ML092330118

U.C. Irvine Nuclear Reactor Facility Annual Report for July 1st, 2008 to June 30th, 2009

ML092330118
Person / Time
Site:	University of California - Irvine
Issue date:	08/11/2009
From:	Geoffrey Miller University of California - Irvine
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML092330118 (10)

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UNIVERSITY OF CALIFORNIA, IRVINE BERKELEY .. DAVIS IRVINE LOS ANGELES RIVERSIDE SAN DIEGO

• SAN FRANCISCO SANTA BARBARA

• SANTA CRUZ George E. Miller IRVINE, CA 92697-2025 Senior Lecturer Emeritus (949) 824-6649 Department of Chemistry and FAX: (949) 824-6082 or (949) 824-8571 Supervisor, Nuclear Reactor Facility Internet: GEMILLER@uci.edu August 11, 2009 US Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Re: Docket 50-326; License R-116 Annual Report 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 2008 through June 30th 2009.

Sincerely, qr1J~K~ (Q,- -

George E. Miller Reactor Supervisor cc: American Nuclear Insurance, 95 Glastonbury Blvd, Glastonbury CT 06033, Policy NF- 176 Dean of Physical Sciences, John Hemminger Already distributed:

Marcus Voth, US Nuclear Regulatory Commission One White Flint North, 11555 Rockville Pike, Rockville, MD 20852-2738 Reactor Operations Committee Members, UCI '

AA-7Z

U. C. IRVINE Nuclear Reactor Facility Annual Report for July 1st, 2008 to June 30t, 2009 Facility License R-1 16 Docket 50-326 Prepared in Accordance with Part 6_7f of the Facility Technical Specifications by Dr. G. E. Miller Reactor Supervisor UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 1

Section 1.

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

Reactor utilization, apart from operator training and maintenance, is thus almost 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 in class work by undergraduates learning tracer and activation analysis techniques using small quantities of short-lived activated materials.

Enrollment in the Winter Quarter 2009 laboratory course in Radioisotope Techniques using the facility was 45 students with 3 graduate teaching assistants, who also learned these techniques.

Use is also made of the facility by other educational institutions, and a modest Nuclear Science Outreach program to middle schools and high schools has .been continued. This program has involved tours, class demonstrations, and analyses of samples submitted by faculty. Direct financial grant support has not been available during this period. A seismic upgrade to the building (Rowland Hall) in which the reactor is housed has been completed.

Operations have continued at a steady low rate, slightly above last year's. Criticality was achieved for 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br />, and the total energy generated was equivalent to 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> at full steady state power.

67 separate experiments were performed, and over 1000 samples were irradiated (sometimes multiple samples are included in a single capsule and are not always separately logged). 7 moderate level mixed isotope shipments were made and 1 isotope tracer (82Br) ,all Yellow II category. No pulse operations have been performed, even-for test or demonstration purposes.

No unusual maintenance or surveillance activities were conducted during this period.

An NRC general inspection was carried out during December 2008 (2 nd -4 th). No violatons were noted.

In 2008-9, Reactor Operations Committee meetings were held on August 28th 2008 and January 27h 2009 in accordance with Technical Specification schedule requirements.

No follow-ups or incidents have been forthcoming regarding security or emergency response. An exercise was held March 16th, 2009 for the UCI EH&S emergency responise team with debriefing and evaluation and creation of an After Action Report (AAR) designed to improve training as related to response to a laboratory radiation-spill event.

Inspections continue to be routinely conducted monthly and quarterly by the Radiation Protection staff of EH&S at UCI. These have identified that -newreduced frequency schedules authorized last year have been properly maintained, and results justified the reduced frequencies in the light of the lower level of operations, increased instrument-reliability, and the continued finding of absence of significant levels of contamination or personnel exposure.,

No operator training was conducted.

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 2

Section 2. Data Tabulations for the Period July 1st, 2008 to June 30th, 2009 TABLE I.

