ML021270435

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Annual Progress Report 2001-2002 for the University of Missouri-Rolla Reactor Facility
ML021270435
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Site: University of Missouri-Rolla
Issue date: 04/25/2002
From: Tokuhiro A
Univ of Missouri - Rolla
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Document Control Desk, Office of Nuclear Reactor Regulation
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4MISS oNuclear University of Missouri-Rolla Reactor Facility 70 1870 Miner Circle Rolla, MO 65409-0630 Phone: (573) 341-4236 L FAX: (573) 341-4237 April 25, 2002 Document Control Room Attention: Director Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Stop 012-D3 Washington, D.C. 20555-0004

Dear Sir:

Please find enclosed the Annual Progress Report 2001-2002 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, Dr. Akira T. Tokuhiro Reactor Director mk Enclosure xc: Marvin Mendonca, Project Manager (NRC)

Chancellor Gary Thomas (UMR)

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

Mr. Ray Bono, Radiation Safety Officer(UMR)

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

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

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

University of Missouri-Columbia Research Reactor (MURR)

Dr. Arvind Kumar, Chairman of Nuclear Engineering (UMR) A-(Dc--)-D

PROGRESS REPORT 2001-2002 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY

PROGRESS REPORT 2001-2002 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY

PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1, 2001 to March 31, 2002 Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla

i

SUMMARY

During the 2001-2002 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 287 hours0.00332 days <br />0.0797 hours <br />4.74537e-4 weeks <br />1.092035e-4 months <br />. The major part of this time, about 78% was used for class instruction, research, and training purposes.

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 2,936 student hours. The reactor was visited by about 2,171 visitors during the past year. There were 272 partic ipants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 3,833 kilowatt-hours of thermal energy using approximately 0.17 grams of uranium. A total of 227 samples were irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory.

ii Table of Contents 1.0 IN TR ODU CTION ......................................................... 1 1.1 Background Inform ation ............................................ 1 1.2 General Facility Status .............................................. 2 2.0 REACTOR STAFF AND PERSONNEL .................................. 4 2.1 R eactor Staff ..................................................... 4 2.2 Licensed Operators ................................................ 4 2.3 Radiation Safety Committee ............................. ........ 4 2.4 H ealth Physics .................................................... 5 3.0 REACTOR OPERATIONS .................................................. 5 4.0 PUBLIC RELATION S ..................................................... 11 5.0 EDUCATIONAL UTILIZATION ............................................. 12 6.0 REACTOR HEALTH PHYSICS ACTIVITIES ................................. 16 6.1. R outine Surveys .................................................. 16 6.2. By-Product Material Release Surveys ................................. 16 6.3. Routine M onitoring ............................................... 16 6.4. W aste D isposal ................................................... 17 6.5. Instrum ent Calibrations ............................................ 18 7.0 PL AN S ................................................................. 18 7.1. Administrative Changes ............... ............................. 18 7.2. R elicensing ...................................................... 18 7.3. Strategic Plan .................................................... 19 7.4. Instrumentation Upgrade ........................................... 19 APPENDIX A. Standard Operating Procedures Changed During The 2001-2002 Reporting Year APPENDIX B. Revised SAR Pages For The 2001-2002 Reporting Year

iii List of Tables Table 3-1. Core 101W Technical Data ............................................. 6 Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns ............................ 8 Table 3-3. M aintenance ......................................................... 9 Table 3-4. Reactor Utilization ................................................... 12 Table 3-5. Experimental Facility Use Other Than The Reactor ......................... 12 Table 4-1. Public Relations Program ............................................. 13 Table 5-1. UMR Classes at Reactor Facility 2001-2002 Reporting Period ................ 15 Table 5-2. Reactor Sharing Program .............................................. 16 List of Figures Figure 3-1. UM RR Core Configuration ............................................ 7

1

1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Rolla Reactor (UMRR)

Facility for the period April 1, 2001 to March 31, 2002.

The reactor is operated as a university facility, available to the faculty and students from vari ous departments ofthe 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 Information 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 acquisition equipment. The

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

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

The license for UMRR has been extended to January 14, 2005, Amendment No. 16 (August 6, 1999). We have been working on relicensing during this period and will continue.

We are continuing efforts to upgrade our console using grant awards from DOE combined with money directly from reactor funds. We have received grant funds for Reactor Instrumentation upgrade in Spring 2001 and received notice of additional instrumentation funds for the Spring 2002.

The reactor has funded 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 Columbia on December 15, 2001. There were no significant areas of concern. We have entered into an agreement with the University of Missouri-Columbia to audit each other. This has been a very beneficial arrangement for both facilities involved.

The reactor staff has continued to review the operation of the Reactor Facility in an effort to improve the safety and efficiency of its operation and to provide conditions conducive to its utilization by students and faculty. 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

3 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, "Modem Physics"; Physics 207 "Modem Physics II, Physics 322, "Advanced Physics"; Chemical Engineering 261, "Introduction to 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:

Index Index (Page 1)

SOP 101 General Operating Procedures (Page 2)

SOP 102 Pre-Startup Checklist Procedure (Pages 3, 5, 7 & 8)

SOP 106 Restart of Reactor When It Is Not Secured SOP 107 Permanent Log, Hourly Log and Operational Data SOP 204 Demineralizer Regeneration (Page 1)

SOP 308 Restoration of AC Power Following A Power Outage (Page 1)

SOP 507 Emergency Procedures-Administrative Responsibilities (Page 2)

SOP 604 Radioactive Waste Handling Criteria (Page 1)

SOP 711 Beam Hole Facility (Page 2)

SOP 800 Semi-Annual Checklist (Page 8)

SOP 801 Log and Linear Drawer Calibration (Pages 2, 3 & 4)

SOP 810 Weekly Check (Pages 4, 5, 8, 10 & 11)

The above listed SOP revisions are provided in Appendix A.

4 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Director and Senior Operator Dr. Akira Tokuhiro William Bonzer Reactor Manager & Senior Operator Senior Secretary Mendy Kell Senior Operator & Sr. Lab Mechanic James Jackson Brian Porter 1) Senior Electronics Technician 1)Hired Effective April 30, 2001 2.2 Licensed Operators Name License Senior Operator William Bonzer Senior Operator James Jackson Senior Operator Akira Tokuhiro Reactor Operator Dan EstelI Reactor Operator Jeremy Gorelick' Reactor Operator Craig Heimericks1

'Effective March 27, 2002 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 01/22/01, are listed 09/13/01, 12/13/01, and 3/06/02 during the reporting period. The committee members below.

Name Department Civil Engineering Dr. Mark Fitch, (Chairman)

Environmental Health and Safety Services Mr. Ray Bono (Secretary, ex-officio, non-voting)

Nuclear Reactor, Reactor Manager Mr. William Bonzer Biological Sciences Dr. Roger Brown Physics Dr. Robert DuBois Nuclear Engineering Dr. Arvind Kumar Chemistry Dr. Ekkehard Sinn Director, Business Services Mr. Randy Stoll Director, Nuclear Reactor Dr. Akira Tokuhiro Nuclear Engineering Dr. Nick Tsoulfanidis

5 2.4 Health Physics Health Physics support is provided through the Environmental Health and Safety Department which is organizationally independent of the Reactor Facility operations group. Health Physics personnel are listed below:

Name Title Mr. Ray Bono Campus Health Physicist & Radiation Safety Officer Mr. Brian Smith Industrial Hygienist Allison Adams HP Technician Michelle Minard HP Technician LeAnn Splitter HP Technician Julie Tucker HP Technician 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.

6 Table 3-1. Core 101W 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 unplanned normal shutdowns) along with their causes and corrective actions. There were four unscheduled scrams. Two scrams were caused by noise spikes within the safety channel/magnet drawer. The drawer was repaired and we are in the process of replacing the safety channels and magnet power supply. The other two scrams occurred due to loss of AC power to the reactor facility and decreasing magnet current for a control rod magnet. Both of these scrams did not initiate a trip signal due to the nature of the scram. Five of the nine rundowns listed were due to 120% Demand trips, which were caused by noise spike when switching scales on the Linear meter. Plans are in effect to replace the existing Linear channel with Gamma-Metrics Linear instrumentation equipment.

