ML19256B134

Annual Operating Rept Covering Number of Hours of Operation, Rod Drop Tests,Maint,Sops,Tech Spec Changes,Experiments, Surveillance & Unplanned Shutdowns

ML19256B134
Person / Time
Site:	University of Virginia
Issue date:	01/11/1979
From:	Farrar J VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7901240117
Download: ML19256B134 (13)

Text

,

UNIVERSITY OF VIRGINIA N

SCHOOL OF ENGINEERING AND APPLIED SCIENCE D

CHARLOTTESVILLE. 12908 DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS TELEPHONE:

804 924 7138

.EACrOR r ciun January 11, 1979 Division of Reactor Licensing U.S. Nuclear Regulatory Commission Office of Regulation Washington, D.C.

20545 RE: Docket _No. 50-62, License No. R-66 Docket' No. 50-396, License No. R-123 Gentlemen:

We hereby submit as required by Section 6.7.e of the Technical Specifications our annual report of the operations of the University of Virginia Research Reactor, License No. R-66, Docket No. 50-62 and the CAVALIER reactor, Licet se No.123, Docket No. 50-396 during the period January'1,1978 through December 31, 1978.

A.

UVAR Reactor The UVAR reactor was operated during the year as follows:

Hours Operated Mlf Hours First Quarter 101.5 88.74 5econd Quarter 136.5 150.84 Third Quarter 357.5 634.02 Fourth Quarter 91.5 96.98 TOTAL 687.0 970.58 Of the total number of hours operated 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> were for commercial work outside the facility, 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> were for the Philip Morris Co. which included both commercial work and graduate thesis work, and 511 hours0.00591 days <br />0.142 hours <br />8.449074e-4 weeks <br />1.944355e-4 months <br /> were for academic work.

1.0 Rod Drop Tests and Visual Inspection Rod drop tests were made on the UVAR reactor during the year and the results are as follows:

Magnet Rod Magnet Free Rod Current (mal Position (inches)

Release (ms)

Drop (ms)

Total (ms 3-6-78 1

160 26 25 472 497 2

160 26 47 505 552 3

160 26 16 472 488 7901240117

_o V

7-7-73 O

1 150 26 a

461 D

473 2

150 26

'? 8 491

\\

520 3

160 26 27 463 490

Division of Reactor Licensing Page 2 January 11, 1979 bbgnet Rod Magnet Free Rod Current (ma)

Position (inches)

Release (ms)

Drop (ms)

Total (ms) 8-17-78 1

ISS 26 8

481 489 2

150 26 34 496 530 3

160 26 19 475 494 8-28-78 Performed maintenance on Rod #2 2

160 26 39 492 531 9-21-78 1

160 26 21 470 491 2

160 26 46 486 532 3

160 26 18.5 466.5 485 Tr. rod drop times continue to be well within the limits required by the Techt..cr.1 Specifications.

The UVAR control rods were visually inspected on September 18, 1978. The following is abstracted from the reactor log book.

Safety Rod #1

- Rod inspected under - 3 feet of water.

Dose rate. at surface of ew rub marks at top of rod. No evidence of water 15 mr/hr.

r cracking.

0. L'a" gage tight at top of rod.

0.950" gage passes easily.

Rod inserted in fuel element T-34 in grid position 34.

Safety Rod #2 - Rod inspected under - 2 feet of water.

Dese rate at surface of water 30 mr/hr. No evidence of c' racking.

0.900" gage passes easily.

Rod inserted in fuel element T-36 in grid position 46.

Safety Rod #3 - Rod inspected under - 3 feet of water.

Dose rate at surface of water 10 mr/hr. No evidence of cracking.

Rub mark near top of rod.

0.900" gage tight.

O'.950" gage passes easily.

Inserted rod in fuel element T-35 in grid position 25.

Although it is not required by the Technical Specifications the regulating rod was also inspected.

Regulating Rod - Rod inspected under - 2 feet of water.

