ML20106H014
| ML20106H014 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 01/24/1985 |
| From: | Farrar J VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8502150147 | |
| Download: ML20106H014 (12) | |
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r A,1 UNIVERSITY OF VIRGINIA DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PIIYSICS NUCLEAR REACTOR FACILITY L
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III P J SCIIOOL OF ENGINEERING AND APPLIED SCIENCE CHARLOTTESVILLE, VA 22901 2
January 24,198g Teleptione: 8n924m I
Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Cecil 0. Thomas Gentlemen:
We hereby submit, as required by Section 6.6.2 of the Technical Specifications, our annual report of the operations of the University of Virginia Reactor (UVAR), License Number R-66, Docket number 50-62 and the CAVALIER Reactor, License Number R-123, Docket Number 50-396 during the period January 1, 1984 through December 31, 1984.
A. UVAR Reactor The UVAR reactor was operated during the year as follows:
Hours Operated MW Hours First Quarter 715.75 1262.14 Second Quarter 848.0 1539.81 Third Quarter 1071.5 1969.57 Fourth Quarter 531.0 915.87 Total 3166.25 5687.39 1.0 Rod Drop Tests and Visual Inspection Technical specification requirements:
Rod drop times measured at leasi semi-annually magnet release < 50 msec free drop time < 700 msec Rod visually inspected at least annually
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.. N-Rod drop tests were made on the UVAR reactor as follows:
Magnet- . Magnet Free Drop Total Dets Rod current (ma) . (inches)
Rod Position release (msec) (msec) (msec)
- 1-25-84 1 160- 26 21.7 458.9 480.6 2 160 26 39.3 467.7 507.0 3 60 26 49 566 615.0 3-13-84 Replaced Rod #3 3 60 26 35 458 493 J4-17-84 1 160- 26 17.3 485 502.3
.2 160 26 22.8 470 492.8 3 60 26 21.3 449 470.3 5-8-84 1 160 26 15.0 473 488
-2 160 26 37.0 471 508 3' 70 26 13.0 455 468 8-27-84 1 160 26 7 502 509
-2 160 26 30 476 506 3 70 26 19 461 480
?ll-6-84 '1 160 26 18.4 495 513.4
-2 160 26 29.7 476- .505.7.
3 70 26 41.6 594 635.6
.Th3 rod drop. times continue to be within the limits required-by the Technical-
'Sp:cifications E 'The UVAR control rods were visually inspected twice'during the year.
The following is abstracted from the reactor log book.
Date 5-8-84 ~
Rod #1 -- Visually inspected rod .under approxima'tely 1 1/2 feet. of ,
water.- Dose rate at surface of water approximately 750 ar/hr. . Some rub marks ~at top of rod. 'No evidence of cracking. Passes 0.950 inch gage easily..
Rod #2 - Visually inspected rod under approximately 1 1/2 feet-of water. Dose rate at surface of water approximately.500 ar/hr.: No evidence of cracking.; 0.950 inch gage passes easily.
Rod #3 - Visually inspected rod under approximately 1 1/2 feet'of-water.- Dose rate at surface of water-approximately 1 R/hr.
,'No evidence of cracking. 'O.950 inch gage passes easily.
Date'11-5-84 Rod #1 - Visually inspected rod under approximately 3 feet'of water.
Dose rate at surface.of water approximately 35 ar/hr. No evidence of cracking. sNo rub marks. 0.950, inch gage passes easily.
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3 Rod #2 - Visually inspected, rod under approximately 3 feet of water.
Dose rate at surface of water approximately 17 mr/hr. No evidence of cracking. 0.950 inch gage passes easily.
l Rod #3 - Visually inspected rod under approximately 3 feet of water.
Dose rate.ac surface of water approximately 35 mr/hr. No evidence of cracking. 0.950 inch gage passes easily.
Regulating Rod - Visually inspected rod under approximately 3 feet of water. Dose rate at surface of. water approximately 17 mr/hr. Rub marks along side and top of rod. 1.00 inch gage passes easily.
2.0 Maintenance Operations The following maintenance was performed on the UVAR system during the calendar year 1984.
I 1-6-84 Noise spikes on Power-Range Channel-f2. Replaced detector and cable. connectors.. System checked out o.k.'
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1-26-84 Linear channel noisy. Replaced detector. System checked out 7l o.k.
i l 1-30-84 Spurious period scramfon Intermediate Range Channel. Replaced l
3; connectors on detector. System checked out o.k.
2-22-84' Compensating voltage to linear channel not functioning l
properly. Replaced compensating voltage cable from console to
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reactor bridge. System checked out o.k.
