ML20206E773

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Progress Rept 1998-99 for Univ of Missouri-Rolla Reactor Facility for Period 980401-990331. with
ML20206E773
Person / Time
Site: University of Missouri-Rolla
Issue date: 03/31/1999
From: Freeman D
MISSOURI, UNIV. OF, ROLLA, MO
To:
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9905050242
Download: ML20206E773 (43)
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Univ rcity of Mic::ouri-Rol)a56 - I?

Nucle:r Re:ctor Fccility a to 1870 Miner Circle

( Rolla, MO 65409-0630 Phone: (573) 341-4236 s\ %j FAX: (573) 341-4237 April 28,1999 Document Control Room Attention: Director Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Stop 10-D-21 Washington, D.C. 20555

Dear Sir:

Please find enclosed the Annual Progress Report 1998-99 for the University of Missouri-Rolla Reactor Facility (License R-79). This report is being filed under the reporting requirements of our Technical Specifications. Copies of this report are also being sent to our Regional Administrator and Project Manager.

Sincerely, n> A Dr. David W. Freeman j Reactor Director i Enclosure fll xc: Marvin Mendonca, Project Manager (NRC)

RegionIII Administrator (NRC) [ h Dr. John Park, Chancellor (UMR) )

Dr. Lee W. Saperstein, Dean, School of Mines & Metallurgy (UMR)

Dr. Albert Bolon, Nuclear Engineering (UMR)

Mr. Ray Bono, Director, Health & Safety Services (UMR)

Dr. Robert Mitchell, Dean, School of Engineering (UMR)

Dr. Russell Buhite, Dean, College of Arts and Science (UMR)

Mr. Bruce Ernst, American Nuclear Insurers American Nuclear Insurers, c/o Librarian I Dr. Mark Fitch, Chairman, Radiation Safety Committee (UMR)

Radiation Safety Committee University of Missouri-Columbia Research Reactor Nuclear Engineering Faculty Reactor Staff .

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PROGRESS REPORT 1998-99 -

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PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1,1998 to March 31,1999 4

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

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SUMMARY

l During the 1998-99 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 354 hours0.0041 days <br />0.0983 hours <br />5.853175e-4 weeks <br />1.34697e-4 months <br />. The major part of this time, about 94% was used for class instruction, 1

research, and training purposes.

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

The reactor facility supported several UMR courses over the year for a total of 3,004 student-hours. The reactor was visited by about 3,315 visitors during the past year. There were l l

961 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

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The reactor produced 10,151 kilowatt-hours of thermal energy using approximately 0.523 grams of uranium. A total of 218 samples were irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory.

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Table of Contents '

l .0 INTROD U CTI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.1 Background Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.2 General Facility Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

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t 2.0 REACTOR STAFF AND PERSONNEL . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . 5 2.1 Reactor S taff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.2 Licensed Operators . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.3 Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.4 Health Physics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3.0 REACTOR OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.0 PUB LIC REL ATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 5.0 EDUC ATIONAL UTILIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 6.0 REACTOR HEALTH PHYSICS ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 6.1. Ro uti ne S urvey s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 8 6.2. By-Product Material Release Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 6.3. Routine Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 6.4. Waste Di sposal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 6.5. Instrument Calibrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 7.0 P L AN S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0 7.1. S trategic Pl an . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0 7.2. Instrumentation Upgrade . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 7.3. Reli censing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 i APPENDIX A. Revised SAR Pages For The 1998-99 Reporting Year APPENDIX B. Standard Operating Procedures Changed During The 1998-1999  :

Reporting Year i

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iii List of Tables Table 3-1. Core 10 l W Technical Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Table 3-3. Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 Table 3-4. Reactor Utilization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Table 3-5. Experimental Facility Use Other Than The Reactor . . . . . . . . . . . . . . . . . . . . . . . . 14 Table 4-1. Public Relations Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 Table 5-1. UMR Classes at Reactor Facility 1998-99 Reporting Period . . . . . . . . . . . . . . . . . . 16 Table 5-2. Reactor Sharing Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 List of Figures Figure 3-1. UMRR Core Configuration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1

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1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Rolla Reactor (UMRR) Facility for the period April 1,1998 to March 31,1999.

The reactor is operated as a university facility, available to the faculty and students from various departments of the university for their educational and research programs. Several other college and pre-college institutions have made use of the facility during the reporting period.

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

1.1 Background InformatiQD 1

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 reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. The reactor is a light water open pool reactor cooled by natural convection flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The licensed power was upgraded to 200 kW in 1966. During the summer of 1992, the reactor fuel was converted from high-enriched uranium fuel to low-enriched uranium.

The facility 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 laboratory that has gamma and alpha spectroscopy capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, and state-of-the-art data acquisition and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data

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acquisition equipment. The beamport experimental area is equipped with NE-213 and time-of-flight neutron spectroscopy systems.

1 1.2 General Facility Status The UMRR operated safely and efficiently over the past year. No significant safety- ,

I related incidents or personnel exposures occurred. On March 2,1999, Dr. David Freeman, who had been serving as both Reactor Manager and Acting Director for several years, officially 1

replaced Dr. Albert Bolon as Director of the facility. The Reactor Manager position has been '

eliminated. This change has been reviewed and approved by NRC. SAR pages describing the i

administrative structure have been revised and are presented in Appendix A.

A large effort is now underway in preparing our relicensing submittal, due to NRC in October,1999. The submittal will include a revised Safety Analysis Report (SAR), Technical Specifications, Requalification Program, and Security Plan. In March,1999, we received word that we have been awarded $53,000 from DOE, primarily to support the relicensing project.

We are continuing efforts to upgrade our console using grant awards from DOE j combined with money directly from reactor funds. We received an additional grant for instrumentation funding in the summer of 1998 and have recently received verbal notice of ,

I another instrumentation grant award for the Spring of 1999.

