ML20148D799

Reactor Facility Annual Rept 1987

ML20148D799
Person / Time
Site:	University of Virginia
Issue date:	12/31/1987
From:	Farrar J VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:	Alexander Adams NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
NUDOCS 8803240315
Download: ML20148D799 (40)

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i 1987 ANNUAL REPORT UNIVERSITY OF VIRGINIA REACTOR FACILITY Table of Contents I.

INTRODUCTION A. Reactor Facility Reporting Requirements

1) Reporting Period

2) Basis for Reporting B.

Reactor Facility Description

1) 2 MW UVAR Reactor

2) 100 Watt CAVALIER Reactor

3) Past Operating History

4) Summary of 1987 Reactor Utilization 1)

UVAR Reactor

11) CAVALIER Reactor

5) Special Facilities C.

Reactor Staff Organization

1) Operations Staff

2) Health Physics Staff

3) Reactor Safety Committee II. REACTOR OPERATIONS A. UVAR Reactor

1) Core Configurations

2) Standard Operating Procedures

3) Surveillance Requirements

4) Maintenance

5) Unplanned Shutdowns

6) Pool Water Make-up

7) Fuel Shipments i)

Fresh Fuel

11) Spent Fuel

8) Operator Training i)

Reactor Facility Staff

11) Utility Personnel iii) Disadvantaged American Operator Training Program

9) Reactor Tours B. CAVALIER Reactor

1) Core Configuration

2) Surveillance Requirements

3) Maintenance

4) Operator Training

. - ~ -

ii III. REGULATORY COMPLIANCE A.

Reactor Safety Committee

1) Meetings

2) Audits

3) Approvals B.

Changes to Reactor Facility

1) LEU Conversion Plans C.

NRC Inspections D.

Licensing Action IV.

HEALTH PHYSICS A.

Personnel Dosimetry

1) Visitor Expcuure Data

2) Reactor Facility Personnel

3) Dosimetry for Specific Activities B.

Effluent Releases

1) Gaseous Effluents

2) Liquid Effluents

3) Solid Waste

4) Spent Fuel Shipments C. Environmental Monitoring

1) Air Samples

2) Water Samples D. Radiation and Contamination Levels E.

Summary V.

RESEARCH, EDUCATION AND REACTOR SERVICES A. Irradiation and Other Research Facilities Available B.

Research Activities C.

Service Projects D.

Reactor Sharing Program E.

Reactor Facility Supported Courses and Laboratories F. Degrees Granted by the Department of Nuclear Engineering and Engineering Physics

iii VI.

FINANCES A.

Expenditures B.

State Support and Service Income

1 1987 ANNUAL REPORT University of Virginia Reactor Facility I.

INTRODUCTION A.

Reactor Facility Reporting Requirements 1)

Reporting Period This report on Reactor Facility activities during 1987 covers the period January 1, 1987 through December 31, 1987.

2)

Basis for Reporting An annual report of reacter operations is required by the UVAR and CAVALIER Technical Specifications, section 6.6.3. Additionally, it is the desire of the facility management to document and publicize the most important results derived from reactor operations.

B.

Reactor Facility Description The Reactor Facility is located on the grounds of the University of Virginia at Charlottesville, Virginia and is operated by the Department of Nuclear Engineering and Engineering Physics.

The Facility houses the UVAR 2 MW pool type research reactor and CAVALIER 100 watt training reactor.

The Facility also has a 13,000 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, and a fully equipped machine shop and electronic shop.

1) 2 MW UVAR Reactor The UVAR reactor is a light water cooled, moderated and shielded "swimming pool" type reactor that first went into operation at a licensed power level of one megawatt in June 1960, under facility license No. R-66.

In 1971, the authorized power level was increased to two megawatts.

In September of 1982, the operating license for the UVAR was extended for 20 years.

Figure 1 shows a layout of the reactor and the various experimental facilities associated with it.

2 UVAR Experimental Facilities TANGENTIAL BEAM PORT

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SOUTH ACCESS FACILIT Y RESEARCH FACILITIES Two Neutron Beam Ports, one currently utilized Other short or long term irradiation facilities o

for Neutron Radiography with temperature and environmental control Two Access Ports (6'x4'), one currently con-e 8,000 Ci Cobalt 60 Camma Irradiation f acility figured for a High Energy Gamma Photon Beam Hot Cell, with remote manipulators Hydraulic Rabbit, for activation analysis o

Machine Shop, fully equipped (sample size < 0.69' diameter,6" length)

Electronic ! hop, w ell equipped Pneumatic Rabbit, for activation analysis e

Several Radiochemistry labs provided with fume (sample size 1" diameter and < 2.3* leng:h) hoods, counters and laboratory equipment Heated Epithermal Neutron Irradiation Facility, Computerized data acquisitson / analysis system e

for trace element analysis e

Figure 1

3 2) 100 W CAVALIER Reactor The CAVALIER (Cooperatively Assembled Virginia Low Intensity Educational Reactor) first went into operation in October 1974, under facility license R-123, at a licenced power of 100 watts.

The reactor-was built to accommodate reactor operator training and perform experiments for undergraduate laboratory The operating license was renewed in May courses.

1985, for'a period of 20 years.