Experiment Approvals on file 2 Experiments performed (including repeats) 67 Samples irradiated 1011+

Energy generated this period (Megawatt hours) 11.9 Total, 69 element core = 127.0

>74 element core = 1327.3 Total energy generated since initial criticality 1454.3 Mwh Pulse operation this period 0 Total reactor pulses to 6/30/06 978 Hours critical this period 88.0 Total hours critical to date 8428.5 Inadvertent scrams or unplanned shutdowns or events at power 5 Visitors to reactor - as individuals or in tour groups - 184 Maximum dosimeter recorded for visitors - all less than 1 mrem Visiting researchers (dosimeter issues) 16 Maximum exposure recorded at one visit 20.3 mrem Visiting researchers (badged) 2 Students in class badged 48 Exposures reported for quarter (range: 23-37 mrem) average 30 mrem TABLE II Reactor Core Status 6/30/09 (unchanged from 6/30/08)

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 34 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 Total core positions accounted for 127 Core excess, cold, no xenon (as of 6/16/2009) $2.64 Control rod worths (calibrated 6/01/2009) REG $2.96 SHIM $3.60 ATR $1.81 FTR $0.70 Total: $9.07 Maximum possible pulse insertion $2.51 Maximum peak power recorded (no pulse operation during this period) - Mw Maximum peak temperature recorded in pulse (B-ring) Cg UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 3

Section 3.

Inadvertent Scrams, Unplanned Shutdowns, Events at Power TABLE III.

Date Time Power Type and Cause 2009 2/17 16:15 50kw Student reported rabbit did not return on time out of pneumatic transfer system. Found shelf support had been improperly inserted in terminus.

Reversed this, sample returned and placed in lead pig to decay.

Irradiation of further samples continued successfully' 2/18 19:52 248 kw Linear power scram - REG rod UP switch "hung" during adjustment causing rod to continue to rise. Failure did not repeat, and reactor, power restored to 250 kilowatts with no further event.

2/24 13:34 1.5 watts Excessive noise noted in linear channel during start-up. Cables in rear of unit re-plugged and re-tiedG Cured problem.

2/25 16:25 40 kw Rabbit sample failed to return as end cap of transfer tube broke.

Sample retrieved immediately using "sticky" rabbit and operation continued with new transfer tube. Sample and parts of transfer tube were transferred to lead contained for decay (were only <10 mr/hr at surface).

3/4 09:55 2590 kw Rabbit tube did not return. Use of manual return switch effected return.

Sample removed to storage. Transfer valve system lubricated as suspected cause of problem. Continued operation with no subsequent problems.

UCI Nuclear ReactorFacility Annual Report 2008-2009 Page 4

Section 4 Maintenance and Surveillance The following non-routine maintenance/surveillance activities were carried out during this period.

Any reactor operation related items have been included above and are not repeated here.

2008 July 29th 11:42 5.4 magnitude earthquake in Chino Hills felt by many. Reactor not operating.

Facility inspection failed to reveal any noticeable effects. USGS Shake map indicates MM IlI-IV only at site. Earthquake SCRAM switch was not tripped (MM-V needed).

August I1th 10:36 Building power failure, reactor not operating. Emergency generator operated within 30 seconds to power radiation systems, etc. Power restored by 10:50.

August 2 1st 15:30 Console power switch failed in ON position. Microswitch responsible was replaced 8/22/08. All functions restored.

November 22-25th Purification pump removed from service. New pump installed to improve flow in system. Pump is identical model. All functions restored.

2009 January 14,15,16th Traimnig tours conducted for personnel from three local fire department units (Irvine, Newport Beach, OC Airport).

May 29 th Rod drop times measured prior to rod and power calibrations. All 4 rods within specifications. SHIM, REG, and ATR rods calibrated. REG rod calibrated slightly higher (by 5.7%) than in 2007. Other rods were within 2%.

June 1st FTR rod calibrated. Total worth for four rods was increased by 1.4% only.

Power calibration preformed. Measured power agreed with all channel indications (at 200 kilowatts power) so no adjustments of channels were performed.

June 16th Failure of Radiation Area monitor (Thermo-Eberline RMSII) station 3 by sudden spike in indicated level. No sign of unusual radiation level on any other station.

Diagnosis is GM tube beginning to fail. Replaced with spare unit. All operations check as normal - monitored for over an hour period to be sure of reliability of new unit.

Section 5 Facility Changes and Special Experiments Approved

.No changes or special or unusual experiments were requested or approved during this period.

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 5

Section 6 Radioactive Effluent Release.

(a) 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 pneumatic transfer system for samples, this is a conservative estihlate in that assumption is made that all use of the PT is at full steady state power level (250 kW) when, in fact, considerable 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 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 of lower masses of concrete structures in the vicinity. In fact the data have been consistently, at 20-25 mrem per year below background level, so confidence of exposure less than 5 mrem over background seems possible.

Release estimates based on operational parameters are as follows:

(1) Operation of pneumatic transfer system (7/1/08-6/30/09):

a. Minutes of operation: 274 minutes

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

c. Flow rate of exhaust air: 1.2 x 108 mL/min.