We have purchased three new instrument drawers from Gamma-Metrics 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 plan to install these three drawers in our control console as direct replacements for our existing Start-up, Log N and Period, and Linear drawers under the

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provisions of 10CFR50.59.

Graduate research aimed at characterizing pool water temperature profiles has continued j this year and utilizes newly acquired computer data acquisition equipment coupled with several temperature sensors. This research will lead to improved power measurements and live time reactor power measurements. The work has been funded from reactor accounts and has resulted in a Master's thesis (May,1999). l The reactor is currently funding a graduate student to perform research in support of the relicensing effort. To date this research has focused on atmospheric dispersion modeling and dose assessments associated with normal operations and accident conditions.

The Reactor Facility was audited by an independent auditor from the University of I

Illinois in July,1998. There were no significant areas of concern. We have entered into an j agreement with both the University ofIllinois and the University of Missouri-Columbia to rotate audits. This has been a very beneficial arrangement for all facilities involved.

The reactor staff has continued to review the operation of the Reactor Facility in an effort to improve the safety and efficiency ofits operation and to provide conditions conducive to its utilization by students and faculty. An " outreach" program, implemented over the past 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,

. additional classes have been using the Reactor Facility to augment their programs, including Physics 4 & 5, " Concepts in Physics"; Physics 7, " Environmental Physics"; Chemistry 8,

" Qualitative Analysis Laboratory"; Physics 107," Modern Physics"; Physics 207 " Modern i l

Physics II, Physics 322, " Advanced Physics"; Chemical Engineering 261, " Introduction to

4 Environmental Engineering"; Chemistry 2, " General Chemistry Laboratory"; Mechanical Engineering 229, " Energy Conversion"; Life Science 352, " Biological Effects of Radiation";

Chemistry 251, " Intermediate Quantitative Analysis"; Chemistry 355, " Instrumental Methods Laboratory"; Civil Engineering 310, " Senior Design Class", Basic Engineering 50, '! Engineering Mechanics - Statics", and Engineering Management 386, " Safety Engineering Management".

SOPS have been revised over the past year in order to improve our operations and efficiency. The following is a list of SOPS revised during the reporting period:

SOP 102 Pre-Startup Checklist Procedure (Page 3)

SOP 105 Reactor Shutdown & Reactor Securing Procedures (Page 3 and 4)

SOP 501 Emergency Procedures For Reactor Building Evacuation (Page 7)

SOP 508 Tomado Threat (Page 1)

SOP 509 Fire (Page 1)

SOP 615 Radiation Work Permit (Pages 2 and 5)

SOP 620 Decontamination Procedures (Page 3)

SOP 800 Semi-Annual Checklist (Page 2)

The above listed SOP revisions are provided in Appendix B.

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5 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Tele David Freeman Director Mendy Kell Senior Secretary William Bonzer Senior Electronics Technician James Jackson Senior Lab Mechanic 2.2 Licensed Ooerators Nams License David Freeman Senior Operator William Bonzer Senior Operator James Jackson Reactor Operator Albert E. Bolon (Inactive) Senior Operator 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/24/98, 9/11/98,12/18/98, and 3/29/99 during the reporting period. The committee members are listed below.

Name Department Dr. Mark Fitch, (Chairman) Civil Engineering Mr. Ray Bono (Secretary, ex-officio, non-voting) Occupational Health and Safety Services Mr. David Freeman Nuclear Reactor Dr. Nord L. Gale Life Sciences Dr. Edward Hale Physics Dr. Arvind Kumar Nuclear Engineering Dr. Oliver K. Manuel Chemistry Mr. Randy Stoll Director, Business Services Dr. Nick Tsoulfanidis Nuclear Engineering l

6 2.4 Health Physics l Health Physics support is provided through the Occupational Health and Safety Services 1

Department which is organizationally independent of the Reactor Facility operations group.

H alth Physics personnel are listed below:

Name Illis Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Director, Occupational Health & Safety Services and Campus Health Physicist Mr. Brian Smith Safety Specialist Scott Gizzie0 HP Technician David Alford 2) HP Technician Rachel Ragland HP Technician Joshua Williamson') HP Technician Kasi Johnson d) HP Technician Micah Hackett" HP Technician

' Terminated effective 1/22/99.

2 Terminated effective 3/12/98. l 3 Terminated effective 8/7/98.  !

d) Employed effective 1/4/99.

5) Employed effective 1/4/99.

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3.0 REACTOR OPERATIONS Core designation 101W 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 worths were measured in cold, clean conditions.

Table 3-1. Core 10lW Technical Data Parameter Value Rod 1 2.73% Ak/k 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
  • Assumes Rod 3 (highest worth rod) and Reg Rod are fully withdrawn.

Table 3-2 presents a listing of unscheduled shutdowns (scrams, rundowns, and unplamled normal shutdowns) along with their causes and corrective actions. There were no unscheduled scrams. Two of the three rundowns listed were due to noise sensitivity of our new Gamma i

Metrics Wide Range Log drawer. The drawer appears to be especially sensitive to switchmg j noise when the reactor is at or near full power. Switching associated with the auto controller and rod movements can induce enough noise to trip the 120% Full Power rundown. We have worked

8 Figure 3-1. UMRR Core 101W Configuration mammme mummmmmesummmmum mummmme mumummmemummmme A

B S C F-8 F-4 C-4 D F-13 C-1 F-3 F-2 F-12 F-15 E F-10 C-2 F-1 C-3 F-9 F-14 F

__ggggg 1 2 3 4 5 6 7 8 9 KEY TO PREFIXES F - Standard Elements C - Control Elements BR - Bare Rabbit CR - Cadmium Rabbit S - Source lloider

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with Gamma Metrics to resolve the situation. Gamma Metrics supplied us with a replacement AC filter; however, that did not change our situation. We are continuing to work with Gamma Metrics to resolve the problem.

