ML20012A396
| ML20012A396 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 12/31/1989 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20012A394 | List: |
| References | |
| NUDOCS 9003090381 | |
| Download: ML20012A396 (23) | |
Text
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TRIGA REACTORS FACILITY j-i
-i TRIGA Mark i Reactor l
ANNUAL REPORT prepared to satisfy the requirements of U.S. Nuclear Regulatory Commission Ucense No. R-38 f
February,1990 90030903s3 9003o3 PDR ADOCK 05000099 j R
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TRIGA Reactors Facility ANNUAL REPORT TRIGA Mark i Reactor
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This report documents operation of the General Atomics (GA) TRIGA Mark I l
non-power reactor for the period January 1 - December 1989.
The Mark I re-actor - one of two reactors operated by GA at its San Diego, California facilities - is a pulsing type reactor with a licensed steady state operat-ing power of 250 kilowatts, and maximum reactivity insertions during tran-sient operations of $3.00.
It is operated by GA under 1.icense No. R-38 granted by the Nuclear Regulatory Commission (Docket No. 50-89).
This re-port is being prepared and submitted to satisfy the requirements of Section 9.6(e) of the R-38 Technical Specifications.
This report is presented in eight parts, consistent with the information required by the applicable Technical Specifications.
- 1.
SUMMARY
OF OPERATIONS.
i 1.1 Operating Experience.
The TRIGA Hark I reactor was operated during calendar year 1989 for numerous steady-state irradiations as well as pulsing operations.
The following represents a summary of reactor use during this period:
1.1.1 The reactor generated a total of 47.5 MWh of energy.
1.1.2 The reactor was pulsed 216 times, for a total of 11.719 pulses to date.
1.1.3 The reactor consumed 2.6 grams of U-235.
1.1.4 A total of 400 irradiation requests were processed during the period.
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h 1.1.5 The,re were no reportable occurrences during the period.
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1.1.6 Four applications for f acility modifications under 10CFR50.59 7
were approved and implemented.
In addition, one facility modification approved during CY1988 for the final installation of a microprocessor based instrumentation and control system.
was implemented during this reporting period.
p 1.1.7 One Spec 5a1 Experiment, to allow irradiation of lithium targets in support or the New Production Reactor program, was 7
approved and conducted during this period.
1 l1. 8 No license amendments were submitted during this period.
'i.1.9 The facility conducted a reactor operator training program for two trainees (one RO and one SRO), and one RO upgrade to SRO.
All candidates successfully passed the NRC license examination during the year.
1.1.10 The following types of operations were conducted to support the various users of the reactor:
- neutron activation analysis (2417 samples).
- radiation hardness testing of electronic piece parts and small circuits.
- neutron radiography.
- reactor fuel studies.
- testing of commercial reactor instrumentation.
- operator training for new trainees and operator requali-fication exercises.
1.2 Facility Changes and Modifications.
The major change implemented in the Mark I reactor facility in January, 1989 was the complete removal and decommissioning of the analog instrumentation and control (I&C) i
e system installed in 1980, and the installation of a microprocessor based IEC system to operate the reactor.
The installation of such a system was approved by the facility safety committee on the basis of 9
an application and supporting safety evaluation submitted by the fa-cility under 10CFR50.59.
The standard operating procedures were si-multaneously revised to reflect this change in operations.
All li-censed operators were trained and requalified on the new system as part of the changeover to the new I&C system.
Several subsequent im-provements to the system as originally installed were made during the course of the year under 10CFR50.59 applications: these changes are i
described in Section 5 of this report.
The second change of significance was the installation - also approved under a 10CFR50.59 application -
of a new continuous air monitoring (CAM) system for airborne radioactivity.
The new CAM replaces an older existing unit which was showing deteriorating detection ef fi-ciencies and was becoming very hard to maintain.
Other changes to the facility included:
- installation of new on-line conductivity and demineralizer water flow indicators and alarms.
installation of reactor pool water level (low and high) sensors with alarms.
- Complete refurbishing of the plumbing and electrical systems for the reactor pool water treatment system.
The above modifications are described further in Sections 4 and 5 of this report.
1.3 Surveillance Tests and Inspections.
Surveillance tests and inspec-tions were performed as required by Sections 3.0 (Reactor Pool), 4.0 (Reactor Core) and 5.0 (Control and Safety Systems).
