ML20070N761

Progress Rept for Univ of Missouri-Rolla Nuclear Reactor Facility

ML20070N761
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Site:	University of Missouri-Rolla
Issue date:	04/29/1994
From:	MISSOURI, UNIV. OF, ROLLA, MO
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ML20070N754	List: ML20070N752 ML20070N761
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l PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY l

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APRIL 1,1993 TO MARCH 31,1994 Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla Albert E. Bolon, Director David W. Freeman, Manager Nuclear Reactor Facility University of Missouri-Rolla Rolla, Missouri 65401 9405090175 940429 PDR ADOCK 05000123 R PDR

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SU3131ARY i

! I l During the 1993-94 reporting period the University of Missouri-Rolla Reactor (UMRR)

I was in use for 440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br />. The major part of this time, about 60%, was used for class instruction and training purposes.

The UMRR operated safely and efficiently over the past year. No significant safety-related incidents or personnel exposures occurred.

l In July 1992 the reactor fuel was converted from the original high-enriched uranium l (HEU,90% U-235) to new low-enriched uranium (LEU,19.8% U-235). The HEU is presently l

stored in the fuel storage area at the end of the reactor pool. i 1

, The reactor facility supported several UMR courses over the year for a total of 2,647 l student-hours. The reactor was visited by about 3,200 visitors during the past year. There were ,

1 687 participants in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 8,649 kilowatt-hours of thermal energy using approximately 0.446 grams of uranium. A total of 259 samples were irradiated at the reactor with most of them being analyzed in the Reactor Counting Laboratory.

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ii TABLE OF CONTENTS

1.0 INTRODUCTION

. . . I 1.1 Background Information. . . I 1.2 Facility Status . .2 1.2.1 General . . . 2 1.2.2 Reportable Occurrence . . 4 2.0 REACTOR STAFF AND PERSONNEL. .. . 6 2.1 Reactor Staff 6 2.2 Licensed Operators. . 6 2.3 Radiation Safety Committee . 7 2.4 Health Physics 8 3.0 REACTOR OPERATIONS . 9 4.0 PUBLIC RELATIONS. . . .. .. . .. .20 5.0 EDUCATIONAL UTILIZATION . . .22 6.0 REACTOR HEALTH PHYSICS ACTIVITIES .27 6.1. Routine Surveys. . . . . 27 6.2. By-Product Material Release Surveys . . .27 6.3. Routine Monitoring . . .28 6.4. Waste Disposal . . . . .. . . .. . . 29 6.5. Instrument Calibrations . . . . 29

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TABLE OF CONTENTS (cont.)

7.0 PLANS. . . .30 7.1. Reactor Instrumentation Upgrade . .30 )

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7.2. Shipment of HEU Fuel OtYsite. .

, .31 7.3. LEU Fuel Characterization .31 l

7.4. Expansion of Research Capabilities . .3 l l l

APPENDIX A. Standard Operating Procedures Changed During the Past Year .32 l

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1.0 INTRODUCTION

This progress report covers activities at tlie University of Missouri-Rolla Reactor (UMRR) Facility for the period April 1,1993 to March 31,1994.

The reactor is operated as a university facility, available to the faculty and students from various departments of the university for their educational and rescarch programs. Several other universities, colleges, and high schools have made use of the facility during this reporting period.

The facility is also available for the training of reactor personnel from nuclear electric utilities.

Trace element analysis using neutron activation and neutron radiography are performed at the i

facility.  ;

i 1.1 Background Information i

The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9th,1961. The UMRR was the first operating nuclear reactor in the state of Missouri. The l

reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. The  !

I initiel licensed power was 10 kW. The licensed power was upgraded to 200 kW in 1966. During l the ;ummer of 1992, the reactor fuel was changed from high-enriched uranium (HEU,90% U- l 235) fuel to low-enriched uranium (LEU,19.8% U-235) fuel. The LEU fuel is performing with l

no problems. l The reactor is a light water open pool-type reactor cooled by natural convection flow.

l The fuel is MTR plate-type fuel.

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iv LIST OF TABLES Table 3-1. Core 10lW Technical Data . . . .10 Table 3-2. SCRANIS . . . .12 Table 3-3. Rundowns And Unplanned Shutdowns . .13 Table 3-4. Ntaintenance .15 Table 3-5. Facility Use Other Than The Reactor . .

.19 Table 3-6. Reactor Utilization . .. . . 19 Table 4-1. Public Relations Program .

.20 Table 5-1. UNIR Classes at Reactor Facility 1993-94 Reporting Period. .23 Table 5-2. Reactor Sharing Program .24 LIST OF FIGURES Figure 3-1. UMRR Core Configuration .

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l iii TA13LE OF CONTENTS (cont.)

7.0 PlebNS. . . . .30 7.1. Reactor Instrumentation Upgrade .. . . 30 7.2. Shipment of HEU Fuel OtYsite. . . . .31 7.3. LEU Fuel Characterization .31 7.4. Expansion of Research Capabilities . .31 APPENDIX A. Standard Operating Procedures Changed During the Past Year .32

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The titeility is equipped with several experimental facilities including a beam port, thermal column, pneumatic rabbit system and several manual sample irradiation facilities. Additionally, the facility is equipped with a counting laborvory that has gamma and alpha spectroscopy capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, and modern spectmm analysis sot 1 ware. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment.

1 1.2 Facility Status The UMRR operated safely and efficiently over the past year. No significant safety-related incidents or perrannel exposures occurred.

1.2.1 General I

The LEU conversion project is nearly complete. Several core characterization studies i

have been completed with the new core. A master thesis is being completed that involves the I detailed measurement of dose rates associated with the HEU fuel. The results of the measurements show that the dose rates in water at a distance of 3 feet from the element tenter l range from about 3 mr/hr to 20 mr/hr and that the 10 foot in air dose rates per element vary from about 20 mr/hr to 180 mr/hr. This information is being used to develop an ALARA procedure for transferring the fuel elements from the pool storage pit to the shipping cask.

We received a fourth grant award from DOE to purchase new nuclear instruments (NI) for the UMRR console. The cost of the upgrade is being shared directly from reactor funds. The total funds received from DOE combined with money committed from the reactor account totals 4

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1.0 INTRODUCTION

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( This progress report covers activities at the University of Missouri-Rolla Reactor l \

l (UhlRR) Facility for the period April 1,1993 to March 31,1994.

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l The reactor is operated as a university facility, available to the faculty and students from l

various departments of the university for their educational and research programs. Several other l universities, colleges, and high schools have made use of the facility during this reporting period.

l The facility is also available for the training of reactor personnel from nuclear electric utilities.

l Trace element analysis using neutron activation and neutron radiography are performed at the facility.

1.1 Background Information The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9th,1961. The UNIRR was the first operating nuclear reactor in the state of Missouri. The reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. The initiallicensed power was 10 kW. l'he licensed power was upgraded to 200 kW in 1966. During

, the summer of 1992, the reactor fuel was changed from high-enriched uranium (HEU,90% U-1 l 235) fuel to low-enriched uranium (LEU,19.8% U-235) fuel. The LEU fuel is performing with no problems.

The reactor is a light water open pool-type reactor cooled by natural convection flow.

The fuelis MTR plate-type fuel.

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. i to $167,000 available for the console upgrade. We plan to replace our existing five channel NI system with a three channel system. We have purchased and received three new instrument i drawers from Gamma-NIetrics, including 1) a wide-range log fission chamber based drawer,2) a wide-range linear CIC based drawer, and 3) a log and linear CIC based drawer. We presently ,

i j plan to install these three drawers in our control console as direct replacements for our existing i

j Start-up, Log N and Period, and Linear drawers under the provisions of 10CFR50.59. Parallel

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with this, we will be submitting a request to NRC for approval for desired console revisions that may involve "unreviewed safety questions" l We have purchased a Yokogawa micro-R 1000 temperature stripchart recorder. We plan

to replace our existing pool temperature recorder with the new Yokogawa recorder shortly. The 1

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replacement is being performed under 10CFR50.59 and already has UhlR Radiation Safety i

Committee approval.

] The Reactor Facility was audited in June of 1993 by an independent audit team from the

University of NIissouri-Columbia Research Reactor. The audit team found "No major areas of k

concern, all discrepancies found were minor" Additionally, the audit report stated that l " recognition should be given for the great improvement in overall recordkeeping" The reactor staff has continued to review the operation of the Reactor Facility in an effort

. to improve the safety and etliciency ofits operation and to provide conditions conducive to its 1,

utilization by students and faculty. An " outreach" program, implemented over the past 3 years, has been continued in order to let both students and faculty in a number of departments across campus know how the reactor could be used to enhance course work and research. As a result, i additional classes have used the Reactor Facility as a part of their laboratory courses, including 1

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Chem 251, Intermediate Quantitative Analysis, and Chem 355, Instrumental Methods Laboratory. I In May,1993 an NRC licensing examiner visited our facility. All of our candidates passed 1

with the following results:

Candidate License Dr. Albert E. Bolon SRO Requal .

l Dr. Shahla Keyvan Reactor Operator ]

Hatem Khouaja Reactor Operator Matthew McLaughlin SRO Upgrade During the summer and early fall, much manpower was consumed tighting the NRC 1

proposal to invoke licensing fees in excess of S60,000 on our facility. Our etTorts appeared to be i fruitful as NRC reinstated our exemption from the fees.

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l 1.2.2 Broortable Occurrence i In October,1993, the UMRR experienced a reportable occurrence. The occurrence involved operating the reactor with an inoperable period channel. The root cause was determined l

to be equipment failure combined with operator error. Several strong corrective actions have been implemented that have included equipment repair, increased operator training, and Standard Operating Procedure (SOP) revisions. The entire event and details of the corrective actions were presented to NRC in a report entitled, " Report on the Operation of the University of Missouri-Rolla (UMR) Reactor Facility With an Inoperable Period Channel", November 9,1993.

Corrective actions implemented and lessons learned from this experience have strengthened the overall reactor operations program at UMR.

5 A modification was made to the Period Channel" Trip Test" switch under 10CFR50.59.

The original switch was a specia'ty part that combined a triple pole double throw spring return slide switch with a I kohm potentiometer. This switch failed due to wear leading to the equipment failure involved in the reponable occurrence. A direct replacement could not be found. Thus, the component was simply replaced with two separate readily available components; l) a spring return toggle switch and 2) a simple 1 kohm potentiometer. The change was preapproved by the Reactor Manager, Director, and the Radiation Safety Committee under 10CFR50.59. The 50.59 Safety Evaluation determined that the modification did not involve an unreviewed safety question.

Several SOPS have been improved in light oflessons learned with the reportable occurrence, including SOP 101, " General Operation Procedures" SOP 102, " Pre-Startup Checklist" SOP 103, " Reactor Startup to Low Power" SOP 104, " Reactor Power Changes and Stable Operations" SOP 105, " Reactor Shutdown & Reactor Securing Procedures" SOP 106, " Permanent Log, Hourly Log and Operational Data" The above listed SOPS plus the other SOPS revised during the reponing period are a

provided in Appendix A.

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6 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Nnme Iills Albert E Bolon Director David Freeman Reactor Nfanager Carl Barton" Senior Electronic Technician Juls Williams" Lab Niechanic Linda Pierce Senior Secretary hiatt hlcLaughlin 2) Senior Reactor Operator William Bonzer Senior Electronics Technician James Jackson" Senior Lab N!echanic Hatem Khouaja" Reactor Operator 2.2 Licsnted Operators Namt License Albert E. Bolon Senior Operator Carl Barton" Senior Operator David Freeman Senior Operator hiatt N!cLaughlin 2) Senior Operator Hatem Khouaja" Reactor Operator 6

Shabla Keyvan ) Reactor Operator D Began part-time 9/1/92,

2) Senior Operator effective 6/11/93.

3) Employed effective 2/21/94.

0 Reactor Operator effective 6/21/93.

" License Expired effective 9/9/93.

') Reactor Operator effective 6/21/93

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i 2.3 Radiation Safety Committee The Radiatica Safety Committee meets quarterly. The committee met on 6/29/93, 9/29/93,12/6/93, and 3/4/94 during the reporting period. The committee members are listed below:

Name Department Dr. Nord L. Gale (chairman) Life Sciences Mr. Ray Bono (secretary, ex-officio, Occupational Health and non-voting) Safety Services Dr. Ernst Bolter Geology and Geophysics Dr. Oliver K. Manuel Chemistry Dr. Albert E. Bolon Reactor Director Dr. Nick Tsoulfanidis Radiation Safety Officer Dr. Edward Hale Physics Dr. Arvind Kumar Nuclear Engineering Mr. David Freeman (ex-officio, Nuclear Reactor non-voting)

Mr. Randy Stoll Business Services

8 2.4 Health Physics Health Physics support is provided through the Occupational Health and Safety Sersices (formerly the Environmental Health and Risk Management) Department which is organizationally independent of the Reactor Facility operations group. Health Physics personnel are listed below:

e Name 11th Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Director, Occupational Health &

Safety Services and Campus Health Physicist Mr. Charles Hooper" HP Technician Miss Lisa Stiles HP Technician Mr. Chad Little HP Technician Mr. Justin Hiller HP Technician Mr. Paul Jason Dobson 2) HP Technician Mr. Darrell Liles') HP Technician Terminated effective May 7,1993.

2> Employed effective May 19,1993.

3) Employed effective February 1,1994.

9 3.0 REACTOR OPERATIONS Core designation 101 W is presently in use. The "W" mode core is completely water reflected and is used for normal reactor operations. The "T" mode (core positioned near graphite thermal column) may be used for various experiments, including beam port and thermal column experiments.

Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of core 101W. The excess reactivity, shutdown margin, and rod wonhs were measured in cold clean conditions.

Tables 3-2 and 3-3 present a listing of unscheduled shutdowns (scrams, rundowns, and unplanned normal shutdowns) along with their causes and corrective actions.

Maintenance activities are listed in Table 3-4.

Table 3-5 shows facility use other than the reactor and Table 3-6 shows reactor utilization.

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Table 3-1. Core 101W Technical Data Parameter Value Rod 1 2.73% Ak/k I

Rod 2 2.69% Ak/k Rod 3 3.22% Ak/k Reg Rod 0.371% Ak/k Excess Reactivity 0.496% Ak/k Shutdown Margin

• 4.92% Ak/k

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Rod 3 and Reg Rod are assumed to be fully withdrawn.

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Figure 3-1. U31RR Core Configuration DATE July 28.1992 LOADING NUMBER 101W s

A B S C F-8 F-4 C-4 D F-13 C-1 F-3 F-2 F-12 F-15 c' E F-10 C-2 F-1 C-3 F-9 F-14 F CR F-5 F_-6 , F-7 BR 1 2 3 4 5 6 7 8 9 KEY TO PREEIXES F - Standard Elements C - Control Elernents BR - Bare Rabbt CR - Cadmium Rabbit S - Source Holder

12 Table 3-2. SCRAMS Date Cause 04/12/93 Manual Scram.

Cause: Startup Channel CR < 2 counts per second light came on at 2 kW power. i SRO on duty manually scrammed Reactor.

Corrective Action: System checked and cable connectors cycled.

1 09/09/93 Manual Scram.

l Cause: Magnet #2 current was reading high. Manually scrammed reactor to l l remove magnet current as soon as possible to prevent overheating the magnet l l (which can lead to tedious repair work).

Corrective Action: Performed maintenance on Magnet #2 power supply.

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Table 3-3. Rundowns And Unplanned Shutdowns 1 Note: Most of the rundowns listed below were due to switching problems in the Linear instrument while manually changing scales. A new Linear instrument has been purchased from Gamma-N!etrics that, when installed, will eliminate the spurious rundown trips.

Date Cause 04/05/93 120% Demand Rundown.

Cause: When student operator switched Linear scales, the switch button did not properly latch.

Corrective Action: Student operator given further instmetion on how to properly switch scales. SRO permission to restart granted. Reactor restarted.

04/08/93 Unplanned shutdown of reactor.

Cause: Safety Channels reading low while reactor was at high power.

Corrective Action: NIaintenanced Safety Channel.

04/26/93 Regulating Rod on Insert Limit Rundown.

Cause: Student operator switched to auto with regulating rod at 3 inches.

Corrective Action: SRO on duty instructed student operator. SRO permission to restart granted. Reactor restarted.

04/26/93 120% Demand Rundown.

Cause: Linear scale switch did not latch properly as student operator switched scales.

Corrective Action: SRO on duty instructed student operator on how to properly switch scales. SRO permission to restart granted. Reactor restarted.

09/01/93 120% Demand Rundown.

Cause: Spike on linear recorder when changing scales on Linear meter.

Corrective Action: No corrective action necessary. SRO permission to restart granted. Reactor restarted.

09/28/93 120% Dernand Rundown. '

Cause: Student operator changing scales on Linear.

Corrective Action: No corrective action necessary. SRO permission to restart granted. Reactor restarted.

10/26/93 Unplanned Shutdown of Reactor.

Cause: Inoperable Period signal.

Corrective Action: Period Amplifier was maintenanced.

14 Table 3-3. Rundowns And Unplanned Shutdowns (cont.)

Ibue Cause 12/09/93 Unplanned Shutdown of Reactor.