Since the 120% Full Power trip is set on the log power signal, the voltage change between 100% and 120% on an eight decade scale is very small. In the future we may argue that it is inappropriate to have a 120% trip on a logarithmic power channel and seek to change that particular technical specification. Although this situation is not considered a safety problem, we are committed to continue efforts to resolve the matter in a timely fashion.

Maintenance activities are listed in Table 3-3. Table 3-4 shows reactor utilization and Table 3-5 shows other facility usage.

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10 Table 3-2. Scrams, Rundowns, and Unplanned Shutdowns jlatt Cause 12-01-98 Unplanned Shutdown. Observed no tumaround on Safety Channel #2 at 10KW.

Reactor promptly shutdown.

Cause: Defective vacuum tube in the Safety Channel pre-amp.

Corrective Action: Reactor shutdown. Replaced the vacuum tubes in the Safety Channel pre-amp. Checked settings for zero, span and trips for Safety Channels #1 and #2. Repositioned UIC #1 and #2 with reactor at 50% power.

12-30-98 Unplanned Shutdown. Observed power reading discrepancy between the Linear Channel and the Log and Linear Channel during start up to low power. Reactor promptly shutdown.

Cause: Found poor high voltage cable connection on the Linear Power Supply.

Corrective Action: Performed maintenance checks on the Linear Channel and the Log and Linear Channel. The high voltage cable was tightly latched to the high voltage power supply and the Linear Channel was tested with a neutron source at the Linear CIC for normal action. The reactor was taken to low power to verify both channels reading reactor power correctly.

1-21-99 Reactor Rundown.120% Full Power Rundown. Reactor at 100% power. Trip occurred when switching into the auto mode.

Cause: Spurious noise signal from auto / manual switch when switching from manual control to auto control.

Corrective Action: No corrective action necessary. SRO on duty granted permission to restart.

2-12-99 Unplanned Shutdown. Observed unusually noisy Linear signal at 10W.

Reactor promptly shutdown.

Cause: BNC connector on the compensating voltage cable.

Corrective Action: Replaced the BNC connector on the compensating voltage cable.

2-22-99 Reactor Rundown.120% Demand Rundown. Reactor increasing from 2KW to 20 KW, rundown occurred while upscaling the Linear pico-amp meter.

Cause: Spurious noise signal from the Linear pico-amp range selector switchbank while switching from the 2KW to the 20KW scale.

Corrective Action: No corrective action necessary. SRO on duty granted  !

permission to restart. j 3-29-99 - Reactor Rundown.120% Full Power Rundown. Reactor at 90% power. Trip occurred when switching into the auto mode.

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Table 3-2 continued.

Cause: Spurious noise signal from auto / manual switch when switching from manual control to auto control.

Corrective Action: No corrective action necessary. SRO on duty granted permission to restart.

Table 3-3. Maintenance '

Cause Data 4-24-98 Problem: At 95% power, Safety Channel #1 was reading 99% and Safety Channel

  1. 2 was reading 92%.

Corrective Action: Repositioned UICs to read 95%. I i

1 5-13-98 I'.oblem: Safety Channel #2 zero setting had drifled below zero with reactor 1 shutdown.

Corrective Action: Adjusted the zero setting on the Safety Channel pre-amp. ]

Checked zero, span and trip settings for the channel. Adjusted UIC #2 to read 50% l at 100KW power. l 7-22-98 Problem: Semi Annual Calibration performed, routine preventive maintenance.

Corrective Action: Adjusted Log and Linear CIC, Safety Channels UIC #1 and UIC

  1. 2 for proper calibration after thermal power calibration.

8-04-98 Problem: Performed routine visual rod inspection.

Corrective Action: Unloaded reactor core, removed control rod drive shrouds and magnets. Removed control rods and visually inspected them. Installed control rods, magnets, control rod drive shrouds and fuel elements. Performed control rod drop time tests. The visual rod inspections and rod drop time tests passed technical I specification limits.

9-04-98 Problem: Safety Channel #1 zero setting had drifted low with reactor shutdown.

Corrective Action: Replaced a vacuum tube in the Safety Channel pre-amp.

Adjusted the zero, span and trip settings in the Safety Channel #1 drawer. Adjusted the Safety Channel UIC #1 for a 100% reading at full reactor power.

Il-03-98 Problem: The zero settings for Safety Channels #1 and #2 had drifted from zero with reactor shutdown.

Corrective Action: Adjusted zero, span and trip settings for both Safety Channel #1 and #2. Repositioned UIC #2 at 150KW.

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Table 3-3. Continued 11-04-98 Problem: Safety Channels #1 and #2 read high at 150KW.

Corrective Action: Repositioned UIC #1 and #2 to read 75% at 150KW.

11-12-98 Problem: Regulating Rod had a intermittent response to being withdrawn instead of k a continuous action.

Corrective Action: Replaced the withdrawal and insert relays for the regulating rod.

Raised control rods to shim range and raised the regulating rod to fifteen inches, lowered to less than an inch and raised to fifteen inches to check for proper action.

1 11-12-98 Problem: Safety Channel #1 was reading 95% at full power. l Corrective Action: Repositioned UIC #1 to read 100% at full power. l 12-01-98 Problem: Safety Channel #2 did not show turnaround at 10KW. I Corrective Action: Reactor shutdown. Replaced the vacuum tubes in the Safety l Channel pre-amp. Checked settings for zero, span and trips for Safety Channels #1 j and #2. Repositioned UIC's #1 and #2 with reactor at 50% full power.

1 12-02-98 Problem: At 100% Power, Safety Channels #1 read 103% and Safety Channel #2 i read 97%.

Corrective Action: Repositioned UIC's #1 and #2 to read 100% at full power.

12-03-98 Problem: At 100% Power, Safety Channels #1 read 97% and Safety Channel #2 read 98%.

