ML20052B651
| ML20052B651 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 04/01/1982 |
| From: | Bolon A MISSOURI, UNIV. OF, ROLLA, MO |
| To: | |
| Shared Package | |
| ML20052B649 | List: |
| References | |
| NUDOCS 8205030414 | |
| Download: ML20052B651 (61) | |
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{{#Wiki_filter:- E 7 Progress Report 1981-1982 I University of Missouri - Rolla Nuclear Reactor Facility M d b b' ' I cu r1 T-- u m . _ e - v e-L. 3 m = m O O I OO _ CCO I OOOOvOOOO _ i O00000000 I 820503 0 y/y
L r L I u PROGRESS REPORT E FOR THE E UNIVERSITY OF MISSOURI - ROLLA NUCLEAR REACTOR FACILITY L e APRIL 1,1981 to MARCH 31, 1982 I Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri - Rolla By Albert E. Bolon, Director g Nuclear Reactor Facility B University of Missouri - Rolla Rolla, Missouri
[ Table of Contents E I. I n t ro d u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. Perso nnel a nd Reac to r S ta ff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 III. S u p po r t i ng Fa c i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 [ IV. I mp ro v eme n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 V. Rea c to r O pe ra ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 [ VI*. Pub l i c Rel a ti o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18
)
VII. Educa tio na l U ti l i za tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 VIII. Reactor Heal th Phys ics Activi ties. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 { IX. Plans .......................................................... 24 [ X. S uma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 XI. Appendices...................................................... 28 b A. 30 Semi Annual Checks (S0P - 809)......................... B. I ndependent Aud i t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 { [ ! [ [ [ ' [ [ i
r-L [ List of Tables c I. UMRR Co re a nd Ra c k S to ra ge Fo nn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 II. Facil1ty use of Core Grid Plate Locations around the core..... 9 III. Facility use other than the Grid Space around the core. . . . . . . . 10 IV. Re a c to r U t i l i z a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 V. Scrams and Rundowns........................................... 12 VI. Maintenance................................................... 14 VII. Core Loading and Unloading.................................... 16 VIII. Core Technical Data........................................... 17 I 4 if
[ I. Introduction b This progress report is prepared in accordance with the requirements of ( the Nuclear Regulatory Comission 10 CFR 50.71 concerning the operation of the University of Mi souri - Rolla Nuclear Reactor Facility (License [ R-79). This reactor, a swiming 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 Comission 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 for their educational and research programs. Several other universities have made use of this 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 b 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 b and research. [ F
II. Reactor Staff and Personnel [ A. Reactor Staff [ Name Title [ D. Ray Edwards (1) Director Albert E. Bolon (2) Director { Alva E. Elliott (3) Reactor Manager b R.L. Jones (4) Reactor Maintenance . Engineer Carl Barton Electronic Technician [ Karen Lane Secretary { Juls William Assistant Lab Mech 6nic Mike Middleton Reactor Operator Charles Ruggeri Student Research Assistant [ B. Licensed Operators [ Name License Alva E. Elliott (3 ) Senior Operator R.L. Jones (4 ) Senior Operator Carl Barton Reactor Operator [ Karen Lane Reactor Operator Michael Middleton Reactor Operator 1). Served through June 5, 1981. [ 2) Served since June 6, 1981.
- 3) Retired effective March 19, 1982
{ 4) Resigned effective February 19, 1982.
[ C. Radiation Safety Comittee [ Name Department Nord L. Gale (chairman) Life Sciences { Ray Bono (secretary) (ex officio) Health Physicist b Ernst Bolter Geology and Geophysics 0.K. Manuel Chemistry b Albert E. Bolon Reactor Director { N.T. Tsoulfanidis Radiation Safety Officer Ed Hale Physics b This committee, which serves as the Reactor Advisory Comittee, is required to meet at three month intervals. However, in practice the frequency of [ the meetings is usually greater. D. Health Physics b Name Ti tle Nick Tsoulfanidis Radiation Safety Officer [ Ray Bono Campus Health Physicist [ Dan Carter Health Physics Technician E. Independent Audit [ Dr. Franklin Pauls, former Reactor Director, acts as the independent auditor of the Reactor Facility. He reviews all records, procedures, b and operating methods of the facility on a semi-annual basis. Semi-annual audits were completed on May 1981 and October 1981 and are in- { cluded in the Appendix of this report, b b -
l III. Supporting Facilities l l Several supporting facilities are either opera ~ted or maintained by the I reactor staff for users of the reactor. These greatly contribute to the efficiency of research and educational programs available to the faculty l and students of the University of Missouri - Rolla, as well as other universities. ' I Analog Computer: This computer is currently available to faculty and stu-l 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. Slow Neutron Chopper: A slow neutron chopper is available for student use at the reactor facility. This chopper, was constructed as a Masters re-I search project, and can be mounted on the face of the thermal column door. I 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 programer, 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. I I
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 by use of nitrogen gas is available. This allows for a variation in void as a function of core height, total volume, or volume change. [ [ [ [ [ [ E [ [ [ ' E E F o
IV. Improvements The following items are considered improvements to the existing facilities during this reporting period. (1) The power supplies of the MCA and SCA were changed from unregulated to regulated power. (2) A separate intercom system was installed for use between the experimenters at the thermal column and the counting room. (3) Programming is being done on our Apple II computer to provide us with .R u a weekly update of the facility's operation and fuel usage. (4) A remote T.V. monitor was installed in the Reactor Engineer's office to faciliate in identification of personnel who wish entry into secure l area. (5) The pneumatic transfer system was rebuilt, replacing hoses from the glove box to the bare and the cadmium lined rabbit tubes, valves, and wiring. l g ~ u V. Reactor Operations A. Facility Use Table 1 depicts the current core loading which is designated as core 67. _ The number 67 denotes the sixty-seventh core configuration (assembly and ~ location), that has been used at the reactor facility since the original ~ operating license was issued in 1961. This core 67 has been in use since December of 1978 and is periodically checked for all parameters listed in Table 8 (core data). The core was unloaded for Control Rod Inspection I during the month of September 1981. It was partially unloaded (4 or 5 assemblies) approximately 6 times for training exercises in fuel handling and 1/M plots during core loading during this reporting period. On March 19, 1982 the core was unloaded to less than half a critical mass in order that the reactor would be in a secured safe condition until another indi-vidual became licensed as a senior operator. Tables 2 through 7 give additional pertinent information about the reactor for the reporting period. i
1 l Table 1. UMRR Core and Rack Storaae Form I l DATE December 19, 1978 LOADING NUMBER 67T* I R1 R2 R3 R4 R5 R6 F7 R9 R9 R10 R11 R12 R13 R14 R15 _P CA RACK STORAGE FACILITY L F-13 F-20 HF-1 F-22 F-2 F-5 F-3 , F-18 F-21 16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 R29 R30 l KEY TO PREFIXES T - Standard Elements C - Control Ele =ents HF - Half Tront Element HR-1 F-14 F-1 C-4 HR - Half Rear Element F-8 C-1 F-16 F-9 F-4 F-10 CA - Core Access Element F-6 C-2 F-19 C-3 F-12 F-11 IP - Isotope Production Element S - Source Holder BRT F-17 F-15 F-7 CRT 1 2 Other 3 4 5 6 7 8 9 SRIDGE SIDE UMRR CORE STATUS hlem. Pos.I Mass Elem.lPor. Mars Elen Pos. Mass biR-1 C3 84.912 F-16 l DS 170.270 F-12 E7 168.774 Bridge Position h-8 D3 170.229 F-19 E5 170.264 F-10 D8 170.193 169.160 " ** * %-6 E3 F-15 F5 168.889 F-11 E8 168.969 ** d-14 C4 170.210 C-4 C6 102.112 B:-l D4 102.112 F-9 D6 170.178 (_C-2 E4 102.125 C-3 E6 101.978 I-17 F4 169.111 F-7 F6 170.154 [F-1 C5 170.223 F-4 07 170.206l 6://- 0.905% 076oF (8-26'80_ Total Mass crams 2870.069 (measured value)
- T designates the thermal column-reflected mode.
and W designates the water-reflected mode. Table 2. l Facility Use of C9re Grid Plate Locations around the Core Number of Facility Hours Used j A-4 0.167 i A-7 0.250 B-3 0.167 l B-4 0.15 B-5 0.6 B-6 0.167 B-7 ') . 283 B-8 0.167 C-2 0.067 C-3 1.117 C-4 0.35 C-7 1,484 j C-8 0.05 0-2 0.167 D-5 0.55 D-6 0.167 D-7 0.167
- D-8 0.9
, D-9 0.3 F-3 11.683 , Total 19.75 I II I
- I
! Table 3. l Facility Use Other Than the Grid Space around the Core Facility Hours l Neutron Chopper
- Bare Rabbit 11.68 Beam Port l
Reactor Console 556.76 Thermal Column 2.95 Total 571.39 I I il I 4
. Table 4.
