ML20101B288

Annual Rept for 830626-840630

ML20101B288
Person / Time
Site:	University of California - Irvine
Issue date:	06/30/1984
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:	NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
References
NUDOCS 8412200233
Download: ML20101B288 (15)

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U.C.IRVINE Nuclear Reactor Facility Annual Report. -

for June 26th, 1983 to June 30th, 1984 Facility License: R-116 Docket: 50-326 Prepared in Accordance with Part 6.7f of the Facility Technical Specifications by Dr G.E. Hiller Reactor Supervisor 8412200233 840630 PDR ADOCK 05000326 R PDR

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l Section 1.

Operations l

l Operation of this facility is in support of the Department of l Chemistry program in research and education in the use and application of radiochemical techniques and radioisotope utilization in chemical studies.

Reactor utilization, apart from operator training and maintenance, is thus entirely for . sample irradiation. Samples come from diverse origins related to forensic science, fossil fuels, geochemistry, art and archeological studies, chemical synthesis, industrial quality control, i enzyme studies, trace element pollution, etc. The reactor was also used in t class work by' undergraduates learning tracer and activation analysis -

techniques.using small quantities of short-lived activated materials.

I 10 research students and 2 post-doctoral associate have used the i-facility under the guidance of three faculty in Chemistry. These include l.

l visiting students from Brazil, and West Germany. Currently the facility

1. has 2 licensed senior operators.

No major changes have been made in this period to the facility. The I

annual inspection of core components indicated that all fuel elements and control rods were in good condition.

j Operations in general have been higher than last year, partly because l the facility has seen additional use by UCLA researchers following shutdown of the UCLA reactor. Data on the operations is presented in Section 2.

Difficulties were experienced on June 30th/ July 1st with the adjustable transient rod (ATR). This was reported as -an abnormal occurrence to the NRC and a copy of the written report is attached as Appendix A. Subsequent to that time, further and more complete cleaning of the air supply system and buffer tanks was necessary, as solenoid valve operation irregularities recurred. During the year some difficulties were

! experienced with the SHIM and REG rod drive mechanisms. Complete overhaul I

j was finally carried out at the end of the summer of 1984 to cure these l problems. Unusually humid and warm weather for two successive summers l-seems to have been to blame for this need.

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While unloading samples on October 10th,1983, the operator " fished up" a small metal bracket that must have been wedged in the rotating sample rack for some time. This was highly radioactive ( atiove 20 R/hr ),

but was eventually removed and handled with minimal personnel exposure.

The bracket formed part of a sample handling device broken over a year earlier.

NRC inspections for security and for radiological safety have been carried out during this period. As a result of the second inspection, a citation was issued regarding the lack of meetings of the Reactgr Operations Committee. No other items of non-compliance were identified.

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Section 2.

Data ~ Tabulations for the Period June 26th,1983 to July 1st, 1984 TABLE I.

Experiment approvals on file 8 Experiments performed (including repeats) ,

304 Samples irradiated 2951 Energy generated this period (Megawatt hours): 45.6 Mwh Total, 69 element core 127.0

>74 element cores 819.8 Total energy generated since initial criticality: 939.8 Mwh Pulse operation this period: 13 of which greater ~than $2.00 insertion: 13 Total pulses to 6/30/84 688 Hours critical this period: 289

Total hours critical to date

5009 Operator training and requalification, hours: 7 Inadvertent scrams or unplanned shutdowns: 14

! Visitors to reactor - admitted: 978 Maximum dosimeter recorded for visitors: 0 mrem l Visiting researchers (dosimeter issues): 112 Maximum dose recorded: 1 mrem j Visiting researchers (badged): 4 l

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TABLE II.

Reactor Status 6/30/84 Fuel elements in core (including 2 fuel followers): 80 Fuel elements in storage (reactor tank) - used: 28 Fuel elements unused (instr.umented element): 1 Graphitie~ reflector elements in core: 34

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Graphite reflector elements in reactor tank storage: 0 Experimental facilities in fuel elemeni positions: 4 Water filled fuel element positions: 7 Core excess, cold, no xenon: $2.83 Control rod worths (1/18/84):

REG $2.85 SHIM $3.68 .