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.3-13-84 Indication. that. rod #3 may be -rubbing inside guide tubei ,.
L Disassembled and replaced rod #3. ' Magnet release time measured-L' to be 35 maec compared to 49 asec measured.on.1-25-84.-
r 5-7-84 Drained and cleaned cooling. cover and_ secondary side of heat?
(5-8-84 ' exchanger as part of yearly preventative maintenance'.
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, 6-11-84 Noise in area radiation monitor (reactor bridge) cause'd two L spurious scrams. Exchanged reactor bridge detector with
-demineraliser room detector. System functioning properly. .
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'7-16-84 a) Power Range il noisy.-~ Replaced 'etector d and connectors.
Checks:o.k.. ,
. b) 'Demineraliser pump noisy. Found badly worn coupling insert.' . Replaced insert'. and 'put. system back .intol ,
. operation.
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7-19-84 .Small-leak in' outlet piping,from domineralizer pump prior to.
_ . entering carbon-filter.- Epoxyed area and put system back into
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. s 7-23-84 UVAR Room Argon Monitor - background reading unusually high when performing check-list. Checked system and found bad detector. Replaced detector. System functioned normally.
9-12-84 Regulating Rod would not respond to servo control. Cleaned and lubricated lead screw. Replaced capacitor. System functioned normally.
9-21-84 Leak in demineralizer system overnight causing reactor pool 9-25-84 level to drop approximately 1 foot until float switch secured entire system. Contaminated water in demineralizer room and heat exchanger room. De-contaminated areas. Replaced piping from discharge side of pump to carbon filter. Adjusted float switch to secure demineralizer if pool level drops 1-2 inches.
Put system back into operation. No leaks detected.
9-24-84 Power Range channel #2 noisy. Replaced detector and connectors. System checked out o.k.
p 10-8-84 Reactor Room truck door gasket cracked at top of door.
Replaced gasket.
10-9-84 Demineralizer Room area monitor - small variations in readings.
cleaned connectors on detector. Functions normally.
10-18-84 Constant Air Monitor - Vacuum pump making excessive noise, suggesting bad bearings. Replaced pump-motor assembly and intake and exhaust filters. Functions normally.
11-9-84 Pool Level Demineralizer Trip System - added second back-up float switch to existing system in series with existing switch.
New system will also sound alarm in hallway outside reactor room to alert personnel when room is not occupied.
11-27-84 Intermediate Range Channel - Oscillating noise in level and period circuits from H.V. power supply. Found interference from battery charger for_ Pneumatic Rabbit system feeding through primary side of E.V. power supply. Connected Battery charger to different circuit. Noise eliminated.
12-5-84 Power Range #2 erratic. _ Replaced detector - system checks out
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o.k.
.12-20-84 Source Range Channel - erratic signal. Found bad - 6 volt power supply to pre-amp.- Installed temporary 6' volt battery.
to pre-amp until permanent power supply can be replaced.
System checked out o.k.
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1 23.0 Operating Procedures The UVAR standard operating procedures were rev'ised during the year as follows:
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5 January, 1984 - Section 12 (Emergency Procedures) was revised and expanded.
February, 1984 - Section 5 concerning start-up procedures was expanded.
March, 1984 - Section 6 concerning sample irradiations was expanded.
July,'1984 - _Section 7.4 concerning control rod calibration was revised and expanded.
-October, 1984 - Section 10.4 concerning Health Physics surveys was revised.
December, 1984 - Section 6 concerning sample irradiations was expe.nded.
Section_10 concerning liquid releases was expanded.
Section 12 changes were made to the " Emergency Actions" list.
These changes were reviewed and approved by the Reactor Safety Committee.
4.0 Experiments 4
a) A broad program of activation and analysis, work was done during the year for the Departments of Nuclear Engineering and Engineering Physics, Chemistry, Radiology and the Clinical Chemistry Laboratory of the U.Va. Hospital.
b) A'. series of, experiments were' performed during the year for.
the Electric Power.Research Institute involving radiatien damage studies of pressure ~ vessel samples. 'Nine different'
, capsules were run during the year. These experiments were terminated in October 1984, c) A-series of-experiments were performed during the' year for the Carolina Power and_ Light Company;that involved the_ study of' degradation in fiberglass insulation due to radiationLand high' temperature, d). A continuing' program of tobacco research was performed for.
the Philip Morris Company..
e) A series of' neutron? radiography experiments were performed
- during the year utilizing the neutron beam ports..
2 f)' ' The south tangentiallbeam port. facility was used'during the year to measure photo-fission cross sections utilizing a centrifuge.
g) The following Academic < Institutions utilized the facility for tours and activation-analysis experiments.
