ML15218A020

University of California-Irvine - Annual Report Submittal, Per Technical Specification 6.7f

ML15218A020
Person / Time
Site:	University of California - Irvine
Issue date:	07/30/2015
From:	Geoffrey Miller University of California - Irvine
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15218A020 (15)

Text

UNIVERSITY OF CALIFORNIA, IRVINE BERKEULEY

• DAVIS - IRVINE

• LO*SANGELES

• RIERIE - SAN DIEGO -:SAN VRANCISCO *

• SANTA BARBARA - SANTA CRUZ George E. Miller IRVINE, CA 92697-2025 Senior Lecturer Emeritus (949) 824-6649 Departmentof Chemistry and FAX: (949) 824-6082 or (949) 824-8571 Supervisor, Nuclear Reactor Faciiliy lnternet GEMILLER~uci~edu July 30 t , 2015 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 Gentlemen:

Please frnd enclosed the annual report for the UCI Nuclear Reactor Facility, covering the period July 1st 2014 through June 30th 2015.

Electronic copies are being provided as indicated below.

Thank you.

Sincerely, George E. Miller Reactor Supervisor Cc.,w/enc (*electronic copies)

American Nuclear Insu~rance, 95 Glastonbury Blvd, Glastonbury CT 06033, Policy NF- 176

• Ken Janda, Dean of School of Physical Sciences, UCI

• Johnn~y Eads, US Nuclear Regulatory Commission

• Linh Tran, Project Manager, US Nuclear Regulatory Commission

• A Shaka, Chemistry Dept., Director, UCI Nuclear Reactor Facility

• • Reactor Operations Committee Members, UCI

U. C. IRVINE Nuclear Reactor Facility Annual Report for July I1t, 2014 to June 30 ti, 2015 Facility License R- 116 Docket 50-326 Prepared in Accordance with Part 6.7f of the Facility Technical Specifications July, 2015 by Dr. George E. Miller, Reactor Supervisor Jonathan Wallick, Associate Reactor Supervisor and Nuclear Engineer UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg 1 Page

Section 1. Operations Summary (additional details given below)

Operation of this facility supports UCI research and education programs in the Department of Chemistry (CHiEM) 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 (ChIEMS).

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 2014 laboratory course in Radioisotope Techniques using the facility was 34 students with 3 graduate teaching assistants, who also learned these techniques. An additional class teaching the fundamentals of nuclear instrumentation was piloted in the Spring Quarter 2015, with ten students total in attendance.

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. Security upgrades are in the process of being finalized, which have been funded by the DOE GTRI program.

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 remained steady as student use has become stable. Criticality was achieved for 253.95 hours0.0011 days <br />0.0264 hours <br />1.570767e-4 weeks <br />3.61475e-5 months <br />, and the total energy generated was equivalent to 160.81 hours9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br /> at full steady state power. 145 separate experiments were performed, and over 2880 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, all Yellow II category, totaling 29.5 GBq of activity. Twenty-five relatively low power pulses were performed this year, all without incident. Six 50.59 changes were approved this year: (i) a new pressure monitoring system; (ii) replacement ion exchange resin tanks; (iii) water level meter recalibration; (iv) radiation monitor calibration procedure changes; (v) relocation of a pressure monitoring point for the new pressure monitoring system; (vi) experiment authorization amendment for increased activity production. No unusual surveillance results/activities were notedlconducted during this period. No new experiments have been approved this year.

A routine NRC inspection June 8k" to the 11th of 2015, resulted in no Notices of Violation or follow-up items. In 2014-2015, Reactor Operations Committee meetings were held on October 15th, 2014 and February 1 7 th, 2 0 1 5 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, and reactor operators capitalizing on lessons learned in GTRI training at the Y-12 site.