Cause: Power flicker caused S/S Rod #3 to drop.

Corrective Action: Other rods were inserted.

02/10/94 120% Demand Rundown.

Cause: Student operator failed to properly upscale Linear.

Corrective Action: Student operator given additional instruction regarding changing scales. SRO permission to restart granted.

02/15/94 120% Demand Rundown.

Cause: Spike occurred when switching scales on Linear.

Corrective Action: Student operator given additional instruction on changing scales on meter. SRO permission to restart granted. Reactor restarted.

02/22/94 120% Demand Rundown.

Cause: Switching scales on Linear.

Corrective Action: No corrective action necessary. SRO permission to restart granted. Reactor restarted.

03/07/94 120% Demand Rundown.

Cause: Student operator improperly switched scales on Linear.

Corrective Action: Student operator given additional instruction for properly switching scales. SRO permission to restart granted. Reactor restarted.

03/08/94 120% Demand Rundown.

Cause: Student operator switched scales on Linear.

Corrective Action: Student operator given further instruction on properly switching scales. SRO permission to restart granted. Reactor restarted.

15 Table 3-4. Maintenance flate Onlle 04/08/93 Problem: Safety Channel #1 and #2 reading low at full power.

Cause: Safety Channel calibration drifted.

Corrective Action: Checked zero level and adjusted full meter span level.

04/12/93 Problem: Start-up Channel lost its reading of 102 counts and dropped to zero counts for 10-15 seconds. Then returned to it 103 counts.

Cause: Could not precisely determine cause.

Corrective Action: Checked all cable connections, H.V. power supply, and recorder wiring. Could not duplicate symptoms. System working normally.

04/21/93 Problem: Semi-Annual RAM Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration.

04/27/93 Problem: Semi-Annual Neutron RAM Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration.

05/17/93 Problem: While the reactor was shutdown, the Safety Channel annunciator tripped and could not be reset.

Cause: Defective preamp vacuum tubes.

Corrective Action: Replaced preamp vacuum tubes, calibrated safety channel meters.

05/18/93 Problem: While the reactor was shutdown, the Safety Channel tripped annunciator.

Cause: Defi:ctive power supply tubes.

Corrective Action: Replaced power supply vacuum tubes. Calibrated safety channel meters.

05/19/93 Problem: Safety Channel #1 and #2 zero settings were lower than normal.

Cause: Zero settings had drifted.

Corrective Action: Adjusted zero settings.

05/24/93 Problem: Bridge RAM operating light was not illuminated.

Cause: Defective bulb.

Corrective Action: Replaced bulb.

05/24/93 Problem: Demineralizer RAM operating light was not illuminated.

Cause: Defective bulb.

Corrective Action: Replaced bulb.

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16 Table 3-4 Maintenance (cont.)

Dme Cause 06/08/93 Problem: Safety Channel #1 read 90% at full power.

Cause: Meter span had driRed.

Corrective Action: Adjusted zero and meter span. Reposition UIC to proper readings during next full power run.

06/14/93 Problem: Safety Channel #1 and #2 read too high at full power.

Cause: Zero settings had shined.

Corrective Action: Reset zero settings. Check meter span.

06/29/93 Problem: Semi-Annual Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration on 07/09/93.

07/08/93 Problem: Conductivity bridge - could not set zero and check (span).

Cause: Power supply had ripple on the -16 V output.

Corrective Action: Replaced 16 V zenor diode, de bridge, and capacitor. Reset zero and checked for proper settings.

07/19/93 Problem: Safety Channel tripped annunciator while Reactor was shutdown.

Cause: Power supply vacuum tube was defective.

Corrective Action: Replaced vacuum tube.

07/22/93 Problem: Magnet #3 current would not adjust to 15 mA above drop current.

Cause: Weak power vacuum tubes.

Corrective Action: Checked vacuum tube voltages and replaced tubes. Checked drop out currents.

09/13/93 Problem: Magnet #2 current would not adjust to a low level.

Cause: Defective vacuum tube.

Corrective Action: Replaced vacuum tube and checked current range for magnet

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09/14/93 Problem: Magnet #3 current level would not adjust.

Cause: Defective magnet coil.

Corrective Action: Remove magnet from pool, replaced coil, and re-installed  !

magnet in pool. Performed rod drop time measurement.

09/16/93 Problem: Demineralizer RAM levels were fluctuating.

Cause: Defective GM detector tube.

Corrective Action: Replaced GM detector tube, checked H.V., and cable connections. Calibrated RAM.

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Ihtte Cinic 09/21/93 Problem: Magnet #3 would not lift rod.

Cause: New magnet coil required more current than old coil.

Corrective Action: Check voltages of power supply and tubes. Replaced vacuum tubes. Installed pre-approved temporaryjumper across a current limiting resistor (R74) to provide an additional 4 to 6 mamps to the coil. No safety functions were in any way compromised by this adjustment. Removedjumper 09/27/93.

10/19/93 Problem: Maximum magnet current would not attain 10 rnA above rod drop currents.

Cause: Defective power supply resistor.

Corrective Action: Replaced power supply resistor, adjusted power supply soltages, checked zero and meter span calibration. Checked current levels to magnets.

10/26/93 Problem: Period recorder and period meter not responding to period changes.

Cause: Found a broken trip test switch / potentiometer on Log N drawer.

Corrective Action: Replaced the trip test switch / potentiometer. Approval for this change was obtained by the Radiation Safety Committee under 10CFR50.59. The trip test switch / potentiometer was replaced by an individual switch and individual potentiometer. Normal trip tests and startup checks were performed to check equipment operation.

I1/01/93 Problem: Semi-Annual RAM Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration.

I1/02/93 Problem: Inspection of control switch on Startup Channel.

Cause: Preventative maintenance.

Corrective Action: Performed a visual inspection and a contact resistance test of switch. Switch checked good.

I1/10/93 Problem: Semi-Annual Neutron RAM Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration.

I1/22/93 Problem: Replacement of magnet current meter cables.

Cause: Preventative maintenance.

Corrective Action: Replaced cables. Checked scram response.

18 Table 3-4. Maintenance (cont.)

D. ale Cause 12/22/93 Problem: Semi-Annual Calibration.

Cause: Routine maintenance.

Corrective Action: Completed calibration on 01/12/94.

01/21/94 Problem: Period recorder display slightly off of = at steady state.

Cause: Period recorder indicator needs repositioned.

Corrective Action: Repositioned period recorderindicator. Adjusted period meter infinity and span. Adjusted period recorder adjustment (R22) on Log N drawer.

02/21/94 Problem: Safety Channel #1 meter responded slugishly.

Cause: Defective resistor in meter circuit.

Corrective Action: Replaced resistor and performed a meter calibration.

Repositioned UICs at full power.

19 Table 3-5. Facility Use Other Than The Reactor Elej!ity liettr3 Bare Rabbit Tube 10.2 Cadmium Rabbit Tube 4.49 Other Core Positions 4.79 Total 24.0 Table 3-6. Reactor Utilization I. Reactor use 440 hr

a. Research and irradiation nins 105 hr

b. Instruction runs 252 hr

c. Maintenance runs 28.2 hr

d. Training 54.3 hr

2. Time at power 184.6 hr

3. Energy generated 8649 kw-hr

4. Total number of samples 259

5. Sample hours 24.0 hr

6. U-235 irradiation time 0.377 g

7. U-235 fissioned and converted 0.446 g

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20 4.0 PUBLIC RELATIONS The reactor statYeontinues to educate the public about applications of nuclear science.

Over 3,200 persons toured the facility during this reporting period. Tour groups are typically given a brief orientation and/or demonstration by a member of the reactor staff.

Table 4-1 lists some of the major occasions or groups and number of visitors for each event.

Table 4-1. Public Relations Program DATE PARTICIPANTS NUMBER 04/17/93 UMR Spring Open House 128 04/22/93 UMR Chemistry Laboratory 18 04/22/93 Girl Scout Troop #327 4 l 04/27/93 UMC Operator Training 5 05/05/93 UMC Operator Training 5 05/05/93 University of Missouri Curators 8 06/07/93 UMR Jackling Tours 44 06/07/93 UMR Fundamentals of Engineering 21 06/08/93 Teachers from Thailand, Dr. Sheffield 15 06/08/93 UMR Funda .erds of Engineering 11 06/14/93 UMR Jacklii.3 Tours 42 06/17/93 Missouri T achers - Junior High & High School 14 l

06/21/93 UMR Jackh. g Tours 37 '

06/23/93 Boys Town 15 06/25/93 Show-M: Bicycle Tour 29 07/16/93 Thailand Teacher Training. Dr. Sparlin 13 l

08/02/93 UMR Funamentals of Engineering 31 j I

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21 Table 4-1. Public Relations Program DATE PARTICIPANTS NUN 1HER 08/03/93 UNIR Fundamentals of Engineerin<t 37 08/04/93 UhlR Fundamentals of Engineering 14 08/09/93 UNIR Fundamentals of Engineering 19 '

08/10/93 UNIR Fundamentals of Engineering 12 08/l1/93 UMR Fundamentals of Engineering 19 08/12/93 UNIR Fundamentals of Engineering 4 08/13/93 UNIR Fundamentals of Engineering 7 08/14/93 UNIR Fundamentals of Engineering 2 08/24/93 UNIC Operator Training 13 10/09/93 UNI Rolla Day 204 10/16/93 UMR Parents Day 185 12/17/93 Rolla Emergency Preparedness Training 5 l 02/17/94 UNIR TEANIS Testing 26 1 02/18/94 National Society of Black Engineers 18

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02/19/94 Boy Scouts hierit Badge Day 15 l

03/11/94 Society of Women Engineers Il 03/15/94 Cub Scouts 12 l l

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5.0 EDUCATIONAL UTil IZATION The reactor facility supported several UMR courses in the past year for a total of 2,647 student-hours. The number of UMR students utilizing the facility was 972. This increased usage is a direct result of an aggressive and continuing campus wide " outreach" program. The reactor facility provided financial support for three students with hourly wages and one PhD candidate with a Graduate Research Assistantship. Additionally, students from several universities, colleges and high schools have used the facility.

Table 5-1 lists UMR classes taught at the facility along with associated reactor usage for this reporting period.

The Reactor Sharing Program, which is funded by the U.S. Department of Energy, was established for colleges, universities, and high schools which do not have a nuclear reactor. This year,687 students and their instructors participated in this program. Table 5-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of our participants were high school students. We normally schedule high school students to see other items ofinterest at UMR after they have visited our facility, such as the Computer Integrated 1

Manufacturing (CLM) Lab, Mineral Museum, Computer Center, Experimental Mine, Solar Car, )

Electron Microscope, and Stonehenge. Therefore, the Reactor Sharing Program serves as a j strong campus wide recruiting tool by getting high school students to the university and hopefully sparking some interest in our campus. I 1

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l 23 Table 5-1. UMR Classes at Reactor Facility l 1993-94 Reporting Period TIME AT l

1. OF REACTOR STUDENT DATE CLASS NUMBEWilTLE STUDENTS (hrs) IIOURS Summer 1993 NE 400, Special Problems 1 40 40 Summer 1993 NE 490, Research 1 10 10 04/22/93 Chem S, Qualitative Analysis Lab 18 2 36 04/27/93 NE 204 Nuclear Measurements 9 1 9 04/29/93 NE 204, Nuclear Measurements 7 0.5 3.5

! Fall 1993 NE 490, Research 1 10 10 1

Fall 1993 NE 304, Reactor Laboratory 14 53 742 Fall 1993 NE 306, Reactor Operations 6 36 216 09/20/93- Chem 2. Laboratory 667 0.5 333.5 09/23/93 l 09/24/93 NE 205, Fundamentals of 9 0.5 4.5 Nuclear Engineering 11/16/93 NE 105, Intro to Nuclear 30 1 30 Engineering 12/01/93 Chem 251, Inter. Quantitative 17 2 34 Analysis & Chem 355, Inst.

Methods 12/08/93 Physics 107, Intro to Modern 45 0.5 22.5 Physics Winter 1994 NE 490, Research I 80 80 Winter 1994 NE 306, Reactor Operations 8 36 288 Winter 94 NE 308, Reactor Laboratory II 13 55 715 02/14/94 Chem 2, Laboratory 105 0.5 52.5 03/l5/94 CE 362, Public Health & Safety 20 1 20 TOTAL 972 329.5 2646.5

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l Table 5-2. Reactor Sharing Program (1993-1994) l l

DATE PARTICIPANTS NUMBER i 04/05/93 Whitfield High School 16 1

04/07/93 East Central College, Union 32 04/12/93 John F. Hodge High School, St. James 12 04/13/93 Rolla Niiddle School 57 04/14/93 Crocker High School 16 04/20/93 Southwest Missouri State University, Springfield 11 04/21/93 Parkway South High School, St. Louis County 37 l

1 04/26/93 St. Pat's 5th Grade. Rolla 16 1

04/28/93 Linn Technical College 6 04/29/93 Westminster College, Fulton 4 05/04/93 Seckman Junior High School, St. Louis County 13 i

05/07/93 Salem 6th Grade 25 .

05/12/93 Potosi 8th Grade 10 05/13/93 St. Pat's 8th Grade, Rolla 9 05/17/93 Vienna High School 12 05/20/93 Crossroads High School, St. Louis County 20 06/09/93 Rolla Vo-Tech Radiology 13 Fall 1993 Adria Fatchett, Potosi High School l 10/06/93 Laclede County High School, Conway 13 10/13/93 Plato High School Science Club 25 10/13/93 Rolla High School Science Club 18 10/20/93 Francis Howell High School, St. Charles 42  ;

l 10/27/93 Mountain Grove High School 3I i1/03/93 Macks Creek High School 16 11/10/93 Eldon High School 16 02/94 Andy Tate Hillcrest High School, Springfield 3 02/24/94 Hazelwood West Hiuh School 26

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25 Table 5-2. Reactor Sharing Program (1993-1994)

DATE PARTICIPANTS NUMBER 03/03/94 Mountain Grove Christian Academy 17 03/07/94 UMC NE 404, Columbia 4 l 03/10/94 Sullivan High School 16 l

l 03/11/94 Viburnum High School 20 1

03/16/94 Robin Searcy. Hazelwood-West High School 2 03/l7/94 Mark Twain 2nd Grade Rolla 21 03/24/94 Waynesville High School 29 i

03/28/94 UMC NE 404 Columbia 3 03/29/94 Rolla 5th Grade 52 ,

l 03/31/94 Belle High School 23 I TOTAL 687 i l

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26 I

Nuclear Engineering graduate students at the University of Missouri-Columbia (UMC) l i

came to the UMR Reactor twice in the past year to perform various reactor experiments as a  !

regular part of their NE 404, " Reactor Laboratory" course. Each laboratory session lasted about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and covered a wide variety of reactor experiments, including measuring the axial flux profile, suberitical multiplication / approach to criticality, rod worth measurements, shutdown margin and excess reactivity measurements, and student hands-on reactor operations. Although l

l UMC has its own reactor facility, it is typically unavailable for student use for the types of experiments performed at the UMR Reactor. Thus, the UMR Reactor Facility complements the larger UMC Research Reactor Facility by providing a unique facility for reactor laboratory experiments.

The UMR Reactor Facility has provided day long operator training sessions for licensed operators at the UMC Reactor. Because of our facility's availability and design, the operators l

receive unique training. We hope to provide operator training sessions to the UMC operators on a regular basis.

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27 6.0 REACTOR llEALTil PIIYSICS ACTIVITIES The health physics activities at the Uh1R 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 recorded. In addition, health physics activities include calibrations of portable and I stationary radiation detection instmments, personnel training, special surveys and monitoring of non-routine procedures.

1 l

6.1. Routine Surveys j h!onthly radiation exposure surveys of the facility consist of direct gamma and neutron 4

I measurements. No unusual exposure rates were identified. NIonthly surface contamination surveys consist of 20 to 40 swipes counted separately for alpha, and beta / gamma activity. No l

significant contamination outside of contained work areas was found.

j 6.2. Bv-Product hiaterial Release Surveys There were no shipments of by-product material released off-campus from the reactor facility during this reporting period.

28 4

6.3. Routine Monitoring Thirty-seven reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Six are read twice per month (Reactor Staff) and thirty-one are read once per month. There are four area beta-gamma / neutron badges assigned.

Twenty-five campus personnel and students are assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 22 monitor and spare badges assigned on campus. In addition,6 direct-reading dosimeters are used for visitors and high radiation area work. There have been no significant persoimel exposures during this reporting period.

Visitors are monitored with direct reading dosimeters. No visitor received in excess of 5 an indicated millirem Airborne activity in the reactor facility is monitored by a fixed-filter, particulate )

continuous air monitor (CAM) located in the reactor bay. Low levels of Argon-41 are routinely detected during operations.

Pool water activity is monitored monthly to ensure that no gross pool contamination or fuel cladding rupture has occurred. Gross counts and spectra oflong-lived gamma activity are compared to previous monthly counts. From April 1993 through March 1994 sample 4

concentrations averaged 19.7 x 10 Ci/ml.