ATR $1.79 FTR $0.67 Total: $ 8.99 Maximum possible pulse insertion: $2.46 Maximum peak po u r attained (5/29/84) ($2.46 insertion) 1040 Mwatts Maximum peak temperature observed (8-ring) 228 C 5

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• Section 3.

Inadvertent Scr,ams_and , Unplanned Shutdowns TABLE III.

Date Time Power Type and Cause INJ IDSUI 15:56 250 kw Shim rod drop. Operator touched CONT /0N button.

6/28 16:12 -250 kw Shim rod drop again - this time lamp burned out.

7/1 1.5 w ATR rod raised inadvertently by cylinder. See report.

8/17 11:33 250 kw Manual scram. Incorrect samples placed in core.

8/25 11:38 3w Period scram - operator inattention during start-up.

9/7 13p46 3 kw Linear scram - operator range switch error.

10/12 11:27 250 kw HV and power scram -

power problems at supply.

Experiment terminated for day as noise continued.

1984 T7rE 10:59 1.5 w Linear power scram. Operator range switching error.

1/19 11:59 250 kw Manual scram. Sample terminus alarm sounded on sample return. Sample moved to lead shield.

2/16 10:06 <1.5 w Seismic scram. Incorrect reset after start-up tests.No observable seismic activity.

4/5 10:46 250 kw % Power scram. Meter at 102%, sample loading irregularity caused chamber fluctuations.

4/10 11:56 250 kw Manual scram. Experimenter using delayed neutron system reported sample had not returned. Sample retrieved by continued operation of transfer system. -

5/26 12:55 1.5 kw HV scram. Momentary building power failure.

5/29 19:28 100 w Linear scram. Trainee error in range switching.

5/29 20:15 300 w Linear scram. Trainee error in range switching.

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Section 4.

Maintenance and Surveillance.

All critical items (fuel elements, controT " rods, detector systems) continue to be found in good condition during routine inspections. There are a few new and recurring items given special attention this year.

The following special items were noted this year:

(a) Rod drive mechanisms (see also Appendix A.') .

A number of problems were noted with " sticking" rod drives, both SHIM and REG. Usually the system would respond to cleaning and spraying with silicone lubricant - but only for a while. This problem was particularly noticeable during hot humid weather, especially when air conditioning systems were down, or not coping. Eventually a drive was dismantled.and taken to the reactor manufacturer for inspection. The diagnosis was that the " plastic" seals through which the draw. tubes slide had swollen with moisture absorption, thus causing insufficient clearance. The seals were lapped down on inner and outer surfaces, and the rod drives now behave as required.

The ATR and FTR drive air systems needed extensive cleaning. The first attempt failed to note that metal turnings, from tank port threading, were still residing in the b ttom of one of the buffer supply tanks. Since the tanks were removed from under the bridge and carefully scoured, no further problems have occurred.

(b) In order to facilitate adjustment of ion chamber heights during power calibration activities, slight modifications were made in how the ion

• chamber supports are fastened to the side of the reactor tank.

(c) The pneumatic tube sample system blower was serviced on 4/27/84. New bearings were needed to replace " seized" ones. The system now functions well.

Section 5.

Facility Changes and Sp_ecial D eriments,, Approved. _

No significant changes or special experiments were approved during this period.

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Section 6.

Radioactive Effluent Release,s,.,

(a) Gases. The major direct release to the environs is Argon-41 produced during normal operations. Very small amounts of other short-lived gases may be released from irradiated materials in experiments.

Releases are estimated based on original estimates at point of origin within the facility and taking only dilution into account. An integrated dose estimate is provided by an environmental dosimeter (calcium sulfate-dysprosium) hanging directly in the exhaust at the point of stack discharge. This is changed and read quarterly. The results substantiate the projection that the submersion dose to an individual standing continuously in the stacM discharge for one year would be less than the combined reliability limit of t.he four dosimeters, or less than 20 mrem per year.

The exact ouarterly dose readings obtained are given in Section 7 of this report. The location is location 5 in Table IV.

Release estimates are as follows:

(1) Operation of pneumatic transfer system (6/26/83 - 6/30/84):

Total time of operation (assumed to be at 250 kw): 2649 minutes.

