ML20217P378

Progress Rept,1997-98 for Univ of Missouri-Rolla,Nuclear Reactor Facility. Rept Covers Periods 970401-980331

ML20217P378
Person / Time
Site:	University of Missouri-Rolla
Issue date:	03/31/1998
From:	Freeman D MISSOURI, UNIV. OF, ROLLA, MO
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9805060259
Download: ML20217P378 (65)

Text

University of Missouri-Rolla

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( ) Rolla, MO 65409-0630 g%,m,,>/ Phone: (573) 341-4236 FAX: (573) 341-4237 April 30,1998 Document Control Room Attention: Director Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Stop 10-D-21 Washington, D.C. 20555

Dear Sir:

Please find enclosed the Annual Progress Report 1997-98 for the University of Missouri-Rolla Reactor Facility (License R-79). This report is being filed under the reporting requirements of our Tecimical Specifications. Copies of this report are also being sent to our Regional Administrator and Project Manager.

Sincer ,

9805060259 980331 [ tut 8 PDR ADOCK 05000123 R PDR ) avid W. Freeman, PhD Reactor Manager mk

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Enclosure

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xc: Marvin Mendonca, Project Manager (NRC)

Region III Administrator (NRC) , . .

Dr. A. E. Bolon, Reactor Director (UMR)

Dr. John Park, Chancellor (UMR) f7)[.h

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

Mr. Ray Bone, Director, IIealth & Safety Services (UMR)

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

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

Mr. Bruce Ernst, American Nuclear Insurers l American Nuclear Insurers, c/o Librarian Dr. Nord Gale, Chairman, Radiation Safety Committee (UMR)

, ,, IoO Radiation Safety Committee University of Missouri-Columbia Research Reactor Nuclear Engineering Faculty Reactor Staff an equal opportunity institution

_ . . . _ _ _ . _ _ _ _ _ _ . _ . _ _ _ . . . _ _)

PROGRESS REPORT 1997-98 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY l

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l PROGRESS REPORT l

1997-98 l

UNIVERSITY OF MISSOURI-ROLLA ;

NUCLEAR REACTOR FACILITY

PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA

. NUCLEAR REACTOR FACILITY April 1,1997 to March 31,1998 Subraitted to The U.S. Nuclear Regulatory Commission and  ;

,, The University ofMissouri-Rolla l

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SUMMARY

During the 1997-98 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 395 hours0.00457 days <br />0.11 hours <br />6.531085e-4 weeks <br />1.502975e-4 months <br />. The major part of this time, about 89%, was used for class instruction, research, and training purposes.

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

l The reactor facility supported several UMR courses over the year for a total of 2814 l 1

student-hours. The reactor was visited by about 2,898 visitors during the past year. There were '

794 participants in the U.S. Department of Energy Reactor Sharing Program. 1 The reactor produced 6789 kilowatt-hours of themial energy using approximately 0.350 grams of uranium. A total of 236 samples were irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory.

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11 Table of Contents l l

1.0 INTRO DUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.1 Background Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I

1.2 General Facility Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1

2.0 REACTOR STAFF AND PERSONNEL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.1 Reactor S taff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 l . 2.2 Licensed Operators . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

! 2.3 Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2.4 H eal th Phy sics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.0 REACTOR OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 4.0 PUB LIC RELATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 l

5.0 EDUCATIONAL UTILIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 6.0 REACTOR HEALTH PHYSICS ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 6.1. Routine S urveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

6.2. By-Product Material Release Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

! 6.3. Ro utine Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 6.4. Waste Di spo sal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 6.5. )

Instrument Calibrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

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7. 0 P L AN S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 7.1. Strategic Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . . . . . . . . . 2 3 J

7.2. Instrumentation Upgrade . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 7.3. Relicensi n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . 2 3 APPENDIX A. Standard Operating Procedures j Changed During The 1997-1998 '

. Reporting Year APPENDIX B. Revised SAR Pages i For The 1997-98 Reporting Year l

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! List of Tables Table 3-1. Core 10 l W Technical Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns . . . . . . . . . . . . . . . . . . . . . . . . . . . I1 Table 3 -3. Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 ,

Table 3-4. Reactor Utilization . . . . . . . . . . . . ....................................16 I Table 3-5. Experimental Facility Use Other Thr: The Reactor . . . . . . . . . . . . . . . . . . . . . . . . 16 l Table 4-1. Public Relations Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

)

Table 5-1. UMR Classes at Reactor Facility 1997-98 Reporting Period . . . . . . . . . . . . . . . . . . 19 l

. Table 5-2. Reactor Sharing Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 1

List of Figures Figure 3-1 UMRR Core Configuration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 i

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1.0 INTRODUCTION

This progress report covers activities at the University ofMissouri-Rolla Reactor (UMRR) Facility for the period April 1,1997 to March 31,1998.

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 Backuround 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-type reactor cooled by nrtural convection flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 LW. 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 fuel.

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 modern spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment. The beanport experimental 1

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2 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.

We are continuing efforts to upgrade our console using grant awards from DOE combined 4

with money directly from reactor funds. We have replaced several pieces of console equipment under the provisions of 10 CFR50.59. We have purchased three new instrument drawers from Gamma-Metrics including 1) a wide-range log fission chamber based drawer,2) a wide-range linear CIC based drawer, and 3) a log and linear CIC based drawer. We plan to install these three drawers in our control console as direct replacements for our existing Start-up, Log N and Period, and Linear drawers under the provisions of 10CFR50.59. Parallel with this, we will be submitting a request to NRC for approval of plans to replace our existing five channel NI system with a three channel system.

In the winter of 1998, the beamport experimental facility was upgraded by the construction of a shield wall and a locking cage door to allow researchers access to computer data acquisition equipment located adjacent to the open beamport facility. Graduate student research is underway that involves setting up NE-213 and time-of-flight neutron spectrometers and a

. prompt gamma spectroscopy system.

In the Spring of 1997, $27,165 of funding was received from the Missouri Research Board for doctorial research performed by a reactor staff member on neutron spectrum unfolding. The research led to a completed dissertation with great promise of future funding.

3 Graduate research aimed at characterizing pool water temperature profiles has continued this year and utilizes newly acquired computer data acquisition equipment coupled with several temperature sensors. It is hoped that this research will lead to live time reactor power

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measurements can be made during operations. This work will be completed and will result in a Master's thesis.

4 Seed research was initiated in the area of ultra-low background alpha counting with hopes of future funding from industry sources.

The Reactor Facility was audited by an independent auditor from the MURR Reactor Facility in September,1997. There were no significant areas of concern. We have entered into an agreement with both the University ofIllinois and the University of Missouri-Columbia tc rotate audits. We feel this has been very beneficial to all facilities involved.

The reactor staff has continued to review the operation of the Reactor Facility in an effort to in Ave 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 ofdepartments across campus know how the reactor could be used to enhance course work and research. As a result, additional classes have been using the Reactor Facility to augment their programs, including Physics 4 & 5, " Concepts in Physics"; Physics 7, " Environmental Physics"; Chemistry 8,

" Qualitative Analysis Laboratory"; Physics 107, " Modem Physics"; Physics 322, " Advanced Physics"; Chemical Engineering 261, " Introduction to Environmental Engineering"; Chemistry 2, u

" General Chemistry Laboratory"; Mechanical Engineering 229, " Energy Conversion"; Life Science 352, " Biological Effects of Radiation"; Chemistry 251, " Intermediate Quantitative

4 Analysis"; Chemistry 355, " Instrumental Methods Laboratory"; and Engineering Management 386, " Safety Engineering Management".

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 were revised during the reporting

. period:

SOP 102 Pre-Startup Checklist Procedures (Pages 1 thru 8)  !

SOP 105 Reactor Shutdown & Reactor Securing Procedures (Page 3 only)

SOP 209 Securing The Building (Pages 1 and 2 only)

SOP 302 Inspection of Control Rods (Pages 1 and 2 only)  !

SOP 305 Operation Without Magnet Contact Light (Page 1 only)

SOP 310 Facility Modifications (Pages 1 and 2 only)

SOP 501 Emergency Procedures For Reactor Building Evacuation (Page 7 only) l SOP 654 Measurement of 4'Ar Concentration in the Reactor Building Air (Page 1, 2 and 3 only)  ;

SOP 710 Insertion and Removal of Experiments (Pages 2 and 3 only) l SOP 800 Semi-Annual Checklist (Page 1 thru 8 only)

SOP 810 Weekly Check (Pages 5 and 7 only)

The above listed SOPS are provided in Appendix A.

