ML20195E656

Triga Mark I Reactor Annual Rept for CY98, Dtd Apr 1999

ML20195E656
Person / Time
Site:	General Atomics
Issue date:	12/31/1998
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20195E652	List: ML20195E647 ML20195E656
References
NUDOCS 9906140044
Download: ML20195E656 (13)

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T GA* Reactors -

TRIGA* Mark i Reactor ANNUAL REPORT CALENDAR YEAR 1998 prepared to satisfy the requirements of U.S. Nuclear Regulatory Commission Facility License R-38 Docket No. 50-89 April,1999 9906140044 990414 9 GENERAL AFDAffCS DR ADOCK 0500

TRIG A " Reactors TRIGA* Mark i Reactor ANNUAL REPORT CALENDAR YEAR 1998 prepared to satisfy the requirements of U.S. Nuclear Regulatory Commission Facility License R-38 Docket No. 50-89 April,1999

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9906140044 990414 CENERAL A70ASC'S 7 - -w9

TRIGA REACTORS FACILITY I *

• TRIGA Mark I Reactor ANNUAL REPORT Calendar Year 1998 TABLE OF CONTENTS Section Page I'NTRODUCTION.. ....... .. . ................................................................. . .. . . I

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SUMMARY

OF FACILITY ACTIVITIES .. ....... .. .... .... . . ...... ........ . ....... ...... .2 l

1.1 Possession and Storage Experience......... . . ... ... . . ..... ......... .. .. .. .......2 1.2 Facility Changes and Modifications.. ........... ... . . .......... . ...... . . . . . . . . . . .2 1.3 Surveillance Tests and Inspections... ... . . ... . .. ....... ...............................3

2. MAINTENANCE ACTIVITIES ..... . ... . .... . . . . . ...... . ........... .... ......... ... .... . 6 2.1 Reactor, Mechanical, and Auxiliarj Systems.... ... ... .. .......................6 2.2 Instrumentation and Control System.. ... . . . ... ... .... ...... ..... ... .. . . . . . .........7

3. 10CFR50.59 FACILITY MODIFICATIONS AND SPECIAL EXPERIMENTS. ..... 8 4 4

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RADIOACTIVE EFFLUENTS AND WASTE GENERATION....... . .... . ..... ... . . ...

ENVIRONMENTA L w!ONITORING.. . .. . . . . . . . ..... . . ... ..... ... . . . . . . . . . 10 9

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SUMMARY

OF PADIATION EXPOSURES AND RADIOLOGICAL SURVEYS ... ...11 6.1 General Atomics Staff Whole Body Exposures............. . . .......... .. . . . . . . . . . . . I 1 6.2 Non General Atomics Staff Whole Body Exposures . . .............. .... . .... .... .. . .. I 1 6.3 Roetine Wipe Surveys of Mark I React <>r Facility . ... . .. ....................... .. ... . I 1 6.4 Routine Radiation Measurements of Mark I Reactor Facility.. . . . . . .. . . . . . . . I 1

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INTRODUCTION This report documents operation of the General Atomics (GA) TRIGA* Mark I non-power reactor for the period January 1 - December 31,1998. The Mark I reactor - possessed by GA at its San Diego, California facilities - has been non-operational for the duration of the reporting period. It is possessed by GA under License No. R-38 (Amendment No. 35) granted by the U.S. Nuclear Regulatory Commission (DocLet No. 50-89).

This report is being prepared and submitted to satisfy the requirements of Section 9.6(f) of the R-38 Technical Specifications, as amended. This report is presented in six parts, consistent with the information required by the applicable Technical Specifications.

TRIGA is a registered trademark of General Atomics

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SUMMARY

OF FACILITY ACTIVITIES l.1 Possession andStorage Experience

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The TRIGA Mark I reactor was under a Possession-Only-License during calendar year 1998. Consequently, there were no reactor operations during the period. The following represents a summary of possession and storage e:perience during this period:

The TRIGA Reactors Facility Reactor Operator Re-qualification Program was approved by the NRC on March 3,1998.

