ML19309H885

Annual Progress Rept of Univ of Mo,Rolla Nuclear Reactor Facility,Apr 1979-Mar 1980.

ML19309H885
Person / Time
Site:	University of Missouri-Rolla
Issue date:	03/31/1980
From:	Elliott A MISSOURI, UNIV. OF, ROLLA, MO
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ML19309H878	List: ML19309H877 ML19309H881 ML19309H885
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! PROGRESS REPORT t

0F THE UNIVERITY OF MISSOURI - ROLLA NUCLEAR REACTOR FACILITY 1

APRIL 1,1979 to MARCH 31, 1980

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i Submitted to The Nuclear Regulatory Commission and The University of Mi'ssouri - P. olla j

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By Alva E. Elliott, Manager Nuclear Reactor Facility

, University of Missouri - Rolla Rolla, Missouri 1

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l Table of Contents I. I n t ro d u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. Pe rsonnel , a nd Heac 6c r S ta f f . . . . . . .'. . . . . . . . . . . . . . . . . . . . . . . . . 4 III. S up po r t i ng Fa c i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 IV. I mp ro v eme n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

. V. Rea c to r O pe ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 VI. Pub l i c Re l a t i o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

. VII. Educa tiona l U ti l i za ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 1

VIII. Reac tor Heal th Phys i cs Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 t .

IX. Plans ....................................................... 27 X. Summary ..................................................... 28 i

I XI. Appendices .................................................. 29 A. 50P - 809 Semi Annual Checks . . . . . . . . . . . . . . . . . . . . . . . 31 B. I nde penden t Au d i t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7 6

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!. Introduction j i

This progress report is repared in accor' dance with the requirements of the Nuclear Regulatory Coninission 10C FR 50.71 concerning the opreation of the University of Missouri - Rolla Nuclear Reactor Facility (license R-79).

This reactor, a swimming pool type modified BSR, war, first licensed as a 10 Kw training and research facility with inicial criticality on December 9, 1961. In January 1967 an amendment was granted by the Nuclear Regulatory 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 stodents of the various departments of the university for their educational and research programs. Several other universities has made use of this facility during this report-ing period. The facility is also made available; for the purpose of training reactor personnel, to the nuclear industry and electric util-ities.

The reactor staff has continued to review the operation of the reactor facility in an effort to improve the safety and efficiency of its opera-tion and to provide conditions conductive to its utilization by students and faculty from this and other universities. The following sections ,

of this report are intended to provide a brief outline of the various aspects of. the operation of this facility including its utilization for l

education and research.

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II. PERSONNEL AND REACTOR STAFF A. Reactor Staff Name Title Dr. D. Ray Edwards Reactor Director Alva E. Elliott Reactor Manager R. L. Jones Senior Reactor Operator .

Carl Barton Electronic Technician Karen Lane Secretary Juls William Lab Mechanic Tom Shannon Student Research Assistant Ray Bono Campus Health Physicist B. Licensed Operator Alva E. Elliott Senior Operator R. L. Jones Senior Operator l

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C. Isotopes and Safety Committee Nord L. Gale (chairman) Life Sciences Ray Bono (secretary) Health Physicist Ernst Bolter Geology and Geophysics Otto H. Hill (resigned Feb. 80) Physics

0. K. Manuel Chemistry; T. J. Dolan Nuclear Engineering D. Ray Edwards (ex officio) Reactor Director Alva E. Elliott (ex officio) Reactor Manager N. T. Tsoulfanidis (ex officio) Radiation Safety Officer This committee is required to meet at three month intervals. However in practice, the frequency of the meetings are usually jreater.

1 D. Independent Audit i

Dr. Franklin Pauls, former Reactor Directoc, acts as the independent auditor of the Reactor Facility. He reviews .all records, procedures,  !

and operating methods of the facility on a semi-annual basis.

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III. SUPPORTING FACILITIES j 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.

Analog Computer: This computer is currently available to faculty and students and is used in scheduled classes for both graduate and under-graduate students. Several units of auxiliary equipment are also avail-able 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, constructed as a masters research project, is mounted on the face of the thermal column door.

Neutron Diffractometer: A single crystal neutron diffractometer unit is available for use at the reactor. This unit, constructed as a masters level project, has also been used for doctoral research.

Activation Analysis Lab: The activation analysis lab has proven to be the most utilized sup')orting facility. The laboratory contains one 400 channel analyzer, and one 4096 channel analyzer, with NaI or GeLi Selectable Detector input. Included in the auxiliary equipment is a tape punch, X-Y plotter, IBM electric typewriter, multi-scaler program-mer, digital pulse stabilizer, a scope camera, and a teletype terminal.

Three scalers are included in the laboratory equipment with the appro-priate detectors for counting alpha, beta, and gamma radiation.

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• A GeLi detector with background shield and a four ton low background lead shield that houses two 3X3 sodium iodide crystals is available.

These detectors are used in conjunction with the multi-channel analyzers.

Several other units of equipment are available for the detection and evaluation of radioactive materials.

Pneumatic Tube Assembly: A dual tube pheumatic system is installed in the core of the reactor. This is a dual tube system, one tube being cadmium lined, the other bare. This system is a positive pressure type, using nitrogen as the propellant.

Dynamic Void: A method of introducing a void on the perifery of the core by use of nitrogen gas. This allows for a variation in void as a function of core height, total volume or volume change.

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IV. IMPROVEMENTS THe following items are considered improvements to the existing facili-ties during this reporting period.

(1) The previously purchased Solid State Area Radiation Monitoring sys-tem will replace the original Radiation Area Monitor that has been in service since 1961. The system was to be installed during the previous reporting period but manpower restriction prevented its timely instal- 1 1

lation and testing. Current plans call for installation and testing dur- '

ing the Sunrner of 1980.

(2) The purchased Magnet Power Supply and Safety Amplifier which will l replace the present system that has been in use since 1961. The new system is of solid state construction and should improve the operating reliability of the entire facility. Current plans call for installation l

and testing during the Suniner of 1980. l (3) The construction of a new office / reception and entrance to the reactor facility was completed. This has increase the useable floor  !

l space by approximately 300 sq. ft. and separates the office from the  !

controlled access area.