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6.4. Waste Discosal l

Release of gaseous and particulate activity through the building exhausts is determined by .i relating the operating times of the exhaust fans and reactor power during fan operation to i

previously measured air activity at maximum reactor power. During this period 5.01 millicuries l

were released into the air. The released isotope was identified as Ar 41.

l Solid waste, including used water filters, used resins and contaminated paper is stored i L

and/or transferred to the campus waste storage area for later shipment to a commercial burial site.

Radioactive waste released to the sanitary sewer is primarily from regeneration of the ion- )

l  ;

l exchange column. The water is analyzed for radioactive contamination and approval is required l l

1 before the water is released. During this period two releases associated with resin regeneration l

i 1 were discharged to the sanitary sewer totaling approximately 214 gallons of water with a total l gross activity of 4.12 microcuries.

6.5. Instrument Calibrations  ;

During this period, portable instruments and area monitors were calibrated at six month j intervals.

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30 7.0 PLANS

, The reactor staff will be heavily involved in four major projects during the next reporting period; l) procuring, testing and installing new reactor nuclear instrumentation (NI),2) preparing to ship HEU fuel offsite,3) continued characterization of the LEU fuel and core, and 4) continued expansion of research capabilities.

7.1. Reactor Instrumentation Upgrade We have acquired three new NI channels from Gamma-Metrics which will ultimately replace our existing five channel system. Additionally, we have recently purchased a Yokogawa micro-R 1000 temperature recorder. A total of $167,000 has been secured for the console upgrade. The U.S. DOE has provided $137,000 and $30,000 is being directly provided by the UMR Reactor.

As instruments are procured, extensive review documentation will be established and appropriate approvals will be obtained. NRC will be notified of our intended changes in a timely fashion.

Detailed testing is now being perfomied and extensive operational data is being collected.

We have received word that the DOE Instrumentation Program has been discontinued. Although i

1 we had great hopes of receiving future funding, we feel very fortunate to have received as much j 1

as we have under the program. We feel that the funds we now have are sufficient for providing l l

almost a complete console upgrade. As the new equipment is installed, the reliability and efficiency of console operations will be greatly increased.

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l 31 7.2, Shipment of HEU Fuel Offsite EtTorts will continue during the next reporting period to ship our HEU fuel offsite. We hope to complete the project within the next year. Measurements and analyses have been completed that have characterized dose rates associated with each element.

Once the HEU fuel is shipped offsite, we plan to submit a revised Security Plan to NRC to reduce some of our current security requircrients.

7.3. LEU Fuel Characterization Over the past year we have continued with characterization studies for the new LEU fuel.

We plan to continue the studies and to that end we have submitted a proposal to DOE for

! funding. In particular, we would like to do detailed gold wire flux mapping of the core, detailed I

energy spectrum characterization of our experimental facilities, and a precise measurement of reactor kinetics parameters.

7.4. Expansion of Research Capabilities l

Over the next year, efforts will continue to expand the facility's research capabilities. In particular, we are placing much emphasis on computer interfacing with the new console equipment. The new equipment has been specially designed to provide isolated signal outputs dedicated to interfacing with computer data acquisition stations. There is great faculty interest in this capability with planned research in the areas of artificialintelligence, neural networking and an

! " operator advisory" system.

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APPENDIX A.

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l STANDARD OPERATING PROCEDURES i l

CHANGED DURING THE PAST YEAR l l

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** ,

SOP: 100 TITLE: PREAMBLE '

Revised: November 4, 1993 Page 1 of 2 l

l A. Purcosq The purpose of this document is to set forth the procedures for routine and emergency operations of the University of  !

l Missouri-Rolla Reactor. The goal of these procedures is to l assure that the UMRR will be operated safely, presenting no l hazard to the public or to the operating staff, and second- -

arily, that reactor equipment will be safeguarded. It is l mandatory that all personnel involved with reactor operations l be completely familiar with these procedures and that these i procedures be followed.

B. Precautions _Prerecuisites, or Limitations

1. These procedures are intended to reflect and implement Facility License Number R-79, as amended, and Title 10 of the Code of Federal Regulations. '

2. Only two copies of the SOPS are to be considered con-trolled copies. The controlled copies shall contain all of the approved procedures and will incorporate new or l revised procedures as they are approved. The controlled copies should be retained in the office reception area (Reactor Manager's Copy) and in the Control Room (Control Room Copy). All other copies of SOPS are to be l considered complimentary only and shall not be used for l facility evolutions.

3. The SOPS shall be reviewed annually by either the Reactor Manager, Reactor Director, or a licensed operator.

Identified weaknesses, inadequacies, or recommendations i for improvements should be discussed with the Reactor Manager to determine if revision to the SOPS is required.

4. Changes that do not change the original intent of the procedures may be made with the approval of the Facility Director.

5. Substantive changes to the approved procedures shall be made only with the additional approval of the Radiation Safety Committee, i

Written By: David Freeman Approved By: Albert Bolon i dY M[ QQ1

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** j SOP: 100 TITLE: PREAMBLE i Revised: November 4, 1993 Page 2 of 2 I l

6. Handwritten revisions to the Controlled SOPS may be made provided the following conditions are satisfied: Re a) Handwritten revisions are clearly legible and neatly made in rad ink in both Control SOPS.

b) Handwritten revisions are reviewed and approved by l both a Senior Operator and the Reactor Director.

Review and approval shall be documented by initial-ing and dating the revision.

c) Handwritten revisions should be listed on the revision form located in the front of the Reactor Manager's controlled copy of SOPS in red ink.

l In the absence of the Reactor Director, the Reactor Han-ager may review and temporarily approve handwritten revisions provided the Reactor Director reviews the I revision as soon as practical upon his return.

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l Written By: David Freeman Approved By: Albert Bolon U

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** I

) SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: November 4, 1993 Page 1 of 4 I

A. Purcose:

To provide written procedures for routine reactor operation.

1' B. Precautions, Prerecuisites, or Limitations:

1. Reactor operations must at all times meet the require- i ments of the Facility License R-79, Technical 4

Specifications, and the Physical Security Plan.

2. At least two persons, one of whom is a Senior Operator, '

l shall be present in the Reactor Building when the reac-tor is operating.

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3. a) A licensed operator who is responsible for reactor Rev.

operation shall be present in the control room at all times when the reactor is operating. )

b) Students and trainees may operate the reactor controls subject to the following conditions. In j

such cases the licensed operator maintains complete and total responsibility for all aspects of reactor operations.  !

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i) Students and trainees may operate the reactor j controls under the direct supervision of a licensed operator provided the excess I

reactivity is less than 0.7% delta k/k.

ii) Trainees may operate the reactor controls i

under the direct supervision of a Senior l Reactor Operator when the excess reactivity is greater than 0.7% delta k/k and less than 1.5% delta k/k. l 1

4. The reactor will be operated with the minimum amount of 4 excess reactivity necessary to fulfill operational

, requirements as determined by the Reactor Director. ,

5. Personnel in the Reactor Building should be informed over the public address system about changes made to the reactor status.

l Written By: David Freeman Approved By: Albert Bolon

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• • • UKR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL P.ROCEDURES Revised: November 4, 1993 Page 2 of 4

6. All reactor operational personnel are responsible for entering in the appropriate log book any work on or around the reactor or reactor components important enough to justify a record for future reference.

7. All personnel are responsible for notifying the Senior Operator on Duty of any work being done that could either directly or indirectly affect reactor operations.

8. Radioactive samples or sources will be removed from the core or thermal column only under the direction of a Senior Operator, or the Campus Health Physicist (or his designated representative).

9. Log books will be kept in the control room safe, except the one currently in use, which may be kept on the con-sole. If the books are removed from the control room, I permission must be granted by the Reactor Manager. Any books removed shall be returned as soon as possible. j

10. Completed recorder chart paper will be dated and filed I in designated areas, and kept on file for at least the minimum required time. Loc N charts are to be kent as )

a cernanent record.

11. Changec in Core-Mode (T or N) ill- bc noted-in--t-he-pcr D mane n.t-Log-bcck , inc1uding-da-te-and tiac . 74 %

1

12. Only the Senior Operator on Duty may key bypass control ,

channel automatic functions. The use of any interlock l bypass key requires a permanent log entry for insertion i I

and removal. This log entry shall include date and time. This requirement does not apply when the reactor is shut down (e.g. performance of the Weekly Checklist procedure).

13. Any abnormal behavior or abnormal change in core R4 reactivity associated with reactor startup or operation should be reported to the Senior Operator on Duty immediately. If there is any doubt about reactor safety, the reactor shall be immediately shut down by the Operator-on-Duty. The cause should then be determined and corrective action taken.

t Written By: David Freeman Approved By: Albert Bolon Mdb

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l *** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: November 4, 1993 Page 3 of 4

14. Only a Senior Operator can give permission to restart the reactor after a scram or rundown.

15. The Standard Operating Procedures (SOP's) should be followed to the extent practicable, especially whenever the Pre-Startup Checklist is being completed, when the reactor is being started, or when the reactor power is being changed.

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16. The Senior Operator on Duty has the authority to instruct the reactor operator to disregard certain SOP's provided that no safety requirements are violated. (For example SOP 305 does not have to be performed every pre-startup checklist.)

l 17. All scrans and rundowns shall be noted with explanation of the cause and corrective action in the permanent log book.

18. The following procedures are to be performed by the Reactor Senior Electronics Technician or other )

L #/ qualified individual as determined by the Reactor i Manager. A licensed operator will participate when reactor operation is involved (e.g. Rod Drop Time Measurements). ,

1 SOP 609, " Radiation Area Monitor (RAM) Calibrations" SOP 800, " Semi-Annual Checklist" SOP 801, " Log N and Period Channel" SOP 802, " Linear Channel" SOP 803, " Log Count Rate (LCR) Channel" SOP 804, " Safety Amplifier System" SOP 805, " Auto Control System" .

SOP 806, " Temperature Recorder" SOP 807, " Neutron RAM System" SOP 809, " Relay Test" SOP 811, " Fire and Smoke Alarm System" SOP 813, " Rod Drop Time Measurement" SOP 818, " Functional Test of Building Security System" Written By: David Freeman Approved By: Albert Bolon fahAUA &Qf&

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** l SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDUPIS Revised: November 4, 1993 Page 4 of 4 1

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19. The following procedures are to be performed by the Health Physicist or other qualified person (s) as determined by the Health Physicist:

SOP 604, " Release of By-Product Materials on Campus" SOP 610, " Radiation Area Survey" SOP 611, " Contamination Survey" SOP 612, " Pool Water Tritium Analysis" SOP 613, " Sealed Source Leak Test" SOP 614, " Measurement of 41Ar Concentration in the Reactor Building Air" SOP 616, "Use of Respirators"

20. Only person (s) specifically approved by the Reactor Manager shall perform the following procedure:

SOP 204, "Demineralizer Re;eneration" Written By: Dav- r eman Approved By: Albert Bolon kNbb

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l *** UMR REACTOR STANDARD OPERATIWJ PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: November 12, 1993 Page 1 of 9 A. Purnose:

1 \

I The purpose of the checklist is to verify that reactor sys- l l tems are operating correctly prior to reactor start-up. )

l l B. Precautions. Prerequisites, or Limitations. 4

1. A licensed operator shall be responsible for performing the pre-startup checklist. The operator may assign various steps to be completed by unlicensed personnel;

, however, the operator is still fully responsible for j the proper performance of the checklist.

2. The checklist shall be completed prior to the first reactor start-up of the day. The checklist shall be completed prior to a reactor start-up after a " Secure" checklist has been completed.

3. After each step on the checklist is performed the oper-ator will record the readings made, or in cases where l no readings are required, will simply check the l

appropriate blank on the form.

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4. Any malfunction or abnormality identified during performance of the checklist shall be immediately  :

reported to the Senior Operator on Duty, and corrected as necessary before completion of the checklist.

C. Procedure Complete the checklist in accordance with the following  ;

l steps: '

l l 1. Date - Record the date using the rubber date stamp.

l i 2. Time - Record the time shown on the console clock.

3. Core Loading - Enter core loading number and mode.

4. Verify that the P.A. system is operable. Turn on the j bridge intercom and video monitor.

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l Written By: Davi eeman Approved By: Albert Bolon l

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: Novernber 12, 1993 Page 2 of 9

5. RAM System Check:

a. Announce, "THE BUILDING ALARM WILL SOUND. THIS IS A TEST. DO NOT EVACUATE THE BUILDING."

b. Check that the setpoints and automatic functions of the RAM systems meet the criteria listed below.

For each High Radiation Alarm, verify that both the audible alarm and the visual annunciator are actuated. Reset the annunciator panel after each High Radiation Alarm check.

CHANEL SETPOINT ACT0MATIC ACTION

1. BridgeRAM 10 - 18 mR/hr High Radiation Alan

2. Bridge R)3 15 - 28 nR/hr BuildingEvacuationAlars

3. Denin R13 10 - 18 nR/hr High Radiation Alan

4. Basenent R13 10 - 13 mR/hr HighRadiationAlars

c. Announce, " TEST COMPLETE, ACKNOWLEDGE ALL FURTHER ALARMS".

6. Verify that all monitors read between 1 to 8 mrem /hr.

7. Nitrogen Diffusers Status: Turn on nitrogen diffuser pumps as desired. Record status of pumps as "ON" or "OFF". (Note: At least one pump should be turned on for operations in excess of 20 kW.)

8. Beamport and Thermal Column Status: Record the status of the beamport and thermai column ("op'en" or " shut")

as indicated by 1) the " Beam Port or Thermal Column Open" annunciator light and 2) the Beam Port Indication light. Notify the Senior Operator on Duty if either facility is "open".

9. Linear Channel:

a. Depress the zero check button; verify that the digital display reads ".0000".

I Written By: Davi F eman Approved By: Albert Bolon 7"* # Adb

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: November 12, 1993 Page 3 of 9 1

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b. Depress the zero check button again to release the check function. Set the Linear compensating voltage to obtain a Linear reading between 0.02 and 0.05 on the 2 W scale. Following a high power run, the SRO on Duty may adjust the Linear compensating voltage as appropriate.

c. Record the Linear reading. Record the scale.

10. CIC Voltages: Record the high voltage (HV) and compensating voltage (CV) settings of the Linear and Log N Power supplies. Values should correspond approximately to those presented in the table below:

CIC HV CV

-Linear 480 2 to 8 Log N 540 6

11. Turn recorders on and date them. Reset the annunciator panel.

12. Core Check: Turn the pool lights on,

a. Check the water level in the pool.

b. Visually inspect the core and pool for abnormalities. Check in-core experiments.

c. Insert the source into the core source holder. lRs.

13. Start-Up Channel Test: Turn the Log Count Rate selector switch to 102, 10' , and 10?. . Verify that the meter and recorder follow. Return the selector switch to the " OPERATE" position.

14. Verify Fission Chamber Response: Insert the fission chanber until the green Insert Limit light comes on.

Observe the count rate. Raise the fission chamber until the count rate shows a definite decrease.

Written By: Da'if FrAeman Approved By: Albert Bolon

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES '

I Revision: November 12, 1993 Page 4 of 9 l

15. Insert the fission chamber to insert limit. Verify that the count rate is greater than 2 cps. (Following a high power run, the SRO on Duty may position the fission chamber as desired as long as a count rate greater than 2 cps is maintained.)

16. Log N Test: Check that the meter generally follows the recorder response for the " LOW" and "HIGH" check.

a. Turn switch on Log N to " LOW". Verify the receipt of the Log N/ Period Non-Operative Scram audible and visual alarm and that the Log N recorder and meter read about 0.01 kW.

b. Turn the switch to "HIGH" and verify that the recorder and meter read about 8 kW.

c. Reset the annunciator panel.

17. Period Response Test:

a. Turn the period switch to " CALIBRATE". Verify the receipt of the Log N/ Period Non-Operative Scram.

Check that the Period recorder and meter read about 6 seconds.

b. Verify the annunciator panel for Log N and Period Nonoperative, 30 sec period and 15 sec period lights. Reset the annunciator panel. (Note: The 5 second Period Scram may also be illuminated.)

18. Turn on the magnet power using the key switch. Push the Scram Reset button to energize the magnets. Reset the annunciator panel. If a magnet contact light is out, notify the SRO on Duty.

19. Record inlet temperature. Notify the SRO on Duty if the inlet temperature is below 60*F.

20. Record the magnet currents. (Typical readings should be between 25 and 85 mamp.)

21. 150% Power Scram Check:

a. Withdraw shim rods to 3 inches.

Written By: Da qid e ian Approved By: Albert Bolon la@, 6tl Q

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• • • UMR REACTOR STANDARD OPERATING PROCECURES ***

l SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES I i Revision: November 12, 1993 Page 5 of 9 l l

4

b. Depress the test button on safety amp and hold until the 4 red lights come on. Observe that the I scram occurs prior to 150%.

c. Verify that the rods have dropped and that the ,

audible and visual alarms have actuated.

i d. Reset the drawer and annunciator panel.

22. Log N/ Period Non-Operative Scram and 15 second Rundown Test:

a. Withdraw shim rods to 3 inches.

2

b. Turn the period test switch to " CALIBRATE" to i provide a 6 second period indication. Check for i i the Log N Inoperative Scram, Manual Scram, 15 l

) Second Rundown, and 30 Second Period lights on j annunciator panel.

c. Try to stop the run down by lifting the shim joy ,

stick. l 1

d. Stop the rundown with the rundown reset button.