A summary of the results are presented below:
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e 1.3.1 Pool Water.
The pool water was sampled on a continuous basis for conductivity using an on-line sensor. installed in the wa-ter treatment system flow. Water conductivity was maintained i
vell below the limit of 5 micro-mhos per centimeter averaged over one calendar month required by the Technical Specifica-l L
tions.
Water level sensors were installed during the reporting pe-riods this ensured that the pool water level always was main-tained at acceptable levels.
In addition, a visual check of t
pool water level was made as part of the Daily Startup Check-list.
Redundant pool water temperature monitors were used to ensure that bulk pool water temperature is maintained within accept-able limits.
1.3.2 Reactor Core.
The reactor fuel was inspected for bending and length changes, as well visually for deterioration and dam-age, during the month of December, 1989.
All elements were found to be satisf actory: however, one aluminum clad fuel element (FEi 3667)' was damaged as a result of being dropped to the bottom of the pool when attempting to place it in the fuel inspection and measurement device. The drop resulted in the bottom fitting of the element being bents it subsequently did not pass the necessary surveillance tests, and was removed from service.
It was replaced in the core by another fuel element from storage.
It is to be noted here that the older aluminum clad elements are still in use in the Mark I reactors all new TRIGA fuel now manufactured uses stainless steel clads.
1.3.3 Control Rods.
All control rods were removed from the core -
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and visually inspected for deterioration in December, 1989.
j All control rods were found to be in satisfactory condition.
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f As part of the routine control rod surveillance procedures, the central transient (pulse) rod and its mechanical compo-nents (air piston, lip seal, anvil and accumulator) were in.
t spected, cleaned and lubricated twice during the calendar F
year as part of the routine surveillance activities (June and December, 1989). During the first surveillance activity, the rod itself was replaced, as its inspection revealed an appar-ently defective weld along the top of the rod.
No deteriorae tion or undue wear were noted on the rod damper assembly it-self the assembly had been completely overhauled in 1987.
1.3.4 Reactor Safety Systems.
Surveillance and calibration of re-actor safety systems was carried out as specified in the R-38 Technical Specifications and reactor operating procedures.
The calibrations and checks on the scram functions of the mi-numum required safety system scrams were verified on a rou-tine basis, with the surveillance on power level, fuel tem-perature measuring channels and manual scram capability per-formed on a daily basis prior to reactor startup, to ensure p
that the channels are operating as intended, and that the set points for these channels are within the limits specified in i
the Technical Specifications.
A calorimetric determination of reactor power was performed monthly to verify the calibration of the three power measur-ing channels.
In conformance with reactor operating proce-dures, the calibration of the power measuring channels was considered acceptable if the deviation of the measured value from the indicated power was less than five percent: the power measuring channels were adjusted to conform to the cal-orimetric value if the deviation was greater than five per-
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cent. During the reporting period, three such adjustments to the power level channels were made.
However, it is noted that only on one of these adjustments was the deviation actu-ally greater than five percent.
For the other two on which the deviation was less than 52, the adjustments were made re-gardless because micrometer detector adjustment devices in-stalled.in 1988 now give greater precision and sensitivity in making these adjustments, which allows a more accurate indication of power level to be obtained, i
1.3.5 Radiation Monitorina.
The primary instruments utilized dur-ing the reporting period for facility radiation monitoring were a continuous beta-gamma air monitor, radiation area mon-itors, water and air filter monitors, and a variety of por-table survey meters.
Their use and calibration is described below Continuous Air Monitor (CAM).
During 1989, the continuous air monitoring system that was in use for monitoring the air above the reactor pool was upgraded with a newer system pro-cured from Ludlum Measurements, Inc.
that provides signifi-cantly higher detection efficiencies as well as reliability.
The CAM alert and alarm set points were checked on a weekly basis by activating them with a check source. Calibration of the system was performed semiannually using two Sr-90/Y-90 calibration sources with calibration traceable to the Na-tional Institute of Standards and Technology (NIST).
Two sources were used to allow calibration at low and high count rates.
Radiation Area Monitors (RAM).
Two area monitors (Eberline Instrument Corp.) were used for monitoring area radiation levels in the reactor room.
The low level monitor was used to provide an alarm when the area radiation levels exceeded e
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20 mR/h: the high level monitor alarmed at levels exceeding 100 mR/h.