Total release computed: (a x b x c) = 2.0 x 103 microcuries (2) Release from pool surface (7/1/08-6/30/09):

a. Total hoiirs of operation at full power (Mwh x 4) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

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) 3.5 x 103 microcuries

d. Total of (1) and (2) emission in 1 year = 5.5 x 10 microcuries

e. Total'effluent released in 1 year (525960 minutes/yr. x c) = 6.3 x 1013 mL Concentration averaged over 12 months (d/e) = -< 0.9 x 10-10 microcuries/mL Since 20 x 10-10 microcuries/mL provides an annual exposure for constant immersion of 10 mrem, this corresponds to < 0.5 mrem potential additional radiation exposure to an individual standing breathing in the effluent stack for the entire year.

This is a little higher than 07/08 owing to increased operations and assumes no dilution of the plume at or beyond the stack. It also conservatively assumes all reactor operation were at 250 kw power, whereas significant operation for student class experiments was at 100 kw or 50 kw power levels.

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 6

Section 6. (continued)

(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 UCI Environmental Health and Safety (EH&S). Disposals to this custody are given below. It is important to note that activity values are estimated at the time of transfer to EH&S control. Since few shipments are being made-from campus, decay to negligible levels occurs for all medium-lived radionuclides. Teaching course items (used for training in liquid scintillation counting techniques) may be a mixture of reactor generated byproducts and purchased materials (exclusively 14C and 3H).

DRY WASTES:

One transfer of 1 cubic foot container of dry waste were disposed during this period (7/1/08 through 6/30/09) estimated at a total quantity in 2 cu ft of 0.30 millicuries of mixed activation products (measured as 60Co equivalent at time of transfer).

LIQUIDS:

1 gallon of 3H - containing liquid waste was transferred during this period measured (by LSC) as 0.1 millicuries total, in aqueous solution. This was entirely byproduct (generated by irradiation of LiOH enriched in 6Li). No 14 C was disposed or purchased this year.

Section 7.

Environmental Surveillance.

Calcium Sulfate/Dysprosium thermoluminescent dosimeters have been placed at nine locations around the UCI Campus for many years. Starting July 1 2004, these are provided by Global Dosimetry Solutions (GDS), Costa Mesa, California. The GDS packs have three chips in each pack which are averaged for exposure recording. One pack is kept on the edge of campus in a wood frame house in University Hills. GDS also runs multiple control samples. On August 2 2nd 2007, the ,

locations of these monitors (following ROC discussion and approval) were changed to reflect new building construction at UCI, ease of access for quarterly exchange, and the need to demonstrate absence of effects of reactor use on the campus populations. All dosimeters are now housed in small metal lock-boxes (except for location 10). The table below lists the new locations.

Contamination surveys consisting of wipe tests and G-M surveys have shown mostly a "clean" facility with significant, removable contamination only in areas coming into direct contact with samples removed from the reactor-, and on sample handling tools. Trash is surveyed before disposal and not disposed unless found to be free of removable and fixed contamination.

Table of Locations for Environmental Dosimeter Packs.

1. Below window of reactor room south wall (outside the facility).

2. In hallway on exterior of west wall of facility (inside building).

3. On exterior (north) wall of reactor room - on loading dock.

4. Rowland Hall, room 156 doorway, (over reactor facility).

5. Exhaust air flow from reactor room, roof level (hung in center of duct).

6. McGaugh Hall, hall doorway to laboratory 5346.

7. Langson library across campus, Room 547 closet exterior door.

8. Reines Hall, Gas cylinder storage door, room 5001.

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

10. 12 Perkins Court, University Hills, private residence (wood frame house).

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 7

TABLE IV.

Environmental Dosimetry Data.

2008-2009 Average Total Exposures in mrem (inc1~din~ "control hackm-ound"~

(including "control background")

L ........

Location. Quarter Annual Prior year Excess(08-09) over control 2/08 3/08 4/08 1/09 Total Totals mr 2008/9 2007/8 ANNUAL

1. S. Facility perimeter 22 23 29 27 101 124 -7

2. W. Facility perimeter 23 25 29 29 106 103 -2

3. N Facility perimeter 26 26 33 30 115 121 7

4. Hallway over facility 21 22 27 25 95 97 -13

5. Facility main air exhaust 21 21 23 24 89 97 -19

6. McGaugh Hall top floor 22 22 27 28 99 110 -9

7. Langson Library top floor 26 26 32 31 115 125 7

8. Reines Hall top floor 22 24 28 28 102 101 95-:=.:

9. Facility fume hood exh. 21 22 22 24 897 -i9

10. On-campus housing 19 20 24 26 89 82 -19 Background control (GDS) 23 25 30 30 108 107 0 Discussion Raw data is presented here, along with controls and prior year comparisons. Within this range, the data vary with significant consistency. Locations 1, 3, and 7 are usually the highest, 10 the lowest.

