ML20077J898

Annual Rept for Uci Nuclear Reactor Facility for Jul 1990 - June 1991

ML20077J898
Person / Time
Site:	University of California - Irvine
Issue date:	06/30/1991
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9108050228
Download: ML20077J898 (10)

Text

m UNIVERSITY OF CALIFORNIA, IRVINE _.

staKrttY e DAVIS e IRV1NE e LOS ANGELE5 e k!VERSIDE e $AN DifGO e SAN FRANCISCO SANT A BARBARA e SANTA CRU2

. DEPARTMENT OF CHEMISTRY IRVINE. CALIFORNIA 92717 NUCLEAR REACTOR FACILITY SUPERVISOR: DR. O.E. MILLFR TEL-(714) 8546649 OR 714-85&6082 U.S. Nuclear Regulatory Commission July 26th 1991 Document Control Desk Mail Station F1-137 Washington, D.C. 20555 Re: Docket 50-326. License R-116 Annual Renort Submittal. Tech Spec 6.7f Ladies / Gentlemen:

Please find enclosed three(3) copies of the annual report for the UCI Nuclear Reactor Facility, covering the period July 1st 1990 through June 30th 1991. This report is submitted in accord with license regulations and Technical Specifications as referenced above.

Sincerely,

( k1b.

George E. Miller Reactor Supervisor GEM /mm cc: Region V, NRC,1450 Maria Lane, Suite 210, Walnut Creek CA 94596 American Nuclear Insurance, The Exchange,270 Farmington Ave, Farmington, CT 06032, Policy NF-176 Reactor Operations Committee members and alternates W.J. Evans, Vice Chair, Chemistry l

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i U.C.IRVINE Nuclear Reactor Facility Annual Report for July 1st 1990 to June 30th 1991 Facility License R-116 Docket 50-326 Prepared in Accordance with Part 6.7f of the Facility Technical Specifications by Dr G.E. Miller Reactor Supervisor i

UCI Reactor Annual Report 90 Page 1

Section 1.

Operations Operation of this facility is in support of the Depanment of Chemistry program of research and education in the use and application of radiochemical techniques and radioisotopes 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 archaeological studies, chemical synthesis, industrial quality control, enzyme studies, trace element pollution studies, etc. The reactor is also used m class work by undergraduates learning tracer and activation analysis techniques using small quantities of short-

lived activated materials.-

l Some use is made of the facility by other educational institutions supported by the Reactor L Sharing Program of DOE since September 1st 1987. This program has involved tours, class demonstrations, and analyses of samples submitted by faculty.

A number ofitems have needed maintenance during this period (see Section 4), but most

. inspections have found the facility to be in goed condition. During the annual inspection, no abnormalities were found for the fuel or control rod systems.

An emergency drill was held on June 5th 1991. Practice was gained in handling of an intruder / terrorist and taking of hostages in the facility. Tested were coordination of response with the campus police and communication with administration and the public information ofDce

- Lessons learned included the fact that such drills need very careful planning to avoid creating dangerous uncertainty as to whether the situation is real or is a drill, One abnonnal occurrence was reported during this period. A circuit breaker failure occurred in the low voltage power supply in the continuous air monitor (CAM) that was not noticed l until the reactor had been operated for a while. The required notincation and follow-up reports were made to NRC. As no release of radioactivity occurred, there was no actual hazard to individuals.

L UCI Reactor Annual Report 90 91 - Page 2 l

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1 Section 2.

Data Tabulations fodhe Period Julyh.J9911to June 30th.1991 IAliLE I.

Experiment Approvals on file- .

8 Experiments performed (including repeats) 127 Samples irradiated 832 Energy generated this period (Megawatt hours) 20.5 Total,69 element core = 127.0

>74 element core = 1075.0 Total energy generated since initial criticality - 1202 Mwh Pulse operation this period- 0 Total pulses to 6/30/89 941 Ilours critical this period - 119 Total hours critical to date 6530 Inadvertent scrams or unplanned shutdowns 3 Visitors to reactor - admitted 540 Maximum dosimmer recorded for visitors 0, mrem Visiting reseamhers (dosimeter issues) 35 Maximum dose recorded 11. mrem Visiting researchers (badged) 5 TABLE !I Reactor Status 6/30SO l Fuel elements in core (including 2 fuel followers) 82 Fuel elements in storage (reactor tank used) .