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e. Verify that the rods have dropped. I

! f. Push the scram reset button and reset the annunciator panel.

1 23. Period Trip Test:

1

a. Withdraw shim rods to 3 inches.  !

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b. Hold the trip test toggle switch in the " Test" Rev. l position. I

c. Rotate the " Trip Test" knob slowly and observe l that the 30 second rod withdraw prohibit annunciator is actuated with a simulated period 1 30 seconds.

i d. Continue to rotate the knob and observe that the l l 15 second period rundown occurs with a simulated l

! period 1 15 seconds. '

Written By: Da ' d cFr man Approved By: Albert Bolon hM k\k T>

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES i

Revision: November 12, 1993 Page 6 of 9

e. Continue to rotate the knob until the period scram is received. Verify that the Period scram occurs at a value > 5 seconds and that the shim rods have dropped.

4

f. Release the " Trip Test" toggle switch and make Rei sure that it springs back to the " operate" position.

G. Reset the Period trip on the Log N drawer. Reset the rundown. Reset the annunciator panel.

24. Manual Scram:

a. Raise shim rods to 3 inches.

b. Push the manual scram button. Verify that the rods have dropped by visually observing the video display and noting that the blue magnet contact lights are off.

c. Push the scram reset button and reset the annunciator panel.

25. Push the annunciator test button and check for burned out bulbs. Replace any burned out bulbs. Reset the annunciator panel.

26. Verify that the magnets are on and that all rods are on insert limit.

27. Prepare hourly and permanent logs.

28. Detector Response Check:

a. Inspect the core. Make certain c' ore cooling is Re clear and experiments are firmly secured.

b. " Spike" the Log N and Period CIC and the Linear CIC by positioning the neutron source next to the detectors.

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c. Insert the source into the holder.

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l Written By: David'~ree an Approved By: Albert Bolon fM'/H Q% L @sW ,

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: November 12, 1993 Page 7 of 9 i

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d. Observe the Log N, Period and Linear recorders to Rev.

verify proper response to the source spike. ,

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e. Observe the Startup Channel recorder to verify l

, that the recorder responded properly with a )

l decreased count rate when the source was moved away from the core. I l

f. Reset the annunciator panel. l l

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29. Raise the shim rods to 6 inches. Record the time on l

both the checklist and in the permanent log.

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30. Announce, "THE REACTOR WILL BE STARTED AND TAKEN TO A POWER OF WATTS".

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! 31. Record the intended power level. l

32. Review the Pre-Startup Checklist. Verify that all of the steps have been completed. The licensed operator responsible for performing the checklist will initial the checklist thus verifying that it has been properly l completed.  !

33. The Senior Operator on Duty will initial the checklist l verifying that all items have been completed and any problems identified have been satisfactorily resolved.

l 34. Record the date using the rubber date stamp.

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l I Written By: Dayfd -n Approved By: Albert Bolon dhY N GQ oW

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** l SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES '

Revision: November 12, 1993 Page 8 of 9 1

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UKRR PRE-STARTUP CECKLIST (SOP 102)

1. Date

2. Ti:e (Console Clock)

3. CoreLoading

4. P. A., Inter:en, Video Monitor On

5. P14SystesCheck

6. Radiation Level Normal

7. Nitrogen Diffuser Status No. 1 (RequiredwhenP>20kW)

No. 2

"' 8. Baas Port and thersal Column Status l

9. LinearChannel Iero MeterReading Scale

10. C.I.C. Voltages LinearHV(-430)

LinearC7(-1)

LogNHV(-540)

LogNC7(-6)

11. Recorders On and Dated Ro

12. Core Check (Lights On) LevelCheck Inspect Core SourceInserted  !

13. Start-Up Channel Test

14. Verify Fission Chanter Response

15. Fission Chanber Inserted, Count Rate > 2 CPS  :

1 I

16. Log N Test 1

Written By: Davi man Approved By: Albert Dolon f" 0.{ h h

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: November 12, 1993 Page 9 of 9

17. Period Response Test

13. Maget Power On, Scras Reset, Board Reset

19. Inlet Te:penture (CE)

20. Mapet Currents (sillia:ps) No. 1 No. 2 1 No. 3 l

l 21. 1501 Power Scus Test RaiseRods3in.

Push " Test

• Button

22. Log N/ Period Non-Cperative Scras RaiseRods3in, and 15 Sec Period Rundown Test SelectSwitchto

" Calibrate

23. Period Trip Test

24. Manual Scras Test RaiseRods3in.

Push Minual Scris 25.AnnunciatorTest,AllLightsOn

26. Magets On, Rods on Insert Litiit

27. Prepare Ecurly and Permanent Logs

23. Detector Response Check Inspect Core Log N Spike PeriodSpike LinearSpike StartupChannel

Response

29. Raise Rods to 6 in., Record Time in Both Logs 30.AnnounceIntentiontoStart

, 3L. Intended Power Level i

32. Pre-StartupCheckProperlyCospleted(Lic.Op. Initials)

33. Senior Operator's Initials

34. Date Davi eman Approved By: Albert Bolon Written By: ~ ans x WL%~

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 1 of 7 s

A. EURPOSE i

To provide a safe and consistent method for performing a reactor startup to a low power level.

B. PRECAUTIONS. PREREQUISITES. LIMITATIONS

1. The Pre-Startup Checklist shall be completed and J approved by the SRO on Duty prior to commencing reactor startup.

l

2. The reactor will be considered " clean" if shutdown for more than 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />. The reactor will also be considered " clean" if power levels within the past 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> have not exceeded 20 kW-hr.

3. The reactor will be considered " hot" following a shutdown while the neutron population is still

decreasing as determined by the Startup Channel count rate.

1

4. The reactor will be considered "high residual" when it is neither " clean" nor " hot" as defined above.

5. The licensed operator shall control all reactivity changes to the reactor by direct manipulation or by directing the manipulation of the controls and experiments being conducted at the facility.

6. The operator must be alert and attentive at all times during reactor operations. All nuclear instruments

] (Startup, Linear, Period, Log N, Safety No. 1 and Safety No. 2) must be closely monitored for proper response. If at any time an improper, response is suspected, the Senior Operator on Duty shall be notified and a reactor shutdown initiated as deemed i necessary by the Reactor Operator.

7. The console operator should scram or shut down the reactor without hesitation if any doubt exists about reactor safety.

4

/ \

I Written By: David Approved By: Albert Bolon PS1?> as*Freeman (M@k J

e

i l

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

l SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 2 of 7

8. If a scram or rundown occurs permission to restart the reactor can only be authorized by the Senior Reactor Operator on Duty.

C. STARTUP TO LOW POWER PROCEDURE FOR A CLEAN CORE l

1. Initial Reactor Status - The Pre-Startup Checklist shall be completed and approved. The shim rods should be at 6 inches and the neutron source inserted into the core.

2. Withdraw Rods To Shim Range:

a. Withdraw the Shim Rods to a position between 12.5 and 13.0 inches. Verify that the yellow Shim Range indicator lights are illuminated.

b. Withdraw the Regulating Rod to 15.0 inches.

c. MILESTONE - VERIFY DOUBLING: Verify that the l

Startup channel count rate has approximately doubled, showing a clear increase in response to tho rod withdraws. If a clear increase is not observed, the startup shall be halted and the SRO on Duty notified.

3. Withdraw Shim Rods To 18 Inches:

i a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to an approximate 84 second period.)

b. Withdraw the Shim Rod bank in one inch (or less) increments, pausing between each pull as specified above.

c. Verify that the Startup Channel responds properly to each rod pull.

d. Continue until the Shim Rods are at 18.0 inches'.

~

Written By: David Fre Approved By: Albert Bolon p2 8::pJ1ap

t uf W

. _ . - - _ _ _ _ . . _ . ~ . _ _ _ _ _ __ -.. _ _ __ __ __ _ ___

l I

l l *** UMR REACTOR STANDARD OPERATING PROCEDURES ***

i SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 3 of 7 1

4. Withdraw Shim Rods To Instrument Turnaround:

a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds

. between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This I corresponds to an approximate 85 second period.)

b. Withdraw the Shim Rod bank in 0.25 inch (or less) increments, pausing between each pull as specified above.

c. Verify that the Startup Channel responds properly to each rod pull,

d. Closely observe the Linear, Period, and Log N channels for " turnaround" (i.e. rising neutron signal indication).

e. MILESTONE - IDENTIFY " TURNAROUND": Linear, Period, and Log N " turnaround" must be identified before the Startup Channel signal reaches full scale. If the Startup channel nears the top of its scale and proper turnaround is not observed, than the power shall be leveled in the operating range of the Startup Channel and the SRO on Duty notified.

f f. After positive " turnaround" is noted on each the l Linear, Period, and Log N channels, the fission l chamber may be withdrawn to a convenient height (normally the fission chamber should be adjusted to read approximately 100 count per second).

g. The Startup Channel signal should not be allowed to increase off scale.

5. Continue Power Increase and Level At Low Power:

a. After instrument " turnaround" has been confirmed, limit the rate of power increase to an approximate 50 second period as indicated-by the Period Channel. The Senior Operator on Duty may authorize shorter periods.

i Written By: David Fr.eemaa Approved By: Albert Bolon d f.'/4 , hN

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 4 of 7

b. Upscale the Linear Channel as necessary when it reaches approximately 60% of the selected scale.

c. The neutron source should be withdrawn from the core when the Linear is on the 20 Watt scale.

d. Level reactor power between 2 and 20 Watts, e .. Place the reactor in autocontrol as desired.

I

f. RAFT (Reset, Announce, Eission Chamber, Time):

i) Eeset the annunciator panel. Verify that the

" Manual" light is off when in auto control.

l ii) Announce the reactor power over the building PA.

iii) Position Eission Chamber to read midscale.

iv) Record Time at power in the permanent l logbook.

g. Complete the Hourly Log sheet.

6. Refer to the appropriate SOP for further operations.

I D. REACTOR RE-START WITH A HOT CORE (DECREASING SOURCE RANGE COUNT RATE FOLLOWING A SHUTDOWN) l 1. Position the fission chamber low enough such that the ,

count rate will not go below 2 cps during the startup.

l At the same time, try to position the detector high enough to have as much range for increasing count rates as possible. '

2. Adjust the Linear compensating voltage until the signal  ;

follows the actual power decay or until the lower limit j

of sensitivity is reached. Make sure the Linear signal

! is positive.

1

3. Record the intention to restart the reactor and the intended power level in the permanent logbook.

l

^'

Written By: David Freema Approved By: Albert Bolon lmk IC'Y h hW%

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 5 of 7

4. If the reactor is being restarted following an automatic scram or rundown or following an unanticipated shutdown, permission to restart must be granted by the SRO on Duty.

5. Withdraw Rods to Shim Range

a. Withdraw the Shim Rods to a position between 12.5 and 13.0 inches. Verify that the yellow Shim Range indicator lights are illuminated.

b. Withdraw the Regulating Rod to 15.0 inches.

c. Readjust the fission chamber position and Linear Compensating Voltage as needed. Doubling in count rate need not (and most likely will not) be observed at this point.

6. Withdraw Shim Rods To 18 Inches:

a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to an approximate 84 second period.)

b. Withdraw the Shim Rod bank in one inch (or less) increments, pausing between each pull as specified above.

c. Verify that the Startup Channel responds properly to each rod pull. The rate of decrease in the count rate should slow and may turnaround and begin to rise depending on the power history.

d. Continue until the Shim Rods are at 18.0 inches.

7. Withdraw Shim Rods To Instrument Turnaround:

a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Written By: David redMa Approved By: Albert Bolon fd lUk $k W

J

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 6 of 7 i

Startup Channel recorder to 45 degrees. (This corresponds to an approximate 85 second period.)

b. Withdraw the Shim Rod bank in 0.25 inch (or less) increments, pausing between each pull as specified above.

c. Verify that the Startup Channel responds properly to each rod pull. The rate of decrease in the

countrate should slow and eventually turnaround

and begin to rise.

d. Closely observe the Linear, Period, and Log N l channels for " turnaround" (which means a positive j signal response). )

2 l

e. MILESTONE - IDENTIFY " TURNAROUND": Linear, Period, I and Log N " turnaround" must be identified before i the Startup Channel signal reaches full scale and i prior to obtaining shim rod positions within one inch of the critical rod heights before shutdown.

If these conditions are not met, notify the SRO on l l'

Duty and insert rods to shim range and reposition the fission chamber and readjust the Linear

, compensating voltage as necessary. Repeat Steps l C.5 through C.7 as necessary to satisfy this requirement.

f. After positive " turnaround" is noted on each the i Linear, Period, and Log N channels, the fission ,

j chamber may be withdrawn to a convenient height l j (normally the fission chanber should be adjusted to read approximately 100 count per second).

g. The Startup Channel signal should not be allowed i to increase off scale.

8. Continue Power Increase and Level At Low Power:

a. Complete this step as specified for a clean core.

j 9. Refer to the appropriate SOP for further operations.

Written By: David Freeman) Approved By: Albert Bolon be b

_ . _ _ ~ . _ - _

• • • UKR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Complete Revision: December 23, 1993 Page 7 of 7 E. STARTUP TO LOW POWER PROCEDURE FOR A HIGH RESIDUAL CORE

1. Perform the startup steps as prescribed for a clean core except:

a. pause slightly longer between rod withdrawals,

b. the Linear compensating voltage may be readjusted with shim rods at 6 inches, as necessary.

Inmediately following a high power run it may not be possible to adjust the compensating voltage as low as 0.05. In such instances, adjust the compensating voltage to obtain the lowest stable positive signal. The SRO on Duty is to be notified in such instances.

c. be prepared for the reactor to behave differently than usual, and

d. be prepared for the critical rod heights to be

, dif ferent than for a cold, clean core.

Written By: Dav4 rennan Approved By: Albert Bolon fCN$pA/l $0 W

i i

• UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Complete Revision: December 23, 1993 Page 1 of 5 i

A. PURPOSE

] To provide for a safe and consistent method to 1) change power after the reactor has been leveled at lvJ power and 2) operate the reactor at steady-state power.

B. PRECAUTIONS, PREREOUISITES. OR LIMITATIONS

1. This procedure is applicable after SOP 103, " Reactor .

Startup to Low Power" has been completed. j J

2. Both safety channels should begin to show turnaround at )

) about 5 kW. If turnaround has not been observed by a

! power of 10 kW, the reactor will be shut down and the SRO on Duty notified. l i

] 3. At least one nitrogen diffuser should be turned on for operations greater than 20 kilowatts. This requirement may be waived by the SRO on Duty for special tests.

Reactor bridge radiation levels shall not be allowed to l equal or exceed 30 mr/hr. l l

4. Prior to taking the reactor to a power level in excess of 100 kW, the reactor must first be leveled at a power between 10 kW and 100 kW and hourly logs taken to verify the proper operation of the reactor instrumentation. This requirement is only applicable l to the first power increase above 100 kW for a i j particular operational run.

4 5. At least one building exhaust fan shall be turned on

for reactor operations at 200 kW.

j 6. At least one building exhaust fan should be turned on when the constant air monitor reaches a value of about 600 cpm.

7. The licensed operator shall control all reactivity changes to the reactor by direct manipulation or by directing the manipulation of the controls and experiments being conducted at the facility.

David Freeman Written By: Approved By: Albert Bolon a

t flb h,Ah-

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

sop: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Complete Revision: December 23, 1993 Page 2 of 5

8. The operator must be alert and attentive at all times during reactor operations. All nuclear instruments (Startup, Linear, Period, Log N, Safety No. 1 and Safety No 2) must be closely monitored for proper response. If at any time an improper response is suspected, the Senior Operator on Duty shall be notified and a reactor shutdown initiated as deemed necessary by the Reactor Operator.

9. The console operator should scram or shut down the reactor without hesitation if any doubt exists about reactor safety.

10. If a scram or rundown occurs, permission to restart the reactor can only be authorized by the Senior Reactor Operator on Duty.

C. POWER INCREASE PROCEDUR_E

1. Record the intent to increase power with the time in the permanent logbook.

Examole: 1028 Reactor started to 20 kW.

2. Announce the intention to increase power over the PA system.

EKampln: " Reactor power will be increased from 20 W to 20 kW."

3. Switch the reactor to " Manual" control.

4. Carefully monitor all nuclear instruments (Start-up, Linear, Period, Log N, Safety No. 1 and Safety No. 2) for proper response during the power transient.

5. Withdraw rods in small increments while carefully  !

monitoring the " prompt jump" on the Period Channel.

The prompt jumps should normally not be allowed to ,

reach a 30 second period.

l l

l Written By: David Fr3n an Approved By: Albert Bolon l p iir k t ong g& l 1

l l

I

• • • UMR REACTOR STANDARD OPERATING PROCEDURFS **

SOP: 104 TITLE: REACTOR POWER C'.IANGES AND STAllLE OI FRATIONS Complete Revision: December 23, 1993 Page 3 or S

6. Limit the rate of power increase to an approximate 50 second persistent period as indicated by the Period Channel. The Senior Operatcr on Duty may authorize shorter periods.