One minor revision was made to the Safety Analysis Report to reflect the fact that the constant air monitor strip chart recorder had been moved from the auxillary to the primary console. The revision is provided in Appendix B.

A large effort is being initiated to begin the facility's relicensing process. The current

, license extends until November 20,1999. Efforts are currently underway to revise the facility's l

l Safety Analysis Report, Emergency Plan and Physical Security Plan.

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'l 2.0 REACTOR STAFF AND PERSONNEL 4

2.1 Reactor Staff Name Tjiti.s

. Albert E. Bolon 2) Director David Freeman Reactor Manager and Acting Director  ;

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Linda Pierce Senior Secretary Mendy Kell 0 Senior Secretary William Bonzer Senior Electronics Technician James Jackson Senior Lab Mechanic 1

2.2 Licensed Operators  ;

Name L.icense i

Albert E. Bolon 2) Senior Operator David Freeman Senior Operator

, William Bonzer Senior Operator j James Jackson Reactor Operator I

DEmployed effective March 2,1998.

2) Inactive status 4

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2.3 Radiation Safety Committee '

The Radiation Safety Committee meets quarterly. The committ:e met on 6/24/97, 9/19/97,12/15/97, and 3/11/98 during the reporting period. The committee members are listed below:

4 Name Department Dr. Nord L. Gale (chairman) Life Sciences l

Mr. Ray Bono (secretary, ex-officio, Occupational Health and  ;

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

Mr. Randy Stoll Director, Business Services

7 2.4 Health Physics Health Physics support is provided through the Occupational Health and Safety Services Department which is organizationally independent of the Reactor Facility operations group.

Health Physics personnel are listed below:

Name Illig Dr. Nick Tsoulfanidis Pediation Safety Officer Mr. Ray Bono Director, Occupational Health &

Safety Services and Campus Health Physicist l

Mr. Brian Smith Safety Specialist '

David Wells 0 HP Technician Scott Gizzie HP Technician David Alford HP Technician Rachel Ragland23 HP Technician Joshua Williamson$) HP Technician

, Ben Brown') ' HP Technician

. Terminated effective 6/14/97,

2) Employed effective 10/5/97.

3) Employed effective 1/5-98.

') Employed effective 4/21/97, Terminated effective 2/9/98.

8 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 i 1

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 j

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i core 101W. The excess reactivity, shutdown margin, and rod worths were measured in cold clean conditions.

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  ;

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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. All but two of the rundowns  !

listed were due to noise sensitivity of our new Gamma Metrics Wide Range Log drawer. The l

1 drawer appears to be especially sensitive to switching noise when the reactor is at or near full '

power. Switching associated with the auto controller and rod movements can induce enough i

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I noise to trip the 120% Full Power rundown. We have worked with Gamma Metrics to resolve l

the situation. Gamma Metrics supplied us with a replacement AC filter; however, that did not I

change our situation. We are continuing to work with Gamma Metrics to resolve the problem.

I Since the 120% Full Power trip is set on the log power signal, the voltage change between

. 100% and 120% is very small. In the future we may argue that it is inappropriate to have a 120%

trip on a logarithmic power channel and seek to change that particular technical specification.

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l Although this situation is not considered a safety problem, we are committed to continue efforts to resolve the matter in a timely fashion.

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

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1 10 Figure 3-1. UMRR Con c 101W Configuration i

A I

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

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11 Table 3-2. Scrams, Rundowns, and Unplanned Shutdowns Dait Cause 04/18/97 Reactor Rurdown.120% Full Power rundown. Reactor at 100% power in manual control and stable.

Cause: Spurious noise signal from auto controller.

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

. 04/18/97 Reactor Rundown.120% Full Power rundown. Reactor at 100% power, in auto control and stable.

Cause: Spurious noise signal from auto controller.

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

04/21/97 Reactor Rundown.120% Full Power rundown. Reactor at 95% power, in auto control and stable.

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

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

07/08/97 Unplanned shutdown. Reactor shutdown to zero inches after withdrawing control rods to shim range (suberitical).

Cause: Linear recorder displayed erratic readings.

Corrective Action: Recycled connectors on linear channel. SRO on duty granted permission to restart the reactor.

07/17/97 Reactor Rundown.- 120% Full Power rundown. Reactor at 100% power, in auto I control and stable.

Cause: Spurious noise signal from annunciator acknowledge switch while

, switching from auto to manual control.

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

09/04/97 Reactor Rundown.120% Full Power rundown. Reactor power increasing from 50% to 100% power when rundown occurred.

Cause: Spurious noise signal.

Corrective Action: Log and Linear drawer was examined and found operational.

SRO on duty granted permission to restart reactor.

12 Table 3-2. Continued 09/25/97 Reactor Rundown.120% Full Power rundown. Reactor leveling power to 200kW (100% power). Rundown occurred when a rod adjustment was performed.

Cause: Spurious noise signal from rod relay orjoy stick switch. No corrective action taken. SRO on duty granted permission to restart reactor.

10/15/97 Reactor Rundown. 120% Demand Rundown. Reactor increasing in power from 10W to IkW for doubling time experiment.

Cause: Linear meter push button switch (spring loaded) popped out during switching.

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

10/31/97 Reactor Rundown. 120% Full Power rundown. Reactor increasing in power from 50% to 100% power.

Cause: Spurious noise spike when near 100% power.

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

10/31/97 Reactor Rundown. 120% Full Power rundown. Reactor increasing in power from 50% to 100% power.

Cause: Spurious noise spike when near 100% power.

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

I1/18/97 Scram. Loss ofmagnet power while at 10W, no annunciator scram indication.

Cause: AC power flicker to the reactor building.

Corrective Action: No corrective action taken. SRO on duty granted permission to restart the reactor.

. I1/21/97 Reactor Rundown. 120% Full Power rundown. Reactor at 180kW (90% power) and in auto control. Operator switched from auto to manual control when rundown occurred.

Cause: Spurious noise spike from auto controller circuit.

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

12/04/97 Reactor Rundown. 120% Full Power rundown. Reactor increasing from 50% to 100% power. Rundown occurred while repositioning control rod #3.

Cause: Spurious noise signal from rod #3 circuit.

13 Table 3-2. Continued Corrective Action: No corrective action taken. SRO on duty granted permission to restart the reactor.

12/04/97 Reactor Rundown.120% Full Power rundown. Reactor at 100% po,ver, in manual control.

Cause: Spurious noise spike from auto control circuit while switching from manual to auto control.

Corrective Action: No corrective action taken. SRO on duty granted permission to restart the reactor.

12/04/97 Reactor Rundown.120% Full Power rundown. Reactor increasing in power to 100% power.

Cause: Spurious noise spike from regulating rod circuit.

Corrective Action: No corrective action taken. SRO on duty granted permission to restart the reactor.

Table 3-3 Maintenance D. alt Cause 04/21/97 Problem: The constant air monitor test signal output reading shined.

Corrective Action: Temporarily installed two fixed resistors in place of the

" low" calibration potentiometer.' Performed a source check. On 5/9/97 removed the temporary resistors and installed the pennanent replacement potentiometers for low and high calibration. Calibrated the constant air monitor to a pulser and checked its operation with gamma source.

05/07/97 Problem: The period recorder pen had shifted to the right about 0.25 inches.

Corrective Action: Repositioned and secured the period recorder pen. Checked zero, span and infinity setting on the Log and Linear drawer and recorder.

07/02/97 Routine Semi-Annual Calibration of reactor instrumentation. Calibration completed successfully.

07/l1/97 Linear CIC cable replacement. Replaced cables and isolated the CIC from electrical ground for future instrumentation upgrade. Performed Linear Channel calibration after completing Linear cable replacement.

09/04/97 Problem: Zero settings on Safety Channels #1 and #2 drifted.

14 Table 3-3. Continued l

Corrective Action: Adjusted zero and span settings for Safety Channels #1 and

1. 2. Checked trip point settings Repositioned Safety Channel UICs #1 and #2 for 100% Full Power at 200kW reactor power.

09/25/97 Problem: Safety Channel UICs #1 ad #2 read lower than 100% at 100% reactor

! power.