(4) A update to the Multi-Channel Analyzer (40% channels) was recently l purchased. This allows for faster and improved results, for various l 1

operations concerning the counting of samples for discharge, release or i

experiments. The update consists of a custom isotope library and 100 MHZ-ADC. )

1 (5) Three portable health physics ion chamber radiation detectors were  !

purchased to replace old cutie pies. These instruments serve both lab and staff for experiments or routine facility use.

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(6) Closed. circuit video core monitor and camera for control room

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observation of sanples that are placed into the reactor core and

routine visual observation of the reactor core.

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V. REACTOR OPERATIONS Facility Use Table 1 depicts the corrent core loading designated as 67. The number 67 denotes the Sixty Seventh core configuration (assembly and location),

that has been used at the reactor facility sinc 6 the original operating license was issured in 1961.

Table Ib shows the only other core loaded in this reporting period. This core was a result of misplacement of a fuel assembly (F10) during a Fuel Handling Lab. This lab experiment was being conducted for measurement necessary for a sub-critical multiplication curve the fuel assembly was inadverently loaded in position C7 instead of the intended position of D8. The excess reactivity of this core (68) was measured and the assembly was relocated to its intended position. Licensed operators involved in the action were required to review the fuel handlong proce-dures. There has been at least eight fuel transfers since this problem occurred and all have been accomplished successfully.

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i UMRR CORE AND RACK STORAGE FORM j TARLE 1 l Original Loading DATE December 19, 1978 LOADING NUMBER 67T kl R2 R3 R4 R5 R6 R7 R8 R 'l RIO Rll 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 R1b R17 R18 R19 R20 R21 1,< .' ? R23 R24 R25 R26 R27 R28 329 R30 KEY TO PREFIXES A F - Standard Elements a 5 IIF - Half Front Clement c HR-1 F-14 F-1 C-4 IIR - Half Rear Element 13 F-8 C-1 F-16 F-9 F-4 F-10 CA - Core Access Element c F-6 C-2 F-19 C-3 F-12 F-11 IP - Is t Pe Production Eleme S - Source Holder r BR F-17 lF-15 ,F-7 CR -

Other 1 2 3 4 5 6 7 8 9 BRIDCC SIDE tiMRR FORE STATUS

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1;le m. f l'on . f M.isa I:lem. 1%s. Ma m I: l .*m re m . Mass liR- 1 C3 84.912 F-16 D5_ 120.270 F-12 E7 168.774 Bridge Position F-8 D3 170.229_ F-19 E5 170.264 F-10 08 170.193 Inches from T.C. o.o ,

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 06 170.178 C-2 E4 102.125 C-3 E6 101.978

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F4 169.111 F-7 F6 170.154 1 l F-1 C5 170.223 F-4 , _D7 170.206 -

l 1. Ar / P- 0 one ra7p? p To t.i t Ma:m r: rams 2870.069 (measurerd value)

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UMRR CORE AND RACK STORAGE FORM TABLE 11 DATE June 26, 79 LOADING NUMBER 68T kl R2 R3 R4 R5 R6 F7 R >l R 'l RIC Rll R12 R13 R14 R15 IP CA HR1 RACK STORAGE FACILITY F13 , F20 HF1 F22 F2 E5 F3 F18 F21 R16 R17 R l 53 R19 R20 R21 1,< ? ? R ?.i R24 R25 R26 R27 R 2 fl R29 R30 KEY TO PREFIXES A . I ~ I'tandard Elements 3

C - Control Elements HT - Half Front Element c F14 F1 C9 F10 IIR - Half Rear Element o F8 C1 F16 F9 F4 CA - Core Access Element E F6 C2 F19 C3 F12 Fil

• P' " " I" S - Source Holder r BR F17 FIS F7 CR Other 1 2 3 4 5 6 7 8 9 IIRIDGE SIDE t'MRR COPI' STAT 11S Flem. 'Pos.! Mass Elem. I'ns . Ma r,s ElemI Pos. Mass FA D3 170.229 F19 E5 170.264 F12 E7 168.774 Bridge Position F6 E3 164.16n F1R FR 16R_RR4 F11 FR 16R_Q64 F14 c4 170.210 C4 C6 102.112 Inches from T.C. Q C1 04 102.112 F9 D6 170.178 C2 E4 102.125 C3 E6 101.978 F17 F4 169.111 F7 F6 170.154

_ F1 C5 170.223 F4 07 170.206

,._fl6 DS 170.270 F10.._.CZ_ 1Z0.193 _

"..tr / K 0.92% Tot.i t M.iss Grams 2785.157 (meamired value) 1

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Table 2 4

Facility use of core or core plate locations Number of Facility Hours Used 83 - 0.05 B4 - 10.85 B5 - 0.66 l B6 - 0.06 ,

C2 - 0.06 I i

C3 - 0.6  ;

C4 - 0.61 C5 - 3.4 C7 - 15.57 C8 - 0.03 D2 - 1.85 D3 - 1.52

, D4 - 0.32 05 - 2.83 06 - 2.4 07 - 1.78 08 - 1.6' l

09 - 1.15 E2 - 0.45 E3 - 0.6 ES - 1.15 E7 - 1.2 E8 - 0.6 F3 - ,

20.73 F5 - 0.68 F7 - 1.0 71.75 Total i

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Table 3 Facility use other than the space around the core includes 1

Facility Hours I Neutron Chopper 8.48

Cadinum Rabbit 1.0

. Bare Rabbit 25.3

. Beam Port 4.95 Reactor Console 1013.59 Thermal Column 9.46 1062.78 Total l

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i Table 4 4

i Samples Irradiated -- Major Users i

Chemistry 33 1

Nuclear Engineering 225 j

Misc. 26.2 l Total 284.2 i

Table 5 Number of Samples Less Than 1 Hour 222; Hours 59.2 Number of Samples 1 Hour or more 27 ; Hours 44.5 Total Samples 249 -

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Table 6 Hours in Use 903

Hours at Power 324 KW Hours 23333 Hours for Researen 81

, Hours for Instruction 404 Experimenter Hburs 1273.7 Sample Hours 103.6 Average Number of Experiments 1.18 Average Number of Samples 0.8 235 Grams U Burned 0.8504 235 Grams U Burned and Converted 1.0066 1

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Table 7 Unscheduled Shutdowns 7-17-79 Rundown; 120% Denand... Operator error on change of Linear NI scale during Shutdown of reactor before reaching 30% of present scale. Reactor power approximately 10 watts.

