ML20203M773

Forwards Progress Rept for Univ of Missouri-Rolla Nuclear Reactor Facility, Apr 1985 - Mar 1986

ML20203M773
Person / Time
Site:	University of Missouri-Rolla
Issue date:	04/29/1986
From:	Bolon A, Straka M MISSOURI, UNIV. OF, ROLLA, MO
To:	NRC
References
NUDOCS 8605010687
Download: ML20203M773 (1)

Text

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Nuclear Reactor Facility UNIVERSITY OF MISSOURI-ROLLA Nuclear Reactor Rolla. Missoun 65401-0249 Telephone: (314) 341-4236 April 29, 1986 United States Nuclear Regulatory Comission Washington, D.C. 20545 RE: License R-79, University of Missouri-Rolla Reactor Docket No. 50123.

Dear Sirs:

The following Progress Report for the Uriiversity of Missouri-Rolla Reactor (R-79) for the period April 1,1985 to March 31, 1986, is sent for your review and inspection.

Sincerely, Albert E. Bololi Reactor Director, S0 k5 Milan Straka Reactor Manager, S0 1p Enclosure (10 copies) i l

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• I I Progress Report iI 1985-86  ;

I University of Missouri-Rolla l Nuclear Reactor Facility  !

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I I PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY I

l APRIL 1, 1985 to MARCH 31, 1986 1

,I Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla I

.I By Albert E. Bolon, Director Milan Straka, Manager Nuclear Reactor Facility I University of Missouri-Rolla Rolla, Missouri 65401 I

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i Summary During this reporting period the' University of Missouri-Rolla Reactor was in operation for 287 hours0.00332 days <br />0.0797 hours <br />4.74537e-4 weeks <br />1.092035e-4 months <br />. The major part of this time, 89%, was used for class instruction and training purposes. About 5% of the reactor time was used for research and irradiation service and 6% was needed for maintenance runs.

l There were 38 students enrolled for course work at the reactor. This com-mitted the facility to 53 student-hours of classes. The reactor was visited by more than 1500 visitors during the past year. Many of them expressed their opinion that the facility still remains the major attraction on this campus. There were about 100 participants in the Reactor Sharing Program I this year. The facility has been reimbursed for this program from a grant awarded by the Department of Energy.

The reactor produced 5 MW hours of energy using 0.26 g of uranium. A total of 106 samples have been irradiated at the reactor with most of them being analyzed in the Reactor Counting Laboratory. The request for an extension of the operating license was successful and the license has been. extended l until November 20, 1999.

Two one-week training programs for reactor operator trainees of a midwest utility were conducted during this reporting period. The reimbursement helped to defray facility costs and also helped to improve research and instructional capabilities.

Research at the reactor concentrated on trace element analysis and material irradiation. Two research projects are being performed for on-campus investi-gators and one for an off-campus investigator. A proposal to study collet-tion efficiency of man-made scavengers using the neutron activation analysis I received funding from the Weldon Spring Endowment Committee. Another propo-sal is being prepared in order to obtain funds for the reactor fuel conversion.

A paper on the calculation of radioactive contaminant dispersion was pre-sented by one staff member at the ASME Annual Meeting for 1985.

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ii TABLE OF CONTENTS Summary i

List of Tables iii I.

Introduction.......................,..................... 1 II. License Extension.......................... ............. 1 I III.

Reactor Sta f f a nd Personne l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 A. Reactor Staff........................................ 2

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B. L i cen s ed 0p e ra to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1 i

C. Radiation Safety Committee........................... 2 D. Health Physics....................................... 3 IV. Supporting Facilities.................................... 3 Y. Improvements............................................. 4 VI. Rea c to r Ope ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 A. Facility Use......................................... 4 I B.

Data...........................................

Core 16 VII. Public Relations........................................ 17 VIII. Educational Utilization................................. 17 IX. Reactor Hea l th Phys ics Act i v i ti es . . . . . . . . . . . . . . . . . . . . . . . 18 X.

Plans...................................................

I Appendices 20 I

A. Semi-Annual Checks (SOP-800).........................A-1 I ,

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I iii LIST OF TABLES

1. UMRR Core Configuration and Rack Storage Form. . . . . . . . . . . . 5

2. Use of Core Grid Plate Locations . . . . . . . . . . . . . . . . . . . . . . . . . 6 I 3.

4 Faci li ty Use Other Than the Reactor. . . . . . . . . . . . . . . . . . . . . .

Rea c to r U t i l i za t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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5.a. Rundowns.................................................

I 5.b. Scrams...................................................

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6. Maintenance.............................................. 11 7 Core Loading and Unloading............................... 15

8. Co re Tec h n i c a l Da t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 I

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1 Research Equipment Needs of the UMR Reactor Facility l

( i n ' 86 d o l l a rs ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3

10. Instructional Equipment Needs of the UMR Reactor Facility (in '86 dollars)................................ 21 I

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1 I I. Introduction l l

I l This progress report is prepared in accordance with the requirements of the Nuclear Regulatory Commission 10 CFR 50.71 concerning the operation of the University of Missouri-Rolla Nuclear Reactor Facility (License R-79).

I The reactor, a swimming pool-type, is operated as a university facility available to the faculty and students of the various departments of the university for their educational and research programs. Several  ;

other universities and colleges have made use of the facility during this reporting period. The facility is also made available for the l

purpose of training reactor personnel for the nuclear industry and electric utilities.

I The reactor staff has continued to review the operation of the Reactor I Facility in an effort to improve the safety and efficiency of its operation and to provide conditions conducive to its utilization by students and faculty from this and other universities. The following i

sections of tais report are intended to provide a brief description of the various aspects of the operation of this facility, including its utilization for education and research.

I II. License Extension The effort to extend the operating license beyond November 20, 1989, was a successful one. On April 16, 1985, the NRC extended the license until November 20, 1999.