Figure 2 shows a layout of this reactor and its control room.

3)

Past Operating History i) UVAR Reactor The UVAR reactor operating history is as follows:

Year (s)

MWhours Hours ODerated 1960-1965 1218 1500 1966-1970 2742 3000 1971-1975 1654 1800 1976-19i8 1769 1480 1979 4426 2764 1980 4610 2863 1981 4988 3568 1982 5507 3024 1983 6079 3556 1984 5687 3166 1985 927 718 1986 1330 891 1987 1220 801 During the years 1979 through 1984, the UVAR reactor was operated ~310 hours per week to irradiate metal specimens for radiation damage studies on pressure vessel steels.

Since that time, the reactor staff has been on an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 5 day per week schedule. The intent of the reactor management is to perform various on-going small and diverse irradiation projects, rather than a single large irradiation project. The areas where irradiations have been or are being sought are mineral irradiations, semiconductor transmutation doping, isotope production for industry or medicine, and NAA or ENAA on large numbers of similar samples.

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5

11) CAVALIER Reactor The CAVALIER reactor operating history is as follows:

Years Watt-Hours Hours Operated 1974-1980 2128 758 1981-1985 1278 388 1986 147 37 1987 28 29 The CAVALIER reactor has been used primarily for reactor operator training and undergraduate lab experiments. It has also been useful in the obtention of benchmarks for the computer codes under implantation at the Facility in connection with the low enriched uranium fuel conversion studies for the UVAR reactor.

4) Summary of 1987 Reactor Utilization i) UVAR Reactor During 1987, the UVAR was operated for 801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br /> and a total integrated power of 1220 Megawatt-hours. The following experiments were performed utilizing the UVAR reactor:

1554 NAA samples were run in the pneumatic rabbit system 156 NAA samples were irradiated in the radiation basket 3 samples were irradiated for electrophoresis experiments 2 sets of samples were run in the mineral irradiation facility 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> of reactor operations were dedicated to Neutron Radiography

11) CAVALIER Reactor During 1987, the CAVALIER reactor was operated for 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> and a total integrated power of 28 watt-hours.

The CAVALIER was utilized for operator training involving students within the Department of Nuclear Engineering, trainees from the Virginia Power Co. and a summer course for high school teachers.

6

5) Special Facilities The following facilities are operated in connection with the UVAR:

• Two neutron beam ports, of 8

inch diameter, 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 baam.

• Hydraulic rabbit, for activation analysis, permitting samples with dimensions of less than 0.69 inch diameter and 6 inch length.

Pneumatic rabbit, for activation analysis, permitting sample diameters of 1 inch and length not exceeding 2.3 inches, accessing either a thermal or an epithermal irradiation facility.

• Epithermal neutron irradiation facility, for trace element analysis with reduced thermal neutron flux.

• Solid gel irradiator for elec'crophoresis.

• Epithermal neutron mineral irradiation facility.

• Irradiation facilities with environinental control.

• Cobalt-60 gamma irradiation facility with 13,000 Ci permitting exposures at rates up to 230,000 R/h.

= Small hot cell, with remote manipulators.

• Machine and Electronic Shops, well equipped.

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

• Low-background counting rcom with shielded solid state detectors and computerized data acquisition / analysis system.

7 C.

Reactor Staff Organization

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

Personnel on the reactor staff as of the end of 1987 were:

R.U Mulder - Reactor Director J.P.

Farrar - Reactor Administrator P.E.

Benneche - Reactor Supervisor B. Hosticka - Research Scientist

• D.W. Freeman - Research Scientist

• R.L. Ritenour - Senior Reactor Operator T.L.

Nguyen - Senior Reactor Operator V.G. Hampton - Electronic Shop Supervisor J.S.

Baber - Machine Shop Supervisor V.E. Thomas - Reactor Facility Secretary Paid from reactor services income account

2) Health Physics Staff at the Facility 6

O.T.

Hale - Reactor Health Physicist The Health Physicist is assisted by a Reactor Staff member. Other health physicists and technicians employed by the University are on call with the Office of Environmental Health and Safety.

3) Reactor Safety Committee The Reactor Sa fety Committee is composed of the following individuals:

J.L. Meem - Professor Emeritus - Chairman J.S. Brenizer - Assistant Professor - Nuclear Engr.

B.G.

Copcutt - U.Va. Radiation Safety Officer R.U. Mulder - Director, Reactor Facility A.B. Reynolds - Professor, Nuclear Engineering R.A.

Rydin -

Associate Professor, Nuclear Engr.

K.R.

Lawless - Professor, Material Science g

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9 II.

REACTOR OPERATIONS A.

UVAR Reactor

1) Core Configurations A typical UVAR core configuration 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 MTR plate-type elements, utilizing a U-AL alley.

The fuel is approximately 93% enriched.

Two kinds of fuel elements are used:

older flat plate fuel elements that have 12 fuel plates per element, with a U-235 loading of approximately 165 gm/ element; and newer curved plate elements that have 18 fuel plates per element, with a loading of approximately 195 grams / element.

A plan view of these elements is shown in Figure 5.

2) Standard Operating Procedures Five of the UVAR standard operating procedures were changed during 1987, in the areas of checklists, neutron beamport facilities and radiation control.