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.. Corrective Action: Repositioned Safety Channel UICs #1 and #2 to 100% with reactor at 100% power (200kW).

.- 10/06/97- Problem: Zero settings on Safety Channels #1 and #2 drined.

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

Checked trip point settings. Repositioned Safety Channel UICs #1 and #2 for 100% Full Power at 200kW reactor power.

10/23/97 Problem

Zero settings on Safety Channels #1 and #2 drined down.

I Corrective Action: Adjusted zero settings and checked readings at 50% Full Power with reactor at 100kW.

l 10/31/97 Problem: Safety Channel #1 and #2 zero settings drifted to below zero readings.

Corrective Action: Replaced vacuum tubes in Safety Channels #1 and #2. Reset zero, span and trip settings. Repositioned UICs #1 and #2 at 75% with reactor at 75% of Full Power. Checked Safety Channels #1 and #2 at 100% reactor power for 100% meter readings.

i 11/14/97 Problem: Log and Linear drawer did not show~an active Log N signal when beginning a prestart-up checklist.

Corrective Action: Determined the Log and Linear drawer received the Log N signal but did not display it. Recycled boards in the drawer. Called the

• manufacture (Gamma Metrics) for instruction. Replaced relay K1 (relay for .

input / test signal) in the signal input circuit. Performed semi-annual calibration test, weekly checklist test and prestart-up test. The drawer performed accurately and in

, a normal manner. Connected the control room computer to monitor the isolated Log N output from the Log and Linear drawer to monitor for a loss of signal.

12/04/97 Problem: Safety Channel #1 was reading a little above 90% and Safety Channel #2 was reading a little below 90% with reactor at 90% power.

Corrective Action: Repositioned Safety channel UICs #1 and #2 to read 90%.

01/13/98 Routine Semi-Annual Calibration of reactor instrumentation - Calibration completed successfully.

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15 Table 3-3. Continued 01/30/98 Problem: Performing preventative maintenance check on the Safety Channels drawer.

Corrective Action: Replaced a BNC connector on a H.V. cable and replaced vacuum tube 5965 in the pre-amp.

02/02/98 Problem: Safety Channels #1 and #2 were not reading correctly at 90% reactor

. power.

Corrective Action: Repositioned Safety Channel UICs #1 and #2 to read 90% at 90% reactor power.

02/10/98 Problem: Could not verify doubling of start-up channel counts during start-up to low power.

Corrective Action: Replaced H.V. power supply for start-up channel fission chamber.

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i Table 3-4. Reactor Utilization  !

1. Reactor use 395.16 hr.

a. NE Classes, Reactor Sharing, and Other Instructions 352.00 hr.

b. Maintenance Training 43.47 hr.

2. Time at power 181.30 hr.

3. Energy generated 6788.90 kW/hr

4. Total number of samples 236

5. U-235 Burned 0.295656 g ,

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6. U-235 Burned and Converted 0.34997 g Table 3-5. Experimental Facility Use Other Than The Reactor l Facility Hours l

Bare Rabbit Tube 6.02 hr. '

Cadmium Rabbit Tube 2.28 hr.

Beam Port 0.00 hr.

Other Core Positions 2.22 hr.

Total 10.52 hr.

17 4.0 PUBLIC RELATIONS The reactor staff continues to educate the public about applications of nuclear science. Over 2,898 persons visited the facility during this reporting period. Tour groups are typically given a brief orientation and/or demonstration by a member of the reactor staff. '

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

Table 4-1. Public Relations Program DATE PARTICIPANTS NUMBER 04/03/97 UMR NE 204, Individual Project, Jeff Shelton 1 04/14/97 UMR Chemistry Labs 79 04/21/97 UMC NE 404, Advanced Reactor Laboratory 7 4/22-5/1/97 UMR NE 204, Nuclear Radiation Measurements 9 05/09/97 UMR Physics 107, Modern Physics 22 0 /09/97 UMR Jackling Institute 45 06/16/97 UMR Jackling Institute 50 06/23/97 UMR Jackling Institute 35 06/25/97 UMR Introduction to Engineering 37 06/27/97 UMR Introduction to Engineering 27 07/15/97 Explorer Group 7 07/22/97 UMR Physics / Chemistry Academy 26 07/23/97 UMR Introduction to Engineering 49 07/25/97 UMR Introduction to Engineering - 3 07/30/97 UMR Introduction to Engineering 148 07/28-08/15 UMR Jackling 11 Students 3

, 9/22 9/25/97 UMR Chemistry Labs 553 10/18/97 UM-Rolla Day Open House 110 10/21/97 Boy Scout Explorer Troop #107 9 10/25/97 UMR Parents Day 118 I 12/01/97 UMR Offsite Emergency Training 14 01/20/98 UMR NE 204 - Radiation Measurements 7 1 03/28/98 UMR Spring Open House 63 02/18/98 UMR Chemistry Labs 98 02/19/98 UMR Basic Engineering 21

{

02/23/98 UMR EngMgmt 386 - Safety Engineering Management 27 03/24/98 UMR NE 204 - Radiation Measurements 6 1/0.01m/QR I1Mr NF 404 Advanced Renctnr I .nhnentnev 16

18 5.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 2,814 student-hours. The number of UMR students utilizing the facility was 823. This usage is a direct result of an aggressive and continuing campus wide " outreach" program. The reactor facility provided financial support for six students with hourly wages, one PhD candidate, and one post-doctorial student. Additionally, students from several universities, colleges and high schools have ,

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

l The University of Missouri-Columbia Nuclear Engineering Department sent its NE 404,

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

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

The Reactor Sharing Program, which is funded by the U.S. Department of Energy, was ..

, established for colleges, universities, and high schools which do not have a nuclear reactor. This

{

year,794 students and instructors from 35 institutions participated in the program. Table 5-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The

- majority of our participants were high school students. We coordinate with the Admissions Office  !

I to schedule high school students to see other items ofinterest at UMR after they have visited our  !

facility, such as the student group of An. ican Nuclear Society, the Computer Integrated Manufacturing Lab, the Foddry, Ceramics Engineering, Mineral Museum, Computer Center, i

1 19 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.

Table 5-1. UMR Classes at Reactor Facility 1997- 98 Reporting Period CLASS NUMBER / TITLE # OF TIME AT STUDENT STUDENTS REACTOR HOURS 04/03/97 UMR NE 204, Individual Project, Jeff Shelton 1.00 1 1.00 04/14/97 UMR Chemistry Labs 79 0.50 39.50 04/22-05/1/97 UMR NE 204, Nuclear Radiation Measurements 9 2.00 18.00 05/09/97 UMR Physics 107, Modern Physics 22 0.50 11.00 9/22/97- UMR Chemistry Labs 553 0.50 276.50 1/20/98 UMR NE 204 - Radiation Measurements 7 2.00 14.00 02/18/98 UMR Chemistry Labs 98 0.50 49.00 02/19/98 UMR Basic Engineering 21 0.75 15.75 02/23/98 UMR EngMgmt 386 - Safety Engineenng Management 27 1.00 27.00 03/24/98 UMR NE 204 - Radiation Measurements 6 0.75 4.50 Fall 1997 UMR NE 490, Research (Scott Gizzie - Nuetron Spectroscopy) 1 22.50 22.50 Fall 1997 UMR NE 490, Research (Eric Stevenson - Thermal Power 1 75.00 75.00 Fall 1997 UMR NE 304, Reactor Laboratory 1 13 30.00 390.00 Fall 1997 UMR NE 306, Reactor Operations 9 30.00 270.00 Fall 1997 UMR 490, Research (David Freeman, Genetic Algonthm 1 80.00 80.00 Wirit;r 1998 UMR NE 306, Reactor Operations 3 32.00 96.00 Wint;r 1998 UMR NE 308, Reactor Laboratory 11 14 80.00 1120.00 Wint:r 1998 UMR 490, Research (David Freeman, Genetic Algorithms) 1 200.00 200.00 Wint:r 1998 UMR NE 490, Research (Eric Stevenson - Thermal Power) 1 80.00 80.00 Wint r 1998 UMR NE 490, Research (Scott Gizzie - Nuetron Spectroscopy) '

1 24.00 24.00 Totals 823 663.00 2813.75

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Table 5-2. Reactor Srjring Program (1997-1998)  ;

