ML20204G554

Univ of Virginia Reactor Facility 1998 Annual Rept

ML20204G554
Person / Time
Site:	University of Virginia
Issue date:	12/31/1998
From:	VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:
References
NUDOCS 9903260178
Download: ML20204G554 (37)

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g UNIVERSITY OF l VIRGINIA I

REACTOR FACILITY I i I

1998 l ANNUAL REPORT I

E

[ L E

[ This repon was compiled by the following personnel:

Section IV, Health Physics -

Deborah Steva, Reactor Health Physicist All other sections -

Paul Benneche, Reactor Supervisor

I 1998 ANNUAL REPORT UNIVERSITY OF VIRGINIA REACTOR FACILITY Table of Contents Eage I. INTRODUCTION ... .........................................1 I A. Reactor Facility Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1. Reporting Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

2. B asis for Reporting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 I B. Reactor Facility Description . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 1

- 1. 2 MW UVAR .........................................1

2. 100-watt C AVALIER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 3. Past Operating History . . . . . . . . . . . . . . . . . . . . . . . . . . ...... .. 3 a . U V AR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 3

b. CAVALIER ................. ...................... 5

4. Summary of l998 Reactor Utilization . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 a.UVAR............................ ..... .. ...... 5

5. Special Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 l Reactor Staff Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 C.

1. Operatio ns Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

2. Health Physics Staff . . . . . . . . . . . .................. ....... 7 l

3. Reactor Safety Committee . . . . . . . . . . . . . . . . . . . ..... ........ 7 '

l II. REACTOR OPL A ATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 A. UVAR. ................................................9 l 1. Core Configurations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 I 2.

3.

Standard Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 9

a. Rod Drop Tests and Visual Inspection . . . . . . . . . . . . . . . . . . . . . . . 9

[

b. Tests and Calibrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 y 4. M aintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 l

5. Unplanned Shutdowns ................................ . . 15

6. Pool Water Make-up . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

7. Fuel Shipments . . . . . . . . . . . . . . . . . . . . . . ......... . . . . . . . 15

a. Fre sh Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

b. S pent Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . 15

8. Personnel Training and Instruction . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

a. Reactor Facility Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

b. Summer Course for High School Teachers . . . . . . . . . . . . . . . . . . . 16

9. Reactor Tours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 B. CAVALIER ............... .......... ..............16

1. Reactor Shutdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 16

l 11 l Eage III. REGULATORY COM PLIANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 A. Reactor Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

1. M eet ing s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 -

.I 2. Au d it s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 i 3. App ro vals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

4. 10 CFR 50.59 Reviews . . . . ................ . . . . . . . . . . . . . 17 l

B. I n spectio ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

)

1 l

C. Lice nsing Actio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 l D. Emergency Preparedness . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 l

IV. HEALTH PHYS ICS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 A. Personnel Dosir.ietry . . . . . . ............... ............ . . . 19 l

1. Visitor Exposure Data For 1998 ............................. 19

2. Reactor Facility Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19

a. Monthly Whole Body Badge Data . . . . . . . . . . . . . . . . . . . . . . . . . 19 I b.

c.

Neutron Exposures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 Extremity Exposures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 l

d. Direct-reading Dosimeter Exp 7sures . . . . . . . . . . . . . . . . . . . . . . . 21 I B. Effluents Released During 1998 ................................21

1. Airborne Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

2. Liquid Effluents . . ....................................21

3. Solid Waste Shipments . . . . . . . . . . ........................22

~

C. Environmental Surveillance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24

1. Wate r S ampling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24

^

2. Ai r S amp li ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4

3. Outside Area TLD Network . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 D. UVAR Facility liealth Physics Surveys . ..........................26

1. Radiation and Contamination Surveys ...................... . . 26

Airborne Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 27 E. Quality Assurance .........................................27 L F. Unusual Occurrences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 F. S u mmary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 8 I

l

. ~- .. .. . . _ - _ . . - -- .- , - _ . - .- _ _

l.

l l iii l

I h2 l V. RESEARCH, EDUCATION AND SERVICE ACTIVITIES .................29 l

t A. Irradiation and Other Research Facilities Available . . . . . . . . . . . . . . . . . . . . 29 l

l l B. Research Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......29 l

C. S ervice Projects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 l

l D. Reactor Sharing Program . . . . . . . . . . . . . ................ . . . . . . 30 l

l E. Reactor Facility Supported Courses and Laboratories . . . . . . . . . . . . . . . . . . 30 F. Degrees Granted by U.Va. in Nuclear Engineering . . . . . . . . . . . . . . . . . . . . 31 l

VI. FINANCES ...............................................32 l

l A. Expenditures . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ..............32

! B. Income ...............................................32 l

l C. State Support / Research and Service Income . . . . . . . . . . . . . . . . . . . . . . . . 32 1

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1 1998 ANNUAL REPORT University of Virginia Reactor Facility I. INTRODUCTION l A. Reactor Facility Recorting Recuirements

1. Reoorting Period This report on Reactor Facility activities during 1998 covers the period January 1, 1998 through December 31,1998.

2. Basis for Reoorting An annual report of reactor operations is required by the UVAR Technical Specifications, Section 6.7.2. Additionally, it is the desire of the Facility management to document and publicize the most important results derived from reactor operations.

B. Reactor Facility Descriotion The University of Virginia Research Reactor (UVAR) was operated from June 1960 I through June 1998. The Administration of the University of Virginia School of Engineering and Applied Science, with the approval of the University's Board of Visitors, decided to permanently cease reactor operations on July 1,1998 and to begin the process of decommissioning the Reactor Facility.

The Reactor Facility is located on the grounds of the University of Virginia (UVA) at Charlottesville, Virginia and is administratively a part of the Office of the Vice President for Research and Public Service. The Facility houses the two megawatt UVAR, a pool type research reactor, and the Cooperatively Assembled Virginia Low Intensity Educational Reactor (CAVALIER), a 100 watt training reactor, which was shut down in 1988 and is also awaiting decommissioning. The Facility also has a 2,000 curie cobalt-60 gamma irradiation facility, a hot cell facility with remote manipulators, several radiochemistry laboratories with fume hoods, radiation detectors, counters and laboratory counting equipment, computerized data acquisition-analysis systems, r machine and electronics shops.

1. 2 MW UVAR The UVAR is a light water cooled, moderated and shielded type reactor that first

! went into operation at a licensed power level of one megawatt in June 1960, under license No. R-66. In 1971, the authorized power level was increased to two megawatts. In September 1982 the operating license for the UVAR was extended for 20 years. The UVAR was converted to low enriched uranium (LEU) fuel during 1994. The fuel elements used in the reactor were moved to storage locations on the bottom of the reactor pool on September 3,1998, where they will remain I

2 I

until their transfer to the federal government's Savannah River Laboratory. The four control rod elements used in the reactor have been shipped, and the remaining I used and unused fuel elements should be shipped in 1999. Figure 1 shows a layout of the reactor and the various experimental facilities associated with the UVAR.

