ML20138G892

Progress Rept for Univ of Missouri-Rolla Nuclear Reactor Facility Apr 1996-Mar 1997

ML20138G892
Person / Time
Site:	University of Missouri-Rolla
Issue date:	03/31/1997
From:	Freeman D MISSOURI, UNIV. OF, ROLLA, MO
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9705070002
Download: ML20138G892 (58)

Text

l y a Nuclear Reactor UNIVERSITY OF MISSOURI-ROLLA Roita,Mo"sN 4I Missouri's Technological University Telephone (573) 341-423e FAX (s73) 341-4237 April 29,1997 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 fmd enclosed the Annual Progress Report 1996-97 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, l gt YU avid W. Freeman Reactor Manager lp ,

Enclosure l l

xc: Marvin Mendonca, Project Manager (NRC) l RegionIII Administrator (NRC) I Dr. A. E. Bolon, Reactor Director (UMR)

Dr. John Park, Chancellor (UMR)

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

Mr. Ray Bono, Director, Health & Safety Services (UMR) i Dr. Robert Mitchell, Dean, School of Engineering (UMR) {g 9, ,

Dr. Glen Haddock, Interim Dean, College of Arts and Science (UMR)

Mr. Bruce Ernst, American Nuclear Insurers

/AW i American Nuclear Insurers, c/o Librarian Dr. Nord Gale, Chairman, Radiation Safety Committee (UMR) l Radiation Safety Cc,mmittee University of Missouri-Columbia Research Reactor Nuclear Engineering Faculty Reactor Staff l p o

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PROGRESS REPORT l

1996-97

! UNIVERSITY OF MISSOURI-ROLLA i

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NUCLEAR REACTOR FACILITY i

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l PROGRESS REPORT l FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY l

1 April 1,1996 to March 31,1997 Submitted to l

The U.S. Nuclear Regulatory Comnussion and ,

The University of Missouri-Rolla I Albert E. Bolon, Director l David W. Freeman, Manager Nuclear Reactor Facility University ofMissouri-Rolla Rolla, Missouri 65401 4

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SUMMARY

During the 1996-97 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 323 hours0.00374 days <br />0.0897 hours <br />5.340608e-4 weeks <br />1.229015e-4 months <br />. The major pan of this time, about 92%, was used for class instruction, j research, and training purposes.

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

t i l The reactor facility supponed several UMR courses over the year for a total of 2,259.5 l

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student-hours. The reactor was visited by about 2,901 visitors during the past year. There were l l 759 participants in the U.S. Depanment of Energy Reactor Sharing Program.

l The reactor produced 5743.14 kilowatt-hours of thermal energy using approximately 0.2964 grams of uranium. A total of 176 samples were irradiated at the reactor with most of them being analyzed in the Reactor Comning Laboratory.

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u Table of Contents

1. 0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . I 1.1 Background Information . . . .

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.l.2 Facility Status . ......... ........................... .......... 2 l 1.2.1 General . . ........ .............. .......... ............... 2 I

i 2.0 REACTOR STAFF AND PERSONNEL . . . . . . . . . . . . . ............ ...... 5 2.1 Reactor Staff . . . . . . . ............ ... .. ................. .5 2.2 Licensed Ooerators . . . . . . . . . . . . . ......... . ................. . 5 2.3 Radiation Safety Committee . . . . . .. ....... .. ... ........... .6 2.4 Health Physics . . . . . . . . . . . . ..... . ,. .. ..... .. ..........7 3.0 REACTOR OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . .......... ...... .8 4.0 PUBLIC RELATIONS ...........................................15 5.0 EDUCATIONAL UTILIZATION . . . . . . . . . . . . . . ................. . . . . 16 6.0 REACTOR HEALTH PHYSICS ACTIVITIES . . . . .. ...............,,...19 6.1. Routine Survevs . . . . . . . ..... ............... ... ............19 6.2. By-Product Material Release Survevs . . .. ................ . 19 6.3. Routine Monitoring . . . . . . . . . . . ............................'20 6.4. Waste Disoosal . . . . .......... . ... ....... .. ....... .... 21 6.5. Instrument Calibrations . . ... ..... ................... ..... . 21 7.0 PLANS . . . . . ....... .. .. ........... ....... ... ..... ...... 22 7.1. Strategic Plan . . . . ............ ... ... ........ ......... . . 22 7.2. Instrumentation Ungrade . . . . . . . ............ ..................22 7.3. Relicensing ..... . ... .... ... . . .. . . . . . . . . . . . 22 APPENDIX A. STANDARD OPERATING PROCEDURES CHANGED DURING THE 1996-1997 REPORTING YEAR l I

APPENDIX B. REVISED SAR PAGES FOR THE 1996-97 REPORTING YEAR i i

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List of Tables -

Table 3-1. Core 10lW Technical Data . . . . . . ............... ............ . ... 9 Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns . . . ........... . . . . . . . 11 l l Table 3-3. Maintenance . . . . . . . . . . . . . . . . . . . . . . . ......... .... .... . . . . . . . 12 ,

l Table 3-4. Experimental Facility Use Other Than The Reactor . . . . . . . . . . . . . .. . . . . 14 ,

l Table 3-5. Reactor Utilization . . . . . . . . . . . . . . . . . . ..... . .......... ...... 14  ;

l Table 4-1. Public Relations Program . . ...... ..... ................. .. .. 15 l Table 5-1. UMR Classes at Reactor Facility i l 1996-97 Reporting Period ....... ...... ............. .. . . . . . . 17 i Table 5-2. Reactor Sharing Program . ....................................18 List of Figures Figure 3-1. UMRR Core Configuration . . . . . . . . . . ... ..... .. ........ . . 10 t

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1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Ro!!a Reactor (UMRR) Facility for the period April 1,1996 to March 31,1997.

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

1.1 Background Information The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9th,1961. The 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 Laboratoy. The initiallicensed 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 (HEU, 90% U-235) fuel to low-enriched uranium (LEU,19.8% U-235) fuel.

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

The fuel is MTR plate-type fuel.

l The facility is equipped with several experimental facilities including a beam port, thermal column, pneumatic rabbit system and several manual sample irradiation facilities. Additionally, t

the facility is equipped with a counting laboratoy that has gamma and alpha spectroscopy

capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, and modern spectrum analysis software. The alpha spectroscopy system i

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2 consists of a surface barrier detector and data acquisition equipment.

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

1.2.1 General During the summer of 1996, the HEU fuel was successfully shipped to Savannah River thus officially completing the LEU conversion project. Twenty-eight fuel elements were shipped in three separate shipments. The shipments went smoothly with no significant problems. We would like to extend a special thanks to the staff at the Missouri University Research Reactor r (MURR) who provided much support to make the project a success.

We are continuing efforts to upgrade our console using grant awards from DOE combined with money directly from reactor funds. Funds received from DOE combined with matching funds from our reactor account total to $167,000. We plan to replace our existing five channel NI system with a three channel system. We have purchased and received 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 presently 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 provisions of 10CFR50.59. Parallel with this, we will be submitting a request to NRC for approval for desired console revisions that may involve "unreviewed safety questions" In Febmary,1997, we replaced our old radiation area monitoring (RAM) system with a new Eberline RAM system. A detailed 50.59 review was submitted to the UMR Radiation Safety

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l Committee and was approved with the determination that no unreviewed safety question was involved. The change required minor revisions to pages 3-46 and 3-47 of the SAR (see Appendix

! A). The new system is performing well and we are quite pleased with it.

