ML16272A086

University of California, Irvine - Annual Report Submittal in Accordance with Technical Specification 6.7.1

ML16272A086
Person / Time
Site:	University of California - Irvine
Issue date:	09/26/2016
From:	Shaka A University of California - Irvine
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16272A086 (15)

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UNIVERSITY OF CALIFORNIA, IRVINE Department of Chemistry 1102 Natural Sciences II University of California, Irvine Irvine, CA 92697-2025 Monday, September 26, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

University of California- Irvine, Docket Number 50-326, License Number R-116, Annual ReportSubmittal in Accordance with TechnicalSpecification 6.7.1

DearSir or Madam:

By way of this letter, the University of California, Irvine is submitting the annual operating report as required by TechnicalSpecification 6:7.1 of license number R-116, covering the period of July 15\

2015 through June 301\ 2016.

Electronic copies are being provided as indicated below.

9 If you have any questions regarding this matter, please contact me at (949) 824-6082.

Sincere Dr. Athan James Shaka Reactor Director

Enclosure:

As stated CC with

Enclosure:

• American Nuclear Insurance, 95 Glastonbury Blvd., Glastonbury CT 06033, Policy NF-176

• Ken Janda, Dean ofSchool of PhysicalSciences, University of California, Irvine

• Johnny Eads, inspector, U. S. Nuclear Regulatory Commission

• Linh Tran, Project Manager, U.S. Nuclear Regulatory Commission

• George Miller, Chemistry Department, ReactorSupervisor, University of California, Irvine

• Reactor Operations Committee Members, University of California, Irvine

U. C. IRVINE Nuclear Reactor Facility Annual Report for July 1st, 2015 to June 30th, 2016 Facility License R-116 Docket 50-326 Prepared in Accordance with Part 6.7f of the Facility Technical Specifications July, 2016 by Dr. George E. Miller, Reactor Supervisor Jonathan Wallick, Assistant Nuclear Engineer UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 1

Section 1 Operations Summary (additional details given below)

Operation of this facility supports UCI research and education programs in the Department of Chemistry (CHEM) and the Department of Chemical Engineering and Material Science (ChEMS).

Research is being conducted in application of radioisotopes as tracers and radiochemical analytical and separation techniques including applications to nuclear waste separations (ChEMS).

Reactor utilization, apart from operator training and maintenance, is for analytical sample irradiation and production of isotopic tracers. Analysis samples come from diverse origins related to forensic science, fossil fuels, geochemistry, art, and archaeological studies, chemical separations in nuclear fuel cycle experiments, 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 Fall Quarter 2015 laboratory course in Radioisotope Techniques using the facility was 33 students with 2 graduate teaching assistants, who also learned these techniques.

Support for UCI faculty and students includes grants from NRC and DOE (NEUP and NSSA),

and partnerships with national laboratories (PNNL, LLNL, LANL, and INL).

Use is also made of the facility by other educational institutions, both for research and for visits/tours. A modest Nuclear Science Outreach program (NSOP) using UCI students to present talks and a laboratory to middle and high school classes has been continued. This program has also involved tours, class demonstrations, and analyses of samples submitted by faculty.

Operations have increased substantially as student use and interest has risen. Criticality was achieved for 313.61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br />, an increase of 23% from last year, and the total energy generated was equivalent to 241.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> at full steady state power, up 50% from last year. 186 separate experiments were performed, up 28%, and over 4000 samples were irradiated, up 39% (sometimes multiple samples are included in a single capsule and are not always separately logged). 3 moderate level mixed isotope shipments were made, all Yellow II category, totaling 1.04 GBq of activity. No pulses were performed this year. Four 10 CFR 50.59 changes have been initiated and three have been completed during the course of the last year: (i) the pool water level monitoring channel alarm was set higher to align with the proposed technical specifications of the license renewal in progress; (ii, iii, and iv) a large portion of the adjacent loading dock is being converted into a laboratory space for a new professor and needed security and dosimetry changes. A few unusual surveillance results/activities were noted/conducted during this period: failure of the pneumatic transfer system blower motor; failure of the air operated solenoid valve for the FTR; power failure of a radiation area monitor; and replacement of the ion exchange resin tanks. No new experiments have been approved this year.