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I 3

2. 100 W CAVALIER l The CAVALIER first went into operation in October 1974, under license R-123, at a licensed maximum power of 100 watts. The reactor was built to accommodate reactor operator training and perform experiments for undergraduate laboratory courses. The operating license was renewed in May 1985, for a period of 20 years.

Figure 2 shows a layout of this reactor and its control room. A dismantlement plan was submitted in November,1987 to the U.S. Nuclear Regulatory Com. mission (NRC). The NRC requested a decommissioning plan which was submitted early in 1990. An order to decommission was issued by the NRC on February 3,1992.

The reactor will be decommissioned in the near future.

3. Past Onerating History

a. UVAR The UVAR operating history is shown in Table 1.

TABLE 1 Operating History of University of Virginia Reactor Year (s) Megawatt-hours Hours Operated 1960-1970 3,960 4,500 1971-1975 1,654 1,800 1976-1978 1,769 1,480 1979-1980 9,036 5,627 1981 4,988 3,568 1982 5,507 3,024 1983 6,079 3,556 1984 5,687 3,166 1985 927 718 1986 1,330 891 1987 1,220 801 1988 910 621 1989 1,378 869 1990 1,837 1,087 1991 2,360 1,365 1992 2,428 1,450 1993 2,663 1,533 1994 1,594 1,016 1995 1,703 1,079 1996 1,741 1,083 1997 1,954 1,230 1998 (to 7/1) 686 437 after 7/1/98 shutdown shutdown During the years 1979 through 1984, the UVAR was operated approximately 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> per week to irradiate metal specimens for radiation damage studies on pressure vessel steels. Since that time, the reactor has operated on a variable schedule up to about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week. The UVAR first operated at full power with LEU fuel on May 12,1994.

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b. CAVALIER The CAVALIER operating history is shown in Table 2.

TABLE 2 Operating History of CAVALIER Year (s) Watt-hours Hours Operated 1974-1980 2,128 758 1981-1985 1,278 388 1986 147 37 1987 28 29 1988-present shutdown shutdowTi l

The CAVALIER was used primarily for reactor operator training and undergraduate lab experiments, although it has not been operated over the past nine years. The last date of operation was August 4,1987.

The CAVALIER fuel and start-up source were unloaded on March 3,1988.

A decommissioning plan was submitted to the NRC in January,1990. An order to decommission was issued by the NRC on February 3,1992.

Decommissioning should be completed in the near future.

4. Summarv of 1998 Reactor Utilization

a. UVAR During the first six months of 1998 (the period during which the reactor was operated), the UVAR was operated for 437 hours0.00506 days <br />0.121 hours <br />7.225529e-4 weeks <br />1.662785e-4 months <br /> and a total integrated power of 686 Megawatt-hours The following projects were performed utilizing the UVAR (some were performed concurrently with others):

- 9 neutron activation analysis (NAA) samples were run in the I pneumatic rabbit systems (total activation time: 16 minutes)

- 3 sources were produced in the rabbits in 7.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

. - 2 irradiation cycles of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> each were completed in the mineral irradiation facility (MIF), total of 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.

18 containers or specimens were irradiated in the canister irradiation facility (CIF) for a total irradiation time of 182 hours0.00211 days <br />0.0506 hours <br />3.009259e-4 weeks <br />6.9251e-5 months <br />.

- 105 items were irradiated in the Small Animal Irradiation Neutron Tube l (55 live mice for a total of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />,30 mouse phantoms for dosimetry measurements for 5.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 cell samples in 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

- there were 53 hours6.134259e-4 days <br />0.0147 hours <br />8.763227e-5 weeks <br />2.01665e-5 months <br /> of radiography completed using the 8" neutron beam port and 212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> of counting experiments using the two one-half inch neutron beams of the southeast neutron beam port facility.

l Student Laboratory Experiments l - Reactor Operator Training l

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6

5. Snecial Facilities The following facilities are operated in connection with the UVAR:

• Two neutron beam ports, of eight-inch diameter entrance, stepped to 10 inches at the exit, are available. One beam port is currently dedicated to neutron radiography.

• Two access ports (6 ft x 4 ft). One port is currently configured for a high energy photon beam, and the other port for a neutron beam.

• Hydraulic rabbit, for activation analysis, permitting samples with less than 0.69 inch diameter and 6 inch length (not used in 1998).

• Two pneumatic rabbit facilities, for activation analysis and source production, permitting sample diameters of one inch and length not exceeding 2.3 inches. One facility is for irradiation with thermal neutrons and the other is cadmium lined for the use of epithermal neutrons.

• Solid gel irradiator for electrophoresis (not used in 1998).

• Epithermal neutron Mineral Irradiation Facility (MIF).

• Small Animal Irradiation Neutron Tube (SAINT), for irradiating mice in conjunction with Boron Neutron Capture Therapy experiments.

l

• A rotating irradiation facility (RIF) used to equalize neutron fluence during irradiation of a large number of specimens (not used in 1998).

• Epithermal neutron irradiation facilities with heaters for sample temperature control (not used in 1998).

• Cobalt-60 gamma irradiation facility with 2,000 curies, permitting underwater exposures at rates up to 80,000 Rads per hour.

• Depleted uranium subcritical facility (not used in 1998).

• Small hot cell, (10 ft x 6 ft x 12.5 ft high) with remote manipulators, currently housing equipment for X-ray radiography. ,

l

• Machine and electronic shops.

• Several radiochemistry labs with fume hoods, counters and standard lab equipment.

• Low-background counting room with shielded, solid state germanium l and silicon detectors and computerized data acquisition / analysis system.

I .

lI 7

I C. Reactor Staff Organization

1. Operations Staff A NRC approved Reactor Facility organization chart is shown in Figure 3.

Personnel on the reactor staff as of the end of 1998 were: ,

RU. Mulder . . Reactor Director P.E. Benneche . Reactor Supervisor (SRO)

C. A. Bly . . . . . Senior Reactor Operator (SRO)

M.J. Cook . . . . Part-time Student Assistant K.M. Jones . . . . Part-time Student Assistant V.S. Thomas . . Reactor Facility Secretary )

B. Hosticka . Research Scientist (SRO)

(former Reactor employee, currently employed by another UVA department)

2. Health Physics Staff at the Facility D.P. Steva . . . . Reactor Health Physicist D. A. Moody . . . Radiation Safety Technician The Health Physicist is assisted by students employed by the Reactor Facility. Other health physicists and techn:cians are on call through the Office of Environmental Health and Safety.