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In August,1996, we replaced the strip chart recorder associated with the constant air monitor (CAM). A detailed 50.59 review was submitted to the UMR Radiation Safety Committee l 1

and was approved with the determination that no unreviewed safety question was involved. The l change required a minor revision to S AR page 3-48 (Appendix A). The new recorder is I

performing well.

The Reactor Facility was audited in June,1996, by an independent auditor from the University ofIllinois Reactor Facility. We have entered into an agreement with both the University ofIllinois and the University of Missouri-Columbia to rotate audits. We feel this has been very beneficial to all facilities involved. l The reactor staff has continued to review the operation of the Reactor Facility in an effort I

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 l 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 1

Physics 4 & 5, " Concepts in Physics"; Chemistry 8, " Qualitative Analysis Laboratory"; Physics 107, " Modern Physics"; Physics 322, " Advanced Physics"; Chemical Engineering 261, 1

I " Introduction to Environmental Engineering"; Chemistry 2, " General Chemistry Laboratory";

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I Mechanical Engineering 229, " Energy Conversion"; Life Science 352, " Biological Effects of

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Radiation"; Chemistry 251, " Intermediate Quantitative Analysis"; Chemistry 355, " Instrumental Methods Laboratory"; and Engineering Management 386, " Safety Engineering Management" In April,1996, the reactor was utilized to produce Y-90 for Dr. Roger Brown of the Life Sciences Department for his research involving arthritis.

Much effort has been invested over the past year in revising SOPS to improve our >

operations and efficiency. The following is a list of SOPS revised during the reporting period:

SOP INDEX Index (Page 3 only)

SOP 100 Preamble SOP 102 Pre-Startup Checklist Procedures (Pages 4 and 8 only)

SOP 105 Reactor Shutdown & Reactor Securing Procedures (Pages 2 and 4 only)

SOP 112 Fuel Management SOP 150 Response to Alarms (Page 1 only)

SOP 207 Fuel Handling (Page 1 only)

SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7 only)

SOP 507 Emergency Procedures - Administrative Responsibilit ies (Page 2 only)

SOP 615 Radiation Work Permit (Page 1 only)

SOP 655 Radiation Area Monitor (RAM) Calibrations SOP 704 (Deleted)

SOP 710 Insertion and Removal of Experiments (Pages 5 and 7 only)

SOP 800 Semi-Annual Checklist (Page 8 only)

SOP 807 (Deleted)

SOP 810 Weekly Check (Pages 3,7, and 11 only)

The above listed SOPS are provided in Appendix B.

Efforts are currently underway to revise the facility's Emergency Plan to reduce the number of emergency categories. The facility's Physical Security Plan is also being revised to reflect the shift from a " moderate significance" to " low significance" facility as a result of shipping the HEU fuel offsite.  ;

A large effort will be initiated to begin the facility's relicensing process. The current license extends until November 20,1999.

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5 l 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff  :

i Name Title r

Albert E. Bolon Director David Freeman Reactor Manager ,

Linda Pierce Senior Secretary .

William Bonzer Senior Electronics Technician  ;

James Jackson Senior Lab Mechanic Hatem Khouaja2) Reactor Operator 2.2 Licensed Ooerators l Name License .

Albert E. Bolon Senior Operator -

4 David Freeman Senior Operator Hatem Khouaja2) Senior Operator l William Bonzer Senior Operator  :

i James Jackson Reactor Operator  !

Jason McDaniel4 Reactor Operator

" Terminated effective June 8,1996.  ;

2) Terminated effective July 8,1996, i i

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6 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/12/96, 9/27/96,12/17/96, and 3/14/97 during the reporting period. The committee members are listed below:

Name Deoartment Dr. Nord L Gale (chairman) Life Sciences i

Mr. Ray Bono (secretary, ex-officio, Occupational Health and non-voting) Safety Services Dr. Mark Fitch Civil Engineering Dr. Oliver K. Manuel Chemistry Dr. Alben E. Bolon Reactor Director Dr. Nick Tsoulfanidis Radiation Safety Officer Dr. Edward Hale Physics Dr. Arvind Kumar Nuclear Engineering l Mr. David Freeman (ex-officio, Nuclear Reactor non-voting)

Mr. Randy Stoll Director, Business Services 1

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2.4 Health Physics i

1 Health Physics support is provided through the Occupational Health and Safety Senrices (formerly the Environmental Health and Risk hianagement) Department which is organizationally  ;

1 l independent of the Reactor Facility operations group. Health Physics personnel are listed below:

1 Name Title  ;

I Dr. Nick Tsoulfanidis Radiation Safety Officer l hir. Ray Bono Director, Occupational Hea.th &

Safety Services and Campus Health Physicist hir. Brian Smith

• Safety Specialist hir. Chad Littlen HP Technician 2

hir. Darrell Liles > HP Technician his. Rebecca SteinmanM HP Technician hir. Brian Richardson') HP Technician David Wells HP Technician Scott Gizzie HP Technician David Alford 3 HP Technician UTerminated effective 5/3/96.

2 Terminated effective 9/12/96.

3 Terminated effective 5/24/96.

' Terminated effective 1/29/97.

UEmployed effective 1/27/97.

0 Employed effective 3/3/97.

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8 3.0 REACTOR OPERATIONS t

Core designation 10lW 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 f i

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 i n

conditions.

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

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

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i 9 l Table 3-1. Core 101W Technical Data i 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.

l 10 Figure 3-1. UMRR Core Configuration DATE July 28.1992 LOADING NUMBER 101W ,

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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 CR F-5 F-6 F-7 BR 1 2 3 4 5 6 7 8 9 KEY TO PREFIXES F - Standard Elements

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C - Control Elements BR - Bare Rabbit CR - Cadmium Rabbit S - Source Holder

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11 Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns Dait Cause 04/17/96 Unplanned Shutdown. Reactor power was being increased from 600 W to I kW.

During power increase, rod #1 dropped, shutting the reactor down.

Cause: Control Rod #1 dropped due to insufficient magnet current.

Corrective Action: SR.O on duty granted permission to increase magnet current and to restart reactor.

l 11/06/96 Unplanned Shutdown. During reactor stanup to 10 W, control rod #2 dropped l due to AC power flicker to building.

l Cause: Flicker in building AC power caused control rod #2 to drop.

Corrective Action: SRO on duty observed Rod #2 dropped due to an AC power flicker. No corrective action was necessary. SRO permission to restan was granted.

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I 12 Table 3-3. Maintenance Haig Cause 05/20/96 Problem: Magnet #1 magnet contact light would not turn off. Reactor was shut down and secured at the time of the problem.

Corrective Action: Magnet #1 light switch has not worked for years and cannot be repaired or replaced. Removed Magnet #1 light bulb from its socket. Performed a visual Rod Drop Test for Control Rod #1. (Note: The inoperable magnet contact light switch was discussed during the last NRC inspection. As a result of those discussions, the Tech Specs were amended (Amendment 14) to remove reference to the magnet contact lights.)

05/22/96 Routine Semi-Annual Calibration of reactor instmmentation - Calibration completed successfully.

06/24/96 Problem: Magnet #1 has failed while reactor was shut down.

Corrective Action: Removed Magnet #1 from pool. Repaired and reinstalled Magnet #1. Performed R.od Drop Time Test for Control Rod #1.

07/08/96 Problem: Magnet #1 failed while reactor was shut down.

Corrective Action: Removed Magnet #1 from pool. Repaired and reinstalled Magnet #1. Performed Rod Drop T;me Test for Control Rod #1.

