ML20084D299
| ML20084D299 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 03/31/1984 |
| From: | Bolon A, Straka M MISSOURI, UNIV. OF, ROLLA, MO |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405010282 | |
| Download: ML20084D299 (98) | |
Text
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g ist Progress Report
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1983-1984
! University of Missouri-Rolla
[ Nuclear Reactor Facility
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PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI - ROLLA NUCLEAR REACTOR FACILITY APRIL 1, 1983 to MARCH 31, 1984 Submitted to The U.S. Nuclear Regulatory Comission and i
The University of Missouri - Rolla l
By Albert E. Bolon, Director Milan Straka, Manager Nuclear Reactor Facility
( University of Missouri - Rolla Rolla, Missouri 65401
Sumary During this reporting period the nuclear reactor at the University of Missouri-Rolla was in operation about 425 hours0.00492 days <br />0.118 hours <br />7.027116e-4 weeks <br />1.617125e-4 months <br />. The major part of this time, 84%, was used for class instruction and training purposes. About 6% of the reactor time was used for research and irradiation and about 10% was needed for the maintenance runs.
There were 30 UMR students enrolled for courses at the Reactor Facility.
The facility was thus committed to over 46 student-hours of classes during the fall, sumer, and spring semesters. The reactor was visited by 2,969 visitors during the past year. This is an increase of 36% when compared to j the last reporting period.
An educational program was established for students and their instructors from colleges and universities which do not own a nuclear reactor. The l Reactor Facility is reimbursed for this program from the Reactor Sharing program funded by the Department of Energy. There wereabout 101 participants l in this program.
The reactor produced approximately 6.3 MW-hrs of energy using 0.325 g of U-235. A total of 387 samples were irradiated during this reporting period with most of them being used and analyzed at the reactor facility. Further-more, three research projects for material irradiation and neutron activation analysis were established for on-campus investigators. The reactor staff was heavily involved in the process of the license renewal for the facility.
( Research activities at the reactor concentrated on the neutron flux evaluation at difforent irradiation pasitions and on further improvements in the trace 1
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element analysis. Two papers on the facility uses and on-going programs were presented at an International Meeting in Cambridge, Mass.
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Table of Contents Summa ry 11 List of Tables v I. Introduction .................................................... 1
!!. Re a c to r S ta f f an d Pe rs on nel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 A. Re a c to r S t a f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 B. L i ce n s e d 0 pe ra to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 C. R a d i a t i o n S a fe ty Co mm i t tee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 D. Health Physics............................................... 3 E. I n de pe nde n t A ud i t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
!!!. S up po r t i n g Fa c i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 IV. I mp ro v e ne n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 V. Re a c t o r O pe ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 A. Facility Use ................................................ 7 B. C o re D a t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 VI. P u b l i c R e l a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 VII. E d u c a t i on a l U t i l i z a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .,. . . . . 19 VI!!. Reactor Heal th Phys i cs Ac ti vi ties . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 IX. Plans .......................................................... 23 Appendices ........................................................... 24 A. I n de pe n de n t A u d 1 t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 B. Semi- Annual Check s ( 50P-809 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 C. Revised 50P's .............................................. 68 iv
List of Tables
- 1. UMRR Core Con fi gura tion and Rack S torage Form. . . . . . . . . . . . . . . . . . . . . 8
- 2. Use of Core Grid Pl a te Loca tions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
- 3. Facili ty Use Other Than the Reactor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 4. Re a c to r U ti l i z a ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
- 5. Scrams and Rundowns............................................... 10
- 6. Maintenance....................................................... 14
- 7. Co re Loa di ng a nd Unl oa di n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
- 8. Co re Te ch n i c a l Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 l
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I. Introduction 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).
The reactor, a swimming pool-type, modified BSR, was first licensed as a 10 kW training and research facility with initial criticality on December 9, 1961. In January 1967 an amendment was granted by the Nuclear Regula-tory Commission to upgrade the facility, allowing an increase in power level to 200 kW.
The Nuclear Reactor Facility is operated as a university facility available to the faculty and students of the various departments of the university fnr 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 purpose of training reactor personnel for the nuclear industry and electric utilities.
The reactor staff has continued to review the operation of the reactor 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 sections of this 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.
II. Reactor Staff and Personnel A. Reactor Staff Name Title Albert E. Bolon Director Milan Straka Reactor Manager Daniel Carter Reactor Maintenance Engineer Carl Barton Electronic Technician Karen Lane Sr. Secretary Juls William Lab fiechanic Scott Linn Student Assistant Level II B. Licensed Operators Name. License Albert E. Bolon Senior Operator Daniel Carter Senior Operator Carl Barton Senior Opera tor Karen Lane Reactor Operator Milan Straka Reactor Operator I
C. Radiation Safety Committee Name Department Dr. Nord L. Gale (chairman) Life Sciences Mr. Ray Bono (secretary) (ex officio) Health Physicist 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 This committee, is required to meet at three month intervals. However, in practice the frequency of the meetings is usually greater.
D. Health Physics Name Title Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Campus Health Physicist Ms. Paula Brewer Health Physics Technician E. Independent Audit Independent audits of the facility consisting of reviewing all records, procedures, and operating methods are per forwed semi-annually. Dr. Franklin Pauls, former Reactor Director, performed the first audit for the reporting period in May 1983. The second audit, in January 1984, was performed by Dr.
J.C. McKibben and Mr. Barry Bezenek, both from the University of Missouri Re-search Reactor located at Columbia. Reports about both audits are enclosed in Appendix A.
III. 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 .
Analog Computer: This computer is currently available to faculty and stu-dents and is used in scheduled classes for both graduate and undergraduate students. Several units of auxiliary equipment are also available to widen the scope of its operation.
Activation Analysis Laboratory: The activation analysis laboratory has proven to be the most-utilized supporting facility. The laboratory contains a 4096 channel analyzer, with NaI or GeLi selectable detector input. In-cluded 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 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.
Pneumatic Tube Assembly: A dual tube pneumatic system is installed adjacent to the core of the reactor. One tube is cadmium lined, and the other is bare. This system is a positive pressure type and uses nitrogen as the propellant.
Dynamic Void: A method of introducing a contained void on the periphery of the core is available. This allows for a variation in void as a function of core height, total volume, or volume change.
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IV. Improvements A continuous effort to enhance availability and reliability of the facility is being undertaken by the reactor staff. During this reporting period the following improvements have been made:
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- 1) More reactor staff personnel became licensed by the NRC. The )
facility has now 3 Senior Reactor dperators and 2 Reactor Operators licensed.
l 2) Input for the Fuel Burnup program was switched from the card i
deck to the terminal reader. l
> l f 3) Multichannel Analyser is being interfaced with a Apple II+ computer.
- 4) Some signal and power supply cables were provided with shields to protect agairat mechanical damage. )
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V. Reactor Operations A. Facility Use l
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Table 1 depicts the current core loading which is designated as core 67, t
l The number 67 denotes the sixty-seventh core configuration (assembly and location), that has been used at the reactor facility since the original I operating license was issued in 1961. This co're 67 has been in use since December of 1978 and is periodically checked for all parameters listed in Table 8 (core data).
i Tables 2 through 7 give pertinent information about the reactor facility and its operation during the reporting period. Listing of semi-annual facility checks is included in Appendix B.
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l Table 1. UMRR Core Configuration and Rack Storage Form 1
DATE December 19, 1978 LOADING NUMBER 67T or 67W R1 R7 R3 R4 R5 R6 R7 R8 R9 R10 R11 R12 R13 R14 R15 IP CA RACK STORAGE FACILITY F-13 F-20 HF-1 F-22 F-2 F-5 F-3 F-18 F-21 R16 R17 E1E R19 R20 R21 R22 R23 R24 R25 R26 R27 R26 R29 R30 KIT TO PREF!XES A F - Standard Elements 3
C - Control Elements HT - Italf Front Element C HR-1 F-14 F-1 C-4 HR - Half Rear riement D F-8 C-1 F-16 F-9 F-4 F-10 CA - Core Access Element IP - Isotope Production Element E F-6 C-2 F-19 C-3 F-12 F-11 S - Sourco Holder r BRT F-17 F-15 F-7 CRT Other BRT- Bare Rabbit Tube 6 7 8 9 CRT- Cadmium Rabbit Tube BRIDGE CIDE UMRR CORE STATUS Elem. 'For.Ih s t. Elem. Poc. Mars Elem Pos. Mass HR-1 C3 84.912 F DS 170.270 F-12 E7 168.774 F-8 D3 170.229 F-19 E5 170.264 F-10 D8 170.193 F-6 E3 169.160 F-15 F5 168.889 F-11 E8 168.969 F-14 C4 170.210 C-4 C6 102.112 C-1 D4 102.112 F-9 D6 170.178 C-2 E4 102.125 C-3 E6 101.978 F-17' F4 169.111 F-7 F6 170.154 F-1 C5 l170.223 F-4 07 170.206 Total Mass Gram:: 2869.744 T designates the thermal column-reflected mode, and W designates the water-reflected mode.
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Table 2.
Use of Core Grid Plate Locations Location . Hours A-7 0.083 A-9 0.217 B-2 0.133 8-3 0.517 8-4 0.517 B-6 0.533 B-7 0.117 B-9 0.233 C-2 0.250 C-3 0.283 C-4 1.350 C-5 3.783 C-6 0.167 C-7 5.117 C-8 1.533 C-9 0.200 D-2 0.433 <
D-3 0.250 0-5 4.933 D-6 1.883 D-7 0.993 D-8 0.633 D-9 0.700
.E-3 0.183 E-5 0.767 E-7 0.100 E-8 .0.117 E 0.300-F-5 0.083 F-9 1.183 Total .
27.591 Table 3.
Other Facilities Facility Hours i
Bare Rabbit Tube 10.150 Beam Port 1.167 Reactor Console 1338.469 Thermal Column 0.167 i
Total 1349.953 f
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Table 4 Reactor Utilization Reactor use (hr) 425.49 Research & Irradiation (hr) 26.24 runs Instruction runs (hr) 357.88 Maintenance runs (hr) 41.37 Maintenance (reactor shutdown) (hr) 1654.51 Time at power (hr) 182.0 Heat generated (kW.hr) 6299.98 Total number of samples 387.0 Sample hours (hr) 45.05 Research & Instruction usage II) -(1%) 18.5 U-235 burned (g) 0.274 U-235 burned and converted (g) 0.325 l
II) Based on 2080 working hrs. per year.
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Table 5 Scrams and Rundowns Date Event f
i 4-13-83 120% Demand rundown Cause: Cover on linear recorder had been removed because of bad fastener.
Corrective Action: Replaced cover and taped.
! 5-4'83 120% Demand rundown Cause: Void tube influencing linear CIC Corrective Action: Moved void l 5-4-83 120% Demand rundown Cause: Void tube influencing linear CIC Corrective Action: Moved void
[ 5-4-83 120% Demand rundown Cause: Void tube influencing linear CIC Corrective Action: Moved void
( 5-13-83 Scram Cause: Lightening caused momentary surge in power.
Corrective Action: No corrective action necessary.
7-18-83 120% Demand rundown Cause: Moved fuel element too close to linear CIC.
Corrective Action: None 7-18-83 120% Demand rundown Cause: Moved fuel element too close to linear CIC.
Corrective Action: None 8-25-83 Scram Cause: MCA power being turned off and on caused fluctuation in regulated power.
Corrective Action: None 9-2-83 120% Demand .undown Cause: Mismatch between linear and log N channels.
{ Corrective Action: Corrected mismatch between linear and Log N channel.
10-3-83 Scram Cause: MCA power switched off and on.
Corrective Action: None 10-4-83 Log N inoperative Scram Cause: Building power surge caused by Thunder storm in area.
Corrective Action: None 10-11-83 Scram Cause: MCA power switched off and on, Corrective Action: None 10-19-83 120% Demand rundown Cause: Linear scale not switched.
Corrective Action: SRO switched scales and terminated rundown.
Table 5, continund.
Date Event 11-3-83 120% Demand rundown Cause: Operator error - Turned micro-micro anneter scale wrong way.
Corrective Action: None 11-15-83 120% Demand rundown Cause: Moving void tube in core.
Corrective Action: None 11- 8-83 120% Demand rundown Cause: Operator error - Turned micro-micro ammeter scal'e wrong way.
Corrective Action: None 12-29-83 Scram Cause: Connected Log N signal cable. ,
Corrective Action: SOP's for precheck and start-up checkout revised to give definite .ir.dication.
Table 6 Maintenance Date Event and Corrective Action 4-4-83 Adjusted Log N CIC as indicated by power calibration. (From 18 KW to 24 KW).
4-20-83 Replaced coax cable on fission chamber.
5-5-83 Replaced normal operate lamp in No.1 and No. 3 RAM modules.
5-5-83 Replaced K 27 and K 28 behind console due to spurious rod drops that have occurred.
5-10-83 Replace V1, V2 and V3 (Magnet current power supply).
