ML20058L596
| ML20058L596 | |
| Person / Time | |
|---|---|
| Site: | University of California - Irvine |
| Issue date: | 06/30/1990 |
| From: | Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9008070322 | |
| Download: ML20058L596 (11) | |
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l!NIVERSITY OF CALIFORNIA, IRVINE 1..- -
e DIRKil!Y . tw15 . IRi%T .1.o5 AM4115 . ElVIR510t' . 5AN DIEGo . LAN FRANCISCO 1ANTA MRMRA . $AhTA CRL'Z u
. DEPARTMENT or CIIEMISTIW IRV1Nf, CALIiORNI A 92717 i
i August 4th,~1990 I i
U.S. Nuclear Regulatory Commission,
,y Document Control Desk, ~
Mail Station PI-137, Washington, D.C. 20555 Rei Docket 50-326, License R-ll6 Annual Report, U.C.Irvine Nuclear Reactor Facility l Gentlement l i
Picase find enclosed three copies of the annual report for the UCI Nuclear i
-Reactor Facility, covering the period July 1st 1989 through June 30, 1990. l
'This report is submitted in accordance with Section 6.7f of the Technical !
-Specifications for the facility.
Sincerely,= _i
.k, b
George E. Miller l
, Reactor Supervisor -I GEM /mm cc: Region V, NRC j
, American Insurance i Reactor Operations Committee members L.E. Overman, Chair Chemistry-W.J. Evans, Vice Chair for Facilities and Instrumentation, Chemistry H
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U.C.IRVINE Nuclear Reac'or Facility-Annual Report for July 1st 1989 to June 30th 1990 FacilityLicense R-116 Docket 50-326-Prepared in Accordance with Part 6.7f of the Facility Technical Specifications by Dr G.E. Miller Reactor Supervisor UCI Reactor Annual Report 89 Page 1
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Section 1.
Operations Operation of this facility is in aupport of the Department of Chemistry program of research and education in the use and application of radiochemical techniques and radioisotopes in chemical studies.
Reactor utilization a aart from operator training and maintenance is thus entinly for sample inadiation. Samples come from diverse origins related to forensic science, fossil fuels, geochemistry, art, and archaeological studies, chemical synthesis, industrial quality control, c;ayme studies, trace element pollution studies, etc. The reactor is also used in class work by undergraduates leaming tracer and activation analysis techniques using small quantities of short-lived activated materials.
Some use is made of the facility by other educational institutions sup 3oned by the Reactor Sharing Program of DOE since September 1st 1987. This program has invo;ved tours, class demonstrations, and analyses of samples submitted by faculty.
l A number of items have needed maintenance during this period (see Section 4), but most inspections have found the facility to be in good condition. During the annual inspection, no abnormalities were found for the fuel or control rod systems.
- An emergency drill was held or. March 30th 1990. Practice was gained in handling of a potential fire in the facility, evacuation of the building, monitoring of personnel, clean up, and re-Cutry.
Additional fuel was obtained during the year (8 1-89)in the form of one standard fuel
- element, one fuel follower control rod, and three instrumented fuel elements. These were transferred from U.C. Berkeley to this facility. They are currently stored as spares. This increased the facility quantity of U-235 on hand by 183 grams.
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UCI Reactor Annual Report 89-90 Page 2
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- w. i Section 3.
Inadvertent Scranis and Unnlanned Shutdowns TABLE 111.
Da Ihm Power Tvoc and Cause 12.83 <
9/6_ 17:37 .01w Period scram operator- error observing period meter.
9/6 17:44 30.kw Linear scram on switching into AUTO from SS. i Switching transient t 9/22 11:08 10.kw Seismic scram - seismic switch not properly set after start up test.
, No seismic activity, 10/26 12:35 100.kw Linear pwer scram on switching into AUTO from SS.
Switching transient. ;
10/30 12:30 3. w Period scram on switching into AUTO from SS.