7. Upscale the Linear Channel as necessary when it reaches ,

approximately 60% of scale. If the Linear Channel is l reading 60% or greater prior to initiating the power  ;

increase, it may be upscaled before beginning the power increase.

8. Level the reactor at the desired power.

9. Place the reactor in autocontrol.

10. RAFT (Reset, Announce, Eission Chamber, Timo):

a. Reset the annunciator panel. Verify that the

" Manual" light is off when in autocontrol.

~

b. Announce the reactor power over the building PA. j

c. Position Eission Chamber to read midscale.

d. Record Time at power in the permanent log.

l Example: 1032 Reactor at 20 kW.

l 11 Complete the Hourly Log Sheet.

D. EQWER DECREASE PROCEDUR_E

1. Record the intent to change power in the permanent logbook.

Exaggl_n: 1401 Reactor power decreased to 60 kW.

2. Announce the intention to change power over the PA system.

Examole: " Reactor power will be decreased from 200 kW to 60 kW."

F

3. Switch the reactor to " Manual" control.

I l

Written By: Dav Approved By: Albert Bolon p k,idhEreeman ggg

• • • UKR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Complete Revision: December 23, 1993 Page 4 of 5

4. Carefully monitor all nuclear instruments (Start-up, Linear, Period, Log N, Safety No. 1 and Safety No. 2) for proper response during the power transient.

5. Insert rods to achieve the desired rate of power decrease.

6. Reposition the Fission Chamber as necessary to keep the reading on the upper half of the scale.

7. Downscale the Linear Channel as necessary when the reading reaches about 8%.

8. Level reactor power at the desired power level.

9. Place the reactor in autocontrol.

10. RAFT (Reset, Announce, Eission Chamber, Time):

a. Reset the annunciator panel. Verify that the

" Manual" light is off when in autocontrol.

b. Announce the reactor power over the building PA.

c. Position Eission Chamber to read midscale.

d. Record Time at power in the permanent log.

Example: 1406 Reactor at 60 kW.

11. Complete the Hourly Log Sheet.

E. STEADY STATE POWER OPERATIONS

1. Constant Power - Automatic Control

a. In the event an abnormality is detected in the automatic control system, the reactor shall be switched to manual control and the Senior Operator on Duty notified.

("

l Written By: Day.jp n Approved By: Albert Bolon

[ p aae n @gfg

• *

• UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPEMTIONS Complete Revision: December 23, 1993 Page 5 of 5

b. The position of the regulating rod should be monitored to assure that it does not reach the insert or withdrawal limit while in auto control.

In the event the regulating rod reaches approximately the 6 inch or 18 inch position, switch to manual and reposition rods while maintaining the constant power level. If the safety rods approach the withdrawal limit or lower limit of shim range, the Senior Operator on duty should be notified.

c. Complete the Hourly Operating Log at hourly intervals.

2. Constant Power - Manual Control

a. The power level should be maintained constant by manually adjusting rods. The Operator will continuously monitor the instrumentation. All entries in the permanent Log or the Hourly log should be recorded by an assistant.

b. At hourly intervals, an assistant should be summoned to record the appropriate information in the Hourly Operation Log.

1 l

I l

1 Written By: David Freeman Approved By: Albert Bolon j ab h

t

• *

• UMR REACTOR STANDARD OPERATING PROCEDURES * *

• SOP: 111 TITLE: MEASUREMENT OF CORE EXCESS REACTIVITY AND DETERMINATION OF SHUTDOWN MARGIN l Revised: March 30, 1994 Page1of3 l A. EURPOSE:

To provide for the consistent and safe method of measuring core excess reactivity and for determining shutdown margin.

B. PRECAUTIONS. PREREOUISITES. OR LBIITATIONS:

1. The reactor should be " clean" when perfonning this procedure. The reactor will be considered clean if operations within the previous 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> have been limited to 20 kilowatt-hours.

2. Refer to SOP 109 and SOP 110 for rod calibration procedures.

3. Following any change in core con 6guration involving reactivity changes greater than 0.2% delta k/k, including any control rod grid position changes, the excess reactivity of the core shall be determined for both the W and T modes.

4. The shutdown margin shall be determined after the excess reactivity of the core i and the total worth of each control rod have been experimentally determined for a '

l new core con 6guration.

5. Excess reactivity and shutdown margin requirements are as follows:

a. Students and trainees may operate the reactor under the direct supervision of a licensed Reactor Operator provided the excess reactivity is less than 0.7% delta k/k.

b. Trainees may operate the reactor under the direct supervision of a Senior Reactor Operator when the excess reactivity is equal to or greater than 0.7% delta k/k and less than 1.5% delta k/k. I

c. The excess reactivity will be no more than h5%4 elta k/k, except that the i

excess reactivity may be increased up to a maximum of 3.5% delta k/k for purposes of control rod calibration only. This increase in excess reactivity above 1.5% delta k/k will be permitted no more than twice a year and for no more than five consecutive working days each time. The reactor shall . ,

be operated only by a licensed Senior Operator when the excess reactivity is greater than 1.5%.

Written By: David W. F eman Approved By: Albert E. Bolon y@ ' at Ak.A

l 4

s

< *" UMR REACTOR STANDARD OPERATING PROCEDURES *"

j SOP: 111 TITLE: MEASUREMENT OF CORE EXCESS REACTIVITY i AND DETERMINATION OF SHUTDOWN MARGIN

Revised

March 30, 1994 Page 2 of 3 i

d. The minimum shutdown margin under any condition of operation with the

highest worth control rod and any non-scrammable control rod fully i withdrawn shall be no less than 1.0% delta k/k.

i j C. EXCESS REACTIVl_TY MEASUREMENT PROCEDURE:

i j Excess reactivity may be measured by either the Positive Period Method or the Static Method. Both uethods are descibed below.

1. Positive Period Method

a. Take the reactor critical at a low power (e.g. 20 watts).

b. Verify that the neutron source is removed from the source tube.

c. Log the critical rod positions.

d. Use the positive period method described in SOP 110 to measure the reactivity wonh of each rod tip. The rod tip is that portion of the rod between the critical rod position and the fully withdrawn position. For

,. example, if the critical rod height of a rod was 21.0 inches, the rod tip would be the portion of the rod between 21.0 inches and fully withdrawn (24.0 inches).

e. The excess reactivity is the sum of the reactivity worths of all four rod tips.

2. Static Method

a. Obtain Critical Rod Heights. Obtain critical rod heights for the reactor at a low power of 20 watts with the neutron source removed.

b. Determine Critical Rod Worths. Use the rod worth curves to determine the reactivity worth of each rod at its respective critical rod height.

c. Sum Critical Rod Worths.' Sum the critical rod worths found above for all four rods, fp*,,,,,,.

tal

d. Sum of the Total Rod Worths. Sum the total reactivity worths for each rod when fully withdrawn (use the rod worth curves), p*,,,,1 .

Written By: David W. F eeman Approved By: Albert E. Bolon

, 4e euf.6k

1 1

l l

- *** UNIR REACTOR STANT)ARD OPERATINO PROCEDURES ***  :

SOP: 111 TITLE: SIEASURESIENT OF CORE EXCESS REACTIVITY l l

AND DETER.\lTNATION OF SHUTDOWN SIARGIN Revised: March 30, 1994 Page 3 of 3 l

e. Compute Excess Reactivity. Calculate the core excess reactivity pw.,,

by subtracting the sum critical rod worths from the sum of the total rod worths as follows:

4 4 n...... =ga:....-ga:.....s D. SHUTDOWN NIARGIN DETER 3tINATION PROCEDURE:

1. Determine the Total Rod Worths. Sum the total reactivity worths for each rod when fully withdrawn for all four rods (use the rod worth curves).

2. Determine the Excess Reactivity. Determine the excess reactivity by one of the methods described in Section C above.

3. Determine the Total High Rod Worth. Using the rod worth curves, determine the total worth of the highest worth rod when fully withdrawn, p"f,"*d .

4. Determine the Total Reg Rod Worth Using the rod worth curves, determine the total worth of the regulating rod when fully withdrawn, p;*;,,"*d , .

5. Calculate the Shutdown alargin. Calculate the shutdown margin by subtracting the excess reactivity, the total high rod worth, an( the total regulating rod worth from the sum of the total rod worths as shown below:

4

= = E p;...,

.*1 p,..... -p'.::,"*' - p;' . , "'

9 Written By: David ydrapan Approved By: Albert E. Bolon udi }"Wb gQjgk

l

• • • UMR REACTOR STANDARD OPERATING PROCEDOWIS ** *

SOP

150 TITLE: RESPONSE TO ALARMS Revised: February 21, 1994 Page1 of4  ;

l A. PURPOSX )

. To provide for the proper operator response to alarms while the reactor is operating. l j l 1

B. _PR ECA UTIONS. PREREOUISITES. LDI1TATIONS

1. Reh to SOP 501," Emergency Procedures Building Evacuation" for response l

procedures to a building evacuation alarm. l

2. Refer to SOP 151, " Response to ; Figh Area Radiation Alarm" for response precedures to a High Area Radiatiw /sbrm.

3. Authc rization to restart the reactor following a scram or rundown can only be made q by a Senior Reactor Operator.

C. SCRAM RESPONSE PROCEDURE

1. Upon receipt of a SCRAM Alarm, the operator will:

a. Acknowledge the alarm.

b Verify that the shim rods have inserted (audibly, visually, or by observing magnet contact lights and currents).

c. Verify power is decreasing appropriately.

d. Fully insert all rod drives.

e. Notify the SRO on Duty.

f. Record the following information in the permanent logbook:

i) time of scram ii) type of scram (e.g. Bridge Motion, Manual, etc.)

% Written By: David Fre a Approved By: Alben Bol n fah/WIE && W

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 150 TITLE: RESPONSE TO ALAIOlS I Revised: February 21, 1994 Page 2 of 4

2. The SRO on Duty will:

a. Determine (to the extent possible) the cause of the scram.

J b. Initiate corrective actions as necessary.

c. Record the following information in the permanent logbook:

i) cause of SCRASI l -

ii) corrective action taken j lii) SRO " permission granted" to restart Note: In certain instances no corrective action will be necessary, such as a scram due to an AC power flicker. In these cases log the corrective action as "No corrective action necessary"

d. Permission to i = start the reactor must be granted by the SRO on Duty prior i to reactor restart.

]

D. RUNDOWN RESPONSE PROCEDURE i

1. Upon receipt of a RUNDOWN Alarm signal, the operator will:

a. Acknowledge the alarm

b. Verify that control rods are inserting.

c. Verify that power is decreasing.

a

d. Notify the SRO on Duty.

e. If the alarm is a "HIGH AREA RADIATION" alarm, refer to SOP 151.

Written By: Davi n Approved By: Albert Bolon ah'W {0 -

i

• • • L%1R REACTOR STANDARD OPERATING PROCEDUlkES $*

SOP: 150 TITLE: RESPONSE TO ALARMS ,

Revised: February 21, 1994 Page 3 of 4 1

1

f. A licensed operator may stop the Rundown in the event that the alarm l condition has cleared. The Reactor may not be restarted (i.e. rods may not j be withdrawn) until items under Step D.2 have been completed. l l

1

g. Record the following information in the permanent logbook: '

i) time of rundown l 1

ii) type of rundown (e.g. Low CIC Voltage,120% Demand, etc.)

1

2. The SRO on Duty will:

a. Determine (to the extent possible) the cause of the rundown.

b. Initiate corrective actions as necessary.

j c. Record the following information in the pennanent !ogbook:

i) cause of the rundown ii) corrective actions taken iii) SRO " permission granted" to restart Note. In certain instances no corrective action will be necessary, such as a rundown due to an AC power flicker. In these cases log the corrective action as "No corrective action necessary" I d. Permission to restart the reactor must be granted by the SRO on Duty prior to reactor restart. l l

l l

l l

Written By: David Freema Approved By: Albert Bolon "Y

f415 &h hkW

l 1

l i

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 150 TITLE: RESPONSE TO ALARMS Revised: February 21, 1994 Page 4 of 4 E. RESPONSE TO A ROD WITHDRAWAL PROHIBIT ALARM Upon receipt of a ROD WITHDRAWAL PROHIBIT Alarm the operator will:

1. Acknowledge the alarm.

2. Notify the SRO on Duty if the alarm is unexplained or unexpected.

3. Identify and correct the cause of the alarm.

4. Reset the annunciator panel after the cause of the alann has been corrected.

5. The Reactor shall be shutdown if the alarm condition cannot be remedied or if reactor safety is compromised in any way.

F. WHITE LIGHT ANNUNCIATOR ALARM 1

-I Upon receipt of a white light annunciator alarm the operator will:

1. Acknowledge the alarm.

2. Notify the SRO on Duty if the alarm is unexplained or unexpected.

3. Determine and implement further corrective actions as deemed necessary.

4. In the event of a " Basement Sump Level High" alarm, the operator should have the basement area checked for excessive water in the basement. I l

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5. In the event of a " Pool Demineralizer Effluent ConductMeyffigh" alarm the operator should have the demineralizer conductivity checked and a visual check at the demineralizer return line in the pool for potential leaking resins.. If a problem is identified with the Demin system it should be taken off-line and the SRO notified.

6. The reactor shall be sht.tdown if reactor safety is compromised in any way.

Written By: Davi -

. Approved By: Albert Bolon f*$, A' &&N&

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• U51R REACTOR STANDARD OPERATING PROdNDURES *** I SOP: 151 TITLE: RESPONSE TO A HIGH AREA RADIATION ALARM Revised: February 25, 1994 Page1of2 I

A. PURPOSE l

To provide for the proper response to a High Area Radiation Alarm. l l

B. PRECAUTIONS, PREREOUISITES. LIMITATIONS l

1. Personnel in the affected area should evacuate the area and report to the control  !

room. If the Building Evacuation Alarm is sounded, proceed as directed in SOP 501," Building Evacuation Procedure" j

2. The Building Evacuation Alarm may be actuated at any time it is deemed warranted for the protection of personnel within the facility.

C. PROCEDURE 1

1. Upon receiving an unanticipated High Area Radiation Alarm:

a. The Reactor Operator will i) announce the location and indicated dose rate of the affected area.

ii) verify that the reactor rundown has occurred and that rods are inserting.

iii) immediately scram the reactor if personnd or reactor safety is in question.

iv) initiate a building evacuation at any time it is deemed warranted.

b. The SRO on Duty will i) report to the control room for a status report.

Written By: David Fr . Approved By: Albert Bolon D&M

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• UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 151 TITLE: RESPONSE TO A HIGH AREA RADIATION ALAR 31 Revised: February 25, 1994 Page 2 of 2 ii) proceed to the affected area with a survey meter to determine if abnormal radiation levels actually exist.

iii) determine if a building evacuation is necessary.

c. If a Building Evacuation is initiated (either manually or automatically) evacuate the building per SOP 501, " Building Evacuation Procedure"

2. Prior to restarting the reactor, complete the steps listed in SOP 150, " Alarm Responses" Section D, " Rundown Response Procedure"

3. The key-bypass for the High Radiation Area alarm may be used at the discretion of Rev.

the SRO on Duty if all of the following criteria are met:

a. The high dose field is anticipated and explained.

b. The high dose field area access is controlled to prevent personnel overexposure.

c. The dose field in the occupied areas of the building are monitored and found to be less than 5 mrem /hr. This dose rate restrictkn is not intended to apply to facility staff who are cognizant and working in the affected area on a specific task.

d. The dose field outside of the building adjacent to the affected area is surveyed and found to be such that an individual can receive no more than 2 mrem in any one hour period.

e. The key-bypass must be logged into the permanent logbook with the name lRev of the SRO authorizing its use.

k. David FJaema Approved By: Albert Bolon Written By: pro ausk

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** I

SOP

200 TITLE: BRIDGE MOVEMENT PROCEDURE Revised: December 23, 1993 Page 1 of 1 l A. EURPOSE To provide a safe and consistent means to move the reactor Rev.

bridge.

i B. PREC6UTIONS. PREREOUISITES. OR LIMITATIONS

1. When moving the bridge to the T-mode, verify that the new core excess reactivity meets operational requirements, e.g. if the T-mode excess reactivity is greater than 0.7% Ak/k, students will not be allowed to  ;

operate.

2. Move the bridge slowly and carefully to avoid damaging cables or equipment.

3. The bridge normally moves easily and freely. If any binding is observed, check for obstructions.

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B. PROCEDURE I l

1. Request permission to move the reactor bridge from the Senior Reactor Operator on Duty.

Rev.

2. Verify that the reactor is completely shut down.

3. Loosen the manual bridge clamps and carefully move the bridge to the new location.

4. Lock the bridge in the new location by tightening the manual bridge clamps.

5. Reset the bridge motion scram switch.

6. Record the change in core mode (T or W) in the permanent logbook including date and time.

7. Change the core mode display in the control room as l appropriate. l 1

1 Written By: Davi

• man Approved By: Albert Bolon e An

'7p3 At/c $bthu

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 206 TITLE: INSTALLATION AND REMOVAL OF EXPERIMENTAL FACILITIES Issued: May 20, 1993 Page 1 of 2 A. Purpose To provide for safe and efficient installation and removal of experimental facilities in and around the reactor core.

