ML20215P001

Annual Rept for Jul 1985 - June 1986

ML20215P001
Person / Time
Site:	University of California - Irvine
Issue date:	06/30/1986
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:	NRC
References
NUDOCS 8611100202
Download: ML20215P001 (12)

Text

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.U.C.IRVINE Nuclear Reactor Facility Annual Report for July 1st,1985 to June 30th,1986 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

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i 8611100202 860630 PDR ADOCK 05000326 R

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s Section 1.

Operations Operation of this. facility is in support of the Department of Chemistry program in research and education in the use and application

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

7 research students and 2 postdoctoral associates have used the facility regularly under the direction of three UCI faculty. These In addition, 5 include one visiting student from West Germany..

students and post-doctoral associates from two other campuses of the University' of California and several from other colleges and universities in Southern California have been served by the facility.

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

'few items of minor equipment were repaired.

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

~0perations have continued at the level shown last year as a result of both internal and external uses. Data on the operations is

-shown in Section 2.

Two new reactor operators were trained and licensed this year, and one senior operator was relicensed. Her license had been allowed to expire inadvertently.

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- tl Section 2.

Data Tabulations for the Period July 1st, 1985 to June 30th, 1986 TABLE I.

Experiment Approvals on file 8

Experiments performed ( including repeats )

.370 Samples irradiated 3909 Energy generated this period (Megawatt hours) 46.6-127.0 Total, 69 element core 916.5

>74 ele' ment core Total energy generated since initial' criticality 1043 5 Mwh

' Pulse operation this period 22 Total pulses to 6/30/85 728 Hours critical this period 270 Total hours critical to date 5562 Inadvertent scrams or unplanned shutdowns 12 Visitors to reactor - admitted 875 Maximum dosimeter recorded for visitors 1 mrem Visiting researchers (dosimeter issues) 39 Maximum dose recorded 6 mrem Visiting researchers (badged) 3 3

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TABLE,II, Reactor Status 6/30/86 Fuel elements in core ( including 2 fuel followers )

80 Fuel elements in storage ( reactor tank - used )

~28 Fuel elements unused (instrumented element) 1 Graphite reflector elements in core 34 1

Graphite reflector. elements in reactor tank storage Water filled fuel element positions-7 4

Experimental facilities in core positions 2

Non-fuel control rods 127 Total core positions accounted

$2.48 Core excess, cold, no xenon Control rod worths (1/16/86)~

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REG

$2.80 SHIM

$3 77 ATR

$2.03 FTR

$0.68 Total:

$9.28 Maximum possible pulse insertion (from sub-critical)

$2.71 Maximum peak power recorded (4/09/86)( $2.71(sc) ins ) 850 Mw 210 oC Maximum peak temperature recorded (B-ring) i l

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Sect' ion 3 i

Inadvertent Scrams and Unplanned Shutdowns TABLE III.

Date Time Power Type and Cause 1985 7/18 18:46 250 kw % Power scram. At ca. 102%' setting caused by gamma build up in samples in rotating rack.

8/12 12:19 250 kw % Power scram. At ca. 1025 setting caused by gamma build up in samples in rotating rack.

10/10 11:55 80 kw Cap came of pneumatic transfer sample container (rabbit) leaving sampel in core.

Sample retrieved with vaccuum tube after unplanned reactor shutdown.

10/14 16:35 80 kw Repeat of problem of 10/10.

11/11 10:31

<10 kw Seismic scram. Incorrect reset after daily test. No seismic activity observed.

12/15 14:09 250 kw % Power scram. At ca. 102% setting caused by gamma build up in samples in rotating rack. Linear power indication was 96%.

12/18 09:38 250 kw % Power scram. Same cause as 12/15 event.

1986 1/14 10:55

<1.5 w Period scram. Trainee error during start to critical.

1/22 11:18

<1.5 w Period scram. Second trainee error during start-to critical.