3. Reactor Safety Committer The Reactor Safety Committee was composed of the following individuals (as of the end of 1998):

W.R. Johnson . . Professor Emeritus, Nuclear Engineering (Chair)

R. A. Rydin . . . Associate Professor, Nuclear Engineering R.U. Mulder . . . Reactor Director & Assoc. Professor, Nuclear Engineering R.G. Piccolo . . . University Radiation Safety Officer D.P Steva . . . . Radiation Safety Specialist, UVA Office of Environmental Health & Safety l

[ r~l Fl El T1 I I I M President, University of Virginia t

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9 II. REACTOR OPERATIONS

._ A. UVAR

1. Core Configurations A typical UVAR core configuration, the one used throughout the first six months of 1998, is shown in Figure 4. The reactor employs three boron-stainless steel safety rods and one stainless steel regulating rod for fine power control. The fuel elements are of the Materials Test Reactor (MTR) flat plate-type elements, utilizing U3Si2 . The fuel is approximately 19.7% enriched in the U-235 isotope. The fully loaded elements have 22 fuel plates per element, with an initial loading of approximately 275 grams of U-235 per element. The control rod elements and partial fuel elements have 11 fueled plates with an initial loading of approximately 137 grams U-235 per element. A plan view of these elements is shown in Figure 5.

The reactor fuel was permanently unloaded off of the grid plate and placed in storage racks at the bc*om of the pool in September of 1998.

2. Standard Ooerating Procedures (SOP)

.I During the year, changes were made to Chapter 10, Radiation Protection, of the SOP's. The Reactor Safety Committee reviewed and approved these changes.

3. Surveillance Reauirements The following surveillance items were completed during the year as required by Section 4.0 of the Technical Specifications:

a. Rod Drop Tests and Visual Insoection I Rod drop times are measured at least semi-annually, or whenever rods are moved or maintenance is performed.

Magnet release time should be less than 50 milliseconds and free drop time less than 700 milliseconds.

Rods are visually inspected at least annually for physical integrity.

Rod drop times were measured on the UVAR and are shown in Table 3.

l I

l 10 UNIVERSITY OF VIRGINIA REACTOR CORE LOADING DIAGRAM l l

CORE LOADING 95-3 SHUTDOWN MARGIN - 3.164 $ (Base)

DATE 1-28-98 EXCESS REACTMlY +3.254 $ (Base)

U-235 4449a. 9-30-97 EXPERIMENT WORTH 0.84 $

F- Normal Fuel Element P- Grid Plate Plug PF- Partial Fuel Element THERMAL RABBIT- Thermal Pneumatic Rabbit F-CR - Controf Rod Fuel Element EPI-RABBIT - Epithermal Pneumatic Rabbit G- Graphite Element SOURCE G - Graphite Source Element .

F-REG -Control Rod Fuel Element with Regulating Rod l Rod Worths #1 - 3.651$ #2 - 3.563$ #3 - 2.855$ Rea - 0.455$

MINERAL IRRADIATION FACILITY (MIF)

MIF LEAD SHIELD F F F-REG F F G VS015 VS009 VC001 VS013 VS004 P P 11 12 13 14 ,

1,5 16 17 18 F F CR1 PF F F G VS006 VC002 VP001 VS007 VS008 P P 21 22 23 24 25 26 27 20 F F F F-CR2 F G VS001 VS010 VS002 VC003 VS012 P P 31 32 33 34 35 36 37 38 F F F CR3 F F G VS014 VS003 VC004 VS005 VS011 P P 41 42 43 44 45 46 47 48 SOURCE G G G G G G P P 51 52 53 54 55 56 57 58 EPI-G G G RABBIT G G G G 61 62 63 64 65 66 67 68 THERMAL G G RABBIT G G P G G 71 72 73 74 75 76 77 78 G G G G G G G G

!l si 82 83 84 e5 86 87 88

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12 TABLE 3 Measured Control Rod Drop Times on UVAR Rod Magnet Rod Magnet Free Total Number Current Position Release Drop Drop (m-amps) (inches) Time Time Time (msec) (msec) (msec) 5-11-98 Semi-annual Surveillance 1 170 26 21.8 480.8 502.6 2 170 26 42.2 465.0 507.2 3 70 26 32.0 470.2 502.2 The rod drop times continue to be within the limits required by the Technical Specifications (700 msec free drop and 50 msee magnet release).

The UVAR control rods were visually inspected on 5-11-98. The following is abstracted from the surveillance files:

Rod #1 - Inspected rod under water. No cracks or significant rub marks were observed. A 0.90 inch gauge easily passed over the rod.

Rod #2 - Inspected rod under water. No cracks or significant rub marks were observed. Surface roughness noted on almost entire surface.

Reddish-brown discoloration near top. A 0.95 inch gauge passes easily.

Rod #3 - Inspected rod under water. No cracks or significant rub marks were observed. Same reddish-brown discoloration noted. A 0.95 inch gauge passes easily.

All of the rods appear essentially the same as in previous inspections.

b. Tests and Calibrations Data on these tests and calibrations are on file at the Facility.

1) Monthly Operational checks of the ventilation duct, personnel door, truck door and emergency exit cover were performed as required.

j 2) Semi-Annually A visual inspection of gaskets on personnel door, ventilation duct and truck door was completed.

Calioration checks of source range channel, linear power channel, core j gamma monitor, bridge radiation monitor, reactor face monitor, duct I

i 13 argon monitor, constant air monitor, pool level monitors, pool temperature monitor, core differential temperature monitor, and primary flow instrument were done.

3) Annually I

The emergency cooling system was tested on December 22,1998. The i results are as follows: l I

i=

S.E. Tank S.W. Tank (gal / min) (gal / min) i minimum required flow 11.0 11.5 l 12-22-98 actual flow 12.2 12.8 l last five year range 11.9-12.5 11.9-12.8 No pattern was observed in the variation of the test results for the last five years.

4) Daily Checklist The daily checklist, which is completed when the reactor is to be operated, provides for checks on all the significant automatic shutdown systems associated with the reactor.

5) Reactor Pool water Ouality The Technical Specifications require that the pH and conductivity of the pool water be measured at least once every two weeks. These measurements were actually made on a daily basis when the reactor was operating and at least once each week. These measurements have indicated that the water quality was maintained well within the Technical Specification limits of pH between 5.0 and 7.5 with conductivity < 5 micromhos/cm.

6) Core Configuration Changes The UVAR core configuration was not modified during 1998. The core was permanently unloaded on September 3,1998.

7) Communication Checks The security system and emergency communications with the University Police and Fire Department were checked on a weekly basis throughout the year. These checks confirmed the availability of systems and communication equipment.