The Reactor Safety Committee reviewed and approved these changes.

3) Surveillance Requirements The following surveillance items were completed during the year as required by section 4.0 of the Technical Specifications:

1)

Rod Drop Tests and Visual Inspection a) Technical Specification Requirements 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 l

milliseconds and free drop time less than 700 l

milliseconds.

1 Rods are visually inspected at least annually.

FIGURE 4 10 UVAR REACTOR LOADING CHART Date,__________

Shutdown Margin __________ % celta-k/x U-235________gr.

Excess Reactivity ________ X delta-k/k Secured Exp.

Worth.,____ X delta-k/k F= Fuel Element CR= Control Rod MIF= Mineral Irradiation Facility ER= Epithermal Rabbit Pneumatic fube Ga Graphite P= Plug TR= Thermal Rabbit Pneumatic Tube HR= Hydraulic Rabbit Tube S= Source Element

's RD= Radiation Basket

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12 Rod drop times were measured on the UVAR reaccor as follows:

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January 21, 1987 l

Magnet Rod Magnet Free Total Current Position Release Drop Drop Hod (ma)

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160 26 43 476 519 3

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( With changed core loading on February 11, 1987 )

1 170 26 30 496 526 2

160 26 39 458 497 3

65 26 48 454 502 July 31, 1987 1

165 26 28 489 517 2

160 26 40 455 495 3

65 26 25 450 475 The rod drop times continue to be within the limits I

required by Technical Specifications.

The UVAR control rods were visually inspected on February 9,

1987.

The following is abstracted from the reactor log book and the surveillance files:

l Rod #1 - Inspection of rod was undet approximately 5 feet of water. Rod passed 0.95 inch gage easily. Visual inspection revealed no evidence of cracking.

Rod #2 - Inspection of rod was under approximately 5 feet of water.

No rub marks or evidence of cracking was seen.

Rod passed 0.95 inch gage test easily.

Rod #3 Inspection of rod was under approximately 5 feet of water.

No evidence of cracking was observed, however a previously observed rub mark was seen on the south edge of the rod about halfway down. Rod passed 0.95 inch gage test easily.

Rec. Rod-The rod was inspected under approximately 5 feet of water.

Rod was judged to be in good shape and passed the 1.00 inch gage easily.

13 ii)

Tests and Calibrations a)

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

b)

Semi-Annually Visual inspection of gaskets on personnel door, ventilation duct and truck door was completed.

Calibration checks of source range channel, linear power channel, core gamma monitor, bridge radiation monitor, reactor face monitor, duct argon monitor, constant air monitor, pool level monitors, pool temparature monitors, core differential pool temperature monitors, and primary flow were done.

c)

Annually The emergency cooling system was tested during the month of September 1987.

The results were as follows:

S.E. Tank S.W. Tank (cal / mini (cal / min) minimum required flow 11.0 11.5 9-29-87 actual flow 11.7 12.9 d)

Daily Checklist The daily checklist, which is completed when the reactor is to be operated, provided for checks on all of the automatic shutdown systems associated with the reactor, e)

Technical Specifications 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.

14 f)

Core Configuration Changes The core configuration for the UVAR reactor was changed 4 times during the year, in order to accommodate experiments and to rotate the remaining fuel stored in the pool through the reactor to keep it self-protecting for security purposes, g)

Communication Checks The security system and emergency communications with the University Police were checked on a weekly basis throughout the year.

h)

Alarm System Checks The fire alarm system was checked during the month of December for proper alarm functions, both in the Facility and at the University Police Department.

Data on all of these tests and calibrations are on file at the Reactor Facility.

4.

Maintenance The following maintenance was performed on the UVAR j

reacter system during the calendar year 1987:

l February 10, 1987:

Control Rod Drive #2 - Short circuit in magnet. Corrective action: Replaced coil l

wire to electromagnet and performed rod drop test.

1 February 24, 1987:

Liquid Waste System - Leakage and inaccurate reading on line pressure gauge. Corrective action: Replaced pressure gauge and installed PVC gauge guard isolation section.

May 6, 1987:

Recirculating pump for waste tanks. 15 amp. fuse blown, fuse holder scorched.

Corrective action: Replaced fuse holder and fuse -- works normally.

May 13, 1987:

Hold-up station picoammeter:

Inconsistant readings. Corrective action:

cleaned wafer switches and replaced resistors.

15 i

June 12, 1987:

Erratic period trips on Intermediate Instrument. Corrective action: Removed detector, checked and cleaned all connectors. Problem cleared up.

July 13, 1987:

Source Range - lost indication on period and level meters. Corrective action:

Found amplifier and Oscillator modules out of adjustment. Recalibrated system.

Checks out O.K.

t August 18, 1987:

Duct and room Argon monitors - Readings decreased over time. Corrective action:

l Found and replaced bad detectors. System l

checked out O.K.

l August 24, 1987:

Linear Recorder signal Oscillating from Servo signal causing period fluctuations Corrective action: Moved Servo signal cutout ground from rate feedback circuit to Preamp out circuit thus eliminating the preamp signal from being amplified when Servo is not engaged.

September 18, 1987 Pool Temperature System: Installed

(

interlock in system so that rods cannot be withdrawn with system in calibrate mode.