5-17-83 Replaced coax cable from fission chamber to preamp.
5-24-83 Removed conductivity meter for maintenance.
7-26-83 Replaced shim range switches. Replaced Reg. rod insert limit switch.
7-27-83 Replaced Reg. rod insert limit switch. Repaired bridge RAM module (detector).
7-29-83 Replaced shim range switch on No.l. Repaired switch activation device. Replaced spring on No.3 shim range switch.
9-7-83 Replaced Amphenol connector and cable to magnet No.3. '
Repaired short in connector to magnet No.3.
9-19-83 Rebuilt magnet No.3.
9-22-83 Repaired magnet No.3 Soldering flux caused magnet to short out.
9-26-83 Removed resistivity meter for maintenance.
11-2-83 Reinstalled resistivity meter.
11-3-83 Adjusted Log-N CIC to 50 KW as per power calibration.
12-6-83 Repaired No.3 shim range light by adjusting spring tension on switch.
12-7-83 Repaired RAM detector at demineralizer.
1-3-84 Replaced relay in demineralizer resistivity meter. Removed and replaced power wires for demineralizer.
1-15-84 Repaired door alarm sensors.
3-2-84 Replaced spring on No.3 shim range switch.
Table 7.
Core Loading and Unloading Date 7-18-83 Unloading core to subcritical for purpose of inspecting the control rods.
7-19-83 Loading core to the previous configuration (67W).
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B. Core Data I
During this reporting period only one core designation has been used.
) The "W" mode core was used for normal 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 or thermal column experiments. The excess reactivity was l measured for cold, clean critical conditions. In day-to-day operation l the excess reactivity is quite often lower due to the temperature increase of the pool.
Table 8. Core Technical Data 12 2 Average Thermal Flux 1.6X10 n/cm -sec at 200 kW 12 2 Maximum Thermal Flux 2.8X10 n/cm -sec at 200 kW ll 2 Average Epithermal Flux 1.6X10 n/cm -sec at 200 kW Worth of Thermal 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) 0.92% Shutdown Margin (in "T" mode) 4.37%.
Void Coefficient -6.6X10-7o/cm3Da te11-16-83 Limit -2.0X10-7o/cm3 Temperature Coefficient -1.3x10~4 o/oF Date 12-15-83 Limit -4.0X10-5, fog Reactivity Addition Rate (max %aK/K/sec)
I 0.019 II 0.019 III 0.026 Reg. 0.01 Rod Drop Time (24")
I 470 msec, II 460 msec, III 480 msec, Date 1-4-83 Magnet Separation Time (at Imx)
I 38 msec, II 30 msec. III 26 msec, Date 1-4-83
VI. Public Relations The reactor staff continues to put forth considerable effort to help educate the public about the application of nuclear energy. Over 2,969 persons have toured the facility during this report period. This is an increase of 36% when compared to the last reporting period. Tours in-cluded groups representing social, military, civic, industrial, govern-mental and educational fields. These groups are usually given a brief orientation lecture by a member of the reactor staff. These lectures are augmented by visual aids such as slides and displays. Many high school, junior college and college groups have attended the various lectures and open houses.
Some other groups have 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. A guided tour by the reactor staff includes a brief description of the basic nuclear reactions, components of a nuclear reactor, a few specific examples of how nuclear energy is used in the industrial and educational fields and how nuclear energy helps the environmental situation.
Posters to display for the public capabilities and uses of the UMRR have been made and installed in the reactor bay area. Two staff members par-ticipated in the International Symposium on the Use and Development of Low and Medium Flux Research Reactors presenting two papers about the facility's achievements and programs.
The Nuclear Engineering faculty are members of various social civic,
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professional, and governmental committees. The faculty and students also are involved in speaking engagements around Missouri concerning the reactor facility and in informational programs at high schools and colleges.
VII. Educational Utilization Approximately 30 UMR students, graduates and undergraduates, have participated in classes at the facility, utilizing 48 student-semester hours of al-located time. Also students from several colleges, and high schools have used the facility.
The following is a list of scheduled classes at the facility along with the total hours of reactor use for this reporting period.
NE 204 Nuclear Radiation Measurements 3.9 NE 304 Reactor Laboratory I 70.83 NE 306 Reactor Operations 194.98 NE 308 Reactor Laboratory II 39.0 NRF-4 Reactor Operator Training 49.17 Preliminary Research 26.24 The current enrollment in Nuclear Engineering is 73 students. During this reporting period the reactor was used 84.1% for instruction 36.2% for research, and 9.7% for maintenance.
A program called Reactor Sharing Program, funded by the Department of Energy, was established for colleges and universities which do not own a nuclear re-ac tor. About 101 students and their instructors participated in this program.
f VIII. Reactor Health Physics Activities The Health Physics activities at the UMR Reactor Facility consist pri-marily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity and waste disposal.
Releases of all by-product material to authorized, licensed recipients
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are surveyed and recorc'ed. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.
Routine Surveys Monthly radiation surveys of the facility consist of direct gamma and 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 ganna activity. In 12 monthly surveys, no significant contamination outside of contained work areas was found.
By-Product Material Release Surveys During the period, 2 shipments of by-product material were surveyed and released from the reactor facility. Total activity released was 0.581 mci.
The shipments were utilized on the UMR Campus.
Routine Monitoring Twenty-three reactor facility personnel and students frequently involved with operations in the reactor facility are currently assigned beta-gamma, neutron film badges which are read twice each month. There are 4 beta-ganra, neutron area badges assigned and one test badge to check accuracy of exposure reports. Fourteen campus personnel and students are assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 13 beta-gamma area and spare badges assigned on campus. In addition, 7 direct-reading dosimeters are used for visitors and high radiation area work. There have been no personnel over exposures during the period.
Airborne activity in the reactor facility is constantly monitored by a fixed-filter, particulate continuous air monitor (CAM) located in the reactor bay. Rb-88 and Cs-138 are the particulate daughters of Kr-88 and Xe-138 which are particulate activity monitored above the natural background of radon daughter products.
Argon-41, Krypton-88 and Xenon-138 are the gaseous activity routinely detected during operations.
Pool water activity is monitored monthly to insure that no gross pool contamination nor fuel cladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are compared to previous monthly counts. From April through March sample concentrations averaged 2.73x10-6 pCi/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 6.07 millicuries were released into the air. Released isotopes were identified as Kr-88, Rb-88, Xe-138, Cs-138 and 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 11 releases to the sanitary sewer totaling approximately 8,985 gallons of concentrated resin regen-eration solution and pool water were discharged with a total activity of 0.581 millicuries. Isotopes released were: Hydrogen-3, Sodium-24, Cr-51, Mn-54, Fe-59, Co-58, Co-60, La-140, and Ba-140. All isotopes released were below 10 CFR 20 g Appendix B. Table I, Column 2 limits.
Instrument Calibrations During this period, portable instruments were calibrated four times. Remote area monitors were checked for calibration four times.
I IX. Plans Presuming that the re-licensing process, which is presently underway, will be completed and that continued operation of the reactor will be approved by the U.S. NRC3 the reactor management would like to spend a lot more time and effort upgrading the facility's research capability. Although extra efforts have been made to inform academic department chairmen and research center directors of the current availability of the reactor and the various associated counting systems, we have not generated very much research activ-i ty. We also try to inform the individual faculty members / researchers, who we believe might be doing research that could utilize the UMR Reactor, that we would be pleased to cooperate with them.
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(L1) detector. Likewise, it would be beneficial to have an auto-matic sample handling system so that a large number of samples (say at least 24 of them) 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 with other researchers.
Last year we indicated that we had submitted a proposal to the U.S. Depart-ment of Energy for support in the University Reactor Sharing Program. We were selected for $9000 financial support. To date four separate groups from Linn Technical Institute have come to campus for a day each. The University of Arkansas will send 10 graduate students for two days in April.-
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Other schools are expected to use the reactor for education or research before the end of the contract in August. We hope to be selected for an extension of that program.
Last year's plan to have at least three licensed senior operators has been accomplished. The two current reactor operators are planning to take the senior operator's examination early this coming reporting period. Two Electrical Engineering students, who served as operators in U.S. Navy nu-l clear submarines and who have satisfactorily completed our student reactor operator training program, have expressed an interest in taking the NRC reactor operator's examination. If all of these individuals pass their examinations, we would be very well staffed next year.
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 and solid-state power L
range (safety)channelsthatwerep%hasedseveralyearsagoandnotin-stalled.because we were in the miust of re-licensing. The Technical Specifications and Final Safety Analysis Report will incorporate descrip-tions of the new systqa. Without a doubt, the solid-state devices should be more reliable than the present vacuum tube ones, which were original equipment. -
Following discussions with the NRC licensing representatives, we feel that pursuit of operating with a mixed core of MTR-type and TRIGA-type fuel is insurmountable. A complete conversion to TRIGA fuel apparently would in-volve a complete relicensing of the facility, including the construction permit stage. Thus, we have decided not to attempt such a change [over of fuel.
1 APPENDICES
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APPENDIX A
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Research Reactor Facility
, UNIVERSITY OF MISSOURI Aesearen Pa - ..
columena. Missoun 65211 ,,.( 4 '
Te.ephone (314) 882-4211 ,/'. '
February 24, 1984 , b.
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Dr. Albert Bolon ,
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Reactor Director University of Missouri-Rolla Gh1
.g Nuclear Engineering, Building C *r Rol1a, Missouri 65401
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Dear Dr. Bolon:
6 On Tuesday, January 10, 1984, Barry Bezenek and I conducted a Reactor
- Facility Inspection of the UMR-Reactor. This inspection concentrated on just a i.B.h.'l few of the arecs given in your inspection form. The detailed comments from the C: ' " . . -
inspection are primarily contained in this letter with the inspection form
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l attached indicating both the few areas reviewed in detail and those briefly '. #
scanned. . . ....,y
- ,e
( The Operator Requalification Program records were reviewed in detail. In- , ;,. *c'.
provements should be made in the documenting of Nuclear Instrumentation checks, - l < '3 review of changes to Standard Operating Procedures, and Abnormal and Emergency i' ; ' ;
( procedure reviews. One page of the 1982 requalification documentation for an -:. f operator was missing. UMRR may want to consider removing the completed requali- 7.. ;,-
fication sheets at the end of each year, instead of leaving them mixed in with c ' f the new working documents. This may reduce the potential of them being acciden- l v 4.c '
tally lost. #
fM The Health Physics records were reviewed in detail and were found to be '
( well maintained. However, two changes to current practices are recommended. 1'.7',
Radiation and swipe surveys should be conducted in the upstairs offices. This c; ' .; M could be performed infrequently but should be done since these areas are manned .
?/
during reactor operations, and personnel eat and drink in the of fices.
( # - ,,
Secondly, you nuy want to consider revising the method cf calculating the ', 'M U monthly air release. Your current method makes the amount of Ar-41 released y .:'t /
heavily dependent on which fan is in operation. The dif ference in flow rate .
between the fans should primarily affect the equilibrium concentration value in the building and only slightly affect the release rate. The lower the flow rate
~
.y the slightly less Ar-41 is released due to the longer holdup time allowing more to decay before being released.
.! )
1 N' mr n v1]a 4 jh COLUMBIA KANSAS CITY ROLLA ST LOUIS ) .
M .neaue ocoonun. consta.o-
l l
\ f f Dr. Albert Bolon February 24, 1984 Page 2 dN . Production - Removal l E
. p - AN F.R. N N = # of atoms of Ar-41 per unit volume in atoms /ml P = # of atoms Ar-41 released per minute divided by total building volume in atoms ml-min A = Decay constant for Ar-41 = 6.3 x 10-3 mil-l F.R. = Flow Rate for designated fan in cfm.
Vol = Building Volume in ft 3 4.455 x 104 ft3 In equilibrium dN = 0 E
P= [A+F.R.)N
\ Vol )
N= P A + F.R.
tot Using this relationship the following table can be constructed for equilibrium values.
Fan 1 or 2 3 No Fans F.R. 15,000 cfm 5,000 cfm 0 F.R./Vol 3.367 x 10-1 min-1 1.122 z 10-1 min-1 0 N [a tomsi 2.915P 8.436P 158.7P
\ ml [
ReleaseRate[atonsi 1.238 x 10 9P 1.194x10 9P O (min /
atmosphere. A test would have to This be run assumes constant to determine P for release typical pool rateconditiorff to the building) This could be done with no fans on and plotting the buildup of activity in the building.
f,f: _ r .&. YAbt v/c w e{ N.w _
5 O. \E!. .
tj[a .wh, s> , n t ,. ( pc. L c &)
. , L V q -
t w L a. u.R la c. i J r. v $, k I
yy( )eq 6 y;
,/(, g,
" - ~ ~ -
g
N ?