7 Figure 3-1. UMRR Core 101W Configuration 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-i 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 PREFIXES F - Standard Elements C - Control Elements BR - Bare Rabbit CR - Cadmium Rabbit S - Source Holder

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

Table 3-2. Scrams, Rundowns, and Unplanned Shutdowns Date Cause 4/20/2001 Reactor Rundown. 120% Demand Rundown. Student operator did not firmly depress Linear meter switch when downscaling the Linear Channel, which caused Linear recorder to advance 120% reading. Corrective action involved instructing the student to fnrmly depress the switch when changing scales. SRO permission granted to restart reactor.

5/21/2001 Reactor Rundown. 120% Demand Rundown. Noise spike on Linear Channel caused rundown, no corrective action taken. SRO permission granted to restart reactor.

7/23/2001 Reactor Rundown. 120% Demand Rundown. Reactor operator downscaled to soon.

No corrective action taken. SRO permission granted to restart reactor.

8/02/2001 Reactor Scram. Log-N Non-Operative Scram. Reactor operator accidentally depressed the non-operate switch on the Log & Linear drawer. No corrective action taken. SRO permission granted to restart reactor.

8/9/2001 Reactor Rundown: 15 second Rundown. While loading a fuel element into the core the reactor operator move the fuel element too close to the Log N Channel CIC detector, which caused a period spike. The control room operator instructed the operator handling the fuel element to stay further away from the CIC detector and to move the fuel element slowly by the CIC. SRO permission to restart reactor was granted.

10/19/2001 Reactor Scram: Scram occurred due to loss of ac power to the reactor building, no particular trip caused the scram. No corrective action taken. SRO permission granted to restart reactor.

11/30/2001 Reactor Rundown. 120% Demand Rundown. Noise spike occurred when up-scaling linear meter. No corrective action taken. SRO permission granted to restart reactor.

9 Table 3.2 cont'd.

1/03/2002 Reactor Rundown: 120% Full power Rundown. Noise spike from control room instrumentation caused Log N power indicator trip. No corrective action taken. SRO permission granted to restart reactor.

2/1/2002 Reactor Scram: 150% Full Power Scram. Noise spike caused Safety Channel #2 trip. Corrective action taken was to look at cable connections, reseat a ground wire, and reposition UICs 1 & 2 at 90% of full power. SRO permission to restart reactor was granted.

2/5/2002 Reactor Scram: Scram occurred due to control rod #2 dropping while critical at 12 W. #2 magnet current was 5 mA lower than during the pre-startup checklist. Magnet

  1. 2 current was turned up 7 mA for corrective action. SRO permission granted to restart reactor.

2/15/2002 Reactor Rundown: 120% Full Power Rundown. Noise spike from control room instrumentation caused trip to occur when switching from auto to manual for the auto-controller. No corrective action taken. SRO permission granted to restart reactor.

2/22/2002 Reactor Rundown. 120% Demand Rundown. Noise spike occurred while changing up scaling. No corrective action taken. SRO permission granted to restart reactor.

3/19/2002 Reactor Rundown. 120% Demand Rundown. Noise spike in Linear recorder caused rundown. No corrective action taken. SRO permission granted to restart reactor.

Table 3-3. Maintenance Date Cause 3/29/2001 Problem: Zero settings on Safety Channel meters drifted.

Corrective Action: Adjusted the zero settings.

4/20/2001 Problem: Zero settings on Safety Channel meters drifted.

Corrective Action: Adjusted the zero settings.

5/7/2001 Problem: Zero settings on Safety Channel meters drifted.

Corrective Action: Adjusted the zero settings.

5/18/2001 Problem: Noise spikes observed on both Safety Channel meters while reactor is shutdown.

Corrective Action: Reinstalled ground wire from the Safety Channel pre-amplifier to ground.

10 Maintenance cont'd.

5/29/2001 to Problem: Semi-Annual Calibration 7/27/2001 Corrective Action: Performed routine semi-annual calibration, which calibration of electronic equipment and a thermal power calibration.

6/14/2001 Problem: Zero setting on Safety Channel 1 drifted.

Corrective Action: Adjusted zero setting for Safety Channel 1.

7/30/2001 Problem: Zero settings on Safety Channel meters drifted.

Corrective Action: Adjusted the zero settings.

8/07/2001 Problem: Routine control rod visual check.

Corrective Action: Remove magnets, more than half the fuel elements, and one control rod from core for a visual inspection of the control rod. Replace control rod before removing another for inspection. Inspected three control rods. Replaced control rod, fuel, and magnets. Performed rod drop time tests.

8/9/2001 Problem: Upper connector of drive extension shaft #1 had worn threads.

Corrective Action: Replaced upper connector of drive extension shaft #1.

8/27/2001 Problem: Rod drop current for magnet #3 would not adjust lower than 28 mA.

Corrective Action: Switched vacuum tubes for magnets #2 and #3, then replaced the vacuum tube for magnet #2.

9/17/01 Problem: Safety channel zero settings drifted.

Corrective Action: Adjusted zero settings for Safety Channels 1 and 2.

10/04/2001 Problem: Auto-Controller intermittently not withdrawing regulating rod.

Corrective Action: A general check of the auto-controller cable connections and relay contacts was performed.

10/16/2001 Problem: Beam port shutter door is closing slower than normal.

Corrective Action: Beam port shutter door was removed from beam port, shutter and motor checked for proper action, and shutter reinstalled into beam port.

10/17/2001 Problem: Auto-controller not withdrawing the regulating rod.

Corrective Action: A general check of the auto-controller cable connections and cleaning relay contacts was performed.

10/23/2001 Problem: Fission chamber will not withdraw.

Corrective Action: Reconnected the steel cable that repositions the fission chamber to the motor pulley that raises and lowers the steel cable.

11 Maintenance Cont'd.

10/29/2001 Problem: Conductivity cells needed labeled.

Corrective Action: Label both conductivity cells as #1 pool and #2 demineralizer.

11/09/2001 Problem: Testing spare auto-controller.

Corrective Action: Replace auto-controller with spare, tested spare without reactor operations, and reinstalled original auto-controller.

12/10/2001 to Problem: Semi-Annual Calibration 2/08/2002 Corrective Action: Performed routine semi-annual calibration, which calibration of electronic equipment and a thermal power calibration.

12/17/2001 Problem: Joystick control for control rods 1, 2, and 3 was intermittent at repositioning control rod 3.

Corrective Action: Replaced the normally open withdraw and insert switches.

1/02/2002 Problem: Linear recorder pen stopped moving while performing a weekly checklist.

Corrective Action: Restrung the cord for the pen. Check calibration of the recorder.

1/03/2002 Problem: Linear channel and Log N channel had a discrepancy comparing the power indications on their meters.

Corrective Action: Checked both channel instrumentation with pico-amp source and repositioned the Log N CIC detector.

1/05/2002 Problem: Linear Power supply high voltage read low.

Corrective Action: Replaced the V9 vacuum tube socket.

1/17/2002 Problem: Safety Channels 1 and 2 were not reading correctly at 90% full power.

Corrective Action: Repositioned UIC detectors 1 and 2 to read 90%.

1/30/2002 Problem: Constant Air Monitor (CAM) read zero counts per minute on the CAM recorder.

Corrective Action: Replaced a transistor, zener diode, resistor, capacitor and pot in the electronic circuit of the CAM. Calibrated the CAM to a pulser.

2/07/2002 Problem: Safety Channel zero settings drifted.

Corrective Action: Adjusted zero settings for both channels and repositioned UIC

  1. 2.

2/08/2002 Problem: Safety Channel meters reading low at 90%.

Corrective Action: Repositioned UICs 1 & 2 to read 90%.

12 Maintenance Cont'd.

3/1/2002 Problem: Control rod drive #1 brake will not hold the rod in place, the rod keeps inserting into core.

Corrective Action: Replaced a spring and solenoid on the rod drive brake mechanism. Performed rod drop time test on rod number 1.

3/7/2002 Problem: Safety Channel zero settings are below zero.

Corrective Action: Reseated cable connections to the Safety Channel pre-amplifier and reseated vacuum tubes.

