ML20154B465

Annual Operating Rept for 1985

ML20154B465
Person / Time
Site:	General Atomics
Issue date:	02/27/1986
From:	Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	Thomas C NRC
References
38-8072, NUDOCS 8603040311
Download: ML20154B465 (7)

Text

! -v In Reply G A Technologies Inc. Hefer To: 38-8072 PO BOX 85608 February 27, 1986 SAN DEGo. CAUFORNtA 92138 (619) 455-3000 Mr. Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of 1,1 censing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l

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Subject:

Facility Licenzo R-38; Docket 50-89 l Submittal of Annual Report (3 copies)

Dear Mr. Thomas:

The folicwing is an annual report required by the applicable Technical Specifications of the Mark I TRIGA reactor. The present report covers the operation for the year 1985. The numbered sections below are those referred to in Section 9.6e of the Technical Specifications.

Part I A brief narrative summary of (1) operating experience (including experi-

, ments performed), (2) changes in facility design, performance charactor-l istics and operating procedures related to reactor safety occurring dur-ing the reporting period, and (3) ret ults of surveillance tests and in-spections.

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1. The Mark I reactor was operated during the year to provide 287 pulses (10703 to 10989) and numerous steady-state irradiations for experiments. The cperations included: activation analysis, neutron radiography, King furnace high-temperature studies of reacter fuel, numerous irradiations of samples or pleces of equipment, trotning i and requalification exercises for operator trainees, and testing of corrnercial instrumentation.

2. No changes in facility design, performance characteristics, or op-  ;

erating procedures related to s'afety occurred durin6 this reporting l period.

l l 3. The surveillance tests and inspections were performed as required by l Sections 3.0, 4,0 and 5.0 of the Technicai Specifications. Sorre re-sults are presented below.

Fuel Surveillance i

, The fuel was inspected visually and for bending and length changes l

December 16-17, 1985. All elements except two were satistnotory.

These two elements, Nos. 1671 and 3173, were snug or tight in the 1/32-inch bend jig. They both passed the 1/16-inch bend jig test. 30 f

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! However, both were difficult to remove from the core and do not I slide into some core positions. These two elements have been re- +

moved from further service.

Control Rod Surveillance The visual inspection for deterioration was conducted December 18, ,

1985. All control 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, clean-ed as required, lubricated, and reassembled on July 1, 1985 and December 18.-1985. 'A rubber boot in the shock absorber was found to have a crack. The rubber boot is not essential but will be re- " "

placed in the future. i Reactor Safety Systems As specified in the Technical Specifications Channel Tests of the ',

reactor safety system channels, Channel Calibraticns of the Power  ;

Level monitoring channels, Calibration of the Temperature measuring .

channels, Channel Checks of the power-level measuring channels, and Channel Checks of the fuel-clement temperature measuring channels

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were performed. The tests were performed at least as often as re-quired, and the results were satisfactory. In no case was a re-quired safety channel' scram found to be operating outside the speci-fied safety limits. The reactor power-level monitoring channels '

j were calibrated at least monthly during the reporting period, the j last in the year on December 19, 1985. Three of these monthly tests required changes in the calibration of at least one of the'five chan- ,

nels by an amount greater than 5%.

4 The monitor and survey systems were under. surveillance during the  !

reporting period. The frequency of onlibrations was as indicated below.

Continuous Air Monitor Alarm setpoints were checked daily. The system was calibrated semi-annually with three U-235 sources in front of detector (600 ets/ min, 1500 ets/ min, 5000 ets/ min).

[gerline Area Monitor _s Operation was checked daily; alarms were activated in response to a source nVory two weekst calibration was performed semiannually with a 44C1.cs-137 source.

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Cecil 0. Thomas 38-8072 Part II A tabulation showing the energy generated by the reactor (in megawatt-hours).

The energy generated in 1985 by the Mark I was 48,143 9 kilowatt-hours (48.14 megawatt-hours).

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.

i Seven unplanned scrams occurred during the year. None had essential j safety implications. The details are as cited below.

1. Ap_r_il 10 1985. A scram from full power was caused by flux tilt in the core during a neutron radiography run. The operator neglected to set the auxiliary power channel go full scale as is usually done during this operation. As a result the flux tilt scrammed this chan-nel. No safety implication.

2. May 16, 198Q. A less experienced RO (licensed) caused a scram on Percent Power (1) during a neutron radiography run by not realizing

, the effect of flux tilt. Operator error; no safety consequence.

l 3 May 17. 1985 Scram from 250 KW when operator noticed that Fuel Tem-perature #1 was reading "0". By jiggling the TRIP TEST switch, he inadvertently caused a scram. Even without this channel, two other temperature channels were functioning correctly. No safety implica-tions.

4&5. May 24 1983. A less experienced R0 (licensed) caused a scran from full power by not taking account of the fluctuation in power reading caused by a rotating Lazy Susan (sample irradiator), A second scram on the same channel occurred on restart. Operator error. No safety implications.

6 May 31, 1985. The Magnet GN lamp burned out. This caused the REG ROD to scram automatically. The light bulb was replaced and operation returned to normal. No safety implication.

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7. August 22, 1985. The Fuel Temperature #1 thermocouple opened during a run, causing the FT #1 temperature meter to go full scale causing a scram. There was no safety implication because adequate addi-tional temperature channels were in use.