Reactor Utilization Hours in Use 1701.0 Hours available, But Not in Use 379.0 Hours at Power 170 m Hours of Maintenance 824 m kW Hours 5903.4 Hours for Research 23 7 Hours for Instruction 591.0 l Experimenter Hours 1503.6 E Sample Hours 85.7 L Average Number of Experiments 1.04 Average Number of Samples 0.21 Total Number of Samples 219 E Hours in Use is a total of Instruction, research and maintemoce hours. With maintenance hours being only those hours when the reactor remained shutdown during the entire day. I l L F l L [ -
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Table 5. I Scrams and Rundowns I Date i Event 4-10-81 Scram, intentional (training). 4-13-81 Scram, intentional (training). 4-13-81 Scram, intentional (training). 4-13-81 Scram, intentional (training). l 4-15-81 4-20-81 initiate <30 sec. period by pass (training). Scram, intentional (training). l 4-27-81 4-30-81 Scram, intentional (training). Rundown, <15 sec. period (void tube by detector). 4-30-81 Rundown, hi-radiation spurious trip. 7-07-81 Scram, intentional (training). 8-04-81 <2 cps by pass used for core loading. 8-04-81 <2 cps by pass removed. 8-19-81 Scram, intentional (training). 8-21-81 Scram, intentional (training). 8-24-81 Scram, building evacuated (alarm due to sample escaping from rotor and surfacing). Radiation level on surface of pool under detector was 25 mr/hr. 8-31-81 Scram, intentional (training). 9-14-81 Scram, intentional (training). 10-29-81 Scram, (caused by failure of voltage regulator tube in safety amp). 11-03-81 Rundown, 120% demand, (void tube placed too close to detector). 11-03-81 Rundown,120% demand, (void tube placed too close to detector) . 11-04-81 Rundown, 120% demand, (void tube passed between detector and core). 11-04-81 Rundown, <15 sec. period (void tube passed between detector and core). 11-12-81 Runewn, hi-radiation,15 mr/hr. 11-12-81 Rundown, hi-radiation, 7 mr/hr. I idole 3, C00Linueo. Date Ev nt 11-19-81 Scram, intentional (training). 11-20-81 Scram, intentional (training). ' 11-24-81 Rundown, <15 sec. period (caused by water filling the void). L 11-24-81 Rundown, <15 sec. period (during void experiment). 11-24-81 Rundown, <15 sec. period (during void experiment). [ 11-24-81 Rundown, <15 sec. period (during void experiment). 11-24-81 Rundown, 120% demand (void tube passed between [ detector and core). I 11-24-81 Rundown, 120% demand (void tube passed between { detector and core). 11-24-81 Rundown, <15 sec. period (void tube passed between detector and core). 11-24-81 Rundown, <15 sec. period (void tube passed between detector and core). 12-09-81 Scram, intentional (training). 1-05-81 Scram, intentional (training). ( 1-13-82 Scram, intentional (training). I 1-14-82 Scram, intentional (training). [ 1-28-82 Scram, intentional (training). 2-23-82 Due to running the reactor in the thermal mode without increasing the set point on the rundown limit. { 2-26-82 Scram, intentional (training). 3-09-82 Rundown,120% demand (student did not notice reactor was not on servo). 3-10-82 Scram, intentional (training). 3-10-82 Scram, intentional (training). 3-19-82 Scram, (fuel element tco close to detector during b fuel removal). [ [ [ [ [ --
Table 6. Maintenance Date Event and Corrective Action I 4-25-81 Hi-radiation alarm on console - found no indication of i Hi-radiation on RAMS. Checked building found no radiation level above normal. Replaced A4 (LM327) and A6 (7474) integrated circuit- in log area monitor module. 8-20-81 Keithley 410, SN19683 micro-micro amp mike removed and l 8-24-81 SN19650 replaced for semi-annual . Replaced all hoses on rabbit tube. Dose rate of 100 R@ 2 ft. below pool water surface on lower part of tubes. 9-28-81 Control rod inspection. 9-5-81 Placed source range detector cables in steel flex conduit. I- Placed linear and log n detector cables in aluminum flex conduit. Replaced blower hose on glove box and mounted blower on upper level . 9-6-81 Adjusted CIC (linear & log n) in accordance with power calibration dated 8-5-81. 9-11-81 Discharge hose on pool purification pump blew off due to high discharge pressure (60 lb). High pressure caused by clogged filters, 50 lb. differential pressure. Refilled pool with 1370 gallons and started. I 9-25-81 10-22-81 No. 2 magnet bad - replaced no. 2 magnet. No. 2 magnet bad - replaced no. 2 magnet. 11-05-81 No. 2 magnet current 120 ma. Found lead wire grounded I to case. Repaired and returned to service. 11-12-81 Dropped all shim rods. Found voltage regulator tube in safety amp bad. Replaced voltage regulator tube. 11-12-81 Dropped #1 and #2 rods. Safety amp malfunction. l 11-12-81 11-12-81 Dropped #2 rod. Safety amp malfunction. Dropped #2 rod. Voltage fluctuation. 12-10-81 Keithley 410 micro-micro amp became erratic. Removed SN19650 and replaced with SN19683. I noDie 0 Coll 9 t illu eG . I Date Event and Corrective Action 1-29-82 At shutdown shim red #3 would not drive in. Gear loose on motor shaft. Put new pin in to drive rod in. Re-moved motor for repair of adapter. 2-03-82 Replaced motor on #3 shim rod drive checked rod withdrawal ,I speed and found it to be 241.6 sec for 24 inches or full withdrawal. 2-04-82 During weekly check a problem was noted with #3 safety rod. Micro switch for insert limit was found to be broken. Replaced micro switch and returned to service. 3-18-82 , RAMS no. 3 found inoperative. No reading on meter. I I lI 'I Table 7. Core Loading and Unloading I l Da te Fuel Handling Maneuver 7-21-81 unloaded core for purpose of replacing rabbit tube hoses. 8-04-81 reloaded core. 8-25-81 unloading core for training. 8-25-81 reloaded core for training. 8-26-81 unloaded core for training. 8-26-81 reloaded core for training. 9-07-81 unloaded core for training. 9-07-81 reloaded core for training. 9-09-81 loaded HR-1 for training. g 9-24-81 unloaded core for training.
;E 9-24-81 reloaded core.
1-14-82 unloaded core for training. ! 1-14-82 reloaded core for training. 1-26-82 unloaded core for training. 1-26-82 reloaded core for training. 1-26-82 loaded HR-1 for training. 3-19-82 started core unloading for S0 exam. 3-19-82 started core loading for 50 exam. I l - - - -
u B. Core Data . F u During this reporting period only one core designation has been used to any r L extent. The "W" mode core was used for normal reactor operations, since , students cannot operate the reactor when the excess reactivity is above 1 O.7%. The "T" mode is used for extended operation ( >3 hrs), beam port or thermal column experiments. The excess reactivity was measured for cold, { clean critical conditions. In day-to-day operation the excess reactivity is quite often lower due to the temperature increase of the pool. b Table 8. Core Technical Data [ Average Thermal Flux 1.6X10 12 at 200 kW 12 Maximum Thermal Flux 2.8X10 at 200 kW 11 Average Epithermal 1.6X10 at 200 kW Worth of Thermal Column 0.37% 0 76oF Worth of Beim Port Not detectable [ Rod Worth I 2.64% , II 2.65% , III 3.36%, Reg. 0.347%, Date 9-29-81 b Excess Reactivity 0.48% Shutdown Margin 4.8% Void Coefficient -4.0X10 -7 o/cm 3 Date 11-03-81 Limit -2.0X10 -7 o/cm 3 { Temperature Coefficient -8.4X10 -5 o/oF Date 11-12-81 Limit-4.0X10 -5 o/oF b xenon-free temp. coeff. -2.25X10 -5 o/oF Reactivity Addition Rate (max % AK/K/sec)' 10.01776K/K/sec, II0.0183aK/K/sec, III0.02274K/K/sec, Reg. 0.0072aK/K/sec Date 8-04-81 { Rod Drop Time (24") b I 500 msec, II 320 msec , III 520 msec, Date 8-04-81 Magnet Separation Time b i I 30 msec , II 40 msec , III 30 msec , Da te 8-04-81 [ .