DATE PARTICIPANTS NUMBER I 04/15/97 Crossroads High School Tanda Pommier, Instructor 32 04/15/97 Newburg 6th Grade, Linda Davis, Instrucar 41 04/16/97 St. Patrick's 5-8 Grade, Cindy Campbel, instructor 45 04/22/97 Waynesville High School, Julie Kosbar, instructor 26 04/23/97 Rolla High School, Erin Mulanax, instructor 35

, 04/28/97 West Plains Middle School, Barbara Alsop, instructor 30 05/02/97 Potosi 8th Grade, Alan Ziegler, Instructor 16 05/06/97 Vienna High School, Terry Buechter, instructor 20 05/06/97 Sockman Junior High School, Vera McCullough, instructor 15 05/08/97 St. James High School, Jim Jenkins, instructor 14 05/12/97 Red Bud High School, Dan Flowers, instructor 12 05/20/97 St. Mary's 7th Grade, Mr. Gregory, instructor 9 05/21/97 Raymondville Junior High School, Ron Antle, instructor 20 1 10/01/97 Rolla Home School, Grade 7-12, Roger Shiffler, Contact 16 10/08/97 Hazelwood Central High School, Cathy Sylve, Instructor 32 10/09/97 Rolla Home School, Grade 1-6, Roger Shiffler, Contact 18 10/15/97 St. Louis Public Schools, Junior High School, Barbara Howard, Contact 35 11/14/97 Laura Richardson, Potosi High School, Bill Nelson, Instructor 1 11/05/97 Newburg High School, Peggy Brown, Instructor - 32 11/06/97 East Central College, Debbie Schatz, instructor 13 11/17/97 Winfield High School, Diana Lehmkuhl, instructor 20 l 11/12/97 Rolla Technical Institute Radiography, Maggie Ogden, instructor 13 11/19/97 Bobby Avila, Potosi High School, Bill Nelson, Instructor 1 11/19/97 Christie McCoy, Potosi High Shool, Bill Nelson, instructor 1 11/20/97 Mansfield High School, Pam Probert, Instructor 23

, 11/20/97 Ft. Wood Home School, Anne Johnson, Contact 8 11/25/97 Higginsville High School, Art Ozzias, instructor 17 12/01/97 Ash Grove High School, Sally Keith, instructor 10 12/04/97 Willow Springs High School, Kay Carter, instructor 11 12/05/97 Washington High School, Rick Schwentker, Instructor 53 01/e9/98 Ritenour High School Richard Wrtt, Instructor 11 02/12/98 Sullivan Grade School, David Miller, instructor 32 02/17/98 Thomas Jefferson High School, Brett Green, instructor 24 03/10/98 Hazelwood West High School, Gail Haynes, Instructor 27 03/11/98 Summersville High School, Joni Appleton, Instructor 17 03/13/98 Rolla Middles School- 5th grade, Elaine Edgar 50 03/17/98 Fair Grove High School, Janet Beavers 5 I

03/24/98 Southwest Missouri State Universitv- Dr. Robert Mayanovic, Instructor 9 TOTAL 794

21 6.0 REACTOR HEALTII 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 ar d stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

6.1. Routine Surveys Monthly radiation exposure surveys of the facile.) 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 during this reporting period. E 6.3. Routine Monitorine Thirty-nine reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Four are read twice per month (Reactor Staff) and thirty-five are read once per month. There are four area beta-gamma / neutron badges assigned.

Thirty campus personnel and students are assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 17 area monitor and 2 spare

22 badges assigned on campus. In addition,5 digital direct-reading dosimeters,5 chirpers, and 6 ion-I chamber dosimeters are used for visitors and high radiation area work. There have been no significant personnel exposures during this reporting period.

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

Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous air l i

monitor (CAM). Low levels of Argon-41 are routinely detected during operations. j i

Pool water activity is monitored monthly to ensure that no gross pool contamination or fuel cladding rupture has occurred. Gross counts and spectra oflong-lived gamma activity are com-pared to previous monthly counts. From April 1997 through March 1998 sample concentrations averaged 6.45E-7 pCi/ml.

Release of gaseous and particulate activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During this period 134.329 millicuries of Ar-41 was released into the air.

o 6.4. Waste Disoosal Solid waste, including used water filters, used resins and contaminated paper is stored ,

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

Water is analyzed for radioactive contamination and approval is required before the water is released. During this period no waste was transferred from the reactor facility to the Dangerous Materials Storage facility.

1 1

23 6.5. Instrument Calibrations I During this period, portable instruments and area monitors were calibrated annually.

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

l 7.1. Relicensing Relicensing activities will intensify during the upcoming reporting period. Our present j 1

license is valid until November,1999. Several documents will be revised including the SAR, Technical Specifications and Emergency Plan.

7.2. Strategic Plan A strategic plan is being 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 identifie; strategic goals and action items. The action items will be initiated over the coming year and will guide the facility towards its vision.

. 7.3. Instrumentation Uoerade 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 NRC approval.

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APPENDIX A.

STANDARD OPERATING PROCEDURES i

1 CHANGED DURING THE 1997-1998 REPORTING YEAR 1

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE j Revised: February 16,1998 Page 1 of 8

< A. PURPOSE:

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l The purpose of the checklist is to verify that reactor systems are operating correctly prior to ;

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reactor stact-up.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS:

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

!* the operator is still fully responsible for the proper performance of the checklist.

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

l 3. After each step on the checklist is performed the operator will record the readings l

made, or in cases where no readings are required, will simply check the appropriate blank on the form.

)

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, 4. Any malfunction or abnormality identified during performance of the checklist shall be immediately reported to the Senior Operator on Duty, and corrected as necessary before completion of the checklist.

C. PROCEDURE Complete the checklist in accordance with the following steps:

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

2. Initials - Record the initials of the person performing the checklist.

3. Time - Record the time shown on the console clock.

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

5. Verify that the P.A. system is operable. Tum on the bridge intercom and video monitor.

Revised By: William Bonzer Approved Bv: David Freeman CON n Ibgo +'

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: February 16,1998 Page 2 of 8

6. RAM System Check:

a. Announce, "THE BUILDING ALARM WILL SOUND. THIS IS A TEST.

DO NOT EVACUATE THE BUILDING."

b. Check that the setpoints and automatic functions of the RAM systems meet the criteria listed below. For each High Radiation Alarm, verify that both the audible alarm and the visual annunciator are actuated. Reset the annunciator panel after each High Radiation Alarm check.

CHANNEL SETPOINT AUTOMATIC ACTION

1. Bridge RAM 10 - 18 mR/hr High Radiation Alarm

2. Bridge RAM 15 - 28 mR/hr Building Evacuation Alarm

3. Demin RAM ,10 - 18 mR/hr High Radiation Alarm

4. Basement RAM 10 - 18 mR/hr High Radiation Alarm

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

7. Verify that all monitors (Bridge, Demin, Basement, and Neutron RAM) read below 1 mrem /hr.

8. Beamport and Thermal Column Status: Record the status of the beamport and thermal column ("open" or " shut") as indicated by 1) the " Beam Port or Thermal Column Open" annunciator light and 2) the Beam Port Indication light. Notify the Senior Operator on Duty if either facility is "open".

9. Linear Channel:

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

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

c. Record the Linear reading. Record the scale.

Revised By: William Bonzer Approved By: avid Freeman LUOw $ 0)

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: February 16,1998 Page 3 of 8

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

1 HV - 480 VDC CV ~ 2 to 8 VDC I 1. a. Turn on and date the Startup, Linear, and Log / Period recorders. Reset the annunciator panel.

8

b. Observe the temperature recorder " RCD" is illuminated in the upper left hand I corner of the display.

12. Core Check: Tum the poollights on.

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a. Check the water level in the pool.

b. Visually inspect the core and pool for abnormalities. Check in-core experirr. mts. ,

c. Insert the source into the core source holder.

13. Start-Up Channel Test: Turn the Log Count Rate selector switch to 10 2,10 ,3 and 10 4.

Verify tlat 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 Rev.

Limit light comes on. Observe the count rate. Raise the fission chamber until the count rate shows a definite decrease. 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.)

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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 B id Freeman wu %g 7.w

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: February 16,1998 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. Verify that the digital meter and recorder read within the tolerances of the

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following table. The bargraph should gererally follow the digital display and recorder.