Dr. Albert Bolon February 24, 1984 Page 3 The console logs, Startup Checkout sheets, and Shutdown Checkout sheets were reviewed in detail. The log book accuracy had made good . improvement compared to that observed in December 1982 audit. The following recommendations are based on this part of the review.
a) On July 13, 1983, a Startup Checkout sheet was not used for a startup
=
immediately following a shutdown in which the Shutdown Checkout sheet was completed. This is allowed by SOP 102 due to the phase "...
unless otherwise specified by the Senior Operator on duty." You may want to more clearly define the Senior Operator's discretion in this situation; i.e. require him to do at least the steps that return equipment to operation that were secured while completing the Shut-down Checkout sheet.
p b) Suggest it would be beneficial to log when a control rod is removed
_, and when it is reinstalled during the inspection of control rods.
e-c) It was noted a Startup Checkout sheet was completed by procedure prior to raising the control rod to 50% for refueling during the control rod 7 inspection procedure, but was not done prior to raising the rods for refueling. This looks inconsistent in our superficial review but may be quite justifiable if reviewed in detail, therefore this ooservation is stated for your consideration.
d) The UMRR staff should evaluate how they will document their decisions to operate with instrumentation / equipment inoperable, i.e. Rod Magnet Contact Indication, Rod Prohibit, etc.
e) Recommend any time a safety system component is discovered inoperable that the reactor be immediately shutdown then try to correct the problAm..
f) Recommend modification reviews be completed on any change to a reactor related system prior to making the change, such as the antisiphon change to the pool system.
We found the operations being conducted in a satisfactory manner with no sig-nificant problem areas identified.
Sincerely, i_ +
J. C. McKibben Reactor Manager JCHK:vs
Attachment:
Inspection Form cc: Ray Bono
f f REACTOR FACILITY INSPECTION -- Date(s} dm (Oilid 4 (Phone: 341-4236)
/
Date(s) of last NRC inspection b \
m (3-} b ; l 3 N s
f Date(s) of last "inhouse" inspection M ao $ G dI9. (32 3 Log Book Inspection:
Log Book Number Page From entry: \/i 12. Date/l 5 2 /P;3 Through entry: Vl Bf l f 9 ,/ 4 4 Follow up items from previous inspection (item, follow-up):
l "7
(
13 ,
l W h S.0 2 OK Comments A. Technical specifications--------------
Appendix A -- Jan. 6, 1967
/
- 1. (2.1 ) Ventilating fans------------
Automatic closure ----------------
- 2. (3.1) Pool water depth (16 ft. min y aboye core)-----------------------
- 3. (3.1) Inlet water temperature f 60oF <t <135cF--------------------
l 4. (3.2) Radiation one meter above .
l pool <5 mr/hr -------------------- /
- 5. (3.2) Resistivity >0.5 megohm-cm- r
- 6. Fuel ----------------------------- Type of elements: MTR Other (4.1.3) o ex <1.5% --------------- Present loading (s):
- 1.5% <pex<3.5% five consecutive Dates
days twi ce a year----------------- %9 (1)
- 7. Control rod: (9.5) condi tion----- (2)
(4.2.3) Reactivity shutdown Date Inspected:
ma rgi n a t l eas t 8% ---------------
(4. 2.4) Drop time <600 msec------- (9.3) Dates: (1)
(4.3.2) Limit lights; shim range (2) lights, magnet contact fights-----
- 8. Neutron source (min. 10 n/sec----
(
r r OK Coments
- 9. Safety systems (annunciator)------ #
( 5.4) S ta rt-up cha nnel ------------
(5.4) Linear channel-------------- /V (5.4) Log N - Period channel------
(5.4 Safety channel #1----------- /
(5.4 Safety cha nnel #2------- '--- '
. 10. {5.5 Magnet release time <50 msec
- 11. (5.7) Radiation levels <0.1 mr/hr Location Reading Pool surface above core Near demineralizer Beam room
- 12. (5.8) Portable survey instruments List:
Neutron Alpha Gama Beta Other
- 13. Experimen tal facilities--------- ~rNGive example as to how it is used.
H u n g s ampl es ---------------------- b;W (6.1.1) Core access element------- w .
' (6.1.1) Isotope prod. element----- p , yc , g y\,_4 (6.1.2) Rabbit tube--------------- n .
(6.1.2) Thermal column------------ Nw-T4A cNd.vE qd (6.1.2 Beam port----------------- M g A7 , 9 i.
g (6.2.2) Documentation of exps.---- A ,, -
p (6.2.3) Single independent exp- D D.-3 k
- QM eriment: p <0 AkM -
(6.2.4) Sin!Iemo.7%--------------
vable experiment:
p <0.4% --------------
ex 0.6% all movable exp.--- t (6.2.5) Experiments having moving I parts: p <0.05%-------------- /
(6.2.6) Poshion of any/all exp.-- _/
- 14. General Operating Limitations (7.1) Startup: Sr. Oper.
(in the control room)plus one
, (7.1) Operation: S.O. plus one---
(in building)
(7.4) No fuel position vacancies in core; loading (wall chart)-----
f g
1 g { Pago 3 l
OK Coments
- 15. Fuel Storage & Transfer wal l ch a r t -----------------------
8.3) Fuel handling tools locked-- ,
8.4) Fuel transfer--three men V Sr.0per. ; Lic.Oper. ; plus one----
- 16. 10.1) New loading: approach to critical exp.(reason & date)------
(10.2) Core configuration change:
one grid position. (Reason & date I (10.3) Loading change of more than one grid position-unload 50%------
- 17. Instruments functioning (Table I)- g (On weekly check list *)
Scram: Manual-------------------- startup Pe ri od <5 s ec . ------------ '
- 150% full power----------- ? startup B ri dge mo ti o n------------- ,,,,-
- Log N- Period non-op------ *startup Rundown: 120% power (linear)----- /
- Period <15 sec ----------- #
- Reg Rod (insert limit-auto /
rundown) 120% full power (log N)--- /j
- Low CIC vol tage----------- startup High radia tion------------ # startup Rod pronibit: Period <30 sec----- #
- Any recorder off---------- V
- Low count rate------------ V
- Reg Rod prohibit (rods < td,b2 ^~ -
below shim range)--------- q a*c.
~
6 g Inl e t temp . > 135oF-------- "
^
- ~
- { '~
Servo-prohibit on reg. red-------- #
- 18. Check Lists and records y Log book checked------------------ y (9.1) Daily facility check list---
(9.3) Instrument channels & area Dates: (1) monitors-calibrated at 90 day i n te rval s------ ------------------- V (2)
(3)
(4) t/
UMRR startup check list-----------
Hourly records-note variations---- gd Wh dl, c, Shut-down check list-------------- j, g3- J . - . 3 -%
g Weekly check l i s t----------* ------
Work load log----------------- ---
g, W M O M % @--
Six month systems check---------- V Dates: (1)
, (2)
,e a <
. Ii n * *
- g,p's 9 . tv. + , (. .Y *k , /] 4
- i
( ( Page 4 i
OK Cornments B. Records
- 1. Log books--------------------- Current book number _ V l Other Stored
- 2. Reco rder cha rts--------------- # Stored: where ar.d for how long Log N ( pennanent)------------- V Located:
- 3. Evacuation alarms: number and V
cause------------------------- 1. 5/l5/83 2' "/M/83
- 4. Evacuation procedures, drills- / 12// S /8 3
- 5. Use o f by-pass keys----------- 1. ;ggq
- 6. Key security------------------
General securi ty--------------
Night use of building---------
- 7. 50P S - Note any revisions---- Y g- [ w'4 e fy .,
f O L . M t. )d l+.' G.
, __ a -
- 8. Film badge, dosimeter---------
- 9. Night watchman record---------
C. Reactor Bay
- 1. General condition of pool-----
- 2. General condition of storage-- V
- 3. Use of cable trench----------- "
- 4. Nitrogen diffuser------------- V
- 5. Miscellaneous (List)----------
D. Control Room-----------------------
Lis t of current operators---------- / Senior operators:
&bE kb Q lh??-.
Da., car b s p 9,nas E. Office (film badge rack, etc.)----- C.M b A L 7,198 5 F. Counting Room---------------------- Operators:
G. Rooms & S torage ups tairs----------- N'" b.kee M i,l'7 63 M If a.n birAka. 8 21983 7
e
i
,' f f Pago 5 OK Comments H. S ta i rvel l & pump a rea------------------ 7
- 1. Demineralizer system---------------< .
- 2. Outside air fil ters----------------
I. S tai rs and beam room------------------- #
- 1. Thermal column--------------------- #
- 2. Beam tube-------------------------- /
- 3. ' Fuel s to ra g e-----------------------
- 4. Liquid & solid waste storage-------
J. Health Physics 1.
2.
Sample removal--------------------- / l SO P ' S ( l i s t ) ----------------------- Up,
- 3. Excursion or incident monitor------
- a. Film badge placement----------- "
- b. O th e r--- --- - ---- - -- - -- --- --- - -- " .
4 F V
-D a.ilmSbadge, ta f f----dosimeter
-- ---- - --- records------
- b. S tu d e n ts ----------------------- #
Guests------------------------- '
c.
i d. Night watchman----------------- V
- 5. Possible detection of fuel element rupture-------------------- /
- 6. Rad i a ti on s u rvey------------------- V Dates:
- a. Periodic swipe tes ts----------- V
- b. Pool water--------------------- V
- c. Inside air--------------------- V , c0
- d. Ou ts i de a i r-------------------- / 'M h CAM e.
f.
Neutron level (sub-critical --- #
Mi sc. i tems ( l i s t)---------)---- -
ddw
'- 3 ww C
4
- 1 Fl- 3 "
C- \
- 7. Emergency box (Physics Bldg.)------..U b " "--
General comments:
aa W /
i I
g "W-e
- D o
m-_-___----_ -_
7 s;.... . . ; ,a >. . . s. v. : > .. . ,:,.~:> .; ,...:.a
. .;r . - .:..:~.. . ;. ~-
g h w sv1 ' ,L L T )
G F. LACT 0h .'ACILL T'.' 2 : ; C T: P' -- Dr. e ( r ) )')h, /6 ( / 7 / 9 P 3
('rhone: 341-4230) e '
(
Date(s) of last NRC inspecticn de M 1 (C1d ,Q n _ 3' 9 l9 Q D 0 Date(s) of last "inhouse" inspection b , i c # 4, P 'l.
Log Book Inspection:
Log Book 1; umber Pace Date From entry: ~3[ 2sr (9 m l L \ 9 0 2.
Through entry: 'VT m h, f g I S r ?
- r. >
Follow up itecc from previouc incpection (ith=; fol)ow-up):
\
s a ks**
l
$M a$N
,'J.,
l 0F. I Cc=.cnts A. Technict.1 specificctient ----------- 7 / Changes. _,o_,, if sc, li st Ar.rendi7. A -- Jan. 6, 19C7 i I ) \.,C '
i I
I
- 1. (2.1) '.entilctin. far.1 ----------- g i Au t e nt. t i c c1crure -----------------/
- 2. (3.1) icci ..c.ter depth '1C ft. min!
above core) _______________________/
- 3. (3.1) Inlet water terrerature 600F < t < 135 F -/
- 4. (3.2) Radiation one me t er above pool <, 5 nr/hr ,/
- 5. (3.2) Re rir tivity > C .i r egeh:.-et-f /
- 6. Fuel / 1' Tyne of elenents:c t'. r r M,TRr (fe . - el. ,
f u 04. 1 [3. 1 .275 (4.1.3) -ex<1.5---------------g i
7 7,. ,.n t inaCing(c):67 w 4 477 ir. orer.
1.5 ; (pex ( 3.51 five : secutive, /g 3ates: (3) ;O-d ay s tv/i c e a y ea r .
- (2)
- 7. Control rod: (9.5) c e ni -icn -----/ Date inspectec: sri 9ea.
(4.2.3) Reactivity !.uti n margin at least 8. ---- --------/ l f,
k (3qrg 2 (4.2.4) Drop time < CZ -_sec ----- -/ (9.3) Dates: (1) Ch_v 2 C ( f t 2 (4.3.2) L1=it lights; sr_m range (2) lights; hts ---- -V- - em M y -$ *+ W ca -
ma gne t(min.1
- 8. Neutron source c on ta c- t n~_ _ g/s e c-y) -- i
- 4 n. C u .
- -.. -~ . - . . -
{
2 i ~
I Fage 2 1
[
'OEi Co =antc d
- 9. Saf ety systems (annunciator) ---- A / =
(5.4) Start-up channel ------------ y i
y (5.4) Linear channel ,
5""
( 5.4) Log N - Peroid channel ------ y
[
I (5.4) Safety channel #1 -----------./i
( 5.4) Saf ety channel #2 --- ------- -
- 10. (5.5) Magnet release time < 50 msee e i Reading
- 11. (5.7) Radiation levels ( O.1 mr/hr- v', Location g4 3
iFool surface above core ------------ p j Near demineralizer .