The alarm set points were checked daily, with alarm testing itself performed biweekly using a check source.
Calibration was performed semiannually using a 4 mci Cs-157 source on a calibration range.
All calibrations were traceable to HIST.
Water and Air Radiation Monitors.- Separate radiation moni-tors were used to monitor the radiation levels in the reactor L
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pool water and the reactor room air ventilation system.
Their operation and alarm set points (45 mR/h and 5 mR/h) were checked daily with alarm testing performed on a weekly basis.
The monitors were calibrated on a semiannual bais.
Portable Radiation Monitors.
Several types of portable radi-ation monitors were in use at the facility.
Examples are the Eberline R02 and R02A beta-gamma survey meters, the Ludlum pancake probes, the Ludlum MicroR meter and the' LFE SNOOPY neutron survey meter.
All portable radiation monitors were calibrated on a semiannual basis.
- 2. ENERGY GENERATION 1
The total energy generated during calendar year 1989 as a result of Mark 1 operations was 47,455 kilowatt-hours.
Figure 1 is a bargraph showing reac-tor usage on a monthly basis during the year.
The significantly higher us-age during September, 1989 (11,764 kwh) reflects numerous the full power runs carried out during this month to support the irradiation of lithium targets for the New Production Reactor fuel testing program.
- 3. EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS The total number of unscheduled scrams during 1989 operations was 19.
This represents a decrease of 751 from the relatively large number of scrams ex-I p
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perienced during 1988 (82), the majority of which were associated with the g
on-going testing at that time, of the microprocessor based instrumentation and control system, as well as the large number of trainees undergoing op-erator training during CY1988.
None of the 16 scrams experienced in 1989 had any effect on, or consequence for, the safe operation of the Mark / reactor.
In fact, all safety channels functioned as L
intended in shutting down the reactor when trip setpoints were reached, or an error condition was otherwise detected in the reactor operating systems.
The causes of the scrams are grouped into the following four general categories:
Scram Channel Cause Number Power level Operator error 7
Power level Noise in signal 1
Power level Fluctuations caused by 1
samples being irradiated Power level Faulty control rod 1
drive UP switch System Computers Various communications 6
errors and watchdog time-outs.
System Computers Operator action 3
19
- 4. MAINTENANCE ACTIVITIES All maintenance activities performed during the year generally fall into three categories:
(1) routine preventative maintenance, (ii) routine cali-bration activities and (iii) ongoing upgrade activities associated with re-placement of older components and systems with state-of-the-art technology, or simply due to wear and tear from the many years of use.
Significant ac-tivities in this area are described below:
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4.1 Reactor, Mechanical and Auxiliary Systems i,
January, 1989.
Preventative maintenance and general upgrades on the central transient rod (CTR) air supply system was per-formed.
This consisted of (i) replacement of air re-ducer and water / moisture separator units. (ii) re-g placement of a leaky float valve, and (iii) relocation of the above in reactor room for ease of access.
v February, 1989. New surge suppressors were installed on CTR to replace damaged ones.
A holder for locating the startup neutron source was installed on tbs; fission chamber housing.
This holder allows the operator to obtain repeatable positioning of the startup source when moved from the core to a position adjacent to the fission chamber for perform-6 ing detector sensitivity checks during daily startup checks.
June, 1989.
A holder similiar to the above was installed along the reactor tank wall to conveniently position the source I
away from the fission chamber, as opposed to the position adjacent' to the chamber.
This position is used to reduce the neutron count rate at the chamber to a value below which the rod withdrawal prohibit in-terlock for minimum source counts could be tested.
During semiannual inspection of the CTR, an apparent weld defect was noticed on the top weld of the rod.
Upon recommendation of a mettalurgical expert, this rod (serial #1) was then removed from service and re-s placed with a spare (serial #14).
Both rods were,
c found to have approximately equal worths. At the same r'
time, the guide tube for the rod was also refurbished L
(see also Section 1.3.3).
i July, 1989.
The reactor pool water treatment system was completely r
refurbished. Nearly all of the existing aluminum pip.
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ing was replaced with PVC piping.
Valves with quick i
disconnects were installed for ease of maintenance, Power to the pump motor was routed through relay-con-g trols to allow remote control from the main operator j
l console.
l October, 1989.
Installation of a new diffuser system was completed.