Linear Recorder: noise in recorder l

interfers with Intermediate Range Period circuit. Corrective action: Ground signal to power amplifier when Servo not engaged. Cleared problem.

October 8, 1987 N-16 Monitor: readings were outside I 5%

tolerance when signal introduced.

Corrective action: Adjusted pot to bring signal within tolerance.

October 16, 1987 Performed annual cleaning of cooling tower and secondary system.

October 19, 1987 Duct Argon Monitor: Signal off scale on low range. Corrective action: Found and rep). aced bad detector. Checks out O.K.

October 26, 1987 S.'condary pump tripped: Found and rcplaced two blown fuses.

November 5, 1987 Source Range Recorder: Makes loud noise when running. Corrective action: Found and replaced bad bearings.

16 December 2, 1987 Power Range #1:

H.V.

power supply reading low. Corrective action: found corrosion on connectors at detector.

replaced connectors. Checks 0.K.

5.

Unplanned Shutdowns The following unplanned shutdowns occurred on the UVAR reactor during the calendar year 1987:

Jan. 16, 1987 Scram due to operator error - forgot to change range switch from 200 KW to 2 MW.

Reset console and started up again.

February 20, 1987 Scram due to noise in Intermediate Period channel. Restarted reactor.

March 18, 1987 Scram due to noise in Intermediate Period channel. Restarted reactor.

April 17, 1987 Rods dropped from signal spike on Intermediate Range channel. Restarted.

May 12, 1987 Scrammed with Rods #2 and #3 at about one inch withdrawn and Rod #1 and Reg Rod fully seated due to period channel noise.

May 27, 1987 Scram due to building power failure.

June 9, 1987 Scram due to buildiing power failure during storm. Restart.

June 12, 1987 4 scrams - noise in period circuit.

t l

June 19, 1987 Rod #3 dropped while adjusting rod l

positions. Restart, l

{

June 24, *987 Scram from experiment temperature monitor noise. Staff member moved wires. Restart.

June 29, 1987 Range switch scram. Operator failed to move switch prior to taking power above l

200 Kw.

August 6, 1987 Scram on Power Range #2 from noise while adjusting the Regulating Rod.

August 11, 1987 Scram in period circuit while adjusting rods.

Scram due to noise in period circuit.

i

17 August 19, 1987 Scram - Loss of building power - Storm.

Scram - Noise in reactor face monitor.

Scram - While adjusting compensating voltage to Intermediate circuit. Reactor was sub-critical at time.

August 21, 1987 Scram - noise in Bridge radiation monitor August 25, 1987 Scram - noise in period circuit.

September 15, 1987 2 scrams - noise in period circuit.

October 13, 1987 Scram - noise in period circuit.

October 19, 1987 Scram - noise in pump-off circuit, reactor was sub-critical at time.

October 20, 1987 Scram - noise in period circuit.

October 29, 1987 Scram - noise in period circuit.

November 18, 1987 2 scrams - noise in period circuit.

Scram - North Beamport interlock - no one was in Blockhouse at the time.

Most of the shutdowns were caused by electronic noise and in no way effected reactor safety but was merely a uusiance to reactor operation.

6)

Pool Water Make-up During the calendar year 1987, make-up water to the UVAR pool averaged approximately 23 gallons per day. Over the past 10 years, the pool water make-up has varied from a minimum of 21 gallons per day to a maximum of 85 gallons per day, depending on reactor operation. The loss of water is mostly due to evaporation from the pool while operating at full power.

7.

Fuel Shipments 1)

Fresh Fuel No fresh fuel was recieved at the facility during 1987, ii)

Spent Fuel During the months of September and October 1987, 36 spent fuel elements were shipped to the Savannah River facility utilizing the G.E.

700 shipping cask.

18 8.

Operator Training i)

Reactor Facility Staff At the end of 1987 the staff had five senior reactor operators and one regular operator. All licensed operators participated in the Facility's operator requalification program, which was carried out during the year. The program consisted of periodic lectures, participation in the daily operation of the facility (including performing check-lists and start-ups of both reactors) and taking an annual written examination administered by the Facility management.

ii) Utility Personnel In July 1987, 12 trainees from the Virginia Power Company attended a training seminar at the Facility.

They received hands-on experience at the console of the CAVALIER reactor and were given lectures in applied health physics, reactor instrumentation and the use of portable monitors.

They participated in laboratory experiments that involved "approach to critical" and prediction of "critical rod heights", activation analysis, half-life determinations and shielding experiments.

iii) Disadvantaged American Reactor Operator Training A second two year operator training program for minority and disadvantaged Americans, sponsored by the Department of Energy, was initiated in early 1987. The following Educational Institutions were awarded sub -

contracts to participate in the program: Oregon State, Ohio State, The University of Missouri at Columbia and The University of New York at Buffalo. The trainees at Missouri and Oregon State dropped out of the program in the fall of 1987. The trainee at Virginia left the program in December, 1987. Buffalo was late getting started in the program but had a trainee on board by December, 1987. Virginia intends to hire another I

trainee to complete the second year of the program. DOE has informed Virginia that no more funds will be made available for the program and it is anticipated that the program will terminate at the end of 1988.

1

19 9.

