to upgrade existing cabling that has deteriorated.
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- 11. MISCELLANE0US ~
.The following personnel participated-satisfactorily in the AGN
. operator requalification program.
Carl Erdman S0P-4136
. Gerald Schlapper fS0P-4210 David Carpenter-S0P-4471 The following were - trained - for licensing and received senior reactor operator'~ licenses based on satisfactory performance - on the USNRC administered SR0 exam.
Art Flores 50P-43027 effectiv'e 3 November 1983 Randy White SOP-43026 effective 3 November 1983 Upon receiving his BS degree in Nuclear-Engineering, Mr. Carpenter was named the Reactor Supervisor for the. AGN-20iM facility.
He replaced Dr.-
Gerald Schlapper, who had served'in that capacity until a replacement could be found for Mr. Barry Willits.
C Full implementation of Emergency Plan was completed within 120 day limit of USNRC after its review and evaluation dated 24 June 1983.-
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't TEXAS A&M UNIVERSITY COLLEGE OF ENGINEERING COtt(GE STATION TEXA5 77843-3133 DEPARTMENT NUCLEAR ENGINEERING 32@ BOWS %
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Jll i i 1984 I
July 6, 1984 John Collins Regional Administrator 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012
Reference:
License No. R-23, Docket No. 50-59
Dear Sir:
Enclosed are the signed original and twelve (12) copies of the annual operating report for the period June.1,1983 to May 31,1984 for the AGN-201M Reactor Facility. Any questions concerning this report may be directed to nlyself at (409) 845-4988.
Respectfully, C
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David C. Carpenter AGN-201M Reactor Supervisor Texas A&M University DDC/sgw d't COLLEGE Of ENGINEERING TEACHING RESEARCH EXTENSION
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