ML20235Q375

Triga Mark I Annual Rept for 1988

ML20235Q375
Person / Time
Site:	General Atomics
Issue date:	02/16/1989
From:	Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	Chris Miller Office of Nuclear Reactor Regulation
References
38-1349, NUDOCS 8903020598
Download: ML20235Q375 (12)

Text

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CENERAL ATOMECS

,fo OST February 16, 1989 38-1349 Mr. Charles L. Miller, Acting Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III/IV/V and Special Projects U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Subject:

Facility License R-38; Docket 50-89 Subnittal of TRIGA Mark I Annual Report (3 copies)

Dear Mr. Miller:

I The following is the annual report required by the applicable Technical Specifications of General Atomics' Mark I 'IRIGA reactor (License R-38) . This report covers the operation for the calendar year 1988. The numbered paragraphs below are those referred to in Section 9.6e of the Technical Specifications for the Mark 1 TRIGA reactor.

PART I: A brief narrative sumary of (1) operating experience (including experimnts performed), (2) changes in facility design, performance characteristics and operating procedures related to reactor safety occurring during the reporting period, and (3) results of surveillance tests and inspections.

1. The Mark I reactor was operated during the year to provide 266 pulses (Pulse Nos. 11237 to 11502) and numerous steady-state irradiations for experiments. The operations included: l activation analysis, neutron radiography, King furnace high-temperature studies of reactor fuel, numerous irradiations of electronic piece parts and pieces of equipment, training for l

customer operator trainees, requalification exercises for facility operator trainees, and testing of comercial reactor instruments-tion. The number of samples for neutron activation analysis and ,

radiochemistry was 1,739. d The above types of activities are the normal ones generally i experienced over the past 30 years. In addition to these, onc i extended yearlong operation was conducted. This consisted of a series of tests under the application of 10 CFR 50.59 towards final operational testing of a new, microprocessor based, state-of-the-art control and instrumentation system for research reactors. These tests were performed under a continuing program that was described in the 1986 and 1987 Annual Feports for the same facility. An extensive set of continuing tests and opcra-tional verification of the system was conducted and completed in December 1988. A second application under 10 CFR 50.59 was j 8903020598 890216 ,,/

PDR ADOCK 05000089 I p PDC 10955 JOHN JAY HOPKINS DRIVE, SAN DIEGO, CA 92121 1194 PO DOX 85608. SAN DIEGO, CA 92138-5608 (619)455-3000 r{ i

4 generated and approved by the reactor cafety committee in December 1988 for the removal fra the facility of the earlier analog console and the installation and final acceptance tests of the new Instrumentation and Control (I&C) System. This reoval and in-stallation process was initiated early in January 1989.

No reportable occurrences arose with this facility during 1988.

2. The only changes to the facility were the modifications to the Mark I reactor core instrumentation that were required for the -

continued testing and installation of the digital I&C System.

Such changes included:

(a) installation of micrometer adjustments for the power monitor detectors; (b) installation of an additional detector and housing for the additional power channels being tested on the I&C System; and (c) relocation of the increased number of neutron detectors being used for the old and new consoles.

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 represe.nted below.

Fuel Surveillance The fuel was inspected visually and for bending and length changes on December 12, 1987. All elements were satisfactory but one (FE

1. 1590) was damaged by dropping during the inspection. As a result, its bottom weld was misshaped and could not be reinserted into the core. In addition, at an earlier time in the ye.ar, fuel element #1737 was required to be noved in the course of installing in-core experiments. On November 14, 1988, this element was very hard to remove although it had been easy to move up until that time. Inspection revealed a shallow gouge in the clad surface just below the core center line. No fission products have been released from thir element. The elment has been removed from service but at a later date we may investigate further the depth of the gouge and consider the possibility of returning it to service if a simple surface adjustment can be made.

Control Rod Surveillance The visual inspection for deterioration was conducted December 15, 1988. All control rods were found to be in satisfactory condition.