25 Fuel elements unused (4 instrumented elements + 1 element + 1 FFCR) 6--

Graphite reflector elements in core 33 Graphite reflector elements in reactor tank storage 1 Water filled fuelelement positions 6 Experimental facilities in core positions 4 Non-fuel control rods 2 Total core positions accounted 127

! Core excess, cold, no xenon $2.96 Control rod worths (1/21/91)

REG $2.92 L SillM $3.66 L A'IR $1.80 EIR 50.75 Total: 59.13 Maximum possible pulse insertion $2.54 Maximum peak power recorded (9/8/89) (no pulses made this report period) 980. Mw -

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! Maximum peak temperature recorded (B-ring) 270." C UCl Reactor Annual Report 90 91 - Pago 3 l

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Section 3.

Inadvenent Scrams and Unolanned Shutdowns TABLE IIL Dale Iime Power Tyne and Cause i

1220 7/13 12:15 30 w SHIM rod dropped. No magnet contact. Lamp failed, replaced, and magnet current adjusted to lower value to prolong lamp life. l 1

7/17 22:07 - 220 kw Linear scram on switching from AUTO into SS at 80% power. I Switching transient j 1221 5/15 09:16 250 kw  % Power and period scram after loading additional sample tube into rotating specimen rack. (Period scram initiated by % Power scram shutdown.)

Section 4 Maintenance and Surveillance

'Ihe following non-routine maintenance activities were carried out during this period:

7/15SO -Bulb replaced in SIIIM magnet current indicator after failure. After replacement, magnet current found to be higher than specified and was reduced by potentiometer adjustment to

spec value.

7/17/90 - A revised version of security system software was installed to fix a problem with Auto-Alarm Setup not always functioning.

9/t4/90 - CAM low voltage power lost during a reactor run. Reported as Abnormal Occurrence.

See separate report for details.

10/18/90 - facility inspected following small earthquake. No sign of damage. Motion sensor tripped by quake, but reactor seismic trip was not tripped. Reactor not in operation during quake.

10/25SO Portal monitor malfunctiwed, alarming all channels. Checked and reset all detectors, replaced RESET lamp which had failed.

I1/ ISO New 50% time radiological safety staff person commenced duties at facility (S. Kent) i- 11/29B0 Security system monitor screen failed to display. Rebooting of system cured problem.

12/17S0 Failure experienced with fume hood in reactor lab. No chemical experiments run during

- down time period.

l 12/22/90 During annual rod maintenance, replaced control rod drive connecting linkage bolts and antivibration nuts which had become worn and loose.

UCI Reactor Annual Report 90 Page 4

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Section 4 Maintenance and Suiveillance (continued) 1/17S1 Portal monitor detected significant shoe contamination following handling in reactor lab of old purchased Sr-90 solution source (1 millicurie level) which had crystallized. Several track spots were found and decontaminated. Facility floor completely surveyed during clean-up.

4/2(V91 Problem reported with false security alarm which may have been caused by building power interruption.

5/14S1 FTR rod not firing when actuated. Contacts on AIR switch cleaned and adjusted to restore correct operation.

6/3S1 CAM monitor reported as not responding to TEST circuit initiation. Problem could not be repeated.

5/24S1 through 6/8S1 replaced entire existing 5 channel Radiation Area Monitoring system with new Eberline 6 channel system. Stations installed at same locations, but a PT terminus station added.

6SSI Commenced removing and servicing reactor pool lights to install new lamps and gaskets, in most cases, !ampholders have had to be replaced and rewired becasue of corrosion. Most gaskets and lenses " frozen" in place requiring much effort to dismantle. Entirely new, clean gaskets being used for reassembly, using no scalants.

6/28SI Pasadena (Sierra Madre) earthquake (Richter 6.010.1) tripped seismic switch and motion sensors but reactor not in operation. No damage apparent on facility inspection.

It should be noted that during this period, the main building (Physical Sciences 1) has been under extensive renovation on all six floors. This has caused numerous small problems with power and utility full or panial interruptions. The staff has had to be especially vigilant to affirm functionality of all systems before reactor operation, and to maintain emergency access and egress routes at the facility.

Section 5 Facility Chances and Special Exnerimentdporoved No significant changes or special experiments were approved during this period.

UCI Reactor Annual Report 90 Page 5

I Section 6 Radioactive Efnuent Release.

(a) Gases.

The major direct release to the environs is Argon-41 produced during nonnal 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 pneumatic transfer system for sam 3!es, this is a conservative estimate in that assumption is made that all use of the FI' 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 4 Dy) hanging directly in the exhaust at the point of stack discharge,it is considered unnecessary to provide further checks of these estimates. The dosimeter data confinn 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. Cur the years that data have been collected, the accumulated exposure at the exhaust location have been lower than for " control" points because of lower masses of concrete structures in the vicinity.