Contents of the license and technical specifications have not been changed.

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I III. Reactor Staff and Personnel A. Reactor Staff Name Title Albert E. Bolon Director Milan Straka Reactor Manager Carl Barton Senior Electronic Technician Juls Williams Lab Mechanic Francis Jones Reactor Maintenance Engineer Gail Frenchl ) Senior Secretary B. Licensed Operators Name License Albert E. Bolon Senior Operator Carl Barton Senior Operator l

Milan Straka Senior Operator Francis Jones2 ) Reactor Operator I i

1) terminated on February 14, 1986

2) effective on September 5, 1985 l

C. Radiation Safety Committee Name Department Dr. Nord L. Gale (chairman) Life Sciences I Mr. Ray Bono (secretary) (ex officio) Environmental Health and Risk Management l

Dr. Ernst Bolter Geology and Geophysics Dr. Oliver K. Manuel Chemistry Dr. Albert E. Bolon Reactor Director Dr. Nick Tsoulfanidis Radiation Safety Officer Dr. Edward Hale Physics I This committee is required to meet at three month intervals. However, in practice the frequency of the meetings is usually greater.

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3 I D. Health Physics Name Title Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Director, Environmental Health and Risk Management Mr. Darrel Holloway Health Physics Technician I

IV. Supporting Facilities Several supporting facilities are either operated or maintained by the reactor staff for users of the reactor. These greatly contribute to the efficiency of research and educational programs available to the faculty and students of the University of Missouri-Rolla, as well as other universities.

I Activation Analysis Laboratory: The activation analysis laboratory has l

proven to be the most-utilized supporting facility. The laboratory I contains a 4096 channel analyzer, with Nal or GeLi selectable detector input. Included in the auxiliary equipment is a tape punch, multi-scaler programmer, a scope camera, and a teletype terminal. Three scalers are included in the laboratory equipment with the appropriate detectors for '

counting alpha, beta, and gamma radiation. A shielded detector with  !

four ton low-background lead shield housing two "3x3" sodium iodide I crystals, is also available for coincidence counting. These detectors are used in conjunction with the multi-channel analyzer. Several other units of equipment are available for the detection and evaluation of radioactive materials.

Potential suppliers of computer-based gamme-spectroscopy systems have been contacted and their products are being evaluated. It is intended to acquire a new system in the spring of 1986.

I Pneumatic Tube Assembly: A dual tube pneumatic system adjacent to the core of the reactor is used to transport the samples for irradiation.

One tube is cadmium lined, and the other is bare. This system is a positive pressure type and uses nitrogen as the propellant.

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I e I V. Improvements I A continuous effort to enhance availability and reliability of the I facility is being undertaken by the reactor staff. During this re-porting period the following improvements have been made:

1) A new solid-state /9-ammeter with a digital readout has been installed in the linear power channel.

I 2) A compensated ion chamber in the log power channel has been replaced with a new one.

I 3) Most of the Standard Operating Procedures have been trans-ferred and are now maintained on the Apple II and computer file library.

I VI. Reactor Operations A. Facility Use Table 1 depicts the current core loading which is designated as core 67.

The number 67 denotes the sixty-seventh core configuration (assembly and location), that has been used at the Reactor Facility since the original operating license was issued in 1961. This core 67 has been in use since December of 1978 and is periodically checked for all parameters listed in Table 8 (core data).

Tables 2 through 7 give pertinent information about the Reactor Facility and its operation during the reporting period. Listing of semi-annual electronic checks is included in Appendix A.

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5 Table 1. UMRR Core Configuration and Rack Storage Form DATE 31 March,1986

• LOADING NUMBER 67T or 67W R1 R2 R3 R4 R5 R6 R7 R8 R9 R10 R11 R12 R13 R14 R15 I HF-1 F-13 F-20 F-22 RACK STORAGE FACILITY I .

F-2 F-5 F-3 F-18 F-21 R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 R29 R3o KFY TO PRETIXES A

T - Standard Elements B S C - Control Elements C HR-1 F-14 F-1 C-4 HT - Half Front Element HR - Half Rear Element D F-8 C-1 F-16 F-9 F-4 F-10 S - Source Holder g F-6 C-2 F-19 C-3 F-12 F-11 7 BRT F-17 F-15 F-7 CRT I 1 2 BRIDGE SIDE 3 a s r, 7 8 UMRR CORE STATUS 9

Other BRT- Bare Rabbit Tube CRT- Cadmium Rabbit Tube l

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• T designates the thermal column-reflected mode, I and W designates the water-reflected mode.

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USE OF CORE GRID PLATE LOCATIONS I 'cu" A8

"-e 0.067 B3 0.050 84 1.417 88 0.100 C2 0.117 I C3 C4 0.200 0.133 C5 0.250 C7 4.367 C8 0.117 3 02 0.133 05 0.083 D6 1.067 07 0.067 08 0.050 09 0,117

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E2 0.033 E3 0.067 ES 0.233 E7 0.117 E8 0.067 E9 0.100 I

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7 I Table 3.

FACILITY USE OTHER THAN THE REACTOR I Facility Bare Rabbit Tube Hours 8.900 Beam Port 7.050 Reactor Console 266.505 I Total 282.455 I

Table 4.

REACTOR UTILIZATION I Reactor use 287 hr '

l Research & Irradiation runs 13 hr Instruction runs 255 hr i Maintenance runs 19 hr Time at power 127 hr Heat generated 5016.73 kw-br Total number of samples 106 Sample hours 18 hr Research & Instruction usageII) 12.9 %

U-235 burned 0.218 g U-235 burned and converted 0.259 g l (II 8ased on 2080 working hours per year.

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I Table Sa. l RUNDOWNS pate Time cause I 05-09-85 1012 (120% demand) Student operator was switching from higher scale to lower scale on pp-ammeter. Student instructed to be more careful.

06-28-85 1422 (120% demand) While switching scales on linear  !