A routine NRC inspection June 14th to the 16th of 2016, resulted in no Notices of Violation or follow-up items. In 2015-2016, Reactor Operations Committee meetings were held on September 24th, 2015 and March 22nd, 2016 in accordance with Technical Specification requirements.

No follow-ups or incidents have been forthcoming regarding security or emergency response.

One emergency drill / exercise has been held this past year involving the UCI EH&S radiological personnel, Orange County Fire Authority, UCI Police Department, Orange County Health Department, Irvine Police Department, and reactor operators capitalizing on lessons learned in GTRI training at the Y-12 site. The exercise was held on September 23rd, 2015, to large success, involving all agencies previously named, running tabletop scenarios with different subgroups.

Inspections/audits continue to be conducted quarterly by the Radiation Protection staff of EH&S at UCI. These have identified that frequency schedules have been properly maintained, and results continue to show absence of significant levels of contamination or personnel exposure. A new Radiation Safety Officer has been hired in the last year, as the previous individual left UCIs UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 2

EH&S team. The UCI Medical Centers Radiation Safety Officer was acting Radiation Safety Officer until the new hire and certification was completed.

No new operator trainees underwent training this year. No NRC operator examinations have taken place this year. As of June 30th 2016, 5 SROs and 4 ROs were licensed and active. One SRO is currently inactive.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 3

Section 2 Data Tabulations for the Period July 1st, 2015 to June 30th, 2016 TABLE I.

Experiment Approvals on file 5 Experiments performed (including repeats) 186 Samples irradiated 4000 Energy generated this period (Megawatt hours) 60.31 Total, 69 element core = 127.00

>74 element core = 1571.07 Total energy generated since initial criticality 1698.07 Mwh Pulse operation this period 0 Total reactor pulses to 6/30/2016 1010 Hours critical this period 313.61 Total hours critical to date 9916.11 Inadvertent scrams or unplanned shutdowns or events at power 6 Visitors to reactor - as individuals or in tour groups - 737 Maximum dosimeter recorded for visitors - all less than 0.2 mrem Visiting researchers (Temporary Self Indicating Dosimeters) 28 Maximum exposure recorded at one visit 6.9 mrem Visiting researchers (Thermoluminescent Dosimeters) 49 Students and teaching assistants in class, badged 35 Exposures reported for quarter (range: 0-42 mrem) average 18.7 mrem Isotope Shipments this Period (Mixed Activation Products = 0.03 Ci total) 3 TABLE II Reactor Core Status 6/30/16 (core configuration changed as of 11/6/12)

Fuel elements in core (including 2 fuel followers) 84 Fuel elements in storage (reactor tank - used) 23 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 2 Experimental facilities in core positions 5 Non-fuel control rods 2 Total core positions accounted for 127 Core excess, cold, no xenon (as of 6/30/2016) $2.80 Control Rod Worths (Calibrated 1/20/2016) REG $2.95 SHIM $3.43 ATR $1.74 FTR $0.68 Total: $8.80 Maximum possible pulse insertion (calculated) $2.42 Maximum peak power recorded No Pulses This Period Maximum peak temperature recorded in pulse (B-ring) 196.7 °C UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 4

Section 3 Inadvertent Scrams, Unplanned Shutdowns, Events at Power TABLE III.