I

14

4. Maintenance The maintenance performed on the UVAR systems during the calendar year 1998 is shown in Table 4. No significant trends were noted in the maintenance.

I TABLE 4 Reactor System Maintenance Performed in 1998 Date System Problem Corrective Action 01-09-98 Regulating rod rod will not drive in either added BNC connector to replace (by mistake listed in 1997) direction RCA type connector 01-13-98 Reactor console power key switch will not turn off the replaced key switch reactor console electrical power 01-13-98 Control rod #2 position display of rod position not replaced IC QA4 indication working, giving meaningless indication 03-03-98 Linear / N-16 recorder chart recorder paper not moving paper drive motor disassembled, cleaned and lubricated 03-06-98 Evacuation alarm system not loud enough in UVAR added additional horn above reactor room UVAR control room 04-22-98 Regulating rod position display unstable when reg. rod at replaced IC's QA4 and QA2 indication approximately 7 incho 05-05-98 Manual reactor scram on is very sensitive to touch cleaned contacts on switch ground floor 05-11-98 Security system polic: :alled, system indicates phone line problem, eventually

" trouble" on their alarm box cleared up with no action 05-26-98 Constant air monitor not responding at all replaced Ql, then replaced entire circuit board with one from an RM-14 detector I

lI l 15 l

l 5. Unplanned Shutdowns The 8 unplanned shutdowns which occurred on the UVAR during the calendar year 1998 are shown in Table 5. I TABLE 5 l Unplanned Reactor Shutdowns in 1998

! Date # Shutdown Mechanism 01-08-98 1 Scram - Momentary building power failure.

01-09-98 i Scram - Momentary building power failure.

01-29-98 1 Scram - Intermediate range period; due to movement of neutron source.

03 16-98 1 Scram - Momentary building power failure.

05-04-98 i Scram - Momentary building power failure.

06-09-98 i Scram - Momentary building power failure.

06-16-98 1 Scram - Momentary building power failure.

06-23-98 1 Scram - Momentary building power failure.

l None of the unplanned shutdowns had " reactor safety significance".

6. Pool Water Make-un During the year, the daily makeup of water to the reactor pool averaged 62 gallons.

Much of this is due to evaporation while operating the UVAR at 2 Mw.

7. Fuel Shinments

a. Fresh Fuel

- No fresh fuel was received at the facility during 1998.

b. Spent Fuel in November 1998, 'ie four control elements used in the UVAR were shipped to the Savannah River Laboratory in South Carolina. An amendment to the b Certificate of Compliance for the shipping cask is being f'malized and once this is accomplished the remaining spent fuel will be shipped to Savannah River (anticipated to be in the spring of 1999).

8. Personnel Training and Instruction i

a. Reactor Facility Staff

{ At the end of 1998 the reactor staff consisted of two individuals possessing senior reactor operator (SRO) licenses. One of these two individuals was laid off by the University at the end of January 1999; his position was considered unnecessary with the reactor in the current shutdown mode. One other

16 University employee, who used to be employed at the Reactor, also maintained (and is maintaining) an SRO license. All licensed operators participated in the Facility's operator requalificatica program, which was carried out during the year. The program consists of periodic lectures, participation in the daily operation of the Facility, performing checklists and start-ups of the reactor and a biennial written examination.

J b. Summer Course for School Teachers During the month of June 1998,34 high school and middle school teachers from within the state of Virginia attended a one week special course at the i Reactor Facility entitled: " Science of Nuclear Energy and Radiation". The course consisted of formal lectures, laboratory experiments with the UVAR reactor in (he areas of sub-crPical multiplication, basic radiation ;oun;ing, and gamma-ray analysis. During the week the teachers also visited the North

'I Anna Nuclear Power Station.

9. Reactor Tours During the calendar year 1998, the staff guided 37 groups on tours along with a number of individual tours of the Facility, for a total of 602 visitors.

B. . CAVALIER Reactor I 1. Reactor Shut Down The reactor was completely and permanently unloaded during the first week of March,1988. A decommissioning order was issued by the NRC on Feb;uary 3, 1992. The decommissioning should De completed in the near future.

i III. REGULATORY COMPLIANCE A. Reactor Safety Committee g 1. Meetings I

Di :ng 1998, the Reactor Safety Committee met two times, on the following dates:

l February 23, ly98 June 26,1998 The Te&tical Specifications require the committee to meet at least twice each year, i

2. Audits b During the year sub-committees 'the Reactor Safety Committee performed two audits of the Facility. One audit ,. #ne reac:or operations records is required every year and was complet 1 on June 22,1998. The second audit was completed on

17 i

April 20,1998 of the quality assurance program, requalification program and training. An audit in these areas is done every two years.

3. Aporovals The Small Animal Irradiation Neutron Tube was approved for routine use (2/23).

A change to the organization chart in the Technical Specifications, with the corresponding changes to the text, was approved for submission to the NRC (2/23) and this amendment (#23) was issued by the NRC on June 15,1998. A similar I amendment was requested for the CAVALIER Technical Specifications and this amendment (#8) was issued by the NRC on July 7,1998.

l l

A near complete revision of the UVAR Technical Specifications, which will l eventually constitute a possession only amendment to the reactor license, was approved by mail ballot in September 1998. As of March 1999, the Reactor Staff j and the NRC are still going through iterations of providing additional information i about these changes.

A revised Reactor Operator Requalification Program was approved for submission to the NRC in July. This was approved by the NRC on October 27,1998.

During the year, the Reactor Safety Committee approved several changes to Chapter 10, Radiation Protection, of the UVAR Standard Operating Procedures, p 4. 10 CFR 50.59 Reviews t

No 10CFR50.59 analyses were performed during 1998.

B. Inspections During 1998 the Facility had two NRC compliance inspections, at the following times and in the areas of:

January 26-28,1998 #50-62/98-201 Radiation protection & safety November 16-19, 1998 #50-62/98-202 Comprehensive inspection l

I The January inspection resulted in one minor violation (level IV) concerning the frequency of testing of the building evacuation alarm, as required by the UVAR Emergency Plan. The April 1,1998 response to this violation was accepted by the NRC on May 4,1998.

The November inspection resulted in one minor violation (level IV), with four parts, related to the proper labeling and paperwork related to the shipping of radioactive material and spent fuel. The Reactor Facility response to this violation was accepted by the NRC in January,1999.

l 1

18 C. Licensing Action

1. A new security plan was submitted to the NRC for approval on February 22,1996.

At the request of the NRC, this submittal was withdrawn by a letter dated July 15, 1998.

