ML20212C290
| ML20212C290 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 02/25/1986 |
| From: | Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Berkow H Office of Nuclear Reactor Regulation |
| References | |
| 38-1030, NUDOCS 8703030752 | |
| Download: ML20212C290 (8) | |
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G A Technologies Inc.
PO Box 85608 SAN DiEGO. CAUFORNIA 92138 (619) 455-3000 February 25, 1987 38-1030 Mr. Herbert Berkow, Director Standardization and Special Projects Directorate Division of IHR Licensing-B U.S. Nuclear Regulatory Caraission Washington, D.C. 20555
Subject:
Facility License R-38; Docket 50-89 Subnittal of Annual Peport (3 copies)
Dear Mr. Berkow:
'Ihe following is an annual report required by the applicable Technical Specifications of GA Technologies Inc.'s (GA) Mark I TRIGA reactor (License R-38).
'Ihe present report covers the operation for the year 1986. 'Ihe numbered sections below are those referred to in Section 9.6e of the 'mchnical Specifications for the Mark I TRIGA reactor.
Part I A brief narrative sumary of (1) operating experience (including experi-ments performed), (2) changes in facility design, performance character-istics and operating procedures related to reactor safety occuring during the reporting period, and (3) results of surveillance tests and inspec-tions.
1.
'Ihe Mark I reactor was operated during the year to provide 62 pulses (10990 to 11052) and numerous steady-state irradiations for experi-ments. The operations included: activation analysis, neutron radie graphy, King furnace high-tsperature studies of reactor fuel, neerous irradiations of sanples or pieces of c@ignent, training and requalification exercises for operator trainees, and testing of cm-mercial instrumentation.
The number of samples for neutron activation analysis and radiochenistry was 1,878.
2.
No changes in facility design, perfornance characteristics, or oper-ating procedures related to safety occurred during this reporting period.
3.
'Ihe surveillance tests and inspections were performed as required by Sections 3.0, 4.0 and 5.0 of the 'mchnical Specifications.
See results are presented below.
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,. Fuel Sarveillance The fuel was inspected visually and forL bending and length changes er 29-30,1986. All elements were satisfactory.
Control Bod airveillance the visual inspection for deterioration was conducted December 30, 1986. All control rods were found to be in satisfactory condition.
Pulsina System Sirveillance The mechanical components of the pulsing ~ system (pulse control rod, air piston, lip seal, anvil, and e-1ator) were irspected, cleaned as required, lubricated, and reassembled on June 30, 1986 and December 30, 1986.
Reactor Safety Systems As specified in the Technical Specifications, channel tests.of the reactor. safety system channels, channel calibrations of the power level monitoring channels, calibration of the temperature umaanring channels, channel checks of the power-level measuring channels, and channel - checks of the fuel-element temperature measuring channels were performed.. The tests were performed at least as often. as required, and the results were satisfactory.
In no case was a required safety channel scram found to be operating outside the specified safety limits. The reactor power-level monitoring channels were calibrated at least monthly during the reporting period.The last in the year (which should have been performed in December) was delayed until the first working day of 1987 and was performed before any other reactor operation on January 5, 1987.
Five neutron detectors were checked during each of the twelve calibrations; eleven adjustments of more than 5 percent were required during the year.
The monitor and survey systems were under surveillance during the reporting period.
The frequency of calibrations was as indicated below.
Continuous Air Monitor Alarm setpounts were checked daily.
The system was calibrated semi-annually with three U-235 sources in front of the. detector (600 cts / min, 1500 cts / min, 5000 cts / min).
Eberline Area Monitors Operation was checked daily; alarms were activated in response to a source every two weeks; calibration was performed semiannually with a 4 mci Cs-137 source.
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Portable airvey Meters The I!berline B02 and R02A meters, the Luditan pancake Gt meters (Model 3),-and the IEE SN00ET (neutron) meters were calibrated seniannually in GA's calibration facility.
Part II A tabulation showing the. energy generated by the reactor. (in megawatt-p hours).
The energy generated in 1986 by the Mark I was 35,732.18 kilowatt-hours -
(25.73 megawatt-hours).
Part III The ntsaber of emergency shutdowns and inadvertent scrams, including the i
effect, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required, if any.
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.During 1986, 10 scrams occurred.. Of these, 6 were operator errors, the ranaining were inadvertent.
Of the 6 operator errors, three were by trainees. None were of major safety significanoe to the facility.
1.
2/12/86 Reg rod scranmed due to burnout of the MAGET ON liaht laQh.
f 2.
3/7/86 Percent Power #2 Scrammed.
While testing a preanplifier -
l in the IDG channel, the preanplifier failed causing the -
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REG RCD to drive out (SERVO M3)E) causing a scram at 1104 full power.
