ML20237G954

Univ of California,Irvine,Nuclear Reactor Facility Annual Rept for Jul 1986 - June 1987

ML20237G954
Person / Time
Site:	University of California - Irvine
Issue date:	06/30/1987
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8708240305
Download: ML20237G954 (11)

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U.C.IRVINE

r.a ' Nuclear; Reactor Facility -

• Annual Report

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for July 1st '1986'to June 30th 1987 , i

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Facility License: R-116

. Docket 50-326

-Prepare'd in Accordance with Part'6.7f of the Facility- Technical Specifications i

by Dr G.E. Miller Reactor Supervisor q

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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 ofi 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 'uels, geochemistry, art, and archeological. studies, chemical synthesi;, industrial quality

- control, enzyme studies, trace element pollu tion studies, etc. The reactor is also used. in class work by undergraduates learning tracer : i and activation analysis techniques using small quantities of  !

short-lived activated materials.

A number of. items have needed maintena ice during this period ( see Section 4), but most inspections have fount the facility to be in good condition. During the annual inspection, ro abnormalities were found for the fuel or control rod systems.

A significant number of maintenance C rficulties have been experienced with a security alarm reporting system. Changes in the operation of this system will be made shortly. However, no signs of any

- unauthorized intrusions or unauthorized activities have been noted.

l An emergency drill was held'on December 19th 1986, in conjunction I with a general safety exercise for the Physical Science Building.

Practice was gained in handling of. a potentially contaminated injured individual, transportation, monitoring of emergency personnel, and clean-up.

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UCI Reactor Annual Report 86-87 )

Page 1 L _ _

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i Section 2. j Data Tabulations for the Period July 1st, 1986 to June 30th,1987 I

TABLE I. '

Experiment Approvals on file 8 Experiments performed ( including repeats ) 239 i Samples irradiated 2434 Energy generated this period (Megawatt hours) 33.6 Total, 69 element core = 127.0 j

'74 element core = 950.1

Total energy generated since initial criticality 1077.1 Mw5 Pulse operation this period 50 Total pulses to 6/30/86 778

( Hours critical this period 216 Total hours critical to date 5780 )

Inadvertent scrams or unplanned shutdowns 3 Visitors to reactor - admitted 940 )

Maximum dosimeter recorded for visitors 1 n. rem Visiting researchers (dosimeter issues) 29

, Maximum dose recorded 19 mrem Visiting researchers (badged) 91 )

1 TABLE II l Reactor Status 6/30/87 l l Fuel elements in core ( including 2 fuel followers )

l 81 Fuel elements in storage ( reactor tank - used ) 26 Fuel elements unused (instrumented element) 1 i Graphite reflector elements in core 34 l Graphite reflector elements in reactor tank storage 0 Water filled fuel element positions 6 Experimental facilities in core positions 4 Non-fuel control rods 2 i Total core positions accounted 127 Core excess, cold, no xenon $2.86 Control rod worths (12/12/86)

REG $2.88 l SHIM $3.34 ATR $1.92 l

FTR $0.70 l l Total:

58.84 Maximum possible pulse insertion $2.62 Maximum peak power recorded (5/29/87) 88gMw Maximum peak temperature recorded (B-ring) 230 C LCI Reactor Annual Report 86-87 Page 2

Section 3.

Inadvertent Scrams and Unplanned Shutdowns TABLE III.

Date Time Power Type and Cause 1986 i T/Pl-9/16 Operations suspended pending NRC discussions regarding '

possible interlock non-function as a result of installation fault on rod drives.

10/1 09:38 250 kw % Power scram. At ~104% setting. Unbalanced sample load in rotating rack and gamma activity build up {

caused upward drift.

1987 T72I 10:57 250 kw % Power scram. At '104% setting. Unbalanced sample l

load in rotating rack and gamma activity build up caused upward drift.

5/11 Operations suspended - high CAM reading traced to failure of 24 volt D.C. supply in CAM.

I 5/18 14:09 250 kw % Power scram. At 102% level caused by gamma build up in samples in rotating rack.

Section 4 l

Maintenance and Surveillance l

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

7/23/86 - Screws were lost from the rotary rack specimen removal tool.

The tool was repaired and the screws recovered.

l 8/22/86 - Problems again developed with use of the specimen removal i tool. A new spacer and rivet were installed. I 8/29/87 - Fuel changes were made to the core to increase the available l i

reactivity excess.1 additional fuel element was added to the F-ring in place of a graphite element which was relocated to the G-ring. The fuel was a previously used element which had been held in a storage rack in the reactor pool. The excess was increased from $2.48 to $2.80.

9/10/86 - Telephonc reports were received from the reactor manufacturer (GA) and NRC to indicate that a situation had been discovered at the U.

of Illinois TRIGA wherein the FTR pulse rod prevention interlock could be defeated by driving the REG or SHIM rods to their fully UP position.