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

1OpA 4.0 E 2.5 E -5 0-1%

0.luA 8.4 E 1.2 E -1 0-l%

ImA 8.4 E 1 - 1.2 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 mA 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.

I8. 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.

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

Revised By: William Bonzer Approved By*

' d Freeman LUN*n kon g xaA

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: February 16,1998 Page 5 of 8 21.150% Power Scram Check:

a. Withdraw shim rods to 3 inches.

b. Depress the test button on safety amp and hold until the 4 red 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 l Low CIC Voltage Rundown visual and audible alanns.

c. Verify that the rods have dropped and rod drives are running dowm. 3

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.

1

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 anmmciator 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 swi:ch.

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 Approved id Freeman e ay p.

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CONTROLLED COPY l

• • • UMR REACTOR STANDARD OPhhATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE l Revised: February 16,1998 Page 6 of 8

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

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

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27. Prepare hourly and permanent logs.

28. Detector Response Check:

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

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

c. Insert the source into the holder.

d. Observe the Log / Period and the Linear recorder traces to verify proper response to the source spike.

e. Observe the Startup Channel recorder to verify that the recorder responded properly with a decreased count rate when the source was moved away from the core.

f. Reset the annunciator panel.

29. Raise the shim rods to 6 inches. Record the time on both the checklist and in the permanent log.

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

31. Record the intended power level.

32. Announce, "The Reactor Will Be Started and Taken to a Power of Watts".

33. Review the Pre-Startup Checklist. Verify that all of the steps have been completed.

The licensed operator responsible for performing the checklist will initial the checklist thus verifying that it has been properly completed.

34. The Senior Operator on Duty willinitial the checklist verifying that all items have been completed and any problems identified have been satisfactorily resolved.

I

35. Record the date using the rubber date stamp.

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Revised By: William Bonzer Approved By: D'a7id'I'r'dr man wsa 1&yn &a L l

J CONTROLLEB COPY

• UMR REACTOR STANDARD OPERATING PROCEDURES

• SOP; 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: February 16, 1998 Page 7 of 8 1 Date l

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2. Initials of the Person Performing Checklist e

3. Time (Console Clock) 1

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

9. Linear Channel Zero Meter Reading Scale

10. Linear C.I.C. Voltages HV (~480) l CVJ~ 2 to 8)

11. Recorders On and Datei Check " RCD" Light on Temp. Recorder

12. Core Check (Lights On) Level Chack

, inspeg Core ___

Source Inserted h( ,

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13. Start-Up Channel Test 1

14. Verify FC Res;>onse, FC Inserted, Count Rate > 2 CPS

15. Log Count Rate HV Power Supply F 400 VDC)

16. Log and Power Range Test

17. Period Response Test

18. Magnet Power On, Scram Reset Board Reset

19. Inlet Temperature PF) I l

Revised By: William Bonzer Approved By avid F eman i iOknQ },a 'fp!!' 1 l

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I C 0 iq ! n e d . 8 t.? i f i

• " UMR REACTOR STANDARD OPERATfNO PROCEDURES

• SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE l Revision: February 16, 1998 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" 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.1 No. 2 e 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:

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eman wu Revised By: William BonLer y,

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• " UMR REACTOR STANDARD OPERATING PROCEDURES **

• SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Page Revision: September 18, 1997 Page 3 of 4

9. Verify both Nitrogen Diffusers are off.

10. Verify that all vent fans are off.

i1. Secure the rabbit system by assuring the on/off switch of the manual control box is in the I Rev. j "off' position and that the gas bottle is shut. Return the glove box key to the safe.

12. Log time using the console clock.

e

13. Initials of person performing checklist.

14. Senior Operator on Duty ,nallinitial.

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Revised By: William Bonzer Approved Freeman wn wy 7 ,

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duit!.d bi J D Ed,TDG A ?:fj 4R

• • • UMR REACTOR STANDARD OPERATING PROCEDURES * **

SOP: 209 TITLE: SECURING THE BUILDING Revised: November 25, 1997 Page 1 of 2 A. PURPOSE To ensure that the Reactor Facility is properly secured whenever the facility is to be left unoccupied. i 1

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS P

1. This procedure is to be completed at the end of each workday or whenever the building is to be left unoccupied by authorized personnel.

2. A person who has been authorized to have the necessary keys shall secure the building. (This includes members of the University Police.)

3. If the intrusion alarm system is inoperable, contact a Senior Reactor Operator to inform them of the difficulty, and remain at the office area until relieved by a member of the University Police or another person who has Unescorted Access clearance.

4. If a person who has been authorized to have the necessary keys is not available to secure the facility, then the University Police should be contacted to secure the building. In that case a member of the Reactor Facility staff should remain in the oflice area until a member of the University Police who has the proper keys arrives.

The University Police should be reminded of SOP 209 for guidance in the proper securing of the building.

. C. PROCEDURE

1. Verify that the bay door, basement door, fuel handling tools and lock box are properly locked.

2. Turn off building ventilation fans.

3. Turn offinterior building lights. At least one light should be left on in the Reactor Bay and in the sub-basement level.

Written By: James Jac so Approved By: a ma

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• • • t IR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 209 TITLE: SECURING THE BUILDING Revised: November 25, 1997~ Page 2 of 2

4. Generally check the building including the bay, attic and sub-basement areas to verify Rev.

that no personnel remain, that there are no unusual packages or suspicious objects, nor fire hazards present.

5. Check for the proper storage of SNM by visually observing that the following items are in otder: l

a. the core and storage pit areas,

b. the Detector Box, and

c. PuBe Source shield stack.

6. Turn off or unplug appliances such as fans, coffee pots, sealing heater, etc., which do not need to be left on.

7. Activate the intrusion alarm system and lock the main personnel access door.

8. Check the security badge rack to make certain all of the security badges are properly accounted for.

9. Notify the University Police that the building has been secured and the alarm system has been activated.

S O

Written By: ames Jac o Ap av Freeman l

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• aa UMR REACTOR STANDARD OPERATING PROCEDURES aaa SOP: 302

Title:

INSPECTION OF CONTROL RODS Revised: August 30, 1988 Page 1 of 2 A. Reactivity Recuirements Bef ore a control rod can be removed from the core, all fuel elements necessary to insure the loading is below 50% of the critical mass when all rods are removed, shall be removed from the core.

, B. Personnel Recuirements For this procedure there must be a Senior Operator on Duty, one Reactor Operator and one assistant with some fuel han-dling experience in the bay area. Also a health physicist or his representative shall be present.

C. Material Recuirements Control rod removal jumper cable.

Control rod removal saf ety basket .

D. Procedure

1. Person in charge will contact the Reactor Manager to obtain permission.

??DN?

2. The startup check out will be completed, and the. con- ((Uiq7 tr ol r ods wi th dr awn t o -. _ _ -- __ - . s k . +. W"'#- '

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3. Fuel transfer forms (SOP 4FOG) will be filled out and checked for accuracy.

. 4. Fuel will be transferred one element at a time as directed by person in charge until all required ele-ments have been removed in accordance with SOP 207. If the fuel has been previously unloaded (eg. the day before) it is not necessary to repeat the startup check out procedures however, it would be proper to have the recorders on.

5. The control rods will be fully inserted into the core and magnet power de-energized.

6. The scram magnet extension and control rod drive shroud will be removed and suspended from bridge. One of the extensions must be completely removed from the shroud.

Written By:

/

ton so--

Approved By:

W b Albert Bolon arr B

aaa L iCONTROLLED COM UMR REACTOR STANDARD OPERATING PROCEDURES *aa -

SOP: 302 Tit 1e: INSPECTION OF CONTROL RODS Revised: August 30, 1988 Page 2 of 2 ,

I g g )),7 oup d hN lhM P" fb

7. Connect the control red ressual j"rper cable ic the- M l me.uci ext er. ica and -the ner mal magnet uvuuevtec . 'a U l

8. Place the rod removal safety basket as close to the l rod to be removed as possible, i

9. The scram magnet will manually be pla:ed on the rod g to be removed and magnet power energized,ter-trormal car i

-r-ent -pl u s 20 aa. l

10. The Senior Operator will carefully supervise the withdrawal of the control rod element and place it in the safety basket. Nuto. c oc e mu s i 've taken iv kecy the extcasica and red vertical iv vievent dreppium the-

• 1M>ds-c u 3: lle rj .n= r v7.