Reactor Tours During the calendar year 1987, the staff guided 40 groups on tours of the Facility, for a total of 789 visitors.

B.

CAVALIER Reactor 1)

Core Configuration A typical CAVALIER core configuration is shown in Figure 6.

The reactor employs 4 boron-stainless steel control rods.

The control rods are positioned at the four corners of the reactor in order to minimize relative rod worth and excess reactivity.

An "experimental" fuel element (grid position 43) is used to adjust excess reactivity by either inserting or removing individual fuel plates from this element (12 of 18 plates being removable).

The curved fuel elements used in the CAVALIER reactor are identical to those used in the UVAR reactor.

2)

Surveillance Requirements The following tests and calibrations were performed on the CAVALIER system during 1987 as required by section 4 of the Technical Specifications:

1) At intervals not exceeding six months:

Calibration of the source range channels; log N channel; log G channel; linear power channel; pool level monitor; radiation monitoring system; and boron concentration in the ARIS system.

All of these tests and calibrations were within the limits required by the Technical Specifications.

ii) A flow test of the ARIS system was performed as follows:

Time to Emotv Tank Tested November, 1987 31.8 seconds maximum time limit 60 seconds lii) Control Rod Calibrations were performed on 6-30-87.

iv) The daily checklists, which were completed when the reactor was to be operated, provided for checks on all of the required scram systems associated with the reactor.

Data on all of the tests and calibrations are on file at the facility.

20 Figure 6 CAVALIER REACTOR LOADI!iG CHART Loading No.

Date Total Mass gram U-235 F - Nor::al Fuel Element Excess Reactivity P - Partial Fuel Element C - Control Rod Fuel Element E - Removable Plate Fuel Element Shutdown. Margin AL Wire Mesh b[

'/[

m.

u u

II ll

., F

,, E G

/

m,i i mi i F

F

,F,F

/

e s

F F

., F F

.i,,

m,,

m 8

F F

G

,, \\ u

,,, /

4

///4 6

21 3)

Maintenance The following maintenance was performed on the CAVALIER reactor system during the calendar year 1987:

2-3-87 Log N channel: Intermittent failure in 107 position test mode. Corrective action: Replaced Modulator L and performed calibration of channel.

J i

2-27-87 Rod Drive #2 Indicator: Not indicating rod movement.

Corrective action: Found and repaired loose coupling between position potentiometer and rod drive.

6-12-87 Linear Micro-voltmeter: Erratic readings at power.

Corrective action: Found and replaced weak batteries 6-17-87 Linear Micro-voltmeter: Reading slightly negative.

Corrective action: Adjusted OP-Amp in summing and splitting circuit to null position.

6-23-87 Source Range: Not responding properly: Corrective Action: Found and repaired bad connections.

Realigned drawer.

7-29-87 Rod #3 Drive Unit: Coupler at clutch plate loose and clutch plate dragging on magnet. Corrective action: Readjusted clutch plate and tightened coupler. Performed rod drop test. Well within Tech. Spec. requirements.

7-30-87 Rod #4 Driva Unit: Clutch slipping when engaged.

Corrective action: Found and tightened loose coupler next to rod drive pinion. Performed rod drop test.

Well within Tech. Spec. requirements.

8-18-87 Log N Channel: Interlock not functioning properly.

Corrective action: Found and repaired broken wire.

9-03-87 Log N Channel: Failed channel test during daily checklist. Corrective action: Replaced Modu.ator L and realigned and calibrated instrument.

9-04-87 Log G Channel: Failed channel check during daily checklist. Corrective action: Replaced Modulator L and performed calibration on drawer.

9-04-87 Source Range #1: Failed channel check during daily checklist. Corrective action: Replaced Amplifier B and calibrated instrument.

12-15-87 Source Range Channels: No response. Corrective action: Found water had flooded detector wells due to heavy storm over several days. Water had l

22 seeped through wall and entered wells. Dried out detectors and wells and performed source check.

responds o.K.

4)

Operator Training The CAVALIER reactor was utilized for training in undergraduate laboratory experiments that included approach to critical, prediction of critical rod heights and control rod calibration.

The CAVALIER was also used by the Reactor staff to teach new reactor operator trainees.

The CAVALIER reactor was also used in training sessions for a dozen Virginia Power nuclear reactor operator trainees.

During the month of August, 1987 ten High School teachers spent a week at the facility in a special course entitled "Science of Nuclear Energy", "Environmental Issues and Safety". The CAVALIER was utilized to give the teachers hands-on experience and several experiments were performed with the CAVALIER.

l l

l l

23 III. REGULATORY COMPLIANCE A.

Reactor Safety Committee

1) Meetings During 1987, the Reactor Safety Committee met fourteen times, on the following dates:

January 13,1987 July 24,1987 March 3, 1987 August 11,1987 March 12,1987 S6ptember 16,1987 April 21,1987 October 28,1987 May 19,1987 November 4,1987 July 1,1987 November 11,1987 July 15,1987 December 9,1987

2) Audits Sub-committees of the Reactor Safety Committee performed two audits of the Facility's operation during the year, in the areas of: Quality Assurance Program; checklists and start-ups; and the Neutron Radiography Facility.