Dose rate at surface of water 2.5 mr/hr. No evidence of cracking.

0.950" gage tight at top cfrod.1.00" gage passes easily.

Inserted rod in fuel element T-33 in grid position 55.

As in previous examinations, the results of the gage measurements do not indicate anv swelling of the rods.

Division of Reactor Licensing Page 3 January 11, 1979 2.0 Maintenance Operations The following maintenance was performed on the UVAR system during the year.

None of these items effected the safe operation of the reactor.

a) February -

1.0 Replaced relays in secondary console with new, sealed type relays to improve reliability of system.

2.0 Replaced amplifier tubes in N-16 monitor to improve response of system.

b) April -

1.0 Replaced tubes and a resistor in high voltage section of area monitor system. High voltage was too low.

c) May -

1.0 Replaced broken resistor in compensating voltage module in Log N drawer.

Voltage was not adjustable.

d) June -

1.0 Replaced power range detectcr #1.

Detector response was not linear.

e)

August --

1.0 Installed newarea monitoring system for bridge and face monitors.

Original system was old and needed upgrading.

2.0 Replaced magnet current resistors in scram logic drawer. Magnet current was not adjustable.

3.0 Replaced Safety Rods #1 and #2 rod seating switches. Switches were broken during rod drop tests.

4.0 Installed new lon exchange system, to be used in parallel with old system, to decrease the number of shut downs required for regeneration.

f) September -

U able to 1.0 Peplaced - 10 volt power supply in scram logic drawer.

n reset scram.

2.0 Replaced thermistor temperature monitor in secondary system.

Thermistor was not functioning.

Division of Reactor Licensing Page 4 January 11, 1979 f) September - (continued) 3.0 Rewired Rod #1 drive system. Wiring was worn and deteriorated.

4.0 Replaced broken seating switch on Rod #1 system. Switch broke during rod drop test.

5.0 Moved constant air monitoring system to better location in reactor room to increase sensitivity.

g) October -

1.0 Replaced integrating circuit module in AT system for alarm function.

Alarm was not operating properiy.

2.0 Replaced transformer in N-16 instrument. Old transformer burned out.

h) November -

1.0 Replaced power range #2 detector.

Detector response was not linear.

2.0 Replaced transistor in Bi-stable in Log N pc -iod circuit. Circui.

would not calibrate properly.

3.0 Operating Procedures The standard operating procedures for the UVAR reactor were upgraded during August and December 1978.

1)

The August 1978 change involved the requirement of completing a daily check list, which is normally completed prior to starting up the reactor.

Since we are anticipating around the clock operation the procedures were changed as fo' lows:

A check list shall be completed each day the reactor is to be operated or prior to the initial start-up if the reactor is tp be operated continuously for long periods of time.

This change was reviewed and approved by the Reactor Safety Committee.

2) The December 1978 change involved upgrading the reactor facility security program. A new section 13 was added to the procedures to limit access to the UVAR reactor room. A push-button combination lock was installed on the outer door of the UVAR reactor room to limit access to authorized individuals.

The previous requirement of having the escape manhole cover open during reactor operation was changed to allow the cover to be closed and secured during reactor operation.

Division of Reactor Licensing Page 5 January 11, 1979 These changes were reviewed and approved by the Reactor Safety Committee.

The provision of having the escape manhole cover closed during reactor operation required a change to the Technical Specifications. This item was approved by the NRC and issued as amendment number 13 tc the UVAR License on December 22, 1978.

4.0 Experiments a) A broad program of activation analysis work was carried out during the year.

Activations were done for members of the Nuclear Engineering Department, the Chemistry Depgytment, the Radiology Department, and the Clinical Chemistry Laboratory.

A continuing program of activation analysis was performed for the Philip Morris Co.

The following Academic Institutions utilized the facility for activation analysis experiments a) Sweet Briar College d) James Madison University b) Randolph Macon College e) Mary Washington College c) Lynchourg College f) Hampton Institute b) Two experiments were performed during the year for organizations outside the University.