Date Time Power Type and Cause 2015 07/28 11:17 250 kW Linear scram. The linear power monitor initiated a scram while operating at 100% of the 250 kW range. All control rods dropped and the reactor was put into a safe condition. The cause of the failure was an operator attempting to determine the source of noise in the signal of the paper recorder on the linear power channel. While attempting to determine the source, the operator began tapping different external components of the linear power monitor and the scram occurred as a result of the slight mechanical shocks. The operator was counselled regarding troubleshooting while at power and instructed to refrain from doing so, instead to inform technical staff and troubleshoot offline. Restart was authorized by the SRO. Troubleshooting later eliminated the spurious noise in the signal. Root cause was determined to be errant noise of an unknown origin and was not reproducible.

08/07 09:13 250 kW Linear scram. The linear power monitor initiated a scram while stabilizing power at 100% of the 250 kW range. At approximately 106% of the 250 kW range, the linear power monitor initiated a scram.

All control rods dropped and the reactor was put into a safe condition.

Troubleshooting was performed and root cause of the failure was determined to be a stuck button, the REG UP button, and operator error in the individual not responding quickly enough to correct the condition. The event was not found to be reproducible, though the operator was cautioned to be more aware of such events and immediately depress the DOWN buttons for both SHIM and REG in such an event. Restart was authorized by the SRO.

08/13 15:58 1.5 W Period scram. A period scram occurred during a routine start up to 250 kW watts. All control rods dropped and the reactor was put into a safe condition. The root cause of the failure was operator error, in that the operator was not conscious enough of the period being established during the start up. The operator was counselled to be more attentive to reactor period during start up. Restart was authorized by the SRO.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 5

08/31 16:15 250 kW Linear scram. The linear power monitor initiated a scram while stabilizing power at 100% of the 250 kW range. At approximately 106% of the 250 kW range, the linear power monitor initiated a scram.

All control rods dropped and the reactor was put into a safe condition.

Troubleshooting was performed and root cause of the failure was determined to be a stuck button, the REG UP button, and operator error in the individual not responding quickly enough to correct the condition. The event was not found to be reproducible, though the operator was cautioned to be more aware of such events and immediately depress the DOWN buttons for both SHIM and REG in such an event. Restart was authorized by the SRO.

2016 01/07 12:07 250 kW High Voltage scram. The linear power monitor initiated a scram while operating at 100% of the 250 kW range. All control rods dropped and the reactor was placed into a safe condition. Troubleshooting was performed and the root cause was unable to be determined. During troubleshooting, the NON-OP light on the linear power monitor extinguished due to no apparent reason. All wiring connections between detector, the linear power monitor, and scram circuits was visually inspected and physically ensured to be secure, revealing no obvious faults. Restart was authorized by SRO and no further occurrences have been observed.

02/22 16:15 250 kW Linear scram. The linear power monitor initiated a scram while stabilizing power at 100% of the 250 kW range. At approximately 106% of the 250 kW range, the linear power monitor initiated a scram.

All control rods dropped and the reactor was put into a safe condition.

Troubleshooting was performed and root cause of the failure was determined to be a stuck button, the REG UP button, and operator error in the individual not responding quickly enough to correct the condition. The event was not found to be reproducible, though the operator was cautioned to be more aware of such events and immediately depress the DOWN buttons for both SHIM and REG in such an event. Restart was authorized by the SRO.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 6

Section 4 Maintenance and Surveillance and Other Incidents 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.

2015 08/13 On August 13th, 2015, the pneumatic transfer system blower motor failed and the pneumatic transfer system was removed from service. After performing a clean and inspection and a carbon brush replacement, it was determined that the commutator of the motor was damaged beyond usability and required resurfacing and motor rewinding. On September 30th, 2015, the motor was removed from the system, surveyed for fixed and removable contaminations, released from radiological control, and transferred to an external motor shop. On October 23rd, 2015, the motor was returned and reinstalled in the pneumatic transfer system. A functional test was performed and the motor was found to operate satisfactorily. The pneumatic transfer system was then returned to full service.

08/25 On August 25th, 2015, the water purification filters were replaced to correct an excessive differential pressure across the component due to particulate accumulation.