Trainee operator linear range switch 1/29 16: 10

~3 w

error.

2/12 16:23 250 kw Period scram. Trainee error while banking control rods at full power.

5/09 12:15 250 kw Seismic scram. Improper reset after daily test. No sign of seismic activity.

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4 Section 14;,

Maintenance and Surveillance.

-All critical systems (fuel elements, control rods, safety systems) continue to be found in good condition during routine inspections.

Relatively little special maintenance was needed this year. Problem areas involved microswitches on control rod drives, an electrical connector to a control rod drive, and the mechanical gear chain on the drive. The console recorder needed servicing on two occasions.

The pool water conductivity gradually climbed, reaching the self established change-out limit of 2 micromhos/cm. In June, 1986 new resin was installed and the old shipped to E,H, and S for disposal.

This procedure was accomplished smoothly without any spillage of radioactive materials or personnel exposures. The conductivity of the pool water is now very low.

The security / safety systems computer developed several minor problems, but all were fixed. A more frequent problem exists with the system for. transfer of alarms directly to the UCI Police dispatch desk. This system is antiquated and has become unreliable. The UCIPD is due to move to a new facility in Spring, 1987.

It is hoped that a complete new alarm receipt system will be installed at that time.

Meanwhile' the back-up system of telephone dialling has served well in maintaining security response.

Section 5.

Facility Changes and Special Experiments Approved.

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

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Section 6.

Radioactive Effluent Releases.

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

Releases are estimated based on original estimates at point of origin within the facility and taking only dilution into account.

Since the greater release is from operation of the pneumatic sample transfer system,, this is a conservative estimate in that-the assumption is made that all use of this facility is at full reactor power (250 kilowatts) when, in fact, some of'the time the facility is used with the reactor at a lower power level. 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 an individual standing continuously directly in the stack discharge flow for one year would receive a submersion dose less than the reliability limit of the four combined dosimeters, or less than 20 mrem per year. In fact, because of the distance of this dosimeter (location 5 in Section 7, Table IV) from adjacent structures, the exposure at this point has consistently been lower than that at most " control" remote locations where the dosimeter is closer to concrete or other building structures.

The quarterly data are presented, along with all other environmental dosimeter readings, in Table IV, Section 7 Release estimates based on operational parameters are as follows:

(1) Operation of pneumatic transfer system (7/1/85 - 6/30/86):

Total time of operation:

1608 minutes

-8 Release rate assumed 6 x 10 microcuries/ml 6

Flow rate of exhausted air 2 x 10 ml/sec 4

Total release computed

.1.2 x 10 microcuries (2) Release from pool surface (7/1/85 - 6/30/86):

Total hours of operation at power (Mwh x 4) 186 hours0.00215 days <br />0.0517 hours <br />3.075397e-4 weeks <br />7.0773e-5 months <br />

-8 Release rate assumed

<1 x.10 microcuries/ml 6

Flow rate of exhaust air 2 x 10 ml/sec 4

Total release computed

<1.3 x to microcuries 4

2.5 x 10 microcuries Total of (1) and (2)

-10 Concentration averaged over 12 months =

<4 x 10 microcuries/ml This is similar to values reported in earlier years and remains lower than MPC even assuming no dilution of the plume at the stack.

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g (b) Liquids and Solids.

Liquid and solid wastes from utilization of by product materials are disposed through a University contract.

Waste is transferred tp the custody of the Campus Environmental Health and Safety Office for. final packaging and shipping according to applicable State and Federal ragulations. Spent filters from.the pool water purification system are also disposed in this way. Spectrometric measurements indicate that these are contaminated with long, medium and short-lived isotopes in low quantities that would be expected from activation of reactor components of stainless steel and aluminum alloy. One charge

( 6 cubic feet ) of ion exchange resin from this system was transferred for. disposal during this period.

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.