6-15-79 Reactor Trip; 150% Full Power... Relay setpoint (1A) drifted to 200Kw from a normal value of 280Kw (140%). Reactor power was 200Kw.

6-20-79 Rundown; 120% Demand. . . Operator error on failure to change Linear NI scale while attempting a power change from 20w to 60w. Reactor power approximately 24 watts.

6-20-79 Rundown; 120% Demand... Operator error on failure to change Linear NI scale while attempting to increase Reactor power from 20w to 60w. Reac-tor power approximately 24 watts.

6-22-79 Rundown; 120% Demand. . . Compensation voltage on Linear NI was being de- -

creased by instructor for training. Reactor power approximately 60 watts.

6-22-79 Rundown; 120% Demand... Compensation voltage on Linear NI was being de-creased by instructor for training. Reactor power approximately 60 watts.

6-26-79 Rundown; 120% Demand. Fuel Assembly moved to close to Linear NI CIC.

Reactor was subcritical.

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6-26-79 Rundown; Reg. Rod Insert Limit on Auto... Operator error while attemp-ing to measure Kex of core. Rod Control System was placed on Auto at a kcactor power level of 20 watts.

9-14-79 Rundown; High Radiation Area... Spurious Alarm on #3 Radiation Area Moni-

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tor Channel. Investigated possible causes, rundcan terminated and reactor power returned to 10Kw.

9-27-79 Rundown; High Radiation Area. . . Spurious Alarm on #3 Radiation Area Moni-i tor Channel . Investigated possible causes, rundown terminated and reac- l tor power returned to 600w.

10-8-79 Rundown; High Radiation Area. . . Operator error while taking hourly logs the check source for #1 Radiation Area Monitor was activated causing a-building evacuation alarm and run.down. Building was evacuated and reac-tor shutdown until actual cause could be determined. Reactor power was 2Kw.

11-5-79 Rundown; 120% Demand... Operator error on failure to change Linear NI scale while increasing reactor power. Reactor power at 24 watts.

3-18-80 Reac' tor Trip; 150% Full Power... Operator error while adjusting Log N CIC the wrong detector (i.e. #1 UIC) was moved causing trip. Reactor was restarted, #1 UIC readjusted and the Log N-CIC adjusted as was intented.

Reactor power was 180Kw.

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Table 8 Maintenance 6-15-79 '

Adjusted safety amp relay (IA) for 140% of full power and relay (18) for 145% of full power. There was no apparent reason for drift of setpoint.

System checked and returned to service.

8-23-79 Replaced Linear Range NI amplifier (#19654) with other unit (#19683) due to noise spikes on low ranges. Linear NI amplifier was sent to manufac-ture for repair and calibration.

10-10-79 Replaced linear Range NI compensated Ion Chamber detector with new detec-tor purchased and available from supply inventory. Old detector would no longer compensate for y activity at maximum allowable voltage.

10-30-79 Replaced check source solonid on #2 Radiation area monitor. During a startup check out of reactor, the check source test produced no detector ,

response. Upon investigation, it was determined that the solcnid had opened.

Table 8 Main tenance ,

6-15-79 Adjusted safety amp relay (1A . for 140% of full power and relay (18 for 140% of full powe e

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l Core Da ta During this reporting period only core designation has been used to any extent. The "W" mode core was used for normal reactor operations since students cannot operate the reactor when the excess reactivity is above i

0.7%. The "T" mode is used for extended operation (>3 hrs), beam port  ;

or thermal column experiments. The excessp was measured cold, clean

, critical. In day to day operation the excess p is quite often lower due to temperature increase of the pool.

i Core Technical Data .

1 Average Thernal Flux 12 1.6X10 at 200 Kw Maximum Thermal Flux 2.8X10 12 at 200 Kw Average Epithermal 1.6X10ll at 200 Kw Worth of Thermal Column 0.37% @ 76'F Worth of Beam Port Not detectable Rod Worth.

I. 2.64% II. 2.65% III. 3.36% Reg. 0.347% Date 1/10/79 Excess Reactivity 0.905% Shutdown Margin 4.385%

Void Coefficient -7.8X10 -7 p/cm 3 Date November 15, 79 Limit -2.0X10 -7 p/cm 3 Temperature Coefficient -6.6X10 -5 p/oF . Date Nov. 7, 79 Limit -4.0X10 -5 p/oF Reactivity Addition Rate (max p/sec)

I. 0.018% p/sec II. 0.0185% p/sec III. 0.024% p/sec Reg. 0.065% p/sec Date 1/10/79 Rod Drop Time (24")

I. 500 msec II, 510 msec III. 480 msec Date Jan. 10,80 Magnet Separation Tine I. 20 msec II. 10 msec III. 20 msec Date Jan 10, 80 9

VI. Public Relations The reactor staff has put forth considerable effort to educate the public in the field of nuclear energy. Over 2275 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 pre-orientation lecture by members of the reactor staff. These lectures are augmented by visual aids such as slides and displays. Many high school, junior college and college groups, (from this and other universities) have at-tended 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 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 industrial and educational field and how nuclear energy helps the environmental situation.

The Nuclear Engineering faculty are members of various social civic, professional, and governmental committees. The faculty and students also are involved in speaking engagements around Missouri and several other states concerning the reactor facility and in recruiting programs at high schools and colleges.