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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 15, 1988, and December 15, 1988. The heavily rebuilt (in 1987) rod damper assembly was inspected carefully. No deterioration or undue wear were noted. Ma..ntenance of the cylinder UP limit switch cam actuating surface was machined to improve microswitch action.

Acklitional attention will be given to this item early in January 1989 to improve its operation still further. No safety issue is involved.

Reactor Safety Surveillance 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 tmperature measuring channels, channel checks of the power-level macuring channels, and channel checks of the fuel element temperature measuring channels were perfomed. 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 response of five individual neutron detectors was checked during each of the twelve monthly calibrations; eight adjustments of more than five percent were required durirg the normal monthly calibration. Five additional l

power calibrations were perforned (again, each involving five '

detectors) for a variety of reasono: sme to give e.xperience to operators-in-training; some to make additional checks on calibration of the new I&C System being tested (nine of these required additional adjustments greater than five percent); and some simply to repeat or check earlier results.

Radiation Monitor Surveillance The radiation monitor and survey systems were under surveillance during the reporting period. The frequency of calibrations was as indicated below.

Continuous Air Monitor Alarm setpoints were checked daily, alarms were activated with a check source once a week. The system was calibrated semiannually uith two Sr-90/Y-90 sources in front of the detector (9,520 and 110,000 CPM).

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l Ebccline Area Monitors J Operation was checked daily; alarms were activated in response to a source every two weeks; calibration was performed semiannually with a nominal 4nci Cs-135 source.

Portable Survey Meters The Eberline RO2 and RO2A meters, the Ludlum pancake GM meters (Model 3), the Ludlum microR meter (Model 19), the victoreen meter (Model 488A) for fast, slow neutrons, and the LFE SNOOPY (neutron) meters were calibrated in GA's calibration facility. The RO2 and RO2A meters were calibrated quarterly; all others, Calibrated semiannually.

PART II: A tabulation showing the energy generated by the reactor (in megawatt-hours).

The energy generated in'1988 by the Mark I was 42,503 kilowatt-hours (42.5 megawatt-hours). The accompanying bar graph shows reactor usage on a monthly basis during the year.

PART III: The number of emergency shutdowns and inadvertent scrams, including the effect, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required, if any.

The total number of scrams in 1988 was 82. The increase above the 38 listed for 1981 is due mainly to the increased intensity of the testing program for marry components of the digital I&C Systen. The 82 scrams fall generally int.o the following time distributions:

Scrams in 1988 No. of No. of Month Scrams Month Scrams January 10 July 5 February 5 August 18*

March 5 September 5 April 5 October 13**

May 3 November 5 June 9 December _4_

'Ibtal 82 Total Number of Scrams: 82 Monthly Average: 6.8 Standard Deviation: 3.5

• I&C tests.

• • Customer operator training.

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Four months had notably increased activity on the testing project accompanied by an increased frequency of scrams (January, June, August, and October) . The increased frequency of scrams during January, June and August can also be correlated with increased usage (kW-hrs) during these months which is also related to near full powr testing of the new ISC system. Much of the increase in Octobec, however, was due to student trainees. The 82 scrams fall general]y into the following categories:

1. Operator error during 8-week training program (October) 8

2. Operator error during routine operations 6

3. Operational tests associated directly with digital I&C system 30

4. Spurious scrams, interaction of two consoles (licensed 38 analog and under-test microprocessor based) when used  !

simultaneously; pulsing tests with new I&C System, inter-mittent connections in Percent Power #2 channel of analog console, deliberate scrams to test bc,undaries of software package being tested sometimes (several times per day).

82 The relatively large nunber of scrams (30 + 38) associated for the nost part directly with the on-line testing program are not unusual in such a test program. The 30 associated with tests with the NM-1000 digital power monitor occurred in the course of elianinating undesir-able features of the NM-1000. Many of the 38 scrans occurring during the tests of the remaining portions of the I&C system were caused {

deliberately by tests on the software to detennine boundary limits.  !