11. De-energize magnet power and disconnect the lext-eunivu .

Caref ully raise the rod in the basket .

12. When the control rod is out of the pool, place the control rod behind as much shielding as necessary, and

, inspect for pitting and cracking. Record general com-ments and any particular inf ormation f or each rod.

13. Using basket, lower rod into the pool, and position i near control rod elements. Position magnet over the rod, energize magnet power and withdrew the control rod s from the basket. Place rod into control rod element , w Y#

gnd de-energiz magnet powe,r.Rud_d.h bv p ,te<"**' f'N~4 >

% 747 grst H.. I + e t ,,,a ad r ^ e.

n u n t < <- c o 4+ h.. W > > w e '

peatb steps la s x 8 th> rough 4 nt n rA.rmtwlhe other 2 control on 4a 1>4 f or{oss.

i . 14. Ne. tk rods.

, 15. Reinstall magnet extensions and control rod drive gp l shrouds. WA + b dr e" r ede te 50" ::rt nr.d r:10:d ;;r: :: ,pc/9 tg I cer=2.,

16. Log results of inspection in reactor log. c, $ 8S Ofl -

17. Have Manager and/or Director review the[esults and M initial.

5, M 2/ze/43 ,g h7 g g , pe (-Gym fe d brcp lIWW ONQG ud>n 6 L

q , (2.e loo d Cord er 50 P Zd 7 l Written By

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Carl Barton

/ W Approved By:

@OW Albert Bolon I

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l IPCONTR0llED QgEy***

• • • UMR REACTOR STANDARD OPERATING PROC SOP: 305

Title:

OPERATION WITHOUT MAGNET CONTACT LIGHT August 30, 1988 Rsvised: Page 1 of 1

)

l General

The Reactor Facility has been advised by the Nuclear Regulatory Commission that operation of the reactor without magnet contact  ;

lights is permissible under the following conditions: l l

1. The operator must perform by audible or visual means the

, necessary functions that the magnet contact light performs automatically. j

2. Any rod t' hat has an inoperative magnet contact light must be withdrawn separately to a distance of 6 inches.

3. Reduce current on this magnet until rod separates, as indi-cated by audible sound from the intercom.

4. Visually inspect rod to confirm separation. (Viewing the REV.

video monitor is sufficient, if applicable.)

5. Restore the current to its former value.

6. During start up determine if neutron flux increase cor-responds to expected rod position as reactor cannot be brought to criticality if any rod is inserted. (The reading on the Log Count Rate recorder should double as the REV.

shim /saf ety rods are withdrawn from 6 inches to shim range and the reg. rod to 15 inches.)

7. Opcration of the scacter will bc prohibitcd whcn the Ibb\

cxeccc rc,:tivit; ic abcvc 1.5%, uniccc all cantact

, lightc arc picpccly pcrforc.ing thcir functionc. 2h%l96 l

Written By: Milan Straka Approved By: Albert Bolon

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• *

• UMR REACTOR STANDARD OPERATING PROCEDURES * *

• SOP: 310 TITLE: FACILITY MODIFICATIONS Complete Revision: April 28, 1997 Page1of2 A. PURPOSE The purpose of this procedure is to provide for the effective review and approval process for facility modifications and to ensure regulatory compliance.

B. PRECAUTIONS. PREREOUISITES. AND LIMITATIONS

1. Review and approval requirements for changes that do not require NRC approval are prescribed in 10 CFR 50 Section 50.59, " Changes, Tests, and Experiments".

Proposed facility modifications do not require NRC approval if the following two conditions are met:

a. the change must not involve a char.ge in Technical Specifications; and

b. the change must not involve an "unreviewed safety question" 10 CFR 50.59 states that an unreviewed safety question is involved if:

a. the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

b. a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis repon may be created; or

c. the margin of safety as defined in the basis for any technical specifications is reduced.

C. PROCEDURE

1. The proposed facility modification should be discussed with the reactor staff.

2. A detailed written description of the proposed modification shall be prepared that includes a safety evaluation that provides the bases for determining whether or not an unreviewed safety question is involved.

3. The detailed description shall be reviewed and approved by the Reactor Director to determine if the facility modification meets the criteria of 10 CFR 50.59.

Reviewed By: William Bonze Approv By: David Fre an LON aahtii

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

, SOP: 310 TITLE: FACILITY MODIFICATIONS Complete Revision: Apri1 28, 1997 Page 2 of 2 I

4.

l The facility modification proposal shall then be presented to the Radiation Safety Committee (RSC) for review and approval (T.S. 6.2.3).

5. If the RSC approves the proposed modification but determines that NRC approval is required, NRC approval must be ol"ained prior to implementation.

6. If the RSC approves the proposed modification under the provisio.ns of 50.59, the l facility modification may be implemented as described in the approved proposal.

7. Training with regard to the design change is to be provided to licensed operators in l

a timely manner and shall be documented on each operator's Requal Form.

8. A description of each facility modification made under 10 CFR 50.59 shall be included as part of the facility's Annual Progress Report to NRC. )

9. Records of facility modifications (including the safety evaluation prepared in Step 2 above) shall be maintained. Records concerning changes to reactor systems, components, or equipment that may affect reactor safety and updated, corrected and as-built drawings of the facility shall be maintained for the life of the facility (T.S. 6.7.3).

O

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Page Revision: July 29, 1997 Page 7 of 7 I

UMR REACTOR EMERGENCY PHONE LIST Reactor Staff HOME WORK David Freeman, Mgr., SRO 364-7269 341 6 William Bonzer, Sr. El. Tech., SRO 368 3727 341-4221 Albert Bolon, Dir., SRO 364-1961

- 341 6 Ray Bono, Health Physicist 364 5728 3416, M, d.403.

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

1. Chancellor, John Park 341-4118 364-6455 341-1114 1

2. Vice Chancellor for Admin. Senices, Mohammad H. Qayoumi 308 1067 341-6.2Dfi,4.122 Rev.

3. Director, UMR Police, William Bleckman 364-1294 341-4)4fi

4. Director, Physical Plant, Manin Patton 364-6278 341-42.52

$. Durector, Health Senice - Infirmary, Dwight

Deardeuff,

MD 364 0809 341-42114 0 . n, School of Mines and Metallurgy, Lee W. Saperstein 368 3782 341-4153 j

7. Kadiation Safety Officer. Nick Tsoulfanidis 341-3595 341-4745 Local l UMR University Police 341-4399 341 A11.1

! Rolla City Police 9-911 Rolla Fire Department 9-911 I Phelps County Hospital 9-911 hev. l Rolla Emergency Management Ageacv 9-911 I State Arencies Missouri Highway Patrol 368-2345 Missouri State Emergency Mgt. Agency (24 hr.) (573) 751-2748 l

Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 ,

o Missouri Bureau of Enviromental Eoidemioloey (573) 751-6160 (573) 751-4674 (after hrs) hev, i Federal Agencies NRC, Lisle, IL, Region III 1-800-522-3025  !

NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 816-5100 (301) 951 0550 (301) 415-0550 i l

Other '

American ?luclear Insurers (860) 561-3433 Radiation Eureency Assistance Center (423) 576-3131 (423) 481-1000 D4 hrs) i Revised 07/24/97 r l N u mf lp jffW Revised By: William Bonzer Approv By: David Freeman l

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

SOP: 654 TITLE: MEASUREMENT OF ' Ar CONCENTRATION IN TH E l

REACTOR BUILDING AIR I Complete Revision: March 20, 1995 Page 1 of 3 A. PURPOSE To test the activity concentration ofAr in the Reactor building air.

.B. PRECAUTIONS OR LIMITATIONS

1. This procedure is to be annually performed by Health Physics personnel.

2. If other gamma activity is observed, then a second count is to be performed on a high-purity germanium detector to determine the isotope and activity.

3. A copy of the measurement results will be provided to the Reactor Manager.

C. PROCEDURE

-1.