Corrective Action: Repositioned UIC's #1 and #2 to read 100% at full power.

12-08-98 Problem: Safety Channel zero settings had drifted lower while reactor shutdown.

Corrective Action: Replaced a vacuum tube in Safety Channel power supply and readjusted the B+ voltage. Checked zero, span and trip settings. Repositioned UICs during next reactor operation which was on 1/5/99.

12-11-98 Problem: Observed significant increased AC voltage output from the AC voltage regulator. This apparently " blew" the Linear Channel detector power supply (see below). Additionally, we suspect that the drift we have been experiencing with the safety channels is attributable to unstable AC from the regulator.

Corrective Action: Replaced the SCR's in the AC voltage regulator and adjusted for 120VAC.

12-18-98 Problem: The high voltage power supply for the Linear Channel detector not functioning.

Corrective Action: The Linear CIC power supply was temporarily replaced with the Gamma-Metrics Linear drawer under the provisions of 50.59. The existing Linear i _-

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power supply drawer was repaired and reinstalled on 1/16/99.

12-29-98 Problem: Noise observed on the Start-up Channel when fission chamber is withdrawn.

Corrective Action: The cable connector between the fission chamber and the pre-amp was electrically isolated with black electrical tape. This prevented the connector from rubbing on the metal shroud the cable traveled in as the fission chamber was inserted and withdrawn.

1-06-99 Problem: Semi Annual Calibration performed, routine preventive maintenance.

Corrective Action: No corrective action necessary, calibration proceeded as normal. 3-99 Problem: With the reactor shutdown, the Log and Linear Channel showed a loss of Log N signal. This occurred after the reactor had been shutdown for several hours following a high power run.

Corrective Action: Removed the Log and Linear CIC detector from the pool.

Cleaned and examined cable connectors and detector sockets. Installed CIC into pool. Performed prestart-up checklist to check cable connections.

2-22-99 Problem: With the reactor shutdown, the Log and Linear Channel showed a loss of Log N signal. This occurred after the reactor had been shutdown for several hours following a high power run.

Corrective Action: Replaced the Log and Linear CIC detector. Repositioned CIC to fine tune the Log and Linear power signal at 2%,50% and 100% full power.

3-08-99 Problem: Magnet current for each control rod magnet drifts.

Corrective Action: Replaced the vacuum tubes for each magnet.

Table 3-4. Reactor Utilization

1. Reactor use 353.70 hr.
a. NE Classes, Reactor Sharing, and Other Instructions 332.68 hr.
b. Maintenance Training 21.02 hr.
2. Time at power 250 hr.
3. Energy generated 10151 kW/hr
4. Total number of samples 218
5. U-235 Burned 0.442058 g
6. U-235 Burned and Converted 0.523264 g 1

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14 Table 3-5. Experimental Facility Use Other Than The Reactor Facility Hours Bare Rabbit Tube 142.17 hr.

Cadmium Rabbit Tube 0.00 hr. .

Beam Port 2.05 hr.

Other Core Positions 1.90 hr.

ll Total 146.12 hr.

4.0 PUBLIC RELATIONS -

l The reactor staff continues to educate the public about applications of nuclear science.

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I Over 3,315 persons visited 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 05/16/98 UMR Graduation " Blue Glow" Tour 29 06/08-6/15/98 UMR Jackling Institute 74 06/17/98 UMR Introduction to Engineering 57 06/18-06/25/98 UMR Jackling Institute 52 07/15/98 - UMR Introduction to Engineering 78 07/16/98 MOACAC-Reality Bus Tour for High School Counselors 11 07/20/98 AHEC - Area Health Education Center 34 07/22/98 UMR Introduction to Engineering 75 09/25/98 UMR Blue Glow Tour for Chemistry Students 61 10/16/98 UMR Scholars Weekend Open House 33 10/17/98 UMR Fall Open House 63 10/31/98 UMR Parents Day Open House , 83 12/18/98 UMR Offsite Emergency Training 19 02/11/99 UMR Basic Engineering TEAMS Competition 42 02/19/04 IIMR Precident's Thv Onen 14nnce 79

n 15 5.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 3,004 student-hours. The number of UMR students utilizing the facility was 988. This usage is a direct result of an aggressive and continuing campus wide " outreach" program. The reactor facility provided financial support for five students with hourly wages, one PhD candidate, and two Graduate Research Assistants. 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 University of Missouri-Columbia Nuclear Engineering Department sent its NE 404,

" Advanced Reactor Laboratory" class to our facility twice during March,1998, (for a total of 12'

- hours) to participate in a wide variety of reactor experiments that they are unable to perform with their reactor. The laboratories are held in the evening (4:00 pm until 10:00 pm) and are conducted by the UMR reactor staff.

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,961 students and instructors from 40 institutions participated in the 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 coordinate with the Admissions Office to schedule high school students to see other items ofinterest at UMR after they have visited our facility, such as the student group of American Nuclear Society, the Computer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum, Computer

16 Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor Sharing Program serves as a strong campus-wide recruiting tool by getting high school students to the university and hopefully sparking some interest in our campus.