B. Precautions. Prerecuisites. or Limitations

1. The reactor shall be shut down prior to the installation or removal of an experimental facility.

2. The following experimental f acilities are approved for use in the reactor gridplate:

a. Bare Rabbit Facility

b. Cadmium Rabbit Facility

c. Core Access Element

d. Isotope Production Element

, e. Sample Rotor Assembly

' Irradiation Fuel Element f.

3. Installation anc removal of the irradiation fuel element I is to be performed in accordance with SOP 207, " Fuel

< Handling" because it contains U-235 fuel.

4. Reactor Director approval muso be obtained prior to the installation, use or removal of any experimental f acility not listed under Item 2 above.

C. Procedure

1. If the experimental facility is a previously approved facility as listed in Item B.2 above, go to Item C.3 below.

2. If the facility has not been previously approved, obtain approval from the Reactor Director. The Director will determine whether or not the facility represents an

" untried" experiment. If the facility is determined to involve an " untried" experiment, a 10CFRSO.59 review will be required.

3. Obtain permission from the Reactor Manager to install or remove the facility.

(' Written By: David Freeman Approved By: Albert Bolon l

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

I SOP: 206 TITLE: INSTALLATION AND REMOVAL OF EXPERIMENTAL FACILITIES Issued: May 20, 1993 Page 2 of 2

4. If the installation or removal of the facility (or f acilities) will be temporary (e.g. removal of a f acility for maintenance), no reactivity measurements will be required provided the original configuration of experimental facilities is re-installed prior to any reactor operations.

5. If the reactor is to be operated af ter the configuration of experimental facilities has been changed, the reactivity worth of the change must be measured. If the change results in a reactivity swing of more than 0.2%

Ak/k, measure excess reactivity in both the W and T modes.

l 6. With the reactor shut down, install and/or remove the l approved experimental facility carefully, under the direct supervision of an SRO.

7. Update the control room data as appropriate.

8. Enter the installation and/or removal of the experimental facilities in the control room permanent logbook.

Written By: David Freeman Approved By: Albert Bolon O

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE. E31ERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Complete Revision. February 21, 1994 Page 1 of 7 A. PURPOSE To provide for the safe and orderly evacuation of the Reactor Building.

B. PRECAUTIONS. PREREOUISITES. OR LDIITATIONS

1. This procedure is not intended to be all encompassing. Personnel may deviate from this procedure as needed to maintain safety. Strong reliance is placed upon the good judgement of operating personnel.

2. Any person may manually initiate the evacuation alarm if it is believed conditions merit such action.

3. The Reactor Manager, Reactor Director, or a Licensed Operator, may silence the evacuation alarm and rescind the evacuation by building announcement if it is determined that the evacuation is unwarranted.

i  ;

4. Upon sounding of the Building Evacuation Alarm, all personnel except for the  !

Reactor Operator and the Senior Operator on Duty will proceed directly and calmly to the Physics Building basement area and remain in this area for further instructions.

5. Persons providing escort for visitors are responsible for the safe evacuation of their visitors and for obtaining the Visitor's Logbook from the front office upon exiting the facility.

6. All persons must remain calm and orderly.

C. EVACUATION PROCEDURE Upon sounding of the Evacuation Alarm: l L REACTOR OPERATOR The Reactor Operator will obtain the " REACTOR OPERATOR EVACUATION CHECKLIST" and follow the steps therein. If the reactor is shut down at the time r

Written By: David Freeman Approved 'By: Albert Bolon

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• " UhlR IGACTOR STANDARD OPERATING PROCEDURES ***

! SOP: 501 TITLE: E31ERGENCY PROCEDURES FOR REACTOR l BUILDING EVACUATION Complete Revision: February 21, 1994 Page 2 of 7 i

, of alarm, the REACTOR OPERATOR EVACUATION CHECKLIST need not be completed. Proper actions for each step in the checklist are described below: j

1. SCRA31 REACTOR

The operator will promptly scram the reactor.

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} 2. VERIFY ROD INSERTION: Verify that the shim rods have inserted (audibly, visually, or by observing the magnet contact lights and magnet currents). Verify power is decreasing appropriately.. j l

3. SECURE SIAGNET KEY: Remove the key from the console and maintain  ;

possession of the key. l

4. ANNOUNCE FACILITY STATUS: Announce the status of the facility over the building PA. State the cause of the alarm and areas of the building to avoid as necessary.

5. RECORD TDIE: Record the console clock time.

6. WAIT IN CONTROL ROO31 FOR SRO: Remain in the control room (or l control room area) for the SRO on Duty, if possible. Repon facility status to i the SRO on Duty upon his arrival. The SRO on Duty may instmet the l operator to proceed differently from the items listed in the checklist. l

7. OBTAIN PERMANENT LOGBOOIUSIETERS: Obtain the console i I

permanent logbook. Obtain survey meters and pocket dosimeters, if convenient.

8. VENT FANS OFF: Verify that a'll three exhaust vent fans are ofE

9. OBTAIN E31ERGENCY KEYS: Obtain the emergency key box. If the key box is not in its usual location, assume someone else has already obtained it.

10. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Leave the facility and proceed directly to the designated Physics Building basement area.

Written By: David Fr in Approved By: Albert Bolon si& N'W QQhw

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: E31ERGENCY PROCEDURES FOR REACTOR )

BUILDING EVACUATION Complete Revision: February 21, 1994 Page 3 of 7 II. SENIOR OPERATOR ON DUTY The Senior Operator on Duty will obtain the SRO EVACUATION CHECKLIST and follow the steps therein. Proper actions for each step are listed below:

1. PROCEED TO CONTROL ROO31: Proceed directly to the control room for a status report from the Reactor Operator.

2. RECEIVE OPERATOR'S REPORT: Determine the facility status from the Reactor Operator.

4

3. OBTAIN SURVEY INSTRUSIENTS: Obtain survey instruments and dosimeters, if possible.

4. VENT FANS OFF; Verify that all three exhaust vent fans are ofE

- 5. ALL PERSONNEL EVACUATED: Verify that all personnel have left the ,

building. I

6. ENIERGENCY KEYS OBTAINED: Obtain emergency key box upon exiting the building. If the key box is not in its usual location, assume the key .

box has already been obtained.

4

7. PROCEED TO PHYSICS BUILDING BASESIENT AREA: Proceed directly to the Physics Building basement area.

HI. Upon arriving at the Physics Building basement area the SRO on Duty will:

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1. Account for all personnel known to have been in the facility. Record the l names of each individual evacuated.

2. Receive reports from personnel on the facility status, as necessary.

Notify the Reactor Manager, Reactor Director, and Campus Health Physicist l 3.

as appropriate. Use the Emergency Phone List as needed.

)

Written By: David Fre Approved By: Albert Bolon 7 2 xua gabW 1

• • • UMR REACTOR STANT)ARD OPERATING PROCEDURES ***

SOP: 501 TITLE: E31ERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Complete Revision: February 21, 1994 Page 4 of 7

4. If personal contamination is possible, frisk each person evacuated fcr contannnation. Isolate contaminated person (s)in the emergency shower area.  ;

1

5. Implement the following procedures as necessary:

e SOP 502 " Emergency Procedure For An Unusual Event" e SOP 503 " Emergency Procedure For An Alert" l e SOP 504 " Emergency Procedure For A Site Area Emergency" l

• SOP 507 " Administrative Responsibilities" e SOP 601 " Decontamination Procedure" i

• SOP 602 " Handling Injured In Radiation Accidents" i

• SOP 603 " Guidelines For Emergency Exposure"

• SOP 605 " Entry Into A High Radiation Area"

6. Take other actions as deemed appropriate.

D. END OF E3IERGENCY, REENTRY, AND RECOVERY

1. In the event that an emergency status is declared (i.e. Unusual Event, Alert, or Site Area Emergency), the Reactor Director or the Reactor Manager and the Radiation Safety Otlicer shall decide when the emergency no longer exists and an "end of emergency" will be declared.

2. Recovery from emergency conditions will be instituted at the highest organizational level activated during the emergency. Procedures will be written, as needed, to recover from the emergency.

3. Personnel approaching the facility for reentry will report to the Emergency Support Center if radiation levels in excess of 100 mrem /hr are encountered.

1 Written By: David Fr Approved By: Albert Bolon f V II (k h F

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

' SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Complete Revision: February 2.1, 1994 Page 5 of 7

- REACTOR OPERATOR -

EVACUATION CHECKLIST

1. SCRAM REACTOR

2. VERIFY ROD INSERTION

3. SECURE MAGNET KEY

4. ANNOUNCE FACILITY STATUS l ._ 5. RECORD TIME

!I.

l 6. WAIT IN CONTROL ROOM FOR SRO l

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7. OBTAIN PERMANENT LOGBOOK / METERS

8. TURN VENT FANS OFF

9. OBTAIN EMERGENCY KEYS

10. PROCEED TO PHYSICS BUILDING BASEMENT AREA _

Written By: DavidEreeman Approved By: Albert Bolon ftY6'i8 } LW

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• UMR RE ACTOR STANDARD OPERATING PROCEDURES **

• l SOP: 501 TITLE: ESIERGENCY PROCEDURES FOR REACTOR I BUILDING EVACUATION Complete Revision: February 21, 1994 Page 6 of 7

- SRO -

1 l

] EVACUATION CHECKLIST l I. IbMEDIATE ACTIONS 1

1. PROCEED TO CONTROL ROOM

2. RECEIVE OPERATOR'S REPORT l i

3. OBTAIN SURVEY INSTRUMENTS J

4. VENT FANS OFF 1

j 5. ALL PERSONNEL EVACUATED 1

6. EMERGENCY KEYS OBTAINED i l

7. PROCEED TO PHYSICS BUIIDING l

{ II. SUPPLEMENTAL ACTIONS  ;

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1. PERSONNEL ACCOUNTABILITY:

1 A. Have all Personnel Evacuated Building?

Yes No l l B. List names of each individual evacuated from l building:

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2. REFER TO SOP 501 SECTION C.III FOR FURTHER

INSTRUCTION.

1 e

4 Written By: David eem Albert Bolon i p,..o/'a Approved By: yg4~

• • • UMR REACTOB51MNDWRIEOMRATING. PRO ~CEDURES ooo SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Complete Revision: February 21, 1994 Page 7 of 7 I

UMR RE ACTOR EMERGENCY PHONE LIST j Reactor Staff HOME WORK David Freeman, Mgr., SRO 364 7269 341 4384 William Bonzer, Sr. El. Tech 368-3727 341-4384 Albe-: Bolon, Dir., SRO 364-1961 341 4746 Matt McLaughlin, SRO 368-3908 341-6552 l Hatem Khouaja, RO 341-3857 341-6551 Shahla Keys an, RO 341-2206 341 4748 C arl Barton, S r. El. Tech. 341-2951 341 4384 Juls Williams, Lab Mech. 674-2874 341 4236 Ray Bono, Health Physicist 364 5728 341 4240.4305.4480 Linda Pierce. Sr Sec 265-3738 34l 4236 i University Administrative Staff

1. Chancellor, John Park 341-4118 364-6455 341 4114

2. Vice Chancellor Admin. Senices,Neil Smith 364-7123 341 412i

3. Director, UMR Police, William Blectanan 364-1294 341 4345

4. Director of Student Activities, Lou Moss 364-1654 341 4208 5 Director, Physical Plant, Marvin Patton 364-6278 341 4252

6. Director, Health Service - Infirmary, Dv,ight

Deardeuff,

MD 364-0809 34l 4284

7. Dean, School of Mines and Metallurgy, Lee W. Saperstein 368-3782 341 4153

' 341-3595 341-4745 8 Radiation Safetv Officer. Nick Tsoulfanidis Locat j l

UMR Umversity Pc tice 341 4300 34l 4111 Rolla City Police 9-91i Rolla Fire Departmen- 9-911 Phelps County Hospiti.1 9-911 Rolla Emereencv Man:nement Acency (Answered bv Police Deot wherLgjosed) 364-1213 State Acencies Missoun Highway Patrol 363-2345 Missouri State Emergency Mgt. Agency (24 hr.) (314) 751-2748 Missouri Dept. of Natural Resources (24 hr ) (314) 634-2436 Missouri Bureau of Radioloeical Health (314) 751 6083 ,,

Federal Acencies NRC, Glen Ellyn, IL, Region In 1 800-522 3025 NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 951-0550 (951-1212. 95 l-6000. 951-6100. 427-4056. 427 4259. 492-8893)

Other American Nuclear Insurers (203) 561-3433 Radiation Emergency Assistance Center (615) 576-3131 (615) 48 l-1000 (24 hrs) -

Revised 02/16/94 l

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Written By: frd d eema Approved By: Albert Bolon

/a5 Y QQ 00w J

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERDIENTS Revised: March 30, 1994 Page1of7 A. PURPOSE To provide for a safe and consistent method for the insertion and removal of experiments in or near the reactor core.

B. PRECAUTIONS PREREOUISITES. ORLDIITATIONS

1. This procedure details the insertion and removal of the following types of experiments:

a. Rabbit Facility Irradiations,

b. Wire, Foil, and Vial Stringer Irradiations,

c. Void Tube Irradiations.

2. Insertion or removal of any other apparatus, device, or materialin or near the core which could conceivably have a reactivity effect on the core (and which is not itself a core component or experimental facility) shall be performed in accordance with written procedures approved by the Reactor Manager or Director. Such procedures will be developed on a case-by-case basis. These experiments will be reviewed by the reactor staff to assure compliance with Technical Specification 3.7 and 4.7. I

3. Untried experiments will be reviewed and approved by the Reactor staff and will '

then be forwarded to the RSC for review and approval.

4. Experiments to be run in the beamport or thermal column are addressed in SOP 711 and SOP 712.

5. Experiments may be insened or removed from the core or core region only under the direction of the Reactor Operator while the reactor is in operation and only under the direction of a Licensed Operator when the reactor is shutdown.

6. The Reactor Operator shall be alert for any abnormal or unanticipated changes in reactivity or reactor status upon insertion or removal of any experiment while the reactor is operating. The reactor shall be immediately shut down if any abnormal Written By: David W. Freeman Approved By: Albert E. Bolon

all & hL.Y.bb

• " UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERDIENTS Revised: March 30, 1994 Page 2 of 7 l

or unanticipated changes in reactivity are obsened or if any unsafe condition is obsen ed.

7. An approve d IRF (SOP 702) is required prior to rabbit facility, wire stringer, foil stringer, o" vial stringer irradiations. The void tube does not require an IRF.

8. The Reactor Operator is responsible for verifying that the experiment has a valid IRF with the appropriate review and approval signatures. The Reactor Operator is responsible for verifying that the proposed experiment meets the requirements (e.g.

irradiation time, power level, location, special instructions, etc.) of the IRF.

C. RABBIT FACILITY: INSERTION AND REMOVAL PROCEDURE I

1. Rabbit System Setup: l

.. j

a. Fully open the nitrogen gas bottle. Normally the gas tank pressure should )

read about 500 psi and the system pressure should be set between about 40 l to 60 psi. I

b. Turn on the rabbit system drawer by setting the selector switch to "I Cycle"

c. Set the rabbit controls to the desired settings.

Typical settings are: -

Irradiate Time: as desired in seconds Tube Selector Switch: as desired (bare or cad)

Transit to Detector: 0.5 sec 1 Transit to Target: 0.5 sec j Delay To Count: 0.3 see Count Cycles: 1 l Channel: 1 Count: 55 sec

d. Insert the rabbit vial into the desired rabbit tube inside of the glovebox.

e. Communicate to the Reactor Operator that the rabbit is loaded and ready to irradiate.

Written By: David W. Freeman Approved By: Albert E. Bolon uk,a hU$,bW

_ _ _ _ _ _ - - _ - - _ - _ - _ _ i

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND RE310 VAL OF EXPERDIENTS Revised: March 30, 1994 Page 3 of 7 l

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2. Reactor Operator- Sample Irradiation And llandling - The Reactor Operator (or his designee) will perform the following steps:

a. Irradiate Sample - Fire the rabbit vial into the core by pressing the

" OPERATE" button on the Rabbit Controller.

b. Record Logs - Record the appropriate information in the permanent logbook using the Sample Experiment Stamp ( See SOP 106) and on the IRF Form (SOP 702).

c. Sample Return  ;

I (1) be cognizant of the approximate end time of the irradiation. Be alert to the possibility of a system failure causing the rabbit to be significantly over-irradiated. l (2) watch for the experimenter's " thumbs-up" signal verifying that the )

sample has returned and that dose rate outside of the glovebox has been measured and found to be less than 10 mrem /hr.

(3) If the dose rate outside of the glovebox is 100 mrem /hr or more, shoot the sample back into the core and turn the rabbit system ofE i The reactor should then be shutdown. Notify the SRO on Duty. l After a sufficient decay time, as determined by the SRO on Duty,  !

l the sample may be brought back to the glovebox and radiation levels rechecked. ,

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3. Experimenter - Sample Handling - Upon return of the rabbit vial to the glove I box the experimenter will:

a. Measure Ambient Dose Rate - Measure the ambient dose rate outside of l the closed glove box: l (1) If the dose rate exceeds 100 mrem /hr the experimenter is to remove l personnel from the glovebox area and notify the Reactor Operator immediately. l (2) If the dose rate is between 10 mrem /hr and 100 mrem /hr, notify the Reactor Operator immediately for further instmetions.

b. Remove Vial From Tube -If the dose rate measured outside the glove '

box is less than 10 mrihr, the vial may be removed from the rabbit tube to the glove box floor.