N W0 SmuJc arcn=tica Evacuate thc aluminum sampic tank to 60 ten. The-tankwof-hianucih dcuy,u and lies , voluiuc vf 6842 uni. NW 7

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2. Backcround Count -Aftec cvacuating the tenk,'t ake a 600 second count with the Nal detector in the Health Physics counting room (ii4 Fulivu Hall) and print out the y

qfg.,7 spectrum to include the area where the

• Ar peak will occur. I 22 Note: Na has a 1.275 MeV gamma and ' Ar has a 1.294 MeV gamma, so by using

, a sodium source for comparison it is easy to determine where the argon peak will occur.

l

. 3. Samoling i

a. The Reactor building air sample is taken with the air tank positioned on the west side of the Reactor pool over the fuel storage area. The Reactor building air sample is taken periodically to detect Ar or any other gaseous activity in the containment building air. 1 V

l Revised By: Ray Bono Approved By: Albert Bolon

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 654 TITLE: MEASUREMENT OF d Ar CONCENTRATION IN THE REACTOR BUILDING AIR Complete Revision: March 20, 1995 Page 2 of 3

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b. Position the air sample tank and open the vie. Allow the tank to completely 4(tstr' fill (45 seconds) and note the time and date of the sampling.

c. When sampling is complete, close the tank valve.

4. Analysis

a. Immediately transfer, within 10 minutes, the air sampling tank to the Nal detector in the Health Physics counting room. Position the tank inside of the lead shield by placing the tank in the lead shield with the hole for the detector on top. This allows the 3x3 Nal to he placed inside the tank without placing the weight of the tank on the detector,

b. Count the sample on a range of 0 to 2 MeV for 600 seconds with the detector ,yg; shielded.

44 , p %g- y

c. When the count is complete, set the start and stop channels to include the 1.294 MeV Ar peak region, print out the spectrum and integrate.

5. Calculations

a. Determine the background count by integrating over the same channels in which the peak of the *Ar sample occurred. The background count should be done prior to the sample and enough r%nnels printed out to obtain the background integral.

b. Do a background subtraction from the peak as follows:

. N = G - B where, N= Net number of counts in the 1.294 MeV peak of"Ar (counts)

G= Gross number ofcounts in the 1.294 MeV peak of"Ar as determined in the integration of the printed spectrum (counts) l B= Gross number of counts found by integrating the background count over the same channels as G above (counts)

Y Revised By: Ray Bono b

Approved By: Albert Bolon b

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 654 TITLE: MEASUREMENT OF d'Ar CONCENTRATION IN TH E REACTOR BUILDING AIR Complete Revision: March 20, 1995 Page 3 of 3

c. Determine the count rate of the 1.294 MeV peak of' Ar as follows:

R = N/t where, R= Count rate in 1.294 MeV peak of' Ar (cps) t= Count time (3econds)

d. Determine the concentration of activity of"Ar taken in the grab sample of the Reactor building air as follows:

A = R/eff where, A= Concentration ofAr activity in sample (pCi/ml) eff = Currently determined efficiency of the counting setup (i.e. Nal gfg detector and-6842 ud sample ca.- f Af)(cps /(pCi/ml))

l

6. Report Record the following data in the notebook labeled "Ar in the Reactor Building."

a. Date of sample

b. Time of sample

c. Count time (t)

d. Net peak count (N)

e. Peak count rate (R)

f. Ar concentration (A)

g. Reactor power level

h. Building air flow rate (ft'/ min or m'/ min)

Y Revised By: Ray Bono Approved By: Albert Bolon

p, c .y .. *g.:  :'

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 710 TITLE: INSERTION AND REMOVAL OF EXPERIMENTS Page Revision: September 18, 1997 Page 2 of 7 or unanticipated changes in reactivity are observed or if any unsafe condition is observed.

l

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

8. The Reactor Operator is responsible for verifying that the experiment has a valid IRF with the appropriate review and approval signatures. The Reactor Operator is responsible for verifying that the proposed experiment meets the requirements (e.g. l irradiation time, power level, location, special instnictions, etc.) of the IRF.

C. RABBIT FACILITY: INSERTION AND REMOVAL PROCEDURE

1. Rabbit System Setup:

a. Fully open the nitrogen gas bottle. Normally the gas tank pressure should read about 500 psi and the system pressure should be set between about 40 to 60 psi.

b. Turn on the control room computer and monitor. Rev.

c. Double click onto the " Rabbit Controller" icon.

d. Enter the name of person using the computer and click "OK"

e. Select and enter the transfer tube to be used for irradiation.

f. Enter the amount of time, in seconds, for the sample irradiation in the

" Irradiation Time" box.

. g. Position the on/off switch located on the manual control box to the "on" position, a red indicator light will come on when the manual control is turned on.

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

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

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

Revised By: William Bonzer Approved By: D eman LA.) b & 0Q) la

1 p, ,- q , -

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• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

'M 710 TITLE: INSERTION AND REMOVAL OF EXPERIMENTS Page Revision: September 18, 1997 Page 3 of 7

a. Irradiate Sample - Fire the rabbit vialinto the core using either the Rev.

computer or manual controller. l

b. Record Logs - Record the appropriate information in the permanent

• l logbook using the Sample Experiment Stamp ( See SOP 106) and on the IRF Form (SOP 702).

c. Sample Return (1) be cognizant of the approximate end time of the irradiation. Be alert to the possibility of a system failure causing the rabbit to be significantly over-irradiated.

(2) watch for the experimenter's " thumbs-up" signal verifying that the sample has returned and that dose rate outside of the glovebox has been measured and found to be less than 10 mrem /hr.

(3) If the dose rate outside of the glovebox is 100 mrem /hr or more, shoot the sample back into the core and turn the rabbit system off.

The reactor should then be shutdown. Notify the SRO on Duty.

After a sufficient decay time, as determined by the SRO on Duty, the sample may be brought back to the glovebox and radiation levels rechecked.

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

a. Measure Ambient Dose Rate - Measure the ambient dose rate outside of the closed glove box:

(1) If the dose rate exceeds 100 mrem /hr the experimenter is to remove personnel from the glovebox area and notify the Reactor Operator immediately.

(2) If the dose rate is between 10 mrem /hr and 100 mrem /hr, notify the Reactor Operator immediately for further instmetions.

b. Remove Vial From Tube - If the dose rate measured outside the glove box is less than 10 mr/hr, the vial may be removed from the rabbit tube to the glove box floor.

Revised By: William Bonzer Approved B avid Freeman wL Q 'A i

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• UMR REACTOR STANDARD OPERATING PROCEDURES 3**j fj [j W ., y jw ' .

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Revised: Apri1 28, 1997 Page 1 of 8 j

Date Commenced Date Completed Total Hours on Hour Meter }

1. Log and Linear Drawer Calibration )

j

a. Log and Linear Log / Period Recorder (1) Cleaned chassis as needed

(

b. LOW CIC Voltage Rundown i

Set Point at A4TPl: VDC x 200 = VDC  !

Verify Rundown Initiated (/):

Verify Alarms Received (/):

c. 120% Full Power Rundown l Set Point:  %

Verify Rundown Initiated (/): l Verify Alarms Received (/): I l

d. Log and Linear Detector / Cable Resistance Check 2

(Cables should read about 10 ohms.) I (1) Signal Cable Resistance: Meg ohms Rev.

(2) High Voltage Cable Resistance: Meg ohms (3) Comp. Voltage Cable Resistance: Meg ohms

e. Drawer Alignment - Perform the steps listed in the following sections of the drawer Instruction Manual: i I

Low Voltage Power Supply Check Complete (Sec. 4.3.1):

i High Voltage and Compensating Voltage Check l

• Low Voltage Set Point at J6: VDC i

• Low Voltage Set Point at A4TP10-A4TPl: VDC l NON-OPERATE LED on (/): l

• Reset High Voltage (J6): VDC l

• High Voltage (A4TP10-A4PP1): VDC l

• NON-OPERATE LED off(/):

• Compensating Voltage at J7: VDC

• Compensating Voltage at ASTP10-A5TPl: VDC I

i L $m 4% U)

Revised By: William Bonzer A proved By: David Freeman  ;

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• • • UMR REACTOR STANDARD OPERATING PROCEDUREq.'***j O , !q-1 - i SOP: 800

Title:

SEMI-ANNUAL CHECKD5h ' ' '- ' ' "  ;

Revised: Apri1 28, 1997 Page 2 of 8 l Log Displays Picommy True Tolerance for Log Log Log initial Date Current Expected True Expected Bargraph Digital Recorder Readings Readine 10 PA 1.0E-5% 7.0E-6 1.4E 5% j

- l 100F A 1.0E-4% 7.0E 5bl.4E-4% i I

1nA 1.0E 3% 7.0E-441.4E 3%

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

l 100 nA 1.0E l% )