The drill was held on September 9t1,2015, to large success, involving all agencies previously named, running multiple instances of the drill 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 is currently being sought, as the previous individual has left UCI's EH&S team. The UCI Medical Center's Radiation Safety Officer is currently the acting Radiation Safety Officer while recruiting efforts are underway.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Page 2

Several potential operators underwent training this year. One NRC operator examination has taken place this year, involving two new trainees and one SRO-Upgrade candidate. The examination took place from June 15"', 2015 to June 17"', 2015 and all candidates passed. As of June 3 0 th 2015, 4 SRO's and 5 RO's were licensed and active. One SRO is currently inactive. By July 3 0 th 2015, the complement of active licensed operators had increased to 5 SRO's and 6 RO's, with one RO gradating and about to leave.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg Page 3

Section 2. Data Tabulations for the Period July 1st. 2014 to June 30th. 2015 TABLE I.

Experiment Approvals on file 5 Experiments performed (including repeats) 145 Samples irradiated 2880 Energy generated this period (Megawatt hours) 40.20 Total, 69 element core =127.00

>74 element core =1510.76 Total energy generated since initial criticality 1637.76 Mwh Pulse operation this period 25 Total reactor pulses to 6130/2015 1010 Hours critical this period 253.95 Total hours critical to date 9602.50 Inadvertent scrams or unplanned shutdowns or events at power 7 Visitors to reactor - as individuals or in tour groups - 599 Maximum dosimeter recorded for visitors - all less than 0.2 mrem Visiting researchers (Temporary Self Indicating Dosimeters) 17 Maximum exposure recorded at one visit 1.3 mrem Visiting researchers (Thermoluminescent Dosimeters) 33 Students and teaching assistants in class, badged 37 Exposures reported for quarter (range: 0-0 mrem) average 0.0 mrem Isotope Shipments this period (mixed act'n products =0.80 Ci total) 7 TABLE II Reactor Core Status 6/30/15 (core confikuration chanoed 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 6/30/2015) $2.87 Control rod worths (calibrated 1/9/2015) REG $3.00 SHIM $3.52 ATR $1.73 FTR $0.68 Total: $;8.93 Maximum possible pulse insertion (calculated) $2.41 Maximum peak power recorded 226 MW Maximum peak temperature recorded in pulse (B-ring) 214.6°C UCI Nuclear Reactor Facility Annual Report 2014-20 15 Pg Page 4

Section 3.

eyiilSrals. Unnlanned Shutdowns. Events at Power TABLE 111.

DT ime~ Poe 07/08 09:32 75W Linear scram. The Linear power monitor initiated a scram when transitioning from the 75 W range to the 250 W range. The cause of the failure was initially thought to be too quick a reactor period.

Restart was authorized by the SRO. However, upon restart, the Linear power monitor was not auto ranging properly, and the operator manually shut down the reactor. Troubleshooting utilizing the Test switch through all 18 ranges of the Linear power monitor showed no fault, and restart was authorized once more. The subsequent startup was successful without further issue. Root cause was determined to be a fault in the Test circuit potentiometer, which was cleared during troubleshooting.

07/22 11:29 100mW Period scram. While raising power to 1.5 W for training, a period scram occurred. Interference from a cellular phone was determined to be the root cause based on previous events with similar conditions and the presence of the device. Restart authorized by SRO after phone was removed from area.

07/23 10:50 75 mW Period scram. A period scram occurred during a routine start up to 1.5 watts due to operator error of a first time operator. Trainee operator counseled on proper start up procedure, restart authorized by SRO.

07/29 11:25 100 mW Period scram. While raising power to 1.5 W for training, a period scram occurred. Interference from a cellular phone was determined to be the root cause based on previous events with similar conditions and the presence of the device. Restart authorized by SRO aiter phone was removed from area.

09/10 09:36 75 mW Period scram. A period scram occurred during a routine start up to 1.5 watts due to operator error of a first time operator. Trainee operator counseled on proper start up procedure, restart authorized by SRO.