Table 3-4. Reactor Utilization

1. Reactor use 286.5 hrs.
a. NE Classes, Reactor Sharing, and Other Instructions 222.9 hrs.
b. Maintenance Training 63.6 hrs.
2. Time at power 105 hrs.
3. Energy generated 3833 kW/hrs
4. Total number of samples 227
5. U-235 Burned .1669 g
6. U-235 Burned and Converted .1977 g Table 3-5. Experimental Facility Use Other Than The Reactor Facility Hours Bare Rabbit Tube 13.42 hr.

Cadmium Rabbit Tube 1.24 hr.

Beam Port 2.00 hr.

Other Core Positions 1.965 hr.

Total 18.625 hr.

13 4.0 PUBLIC RELATIONS The reactor staff continues to educate the public about applications of nuclear science.

Over 2,171 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 2001-2002 DATE PARTICIPANTS NUMBER 04/13/01 UMR Preview Day 18 04/2-4/21/01 UMIR Preview Day 56 4/02/01 UMC NE 404, Advanced Reactor Laboratory 6 05/19/01 Graduation Blue Glow Tour 44 05/21/01 Fort Leonard Wood Tour 16 06/08/01 UMR Preview Day 32 06/11/01 Jackling I Institute 42 06/21/01 Intro to Engineering 70 06/25/01 Intro to Engineering 44 07/12/01 UMR Police Dept - NAA of Paint Samples 7 07/13/01 UMR Chemistry Academy, (PRIMO Ahec) 24 7/19-7/20/01 Intro to Engineering 42 07/23-7/30/01 Nuclear Engineering Summer Camp 115 7/27/01 Intro to Engineering 12 08/20/01 Fort Leonard Wood Tour 22 10/16/01 Rolla Police Department Tour 7 10/18/01 ANS Teacher Workshop 8 10/20/01 UMR Family Day 33 10/29/01 Miner Monday Open House 3 12/03/01 Missouri High School Teachers & Counselors Tour 8 12/07/01 Blue Glow Open House 13 12/17/01 Offsite Emergency Training - Emergency Scenario 9 02/16/02 Boy Scouts Tour 52 02/18/02 President's Day Open House 47 02/21/02 Basic Engineering TEAMS Competition Tour 48 02/25/02 UMC NE 404, Advanced Reactor Laboratory 9 0318/02 UMC NE 404, Advanced Reactor Laboratory 8 03/25/02 Fort Leonard Wood Tour 26 TOUR FOR 2001-2002 821

14 5.0 EDUCATIONAL UTILIZATION a total of 2,936 The reactor facility supported several UMR courses in the past year for This usage is a student-hours. The number of UMR students utilizing the facility was 287.

program. The reactor direct result of an aggressive and continuing campus wide "outreach" and two Graduate facility provided financial support for three students with hourly wages, colleges and high schools Research Assistants. Additionally, students from several universities, have used the facility.

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

The University of Missouri-Columbia Nuclear Engineering Department sent its NE 404, Spring of 2002, (for a total of "Advanced Reactor Laboratory" class to our facility twice during that they are unable to perform 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />) to participate in a wide variety of reactor experiments pm until 9:00 pm) and are with their reactor. The laboratories are held in the evening (2:00 conducted by the UMR reactor staff.

of Energy, was The Reactor Sharing Program, which is funded by the U.S. Department not have a nuclear reactor. This established for colleges, universities, and high schools which do York City at the two World Trade year, due to the September 11, 2001 terrorist activities in New immediately following this Center towers, we have restricted tours and campus class activities has been temporarily event. The number of students participating in the tours and classes in the program. Table 5 reduced to 272 students and instructors from 18 institutions participated Sharing Program. The 2 lists those schools and groups that were involved in this year's Reactor with the Admissions majority of our participants were high school students. We coordinate

15 Office to schedule high school students to see other items of interest 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 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. Student and instructor events are presently returning to the level of activities -previous to September 11, 2001 event.

Table 5-1. UIVIR Classes at Reactor lacifity 2001-2002 Reporting Period CLASS NUMBER/TITLE # OF SITIME AT ISTUDENT STUDENTS REACTOR HOURS 01/15/02 UMR NE 204 - Radiation Measurements 8 2.00 16.00 01/23/02 UMR NE 25 - Nuclear Technology Applications 7 2.00 14.00 02/13/02 UMR NE 25 - Nuclear Technology Applications 6 1.00 6.00 04/17/01 UMR NE 204 - Radiation Measurements 5 3.00 15.00 04/19/01 UMR NE 204 - Radiation Measurements 5 2.00 10.00 04/24/01 UMR NE 204 - Radiation Measurements 6 3.00 18.00 04/30/01 UMR Physics 6, Dr. Pringle, Instructor 16 1.50 24.00 11/14/01 UMR NE 25 0 Nuclear Technology Applications 7 2.00 14.00 12/10/01 UMR NE 25 - Nuclear Technology Applications 7 2.00 14.00 02/20/02 UMR Chemistry Labs, Terry Bone 89 5.00 445.00 02/21/02 UMR Chemistry Labs, Terry Bone 41 2.00 82.00 03/06/02 UMR Engineering Mgmt. 386- Safety Mgmt - Dr. Susan Murry 31 1.00 31.00 03/20/02 UMR NE 25 - Nuclear Technology Applications 8 1.00 8.00 Fall 2001 UMR NE 304, Reactor Laboratory I 10 36.00 360.00 Fall 2001 UMRNE 306, Reactor Operations 6 36.00 216.00 Fall 2001 UMR Physics student, Kurt Koch, Irrad. Electronic Semi conductors 1 65.00 65.00 Fall 2001 UMR Nuclear Engineering Special Projects-Irrad. of Glass Blocks 2 10.00 20.00 Fall 2001 UMRR Student Operator Training 7 40.00 280.00 Fall 2001 UMR CE490, Research (Ellen England, Filtration of Contam. Water) 1 50.00 50.00 Winter 2002 UMR NE 306, Reactor Operations 6 36.00 216.00 Winter 2002 UMR NE 308, Reactor Laboratory II 9 80.00 720.00 Winter 2002 UMRR Student Operator Training 7 30.00 210.00 Fall 2001 UMR Physics Res. w/Dr. Bertino-Reactor Core- Gamma Exposure 1 42.00 42.00 Winter 2002 UMR Physics Res. W/Dr. Bertino-Reactor Core- Gamma Exposure 1 60.00 60.00 Totals 287 512.50 2936.00

16 Table 5-2. Reactor Sharing Program (2001-2002)

DATE PARTICIPANTS NUMBER 04/11/01 Pleasant Hope High School, Lori Whitlock, Instructor 25 04/19/01 Parkway West High School, Ellen Wilke, Instructor 22 04/24/01 Southwest Missouri State University, Dr. Robert Mayanovic, Instructor 6 04/25/01 Waynesville High School, Christaine Dornhoefer, Instructor 33 05/01/01 Waynesville High School, Michelle Hill Peters, Instructor 23 06/13/01 Licking High School, Barry Reynolds, Instructor 10 07/06/01 Central High School 30 10/23/01 ast Central College, Laura Deason, Instructor 10 11/06/01 Steelville High School, Charles Hawkins, Instructor 21 11/14/01 Pleasant Hope High School 14 11/27/01 Ash Grove High School, Sally Keith, Instructor 13 03/12/02 Hazelwood West High School, John Schmoogee & Carl Herman, Instructor 14 03/19/02 Parkway North Middle School, Ellen Wilke, Instructor 21 03/08/01 Fair Grove High School, Janet Beavers 26 Justin Miller, Jefferson City H.S., Individual Science Project 1 Kevin Johnson, West Plains H.S., Individual Science Project 1 Justin Munson, Warsaw H.S., Individual Science Project 1 Alfred Schovanez, Washington H.S., Individual Science Project 1 TOTAL 272 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.

17 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 surveys consist of 20 to 40 swipes counted separately for alpha, and beta/gamma activity. No 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. There was one shipment released on-campus consisting of 24 magnet chips containing 0.0 14 millicuries activity during this reporting period.