3) Approvals The Reactor Safety Committee approved five changes l

to the Standard Operating Procedures during 1987 in l

areas of: Radiation Control, Material Irradiation and checklists. The committee also approved procedures for ther shipment of spent fuel.

The Reactor Safety Committee approved three experimental facilities in the area of neutron radiography, mineral irradiation and use of the Cobalt-60 facility.

1 1

l l

24 B.

Changes to the Reactor Facility 1)

LEU Conversion Plans There were no changs:t t' the reactors and their systems during 1987. However,.ne NRC mandated in 1986 a change from High Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel, with the date of conversion to depend on several factors.

The U.Va. Facility will be among the initial group of research reactor facilities to convert to LEU fuel. A study funded by DOE was begun in the spring of 1986 to accomplish this. A management decision has been made to shut down the CAVALIER reactor and a Dismantlement Plan has been submitted to the NRC. The facility is awaiting NRC action on this request. No firm date has been set for the UVAR conversion. It will depend on availability of new LEU fuel and spent fuel shipping arrangements.

C.

NRC Inspections During 1987 Facility underwent three NRC compliance inspections, at the following times and in the areas of:

May 18,1987 Emergency Prepardness May 26,1987 Health Physics July 6,1987 Neutron Radiography On July 2,1987, several students and staff members were inctalling additional shielding and modifications to the blockhouse surrounding the neutron radiography facility when it was discovered that one of the neutron beamports was partially drained, emitting a beam of radiation into the blockhouse. Personnel film badges were mailed to the vendor the same day for immediate processing and the NRC was notified by telephone of the incident. Film badge results were recieved the next day and indicated no over exposure of personnel, however the "RC held an Enforcement Conferenco at the Reactor Facility on August 13,1987 and, as a result of this conference, proposed a

$2500 fine on the facility for a potential overexposure of personnel.The facility has appealed this fine and requested mitigation.

D.

Licensing Action During 19 37, a revised Security Plan, a revised QA/QC Program,a request for license ammendment for use of the Cobalt-60 Facility, and the CAVALIER Dismantlement Plan were submitted to the NRC.

l

25 IV.

HEALTH PHYSICS A.

Personnel Dosimetry Visitor Exposure Data for 1987 1)

During 1987, there were 2711 visitor entrics into the Reactor Exposure received by visitors is measured with self-reading dosimeters. The majority of visitors received one or less Facility.

No visitor received more than five mR of mR of total exposure.

total exposure.

Reactor Facility Personnel Dosimetry Data for 1987 2)

Silver-halide film badges are used to measure deep and shallow Badges beta-gamma doses received by Reactor Facility personnel.

are supplied and processed by a NVLAP - certified vendor.

This Neutron doses are measured using proton - recoil plastics.

badge data becomes the permanent record of dose received forInf whole-body gamma, bata, x-ray and neutron radiation dose data Facility personnel.

(deep dose only) from January 1, 1987 to December 31, 1987.

26 The dose distribution for Reactor Facility personnel is as follows:

Dose Received Occurrences in 1987 (mrem)

Not Measurable 39 10 20 20 22 30 4

40 2

50 3

60 3

70 1

80 0

90 0

100 - 200 8

200 - 300 1

300 - 400 1

400 - 500 1

Total Number 105 of Badged Personnel During 1987, a total of 2.49 man-rem was received by badged reactor facility personnel.

3)

Dosimetry Information for Specific Activities Self-reading dosimeters are worn when handling irradiated material that produces exposure rates greater than 100 mR per hour, measured one foot from the source.

These exposures are recorded in a log book kept in the control room.

This exposure information is helpful in assessing the amount of exposure received during specific operations.

27 The following task-related exposures were obtained from the control room log:

Task Exposure (Man-R)

Waste drum preparation 0.057 Monitor calibrations 0.019 Fuel movement operations 0.005 Fuel shipping 0.027 Mineral irradiation 0.006 operations Health physics 0.183 surveillances/ source leak tests l

Demineralizer room 0.058 eperations B.

Effluents Released During 1987 1)

Gaseous Effluents 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 methodology described in this memorandum assumes: (a) a maximum production rate for Ar-41 (given the present UVAR core loading), (b) immediate evolution of Ar-41 from the pool water into the UVAR confinement atmosphere, (c) no decay and (d) air saturating the UVAR pool water at 680 F.

Based on this method, and using the known amount of time the reactor was at power during 1987, a total release of 1,76 Curies of Ar-41 has been calculated.

2)

Liquid Effluents Liquid radioactive waste is released off-site after having been sampled for gross beta activity and diluted (if necessary).

During 1987 there were forty-two releases of liquid effluent to the environment.

The average concentration per release was 1.88 x 10 -8 yCi/ ml.

The total gross beta activity released was 0.745 Ci.

The total liquid volume released was 37,347,964 liters.

Tritium release activity is calculated by first taking a discharge tank sample and analyzing it for tritium using a liquid scintillation counter.

Release values for tritium are then calculated using a known pond water dilution ratio.

Pond samples are also regularly analyzed for tritium and this activity (if detectable) is included in the total release calculation.

28 3)

Solid Waste Shipments Waste shipments are responsible for significantly reducing background dose rates in many areas of the Facility.