07/15/96 Problem: Magnet #1 failed while reactor was shut down.

Corrective Action: Removed Magnet #1 from pool. Repaired and reinstatied Magnet #1. Performed Rod Drop Time Test for Control Rod #1.

07/18/96 Problem: Magnet #1 failed while reactor was shut down.

Corrective Action: Removed Magnet #1 from pool. Identified and replaced leaking swage-lock connection in assembly that had been causing previous failures.

Repaired and reinstalled Magnet #1. Performed Rod Drop Time Test for Control Rod #1.

12/19/96 Problem: Startup Channel did not respond properly during Pre-Stanup Checklist.

Reactor was shut down when problem was identified.

Corrective Action: Repaired the pre-ampliner for the Startup Channel.

12/26/96 Routine Semi-Annual Calibration of reactor instrumentation - Calibration completed successfully.

02/17/97 Installation of new RAM system - Installation performed without any problems.

Calibrated the RAM system and performed post installation test of trip functions and operator training of new RAM system before routine reactor operations.

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02/18/97 Problem: Loss of Log N signal. Reactor was in pre-stanup tests. Period l annunciators activated when Log N signal returned to normal. Reactor was shut I l down when problem was identified, i l Corrective Action: Replaced a barrel connector for the Log N signal cable. SRO '

j permission to restart was granted. Log N signal monitored by isolated computer equipment 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day for months following repair; No reoccurrence

_i identified. J l- 02/19/97 Problem: Shim Range #2 light flickers causing a rod withdrawal prohibit. l Corrective Action: Replaced the Shim Range #2 micro-switch.  !

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14 Table 3-4. Experimental Facility Use Other Than The Reactor Facihty Hauts Bare Rabbit Tube 7.11 hr.

Cadmium Rabbit Tube 0.17 hr.

Beam Pon 2.72 hr.

Other Core Positions 2.78 hr.

Total 12.78 hr.

Table 3-5. Reactor Utilization

1. Reactor use 322.57 hr.

a. NE Classes, Reactor Sharing, and Other Instructions 296.00 hr.

b. Maintenance Training 26.57 hr.

2. Time at power 145.78 hr.

3. Energy generated 5743.14 kW/hr

4. Total number of samples 176

5. U-235 Burned 0.2501 g i

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6. U-235 Burned and Converted 0.2964 g

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i 15 4.0 PUBLIC RELATIONS The reactor staff continues to educate the public about applications of nuclear science.

Over 2,901 persons visited the facility during this reporting period. Tour groups are typically given a brief orientation and/or dernonstration 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 06/10/96 UMR Jackling Institute 43 06/17/96 UMR Jackling Institute 33 06/24/96 UMR Jackling Institute 39 09/23-26/96 UMR Chemistry Labs 645 10/04/96 UMR Chemistry Labs " Blue Glow" 30 10/12/96 UM-Rolla Day 82 10/19/96 UMR Parents Day 89 11/26/96 General Gill Tour. Ft. Leonard Wood 16 12/06/96 UMR Offsite Emergency Training 14 02/13/97 UMR Basic Engineering 53 02/17/97 UMR President's Day Open House 32 03/07/97 UMR Reactor Blue Glow Tours 130 03/22/97 UMR Spring Open House 80 03/28/97 UMR American Nuclear Society Student Conference 13 03/31/97 UMC NE 404, Advanced Reactor Laboratory 7 I

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16 5.0 EDUCATIONAL UTILIZATION The reactor facility suppo ted several UMR courses in the past year for a total of 2,259.5 student-hours. The number of UMR students utilizing the facility was 892. 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 one post-doctorial student. 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 April,1997, (for a total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) 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 ofEnergy, was established for colleges, universities, and high schools which do not have a nuclear reactor. This year,759 students and instructors from 28 institutions participated in this program. Table 5-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of our participants were high school students. We 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 Center,

17 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 ,

l university and hopefully sparking some interest in our campus.

4 l Table 5-1. UMR Classes at Reactor Facility ,

1996-97 Reporting Period

! DATE CLASS NUMBER / TITLE #OF TIME AT STUDENT

. STUDENTS REACTOR HOURS  !

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., (h rs) j 04/23/96 UMR Phyf 3 E. 1 Modern Physics 7 0.5 3.5 -

, 04'30/96 UMR NE 204. Nuclear Radiation Measurements 8 2.0 16.0 ,

Fall 1996 UMR NE 304. Reactor Laboratory I 8 53.0 424.0 Fall 1996 UMi1 NE 306. Reactor Operations 3 36.0 108.0 Fall 1996 UMR NE n90, Research (Eric Stevenson - Thermal 1 255.0 255.0 l Power Calibration) 09/23-26/96 UMR Chemistry Labs 645 0.5 322.5 10/04/96 UMR Chemistry Labs " Blue Glow" 30 0.5 15.0 11/25/96 UMR NE 105. Introduction to Nuclear Engineering 5 0.5 2.5 .

12/11/96 UMR Physics 107. Modern Physics 49 0.5 24.5 Fall 1996 UMR Physics 322 - Adv. Physics Lab 1, J. Gray, 3 33.0 99.0 P.Berryhill B. White, lnd Project (F-Centers)

Winter 1997 UMR NE 306. Reactor Operations 3 36.0 108.0 Winter 1997 UMR NE 308. Reactor Laboratory 11 7 60.0 420.0 L Winter 1997 UMR NE 490, Research (Eric Stevenson - Thermal 1 255.0 255.0 l Power Calibration) i Winter 1997 UMR NE 490, Research (David Freeman - Genetic 1 80.0 80.0 i Algorithm Unfolding) 01/23/97 UMR NE 204. Nuclear Radiation Measurements 16 3.0 48.0 ,

02/03/97 UMR Life Science 352. Biological Effects of Radiation 13 1.0 13.0 ;

02/05/97 UMR Life Science 352. Biological Effects of Radiation 14 1.0 14.0 02/13/97 UMR Basic Engineering 53 0.5 26.5 l 02/24/97 UMR EngMgmt 386. Safety Engineering Management 25 1.0 25.0 {

TOTAL 892 819 2259.5 l I

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18 Table 5-2. Reactor Sharing Program (1996-1997)

DATE PARTICIPANTS NUMBER 04/10/96 Rolla Middle School- Special Needs. Anita Keck, instructor 23 04/12/96 Rolla 5th Grade Martha Spurlock, instructor 24 04/16/96 Southwest Missouri State University. Dr. Robert Mayanovic, instructor 8 04/17/96 Mt. Vernon High School, Charles Bowman, Instructor 17 04/17/96 Steelville High School Charles Hawkins. Instructor 18 04/18/96 St. James High School, Jim Jenkins, Instructor 14 04/23/96 Kate Brown. Individual Project. Whitfield High School 1 04/24/96 Crossroads High School. Tanda Pommier. Instructor 35 04/25/96 Whitfield High School. Tom Rodgers. Instructor 37 05/01/96 New Gateway & Hickson Jr. High Schools Barbara Howard. Contact 36 l 05/02/96 Vienna High School Geraldine Fritchey, Instructor 4 05/03/96 Potosi 8th Grade, Alan Ziegler, instructor 12 l 05/15/96 Raymondville Jr. High School, Ron Antle. Instructor 29 06/21/96 Vienna High School, Paula Brian Contact 37 10/15/96 Ralph Bunch International Studies Middle School. Barbara Howard. Contact 16 10/15/96 Hazelwood Jr. High School 19 10/22/96 Crocker High School. Laura Jay, instructor 29 10/23/96 Rolla Technical lnstitute Radiography. Maggie Ogden, Instructor 15 10/29/96 Dixon High School, Bernard Rowden. Instructor 13 10/29/96 Mack's Creek High School. Lisa Mandina, Instructor 23 10/31/96 Southwest Missouri State University, Dr. Robert Mayanovic, instructor 7 l 11/05/96 East Central College Debbie Schatz,inskuetor 6 l 11/12/96 St. Charles. West High School, Rebecca Teague, Instructor 36 11/13/96 Higginsville High School. Art Ozias, instructor 15 l 11/22/96 Washington High School. Rick Swentker. Instructor 87 l 12/05/96 Fairview Elementary School. West Plains. Regina Kissinger, instructor 37 12/10/96 Summersville High School, Joni Appleton. Instructor 9 01/29/97 Rolla Jr. High School (8-9 Grade) 13 j 02/18/97 Thomas Jefferson High School John Hambacker, instructor 18 l