Initial differential pressure was 13.47 psid, and after replacement it was observed to be <1 psid. The radiation level of the used filters was measured to be less than 0.05 mr/hr on contact. The filters were stored for drying and later gamma spectrometry assessment. No unexpected radioisotopes were found upon gamma spectrometry of the filters.

10/09 On October 9th, 2015, an alarm was reported by the police department to an SRO after normal working hours. Entry into the facility revealed the alarm to be false in nature, related to a secondary radiation monitoring system. The following working day, all alarms were tested and found to operate satisfactorily.

10/14 On October 14th, 2015, during a reactor shutdown from 1.5 W, a strange noise was observed during the scram. Investigation revealed the noise source to be originating from the FTR solenoid operated air valve. The valve was found to be stuck in the venting position, preventing the FTR from ejecting out the core, but remaining stationary in the core. A cleaning and inspection of the FTR air valve showed an o-ring had bound in the diverting part of the valve, causing supply air to vent to atmosphere during attempted operation. Replacements were ordered and all reactor operation was suspended until the maintenance activity and subsequent testing were completed. On October 16th, 2015, all O-rings were replaced and valves fully cleaned and lubricated for both the FTR and the ATR. Proper operation was tested and verified by cycling the valves several times. Rod drop testing was them performed and found to be within specification. Normal operation was then permitted once again.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 7

2016 01/19 On January 19th, 2016, the SHIM, REG, ATR, and FTR rod calibrations were performed. A new preliminary excess of $2.88 was found. Final results for rod worth were: SHIM $3.43 REG $2.95, ATR $1.74, FTR $0.68 for a total of $8.80. Final core excess was reported to be $2.81. On January 19th, 2016, power calibrations were also performed. 79.0% actual power was found for the previous setting of 80.0%,

requiring adjustment of balance potentiometers on the channels. All instrumentation is now in correct alignment for calculated power level values.

02/09 On February 9th, 2016, radiation monitor iR7040-2 was found to have lost network communications with the radiation monitoring server while performing routine reactor startup checklist. Power to the unit was cycled and the unit failed to turn on.

The unit was placed out of service and a trouble call was placed with the manufacturer. Through troubleshooting the unit, it was discovered that a small, internal battery had exhausted and needed replacement. Pneumatic transfer system operations, monitored by the device, were suspended until repair could be affected to the unit. On February 17th, 2016, a replacement battery was installed in the unit and the unit then functioned normally. The unit was returned to service and pneumatic transfer system operations were then authorized to resume.

06/01 On June 1st, 2016, the ion exchange resin tanks and a moderate portion of purification system piping was replaced. This was done to alleviate the large differential pressure across the resin tanks due to accumulated blockage and channeling that had occurred over the past twenty years of use. The complete tanks were removed from the system and replaced with lighter, composite style tanks filled with an equivalent resin of the same volume. The used resin tanks are being stored for decay and drying, which will be disposed of at a later date. The removed piping was completely disassembled, dried, checked for fixed and removable contamination, released from radioactive control, and disposed of. A 50.59 screening form is on file for this change.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 8

Section 5 Facility Changes and Special Experiments Approved Four 10 CFR 50.59 changes have been initiated and three have been completed during the course of the last year.

The first change was for changing the alarm set point of the pool water level monitoring channel to a higher level in accordance with the proposed technical specifications of the renewed reactor facility license. The change also included changing the required numbers on the startup and shutdown checklist forms, as well as including the addition of a newly licensed SRO at the facility. The change was approved and completed.

The second, third, and fourth changes all resulted from the conversion of a space adjacent to the reactor facility from an open loading dock to an enclosed laboratory space. The second change was in specific reference to the need to move an environmental dosimeter a few feet to one side along the same wall and installation of a secondary environmental dosimeter in the space. The third change was in specific reference to the need to implement additional security measures along the wall now adjacent to a laboratory space and an update to the security plan, which has been completed. The fourth change was a general reference to the fact that the space was previously an open loading dock and is being converted to an enclosed laboratory space adjacent to the north wall of the facility. Since the conversion is still in progress at the time of this report, changes two and four remain outstanding and awaiting completion.