Much of the solid waste collected during 1987 resulted from a major "house-keeping" effort by the Reactor Facility Staff to reduce the Facility's inventory of unusable research material.

In total, 180 cubic of feet of solid waste was shipped for burial at a contractor disposal site.

The total activity shipped was 0.854 Ci.

The shipment consisted mostly of radioactive LSA, with activated metal components and fragments comprising the rest of the volume.

4)

Spent Fuel Shipments During 1987, four shipments of "spent" enriched reactor fuel were shipped to Savannah River Plant for re-processing.

A total of 32,759 Ci of mixed fission products was shipped via commercial carrier.

C.

Environmental Monitoring Program Results 1)

Environmental Air Samples Environmental air samples are taken monthly outside of the Reactor building and within the owner controlled area.

All air sample values measured below the lower limit of detection of the instrument used (4.15 x 10-11 pCi/ ml.).

2)

Environmental Water Samples Four environmental water samples are taken monthly at the following locations:

a.

The University water filtration plant b.

The creek adjacent to the Barracks Road Shopping Center.

This location is downstream of the main University water discharge point; two samples are taken at this point c.

The creek that feeds the Reactor Facility pond, used as a source of dilution water All 1987 concentrations were below instrument LLD values of 2.8 x 10~9 pci/ml.

29 D.

Radiation and Contamination Level Summary Loose surface cor4tamination is expected in only one radioactive material storage area.

The levels of contamination found there are below the procedural definition of "contaminated area" of 1000 dpm/100 cm,

2 Access is controlled to this area. If loose surface contamination is greater than or equal to 50 dpm/100 cm,

2 that area is decontaminated immediately.

Required health physics radiation level surveys were performed during 1987.

There was no overall increase in background or systems-related radiation levels.

E.

Summary Daring 1987 no State or Federal limits for exposure to personnel or the public were exceeded.

30 V.

Research. Education and Service Activities A.

Irradiation and Other Research Facilities Available An overall description of the experimental facilities available at the UVA reactor are listed in section I.B.S.

During 1987, two of these facilities underwent major modifications as outlined below.

Additional effort was made on the design of a Cold Neutron Irradiation Facility for future installation at the UVA Reactor Facility.

1.

The neutron radiography facility was modified by raising the roof of the shielding blockhouse by one course of concrete blocks in order to allow a reasonable amount of head clearance.

On top of this roof was placed a sufficient quantity of graphite, paraffin, cadmium and a boron compound to reduce the neutron levels to below that of a high radiation area.

Changes were also made in the system which moves the water shield in the north neutron beam port.

These changes were designed to reduce the possibility of draining the beam port unintentionally.

A number of additional changes were and are being made to prevent any possibility of the accidental exposure of personnel to high radiation levels.

2.

The cobalt-60 irradiation facility located in the UVAR reactor pool was modified in order to accommodate two special experiments.

Currently, the facility possesses 71 cobalt-60 pins each containing about 125 curies of Co-60 (as of December 1987).

Fifty-four (54) of these were moved to a new facility located on an underwater table hanging from the reactor pool wall.

This facility has space for 42 containers (3 inches in diameter) in gamma ray fields of varying strength.

This will be used over the next few years to irradiate wire insulation and other plastic-like components used in nuclear power plants.

The gamma flux rates and the total fluences will be varied as part of these tests related to nuclear power plant life extension.

Also to be tested in this facility are the glow plugs intended to ignite hydrogen produced during a nuclear plant accident.

The conditions of this test will be at varying levels of temperature, humidity and radiation level.

31 B.

Research Activities 1.

A continuing program of research was pursued on behalf of a major tobacco company.

This work was supervised by Dr. Jack Brenizer and conducted primarily by graduate students with Reactor Facility staff assistance.

The major projects were neutron radiographic examinations of burning cigarettes, neutron activation analysis of various products used in the tobacco industry and the analysis of the distribution of smoke from a smoked cigarette through spiki'ng of tobacco with radioactive isotopes.

2.

Staff assistance was provided for two major projects and several minor projects utilizing the cobalt-60 irradiation facility.

The major projects are on behalf of sponsors related to the nuclear power industry and involve the gamma irradiation of radiation sensitive components from nuclear power plants.

Drs.

Albert Reynolds and W. Reed Johnson are the principle investigators for these projects.

3.

A detailed sampling of both water and soil from a wide area around the Reactor Facility was conducted by a graduate student with staff help.

These samples have been analyzed for both natural and man-made radioisotopes as part of a study to determine the extent of any low level radioisotope contamination around the building.

This work is under the direction of Drs. Tom Williamson and Robert Mulder.

4.

Staff, faculty and students have been and are continuing to be involved in the safety analysis of the low enriched uranium fuel proposed for use in the UVAR Reactor.

This study is being funded by the Department of Energy.

The principsi faculty members involved are Drs. Roger Rydin 7:nd Robert Muld9r.

32 C.

Egrvice Proiects 1.

Iodine determination by epithermal neutron activation analysis (ENAA) was performed on behalf of several sponsors.

The substances analyzed were infant formula, liquid diet supplements, surgical diets, pet foods and various chemical compounds.

2.

Rhodium determinations by neutron activation analysis (NAA) were performed on a number of chemical mixtures for one major chemical manufacturer.