[ A new TRIGA Reactors Facility " Physicist-in-Charge" (PIC), Mr. John Greenwood, was appointed on July 31,1998.

Three individuals completed the requirements of the Reactor Operator Re-Qualification program and have been re-instated as Limited SROs. Their licensed duties will be limited to fuel storage and handling, maintenance and monitoring of the facility, and the enforcement of all applicable procedures.

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There were no reportable occurrences during the year.

Two NRC inspections were conducted during the period. No significant safety problems were noted during the first inspection on February 17-18. The second inspection on May 4-7 identified three violations. Corrective action was implemented f toward these violations. These corrective actions were acceptable to the NRC and will be reviewed during future inspections. The matter was satisfactorily resolved on July 22,

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{ There was one application for a facility modification under 10CFR50.59 that was submitted, approved and implemented during this reporting period.

1.2 Facility Changes andModifications There were no changes madfin the performance characteristics or mechanical design

1. the Mark I reactor facility during the reporting period. One facility modif%ation w- made regarding the Instrumentation and Contiel System and is describ;d in

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Section 3 of this report. The fuel remains out of the reactor tank in long term storage.

All SNM, sealed sources, fission chambers and fuel elements (both irradiated and virgin) have been removed from the Mark I facility. Activated hardware and control rods remain in the Mark I tank which is maintained full of water.

1.3 Surveillance Tests andInspections Surveillance tests and inspections were performed as required by the R-38 Technical Specifications. Criticality alarm tests were performed monthly. Because no reactor operations are allowed under the POL, tests and inspections required for the reactor core, control rods and reactor safety systems are no longer applicable. A summary of the tests and inspections performed is presented below:

1.3.1 Pool Water. The pool water was sampled on a continuous basis for conductivity using an on-line sensor installed in the water treatment system flow stream. Conductivity measurements were recorded weekly. Water conductivity was maintained well below the limit of 5 micro-mhos per centimeter averaged over one calendar month as required by the Technical Specifications. Measured values are verified and calibrated with a VWR hand held conductivity monitor which is calibrated separately by Quality Assurance off-site. Pool water was sampled on a quarterly basis for determination of radionuclide content including the presence of any fission products, as well as the determination of corrosion product concentrations.

Water level sensors with audible and visual alarms were used to ensure that the sump water level did not exceed acceptable levels. A visual check of '

pool water level was made a.e part of the Weekly Maintenance Checklist.

Makeup water was added quarterly to replenish water lost to evaporation.

Pool water temperature monitors were used to ensure that bulk pool water temperature is maintained within acceptabla limits. A chromel/alumel thermocouple sy. tem is the primary measurement method. The measurements are verified and calibrated using a Fluke hand held digital thermocouple temperature readout. This monitor is calibrated separately by

- Quality Assurance off-site.

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1.3.2 Radiation Monitoring. The primary instruments utilized during the reporting period for facility radiation monitoring were a continuous beta-gamma air monitor, radiation area monitors, water and air filter monitors, a console monitor, and a variety of portable survey meters. Their use and calibration is described below:

Continuous Air Monitor (CAM). The CAM (Ludlum Model 333-4) alert and alarm set points were checked on a weekly basis by activating them with a check source. Calibration of the system was performed annually ufag two Sr-90/Y-90 sources with a calibration traceable to the National 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 20 mR/h; the high level monitor alarmed at levels exceeding 5000 mR/h. The alarm set points were checked weekly, with alarm testing performed biweekly using a check source. Calibration was performed annually using a 4 mci Cs-137 source on a calibration range at General Atomics. All calibrations were traceable to NIST.

Water and Air Radiation Monitors. Separate radiation monitors (Eberline RMS II) v,ere used to monitor the radiation levels in the reactor pool water and the reactor room air ventilation system. Their operation and alarm set points (50 mR/h and 5 mRih respectively) were verified on a weekly basis.

The monitors were calibrated on an annual basis using the General Atomics calibration range; all calibrations were traceable to NIST.