10/21 08:01 250mW Linear scram. During routine start up, a Linear scram occurred when the instrument attempted to automatically switch between the 250 mW and 750 mW ranges. While troubleshooting, the event could not be reproduced and the instrument operated normally. Restart authorized by SRO.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg Page 5

2015 04/02 13:01 150mW Period scram. A period scram occurred during a routine start up to 1.5 watts due to operator error during requalification training. The operator was counseled on proper start up procedure. Restart authorized by SRO.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg 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.

2014 Sept 11th" On September 11t, 2014, the water purification filters were replaced to correct an excessive differential pressure across the component due to particulate accumulation.

Initial differential pressure was 11 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.

Oct 15dh On October 16 th, 2014, a new pressure monitoring system was installed to replace the existing pressure gauges located throughout the purification and cooling systems.

This new instrument is a digital meter with a selector switch mounted inside a waterproof enclosure near the water systems. Pressure inlet and outlet of the purification filters, outlets of the ion exchange tanks, inlet and outlet of the heat exchanger secondary side (no previous indications) are be monitored by this meter. A 50.59 form is on file for this change.

Oct 2 4 th On October 24th 2014, the pool water level meter was recalibrated to measure in feet from the bottom of the pool rather than the arbitrary units it had indicated in up to that point. The two foot long detector was calibrated such that the top of the detecting range was level with the top of the pool, which is 25 feet deep, and the middle of the detector, 1 foot lower, was calibrated to indicate 24 feet. All calibrations were successful and agree with manual readings of current pool water level. The relative alarm level remained unchanged - now set at 24 feet above the pool bottom. A 50.59 form is on file for this change.

Oct 30th' On October 30t% 2014, the location of point number five for the pressure monitoring system was changed from the outlet of the chilled water side of the heat exchanger to the outlet of the cooling pump on the reactor coolant side of the heat exchanger. This provides comprehensive indication of a differential pressure between the two sides of the heat exchanger at the points of interest to prove that pressure of the chilled water side is always higher than that of the reactor coolant side. A 50.59 form is on file for this change.

Dec 17 th On December 17t% 2014, the Wide Range Linear Monitor was cleaned and inspected at the recommendation of the manufacturer to correct the intermittent issues present with the instrument's auto range-changing behavior. The maintenance was performed per the instrument's manual and operations were postponed until a new power calibration was performed. The instrument has been free of issues since.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg Page 7

2015 Jan 9"a On January 9t1,2015, the SHIM, REG, ATR., and FTR rod calibrations were performed. A new preliminary excess of $2.96 was found. Final results for rod worth were: SHIM $3.52 REG $3.00, ATR $1.73, FTR $0.68 for a total of $8.93. Final core excess was reported to be $2.90. On January 9t', 2015, power calibrations were also performed. 84.6% 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.

May 41h On May 4t', 2015, the water purification filters were replaced to correct an excessive differential pressure across the component due to particulate accumulation. Initial differential pressure was 18.3 psid, and after replacement it was observed to be 0.3 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.

June 8 th On June 8"', 2015, the exhaust flow rate from the reactor room was noted to be intermittently low out of specification at 3206 CFM, failing to meet the minimum requirement of 3500 CFM. A trouble call to facilities management was placed and the condition was corrected on June 9"', 2015.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg Page 8

Section 5 Facility Changes and Special Experiments Approved Six 10 CFR 50.59 changes have been implemented during the course of the last year.

The first change was for a new pressure monitoring system installation in order to replace the aging pressure gauges used for indication throughout the purification and cooling systems. This new instrument is a digital meter with a selector switch mounted inside a waterproof enclosure near the water systems. Pressure inlet and outlet of the purification filters, outlets of the ion exchange tanks, inlet and outlet of the heat exchanger secondary side (no previous indications) are to be monitored by this meter.

The second change analyzed and approved was for the intended replacement of the ion exchange resin tanks used in the purification system. The screening process was completed for installation of new tanks with the same type of resin used previously, however the acquisition and installation of the tanks is still in process. It is anticipated that this change will be completed within the next calendar quarter.