Release estimates based on operational parameters are as follows:

(1) Operation of pneumatic transfer system (7/lNO-6/30/91):

a. Minutes of operation: 457.4 minutes

b. Release rate assumed: 6. x 10-8 microcuries/ml 8

c. Flow rate of exhaust air: 1.2 x 10 ml/ min 3

Total release computed:(a x b x c) = 3.3 x 10 microcuries (2) Release from pool surface (7/1/90 6/30/91):

a. Total hours of operation at power (Mwh x 4) = 82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br />

b. Release rate assumed: <l. x 10-8 microcuries/ml 8

c. Flow rate of exhaust air: , 1.2 x 10 ml/ min 3

Total release computed:(a x 60 x b x c) = 5.9 x 10 microcuries Total of (1) and (2) emissica in 1 year = 9.2 x 10 3 microcurie:

Concentration averaged over 1 n atlh e c 1.5 x 10-10 microcuries/mi This remains simihir to values reported in preyious yens and remains lower than MPC even assuming no dilution of the phnne at the stack.

UCI Reactor Annual Report 90 91 - Page 6 ,

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(b) Lioulds and Solids.

p Liquid and solid wastes from utilization of by-product materials are disposed through a l University contract. Waste is transferred to the custody of the Campus Environmentalllealth and l Safety Office (E,ll&S). Direct disposals from this facility are given below. It is important to note I that activity values are estimated at the time of transfer to E,Il&S control. In all instances, considerable time elapses before final shipment from campus, so that substantial decay may occur for medium lived radionuclides.

L DRY WASTES: 6 cubic feet - less than 10 microcuries mixed activation products and waste from

! decontamination of a Sr-90 spill, <100 pCi.

LIQUIDS: 2 gallons - estimated less than 1 microcurie. Most of this was from student labo:atory work with matrerials produced with the reactor.

Section 7.

l Environmental Surveillance.

l Calcium sulfate / Dysprosium themioluminescent dosimeters in pack s supplied by the Radiation Detection Company, Sunnyvale, California are placed at nine locations around the UCI Campus. One pack is kept on the edge of campus in a wood frame house in University llills. In fact, the average of the more remotely located " concrete environment" packs on campus is used as l the background for comparison purposes, since a more similar microenvironment is experienced by such packs.

Table of Locations.

l 1. Window of reactor room cast wall (inside the facility).

2. In hallway on exterior of south wall of facility,

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 (hung in center of duct at final release point).

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

7, Main library building across campus,5th floor office.

I 8. Computer Science building,4th floor office, in window, l

9. Fume hood exhaust, roof level, from reactor laboratory (hung in center of duct).

10._12 Perkins Court, University liills, private residence (wood frame house).

1 l

l l

UCI Reactor Annual Report 90 91 - Page 7 l

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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 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 conkently shows higher readings presumably because it is on a warm, outside, cement wall.

TABLEIV.

Environmental Dosimetrv Data.

1990-1991 Average Exnosures in mr.

I ocation. Oaaner Igal Total less 2SO 3No 4NO INI background (391 25) 1 10 10 9 8 37 0 2 10 10 8 8 36 0 3 11 10 10 10 41 2 4 3 0 3 3 9 0 5 8 6 5 5 24 0 l- 6 13 11 11 11 46 7 7 18 14 15 13 60 21 8 3 2 3 3 11 0 9 6 7 6 5 24 0 10 3 0 2 1 6 0 Average oflocations 6,7, and 8 used for " background" ( = 39) l-i l

l l

l-l l

I UCI Reactor Annual Report 90 Page 8 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 are presented in Table V. Much of this exposcre is acquired in the course of isotope handling experiments, and in some instances has been accumulated in areas outside the facihty,in locations licensed by the State of California. A substantial exposure is experienced by some individuals during required calibration of radiation monitoring equipment.

Twenty-five(25) persons were monitored on a continual basis using film badges, and all of these were also issued with finger dosimeter rings. These were required to be worn while handling isotopes. Film badges were generally worn at waist level by all personnel. An additional twenty-two(22) students were issued badges during the Fall quaner,1990 for a laboratory course in radioisotopes, during which they spent some hours in the facility. These exposure listings have been included in 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, removable contamination in areas coming into direct contact with samples removed from the reactor,and on sample handling tools.

TABLE V.

Personnel Exnosure Summary for 5/lNO to 4/30/91 (in mrem)

Individuah - Whole Body Fincer Rine Deep Shallow Shallow 1 55 90 1160 1 0 0 480 1 0 40 230 1 0 0 120 1 0 0 50 20 0 0 0 22 0 0 (students in class)

Totals 'N 3 Ud- M Additional aggregated data from self-reading dosimeters:

1 17 (4 visits) 1 13 (3 visits) 1 12 (5 visits) 1 I (1 visit) 10 0 (26 visits)

UCI Reactor Annual Report 90-91 Page 9

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