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- 1) Virginia Institute of Marine' Science = 8)*Bridgewater College
- 2) Mary Washington College 9) University of S. Carolina
- 3) Brandeis University 10) Rappahanock High School
- 4) James Madison University- 11) Fairfax High School
- 5) Junior-Science Symposium- 12) Virginia Polytechnic &
- 6) Longwood College State University
- 7) Lynchburg College 13) Piedmont Community College
. 14) J. Sargeant Reynolds Community College 5.0 Surveillance Requirements a).The following tests were performed 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 six months.
- 1) Visual inspection of gaskets on personnel door, ventilation-duct and truck door.
- 2) Calibration checks of source range, intermediate range, power range, linear power, core gamma monitor, bridge radiation monitor, reactor face monitor, duct argon monitor, constant air monitor, pool level monitors, pool temperature monitors, core differential pool temperature and primary flow, c) The daily checklist, 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 cooling system was tested during the month of September 1984. The results are as follows:
S.E. Tank ~S.W. Tank Required flow, gal / min- 11.0 11.5 9-24-84" Actual flow,-gal / min 12.3 13.5'
-The flow continues to be greater than that. required by the Technical Specifications Data on all of these tests and calibrations is on ' file-at the1 facility.-
e)' Pool Make-up-
- During the calendar year 1984 make-up water to the UVAR.' pool averaged 84.5 gallons / day.-
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6.0 Unplanned Shutdowns :
Following is a list of unplanned shutdowns on the UVAR l reactor during the calendar year 1984 1-3-84~ Scram - Instrument noise on Power Range #2 1-5-84 3 Scrams - Instrument noise on Power Range #2 1-8-84 Scram --Instrument noise on Reactor Face Monitor 1-17-84 Scram - Instrument noise on Power Range #2 1-26-84 3 Scrams - Instrument noise on Intermediate channel period - power was steady.
2-1-84 2 Scrams - Noise on Power Range #2 2-8-84 Scram - Noise on Reactor Face Monitor Scram - High reading on bridge monitor while moving fuel at.far end of pool 2-14-84 Scram - Power Range #2 - causad by malfunction of linear recorder in servo.
2-22-84 Scram - Power Range #1 - caused by malfunction of linear recorder in servo.
'2-28-84 Scram - Intermediate period - moving SB-Be source near detector.
3-7-84 Scram Operator forgot to move range switch when going above 200 kw.
Scram - Power Range #2 - reactor was operating at 200 kw.
3-26 Scram - Noise on Reactor Face monitor.
4-17-84 Scram - Intermediate Period - moving SB-Be source near detector.
Scram - Power Range #2 - moved range switch too early while decreasing power.
4-28 Scram - Range switch indication.
4-30-84 Scram - Noise'in Power Range #2 while moving rods.
'5-8-84 Scram - Intermediate Period when moving source near detector.
5-10-84 Scram _- Intermediate Period when moving-source near detector.
5-23-84 2 Scrams - Loss of Building Power.
5-25-84 Scram -' Noise in Bridge Radiation Monitor.
6-1-84 Scram - Loss of Power in Secondary Console.
6-5-84 Scram - Loss of Building Power.
6-7-84 Scram'- Noise.in Bridge Radiation Monitor.-
- 6-9-84 Scram - Loss of Building Power.
6-11-84 3 Scrams -fNoise in Bridge Radiation Monitor.
7-6-84 Scram - Bridge radiation monitor when sample was removed from rabbit.
7-6-84 Scram - Loss of Building Power during storm.
.7-11-84 Scram - Noise in console --indicated primary. pump off although pump was running.
7-20-84 Scram - Noise while moving regulating rod.
8-6-84 Scram - Noise in Intermediate period channel.
8-8-84.
Scram - Loss of building power.
8-13-84 . Scram . Loss of building power.
2 Scrams - Noise in Range switch.
' Scram - Noise in Power Range #2.
8-22-84 Scram - Power Range #1 while adjusting detector position.
10-9-84 Scram - Noise-in console.-
Shutdown . Rod #3 dropped.
10-10-84 Scram - Noise in Power Range #2.
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~10-23-84 Scram - Building Power failure.
10-24 Shutdown - Rod #3 dropped.
10-30-84 Shutdown - Rod #3 dropped.
.11-15-84 Scram - moving Sb-Be source near detector.
20-84 Scram-- Noise in Power Range #2.
~12-18-84 Scram - moved power range switch.
12-21-84 Scram - noise in Bridge monitor'.
Scram - noise in Power Range #2.
.B. CAVALIER Reactor.