- B e am ro om ---- -- ---- -fi
~'
- 12. (5.8) Portable survey instruments e j
List:
Ueutron M , Alpha -
Y -
~
Samma Beta l Other ,
l -
- 13. Experimental f acilitie s ----------- / ' liv e exam:le es t.o how used. -
Hun g s ampl e s - ---- - - ------ -- -- - - -- / ;
( 6.1.1) Core acc e s s element --- --- / i
( 6.1.1) Iso tope prod element --- 1 v ' _
( 6 .1.2 ) Rabbi t tub e ------------- Ly i
. ( 6.1.2 ) Thereal column ------------v i d (6.1.2) Beam port --------------- ey , s (6.2.2) Documentation of expa. ----/ f (6.2.3) Sin le indep,endent ext- l t
eriment: 4
( 6.2. 4 ) Si [fe m, 0.7 ,ex------------ e /
ovable D L 0.4% --- periment:-
/ m" 0.64'f11 movable exu. -- -- a / J (6'E.5) Experiments having moving ; / '
parts: 4 0.05'. ------------- e j (6.2.6)- oiition of any/all exp. i/g m
- 14. General Operating Limitations br.Oper. plus one -l /
s (7.1) Startup: '
(in the control room)
(7.1) Operation: S.O . plus one -- / *
(in building)
(7.4) No fuel position vacancies in core; loading (wall chart) ---- / g E
J
\
\ *
- 8 Page 3
~
lok i comments
- 15. Fuel storage ec Transf er % e t oi. i --mN-M
\
wall chart ------------------------ V A
- h. " ' = 0 Is'19t 3 I ,
(8.3) Fuel handling tools locked ---/
(8.4) Fuel transfer--three men v' (Sr. Oper.; Lic. Oper.; plus one --
- 16. (10.1) New loading: approach to critical exp. (reason & date)------ / Q-(10.2) Core configuration change: AR,1f p M'o M 23,8tif3 E one grid position. (Reason & date) /
(10.3) Loading change of more than!
one grid po sition-unload 50% ------ /
- 17. Instruments functioning (Table I)- p/ (On weekly check list - *) i Scram: l' anu al --- - --- - -- --- -- -- -- - / -.startup
/-
- P eriod <. 5 s ec . 150); f ull power ----------L
v - startup Bridg e mo tion ------------h / -
- Log N - P eriod non-op ----- - *startup Rundown: 120% power (linear) ----- -
- Period < 15 see ----------- **
Reg Rod (insert limit-auto r un d o wn ) - - - - - - - -- - - - - - --- - / - .*
120 ', full power (log N) ---/ So Low CIC voltage
/ Istartup Hi::h radiation ----------Lv startup Rod prchibit: Period < 30 sec . -- -----------)
Any recorder off ----------v .*
./ -
Low count rate ------ ---- -v*
Reg Rod prohibit (rods
/-
.below shim range)0 Inlet temp. > 135 F ------ -V-4 Servo-p: :hibit on reg. rod ------- -/-',
- 18. Check T '-ts and records Lo g bc c k c hec k e d ----------------- / 3# @ du (9.1) DL-.ly f acility check list -- -/ i (9.5) I .7ru=ent channels & area Dates: @(Miw 30./9 IMP
(' A monitors-:alibrated at 90 day M )Jd
- ) Lv 44.ne3 interva'-. ------------------------ -/ '
)
U;J.E str up check list ----- ---- -/
Heurly r- ords-no te varia tions --- -/
1, hut-do.- check list ------------- - /'
Vleekly e e k l i s t -- ---- -- - -- - ---- - v' Work les_ log -------------------- -(4
.Six =.:n . systems check ---------- -/ Dates:
k /0.I9 P3 (2) VJ e ts.; 91 w y
. c Us - C-bMN n i s, w "I
i i
. 1 1 Pege 4 iOKI comments B. Records
- 1. Lo g b o ok s ---- ---------- --- -- -- -l v- Current book number 1 -
Other # Stored M# m Stored: where and f6r how long
- 2. R ec ord er char Log N (permanent) t s --------------- ' V
/ Located: A- DO W$
l 3. Evacuation alarms: number and cause l/
- 1. h. '30, l i f 2. b-
% -c . . . n & ' xm Re -
t
- 2. #
- 4. Evacuation procedures, drill s
- 5. Us e of by-pa s s k ey s -----------' / 1.
7 /--84 If 'Tf'$e 27,1993 7~4 30 * -
- p. 4 I, t9 0 T4 'So"-
. /
- 6. Eey 3 enersalecurity s e curit ------------------
y ---------------! v Night use of building ---------- /
- 7. SOP 'S - Note any re 1sions -----.v V
- 8. Film badge, de sime ter --------- /
- 9. Night watchman r ecord ---------7 /
1 C. Reactor Bay
- 1. General condition of pool -----
- 2. General condition of storace - -/ y/
- 3. Us e of c able trench ------------ v
- 4. Nitrogen diff user ------------ 7 y
- 5. Eiscellaneous ( Li s t ) -- --- ----- / L%
D . Contro l Ro om -- ---- --- ------- - ------ /
List of current operators ---------. / Senior gp erst =s:
d.d. r h - % /.,//ft g,6 Operators:
Wm h $b o %^
" W7 1,ttf3 E. Office (film badge rack, etc .) ----- / CM k IO C-W - M # 4 , / /f.?
M, C. ~%e f- y . Io,i182 F . Co un ting Ro om - ---- --- -- - -- -- - -- --- /
G. Rooms &, Storage up stair s ----------- /
l
~
' # Pego 5 C lOh Comments H . St airw ell ec pump ar e a ------------- e
- 1. Demineralizer sy st em ----------- y
- 2. Out side air filt er s ------------ v jMkM b
- 1. Stair s and b eam ro om ------- .----- 7/ } l
- 1. Thermal column --------------- Iv 2
3 .. B Fu eelam tub ge e-------------
s tora ----------------------- -- b-
- 4. Liquid le solid waste storage --- /
l J. Health Physics
- 1. bampl e r emov al ----------------- /
2 . SOP ' S ( li s t ) ------------------- /
- 3. Excursion or incident monitor -- 7 N
- n. Film badge placement -------. /
b . O th e r - - - - - - - - - - - - - - - - - - - - -- - v
- 4. Film badge, dosimeter records -- /
V
- a. Staff ----------------------
b . Stud ent s -------------------f /
c . 3u e s t s - - --- - - - -- - -- - --- -- - /
d . 1:ir,ht watchman -------------- /
- 5. Possible detection of fuel .
j gp el e:n ent rup tur e ----- --- - --- ---- /- -
2
- 6. Radiation survey ------------- 7 / -Dates: 8+h.jsg p/21/vf #[3 feb /2th/[so
- a. P eriodic swipe te st s ------- /
- - 8 85 b . P o ol w at er --------- --------- er.
c . In s i d e air - ------ -------- -- /
d . O ut s i d e a ir -------- ---- ---W.A ,
- e. tie.utron level ( sub-critical - V.A
- f. Fisc. items ( lis t ) --- ------./
~
(lo " W & ysz .icle - -:- p- - V .-
h(
- 7. Emergency box (Fhysics Bldg.) -- /
gqq g General com=ents: The evertl] oneration cf the reacter f acility is er. 11 ant. In this I weule include reactor start-up, racond keepint and cv r.bility of record s, heure-keenin ;, eve #essional ettitude of the ste#f, e-p g.( I would like to enke severe.2 connents. These Pave been discussed with t ecricte staff r.cnbers.
- 1) Lately there hr.ve been r.cre than the usuni "sourieus" rundrwns and/cr scrams. Remedici measures are in progress end it may vary wil] be that the su ner maintenance pre.rc- wi)) trke care of the treblem. I trink thst in the fall spec'al attention sheuld be q$ven as to 'rhether they still occur. I don't see that they, in cny wey, endanger the safe oper$ tion of the reactor but t)ey are e nuisance.
(2) The semi-annual che:k cnd report woe started Jan.10, 1993 but at th's date (rcy 16, 1983) has net been cercleted. This needs to reviewed in the Fall 1963 independent audit.
, d 4
- Page 5 b (3) One week the weekly check was not made but a sheet inserted at the oppropriate week explained why not--excellent procedure.
(4) The Daily Facility check was not done in the usual manner, nor r2 corded, during the week of May 9. (J. 7.'112iams who usually does this was on vacation.) Someone should have been assigned to make '
the check.
(5) I'm somewh.t disturbed in thet the basement floor is wet. I understand the building leaks. gj Health physics records are in good order. Ray Bononiseems to be "on top of things".
Signed: (D, . h, Copy to: l Dr. A. E. Solen 1 Nuclear Renctor Facility Dr. N. L. Nord Chairman, Radiation and darety Committee 3-3 Chem O
+
l
- Suecial 1;uclee.r rateric1( ( 2"3) l Position Name l Reactor Director --- -b ---- W-
%-.o Reactor Supe'"?i@x " -- ---------
Sul: Custo'dian - -
- 1. (See p. 2) Procedures reviewed annua 137 by the Reactor Supervisor:
Date Name Gn < 9 ('l2 L. Gt W .
- 2. SNC Records: '7here kep,t? $& M
- ^ ^ ^" }
(1) Position and/or change of rosition of non-irradiated fuel: W (2) Position und/or change of position of irradiated fuel: M (3) sun'. receipts: hy h^ - 1 M '
(4) SNC shipments: M (5) Semi-annual L:nterici Status Reoort:
!!.ost recent previous report: Date h.430.19P2.
Current recort:
Date M i (5 g'3 (6) Annual Physical Inventory (SUM status log): C/(
. Date Previous report: 1o,1982 Current report: J IF,l9 73 (7) SNM loss, theft or sabotage reported: M '
Date To whom reported (Director Region III NRC)
(8) (See p. 5) Violations of Written Procedures:'h ce R- -
(9) SN!.' Internal Control Areas: /
Dry storage aren (basement): FK Rsactor:
(
Containment building g c- - - - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _
. 6 i Operator Requalifiestion During License Period A. Examination Review Sheet ( Annual exam -- usually in summer)
Name of Operator License number Exam cates Comments 5-year and date record 1
S O P ~ 3 0 0 u 1. MM .
- d. .
6, i1S2.
MM o p - sm 3 <
I. M 4, 9 r3 b L A%f7tz.
M 4.f9 F 1 d' O p._ 3co5i e
Q (4, ( 7 (2.
4*
cP-3864+ l 0- Y 4,t9 V- ,,'oga.
~
B. Ferformance Evaluation (Semi-annual)
Name of Opernter Evaluation Date Comments 1.
. m a
2.
Y de d-h {lfS1 M s.
C . S a>L~. nc a a t,m 2-R 4.
D. % &c.e. 2,19 2 3- %
C. .n the Job Training: Pro _m sa Re (Annual Summary)
- (Notebook kept by the oper_ ,or.) port Name of Ooerator Annual _ummary Date Conments 2*
W W 1991 w()
OM 4.
mac. _ Cu - % - _ _ _ _ _ _ - _ _ _ _ _
l l
(
APPENDIX B .
1
C 0
I Semi Annual Check List l
DEL re -
Date Commenced Date Completed - '"#^' .' "/ > J i -,
o<+!4 Total Hours on, Hour Meter / '
'. 6
- 1. Vacuum Tube Test and Clean Chassis Initial
- a. Log N Power Supply (1) Cleaned chassis Date MLA k'53 / E /// $
(2) Tested all vacuum tubec /'/ cf'/ /'3 Replaced: tube # tube type f ' f-
, ', ', U ' '
t I ,
l l l
h (3) Additicnal Cor.cente i
- b. Linear Power Supply Date (1) Cleaned chassis (7 c/// 3 .
(2) Tested all vacuum tubes /r' '/ / / 9 Replaced: _ tube # tube type s f
'\ .1 y)V' L (3) Additional Co'mments .
2
- c. Safety Amplifier Date DEC . :;,..