Iable 5-1. UMM Llasses at Meactor tactInty 1998- 99 Reporting Period CLASS NUMBERtlII LE #OF TIME AT STUDENT STUDENTS REACTOR HOURS 04/07/98 UMR NE 204, Radiation Measurements 7 1.50 10.50 04/09/98 UMR Basic Engineering 50 2 1.00 2.00 04/21/98 UMR NE 204, Nuclear Radiation Measurements 5 2.00 10.00 04/28/98 UMR NE 204, Radiation Measurements 6 2.00 12.00 04/28/98 UMR Physics 7 11 0.50 5.50 09/21-24/98 UMR Chemistry Labs 609 0.50 304.50 09/25/98 UMR Blue Glow Tour for Chemistry Students 61 0.50 30.50 10/19/98 UMR Engineering Management 386-Safety Systems 16 1.00 16.00 11/06/98 UMR Physics 207 7 1.00 7.00 11/24/98 UMR Physics 6 15 0.75 11.25 01/12/99 UMR Civil Engineering Senior Design Class 24 1.00 24.00 01/19/99 UMR NE 204, Radiation Measurements 10 2.50 25.00 01/20/99 UMR NE 25, Nuclear Technology Applications 12 1.00 12.00 02/01/99 UMR Engineering Management 386 25 1.00 50.00 02/03/99 UMR NE 25, Nuclear Technology Applications 12 1.00 12.00 02/04/99 UMR Life Science 352, Biological Effects of Radiation 12 1.45 17.40 02/17-18-99 UMR Chemistry Labs 90 0.50 180.00 02/24/99 UMR EngMgmt 386, Safety Engineering Management 23 1.00 11.50 03/03/99 UMR Chemistry Labs 12 0.50 9.00 ,

Fall 1998 UMR NE 304, Reactor Laboratory 1 6 30.00 180.00 l Fall 1998 UMR NE 306, Reactor Operations 4 36.00 144.00 ,

Fall 1998 UMR NE 490, Research (Eric Stevenson, Thermal Power Cal.) 1 300.00 300.00 l Fall 1998 UMR NE 490, Research (Scott Gizzie, Relicensing) 1 240.00 240.00 j Fall 1998 UMR NE 490, Research (David Freeman, Genetic Algorithm i 100.00 100.00 Fall 1998 UMR490, Research (Bill Dennis, Geology, Lake sediments 1 45.00 45.00 Winter 1999 UMR NE 490, Research (Eric Stevenson, Thermal Power Cal.) 1 300.00 300.00 Winter 1999 UMR NE 490, Research (Scott Gizzie, Relicensing) 1 320.00 320.00 Winter 1999 UMR NE 306, Reactor Operations 6 36.00 216.00 Winter 1999 UMR NE 308, Reactor Laboratory 11 7 80.00 560.00 Totals 988 1507.70 3004

17 Table 5-2. Reactor Sharing Program (1998-1999)

DATE PARTICIPANTS NUMBER 04/08/98 Crossroads High School, Tanda Pommier, instructor 31 04/13/98 Laquey High School, (Admissions arranged) 35 04/14/98 Steelville High School, Charles Hawkins, Instructor 15 04/16/98 John F. Hodge High School, St. James, Jim Jenkins, instructor 15 04/27/98 West Plains, Elementary, Kathleen Aid, Instructor 14 05/04/98 Columbia Hickman High School, Polly Hendren, instructor 11 05/05/98 St. James 5* Grade, Kathy Salter & Cece White, Teachers 50 05/06/98 Rolla Middle Schools, Mrs. Christy Brown, Instructor 20 05/07/98 Waynesville High School, Julie Kosbar, instructor 30 05/08/98 Potosi 8* Grade, Alan Ziegler, Instructor 9 05/14/98 Lebanon High School, John Sode, instructor 35 10/07/98 Webb City High School, Terry Rose, instructor 20 10/08/98 St. Charles-West High School, Rebecca Teague, Instructor 58 10/15/98 St. Louis Public Schools, Junior High School, Contact 30 11/03/98 Lebanon High School, John Sode, Instructor 65 11/04/98 Mansfield High School, Pam Probert, Instructor 21 t 11/10/98 East Central College, Debbie Schatz, Instructor 13 11/11/98 Hazelwood Central High School, Cathy Sylve, Instructor 20 11/12/98 Nixa High School, Laura Pendergrass, Instructor 8 11/18/98 Fair West Plains High School, Regina Kissenger, Instructor 37 11/24/98 Andy Ramakrishna, Jefferson City High School, Individual Project i 12/01/98 Laura Richeson, Potosi High School, Bill Nelson, instructor, Ind. Project 1 12/03/98 Crocker High School, Joseph Nocchi, instructor 14 12/03/98 Cassie Avila, Potosi High School, Bill Nelson, Instructor, Individual Project 1 12/09/98 Ritenour High School, Richard Witt, Instructor 17 12/09/98 Karla White, Potosi High School, Bill Nelson, Instructor, Individual Project 1 12/11/98 Willow Springs 6* Graders, Jeanette Ronse, Teacher 11 02/23/99 Rolla Area Home Schoolers, Michieline Edwards (3'8 grade and up) 11 02/25/98 Thomas Jefferson High School, Kcthy Weibrecht, instructor 30 02/25/99 Waynesville High School, (Admissions arranged) 29 03/02/99 Rebecca Moneymaker, Newburg High School, Peggy Brown, Instructor 1 03/03/99 Rebecca Adams, St. James High School, Jim Jenkins, Instructor 1 03/10/99 Climax Springs High School, Karen Foote, instructor 21 03/11/99 Hazelwood West High School, Gail Haynes, Instructor 27 03/11/99 Washington High School, Rick Schwentker, instructor 70 03/17/99 Brentwood High School, Rich Nieman, Instructor 35 03/19/99 Rolla Middle School. 5* grade, Mrs. Edgar /Mr. Conway, Instructors 43 03/23/99 Meramac Valley Home Schoolers Assoc., Wendy Pelton, instructor 22 03/31/99 Waynesville High School, Julie Kosbar, Instructor 23 03/31/99 Rol!a Middle School,6* Grade, Coco Taylor, Instructor 65 TOTAL 961

i 18 6.0 REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the UMR Reactor Facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity and waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

6.1. Routine Surveys Monthly radiation exposure surveys of the facility consist of direct gamma and neutron measurements. No unusual exposure rates were identified. Monthly surface contamination .

l 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.