Repeated in opposite direction at 12:33 r 0
10/30 12:39 .250kw Manual scram by operator when noticing period meter not responding properly to changes in power, .
1220 1/31 10:00 1.5 w Period scram - trainee operator error during start up.
3/13 14:36 250kw Linear power scram on switching into AUTO from SS.
Operator set demand potentiometer too high.
5/10 14:51 15kw SHIM rod dropped during operation - re?eated at 15:53 <
Light bulb in magnet circu,ti failing/faileca <
6/6 17:29 50kw Seismic scram - seismic switch not properly set after start-up test.
No seismic activity.
UCI Reactor Annual Report 89 90 Page 4 l
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Section 4 l
Maintenante and Surveillance l The following non routine maintenance activi3es were carried out during this period:
7/5/89 -The Radiation Area Monitor station in the lab area went into high alarm while the facility I was unoccu
- tested OK. pied in the evening. No excess radiation level was found. Monitor reset and L 7/13/89 - Repeat of above. No problem could be identified.
Much later, the main power supply was found to be noisy. Re 3 lacing the smoothing capacitors removed the noise and fixed the irregular alarm pro alem from this station.
7/27/89 The SERVO potentiometer adjustment knob became loose and could not be repaired. A complete new potentiometer of a different style was installed.
8/10/89 New chart recorder motors were installed as both LOG and LIN channel recorders had become so wom that smooth operation could not be obtained.
8/16/89 New capacitors were installed in the ion chamber voltage supplies to reduce ripple in the
- compensation voltage circuits. This helped reduce low level noise at the linear recorder.
8/17/89 The semi-annual rod caliorations done at this time indicated several shifts in rod worths -
that seemed larger than usual. Considerable effort was expended and failed to locate any specific c!use. Re-ccamination of rod worth data obtained over nine years indicated tha't the variations were quite large (differences of 10-15%) on several occastons, and these were not out ofline with general trends, the data were thus accepted.
9/2/89 RAM lab area alarmed at aight again (See first entry above).
10/6/89 The sample removal device used for removal of samples from the rotary specimen rack fractured during use and had to be repaired. All broken parts and samples were retrieved.
10/19/89 The monitor device installed on the pneumatic transfer system load / unload port sounded high alarm while no experiments were being conducted. Electronic malfunction had occurred. Cleaning uni: seemed to fix problem. The problem recurred on 10/26/89.
10/30/89 Period meter switch cleaned to cure problem of open circuit giving no period readings.
'l1/1/89 SHIM magaet current ON light bulb replaced after failure (rod would not raise).
11/15/89 A small (about 1 microcurie) radioactive spill occurred because an irradiated sample of bone ash broke open as it was being retrieved from the pneumatic transfer system terminus where it had been left by a fractured rabbit tube. The area was properly decontaminated from the mostly P-32 radioactivity. No personnel exposures above background were recorded.
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UCI Reactor Annual Report 89 90 Page 5 t
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N 12/12/89 Durin,g start up checks the operator reported that the FTR UP light had failed to extinguish following a scram test on the rod. The Reactor Supervisor was called and found the rod to be stuck slightly in the partly UP position from which it easily was dislodged by pressure. Regaat firings produced the same effect. The itactor was shut down, and the event reporten as an A > normal Occurrence.A full written report has been made to NRC.
The plastic piston in the underwater shock absorbed unit had cracked. A new piston was made and installed. Proper rod function was established before reactor operation was resuined. Full annual malatenance was conducted in the mean time. The refurbished rod ~
, was reinstalled on 12/26/89.
12/26/89 As part of ann.:al n 'tintenance, the console FUEL TEMPERATURE and the MODE switch were dismantled, cleaned, and lubricated for smoother, glitch free operation.
12/29/89 The LINEAR recorder amplifier was inspected as sluggish behavior was observed. The s chop xr circuit had a metal washer incorrectly installed which interfered occasionally with the c Topper operation. Conect installation cured the problem.
1/30/90 The battery back-up was replaced in the security computer system. Frequent POWER FAIL indications were being obtained.