During the calendar year 1984 the CAVALIER reactor was operated as
_ follows:
Hours Operated Watt-hours First Quarter 20.5 379.5 Second Quarter 5.0 4.5 Third Quarter 0 0 Fourth Quarter 0 0 TOTAL 25.5 384 The CAVALIER was unloaded on May 4, 1984 in order to utilize the fuel elements in the UVAR reactor, which was operating around the clock. New fuel elements were received during the fall and we presently plan to reload the CAVALIER during the month of January, 1985.
Application for renewal of the CAVALIER operating license, which .
.was due to expire on July 30, 1984, was submitted to the NRC on June 22,.
1984. Mr. R.E.-Carter of the NRC and three individuals from.Los. Alamos-Laboratories were at this facility on November 7,~ 8 and 9, 1984 to
. review our license renewal.. The review is still-in progress.
- 1.0 Rod Drop Tests
. Technical!S pecification requirements:
-magnet release ~ time < 100 milliseconds free drop time < 700 milliseconds Rod position .
Magnet Release. Free Drop Total Drop-
' ; D:th .: , Rod inches) Voltage Time :(msec) . Time (msec) -(msec) ~
12-23-84L c1 26 35. 97 .470- 567:
2 26 35 33 438 471'
, 3- 26 35 :77- 528 605~
41 .26 - 35 92 .451 543 1Thf rcd drop; times will'be re-measured when the CAVALIER. reactor. is reloaded and prior
- to achieving criticality.-
~2.0 Maintenance a) The-followingimaintenance was performed on the CAVALIER system during the calendar year 1984.
. 19-20-84 !Replacediali coaxial? cables ~and most, module ~and drawer connectors on source range #1l& #2 channels and Log N
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channel. 'Also installed drawer. slides on these systems.-
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10-30-84' High voltage 1ow on radiation area monitor #2 (demineralizer
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pit). Replaced all filter capacitors and checked out system.
.11-1-84 Irratic indication and constant 5 second period on Source Range #1. Replaced oscillator module and pulse amplifier and connector. System calibration o.k.
b) During the calendar year 1984 make-up water to the
. CAVALIER tank averaged approximately 2.5 gallons / day.
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3.0 Operating Procedures Section 12 on Emergency Procedures was revised and expanded in
- January, 1984.
An 4.0 Surveillance Requirements
.The following tests and calibrations were performed on the CAVALIER
' system during the calendar year 1984.
a).The following tests were conducted at intervals not exceeding six months.
. 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.
All of these tests and calibrations were within limits-required by the Technical Specifications, b) Flow tests of the ARIS system were performed as follows:
Date Time to empty tank 5-24-84 32 seconds-11-28-84 -30 seconds
.These tests were well within-the required time of approximately one minute.
c) Control rod calibratiens will be performed when the CAVALIER-is reloaded.
d) The daily checklist which is. completed when.the reactor is to
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be operated,-provides for_ checks onfall:of'the' required-
- scram systems associated _with the reactor.<
Data on all of.these tests and calibrations is-on filecat the facility, m
5.0 Unplanned' Shutdowns
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The-following unplanned sshutdowns occurred on the CAVALIER ireactor-during;the! calendar year 1984.
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- 1-9-841 . ' scram - noise in console.
1-10-84~ .3 ' scrams .- noise 1Ln console.
'l-11-84: : scram Jelectronic noise.:
'l-12-84 .high'. power scram'at'approximately 57 watts when
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leveling off.
?1-13-84 scram - noiseiin console
'. 3-28-84. .high nower'scramLat approximately 58 watts when leveling
- off.
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10 C. Health Physics a) Atmospheric Release The following effluent was released to the atmosphere during the calendar year 1984 as a result of reactor operation.
41 Ar 8.19 curies based on conservative calculations.
.b) Solid Waste During.the calendar year 1984 approximately 61 cubic feet of solid waste was shipped from the Reactor Facility by Teledyne Inc. The activity of the waste was as follows:
Isotope Activity (millicuries)
Na 0.007 Na 0.017 56 Mn 0.40 59 Fe 0.022-Co 0.006 60 Co 0.022 65 Zn 0.013 131 I 0.001 1
Cs 0.006 TOTAL' O.494 millicuries c) Liquid Waste Liquid waste from .the re' generation of - the demineralizer system?
r was released.during the year and diluted with water from the hold-up pond.-
Activity (uci) Volume-(gallons)-
First-Quarter. 559.24 4,468,190 Second: Quarter 1061 06 5,016,100
' Third' Quarter' 442.20 1,170,900
~ Fourth Quarter 101.44 2,235,140
- TOTAL .2163.94 12,890,330'
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, :The average l specific activity released was 4.4:x 10 ci/ml.