A 50.59 change initiated in reporting year 2014-2015 relating to the installation of replacement resin tanks was completed this year, as described in section 4 of this report, entry 2016-06/01.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 9

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 measurements 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 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 (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 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 locations 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 (7/1/54-6/30/16):

a. Minutes of operation: 821.6 minutes

b. Release rate assumed: 6.0 x 10-8 microcuries/mL

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

d. Dilution factor: 0.01 Total release computed: (a x b x c x d) = 5.92 x 101 microcuries (2) Release from pool surface (7/1/15-6/30/16):

a. Total hours of operation at full power (EFPH) = 241.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />

b. Release rate assumed: 1.0 x 10-8 microcuries/mL

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

d. Dilution factor: 0.01 Total release computed: (a x 60 x b x c x d) = 1.74 x 102 microcuries

e. Total of (1) and (2) emission in 1 year = 2.33 x 102 microcuries

f. Total effluent released in 1 year (525960 minutes/yr. x c x d) = 6.31 x 1011 mL Concentration averaged over 12 months (e/f) = ~< 3.69 x 10-10 microcuries/mL

-9 Since 2 x 10 microcuries/mL provides an annual exposure for constant immersion of 10 mrem, this corresponds to < 2.0 mrem potential additional radiation exposure to an individual standing in and breathing in the effluent stack for the entire year.

Exhaust is diluted by a factor of 100 before release and the mixed plume is released at ~100 feet above the roof level (200 feet above surrounding ground, granting even greater dilution).

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 10

(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:

Five transfers of 2 cubic foot containers of dry waste were disposed during this period (7/1/15 through 6/30/16), estimated at a total quantity in 10 cu ft of 34.7 microcuries of mixed activation products (measured as 60Co equivalent at time of transfer).

LIQUIDS:

Three transfers of 2.5 gallon containers of liquid constituent were made this year. The first contained 1440 microcuries of 3H along with 0.05% trace elements of NaF, the second 570 microcuries of 3H along with 0.05% trace elements of NaF, and the third 20 microcuries of 32 P.

UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 11

Section 7 Environmental Surveillance.

Calcium Sulfate/Dysprosium thermoluminescent dosimeters are in place at 12 locations around the UCI Campus for environmental monitoring purposes. These are now provided by Mirion Technologies, Irvine, California (formerly Global Dosimetry Systems). The environmental packs have three chips in each pack which are averaged for exposure recording. Mirion runs multiple control samples in addition to the locations listed below. All dosimeters are housed in small metal lock-boxes (except for locations 10 and 12). The table below lists the locations. One dosimeter is located in a radiochemistry laboratory in Engineering Tower, Room 521 (#12), for a total of 12.

Routine 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 of unless found to be free of removable and fixed contamination.

Table of Locations for Environmental Dosimeter Packs.

1. South Reactor Facility Perimeter

2. West Reactor Facility Perimeter

3. North Reactor Facility Perimeter

4. Reactor Facility Main Air Exhaust

5. Rowland Hall, First Floor Hallway Over Reactor Facility

6. McGaugh Hall Top Floor

7. Langson Library Top Floor

8. Reines Hall Top Floor

9. Reactor Facility Emergency Exhaust Duct

10. On-campus Housing

11. Rowland Hall Building Fume Hood Exhaust Duct

12. Engineering Tower Room 521 UCI Nuclear Reactor Facility Annual Report 2015-2016 Page 12

TABLE IV.

Environmental Dosimetry Data.