6.3. Routine Monitoring Forty-two reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Four (Reactor Staff) have beta, gamma, neutron, Luxel, optically stimulated luminescence (OSL) badges which are read twice a month. Eight staff and students have the same type badges which are read monthly. There are four area beta, gamma, neutron, Luxel, OSL badges and two personnel get TLD ring badges for extremity monitoring. There are 25 area badges assigned on campus for beta and gamma monitoring. In addition, 5 digital direct-reading dosimeters, 5 chirpers and 2 pocket ion chamber dosimeters are used for visitors and high radiation work. There have been no significant personnel exposures during this reporting period.

19 7.0 PLANS The reactor staff will be heavily involved in four major projects during the next reporting period; 1) relicensing 2) implementation and revision of the new strategic plan, 3) installing new reactor nuclear instrumentation, 4) reactor operator training program.

7.1 Administrative Changes UMRR is fully staffed. Mr. Brian Porter has filled the vacant Senior Electronics Technician position as of April 30, 2001. Mr. Porter will be training soon to become a licensed reactor operator.

7.2. Relicensing Relicensing activities will continue during the upcoming reporting period. Our present license has been extended and is valid until January, 2005. Emphasis will be directed toward the SAR accident scenarios and Emergency Plan.

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

S7.4. Instrumentation Upgrade 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 new Safety Channels, magnet power supply and Linear drawer 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.

7.5 Reactor Operator Training The first group of reactor operator trainees took the NRC examination during the week of March 11, 2002. Three trainees passed their examination and are licensed UMRR Operators, effective March 27, 2002. Four trainees did not pass part of the written examination and will retake the section they failed. This should be completed by early fall. The new operators will assist the reactor staff with operations and training efforts for the next group of trainees.

APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2001-2002 REPORTING YEAR

  • UMR REACTOR STANDARD OPERATING PROCEDURES
  • SOP: INDEX

Title:

INDEX Revised: August 1, 2001 Page 1 of 3 SOP 100-199 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational Procedures SOP 102 Pre-Startup Checklist Procedures SOP 103 Reactor Startup to Low Power SOP 104 Reactor Power Changes and Stable Operations SOP 105 Reactor Shutdown & Reactor Securing Procedures SOP 106 Restart of Reactor When It Is Not Secured Rev SOP 107 Permanent Log, Hourly Log and Operational Data SOP 109 Determination of Control Rod Worths by the Rod Drop Method SOP 110 Calibration of Control Rods by Positive Period Method SOP 111 Measurement of Core Excess Reactivity and Determination of Shutdown Margin SOP 112 Fuel Management SOP 150 Response to Alarms SOP 151 Response to a High Area Radiation Alarm SOP 200-299 Facility Operations SOP 200 Bridge Movement Procedure SOP 204 Demineralizer Regeneration SOP 206 Installation and Removal of Experimental Facilities SOP 207 Fuel Handling SOP 208 Reactor Security SOP 209 Securing the Building SOP 210 Occupying Building When Intrusion System Inoperative SOP 300-399 Special Operations SOP 301 Pool Water System SOP 302 Inspection of Control Rods SOP 305 Operation Without Magnet Contact Light Revised By: William Bonzer Approved By: Akira Tokuhiro I'm- (2ý L-

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: March 20, 1995 Page 2 of 3

7. Log books will be kept in the ee e,1-ree

-- safe, except the one currently in use, tA which may be kept on the console. If the books are removed from the control room, permission must be granted by the Reactor Manager. Any books removed shall be returned as soon as possible. IRev.

8. Only the Senior Operator on Duty may key bypass control channel automatic fumctions. The use of any interlock bypass key requires a permanent log entry for insertion 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).
9. Any abnormal behavior or abnormal change in core 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. jRev.
10. The Standard Operating Procedure (SOPs) 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.
11. The Senior Operator on Duty has the authority to instruct the reactor operator to disregard certain SOPs provided that no safety requirements are violated. (For example, SOP 305 does not have to be performed every pre-startup checklist.)
12. All surveillance time intervals referred to in the SOPs are as defined in Section 1 of, Rev.

the Technical Specifications.

13. The following procedures are to be performed by the Reactor Senior Electronics Technician or other qualified individual as determined by the Reactor Manager. A licensed operator will participate when reactor operation is involved (e.g. Rod Drop Time Measurements).

SOP 655, "Radiation Area Monitor (RAM) Calibrations" ]Rev.

SOP 800, "Semi-Annual Checklist" SOP 801, "Log N and Period Channel" SOP 802, "Linear Channel" Revised By: David FreemaaA Approved By: Albert Bolon

UMR REACTOR STANDARD OPERATTNG PROCEDURES ***

SOP: 102 TITLE: IPRE-STARTUP CHECKLIST PROCEDURE Page Revision: February 18, 2002 Page 3 of 8

10. Linear CIC Voltage: Record the high voltage (HV) and compensating voltage (CV) settings of the Linear power supply. Read the.CV setting by depressing the meter range Rev.

switch and multiplying the meter reading by 0.1. Record to the nearest tenth of a volt.

Values should correspond approximately to the following:

HV - 540 VDC CV - 2 to 8 VDC

11. a. Observe the temperature and CAM recorder "RCD" is illuminated in the upper left hand comer 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 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 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 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.

Revised By: William Bonzer Approved By: Akira Tolcuhiro

/vy.

  • UMR REACTOR STANDARD OPERATING PROCEDURES **

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Page Revision: February 1, 2002 Page 5 of 8

21. 150% Power Scram Check:
a. Withdraw shim rods to 3 inches.
b. Depress the scram test and reset buttons on safety amp and hold until the 4 red Rev.

lights come on. Observe that the scram occurs prior to 150%.

c. Verify that the rods have dropped and that the audible and visual alarms have actuated.
d. Reset the drawer and annunciator panel.
22. Log and Linear Drawer Non-Operative Scram and Rundown Test:
a. Withdraw shim rods to 3 inches.
b. Depress the NON-OPER keypad switch. Check for the Non-Operate Scram and Low CIC Voltage Rundown visual and audible alarms.
c. Verify that the rods have dropped and rod drives are running down.
d. Try to stop the rundown by lifting the shim joy stick.
e. Stop the rundown with the rundown reset button.
f. Reset the scram, rundown, and annunciator panel.
23. Period Trip Test:
a. Withdraw shim rods to 3 inches.
b. Depress and hold the PERIOD TEST keypad switch. Verify that the 30 Second Rod Withdrawal Prohibit annunciator is activated with a simulated period greater than or equal to 30 seconds.
c. Continue depressing the PERIOD TEST keypad switch. Verify that the 15 Second Rundown is activated with a simulated period greater than or equal to 15 seconds.
d. Continue depressing the PERIOD TEST keypad switch. Verify that the 5 Second Scram is activated with a simulated period greater than 5 seconds by observing a loss of magnet current and the annunciators.
e. Release the switch.
f. Reset the scram, rundown, and 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.

Revised By: William Bonzer /, Tokuhiro Approved By: Akira LA-QL \

    • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Decurter 6. 2001 C,NT RULED ANPY Page 7 of 8

1. Date
2. Initials of the Person Performing Checklist
3. Time (Console Clock)
4. Core Loading
5. P.A., Intercom, Video Monitor On
6. RAM System Check
7. Radiation Level Normal
8. Beam Port and Thermal Column Status (OPEN or SHUT) __Rev
9. Linear Channel Zero Meter Reading Scale
10. Linear C.I.C. Voltages HV (-540)

CV (-2 to 8)

11. Recorders On, Dated, "RCD" Light On Temp. & CAM Recorders
12. Core Check (Lights On) Level Check Inspect Core Source Inserted
13. Start-Up Channel Test
14. Verify FC Response, FC Inserted, Count Rate > 2 CPS
15. Log Count Rate HV Power Supply (+400 VDC)
16. Log and Power Range Test
17. Period Response Test Approved By: Akira Tokuhiro Revised By: William Bonzer

I

"**UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITL - ISL UR "

Revision: Deceffber 6. 2001 *j Page 8 of 8 II 7 7 T

10. viapetr ower n- Q 'Poaf T-tnvkrd Reset
12. LLLJA
20. Magnet Currents (milliamps) No. 1 No. 2 No. 3
21. 150% Power Scram Test Raise Rods 3 in. Push "Test" Button
22. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press Scram Test NON-OPER switch.
23. Period Trip Test
24. Manual Scram Test Raise Rods 3 in. Push Manual Scram
25. Annunciator Test, All Lights On
26. Magnets On, Rods on Insert Limit
27. Prepare Hourly and Permanent Logs
28. Detector Response Check Inspect Core Log Spike Period Spike Linear Spike Startup Channel

Response

29. Raise Rods to 6 in., Record Time in Both Logs
30. Nitrogen Diffuser Status No. I (ON or OFF) No. 2 Rev.
31. Intended Power Level
32. Announce Intention to Start
33. Pre-Startup Check Properly Completed (Lic. Op. Initials)
34. Senior Operator's Initials
35. Date Approved By: Akira Tokuhiro Revised By: William Bonzer

CONTROLLED CP,"

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 106 TITLE: Restart Of Reactor When It Is Not Secured New: August 1, 2001 Page 1 of 2 A. Purpose To be used when the reactor is shutdown to zero inches, but not secured. A restart may be initiated without an additional Pre-Startup Checklist being completed.