Reference to the scram frequency in Novmber and December verifies '

that finally the testing and modifications were nearly complete and nearly routine runs (under Phase V of the test program) were being conducted. It is confidently believed that routine operations can be conducted with the new I&C system (installed early in January 1989) without an unusual number of inadvertent scrams.

It should be enphasized that none of the 82 scrams experienced in 1988 had any effect on, or consequence for, the safe operation of the Mark I reactor. In fact, it can be stated that each of the safety channels under test as part of the new I&C System performed as intended during the various test phases conducted during 1988.

PNtI' IV: Discussion of the 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. 1/13/88 Stopped a small demineralized water leak fram the demineralized pump discharge. Replaced about 8-inches

of aluminum pipe with a Schedule 80 PVC pipe. No safety implications since the tiny leak of water involved only purified water.

2. 1/15/88 Calibrated all fuel element thermocouple.

3. 1/15/88 Replaced the thermistor temperature probe for the bulk- tank water temperature monitor with a previously used but serviceable unit. The replaced probe failed probably due to water soaking into the sensor head.

No safety implications.

4. 1/26/88 Installed UNISLIDE adjusters for the Percent Power #2 channel and pulse detectors. The use of such adjusters permits very fine adjustment of position for i these detectors.

5. 2/5/88 Repaired Cooling Towers Numbered 3 and 4. This involved draining, cleaning and sealing the bottom sumps, replacing rusted out baffles, and cleaning the nozzles.

6. 2/25/88 Cleaned spray nozzles in Cooling Towera Numbered 1 and 2.

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7. 3/1/88 Replaced a faulty heater controller (CJ-1) in the digital readout for the fuel tunperature T3 meter. No l safety implications since two other fuel temperature i monitor channels satisfied the requirements of the

'Ibchnical Specifications.

8. 3/2/88 Installed a UNISLIDE adjuster for the detector on the Percent Power #1 channel. (See No. 5. above).

9. 3/7/88 Installed a new detector housing on the north side of the reactor to hold a CIC detector chamber for the new NPP-1000 safety channels (this channel is part of the new I&C system). A CIC Westinghouse detector (WL 8105 Ser # 1688) was used that had been used years ago in the Mark F.

10. 3/17/88 Replaced a LINEAR MPLIFIER card with a spare card for Percent Power #1 channel.

11. 4/1/88 Installed UNISLIDE adjuster for the fission chamber for the Wide Range Channel.

12, 4/29/88 In order to accommodate the flux nonitors for the two consoles, seven out-of-core detectors are required.

On this date three of the seven were relocated to more favorable positions around the core.

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13. 5/2/88 Removed CIC detector (Ser. No.1688) fran the reactor to the radioactive waste storage yard. This detector had been used on the Mark F TRIGA reactor for many years in the early 1960s. Its operation was unsatis- 1 j

factory since it was installed 3/7/88 (See Item 12) '

but there was no safety problem, especially since this was a third steady-state channel and no power channel j is required in the Pulse Mode.

14. 5/25/88 Received two repaired control rod drives (Serial Nos. {

183, reg rod, and 189, standard rod). l l

15. 6/2/88 Installed a new thennistor probe for the tank water temperature censor. I

16. 6/3/88 Added a four-inch extension on the housing for the l.

pulse detector to prevent the detector from caning up out of the housing when it is raised for adjustmen* ,

I necessary for pulsing with the analog console.  !

17. 6/10/88 I Replaced a ZERO potentiometer in the IDG recorder for l the analog console.

18. 6/15/88 Completed the SEMIANNUAL inspection on the transient rod drive system. Also replaced REG ROD drive Serial l

No. 188 with drive Serial No. 183. Drive Serial No.

188 had a short in a winding for the Position

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Indicator circuit which resulted in non-linear position readouts at one point in its travel.