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

6.3. Routine Monitorine i 1

Thirty-two reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Four are read twice per month (Reactor Staff) and )

\

twenty-eight are read once per month. There arc four area beta-gamma / neutron badges assigned.  !

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19 Thirty-six campus personnel and student are assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 24 area monitor and 5 spare badges assigned on campus. In addition,5 digital direct-reading dosimeters,4 chirpers, and 6 ion-chamber dosimeters are used for visitors and high radiation area work. There have been no significant personnel exposures during this reporting period.

Visitors are monitored with direct reading dosimeters. No visitor received in excess of 5 millirem.

Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous air monitor (CAM). Low levels of Argon-41 are routinely produced 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 1998 through March 1999 sample concentrations averaged 3.34 x 104 Ci/ml.

Release of gaseous Ar-41 activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power, During this period, an estimated 77.31 millicuries of Ar-41 was released into the air.

6.4, Waste Disoosal Solid waste, including used water filters, used resins and contaminated paper is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site.

Water is analyzed for radioactive contamination and approval is required before the water is l i

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l 20 released. During this period fifteen cubic feet of waste consisting of regeneration filters and laboratory waste con *aining trace amounts of Co-60 and Cs-137 was transferred from the Reactor Facility to the Dangerous Material Storage Facility.

6.5. Instrument Calibrations During this period, portable instruments and area monitors were calibrated annually.

7.0 P L A N S l

The reactor staff will be heavily involved in three major projects during the next reporting period; l) relicensing 2) implementation and revision of the new strategic plan,3) installing new reactor nuclear instrumentation.

l 7.1. Relicensinn .

Relicensing activities will intensify during the upcoming reporting period. Our present license is valid until November,1999. Our relicensing application package is due October 20, 1999. Several documents will be revised including the SAR, Technical Specifications, Emergency Plan and Physical Security Plan.

7.2. Stratenic Plan i

A strategic plan has been developed to help the facility achieve its vision "to become nationally recognized as the leading educational and training university reactor in the country and to become recognized as the leading 200 kW facility in terms of research". The strategic plan l

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21 identifies strategic goals and action items. The action items will be initiated over the coming year and will guide the facility towards its vision.

7.3. Instrumentation Unarade The reactor console upgrade is well underway. Several pieces of new equipment have been installed under the provisions of 10 CFR Part 50.59. We plan to install a new Linear drawer, Source Range drawer and a new annunciator panel during the upcoming reporting period. Most of the changes will be made under the provisions of 50.59 ; however, some changes may require NRC approval.

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1 APPENDIX A.

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REVISED SAR PAGES 8-1 and 8-2 FOR THE 1998-99 REPORTING YEAR l

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8. ADMINISTRATIVE CONTROLS i

8.1 Organi z ati onal Structure The organization of the University of Mi ssouri-Rol l a as celated to ensuring the proper use of the nuclear reactor and radi oactive materi al s i s shown in Fi gure 25. * Thi s organization i I

involves a single, major committee, the Radiation Safety Committee.

8.2 Radiation Safety Committee The reactor is operated under NRC License R-79 granted in 1961. As required by the license, a reactor advi sory committee

{

was appointed at the time and, as time went by, it has been called by different names. Its present, off i ci al title is the UMR_ Radiation Safety Committee. 7':  : ;2-i:2 tic- _t'i- t':

n 1_ e t s; ;_ ;;_ i ; e x em u\

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g ,,g, "ricte- "2ci1ity it 05 - ir "i g a: 2 '. .

l The UMR Radiation Safety Committee has the dual responsibi1i ty of

  • 1 I

I I

(1)

Advising the administration regarding matters relating to l

custody and use of radioisotopes on campus.

(2)

Revi ewing _ and making recommendations concerning ex p er i men t a l and operational act i vi ti es of the UMR Nuclear 1

l l

8-2 > :. lJ Rev.

THE CURATORS CHANNELS OF UNIVERSITY OF MISSOURI RESPONSIBILITY

...-.-.....-.. CHANNELS OF PRESIDENT COMMUNICATION UNIVERSITY OF MISSOURI CHANCELLOR RADIATION SAFETY UNI. OF MO.-ROLLA ........ COMMITTEE DEAN VICE CHANCELLOR SCHOOL OF MINES ADMIN. SERVICES (LEVEL 1) I DIRECTOR ... ........ RADIATION SAFETY ,,j NUCLEAR REACTOR -..----..--- --.... OFFICER (LEVEL 2) --..--..,

l SENIOR REACTOR HEALTH PHYSICIST

- ~ ~ - - - ~ ~ - - -

OPERATORS REACTOR OPERATORS HEALTH PHYSICS AND STAFF STAFF I

REACTOR OPERATIONS HEALTH PHYSICS Figure 25. Organizational structure of the University of Missouri related to the UMR Nuclear Reactor Facility l

l

APPENDIX B.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 1998-1999 REPORTING YEAR i

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,,, . , . . . , . . . .. A .4

      • UMR REACTOR STANDARD OPERATING PROCEDURES "*

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Page Revision: Apri1 14. 1998 Page 3 of 8

10. Linear CIC Voltage: Record the high voltage (HV) and compensating voltage (CV) settings of the Linear power supply. Values should correspond a proximately to the following:

HV ~ 480 VDC CV ~ 2 to 8 VDC

11. a. Observe the temperature recorder " RCD" is illuminated in the upper left hand Rev.

corner of the display.

b. Turn on and date the Startup, Linear, and Log / Period recorders. 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.
13. Start-Up Channel Test: Turn the Log Count Rate selector switch to 10,10', 2 and 104 .

Verify that the meter and recorder follow. Return the selector switch to the

" OPERATE" position.

14. Verify Fission Chamber Response: Insert the fission chamber until the green Insert Limit light comes on. Observe the count rate. Raise the fission chamber until the count rate shows a definite decrease. Verify that the 2 cps alarm trips at a count rate greater Rev.

than or equal to 2 cps. 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.)