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VI. Public Relations [ The reactor staff continues to put forth considerable effort to help educate ( the public about the application of nuclear energy. Over 1878 persons have toured the facility during this report period. This includes groups re- [ presenting social, military, civic, industrial, governmental 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 groups [ from other universities have spent an entire day at the facility becoming acquainted with the reactor and performing simple experiments. Usually these groups are from colleges which have no reactor facilities. A guided b 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. [ l l The Nuclear Engineering faculty are members of various social civic, pro-fessional, and governmental committees. The faculty and students also are ! ( involved in speaking engagements around Missouri concerning the reactor fa- l cility and in informational programs at high schools and colleges.
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[ [ [ [ [_. . . . . _ _ _ _ - _ - _ _ - _ _ - _ _ _ _ _ _ .
N [. VII. Educational Utilization [ Approximately 32 UMR students, graduates and undergraduates, have participated [ in classes at the facility, utilizing 49 student - semester hours of al-located time. Also students from several colleges, and high schools have b 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 2 Introduction to Nuclear Engr. 1.3 NE 204 Radiation Measurement 0.1 NE 304 Reactor Physics Laboratory I 58.8 NE 306 Reactor Operations 77.4 b NE 308 Reactor Physics Laboratory II 33.2 Reactor Operator Training Program 379.3 [ Preliminary Research 45 The current enrollment in Nuclear Engineering is 75 students. During this [ reporting period the reactor was used 96% for instruction and 4% for research. E The use of the nuclear reactor by departments other than Nuclear Engineering on this campus has continued to decrease. This condition seems to be a common occurrence with campus reactors that have been in service for a considerable number of years. This is reflected in the amount of time the [ reactor was used for research during this (and previous) reporting periods. It should be noted, however, that the reactor use has remained very high in b the area of training, b The Nuclear Reactor Facility was accepted, by the Union Electric Company of [ l l St. Louis, Mo., to provide several two-week programs in operational training. This training augments Phase One of their commercial nuclear reactor operator training program, with actual hands-on experience in start-up, shutdown, fuel I handling, etc. This training was provided during April, August, September of 1981 and January of 1982. Seven groups, consisting of 39 individuals, were involved. I I I I I I I I I I I I I
VIII. Reactor Health Physics Activities The Health Physics activities at the UMR Reactor Facility consist primarily 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 are surveyed and reco rded. 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 full power. No unusual exposure rates were I found. Monthly surface contamination surveys consist of 20 to 30 swipes counted separately for alpha and beta-gamma activity. In 12 monthly surveys, no significant contamination outside of contained work areas was found. By-Product Material Release Surveys During the period, 9 shipments of by-product material were surveyed and released from the reactor facility. Total activity released was 5.283 mci. Five of the shipments were off campus which accounted for 5.0 mci of the total activity. The other 4 shipments were utilized on the UMR Campus. Routine Monitoring Thirtyeight reactor facility personnel and students frequently involved with operations in the reactor facility are currently assigned beta-gama, neutron film badges which are read twice each month. There are four beta-gama, neutron area badges assigned. Fourteen campus personnel and students are I I l l l assigned beta-gama film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 22 beta-gama area and spare badges assigned. In addition, 7 direct-reading dosimeters are used for visitors l and high radiation area work. There have been no personnel over exposure during the period. ' l l Airborne activity in the reactor facility is constantly monitored by a 1 fixed-filter, particulate air monitor (CAM) located in the reactor bay. Rb-88 and Cs-138 are the particulate daughters of Kr-88 and Xe-138 which l are monitored particulate activity 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 con-tamination nor fuel cladding rupture has occurred. Gross counts and spectra of long-lived gama activity are compared to previous monthly counts. From April through March sample concentrations averaged 5.27x10-6 ci/ml. Waste Disposal Release of gaseous and particulate activity through the building exhausts l 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 3.11 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 comercial burial site. Radioactive waste released to the sanitary sewer is primarily from regeneration of the resin exchange I [, column. During this period 7 releases to the sanitary sewer totaling ap-proximately 4,100 gallons of concentrated resin regeneration solution and { pool water were discharged with a total activity of 0.541 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. [ 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. b [ [ [ [ [ E [ [ [ [ [ r IX. Plans I l During the future reporting period the reactor staff will complete replacement l of all originally installed, control room instrumentation. The final items to be purchased consist of two compensated ion chamber power supplies for l the linear and log-n intennediate range nuclear instruments. The source range, magnet power supply, and power range equipment has been previously l purchased and needs only to be installed. l There will be one-ten day Reactor Operator Training program in September of 1982 for Union Electric Company of St. Louis, Missouri. With the completion of this program our servic'; to U.E. will be completed for their initial operator licensing effort. Continued programs (of perhaps five-day classes) will be provided for replacement operators and new professional employees. There are plans to obtain another utility user whose initial licensing effort is just beginning. I The facility is still involved in a re-licensing effort that began in November of 1979. We have been informed by the NRC that their review of the initial facility documents will be completed and the resulting questions / answer series will begin shortly. I It is anticipated that the reactor staff will be expanded to include at i least three licensed senior operators. Operator licensing exams for three l SR0's and one R0 were administered on March 18 and 19 of 1982. These indi-viduals scheduled for licensing have been members of the staff for some time and will therefore, require only a change in job title / duties. This should allow the facility to expand its operation without (or with only minor) increase in operating cost to the University. I -
The positions of Reactor Manager and Reactor Maintenance Engineer will be filled as soon as is reasonably possible. The individuals who take each of those two positions will be expected to obtain their senior operators [ licenses as soon as they can. On April 12 word was received from the U.S. NRC that Dr. Albert Bolon and { Mr. Michael Middleton had passed the Senior Operators examination and the b effective date of their licenses was April 6,1982. The results of the other two candidates were still pending). [ [ , l b [ [ E [ [ [
X. Summary l The University of Missouri - Rolla Nuclear Reactor was in use approximately O.7% of the time class was in session at the University (40 wks) or 8.2% of the total available time based on a 2080 hour work year. (These percentages utilize the established method for use rate and are some what misleading.) A more reasonable percentage of use would be 38% (1) and 30% (2) respectively. l The total maintenance time of the facility was 824 hours (40%) which provided a total availability (reactor operaticnal) of 1248 hours (60%). It should be noted that during this reporting period approximately 250-hours of maintenance time was used for new equipment installation and that the facility was operating with only two licensed senior operators instead of the normal complement of three. I A total of 5.9 megawatt-hours of energy was produced using 0.304 grams of U-235. The percentage of usage was 96% for instruction and 4% for research. A total of 219 samples were irradiated during this reporting with most of the samples being used on a intra-campus basis. The reactor was visited by 1878 people during the past year. At the same time there were 32 UMR students enrolled for courses at the Reactor Facility. ,I The facility was thus committed to over 49 student-hours of classes in-volving about 20 hours per week during the fall and spring semesters. There were no classes at the reactor during the summer of 1981 to allow for an extended maintenance period. l 2 1 Hours of instruction plus hours of research = 1600 hours Hours of instruction plus hours of research = 2080 hours The facility continues to be utilized by electrical utilities for operator training. Seven-ten day non credit University Extension Programs were completed with approximately 379 hours of facility time being used for [ these programs. These programs provided $43,160 to the University with net revenue of $9096 to the facility. These funds went to salaries and [- wages for the staff involved in conducting the programs. [ [ [ [ [ [ ' [ [ [ [ [ [ [ [
l l 1 l I l I I I e t I ! 6 k I i l APPENDICES e I 1 I J e i i I l lI l l
s l 1 d ) 1 'I 1 1 i I APPENDIX A . 1 i I l i i j lI t I l
Semi Annual Check List (1) Date Commenced /2 -// - 8 ' Date Completed " '^* T Total Hours on Hour Meter '/9s2,8 ! Vccuum Tube Test and Clean Chassis Initial
- a. Log N Power Supply 3 1982 (1) Cleaned chassis [
(2) Tested all vacuum tubes /2 NN Replaced: tube # tube type na (3) Additional Comments None
- b. Linear Power Supply (1) Cleaned chassis @ JAN 2 31982 (2) Tested all vacuum tubes [
Replaced: tube # tube type V3 f65/ VN 54 5i il /L) [L, f / I s (3) Additional Comments
- 1. Due to the reactor being inoperable from March 19-March 31,1982, it was impossible to complete the Semi-Annual Check. It will be completed as soon as possible when the core has been reloaded.