Release rate assumed 6 x 10-8 microcuries/ml F1'ow rate of exhaust air 2 x 10 6 ml/sec Total release computed 1.9 x 10 microcuries (2) Release from pool surface (6/26/83 - 6/30/84)

Total hours of operation at power (Mwh x 4) 182 hours0.00211 days <br />0.0506 hours <br />3.009259e-4 weeks <br />6.9251e-5 months <br />

-8 Release rate assumed <1 x 10 microcuries/ml Flow rate of exhaust air 2 x 10 6 ml/sec Total release computed <1.3 x 10" microcuries Total of (1) + (2) = 3.2 x 10 0 microcuries Concentration averaged over 12 months = <5 x 10-10 microcuries/ml This is higher than the level reported last year because of increased operations and remains lower than MPC even assuming no additional plume dilution at the stack.

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(b) Liquids and - Solids. Liquid and solid wastes from utilization of

- by-product materials are disposed throug;t a University contract. Waste is transferred to the custody of the Campus Environmental Health and Safety Office for final packaging and shipping. Wastess from . filters in the pool water cooling system are also disposed in this way. Spectrometric measurements indicate that these are contaminated withrmedium and short-lived by-product isotopes in low quantities.

Some of the materials generated in experiments in this facility are transferred to other users operating under State of California license and final disposal of. such materials is not under the control of this facility.

Disposals by the facility were as follows: (activities are estimated as of time of transfer to E, H and S control).

Dry wastes: A cubic feet - 3 microcuries mixed activation products.

Liquids: 7 gallons 74 microcuries mixed activation products.

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Total: 77 microcuries e-

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s Section 7.

Environmental Surveilla.nc,e,.

Calcium-sulfate:Dysprosius thermoluminescent dosimeters in packs supplied by the Radiation Detection Company, Sunnyvale, California are placed at nine locations around the U.C.I. campus. One pack is kept off-campus in a wood frame house (second story) as a control. The average of the remotely located packs on campus is in fact used as a " concrete environment"

. background for comparison purposes for evaluation of' packs placed closer to the facility.

Table of Locations.

1. Window of reactor room ( inside the facility ).

2. Between_ reactor laboratories and radiochen.ical laboratory, in hallway.

3. Loading dock, adjacent to west wall of reactor facility.

4. Classroom 152, over reactor facility.

5. In roof exhaust air flow from reactor room.

6. Steinhaus Hall ( Biological Sciences building ), 4th floor.

7. Library building across Campus, 5th floor office.

8. Computer Science building, 4th floor.

9. Fume Hood exhaust, roof level, from reactor laboratory.

10. 17941 Spicewood Way, Irvine. (Control location about 2.5 miles from Campus)

Table IV shows the data as received from RDC for the period. All levels are as expected. Those above background reflect the neutron generator operating schedule (nitrogen-16 formed in the cooling water) and sare essentially similar to those reported in prior years. As noted before, areas 1 and 2 are partly controlled so that the maximum possible annual dose to an individual in a true 'off-site' location would be estimated to be less than 40 mrem ( above background ) from operations at this facility, using this data. The main and fume hood exhaust dosimeters continue to show no detectable dose, above background, in the exhaust stacks from the facility.

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TA8LE IV.

Environmental Desimetry Report Data.

1983-84.

Average Exposures in mr.

Location. Quarter. Total. Total less Backaround ~

2 3 4 1 (71 + 18) l 54 122 31 15 222 151 2 . 46 40 31 14 131 60 3 . 26 21 16 11 74 3 4 32 22_ (missing) 4 (58) 0 5 25 18 8 7 58 0 6 42 15 18 15 90 (19) 7 34 19 11 13 77 ( 6) 8 26 12 4 4 46 (0) 9 29 (missing) 22 13 (64) 0 10 49 7 6 5 67 0 Average of locations 6,7,8 used for background.

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Section 8.

Radiation Exposure to Personnel.

The annual exposures reported as a result of finger-ring and film badge dosimetry are presnted in Table V. Essentially all of these exposures are acquired in the course of isotope handling experiments and in some instances will have been accumulated in areas outside the facility, lic'ensed by the State of California.

Twenty-four (24) persons were monitored on a continual ~ basis using film badges, of these nineteen (19) were also issued finger rings. These ~ were required to be worn while handling isotopes. Film badges were generally worn at waist level by all personnel. An additional twenty-eight (22) students were issued badges and finger rings for nine weeks during a laboratory course in Radioisotope Techniques. They entered the facility for some of their experiments, but not for all. Their exposure records have not been included in this listing.

