ML19341C600
| ML19341C600 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 02/27/1981 |
| From: | Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| 38-2045, NUDOCS 8103030818 | |
| Download: ML19341C600 (7) | |
Text
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l GENERAL ATOMIC COMPANY l
PO. BOX 81008 In rep y SAN DIEGO, CALIFORNlA 92138 giq4s>>xo February 27, 1981 Refer To:
38-2045 Mr. James R. Miller, Chief Standardization and Special Frojects Branch Division of Licensing U.S. Nuclear Regulatory Connission Washington, D.C. 20555
Subject:
Facility License R-38; Docket 50-89 Submittal of Annual Report (3 copies)
Dear tk. fuller:
The following is a routine annual teport required by the applicable Techni-cal Specifications.
The present report covers the operation for the year 1980. The nunbered sections below are those referred to in Section 9.6e.
part 1 A brief narrative summary of (1) operating experience (including experiments performed), (2) changes in f acility design, performance characteristics and operating procedures related to reactor safety occurring during the report-ing period, and (3) results of surveillance tests and inspections.
1.
The Mark I reactor was operated during the year to provide 17 pulses and steady-state irradiations for nuncrous experiments.
The operations included: activation analysis, neutron radiography, King furnace high-temperature studies of reactor fuel, numerous irradiations of samples or pieces of equipnent, and training ex-ercises for operator trainees.
2.
The 15-year-old reactor console was replaced with the latest TRIGA console.
The console used since about 1965 was still operational but exhibited synptons of its age.
Several conpenents could no longer be repaired since codern replacement parts do not duplicate those used earlier. One circuit after another was rewired to ac-cept nodern repairs.
During the interval February 15 to March 1, 1980, the whole console was replaced with the latest TRICA control
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console which includes the 10-decade vide range power nonitor for E
the:LIN and LOG channels.
Complete Safety Analysis was conducted E--
and approvals obtained prior to the console exchange. A Safety Com-mittee approval was obtained for routine operation after the ex-D*
change was complete, and tests related thereto were completed.
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I James R. Miller 38-2045 The new console meets all the requirements of the Technical Speci-fications but uses different channels to meet the requirements in some cases. For instance, the two power scrams (110%) formerly were provided by the LIN channel and Percent Power channel. Now two Percent Power channels are used.
Formerly, a period scram at 3 sec period was available at the console though not required by the Technical Specifications. The new console has no provision for period scram since TRIGA reactors do not require this.
3.
The surveillance tests and inspections were performed as required by Sections 3.0, 4.0 and 5.0 of the Technical Specifications.
Some results are presented below.
Fuel Surveillance The fuel was inspected viaually and for bending and length changes on Decenber 18, 19, 1980. All elements were satisfactory.
Control Rod Surveillance The visual inspection for deterioration was performed on December 19, 1980. All rods were found to be in satisfactory condition.
Pulsing System Surveillance The mechanical components of the pulsing system (pulse control rod, air piston, lip seal, anvil, and accumulator) were inspected, cleaned as required, lubricated, and reassembled on June 19 and December 19, 1980.
Reactor Safety Systems As specified in the Technical Specifications, Channel Tests of the reactor safety system channels, Chanael Calibrations of the Power Level monitoring channels, Calibration of the Temperature neasur-ing channels, Channel Checks of the pover-level measuring channels, and Channel Checks of the fucl-cicnent temperature measuring chan-nels were performed. The tests were perforued at least as often as requireds and the results were sat isf actory.
Ir 1.
case was a required sr:ety channel scram found to be operating outside the specified safety limits. The reactor power-level monitoring chan-nels were calibrated at least monthly during the reporting period, the most recent on December 22, 1980.
Three of these monthly tests required changes in the calibration of at least one channel by an amount greater than 5% but less than 10%.
The monitor and survey systems were under surveillance during the reporting period. The frequency of calibrations was as indicated below.