Data for this year reflects several issues:

• all but the location 3 and 7 are less than GDS control background level.

" Location 7 is on top floor of a large building and may experience greater cosmic flux, as well as concrete releases.

, Location 3 is on a heavy concrete wall.

• Location 1 is a hallway with an extremely low occupancy rate. (See additional note below).

" In spite of somewhat increased operations, levels are statistically within range of previous year.

Exposure estimated to a single individual in an uncontrolled area at this facility is still very minimal.

-Locations 1 and 2 are in or hallways with extremely minimal occupancy or travel, especially since security policy is to maintain permanently locked doors to the hallways on this floor level (access only to individuals with building keys). The rooms overhead (location 4) are casually occupied by very few individuals (one or two at the most) in the space above the reactor core. 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. Over many years, the data at each specific location has shown remarkable consistency. The net conclusion is that, within precision of measurement, and compared to distant control areas (numbers 7 and 10), we are operating ALARA with very minimal levels (within statistical error of zero) of potential (full 24/7 occupancy) public exposure over normal background levels.

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 8

Section 8.

Radiation Exposure to Personnel.

Personnel exposure data are summarized in Table V.

UCI issued TLD badges to UCI students or researchers regularly utilizing radiation. Finger dosimetry (TLD) rings are also issued to personnel who might be regularly handling radioactivity. Dosimeters are read quarterly by Global Dosimetry Solutions, and results are presented in Table Va. Data for the second quarter 2009 were not available as of this report, so these are for 12 months of operations since April 1, 2008. Reporting categories are DEEP, EYE, and SHALLOW. Other individuals visiting or casually working in the facility were issued DOSIMAN/R. Results are shown in Table Vb.

3 persons were issued TLD badges on a continual basis; 2 were also issued with finger TLDs. 45 students and 3 teaching assistants in a Radioisotope Techniques class were TLC badged. Reported exposures fell in a narrow range averaging 30 mrem each person for the quarter.

Table Vb. also lists all visiting individuals that were issued with DOSIMAN/R monitors that record in units of 0.1 mR. A tour visitor accumulates 0.0 or 0.1 mR during a 45 minute visit to the facility.

Any reading above 0.1 is tabulated separately.

TABLE Va.

Personnel Exnosure Renort Summary for 12 months: 4/1/08 to 3/30/09 (in mrem)

Individuals Whole BFin erRing DEEP EYE SHALLOW (Shallow) 11 40 64 84 376 22 23 44 44 131 13 0 0 0 0 Totals 63 108 128 507 484 23-37 (mean 30) 23-37 (mean 30) 23-37 (mean 30) not issued class total 1440 1440 1440 -

Totals 1503 1548 1568 507 1 1 - 1-

_(2 persons)

Aggregated non-zero data from self-reading dosimeters issued to researchers or visitors in addition to TLD badges are:

Persons Admissions Total Accumulation (per person) (mrem) 21 6 1.6 11 2 20.6 21 4 0.4 71 7 1.3 48 visitors logged I each 0.0 each 117 in tour groups5 1 each 0.0 to 0.1 each monitor Summation (177 persons) 184 23.9 mrem

1. Individuals doing extensive or casual activation analysis and radiochemical work at the facility. Most of the exposure is a result of C1-38 or Al-28 radioactivity production.

2. Individuals receiving exposure as a result of operator/trainee and/or calibrating activities in the facility.

3. Individual who did NOT ENTER THE FACILITY AT ALL during this period, so ring exposure reported is an indication of range of general background/precision where the badges are stored when not in use.

4. Reported for students and teaching assistants in Radioisotope Techniques class Jan-March 2009. Note badges kept 24/7 in laboratory room. All also ran samples by NAA as well as working with sealed sources.

5. 3-10 dosimeters were issued for tour groups larger than 10 persons. Policy has now been changed to issuing I each for groups up to 10 and 10 randomly for larger groups. No readings > 0.1 mrem were recorded.

Personnel exposures continue to be very low at this facility in keeping with ALARA efforts.

UCI Nuclear Reactor Facility Annual Report 2008-2009 Page 9