Console Radiation Monitor. A radiation monitor (Eberline RMS II) monitors dose rates at the reactor console. Its operation and the alarm set point (2.5 mR/h) were verified on a weekly basis. The monitor was calibrated on an annual basis.

Portable Radiation Monitors. Several types of portable radiation monitors were in use at the facility. Examples are the Eberline RO2 and RO2A beta-gamma survey meters, the Ludlum pancake probes, the Ludlum MicroR meter and the LFE SNOOPY neutron survey me'er. All portable radiation monitors were calibrated on a semiannual basis, with the exception of the SNOOPY neutron survey meters, which were calibrated on an annual basis.

2. MAINTENANCE ACTIVITIES All maintenance activities performed during the year generally fall into three categories: (i) routine preventative maintenance, (ii) routine calibration activities, and (iii) activities associated with replacement of older components and systems simply due to wear and tear from the many years of use. All maintenance activities are recorded in the POL logbook.

Two maintenance checklists were prepared during the reporting period to be consistent with the requirements of the Possession-Only-License. These checklists are adhered to on a regular schedule, one being weekly and the other being quarterly. Activities in this area are described below:

2.1 Reactor, Mechanical, and Auxiliam Systems Annual cooling tower and secondary system maintenance was performed. Pump seals and bearings were replaced and the pump shaft reground. Routine maintenance on the 2 MW cooling tower (which remains online) was done periodically throughout the year. The pressure drop across the strainer was checked to determine if cleaning was necessary. The four 250 kW cooling towers remain isolated from the system.

Routine ventilation system maintenance was performed throughout the period with scheduled changes of the louvre filters and ventilation filters and prefilters carried out.

The pressure drop across the demineralizer filter is checked weekly and We filter changed as necessary.

Filters for the Continuous Air Monitor (CAM) and air flow meters were checked and replaced as required.

Quarterly inspections were performeu .~or the Mark I overhead creme. Any required service was performed as needed to keep the inspection record current.

Periodic checks were made to de, ermine the operability of radiation warning ligats and beacons and interior / exterior lighting. Bulbs were replaced as necessary.

The decipher lock was de-activated to controlled areas. Access is now with a lock and key. The lock is changed annually.

2.2 Instrumentation and Control System The control console was removed from the Mark I reactor room for refurbishment and use elsewhere. The air, water and console monitoring functions were relocated to the Mark F console.

1 Radiation monitors were checked against the required alarm setpoints on a weekly 1 basis. Monitors include two area monitors, CAM, console monitor, air rnonitor and water monitor. Instrument calibration was carried out on schedule.

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3. 10CFR50.59 FACILITY MODIFICATIONS AND SPECIAL EXPERBIENTS There was one new application for a facility modification under the provisions of 10CFR50.59 that was approved for the R-38 facility during the 1998 reporting period.

There were no new Special Experiments that were approved for the R-38 facility during 1998.

When facility modifications or Special Experiments at the R-38 frility are proposed, the applications for the proposed changes or experiments are reviewed prior to implementation by the Physicist-in-Charge and by the TRIGA Reactors Facility Saf.?ty Committee, among others, and approved only after making the determination that the proposals for the changes do not:

(a) involve a change to the R-38 Technical Specifications, or (b) create any unreviewed safety questions as defined in 10CFR50.59.

The approved facility modification concerned the partial removal of the Mark I instrumentation and control system. The components to be removed included the Control System Console (CSC), Data Acquisition and Control Cabinet (DAC), NM-1000 Wide Range Digital Power Monitor, and the Control Rod Drives (CRDs). Review of this facility modification was provided and approval given in May 1998. It was determined that these components were not required because all fueled items have been removed to storage and reactor operation is no longer possible. Radiation Area Monitors, the pool inonitoring panel in the DAC and the control and connecting rods remain in the facility. The stated components were subsequently removed from the facility during the 1998 reporting period.

