ML20207J082

Annual Rept for Jul 1987 - Jun 1988

ML20207J082
Person / Time
Site:	University of California - Irvine
Issue date:	06/30/1988
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808300217
Download: ML20207J082 (11)

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U.C.IRVINE . ,

haclear Reactor Facility Annual Report for July 1st 1987 to June 30th 1988 Facility License R-116 [

Docket 50d26 Prepared in Accordance with Part 6.7f of the Facility Technical Specifications by Dr G.E. Miller Reactor Supervisor i f

4 6% 0 8808300217 880630 f PDR R

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e Section 1.

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

Reactor utihzation apart from operator training and maintenance ts 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 contre!,

enzyme studies, trace element pollution studies, etc. The reactor is also used in class work by undergraduates learning tracer and activation analyefs techniques using small quantitles of short lived activated materials.

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

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 annur.1 inspection.

no abnonnalities were found for the fuel or control rod systems.

The revised security alarm reporting system has functioned well although a few false alarms are still being experienced. No incidents of unauthorized intrusions or unauthorized activities have been noted.

An emergency drill was held on May 23rd 1988. Practice was gained in handling of a potentially contaminated, slightly injured, individual, transportation, monitoring of emergency personnel, and clean up.

l UCI Reactor Annual Report 87 88 - Page 2

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e 7 Section 2.

Data Tahulations for the Period July 1sti 1987 to June 30th.1988 TABLE L ~

Experiment Approvals on file 8 Experiments performed (including repeats) 201 Samples irradiated _

2158 Energy generated this period (Megawatt hours) 42.5 Total. 69 element core = 127.0

>74 element core , = S92.6 Total energy generated since initial criticahty 1119.6 Mwh Pulse operation this period 86 Total pulses to 6/30/88 864 Hours critical this period 244 Total hours critical to date 6023 Inadvertent scrams or unplanned shutdowns 6 Visitors to reactor - admitted 517 ,

Maximum dosimeter recorded for visitors 1. mrem Visiting researchers (dosimeter issues.) 17 Maximum dose recorded 33. mrem Visiting researchers (badged) 53 TABLE II Reactor Status 6/30/88 Fuel elements in core (including 2 fuel followers) 82 Fuel elements in storage (reactor tank - used) 25 i Fuel elements unused (instrumented element) 1 l Graphite reflector elements in core 34 i Graphite reflector elements in reactor tank storage O Water filled fuel element positions 5 Experimental facilities in core positions 4 '

Non fuel control rods 2 1 Total core positicns accounted 127 '

Core excess, cold, no xenon $2.53 ,

Control rod worths (1/20/88)  !

REG $2.48 SHIM $3.22 ATB $1.61 F'IR $0.67 T_qtah $7.98 l Maximum possible pulse insertion $2.28 Maximum peak power recorded (2/25/88) 1000. Mw l Maximum peak temperature recorded (B ring) 235.o C '

l UCI Reactor Annual Report 87 Page 3

Section 3.

Inadvertent Scrams and Unolanned Shutdowns TABLE III.

Date Time Power Tvoe and Cause 1987 11/10 10:09 250.kw Manual scram by operator. Water reported returning with 170 sample. Operations were suspended for inspection of tenninus.

11/17 12:10 250.kw Manual scram by operator after sudden power drop caused by FTR drop due to air pressure loss. Valve on supply line had been inadvertently turned off.

12/08 09:38 1.kw Period scram while raising power caused by malfunctioning IDG channel circuit. ,

12/30 12:18 1.w Linear power scram due to low setting of scram point. Occurred during exce;: check.  ;

1.9.26 1 2/26 13:50 250.kw Period scram. SHIM magnet lamp failed causing SHIM rod to ,

drop. Subsequent power fluctuations caused swings in LOG reading, hence period scram.

5/02 13:57 250.kw  % Power scram. At 104% level caused by gamma build up in samples in rotating rack.