02/18/97 Salem High School Science Club Joe Hackel, Instructor 14 l 1

Winter 97 Andrea Bone. Individual Project. Potosi High School, Bill Nelson, Instructor 1 Winter 97 Sara Adams. Individual Project. St. James High School, Jim Jenkins. Instructor 1 Winter 97 Ellen Eye. Individual Project. Potosi High School. Bill Nelson, instructor 1 Winter 97 Emily McKinney. Individual Project. Potosi High School, Bill Nelson. Instructor 1 03/04/97 Hazelwood Central High School, Cathy Sylve, Instructor 24 03/05/97 Hazelwood West High School, Gail Haynes. Instructor 22 03/18/97 Lebanon High School, John Sode. Instructor 48 03/21/97 Crowder College Upward Bound High Schools. Tiffany Slinkard, Instructor 9 TOTAL 759

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19 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 detectio'n 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 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. Bv-Product Material Release Surveys There were no shipments of by-product material released off-campus from the reactor facility during this reporting period. )

J d.

20

?

6.3. Routine Monitorine t

' Twenty-three reactor facility personnel and students involved with operations in the

.react or acf ility are currently assigned film badges. Four are read twice per month (Reactor Staff) 1 l

. and nineteen are read once per month. There are four area beta-gamma / neutron badges assigned.

l .

L Thirty campus personnel and students are assigned beta-gamma Elm badges, and frequently TLD [

ring badges for materials and X-ray work on campus. There are 15 area monitor and 3 spare l l  !

badges assigned on campus. In addition,5 digital direct-reading dosimeters, 5 chirpers, and 4 ,

ion-chamber dosimetere are used for visitors and high radiation area work. There have been no  ;

i significant personnel exposures during this reporting period.  !

l

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

millirem.  ;

Airborne activity in the reactor facility is monitored by a fixed-filter, particulate continuous air monitor (CAM) located in the reactor bay. Low levels of Argon-41 are routinely detected during operations.

l Pool water activity is inonitored monthly to ensure that no gross pool contamination or i fbel cladding rupture has occurred. Gross counts and spectra oflong-lived gamma activity are  ;

i compared to previous monthly counts. From April 1996 through March 1997 sample i concentrations averaged 1,39E-6 pCi/ml.

f J

- ~-

l t

l 21 6.4. Waste Discosal l

Release of gaseous and particulate activity through the building exhausts is determined by j i

i 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 31.722 millicuries were released into the air. The released isotope was identified as Ar-41.

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

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

t Water is analyzed for radioactive contamination and approvalis required before the water is released. During this period two 55 gallon drums of solid waste containing waste, filters, and

resins was transferred to the Dangerous Materials Storage facility. The total gross activity was

! 0.2263 millicuries.

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

I l

! i i

I i

1 I

l

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

i I

22 7.0 PLANS The reactor staff will be heavily involved in three major projects during the next reporting period; 1) development and implementation of a new strategic plan, 2) instelling new reactor nuclear instrumentation, and 3) relicensing activities.

7.1. Stratecic Plan A strategic plan is being developed to help the facility achieve its vision "to become nationally recognized as the leading educational at.d 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.

7.2. Instrumentation Ungrade 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 will require b%C approval.

7.3. Relicensing Relicensing activities will be initiated during the upcoming reporting period. Our present license is valid until November,1999. We are considering applying for a power upgrade (between 500 kW and 1 MW) as part of the relicensing effort. Several documents will have to be revised including the SAR, Tech Specs and Emergency Plan. We understand that the process is very manpower intensive and hope to make much progress during the next year.

i l

l I

APPENDIX A.

i REVISED SAR PAGES FOR THE 1996-97 REPORTING YEAR l

l

- s-, ea._. a ue -A4 44. s e a_u --.-+4 -- g 4- +4 am 4 A m.a 4 , e up. *4 .Ar.-.._u ._.

_,44a m ,a .- .-__,aa_,.A,r_, , . .-

8 9

s I

\

l .

F l

5 h

3 h

e P

y F

l .

I i

\

l p

f k

'1 l

k l

P P

P I

l i

r 1 i

)

5 l

, -.. , - , - . - . _, .-- -, y

l 3-46 due to N-16 at the pool water surface. The past surveys at full power have shown that the maximum radiation levelis about 3 mr/hr at one foot from the pool water surface.

~

3.6.2 Rad {ition Monitoring Systems The Radiation Area Monitoring (RAM) system consists of three Geiger-Mueller (GM) detectors for monitoring gamma radiation and one BF detector to monitor neutron levels. Also included in the RAM system are associated alarms, indicators, and one automatic protective function.

The function of the RAM system is to monitor radiation levels in specific areas throughout the building. These areas are 1) on the reactor bridge to monitor radiation levels above the reactor pool, 2) near the demineralizer to check for a buildup of l

radioactive ions, and 3) at the area near the thermal column and beam port, where both i i

a GM and a BF-3 detector are mounted to ensure that no increased radiation level is Rev.

2/17/9'!

present before entry is made into the basement level.

There is a remote audible and visual alarm and readout meter. Localindicators Rev.

l 2/17/9" and alarms are located in the control room where the operator can also check the l

l function of each GM monitor. This is done by actuating a solenoid that positions a small i internal check source next to the detector. This checks for proper operation and allows l for checking setpoints.

1

t l

3-47 j When the radiation in any of the monitored areas exceeds the respective setpoint, a trip is actuated in the RAM control unit causing a reactor rundown, alarm annunciation, and providing remote and control room indications of the radiation level Rev.

l 2/17/9 associated dith the RAM system. In addition, the radiation area monitor on the reactor i l

bridge has a second, higher, setpoint which actuates the building evacuation horn.

The RAM system can be by-passed by using a special key to which only a Senior Reactor Operator has an access. Located on the control console, the by-pass switch overrides the high radiation area rundown, but does not impair the radiation alarm or the building evacuation alarm.

The continuous air monitoring system consists of a Continuous Air Monitor (CAM), a recorder, and associated alarm and warning circuitry.'

The function of the CAM is to measure the radioactivity of air-borne particulates by concentrating these solids on a filter paper. Air is drawn through a special filter paper at a controlled rate. The buildup of activity on the paper is detected by a deiger-Mueller tube which gives a reading in counts per minute. The CAM is equipped with an alarm system to give audio and visual warning if the reading exceeds the alarm setpoint.

The C AM is located in the reactor bay area, where it takes 1

l

3-48 in air, and sends a remote signal to the recorder in the control room. :tev.