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4. RADIOACTIVE EFFLUENTS AND WASTE GENERATION During the calendar year 1998,0.00 millicuries of Argon-41 were discharged at the Mark I reactor facility stack to the atmosphere.

All low level radioactive mixed wastes were transferred to GA's Nuclear Waste Phocessing Facility - which operates under NRC license SNM-696 and GA's California Radioactive Materials License No. 0145 for disposal. Low level radioactive waste has been packaged in LSA boxes and remains at the TRIGA Reactors Facility until sufficient quantities are accumulated for transfer to the Nevada Test Site (NTS). All wastes are measured for specific radionuclide activity usinl: high resolution gamma-ray spectroscopy prior to the transfer. Solid mixed wastes are then repackaged as necessary and shipped to an authorized disposal facility by GA's waste processing facility. Normally, liquid waste is transferred to the Nuclear Waste Processing Facility filtration station. In certain cases, liquid waste may first be subjected to volume reduction by evaporation, and the residue waste packaged for disposal as solid waste. Trace quantities of liquid low level waste may also be released into the municipal sewer system, if such waste is found to be within the limits and criteria specified by applicable local, state and NRC regulations.

During calendar year 1998, the GA TRIGA Reactors Facility (R-38 and R-67 licenses) transferred approximately .11 cu. ft. of noncompactable low level radioactive mixed waste (activated and contaminated cadmium) to GA's waste facility for storage and final disposal.

Approximately 5.6 cu. ft. of low level radioactive waste was generated at the TRIGA Reactors Facility during calendar year 1998 and is being stored awaiting transfer and final disposal at NTS.

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( 5. ENVIRONMENTAL MONITORING

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The, environmental monitoring program during 1998 for the TRIGA Reactors Facility remained essentially unchanged from the prior year and included the following:

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• Five (5) emergency air samplers situated on the roof and around the reactor building.

Ten (10) environmental air samplers adjacent to, and near the GA site in accordance with GA's SNM-6% license.

Daily liquid effluent monitoring from GA's main pump house, for gross alpha and beta

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• Annual soil and water sampling at ten (10) stations on the GA site, including stations around the GA reactor building.

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External radiation monitoring of the reactor facilities using five (5) area dosimeters as well as radiation meter surveys conducted periodically.

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Air samplers located in the reactor room to routinely sample room air for airborne radioactivity, as needed.

Additional radiation monitors as described in Section 1.3.2 of this report.

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SUMMARY

OF RADIATION EXPOSURES AND RADIOLOGICAL SURVEYS The.following data summarizes personnel radiation exposures (Rem) and radiological surveys of the facility during 1998. Only those people specified in the Facility Work Authorization (WA) #3132 have been monitored for exposure. Of those authorized to work in the facility, thirteen are General Atomics employees and one is a contractor granted periodic access.

6.1 General Atomics Staff Whole Body Exposures

• Number of individuals monitored: 13 High Exposure: 0.060 Low Exposure: 0.000 Average Exposure: 0.008 6.2 Non General Atomics Staff Whole Body Exposures' '

Number ofindividuals monitored: 1 High Exposure: 0.000 Low Exposure: 0.000 Average Exposure: 0.000 6.3 Routine Wipe Surveys ofMark I Reactor Facility High Wipe: 8.9 p dpm/100 cm2 Low Wipe: < 1 p dpm/100 cm 2 Average Wipe: < 1 p dpm/100 cm2 6.4 Routine Radiation Measurements ofMark iReactor Facility l

l High Measurement: 2 mrem /hr @ 1 foot l

l Low Measurement: 0.2 mR, t/hr @ l foot Average Level: <0.2 mhem/hr @ 1 foot l

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• Includes reactor facility staff and facility support staff authorized to work at the reactor facility. These personnel may also work routinely at other G A radiation facilities; therefore, this dose represents cumulative exposure at all GA facilities.

Includes non-GA personnel who were grar.ted periodic access to the facility for the performance of work. These persoratel may also work routinely at other GA radiation facilities; therefore, this dose represents cumulative exposure at all GA facilities.

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