- c. Lincor Pulco Amplificr 3g
{ (1) Clocn d chocolo /M (2) Tested all vacuum tubes Replaced: tube I tube type [ 4" [ (3) Additional Comments xhau wxig
- d. Scaler Timer (1) Cleaned chassis /i/pfs@[ MN23 m
(2) Tested all vacuum tubes Replaced: tube # tube type
/) 620I
[ [ (3) Additional Comments [
- e. Safety Amplifier JAd O : id (1) Cleaned chassis [ d (2) Tested all vacuum tubes Replaced: tube 6 tube type ra osx g vu on1 E
[ _2-g 9* 6
- M me y e-
I c. Linacr Pulse Amplifier (1) Cleaned chassis '4f' ' 71982 (2) Tested all vacumn tubes [8[I Replaced: Lube # tube type
.Y fitA __
I - (3) Additional Conunents i UD&Hese. kd?fK}Np
. L
- d. Scaler Timer / o (1)
LY7/3/ Cleaned chassis ,, (2)
/5/74
Tested all vacuum tubes Replaced: tube # tube type
'/) 6XC)
II (3) Additional Comments I - I e. Safety Amplifier (1) Cleaned chassis
/$0
/
(2) Tested all vacuum tubes Replaced: tube # tube type 'I ro on V // CAR I lI i i
. ]
(3) Additionsl Comments
.: : un
- f. Area Radiation Moni tor Cb2[ *,N (1) Cleaned chassis *
(2) Tested all vacuum tubes _ ( Replaced: tube i tube type [ ~ w (3) Additional , Comments h '.s (, * -l* '~~ [ .; r D . 9 Micro-Micro Ammeter ,
.T Q
[- 7 8* * '- (1) Cleaned chassis
/ ),. . ' ?'I'5 (2) Tested all vacuum tubes Replaced: tube # tube type
-;7 ,e
[ . E (3) Addit.iona1 Comments Pission Preamp h. (1) Cleaned chassis and inspected h/ f (2) Additional Comments
]/h[M "
{ . 4 n . ( CL [ [ - g
- i. Public Addrocs System (([
(1) Clocned chassis T (2) Tested all vacuum tubes M/f Replaced: tube # tube type (3) Additional Comments
.59l t 0 $5}b- lly; [
- j. Log Count Rate Recorder M[ JAN 2 31932 (1) Cleaned chassis ['Vf['[J (2) Tested all vacuum tubes Replaced: tube # tube type sf *% -<
I (3) Additional Comments
- k. Linear Recorder ))[ .*
- g. _ ; 3,. ,
(1) Cleaned chassis [I,,y/3 (2) Tested all vacuum tubes Replaced: tube # tube type
, i ~~ t .L
!I l l (3) Additional Comments l l !
- 1. Poried R corder [Tjf/ d!'C '. 2 ,';,j.'
(1) Clcanad ch2colo (2) 88d Tested all vacuum tubes Replaced: tube # tube type t I
$4 i
I l j (3) Additional Comments
- m. Log N Recorder ' ~'
7 --
'- (
(1) Cleaned chassis (2) [/dh6f3 Tested all vacuum tubes Replaced: tube # tube type
~7//,2..<
I I (3) Additional Comments I
- n. PAT 60 I (1) ' Cleaned chassis
[h)g , c. gdjyj (2) Tested all vacuum tubes I Replaced: tube #_ tube type llt. r I L E { 8
(3) Additional Commento r l.M
- o. Regulated Power Supply (1) Cleaned chassis
[ N (2) Tested all vacuum tubes /// { Replaced: tube # tube type L E L . (3) Additional C ents
.S ohl &
- p. Conductivity Brigge (1)
/-59'M Cleaned chassis A /u/, #
(2) Tested all vacuum tubes TAdo. 1/#A~r Replaced: tube # tube type E [
- q. Safety Amp Preamp b (1) Cleaned chassis h[/
-(2) Tested all vacuum tubes [2f((' '
( Replaced: tube 4 tube type e
- c. -l'j, r g,,
I( [ . s s, (3) Additional Comments [ - b --
's
_A.________ _ _ - - - - - - - - _ -
- 2. R31cy Tact
- c. Congolo relcyc tasted cnd replaced ce per SOP 815 Mg
- b. Additional Comments g'j jjp
- 3. Detector Resistance
- a. Safety #1 Value FEB 3 1982 (1) Signal to ground [.'ryN 6 /
// j (2) Positive to ground 7. / /// A-v/W (3) Additional Comments l
, b. Safety #2 Value Initial, (1) Signal to ground [ , /. y e m- 8 ///[
(2) Positive to ground hc V /d " [I//83 (3) Additional Comments I c. Log N (1) Signal to ground /.5/ // ' /// (2) Positive to ground Ty /< *
/7 ///3 (3) Negative to ground (4) Additional Comments
- d. Linear (1) Signal to ground /< 1 y /f' ON
() j' . ( / /,- " Positive to ground [Y)/ 3 I (3) (4) Negative,to ground Additional Comments j . y y / /' "
/~//// 3
- 4. Calibration Checks Note:
Any instrument found to be out of calibration should be realigned in accordance with its technical manual.
f A. TcmperOture RCcordar r 1. R.cding i Tharmometer - Recorde 1 BooF 2
'79 80up
+ 3 99 800F ,7 0 1 1400F ffb c 2 1406F 3
/39 140oF M/
Note: All readings should be 1 1"F
- 2. 135"F Interlock Trip Point L Initial
/.3 3 '
7 B. Log Count Rate Channel (*YP)}
- 1. Pulse Generator
- Meter FEB 319gg Recorder Initial
, 10 L 100
/t* / :- C's/?7 r
//i 1000
)t'// J
/ ',1 e FW%
10.000
/s [i 0777 5
/ l'SE O J'!;// Y:J/G Note:
Nfi$ F I All readings should give .7 to 1.4 ratio of truc-to observed readings.
- 2. Additional Comments L
C. Linear /9 -/d -I'l
- h. 1. Keithley Meter Recorder 6.66X10 -5 g (,( 79p InitM g/
{ 2.0X10 -5 y, p 7g 6.66X10 -6 gg 7,C
- M y, o
{If '2.0X10-6 6.66X10 7 f, $ 97
/&c gf~
) 2.0X10 2,06 fo/
6.66X10 -8 ggg g M 2.0X10 -8 y, g
~
/
g'fT ~9 79 6.66X10 2.0X10 ~9 6,66 2, M f7 N/_ h 6.66X10 -10 g, gy
~ /h I
/,' -10 97 l 2.0X10 7, g 9,7
~
V { Note: From 10 ~ ~ ' ~f { to 10 the overall accuracy s $1d , e better
^ than 2% of full scale.
<[ \
- i I
^ From 3X10 -9 to 3X10 -13 c the ovarall accurccy should L ba bottcr than 4%.
- 2. Additional Comments u
D. Log N
- 1. Meter Recorder Keithley Initial 100
/2 4) # x/J
~
bW 10 8 $ .4' y'/5 & f),5 ~ l 4, 7 3,4 Wo ONT7 { 0.1 D . f.6 '
.01
[ X /C " # 0d/97$ 6 . D /> ~ 3~, f Vfo~' C
.001 O/sYi
- 0 D 6/2 A . 17 Ym ~ '" @f//b
.0001 B, / #d A r
f, 45 y fo~# /4 -//d Note: L The ratio of true-to-observed readings should be between 0.7 and 1.4.