-4/28/97 1

4 O

APPENDIX B.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 1996-1997 REPORTING YEAR

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX

Title:

INDEX Page Revision: February 17, 1997 Page 3 of 3 SOP 651 - Con: amination Survey SOP 652 Pool Water Tritium Analysis SOP 653 Sealed Source Leak Test SOP 654 Measurement of" Ar Concentration in the Reactor Building Air SOP 655 Radiation Area Monitor (RAM) Calibrations

- SOP 700-799 Experiments SOP 701 Request for Reactor Projects SOP 702 Request for Irradiation SOP 703 Reactor Use Form SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility SOP 712 Thermal Column Facility SOP 800-899 Reactor Instrumentation SOP 800 Semi-Annual Checklist SOP 801 Log N and Period Channel

, SOP 802 Linear Channel SOP.803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier System SOP 805 Auto Control System SOP 806 Temperature Recorder SOP 809 Relay Test Rev.

SOP 810 Weekly Check SOP 811 Fire and Smoke Alarm System -

SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement SOP 816 UMRR Power Calibration SOP 818 Functional Test of Building Security System Written By: David F eenjan Approved B : David Freeman di A ' I i 96

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 100 TITLE: PREAMBLE Revised: February 6,1997 Page 1 of 2 A. PURPOSE The purpose of this document is to set forth the procedures for routine and emergency operations of the University ofMissouri-Rolla Reactor. The goal of these procedures is to -

assure that the UMRR will be operated safely, presenting no hazard to the public or to the operating staff, and secondarily, that reactor equipment will be safeguarded. It is mandatory that all personnel involved with reactor operations be completely familiar with these procedures and that these procedures be followed.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

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

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

3. The SOPS shall be reviewed annually by either the Reactor Manager, Reactor Director, or a licensed operator. Identified weaknesses, inadequacies, or recommendations for improvements should be discussed with the Reactor Manager to determine if revision to the SOPS is required.

4. Each SOP revision shall be listed on the revision form located in front of the Reactor Rev.

Manager's Controlled Copy of the SOPS. Each licensed operator shall acknowledge the revision by initiating the revision form within one month of the change. Approval authority for revisions shall meet the following requirements:

a. Changes that do not change the originalintent of the procedures may be made with the approval of the Facility Director.

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

Revised By: David a and James J ckson Approved B avi reeman pr b . Ot2 ' ' '.Q"1\ }s #

"* UMR REACTOR STANDARD OPERATING PROCEDURES **

• SOP: 100 TITLE: PREAMBLE Revised: February 6,1997 Page 2 of 2

5. Handwritten revisions to the Controlled SOPS may be made provided the following conditions are satisfied:

a) Handwritten revisions are clearly legible and neatly made in I.ed ink in b.01h Control SOPS.

b) Handwritten revisions are reviewed and approved by both a Senior Operator and the Reactor Director. Review and approval shall be documented by initialing and dating the revision.

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

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

1 Written By: Davi ree an and James Ja sop Approved By: avi Fre man a *

()tm:A/l , trWA- ait u

/

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Page Revision: February 17, 1997 Page 4 of 8

16. Log and Power Range Test:

a. Depress and hold the 10pA keypad switch on the Log and Linear drawer.

b. Verify receipt of the "Non-Operative" scram and " Low CIC Voltage" rundown audible and visual alarms.

c. Ve.-ify that the digital meter and recorder read within the tolerances of the following table. The bargraph should generally follow the digital display and recorder.

Keypad Switch Log Scale (%) Power Range (%)

Rev, 10pA 9.0 E 1.1 E -5 0-l%

0.1aA 9.0 E 1.1 E 1 0-l%

1mA 9.0 E 1 - 1.1 E 2 90 - 100 %

d. Release the switch and reset the annunciator board.

e. Repeat Steps a. through d. for the 0.1 uA and 1 ntA switches.

17. Period Response Test:

a. Depress and hold the 3 SEC keypad switch.

b. Verify receipt of the "Non-Operative" scram and " Low CIC Voltage" rundown audible and visual alarms.

c. Verify that the Period bargraph, digital meter, and recorder all read about 3 seconds.

d. Verify that the 30 second,15 second , and 5 second period annunciator alarms are actuated.

e. Release the switch. Clear the annunciator panel.

18. Turn on the magnet power using the key switch. Push the Scram Reset button to energize the magnets. Reset the annunciator panel.

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

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

Revised By: William Bonzer Approved By: D an l

L U N r.41.i 3 h ##  !

• • • UMR REA'CTOR STAND ' 'D OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUI ECKLIST PROCEDURE Page Revision: February 6,1997 Page 8 of 8

20. Magnet Currents (milliamps) No I No 2 No. 3 21.150% Power Scram Test Raise Rods 3 in. Push

" Test" Butten

22. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press Rev.

Scram Test NON-OPER switch.

23. Period Trio Test

24. Manual Scram Test Raise Rods 3 m. Push Manual Scram 25 AnnunciatorTest, AllLichts On 26 Mamets On. Reds on Insert Limit

27. Precare Hourly and Permanent Lees

28. Detector Response Check Insoect Core Log Scike Period Spike Linear Spike Startup Channel

Response

29 Raise Rods to 6 m. Record Time in Both Loss

30. Nitrogen Dt.Tuser Status No. I No.2

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

. m and Ja .eg Jackson Approv < B Freeman Revised is By:@D w ,ra 4w /*

• • • UMR REACTOR STANDARD OPERATING PROCEDURES *** '

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Page Revision: February 17,~1997 Page 2 of 4

6. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (1 button to left) when the Linear Recorder decreases to about 8% of the present scale.

Operation at high power levels will prevent returning to lowest allowed scale (2 watts) and therefore this step is continued only until rods reach their insert limit.

7. Maintain Log Count Rate Recorder > 20 cps by inserting fission chamber.

8. V/ hen the rods are fully inserted to their insert limits (green lights):

a. Return " OPERATE / SHUTDOWN" switch to " OPERATE" or, b. Returnjoysticks to the " NEUTRAL" position.

9. Reactor is now " SHUTDOWN" D. " SECURING" OF REACTOR Refer to form SOP 105.

1. Use date stamp.

2. All Shim Safety and Reg Rod Insert Limit (Green) Lights on.

3. Turn magnet key 90 degrees CCW and remove from console. Hand key to SRO on  !

I Duty.

4. Turn off the Log Count Rate, Linear, and Log / Period recorders. Place date at the top of each recorder chan (use date stamp).

5. Push Annunciator " RESET" The " MANUAL SCRAM", " RECORDERS OFF" and

" MANUAL OPERATION" Annunciators will remain on.

6. Turn the Reactor Bridge intercom switch to the off position (button up). Rev.

7. Return " OPERATE / SHUTDOWN" switch to " OPERATE".

8. Turn TV monitor off.

Revised By: William Bonzer Approved By: David Fre bVj$twu, 0 l9 />G 4

1 1

• • • UMR REACTOR STANDARD OPERATING PROCEDURES "*

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Page Revision: February 17, 1997 Page 4 of 4 SECURE CHECKLIST

,i

1. Date

2. All Rods on Insert Limit

3. Magnet Power OtTand Key to SRO

4. Recorders OtTand Dated

5. Reset Annunciator

6. Reactor Bridge Intercom Off 7 Shutdown Switch to Operate S. TV Monitor Off

9. Nitrogen Diffusers Off

10. Vent Fans Off Rev.

I1. Rabbit System Secured

12. Time Completed

13. Operator's Initials

14. Senior Operator's Initials Revised 2/17/97 i

l' Revised By: William Bonzer Approved By: Davi Freeman vmA9 < .z.w

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

l l

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 112 TITLE: FUEL MANAGEMENT Revised: February 6,1997 Page1of1 I 1

1. An ' individual will be designated in writing as the fuel custodian. He will be responsible for the reactor fuel and special nuclear materials. His duties will be to take physical ,

inventory as required by the NRC (annually) and to report production and consumption of special nuclear material as required by DOE (twice yearly).