The reactor staff is cooperating with several police departments in activation analysis of samples.

l VII. Educational Utilization l l

Approximately 47 UMR students, graduates and undergraduates have participated in classes at the facility, utilizing 2304 student - semester hours of connitted hours. Also students from several colleges, and high schools have used the facility.

l The following is a list of scheduled classes at the facility along with

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the total hours of Rcactor Use for this reporting period. l NE 304 Reactor Lab 69.3 hrs.

NE 306 Reactor Operations 169.98 hrs.

1 NE 308 Advanced Reactor Lab 135.33 hrs. l NE 300 Special Problems 22.86 hrs.

NE 490 Research 0 hrs.

NE 1 Intro. to Nuclear Engineering 5.7 hrs.

The corrent enrollment in Nuclear Engineering is 81 students. During  !

this reporting period the reactor was used 83.3% for instruction and 16.7%

for research, i

The use of the Nuclear Reactor by departments other than Nuclear i Engineering on this campus has continued to decrease. This condition is l a common occurance 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 the area of training.

The Nuclear Reactor Facility was accepted, by the Union Electric Company of St. Louis, Mo., to provide two-two week program of operational

training. This training augments the First Phase of their Commercial Nuclear Reactor Operator Training, with actual hands on experience in Start-up, Shutdown, etc. This training was provided during June and July of 1979. Another two week program was started on the last day of this reporting period (March 31,1980).

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Reactor Heal th Physics Activities for the period April 1,1978 through March 31, 1979 Health Physics activities at the UMR Reactor Facility consist 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 recorded. 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 radiatir,n surveys of the facility consist of direct gamma and neutron measurements with the reactor at full power. No unusual exposure rates were found. Monthly surface contamination surveys consist of 20-30 swipes counted separately for alpha and beta-gamma activity. In 12 monthly surveys, no significant congmination 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 rt: actor facility. Total activity released was 41.07 mci.

All shipments were utilized on the UMR campus.

Routine Monitoring 44 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 five beta-gamma, neutron area and spare badges assigned. 24 campus personnel and students are as-signed beta-gamma film badges and frequently TLD ring badges for materials

and X-ray work on campus. There are 20 beta-gama area and spare badges assigned. In addition, 4 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 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 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 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 1.65X10-0 uCi/ml.

Waste Disposal Release of gaseous and particulate activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During this period 25.15 millicuries were released into the air. Released isotopes were identified as Kr-88, Rb-88, Xe-138, Cs-138 an'd Ar-41.

Soild 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 commerical burial . site. Radioactive waste released to the sanitary sewer is primarily from regeneration of the resin exchange column.

l During this period 4 releases to the sanitary sewer totaling approximately 1200 gallons of concentrated resin regeneration solution were discharged with a total activity of 1.04 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 4 times. Remote area monitors were checked for calibration 4 times. ,

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IX Plans With the construction of a New office / Reception area, completed in June of 1980, the facility has a much improved appearance. This new 200 Sq. ft. area allow visitors to be screened before entrance to the Controlled Access Area (Reactor Facility). This new area is also utilized for records storage and the reactor managers office.

, The mixed core (TRIGA and MTR) fuel testing that was planned for the past year is awaiting NRC approval. The heat transfer characteristics of the mixed core is to be studied as part of a masters thesis during the summer of 1980. Wi r.h this data available it is hoped that testing can get underway at low power during the next reporting period.

An application for license renewal was submitted in November 79. The license renewal is currently being reviewed by the various NRC departments.

Their comment are being awaited before changes or revisions are made in the various documents and Standard Operating Procedures.

The facility has continued with it's involvement in reactor operator training with local electrical utilities. During this past period Two-Ten day programs were completed and another Two-Ten day program one was s tarted. Each program utilized approximately 65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> of instructional time per ten day program. This program is currently being reviewed by the campus administration before expansion is undertaken. The current staffing (Senior Licensed) level does not allow for more than Four-Ten day programs per year. With the addition of another Senior Reactor Operator the program could accept approximately Ten-Ten day programs while continuing all current academic programs.

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1 Y Summary l

The University of Missouri - Rolla Reactor was in use approximately 72% of the time class was in session at the university or 54% of the total available time based on a 40 hr, 52 week year. The total maintance time of the facility was 624 hrs. (30%) and provided for a total availability

, (reactor operational) of 1456 hrs. (70%).

A total of 23.33 megawatt hours of energy was produced using 0.8504 grams of U 235 . The ratio of usa'ge was 83.3% for instruction and 16.7%

for research. A total of 249 samples was irradiated during this reporting period with all samples being used on a intra-campus basis.

The reactor was visited by approximately 2275 persons during the past year. At the same time there were 47 UMR students enrolled for courses at the Reactor Facility. The facility was thus comitted to over 2304 student-semester hours of classes involving about 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> per week during the Fall and Spring semesters.

The facility will continue to be utilized by electrical utility for i operator training. Two-Ten day programs will be completed on April 25, 1980 with two more classes scheduled for August / September 1980. There has been some contact with other utilities and training companies but due to present  !

manpower limitations we are not actively seeking new customers at this time.

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APPENDICES i

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Sami Annual Check List Date Comunenced 9 v/ / 2M

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Date Completed 9/7/77  !

Total Hours on Hour Meter b /.~ r i. )

1. Vacuum Tube Test and Clean Chassis Initial

a. Log N Power Supply

/N[

(1) Cleaned chassis e # ),

(2) Tested all vacuum tubes #

Replaced: tube # tube type f J/ [f

}/-/q f7f/

Y- 9 .f75/

(3) Additional Coussents None b- b. Linear Power Supply (1) Cleaned chassis

/[

(2) Tested all vacuum tubes m7 E

Replaced: tube # tube type f J/ g V~ / 3 .

675/

.~

(3) Additional Comments Mone .

a t

S

.i

~

c. Linear Pulse Amplifier g'/

(1) Cleaned chassis .