(pp-ammeter). l 07-24-85 1355 (120% demand) Rundown due to operator error.

Scale was not changed on linear. Cautioned operator and instructed on changing scales.

1 08-02-85 0952 Less than 15 second rundown due to moving detector I (CIC) too quickly during adjustment. Cautioned personnel in the procedure of moving the CIC.

08-14-85 I 1025 (120% demand) Rundown due to switching scale on linear too soon.

1 08-14-85 1046 (120% demand) Rundown due to linear being switched I on too soon on down scale and power. Cautioned operator.

08-29-85 1033 (120% demand) Rundown due to operator error in selection range button on linear. (New system) 08-29-85 1118 (120% demand) Rundown - operator was checking pcsition for down scaling linear system.

09-19-85 0956 (120% demand) Rundown - operater pushed wrong button on linear. Cautioned operator.

09-19-85 1025 (120% demand) Rundown - operator changed scales I too soon on linear. Reactor was on negative period while on down power. Cautioned operator.

09-19-85 1118 I (120% demand) Rundown - operator error pushing the wrong button on linear. Gave operator further instructions.

I 11-19-85 0901 (120% demand) Rundown - linear scaling increased when scales were changed.

11-19-85 1226 High Radiation Rundown. Demineralizer RAM was not set for power run. Reset RAM.

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RUNDOWNS Date Time Cause 11-26-85 1232 (120% demand) Rundown - switched scales on linear too soon.

12-11-85 1415 High Radiation Rundown. Nitrogen Diffuser not turned on. Turned Nitrogen Diffuser number 1 and I 2 on. Instructed operator on running without Nitrogen Diffuser.

01-22-86 1428 (120% demand) Rundown due to switching linear.

I Cautioned operator on switching scales.

01-24-86 0921 5 second period scram due to noise on Lac N and period channel.

02-05-86 0952 High Radiation rundown from bridge. No radiation detected using Eberline E-120.

C2-18-86 1125 15 second rundown.

02-18-86 1128 15 second rundown.

03-04-86 1506 (120% demand) Rundown.

03-05-86 1525 (120% demand) Rundown occuring simultaneous with changing scales on linear channel.

03-07-86 1109 (120% demand) Rundown.

03-07-86 1535 (120% demand) Rundown - operator switched scales too soon.

03-11-86 0944 (120% demand) Rundown - spurious spike in linear channel.

03-11-86 1615 (120% demand) Rundown - spurious spike in linear channel.

I 03-25-86 1315 (120% demand) Rundown when switching scales on linear.

03-25-86 1326 (120% demand) Rundown when switching scales on linear.

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SCRAMS l l

pate Time Cause 1

12-04-85 1438 Reactor scrammed due tc power spike on Log N Channel: Checked 15 second rundown, 5 second scram,150% full power scram and all connections to Log N system.

I 01-10-86 1313 150% full power scram:

Trip circuits.

Checked Safety Amplifier 01-24-86 0921 5 second spurious scram: Checked Log N and Period I Amplifier. l 01-30-86 0919 150% full power and 5 second spurious scram:

I Checked Log N and period system and linear system with current source.

02-06-86 112 150% full power and 5 second spurious scram:

Checked Log N and period channel trip circuits.

02-06-86 1531 150% and 5 second spurious scram: Spurious spike on period channel: Checked Log N power supply.

02-07-86 1441 150% full power and 5 second spurious scram:

I Checked safety amplifier and Lcg N connectors on bridge.

I 02-11-86 0949 150% and 5 second period spurious scram: Replaced relays in Log N amplifier.

02-19-86 1030 150% fui1 power and 5 second spurious scram:

Removed and replaced Log N Compensated Ion Chamber.

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11 Table 6.

MAINTENANCE Date Time Event I 04-8-85 0901 Period trip test would not operate properly.

Checked switch, moved wires and cculd not duplicate problem.

04-08-85 0904 Log Count Rate indicated less than 2 cps during I weekly check. Checked all connections on LCR system. Could not duplicate problem.

04-16-85 1320 Linear noisy. Replaced V-3, V-4 and R-123:

checked calibratTBn.

04-29-85 1421 Period trip test switch not functioning properly.

Cleaned and rebuilt switch.

05-09-85 1115 Linear noisy. gangedsignalcablesandcleaned ground wiper contact on switch.

05-09-85 1140 Magnet current switch intermitant. Cleaned switch.

05-16-85 1155 Regulation Rod withdraws instead of inserting as it should when put in auto. Changed P.A.T. 60 controller. i 1

06-03-85 1035 Same as May 16.

06-13-85 1625 Magnet No. 1 not raising rod. Replaced magnet No. I coil with spare coil.

I 07-01-85 0951 Period trip test not functioning prcperly.

Cleaned contacts on switch and test control.

07-09-85 1200 Replaced cable from fission chamber to preamp with low noise cable.

08-23-85 1500 Fission chamber being replaced.

08-26-85 0800 Started replacing linear amp (Keithley 410) with Keithley 485 pico-ammeter.

08-27-85 0930 Completed replacing pico-ammeter.

08-30-85 0930 Changed fissien chamber because of noise on channel.

11-06-85 1430 Magnet No. I not operating properly.

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MAINTENANCE Date Time Event 11-13-85 0736 Magnet No. I repaired and installed.

I 01-13-86 1330 Magnet No.1 not operating properly.

Magnet No. 1.

Removed Magnet No. 1 repaired and installed.

I 01-16-86 01-24-86 0945 1630 Checking noise in Log N and Period noise.

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l 01-27-86 1630 Resoldered connections on 10kc oscillator board.

01-29-86 1530 Complete check of Log N and Period amp. Checks satisfactory.

l 01-30-86 0945 - Checking possible causes for spurious scrams.

1200 Replaced V4 in Safety Amp.

01-30-86 1622 Replaced K31 and all 4 withdraw relays.