James R. Miller 38-2045 Continuous Air Monitor Alarn setpoints were checked daily. The systen was calibrated semiannually with three U-235 sources in front of detector (600 cts / min,1500 cts / min, and 5500 cts /nin).
Eberline Area Monitors Operation is checked daily; alarms are activated in response to a source every two vecks; calibration is perforced semiannually with a 4 mci Cs-137 source.
Part 2 A tabulation showing the energy generated by the reactor (in megawatt hours).
The energy generated in 1980 by the thrk I was 33,066 kilowatt-hours (33.07 megawatt-hours).
Part 3 The number of emergency shutdowns and inadvertent scrams, including the ef-fect, if any, oa the safe operation of the reactor, and the reasons for any corrective maintenance required, if any.
A total of five inadvertent scrams occurred in 1980 during an esticated 1000 separate startups and operations. A list of the scrams according to cause, date, and corrective maintenance (if needed) follows.
It nay be noted that one of the five scrams occurred prinarily as a reactor operator error during an operator training session.
1.
A period scram occurred due to a noise glitch when switching from SERVO to STEADY STATE mode.
(1/16/80) 2.
Sane problem as 1.
(1/22/80) 3.
Scram from Fuel Temperature Test Circuit when operator trainee moved test switch during operation.
(3/4/80) 4.
An external scram occurred when the auxiliary console (which houses the junction for several external scrams) was noved slightly to ad-just a deck plate.
Problem was due to a monentary interruption in an external F-am wiring.
(6/4/80) 5.
A Fuel Temperature Scram was caused accidentally when one of the fuel cicnent thernocouples was disconnected from the console to i
perforn a therrocouple calibration.
On the old console this nan-cuver was correct; on the new console, this procedure will cause a scram because the console is designed to be fail safe if a thermoccuple should open during nornal operation. An alternative thernocouple calibration technique is therefore required with the new console.
(6/10/80)
I James R. Id11er 38-2045 Part 4 Discussion of the mesar maintenance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective naintenance required.
1.
As discussed above, the reactor consolo was replaced with the new-est type console. With the console change the following modifica-tions were also required.
(2/15/80 - 3/1/80)
All control rod drive assenblies had to be rewired for de a.
voltage operation for the rod position indication. The prin-cipal change herein was the fact that the old console required a 14-lead cable for the control rod drive asscebly and the new console requires 15 leads, b.
All neutron detectors were relocated and a new, fifth detec-tor (with wide range channel fission counter) was added.
The scram circuitry was altered as required for this install-c.
ation to acet the Technical Specifications requirements.
These are now met with redundancy in fuel tenperature scrans and power channel scrans through use of an auxiliary console.
2.
Safety Rod position indicator was intermittent due to slipping of a set screw on the rod position indicator drive shaft inside the Rod Drive IIcad assembly. A replacement drive unit was installed and the offending unit was sent out for repair. A flat was created on the shaft to accoenodate the set screw which was then retight-ened.
(3/2/80) 3.
The replacenent Safety Rod position indicator (see 2 above) start-ed to slip. Both units were altered by providing a flat on the shaft for the set screw.
(3/5/80) 4.
The radiation monitor for the water systen failed due to a bad in-ternal battery.
It was found on daily checkout and replaced with a spare unit.
(3/24/80) 5.
The Continuous Air Monitor (CA!!) test circuit failed and was found on daily checkout (3/31/80). The CAM was replaced by a spare unit and sent out for repair.
It was returned to service after repair on 4/22/80.
6.
The sparc radiation monitor for the water systen (see 4 above) showed a low battery conditien (4/9/80) on daily checkout. The probica was traced to the high-voltage cable that was chewed by mice or ground squirrels near the detector outside the building.
The cabic was repaired and installed inside a metal conduit to l
prevent further incursions by vild animals. The problen was cured, and this was the probable cause of the failure reported on 3/24/80 in 4 abeve.
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James R. Fuller 38-2045 7.