2/90 Several slight tremors were felt during this month.(esp 2/28 and 3/2) No sign of damage was noted, and none were strong enough to trip the seismic switch.
3/7/90 - A problem was noted with the cooling system in that cooling was not effective in keepu..
pool water below 250C after a long run. The reactor can still run for several hours, so maintenance on the secondary cooling system, which will be tricky, was delayed for now. The problem may be in the controller unit and not in the piping.
3S0 - 4/90 Several false security alarms were received during this period. The problem seemed finally to be cured by readjustment of the +5 volts supply.
5/10/90 The SHIM rod dropped during a run because the magnet current ON light bulb failed.
(Readjustments to the current output were made 7/15/90 since too many occurrences of bulb failum have been noted this year.)
Section 5 Facility Changes and Special Experiments Approved No significant changes or special experiments were approved during this period.
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UCI Reactor Annual Report 89 90 - f age 6
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Section 6 Radioactive Effluent Release.
(n) Gases. The major direct release to the environs is Argon 41 produced during normal operations. Very small amounts of other gases may be released from irradiated materials in experiments.
Releases are computed based on original estimates at point of origin within the facility and taking only dilution into account. Since much of the release is from operation of the aneumatic transfer system for sam?les, this is a conservative estimate in that assumption is mace that all use of the PT is at full steac y state power level (250 kwatts) when, in fact, some use is with the reactor at a lower power level. In view of the small numbers involved, and the fact that an integrated dose -
check is provided by an environmental dosimeter (CaSO Dy) hanging directly in the exhaust at 4
the point of stack discharge,it is considered unnecessary to provide further checks of these estimates. The dosimeter data confirm that an individual standing directly in the exhaust flow for one year would receive an additional submersion dose from the exhaust less than the reliability limit of the dosimeters, or less than 20 mrem per year. The dosimeter data are presented separately in Section 7. Table IV. Over the years that data have been collected, the accumulated exposure at the exhaust location have been lower than for " control" points because oflower masses of concrete structures in the vicinity.
Release estimates based on operational parameters are as follows:
(1) Operation of pneumatic transfer system (7/1/89 6/30/90):
- a. Minutes of operation: 943. minutes
- b. Release rate assumed: 6. x 10 8 microcuries/ml
- c. Flow rate of exhaust air: 8 1.2 x 10 ml/ min i
Total release computed:(a x b x c) = 3 6.8 x 10 microcuries (2) Release from pool surface (7/1/89 6/30/90):
- a. Total hours of operation at power (Mwh x 4) = 112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />
- b. Release rate assumed: <1. x 10-8 microcuries/ml
- c. Flow rate of exhaust air: 8 1.2 x 10 ml/ min Total release computed:(a x 60 x b x c) 3
= 8.0 x 10 microcuries Total of (1) and (2) = 1.8 x 10 4 microcuries Concentration averaged over 12 months = <2.0 x 1010 microcuries/ml This remains similar to values reported in previous years and remains W.,er than MPC even assuming no dilution of the plume at the stack.
UCl Reactor Annual Report 89 Page 7 s
3 (b) Lioulds and Solids.
Liquid and solid wastes from utilization of by product materials are disposed through a University contract. Waste is transferred to the custody of the Campus Environmental Health and .
Safety Office (E,H&S). Direct disposals from this facility are given below. It is important to note that activity values are estimated at the time of transfer to E,H&S control. In all instances, considerable time elapses before final shipment from campus, so that substantial decay may occur for medium-lived radionuclides.
DRY WASTES: 14 cubic feet - less than 26 microcuries mixed activation products LIQUIDS: 2 gallons - estimated less than 1 microcurie. Most of this was from stud nt laboratory work and involved tritium activity and I-125 activity that was purchased on State of Califomia license, and not produced from the reactor.
Section 7.
' Environmental Surveillance.