2. A change to the organization chart in the Technical Specifications, with the corresponding changes to the text, was approved for submission to the NRC (2/23) and this amendment (#23) was issued by the NRC on June 15,1998. A similar amend nent was requested for the CAVALIER Technical Specifications and this amendment (#8) was issued by the NRC on July 7,1998.

3. A revised Reactor Operator Requalification Program was approved for submission to the NRC in July. This was approved by the NRC on October 27,1998.

4. A change to the UVAR Technical Specifications to eliminate the requirement for control rod drop testing and primary flow rate instrument calibration was sent to the NRC on December 3,1998. This amendment (#24) was issued by the NRC on December 21,1998.

D. Emergency Preparedness

1. Three practice evacuations of the Reactor building were conducted during 1998, on l Jan. 30, March 31 and October 23. In each case. all the persons present evacuated the building and gathered at the designated assembly area, as required. In each case, at least the minimum necessary supplies and equipment was carried by the reactor staff to the assembly area.

2. On February 9,1999, the annual emergency drill for the calender year 1998 was initiated at the facility. This drill is normally held in November or December but was completed a little later this year due to planning difficulties and the shutdown of the reactor. This year's scenario involved a staff member of the Environmental I

Health and Safety Office working on a scaffolding beside the outside fuel transfer tank. He "fel!" off the upper level of the scaffolding while placing an initially I unidentified liquid into the tank. He was noticed lying on the ground, next to the tank. The assistance of the rescue squad and the UVA Office of Environmental Health and Safety was sought (the rescue squad was not actually asked to respond, g their participation was postulated). The patient was treated by the reactcr staff until E the rescue squad " arrived". The nature of the " contamination", both radioiogical and chemical, was assessed by the responders.

The actions tested in this drill were: sttff notification, staff initial actions to identify the nature of the accident, contamination control, first aid, required off-site notifications, appropriate use the Emergency Plan Implementing Procedures and the use of assistance by off-site agencies (in this case, the UVA Office of Environmental Health and Safety).

1 l 19 IV. HEALTH PHYSICSI l, A. Personnel Dosimetry

)

1. Visitor Excosure Data For 1998 During 1998, there were 1,397 visitors who toured or assisted wi work at the Reactor Facility. Of these visitors,602 were visitors in tour groups. The highest dose received in any one visit was 0.1 mrem. Most visitors received no measurable dose.

2. Reactor Facility Personnel Dosimetrv Data For 1998

a. Monthly Whole Body Badge Data Radiation doses received by Reactor Facility personnel were measured using Landauer personnel dosimeters. Film badge dosimeters measured expo. cure from beta, X, gamma and thermal neutron radiation. All personnel working with the neutron beamports at the Facility were issued neutron dosimeters in addition to their whole body film badges. The neutron dosimeters used were Landauer Neutrak ER badges that allowed detection of an extended range of neutron energies. All dosimeters were changed out on a monthly basis.

The dose distribution for personnel badged at the Reactor Facility during the period January 1,1998 through December 31,1998 is shown in Table 6.

TABLE 6 1998 Personnel Radiation Doses Received at Reactor Facility Measured Accumulated Number ofIndividuals in Deep Dose Equivalent * (mrem) Dose Range Less than 10 (M) 53 10 - 20 7 21 -30 1 31 - 40 0 41-50 0 51 - 100 0 101 - 150 1 151 -500 0 Greater than 500 0 Number of badged personnel: 62 persons Collective dose for this group: 0.260 rem

• Deep dose equivalent (DDE) as measured by "whole body" film badge dosimeters. These dosimeters have a detection minimum of 10 mrem for gamma, X-rays and thermal neutrons and 40 mrem for energetic beta r particles.

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j The individual who received the highest annual deep dose equivalent l l (140 mrem), was a Reactor Facility staff member routinely involved j l in unloading the mineral irradiation facility and preparing Iridium-l 192 for shipment. During 1998, no doses exceeded the UVA ALARA lavestigational Level 1 of 125 mrem per quarter.

b. Neutron Exnosures

'lnitteen Facility personnel were issued Neutrak ER neutron badges in 1998.

The neutron dose distribution for this group is shown in Table 7.

TABLE 7 1998 Personnel Neutron Doses at the Reactor Facility Measured Accumulated Deep Number of Individuals in Dose Range Dose Equivalent (mrem)

Less than 20 (M) 9 20-40 2 Greater than 40 0 NOTE: These dosimeters have a minimum reporting dose of 20 mrem.

c. Extremity Exnosures During 1998,12 Facility personnel were issued TLD ring badges in addition to their whole body badges. The following is a summary of the extremity doses received by Reactor Facility personnel who wore ring badges during the period January 1,1998 through December 31,1998.

TABLE 8

1998 Personnel Extremity Doses at the Reactor Facility Measured Accumulated Extremity Number of Individuals in Dose Range Dose (mrem)

Less than 30 5 30 - 500 9 501 - 1,250 1 1251 - 5,000 0 Greater than 5,000 0 NOTE: These dosimeters have a minimum reporting dose of 30 mrem ict A and gamma-rays and 40 mrem for energetic beta particles.

t l The individual who received the highest extremity dose (630 mrem), was a Reactor Facility staff member routinely involved in unloading the mineral irradiation facility and preparing Iridium-192 for shipment.

! During 1998 no facility personnel doses (extremity) exceeded the UVA ALARA Investigational Level 1 of 1,250 mrem per quarter.

i 21

d. Direct-reading Dosimeter Exnosures Direct-reading dosimeters (in addition to whole body film badges) are worn by UVAR personnel when they are handling irradiated material that has a calculated or measured exposure rate of greater than 100 mR per hour, ,

measured at one foot from the source. If the exposure totals more than 5 mR l in one day, the exposure is recorded in an exposure log kept in the control room. This information is helpful in assessing the amount of exposure received during specific operations. The total of all exposures recorded in the log book during 1998 was 6.4 mR. The highest individual exposure was 6.4 mR. This exposure was received by a reactor facility staff member handling I B.

irradiated material.

Effluents Released During 1998

1. Airborne Efflitents Argon-41 gaseous release concentrations are calculated using a methodology described in a June 1977 memorandum entitled: " Memo to Senior Operators -

Argon 41 production in UVAR." The Argon-41 activity was calculated from a I known amount of activity released into the reactor room during a leak rate test of the room and readings obtained on the room argon monitor. These readings were then correlated to the normal readings on the argon monitor during 2 MW operation. Using this method, and the known amount of time the reactor was at power during 1998 (685.55 MW-hours), the calculated maximum activity of Ar-41 L released was 0.99 Curies.

2. Liould Effluents Liquid radioactive waste generated at the UVAR is disposed of by one of two means. Liquid waste generated in the student laboratories is poured into approved containers that are collected and disposed of by the Environmental Health and Safety Office. Other liquid wastes generated by the UVAR operation are released to the sanitary sewer in accordance with 10 CFR 20 release requirements.