4 //,'O (1) Cleaned chassis (2) Tested all vacuum tubes C /*I19 Replaced: tube # tube type I
s ,niv k
(3) Additional Comments
- d. Area Radiation Monitor Date..'. '
/t ' p '3 Cleaned chassis (1)
(2) Additional Comments c-
- e. Micro-Micro Amr.eter Date :it '
(1) Cleaned chassis , . . *3 (2) Tested all vacuum tubes .W3 l
Replaced: tube
- tube tyre
-. .A
[ /) "
.j p I v
{
(3) Additional Comments
- f. Fission Preamp Date OLO s i' ' t (1) Cleaned chassis and inspected M.N'/_"3-(2) Additional Comments
3
- g. Public Address System Date - . -
(1) Cleaned chassis [ -/773 (2) Additional Comments
- h. Log Count Rate Recorder Date ;s c : &:
(1) Cleaned chassis (< 27 7 l
(2) Tested all vacuum tubes Replaced: tube f tube type
. n {/
A (v / ~
Vl
- l. i (3) Additional Comments
- 1. Linear Recorder Date ,
(1) Cleaned chassis' 'l 2 7' .'d f
(2) Tested all vacuum tubes /- ,70 Replaced: tube # tube type
, ,16
,ll l Q 'l *
- f (3) Additional Comments
- j. Period Recorder Date DEC: 1333
( /bl//'[)
(1) Cleaned chadsis (2) Tested all vacuum tubes M/ ' ' L/ )
- Replaced tube # tube type
,.oY
,, .yv (3) Additional Comments ,
L 4
- k. Log N Recorder Date nr r' ' I (1) Cleaned chassis /kj7 (2) Tested.all vacuum tubes [///Jg._3
{ Replaced: tube f tube type
- /]!,,, l0 , ,-]'l l
(3) Additional Comments
( 1. PAT 60 Date DEC2 A (1) Cleaned chassis / / /'//
[.'Z///1 5
(2) Tested all vacuum tybes Replaced: tube # tube type 1
/,
f
/ \ i t. i v l
(3) Additional Cecments f m. Safety Amp Preamp Date bd j (1) Cleaned chassis 8
( (2) Tested all vacuum tubes [if '/Y' Replaced: tube # tube type tl : 11 $
/ ,I y'7l i'
(3)' Additional Comments
l 5
- n. Regulated Power Supply Date DEC i me (1) Cleaned chassis [O/9
{ (2) Additional Comments
- o. Conductivity Bridge Date DEC r-(1) Cleaned chassis [1'/'2 (2) Additional Comments k
- 2. R lay Test Date DE C :. '- u. :
{ a. Console relays tested and replaced as per SOP 815 / *+ /, /..) O
- b. Additional Co m ents / ad'ajf
- - W ec
' Y' w u A l
- 3. Detector Resistance Date '
- UF4
- a. Safety 41 Value
/
(1) Signal to ground _ e . .-
/77
~'
(2) Positive to ground 2 ,<~ >; *'A . A.7,-** .,
(3) Additional Com.T. ants l
ll-
- b. Safety 42 Value jg'/c Initial -,
(1) Signal to ground #x<u 'E'# /. < / e ' ', , )
(2) Positive to ground e v'e * /' [ N /]
(3) Additional comments l
1
6
- c. Log N (1) signal to ground #f Y /0 [#M N
( (2) Positive to ground 7 S ///' ' 3 /26fd (3) Negative to ground #. '7 V// ' 7 [W//.I l (4) Additional Comments
- d. Linear (1) Signal to ground ~/ / /C ['//73**
(2) Positive to ground J. / X/c # 7 /T,f/[J (3) Negative to ground /, 4/ v/ v '# /2d7[d l (4) Additional Comments I
4 .Colibration Checks Note Any instrument found to be out of calibration should be
, realigned in accordance with its technical n.anual.
I ,
l -
A. Temperature Recorder Date I 19 # 1
- 1. Reading 9 Thermometer Recorder 1 soor so #/
l 2 soor 9 n 's 3 eonr fM'S l 1 140er /#4 # #
2 140*r toe'E 3 -
14o*r /+f ## -
Note: All readings should be 1 lor ,
- 2. 135'r Interlock Trip reint Initial
,_ /.7 4/ &b
k 7
- 3. Log Count Rate Channel Date DEC2i 90
- 1. Pulse Generator
- Meter Recorder Initial 10 )O /) (26f//7
- ^
l 100 -
Q (-. /oo C&f-)f) 1000 / A n d) j !/ei c) fil?/j
/
10o000 / /18 / 26) /b///) Ol9?O
, Note: All readings should give .7 to 1.4 ratio of true-to observed readings.
- 2. Additional Conenents k
l 1
C. Linear D, ate DEC 2 0193
- 1. Keithley Meter Recorder Initial ,
6.66x10~' A,60 /46} (*@/0 .
[ 2.0x10-5 J. b /fa 4 n #/3 6.66x10~0 /.'7 /P/ C}r f/l//$
2.0x10~0 A,O //1 A l)
' , . D grP 6.66X10~ 6P /#4 #2 M.'/J'/'Y 2.0x10~' 4. ,P /t)/d? fcj//3.
6.66x10~8 44/ //'s d o
6 t//A *
- 2.0x10 ') O /0/$? &/D3 6.66X10~' 4, 9d /M / #4' X'O'// S 2.0x10~' ,1. b // ? Y & #'$
6.66x10~10 6 40 Y8 M () d'si A/* */*3 2.0x10~10 A.D & W Notes From 10~3 to 10~' the 9 ff 'Io ' 8 v//3 overall accuracy should be better tha'n 24 of full scale.
From 3x10~' to 3x10~13 the overall ac'uracy c should be better than 44.
- 2. Additional Comments ipj%)/,f Gk'/'?4$D Swr 9 *'00 M b A' I N '
I 8
D. Log N Late Ud *
- 1. Meter Recorder Keithley Initial 100 ' ' &' y ,i ith.y fdifyg}
10 t- xy.;;;)
l ? ~ 'v.
i?
1 [ v< i,, ('///p 3 0.1 ,'#^} t' yi *v ,9 ; t A
.01 !? . ? i g' . {~ v , m - ? / ? ,,,jj
.001 l' . / / / / ,* vi ~'" A/;) 3
.0001 //> y '" 6,p p
/> ? f t i .,
Note: The ratio of true-to-observed readings should be between 0.7 and 1.4.
- 2. Additional Comments
- 5. Rod Indicator calibration .
Indicator Reading Actual Height I. II. III. Reg.
, ' .p.,
\ 1" } ' l'. !
- 6" . ! -
12" i-18" /. -
24" 1. . :..
- 6. Fire Alarm Check Ot*t JAN 1 ' 10.
- a. Cleanec syster. cor.tainert
.'I
- b. Changed Batterier /*
- c. Checked rull statier.s ,
- d. Checked heat detectors *- *
- ' ' / *
- e. 4 Checked anoke detectort 'I'
- r. All indicator la.ps operate .' ',* *
- 7. Security System Check Date M.") F .'
- a. Door Sensers # ; ' ' '
- b. Motion Detectors .' ...
- c. Duress Alarm / * * '/ ,,
- d. Control Modules Date d. . .
(a) Power Supply (at UMR Police orrice) /
(b) Control Module l'
@ '- i /ki.i .s
. .t i. . . .i j . ' * > ' ', t , ' .. . I s ,' it., . s t s *'
.t
. ;,. ,. ,, , , 3 , .
(,1'/, ;s.* ll4 ;u .. A}.." . .* *
- V A s *
.( ! G'? ? '1
. . i .
- Y' .' ) * ' A * * '-
- Or 'E ,
, 9 Datek,3I t't$. 19 k I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operatinE l
staff.
Director or Fleact LManager
(
h /U l l l
l 6
T 4
r l'
, i l{ SemiAnnualChefkList Date Commenced JUL 2 51983 :
( Data Completed SCT 3 . LEU Total Hours on Hour Meter h,V // R f l 10 Vacuum Tube Test and Clean Chassis Initial
- a. Log N Power Supply jlll 0 f 198-(1) Cleaned chassis l / -YEN (2) Tested all vacuum tubes /I////h Replaced: tube # tube type
(
1/J/'I - <A K / .
l Il f STS S'l I
(3) Additional Comments
( None
- b. Linear Power Supply JUL 2 51983 (1) Cleaned chassis fff$/$
Tested all vacuum tubes b'Y.$$,
(2)
Replaced tube 6 tube type 1//e C15/
(3) Additional Comments i
G o
m
(
l JillY !. G?
- c. Linear Pulse Amplifier ,'
( (1) Cleaned chassis , t (2) Tested all vacuum tubes Replaced: tube 4 tube type I )
l l (3) Additional Comments )
l 1 Nons Jul
- d. Scaler Timnr /,/ ,f,fj (1) Cleaned chassis ,, b.,yj (2). Tested all vacuum tubes Replaced: tube 8 tube type,
-4'?:-1v'.
( 'o I .
(3) Additional Comments JUL 2 51983
- e. safety Amplifier N/8)
(1) Cleaned chassis ~(h'//73 (2) Tested all vacuum tubes Replaced tube 9 tube type
',,I!YLd'$..
(. .
9
L
^
( -
(3) Additional Comments
((
t
- f. Area Radiation Monitor '
[ (1) Cleaned chassis M (2) Tested all vacuum tubes
( Replaced: tube $ tube tyce (3) Additional Comments YLhdCkTc ow f
- g. Micro-Micro Ammeter jgt 3,1993 h193
[
L (1) Cleaned chassis /yf?3 4 (2) Tested all vacuum tubes l Replaced: tube 9 tube type
{
l I .
l
[
t
( (3) Additional Comments
(
JJ'L t, lis]
- h. Fission Preamp r (1) Cleaned chassis and inspected /)
i (2) Additional Comments -
,.s 6
a
'( -
- . 3 I . ..
L
- i. Public Address System JUL 2 61983 #Y/
(1) Cleaned chassis ,
f[ k (2) Tested all vacuum tubes Replaced: tube 9 tube type
.' ns
'(
{
(3) Additional Comments
{
.f SC I > lb
( JUL 2 e 13?3 -
- j. Log Count Rate Recorder //-87 'd, (1) Cleaned chassis A,-///3 f (2) Tested all vacuum tubes i Replaced: tube 9 tube type Ykinx
~"
(
l (3) Additional Comments
( k. Linear Recorder [/h (1) Cleaned chassis '[!'f,f/9 (2) Tested all vacuum tubes Replaced tube i tube type (Allt , -
,c
(
(3) Additional Comments
I/7 L 1. Period Recorder (1) Cleaned chassis M N ?/ )
(2) Tested all vacuum tubes Replaced tube i tube type o
l V$]tmL u
(
(3) Additional Comments
( m. Log N Recorder 6/I (1) Cleaned chassis d'4 '///3 (2) Tested all vacuum tubes
{
Replaced tube 4 tube type
, l u~L
( t,1 (3) Additional Comments
- n. PAT 60 JUL 2 71983 /II (1) Cleaned chassis [/'/@/)
/
(2) Test.ed all vacuum tubes Replaced tube 9 tube type sfk/q /
I
( .
l
(3) Additional Comments
- o. Regulated Power Supply //
(1) Cleaned chassis .
(2) Tested all vacuum tubes Replaced: tube 9 tube type (3) Additional Comments
+ &k rip i
- p. Conductivity Brigge R 2 7 M3 -
- /
(1) Cleaned chassis. M
{
(2) Tested all vacuum tubes
- Replaced: tube 4 tube type Nh 3?We l
- q. Safety Amp Preamp (1) Cleaned chassis JUL 2 7 th43 8/d (2) Tested all vacuum tubes /24673 Replaced: tube 9 tube type 4L e
1 (3) Additiona'l Cosaments i
l
I p
JUL 2 01923 4 2. Relay Test
- a. Console relays tested and replaced as per SOP 815 ['M
- b. Additional Comments A y h,*og fqo pu p Q, vn hwg., aq . 2d i e v \cck
- 3. Detector Resistance gg7 3 1 1983
( a. Safety il Value (1) Signal to ground of . 4 X/4 " [/#3 l (2) Positive to ground B . 4 7v V/a ## MM/3 (3) Additional Comments k
OCT 3 't 1393
- b. Safety 42 ggvalue Initial (1) Signal to ground f j .y / e # N/// 'Y (2) Positive to ground to. 3 I / p # " /64,'8 (3) Additional Comments
'i
[ DCT :
- c. Log N
{( (1)
(2)
Signal to ground #, d//a y /4 #
A'r,'Y/t #5 4///
Positive to ground M//#3 (3) Negative to ground J7,8'X /8 ' A /7&MMI (4) Additional Comments l OW : ' I
- d. Linear .
{ (1) Signal to ground /,/8 f/4' //
(2) Positive to ground .T . 7 l'/o ' A /// /#77 (3) Negative to ground 4 , 7f1/0 '^ / 26 ;; d (4) Additional Comments
- 4. Calibration Checks l Note: Any instrument found to be out of calibration should be realigned in accordance with its technical manual.
{
f C' 'S G" '?
A. Temperature Recorder -
- 1. Reading 8 Thermometer Recorder
{( 1 9a4 96oF /. 9 /'
e l
2 WF '7D ' M 3 9
^h'* F 1J ' #
1 -
$F /24'S 2 lNor 13 / 'f 3 [$5 F / 'l 9# /
Note: All readings should be 1 l'F
- 2. 135'F Interlock Trip Point Initial
/]$ / hrik'/b B. Log Count Rate Channel l 1. Pulse Generator
- Meter Recorder Initial 10 // l6 dij//$
l 100 jpo Ibf N /ys) 1000 l6sa j (,)p /'&f)/}
( 10,000 jyp ppppe !k//)]
Note: All readings should give .7 to 1.4 ratio of truc-to l . observed readings.