15. Observe the Log Count Rate H.V. power supply setting is positive 400 VDC. If setting is different then notify the SRO on Duty.

CONu, p Reviewed By: William Bonzer Approved By- avid Freeman

. . .: 4 a

"* UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Page Revision: April 14,1998 Page 3 of 4

9. Verify both Nitrogen Diffusers are off.
10. Verify that all vent fans are off.

I1. Secure the rabbit system by assuring the controller is turned off and the gas bottle is shut. Return the glove box key to the safe.

12. Shut off the rabbit system nitrogen gas bottle if the rabbit has been used.

Rev.

13. Turn off the core lights.
14. Log time using the console clock.
15. Initials of person performing checklist.
16. Senior Operator on Duty shall initial.

Reviewed By: William Bonzer Approved By: David man O

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"* UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Page Revision: April 14. 1998 Page 4 of 4 SECURE CHECKLIST

1. Date
2. All Rods on Insert Limit
3. Magnet Power Off and Key to SRO
4. Recorders Off and Dated
5. Reset Annunciator
6. Reactor Bridge Intercom Off

, 7. Shutdown Switch to Operate

8. TV Monitor Off
9. Nitrogen Diffusers Off
10. Vent Fans Off
11. Rabbit System Secured
12. Rabbit Gas Off '
13. Core Lights Off
14. Time Compleied
15. Operator's Initials
16. Senior Operator's Initials Revised 4/07/98 Reviewed By: William Bonzer Approved By: *id reema uf3Lo ik r 10 ##

3

CONTRou 2 E l

      • UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 501 TITLE: EMERGENCYPROCEDURES FOR REACTOR BUILDING EVACUATION Page Revision: November 5, 1998 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff HOME WORK David Freeman, Mgr., SRO 364-7269 341-4384 William Bonzer, Sr. El. Tech., SRO 368-3727 34.1-129_1 Albert Bolon, Dir., SRO 364-1961 341-4746 Ray Bono, Health Physicist 364-5728 341-4240.4305.4403 Jim Jackson Sr. Lab Mechanic, RO (573)699-4897 341-4291 Mendy Kell. Sr. Sec. (573) 265-5832 341-4236 Rev.

University Administrative Staff

1. Chancellor, John Park 341-4118 364-6455 341-4_114
2. Vice Chancellor for Admin. Services, Mohammad H. Qayoumi 308-1067 341-69_Ds,4122
3. Director, UMR Police, William Bleckman 364-1294 341-4345
4. Director, Physical Plant, Marvin Patton 364-6278 341-4_252
5. Director, Health Service - Infirmary, Dwight

Deardeuff,

MD 364-0809 341-4284

6. Dean, School of Mines and Metallurgy, Lee W. Saperstein 368-3782 341-4_15]
7. Radiation Safetv Officer. Nick Tsoulfanidis 341-3595 341-4745 Local UMR University Police 341-4300 341 .4.111 Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9-911 Rolla Emereency Manacement Acency 9-911 State Agencies Missouri Highway Patrol 368-2345 Missouri State Emergency Mgt. Agency (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.)

(573) 634-2436 Missouri Bureau of Environmental Eoidemioloey (573) 751-6160 (5731751-4674(aner hrs)

Federal Agencies NRC, Lisle, IL, Region III 1-800-522-3025 NRC Dutv Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 816-5100 (301) 951-0550 (3011 415-0550 Other American Nuclear Insurers (860) 561-3433 Radiation Emereency Assistance Center (423) 576-3131 (423) 481-1000 (24 hrs)

Revised 08/25/98 LU '

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) Revised By: William Bonzer Approved By. David Freeman

CONTROLLES COM

      • UMR REACTOR STANDARD OPERATINO PROCEDURES ***

SOP: 508 TITLE: TORNADO THREAT Revised: Nov. 5, 1998 Page1of 1 A. TORNADO IN IMMEDIATE VICINITY OF REACTOR BUILDING

1. SCRAM reactor.
2. Remove and secure the magnet power key.
3. Announce over the building PA that all personnel are to immediately proceed to the rear of mid-level basement due to the tornado threat. Rev.
4. Close the security door.
5. Time permitting, the SRO on Duty will assure that all personnel have evacuated to the mid-level basement area.
6. Time permitting, obtain the key to the subbasement beamport cage area and assemble personnel in this area.
7. Wait for the tornado to pass.
8. After the tornado has passed, inspect the facility for damage. Re-establish physical security if necessary.

9.

The Reactor Director will evaluate the situation to determine whether or not an Unusual Event should be declared per the Emergency Plan.

B. TORNADO EXPECTED IN THE REACTOR BUILDING AREA .

1. Complete normal reactor shutdown if time permits, otherwise go to Step 1 above.

Reviewed By: William Bonzer Approved By: David -

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      • UMR REACTOR STANDARD OPERATINO PROCEDURES ***

SOP: 509 TITLE: FIRE Revised: April 7,1998 Page1 of 1 A. FIRE THREATENING REACTOR OPERATION

1. SCRAM Reactor.
2. Remove and secure magnet power key. Rev.
3. Pull fire alarm station located to the left of the front security door. (Note: There is another fire alarm station on wall to the left of the mid-basement exterior door.)
4. Evacuate building per SOP 501.
5. Call Fire Department.
6. Make sure physical security is re-established as soon as possible after fire is out.
7. In the event of a prolonged fire, the Reactor Director will evaluate the situation to determine whether or not an Unusual Event should be declared per the Emergency Plan.