Samples of the waste tank water and.the hold-up-pond were analyzed
~ independently by " Controls for Environmental Polution Inc." of Santa Fe,-
New Mexico. They performed an~ isotopic analysis'forflodine-129,-
Radium-226'a'nd Radium-228.':The_ analysis ~showed'these isotopes to be _ ;
-below their minimum limits =of detectability'as follows:- s
- -Tank WaterJand Pond Water _- Iodine-- 129 --< l~x 10 ':pci/ml-
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Ra'dium' 226 . <i0.6 x'10 uci/ml
. Radium - 228 < 1.x 10 -9 pei/mi ~
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-based on this analysis and the provisions of 10 CFR part 20, note t 7
appendix B, table C the MPC for our liquid effluent release is 1x10 pci/ml.
3.0 Personnel Monitoring During the calendar year 1984 approximately 150 personnel including faculty, staff and students were monitored by film badges supplied by the R.S. Landauer Company. The highest exposures were to five staff members directly involved with the operation of the facility and the handling of samples used in activation analysis.
Whole Body Dose (as of 10-31-84) Extremity Dose Individual A 420 mrem 30 mrem Individual B 330 mrem 410 mrem Individual C 330 mrem 1170 mrem Individual D 280 mrem 1600 mrem Individual E 150 mrem 1700 mrem During the year the facility had 2266 visitors. These visitors were monitored with direct reading dosimeters and received no significant exposure.
D. Miscellaneous
- 1) Formal. meetings of the Reactor Safety Committee were held on the following dates:
February 24, 1984 October 26, 1984 April 30, 1984 December 12, 1984 May 21,-1984 December 19, 1984 July 25, 1984 A subcommittee of the Reactor Safety Committee performed audits of the facility operations during the months of January, May and September 1984,
- 2) a. An NRC inspector visited'the facility on October 1st, 2nd,~3rd 1984 to inspect our Radiological Safety Program._ Several:
apparent violations were found. As a result of this inspection an Enforcement Conference was held'at'this facility on October 22, 1984. As of this'date we have had no formal report on:either the inspection.or the Enforcement Conference.
- b. An'ANI Insurance Inspector visited our facility-on December 17, 1984.
- 3) a. A revised Emergency Plan for this facility was submitted to the NRC on July 12, 1984. The plan was approved effective October.
-3, 1984.. An extension period to have effective implementing
. procedures in place was requested and granted. The deadline for these implementing procedures is April 3, 1985. The procedures are being written and.we expect to have them reviewed and approved by our Reactor Safety Committee.before this date.
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- b. 1) An evacuation drill of the facility was held on October 10, 1984.
- 2) An emergency drill that involved a simulated accident with two injured and contaminated victims was held on November 8, 1984. The drill involved the reactor staff, Health Physics Personnel, the University Police, the Local Rescue Squad and the University Hospital Emergency Room. The Hospital initiated their Radiation Emergency Plan when notified of the " accident" and the " victims" were transported to the emergency room by the local rescue squad, assisted by the U.Va. Police. the NRC office at Region II in Atlanta was notified in advance of the drill and they sent three NRC personnel from the North Anna Power Plant to observe.
- 4) A new pneumatic rabbit system was installed in the UVAR reactor and a pneumatic transfer system for transporting samples from-the reactor. room to the counting room was put into operation during the year. These systems were reviewed and approved by the Reactor Safety Committee.
L 5)' a) Twenty four spent fuel elements were shipped to Savannah River
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for reprocessing on June 4, 1984 and June 8, 1984..
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b) Twenty seven new fuel elements.were received during the year:
'from'the Babcock 1and Wilcox Company. JThese elements were fabricated by Atomics International and were shipped to B&W
'when they took over the aluminum fuel-element business.
s E.. Personnel
~ 1) Dr. J.S. Brenizer resigned'as Director.of the Reactor Facility on June 30,-1984. Dr. R.U. Mulder became Director effective
- July 1,1984.
12)_ Reactor Operator exams were given during the month of April,.
1984_and resulted in~ licensing of three' reactor. operators.E s
- 3) The Environmental Health and Safety office assigned Mr. .J.E.
-Henderson asiHealth Physicist for the Reactor _ Facility on-May 1, 1984. _He is assisted by a full time health physics technician.
1This report h' Ias been reviewed and approved by = the Reactor Safety .
Committee.-
Sincerely, l' ,
Farrar, Reactor Supervisor-.
'J.P.
LU.Va. Reactor l Facility cc: Office of Inspection and Enforcement f Region IIL 1
}
Atlanta,' Georgia-
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