- 2. Additional Comments C. Linear
- 1. Keithley Meter Recorder Initial <
6.66x10~0 d. A e /A d Ocp/f3 2.0x10 ~I E :) /J 6 41,'/3 6.66X10-6 g , ,_ g ,,g p ,,,,3 2.0x10-6 y,g j,y g ggjffg l 6.66x10~' ].AL /n // fi ts/91
~
2.0X10 f. // /d O 8// /3 6.66x10~* /,.ld /d D $ sly 13 l
2.0X10~' G,O /A 0 (E6 '//7 6.66x10'* }.8$ }d /) $tf/f]
2.0X10~' 2. /1 }D / / Pr)// 5 1 6.66X10~10 $,/s/, //) % fry'/ f]
( 2.0X10-10 4g Notes From 10~3 to 10 ~8 jg y g,jjp
the overall accuracy should he better than 24 of full scale.
-g. '
.....ne - - ---4
From 3X10"I to 3X10 ~13 the overall accuracy should be better than 4%.
( 2. Additional Comments AUGJ' 21993 D. Log N
- 1. Meter Recorder Keithley Initial 100 /6' O . o 55&> 'S (Eff3 10 ja E~X/o~' D6'b 1 1 S~X /n 7 0*'i.Tf8
{ 0.1 ty . I d X /0 ' '~ 0/N/3
.01 O o 0t 6 X/o
- Y 0103
.001 0.Oe/3 Cf/O'" G/E/3
.0001 00oo1 .S~X / O ' ~ " (W *J Note: The ratio of true-to-observed readings should be between 0.7 and 1.4.
- 2. Additional Comments
- 5. Verification of Rod Drop Times ll> ' ' I5 7 '
(
- a. Rod # Rod Height separation Time Rod Drop Time (inch) (< 50 msec) (< 600 mcoe at 2 (-
l 1 6
) , 4 . , . , u ,; & 9s ,.. u.
1 ,s .u ., . . . . .; . . .
1 )P sf 3 < . ,,.e ,.
1 ?a j/ 9f' . , , , <:, e j 2
- 7. $ .n, r,e _; y 4 . , , , . ; .
2 /7 :? t. /. , , .. . .c 2 /2 _
4 ? t, r o , e. g 2 AN _ 6' 9 t ' s ' ' De 3 6 A 8 '? x re e 3/t -rn u e l 3 /.2 2 Sv > > , , f, -
3 /P 4'4A u,>;n.
3 M fj /' w &c
- b. Date performed ./f/w *?/ /9/3 Preformed by dM
[dS E6%
Director or supervisor .
\ . .
l
^
_w
L
- 6. Void Coefficient Determination f a. Value of void coefficient t 4K/K/cm 3
- b. Calculation performed by
- c. Date performed
{
- d. Director or Supervisor
{ 7. Temperature Coefficient Determination
- a. Value of temperature coefficient t A K/K/*F
- b. Calculatione performed by
- c. Date performed
- d. Director or Supervisor
{
8 Rod Speeds Time (Sec) I. II. III. Reg.
{
0-24" M yl0 2 ke s9ec Ju , St%. JA%! / J h'-
{ (3) Additional Comment Date .' 2" ' ' Performed By @'// $
- 9. Rod Indicator Calibration Indicator Reading 'IUL <' e li"n
{ Actual Height I.* II. III. Reg.
1" / / / /
6" l is l- f.
. \
12" /_Q /A /'2 ,A
' I 18" / Tr / f- /P / P'
[
24" l)L) 94 S4 ,:%I
- 10. Results of Annual Control Rod Inspection
{
A. Control Rod Number 1 lop sf tid Anor inc*sMYp7~ .
- /o/* of rs) fle we sor &*U57 dr//oe ,f rsk (r~/ & em c.rnh 7
'{ Poi //e h 4 9 .
Ts,, ,; e,x .sn ,,nar & a e4+~ o d. 1 I;r??u ?w fcee [t'e k hty* Af ?
l 11.b Control Rod Number 2 5p s$ ro ) $-m e on Mr n /Ac T N rri. dale a C ro k k o e r- r n e e n To u 7 ' \ Su N ~ rS tok 4 e /-b o m o r n kwa T
# " A t"" ri@ew $ , /.94 Tem e d r/T rc hacklist Procatira men tet.3TARTUP CMEOK LI%f Page 2
- 17. Scater on Oa.nt and u .eting
- 18. Cheva P6ssten Cmaster Response it. Ptssion Cnaccer on Insert Liett and Count late Greater tnan 2 CPS
- 20. Test Log 4 pec areer #essanse 21 Test PortoJ Pecorcer Response
( 22. Magnet Power CA. Scras #eset. Board Asset
- 23. Magret he. 1 Currents tpeas to. J Valwet) 40. ] l Jo. Creca tic % Raise 8048 ) in.
Power Pwan ' test" Button Scram on !arety amp Panel 2$. Cr.een Los hl palse RoJs ) an. ( Perted Non. Select Sutten to operative Scram Centerate and 15 see Perted #andown
- 26. Test Manwal patse Reis 1 in.
Scree Pusn Manvat Scrae
- 27. Test annweetator. All Llante on
- 28. All Pagnet Contaete Mate, Reg. Sod on Insert Lielt
- 21. Prepare Nowrly and Permanent Loge
- 10. Reise Reds to 4 in., Record flee ll. leepect Core
- 31. Announce Intention to Start
)). Intended Power Leve!
14 Pro.Startwo Ceets Completed ( is, senter coerster's initiene noe.r, sosone _
> j @% & %A.o n.
APPROVED BYr 4te, art 09 ton 4RITTEN BY: iciran tina '/2a 2.w/ (
l UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'1VR [ STANDARD OPERATING PROCEDURES S.O.P.: 103 REVISED: 2-2-84 PAGE 1 0F 5 ( TITLE: Reactor Start Up Procedure A. Purpose To insure a safe and consistent method for starting up the reactot from a clean or high residual condition. The ( reactor will be considered clean if shutdown for more than 52 hours. The reactor will also be considered clean if { power levels within the past 52 hours have not exceeded 20kW for 1.0 hour or it's equivalence. B. Precautions, Prerequisites, Limitations
- 1. SOP 102 shall have been completed and approved by the SPD on Duty prior to commencing reactor startup.
- 2. The SRO on Duty shall remain in the control room (audible and visual contact with console operator) during startup, power-change and shutdown of the reactor.
- 3. There will be at least two, but no more than nine people in the
( control room during reactor startup, power change or shutdown.
- 4. When the reactor is in a stable condition there shall be no more than nine people in the control room at any time. One of these individuals shall hold a valid Operators license or Senior license.
- 5. The console operator (licensed PD or student under supervision f of SRO) shall control all reactivity changes to the reactor by direct manipulation of the controls or by directing the ma-nipulation of experiments being conducted at the facility.
(
- 6. Only a licensed Senior Reactor Operator may terminate the action of automatic reactor controls. If a scram, rundown or rod withdrawal prohibit occurs with a licensed Operator or student at the control, the permission to terminate the automatic control or a restart of the reactor can only be authorized by a licensed Senior Reactor Operator.
7 Nitrogen diffuser operation is required for reactor power f greater than 20 kilowatts. This requirement is at the f WRITTEN W get gy mmD M 3,ks' , , , I
( ( UNIVERSITY OT MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES ( S.O.P.: 101 REVISED: 2-2 % PAGE 2 0F 5 TITLE t Reactor start Un Procedure discretion of the senior Operator on Duty and may be suspended for special tests, experiments or equipment checks. The reactor ( bridge radiation levels shall not be allowed to equal or exceed 30 mr/hr.
- 8. Building exaust fan operation is required for reactor power
( level of 200 kilowatts or when the constant air monitor recorder reaches a value of 500 counts / minute. Exhaust fan operation should continue af ter the reactor is shutdown until a less than 500 counts / minute reading is obtained or until the reactor building is secured at the end of the day. See SOP 505 for securing the reactor building. ( 9. The safety channel meters s..euld tegin to give a definite Fe?. positive indication when the reactor power is at about 5 kW. ( 10. If the desired reactor power is greater than 20 W, the reactor shall first be taken to 20 W, (or some similar low power as ( specified by the Senior Operator on Duty), put in automatic control, and the hourly logs taken. The Reactor Operator shall check that all instrumentation is functioning properly.
- 11. If the desired reactor power is greater than 20 kW, the reactor shall be taken to 20 kW, put in autenatic control, and the hourly logs taken. The Reactor Operator shall check that all in.
atrumentation is functioning properly, especially the safety ( (power) channels. C. Procedures
- 1. Clean core, shim rods at 6 inches and neutron source installed.
- 1. While observing the log count rate recorder for any un-expected increase, withdraw all shim rode to shim range.
Do not exceed an rod position indicator value of 12.5 in-ches. The shim range indication lights (yellow-below ( rod position indicator for each shim rods) will come on WRITTEN BY Karen Lane .er, at APPROVED BY a r 's en
( UNIVERSITY OT MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.t 101 REVISED: 2-2-84 PAGE 3 or 5 TITLE t Peseter Start Up Procedure between 12.0 and 12.5 inches.
- 2. While observing the log count rate recorder for any un-expected increase, withdraw the regulating rod to 15.0 inches. Note the increase in counts per second on the log
( count rate recorder.
- 3. While observing the log count rate recorder withdraw the shim rods an additional 1.0 inch. The console operator
{ should not cbtain a slope of less than 1.0 (angle of less than 450 from horizontal) during or af ter rod withdrawal.
- 4. Monitor the value on the linear recorder. If the reading reachos 80% of selected scale, change the range selector switch one position counter clockwise (up scale).
- 5. Continue steps 3 and 4 until a shim rod height of 10.0 f inches is obtained. Pause for a short amount of time be-tween each 1.0 inch withdrawal, (approximately 5 seconds) .
f 6. While observing the log count rate recorder withdraw the shim rod an additional 0.25 inches. The console operator should not obtain a slope of less than 1.0 (angle of less than 450 from horizontal) during or after rod withdrawal.
- 7. Continue steps 4 and 7 until the reactor goes critical.
Pause for a short amount of time between each 0.25 inch withdrawal. When the log count rate recorder shows a ( steady constant increase in value without shim rod with-drawal is an indication that the reactor is critical.
- 8. Observe the log n recorder and the period recorder for indication that they are within their operating range.
( The period recorder will indicate a period of less than infinity (c) and there will be an increasing power level indication on the log N recorder (vertical line). f . WRITTEN BYt y, p,n t,n, "$b,, .h APPROVEDBYah)
{ UNIVERSITY Ol' MISSOURI-ROLLA - NUCLEAR REACTOR ( STANDARD OPERATING PROCEDURES S.O.P. 101 PEVISEDt 2-2-84 Pact 4 01 5 TITLE t Retetor Start Un Procedure Typically the period and log N meters and recorders will Rev. ( begin to provide positive indications when the log count rate recorder is at approximately 3x10 3.
- 9. When the log count rate recorder reaches full scale (10 4) withdraw the fission chamber until an log count rate re-corder reading of 10 is obtained. Prior to withdrawal of the fission chamber the operator shall have indication of
( reactor power on the linear and log n recorders. 10, Establish a reactor period as requested by the senior operator on Duty, (or approximately 50 seconds) and untinJe ( the reactor power increase to the desired power level on the linear range selector.
- 11. When the linear recorder reaches approximately 984 a
" green" Auto Permit light will come on. This will allow f the regulating rod to be placed in Automatic Control (signal from linear recorder) . When the auto pemit light occurs,
{ insert the shia rods in " bumps" until the period recorder indicates a reactor period of approximately 400 seconds.
- 12. Allow reactor power to increase to 101% on the linear recorder and place the regulating rod in automatic control.
This is done by placing the " Manual Auto" switch (below the auto permit light) in the auto position. When the " Auto" light comes on release the switch (return to neutral) . (
- Note: This step assumes an auto setpoint at 100% of linear recorder, for values other than 2004 the shim rod insertion should occur at -24 of setpoint and " auto" selected at +14 of setpoint.
( WRITTEN SYI karen Lane '..'8 de' ' ed APPPOVED tp,,BYea.n pogon w&n.
( ( UNIVERSITY OT MISSOURI-ROLLA - NUCLEAR REACTOR STANEARD CPERATING PROCEDURES S.0.P.: 101 REVISEDr 2-2-84 PACE 5 OT 5 TITLE t peneter Start Up Precedure
- 13. Insure that the regulating rod momentarily inserts (white light) and is satisfactorily controlling reactor power at the intended setpoint (red pointer on linear recorder) .
- 14. Roset the Manual Operations Annunciator.
( 15. Record the time from the console clock in the Hourly Log (time at power). ( 16. Infor1n personnel of the reactor power level on the but1 ding public address system. "The reactor is at a power level of watts or kilowatts". ( 17. Position the fission charter to achieve a log count rate recorder indication of 102 (mid scale).
- 18. Complete Hourly Logs in accordance with 50P 104.
( ( { { ( ( l 1 o m cN av, x.,.nis,. E . s;. m n0vco ivi liW,htst'~ l
( UW1VERSITY OF M!ss0URI-molt.A - WUC1.EA't itEAC1VR ( STANDAAD OPERATING PROCEDURES 5.0.P.I 104 REVISEDe ,y,p9,gi FAGE i 0F , TITLEI Perm.trent Log, Hourly Los and or argttonal Dses A. Purpose To provide for records of facility operation and major ( maintenance. Any work affecting the reactor, its operation and specific une during operatlon must be clearly and legibly described in the Permanent Log book. ( Hourly logs will detat1 spectfic instrument readings while the reactor is in operation. ( Precautions, Prerequientes. or Limitationet B.