B. Precautions, Prerequisites, Limitations This procedure can only be used during the same day of the last completed Pre-Startup Checklist.

Verify that the daily Pre-Startup Checklist has been completed.

This SOP is not intended to be used in a hot restart situation. ( Refer to SOP 103 D. for a hot restart)

C. Procedure Complete the following steps to re-start the reactor.

1) Verify that a secure checklist has not been completed.
2) Record the time and intended power level in the permanent logbook. (The shutdown time should be in the space immediately above this entry. If not, the SRO on duty should make certain that a complete pre-startup checklist is not needed. The SRO on Duty shall verify maintenance has not been performed on the control room equipment or the reactor core structure since the reactor has been shutdown to zero inches. If maintenance has been performed, the SRO on Duty shall determine if the reactor is operable by performing a channel test, Pre-Startup Checklist, or independent test to verify the repaired equipment is operable.)

The independent test must be checked and verified by a second SRO.

3) Insert the source and inspect the core.
4) Make certain picoammeter is on the 2 watt scale.
5) Adjust the compensating voltage of the linear channel to read between 0.02 and 0.05 on the picoammeter.
6) Verify that all rods or at insert limits.

Cr,]ed BY: Ja s ckson Approved y: Aki7 Tokuhiro

Ct1 RIM LLED O UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 106 TITLE: Restart Of Reactor When It Is Not Secured New: August 1, 2001 Page 2 of 2

7) Turn recorders on and verify that rcd. is illuminated on the temperature and constant air monitor recorders and that both systems are on.
8) Adjust fission chamber to insert limit ( this SOP is not intended to be used in a hot restart situation)
9) Spike the Linear and Logn / Period CIC's. Observe the spikes on the recorders and the proper response by the fission chamber on the log count rate recorder.
10) Turn on magnet current and reset the annunciator and scram. Check magnet currents.
11) Enter the time the shim rods are at six inches into the permanent log book. The I,o6/o SRO on duty shall enteri"Permission granted to restart the reactor" into the permanent logbook '5 r C
12) Announce intentions to start reactor to desire power. Note : Initial power can not exceed 100 kW.
13) Follow procedures in S.O.P. 103 "Reactor Startup to Low Power" to attain desired power level under 100 kW.

Pieated By: Jackson Approved By: Akira Tokuhiro wyc~Z4

CONTROLLED COPY

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND Rev OPERATIONAL DATA Revised: August 1, 2001 Page 1 of 6 A. PURPOSE To provide for records of facility operation and major maintenance. Hourly logs will detail specific instrument readings while the reactor is in operation.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. The licensed Operator on Duty is responsible for the proper completion of all operational logs.
2. Any work affecting the reactor, its operation and specific use during operation must be clearly and legibly described in the Permanent Log book.
3. The Operator on Duty will report any abnormal conditions entered in the operational logs to the Senior Operator on Duty.
4. All log entries are to be made with times recorded from the console clock.
5. All scrams and rundowns shall be documented in the Permanent Log as described in SOP 150, "Response to Alarms".
6. The reactor operator may make entries in the log book when the reactor is leveled at a stable power with the Reg Rod in "Auto". Otherwise,. an operator assistant should record log entries (see SOP 102 or 103 for other conditions prior to log entries).
7. Log entries should be printed, rather than in cursive (except for signatures and initials),

and should be in black ink.

C. PROCEDURE

1. Hourly Log Entries
a. The hourly log sheet will be dated and each person (student, trainee, etc.) operating the reactor will place their signature in appropriate spaces provided at the top of the form.

Revised By: William Bonzer Approved By: a Tokuhiro SL4 JQ~i,

C40NTRLLEDCP

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND[ Rev.

OPERATIONAL DATA Revised: August 1,2001 Page 2 of 6

b. A new hourly log sheet will be started at the beginning of each operational day, or when all available columns have been filled during the current day of operation, (i.e. a new hourly log sheet is not required for each startup checklist SOP 102).
c. The following procedure steps correspond to the numbered steps on the UMRR Hourly Operating Log form.
1. Time from the console clock.
2. Person at the console, initials (student, trainee, or licensed operator).
3. Nominal reactor power level (in watts or kilowatts).
4. Linear recorder reading in percent.
5. Linear Meter Scale.
6. Reg rod in "Auto" and annunciator board reset? Yes or No.
7. Log percent power (digital meter) of the Log and Linear drawer.
8. Check Period Recorder trace for proper indications over the past 10 minutes (approximately) of operation.
9. Log and Linear drawer Power Range reading: on digital meter (%).
10. Record the Log Count Rate Recorder reading.
11. Source removed? Yes or No.
12. Diffuser pumps on? Yes or No.
13. Exhaust fans on? Yes or No.
14. Record the position of Shim Rod #1 to the nearest tenth of an inch.
15. Record the position of Shim Rod #2 to the nearest tenth of an inch.

Revised By: William Bonzer Approved By: Akira Tokuhiro L(yL&L~Ak 20-1/)2

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

PERMANENT LOG, HOURLY LOG AND Rev SOP: 107 TITLE:

OPERATIONAL DATA Revised: August 1, 2001 Page 3 of 6

16. Record the position of Shim Rod #3 to the nearest tenth of an inch.
17. Record the position of the Regulating Rod to the nearest tenth of an inch.
18. Check Radiation Area Monitors (Reactor Bridge, Demineralizer and Beam' Room) for approximately the same values observed during completion of startup checklist (SOP 102).
19. Record Reactor Bridge RAM reading in mr/hr.
20. Check Magnet Currents for approximately the same values observed (and recorded) during the startup checklist (SOP 102).
21. Record the reading on the Safety Channel No. 1.
22. Record the reading on the Safety Channel No. 2.
23. Verify that the time at which a stable power level was obtained is recorded in the Permanent Log. Other entries to the Permanent Log such as samples being irradiated, etc. should also be made at this time. (See section 2 of SOP 104).
24. Record the reactor Inlet Temperature (thermocouple 1 or 3) as displayed on the Pool Water Temperature Recorder.
25. Licensed operator initials.
2. Permanent Log Entries
a. All entries in the Permanent Log shall be preceded by the date (Use the date stamp).

Revised By: William Bonzer Approved By: Aira Tokuhiro

    • UMR REACTOR STANDARD OPERATING PROCEDURES '

SOP: -107 TITLE: PERMANENT LOG, HOURLY LOG AND I Rev.

OPERATIONAL DATA Revised: August 1, 2001 Page 4 of 6

b. During completion of the Startup Checklist (SOP 102) use the Check Out stamp and complete values as they become available. To the right of the purpose the nature of the experiment should also be shown. See the example below:

_C_ _ a) TIme Check Out.Started ME304 . Purpose 10 Z- Time Rods at 6 Inches I c___(0_ Time Reactorat .,l.-0i kw

c. Reactor power changes are made in accordance with SOP 103 and entries are made prior to the start of a power change and at the new stable power level. The example below indicates Permanent Log entries for a power change including shutdown of the reactor:

1028 Reactor started to 600W.

1030 Reactor at 600W.

1035 Reactor shut down.

d. The Sample-Experiment stamp is used to indicate the irradiation of a sample as a Permanent Log entry. This stamp will be used to indicate the production of by product material. The example below indicates the use of this stamp.