This system was installed to reduce the dose effect from N-16 gammas at the surface of the water by slow-ing down the rise time of N-16 to the water surface.
The ' diffuser pump discharges water directly on top of I
the core, causing the N-16 produced to be dispersed and decay (T1/2 = 7 sec.) before it can rise to the top.
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l Rotary action on the lazy susan assembly was lost due to binding of the motor drive shaft.
The problem was l
traced to the motor shaft's gearbox cover coming loose from the gearbox, allowing the cover screws to back into the shaft. The-problem was corrected by placing l
lockwashers on each of the screws, and no internal damage was done to the gear assembly.
Further preven-tative maintenance was performed on the system by-in-stalling a new clutch assembly and complete relubrica-tion of the gearbox.
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h 4.2' Instrumentation and Control Systems l
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January, 1989.
During
- January, 1989, the existing analog instrumenation and control (IEC) system was removed from the facility, and the new microprocessor based l
ILC system, which had been under test as described t
j elsewhere in this report _and in earlier annual facility reports, was moved in place for dedicated use.
The new console under the approved test had previously been used to operate the program reactor for several months, but with the old I&C L
system left in place.
Other console functions, such l
as pit lights, pit cooling and lazy susan control, were transferred to the new console.
This installation is also described elsewhere in this report (Sections 1.2 and 5.1).
Minor modifications to the channel assembly in the new I&C system were made to correct an intermittent problem associated with ramp up to the scram setpoint during daily surveillanc testing.
The problem was traced to missing clad around an integrated circuit and was corrected.
A new microswitch actuator was fabricated and installed on the CTR to allow rod positions to be
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properly displayed on the new console.
February, 1989 Updates to the NM1000 digital wide range power channel software were installed, primarily to improve the timing associated with the prestart checks conducted l=
as part of the daily startup tests.
The Physicist-in-Charge (PIC) reviewed the change to l
ensure that no safety issues were involved.
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Under an approved 10CFR50.59 application. a ground fault detector circuit was added to test the operability of the ground fault detector which monitors for shorts to ground in the scram loop l
(Section 5.2),
A new digital pit water conductivity meter and associated probe was procured and installed in the auxiliary control console.
This change allowed the incorporation of continuous on-line conductivity monitoring and alarm features into the IEC system.
March, 1989 An additional power monitor utilizing micromicro-ammeters as detector output monitors were installed.
This channel is not part of the safety system of the reactor, and is utilized only for additional power monitoring required during specific irradiations.
A problem encountered with gain change inconsistencies-when the NPP1000 power channel was put in the pulse
- mode, was traced to a
gain change hexfet transistor /optoisolator circuit. This circuit changes the gain from high sensitivity to low sensitivity to allow data collection in pulse mode.
The component was replaced with a power hexfet coupled with a relay l-to institute this gain change when the system is put in pulse mode.
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New firmware was installed in the NM1000 wide range l-channsi to allow scram functions to be tested from the operator console with the scram test switch.
Prior to this modification, the operator was required to make this test via special commands entered on the NM1000
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5 microprocessor keyboard.
No safety issues were involved with this change.
i The computer in the control console (IBM 7532) was replaced with a newer unit (Action Instruments BC20).
This modification was to eliminate the need for an expansion chassis required with the IBH7532 computer.
9 Two uninterrupted power supplies (UPS) were installed in the supply of AC power to the IEC system.
This not only allowed clean input line power to be delivered to the system, but will allow the system to continue functioning in case of a power failure.
May, 1989 Updates to the operating sof tware were installed on-the two system computers.
These updates only concerned console features such as operator log on andoperating data, and the ability to clear data errors from the reset keyswitch.
No safety issues were associated with this change.
Current revisions to the NP1000 and NPP1000 and power channel circuitry were installed.
The revisions included changing a component in the channel prestart test circuit to eliminate problems when running L
prestart checks, encountered when the units heated up with prolonged cperation.
Other minor improvements to components were also made.
Again, no safety issues were involved with these modifications.
e June, 1989 All conttol rods were recalibrated as part of the semiannual calibration and maintenance activities.
July, 1989 All fuel temperature channels were calibrated as part
a of the semiannual calibration and maintenance activities.
.The NP1000 and NPP1000 power channels were calibrated as part of the semiannual calibration and maintenance activities.