- 1. All log entries are to be made with times recorded from the Console Clock.
- 2. a) The reactor ooerator thatI make enteium in the log book when the reactor to at a stable power level with the Reg Rod in " Auto", or b) the reactor ie at a stable power level, the Nog rod tu in " Manual" and an operator attittant it mVallable to record log entries (eee GOP 102 or 103 for other cotidi t i one
( prior to log entries). f 3. The Gentor Operator on Duty to responsible for all operational logs. Request his asetetance if in doubt about log enirist.
- 4. All scrame and rundowns shall be noted with an
[ explanation of the cause and corrective acklott in l the Pereanent Log.
- 5. The Gentor Operator on Duty will review all log f entries f ollowing completion of daily operatione.
- 6. The Senior Operator em Duty will report any abnormal conditions entered in the operational lege to the Meactor Manager.
wKlTTEN SYi riet pgeen ////[b APP 90Vic tYi (,I,Y (fply
1 L I L UNIVERSITY OF MISSOURI-IIOLIA - NUCLEAR REACTOR STANDMtD OPERATING PROCEDURES S.O.P.: 104 REVISED: 37,pg,g, PAGE 2 OF 7 [ TITLE: Permanent Log, Hourly Log and Operational Data { C. Procedure ( 1. Hourly Log Entries
- a. The hourly log sheet will be dated and each operator
(- (student, trainee, etc.) will place their signature in appropriate spaces provided. [
- b. A new hourly log sheet will be started at the beginning of each operational day, or when all
[ available columns have been filled during the current day of operation, (i . e. a new hourly log sheet is not required for each startup checklist SOP 102). {
- c. The following procedure steps correspond to the numbered steps on form SDP 104 Time from console clock, based upon 24 hour time.
( 1.
- 2. Operator at the controls, initials.
- 3. Reactor power, as required by SO on duty.
- 4. Linear level recorder reading in percent.
- 5. Linear Level Amplifier Selector Switch scale.
- 6. Reg Rod in " Auto", ygg or og.
{
- 7. Log N Recorder reading in kilowatts.
f 8. Shim Rod #1 Rod Position Indicator Reading to thtgg places ( i e. 21. 2 )
- 9. Same as Step 8 for Shim Rod #2.
{
- 10. Same as Step 8 for Shim Rod #3.
" . an 6.'. 2 'b c W - . WRITTEN BYt Carl Barton yf#r -- APPitOVED BY: Albert E. Bolon
k I L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IVR STANDARD OPERATING PRCCEDURES S.O.P.: REVISED: 12 28-83 PAGE q OF 104 7 TITLE: Permanent Log, Hourly Log and Operational Data
- 11. Same as Step 8 for the Regulating Rod.
- 12. Check Radiation Area Monitors (Reactor Bridge, Domineralizer and Beam Room) for approximately the same values observed during completion of startup checklist (SOP 102).
( 13. Record Reactor Bridge RAM reading in mr/hr. 14 Check Magnet Currents for approximately the same ; (- values observed (and recorded) during the startup ; checklist (SOP 102). l f 15. Reactor Power Level indicated on the #1 Power Range Meter in percent. This mdter corresponds to ! 200 kilowatts at 100%. i
- 16. Same as Step 15 and #2 Power Range Meter. j i
[
- 17. Record the time at which a stable power level was i I
( obtained in the Permanent Log. Other entries to the Fermanent Log such as samples being irradiated, etc. should also be made at this l time. (See section 2 of SOP 104). ( l
- 18. Record the Reactor Inlet Temperature as displayed on the Pool Water Temperature Recorder.
- 19. Project or Class Number for which the reactor is being uti1i:ed.
- 20. Core Loading Number as given to you by the Senior f Reactor Operator on Duty.
- 2. Permanent Log Entries-
- a. All entries in the Permanent Log shall be preceded by the date (Use the date stamp).
- b. During completion of the Startup Checklist (SOP 102) use the Check Out stamp and complete values as they become available. To the right of the purpose the WRITTEN BY: Carl Barton .
APPROVED BY: O'M & f- Albert E. Bolon i
s I L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANIERD OPERATING PROCEDURES S.O.P.: 104 REVISED: 12-28-83 PAGE g OF 7 TITLE: Percanent Log, Hourly Log and Ooerational Data { nature of the experiment should also be shown. See ( the example below: I [
,e e e Ti. .e Check Out Siarted
[ (cc T .e Rea e 6 Ir.f.cs A'i ~ 4 ._ _... I #l:059 A ; ^ ' 5 '"' " ' ji. , Tim:- Reac.'or M t.. o
- kw I
( c. Reactor power changes are made SOP 103 and entries are made prior to the start of a in accordance with ! l power change and at the new stable power level. The example below indicates Permanent Log entries [ for a power change including shutdown of the reactor: 1028 Reactor started to 600W. 1030 Reactor at 600 W. 1035 Reactor shutdown. ( l I y d. The Sample-Experiment stamp is used to indicate the ( irradiation of a sample as a Permanent Log entry. - This stamp will be used to indicate the production of by product material. The example below indicates ( the use of this stamp. l (
^
WRITTEN BY: Carl Barton APPROVED BY: M. h U/ k[.. N E . Bh
s I UNIVERSITY OF MISSOURI-ICLLA - NUCLEAR REACTOR [ STANDARD OPERATING PROCEDURES S.O.P.: 3ng REVISED: 37,pg_gg PAGE 5 OF 7 TITLE: Perannent Lee. Houriv tog and Oeerational Data [
~
EXPERIMENT OPERATOR Meo4/ ch3' d - CO2E CR FACILITY EXPRIMENTER AND START STOP TOTAL [ POSITION EXPERIMENT TIME TIME TIME ( Bau fai&Y %.y k .wd 113c 13c0 3o nin b- V 0 wOMEt(2) ( Note: The number in parentheses () indicates the l number of samples. l
- 3. Recorder Chart Paper Entries f
- a. Date all 5 primary recorders in accordance with SDP
( 102 (startup checklist) and SOP 105 (shutdown checklist). f b. Recorder chart paper is to be replaced immediately after the current roll chart supply is used. During , replacement use the new chart box for the old chart l storage. Date both the old chart and all sides of ( the chart box. Place the chart on storage shelves adjacent to the control room. ( c. All chart paper is retained for a period of TWO YEARS except f or the Lgg_N_Ghgr_t which is retained for the duration of the facility.
- 4. Ventilation Fan Log Entries
- a. After receiving approval from SRO to start or stop a NRI m N ov c ,,.1 ,,,, s w S A>>=Eo or meMtn
L F L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IOR STANIERD OPERATING PROCEDURES S.O.P.: REVISED: 32.pg_gg PAGE OF 7 104 6 TITLE: Pe rmanen t Log. Hourly Loe and Operational Data building exhaust ventilation fan, complete the { requested information on the Fan Operation Log (i . e. t f time, fan #, power level etc.)
- b. Fan Operation Logs are retained in the Facility f
{ Health Physics files. ( ( { l ) ( . l ( l [ [ [ TRImNov c.r1 ea,te, w- ,,,mvEo .v: AMgy1,,
t [ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 104 ( REVISED: 2-2-84 PAGE 7 0F 7 TITLE : Permanent Leg. Hourly Log and Ocerational Data { UMRA HOURLY OPERATIhc LOC (Start a new form eaen day.) Cperator's Signature: (1) (3) (2) (4)
- 1. Time at Po.or
- 2. Operator's Ir.ttsals 3 Nominal Power (W cr Kw) 4 Linear Level Recorder (%)
- 5. Linear Level .:cale (Amps)
- 6. Auto Set tyes or eot
- 7. Leg N (Kw)
- 8. Shia Rod No.1 ( ancnes)
- 9. Snta Rod No. 2 (inenes)
- 10. Enta Rod No. 3 (inches)
( 11. Regulatted Rod (inenes)
- 12. Radiation Levels Normal 13 Record Bridge Monitor (artnr i 14 Magnet Currents Normal
( 15. Power Chamber No.1 (%)
- 16. Power Chanter No. 2 (%)
- 17. Permanent Lcg Entries
- 18. Core Inlet water Temp (*P)
- 19. Project or Class Number
- 20. Core Loading Senior Operator's signature at End of Day NOTE: Readtngs ar.all ee taken at hourly intervals or lesa ducir4 any reactor r n.
f Readinga anall also be taken af ter rescains power or af ter naving changed power level. Ajl1 scrans and rundowns sna11 De noted with esplanation of Rev. 2, cause of scras or rundown in the permanent log book. 2/1s84 _r , WRITTENBY:bac6 25. M c- M% % Carl Barton APPROVED BY: Albert Bolon I
t f L I UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACER L _ STANDARD OPERATING PROCEDURES ( S.O.P.: 306 REVISED: 12-19-83 PAGE j OF 3 TITLE: Estimation of Activity and Reactivity Worth of a 3amele ( A. Purpose The purpose of this procedure is to provide guidance for calculating the radioactivity and reactivity before - ( irradiating samples in or near the core. B. Precauttons, Prerequisites, or Limitations Samples may come out of the reactor with very high radiation levels due to their composition and/or f encapsulation. They may also have an adverse reactivity , effect on the reactor. This could lead to a violation of reactivity limits and/or the initiation of a reactor shutdown. For this reason calculations must be performed to ( evaluate the reactivity effects as well as the activity levels of every sample or group of samples prior to irradiation (SOP 702). C. Procedure
} 1. Calculation of Activity ax m x NA
{ Act (dis /sec) = oa x @ (1-ex (-0.693t)) (eq.1) AW I 1/2 where m = Mass of the element to be irradiated (grams) a = Isotopic abundance of the element f NA = Avogadro's Number (6.02x 102 3 atoms / mole) AW = Isotopic atomic weight (grams / mole) { ca = Isotopic activatiog cross-section (cm2) 4 = Neutron flux (n/cm -sec) T1/2= Hal f life of the produced radioisotope (min) t= Irradiation time (min) ( Ith M lan Straka APPROVED BY: h WRITTEN BY Danie l R . Carter [A.,:. Albart'90109
.n
F L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR t STANDARD OPERATING PROCEDURES S.O.P.: 306 REVISED: 12-19-83 PAGE 2 OF 3 TITLE: Estimation of Activity and Reactivity Worth of a Samole [ r l Sample Calculation: A O.0985 gm sample f Al is to be irradiated in a f flux of 5 x 10 10n/cm -sec. Whatistheactivgyafter5 min. of irradiation? (c a = 0.241b = 0.241 x 10 - cm , T 1/2
= 2.24 min , 3.7x107dis /se: = 1 mci )
23 Act = 1 x 0.0985 x 6.02 x 10 (0.241 x 10-24) (5 x 10 10) 27 7 1-e -r0.693 s6 = 2.08 x 10 dis /sec = 0.56 mai ( , 2.24
- 2. Calculation of Reactivity Worth of a Sample The reactivity worth of a sample when placed in the
[ neutron flux # 3 can be calculated by comparing it to the l reactivity worth p# of a known absorber placed in the neutron flux #a us1ng the following formula 0 m3 W 's W a* 3 93 =p a
- o X x 4 (*S*2) ma s a a ,
where o = Microscopic absorption cross-section (barns) l m = Mass (grams) AW = Atomic weight (grams /mol e) 2 4 = Neutron thermal flux (n/cm -sec.) Subscripts "s" and "a" stand for the sample and absorber properties. Using data from a reactivity experiment with a piece of f indium absorber placed in the position D-5 at the reactor power of 20W the formula (2) can be simplified to 8 8 (eq.3) r [
,s /(ak'ks
= 10-2l AW x ,s 3
(Note: The value of the neutron flux 4 must. correspond to 3 f the reactor power of 20 W.) li_. M-t Iilan S},r da' b WRITTEN BY: Dantal R. Carter [/((. APPROVED BY: Albert Bolon
~ k UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR s STANDARD OPERATING PROCEDURES REVISED: 12.jo.g3 PAGE OF S.O.P.: 306 3 3 TITLE: Estimation of Activity and Reactivity Worth of a Samole [ Sample Calculation: A 2.0 gm sample of Al-27 barns) is to be { irradiated in a flux of 2.6x10 h/cm sec. at 2 kW. (ol n: 0341 What is the expected reactivity worth? 2 0.241 x 2.0 x 2.6 x 10 10 20 [ p 3
= 10-21 x 27 xg
= 1.2 x 10~0 ak/k
- 3. Calculation of Reactivity Worth of a Void
( When a void is placed in or near the reactor core a change in reactivity can be expected. This is due to the void coefficient of reactivity. A void itself will add negative reactivity to the reactor, but the greatest concern [ is the removal or collapse of a void which will add positive reactivity. o The void coefficient as of 12/7/83 is -6.56x10~Iak/k/cm' . at the core periphery. Sample Calculation: A sample will be placed next to the core in an empty 250 m1 bottle. What is the change in reactivity due to the j void? ( p = 250 cm3 (-6.56 x 10~7 ak/k/cm3 ) = -1.64 x 10~" ak/k. ! [ [ [ [ _ 4, &O , v@hYL m
- -ovh e
L F L UNIVERSITY OF MISSOURI-ROLI.A - NUCLEAR REACTOR e STANDARD OPERATING PROCEDURES S.O.P.: 501 REVISED: 1-17 34 PAGE 4 OF 7 TITI.E Emergency Procedures for Reactor Building Evacuation Physicist to collect the following data imediately and to insure that [ the required action is carried out:
- 1. From information available such as direction of travel of the cloud, weather conditions, and an estimate of the amount of
( fuel atomized, the Health Physicist shall decide if it will be necessary to advise any of the surrounding comunities of an impending radiation hazard. He also will insure that [ all UMR personnel, working in areas other than the reactor area, remain or proceed indoors where all windows and doors will be tightly closed and all supply and exhaust ventilation ( fans will be shut down.