2. A physical inventory will be made at intervals prescribed by the NRC (at present, yearly).

The custodian or his designee shall satisfy himself(preferably by direct examination) that the report contains all elements on previous inventory plus items received less items shipped. This inventory will be reponed and transmitted to the Reactor Director.

3. Records of the reactor power history will be maintained in such a manner that the total Rev.

kilowatt-hours for the reactor core can be calculated.

4. Burn-up and production of special nuclear material will be reported at intervals as [

prescribed by the DOE (at present twice yer.rly).

i e

i s

b Approved gy:,pavid reeman Revised By: vid Free y nu dJ- e Jackson

1. 4p l

a. . _ . . . . . . .

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 150 TITLE: RESPONSE TO ALARMS Page Revision: February 17, 1997 Page1of4 A. PURPOSE To provide for the proper operator response to alarms while the reactor is operating.

B. PRECAUTIONS. PRE REOUISITES. UMITATIONS

1. Refer to SOP 501," Emergency Procedures - Building Evacuation" for response procedures to a building evacuation alarm.

2. Refer to SOP 151, " Response to a High Area Radiation Alarm" for response procedures to a High Area Radiation Alarm.

3. Authorization to restart the reactor following a scram or rundown can only be made Rev.

by the Senior Reactor Operator on Duty.

C. SCRAM RES.PONSE PROCEDURE

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

a. Acknowledge the alarm.

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

c. Verify power is decreasing appropriately.

d. Fully insert all rod drives.

e. Notify the SRO on Duty.

f Record the following information in the permanent logbook:

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

I Revised By: William Bonzer Approved By: Davi reem LVE((cal., f ngy j/

"* UMR REACTOR STANDARD OPERATING PROCEDURES * *

• SOP: 207

Title:

FUEL HANDLLNG 1 Page Revision: February 6,1997 Page1 of7 l

-A. Purnose:

To provide for the safe and efficient movement of fuel elements and control rod fuel elements to and from the core and the Fuel Storage Rack.

B. Precautions. Prerequisites. and Limitations:

1. All rearrangements of the core, fuel movement, and associated Health Physics Rev.i monitoring, or other actions involving fuel shall be under the direct supervision of  ;

a Senior Reactor Operator.

2. All fuel movements shall be logged in the permanent log book. l

3. Prior to any fuel movement, a completed Transfer Order Form must be filled out '

and approved by either the Reactor Manager or Reactor Director.

I

4. When moving fuel elements, the fuel handling tool must be kept in a vertical attitude. ,

5. A licensed operator shall visually confirm that there are no unoccupied internal lattice positions in the core before a new core is taken critical.

6. When loading to a new core configuration, measure the core excess reactivity, shutdown margin, and rod worths prior to exceeding a power of 1 kW. Log this  !

information on a Core and Back Storage Form. Rev/

t

7. When loading to a new core configuration that involves a reactivity change greater than 0.2% delta-k/k or changes in control rod locations, excess reactivity and shutdown margin must be determined for both the "W" and "T" modes.

l Revised By: J e Jackson Approved By: David Fr W M

• " UMR REACTOR STANDARD OPERATING PROCEDUPES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Page Revision: July 25, 1996 Page 7 of 7 INR REACTOR EMERGENCY PHONE LIST Reactor Staff HOME WORK David Freeman, Mgr., SRO 364-7269 341-4384 William Bonzer, Sr. El. Tech., SRO 368 3727 341-42.21 Albert Bolon, Dir., SRO 364-1961 341-4746 Ray Bono, Health Physicist 364-5728 341-4240. 4_1Qi,4403 l***

Jim Jackson, Sr. Lab Mechanic, RO (573) 699-4897 341 4291 Rev-Linda Pierce. Sr See (573)265-3738 341-4236 University Administrative Staff

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

2. Vice Chancellor for Admin. Services, Mohammad H. Qayoumi 308-1067 341-4_122 Rev.

3. Dire. tor, UMR Police, William Bleckman 364-1294 341-4_14j

4. Director, Physical Plant, Marvin Patton 364-6278 341-1252 lRev.

5. Director, Health Service - Infmnary, Dwight

Deardeuff,

MD 364-0809 341-4233

6. Dean, School of Mines and Metallurgy, Lee W. Saperstein 368-3782 341-4153 7 Radiation Safetv Officer Nick Tsoulfanidis 341-3595 341-4745 Local UMR University Police 341-4300 341 41.11 Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9 911 Rolla Emergencv M'inagement A2encv 9 911 lRev.

State Agencies Missouri Highway Patrol 368-2345 Missouri State Emergency Mgt. Agency (24 5 ?.) Rev.

(573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 biissouri Bureau of Enviromental Eoidemioloev (573) 751-6160 (573) 751-2748 (24 hrs)

Federal A9encies NRC, Lisle, IL, Region 111 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 (301) 415-0550 Other American Nuclear Insurers (860) 561-3433 Rev.

Radiation Emercencv Assistance Center (423) 576-3131 (423) 481-1000 (24 hrs)

Revis:d 07/25/96 Revi. sed By:

p David eem jm Approved By p., y ., aga, lbert-B lon

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Page Revision: February 17, 1997 Page 2 of 5 -

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

• Missouri State Highway Patrol: 368-2345

• U.S Nuclear Regulatory Commission, Region III:

1-800-522-3025

• Missouri State Emergency Management Agency: Rev.

(573) 751-2748

• Missouri Bureau of Environmental Epidemiology:

(573) 751-6160 or (573) 751-2748 (24 hrs)

• Missouri Department of Natural Resources (24 ' . emergency number): 634-2436

• Radiation Emergency Assistance Center (Oak Ridge, TN):

(615) 576-3131; or (615) 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: 364-1213

c. notifying the University of Missou-i 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 peparation phase.

d. notifying American Nuclear Insurers (203) 561-3433 as soon as possible 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: Davi eman I,LIESS d > d..,9 . lwo Y'

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 615 TITLE: RADIATION WORK PERMIT Page Revision: February 17, 1997 Page 1 of 6 A. PURPOSE to ensure that personnel who do maintenance or repair work on equipment which may be radioactive or contaminated with radioactive material do such work in a controlled fashion, using proper procedures, and wearing proper protective clothing. To reduce worker exposure to as low as is reasonable achievable (ALARA). To document both job control and radiation exposures.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. This SOP will apply only when radiation levelis greater than 5 mrem /hr at 2 feet from the part involved.

2. Any maintenance or repair work that is to be done on a piece of equipment that is expected to be radioactive, shall have Radiation Work Permit (RWP) Form SOP 615 completed to the extent possible, before the actual work proceeds.

3. Workers shall wear radiation monitoring equipment.

4. Regardless of the radiation level, good maintenance practice should prevail. For example, radiation protection procedures should be applied and additional pocket dosimeters, ring badges, eye protective devices, gloves, etc. should be worn.

5. This SOP does not apply to students or other researchers handling radioactive samples. Those experimental procedures are covered by SOP 601.

lRev.

6. After the preliminary portion of the RWP checklist has been completed, it must be reviewed and approved by the Campus Health Physicist and the Reactor Manager or the Reactor Director before the actual work can begin. .