Section 4 Maintenance and Surveillance The following r '-routine maintenance activities were carried out during this period:

7/21/87 - Fuel Temocrature readings were erratic. Connections within the console were re-crimped and the tenninal strip tightened to correct the problem.

7/22/87 The Transient Rods failed to fire when the operator tried a pulse operation. Tae fuse had failed in the 25 volt power supply to the air solenoids. i l

7/23/87 - The REG rod failed to drive UP when required. A 200 ohm resistor in the drive l

current cirect had open-circuited and was replaced.

8/4/87 - An operator noticed two nuts on the top of the rotary specimen rack housing. 'niey proved to be stainless steel, not highly radioactive (less than 2 mr/hr on contact) when removed from the pool, and 1/4-20 size. No scarce for these from reactor components could be I found and it was deduced that they had been accidently Idcked in from the side of the pool and were from non reactor components being worked on in the vicinity.

10/1/87 - An inspection of the facility was conducted at 07:49 following a marked earthauake shock felt widely (on Whittier fault). The seismic switch had tripped, although the reactor was NOT in operation at the time. No sign of water splash, or any other damage was found. A repeat inspection was made on 10/4/87 at 07:00 following an after shock noted at 04:00.

Again, no signs of damage were noted.

UCI Reactor Annual Report 87 Page 4 I

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10/11/87 - A minor problem was found with the Pneumatic Transfer operating system in that a sample was recycled back into the reactor terminus. The solenoid valves were lubricated, but subsequent tests could not reproduce the problem.

11/9/87 The LOG recorder channel needed cleaning and gain adjustment. On the same date, repairs were made to the fixed radiation monitor at the pneumatic system unload port. A new geiger tube was installed and the unit modifled to make plateau determination easier.

11/10/87 - An experimenter reported that a sample had returned wet in the Fr transfer system. Further use was discontinued. Several days later the Fr terminus was removed from core. On 12/4/87 it was removed from the pool for close inspection. Leak testing with air pressure failed to reveal a leak. Tube joints were tightened and system vacuumed out to remove all water traces. After several days in the pool, no water was found inside. On 12/30/87 the terminus was placed back in core and has since functioned normally with no signs of recurrance of the leak.

11/17/87 - Loss of air pressure occurred on the transient rod drives. The main valve had been turned off during maintenenace tests and not turned back on again.

11/20/87 - The samole retrieval devier. could not be recovered from the rotating specimen rack without rupturing the connecting wire. The device was rewired and a length of plastic tubing added as a cover for the last 1 foot of the wire. It is concluded that allowing a slack" wire at the last few inches can permit it to loop around the drive chain support structure and thus get hooked into the mechanism. This has happened before with both this device and with strings and ropes. It is felt that this policy (of a last foot of stiff support) will completely eliminate this happening again.

11/24/87 - The facility seismic trio had been tripped by an earthquake during the night centered at Calexico No evidence of damage to the facility could be found.

12/7/87 - Operation was conducted without good readings from the LOG channel as the device was being electronically serviced. Such operation was authorized by the Reactor Supervisor.

This caused an inadvertent period scram on 12/8/87. Console circuitry was overhauled by 12/30/87, with all channels back in service. During this time, parallel signals were tapped oft to a computer monitoring network via Op-Amp inputs. Original signals were unafTected by this change. We computer will be used to acquire digitized records of reactor power.

1/4/88-1/11/88 Annual core inspection, with measurement of all fuel elements and control rods was accomplished during this period. The only item noted as unusual were some surface damage to a plastic cone in the FTR drive / shock absorber unit. The item remained functional, however, and was reinstalled. It will be reinspected next year.

1/12/88 - It was noted that control rod calibrations varied from previous measurements more than usual. Calculations were carefully reviewed and all data seemed consistent. The change was attributed to the combination of fuel movement made during inspection, and the increased pulsing done during the previous six months.