- 2. Additional Commentu
- 5. Verification of Rod Drop Times
- a. Rod i Rod Height Separation Time Rod Drop Time (inch) (< 50 maec)
(< 600 msec at 24' 1 1 1 2 E 2 l l 2 E 3 3 E 3
- b. Date performed Preformed by Director or Supervisor E
E
t r 6. Void Co3fficicnt Detoroinntion L
- a. Value of void coefficient
- b. % 65/K/cm r Calculation performed by
- c. Date performed c d. Director or Supervisor L
- 7. Temperature Coefficient Determination
{ a. Value of temperature coefficient
% A K/K/o F
- b. Calculations performed by
[ c. Date performed
- d. Director or Supervisor
{ 8. Rod Speeds Time (Sec) I. II. III. Reg.
- t. $
[ 0-24" M/. / AW. t
.231.5 U./ '&
(3) Additional Comment [ { Date FEB 4 1982 Performed ay 8 /// 3
- 9. Rod Indicator Calibration
[ Actual Height Indicator Reading I. II. III. Reg. 1" / / / / 6" 6 6 4 & b 12" /R /4 /x /A 18" /?
/f IV /f
[ 24"
~
M M M N
- 10. Results of Annual Control Rod Inspection
[ A. Control Rod Number 1 [ [ [
ll.b Control Rod Numbbr 2 l l l 11.c Control Rod Nmnber 3 i l 4
- d. Date Performed
- e. Director or Supervisor s
l
- t I
6 0 1 I l r . !'
)
Date 19 I have reviewed the results of this Semi-Annual Check on this date end discussed any problems and/or errors wi th the operating sta'f f. Director or Reactor Manager l u W r L l l L l [ [ W k E
?
I [ I i t T -- -- - I
j UN!VERSITY OF MISSOURI-ROLLA - NUCLEAR REACE R u i STANDARD OPERATING PROCEDURES I lS.O.P.: 817 REVISED: 7-24-75 pAGE 1 OF 1 ' TITLE: Fire Alarm System The UMR Nuclear Reactor building, fire alarm system consists of two type { lmanualalarmstation.of detectors; four heat sensing units and two smoke detecto I F iThe system has a built in circuit failure warning system with an audible E and visible alarm at the control box. The alarm system is normally powered from building power, with batteries 7 for a backup. L When a actual alarm is initiated an internal and an external building fire alarm is sounded and when the building security system is in opera-tion a remote alarm is sounded at the campus police headquarters. b PROCEDURE: E 1. Replace the emergency power supply batteries in the battery box. E st emergency power by securing power to the alarm system (switch 32 in the power panel) and text system operational. d eck the four heat detectors by applying a heat blower on them and acknowledging alarm actuation, audible and visible and their [ resetting after the heat is removed. M Check the two smoke detectors by placing a burning cigarette on l a long pole momentarily removing all power to the alarm control box. l 5 ek the two manual alarm stations and acknowledge alarm actuation, audible and visible and reset. I l
- 6. Check all indication lights operational.
l l ,,
/?$ -
/z e<
l r l ; A4f7
' w I / l E TTEN SY: R.M. Luckett APPROVED BY: D.R. Edwards s _
l _ - - - - - _ - - - - -
a [ REACTOR (Phone: 341-4236)FACILITY IMPECTION -- Dsto( s) k d .3 0 dM^ fI 7/ [ [ #A Date(s) of last NRC inspection h ;G_p,/d, /98/ 32 b Date(s) of last "inhouse" inspection b $ /780 l Log Book Inspection: Log Book Number
- Page Date From entry: 4 46F
)Ln, 7 /9po Thr ough entry: 49. g _ . g3 _ 4 y ggf 0
I yFollow up items from . previous inspection.(it=%; . ... .ofollow-up):
~
=
g w_. 5 n ~. w aas. w - - .. >- , eg I 6v ~ n _ c.Mk cI~Q--. 0rn f M.JL & 3 -uA2JL f>ab ", b-{
-_CE= M - %
I OKl A. Technical specifications ------------ Comments Appendix A -- Jan. 6, 1967 ( Changes h if so, list
- 1. (2.'1) Ventilating fans --- ------- .-
A utoPool ma tic c lo de sure ---------------- -s/ / I 2. 3 (3.1) above core) ----- --------------- -/ water pth (16 f t._ min (3.1) Inlet water 0 temperature I 60oF < t < 135 F ----------- ----- -7 g
- 4. (3.2) pool Radiation < 5 mr/hrone meter
------ -----above --- --
- 5. Fuel (3.2)---------- Resistivit I 6. y ) 0.5 megohm-cm- - y/
------------------ -/ Type of elements: YTR ,
Other m I A ( 4 .1. 3 ) j'"ex < 1. 5.T ----- --- --- -- -- -X Present loading (s): r,7w/ UG4h 1.50 days tWic,x f p { 3.5% five consecutive Uates: Sr. Oper, (1) I 7. Control rod: (9.5) condition ---- -< e a year ------- ------- -Y - = (2) (4.2.3) Reactivit s hutdown Date inspected:
-AQ I margin at least 8%y ------------L--
(4.2.4) Drop time ( 600 msee ----- - v/ (9.3) Dates: - v - (4.3.2) Limit lights; shim range (1) I lights; ma5 net contact B. Neutros source (min.10 gig n hts -----V
/sec) ---/,
(2)( N f _ _ _ _ _ _ . - - - - - - -
Page 2 , 1OKI Comments
- 9. Safety systems (annunciator) ---- 1 / !
I ( 5.4) Start-up channel ------------ / ! (5.4) Linear channel --------------v (5.4) Log N - Peroid channel -----w ( 5.4) Saf ety channel #1 ----------- / (5.4) Safe ty channel #2 ----------j/ ;
- 10. (5.5) Magnet release time (, 50 msee M
- 11. (5.7) Radiation levels ( O.1 mr/hr-- l Location Reading l ! Pool surface above !
core ------------ I '
'Near demineralizer - ,
B eam room ---------h/ ' L/ t, N l 12 (5.8) Portable survey instruments - / List: l Neutron I Alpha Gamma I Beta Other
- 13. Experimental facilities ---------- h!Give example as to how used.
I Hung s ampl e s -------------------- ! t/ (6.1.1) Core access element ----- Ev (6.1.1) Iso tope prod. element --- 1/ ( 6.1.2 ) Rabbit tub e ---- ------ ,- l - ,d- y j I ^^^U.= (6.1.2) Thermal column '/ (6.1.2) Beam port I
/
(6.2.2) Documentation of exps. -- l/ (6.2.3) Sin le independent exu-eriment: 40 ( 6.2. 4 ) Si kfe mo v.ex able 7% -------------- / I o 4 0.4% --- periment: 0.6$*fl.1 movable exo. 's
/ ..
(6*f.5) Experiments having' moving parts: gex 4 0 . 0 5% -------- ------- / (6.2.6)1 Position of any/all exp. ?-/
- 14. General Operating Limitations (7.1) Startup: Sr.Oper. plus one -/
I (in the control room) (7.1) Operation: S.O. plus one -- -/
- (in building)
(7.4) No fuel position vacancies in core; loading (wall chart) ---- -/ e e 9 e
Paga 3 iOKl Comments
- 15. Fuel storage & Transfer l wall chart -------- - -------- -- ./
(8.3) Fuel handling tools locked -.../ (8.4) Fuel transfer--three men I 16 (Sr. Oper.; Lic. Oper.; plus one (10.1) New loading: approach to v OK critical exp. (reason & date)----- J M I (10.2) Core configuration change: I one grid position. (Reason & date) / (10.3) Loading change of more than k kk?! g'^l_ one grid position-unload 50% ----- # 17 I Instruments Scram: Manual functioning (Table I)-I Period < 5 sec. v (on weekly check 11 t - *)
'v *startup I- p 4 o[g/
150% full power ---------- I Bridge mo tion ----------- h <- v *startup Log N - P eriod non-op ----;- /-.*startup Rundown: 120% power (linear) -----/-
- P erio d < 15 s ee --------- i /-,*
Reg Rod------------------ rundown) (insert limit-auto l /. .* I 1207. full power (log N) -- /-.* Low CIC voltage --------- j /- startup High radiation ----------- -/- startup I Rod prohibit: P eriod < 30 sec . ----<-
- Any r ecorder o ff --------
Low co unt ra te ----------- -/-.*
- / -.*
I Reg Rod prohibit (rods below shim range) ----- '--- -/- Inlet temp. 1350F ------ -/- 4 i Servo-prohibit on re>g. rod ------- -v- ~
- 18. Check Lists and records A -W y #^^ [' M/4,17 3P Lo g boo k checked -----------------. v- '
(9.1) Daily facility check list -- -/ O^^*^'[* #~b' I (9.3) Instrument channels & area monitors-calibrated at 90 day Dates: (1) (2) T 20 , b rl/ /P / Pa intervals ------------------------ g (3) I UERR startup check list ------- -- -/ Hourly records-no te variations --- -/ (4) .I Shut-down check list -------------
'Je ekly check l is t -------------- y/
-c "To r k lo ad lo g - - ------ ------- ---- -/
I Six month systems check ---------- -/ Dates: (1) h /9fD (2) I I
~
Page 4 10K Comments B. Records
- 1. Iog books l/ Current book number 6 Other t$' Stored b e,N J e
- 2. Recorder charts ---------------- v Stored:' where and.,Jor how long Log N (permanent) - ---------- I / Locatedt f la 4 { C '
- 3. Evacuation alarms: number and 'u c a u s e - - - - - - -- -- - - - - -- - - - - --- / I. W J4 4,198/
2.