Regeneration of the UVAR demineralizer system is the major source of radioactivity in liquid released from the Facility. Liquid waste from regeneration is

~

collected in three 2,250 gallon tanks on the ground floor of the Facility. The liquid

' waste collected in these tanks is released to the sanitary sewer in accordance with 10 CFR 20 requirements.

In unusual situations, (e.g. draining of the reactor pool, pool leaks, sink drain disposal), an onsite pond may receive radioactive liquid discharges from the

{ facility. The major sources of water in the pond are surface runoff and a creek that flows into it from the west end. Water is periodically released from the pond in a controlled manner via a spillway. A small amount of pond water routinely leaks through the pond spillway to the release standpipe at an average rate of 1.0 gallons per minute. As this is considered release of pond water, the volume and activity released via this pathway was included in the 1998 liquid release totals.

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22 Durine,1998 there were 33 releases of pond water anxi 3 releases to the sanitary sevn (see Table 9). Prior to, and during all liquid releases, water samples are 0.dected and analyzed for radioactivity content. The average concentration of radioactive material (as measured by gross beta particle activity analysis) released in effluent from the UVAR pond was 0.5 x 10~' pCi/ml. This concentration was 17% of the UVAR administrative release limit and was less than the average concentration of radioactive material measured in the water upstream of the pond (0.6 x 10~' pCi/ml). The average tritium concentration in effluent released from the pond was 6.0 x 10-' Ci/ml. This concentration was 0.6% of the applicable Effluent Concentration (EC) limit (1.0 x 10'8 pCi/ml). The total volume of water released off-site, from the pond, in 1998 was 59,000,000 liters (15,500,000 gallons).The total activity (excluding tritium activity) in this volume was 327 Ci.

This activity was primarily from naturally occurring radionuclides contributed to the pond from the runoff in the feeder creek mentioned above. The total tritium activity released in pond water was 65,800 pCi.

The total volume of waste water released to the sanitary sewer was 20,000 litas.

The total tritium activity released to the sanitary sewer was 4,946 Cl. The total of all other radionuclides released to the sewer was 70 pCi. All radionuclides releascd to the sewer were in concentrations that were less than 1.0% of their individual EC limits.

3. Solid Waste Shinments There were no solid waste shipments from the reactor facility in 1998.

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23 TABLE 9 Pond Release Sample Results

• Avg. Gross Beta

• Avg. Gross Beta (exclud ritium) (exclud g tium)

(x10* pCi/ml i2 s.d.) (x10* uCi/ml 2s.d.)

1 0.4 i 0.1 18 0.6 i 0.2 2 0.3 i 0.03 19 0.6 i 0.4 3 0.4 i 0.1 20 0.3 i 0.1 4 0.8 0.2 21 0.7 1 0.2 5 0.5 i 0.1 22 0.6 i 0.1 6 0.6 0.2 23 0.6 i 0.1 7 0.5 i 0.04 24 0.5 i 0. I 8 0.3 i 0.2 25 0.2 i 0.04

~

9 0.3 i 0.2 26 0.6 0.2

~

10 0.6 i 0.3 27 0.4 i 0.3 11 0.5 i 0.1 28 0.6 1 0.2 12 0.5 i 0.5 29 0.4 i 0.1 o

13 0.5 i 0.3 30 0.6 i 0.3

~

14 0.9 i 0.5 31 0.5 i 0.2

~

15 0.2 i 0.2 32 0.2 i 0.2 16 0.6 i 0.1 33 0.811.1 17 0.7 0.2 E

• Three samples are collected during the release. Number reported is the l

E average (or mean) of the 3 samples and i 2 s.d. of this mean.

A priori LLD: 0.3 x 10* pCi/ml

' TABLE 9a 1998 Sewer Release Data Nuclide Release #1 Release #2 Release #3

% of Release  % of Release  % of Release Limit

• Limit Limit H-3 0.05 0.2 0.13 Mn-54 0.003 0.009 0.02 Co-60 0.07 0.1 0.14 Cs-137 0.09 0.04 0.04 Cs-134 0.01 0.02 ND l Cr-51 ND 0.0003 ND Zn-65 0.01 0.01 0.02 Sb-124 0.004 0.2 0.08 Sb-125 0.001 0.004 0.004 E ND - Not detected l

• Release Limit - 10CFR20 Appendix B Table 3 i

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C. Environmental Surveillance

1. Water Samnling I Environmental water samples were collected on a monthly basis from the locations indicated in Table 10. Gross beta particle activity analysis was performed on all water samples collected. The results of the analyses are provided in Table 10. The average gross beta particle activity measured at each location was less than the UVAR Administrative Effluent Concentration Release Limit of 3 x 10-8 pCi/ml.

l TABLE 10 Environmental Water Sampling Results Gross Beta Particle Activity ( x 104 Ci/ml i 2 sigma)

Meadow Creek near Barracks Road,1.8 mi northeast (2 samples I

Upstream of on-site Water filtration plant collected short distance pond 0.26 mi. southeast apart on creek, results are averaged)

January 0.2 i 0.2 0.1 i 0.1 0.3 i 0.01 February 0.4 i 0.1 0.4 1 0.1 0.5 i 0.1 March 0.4 1 0.2 0.3 0.1 0.8 i 0.1 April 0.4 i 0.2 0.3 i 0.2 0.3 i 0.1 May 0.5 0.2 0.01 i 0.1 0.4 i 0.1 0.8 i 0.2 0.3 i 0.1 0.6 i 0.3 I

June July 1.2i 0.2 0.1 0.1 0.9 i 0.2 August 0.5 i 0.2 0.2 i 0.1 0.5 i 0.2 September 1.0 i 0.2 0.2 i 0.1 0.4 i 0.3 October 1.0 i 0.2 0.2 1 0.1 0.6 i 0.2 November 0.4 i 0.2 < 0.3 0.2 i 0.3 December 0.4 0.2 0.2 i 0.2 0.7 i 0.3 Avgi2 s.d. 0.6 0.3 0.2 i 0.1 0.5 i 0.2 A priori LLD: 0.3 x 10*uCi/ml

2. Air Samnling Environmental air samples were collected on a monthly basis at the following locations:

A-1 Roof of reactor building I A-2 Indicator - approximately 0.13 mi. E of UVAR A-3 Control - approximately 3.1 mi. NW of UVAR Fixed sampling locations are utilized to collect air samples at locations A-2 and A-3. Sampling time for these off-site samples is approximately 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. Air

25 samples were collected at location A-1 using a portable air sampler that was run for approximately two hours. All air samples collected at these locations were particulate air samples and were analyzed for gross beta particle activity. Results are provided in Table 11. The airborne radioactivity detected was primarily due to naturally occurring radon and thoron daughters. The average activity measured at each location was less than the Effluent Concentration Limit of 1 x 10~" uCi/ml.