19. 6/16/88 A belt on the exhaust fan broke during a run.

Replaced belts on both the exhaust fan and the CAM.

Replaced heat damaged AC plug for the CAM motor. The ventilator system was off for about an hour to effect the repair. No reactor runs were made during this l period.

20. 6/17/88 Experienced some trouble with the SERVO which hunted l

' excessively. Reinstalled Rod Drive Serial No. 188 and found that the SERVO Tachometer pins on Serial No.183 had been interchanged during the overhaul. Inter-changed these wires to correct problem.

21. 6/21/88 Again replaced Reg Rod drive (Serial No.188) with Serial No. 183. Sent Serial No. 188 out for overhaul.

Among other improvanents, it is expected that the Rod Position Indication will be repaired (See Item 22).

22. 6/28/88 Calibrated thernocouples for fuel element temperature monitor, w_--_________-_____ . _ _ - . -

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23. 7/26/88 Replaced the G-M water nonitor cable which had been l chewed by rodents. Reinstalled a netal conduit cover I over the cable to prevent further attack by rodents.

This cover had been removed earlier in the year to inprove the appearance of the facility.

24. 9/27/88 A problem was noticed in the ability to drive the pulse rod cylinder DOVN. (The transient rod itself was free to fall as required, hence no safety problem). A series of assembly nuts around the base of the moveable cylinder are secured with a lockwire through the nuts. The loose end of the wire was oriented in such a way that it snagged the transient rod air hose at one point in the cylinder travel. The remedy was to bend the stiff wire into such a config--

uration as to avoid ccmpletely the air hose. No safety problem involved.

25. 10/24/88 Installed new external scram circuits for operation with the new I&C system. EXT No. 1 accommodates the auxiliary Keithley monitor channel; EXT No. 2 serves l the KING FURNACE scram system.

26. 12/7/89 Modified the demineralized water piping to accommodate a rotary flow meter which provides a digital readout on the console. This provides an upgraded flow measuring system for the demineralized system which previously had only a visually observed flow gage located at the pump station.

27. 12/15/88 Completed SEMIANNUAL INSPECTION of transient rod system and inspected control rods. No problems were identified.

28. 12/23/88 Replaced roam ventilator fan belt.

The increase from 24 items in 1987 to 28 items in 1988 involving maintenance is not statistically significant but does reflect the i increased activity, much of which was related to the final testing phase and requirements for the new digital I&C System, as well as continuing upgrades and increased maintenance of aging facility equipnent.

PART V: A sunmary of each change to the facility or procedures, tests, and experiments carried out under the conditions of Section 50.59 of 10 CFR 50.

The activities described in this section were all related to one or '

another aspect of the testing of the new digital console. The activities in 1988 involving this console were carried out under the a_________. _.

s program authorized in 1986 under a 50.59 application which described a five phase testing program and a sixth phase devoted to operator requalification on the new Instrumentation and Control (I&C) Systen.

TWo of the items involved review / approval by the Safety Ccmuittee to proceed to the next phase of the original umbrella 50.59 approved in 1986. The third item involved the review and approval of a new 50.59 for the removal of the old, analog console, installation and final tests of the completed new digital I&C Syctem, and the qualification program fcr all facility licensed operators. Two additional items required approval of the Safety Comittee to conduct training courses for custorter operators using the new, digital I&C System which was in the final stages of the testing program.

1. 2/1/88 Approval was requested from the Safety Comnittee to proceed with the Phase IV of the six phase program to test the I&C System. The successful results of the Phase III tests were presented in detail. Approval was granted by the safety Comnittee on 2/17/88.

2. 6/2/68 Approval was raquested from the safety Ccmnittee to pnaceed with the Phase V of the test program to complete tests on the I&C System. The results of the Phase IV testa were presented in detail. Approval to  !

proceed was granted by the safety Ccmnittee on j 6/23/88.