Direct disposals by the facility were as follows:

(activities are estimated as of time of transfer to E H and S control )

Dry wastes: 14 cubic feet -1055 microcuries mixed activation products.

Liquids:

10 gallons --

245 microcuries mixed activation products.

TOTAL 1300 microcuries I

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Section 7.

Environmental Surveillance.

Calcium sulfate: Dysprosium thermoluminescent dosimeters in packs supplied by the Radiation Detection Company, Sunnyvale, California are placed at nine locations around the UCI Campus. One pack is kept off-campus in a wood frame house (second story) in Irvine as a control. In fact, the average of the remotely ( to the reactor ) located " concrete environment" packs on campus is used as the " back ground" for comparison purposes for evaluation of the data for. those packs located closer to the facility.

Table of Locations.

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

2. In hallway between reactor laboratories and radiochemical laboratory.

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

4. Classroom 152, directly over reactor room.

5. In roof exhaust air flow from reactor room.

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, roof level, from reactor laboratory.

10. 15 Spicewood Way, Irvine, private residence about 2.5 miles from facility.

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 formation ) and are essentially similar to those reported in previous years. As noted before, areas (1) and (2) are partly controlled so that maximum possible annual exposure to an individual in a true "off-site" location would be estimated to be much less ~ than 25 mrem (above background) from operations at this facility. The main and fume hood exhaust records continue to show no detectable exposure above background in the exhaust stacks from the facility.

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n' TABLE IV.

Environmental Dosimetry Report Data.

1985-1986.

Average Exposures,in,mr.

Location.

Quarter Total. Total less

Background

( 37+-28 )

2/85 3/85 4/85 1/86 1

18 15 20 9

62 25 2

12 9

to 8

39 2

3 12 11 14 10 47 10 4

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'4 4

3 16 0

5 8 -

5 6

2 21 0

6 11 10 12 8

41

( 4) 7 18 13 20 12 63 (26) 8 2

2 2

2 8

( 0) 9 9

7 10 6

32 0

to 4

4 4

5 17 0

Average of 6,7, and 8 used for background.

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4' 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 these exposures are acquired in the course of isotope handling experiments, and in some instances have been accumulated in areas outside the facility, licensed by the State of California. Some exposure is experienced as a result of handling calibration sources during calibration of radiation monitoring equipment.

Twenty-five (26) persons were monitored on a continual basis using film badges; of these all were also issued finger dosimeter rings. These

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were required to be worn while handling isotopes. Film badges were generally worn at waist. level by all personnel.

Certain individuals and visitors are issued with pocket dosimeters during their period in the facility. The recorded data for these have been summarized in Table I, Section 2.

Contamination surveys consisting of wipe tests and G-M surveys have shown significant removable contamination in areas coming in' direct contact with samples removed from the reactor, and on sample handling tools. No other contamination areas have been found.

TABLE V.

Personnel Exposure Summary for 7/1/85 to 6/30/86 (ijl mrem)

Individuals Whole Body Finger Ring Deep Shallow 1

385 410 320 1

0 55 1610 1

0 0

480 1

0 25 240 1

0 0

190 1

0 0

50 l'

0 0

40 1

35 35 0

1 0

0 30 17 0

0 0

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DEPART & TENT OF CIIEA!1STRY IRVINE, CALITORNI A 92?!?

Nuclear Reactor Facility Supervisor: Dr G.E. Miller Tel: 714-856-6649 or 714-856-6082 November 4th, 1986 U S. Nuclear Regulatory Commission, Division of Licensing, Washington, D.C. 20555 Docket 50-326 License R-116 Gentlemen:

Please find enclosed ten (10) copies of the annual report for 1985-86 for our reactor facility.

I regret that production difficulties have delayed distribution of this report.

Sincerely, George E. Miller Reactor Supervisor GEM /mm Single copies to:

cc: Reactor Operations Committee American Nuclear Insurance Document Management Branch Region V, NRC Ill