02-05-86 1046 Checked possible reasons for bridge RAM reading and increase when regulation rod is withdrawn and inserted. l 02-06-86 0856 Changed bridge RAM detector. l 02-06-86 I Checked period channel and adjusted trips.

1230 02-07-86 0800 Checked Log N Power supply. Changed V4, V7, and V8. Resoldered R2.

02-10-86 0800 Changed V9, V10, V11, and V12 in the safety amp.

Checked connector to Log N CIC on the bridge.

02-10-86 1535 Replaced Log N CIC.

02-11-86 1330 Checked Log N Channel. Ordered .elays K-11, K-21 and add-on relay.

02-12-86 1300 Replaced relays K-11,.K-21 and add-on relay in I Log N amp. Checked connectors on Print Circuit cards.

02-13-86 0845 Checked Log N system with current source from bridge.

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l Table 6. (continued) l MAlhTENANCE Date Time Event 02-17-86 0755 Replaced transistors in regulated power supply.

02-17-86 1605 Checked Log N and Period printed circuit boards.

02-18-86 1225 Checked Safety Amp. Resoldered two broken wires.

Safety Amp aligned.

02-19-86 1100 Removed CIC from pool.

02-19-86 1700 CIC reinstalled in pool.

02-23-86 1613 Disconnected CIC.

02-24-86 0800 Removed CIC from pool.

02-26-86 0900 Checked tubes in Log N Power Supply. Changed V9.

02-26-86 1530 Checked tubes in Safety Amp. Replaced VII and V12.

02-26-86 1800 Replaced K15 in Safety Amp.

C2-27-86 1400 Replaced V8 and V9 in Safety Amp.

02-27-86 Readjusted R84.

I 1600 02-27-86 1615  !

Replaced V15 in preamp.

I 02-28-86 1140 Removed Log N CIC from pool. Replaced cables and connectors on CIC. )

l 03-01-86 1430 Reinstalled Log N CIC in pool.

03-03-86 1130 Removed Log N CIC and checked cables.

03-03-86 1210 Reinstalled Log N CIC. Still no spike on channel.

03-03-86 1330 Removed Log N CIC from pool.

03-03-86 1345 Reinstalled different CIC.

03-03-85 1500 Checked and readjusted Log N amplifier. 1 03-20-86 1130 Removed Magnet No. I from pool.

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MAINTENANCE Date Time Event 03-21-86 1530 Replaced Magnet No. 1 in pool.

03-21-86 1615 Removed Magnet No. I from pool due to short.

03-24-86 1100 Replaced Magnet No. 1 in pool.

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CORE LOADING AND UNLOADING

• Date 4-03-85 UL (67W to subcrit) to determine Reactivity worth of core.

4-03-85 RL (subcrit to 67W) reload to previous configuration.

6-10-85 UL (67W to subcrit) control rod inspection.

6-13-85 RL (subcrit to 67W) return to previous configuration.

• UL - Unload RL - Reload I

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8. Core Data I During this reporting period only one core designation has been used.

The "W" mode core was used for nomal reactor operations, since students are not supposed to operate the reactor when the excess reactivity is above 0.7%. The "T" mode is used for extended operation (>3 hrs), or beam port and themal column experiments.

I measured for cold, clean critical conditions.

The excess reactivity was In day-to-day operation the excess reactivity is quite often lower due to the temperature increase of the pool.

Table 8. Core Technical Data Average Themal Flux 1.6X10 12 2 n/cm -sec at 200 kW Maximum Themal Flux 2.8X10 12 n/cm2 -sec at 200 kW Average Epithermal Flux 1.6X10 ll 2 n/cm -sec at 200 kW Worth of Themal Column 0.46%

Worth of Beam Port not detectable Rod Worth (in "T" mode)

Date 4-16-79 4-16-79 4-16-79 10-10-83 I 2.64% II 2.65% III 3.36% Reg. 0.347%

Excess Reactivity (in "T" mode) 0.73% Shutdown Margin (in "T" mode) 4.56%.

Void Coefficient -7.7X10-7 /cm Date 10-30-84 Temperature Coefficient -1.3X10'4 o/ F Date 11-20-84 Reactivity Addition Rate (max %aK/K/sec)

I I 0.019 II 0.019 III 0.026 Reg. 0.01 Rod Drop Time (24")

I 480 msec, II 465 msec, III 485 msec, C'te 13-1-86 ss '

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VII. Public Relations The reactor staff continues to help educate the public about the app ication of nuclear energy. Over 1,800 persons toured the facility during this report period. Tour groups are usually given a brief- 3 orientation by a member of the reactor staff. "

Some of the groups spent an entire day at the facility becoming ac-quainted with the reactor and performing simple experiments. Usually these groups are from colleges which have no reactor facilities.

VIII. Educational Utilization I Thirty-eight UMR students, graduates and undergr2duates, have partici-pated in classes at the facility, utilizing 53 student-semester hours of allocated time. Also students from several colleges, and high schools have used the facility.

5, The following is a list of scheduled classes at the facility alor:g with  ;

the total hours of reactor use for this reporting period. 'f Course Title Reactor Students Hours NE 2 Introduction to Nuclear Engr. II 7 2.9 NE 304 Reactor Laboratory I 12 38.7 NE 306 Reactor Operationi 10 69.4 NE 308 Reactor Laboratory II 9 28.S The current enrollment in Nuclear Engineering is 58 students.

s A program called Reactor Sharing Program, funded by the Department of Energy, was established for colleges and universities which do not own a nuclear reactor. About 100 students and their instructors participated in this program.

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I 18 IX. Reactor Health Physics Activities The Health Physics activities at the UMR Reactor Facility consist primarily of radiation and contamination surveys, monitoring of per-sonnel exposures, airborne activity, pool water activity and waste I

disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, Health Physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and moni-toring of non-routine procedures. New Health Physics S0P's have been written and implemented.