The third change was to recalibrate the water level meter to indicate in feet instead of arbitrary units to add ease of use for operators. The alarm and warning set points were reprogrammed to be the same as before and will lose no functionality. Start up and shutdown cheek lists were also updated to reflect these changes.

The fourth change was a change to the procedures used to calibrate the new radiation monitoring system installed at the reactor facility, which required a modified calibration procedure to satisfy maintenance requirements. Calibrations, as recommended by the manufacturer, need only take place at 2 year intervals. The procedure also needed to be amended to exclude the provisions for performing channel tests, as this digital, computer based system has no capability to inject a test signal to the instruments.

The fift~h change was to relocate a pressure detector for the new pressure monitoring system mentioned in the first 50.59 change of the year. The location of point number five for the pressure monitoring system was changed from the outlet of the chilled water side of the heat exchanger to the outlet of the cooling pump on the reactor coolant side of the heat exchanger.

This provided comprehensive indication of a differential pressure between the two sides of the heat exchanger at the points of interest to prove that pressure of the chilled water side is always higher than that of the reactor coolant side.

The sixth and final change of the year was an amendment to a long standing experiment authorization for Professor Nilsson and his research group in the department of the Chemical Engineering and Materials Science. The experiment authorization was amended to include a provision to allow an exception to previously limited isotope production. Specifically, the amendment allowed an experiment in which up to 1 Ci of 1-128, which has a 25 minute half-life, to be produced through normal irradiation procedures using the reactor. The authorization was granted after approval from the Radiation Safety Officer and the Reactor Operations Committee.

Additional precautions were be prescribed and observed in order to allow this amendment.

UCI Nuclear Reactor Facility Annual Report 2014-2015 Pg Page 9

,°

-.- ,4.

Becethon 6. Radioactive Effluent Release.

during normal operations.

The ma~jor direct release to the environs is Argon-4 1 produced materials in experiments.-*

Vary small amounts of other eases may be released from irradiated within the facility Releases are computed based on original measurements at point of origin operation of the pneumaitic and taking only dilution into account. Since much of the release is from is made that all use of transfer system for samples, this is a conservative estimate in that assumption use is with the reactor the PT is at full steady state power level (250 kW) when, in fact, considerable that an integrated dose at a lower power level. In view of the small numbers involved, and the fact in the exhaust at the check is provided by an environmental dosimeter (CaSO 4 -Dy) hanging directly of these estimates.

point of stack discharge, it is considered unnecessary to provide further checksflow for one year The dosimeter data confirm that an individual standing directly in the exhaust the reliability limit of the wottt4 rool~ve an additional submersion dose from the exhaust less than in Secton 7, dositietors, or loss than 20 mrnrm per year. The dosimeter data are presented separately at the exhaust

~Over the years that data have been collected, the accumulated exposure concrete structues in looatlons have been lower than for "control" points because of lower masses of background level, the viofulty, In fact the data have been consistently at 20-25 rnrem per year below so confidene 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 (7/1/14-6/30/15):

a. Minutes of operation: 665.7 minutes

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

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

d. Dilution factor:

(ax bx c d)= 4.9 x101microcuries reeasecomuted Tota (7/1/14-6/30/15):

(2) Release from pool surface hours

a. Total hours of operation at full power (Effective Full Power Hours) =160.81

o. Kelease rate assumed:

1.0 x 10o-8 microcuries/mL

e. Flow rate of exhaust air: 1.2 x 108 mLmi

d. Dilution factor: 0.01 Total release computed: (a x 60 x b x c x d) =l.16 x 1&2microcuries

e. Total of(1) and (2) emission in 1 year g

=l L U Ini2 rO_ fl.... .

minutes/ = 6.31 x 1011 mL released in 1 Year. 525960 .x

• f. Total effluent averaged over 12 months (e/f) = .-< 2.59 x 10-10 microeuries/mL Concentration of 10 Since 2 x 109microcuries/mL provides an annual exposure for constant immersion to an individual mrem, this corresponds to < 1.0 mrem potential additional radiation exposure standing breathing in the effluent stack for the entire year.

released at -100 feet Exhaust is diluted by a factor of 100 before release and the mixed plume is above the roof level (200 feet above surrounding ground).