A fission counter and its preatp were permanently installed for the vide range channel. This replaced the units on teaporary loan from the Electronics Division.
(6/9/80) 8.
The internal battery failed for the radiation air monitor. The monitor was replaced with a spare unit.
(9/25/80) 9.
On 12/23/80 thercocouple No. 2 in instrumented fuel clonent TC2122 failed as a signal source for Fuel Temperature Channel 1.
No. 2 thercoccuple was replaced with No. 1 thermocouple in the same fuel element.
Since the console uses more than the minimum number of protective circuits, the Technical Specification requirenents were cet at all times.
Part 5 A summary of each change to the facility or procedures, tests, and experi-ments carried out under the conditions of Section 50.59 of 10 CFR 50.
l.
A 50.59 Request for Approval to Install a New Control Console for TRIGA lark I was made. An extensive Safety review was nade and approval issued to nahe the interchange and provide a set of oper-ational data from linited, nonroutino operation. The exchange was successful, and the perfornance satisfied all questions raised by the Safety Committee. A final approval was issued for routine op-eration.
(2/6/80 - 3/3/80) 2.
A 50.59 Application for Approval to Test on the TRICA Mark I an Uninterruptible Power Supply was made.
The Safety Connittee re-viewed the circunstances and issued the approval.
(6/24/80) 3.
A 50.59 Request for Approval for Unlimited Operation of the B-10 Shielded Flex-O-Rabbit Pneunatic Transfer System at Any Power Level up to and Including 250 kU.
The initial tests at higher power were conducted successfully under approval of the Safety Comnittee and final approval for unlicited operation was granted.
(7/30/80)
Part 6 A summary of the nature and amount of radioactive effluents released or dis-charged to the environs beyond the effective control of the licensee as mens-ured at or prior to the point of such release or discharge.
During the calendar year 1980, 0624 curies of Argon 41 were released from the facility to the atnosphere.
All liquid and solid wastes are transferred to GAC's SNM-696 licensed Waste Processing Facility for ultimate disposal by a licensed disposal vendor.
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James R. !! iller 38-2045 Part 7 A description of any environnental surveys performed outside the facility.
There have been no significant changes to the E:;vironmental Surveillance Program for 1980.
See reference 38-675 dated February 24, 1976, Facility License R-38; Docket 50-89, Submittal of Annual Report, Attachnent I, General Atomic Company Environmental Surveillance Program.
The results of this pro-gram are submitted in our Semiannual Effluent Report.
Par t_ _8_
A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant expcsure, and a brief summary of the results of radiation and contamination surveys performed within the fac-ility.
Facility Personnel Uhole Body Exposures for the Year 1980:
(RE:!)
Number of Employees Monitored Ilich Low Average 4
0.610 0.190 0.377 Nonfacility CAC Personnel k..oie Body Exposures for the Year 1980:
(REM)
Number of Employees Menitored Ilith Low Average 87 1.420*
0.000 0.048 Contractor Personnel Uhole Body Exposures for the Year 1980:
(PSI)
Number of Persons Monitored Iligh Low Average 49 0.250 0.000 0.032 Visitor Whole Body Exposures for the Year 1980:
(PRI)
Number of Persons Monitored Ilich Low Average 58 0.010 0.000 0.000
- Employee working in Neutron Radiography Department.
Routine Ulpe Surveys Iligh Wipe 1837 S DP:!/100 cn Average Wipe 31 S DP:I/100 cn2 i
Low Wipe
< 25 S DPM/100 cm l
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James R. Miller 38-2045 Routine Radiation ifcasurements Ifigh 90 taRem/hr at 1 foot Average
<1 mrem /hr at 1 foot Low
<1 mrem /hr at 1 foot Should you desiro additional inforcation concerning the above, please let me know.
Very truly yours, 6
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'/ d' W1111 ara R. ?!oury Licensing Administrator I;ucicar !!aterials Control Division WR21:hes cc:
R.11. Engelken, U.S.1;RC, Region V.
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