1) An experiment was performed for Science Applications Inc. of La Jolla, Calif' rnia.

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Purpose:

The fission reaction in uranium-238, which has a threshold energy of 1 bbV, is often used to measure fast neutrons.

The question has been raised about contributions to the fission rate by high energy capture gamma rays causing photofissions, specifically from iron capture. This may be a significant contribution when measurements are made near the pressure vessal PWR's.

This experiment was reviewed and approved by the Reactor Safety Committee on April 26, 1978.

Experiment: A one inch thick iron slab, encased in aluminum, was placed in the front row of the grid plate to provide a source of capture gamma rays.

Foil packets, consisting of threshold foils, were placed at distances of - 40, 60, and 80 cm. from the iron out into the pool water.

The experiment was run during the month of May,1978 for a total of 66 FM Hours.

The analysis of the threshold foils was performed at the reactor facility.

Division of Reactor Licensing Page 6 January 11, 1979

2) An experiment was performed during the year for the Electric Power Research Institute.

Purpose:

The purpose of the experiment is to perform studies on radiation damage in pressure vessel samples. Westinghouse Corp. will design and fabricate the samples and U.Va. will supply the reactor space.

Experiment: A preliminary experiment was performed in April,1978 to measure the flux profile in the front row of the grid plate, where the actual experiment will be located. The experiment was operated for 10 MN hours.

This experiment was reviewed and approved by the Reactor Safety Committee in March 1978.

The actual gxperiments will be exposed to a neutron g

fluence of - 10 and we anticipate this will involve

- 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> of full power operation. Present plans are to run three shift operation five days per week. Three different sets of experiments are involved and we estimate - 1 1/2 years to complete the entire experiment.

The Reactor Safe +.y Committee reviewed and approved this experiment in October, 1978. The experiment ~ s presently scheduled to begin early in 1979.

5.0 Surveillance Requirements a) The following tests were conducted on a monthly basis as required by the Technical Specifications.

1) Operational checks of the ventilation dcct, personnel door, truck door, and emergency exit cover.

b) The following tests were perforred at inte'rvals not exceeding 6 months.

1) Visual inspection of gaskets on personnel door, ventilaticn duct, and truck door.

2)

Calibration of Source Range.

Intermed.4 ate Range, Power Range, linear power, core gamma monitor, bridge monitor, reactor face monitor, argon monitor, air monitor, pool level monitors, pool temperature monitor, core differential temperature system, and prinary flow.

c) The daily check list, which is.ompleted when the reactor is to be operated.

provides for checks on all of the required scram systems associated with the reactor. All of these tests and calibrations were within limits set forth in the Tcchnical Specifications.

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

Division of Reactor Licensing Page 7 January 11, 1979 d) The emergency spray system was tested twice during the year and the results are as follows:

S.E. Tank S.W. Tank date required flow (gal / min)+

11.0 11.5 2-13-78 11.6 12.6 8-11-78 11.5 12.3 The flow continues to,be abeve tnat required, e) Pool make-up During the calendar year 1978 make-up water to the pool averaged 27 gallons / day.

6. 0 Unplanned Shutdowns Following is a list of unplanned shutdowns on the UVAR reactor during the calendt.r year 1978.

3-7-78 Period scram while adjusting compensating voltage on Log N channel.

Rods at 10 inches reactor sub-critical.

3-8-78 Noise in period meter-reactor sub-critical.

3-9-78 Noise in period meter-reactor sub-critical.

4-1-78 Area radiation monitor while replacing bad tube in high voltage power supply.

Reactor sub-critical.

5-24-78 Scram at 250 KW.

Ope 1ator error. Failure to throw desensitize switch.

6-2-78 Noise in period meter.

Reactor sub-critical.

6-14-78 Loss of primary pump pow :r.

Circuit breaker trip.