EXPERIMENT -- I-I OPERATOR CORE OR FACILITY EXPERIMENTER & START STOP TOTAL 13AMPLE TIME TIME TIME B.RT 15:!q J  ;

Note: The number in parentheses () indicates the number of samples.

Revised By: William Bonzer Approved By: Akira Tokuhixo

UMR REA' PROCEDURES SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND I Rev.

OPERATIONAL DATA Revised: August 1, 2001 Page 5 of 6

3. Operational Data (Recorder Charts)
a. Date all 3 primary recorders in accordance with SOP 102 (startup checklist) and SOP 105 (shutdown checklist).
b. Recorder chart paper is to be replaced as soon as possible after the current roll runs out. If a power change is in progress when the chart runs out, wait until the reactor is leveled out at the desired power prior to replacing the chart. During replacement use the new chart box for the old chart storage. Date both the old chart and all sides of the chart box. Place the chart on storage shelves adjacent to the control room.
c. All chart paper is retained for a period of FIVE YEARS except for the Log/Period Chart which is to be retained for the DURATION of the facility.
4. Ventilation Fan Log Entries
a. After receiving approval from SRO to start or stop a building exhaust ventilation fan, complete the requested information on the Fan Operation Log (i.e. time, fan #,

power level, etc.)

b. Fan Operation Logs are retained in the Facility Health Physics files.

Example of Fan Operation Log DATE FAN # ITIME TIME PEAK POWER/

ON OFF REMARKS 1 )5 0o 150oo C 1<v,/

k

+ 4 Revised By: William Bonzer Approveýd B:AiTkbr L J C)

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA I Rev.

Revised: A~ugSt 1.O2001 Page 6 of 6 HOURLY OPERATING LOG Date .(Start a new form each day)

Signatures: (1) (4)

(Including Licensed (2) (5)

(6"*

1. Time at Power
2. Initials - Person at Console
3. Nominal Power (W or kW)
4. Linear Recorder (%)
5. Linear Scale (W or kW)
6. Auto Set/Board Reset ( Y or N)
7. Log Level (%)
8. Period Trace Normal (f")
9. Log and Linear Power Range (%)
10. Log Count Rate Recorder (cps)
11. Source Removed? (Y or N)
12. Diffuser(s) On? (Y or N)
13. Exhaust Fan On? (Y or N)
14. Shim Rod No. 1 (inches)
15. Shim Rod No. 2 (inches)
16. Shim Rod No. 3 (inches)
17. Regulating Rod (inches)
18. Radiation Levels Normal (1-)
19. Bridge Monitor (mr/hr)
20. Magnet Currents Normal (1")
21. Power Chamber No. 1 (%)
22. Power Chamber No. 2 (%)
23. Permanent Log Entries (4")
24. Core Inlet Water Temp. (OF)
25. Licensed Operator Initials --

Revised By: William Bonzer Appro Z~d Iy: Akira Tokuhiro

CONiB L COPY UMR REACTOR STANDARD OPERATING PROCEDURES

  • SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: May 15, 2000 Page 1 of 7 A. PURPOSE The purpose of this procedure is to provide guidance for performing the Rev.

resin regeneration, associated sample collection and to make certain that regeneration will not take place until all equipment and retention tanks are in place and functional.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. THIS STATEMENT TAKES PRECEDENCE OVER ALL OTHERS IN THIS SOP AND MUST BE COMPLETED BEFORE PROCEEDING FURTHER IN THIS SOP. Rev.

Additional liquid waste retention tank(s) must be installed before any regeneration takes place. Liquid waste retention capacity must exceed volume of waste that is excepted to be generated. Valves must be installed to allow for the segregation of the different effluent. The installation of such tanks must be performed in accordance with written procedures approved by the Reactor Director. Reactor Directors' permission must be obtained prior to initiating this SOP. The Reactor Director should review this procedure for adequacy and consider the various issues associated with liquid waste discharge such as release limits, solubility (10CFR20) and pH prior to approving a regeneration.

2. Two personnel should be present dressed in lab coats and eye protection for all caustic and acid transfers.

3 The Reactor Manager shouldbe informed when the system is returned to service.

4. Ensure water flow to the make-up sump is maintained to prevent draining of make-up sump which would cause air to be sucked into the demineralizer.
5. WATCH LEVEL WHEN USING ACID AND CAUSTIC TANKS TO ENSURE THAT NO AIR IS DRAWN INTO THE SYSTEM WHEN THE LEVEL IS LOW.
7. Each step must be performed in a timely manner to prevent a faulty regeneration.
7. - EP- 23 Lhtboi
8. The numbers referred to in this procedure are the valve numbers found on the valve tags.
9. Sampling of liquids sent to the retention tank should consist of three grab samples collected at the beginning, middle, and end of each process (i.e. backwash, caustic rinse, and acid rinse).

Sampling of liquids discharged to the sewer system may consist of either grab sampling as described above or "trickle" sampling using a continuous draw sample collection technique during discharge.

Written Byaýames J c Approve& Nich as Tso lfanidis

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 308 TITLE: RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE Complete Revision: February 28. 1996 Page 1 of 2 A. PURPOSE The purpose of this SOP is to ensure that power is restored to equipment in a safe and efficient manner following a trip of unregulated and/or regulated power and to prevent damage to the equipment.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. Personnel restoring unregulated and/or regulated power should be familiar with the operation of the equipment affected.
2. A weekly check should be performed before operating the reactor at a power higher than 20 kW following a loss and restoration of power.
3. Any malfunctions or abnormality of equipment should be immediately reported to the Senior Operator on duty.

C. PROCEDURE

S

1. Reset the unregulated and regulated power supplies, which are located in the equipment room behind the console panel.
2. All annunciator lights, buzzer and 4 red lights on the safety amplifierNk44-&w-be on. [ -,'
3. Push the annunciator acknowledge button to silence the buzzer.
4. Reset the safety amplifier to extinguish the 4 red lights.
5. Reset the Linear power supply located in the control room. (Note: The power supply must warm up for several minutes before it will reset.
6. Press the annunciator panel reset button. The annunciator should now indicate a normal situation. (Note: A normal situation is indicated by all lights being extinguished, except Manual Scram, Recorder Off and Manual Operation.)

Written By: Davy em Approved By: Albert Bolon

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: [D*rcber 6. 2001 Page 2 of 5

b. communicating with and requesting assistance from the following State and Federal Agencies as required:

Missouri State Highway Patrol: (573) 368-2345 Rev

  • U.S. Nuclear Regulatory Commission, Region III:

1-800-522-3025 0 NRC Duty Officer (24 hr.): (301) 816-5100, (301) 951-0550, or (301) 415-0550 a Missouri State Emergency Management Agency:

(573) 751-2748

  • Missouri Bureau of Environmental Health: Rev.

(573) 751-6160 or (573) 751-4674 (24 hrs)

(865) 576-3131; or (865) 481-1000 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

  • Rolla Emergency Management Agency: (573)364-1213
c. notifying the University of Missouri President and requesting University Wide assistance, as needed.
d. acting as Administrative spokesman responsible for communications with the news media and city officials in the absence of both the Vice Chancellor and the Dean.
2. Vice Chancellor - If offsite consequences are expected the Vice Chancellor will be responsible for:
a. assuming the duties of the Chancellor in his absence.
b. functioning as administrative spokesman responsible for communication with the news media and city officials.
c. assisting in the coordination of Control Group activities in the planning and preparation phase.
d. notifying American Nuclear Insurers (860) 561-3433 as soon as possible Rev.

after declaration of an Alert or Site Area Emergency.

e. advising the Chancellor on problems relating to insurance and liability.

Revised By: William Bonzer Approved By: Akira Tokuhiro

19 uJJ ii

"*** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 604 TITLE: RADIOACTIVE WASTE HANDLING CRITERIA Complete Revision: March 20, 1995 Page 1 of 3 A. PURPOSE To ensure that the handling and disposal of radioactive waste is done in such a manner as to maintain personnel exposures as low as reasonably achievable (ALARA) and to assure compliance with all applicable regulations.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. To facilitate disposal, certain radioactive wastes will be segregated at the source.