3.
3/17/86 Percent Power #2 Scram. A trainee was increasing power on a relatively short period, aiming for approximately 180 RW power level.
He didn't realize the magnitude of the lack of synnetry of the core flux due - to the control rod configuration.
The reactor scrammed on 110% on this channel but actual reactor power was less.
4.
3/26/86 Percent Power No. 2 Scram. Trainee operational error.
5.
3/27/86 Percent Power No. 1 Scram. Trainee operational error.
6.
3/28/86 Fuel Tenoerature Thermocouple No. 2 Scratuned. The top TC of fuel element 21227C failed, resulting in a reactor i
scram (fail safe operation).
- 7. -
3/28/86 Auxiliary channel (Keithlev) Scram. The operator adjusted l
the detector moving it in the wrong direction causing an abnormal increase in detector current.
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8.
4/10/86 -Percent Power m. 2 Scram.
Operator error; operator failed to cepensate for flux shifting due to rotation of the Lazy Susan sangle irradiator when the power level was close to full power (250 IGt).
9.
4/28/86 Auxiliarv Keithlev Scram. Operator error due to rotating the RANGE switch in the wrong direction.
- 10. 9/16/86 Percent Power No. 1 Scram.
Trainee operational error while approaching full power (250 IGf).
Part IV Discussion of the major maintenance operations performed during the period, including the effect (if any) on the safe operation of the reactor, and the reasons for any corrective maintenance required.
1.
1/31/86 - Replaced CAM drive motor.
Its bearings were showing signs of wear.
2.
2/6/86 Repaired broken lead to Central Transient Rod (CTR) cyclinder drive motor.
Cylinder would not drive down until after this repair.
3.
2/11/86 Repaired DOWN limit switch for CTR cylinder.
It was
- intermittent and caused -a problem in reliable firing of the rod.
Also added.a shim to the cylinder mount to correct UP light switch action.
4.
3/4/86 and 3/28/86 Readjusted the scran set points for two fuel tenperature scrams.
'Ihe set points for both had drifted downward to 200C.
' Itis is not a safety problem.
Readjusted again on 6/6/86 and 7/18/86.
5.
4/15/86 Replaced drive shaft on ventilation fan motor.
6.
4/23/86 As a preventive maintenance activity, we had two of the spare rod drive motors rebuilt.
'Ibe repaired units were returned on 4/29/86.
7.
5/17/86 Replaced a broken G4 tube (end window type) in CAM.
It was broken when the filter was changed.
It was replaced and the system recalibrated with the new tube.
8.
-6/27/86 Replaced demineralizer pump with a new one.
9.
8/17/86 Replaced the Conductivity Monitor Bridge with a spare unit. A bridge resistor opened.
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10.I8/27/86 ~ Replaced 15 volt DC Power Supply V008 'in left hand draver
'for IAG/LIN channel.
. The old power supply was misbehaving, giving negative. going spikes.
- 11. 9/8/86 Removed the obsolete air breathing attachment fra.the -
facility air ocapressor.. A leak in the moisture separator l
caused excessive cycling of the air ocapressor.
- 12. 9/16/86 Replaced shaft coupler. for the 10 HP cooling system pep motor.
- 13. 9/17/86 A corner seem opened in the welded'altanina box used in the water treatment system.
The _ corner was rewelded and returned to service.
On 11/17/86 an opposite welded seam opened.
It too. was rewelded.
Ch 1/3/87 after experiencing another leak in a corner weld, the box was completely rewelded, using angle altaninum welded over the corners in question.
- 14. 10/10/86 Console modifications.. After experiencing anall but annoying drifts in calibration points for the WIDE RANGE CHANNEL, three' mall air recirculation fans were. installed
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.to control the excessive heating of the chassis. - As a result, the internal temperature was reduced-frm a high of about 450C to a more modest 310C.. Improvement in the stability of calibrations has been observed.
- 15. 10/20/86 Recalibrated fuel temperature scram for-92 channel.
It was reading high (3800) for a real tenperature of 2500C.
A cmplete recalibration of the channel remedied the problem.
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- 16. 10/29/86 to 11/18/86 A possible water leak in the cooling system was investi-gated.
No leak in the tank has been found.
Leaks (later turned out to be pin hole leaks) were-located by sonic methods in the buried aluminum cooling lines.
The leaks were located within 6 feet of the reactor building in altanintan pipes where the bituminous and felt coverings were mitted in the original installation.
The leaks occurred only when the lines were pressurized during the cooling cycle.
For the Mark I, this cooling is required only a few minutes several times per week.
It is planned to excavate and repair the leaks early in 1987.
- 17. 12/16/86 Replaced a burned out motor in the ventilation system.
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and was replaced.