6-22-78 Loss of buildidg power" 6-26-78 Reactor Bridge monitor.

Inadvertently left set point at 2 mr/hr during check list.

7-25-78 Scram at 250 KW.

Operator error.

Failure to throw desensitize switch.

8-4-78 Lass of building power.

8-22-78 High power scram on safety chamber #2 while repositioning rods. Chamber reading high due to long run and temperature. Actual power 9 - 2 Mf.

Division of Reactor Licensing Page 8 January 11, 1979 8-22-78 Header mechanism moved away from grid plate, causing scram.

8-24-78 Header mechanism cocked slightly, causing scram.

8-25-78 Header mechanism moved away from grid plate, sausing scram.

8-29-78 Header mechanism moved awr

' rom grid plate, causing scram. Adjusted reactor bridge to better up header.

8-29-78 Log N period scram while adjusting compensating voltage rods at 10 inches, reactor sub-critical.

9-8-78 Building power failure.

9-13-78 Header mechanism moved away from grid plate.

10-13-78 Noise in period..eter during start-up.

11-14-78 Dropped shim rod, magnet current low.

B.

CAVALIER Reactor During the calendar year 1978 the CAVALIER reactor was operated for 69 hours7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> with an integrated power of - 114 watt-hours.

The CAVALIER was operated primarily for Operator training and lab experiments.

1.0 Rod Drop Tests Rod drop tests performed during the year are listed below.

Position Abgnet Magnet Free Total Drop Date Rod (Inches)

Volts Release (Msec)

Drop (Msec)

(hbec) 3-17-78 1

26 36 95 467 562 2

'26 50 83 465 548 3

26 34 89 436 525 4

26 30 87 459 546 7-10-78 1

26 36 87 454 541 2

26 50 82 456 538 3

26 35 94 453 547 4

26 30 85 472 557 10-11 78 1

26 36 80 455 535 2

26 52 82 448 530 3

26 35 93 433 526 4

26 30 97 500 597 Rod drop times continue to be within th

.4mits set by the Technical Specifications.

Division of Reactor Licensing Page 9 January 11, 1979 2.0 Operating Procedures No changes were made in the CAVALIER operating procedures during the calendar year 1978.

3.0 !!ain tenance The following maintenance was performed on the CAVALIER reactor system during the. year 1978.

a) March 1978 -

1)

Rod # 4 would not stop at upper limit.

Replaced micr'-switch.

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2) Plateau curves shifted on source range channels.

Gain on pre-amps was not adjustable.

Installed new pre-amps for source range channels.

b) May 1978 -

1)

Unable to calibrate Log N Channel.

Rept. aced amplifier B in log N drawer.

Checked o.k.

2) Solid State Relay failure light on in scram logic drawer.

Replaced 4 resistors. Checked o.k.

3) Source range recorder would not track with meter on source range drawer.

Replaced 2 resistors and added a 200 Q potentiometer to recorder to aid calibration.

c) October 1978 -

1) No period indication on start-up on Log N Channel.

Replaced modulator P in Log N drawer.

Checked o.k.

d) November 1978 -

1) Irratic response on Log N recorder.

Replaced servo motor and slide wire contacts.

Checked o.k.

4.0 Unplanned Shutdowns Following is a list of m1 planned shutdowns on the CAVALIER during the calendar year 1978.

a) October 4,1978 - High power scram while measuring period during rod calibration measurements. Scrammed at - 55 watts.

b) Novembec 6,1978 - High power scram while measyring period. Scrammed at

- 55 watts.

Division of Reactor Licensing Page 10 January 11, 1979 5.0 Surveillance Requirements ne following tests were conducted as requiz.d by the Technic &1 Specifications.

a)

Rod drop measurements were made at intervals not exceeding four months.

b) The following tests were conducted at intervals not exceeding six months.