3. #>

F (2) Tested all vacuum tubes "

Replaced: tube 8 tube typt vcwd s

Ql3' 79

, (3) Additional Comments None

d. Scaler Timer M -/

(1) Cleaned chassis m f# I/

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

- FAV e T<e/9-

~

)/si/?p (3) Additional Comments

e. Safet.y Amplifier '

m '/

(1)

(2)

Cleaned chassis Tested all vacuum tubes Mp xeplaced: tube # tube type

&p 4-2 ll9 /

i i

,?

I 2 --

-_., ~ ~ . -

(3) A'dditional Comments

f. Area Radiation Monitor .w,//

(1) Cleaned chassis r

+,t /

(2) Tested all vacuum tubes #

Replaced: tube 4 tube type p/

j y-ddAB (3) Additional Comments 91s w

g. Micro-Micro Ammeter []

(1) Cleaned chassis mfI

,, (2) Tested all vacuum tubes I Replaced: tube 4 tube type (1// *41 !100 '$ 9 0 /$ 2-t///7f (3) Additional Comments

h. Fission Preamp ' '

• ,i (1) Cleaned chassis and inspected M

(2) Additional Comments

[

T/Bt

i. Public Address System

,SL , . , --

// e (1) Cleaned chassis >>//

(2) Tested all vacuum tubes [

Replaced: tube # tube type

.i '! ',Y (3) Additional Comments

j. Log Count Rate Recorder nI ]

(1) Cleaned chassis /)

(2) Tested all vacuum tubes [

Replaced: tube # tube type v///pp (3) Additional Comments

k. Linear Recorder e [ ,/

(1) Cleaned chassis e/

(2) Tested all vacuum tubes [

Replaced: tube i tube type

$ l / l ,)<,_

(3) Additional Comments

_ _ _ _ _ _ . __ .m._ _ __ s .- - - - ----

l. Period Recorder 3m . /

(1) Cleaned chassis **/

(2) Tested all vacuum tubes /

Replaced: tube # tube type

. D j/ // ')/ >,

. (3) Additional Comments -

m. Log N Recorder

-r-. / /

(1) Cleaned chassis d' /

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

Yl'/? cy (3) Additional Comments

n. PAT 60 e IJ (1) Cleaned chassis / ,9 (2) Tested all vacuum tubes Replaced: tube # tube type k

- .- ..'..- -~ . = -~ - - . . . .. - - - . --- - - - - - - -

(3) Additional Comments

o. Regulated Power Supply ^ [/

(1) Cleaned chassis e [7 (2) Additional Comments S/'/79

p. Conductivity Bridge - ()

(1) Cleaned chassis * []

(2) Tested all vacuum tubes #

, Replaced: tube # tube type

's 2/79

q. Safety Amp Preamp

~

e [)

(1) Cleaned chassis /)

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

[

r/W f (3) Additional-Comments

2. Relay Test .

a. Console relays tested and replaged as per SOP 815 /

b. Relays Replaced K-4 k M -

c.f x 29 k'. N '

k - tb

- , - . , _ _ . = - - - - ..

(c) Additional Comments (f Y

3. Detector Resistance

a. Safety #1 Value (147) Signal to ground & </ k'// b MM (149) Positive to ground Rf Xfo d-///S Open Circuit Resistance 1 l y fr) # /2p//3

b. Safety #2 y g jo'#

(143) Signal to ground

~

_ff f/s NM (145) Positive to ground /fX/0" 8*I4 Open Circuit Resistance A /, Yeo" @//T

c. Log N (125) Signal to ground /. f)(/d ['/M (123) Positive to ground R y fo '# $+'/8 (121) Negative to ground 7 0 .V/d # b ///3 Open Circuit Resistance '2 . /j )(/ 0 * /N/N

d. Linear NN (114) Signal to ground /,1 y/4 (112) Positive to ground /.9y/o# / //M (110) Negative to ground A . 4 Y /4 " 8/N Open Circuit Resistance .,7, /, //O '

[-//8

4. Fire Alarm System Tested as Per SOP 817 [f[f/3 [J/h7f j S. Calibration Checks Note: Any instrument found to be out of calibration should be realigned in accordance with its technical manuel.

A. Temperature Recorder

1. Reading # Thermometer Recorder.

1 320F 32. *#/

2 320F -

32 #/

3 32 F 3 Z. #f 1 160 F /fD /- O 2 160 F /6//#7

~

3 160 F /4/ #/O Note: All readings should be 1 loF

2. 135 F Interlock , Trip Point -

1 15..P

}3f d),

[

_ m _=. _ . _ _ . _ _

B. Log Count Rate Channel ' .GM9

l. Pulse Generator

• Meter Recorder Initial 10 100

/A // M')

1000

'Ao 94 64_Z[,

//Fl' //66 Nkh 10,000 //) # /0 " /W//$

Note: All readings should give . 7 to 1.4 ra tio of true-to  !

observed readings. ,

2. Additional Comments C. Linear

1. Keithley Meter.

(gy, s c r>tro) Recorder (%) Initial 6.66X10 ~0 C. c t k <o' " /c'C Q 2.OX10

~

/ cxc'I /c / 0 2 m i) YA}'

m b/

6.66X10 -6 g , , 3,, - g g j .yf m Jj 2.0X10 -6 ,, 9 y 3 , f g , , , 7, ,,,, y j

~

l 6. 6 6X10Y ' "')& C. ) ks)

~

i c2 'h m5 2.0X10 2 . ,. Dc~ '

6.66X10 ~8

__ c / %

m d' }

2.0x10 -8

d. t 2 k<c'~ 9

i. O xi;5

. C C' %- ~ f) v sac y mfJ 6.66X10 ~9 6 6 5 'k /o~9 r c 2. 4 2.0x10 ~0 s. 9c y 4 S

/$

6.66X10 ~0 iso "A NU) / .

d.g ixec~'# /0 / " v' '

2.0X10 -10 ,, g y p ,,- O W 9g fj' i Note: From 10~ to 10 -8 the overall accuracy shoul'd be better than 2% of full scale.