It was confirmed that this situation did indeed exist at UCI due to the MAGNET UP position switch wiring. A separate letter was sent to NRC, dated 9/12/86, regarding this issue. Telephone communication was also established in which it was agreed that an appropriate procedure would be to change the wiring to be in accordance with the original electrical drawings, by adding a connection between used and unused terminals. This was done on 9/16/87, and the system confirmed, by actual testing, to be in accordance with original specifications for both the SHIM and REG control rods. Operations were resumed 9/17/87 following the shut-down period (9/10 to 9/16) while discussions continued.

UCI Reactor Annual Report 86-87 Page 3

i 9/19/86 - An "0". ring eas replaceo in the ATR solenoid valve controlling air flow to the rod cylinder. The valve had developed an

. air leak.

10/22/86 - A Cs-137 check source was accidently lowered into a core position in the specimen rack ( with retctor shut down ) during tests on monitor system. The source was recovered by use of a " snake" tool.

No source or reactor damage was apparent.

11/17/86 - Problems again were experienced with the specimen removal tool, as the plunger mechanism became detached from its wiring support.

ATT the parts were retrieved and the mechanism repaired.

12/5/87 - The automatic telephone dial alarm reporting system did not test out correctly. The unit was mechanically serviced and returned to operation.

12/8/86 - The fuel handling tool cable ruptured while handling a fuel element during annual fuel measurement activities. The fuel was able to be placed in storage with the tool attached. The top portion of the cable was severed in order to gain access to the inner cable. The tool could then be disconnected from the element. Fortunately the piece of cable broken off was sufficiently short that the tool could be reassembled with a slightly shorter cable. Before reassembly, the central cable was completely removed from the outer sheath. It was apparent that build-up of corrosion and dirt had caused high friction leading to the rupture. Good cleaning of the cable and sheath made for smooth operation once reassembly was complete. Tool operation was then satisfactory and fuel inspection was resumed and completed.

1/14/87 - The building compressed air pressure was very low. Facilities ,

Management reported they were using a back-up pump. By 10:00 am, normal  !

pisssure had been restored and reactor operation was started. )

i 1/20/87 - The radiation alarm (Tracerlab RAM T63) provided for the l l unioad port on the rotary specimen rack gave erratic readings. On 1/21/87 the geiger tube and associated capacitors were replaced and the d unit returned to service.

1/26/87 - A pneumatic transfer capsule fractured, so that a sample l

failed to return from core. The reactor was shut down, and the sample retrieved using a vacuum hose passed down the tube. The sample was intact and its surface radiation reading only 2 mr/hr.

2/12/87 - Repairs were made to the radiation monitor (Technical Associates FML-5A) for the pneumatic transfer system terminus, including provision of a new geiger tube, and resetting of the high l voltage supply. Instrument calibration was repeated and the instrument placed back in service by 2/18/87.

2/19/87 - A sample retrieval tool made from a spare rotating rack specimen tube broke while samples were being removed. The tool, parts, and sample were eventually all recovered without reactor damage, significant contamination or exposure to personnel.

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l UCI Reactor Annual Report 86-87 Page 4 l

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l 2/21/87 - The building compressed air supply again was very low in pressure. Reactor operation was postponed until adequate air pressure ,

was restored on 2/23/87.

2/26/87 - The building deionped water supply was found to be at high conductivity (8.5 micrnmhos/o ) and so the pool level could not be adjusted. Facilities management were contacted to repair the situation.

3/3/87 - A water drip was noticed adjacent to the north wall of the facility, and Facilities Management were called to investigate. The problem was traced to a sink in a laboratory area above the facility which was repaired. No water entered the pool from this leak.

4/7/87 - Problems noted with telephone auto-dialer alarm reporting ,

system. The tape drive on that system was serviced and the system l l

restored to operation.  !

l 5/6/87 - During pulse operations, an "off scale" power indication l occurred. It was concluded that an operator had placed the range switch .

i in the " pulse low" position in error. Th' temperature rise for the I pulse was normal for the predicted pulse .,ize.

5/11/87 - The Continous Air Monitor (CAM) (Nuclear Measurements  !

Corporation) exhibited unusually high background readings and did not i respond properly to test sources. A problem with the low voltage (24 1 volt) power supply was repaired and the unit tested to be in  !

satisfactory order. Recalibration was accomplished on 5/14/87.

l 5/18/87 - Problems were again experienced with the recording of peak power during a series of pulses. The problem may have been due to external equipment connected to the circuit for recording of the pulse shapes. All other indications, especially peak temperatures, were

! recorded at expected values.

I 5/18/87 - Difficulties were experienced with the REG rod drive mechanism sticking in the magnet up position. Microswiten adjustments

, were made, and all electrical connections inspected and tightened. The

! rod drive was tested and returned to service.

l Security Alarm System - at various times during this period, problems were experienced with the security alarm system. By June, 1987, the Police Department had moved to new facilties on campus and had discontinued use of the old alarm reporting system. The facility is

! relying on telephonic back-up communication for intrusion detection. It l is intended that a new reporting arrangement be installed within the l next few weeks (July,1987) so that primary and back-up systems are l operative.

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 86-87 Page 5

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Section 6

~ Radioactive Effluent Release.

(a) Gases. The major dTrect 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 pneumatic transfer system for samples, this is a conservative estimate in that assumption is made that all use of the PT is at full steady 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 (CaS03-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 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 dosimete"s, 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 of lower masses of concrete structures in the vicinity.