Routine Surveys Monthly radiation surveys of the facility consist of direct gamma and I neutron measurements with the reactor at power. No unusual exposure rates were found. Monthly surface contamination surveys consist of 20 to 30 swipes counted separately for alpha, beta and gamma activity. In 12 monthly surveys, no significant contamination outside of contained work areas was found.

By-Product Material Release Surveys During the period, there were no shipments of by-product material d

released from the reactor facility.

Routine Monitoring Twenty-eight reactor facility personnel and students frequently involved with operations in the reactor facility are currently assigned beta-gamma, neutron film badges which ara read twice each month. There are 4 beta-gamma, neutron area badges assigned and one test badge to check accuracy of exposure reports. Twenty-two campus personnel and students are I assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 19 beta-gamma area and spare badges assigned on campus. In addition, 4-7 direct-reading dosi-meters are used for visitors and high radiation area work. There have been no personnel over exposures during the period.

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19 Airborne activity in the reactor facility is constantly monitored by a fixed-filter, particulate continuous air monitor (CAM) located in thC reactor bay. Argon-41 is routinely detected during operations.

Pool water activity is monitored monthly to insure tAat no gross pool I contamination nor fuel cladding rupture has occurei. Gross counts and spectra of long-lived gamma activity are compared to previous monthly counts. From April through March sample concentrations averaged 1.94x10-6 uCi/ml. ~

Waste Disposal Release of gaseous and particulate activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously _ measured air activity at maximum reactor power. During this period 46.89 millicuries were released into the air. Released isotopes were identified as Ar-41.

Solid waste, including used water filters, used resins and contaminated paper is stored and/or transferred to the< campus waste storage area for later shipment to a commercial burial site. Radioactive waste released to the sanitary sewer is primarily from regeneration of the resin exchange column. During this period 7 releases to the sanitary sewer totaling approximately 3255 gallons of concentrated resin regeneration solution and pool water were discharged wi.th' a total activity of 0.020 millicuries. No peaks Were identified during the analysis.

Instrument calibrations During this period, portable instruments were calibrated four times.

Remote area monitors were checked for calibration four times.

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y X. Plans h

The reactor management continues their efforts to upgrade the facility's p research capability. Extra efforts have been made to inform academic E department chairmen and research center directors of the current availability of the reactor and the various associated counting systems.

Attempts have also been made to inform the individual faculty members /

researchers, who we believe might be doing research that could utilize 1

the UMR Reactor, that we would be pleased to cooperate with them.

A six-member Reactor Research Advisory Committee has been established to assist the reactor management with ideas for research. The purpose

{ of the committee is to have a knowledgeable group of faculty /reasearchers who would advise the reactor staff regarding areas of potential research and regarding equipment needed in order to develop proper research capability.

A five-year research plan for the Reactor Facility was prepared by the m

Reactor Director and submitted to the Dean in 1985. In order to develop m

a quality research program at the UMR Reactor over the next five years, financial support in the amount of $418,900 would be needed. By the end of the five-year period there would be a research staff of four half-time graduate research assistants, one post-doctoral fellow, and one senior researcher in addition to the present number of operational

. staff. If properly done, some of the funding could be provided by external sources.

The specific research equipment needs of the Reactor Facility are listed in Table 9.

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I 21 Table 9. Research Equipment Needs Of the UMR Reactor Farility (in '86 dollars)

Item Estimated Cost Intrinsic Germanium Detector $10,000 I Microcomputer-based Multichannel Analyzer Isotope Identification Package 16,500 3,000 Printer / Plotter 2,000 Total $31,500 The instructional equipment needs are shown in Table 10.

I Table 10. Instructional Equipment Needs Of the UMR Reactor Facility (in '86 dollars)

Item Estimated Cost Intrinsic Germanium Detector $10,000 Canberra Series 85* Multichannel Analyzer 9,400 Daisey Wheel Printer 1,000 Digital Pulse Generator I Curve Tracer 1,800 700 X-Y Plotter 1,960 X-Y Plotter Interface 460 Eberline Rascal

• Neutron Meter 3,000 Air Sampler 1,200

• or equivalent i-

22 I in conclusion, for a reasonable sum of money the UMR Reactor could be developed into a viable research facility which could benefit the mid-west region of the nation. By the end of the S-year program the research staff would be built up to a level so that they could be self-supporting on research grants and contracts.

I In particular, it would enhance the neutron activation analysis capability of the UMR Reactor Facility if the present pneumatic transfer system were to be modified so that samples could be transferred directly from the core to the Ge(Li) detector. Likewise, it would be beneficial to have an automatic sample handling system so that a large number of samples could be inserted into the Ge(Li) detector and counted. We would also like to develop prompt neutron activation analysis capabilities. The hardware necessary for the suggested improvements would be requested on research proposals prepared by the reactor staff or in cooperation I with other researchers.

The U.S. Department of Energy supports the UMR Reactor through the University Reactor Sharing Program. We received $12,000 financial support this year. Several grcups from Linn Technical Institute have come or will come to campus for a day each. The University of Arkansas j sent four graduate students and a faculty member for two days in March. l Other schools are expected to use the reactor for education or research l before the end of the contract in August. We hope to be selected for I an extension of that program.

Reactor management's plan to have at least three licensed senior operators has been accomplished. In addition, another staff member has his reactor operator's license and plans to take the S0 examination early this summer.

In terms of modifications to the facility which are planned, they include several which have been mentioned in prior Progress Reports. We do plan to install the new solid-state magnet power supply, linear power channel I and solid-state power range (safety) channels that were purchased several years ago and not installed because we were in the midst of re-licensing. Without a doubt, the solid-state devices should be more reliable than the present vacuum tube ones, which were original equipment.

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!I APPENDIX A Semi-Annual Checks (SOP-800) !