From 3X10 to 3X10 -13 the overall accuracy should

)

be better than 4%. '

2. I Additional Comments e

l l

- - - - - - ' - - = ' - ~

~

D. Log N

1. Meter Recorder Keithley Initial

-5 5X10 100 /00 FX'd'

-6 e (/

SX10 10 '? 1, 6 N/o ^6 I/

~7 SX10

~0 1 9 4. 0 X eo -# M) 5X10 0. /

SX10

~9 0.1

.01 i A eo" F . M)

.0/2 6 X// 9 J 5X10 -10 SX10

~11

. dol

.0001

, no m 7Xs* ~D Note:

, ooge /e f x o' // 'd The ratio of true-to-observed readings shouf be between 0.7 and 1.4.

2. Additional Comments Asata meGR dos. O/ '##8 C !* s / As 7/d 8///29 m/} hfs + /0 to E. Automatic Control System for Regulating Rod Final Settings

• Reset [

Rate time ch, 04/J '

Proportional Band 9'd Setpoint f/ .

• Adjust as per SOP 814 F. Radiation Area Monitor

1. SOP 806 completed for RAM ',i-, [cf

2. m f.

SOP

.sa n w807 e- a cgu.plgfed s for m .JRAM

/2 n. (Neutron) f pu ('_-? D }g79 y ,, f'/'$

x4j, _,w, AUG

6. Verification of Rod Drop Times Rod # Rod Height Separation Time

• 6" 12" c Inp? 1 280 3 9ef 18' 24" 6"

• r w S'20 , 3 w, 2 260 7Gd 'frd 570 sr 3 2SU 3 <SO y40 3 '/0 1 c' w

• Time calculated by (Time at normal current + 10 mamps) -

(Time at minimum current + 5 mamps) = separation time.

_g_

/ 2 dv4-/ /7')J Preformed by e / .h

~

b. Dato performed

7. Void Coefficient Determination F

a. Value of void coefficient ~~

. b )('r t . ' M K/K/cm

b. Calculation performed by / <h

c. Date perfo: med l af/.f./r70

~/'

8. Temperature Coefficient Determination

a. Value of temperature coefficient d,I (tc:.' M K/K/oF 6Al

b. Calculations performed by

c. Date performed llf!,.-[ W Y 9 ., Power Calibration as per SOP 816 j/'7p a?)

f-F

a. Additional Comments 6t.L b u h wi 1l ,, u 1 b, Q o,4,.x,o 3mu m A 'k lyy4d d Th s..,.\L e

10. Rod Speeds go, u y,u5 w ,, y g Time I. II. III. Reg.

0-24" 2 'f2 SN. 2+c>4 2 3 Y. 7 $ITM

,~ (3) Additional Comment Date /7d&4c$ Performed By - - - -

11. Rod Indicator Calibration v Actual Height I. II.

Indicator Reading $/" -

III. Reg. '<i,G >

L.

1" / A '2'/ / /

6" // A J', 9'I

• /. /

12" /A /l. Y7 /A /)

18" /9 / \' C  !? /?

24" JT4. n .44 ft/ .34

12. Results of Annual Control Rod Inspection.

• A.1 Control Rod Number 1 JUN 7 379 12 m r. /g. e 1r.[>

1.0 re- y+ e g 4. ,

s deMA Clw C,.~ p.as . - s d y. ~ , . . . j , ., ,

r~ sT w ep# # 7/u g - "ye~.

A.2 Control Rod Drive Mechanism Brake and Solonid 1 '7'

/' B.1 Control Rod Number 2 &"'

$ W * *~

E Ya f h* Yt" /& @$L Sa w enT f~ A.(

B.2 Control Rod Drive Mechanism Brake and Solonid /.}

g /

C.1 Control Rod Number 3 Jyy y.,, .

/

/

N  % mgf l

i C.2

, Control Rod Drive Mechanism Brake and Solonid '/

cf r e_ / S (c % r I.Iru ig e w Le w ~ es A A.I

_f, * * * "

me.e ens me ** "'**'* **"* '"

d. Date Performed g e. Director or Supervisor Date q

,i >' ~/ ' '/

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

i Director or Reac r Manager

.Y .

(f

{

l 9

l l

l .-

t l

t 2_ . - _ _ , _ , _. __

., - -. - , , , , N

, '/

, . . _ , , . . . . . . . - - . . . . .. . _ . = - . _ -

UN.'VEN. TTY OF MISSOUH l-la)la A - NUCLFAR N:AC'n'R a STANDARD UPLHATING PROCEDURES I

s .o . P . 017 PEv t sl:D: 7-24-75 PAGE 1 OF 1 fTITLE: Pire Alarm System *

The UMR Nuclear Reactor building, fire alann system consists of two type jofdetectors;fourheatsensingunitsandtwosmokedetectors,plustwo imanual alarm station.

I The system has a built in circuit failure warning system with an audible jandvisiblealarmat the control box.

i

• The alarm system is normally pewred from building power, with batteries for a backup.

When a actual alarm is initiated an internal and an external building I

fire alarm is sounded and when the building security system is in opera-tion a remote alarm is sounded at the campus police headquarters.

PROCEDURE:

1. Replace the emergency power supply batteries in the battery box.

& Test emergency power by securing power to ths alarm system (switch 32 in the power panel) and text system operational.

F Check the four heat detectors by applying a heat blower on them and acknowledging alarm actuation, audible and visible and their '

resetting af ter the heat is removed.

[ Check the two smoke detectors by placing a burning cigarette en a long pole momentarily removing all power to the alarm control box.

& Check the two manual alarm stations and acknowledge alarm dCtudtion, audibic dnd Visible and reset.

W Check all indication lights operational.

i e .

5 #

I Ii .

1  ;

e b l

. l '

i  !

' WiCTTEN bY: R.M. Luckett . . . . - APPPOVED DY: ---

D R . Edwa.rd"

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

Y

Semi Annual Check List Date Commenced JM07 W Date Completri ' jai 41 i .no Total Hours on liour Meter C( */ */9[-

1. Vacuum Tube Test and Clean Chassis Initial

a. Log N Power Supply *' ,

(1) Cleaned chassis A Y#

(2) Tested all vacuum tubes Replaced: tube # tube type V] s_g; g, O (3) Additional Comments None

b. Linear Power Supply e/

(1) Cleaned chassis #

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

[

' 'ON

.p'8. . .