1/19/88 Fuel changes were made to the core to increase the available reactivity exceu. One additional fuel element was added to the F-ring in place of a graphite element which was relocated to the G-ring. He fuel was a previously used element which had been held in a storage rack in the reactor pool. The excess was increased from $2.45 to $2.76. The new control rod calibrations necessitated by this fuel addition gave numbers that were more consistent with earlier (1987) numbers.

UCI Reactor Annual Report 87-ES - Page 5

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e 1/26/88 Authorization was given for short continued operation above 25 OC as the University chilled water supply was inadequate to maintain low reactor cool temoerature. 30 minutes of run were done, the pool reaching 26 degrees, finally.

2/26/88 - The SHIM niagnet current indicator lame was replaced after it failed.

4/4/88 - Difficulties were reported with the LOG channel not returning to zero after maintenance tests. Investigation showed that the compensation voltage cable connector (which is removed during tests) had become disconnected. It was refar.tened and reconnected. This repair had to be repeated on 5/2/88 using a new connector.

4/26/88 - A samole transfer tube broke leaving the end in core. Subrequent operation of the system returned the missing piece to the unload port. This same problem was noted on 5/26/88.

5/2/88 'Ihe Continuous Air Monigu: input stage (transistor) failed during maintenance testing )

and had to be replaced. j i

5/23/88 - An incident involving a radioactt<e spill was created as an emergency exercise. A i sample ofirradiated ammonium chloride (Cl 38) was used to test response. All activity had 4 I

derayed to background by the following morning. Two days later it was found that the Fr system air blower was inoperative because the CAM alarm system had been set off over a long period of time during the exercise. This resulted in an overly magnetized telay unit which had not disconnected when the current was removed.

i Section 5 1 Factlity Changesjmd Suecial Exoeriments Anoroved No significant changes or spc cial experiments were approved during this period.

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UCI Reactor Annual Report 87-88 Page 6

9 Section 6 Radioactive Efiluent Release.

(a) Gases. 'Ite major direct release to the environs is Argon-41 produced during i m al operations. Very small amounts of other gases may be released from irradia'.ed . materials in experiments.

Releases are computed based on original estimates at point of origin within the facillt)'

and taking only dilution into account. Since much of the release is from operation of the pneumatic transfer system for samples, this is a conservative estimate in that assumption is made that all use of the Fr is at full steady state power level (250 kwatts) when, in fact, so ae 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 dostmeter (CaSO4 Dy) hanging directly in the exhaust at the point of stack discharge, it is considered unnecessary to provide further checks of these estimates. The dostmeter 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 dostmeters, or less than 20 mrem per l year. The dostmeter 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 of lower masses of concrete structures in the vicinity.

Release estimates based on operational parameters are as follows:

(1) Operation of pneumatic transfer system (7/1/87-6/30/88);

a. Minutes of operation: 943. minutes

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

c. Flow rate of exhaust air: 1.2 x 108 ml/ min Total release computed: (a x b x c) = 6.8 x 103 microcuries (2) Release from pool surface (7/1/87-6/30/88):

a. Total hours of operation at power (Mwh x 4) = 170. hours

b. Release rate assumed: <1. x 10 8 microcuries/ml

c. Flow rate of exhaust air: 1.2 x 108 ml/ min Total release computed: (a x 60 x b x c)

= 1.2 x 104 microcuries Total of (1) and (2) = 1.9 x 104 microcuries Concentration averaged over 12 months = <3. x 10-10 microcuries/ml This remains similar to valurs repo:ted in previous years and remains lower than MPC even assuming no dilution of the plume at the stack.

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l UCI Reactor Annual Report 87 88 - Page 7

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I (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 Erwironmental 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 tran.v . to E.H&S control. In all instances, considerable time elapses before final shipment from caiupus, so that substantial decay may occur for medium-lived radionuclides.

DRY WASTES: 8.5 cubic feet - less than 45 microcuries ntixed activation products LIQUIDS: 7 gallons - estimated (tritium) = 100 microcuries. Most of this was from student laboratory work and involved tritium activity that was purchased, and not produced from the reactor.