TABLE 11 Environmental Air Sampling Resvits Gross Beta Particle Activity in Air Particulates ( x 10~" pCi/ml t 2 sigma)

Roof of UVAR 0.13 miles east 3.1 miles northwest Facility of UVAR Facility of UVAR Facility January 2.7 i 0.6 0.4 i 0.04 0.5 i 0.03 February 3.7 i 0.6 0.6 i 0.03 1.6 i 0.1 March 2.7 i 0.5 0.5 + 0.04 0.6 i 0.04 April 3.9 i 0.6 1.010.04 1.2 i 0.0 May 3.3 i 0.6 0.8 i 0.04 1.0 0.04 June 4.6 0.7 1.5 0.1 2.5 i 0.1 July 6.4 i 0.6 1.8 i 0.1 1.9 i 0.1 August 5.5i 0.8 No Data

• 2.210.1 September 8.4 i 1.2 8.6 + 0.2' 1.9 0.1 October 5.2 0.8 7.8 i 1.0' 1.010.04 November 8.3 i 0.6 9.3 i 0.9' 2.6 0.1 December 6.9 0.4 4.8 0.4' 1.2 i 0.1 Avg. 2 s.d 5.1 i 2.0 3.4 i 3.6 1.5 i 0.7

• Sampler malfunction a Sampler out of service, used reactor room sampler, shorter sampling time (lower volume)

Efiluent Concentration (EC) Limit: 1.0 x 10'" Ci Roof sampler a priori LLD: 2.8 x 10~" Ci/ml Indicator and Control Environmental samplers apriori LLD: 6.2 x 10~" Ci/ml

! 3. Outside Area TLD Network TLD's are mounted at B fixed field sites in the vicinity cf the UVAR. All of the sites are outside the UVAR facility but within the area surrounding the facility that is bounded by the exclusion fence. The dosimeters are changed out and read on a quarterly basis. In 1998, additional Aluminum Oxide (Al 2O3) dosimeters were l placed alongside the TLD dosimeters at a number of sites. Table 12 shows the i

l 26 doses recorded by these dosimeters. The doses measured by the Al2 O3 dosimeters are shown in parentheses beside the dose ' measured by the TLD. There was fairly good agreement between the 2 dosimeters except for the fourth quarter. This discrepancy is most likely due to the fact that the control TLD dosimeter for this quarter was not shipped and analyzed with the rest of the badges. This may have introduced some uncertainty into the accuracy of the measurements for this quarter.

The annual total dose measured at each location was less than the annual dose limit of 100 mrem.

TABLE 12 1998 Environmental Surveillance - Outside Area TLD Network Deep Dose Equivalent (mrem) For Periods Shown Below Location 1" 2nd 3rd 4th Annual Annual Quarter Quarter Quarter Quarter Total Net

• 280 M M (0.7) M (-2.2) 20 (5.8) 20 (4.3) 20 281 M 10 (8.5) M (4.9) 20 (8.1) 30 (21.5) 30 282 M 20 (14.7) 10 (-14.6) 30 (6.8) 60 (6.9) 60 283 M M M (2.6) 20 (-1.0) 20 (-1.8) 20

(-3.4)_

284 20 M M 30 50 50 285 hi M hi 20 20 20 286 M M (-7.5) M (-3.8) 10 (-5.2) 10 (-16.5) 10 287 hi hi M 10 10 10 Control M M M M M Control Control M M M M M Contrei M = min. detection limits: 10 mrem for gamma and x-rays,40 mrem for energetic betas.

• Annual Net = Annual Total - Control Annual Total D. UVAR Facility Health Physics Surveys

1. Radiation and Contamination Surveys Daily, weekly and monthly surveys were performed throughout the Facility to monitor radiation and contamination levels. All required area radiation and contamination surveys were performed during 1998. Subsequent to permanent shutdown of the reactor in July, da"y surveys of the reactor room were

' discontinued. The survey frequency for this area was changed to weekly.

i The levels of contamination detected in the Facility during 1998 were generally i

very low (typically less than 50 dpm/100 cm2 ). In keeping with the ALARA policy, most areas are decontaminated if found to have greater than 50 dpm/100 cm2. No increase in background or systems related radiation levels was detected by the routine health physics surveys 1

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2. Airborne Radioactivity Airborne particulate samples are collected in the reactor room as pan of the weekly survey of the Reactor Facility. The average concentration of radioactive material detected in reactor room air (as measured by gross beta particle activity analysis of the particulate samples) was 0.35 x 10~" Ci/ml. The airborne radioactivity detected was primarily due to radon and thoron daughters. None of the measured concentrations exceeded the applicable Derived Air Concentration (DAC) of 3.0 x 10 " Ci/ml.

E. Ouality Assurance The UVAR Facility participates in the U.S. Environmental Protection Agency (EPA)

Laboratory Intercomparison Studies Program as part of its quality control program for I radiation measurement of air and water samples. The UVAR Facility participates in the j following studies: l Gamma In Water on a triennial basis Gross Alpha, Gross Beta in Water on a triennial basis j Tritium in Water on a semiannual basis Three independent determinations for each radionuclide included in a study are made and analysis results are reported to the EPA. A tabulation of all results reported by all participating laboratories is generated by the EPA. This tabulation report contains analytical precision values that are used as a basis for judging a laboratory's performance. Table 13 contains the results of the UVAR's performance in the above mentioned studies.

The normalized deviation of the mean from the known value is calculated from the deviation of the mean from the known value and the standard error of the mean values.

The deviation of the mean from the known value is calculated by subtracting the known value from the average of the laboratory's three results. The standard error of the mean is calculated by dividing the expected precision by the square root of 3 (the number of results). The normalized deviation of the mean from the known value is calculated by dividing the deviation of the mean from the known value by the standard error of the mean.

All intercomparison results provided by UVA indicated very good analytical process precision.

28 TABLE 13 l l

Results of I!PA Radioactivity Measurement Laboratory Inter-Comparison Program l N

ig Date Study- Known Value UVAR reported average value Nonnalized pCi/l Denation*

pCill 1-30-98 3.9 9.3 1.87 l 7-24-98 Gross al in H 2O 12.8 19.2 2.22 l 11-13 98 a 3-13-98 H-3 in water 2,155 2,267 0.56 8-07-98 17,996 18,797 0.77  ;

6-05-98 Gamma in water Co-60 12.0 12.7 0.23 l Zn-65 104.0 106.7 0.46 i Cs-134 31.0 26.3 -1.62 Cs-137 35.0 35.0 0.00 Ba-133 40.0 38.7 -0.46 11-07-98 Gamma in water Co-60 o Zn-65 a NRP Cs-134 a Cs-137 a Ba-133 a NRP - No results reported by UVAR Facility a - EPA reported values not received at time of this report

• If this value is between 2.00 and 3.00 the analytical process precision is in the warning zone: if it exceeds 3.00 it is outside of the control limits specified by the EPA.