Release estimates based on operational parameters are as follows: l I

(1) Operation of pneumatic transfer system (7/1/86-6/30/87): i

a. Minutes of operation: 1186 minutes

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

c. Flow rate of exhaust air: 1.2 x 10 ml/ min Total release computed: (a x b x c) = 8.5 x 10 3microcuries 1

(2) Release from pool surface (7/1/86-6/30/87): j

a. Total hours of operation at power (Mwh x 4) = 134.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 Total release computed: (a x 60 x b x c)

= 9.7 x 103 microcuries Total of (1) and (2) = 1.8 x 104 microcuries 4

l Concentration averaged over 12 months =

'3 x 10-10 microcuries/ml )

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This remains similar to values reported in previous years and remains lower than MPC even assuming no dilution of the plume at the stack. j s

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UCI Reactor Annual Report 86-87 Page 6

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(b) Liquids 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) for final packaging and shipping according to applicable State and Federal regulations, under our agreement license with the State of i California. Spent filters from the pool water purification system are 4 also disposed in this way. I Some of the materials activated in experimerM using the reactor are transferred to other users operating outside tne facility at UCI  !

and in other locations in California. Each of these projects is authorized to possess and use isotopes by the State of California, and disposal of waste from such operations is not under the control of this facility.

Direct disposals from this facility are given below. It is important to note that activity values are estimated at the tir of 3 transfer to E,H&S control. In all instances, considerable time elapses i before final shipment from campus, so that substantial decay may occur -  !

for medium-lived radionuclides. ,

1 DRY WASTES: 9 cubic feet - 245 microcuries mixed activation products  !

i LIQUIDS: No liquid wastes were disposed during this reporting period.

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Section 7.

Environmental Surveillance.

Calcium sulfate / Dysprosium thermoluminescent dosimeters in packs ,

supplied by the Radiation Detection Company, Sunnyvale, California are j 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. It should be i noted that the location of this " control" has changed from previous I years, and is now located much closer to the facility (0.5 miles versus .

2.5 miles) than before, but still in a private residence. 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 radiochemical laboratory.

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, rcof level.

6. Steinhaus Hall (Biologcal Sciences 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 86-87 Page 7

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 operation 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. The air released f rom the facility continues to give no detectable exposure above background for dosimeters immmersed in it.

TABLE IV.

Environmental Dosimetry Data, j 1986-1987 Average Exposures in mr.

Location. Quarter Total Total less 2/86 3/86 4/86 1/87 background I (38+-25) 1 16 10 6 10 42 4 2 10 8 3 6 27 0 3 12 8 6 7 33 0

( 4 5

6 9 1 1 17 0 5 7 0 4 16 0 6 13 14 8 8 43 1 7 18 21 8 13 60 22 8 4 2 4 1 11 0 9 9 9 5 8 31 0 10 2 2 -1 0 3 0 Average of 6,7.,8 used for " background" ( = 38)

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UCI Reactor Annual Report 86-87 (

Page 8 2.

a Section 8.

Radiation Exposure 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 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 required calibration of radiation monitoring equipment.

Twenty-seven(27) 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 fifty-two (52) students were issued badges during the Fall quarter,1986 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 dosime.ter rings.

l 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. Records indicate that one individual handling medium level quantities of isotopes acquired detectable clothing contamination 4 with short-lived isotopes. This contamination was detected by the portal monitor as he was leaving the facility. Sponging the affected area was sufficient to reduce the contamination to acceptable levels.

The individual has been advised to wear a laboratory coat during any subsequent similar activities. 1 TABLE V.

_ Personnel Exposure Summary for 7/1/86 to 6/30/87 (in mrem)

Individuals Whole Body Finger Ring ,

Deep Shallow Shallow )

1 0 150 710 1 0 80 1040 l 1 0 45 700 1 0 35 320 1 0 0 120 22 0 0 0 52(students 0 0 Totals ~M 6 3TG 78W Additional data from self-reading dosimeters:

1 51 (7 visits) 1 40 (6 visits) 1 18 (5 visits) 1 6 (1 visit)

UCI Reactor Annual Report 86-87 Pace 9 1

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~ UNIVERSITY OF CALIFORNIA,' IRVINE _ i lER AElIY

• IWl5

• IRVINE

• LOS Ah0El.E5

• RIVERSIDE e SAN DIEGO e 5AN FRANCISCO SANTA BAR8 ARA e SANTA OLUZ J

1 DEPARTMENT OF CIIEMISTRY IRVINE. CALIfORNI A 92717 .

August 20th, 1987 U.S. Nuclear Regulatory Commission, Document Control Desk, Office of Nuclear Reactor Regulation',

Washington, D.C. 20555

! Docket: 50-326 l Licence: R-116 l l Gentlemen: .

1 Please find enclosed three(3) copies of the annual report for our facility for the period July 1st,1986 - June 30th,1987.

Sincerely,  !

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! George E. Miller  !

Reactor Supervisor l

cc: w/ encl Region V NRC ANLI Reactor Operations Committee i