(3) Additional Comments None ,

1 l

l

__ _ _ __ _m_ _ . . _ . . - . _ _ _ . _ _ _ - --

c. Linear Pulse Amplifier -d" -,

(1) Cleaned chassis p /

(2) Tested all vacuum tubes Replaced: tube # tube type j ./ 9 ray b *//3 6 BKS

~

, (3) Additional Comments None

d. Scaler Timer e (1) a -)

Cleaned chassis e 'y (2) Tested all vacuum tubes #

Replaced: tube # tube type 3 gfja ) A / A id 'I 'l

$ t// r y J7 ^'7 l' ~i j '.L H T7 (3) Additional Comments

e. Safety Amplifier  ?, -//

(1) Cleaned chassis c2777 g l (2) Tested all vacuum tubes

! Replaced: tube # tube type JSN O 71980 l

l

~~

(3) Additional Comments

~

f. Area Radiation Monitor +7 'A/

(1) Cleaned chassis adr, (2) Tested all vacuum tubes )#

Replaced: tube # tube type

\ E SA f

%S @D p% ., ADGA (3) Additional Comments

g. Micro-Micro Ammeter  % [

(1) Cleaned chassis

- (2) Tested all vacuum tubes /

Replaced: tube # tube type 3%Q7 40 (3) Additional Comments

h. Fission Preamp y~ [

(1) Cleaned chassis and inspected ,

(2) Additional Comments g.-

i

_ . _ . _ . . . - - 8 * ' * *

• 9

i. Public Address System ,a )

_ (1) Cleaned chassis r/(4F (2) Tested all vacuum tubes Replaced: tube # tube type jp D1 (3) Additional Comments ,

j. Log Count Rate Recorder 4, e, / J' (1) Cleaned chassis I

(2) Tested all vacuum tubes /

Replaced: tube # tube type

,,h 0 71980 (3) Additional Comments

k. Linear Recorder /d$?tj'T (1) Cleaned chassis //

(2) Tested all vacuum tubes MI Replaced: tube # tube type J;ct 0 71980 (3) Additional Comments

. _ _ _ . . _ _ f I

1. Period Recorder ( '///$

(1) Cleaned chassis e/}

(2) Tested all vacuum tubes [

Replaced: tube # tube type yf30 6

. (3) Additional Comments

m. Log N Recorder

.o

/c;8/)

(1)

(2)

Cleaned chassis Tested all vacuum tubes m V[g Replaced: tube # tube type

~

pgB 1 (3) Additional Comments

n. PAT 60

• //

(1) Cleaned chassis 7 4M,k(

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

-S-9

f (3) Additional Commants o.

Regulated Power Supply * /,/- ,

(1) Cleaned chassis s

(2) Addit'.;nal Comments Y'/

Y

[

p. Conductivity Bridge m /

/p (1) <

Cleaned chassis JANO7t4o n- ,e (2) Tested all vacuum tubes Replaced: tube # tube type o++ ~1" hy meJif ')N~ /

4-f/V

q. Safety Amp Preamp * //,

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

1. [

Replaced:

[

tube # tube type M'O (3) Additional Comments l 2. Relay Test JAN 0 7 E80 *

a. Console relays tested and replaced as per SOP 815 I.

b. Relays Replaced k'4 MGi. ,I 18 f.J M M s e W2$ C/C L / 24 K%

lD9 Ni%/ 22 Y (.

Ve&&.t I A (.dsp./ *f4 V']

(il, L'1 16' I 6, KI'7, x'z. ,., wi ., yz Kg X2') , l(2 G., K'% K, =>Wh KQ g ; g L.,y l w <,p

(c) Additional Comm3nts

3. Detector Resistance

a. Safety #1 Value (147) Signal to ground 2. VM o" .M (149) Positive to ground ),lXio# ik Open Circuit Resistance 2.4 Xio83 k/

gjin. Safety #2 (143) Signal to ground $.($Xio# M

[@ *

(145) Positive to ground T.L y [ .

[/

Open Circuit Resistance 2. 4 A t o# 3 M. , ,7

c. Log N (125) Signal to ground 2 f AM (123) Positive to ground 2, 6 X Joi (121) Negative to ground (m( io # oY/

Open Circuit Resistance /gro#'

. . ,2

d. Linear (114) Signal to ground 7 34:01 (112) Positive to ground 2.c Vio7 M/

(110) Negative to ground Q yto8 M/

Open Circuit Resistance ' 2 y X,o'3 8/_

4. Fire Alarm System Tested.as Per SOP 817 JAN 0 7 W 3Y

~

/

5. Calibration Checks /

Note: Any instrument found to be out of calibration should be realigned in accordance.with its technical manuel.

A. Temperature Recorder *

1. Reading i Thermometer Recorder 1 320F M 2 32oF 32 p 3 320F 3l

[ 1 160 F J6C 2 1600F ]6/ l 3 160 F / h/

Note: All readings should be 1 4 oF

2. 135* F Interlock , Trip Point

[ .

l

)% v F) ,-

( _

5

B. Log Count Rate Channel

1. Pulse Generator

• Meter Recorder Initial 10 ;j pd e6) 100 90 90 m# #

1000 'l s 'O I 'l u d m lY 10,000 16 800 &ld St.9ff Note: All readings should give .7 to 1.4 ratio of e-to observed readings.