Report 20 14-2015 UCI Nuclear Reactor Facility Annual 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:

Three transfers of 2 cubic foot containers of dry waste were disposed during this period (7/1/14 through 6/30/15), estimated at a total quantity in 6 cu ft of 18.1 microcuries of mixed activation products (measured as 6°Co equivalent at time of transfer).

LIQUIDS:

One transfer of a 2.5 gallon liquid constituent was made this year. The contents of the container included 670 microcuries of 3 H along with 0.05% trace elements of NaF.

UCI Nuclear Reactor Facility Annual Report 2014-2015Pae1 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 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 20 14-2015Pae1 Page 12

TABLE IV.

Environmental Dosimetry Data.

2014-2015 Average Total Exposures in mrem (including "control background")

Location. Ouarter Annual Prior year Excess(14-15')

over control 2/14 3/14 4/14 1/15 Total Totals mr 2014/15 2013/14 ANNUAL

1. S. Facility perimeter 29 25 24 29 107 123 -2

2. W. Facility perimeter 30 27 27 32 116 192 +7

3. N Facility perimeter 34 28 28 33 123 133 +14

4. Facility main air exhaust 23 21 19 25 88 100 -21

5. Hallway over facility 24 22 21 26 93 107 -16

6. McGaugh Hall top floor 26 24 24 28 102 111 -7

7. Langson Library top floor 32 29 29 33 123 134 +14

8. Reines Hall top floor 28 26 24 29 107 119 -2

9. Facility emer. exhaust 23 21 21 25 90 102 -19

10. On-campus housing 24 22 21 25 92 109 -17 11 Facility fume hood exh. 24 21 20 24 89 104 -20 12 Engineering Tower 521 25 22 22 25 94 105 -15 Background control -Mirion 28 23 27 31 109 115 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 1 is a hallway with an extremely low occupancy rate. (See additional note below).

• 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.

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

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 2014-2015Pae1 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, 2014. 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. 47 persons were issued TLD badges on a continual basis; 47 were also issued with finger TLDs. 34 students and 3 teaching assistants in a Radioisotope Techniques class were TLD badged. Reported exposures for the Radioisotopes Techniques class were non-existent this year, averaging 0.0 mrem each person for the quarter.

Table V-II. also lists all visiting individuals that were issued with DOSIMANIR monitors that record in units of 0.1 mR. In the course of a few hours, a worker can accumulate 0.2 nmr. A tour visitor accumulates 0.0 or 0.1I 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: 4/1/14 to 3/30/15 (in millirem)

Individuals Whole Body Finger Ring DEEP EYE SHALLOW (Shallow) 11' 201 201 201 1158 32 0 0 0 0 333 0 0 0 0 Totals 201 201 201 1158 374 Range 0-0 (mean 0.0) Range 0-0 (mean 0.0) Range 0-0 (mean 0.0) not issued class total 0 0 0 Totals 201 201 201 1158

_____ (84 individuals) (84 individuals) (84 individuals) (47 persons)

TABLE V-Il A~ggregated non-zero data from self-reading dosimeters issued to researchers or visitors in addition to TLD badges are:

Persons J Admissions (per person)

{ Total Accumulation (mrem) 497 ine 17' vstours grougsd 109ohe visitour og edps 5 each on average 1 each 1 each onaeae0.

jn0.0rto oO 8.8 0.19ahmoio ac 9 oio Total 616 persons Total 696 Total 9.7 mrem I. Individuals doing extensive or casual activation analysis and radiochemical work at the facility. Most of the exposure is a result of CI-38 or AI-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 2014. Note badges kept 24/7 in laboratory room. All also ran samples by NAA as well as working with sealed sources.

5. Issuing I dosimeter each for groups up to 10 and 10 randomnly 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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