LA$w $@3%

Reviewed By: William Bonzer

/a Approved By: avid Freeman

k  ; CONTROLLED COPY

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 615

Title:

RADIATION WORK PERMIT Revised: June 29, 1988 Page 2 of 6 C. Procedure The f ollowing numbers ref er to the step on the Radiation Work Permit (RWP) check list:

1. Use the rubber date stamp.
2. a. Indicate which component, system or part is to be maintained or repaired.

. b. Describe what work is to be d.one.

c. Indicate where the work is going to be performed, e.g. in the bay, etc.
3. a. List all persons who are going to be involved.
b. Estimate the radiation exposures. Use previous experience with the same or a similar component.

if necessary. Otherwise, take quick survey meter readings at two feet from the object to get ap-proximate dose rates. I

c. The Campus Health Physicist should assist with l determining this value, i
4. Additional dosimetry required by the Campus Health Physicist and placement.
5. Additional protective clothing required by the Campus Health Physicist.

S. :uolih W . ,, ;

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' ' ' . . . rc:First r/ requiremer.te by Co-eu. .

7. Special instructions, e.g.. be sure to disconnect the l high voltage before repairing. If continuous HP l coverage is necessary, it should be indicated.
8. Try to anticipate the completion date f or this par-ticular authorization . The RWP may be extended provided the Reactor Manager or Reactor Director so authorizes in writing on the RWP checklist.

Written By:

8 Ma.Edw Approved By:

5 Albert Bolon Francis Jones

E lcom0LLED COPY aaa UMR REACTOR STANDARD OPERATING PROCEDURES aaa SOP: 615

Title:

RADIATION NORK PERMIT Revised: June 29, 1988 Page S of 6 S. R pir:tery pr;t:: tier. r:;uired (C- ru: "'?

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.  ;;rC iw rastrictier.: -- if  ;;l10:510- g{T}

7. Special precautions or instructions for this particular job
8. Termination date
9. Signature and date of each worker who will be involved with this RWP -- that they have read, understood and had an op-portunity to ask questions about their assignments.

l

10. Authorizing signatures and dates A. Campus Health Physicist, or his designated repre-sentative B. Supervisor under whom the work will be performed l

l C. Reactor Manager or Reactor Director or their desig- ,

nated representative l

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'd AQ,, dv 6 Written By: Francis Jones Approved By: Albert Bolon i

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1

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 620 TITLE: DECONTAMINATION PROCEDURES j Complete Revision: ' March 20, 1995 Page 3 of 5 j i

l first use paper towels lightly wetted with water or ordinary cleaning solutions.

If this is ineffective, use Radiacwash or other detergent. Using these solutions may dissolve some of the painted surface. -

3

b. Decontamination of porous concrete floors should be attempted with strong concentrations of the commercial solution or detergent. If all attempts are unsuggsful,,J,h,e, sugac,e, sggoncreyega,y pa, ypjo pegeyngy(gg;pjjfg JrM v Gi% M a n u,wrm u..,wa. .
c. When decontaminating linoleum, care must be taken to avoid driving the gjg radioactive material into the cracks between the linoleum squares if sealer has not been used.

. d. If a dry spill occurs on any surface, it should be wet misted with water, Radiacwash, or similar non-hazardous solution prior to the decontamination process.

4c Cleaning Minor Radioactive Spills

a. - If survey of a spill by a hand-held meter yields a reading of 5 mrem /hr or

. greater at a distance of I foot, if the contamination extends beyond a single room, or if the spill area resists all normal effons for decontamination, Occupational Health and Safety Services or the Health Physicist must be contacted immediately to supervise the decontamination effort. i

b. Put on gloves and protective clothing such as a laboratory coat to avoid body and clothing contamination.
c. Confine spills to as small an area as possible.
d. ' Absorb spilled liquid with absorbent paper or cloth to limit the spread of contamination as necessary. l l e. Define and mark off the contaminated area. Do not remove objects or allow l- people to leave the contaminated area until monitored.

]

M (dkk A Revised by: Ra Bono Approved by: Albert Bolon l

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      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI-ANNUAL CHECKDST Revised: Apri1 28,'1997 Page 2 of 8

{

Log Displays l i

ricommy True Tolerance for Los Log Log initial Date Current Espected True Espected Bargraph Digital Recorder Readinas Readine ]

1 n . s c -u - m . ; n 10 pA 1.0E 5% 7.;,Li,n '.15 Sat g..[D 100PA 1.0E-4% Y^I* $ Yi" 2-17'l7 j 1

1nA 1.0E-3% 7.0E-4 1.4E 3% i

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10 nA 1.0E 2% 7.0E-3%1.4E 2% i i

100 nA 1.0E 1% 7.0E 241.4E4%

ipa 1.0E -0% 7.0E 141.4E 0% l 1

10 pA 1.0E+1% 7.0E-041.4E+ 1% Rev. I 100 pA 1.0E+2% 7.0E+ 1414E+2%

Period Displays Settings Period Bargraph Period Digital Period Recorder Initial Date Display Display Display 80 3 Sec Linear Displays Pico-amp Tolerance for True True Expected IJnear Bergraph Linear Digital Voltage Initial Date Current Espected Readinas Readine Display Display Tolerances 10 A 8%.12% 10*4 0.7V-0.9V 20 pA I8 % 22 % 20 % 1.5V l.7V 30 pA 28?'e 32% 30% 2.3V 2.5V 40H A 38 % 42 % 40 % 3.IV 3.3V 50 kA 48 % 52 % 50 % 3.9 V-4. IV j I

60 pA $ 8%-62% 60 % 4.7V 4.9V '

70 pA 68* e-72% 70 % 5.5V 5.7V 80pA 78482% 80% 6.3V-6.5 V 90 pA 88492% 90 % 7.1V 7.3V 100 pA 98 % 102 % 100 % 7.9V 8.1V 110 pA 108 % 112 % 110 % 8.7V-8 9V 120 pA 118 %-122 % 120 % 9.3V 9.7V 125 uA 123 4 127 % 125 % 9 9V 10.IV b k '. d e. i , s't )

Revised By: William Bonzer Approved By: David Freeman

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