7. The RWP must be leeible Except for the signatures, entries should be printed. Black ink is preferred.

8. Completed RWPs will be stored in retrievable manner by the Campus Health Physicist (HP).

Revised By

William Bonzer Approved By: Dat 'd Freem.

a p bO3Uuh, hewp ,

~

• " UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised: February 17, 1997 Page 1 of 6 A. PURPOSE To provide for the eflicient calibration of the fixed Radiation Area Monitors and to minimize personnel exposure during the calibration.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. The RAMS are to be calibrated annually.

2. The Cs-137 source shall be kept inside the shield. Only the plug will be removed from Rev.

the shield when the detector is to be exposed to the Cs-137 source.

3. The person who handles the Cs-137 source must wear a minimum of a pocket dosimeter and a film badge.

4. The person who handles the neutron source shall wear a neutron dosimeter. Ring badges are optional but advisable.

5. The person who handles the source should minimize their exposure time in close proximity to the source.

6. The reactor must be shutdown and only authorized personnel allowed in the calibration area during the calibration to prevent accidental exposure while the sources are being handled. If a whole body dose > 100 mrem could be received, high radiation area Rev.

controlis required.

7. Nctify the Reactor Manager prior to performing this procedure.

C. PROCEDURE - GAMMA RAM CALIBRATION -

1. Calculate Source to Detector Distances: Calculate source to detector distances to prodde target dose rates of 2 mrem /hr,20 mrem /hr, and 200 mrem /hr. Use the inverse Rev.

2 square law (DR i/DR 2= d 2/d2 i) and the exponential decay law (DR, = DRoe *).

The Cs-137 source (SN5049) was certified to read 114.4 mrem /hr at a distance of 1.64 ft (19.68 inches) on July 23,1979. The halflife of Cs-137 is 30.17 years.

Revised By: William Bonzer. Approved By: Dav' reeman L U b'$L+m su P ra.1gy

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised: February 17, 1997 Page 2 of 6 Using the above information the source to detector distances are calculated as follows:

. 23e d = (19. 68)

DR e I

d = source to detector distance (inches).

DR = target dose rate (i.e.,2 mrem /hr,20 mrem /hr, and 200 Rev.

mrem /hr.

t = source decay time since 7/23/79 (years). l Record the calculated source to detector distances in Column 1 of the table on the Gamma RAM Calibration Form.

2. Dial up the alarm setpoints on each ILOI channel to read greater than about 500 mrem /hr (refer to the equipment technical manual for adjustment).

3. Disconnect the detector cable from the detector. Remove the detector from its location. Rev.

Connect the extension cable from the detector cable to the detector. Place the detector and the shielded source in convenient locations that are a minimum of about one foot above the floor. The detector and source should be the same height above the floor.

4. Place the source at the calculated distances from the RAM, remove the plug from the shield, and stand away from the source to minimize exposure during the calibration.

(Note: the plug has the larger diameter disc.) Take care not to ." aim" the source in the direction of personnel.

5. Exposure levels in the immediate area shall be determined with hand-held instmments when the plug is first removed and again when it is put back in its shield to ensure the radiation levels are ALARA.

6. In the control room, verify that the RAM rnding is within 20% of the target dose rate.

If the RAM reading is not within i 20%, aahst the RAM calibration according to the equipment technical manual Section V.E.3-c.1-7 page 36.

7. Record the readings in the control room in mrem /hr in the table provided in the Gamma RAM Calibration Form.

Revised By: William Bonzer Approv d By: eeman l*"

LQLE5% y

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised: February 17, 1997 Page 3 of 6

8. Repeat the above procedure for all three RAM's.

9. Reset the alarm setpoints as follows:

Location Set Point Function Rev.

Reactor Bridge 15 mrem /br Rundown 20-25 mrem /hr Bldg. Evacuation Demineralizer 15 mrem /hr Rundown Experiment Room 15 mrem /hr Rundown

10. Verify that the setpoints are correct using the alarm test buttons.

I1. Verify that all readings are within 20% of the calculated values.

12. The completed form is to be approved by both the Reactor Manager and Health Physicist.

D. PROCEDURE - NEUTRON RAM CA LIBRATION

1. Calibrate the Neutron RAM using Pu-Be source M-169.

2. Fillin the " calculated mR/h" column on the " Neutron RAM Calibration Form" based on Rev.

the year using the following table (Note: Values presented below are from UNRR-97-1, W. Bonzer):

DISTANCE iTAR (inches) 1995 to 1999 2000 to 2004 2005 to 2009 2010 to 2014 2015 to 2019 2020 to 2024 12 117 mR/h 120 mR/h 121 mR/h 122 mR!h 123 mR/h 123 mR/h 24 37 mR/h 38 mR/h 38 mR/h 38 mPdh 39 mR/h 39 mR!h 36 22 mR/h 23 mR/h 23 mR/h 23 mR/h 23 mR/h 23 mR/h Revised By: William Bonzer Approved B . vid Fr eman iGEli.., $ n

• • • UMR REACTOR STANDARD OPERATING PROCEDUlwS *"

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised: Februa ry 17, 1997 Page 4 of 6

3. Assemble the neutron calibration rig adjacent to the detector. (Note: the calibration is Rev.

specific to the source-to-detector orientation of the neutron calibration rig. If different source-to-detector orientations are used, the calibration values will have to be recalculated - see UMRR 97-1 (W. Bonzer).

4. The person handling the source should handle it remotely by using the extension handle provided with the source.

5. Place the source in the neutron calibration rig at the different distances from the detector, then stand away from the source to minimize exposure during the calibration. (Note:

distances refer to the center-to-center distance for the detector and source.)

6. Exposure levels in the immediate area shall be determined with a hand-held neutron survey meter when the source is first exposed and again when it is put back in its shield to ensure the radiation levels are ALARA.

7. Record the values displayed in the control room in units of millirems per hour (mR/h) on the " Neutron RAM Calibration Form"

8. Verify that all readings are within about 20% of the calculated values. It is understood that the logrithmic output of the neutron RAM may be difficult to read to within 20%

of certain values. In such instances, the person performing the calibration should use their bestjudgement in reading the meter.

9. If the Neutron RAM fails to meet the calibration specifications, adjust the Neutron RAM calibration according to the equipment technical manual,Section V.E.3.c.1-7 page 36.

10. Set the alarm setpoint to less than or equal to an indicated 20 mrem /hr.

I1. The completed form is to be approved by both the Reactor Manager and the Health Physicist.

Revised By: William Bonzer Approved avid reeman l Q(5o i,, ih , # ##

w

l *

"* UMR REACTOR STANDARD OPERATING PROCEDURES **

• SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised: February 17, 1997 Page 5 of 6 Gamma RAM Calibration Form Source (SN 5049) Decay Time (since July,1979): (years)

Calculated Source Target Dose Measured Dose Rates to Detector Distance Rate Reactor Bridge Demin Level Beam Room (inches) (mrem /hr) '

(mrem /hr) (mrem /hr) (mrem /hr)

Rev.

2 0.4 20 4 200 40 _

Alarm setpoints reset verified (Initials) i All readings are within 20% of Target Dose Rates. (Initials)

Calibration Performed By: Date / /

Approved By: Date / /

Reactor Manager Approved By: Date / /

Health Physicist 1

Revised By: William Bonzer Approv - v: Davi Freeman  ;

A LUS 04 *

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALBRATIONS Revised: February 17, 1997 Page 6 of 6 Neutron RAM Calibration Form -

I a

Calibration Source: Pu-Be (SN: M-169)

Distance Calculated Meter Reading Rev.

