ML20040E362
| ML20040E362 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 01/06/1982 |
| From: | Farrar J VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8202040227 | |
| Download: ML20040E362 (13) | |
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UNIVERSITY OF VIRGINIA SCHOOL OF ENGINEERING AND APPLIED SCIENCE
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C H AR LOTT ESVILLE, 22901 D EP A RTM ENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS T ELEPH ON E:
604-924 7136 REACTOR FACILITY
.Tanuary 6, 1982
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RE:
Docket No. 50-62, License No. R-66
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Docket No. 50-396, License No. R-123
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Gentlemen:
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L We hereby submit, as required by Section 6.7.e of the TecNu;ical Specificat ions, our annual report of the operations of the University of Virginia Research Reactor (UVAR), License No. R-66, Docket No. 50-62 and the CAVALIER Reactor, License No. 123, Docket No. 50-396 during the period January 1, 1981 through December 31, 1981.
A.
UVAR Reactor The UVAR reactor was operated during the year as follows:
llours Operated MW llours First Quarter 1030.1 1394.78 Second Quarter 976.5 1703.94 Third Quarter 509 590.02 Fourth Quarter 1052.3 1299.08 TOTAL 3567.9 4988.42 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:
Rod Position Magnet Free Total Ma currbnet (ma)
(inches)
Release (msec)
Drop (msee)
(mseel Rod nt 1-30-81 1
160 26 29 481 510 2
160 26 37 4S7 524 3
160 26 38.5 457 195.5 0
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y, Division of Reactor Licensing Page 2 January 6, 1982 Magnet Rod Position Magnet Free Total Rod current (ma)
-(Inches)
Release (msec)
Drop (msec)
(msec) 3-5-81 1
160 26 20 458 478 2
160 26 26 488 514 3
160 26 13-474 487 5-12-81 Replaced Safety rods #1 and #2 with new rods 1
160 26 27 460 487
.2 160 26 39 452 491 3
160 26 40 466 506 9-28-81 1
160 26 28 454 482 2
160 26 25
-463 488.
3 160 26 35 479 514 The rod drop times continue to be well within the limits required by the Technical Speci fications.
The UVAR control rods were visually inspected twice during the year.
The following is abstracted from the reactor log book.
1-29-81 3afety Rod #1 - Inspected rod under approximately 3 feet of water. Rdb marks at top of rod.
0.95" gage passes casily. No evidence of cracking.
Safety Rod #2 - Inspected rod under approximately 3 feet of water.
No evidence of cracking.
0.95" gage passes easily.
Safety Rod #3 - Inspected rod under approximately 3 feet of water.
Some rub marks at top of rod. No evidence of cracking.
0.95" gage passes easily.
Regulating Rod - Inspected rod under approximately 3 feet of water.
Rub marks at top of rod.
0.95" gage tight at top of rod.
1.00" gage passes easily. No evidence of cracking.
5-12-81 Safety Rods #1 and #2 were removed from service and replaced with new rods.
Safety Rod #1(new) - 0.90" gage tight at top and bottom.
0.95" gage passes easily.
Safety Rod #2(new) - 0.90" gage tight in middle.
0.95" gage passes easily.
Safety Rod #3 -
Inspected rod under approximately 3 feet of water.
Rub marks near top of rod.
0.95" gage passes easily.
No evidence of cracking.
Regulating Rod -
Inspected rod under approximately 3 feet of water.
Rub marks near top of rod.1.00" gage passes easily.
No evidence of cracking.
Division of Reactor Licensing Page 3 January 6, 1982 2.0 Maintenance Operations
)
The following maintenance was performed on the UVAR system during j
the calendar year 1981.
1-12-81 Core Gamma hbnitor - installed an alarm nodule with indication on the common alarm panel.
1-23-81(a) Problem:
AT system alarms at 10.00 F when alarm is set at 10.50 F.
Action:
Found most significant digit comparator chip bad.
Replaced chip and checked out alarm circuit.
(b)
Problem:
Linear chart periodically moves in reverse.
Action:
Found gear on drive motor stripped.
Replaced gear.
1-30-81 Problem: No output from safety rod #3 seating test jack.
Action:
Found broken wire to test jack.
Replaced.
2-4-81 Problem:
Excessive vibration in primary pump.
Action:
Found worn fle x coupling.
Replaced coupling.
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2-27-81 Problem:
Chart drive for linear reactor stalled.
Action:
Found motor jammed.
Replaced motor and gear.
3-16-81(a)
Problem:
Irratic count rate on level indication of Source Range system.
Action:
Found bad connection on source range drawer.
Replaced cable.
(b)
Problem:
With header mechanism up and indicating up scram occurred when placing range switch to "2Mh'" position.
Action:
Found dirty contacts on header relay.