Written By: David eeman Approved By: Albert E. Bolon

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• • • Uh1R REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND RDIOVAL OF EXPERDIENTS I

Revised: March 30, 1994 Page 4 of 7 l

c. Notify Reactor Operator - Give the Reactor Operator a " thumbs up"

! signal to signify that the rabbit has returned and that the dose rate is less than 10 mr/hr.

d. Report 1 Foot Dose Rate - Remove the rabbit vial from the glove box and measure the dose rate at a distance of one foot from the sample. Report the measured dose rate to the Control Room.

l D. STRINGER IRRADIATION (WIRE. FOIL. OR VIALh INSERTION AND REMOVAL PROCEDURE 1, A sample may be irradiated on a stringer inside of a closed vial at the core periphery. The sample must not restrict coolant flow through the fuel plates.

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2. Wires or fot!s may be irradiated on a stringer between fuel plates, between fuel elements, ar.d at the core periphery. The sample or the stringer must not restrict

^ coolant flow or damage the fuel plates.

3. Insertion of Stringer- Reactor Operating

a. Immediately prior to inserting the stringer, the expe.rimenter shall request permission from the Reactor Operator to insert the stnnger into a particular location. Example: " Request permission to insert stringer into Grid Position C8"

b. The experimenter shall receive the operator's verbal approval immediately prior to beginning the insertion.

c. As the stringer comes within about 5 feet of the core, the experimenter should announce: " Approaching the core"

d. The experimenter should slowly insert the stringer into the appropriate location.

e. Once the stringer is seated, the experimenter should announce " Stringer Seated"

f. The operator should record the location and time in the permanent logbook using the Sample Experiment Stamp and on the appropriate IRF.

Written By: David W. an Approved By: Albert E. Bolon fadb,E"' d( h W,h b

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"* UMR REACTOR STANDARD OPERATING PROCEDUKtS ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERDIENTS Revised: March 30, 1994 Page 5 of 7

4. Removal of Stringer - Reactor Operating 1

i a. Immediately prior to removing the stringer, the experimenter shall request permission to remove the stringer from a particular location. Example:

" Request permission to remove stringer from Grid Position C8"

b. The experimenter shall receive the operator's verbal approval immediately prior to beginning the removal.

c. The experimenter shall remove the stringer slowly being alert to any signs ,

of sticking or other complications,

d. ARer the stringer is withdrawn from the core region, the experimenter 4 should announce: " Stringer Clear"

e. The operator should record the time in the permanent logbook and the  ;

appropriate IRF. l l f. If the stringer is to be hung in the pool for decay it should be labeled with a

} radioactive materials tag specifying the experiment's name, type of material,

date and time ofirradiation, and the IRF number.

g. Sample Handling - Upon removal of the stringer from the pool, measure

~

the 1 foot dose rate and record on the IRF form. Handle the sample per i SOP 606. l

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5. Insertion and Removal of Stringer- Reactor Shutdown l a. A stringer sample rnay be inserted into the core region when the reactor is shut down under the direction of a Licensed Operator.

b. A note should be placed on the console alerting the operator to the stringer i location, IRF number and desired irradiation conditions.

l c. Prior to reactor startup, the Reactor Operator will visually inspect the l

. stringer for proper positioning. l

d. The stringer may be removed from the core regiori with the reactor shut l

! down only under the direction of a Licensed Operator. I

e. If the stringer is to be hung in the pool for decay it should be labeled with a l radioactive materials tag specifying the experiment's name, type of material, date and time ofirradiation, and the IRF number.

f. Sample Handling - Upon removal of the stringer from the pool, measure the 1 foot dose rate and record on the IRF form. Handle the sample per SOP 606.

Written By: David W.fF n Approved By: Albert E. Bolon

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

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I "* Uh1R REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERDIENTS I Revised: March 30, 1994 Page 6 of 7 E. VOID TUBE: INSERTION AND REMOVAL PROCEDURE

1. The void tube may be inserted or removed from the core region while the reactor is operating ifit is completely water filled.

2.. The reactor must be shutdown by at least 1% delta-k/k prior to insertion or removal of the air-filled void tube.

3. The void tube may be inserted or removed from the core region with the reactor operating when it is partially filled with water only with the express permission of either the Reactor Manager or Director.

4. The reactor should not be operated at a power in excess of 200 Watts with the void tube inserted unless permission has been granted by either the Reactor Manager or Director.

. 5. Insertion of Void Tube Into Core Periphery Location j a. Immediately prior to inserting or removing the void tube, the experimenter shall request permission from the Reactor Operator to insert the void tube into a particular location. Example: " Request permission to insert void tube into Grid Position C8".

b. The experimenter shall receive the operator's verbal approval prior to beginning the insertion.

c. As the void tube comes within about 5 feet of the core, the experimenter should announce: " Approaching the core" l d. The expuimenter should approach the core from the front and center of the gridf ate with the bottom of the void tube barely above gridplate level.

e. The expe imenter should seat the voide m thuppropriate gridplate location.

f. Once the void tube is seated, announce " Void Tube Seated".

g. The operator shall record the location and time in the permanent logbook.

l l

l l

. Approved By: Albert E. Bolon Written By: David K'<FTEEm ahhot * $6Lbk.$tn l

l

l l

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERLTIENTS Resised: March 30, 1994 Page 7 of 7 l

I l

6. Removal Of the Void Tube from the Core Periphery l

a. Immediately prior to removing the void tube, the experimenter shall request i permission from the Reactor Operator to remove the void tube from a particular location. Example: " Request permission to remove void tube I

from Grid Position C8".

b. The experimenter shall receive the operator's verbal approval prior to ,

removing the void tube. )

c. After permission has been granted and immediately prior to removing the l void tube, the experimenter should announce " Removing void tube from core" l

d. The experimenter should slowly remove the void tube from the gridplate while being alert for signs of sticking or mbbing against the fuel elements.

The void tube should be moved from the core region to the front of the

]

gridplate keeping it barely above gridplate level. I i

e. Once the void tube is removed approximately 5 feet from the core the experimenter should announce " Void Tube Clear"

f. The operator shall record the movement in the permanent logbook.

7. Post Irradiation llandling of the Void Tube.

I

a. Hang the void tube in the pool for decay prior to handling. Assure that it is labeled with a radioactive materials tag.

b. When removing the void tube from the pool follow SOP 606, -

l l

l l

l l

l David )ptWt an Approved By: Albert E. Bolon I Written By:f" hO &fp_h.fW 1

i

• " UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SE31I-ANNUAL CHECKLIST Revised: April 4, 1994 Page 1 of 7 Date Commenced Date Completed Total Hours on Hour Meter

1. Log N and Period Channel Initial

a. Log N Power Supply Date (1) Cleaned chassis as needed

b. Log N Recorder Date (1) Cleaned chassis as needed

c. Log N Detector Date Resistance (ohms)

(1) Signal to ground (approximately 10t ohms)

(2) Positive to ground (approximately 10'* ohms)

(3) Negative to ground (approximately 10 ohms)

d. Log N. Calibration Date (Note: The ratio of expected-to-observed readings should be between 0.7 and 1.4.

The 5x10'"A recorder reading will have a ratio between 0.4 and 2.0.)

Tme Expected PicoAmperg Readings Recorder Meter Initial 5.0x10" A 100 kW 5.0x104 A 10 kW 5.0x10# A 1 kW 5.0x10~8A 0. I kW 5.0x104 A .01 kW 5.0x10 ' A .001 kW 5.0x1 l'" A .0001 kW Written By: William Bonzer Approved By: Albert Bolon Wb$m , $N '

l l

"* UMR REACTOR ETANDARD OPERATING PROCEDURES ***

SOP

800 Title. SEMI-ANNUAL CHECKLIST l Revised: April 4, 1994 Page 2 of 7 1

I l 1. Log N and Period Channel (cont.) Initial l e. Reconnect all cables Reconnection of cables verified

f. Period Recorder Date l

(1) Cleaned chassis as needed i

l 2. Linear Power Channel l a. Linear Power Supply Date l

i (1) Cleaned chassis as needed

b. Linear Recorder L at e___ l l

(1) Cleaned Chassis b c. Linear Calibration (cont.) Date  ;

4 (Note: From 10'5 to 10 , the overall accuracy should be better than 2% of full scale. l From 104to 10' the overall accuracy should be better than 4%. Any l instatment found to be out of calibration should be realigned in accordance l l with procedures.)  !

---

METER-- - ------RE C O RD ER------

! PicoAmp Acceptable Actual Acceptable Actual l

Generator Reading Reading Reading Reading Initial 6.0x10'5A (57 A-63pA) (57W63%)

l 6.0x104 A (5.7 A-6.3 A) (57%-63%)

6.0x104 A (570nA-630nA) (57%-63%)

6.0x10d A (57nA-63nA) (57%-63%)

i 6.0x10*A (5.3 nA-66nA) (53 S 66 % )

6.0x10 A (530pA-660pA) (53%66%) ,

2.0x10 ' A (130p A-260p A) (13%26%)

! Written By: William Bonzer Approved By: Albert Bolon ldUh5 )

• • • UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST l Revised: Apri1 4, 1994 Page 3 of 7 I l

l

2. Linear Power Channel (cont.)

d. Linear CIC Detector Date Resistance (ohms) Initial t

(1) Signal to ground (approximately 10 ohms) t (2) Positive to ground (approximately 10 " ohms)

(3) Negative to ground (approximately lot ohms)

e. Reconnect all cables Reconnection of cables verified

3. Log Count Rate Channel

a. Log Count Rate Recorder Date (1) Cleaned chassis as needed

b. Fission Chamber Preamp Date (1) Cleaned chassis as needed (2) Additional Comments

c. Log Count Rate Channel Calibration Date (Note: All readings should give 0.7 to 1.4 ratio of true-to-observed readings )

P_ulse Generator Meter Bacorder 10 1DD 1.000 10.000 I

d. Reconnect all cables Reconnection of cables verified ,

1 Written By: William Bonzer Approved By: Albert Bolon l U.)h2m $U- 5

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SE311-ANNUAL CHECKLIST Resised: Apri1 4, 1994 Page 4 of 7

4. Safety Channels laitial

a. Safety Preamp Date (1) Cleaned chassis as needed

b. Safety Detector #1 Date Resistance (1) Signal to ground (approximately 10" ohms)

(2) . Positive to ground (approximately 10" ohms)

(3) Additional Comments

c. Safety Detector #2 Date ,

Resistance l (1) Signal to ground (approximately 10" ohms) l l

5 (2) Positive to ground (approximately 10 ohms) l

~

l (3) Additional comments l l

d. Safety Amplifier Date (1) Cleaned chassis as needed

e. Safety Amplifier Adjustments

f. Reconnect all cables Reconnection of cables verified

5. PAT 60 Controller

a. PAT 60 Date (1) Cleaned chassis as needed

b. Check dial settings and record the following l (1) Approach l (2) Proportional Bank l (3) Rate Time l (4) Reset l (5) Gain (if applicable) t I

l Written By: William Bonzer Approved By: Albert Bolo N UEek y> $ \%

L - - --

a ..~.. .s.-u 1.~ =..w,-n.. .. - - -. a r - - - - . . - ~ .- -, - . . .

h i

l *** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST i Revised: April 4, 1994 Page 5 of 7 J

Re

6. Temperature Channel 1 (Note

All readings should be 1 F.)

j a. Verification of Temperature Readings -

4 i

i u s u e

2 u e a i:

e c. a u M p u a O O O

O O i 0 0 0 C) O H d E: O H E O H E O i Temperature Range y g j j y 3 y j 'd

," " g y ."

(Take one reading from each, y y g y .

g temperature range) g g $ g g $ g $

i 60* F-70

• F 70

• F-80

• F f 80*F-90 F l 90* F-125

• F

]

j 125

• F-13 5

• F s

135*F-145 F l

b. Temperature > 135* Rod Withdrawal Prohibit Test t

Thermocouple #1 Thermocouple #3 f

>135'F Trip Temperature 4

! >135*F Annunciator t

i Audible Alarm Rod Prohibit Withdrawal l

' l Initials

, i i

1 1

I J J

$ Written By: William Bonzer Approved By: Albert Bolo <

bil$w6 kewg b m

• UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Revised: Apri1 4, 1994 Page 6 of 7

7. Regulated Power Supply Date Iruttal

a. Cleaned chassis as needed

b. Additional coniments

8. Conductivity Bridge Date

a. Cleaned chassis as needed

b. Additional comments

9. Rod Indicator Calibration Date ,

Actr Height Rod

• Rod 2 Rod 3 Reg. Rod

, 12 ",,

ig

~

24" _

10. Fire Alarm Check Date

a. Cleaned system containers as needed

b. Checked batteries

c. Checked pull stations

d. Checked heat detectors

e. Checked smoke detectors

f. All indicator lamps operate

11. Security System Check Date Initial

a. Door Sensors

b. Motion Detectors _

c. Tamper Switch

d. Duress Alarm

e. Battery Date

f. Additional Comments Written By: William Bonzer Approved By: Albert Bolon Yf % W ~

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SE311-ANNUAL CHECKLIST Revised: April 4, 1994 Page 7 of 7

12. Public Address System Date a

a. Cleaned chassis as needed ,

b. Additional Comments -

13. Area Radiation Monitor Date <

a. Cleaned chassis as needed

b. Additional Comments

14. Portal Detector Date -

a. Cleaned chassis as needed

b. Perform Source Check

c. Additional Comments

15. Constant Air Monitor Date

a. Cleaned chassis and recorder as needed

b. Perform Source Check

c. Additional Comments Date 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 Written By: William Bonzer Approved By: Albert Bolon Ud.An g b

• • • UMR REACTOR STANIMRD OPERATING PROCEDURES ***

SOP: 806 TITLE: TE31PERATURE CHANNEL Complete Resision: April 4, 1994 Page 1 of 2 A. PURPOSE To provide for the consistent method of checking the calibration of the Temperature Recorder.

B. ERECAUTIONS. PREREOUISITES AND LI31ITATIONS

1. Prior to removing or installing reactor thermocouples, permission must be obtained from the SRO on Duty.

2. Record removal or installation of reactor thermocouples in the permanent logbook.

C. PROCEDURE

1. Document each of the following steps in Section 6, " Temperature Channel" of the Semi-Annual Checklist (SOP 800). As each equipment is checked or calibrated, it shall be checked off on th e check list to serve as a record of the date that the item was completed.

2. Verification of temperature readings

a. Remove inlet thermocouple #1, outlet thermocouple #2, and inlet thermocouple #3 fram the po31. Check the dose rate of each thermocouple as it is removed from the pool

b. Place thermocouple (s) in a water bath with a thermometer that meets NIST specifications. This step may be performed with more than one thermocouple at a time. Adjust the temperature of the water bath from about 60*F to about 145 F. Record one simultaneous reading of the thermometer and the thermocouple for each of the following temperature groups:

60

• F-70 *F 70

• F-80

• F 80* F-90

• F 90

• F-125

• F 125'F-135 F 135*F-145 F Written By: Da"i r n Approved By: Albert Bolon f' Y$ &\ 0 hun n

• • • UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 806 TITLE: TE31PERATURE CIIANNEL Complete Revision: April 4, 1994 Page 2 of 2

c. Record the results on the Semi-Annual Checklist.

3. Temperature >135* F Rod Withdrawal Prohibit Test

a. Place inlet thermocouple #1 into the water bath.

b. Adjust the temperature of the water bath to below about 125 F.

c. Have a Licensed Operator energize the console and clear the rod withdrawal prohibits.

d. Verify that rods can be withdrawn. Do not raise rods above 3 inches.

e. Slowly raise the temperature of the bath until the Temperature >135

• F trip is received. Verify that the trip occurred at a temperature less than or equal to 135 F.

f. Log the temperature displayed on the recorder for thermocouple #1 on the semi-annual checidist.

g. Verify that the Temperature >135*F audible alarm is activated.

h. Verify that the Temperature >l35 F annunciator is illuminated.

i. Attempt to withdraw rods.

j. Venfy that rods do not withdraw.

k. Remove inlet thermocouple #1 from the water bath.

1. Reset the annunciator.

m. Repeat steps a-1 for inlet thermocouple #3.

4. FLNAL ASSENIBLY

a. Install #1, #2, and #3 thermocouples into the pool.

b. Check all wiring connections at the bridge thermocouple connector box. ~

Verify that each thermocouple is reading a reasonable ulue.

c. A second knowledgeable person will verify each connection to ensure that the Temperature Channelis properly connected and on line.

Written By: David F - an Approved By: Albert Bolon

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 1 of 14 A. PURPOSE

~

To ensure the proper operation of the control and safety-related instruments of the reactor and to functionally test the Physical Security Alarm System.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. The Weekly Check should be completed on the first working day of each week the reactor is to be operated.

2. The security system and pool conductivity must be checked weekly. The remaining portion of the checklist may be omitted if the reactor will not be operated that week.