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Cecil 0. Thomas g 38-8072

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i i Part IV s

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Discussion of the major maintenance operations performed during the l period, including the effect (if any) on-the safe operation of the reactor, and the reasons for any corrective maintenance required, t

1. Maintenance was required on the electronic system in 1985. The fol-lowing sections detail these efforts.

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a. March 21, 1985. It was observed that the linear recorder'indi-cation shifted when changing from MANUAL,to AUTO mode. The trouble was traced to wiring that had become loose and was .

shorting the negative voltage post to the ground terminal post.

No effect on Safety Channels.

b. June 14. 1985. The rod position in'dicators for REG and SAFE '

rods failed. The old type indicators, which are no longer 1

available, were replaced by tha. new type installed on the Mark

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F console last year. Improved rdadab'ility resulted from use of the new type rod position,indi'cator._

c. August 26, 1985. The TRIP TEST switch failed for Fuel Tempera-

! ture #1. On September 10, 1985 the TRIP TEST switch was re-placed with a new unit. There were no safety implications since adequate other temperature channels were in use.

! 2. Maintenance was required on thesontrol rod drives in 1985. The i details follow. ,

s. February 4 1985. The drive shaft pinion gear drift pin fell i

out making it imoossible to drive the rod up or down. The rod, ,

, of course, was properly in the core. No safety implication. ,

I b. March 4, 1985_. The SHIM Rod drive was replaced with a spare.

3 This unit was reworked to eliminate intermittent problems ob-I served recently. This rod drive was reinserted in the system

', on August-7, 1985, and tested acceptably.- There were no safety 3 problems associated with this maintenance, only annoying opera-tional problems. "

I c. March 4. 1985. Reinserted a drift pin of proper size in Reg l Rod pinion gear. See a. above.

i d. May 28, 1985. The Reg Rod Magnet. winding opened. The Magnet

- head was replaced with a' spare unit. A replacement spare was ordered, t e. September- 10-24,_1985. The SHIM rod drive assembly was re-

- placed with a repaired spare'which had incorrectly wired limit switches and motor drive wiring. A number of wiring repairs t were made and the working unit was finally installed.

Cecil 0. Thomas 38-8072 3 Maintenance on the fuel temperature instrumented fuel elements was performed in 1985. The details follow.

a. August 22, 1985. The last of the three thermocouples in TC 5927 failed. In the future, TC 5927 will be used for core ex-cess reactivity adjustment in the "F" ring. Element TC 2122 will be used for FT (fuel temperature) #1 safety channel, No safety implication,

b. August 28, 1985. A new TC fuel element (TC 6581) was installed This was used for FT #1 Safety channel. No safety implication.

4 Maintenance was performed on the radiation monitoring system in 1985. The details follow,

a. January 18._1985 - The AC cable to the Mark I CAM was replaced.

This resulted in the use of an adequate plug size and less heat-ing at the plug. No safety implication.

b. February 7. 1985. GEL batteries were installed as replacements in the RM-14 units for AIR and WATER monitors. No safety impli-cation.

c. October 24, 1985. The fan belt on the ventilation fan motor for Mark I reactor room system was replaced.

Part V A summary of each change to the facility or procedures, tests, and ex-periments carried out under the conditions of Section 50.59 of 10 CFR 50.

No new applications of 10 CFR 50.59 were made during 1985. The 50.59 ap-plication discussed in last year's Annus1 Report has yet to be modified as needed. The new digital console is still in development by ELEC-TRONICS and has not yet been tested at the TRIGA facility beyond the tests already described last year and which continued into 1985.

Part VI A summary of the naturo and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee is measured at or prior to the point of such release or discharge.

During the calendar year 1985, 0.09 curies of Argon-41 were released from the facility to the atmosphere.

All liquid and solid wastes are transferred to GA's SNM-696 Licensed Waste Processing Facility for ultimate disposal by an authorized disposal vendor.

Cecil 0. Thomas 38-8072 Part VII A description of any' environmental surveys erformed outside the facil-ity.

There have been no significant changes to the Enviror. mental Surveillance Progr am during 1985. ,

Part VIII A summary of radiation exposures received by' facility personnel and visi-tors, including the dates and time of significant exposure, and a brief.

summary of the results of radiation and contamination surveys . performed within the facility.

Facility Personnel Whole Body Exposures fur the Year 1985 (Rem):

Number of Employees Monitored High Low Average 18 0.485 0.025 0.228 Nonfacility GA Personnel Whole Body Exposures for the Year 1985 (Rem):

Number of Employees Monitored High Low Average 81 0.700 0.000 0.019-The majority of these exposures were received at other facilities at the GA site.

Contractor / Customer Personnel Whole Body Exposures for the Year 1985 (Rem):

Number of Persons Monitored High Low Average 1

96 0.760 0.000 0.053 Visitor Whole Body Exposures for the Yeah 1985 (Rem):

Number of Persons Monitored

_ .Hh Low Average 7 0.000 0.000 0.000 Routine Wipe Surveys High Wipe 227 6 dpm/100 cm 2 Avorage Wipe. <25 6 dpm/100 cm Low Wipe <25 6 dpm/100 cm 2 L,, __~___i_________.__

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Routine Radiation-Measurements ,

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H* gh 150 mR/hr 9 1 foot [

Average 2 mR/hr @ 1 foot i Low 0 mR/hr @ 1 foot

. I Should you desire additional information concerning the above, please contact me'.at: .,

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'I i ' GA Technologies Inc.

\P'.0. Box 85693 San Diego, CA 92138 '

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i. Telephone: (619) 455-2823 Very truly yours, l Keith E. Asmussen Manager, Licensing &

i Nuclear Material Control

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he cc: John B. Martin, U.S. NRC, Region V l-I i

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