- 4. Evacuation procedures, drills -- / .
- 5. Us e o f by-pass keys ----------// 1, 5~p t o - - 3 0W l 6 . Key s ec uri ty --------------- --- /
G ener al s ecurity ----------------/ Night use of building ----------/ .
- 7. SOP 'S - Note any revisions -----./
- 8. Film badge, dos ime t er ---------- v'
- 9. Night watchman r ecord ----------./
C. Reactor Bay
- 1. General condition of pool ------ /
- l l
- 2. General condition of storage --- /
- 3. Use of cable trench ------ - /
- 4. Nitro gen diffuser --------- ---- /
- 5. L'isc ellaneous ( Lis t) ------ ----./ we<.
D . Co n tro l R o om ----------------------- v l Lis t of current operators ---------- / Senior operators: k.$. ~TT
- d. 6. 9 0'. Ct. -ggo Operators:
C N 04-lM E. Offica (film badge rack, e tc . ) ----- V (h [ l P . Co un ting Ro om ---------------------- ./
- 3. Rooms & Storage upstairs ----------- v l
r L ]) } Pogo 5 r - lOlk Com=cnts [ R. Stairwell & pump area - -- ------- ^v/
- 1. Demineralizer system ---- -----~
{
- 2. Outside air filters ------------ v .
v I . Stair s and b eam room --------------- /
- 1. Thermal co lumn --- ------------- /
{ 2 . B eam tub e ------------ ----- ---- / 3 . Fuel s to r ag e --- ---------------,-
- 4. Liquid & solid waste storage --- /
l f J. Health Physics ) 1 1. Sampl e remov al ----------------- / . l 2 . SOP ' S ( li st ) ------------ ------/ ' I /
- 3. Excursion a. Film badge or incident placementmonitor
------- -dv/ '
- b. Other ---- ---- ------- - I/
- 4. Film badge, dosimete'r records -- /
- a. Staff - - -------- -- ------ -/ -/
- b. Students --------- ------- - /
- c. 3uests ---- --------- -- - - /
- d. Night watchman ----- - ------
- 5. rossible detection of fuel element rup tur e ---- -- ----- - - /
6 . Radiation survey ------ -------- ./ -Dates:
- a. P eriodic swipe tests -- ----- /
J IN d" " '- b . P o o l w at er ---------------- -- / 16 4 4 C - - d
/
- c. Inside air - ------------- --
d . Out side air -------- -- ;- ---/ '
- e. Neutron level (sub-critical - /
f . Misc . items (list) --- --- -- /
- 7. Emergency box (Physics Bldg.) - s[
General comments: Two items: (1) Day dates are missing--see page 3, item le, right-hand colue.n, of this rcport for pages. One can tell the transition from ene day to the next by noting when the times chang, for example, 1500 hrs to 0800 hrs. (2) Hot water in the emergency shower: The lack of hot water in the ccorgency shower has been noted in the last two inspections (May 1980 & Nov. 1980). I understand that the campus committee on safety says that hot cctsr is not necessary in emergency showers, I disagree on two counts. (c) It seems to me that the combination of radiactive contamination and subccouent bath in a cold hhower could lead to shock and shock can not be ignored. (b) Whatever time it takes to shower in cold water could lead to hypsthermia and that too can not be ignored. I don't understand why the delay. Years ago the physic's building had hot
. catcr in all appropriate Caucets. During the emnhasis on energy conservatior.
hot water f aucets in the rest rooms were turned off. The one in my of fice was not and I had hot water. What has changed? 7hv can't we eqain have hot
- r, . m n ,
7 :c~,pyrr.g w m _~ dei 0 :{ ' mea.o % o ,
~
suidiesc nose.Missowiapot Yl . uL is Tem W6 March 31, 1980 5.r/ERSITY OF MISSOURI ROLLA ME '.CRA:3DUM TO: D.R. Edwards A. Elliott From: Ray Bono
Subject:
UMR Monthly Reactor Health Physics Audit 1 s I Due in May.
- 1. Sealed Sources.
12, 1980 g 2. RAM Calibration. Remote area monitors were calibrated 1980. on March f and will be due again no later than June 30, g 1 l 3. Health Physics Instrument Calibration. All 8,Y and Neutron Health Physics instruments were calibrated on J! arch 12, 1980 and are due again by no later than June 30, 1980. H.P. Reactor Instruments calibrated on 3-12-80: 1.) Eberline Frisker s/n 20G6 2.) Eberline C.M. E-120 s/n 3194 1.) Victoreen Thyac-389 s/n 1202 4.) Eberline Pic-6A s/n 1405 5.) Eberline Pic-6A s/n 1799 6.) Eberline Pic-6A s/n 1851 7.) Victoreen Radector III 2035 s/n 897 (Reactor Emergency B5x, Physics aldg)
- S.) Victoreen 488A s/n 243 (Neutron Instrument) .
4. Swipe Tests of the Reactor Building. Were performed on 3-18-80. !I 5. Air Releases. Complete through February, March has not been typed yet. One water release was recorded on March 3, 1980, with
- 6. Water Releases _.
no detectable activity.
~
I - g
)
)
REACTOR FACILITY I'..JECTIC?' -- Dste( s) Q<J Jll 2 2. 2/,,19 f / (Phone: 341-4236) '
/
Date(s) of last NRC inspection M Date(s) of last "inhouse" inspection 6-hA 30 Dlw 'T,. II - NMl ( Log Book Inspection: Log Book I; umber Pace Date From entry: 5 8'3 hi p_ f /99l
; Through entry: g- g7 4 .
( Ngg _f q ~ '- alp h .' 5 0 9.' M Follow up itrms from urevious intrection (item; follow-up): p w-en.>Z 4=4(?'p F% % h a Q A [l I l0K! Co=ments A. Technical sp ecli'ic ations --- f; Changes % , if so, list 4 Appendix A -- Jen. 6, 15:67 ---------l l L ,4 r J - ' "
- - - - ~ ~
LI4PC k wA-
/ - As a M O M 1.
(2.1) Ventilating fans ---------- Automatic c l o s ur e - - - - - - - - - - - - - - - - p
/
I 2. (3.1) Fool water depth (16 ft. min above core) -----------------------V'
- 3. (3.1) Inlet water temperature 6 0c ? < t < 13 5 ? - - - -- - -- - --- -- - - /
- 4. (3.2) Radiation one meter above g ,g- $
pool < 5 r.r/hr um 5. (3.2) R e s i s t iv ity ) 0.5 megeh:.-cm-, / g - 1 TR M
.. - - - - - - - - - - - - - - - - - - - - - - - - l- - -- - g I Typ e c f a l e .e n t s :Other d a (J lov. -(s): u ( A r, _ ELL I ( 4.1. 3 )j p' ex < 1. 5 . ![lTrr-cent Sr. O=er.