Where this is the case, Health Physics will designate the wastes to be segregated, and it shall be the responsibility of the Reactor Manager to ensure that such segregation takes place.

2. The dose rate at a distance of I foot from any waste container shall be limited to 5 toren/hr. If this dose rate limit is exceeded, the waste container shall be placed in a shielded location and the Health Physicist notified. The Health Physics Staff should then remove the waste from the facility as appropriate.
3. Health Physics approval must be obtained prior to the off-site release of any potentially contaminated solid waste.
4. Contact the -Oeei at!iAl

, HeaSn- --Serv"es-Offie or Thiromentat

-Management Services Office for guidance on handling hazardous or mixed waste. ij~g

5. All liquid and gaseous discharges shall meet 10 CFR 20 requirements.
6. Wastes containing plutonium or more than trace quantities of uranium and thorium, must be segregated as required by Nuclear Regulatory Commission accountability requirements.
7. Certain wastes must be excluded from common containers due to the possibility of corrosion and/or explosion during storage or treatment. Such wastes must be collected separately and include:
a. Hydrochloric and/or hydrofluoric acids
b. All organic liquids.

C. Strong oxidizing and/or reducing agents (permanganates and organics)

Apoe B:-

Revised By: ewl Approved By: Albert Bolon

SICONTROLU 1-0 UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR TAN/i )ARD OPERATING PROCEDURES REVISED: 7-28-75 f/

TITLE: Beam Hole Facility C. Beam Tube Access After Reactor Operation Access to the beam tub e should be attempted only after the reactor has been shutdown and permission has been obtained by the reactor operations personnel. The removal of the shield plugs from the beam hole facility can be d one only when there are no elements in the reactor core or when tihe reactor bridge and core are sufficiently re moved from the beam tul e such that the pool water serves as a shield.

Refer to Se i for bz?idge movement procedure.

D. General Procedure For LJsing Beam Hole Facility /r1

1. Obtain necessary approval for utilization of facility.
2. Prepare complete se hoduale of jqprogromi,in "u"in preparation timo - I,- 6 length of run, rca telr irm-1;;

4=1Pim.q*~i

3. Remove beam hole flange and shield plugs.
4. Insert necessary sa mple, equipment etc into beam tube.
5. Insert beam hole pl ugs.
6. Bolt beam hole flange in place.
7. Advise reactor operations that experiment is ready for reactor operation.
8. When the reactor operational requirements have been completed, access to the beam tube is to be carried out according to steps (9) through (13) which follow:
9. Obtain approval from the reactor operator for removal of the shield plugs. This may require the unloading of the reactor core, the movement of the core and bridge from the immediate

.. , vicinity of the beam tube or a combination of both. See SOP

-+/--i-i- for bridge movement procedure.

10. Remove blank flange and shield plugs from facility in the presencel of the Health-Physics Officer, or Senior Operator.
11. Remove experimental material from tube.

WRITTEN BY: A.E. Elliott IAPPROVED BY: D.R. Edwardst2 e

      • IR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Revised: Deceiter 6. 2001 Page 8 of8

e. Battery 51- ffRaDI
f. High Radiation
g. Low Pool Water
h. Additional Comments:
12. Public Address System
a. Cleaned chassis as needed
b. Additional Comments
13. Hand and Foot Monitor Rev.
a. Cleaned chassis as needed
b. Perform Source Check
c. Additional Comments
14. Portal Detector
a. Cleaned chassis as needed
b. Perform Source Check
c. Additional Comments
15. Constant Air Monitor
a. Cleaned chassis and recorder as needed
b. Perform Source Check
c. Additional Comments
16. Rod Drop Test (SOP 813)
17. Power Calibration (SOP 816)
18. Thermal Column Open Alarms - Verify that the control room audio and visual alarms, and the basement red flashing light comes on when the thermal column is opened by about 1 inch. Verify that the alarms clear when the thermal column door is closed.
19. RAM Calibration - RAM Calibration shall be performed annually. Record the latest date the RAM calibration was performed. Rev.

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 (Date) or Reactor Manager (Date)

Revised By: William Bonzer Approved By: Akira Tokuhiro

J.1

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Complete Revision: March 20, 1996 Page 2 of 4

2. Connect the 'Bere-B',e- " pico-amp source to J5 of the Log and Linear drawer. I LJ Adjust current to 100% full power.
3. Reset annunciator panel.
4. Obtainthe magnet key from the SRO on Duty and have a Licensed Operator raise shim rods 3 inches.
5. Slowly increase current to obtain a reading of 120%.
6. Observe from the Log digital display when the 120% rundown occurs.
7. Observe the 120% Full Power rundown and annunciator. Record values.
8. Reset the annunciator panel.
9. Remove the magnet key from the console and return it to the SRO on Duty.
d. Log and Linear Detector/Cable Check - Discharge each cable through a multimeter by connecting the meter probes to the outer shield and center conductor. Use the highest voltage scale and observe the voltage decline to 0 volts. Measure the resistance of the detector cable with an electrometer at 1000 VDC. Record the results.

The cables should read about 1010 ohms. Again discharge the cables with the multimeter.

e. Drawer Alignment - Perform the steps in Section 4.3.1, "Low Voltage Power Supplies" from the Log and Linear drawer equipment manual.

High Voltage/Compensating Voltage Check

1. Measure HV at J6.
2. Adjust A4R4 as needed to measure 540 VDC.
3. Adjust A4R4 to a lower voltage until the non-operate LED turns on and the Low CIC Annunciator panel alarms.
4. Record the HV at J6 that the trip occurred at.
5. Record the voltage measured from A4TP 10-A4TP 1.
6. Verify that the keypad non-operate switch LED illuminates. Record the results.
7. Adjust A4R4 to measure 540 VDC at J6.
8. Reset annunciator panel.
9. Verify and record the non-operate keypad switch LED goes off.
10. Record the IV at J6. The high voltage at J6 should be 540 VDC +/- 1 V.
11. Record the voltage measured from A4TP10-A4TP .
12. If the Low CIC Voltage trip point needs to be adjusted follow the Log and J

Revised By: William Bonzer Approved By: Albert Bolon

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Complete Revision: March 20, 1996 Page 3 of 4 Linear equipment manual steps 4.3.2.1 and 4.3.2.2.

13. Measure compensating voltage at J7. Adjust A5R4 to 5.8 V as needed.
14. Record compensating voltage level at J7. The compensating voltage should be 5.8 VDC +/- 1V.
15. Record voltage at A5TP10-A5TP1.

Log Amplifier Alignment

1. -For eurrents less h-5=0-nA connect the Keithley pico-amp source to J5 of /

the Log and Linear drawer. Use the readings from the Keithley pico-amp I )

source for the current settings. -AI eeiey-<e te--5-.<em

-am~~-.m withf the0 Picoamp seuce~ and 35. Use-.theMeA.ig

_89-9n-4@8i cihly ic ap eerrcnt meter far the eturrcnt settings . UTse-the fi~ tc "1-101127-L 150N pVIc-aup souree for the higlter euffeitt piee-antp-Pe~atifgs-

2. Complete in the Log Displays Table of SOP 800 for the listed current levels.
3. If alignment is necessary follow steps 4.3.3.1-9 of the Log and Linear equipment manual. Repeat Step 3 following any adjustment in alignment.

Period Alignment

1. Perform Section 4.3.4, "Period Amplifier" in the Log and Linear drawer equipment manual. These adjustments determine the accuracy of the period.

When performing these steps, the following guidance should be used.

a. Set the oscilloscope to read 50 mV/cm (DC mode) and 0.2 sec/cm.
b. Use the single sweep display mode with internal triggering.
c. Save the ramp using the "save mode". After the ramp has been saved, use the cursor feature to automatically read the voltage change for a time span of about 1 second. (Note: The cursor feature provides a more accurate measurement than manually reading the scope.)
2. Complete the Period Displays Table on the Semi-Annual Checklist.

Linear Amplifier Alignment

1. Use the ",Bnzer Box" pico-amp source connected ,-ththe

-Aue ý pfter to the Log and Linear drawer at J5.