- 2. If, from the data collected, a hazard to any community canr.ot be ruled out, he will advise the Director of Administrative
( Planning will, in giving him all necessary information. The Director turn, notify the comunities which might be affected. H. End of Emergency [ The Reactor ?1 rector, or the Reactor Manager, and the Radiation Safety Officer shall w: ide when the emergency no longer exists. Any special precautions regarding the existence of residual contamination shall ( be issued by Health Physics before personnel are allowed back into the area. SOP 601 shall be followed for decontamination. I. Notification of Key Personnel { Notification of key personnel shall be in the order liated for any emergency that may occur at the reactor facility.
- 1. Reactor Manager, Milan Straka Campus Telephone 341 4237 Home Telephone 364-5276 Home Address 705 W 12th, Rolla, Mo. 65401
[ 2. Reactor Director, hibert E. Bolon Campus Telephone 341 4236
. Home Telephone 364-1961
{ Home Address Rt. 4, Box 33, Rolla. Mo. 65401 l WRITTEN BY: KarenI.ane7d[ APPROVED BY: e 7' l
s F L c UNIVERSITT OF MISSOURI-ROLLA - NUCLEAR REACTOR l STANDARD OPERATING PROCEDURES S.O.P.* 501 REVISED: 1-18-84 PAGE 5 0F 7 { TITLE : e. . u_nev o-ne dur., for peactor Building Evacuation [ 3 Health Physicist, Ray Bono Campus Telephone 341 4240 Home Telephone 364-5728 Home Address Rt. 4, Box 190 Rolla, Mo. 65401 4 Radiation Safety Officer, Nicholas Tsoulfanidis ( Campus. Telephone 341 4745 Home Telephone 341-3595 {' Hcme Address Rt. 6, Box 523 Rolla, Mo. 65401
- 5. Reactor Maintenance Engineer, Dan Carter 1 Campus Telephone 341 4236 Home Telephone 364-8628 Hoae Addrtss 308 E. 12th, Rolla, Mo. 65401
( ( . [ [ [ . { I wRmEn BT:. ,aren une e m R0vtD T. ihM6 I
L F-- L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12-15-83 PAGE 1 OF 6 TIM: 9ecuest for Pesetor Proiects [ A. Purpose In accordance with Technical Specification 6.2.2 each project shall be reviewed and approved prior to insertion in ( the reactor. B. Precautions, Prerequisites, or Limitations The use of the reactor shall be restricted to persons ( listed on an approved Project Request Form. The exception to this is the pilot run of a project which may be run under the project NRF (Nuclear Reactor Facility). This shall not be done more than twice on any project. { Section 6.0 (Experiments) of the Technical [- Specifications limits the type ofmaterials that shall be irradiated at this facility. In addition to the limits of Section 6.0 plastics shall not be ex to a neutron fluence in excess of 1x10 1C neutrons /cm 2 , posed ( All projects shall be reviewed for compliance with the { Technical Specificatons by the Reactor Staff. ( C. Procedure The individual who will be in charge of the project will [ be responsible f or properly completing a Project Request L Form (Form SOP 701). The form is submitted to the Reactor Manager. After approval by the Reactor Staff, the request l is forwarded to the Reactor Director. Health Physics Office, I f and the Radiation Safety Committee. Only after approval by the Committee is a project number assigned and an experimenter allowed to run experiments. Copies of the approved Project Request Form are distributed: one copy to { the Radiation Safety Committee, one copy to the Reactor Facility, and one copy to the originator. For each individual run, the experimenter shall submit the Irradiation Request Form (SOP 702). l l ? __I , WRITTEN BY: g .
, Q& APPROVED BYi A o b
s r L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR L STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12 15_g3 PAGE 2 OF 6 TITLE: Request for Reactor Projects . Particular instructions are given below for completing the Project Request Form: [ Item
- 5. The best estimate in hours should be given to facilitate
{ reactor scheduling. I
- 6. Equipment to be brought to the reactor or extra facility equipmen+ requested should be listed.
[ 9. If radioactive materials are to be removed from the reactor building, the person removing the material must have an NRC license to possess and transport this [ material. For University of Missouri personnel this is covered under the University Board License and individual staff members can request a UMR License. [ (For more information contact UNR-Health Physics Office.) ( *
- 10. If the project is not sponsored, write "none" after l sponsoring agency. If the project is sponsored please l list the account number for billing purpo*:es.
[
- 12. A brief description is required. This should be suitable for listing in the Annual Report or other
( publications. The Reactor Facility is participating in th: National Academy of Science Research Reactor Utilization Project to study the utilization of [ University reactors. One item they periodically request is a one page description of each active project.
- 13. An analysis of possible hazards associated with the performance of experiments must be included. This includes the evaluation of the health physics and
{ reactor safety problemst such as sample encapsulation, its expected reactivity worth, and activity of sample at time when removed from the reactor. The list of ( i 1 U- e - WRITTEN BY: Mila ra a P i -
s r w UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACE R STANDARD OPERATING PROCEDURES REVISED: 12-15-83 PAGE 3 OF 6 [ S.O.P.: 701 TITLE: Request for Reactor Projects [ above-mentioned problems is not exhaustive, the details required in the hazards and safety analysis depend markedly on the experiment performed. (If assistance is [ needed with the hazards and safety' analysis of the experiment contact the Reactor Staff.) [ [ [ ( { l { ( ( [ { ( 1'
# ___ b l WRITTEN SY: Mi "S ax APPROVED BY: Al Ioo
r L r UNIVERSITY OF MISSOURI-ROLI.A - NUCLEAR REACNR I STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12-15-83 PAGE g OF 6 { TITLE: Request for Reactor Projects Date Submitted Date Approved by Reactor Staff ( l. Date Approved by Tadiation Safety Committee
- 2. Type of Project: Special Problem, Faculty Research
{ M.S. Research PhD. Research Laboratory Experiment, . [ 3 Faculty Member in Charge 4 Other persons authorized to use Project Number:
- 1. i, 3,
- 5. Estimate Requested Time (in hours) for Each Facility: J Reactor . Thermal Column , Beam Tube
( , Na! Cour.ters Fr.eumatic Tube, Multi-chanr.el ar.alyzer
- 6. Ext ra Equipment to be used in the Facility (please list):
( ( 7. Estimated Starting Date Completien Date
- 6. Msximum Length of Single Reactor Run hrs.
[ 9. List your NRC License No. or U.M. License No. (Please attach copy of license).
- 10. SponsorinE Agency
( Title of Centract or Grant
'lill
< the Nuclear Facility time be paid for by this agency? yes no If no, explain:
- 11. Remarks (Signature of Faculty Member in Charge)
Cate I 1 (1 C // . WRITTEN SY: n a
'd APPROVED BY:
A e P
L r L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR r STANDARD OPERATING PROCEDURES L S.O.P.: PAGE g OF 6 70; REVISED: 12-15-83 [ TITLE: Request for Reactor Projects Date Project Title { Faculty Member in Charge
- 12. Description of Project:
[ I ( [ [ { ( { 1 l l I l l 1 ,v . _ WRITTEN BY: p gf; l 4 APPROVED BY: A o on t a
s ~ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12-15-83 PAGE 6 Or 6 { TITLE : Request for Reactor Projects [ 13. Hazard and Safety Analysis: [ [ [ [ [ [ l l { { l l I WRITTEN BY: M l b ra " APPROVED BY: h a} .
s L f UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR L STANDARD OPERATING PROCEDURES ( S.O.P.: 702 REVISED: 92 15_gg PAGE , OF 2 TITLE: Request for Irradiation [ A. Purpose The purpose of this procedure is to assure that prior to ( each irradiation the details are established and that materials which are not supposed to be irradiated are not. B. Precautions, Prerequisites, or Limitations Researchers should read the Technical Specifications in (- order to know which materials are not supposed to be irradiated (T.S. 6.2.7 through 6.2.9). ( An estimate of the activity of the sample and its reactivity worth must be done prtor to irradiating samples. [ There are Technical Specification limits on the l reactivity worth of movable and immovable samples or l experiments (T.S. 6.2.3 and 6.2.4). f C. Procedure . The UMR Reactor Irradiation Request Form 702 Rev.1 shall be completed and submitted with each sample or group of l samples to be irradtated. If a group of samples are to be I irradiated at the same time, please note the number in item ; 11.f. The items in the form require no special explanation, f except items 12. and 13. A procedure to calculate expected activity of a sample and its reactivity worth is given in SOP 306. It is suggested that the form be submitted on Friday prior to the week in which the irradiation is requested. The lower part of the form shall be completed by the Reactor staff. Before irradiation, the form must be signed by two of the four persons designated under item 18. I f;! ~ WRITTEN BY: Mfth a MED BY: b B
~ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR ~ ~ STANMRD OPERATING PROCEL'JRES S.O.P.: 702 REVISED: 11 4-83 PAGE 2 OF 2 [ TITLE: Irradiation Request Form [
- 1. Name 2.
( 3. Address Telephone Number
- 4. Project or Class Number 5.
( 6. Purpose of Esperiment NRC or UMR License Number (if applicable)
- 7. Equipment or Facility to be Used
- 8. Date to be Performed
- 9. Power Level Desired
- 10. Irradiation Time
- 11. Descriptions j
- a. Material
- b. Physical Fora
- c. Chemical Purity
- d. Weight
- e. Type of Encapsulation
- f. Number of Samples
- 12. Expected Activity
- 13. Expected Reactivity Worth 14 Remarks
{
- i i
- 15. Signature Date FOR REACTOR STAFF USE ONLY
- 16. Date Received
( 17. Analysis of Possible Hasards
- 18. Approved:
Reactor Director Reactor Manager f Reactor Engineer Health Physicists / Radiation Safety Orricer I WRITTEN SY: D.R. Carter h (( APPROVED BY: A.E. Bolon , 'dVfA-t
s e ~ UN!VERSITY OF MISSOURI-ROLIA - NUCLEAR REAC'IOR
-STANDARD OPERATING PROCEDURES REVISED: 2-2-84 PAGE 5 or 5 l.
{ fS.O.P.: 813 I TITLE: Semi-Annual Calibration Of Lor N And Period Channel B001-0164c
- 3. Depress trip test s" itch, and rotate test pot for a five second period reading on the period meter. I
( 4 Adjust R5 ccw until the meter (VOM) trips to ero VDC. i i' l S. Release the trip test switch. ( j 6. Adjust R12 clockwise until the meter (VOM) trips to =13.5 vdc.
- 7. Adjust R5 three turns clockwise. ,
i [ 4
- 8. Repeat steps 4,5,6 6. ;
- 9. Remove test meter (VOM). l
( !
- 10. Reconnect CIC signal cable. (This step is very important. .,
Failure to reconnect the signal cable can cause a violation l Rev. [. of the Technical Specifications, if the reactor is operated.) I i
- 11. Have another, knowledgeable person independently verify that Rev.
f the reconnection has been made. l [ I ( l ! k i f ! i f , l l l .
- a _
; WRITTEN BY:1 'M'
/!![.he,s/W Barton APPROVEDBY:Albe& rt WWW on
l UNIVERSITY OF MISSOURl-ROLLA Nuclear Reactor Facility April 27, 1984 Nuclear Reactor Rol!a, Missouri 65401-0249 Telephone: (314) 341-4236 Mr. Cecil 0. Thomas Chief, Standardization & Special Projects Branch Division of Licensing NRC
\
Washington, D.C. 20555 i Mail Stop 228 l
Dear Mr. Thomas:
Attached is a complimentary copy of the 1983-1984 Progress Report for the University of Missouri - Rolla Nuclear Reactor Facility. l Sincere p$hL hilanStraka l Reactor Manager i {
.o{\
C To - I 9 V a n SQuel opportunity inst + tut:On
'}}