1.51 (Pex ( 3.51 five consecutive;l 3ates: (1) u
- days twice a year 1- - (2) -
./ . Control rod: (9.5) conditien / Dste inspectec: u 7g ggf
( 4.2.3) Reac tivity shutdcwn y F
/
I arcin at least 94 --------------- ( 4.2.4) Drcp time ( 600 nsec ---- / (9.3) Dates: (1) ( 4.3.2) Lirit lights; shim ran;e l/ (2) I lights;
- 8. lieutron magnet source (min.contact n hts 10 6lig/sec) , /
+ b T kl - '
S, I 9 9l To w - '27,1 Sal 71 w - j Q If n j 72 T - -
%198/
I ,y... - Lu. 24, / 9 P/ (
)
I IOKI Comments Pa50 2
- 9. Safety sy stems (annunciator) ---- 17 (5.4) Start-up channel ---------- 1/
(5.4) Linear channel I
'f I (5.4) Log N - Peroid channel (5.4) Saf ety channel #1 (5.4) Safety channel #2 ----------f v/
- 10. (5.5) Magnet release time (50 msee, /[
- 11. (5.7) Radiation levels ( O.1 mr/hri / Location Reading iPool surface above core ------------n k,M Near demineralizer B eam ro om I
--------{A eP u -(
12 (5.8) Portable survey List: N'eutron y struments i /j Alpha [f f h 3 nema q Beta { Other
- 13. Exp erimental f acilities ----------- / Give example as to how used.
I Hung s ampl e s --------------- ---- / (6.1.1) Core access element ----- Ev. Am (6.1.1) Isotope prod. element -- l & CM = v. T. - M D, ". I ( 6.1.2 ) Rabb i t tub e ------------- L e i (6.1.2) Thermal column ---------- Lv, I (6.1.2) Beam port ----------------- -[ I (6.2.2) Documentation of exps. - - - -o7C (6.2.3) Single independent exu-eriment: O I (6.2.4) Si $fe(mov.71 I L 0.4.1 --- -------- ---- v: able ex D periment:!
--------- v O.69*I11 movable ext. ------ v (6*I.5) Experiments having' moving : #
parts: Cex ( O.05% --------------- (6.2.6) IPo sition of any/all exp. er,
- 14. Seneral Operating Limitations I I (7.1) Startup: Sr.Gper. plus one L /
(in the control room) (7.1) Operation: S.O . plus one ---/ I (in building) (7.4) No fuel position vacancies in core;, loading (wall chart) -----/ I
~
l
L
)
Pago 3 [ 15. Fuel storage & Transfer I OK l Comments wall chart -------- --------------. .v (8.3) Fuel handling tools locked ---/ ( (8.4) Fuel transfer--three men , (Sr. Oper.; Lic. Oper.; plus one --cK
- 16. (10.1) New loading: approach to
[ critical gxp. reason & date)----- / g fjgl p , :_ _ _ _ _ - tL. E . 3 [ (10.2) Core configuration change: 71 g 72 g one grid position. (Reason & date) / y 8.8988 TI P (10.3) Loading change of more than: { one grid position-unload 50% ----- / g " y , Y bg h- G
- 17. Instruments functioning (Table I)-t # (On weekly check list - *)
Scram: Eanual --- ------ - -- ----- - L / -.startup rL Period < 5 sec. I
/- o 150% full power ----------
Bridge mo tion ---------- h -/-*
/ - startup Log N - Period non-on ----- y *startup
[ Rundown: 120% power (linear') --- - /.* P erio d <.15 s ee ----------- /-.* Reg Rod (insert limit-auto! ( r un d o ven ) - - - - - - - - - - - - - - -- ~ 7/ * - 120% full power (log N) -- W* Low CIC voltage --------- L f lstartup [ High radiation ------------ / s tar tup Rod prohibit: Period < 30 sec . - L /* Any recorder off -----------v* [ Low count rate --------- - <-* Reg Rod prohibit (rods ' below shim range) , /- , Inlet tenp. > 1350F vo { Servo. prohibit on reg. rod ------- - /-.~ 3
- 18. Check Lists and records Lo g book c heck ed ------------------ / - 428 O
[ (9.1) Daily facility check list I
--/
(9.3) Instru .ent channels & area Dates: (1) 3/20f?l r.onitors-calibrated at 90 day (2) [ in t e rv a l s - -- -- --- - -- -- - -- - - - - ---- / (3) 9/29/f/ (4) U'..:.R s tar tup chec k lis t ------ --- [ Hourly records-no te variations -- -/ p/ dhut-down check list ------------- -r 7/e ekly chec k l is t --------------
-/ , A L o, Q, L @
'.~o r k l o a d l o g - - - - - - - --- - - - - - - -
{
~ ~ ~ ~ ~
Six month systems check ---------- - / Dates: (1) A (7Po ]W (2) (L A Ac3#99/ v g~ E [ - c - - - - - - - - - - - - - -
) ~
Page 4 I - iOKl Comments B. Records I 1
- 1. Log books ---------------------L - Current book number g-Other l- '-t Stored L c . ..mD ,
- 2. Recorder charts --------------- - Stored: where and for how long I Log N (permanent) 's Located: W' '
- 3. Evacuation alarms: nutber and cause ------------------------- / 1. _% ;9&I - . o. G j.c...
- 2. D l
- 4. Evacuation procedures, drills -I /
- 5. Use of by-pass keys y12 -
( 194 /
- 6. 3eneral Key security security--- ----------- - l-/v I --------------
Night use of building ---------- f M
- 7. SOP 'S - Note any revisions - ---./
I 8. Film badge, d os im e t er ---------- /
- 9. Hight watchman r ecord --- ------ /
I , C. Reactor Bay . q^.
- 1. General condition of pool ------ /
- 2. General condition of storage --- --b
-H A ]
- 3. Use of cable trench ----------- /
- 4. Nitrogen diffuser --------- -- 7 v
- 5. Miscellaneous (List) ---------7 og, I
D . C o n tro l R o om -- ------- ----- --- -- -- - / I List of current operators l
'/ Senior operators:
CL L.LW -1920
- k. $. - i12I Goerators:
C.YTl.6 4 - /Tfo E. Office (fi?.m badge rack, e t c . ) --- - / *k'.%. $ w < 1991 M.R. Q 192l l F . Co un ting Ro om - ---------- -------- /
- 3. Roo=s 2: Stor age up s tair s ----------- /
1 1 .I l I .
} ,
} Pego 5 lOhl Com=ents F F.. Stairwell & pump area ------------ Av i
l
- 1. Demineralizer syst em -----------.v
- 2. Out sid e air filt er s ------------ /
)
I v I. Stairs and bcolumn
- 1. Thermal eam room ------------- j /
2 . B e am tub e --- - ------ --- - - -- - -- - - / 3.Fuelstorage------------------f/ I 4. Liquid I.c solid waste storage ---y J. Health Physics 1 1. bampl e r emov al ---------------- I /
- 2. SOP'S (list) / l I
- f. 1
- 3. Excursion or incident monitor
- a. Film badge placement ------- /
b . O th er -- - - -- --- -- -- - - - - j/
-- - /
- 4. Film badge, dosimeter records - /
- a. Staff ----------- -----------
I b . S tud en t s - -- --- ---- ---v' / - -- - -- f ./ c . 3u e s t s - ---- - ---- - - -- - - -- - I /
- d. Night watchman I 5. Possible detection of fuel element rupture 6 . Radia tion surv ey ---------------( -Da t e s :- Ag A 2- g I a. Feriodic swipe te s t s -------- /
b . P o ol w a t er --------- --- ---- -- / O. q I
- c. Inside air - ---------------- /
I d . Ou t si d e a ir -- - ----- ---- - ---v
- e. Neutron level ( sub-critical - /
- f. Misc. items ( li s t ) -- ------ /
I
- 7. Emergency box (Physics Bldg.) - -/
m l General comments: (1) The overall operation of the reactor is very good. The housekeeping is superb. It is not easy to keer a facility and a portion as I clean where a portion en olectronic shop. must (2) There be used as ahot is now classroom, water in the emergency shower. (3) The pcol wall paint seems to be holding its own. It, bewever, (4) Greater care should be taken to have the I nocds sa be watched. entries in the lo; book be correct and comrlete. For e..arrie: (c) On June 9, according to the log book it teck only one minute to check out the reactor. (b) On Aug 24 the reactor was evidently taken from 69'.V to 69T but this was not recorded. (c) On Eept 9 there is a discrepancy between the los book and the U1'RR Start-ur check 2 ist. Log says to core #72 and mentions 72T; the check list nenti' ns o 72'.7 but not 72T. r E. Bolon M f kr. A. E. Elliott
T
)UMRRcctor 1 @y 6 b Health Physicists Survey Instrummnts Calibrated & In-use l
Date: October 18, 1977 I Serial Number _; Inctrument/Model Manufacturer 602 Cutie Pie Survey Meter /CP-3 Technical Associates 477 Cutie. Pie Survey Meter /CP.-3A Technical Associates { 478 Cutie Pie Survey Meter /CP-3A Technical Associates 479 Cutie Pie Survey Meter /CP-3A Technical Associates 3194 G.M. Survey Meter /E-120 Eberline { 2247 Radiation Monitor /RM-14 Eberline 897 High Range Survey Meter /RadectorIII Victoreen L n aa-t h - - - E W PIC -/ A -
- 1405-1202 GM urvey eter/Thfac 3850 Victoreen Victoreen 243 Noutron Survey Meter /488A 163
[ Noutron Dosimeter /D-300C Kaman ha.s. - - g W p3c-i.a -- t 7 97 U-if~ P^ 9 y w - . . E p: . . T r w -LA - 1951 [ tof9j u wuc- W + t= _ E [ [ [ . ( E F - --
) ) Er' Operator Rcoualification During Licence Period l
IA.ExaminationReviewSheet Lame of Operator License (Annual numberexam -- usually inCot:: E-sein. c a t es summer) ment s o-year! { and date EMg - record I 1. Ea - ct.E. & 22act sop 434._e pq,%,9g, ., v
- 2. :
l k . f. SD P =2 ild '~~1 I9,192l l N b [M O P FW73 k '( l iPI
^
l s
~ C .W. 04 o P 5231, 9. - n ti, I 99o B.