1) Calibration of Source Range Channels, Log N Channel, Log G channel, linear power channel, pool level monitor, Radiation monitoring system, and boron concentration in ARIS system.

c) The following tests were conducted at intervals not exceeding twe'.ve months.

1) Measurement of control rod worth.

2) Flow test of ARIS system.

d) The daily check list, which is completed when the reactor is to be operated, prcvides for checks on all of the required scram systems associated with the reactor.

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

C.

Health Physics 1.0 Effluent Release a) A nospheric Release The following effluent was released to the atmosphere during the calende.r year 1978,

1) AR 2.8 curies from operation of reactor 41 AR 0.91 millicuries from activation of experiments b) Solid Waste During the calendar year 1978 approximately 8.5 cubic feet of solid waste was shipped from the reactor by Teledyne, Inc. The activity in this waste was as follows:

Division of Reactor Licensing Page 11 January 11, 1979 Isotopes Activity (millicuries),

Tc 0.06 P

2.35 Cr 0.81 S

3.59 Co 0.22 Na 0.51 TOTAL 7.54 millicuries C.

Liquid Waste Liquid waste from regeneration of the demineralizer system was released duringtheyearanddilutedwigwater om the hold-up pond. The most predominant isotopes in the effluent are S and P Activity (microcuries)_

Volune (gallons)

First Quarter 220.4 5,007,500 Second Quarter 140.5 4,088,000 Third Quarter 65.0 1,594,000 Fourth Quarter 23.0 745,000 TOTAL 448.9 11,434,500

-8 The average specific activity released was 1.04 x 10 pCi/mt.

2.0 Environmental Monitoring During the year the health physicist took air and water samples both at the facility and outside the site boundary. The following table lists these locations and the specific activities obtained from these samples.

Division of Reactor Licensing Page 12 January 11, 1979 Incation Sample Specific Activity (Average of All Samples Reactor Facility Water 5.91 x 10 pCi/mi

-2 Air 0.54 x 10,g pCyce Filter Plant Water 4.18 x 10 pCi/mi

-12 Air 1.33 x 10 pCi/cc Barracks Road Water 6.93 x 10 pCi/mi 1.40 x 10"I uCi/cc Air 3.0 Personnel Monitoring During the year approximately 149 personnel, including faculty, staff, and students were monitored by film badges supplied by the R.S. Landauer Co.

The highest exposures were by three staff members who are directly involved with the operation of the faci-lity and the handling of samples used in activation analysis.

Gamma Exposure Beta Exposure Individual A 200 millirem 50 millirem Individual B 160 millirem 60 milliren Individual C 160 millirem 40 millirem During the year the facility had 2443 visitors. These visitors were monitored with direct and indirect reading dosimeters and received no sigrificant exposure.

D.

Miscellaneous 1)

Formal meetings of the Reactor dafety Committee were held on the following dates.

February 24,1978, March 7,1978, April 4, 1978, April 26, 1978, October 19, 1978 and December 20, 1978 A sub-committee of the Reactor Safety Conmittee audited the operations during the months of March, September and December.

2) Practice emergency drills were held at the facility during the months of April and September.

During the month of April,1978 the staff completed and successfully passed a course in cardiopulmonary resuscitation.

3) NRC compliance personnel vis,ited the facility on the following dates:

May 10, 11, 12 General Inspection October 17, 18, 19 Health Physics Inspection November 28, 29, 30 General Insp::ction December 29 Security Inspection

9 Division of Reactor Licensing Page 13 January 11, 1979 E.

Personnel Dr. B. L. Shriver joined the staff September 1,1978 and will be appointed Director of the Facility effective January 1,1979.

Dr. T.G. Williamson remains as Chairman of the Department of Nuclear Engineering and Engineering Physics.

'Ihis report has been reviewed and approved by the Reactor Safety Committee.

Sincerely, J.P. Farrar, Reactor Supervisor University of' Virginia, Reactor Facility cc: Office of Inspection 4 Enforcement Atlanta, Ga 4

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