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a enggt: 0 t)l J Semi Annual Check List Date Comenced 1]EC le IE Date Completed JAN D 1986 Total Hours on llour Meter Q#g 27

1. Log ti and Period Channel initial I a. tiog N Power Supply DEC 2 01986 DEC 3 01986 (1) Cleaned chassis (2) Tested all vacuum tubes

((/[

Replaced: tube #

df//f3 f tube type I llids I

I I b. Log N Recorder (1) Cleaned chassis Date DEC 2 0 !965 DEC 3 0195F, dfg I (2) Tested all vacuum tubes Replaced: tube # tube type /b/ff/}

$2? ?

I I c. Neutron Detector Check Resistance (ohms) Capacitance (pf)

I (1) Signal to ground (2) Prs tive to ground ft // y a '

• _ //,3 9 o.f [k///

(3) Neg'tive to ground

/g ,X /O

//) , ](N

/2/[ M h ///)

/ /9_I y,(- [////,J) l l

..._,s. .s,. ,

d. Log N Calibration Date OEC 18 985 1 Initial 1 Me ter Recorder Keithley l 100 /d & SA/D 10

/8 gf/3'd' ffQ \

1 l

[#fJg

$X/S 0 Pf/ 8 \

0.1 ,/ ^

4~X/b /?f/J/3

.01 ,0/ $1/i (I/7&

I .001

.0001 474 /

,6DD/

8Ir/[ #

fX fn '

~

/76

/IP/1/3 I Reconnection of Cables Verified Note:

The ratio of true-to-observed readings should be between 0.7 and 1.4 F3 l

e. Period Recorder Date DEC 2 0 M5 (1) Cleaned chassis (2) Tested all vacuum tubes

[tM '

Replaced;

/f//d tube # tube type

,L]h LIE I

2. Linear Power Channel i

a. Linear Power Supply JAN Date L 1986 '

(1) Cleaned chassis l

(2) Tested all vacuum tubes 6t#[

Replaced: /////d tube # tube type I

l} Ol I /~

I l

L F

u

,,- w ,- ,e - - ---,--n,,- -- -

7-,,- *-g w

I b. Linear Recorder Date DEC 2 015 (1) Cleaned chassis (2) Tested all vacuum tubes 8/fe/3 Replaced:

84EfM tube # tube type I

I

c. Micro-Micro Ammeter (Spare) Date /

(1) Cleaned chassis /

(2) Tested all vacuum tubes Replaced: tube # tube type

{

J .? G- -

1 // w l /v //'1 I

1

d. Linear fleutron Detector Check l Resistance (ohms) Capacitance (pf)

(1) Signal to ground 9,/ y/g a (2) Positive to ground

/a)4 4 /@///)

(3) Negative to ground

/,fy,) l

/. J'yff '#

_ / l} .q 9 '_o [ h(fl/h

/ / O '/ ,, -f.

[iW'N )

e. Micro-Micro Ammeter replacement (1) Remove Micro-Micro Ammeter fr m .ons le a J replace with spare (2) Reconnection of cables verified Ol'I ' I- _ b//O lild ra - Msc r o h'es.nwT v (Ibb ~- Tye. ) l'm b" "

c p l oad b ., s.,r,1 ;T a a.

Note:

Any instrument found to be out of calibration should be realigned in accordance with procedures.

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(Linear Cont. ) Record af ter step e. (1) has been performed (1) Keithley Meter Recorder Initidl 5 kYb~ ' faGDI l S* 3 Ovl?03 j

l sexW? . o ts o io ow3 g br66Yb , 'l9 /O 8'/fdT I / A j' k $$Y10~

/, d a

, C6 /

/A/

$/

(09W

' /////70 I ieA10-7 5 $ x10~0

,ogg

.e50/

iso 5a O&nis Op)?f'3 l $10~0 ft), p 2 lb / //////T

$ Lk 10~0 /,aR Cd, 5 (dy)yf3 l S kO~ /, gp // /)d,f ///fpf3

,f 10~'O ,.(D76 Cd {&yjf3

/ 10~'O ,/b2 I

)/)

f4f /0

g. Reconnect all cables Reconnection of cables verified

[l///f3 Pd Note: From 10* to 104 the overall accuracy should be better than 2% of full scale. From 3x10~9 to 3x10-10 the overall accuracy should be better than 4%.

3. Log Count Rate Channel Initial I

I d. Log Count Rate Recorder (1) Cleaned chassis Ddte CEC ;. i . ,;

(2) Tested all vacuum tubes DEC 3 01986 88[ i Replaced:

g.fgg  !

tube # tube type I poin I

b. Fission Preamp Date ' I.'iTJ (1) Cleaned cnassis and inspected 6/1/3

.of ., v . s

b. Fission Preamp (cont.)

(2) Additional Comments I c. Log Count Rate Channel Date OEC P a Pg:,

(1) Pulse Generator

• Meter Recorder Initial 10 3 $ 0$$b i

100 10 * /)

• h//Y 1.000 && /b * /$#fff$

lB*W / L) "

l 10.000 Reconnection of cables verified

/.Ylflh F3 Note: All readings should give .7 to 1.4 ratio of true-to-observed readings I

4. Safety Channels l

a. Safety Preamp Date M i ho I

(1) Cleaned chassis

//[]

(2) Tested all vacuum tubes Replaced:

/ I///3 tube # tube type l /

IJMF

b. Neutron Detector #1 Resistance (1) Signal to ground j, ,5 'yf/3 (2) Positive to ground /, y)cfo'2