2. Connect the voltage meter to ATP10-ATP1.
3. Apply the currents listed in the Linear Displays Table of SOP 800 and Revised By: William Bonzer Approved By: Albert Bolon

-:JLJu 'J U UU Ii~

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Complete Revision: March 20, 1996 Page 4 of 4 record the displayed readingsof, i ,,J

4. If the Linear Amplifier circuit needs aligned, follow steps 4.3.5.1-3 of the Log and Linear equipment manual.
f. Isolated Outputs - Adjust the zero and span on each isolator, as necessary, for equal inputs and outputs.
g. Keypad Switches - Fill out the Keypad Switch Table by depressing the indicated switch and recording the associated readings.
h. Discharge the detector cables at the connectors and the corresponding jacks at the drawer. Reconnect the detector HV, CV, and signal cables. Have an independent knowledgeable person verify cables are properly connected.
i. The person that performed this calibration procedure shall initial and date that the calibration has been properly completed.

Revised By: William Bonzer Approved By: bert Bolon

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 W' WJ KLYCHECK Revised: Decerber 6. 2001~ IPage 4of1I1 2.4. Low CIC Voltage Linear Power Supply

a. Withdraw rods to 3 inches.
b. 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. The under voltage alarm light shall actuate at a Rev.

voltage equal or above 44OVDC.

c. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown in progress).
d. 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.
e. Record value of the trip point.

2.5. Regulating Rod on Insert Limit on Auto

a. Withdraw the Shim/Safety rods to 3 inches and Reg Rod to 0.5 inches (use the shim range bypass).
b. Adjust Linear recorder setpoint so that "auto permit" comes on.
c. With regulating rod at approximately 0.5 inches withdrawn, switch the Reg Rod control to "Auto" and reset the annunciator.
d. Adjust the red pointer (auto setpoint) to be slightly below black pointer (Linear signal) so that an insert on the Reg Rod will result.
e. When the Reg Rod reaches insert limit observe rods inserting, Manual Operation and "Reg Rod insert limit on Auto" annunciators.
f. Acknowledge and reset rundown and annunciators.
g. Record results.
3. Scrams 3.1. Bridge Motion Scram
a. Withdraw rods to 3 inches.
b. Release bridge lock and move the bridge a small distance.
c. Observe a Bridge Motion and Manual Scram annunciators illuminate and that the rods scram. Acknowledge the annunciator alarm.
d. Return bridge to original position and reset all annunciators. Re-insert the magnets.
e. Record results.

Revised By: William Bonzer Approved By: Akira Tokuhiro

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 1, 2002 Page 5 of 11 3.2.A. Non-Operative Scram and Rundown Test

a. Withdraw rods to 3 inches.
b. Depress the "NON-OPERATE" switch.
c. Verify rods have dropped and control rod drives are inserting.
d. Release the "NON-OPERATE" switch.
e. Verify the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated.
f. Reset the Scram, Rundown, and Annunciator panel.
g. Depress and release the test switches listed below. For each verify that the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated. Reset the scram and annunciator panel after each switch is checked. The following switches are to be checked:
  • 1 mA switch,
  • 0.1 gA switch,
  • 10 pA switch, and
  • 3 SEC switch.

3.3. 150% Full Power Scram

a. Withdraw rods to 3 inches.
b. Depress the scram test and reset buttons on safety amp and hold until the 4 red R lights come on. Observe that the scram occurs prior to 150%.
c. Push reset on the Safety Amp., acknowledge the annunciator and observe the 150% Full Power Scram annunciator and Magnet Contact lights are off.
d. Reset annunciator and insert the magnets.
e. Record results.

3.4. Manual Scram

a. Withdraw rods to 3 inches.
b. Push Manual Scram button.
c. Acknowledge the annunciator, observe Manual Scram light and all magnet contact lights are off. Push Scram Reset, Annunciator Reset and insert the magnets.
d. Record results.

Revised By: William Bonzer Approved By: Akira Tokuhiro

CA-00ROLIED COPY

    • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: May 19, 2000 Page 8 of 11

8. Building Evacuation Alarm
1. Announce over the PA, "The Building Alarm will sound. This is a test. Do not evacuate the building."
2. Push the Building Evacuation Alarm and note the audible alarm.
3. Reset Building Evacuation Alarm by pushing Scram Reset.
4. Announce over building PA "Test complete. Acknowledge all further alarms."
9. Nitrogen Diffusers
1. 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.
2. Shutdown the #1 pump and repeat step 1 for the #2 nitrogen diffuser.
3. Record results on form SOP 810.
10. Beam Port Warning Lights
1. Announce over the building PA. "Attention personnel, stand clear of the Beam Port".
2. Open the Beam Port by holding the beam port control switch in the open position until the "Red" (open) light comes on.
3. Acknowledge the annunciator alarm and verify that the Basement Level Warning Light (Flashing Red) activates.
4. 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.
5. Announce over the Building PA "Beam Port secured". Complete SOP 810.
11. S-liutldown Check - Complete a-Shntdewf Checklist (SOP 1-35) to ensure that all A console equipment is secured.
12. Security System Check Inform the campus police (4300) that the security system will be checked.

12.1. Security Door

a. Hold in or close dead bolt on the security door. Rev.
b. Reset the alarm system.

Revised By: William Bonzer Approved By: N* holas fanidis cV'

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: Decenter 6. 2001 5 - Page 10 of 11 WEEKLY SURVEILLANCE CHECKLIST Date Performed

1. Rod Prohibits Alarms (,/) Prohibit (')

1.1. Recorder Off

  • Source Range recorder
  • Linear recorder
  • Log/Period recorder
  • Temperature recorder Set Point Alarms (/) Prohibit (/)

1.2. Source Range <2 cps _ .cps 0 OF 1.3. Inlet Temperature >135 F 1.4. Shim Rods below shim range N/A N/A

2. Rundowns 2.1. RAM Syste Rundown Bldg. Alarm Remote and Set Point Alarms (/) Local Alarm (/*

Station Set Point Bridge mrem/hr mrem/hr Demin mrem/hr N/A Basement mrem/hr N/A Rundown Set Point Alarms (/)

2.2. 120% Demand rundown 2.3. 120% Full Power Rundown 2.4. Low CIC Linear P.S. VDC

(Ž440VDC) IRev.

2.5. Regulating Rod on Insert Limit on Auto N/A Alarms (./) Scram (f)

3. Scrams 3.1. Bridge Motion Scram 3.2. Log and Linear Non-Op. Scram
  • Non-operate switch (raise rods 3")
  • 1 mA switch 0 0.1 jiA switch
  • 10 pA switch
  • 3 sec switch 3.3. 150% Full Power Scram 3.4. Manual Scram Revised By: William Bonzer Approved By: Aldra Tokuhiro

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: Icenrber 5. 2001 Page 11 ofIl j 9RtiLLEI copy Date

4. Period Trips Set Point Alarms (/') Trip Operational (./)

4.1. 30 Sec RWP 4.2. 15 Sec Rundown 4.3. 5 See Scram

5. Rod Drop Currents Drop Current Contact Light Off (./) or SOP305 5.1. Rod#1 mA 5.2. Rod #2 mA 5.3. Rod #3 mA
6. Test of Annunciators 6.1. Interlock Bypass Alarms (/) Operational (/)
  • 30 second period
  • Radiation area high
  • <2 CPS 6.2. Servo Limits: Lin. Rec. Reading  % Permit on at  % Permit off at  %

6.3. Pool/Demineralizer Resistivity Pool Demin Local Alarm (if) Annunciator (/')

_M*-cm _ Mf-cm

7. "Reactor on" Lights Operational (/)

7.1. Main Entrance 7.2. Control Room 7.3. Beam Room Alarm Onerational (,/t:

8. Building Evacuation Alarm Onerational
9. Nitrogen Diffusers Pump Operational (.') Indicator LiQht On (V)
  1. 1
  1. 2
10. Beam Port Warning Light: Annunciator (V) Flashing Light (./)
11. Secure Check List: Completed (./):

IRev

12. Security System Check: Completed (V):
13. Checklist Completed By: Date
14. Reviewed and Approved:

Manager or Director (Rev. 12/06/01)

Revised By: William Bonzer Approved By: Akira Tokuhiro

APPENDIX B.

REVISED SAR CHANGED DURING THE 2001-2002 REPORTING YEAR

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