August, 1989 Wiring in the operator console was completed to allow NM1000 scram checks to be conducted from the console.
Firmware changes to the NM1000 were made earlier to facilitate this change.
A relay board which incorporated the regulating rod magnet current relay was replaced.
This relay board had shown the tendency to malfunction when operating at elevated temperatures in the instrument cabinet.
Septembe r, 1989 A revision to the operating sof tware was installed to incorporate pulse channel reset feature from the console as well as correct the display of certain post-pulse data on the console. No safety issues were involved as a result of this revision.
The switch which allows the operator to drive the regulating rod up failed, causing the reg rod to drive out without operator action (failed open).
The switched was replaced.
A redundant pit water temperature monitor was installed in the auxiliary console.
This monitor uses a Boltr. man's Law sensor versus a RTD type sensor used for the primary monitor thus providing both diversity and redundance for this parameter. L
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October, 1989 Under a 10CFR50.59 application, installation of a scram timer on the operator console was completed. To that end, a separate set of relay contacts not previously in the scram loop were added to the scram circuit. (Section 5.3).
l The pull rod on the regulating rod control rod drive r
f foot switch was replaced: this rod broke while an n
operator trainee was conducting' maintenance activities.
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- A circuit to measure rod drop time on the regulating rod using existing software on the digital IEC was installed.
November, 1989.
Under an approved 10CFR50.59 application, hardware and software changes were implemented to allow surveillance testing to be performed on watchdog timer circuits in both system computers (Section 5.6).
l A software update was implemented in the system software to allow annunciation of a scram on power failure in the NP1000 and NPP1000 analog channels.
This - also required wiring of scram digital inputs to
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different relay contacts on the appropriate relays.
This ' fail-safe" logic had already been in effect in the scram loop, and above change simply allowed it to be sensed by the digital inputs to the system computer l'
for annunciation.
There were no safety implications as a result of this change.
1 December, 1989 Installation of circuits to allow wetchdog timer status annunciator lights on the operator console was l
completed.
This allows the operator to determine l I b
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status of watchdog timers via hardwired indicator lights.
Under an approved 10CFR50.59 application, installation.
of a new continuous air monitoring system to replace the existing unit, was completed (Section 5.4).
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5.10CFR50.59 FACILITY MODIFICATIONS AND SPECIAL EXPERIMENTS Four applications for facility modifications under 10CFR50.59 to the R-38 facility, and one Special Experiment as defined in the applicable Technical Specifications, were approved and implemented.
In addition, one facility modification approved under the provisions of 10CFR50.59 during 1988 was implemented during 1989. These are described below 5.1 Installation of Microprocessor based Instrumentation & Control System.
During December, 1988, the Reactor Safety Committee at GA gave final approval to the facility, to install-a new microprocessor based in-strumentation ano control system (ILC) for the TRIGA Mark I reactor.
This I&C system, which was conceptualized, developed and built by GA, had been undergoing extensive on-line testing on the Mark I reactor since 1986, under a special test program approved and closely moni-tored by the safety committee.
Following completion of this test pro-gram in late 1988, the facility requested - and subsequently received approval from the Safety Committee to decommission the old analog console, and install for routine reactor operations on the Mark I re-actor, the new microprocessor based IEC system (Ref. 1).
The removal of the old system and its replacement by the digitally based system was completed on January 14, 1989.
Routine reactor operations in steady-state as well as pulsing modes were initiated with the new I&C system on January 16, 1989.
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5.2 Addition of a Ground Fault Detector Test Circuit to Instrumentation and received in f
and control System.
Approval was requested February, 1989 - to add to the Mark I I&C system, a circuit to test the operation of the ground fault detector, which monitors for any shorts to pground that may occur in the scram loop (the scram loop s
floats with respect to chassis ground).
While the circuitry for detecting and annuncir, ting such shorts to ground was already designed in the IEC system, no method was available to perform surveillance of this ground fault detector.
The test circuit that was installed under this f acility modification allows a simple check to be performed to l
test the operability of the ground fault detector,
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5.3 Addition of a Scram Timer to the Instrumenation and Control System.
Approval was requested - and received in June, 1989 - to add a timer capable of scramming the reactor a predetermined length of time af ter a pulse, or terminate a steady-state reactor run at some preset time selected by the operator.