[88 f?/f(56 (3) Additional Comments

c. Neutron Detector # 2 Resistance (1) Signal to ground /3 V/d 'l (2) Positive to ground / yfg ' T II7///3 gf/jp s' (3) Additional Comments

e om, o o, ,

4 Safety Channels (cont.)

Initial

d. Safety Amplifier Date DEC 31 1986 (1) Cleaned chassis 9

./ /Y 7 J (2) Tested alI vacuum tubes

[pff/3 Replaced: tube # tube type I

hhl$ -

e. Safety Amplifier Adjustments JAN 3 Baro

f. Replace all cables to safety amplifier

// /

Reconnection of cables verified

/k/

5. PAT 60 Controller

a. PAT 60 Date DEC 3 { jgg (1) Cleaned chassis (2) Tested all vacuum tubes

/1Q/2/

Mj@-

b. Check dial settings and record the following (1) Approach 6D

///h I (2) Proportional Bond /, C (3) Rate Time ,OJ'

[@j//

((ff/[p (4) Reset S 0(//,ff (5) Gain (if applicable) / /// /0[/// )

6. Temperature Recorder MN Date 8 1986

a. Reading # Thermometer Recorder 1 80*F g.O 2 80"F gggj gb ggj,, 5 3 80 F f/ ggf 1 140*F i /f$ ffj']>

/

2 3

140 F 140 F

/ ff / gg'

/ {/ [f',r Note: All readings should be ! I"F

Page 7 of 9 l 6 Temperature Recorder (cont.) Date JAN 8M initial

b. 135 F Interlock Trip Point O&ffg

/3 S' l 7 Regulated Power Supply Date

a. Cleaned chassis b.

Ofd Additional comments

8. Conductivity Bridge Date JAN 3 W6

a. Cleaned chassis b.

gf[

Additional comments

9. Relay Test Date JAN 2

' in

a. Console relays tested and replaced as per SOP 815

b. Relays Replaced , 3 ., , 1 f

/f//

{/ () jV L-h'f)/0

/

10 Rod Indicator Calibration Date JAN 3 1986 l i

Actual Height 1. II. Ill. Reg. /'pyjg_}

1"

/ / ) /

6" f g $ (,

e

, , a , e ,,

18" 19 )@ f.V /

24" . ;y 2// pt/ y

- - _ . , . , - - . , . , - - . _ _ , . - , .__-_s,y,g..._. _ge--, _-_% -.__,.,,,,~,,,._------._,.y3,_._.,___%.,, , . . . , , _..-,,,,,+,-,,,,m*,._----y_f,___..,om,,eywqst---w--geww-pMe- ep -

l t'oge u or :s

11. Fire Alarm Check Date JAN "'< 1986 Initial

a. Cleaned system containers g*l//d

b. Changed batteries dvd

c. Checked pull stations d.

O/ M Checked heat detectors

e. Checked smoke d?tectors 8//Jd All indicator 8Mfh

f. imps operate

[/17 i

12. Security System s ack Date JAN , ;qgg

a. Door Sensors

/bf1/3 OM

b. Motion Detectors

c. Duress Alarm d.

[A//4h Control Modules (at UMR Police office) Date J4N ', c .,

(1) Power Supply

_ M7/[

(2) Control Module gpffd

13. Public Address System Date gn; e.

luog; (1) Cleaned chassis (2) Additional Comments

[lfP 14 Area Radiation Monitor Date E (1) Cleaned chassis ((y)'

(2) Additional Comments I

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^

r.noe v or 9 M

Date < [

'r)

U' I have any reviewed problems the results and/or errors of this Semi-Annual with the operating staff. Check on this date and disc I

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@k4Rw Utrector or 0ti%l Reactor Fanager I I I i I

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Page 1 of 9 Semi Annual Check List Date Comenced 3 196a Date Completed SEP 3- W Sh '.2 5 / 9 W f Tolal flours on flour Meter 93 //g. 7 1

Log N and Period Channel Initial

a. Nog fl Power Supply JUL 3 25 (1) Cleaned chassis (2) Tested all vacuum tubes

[ NN Replaced: tube ' tube type A////O

/lO/lIf

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b. Log (J Recorder Date WL 3 TL (1) Cleaned chassis (2) Tested all vacuum tubes [//e'/) />

Replaced: tube #

,f//MjC/

tube type l]i'LY I

I

c. Neutron Detector Check Resistance (ohms) Capacitance (pf)

(1) Signal to ground 7, 4 p o 'I- SL4 _ f(N;d *

(2) Positive to ground l t3) tiegative to ground 7.6/ y/O

g. o 'xio 't-1, t 2&

8///d

./GA///3

,I Page 2 of 9

d. Log N Calibration Date Jul. 2 61985

1. Meter Initial Recorder Keithley I 100 10

/h '

/.T

,4 ,s'*

C1 to ~

(k//b ft'ky 1

/ 'A ~'

GX to 0.1 . /.X fAf9ff CX lo ~

.01 .O/.R C X /e ' ' f./~?)ffy'$

.001 _ e d /9' C y in "

/()/7h jf//)ff)

.0001 . t o e22 ~"

S')c/ 6 fS//h Reconnection of Cables Verified Note: h/

I e.

The ratio of true-to-observed readings should be betwee[d.7 and 1.4 Period Recorder Date JUL I (1) Cleaned chassis (2) Tested all vacuum tubes 3 nas h/

1 Replaced; tube # tube type

[/[h]

flik/e

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2. Linear Power Channel

a. Linear Power Supply Date JUL  : une (1) Cleaned chassis (2) Tested all vacuum tubes

[

Replaced: tube # tube type f//p-g

/#d I

I I

b. Linear Recorder L Date d[I[ 3 nur I (1) Cleaned chassis

[2///p3 (2) Tested all vacuum tubes g/p//3 l Replaced: tube # tube type I '

CW I

I

c. Micro-Micro Ammeter (Spare) Date JUL 3 Iges (1) Cleaned chassis (2) Tested all vacuum tubes

[ M/

Replaced: tube # tube type

[#NM hM'I)

NOAlb I

d. I Linear tieutron Detector Check Resistance (ohms) Capacitance (pf)

(1) Signal to ground j

_ ,11r/af A? 68/d  !