2015-2016 Average Total Exposures in mrem (including control background)

Location. Quarter Annual Prior year Excess(15-16) over control 2/15 3/15 4/15 1/16 Total Totals mr 2015/16 2014/15 ANNUAL

1. S. Facility perimeter 24 28 31 29 112 107 0

2. W. Facility perimeter 30 37 32 32 131 116 +19

3. N Facility perimeter 29 31 35 30 125 123 +13

4. Facility main air exhaust 22 23 24 24 93 88 -19

5. Hallway over facility 24 24 28 25 101 93 -11

6. McGaugh Hall top floor 25 26 28 27 106 102 -6

7. Langson Library top floor 31 32 35 31 129 123 +17

8. Reines Hall top floor 26 27 30 27 110 107 -2

9. Facility emer. exhaust 21 23 24 23 91 90 -21

10. On-campus housing 22 24 28 24 98 92 -14 11 Facility fume hood exh. 22 21 24 24 91 89 -21 12 Engineering Tower 521 22 23 26 26 97 94 -15 Background control -Mirion 27 28 29 28 112 109 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 9 are usually the highest, 10 the lowest.

Data for this year reflects several issues:

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

• Location 2 is on the other side of a location in the reactor facility temporarily used for source storage.

• Location 3 is on a heavy concrete wall, the other side of which is a location in the reactor facility temporarily used for source storage.

Exposure estimated to a single individual in an uncontrolled area at this facility is minimal. With the exception of two locations near the facility, all dosimetry associated with exposures from the facility indicates lower than control levels. Locations 1, 2, and 3 are in 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 with building keys). The rooms overhead (location 5) 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/building (measured by locations 4, 9, and 11) continues to give no detectable exposure above background. 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 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 2015-2016 Page 13

Section 8 Radiation Exposure to Personnel.

Personnel exposure data are summarized in Table V-I.

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 radioactive sources. TLDs are read quarterly by Mirion Technologies, and results are presented in Table V-I.

Data are for 4 quarters of operations since April 1, 2015. Reporting categories are DEEP, EYE, and SHALLOW. Other individuals visiting or casually working in the facility were issued DOSIMAN/R for which results are shown in Table V-II. 49 persons were issued TLD badges on a continual basis; 49 were also issued with finger TLDs. 33 students and 2 teaching assistants in a Radioisotope Techniques class were TLD badged. Reported exposures for the Radioisotopes Techniques class were higher than normal, likely due to improper storage of dosimetry, on the part of the teaching assistants, near a neutron source, averaging 18.7 mrem each person for the quarter.

Table V-II. also lists all visiting individuals that were issued with DOSIMAN/R monitors that record in units of 0.1 mR. In the course of a few hours, a worker can accumulate 0.2 mr. A tour visitor accumulates 0.0 or 0.1 mR during a 45 minute visit to the facility. Any reading above 0.2 is thus tabulated separately.

TABLE V-I.

Personnel Exposure Report Summary for 12 months: 4/1/15 to 3/30/16 (in millirem)

Individuals Whole Body Finger Ring DEEP EYE SHALLOW (Shallow) 291 75 75 75 1141 02 0 0 0 0 203 0 0 0 0 Totals 75 75 75 1141 354 Range 0-42 (mean 18.7) Range 0-42 (mean 18.7) Range 0-42 (mean 18.7) not issued class total 653 653 653 -

Totals 728 728 728 1141 (84 individuals) (84 individuals) (84 individuals) (47 persons)

TABLE V-II 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) 281 5 each on average 27.8 130 other visitors logged 1 each on average 0.9 607 in tour groups5 1 each 0.0 to 0.1 each monitor Total 765 persons Total 877 Total 38.7 mrem

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

2. Individuals receiving exposure as a result of shipping isotopes, and/or calibration activities in the facility.

3. Individuals who did enter but not carry out radiation related activities during this period, so any 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 Sep-Dec 2015. Note badges kept 24/7 in laboratory room. All also ran samples by NAA as well as working with sealed sources.

5. Issuing 1 dosimeter each for groups up to 10 and 10 randomly for larger groups. No readings > 0.2 mrem were recorded.

Personnel exposures continue to be very low at this facility in keeping with ALARA efforts. Fewer isotope shipments have been made this year, so exposure from that activity is lower.

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