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-.h 19','12/23/86 During a reactor. tank filling operation, the operator inadvertently overfilled the tank causing water to be sucked into the CAM system. This damaged the GM detector.
It was replaced, recalibrated, and the system was dried out.-
i Part V A sunenary of each change to the facility ~ or-procedures, tests, and experiments carried out under the conditions of Section 50.59 of 10CFR50.
1.
3/11/86 Pn1=-IrraMation of anall U235 Doped Concrete Sanoles in TRIGL Mark I._ Three levels of pulses were tried, giving a predicted 50, 100, 125 cal /gm of concrete sample.. The sealed samples developed high pressures (approximately 1000 psi).
The contairunents were tested out-of-core to 1500 psi.
A procedure to handle the radioactive sanples in the Hot Cell was developed to reduce personnel doses.
The criticality Safety Otzunittee (CSC) apprwed the operation and its procedure.
2.
3/6/86 Minor annoes~in written Procedures for Mark I and Mark F:
Pa=nval of Beauirement for Physicist-in-Charae (PIC) or Associate Physicist-irM2iaroe (APIC) to Sian Daily Start-up Checklist. Reviewed and apprwed by CSC.
3.
8/29/86 Review /Acoroval of New, Dicitized Conouterized Control console System for Mark I Reactor.
Various tests of components of the new computerized console were tested under a previous 59.59.
The final series of tests were anticipated and required detailed CSC review and aprwal.
To facilitate the werall tests, the program was split j
into six phases.
The first phases progress up to operating the whole console in the READ ONLY mode.
.Then l
the phases progress into operation of only one control rod by the new console; first during reactor shutdown and 1ater during reactor operation.
Later, more control rods will be operated by the new console. In these phases, all of the safety circuits of the old console as well as the new console are active.
_ At first, the old console has ultimate control of the safety feature during these phases.
Later phases will give prime control of safety circuits to the new console.but the old console will still provide safety scram signals to the new console. Finally, all operation of the Mark I reactor will be tested from the new console.
In addition to the proposed test procedure for the new
- console, a
training and qualification program for operators was also set forth.
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Qic reviewed thoroughly the 50.59 reqtust and approved the progra subject to periodic, in-progress reviews..
PARP VI A sumary of the' nature and amount of radioactive effluents.relamaarl or
. discharged to the. environs beyond the effective. control of the licensee
~
is measured at, or prior to, the point of such release of discharge.
During the calendar year 1986,.021 curies of Argon-41 were released frm the facility to the atmosphere.
All. liquid and solid ' wastes were transferred to GA's Stet-696 licensed Waste Processing Facility for ultimate disposal.
Solid wastes are packaged and shipped to an authorized disposal. facility.
Liquid wastes are handled in a similar. manner, or anall quantities of low level liquid wastes may also be released into the u nicipal sewerage syst s within the limits and criteria specified by applicable local, state, and U.S. IRC' regulations.
PARP VII i
A description of.any enviromental surveys performed outside the facility.
'Ibere have been no significant changes to the Environmental Surve11ance Program during 1986.
PARP VIII A sunnary of radiation exposures received by facility personnel and visitors, including the dates and. time of significant a==>res, and a brief stamary of the results of radiation and contamination surveys performed within the facility.
Facility Personnel Whole Body Pvn=3res for the Year 1986:
(RDO l
Jiigh LgM Average Maber of s ployees Monitored..
17 0.700 0.000 0.321 l
Nonfacility GA Personnel Whole Body Exposures for the Year 1986:
(RDO Jiigh Lgg Averaae Immber of D ployees Monitored..
81 0.440 0.000 0.030
'Ihe majority of these exposures were received at other facilities at the GA site.
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.- ContrMor/Custer Personnel Whole Body Exposures for the Year 1986: (REM)
High JJ2E Average Nunber of Persons Monitored...
76 0.820 0.000 0.116 Visitor Whole Body Exposures for the Year 1986:
(REM)
High lag Averace tomber of Persons Monitored...
14 0.000 0.000 0.000 Routine Wipe Surveys 2
High Wipe 48 Edpn/100 an 2
Average Wipe
<25 Edgn/100 an Im Wipe
<25 edpn/100 an2 Doutine Radiation Measurements High 11 mrem /hr 0 1 foot Average 1
mRen/hr 01 foot Low 0
mrem /hr 0 1 foot Should you desire additional information concerning the above, please contact me at:
GA Technologies Inc.
ATIN: Keith E. Asnussen P. O. Box 85608 San Diego, CA 92138 Telephone (619) 455-2823 Very truly yours, Keith E. Asmussen, Manager Licensing, Safety and l
Nuclear Compliance l
KEA/mk cc: John B. Martin, U.S. NRC Region V l
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