s n. ewuaw oP rs,t Performance Evaluation (Semi-annual) 9An 'W-Name of Operator Evaluation Date Comments P-- v:=:Y - c.D ._ W
- 1. k. h. h g k Pf3/g} l'- - ' - -3 L rs Mn --. x crlu fge rol3lgo;',
%- 3/29/pg M L ->e - -ex gfot.jg, gyg, 8l5/91 O s W := A -
9/nt es - netz4ss E ,-- - ,;. %= ~ w .at s-t' , , -
- 2. An
'3 - -- u-cx 4ll7ffljS/fft ,* IQgs y/f ,9f g c.//, *"--- - u< '/o/esj eg ysi 0.$ 2t M e- . o. - _
e + - w .- a.ae /utos . m ,i,,
$ r - -- . _ , wt --m 1c/12/9/
y l' b 2r. t~ r/#/et % n. sa r . yLs. . , m g,1,, 4" s-C.hi.S Q 6/"/f/ 3 Iz Tidm _ _ 8.D.kl M '7[3-[gl --3) {J Cd b h . C. On the Jo'o Trainin;;: Progress Report ( Annual sur=:ary) (Notebook kept by the operator.) Hame of Ooerator Annual Summary Date Comments g ' d . 4. g .c o. t*. . l 2-P q/e[7/gf
-+.x - p ,u
., c , n .e C
3. es.:. nu X. %. % bu 4-l EC- =h C.m.8 4 1
, 7 .,
l
)cialDuclearrotericls'}")
Position Kame R eac tor Dir ec tor ------------- &h.. Ct 8. Reactor f $"1 ----------- h E N 'M St.T Cu s t o d i an ----------------- MbM l
- 1. (See p. 2) Procedures reviewed annually by the WA Reactor Cua. dr:
Date Name g Q p , . i_._ E . a g I 2. SNI Records: 'llhere kept? M (1) Position and/or change of rosition of non-irradiated fuel: d
-.2.
l (2) Position and/or change of position of irradiated f'uel: % (2 (3) SNK receipts: h (4) SNC shipments: M - E E (5) Semi-annual Material Status Recort: b Most recent previous report: Date 6acde /fS/ Current recort: Date Mygl (6) Annual Physical Inve.ntory (SNM status lo~): UI C I Previous report: Date ja g Current report: (7) SNM loss, theft or sabotage reported: b I Date To whom reported (Director Region III URC) (8) (See p. 5) Violations of Written Procedures: (9) SNM Internal Control Areas: Dry stora5e area (basement): GI Reactor: K Containment building: Q N'fy - X SMKl y: to/Qti ,I s # M. W
~
~
I . I
--------__w___ -
. . _ _ _ 7_ ___ _ ___ __ r ~ _.... .
. ;,a.
e. f k'..
- Leem C Rc.:.a. %ssous. GE/.01 Te% hone: (3141341-4240 January 17, 1980 1 UN*VERSITY OF MISSOURI-ROLLA l
l l MEMO TO: D.R. Edwards and A. Elliott I FROM: Ray Bono and N. Tsoulfanidis I RE: UMR Monthly Reactor Health Physics Audit i On January 4,1980, we performed an audit of Reactor Health Physics l l activities. t!e checked the frequency as well as the method used in l :arrying out the following activities: om Frecuency _ runction_ I 6 months f ' @ fl
- 4. Swice test of reaied sources quarterly 9-22-8f
<. Radiation area monitor (RAM) calibration quarterly-c#
I V3. Health Physics ir.strument calibration Swipe tesi. of reactor buildino monthly 9 -l'l- @ A. ~ monthly - i-M-#l
/5. Air releases regeneration t2.- fl l vt.
v7. Water releases Building survey monthly- 9 Pl monthly-T-424 ~~ N
/S. Routine pool hater analysis monthly- t-3 f-fi I v9. By-product material released vs, fea_ A th % There are eight sealed sources requiring a f, - * ~s -3o -fi
- 1. Sealed Sou_rces.
leak test every sir, months. The last leak check was performed by Ray I T,ono in Nover.ber 1979. All eight sealed sources are due to be leak
.erted again in May 1980.
l 2. C.,AjM Eali_orati_on. The records show that the calibrations have
- en perfomed on scr.edule but in one case, tr.ere tt.izer the first and second quarter of 1979. Theis activity a Tive month gap recorded -
I e "nc the source used for calibration should be the activity at the time
.' Cilibration.
- 3. Health Physics instrument calibration. This is done on a quarterly basis at the Reactor. Copies of all surveys and instrument calibrations Meter should be fctrarded to the Health Physics office upon completion.
I :311brations are in order but a few calibration sheets do not indicate the scale used. Scale used should te recceded. (Don't just say or/hr, be sure to give the upper limit of the scale for all caters. ) Enclosed is a copy of the U.S. '!RC Regulatory Guide Revision 1,G.M. Octcher I .
'979 which :.houlo t e iclic :ed .chen calibratior. .are perforned.
The a- .L.M '.T',N '*J4ty B1S*. lute (art I .
s [I II Nucl: r Reactor Facility Nuclear Reactor Rolla, Missouri 65401 Feb. 19, 1982 ween: ( m m 236 { UNIVERSITY OF MISSOURI-ROLLA l I [ Memo. to: Alva Elliott, Reactor Manager 66 \' b From: Albert Bolon, Reactor Director Re: Corrections and additions to SOP's Alva, I believe the following corrections and/or additions are sufficiently ' substantive that they should be made immediately to the SOP's and the Tech. [ _ Specs. (if we can change them too). [ S0P g line (Preamble 3 3 change "by the S0's" to "by either the R0's, [ SO's, RM or RD" 101 2 S&6 change " possession of the Senior Operator on { duty" to " cognizance of the Reactor Manager" 101 4 4 change "0.6%" to "0.5%" 102 p.2 delete sent. "Always keep one hand on the rod [ 1 drive switch." 107 B.1 3&4 delete "while maintaining direct contact with { the rod control switches." period after " system" 109 C.1 3 period after 600 W. then (This is n a) 109 graphs add reference title & no. 110 footnote (see my book) 112 1 5 ERDA to DOE 112 4 2 ERDA to DOE 115 4 4&S delete sentence (?) "When an element is removed { from the dispicy and stored in a safe place." 115 Fig. 2 change " POOL" to " FUEL" 207 16 2 change "SR0" to " Reactor Manager" { 301 E 3 change "5 megohms" to "0.5 megaohm-cm" 303 A last " 2x10-5%" to "-2x10-7 ak" k 305 firs t change " Atomic Energy" to " Nuclear Regulatory" an equal opportunity institution [ - _ _ - - ---
I S0P S line l 306 title add "for Experiments" change Table of Contents too. 306 throughout c
- f ->f m ~(mass )
601 3 1 change " tritium" to " titanium" 807 2 f. 20K cpm, not 20R cpm l I i i i l 'I I
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