(2) Positive to ground S 9'y'/a# #1 _ A ///J 3 (3) Negative to ground S ? f/A #?

/ 6/d_

I e. Micro-Micro Ammeter replacement (1)

Remove Micro-Micro Ammeter from console and replace with spare [f (2) Reconnection of cables verified I

Note:

Any instrument found to be out of calibration should be realigned in accordance with procedures. I I  :

r'oge 4 or y

f. (Linear Cont. ) Record after step e. (I) has been performed (1) Keithley Meter Recorder i

Initial 6.66x10-5 g,g jg g ggg 2.0x10-b 6.66x10-6 j,d g , ,,

/d d

,g g bM pp;pf 2.0x10~ 2.b /0 0 A(W 6.66x10~ /, b 2.0x10-7 ),9 Ja/ &fb 6.66x10'O /, . ']

/0 / [M 2.0x10*0 l8/ )))/b 6.66x10-9 9,d d.6

)D D [h]b

/4/ MM i 2.0x10~9 6.66x10-10

,2,O

/, . 6'

}f)t?

'l 9 h/ff 2.0x10-10 y,g

((

99 j

g. Reconnect all cables h//

Reconnection of cables verified

,h i I Note: From 10 4 to 10~0 , the overall accuracy should be better than I 2% of full scale. From 3x10-9 to 3x10-10 the overall accuracy should be better than 4%.

3. Log Count Rate Channel Initial

a. log Count Rate Recorder M Date 3 1985  !

(1) Cleaned chassis (2) Tested all vacuum tubes

[lfM/)

Replaced: // # 527 3 tube # tube type A]ois

b. Fission Preamp Date M 0 N' (1) Cleaned chassis and inspected

[*,g'/2

Page 5 of 9

, b. fission Preamp (cont.)

(2) Additional Comments

c. Log Count Rate Channel Date JUL 5 '.',65 (1) Pulse Generator

• Meter Recorder Initial 10 )D /p f/////h 100 //) d l8 $'W /5}//k

/

1,000 /h4d /d ' MM to,000 ja /dd /D ' ff)h Reconnection of cables verified M Note: All readings should give .7 to 1.4 ratio of true-to-observed r

readings I 4 Safety Channels

a. Safety Preamp Date Jill -

(1) Cleaned chassis (2) Tested all vacuum tubes

[

Replaced; tube #

8@M tube type NOJ)F I

.I

b. Neutron Detector #1 Resistance (1) Signal to ground y,5~//d '#

(2) Positive to ground f/f/8

f. # y/d

///geg (3) Additional Comments l

I c. Neutron Detector # 2 Resistance I (1) Signal to ground (2) Positive to ground

'ly wo

9, 3p/g

8///J 8//f3 (3) Additional Comments

Page 6 of 9 4 Safety Channels (cont.)

_In i t i a l I d. Safety Amplifier (1) Cleaned chassis Date JUL 3 1985 M///

I (2) Tested all vacuum tubes Replaced: tube # tube type

/// /fjj Nb AJ 2 g c

e. Safety Amplifier Adjustments

////[

f. Replace all cables to safety amplifier j#///[

I 5.

Reconnection of cables verified r

h,-

PAT 60 Controller I a. PAT 60 Date JUL b 50 I (1) Cleaned chassis (2) Tested all vacuum tubes

[f27[

[//[ 7 ]

b.

Check dial settings and record the following (1) Approach

//// d///[

(2) Proportianal Bond /J (3) Rate Time , ptJ '

6//d (4) Reset 4 0'///h (5) Gain (if applicable) ///j/ [/49' )

((//f8

6. Temperature Recorder Date AtlG i. 3 b'a

a. Reading # Thermometer Recorder 2,) #

fhf 1

80*F 2 80*F f}* &

3 80*F g ;)

l 2 1

kW /# b / '3 cll E

kP%/ jj g bg/

3

E 'AhF~a ju' [,jff]

nn,o. ,,,-,u. .. ... .~

1 Page 7 of ')

6 Tempera ture Recorder (cont. ) Date AUU 3 bob _ luitial i

b. 135"f Interlock Trip Point 7// I

' /3g-t

' i

7. Regulated Power Supply Date JUI. 3 1985 i

a. Cleaned chassis

b. Additional comments j

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i

8. Conductivity Bridge Date MLE!

• jI a.

b.

Cleaned chassis Additional comments

[///

j I 9. Relay Test Date AUG 2 31985

!I a.

Console relays tested and replaced as per S0P 815

b. Relays Replaced

/'.23 g

, [(pp_3 k .w _ _ _

iI 10.

Rod Indicator Calibration Date AUG D E Actual Height 1.

l ((

II. Ill. Reg.

1" / / / /

6" /f g. /, g, 12" J% /% /2. /)-

'I 2c

.u

-n, _ _ a, n,

.I

Pa!p? 8 of 4 i

11 Fire Alarm Check Date SEP 24IW.> ggit,gg

a. Cleaned system containers i

b. Changed batteries g[jp/3

///h 7 c. Checked pull stations u;

d. Checked heat detectors

//7 3

e. Checked smoke detectors Oj

f. All indicator lamps operate l 12. Security System Check Date AUG 2 d 1985 l a. Door Sensors

b. Motion Detectors

/[ff)'$

/// pfy]

l c. Duress Alarm

d. //f[

Control Modules (at UMR Police office) Date AUG 201985 (1) Power Supply hf[

(2) Control Module

! /hff,/'3-

13. Public Address System R 2L E Date (1) Cleaned chassis 4 j

(2) Additional Comments l

I l 14 Area Radiation Monitor AUG 2 919ES Date _

(1) Cleaned chassis (2) Additiona! Comments

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Page 9 of 9 Date h( hy fj-b I have reviewed the results withof thethis Semi-Annual Clieck on this date and discu any problems and/or errors operating staff.

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