Calcium sulfate / Dysprosium thermoluminescent dosimeters in packs supplied by the Radiation Detection Company, Sunnyvale, Califomia are placed at nine locations around the UCI us in a wood frame house in University Hills. In Campus. One fact, the average pack of the moreisremotely kept on the edge of camp' concrete environment" located packs on campus the background for comparison purposes, since a mo e similar microenvironment is experienced by such packs.
Table of Locations.
- 1. Window of reactor room (inside the facility).
- 2. In hallway between reactor laboratories and the radiochemical laboratory.
- 3. Loading dock, adjacent to west wall of reactor room.
- 4. Laboratory 152, directly over reactor facility, approximately over core center.
- 5. In roof exhaust air flow from reactor room, roof level.
- 6. Steinhaus Hall (Biological S:lences building),4th floor.
- 7. Main library building across campus,5th floor office.
- 8. Computer Science building,4th floor office.
- 9. Fume hood exhaust, roof level, from reactor laboratory.
10.12 Perkins Court, University Hills, private residence.
(wood frame house) l UCI Reactor Annual Report 89 90 - Page 8 i
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Table IV shows the data as received from RDC for the period. All levels are as expected and are -
similar to those reported in recent years. 'As noted before, areas (1) and (2) are also partly
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controlled so that maximum possible exposure to an individual in an uncontrolled area is very - !
minimal at this facility with current operations. The air released from the facility (measured by -
locations #5 and #9) continues to give no detectable exposure above background for dosimeters ,
immersed in it. Location 7 consistently shows higher readings presumably because it is on a warm, outside cement wail.
TABLEIV.
Environmental Dosimetry Data.
1989-1990 Averace Exposures in mr.
Location. DuartcI Total Totalless 2/89 3/89 4/89 1/90 backcround (35631) 1 15 7 14 9 45 10 2 20 7 12 9 48 13 3 3 10 lost 11 10 31*
- 4 4- 6- 4 3' 17 0-5 6 5 6 6 23 t 0
6 10 7 12 9 '38 3 7 17 - 7. 17 14 55 20
'8 5 1 2 3 11- 0 9 7 6 6 5 24 0
-10 2 3 1 1 7 0 Average of 6,7,8 used for " background" ( = 35) 4 1
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UCI Reactor Annual Report 89 90 - Page 9 I
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Section 8.
Radiation Exoosure to Personnel; The annual exposures reported as a result of finger dosimeter ring and film badge dosimetry am pmsented in Table V, Much of this exposure is acquired in the course of isotope handling experiments, and in some instances has been accumulated in areas outside the facility, in locations licensed by the State of California. A substantial exposure is experienced by some individuals during requimd calibration of radiation monitoring equipment. 1 Thirty-two(32) prsons were monitored on a contmual basis using film badges, and all of these were also issued with f!nger dosimeter rings, These were required to be worn while handling isotopes. Film badges were generally worn at waist level by all personnel. An additional thirty-five(35) students were issued badges during the Fall quarter,1988 for a laboratory course in radioisotopes, during which they spent some hours in the facility. These exposure listings have been includedin this table.
Certain additional monitoring is done of visiting individuals who are issued with direct reading pocket dosimeters in addition to film badges and finger dosimeter rings.
Contaminations surveys consisting of wipe tests and G-M surveys have shown significant, l removable contamination in areas comir.g into direct contact with samples removed from the reactor,and on sample handling tools.
TABLE V.
Personnel Exoosure Summarv for 7/1/89 to 6/30/90 (in mrem)
Individuals Whole flody Fincer Rine Deep $ hallow $ hallow ~
1 55 610
- . 1 0 30 0
1 20 20 0 '
1 20 20 0 l
1 0 0 90 -
l 1 0 0 70 L 1 0 0 60 l 19 0 0 0
- l. 15 0 0 (students in class)
Totals 5 5 J21 .00 Additional aggregated data from self reading dosimeters:
1 45 (4 visits) ;
l-1 30 (4 visits) 1 29 (2 visits) 1 6 (1 visit) 12 0 l
UCI Reactor Annual Report 89 90 Page 10