G. IJnusual Occurances In September 1998, a pump connection on the sewer release tank failed, allowing water to spray nearby equipment and floors with slightly contaminated water. Access to the area was controlled and the area decontaminated. Follow-up surveys showed no residual contamination above background.

H. Summary During 1998, no Stab or Federal limit for exposure to personnel or the general public l was exceeded.

1 1

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29 V. RESEARCH, EDUCATION AND SERVICE ACTIVITIES l

A. Irradiation and Other Research Facilities Available I An overall description of the experimental facilities available at the UVAR is listed in section I.B.5. During 1998, one relatively new facility vas approved for routine use, to neutron irradiate mice to study the efficacy of Boron Neutron Capture Therapy for the treatment of certain cancers.

No substantial changes were made to any existing experimental facilities.

1 B. Research Activities  !

l

1. Staff assistance was provided to a number of small projects utihzmg a '

I cobalt-60 irradiation facility. Several researchers at both UVA, other universities and some high schools provided a number of different kinds of samples to be irmdiated for either sterilization or to attempt to create genetic mutations.

2. Eagle Picher, a manufacturer of commercial boron products had the Reactor Facility (a professor, staff and students were involved) perform neutron radiography and gaging on a large number of aluminum-boron plates as part of a quality assurance program. These plates are designed to be part of a nuclear power plant spent fuel storage containers. This work is continuing at another university reactor.

3. Industrial Quality, Inc., SBIR Phase Il for U.S. Navy. A major two year program to develop a new electronic neutron imaging system was ongoing. This work involved evaluation of numerous thermal and fast neutron scintillators as well as evaluation of a new CCD camera. One professor and one student were involved in this project.

- 4. A nuclear engineering PhD level graduate student conducted a 1.:rge number of experiments using the Small Animal Irrad!.1 tion Neutron Tube (SAINT) as part of his research utilizing Boron Neutron Capture Therapy on cancerous tumors in mice.

C. Service Projects

1. The project involving the color enhancement of various gemstone grade minerals by fast neutron irradiation was pursued by the reactor staff on behalf of several sponsors involved in the commercial gem trade. The principle contractor is attempting to continue this work at another university reactor.

2. The Protechnics International Company and its subsidiary Spectratec Services, which supply various radioactive sources to industry, had the Reactor Facility l irradiate and ship to them about 30 canisters of a ceramic powder spiked with iridium. This material is used by companies performing oil well drilling. The canisters were irradiated (for 25-35 hours) and shipped three at a time. This work is now continuing at another university reactor.

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3. Co-60 sterilization was completed on a large number of micro-pipettes used for manipulation and fertilization of human eggs prior to their implantation in a ,

woman's uterus. This was a continuing project for a local company, Humagen - l Fertility Diagnostics, Inc. that manufactures and distributes these pipettes. This work is continuing at a commercial irradiator.

D. Reactor Sharing Program The Department of Energy for seventeen years funded a program at the University entitled Reactor Sharing. The purpose of this program was to make available the UVAR facilities to faculty and students at universities and other educational institutions which do not have nuclear science facilities. Over the years, hundreds of students and dozens of professors used this arrangement to enhance both their educational and research opportunities. This program has been terminated along with the termination of reactor operations.

The following is a list of both the directly and indirectly funded activities completed in 1998.

School tours:

Seven tours from high schools, middle schools and elementary schools involving 108 students and teachers.

College tours:

Five tours from colleges involving 70 students and instructors.

Special tours in conjunction with U.Va. programs:

Twenty-seven tours involving 320 individuals; including faculty, staff, students and gucsts.

Individual tours:

Individuals, not part of groups, touring the facility in 1998 totaled 104.

Research projects:

No research projects were conducted as part of the Reactor Sharing Program in 1998.

E. Reactor Facility Supr . , aurses sad _ Laboratories

1. Mademic Courses and LaborMr.Iles During June 1998,34 high School and middle school teachers from the state of Virginia attended a one week special course at the Reactor Facility. The title of the course was " Science of Nuclear Energy and Radiation: Environmental issues and Safety." It consisted of lectures by University of Virginia nuclear engineering faculty, laboratory experiments using the reactor and a tour of the North Anna Nuclear Power Station.

31 F. Degrees Granted by U.Va. In Nuclear Engineering l The following number of degrees were awarded during 1998 by the University of Virginia in the discipline of Nuclear Engineering:

4 Masters of Science, Nuclear Engineering . . . . . . . . . . . . 0 l

Masters of Engineering, Nuclear Engineering . . . . . . . . . 2 l

Doctor of Philosophy, Nuclear Engineering . . . . . . . . . . . 2

TOTAL.................................. 4 i

The following PhD and Master theses by students majoring in Nuclear Engineering ,

i were completed during 1998 in part using services or facilities provided at the l U.Va. Reactor Facility.

Neutronics Methods for the Dynamic Analysis of Source Driven Sub-Critical

Multiolvine Systems, PhD thesis in Nuclear Engineering by Thomas D. Burns, Jr.

An Object-Oriented Implementation of the Invariant Imbedding Method in Reactor Physics Calculations, PhD thesis in Nuclear Engineering by Matthew Forsbacka.

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32 l VI. FINANCES A. Exoenditures Expenditures for 1998 were as follows:

State Suoport Locally Generated Monies Salaries + Fringe benefits: $202,618 $25,283 Operations: 66,608 6,270 Subtotals: $269,226 $31,553 TOTAL EXPENDITURES: $300,779 B. Income Income, both the actual amounts received (for work done in 1998 and in previous years) and billed (in 1998) are shown below:

Va. State support in 1998: $269,226 I Local income received in 1998: 61,223 TOTAL INCOME: $330,449 Total billed in 1998: $73,880 I C. State Sucoort / Research and Service Income The University of Virginia is supported by allocations from the State of Virginia and internally generated monies. Of these monies, a portion is allocated for the activities at the Nuclear Reactor Facility. While the reactor was operating, additional funds were generated by services provided to other educational institutions and to industry. These funds covered expenses not covered by the University budgeted monies. Primarily, these " local" funds covered the hiring of necessary additional personnel. During part of 1998 there was one full-time salaried staff member receiving his salary wholly from local ,

funds. Two students were employed part-time in the capacity of health physics l technicians and general laborers using these funds. I i

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