Section 7.

Environmental Surveillance.

Calcium sulfate / Dysprosium thermoluminescent dostmeters in packs 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 Hills. In fact, the average of the more remotely located concrete environment" packs on campus is used as the background for comparison purposes, since a more 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 radiochemicallaboratory.

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

4. Classroom 158, directly over reactor facility.

5. In roof exhaust air flow from reactor room, rooflevel.

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

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

8. Computer Science building 4th floor office.

9. Fume hood exhaust, rooflevel, from reactor laboratory.

10.12 Perkins Court, University Hills, private residence.

(wood frame house)

UCI Reactor Annual Report 87-88 Page 8

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• o 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. A reduction is observed in levels found within and close to the facility compared to earlier years as the neutron generator within the facility has not been in operation. This has removed any dose due to N-16 production from opemtion of the generator.

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. 'Ite air released from the facihty continues to give no detectable exposure above background for dostmeters immmersed in it.

TABLE IV.

Environmental Dosimetry Dataa 1987-1988 Average Exposures in mr.

Location. Quarter Total Tota 11ess 2/87 3/87 4/88 1/88 background (28+-13) 1 11 9 5 5 30 2 ,

2 8 10 2 5 25 0 3 11 8 9 6 34 6 4 1 0 1 0 2 0 5 6 5 4 3 18 0 6 13 9 3 7 32 4 7 17 12 14 10 53 25 8 2 2 0 0 0 0 9 9 6 6 3 24 0 10 2 -1 -4 -1 -4 0 Average of 6,7,8 used for "background" ( = 28)

UCI Reactor Annual Report 87 88 Page 9

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l Section 8.

Radiation Exnosure to Personnel.

He annual exposures reported as a result of finger dosimeter ring and flim badge dosimetry are presented in Table V. Much of this exposure is acquired in the course ofisotope 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 required calibration of radiation monitoring equipment, l Etrty-two(32) persons were monitored on a continual basis using film badges, and all of l 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 forty-four(44) students were issued badges during the Fall quarter,1987 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 dostmeter 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 Exoosure Summary for 7/1/87 to 6/30/88 fin mreml Individuals Whole Body Finger Ring Deep Shallow Shallow 1 0 90 880 1 0 30 660 1 0 0 180 1 0 0 150 1 0 0 100 1 0 0 70 1 0 0 50 1 0 0 30 23 0 0 0 44 0 0 (students in class)

Totals 5 3 120 2T23 Additional aggregated data from self-reading dosimeters:

1 62 (6 visits) 1 54 (7 visits) 1 8 (2 visits) 1 1 (1 visit) l UCI Reactor Annual Report 87 88 Page 10 l l

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. UNIVERSITY OF CALIFORNIA, IRVINE musinty . nwis . imst . Los 4xAtts . nivrasitr . us inco . us in4visco uxT4 mann4 54xT4 aiuz

. DEPARTMENT OF CIIEMISTRY IRVINE, CALIFORNI A 927 7 Augusti 18th, 1988 Nuclear-Regulatory Commission, Document Control Desk, Mail Station F1-137, Washin6 ton, D.C. . 20555

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Docket 50-326. Fac'ility Annual Report.-

Gentlemen:

Please find enclosed copies of the annual report for the UCI Reactor Facility for.the period July let,'198T to June 30th, 1988'. I regret that this report is a few days in arrears. ' Difficulties' vere' encountered in production of the final copy due to switching of computers /vord processors to_be used.

This report is. submitted in accordance with the Technical Specifications, 6.7f.

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Sincerely k

George E. Miller _

1 Senior Lecturer in Chemistry and Reactor Supervisor Tel: 714-856-66h9 GDi/mm cc: Region V,IGC American Insurance.

ROC Members M.C. Caserio, Chair, Chemistry 1

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