Cleaned contacts.
3-30-81 Problem:
Duct argon monitor indicating zero CPM.
Action:
Found GM tube defective.
Replaced tube and checked system with test source.
4-20-81 Drained and cleaned cooling tower.
i Division of Reactor Licensing Page 4
. January 6, 1982 5-11-81 Replaced Safety Rods #1 and #2 w*ith new rods. Old rods had total exposure of 15445 Mh' hears and were becoming gray.
5-18-81 Problem: Magnet current for Safety Rod #2 not adjustable.
Action:
Found bad potentiometer.
Replaced.
5-21-81 Problem:
Regulating rod would not move in manual or automatic control Action:
Found reduction gear with several broken teeth.
, Installed new gear.
5-29-81 Removed the rod interlock override from Intermediate range system.
6-13-81 Problem: Second digit on AT system not functioning.
Action:
Replaced chip in comparitor.
7-16-81 Problem: Power Range Channel #1 drifts.
Action:
Replaced detector and cable connectors.
Checked out system.
7-22-81 Problem: Compensating Voltage for Intermehiate Range not adjustable.
Action:
Replaced compensating voltage potentiometer.
July, 1981 During the month of July a new filter system was installed in the liquid waster system.
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8-18-81 a)
Replaced carbon filter in demineralizer system.
b)
Cleaned and inspected tubes in lleat Exchanger.
10-9-81 (a)
Installed new primary pump and motor in system.
Primary flow increased from approximately 915 gpm to approximately 1060 gpm.
(b)
Installed new bearings on Secondary pump motor.
11-19-81 Problem: Instrumentation Irratic Action:
Replaced detectors on Intermediate Range, Linear Power and Power Ranges 1 and 2 and calibrated.
12-2-81 Problem:
Room Argon monitor not functioning.
Action:
Replaced GM tube, 12-22-81 Problem: !!cader position pole bent while removing capsules from reactor.
action:
Replaced pole - checked out operation.
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Division of Reactor Licensing Page 5 January 6, 1982 3.0 Operating Procedures The Standard Operating Procedures for the UVAR reactor were upgraded during the months of February, hby, July, and October 1981.
These changes involved modifying and upgrading sections on start-up procedures, procedures for changing the core configuration, instrument calibrations, llcalth Physics procedures, and abnormal conditions procedures.
The changes were reviewed and approved by the Reactor Safety Committee.
4.0 9xperiments n'
A broad program of activation analysis work was carried out during the year. Activations were donc for the Departments of Nuclear Engineering and Engineering Physics, Chemistry, Radiology and the Clinical Chemistry Laboratory of the U.Va. Hospital.
A continuing program of activation analysis was performed for the Philip Morris Company.
The following Academic Institutions utilized the facility for activation analysis experiments.
- 1) Sweet Briar College
- 3) Piedmont Community College 2)
James Madison University
- 4) Lynchburg College i
b)
A series of experiments were 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 experiments and U.Va. will supply the reactor space.
Experiment:
TWo capsules known as the Crack Arrest experiments which were loaded in the reactor during November,1980 were continued into 1981. The irradiation of these capsules were completed on bby 7,1981 for an integrated power of 2596.5 Mh' hrs. These capsules were stored in the North end of the pool and shipped to Battelle Memorial Institute for analysis on October 21, 1981.
A second set of Crack Arrest capsules were loaded in the reactor and run between bby 19, 1981 through July 7,1981. These capsules were removed from the reactor to allow use of the reactor for an operator trai~ning program during the The capsules were re-loaded in the reactor on September 9,1981 and summer.
run through December 21, 1981 for an integrated power level of 2596 MWhrs.
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i Division of' Reactor Licensing i
Page_6 January 6, 1982 Several smaller capsules of steel samples were run in the reactor during the year.
These capsules were fabricated at UVA and the analysis will be performed at UVA.
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 duct, personnel door, truck door and emergency exit cover.
b)
The following tests were performed at intervals not exceeding 6 months.
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- 1) -Visual inspection of gaskets on personnel door, ventilation duct, and truck door.
2)
Calibration of Source Range, Intermediate Range, Power Range, Linear Power, core gamma monitor, bridge monitor, reactor face monitor, argon monitor, air monitor, pool level monitors, pool temperatur monitor, core differential pool temperature, and primary flow, c) The daily check list, which is completed when the reactor is to be operated, provides for checks on all of the required scram systems associated with the reactor.
d) The emergency spray sysytem was tested during the month of February 1981 and the results are as follows:
i Date S,.E. Tank S.W. Tank Feb. 3, 1981 Required Flow, gal / min 11.0 11.5 Actual Flow, gal / min 12.2 12.3 The flow continues to be above that required by the Technical Specifications.