Contamination surveys consisting of wipe tests and G ?4 surveys have shown significant cenovable contamination in isotope handling areas. No other contamination areas have been found.

TABLE V.

Personnel Exposure Summary for 5/1/83.to _6/3_0/84 (in mrem)

Individuals Whole Body Finger-Ring Pen Non-pen 1 130 0 0 1 20 0 120 1 0 0 540 1 0 0 380 1 0 0 310 1 0 0 240 1 0 0 200 1 0 0 180 1 0 0 70 10 0 0 0 5 0 0 not issued 12

APPENDIX A.

UNIVERSITY OF CdLIIORNIA, IRVINE sensun unn . invar . un main nivenm . un ruco . un inman I; uun sana 4n4.uun oum

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samansarror cuEnerav IRVINE, CAUfoANIA 92717 .

July 8,1983 U.S. Nuclear Regulatory Commission Chief, Standardization and Special Projects Branch, Division of Licensing, ,

Washington D.C. 20555 Re: Docket 50-326, License R-116

~ Incident Report for July 1,1983 Reported under Tech . Specs: 6.7.c.3. (abnormal occurrence)

Gentlemen:

An abnormal event occurred Juiy 1,1983 at the UCI Nuclear Reactor Facility.'

During a series of step 1nsertions to generate maximum power and temperature curves, the adjustable transient rod cylinder was withdrawn to a height corre-sponding to a'$2.00 insertion. At the upper limit of the cylinder's travel, ,

, the control rod began to withdraw. The reactor was critical at 1.5 watts and power increased to approximately 1.6 watts with a 20 second period.

The reactor was immediately shut down. This. incident was reported the same day to D. Sternberg of the NRC Region V Office.

Inspection of the cylinder's interior did not indicate a problem. Light ,

oil was applied to the inside walls.This seemed to alleviate but not entirely eliminate the sticking of the piston during cylinder travel.

Another transient rod has experienced similar problems this past month.

Both transient rods are serviced by the :,ame air system, so suspecting the problem may be due to contamination, this system was dismantled.

Fine dirt had accumulated in the air trap since it was serviced during monthly maintenance. ,Some dirt had passed through the trap and filter and entered the buffer tanks which supply air to the rods at 80 psi. These 6 .

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tanks, valves, traps and air hoses were removed and cicaned. The permanent filty in the air trap was cleaned of accumulated debris. Each transient rod was opened, cleaned thoroughly with solvent and lubricated.

Specifications by General Atomics, manufacturer for the TRIGA Reactor,

. call for clean, dry air to be used in the transient rod operation. While

- the air trap is cleaned monthly, the permanent filter attached' to the system is not scheduled for regular maintenance. It is felt that it became overloaded and was no longer able to strain debris from the system. Regular maintenance of this item will most likely be added to our schedule.

When the. system was reassembled each cylinder was tested thoroughly and no problems have since occurred. All rod drop times were in the normal range consistent with values obtained during tests over the last 2 years.

Repairs to the rods and air system have been inspected and approved by the Acting Reactor Supervisor. '

The Facility will continue to operate on a conservative basis in the ,

steady state mode only until Dr. George Miller, Reactor' Supervisor, returns in August. All pulsing operations will be delayed until repairs to the rod

, systems and ala delivery systems have been inspected again and approved by the Reactor Supervisor. Inspectihn of the air system will be made frequently - -

during this time to avoid any further problems. ,

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cerely, ,

Patricia J. gers,

- Acting Reactor Supervisor cc: NRC Region V .

W.Lillyman, The Vice Chancellor V.P. Guinn, Chair, ROC ,

Member, ROC er G.E. Miller, Reactor Supervisor e

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DEPARTMENT OF CIIEMISTRY IRVINE, CALIFORNI A 92747 December 3rd, 1984 U.S. Nuclear Regulatory Commission, Document Management Branch, for Division of Licensing, Washington, D.C. 20556 Cocket: 50-326 Gentlemen:

Enclosed are twelve (12) copies of an annual report for the UCI Nuclear Reactor Facility. I regret that there has been some delay in getting this ready and printed uo for distribution. It should have been delivered in August.

This report is submitted in accordance with the Technical Specifications for the reactor.

Sincerely, a .

George E. Miller Reactor Supervisor

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