(inches) (mR/h) (mR/h) 12 24 1

36 )

i

)

Verify alarm setpoint s 20 mrem /hr. (Initials)

All readings are within about 20% of calculated values. (Initials) i i

Calibration Performed By: Date /_/

I Reactor Manager Approved By: Date / /

Health Physicist l l

! Revised By: William Bonzer Approved By: Davi Free an I w u x ,, p' 1 1

t _ - _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___________ ____________ _____ __ ____ __ -__ ___________L

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERBIENTS Page Revision: February 17, 1997 Page 5 of 7

4. Removal of Stringer- Reactor Operating

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

" Request permission to remove stringer from Grid Position C8"

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

c. The experimenter shall remove the stringer slowly being alert to any signs of sticking or other complications.

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

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

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

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

SOP 601.

5. Insertion and Removal of Stringer - Reactor Shutdown

a. A stringer sample may be inserted into the core region when the reactor is shut down under the direction of a Licensed Operator.

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

c. Prior to reactor startup, the Reactor Operator will visually inspect the stringer for proper positioning.

d. The stringer may be removed from the core region with the reactor shut down only under the direction of a Licensed Operator.

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

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

SOP 601.

Revised By: William Bonzer Approved By: Dav' ~eman

< n b>e n O k ,[ M

"* UMR REACTOR STANDARD OPERATING PROCEDURES "*

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERIMENTS Page Revision: February 17, 1997 Page 7 of 7

6. Removal Of the Void Tube from the Core Periphey

a. Immediately prior to removing the void tube, the experimenter shall request permission from the Reactor Operator to remove the void tube from a particular location. Example: " Request permission to remove void tube from Grid Position C8".

b. The experimenter shall receive the operator's verbal approval prior to removing the void tube.

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

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

The void tube should be moved from the core region to the front of the gridplate keeping it barely above gridplate level.

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

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

7. Post Irradiation Handling of the Void Tube.

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

b. When removing the void tube from the pool follow SOP 601. Rev. ;

1 l

[

Revised By: William Bonzer Approved By: Dav' ree n L U N ea*,.. 0.cyn JY"

~

• • • UMR litEACTOR STANDARD OPERATING PROCEDURES ***

s _ ser suu-

Title:

SEMI-ANNUAL CHECKLIST Page Revision: February 17, 1997 Page B of 8 Initial Dgg

d. Duress Alarm

e. Battery

f. High Radiation Rev.

g. Low Pool Water _

h. Additional Comments:

12. Public Address System

a. Cleaned chassis as needed

b. Additional Comments

13. Area Radiation Monitor

a. Cleaned chassis as needed

b. 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. g, 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 B v Free an

/ t# #

l(yd,'..13mge?

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. s

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Page Revision: February 17, 1997 Page 3 of 11

2. Rundowns 2.1. Radiation Area Monitoring (RMI) System

a. Withdraw rods to 3 inches.

b. Announce "The Building Alarm will sound. This is a test do not evacuate the building." on the Building PA System.

c. Have a second person check that the audible and visual alarms are functional on the remote meters located near the detectors. Using the Bridge RAM check Rev.

source switch (NORMAL green light), record the value at which the High Area Radiation rundown and Building Evacuation Alarm occur. Check the automatic reset of the RAM, reset the Building Alarm (Scram Reset Button),

acknowledge the annunciator, depress Rundown Reset and Annunciator Reset.  !

Record value of alarms.

d. Repeat step 3 for the Demin RAM and Experiment Room RAM except for the Building Evacuation Alarm. j

e. Verify that the Evacuation Alarm actuated between 20 and 25 mrem /hr.  ;

f. Verify that the High Area Radiation alarms actuated between 10 mrem /hr and i 15 mrem /hr. l

g. Upon completion of testing announce " Test Complete. Acknowledge all l further alarms," on the building PA system.

2.2.120% Demand

a. Withdraw shim rods to 3 inches. l

b. Turn off the Linear recorder,

c. Remove Linear recorder potentiometer cover and manually rotate potentiometer arm, note recorder reading when trip point is reached.

d. When inward motion of rods is verified, lower recorder below reset point, reset mndown and all alarms, turn recorder on and replace cover, and compare actual and specified trip points.

e. Record the trip point value and that the audible / visual alarms are functional.

2.3.120% Full Power

a. Depress " LOG TEST" switch.

b. Observe the Log digital display and record the value at which the 120% full power trip occurs.

c. Release the " LOG TEST" switch.

d. Observe the "120% Full Power" annunciator and audible alarm.

e. Reset the annunciator and rundown.

Revised By: William Bonzer Approved B man ax, 2

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Page Revision: February 17, 1997 Page 7 of 11

6. Test of Annunciators Rev.

6.1. Interlock Bypass Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights are functional.

6.2. Seno Limits

a. Note linear level recorder reading.

b. Change the automatic set point for auto permit by adjusting the star wheel.

k Note linear level at which the auto permit light comes on (<+2%). Continue to lower and note reading until the auto permit light goes off(> -2%).

c. Record results.

6.3. Pool Demineralizer Efiluent Conductivity High

a. Record pool and demin effluent readings.

b Check the alarm setpoint by dialing setpoint knob on the resistivity meter to match the needle reading. The local alarm (red alarm light) on the resistivity meter should come on and the console annunciator should alarm.

c. Reset the alarm to a setpoint of 0.5 MO-cm (2.5%) and switch the selector swcch to display Demin efiluent resistivity (" Meas B").

7. " REACTOR ON" Lights With magnet key inserted and all scrams reset check the " reactor on" lights (1) above console (2) at reactor entrance and (3) basement level.

Revised By: William Bonzer Approved By: . avi Freem

[Ut$$dm 0nu,1y a J 1 1

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. v,

'?*t Uhs. REACTOR STANDARD OPERATING PROCEDURES ***

i U54HsI0ll TITLE: WEEKLY CHECK Page Revision: February 17, 1997 Page ll ofil Date

4. Period Trins Set Point Alarms (A Trio Ocerational /A 4.1. 30 Sec RWP 4.2. 15 Sec Rundown 4.3. 5 Sec Scram j

5. Rod Droo Currents Dron Current Contact Licht Off(A or SOP 305 5.1. Rod #1 mA 5.2. Rod #2 mA 5.3. Rod #3 mA

6. Test of Annunciators 61 InterlockBypass Alarms (A Ocerational /A Rev.

• Shim range e 30 second period e Radiation area high e <2 CPS 6 2. Se:To Limits: Lin. Rec Reading  % Permit on at  % Permit otT at  %

6 3. Pool /Demineralizer Resistivity Pool Demin Local Alang60 Annunciator (A MD-cm M D-em

7. " Reactor on" Lichts Ocerational(A  !

i 7.1. Main Entrance 7.2. Control Room 7.3. Beam Room

8. Buildine Evacuation Alarm Onerational(A:

9. Nitrocen Diffusers Pumo Ocerational /A Indicator Licht On (A

1. 1

1. 2

10. Beam Port Warnine Lluht: Annunciator (/) Flashing Light (/)

11. Shut down Check List: Completed (/):

12. Securitv Svstem Check: Completed (/):

13. Checklist Comnteted Bv: Date

14. Reviewed and Anoroved:

Manager or Director (Rev. 2/17/97) 9 MdL:.,b,ap ,w?,,

Revised By William Bonzer Apprq ed By: David Freeman

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