2. Additional Comments C. Linear

1. Keithley Meter , Recorder (%) Initial

~

6.66X10 6. 6X/9' 99 #v * //

~

2.0X10 f. 99X #d V 99 NV E]

6.66X10 -6 g gg)g 6 fg, g ,g 2.0X10 -6 j, p pyg4 ppg ,,, Q

~

6.66X10 ' C66km tc0 % m}

~

2.0X10 2o97e~2 o /o 2 % 2/

Y k 6.66X10 ~0

~

GC Wo'N 9 8 >r ~* ')

2.0X10 2. OXe~ 0 /C0 '! m I f

6.66X10 ~0 C GXm*? 98 % m 's

~

2.0X10 ' /.*/9y ,'9 99'o d's 6.66X10 ~IO 4. i)cv# 96 & m ()

2.0X10 ~0 f. 9 f x't- ~'l V ) &c m)

~

~0 Note: From 10 to 10 the overall accuracy shoul [be better than 2% of full scale.

From 3X10 ~9 to 3X10 -13 the overall accuracy should be better than 4%.

2. Additional Comments g [.N J_ dom ^'

s,,gi(m ms rybt 4 b-- ~>"%

on ) 18 80 rd e

,y

D. Log N

1. Meter Recorder Keithley Initial

-5 fev~#

SX10 100 'to

'/

5X10 10 3. 3 ' l. v'6

- ~ /)-

SX10

-8 1 ,9 i )' ko' # . E)

SX10

-9 0.1 ,// 9 6xec ~ 8 eb SX10 .01 ,o/3 5 7 / y ,7 " >

SX10 -10 .001 ,cce+ 5 > r # '"

-11 '

[/

SX10 .0001 . co o s er 3 % -" #

Note: The ratio of true-to-observed readings shou [d be g between 0.7 and 1.4.

% 2. Additional Comments j'

E. Automatic Control System for Regulating Rod Final Settings

• Reset Rate time b LY Proportional Band 70 Setpoint /b

• Adjust as per SOP 814 F. Radiation Area Monitor g g t) 1960 SOP 806 completed for RAM g g3 33euSOP 2 807 completed for RAM (Neutron)

6. Verification of Rod Drop Times Rod i Rod Heicht

. Separation Time

• C' 12" 18" 24" 6" 1 25Uex $$w e k00 w. 5DD AC .sse l 2 226 ~?52) fli' - Sn o,. 10  :

3

_2TO .'ifd No MMO 2O

• Time calculated by (Time at normal current + 10 mamps) -

(Time at minimum current + 5 mamps) = separation time. -

1 j

i en =

_ ...a. .. " - * " ' " ~

~~*~~.

1

r,

b. Dnts parformed 30I Preformed by '

7. Void Coefficient Determination

~ ~ g"

a. Value of void coefficient.,- 9. D X 10 M K/K/cm

b. Calculation performed by WY/

c. Date performed ,A!.. . - / 6; d7'/') _

8. Temperature Coefficient Determination

a. Value of temperature coefficient -la,h4 fro

- if M K/K/oF

b. Calculations performed by ,.9 (' h

c. Date performed ///en e

/ f[f 5

9. , Power Calibration as per SOP 816 jgN 141950 M V'

a. Additional Comments

10. Rod Speeds Time I. II. III. Reg. ,

0-24~ 24Lo 240.O *? 4 0.1 C C 7 ~. w ..

(3) Additional Comment

$u1 0M l Date Performed by

11. V' Rod Indicator Calibration JAN1'l1PJ Actual Height I.

Indicator Reading II. III.* Reg.

1" [r ), f% l,<' }.I

\n #

6 (. l' l'.O /., (. < -

12" s j. c' l} t ,

O'e' /r ,

18" 'I 'l 0 //.I- It <

• i.. <

24" 'Mr

. . 4,t-

. M, . '

. ./ i

12. Results of Annual Control Rod Inspection. '

A.1 Control Rod Number 1 i

A

)

/

,_ __ __ __ - ....-.--.a.~-

~

g MD A.2 Control Rod Drive Mechanism Brake and Soloni I

"[ ,[i j B.1 Control Rod Number 2 '

i e t* 0 fb B.2 Igulg 90 Control Rod Drive Mechanisn Brake and Solonid I

Control Rod Number 3 l C.1

')d( /Ff

- .s

/ ,

l'

T50 C.2 . Control Rod Drive Mechanism Brake and Solonid M" 9N . -

sa I

/**

, - . - . . . . . -. x .: . . . . .

. - _ . _ . . _ . . _ . . _ _ .____._____.._.___?___.

'~

d. Date Performed

,. e. Director or Supervisor 4

. Date 19 I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

Director or Reactor Manager i

]

4 l

_ , en ~- " ' ~

e .

aAs G 7 080 UU.'.VEldITY OF MISL:Ullh t -kt 'I.l A - f.Us'I.! A h Ular1U k i

dTANDARD uPl.lWi'I NG l' hot l1.lill Wl:. .

r i . J . l' . 817 RI .V I ' .i p,: 7- 288 - 7'> , PAsil I UF 1 .'

TITLE: pire Alarm System

= ____ __ ._.- - ,

l I

The UMR Nuclear Reactor building., fire alarm nyutem conalsts of two tyre of detectors; four heat sensing units and two smoke detectors, pluu two  ;

manual alarm station. '

The system has a built in circuit failure warning system with an audible :

and visible alarm at the control box. i The alarm system is normally powered from building power, with batteries '

for a backup.

When a actual alarm is initiated an internal and an external building l i

fire alarm is sounded and when the building security system is in opera-tion a remote alarm is sounded at the campus police headquarters.

PROCEDURE:

3 0 1980 Replace the emergency power supply bal turies in the battery box.

d. Test emery,ency power by securing power t o t he alarm uvutem (switch 32 in the power panel) and text nyutem operatlonal. '

• /3. Check the four heat detectors by c7 plying a heat blower on them

, and acknowledging alarm actuation, audible and visible and their resetting after the heat is removed.

4 Check the two smoke detectors by placing,a burning cigarette on a long pole momentarily removing all power to the alarm control f box. '

Check the two manual alarm stations or < knowledge alarm actuation, audible and visible an eset.

Check all indication lights o ra 'onal i

I t

l

) ,

1

,/ l WRITTEN BY: R.M. Luckett _, APPROVI D,yY:, ya R2 R warA _ _

,