3.

One hundred large plates designed for use as neutron absorbing material in spent nuclear fuel casks were examined by live time neutron radiography in order to look for any manufacturing defects.

This project was a joint effort of staff, students and one faculty member.

4.

A project involving the color enhancement of various gemstone grade minerals by fast neutron irradiation was pursued by the reactor staff on behalf on one commercial sponsor.

5.

Several reactor irradiations on electrophoresis gels were peyformed for a researcher from the National Bureau of Standards.

These were done in a facility specially designed and built by the reactor staff for this purpose.

6.

A class of nuclear power plant operator trainees spent a day at the reactor facility participating in reactor operations and radioisotope laboratories conducted by the reactor staff.

7.

A project was completed for a researcher from an electric utility who was investigating the measurement of the amount of uranium trapped on the outside of the zirconium cladding when nuclear reactor fuel is manufactured.

8.

A ccmmercial vendot of equipment used by the nuclear power industry contracted with the department to have tested a number of solid state neutron monitors.

9.

A number of small gold pellets were irradiated for the Department of Radiological Physics at the University of Virginia Hospital for use in treating inoperable cancerous tumors.

33 i

D.

Reactor Sharing Procram The Department of Energy has for ten years funded a program at the University called Reactor Sharing.

The purpose of this program is to make available the facilities at certain university reactors to the faculty and students at universities and other educational institutiors which do not have such facilities.

Over the years, hundreds of students and dozens of professors have used this arrangement to enhance both their educational and research opportunities.

This past year a number of tours, laboratories and research projects were conducted under this program.

The following is a list of both the directly and indirectly funded activities completed in 1987.

High school tours: 12 tours from 8 schools involving 263 students and teachers.

College tours:

7 tours from five colleges involving 102 students and professors.

College labs:

6 of the above tours involved laboratories which were participated in by 53 of the people.

Research projectu: Three research projects utilizing neutron activation analysis were conducted during the year.

E.

Reactor Facility Suonorted Courses and Laboratories 1.

Academic Courses and Laboratories

(

The following ccursen and laboratories were taught oy professors in the Department of Nuclear Engineering and Engineering Physics during 1987 utilizing in part service: provided by the Reactor Facility.

NE 488 - Nuclear Power Plant Operations NE 381 - Radiation Detection Laboratory f

NE 382 - Nuclear Engineering Laboratory During August 1987, 9 high 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 and laboratory experiments using the reactors.

L

34 T.

Dearees Granted by the Deot. of Nuclear,

_Encineerina and Encireerina Pnysics The following number of degrees were awarded during 1987 by the Department of Nuclear Engineering and Engineering Physics.

Bachelors of Science 11 Masters of Science 12 Masters of Engineering 1

Doctor of Philosophy

_1 TOTAL 27 One of the Master's theses (Epithormal Neutron Activation Analysis by Thanh Nguyen) and one undergraduate thesis (Radium Contamination of Drinking Water by Roger Aschbrenner) directly used reactor services while many other students used the assistance of the reactor staff in the completion of their theses or dissertations.

35 L

VI.

Finances A.

Excenditureg Expenditures for 1987 were as follows:

State Succort Locally Generated Monies Salaries:

$227,176.49

$128,102.04 Operations:

47,790.02 10,055.92 Subtotals:

274,966.51 138,167.96 TOTAL:

$413,124. 7 (state and local)

B.

State _ Support and Research and Service Income The University of Virginia is supported by allocations from the State of Virginia.

Of these monies, a portion is allocated to the Department of Nuclear and Engineering Physics for the operation of the Nuclear Reactor Facility.

This money pays for many of the expenses directly related to the operation of the reactor but additional monies are necessary to provide for the total services that the facility provides to the university community.

These additional monies are in the form of fees received for research and service work support and in 1987 totaled about

$91,000.

This "not business related income" is used 1

primarily to pay *the salaries of some professional staff members at the facility which are not supported by the state.

Typically, these staff members are also part time students which are pursuing either undergraduate or graduate degrees in nuclear engineering while working full time.

This, in effect, is another form in which the Reactor Facility supports science education at the Department of Nuclear Engineering and Engineering Physics.

1

{

l UNIVERSITY OF VIRGINIA DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PIIYSICS r,A 1 NUCLEAR REACTOR FACILITY

(

J SCIIOOL OF ENGINEERING AND APPLIED SCIENCE CHARLOTTESVILLE. VA 22901 r

Telephone: 80-1-921 7136 March 16,1988 U.S. Nuclear Regulatory Commisaion Document Control Desk Washington, D.C.

20555 Att: Mr. Alexander Adams Jr.

Standardization and Non-Power Reactor Projects Re: Docket No. 50-62 Docket No. 50-396

Dear Mr. Adams,

We hereby submit, as required by section 6.6.2 of the Technical

)

Speci fications, our annual report of the operations of the University j5 Virginia Reactor (UVAR), License No. R-66, Docket No. 50 62 and the CAVALIER Reactor, License No. R-123, Docket No. 50-396 during the period January 1,1987 through December 31,1987.

Sincerely, Q.

hW J.Y.Farrar, Administrator U.Va. Reactor Facility cc: USSRC, Region II A02.0

\\

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