3. The weekly check should be performed by a licensed operator, or a student under the direct supervision of k a licensed operator

4. Complete the Weekly Surveillance Checklist form (Form SOP 810), and forward it to the Reactor Manager (or Director) for review and signature. Any abnormalities, problems, or out of service equipment should be brought to the attention of the Reactor Manager (or Director).

C. PROCEDURE Select the Reactor Bridge Station on the Building Intercom, check the PA system, install the neutron source, turn on all 5 primary recorders (date the recorders), turn on core camera and select core on the monitor selector. Obtain Magnet Power Key and turn on magnet power.

1. ROD WITHDRAW PROHIBIT (vellow lichts):

A. Recorders off ... the rods will not withdraw if any one of 5 primary recorders is turned off.

1. Turn off LCR recorder.

2. Attempt to withdraw rods.

3. Turn on LCR recorder, reset alarm.

4. Turn off linear level recorder.

5. Attempt to withdraw rods.

Written By: David neman Approved By: Albert Bolon fcikA#' (Nh M h

• ** UMR REACTOR STANDARD OPERATING PROCEDURES * *

• SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 2 of 14

6. Turn on linear level recorder, reset alarm.

7. Turn off period recorder.

8. Attempt to withdraw rods.

9. Turn on period recorder, reset alarm.

10. Turn off log N recorder.

11. Attempt to withdraw rods. .

12. Turn on Log N recorder, reset alarm

13. Turn off temperature recorder. .

14. Attempt to withdraw rods.

15. Turn on temperature recorder, reset alarm.

B. Log Count Rate < 2 CPS.

1. Remove source from holder and/or withdraw fission chamber until LCR reads <2 CPS.

Record value at which alarm occurs from recorder.

2. Attempt to withdraw rods.

3. Insert source and/or insert the fission chamber to the insert limit. Reset annunciator.

C. Period < 30 Seconds

1. Depress " Test Trip" switch on Log N & Period Amplifier and adjust for a period < 30 seconds. Record value at which alarm occurs on the recorder.

2. Attempt to withdraw rods.

3. Release test switch, reset alarm.

D. Inlet Temperature Above 135 Degrees

1. With recorder on, remove back cover and manu-ally rotate potentiometer arm until alarm ~

occurs, record trip point.

2. Acknowledge alarm and attempt to withdraw rods.

3. Reset alarm cn temp. recorder, reset alarm on console.

E. Shim Rods Below Shim Range i

Written By: David man Approved By: Albert Bolon h

~ .

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK

Revised

November 12, 1993 Page 3 of 14

1. With all Shim / Safety rods below shim range attempt to withdraw the regulating rod. Note ,

that the regulating rod will withdraw just c

, far enough to clear the insert limit light.

Attempt to withdraw the Shim / Safety rods.

Note that further withdrawal cannot be made.

Insert all control rods to the insert limit and record these results.

2. RUNDOWN CHECK (blue lichts):

A. Radiation Area Monitoring (RAM) System

1. Withdraw rods to 3 inches.

2. Announce "The Building Alarm will sound.

This is a test do not evacuate the building."

on the Building PA System.

3. Using RAM check source switch #1. Note the value at which alarm (s) occurs. Check the automatic reset of the F)JI, reset the -

Building Alarm, (Scram Reset Button),

acknowledge annunciator Rundown Reset and Annunciator Reset. Record value of alarms.

4. Repeat step 3 for RAMS #2 and #3.

5. All alarms values shall be < 20 mr/hr.

6. Upon completion of testing announce " Test Complete. Acknowledge all further alarms,"

on the building PA system.

B. 120% Demand

1. Withdraw rods to 3 inches.

2. De-energize (Linear, Period or Log N) recorder. (Switch to off.)

3. Remove Linear Channel potentiometer cover and manually rotate potentiometer arm, note recorder reading when trip point is reached.

4. When inward motion of rods is verified, lower recorder below reset point, reset the rundown and all alarms, turn recorder on and replace cover, compare actual and specified trip points.

5. Record trip point value.

Written By: Day 1 r man Approved By: Albert Bolon f W$ "" QQ Q

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 4 of 14 C. Period < 15 Seconds

1. Repeat steps 1 through 5 of 2.B for the Period recorder.

D. 120% Full Power

1. Repeat steps 1 through 5 of 2.B for the Log N Recorder.

E. Low CIC Voltage Linear Power Supply

1. Withdraw rods to 3 inches.

2. Push and hold alarm test button on Linear CIC Power Supply. Observe High Voltage meter and record the value when the under voltage alarm light comes on. Release the test button.

3. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown in pro-gress).

_ 4. When the High Voltage on the Linear CIC Power Supply has increased to approximately 500 volts push alarm reset. The under voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and the annunciator.

5. Record value of the trip point.

F. Low CIC Voltage Log N Power Supply

1. Withdraw the rods to 3 inches.

2. Push and hold alarm test button on the Log N CIC power supply. Observe the high voltage meter and record the value when the under voltage alarm light comes on. Release the test button.

3. Acknowledge the annunciator alarm and observe the Low CIC Voltage annunciator light (also check for s 5 sec. period, s 15 sec. period,

< 12 sec. period, and 150% full power).

Reset the period trip light on the Log N &

Period Amplifier. This allows for reset of all annunciator lights except low CIC Written By: David'Freb an Approved By: Albert Bolon fd N &WYC

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 5 of 14 voltage.

4. When the High Voltage on the Log N CIC power supply has increased to approximately 500V, push alarm reset. The voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and reset the annunciator.

5. Record value of trip point.

G. Regulating Rod on Insert Limit on Auto

1. Withdraw the Shim / Safety rods to 3 inches and Reg Rod to 0.5 inches (use the shim range bypass).

2. Adjust Linear recorder setpoint so that " auto permit" comes on.

3. With regulating rod at approximately 0.5 inches withdrawn, switch the Reg Rod control to " Auto" and reset the annunciator.

4. Adjust the red pointer (auto setpoint) to be slightly below black pointer (Linear signal) so that an insert on the Reg Rod will result.

5. When the Reg Rod reaches insert limit observe Manual Operation and " Reg Rod insert limit on Auto" annunciators.

6. Acknowledge and reset rundown and annunciators.

7. Record results.

3. SCRAM (red lichts):

A. Bridge Motion scram

1. Withdraw rods to 3 inches.

2. Release bridge lock and move the bridge a small distance.

3. Observe a Bridge Motion, Manual Scram and Magnet contact lights off. Acknowledge the annunciator alarm.

4. Return bridge to original position and reset all annunciators. Re-insert the magnets.

5. Record results.

Written By: David'Fr man Approved By: Albert Bolon fW O

@hh hW

i W

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 6 of 14 B. Period Trip Test

1. Withdraw shim rods to 3 inches. Rev

2. Hold the trip test toggle switch in the

" Test" position.

3. Rotate the " Trip Test" knob slowly and observe that the 30 second rod withdraw prohibit annunciator is actuated with a simulated period 2 30 seconds.

4. Continue to rotate the knob and observe that the 15 second period rundown occurs with a simulated period 2 15 seconds.

5. Continue to rotate the knob until the period scram is received. Verify that the Period scram occurs at a value > 5 sevonds and that the shim rods have dropped. Record the scram setpoint value. y

6. Release the " Trip Test" toggle switch and i make sure that it springs back to the

" operate" position.

7. Reset the Period trip on the Log N drawer.

Reset the rundown. Reset the annunciator panel.

C. Log N & Period Non-Operative Scram

1. Withdraw rods to 3 inches.

i Written By: David F- ama Approved By: Albert Bolon l JW ffl, 0  %

\

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 7 of 14

2. Turn Log N test from the operate to high or '

low position.

3. Observe Log N Period Amp Non-Operative Scram, Manual Scram, and that the Magnet contact lights go out. Acknowledge annunciators.

Reset Manual Scram and reset annunciator. ,

Insert the magnets.

4. Record results.

D. 150% Full Power Scram

1. Withdraw rods to 3 inches.

2. Push Scram test button on Safety Amplifier.

Hold button until both power range meters read full scale and 4 red test lights are on, and Magnet power light is off.

3. Push reset on the Safety Amp., acknowledge the annunciator and observe the 150% Full Power Scram annunciator and Magnet Contact lights are off.

4. Reset annunciator and insert the magnets.

5. Record results.

E. Manual Scram

1. Withdraw rods to 3 inches.

2. Push Manual Scram button.

3. Acknowledge the annunciator, observe Manual Scram light and all magnet contact lights are off. Push Scram Reset, Annunciator Reset and insert the magnets.

4. Record results.

4. ROD DROP CURRENTS:

1. Withdraw rods to 3 inches.

2. Using a screwdriver slowly reduce magnet cur- "

rent using current adjustment #1, until the

1. 1 magnet contact light goes out (you should -

also hear an audible " click" from the Reactor Bridge Intercom Station). Record this drop current value.

3. Repeat Steps 1 and 2 for Shim Rod No. 2 and No. 3.

Written By: Approved By: Albert olon fDa&vid'FrDyman u @kL W

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 8 of 14

4. Insert all Shim Rods to insert limit.

5. Set all Magnet Currents tt. " normal" (i.e.

Drop Current plus 10 ma).

5. TEST OF ANNUNCIATQRS:

A. Beam Room High Neutron Flux

1. Lower alarm set point by turning red needle on log rate meter to the left. Alarm occurs when black needle is hard against the red needle.

2. Check for local red alarm light and for white annunciator light on control panel. Return red needle to normal (10K) set point, reset alarm and annunciator.

3. Record results.

B. Interlock Bypass

1. Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights.

C. Servo Limits

1. Note linear level recorder reading.

2. Change the automatic set point for auto permit by adjusting the star wheel. Note linear level at which light comes on (<+2%).

Continue to lower and note reading until the auto permit light goes off (> -2%).

3. Reset automatic set point to the 100% level.

4. Record results.

D. Pool Demineralizer Effluent Conductivity'High

1. Record pool and demin effluent readings.

2. Check the alarm setpoint by dialing setpoint knob on the resistivity meter to match the needle reading. The local alarm (red alarm light) on the resistivity meter should come on and the console annunciator should alarm.

\

Written By: Dav'd reem n Approved By: Albert Bolon f# NY &kh NW

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 9 of 14

3. Reset the alarm to a setpoint of 0.5 MG-cm (2.5%) and switch the selector switch to display Demin effluent resistivity (Meas B").

6. " REACTOR ON" LIGHTS:

A. With magnet key inserted and all scrams reset check the " reactor on" lights (1) above console (2) at reactor entrance and (3) basement level.

7. BUILDING EVACUATION ALARM:

A. Announce over the PA, "The Building Alarm will sound. This is a test. Do not evacuate the building."

B. Push the Building Evacuation Alarm (center) of reactor console) and note the audible alarm.

C. Reset Building Evacuation Alarm by pushing Scram w Reset.

D. Announce over building PA " Test alarms complete.

Acknowledge all further alarms."

8. NITROGEN DIFFUSERS:

A. With the bridge intercom station selected, start diffuser #1. The green operation light should illuminate. Note the sound level of the pump and no unusual noise.

B. Shutdown the #1 pump and repeat step 1 for the #2 nitrogen diffuser.

C. Record results on form SOP 810.

9. BEAM PORT AND THERMAL COLUMN WARNING LIGHTS:

A. Announce over the building PA. " Attention person-nel, stand clear of the Beam Port".

Written By: Davi FrE an Approved By: Albert lon 73 (w Wy n w -_- - - - - - -

• UMR REACTOR STANDARD OPERATING PROCEDURES * *

• SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page lo of 14 B. Open the Beam Port by holding the beam port con-trol switch in the open position until the " Red" ,

(open) light comes on.

C. Acknowledge the annunciator alarm and check the Basement Level Warning Light (Flashing Red).

D. Close the Beam Port by holding the Beam Port Switch until the Green (closed) light comes on.

Reset the annunciator and observe that the light "

goes out.

E. Announce over the Building PA " Beam Port secured".

Complete SOP 810.

F. Dispatch a knowledgeable individual to the Thermal Column with the Thermal Column Key. Select the -

Basement Level Station on the Building Intercom. ,

G. Address the operator over the intercom to open the Thermal Column until the warning light comes on (approximately 1 inch).

H. The Control Room Operator should observe and acknowledge the annunciator alarm. Inform the Thermal Column Operator to shut the Thermal Column and ensure the warning light goes off.

I. Reset the annunciator and have the Thermal Column Operator return the key to the locker. Complete form SOP 810.

10. SHUTDOWN CHECK:

A. Complete a Shutdown Check List form 103 to ensure that all console equipment is secured.

11. EECURITY SYSTEM:

Inform the campus police (4300) that the security system will be checked.

t Written By: Da gman Approved By: Albert Bglon d (dWok %b -

.O l

l l

• • • UMR REACTOR STANDARD OPERATING PRCCEDURES ***

sop: 810 TITLE: WEEKLY CHECK

, Revised: November 12, 1993 Page 11 of 14

1. Security Door ,

a. Have police remain on line for the security checks,

b. Hold in or close dead bolt on the security door.

c. Reset the alarm system.

d. Open dead bolt switch by releasing or opening dead bolt and ensure alarm -

occurs in campus police dispatch station.

2. Ultrasonics

a. Hold or close dead bolt on security door. Reset alarm system. 3 g

b. While holding the dead bolt switch, move 1 around or have someone walk toward one of the UT's. Have campus police notify you when the alarm occurs. A different ultra sonic detector should be tested each week.

c. Allow the ultrasonic to reset by moving clear of the detector or stand still.

3. Duress

a. Inform the campus police that the duress alarm will be tested,

b. Momentarily depress the alarm button. .i.

The campus police should indicate the satisfactory operation of this alarm. -

4. Doors

a. While holding the dead"bo'lt switch '

closed, reset the alarm.

b. Open one of the exterior doors equipped with an intrusion alarm. A different door should be tested each week,

c. Have the campus police acknowledge the alarm when the door is opened.

Written By: Davik * .an Approved By: Albert B lon

1. ( b ' bh

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** l SOP: 810 TITLE: WEEKLY CHECK l Revised: November 12, 1993 Page 12 of 14 l i

d. Repeat steps a, b, and c for one of the interior doors equipped with an j intrusion alarm. A different door {

should be tested each week.

e. When all intrusion channels have been tested, ask campus police to check the battery circuit. This completes the security check.

f. When all channels of the security system I have been functionally tested and operate properly, initial the weekly I checklist, Form SOP 810.

l

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4 Written By: Davi n Approved By: Albert Bolon pvo.e &\ @ W \

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 13 of 14 WF.E'CY SETCEILLANCE CHECKLIST E0P3 S0P 810 Date Perfor:ed

1. ROD PRCHIBIT_ Anneristar Prohibit Initial A. Recorder Off (1) Log count rate recorder (2) Line-Ir recorder (3) Period recorder (4) Log N recordet (5) Torperature recorder B. Log count rate <2 CPS Actual Trio Point Annunciator Prohibit Initial, C. Period <30 seconds D. Inlet Te perature >135 0F E. Shin Rods below shis range

2. RCNDCW CHECK A. RAX Systes Re ote and Station Bldc. Alan Local Alan Annuncistor hnd m Trio coint Initial 1.

1.

2.

3.

Actu)1 Trio Point Annunciator Rund7q Initial B. 1201 Demand rundwn C. Period 15 seconds rundown D. 1201 Full Power Rundown E. Low CIC Linear P.S.

F. Low CIC Log N P.S.

G. Reg 21ating Rod on Insert Linit on Auto

3. SCP)3 CHECK Actual Trio Point Annunciator Scras In!tial A. BridgeXotionScran .

B. Period (5 Seconds Scran C. Lcq N Period Non-operative Scran Written By: David Pfeenr n Approved By: Albert Bolon

[ /# bd e

• • • UllR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: November 12, 1993 Page 14 of 14 Date ActualTrioPoid Annunciator Scrin Initial D. 150% full Power Scras E. Manual Scran

4. RCD DROP CU? RENTS Droo Current CgntactLichtOff in!tlil A. Rodil B. Rod 12 C. Rod #3

5. TESTOFAN'ENCIA!qE$

A. Bean loon High Neutron Flux local Alan Licht Ann'aciator Initial B. Interlock Bypass Areciator Initial (1) Shis range (2) 30secondperiod (3) Radiation area high (4) <2 CPS C. Servo Linits Lin. Rec. Reading Penit on at Penit off at IDisill 1 1 D. Pool /Desineralizer Resistivity Esql Denin Local Alam annuncistor Initial L1-cs El-cs

6. "l!LCT02ON" LIGHTS Orentional Initial A. MalaEntrance B. ControlRocu C. Beas Roca

7. BUILDING E'lACUATIO!i Alan Ocentional Initial e

8. NI??0GB DIFFCSER hp Otentional IndicatorLichtOn Initial A. 11 B. l2

9. BEM PORT AND TEERMAL COLUMN WARNING LIGHT Annunclitgr ElashinaLicht Inithl A. Bean Port B. Thenal Column Coroleted Initial

10. SFJT DOWN CHECX LIST Battery Check

11. SECURITY SYSTEM

12. APPROVED AND RE7IEWED Manager or Director (Rev. 6/10/92) i Written By: D man Approved By: Albert Bolon p%x = gugg