This modification was proposed and imple-l mented as an additional scram capability - with its own relay contacts in the scram loop '. that would be available to the reactor operator, and allowed the facility to more fully utilize the enhanced operational capabilities that are offered by the microprocessor based I&C system (Section 5.1).
5.4 Replacement of Continuous Air Honitoring System.
Approval was re-quested and received in June, 1989 to replace the existing beta-gamma continuous air monitor (CAM) used for the detection of air-borne radioactivity above the reactor pool.
The age of the existing monitor (a.1960s vintage Nuclear Measurements Corp. (NHC) Model CRM--
51), coupled with low detection efficiencies it provided, necessitated the move to replace this unit with a Ludlum Heasurements Model 333-4 Continuous Air Monitor.
Both units are fixed filter type air and par-ticulate monitors utilizing standard pancake G-H probes for radiation 1
detection.
The new system provides the facility with a more reliable l i
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radiation monitoring system, and far greater operational flexibility than that provided by the older NMC unit.
5.5 Irradiation of Target Materials for the New Production Reactor.
Ap-proval was requested - and received in August, 1989 - to conduct irra-diations of lithium target materials in support of the New Production Reactor (NPR) program. Approval for these irradiations was granted by the Safety Committee as a Special Experiment to be carried out by the facility.
Irradiations on lithium compact and loose coated particle samples were carried out in specially designed irradiation containers which fit into e cutout region of the annular reflector.
Following appropriate decay periods, the containers were transferred to GA's ra-diochemistry laboratories for performing the tritium separation and analyses.
5.6 Addition of Watchdog Timer Scram Surveillance Testing Circuits to In-grumentation and Control System.
Approval was requested - and re-ceived in November, 1989 - to add to the Mark I IEC sytem,_ circuits which allowed surveillance testing to be performed on watchdog timer scrams.
Watchdog timers are circuits utilized in the microprocessor based IEC system which act as f ail-safe hardware capable of shutting down the reactor in case of a f ailure or hang up in sof tware modules operating in both system computers.
The IEC as originally installed provided relays in the hardwired scram circuit which opened the scram loop in case any of the watchdogs timed out.
The circuitry added un-der this modification provided the operator to perform surveillance testing on these scrams from the control console, similiar to those performed on other hardwired scrams such as power level, fuel tempera-ture, manual scram etc.
- 6. RADIOACTIVE EFFLUENTS DISCHARGED TO THE ENVIRONMENT During the calendar year 1989, 0.0034 curies of Argon-41 were released from the Mark I facility stack to the atmosphere.
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s All liquid and solid wastes were transferred to GA's licensed (under NRC license SNM-696) Nuclear Waste ?rocessing Facility for ultimate disposal.
All waste was measured for specific radionuclide activity prior to the transfer.
Solid wastes are packaged and shipped to an authorized disposal facility.
Liquid wastes are handled in a similiar manner, or trace quantitles of low level wastes may also be released into the municipal sewage system within the limits and criteria specified by applicable local.
state and U.S. NRC regulatione.
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- 7. ENVIRONMENTAL SURVEYS Y
There were no significant changes in the GA Environmental Surveillance Program during 1989.
- 8.
SUMMARY
OF RADIATION EXPOSURES AND RADIOLOGICAL SURVEYS 8.1 Reactor Facility Personnel Whole Body Exposures Number of employees monitored:
24 High Exposure:
0.300 Rem Low Exposure:
0 Average Exposure:
0.081 8.2 Nonfacility GA Personnel Whole Body Exposures Number of employees monitored:
27 High Exposure:
0.315 Rem Low Exposure:
0 Average Exposure:
0.042 8.3 Contractor and Customer Personnel Whole Body Exposures
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Number of persons monitored:
90 High Exposure:
0.500 Rem Low Exposure:
0 Average Exposure:
0.032 7
.s,
8.4 Visitor Whole Body Exposures Number of persons monitored:
37 High Exposure:
0.255 Rem Low Exposure:
0 Average Exposure:
0.009 8.5 Routine Wipe Surveys of Facility High Wipe 14.8 dpm(beta)/100 cm2 Low Wipe
<1 Average Wipes
<1 8.6 Routine Radiation Measurements of Facility High Measurement:
10 mrem /hr at 1 foot Low Hensurements
< 0.1 Average Level:
0.1 s
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RO. Box 85608 e San Diego, CA e m-92138 5608 (619) 4SS-3000
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