All of these tests and calibrations were well within limits set forth
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by the Technical Specifications. Data on all of these tests and calibrations is on file at the facility.
1 e) Pool Make-up During the calendar year 19P1 make-up water to the pool averaged 65 gal / day.
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Division of Reactor Licensing i
Page 7 January 6, 1982
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i 6.0 Unplanned Shutdowns Following is a list of unplanned shutdowns on the UVAR reactor durinn the calendar year 1981.
1-12-81 2 scrams due to header falling away from grid plate 1-14-81 4 scrams due to header falling 1-15-81 Scram due to header falling 1-19-81 Scram when fuel element was accidently moved 1-21-81 Scram due to header falling 1-22-81 3 scrams due to header falling 1-23-81 2 scrams due to header falling 1-26-81 3 scrams due to header falling 1-27-81 Scram due to electronic noise in scram bus Scram on period circuit while adjusting compensating voltage 3 scrams due to header falling 2-5-81 Scram when range switch was moved 2-26-81 Scram from air to header system when switch was accidently actuated 3-16-81 Scram when range switch was moved 4
3-20-81 Scram from bridge monitor when removing sample from rabbit 4-2-81 Scram from Low Pool Level #1 system 4-14-81 Scram-momentary building power failure
. Scram-when moving range switch 4-17-81 Scram-building power failure 5-20-81 Scram-building power failure Scram on period circuit while adjusting compensating voltage 5-28-81 Scram-building power failure 6-5-81 Scram when moving range switch i
6-17-81 Scram-Building power failure 7-1-81 2 scrams from building power failure i
7-8-81 Scram when moving range switch Scram from Bridge monitor when removing tangential beam port from pool 7-13-81 Scram-high power indication 7-15-81 Scram when repositioning power range detectors.
7-16-81 Scram due to fluctuation of power range channel.
7-20-81 Scram on period channel when moving fuel element-reactor was sub-critical at time Scram from noise in console 1
7-22-81 2 scrams while adjusting compensating voltage Scram from pool level #2 system i
7-23-81 Scram-failure to move range switch when going to high power l
'7-27-81 Scram-spurious signal on low flow system 1
7-29-81 Scram when moving range switch 7-30-81 Scram when moving range switch 4'
8-6-81 Scram-failure to move range switch when going to high power 2 scrams fr' m spurious signal in pool level system j
10-12-81 o
i 10-29-81 2 scrams from loss of building power l
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Division of Reactor Licensing Page 8 January 6, 1982 11-25-81
. Scram from loss of building power 12-8-81 Scram from loss of building power 12-15-81 Scram from loss of building power 12-30-81 Scram-Power Range #1-B.
CAVALIER Reactor During the calendar year 1981 the CAVALIER Reactor was operated as follows:
Hours Operated Watt-hours First Quarter 12.5 7.935 Second Quarter 46.0 97.61
'Ihird Quarter 11.5 20.28 Fourth Quarter 16.0 8.26 TOTAL 86.0 134.085 b
1.0 Rod Drop Tests Rod drop. tests performed on the CAVALIER Reactor during th,e year are listed below:
Position U
Volts Release (msec)
Drop (msec)
Drop (msec)
Date Rod (inches)_
2-17-81 1
26 36 65 478 543 2
26 51 51 532 583 3
26 28 34 520 554 4
26 30 77 488 565 6-2-81 1
26 35 73 471 544 2
26 35 36 456 492 3
26 35 64 463 527 4
26 35 87 492 579 10-20-81 1
26 35 73 448 521 2
26 35 32 442 474 1
3 26 35 70 505 575 4
26 35 58 614 672 The zud drop times continue to be within the limits set by the Technical Specifications.
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Division of Reactor Licensing Page 9,
January 6, 1982 2.0 Operating Procedures The operating procedures for the CAVALIER reactor were upgraded in bby and July, 1981. Changes were made in the sections involving the daily check list, start-up procedures and procedure for abnormal
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conditions.
These changes were reviewed' and approved by the Reactor Safety Committee.
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3.0 Maintenance m
Tde following maintenance was performed on the CAVALIER reactor system during the calendar year 1981.
2-13-81,3 Moved area radiation monitor from top of console to wall of fuel storage room to also act as a criticality monitor. Added alarm so the monitor will alarm in UVAR control room as well as the CAVALIER control room.
S-20-81 Problem:
Solenoid operated pawls on rod drive mechanisms sticky.
Action: 'Peplaced solenoids on all four mechanisms with new type.
Checked out o.k.
S-29-81 Problem: Pens not working properly on Linear 6 Log N recorders.
Action:
Replaced with new felt tip pens.
6-29-81 Problem:
Teleflex cable jammed on source drive system.
Action:
Replaced with. cable and drum system and installed new notor.