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3. 9/16/88 The Safety Ccmaittee was asked to review and approve the plan to train two GA customer reactor operators on  !

the use of the new I&C System. Approval had been granted earlier to conduct routine irradiations under appropriate conditions using the I&C System while still in Phase V testing. Approval was granted by the Safety Committee. '

4. 9/29/88 The Safety Ccmnittee was asked to review and approve the plan to train six GA customer reactor operators over an 8-week period using the new I&C S l was still in the Phase V testing program. ystem As inwhich shown j in Item 3 above, the Safety Ccmnittee reviewed and j approved the request.

5. 12/88 In Decent)er 1988, approval was requested from the Safety Ccmnittee to remove the old, analog console anci l

make permanent . installation of the new digital I&C ,

System. To support this request a detailed document i was prepared with the title: " Safety Evaluation under 10 CFR 50.59, Microprocessor Based Instrumentation and Control System for the General Atomics Mark I  ;

Reactor." In this docurent it is demonstrated that: i f

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a. The new I&C System meets all the requirements of l the 'Itchnical Specifications; '

b. No untried techniques are used to provide the safety functions in the new systen;

c. The operator is provided at all times with basic performance data even if the computers fail, i I

d. The two year on-line testing program has demon-stratt'd that the new I&C System provides substan-tial reliability for the reactor safety systems; and

e. No hazards of a different nature that previously analyzed or hazards with increased magnitude are introduced by use of the new I&C System.

The Safety Ccmnittee reviewed all aspects of the 50.59 application and issued on Decenber 20, 1988, an approval to proceed as requested.

The instr.llation as described comenced in January 1989.

PNtT VI: A sunmary of the nature and anount of radioactive effluents released or discharged to the environs beyond the effective control of the licences as measured at, or prior to, the point of such releace of discharge. I During the calendar year 1980, 0.0139 curies of Argon-41 were released from the facility to the atnesphere.

All liquid and solid wastes were transferred to GA's NRC licensed (SNM-696) Waste Processing Facility for ultimate disposal. Solid wastes are packaged and shipped to an authorized disposal faci',ity.

Liquid wastes are handled in a similar manner, or small quantities of low level liquid wastes may also be released into the municipal )

sewerage system within the limits and criteria specified by applicable l local, state, and U.S. NRC regulations, Part VII: A description of any environmental surveys performed l outside the facility. l' There have been no significant changes to the Environmental Surveillance Program during 1988.

l PART VIII: A summry of radiation exposures received by facility l

personne1~and visitors, including the dates and time of significant exposures, and a brief sumary of the results of radiation and contamination surveys perfomed within the facility.

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t Facility Personnel Whole Body Exposures for the Year 1988: (REM)

High Ixw , Average Number of Employees Monitored . . 20 0.860 0 0.149 Nonfacility GA Personnel Whole Body Exposures for the Year 1988: (REM)

High Ioa Average Number of Employees Monitored . . . 13 0.450 0 0.081 The majority of these exposures were received'at other facilities on the GA site.

Contractor / Customer Personnel Whole Body Exposures for the Year _1988: (REM)

High Ioa Averace Number of Percons Monitored . . . 72 0.575 0 0.038 Visitor Whole Body Exposures for the Year 1988: (REM)

High- Low Average Number of Persons Monitored . . . 31 0.120 0 0.007 Routine Wipe Surveys l

High Wipe 13 pign/100 cnf Average Wipe 51 pipn/100 cnf Low Wipe 51 plpn/100 cnF 7 Routine Radiation Measurements High 16 mRan/hr @ 1 foot Average 0.1 mRen/hr @ 1 foot Low ( 0.1 mrem /hr @ 1 foot Should you desire additional information concerning the aoove, please contact me at (619) 455-2823.

Very truly yours,

. 9024~

Keith E. Asmussen, Manager Licensing, Safety and Nuclear Cmpliance KEA/mk cc: John B. Martin, U.S. NRC Recion V

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