4.0 Unplanned Shutdowns
'Ihe fo'11owing unplanned shutdowns occurred on the CAVALIER reactor during the calendar year 1981.
6-2-81 Scram from noise.in Rod #2 relay 6-11-81 Scram froin noise in Rod #4 relay Scram from noisc im Intermediate range 6-16-81 Scram when individual stepped on cables leading to console 6-22-81 ~ Scram from noise in source drive motor Scram from noise in rod drive 6-23-81' -Scram from noise in rod drive 6-29-S1 Scram when energihing source range channel Scram - high power trip 9-22-81 Scram-low water level, spurious signal.
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Division of Reactor Licensing Page 10 January 6, 1982 5.0 Surveillance Requirements The following tests and calibrations were performed on the CAVAL 11!R system.during the calendar year 1981 as required by the Technical Speci fications,
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 Icvel monitor, radiation monitoring system, and boron concentration in ARIS system, c)
The following tests were conducted at intervals not exceeding twelve 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, provides 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.
Ilealth Physics 1.0 Effluent Release a) Atmospheric Release The following effluent was released to the atmosphere during the calendar year 1981.
(AR I) 7.18 curies from operation of the IIVAR reactor.
b) Solid Waste During the calendar year 1981 approximately 125 cubic feet of solid waste was shipped from the reactor facility by Teledyne Inc.
The activity of the waste was as follows:
Division of Reactor Licensing Page 11 January 6, 1982 Isotope Activity (millicuries)
Cs-137 1.0 Co-60 1.4 Ag-110m 3.5 2n-65 2.7 Mn-54 0.268 8.868 millicuries c)
Liquid Waste Liquid waste from the regeneration of the deminerali:er system was released during the year and diluted with water from the hold-up pond.
Activity (microcuries)
Volume (gallons)
First Quarter 150.8 306114 Second Quarter 94.8 272350 Bird Quarter 140.0 197428 Fourth Quarter 13.09 302758 TOTAL 398.69 1,198,650
-8
% e average specific activity released was 8.65 x 10 uci/ml.
2.0 Environmental tbnitoring During the year the llealth Physicist took air and water samples both at the facility and outside the site boundary. De following table lists these locations and the specific activities obtained from these samples.
Location Sample Specific Activity (average of all samples?
Reactor Facility Water 6.08 x 10~
uci/ml
-l' Air 2.36 x 10 uci/cc
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Filter Plant Water 1.67 x 10' uci/ml
-l' Air 4.23 x 10 uci/cc
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-9 Barracks Road Water 7.26 x 10 uci/ml
-l' Air 7.46 x 10 uci/cc 3.0 Personnel bonitoring During the calendar year 1981 approximately 123 personnel, including faculty, staff, and students were monitored by film badges supplied by R.S. Landauer Co.
The highest exposures were by three staff members directly involved with the operation of the facility and the handling of samples used in activation analysis, i
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Division of Reactor Licensing Page 12 January 6,1982 Whole Body Exposure
- Individual A 380 mrem Individual B 340 mrem Individual C 270 mrem
- as of 10-31-81 During the year the facility had 3014 visitors. These visitors were monitored with direct reading dosimeters and receivied no significant exposure.
D.
Miscellaneous
- 1) Formal meetings of the Reactor Safety Committee was held on the following dates:
January 23, 1981 July 28, 1981 February 25, 1981 November 24, 1981 May 7, 1981 A sub committee of the Reactor Safety Committee performed an audit of the facility operations during June 1981 and December 1981.
2) a)
A security inspection of the facility was made by an NRC compliance inspector during the month of May,1981. No items of non-compliance was found, b)
An inspection of the facility was made by an ANI insurance inspector during the month of May,1981.
c)
A general inspection of the facility was made by an NRC compliance inspector during the month of September 1981. No items of non-compliance wero found.
3)
Orientation tours of the facility were given to members of the ll.Va.
Police force during the month of July,1981 and to metabers of the local fire department during 'the months of August and September, 1981 to familiarize them with our facility and operations.
4)
A revised Security Plan and a revised Emergency Plan were submitted to the NRC during the month of July,1981.
5)
Practice evacuations of the facility were held on lebruary 13, 1981 l
and October 30, 1981.
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S Division of Reactor Licensing Page 13 January 6, 1982 E.
Personnel a)
A new position of Research Engineer was established during the year and Mr. C. A. Bly, a Senior Operator on the staff, has been appointed to that position, b)
Reactor Operator examinations were given by the NRC during the month of August 1981 and resulted in the licensing of eight reactor operators and one Senior Operator.
"Ihis report has been reviewed and approved by the Reactor Safety Committee.
Sincerely,
.P. Farrar, Reactor Supervisor INA. Reactor Facility JPF:vs cc: Office of Inspection and Enforcement Atlanta, Georgia