7.0E-2 1.4E-0% i ipa 1.0E 0% 7.0E-1 1.4E 0%

10 A 1.0E+1% 7.0E-0%-1.4E+1% Rev.

100 pA 1.0E+2% 1.0E+1%1gg4 Period Displays Settings Period Bargraph Period Digital Period Recorder Initial Date i Display Display Display on i

3 Sec j

Linear Displays Pico-amp Tolerance for True Teve Ext wed Linear Bargraph Linear Digital Voltage Initial Date Current Espected Readings Reading D6 splay Display Tolerances 10 A 8412% 10 % 0.7V-0.9V 20 A 18 % 22 % 20 % 1.5V-1.7" 30 pA 28432% 30 % 2.3V-2.5 V 40 pA 38442% 40 % 3.1V 3.3V 50 A 48452% $0% 3.9V-4.IV a 60 pA $8462% 60 % 4.7V-4.9V 70 pA 68472% 70 % 5.5V 5.7V

, , 80 pA 78482% 80 % 6.3 V-6.5V 90 pA 88 % 92 % 90 % 7.1V 7.3V 100 A 98%IO2% 100 % 7.9V-8.IV 110 pA 108 4 112 % 110 % 8.7V-8.9V 120 pA 118 4 122 % 120*'e 9.3V 9.7V 125 pA 123 4 127 % 125 % 9 9V-10.IV W a!. b mp yh Revised By: William Bonzer Approved By: David Freeman

• • • UMR REACTOR STANDARD OPERATINO PROCEDURE $ ***,3 a g J1, a . _; VJa !

SOP: 800

Title:

SEMI-ANNUAL C8ECKLIST Revised' Apri1 28, 1997 Page 3 of 8

f. Isolated Outputs (/):

g. Keypad Switches Test Switch Indication 1mA Log:  %

Lin:  %

0.1 uA Log:  %

Per: -100, +100 sec (/)

. Lin: 0 1% (/)

10 pA Log: <  %

3 SEC Per: 3.0 0.1 sec (/)

NON-OPER LED On (/)_

LOG TEST Rising Log Level (/)

Trip #4:  %

PERIOD TEST Rising Period Level (/)

Trip #1: see Trip #2: sec Trip #3: sec LINEAR TEST Rising Linear Level (/)

h. Cables Reconnected (/):

, Independent Verification of Cable Connections (/):

i. Log and Linear Drawer Calibration Complete: Date (Initials)

2. Linear Power Channel

a. Linear Power Supply (1) Cleaned chassis as needed (/):

b. Linear Recorder (1) Cleaned Chassis as needed (/):

V-) $ 5 h p p Revised By: William Bonzer Ap oved By: David Freeman

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• • • UMR REACTOR STANDARD OPERATINO PROCEDURE 5 ***.nm-- q m r - '

<  : J

. SOP: 800

Title:

SEMI-ANNUAL CHECKLIST b ,.

Revised: Apri1 28, 1997 i

s Id V i Page 4 of 8

c. Linear Calibration (Note: From 10 5 to 10 ', the overall accuracy should be better than 2% of full scale.

From 10* to 10 2' the overall accuracy should be better than 4%. Any instrument found to be out of calibration should be realigned in accordance with procedures.)

---

METER-- -----RECORDER-----

PicoAmp Acceptable Actual Acceptable Actual Generator Reading Reading Reading Readin? Initial Dalt 6.0x10A (57pA-63 A) (57%-63%)

6.0x104 A (5.7pA-6.3 pA) (57463%)

6.0x10 'A (570nA-630nA) (57%-63%)

6.0x10-'A (57nA-63nA) (57%-63%)

6.0x104 A (5.3nA-6.6nA) (53%-66%)

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

2.0x10 A (130pA-260pA) (13426%)

d. Linear CIC Detector / Cable Resistance Check (Cables should read about 10' ohms.) i (1) Signal Cable Resistance: Meg ohms Rev.

(2) High Voltage Cable Resistance: Meg ohms (3) Comp. Voltage Cable Resistance Meg ohms

e. Reconnect all cables Reconnection of cables verified

3. Log Count Rate Channel

a. Log Count Rate Recorder (1) Cleaned chassis as needed LC',Jlea L .ny> ,Qg Revised By: William Bonzer Approved By: vid Freeman

1 l

pp~ ' ']~..' ' . ' q j

• • • UMR REACTOR STANDARD OPERATING PROCEDURES P**

SOP: 800

Title:

SEMI-ANNUAL UHECKUST

~

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J b' , d Revised: Apri1 28, 1997 Page 5 of 8 b Fission Chamber Preamp Initial Date l (1) Cleaned chassis as needed (2) AdditionalComments l

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

Pulse Generator Meter Recorder IPitial Dalc l . M 100 L000

_ 10.000

d. Reconnect all cables Reconnection of cables verified

4. Safety Channels

a. Safety Preamp I i

(1) Cleaned chassis as needed

b. Safety Detector UIC #1 (1) Signal Cable Resistance: _,

Meg ohms Rev.

(2) High Voltage Cable Resistance: Meg ohms

c. Safety Detector UIC #2 (1) Signni Cable Resistance: Meg ohms (2) High Voltage Cable Resistance: Meg ohms

d. Safety Amplifier (1) Cleaned chassis as needed

e. Safety Amplifier Adjustments

f. Reconnect all cables Reconnection of cables verified I

Lubh q, , -l Revised By: William Bonzer Approved By: vid reeman

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• • • UMR REACTOR STANDARD OPERATINO PROCEDURESgP**g .. ; , ,, , i , _j g jf SOP: 800

Title:

SEMI. ANNUAL CHECKLIST Revised: Apri1 28, 1997 Page 7 of 8

b. Temperature > 135' Rod Withdrawal Prohibit Test Thermocouple #1 Thermocouple #3

>135"F Trip Temperature l

>l35"F Annunciator Audible Alarm Rod Prohibit Withdrawal Initials

7. Regulated Power Supply Initial h l

a. Cleaned chassis as needed

b. Additional comments l

8. Conductivity Bridge

a. Cleaned chassis as needed 1

b. Additional comments

9. Rod Indicator Calibration Actual Height Rod 1 Rod 2 Rod 3 Reg. Rod 1"

6" 12" 18" 24"

10. Fire Alarm Check Initial h

a. Cleaned system containers as needed

b. Checked batteries

c. Checked pull stations

d. Checked heat detectors

e. Checked smoke detectors

f. Allindicator lamps operate

11. Security System Check

a. Door Sensors

b. Motion Detectors

c. Tamper Switch LUhim I 91 , y Revised By: William Bonzer Approved By: avi Freeman

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• • • UMR REACTOR STANDARD OPERATING PROCEDURESy, '

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SOP: 800

Title:

SEMI ANNUAL CHECKLIST- 9 -

Revised: Apri1 28, 1997 Page 8 of 8 Imtial Dats

d. Duress Alarm

e. Battery

f. High Radiation

g. Low Pool Water

h. Additional Comments:

12. Public Address System

a. Cleaned chassis as needed

, b. Additional Comments

13. Area Radiation Monitor j

. a. Cleaned chassis as needed l

b. Additional Comments l

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 will be completed annually Rev.

during summer semi-annual calibration. During winter semi-annual calibration record the latest date for the RAM Calibration.

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)

Wbak %f I cu J Revised By: William Bonzer Approved By: Davi Freeman

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p , .I i i JN;ldhMAj L i b J; J l *** UMR REACTOR STANDARD OPERATING PROCEDURES ***

l SOP: 810 TITLE: WEEKLY CHECK

) Page Revision: Apri1 28, 1997 Page 5 of 11 l 3.2. Non-Operative Scram and Rundown Test l

! 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 I and audible alarms are activated. l

f. Reset the Scram, Rundown, and Annunciator panel.

g. Depress and release the test switches listed below. For each verify that the j

" Log N Non-operate" and " Low CIC High Voltage" annunciators and audible Rev. I alarns are activated. Reset the scram and annunciator panel after each switch l

l is efnecked. The following switches are to be checked:

• 1 mA switch, e 0.1pA switch, e 10 pA switch, and '

e 3 SEC switch.

l 3.3.150% Full Power Scram

a. Withdraw rods to 3 inches.

b. Push Scram test button on Safety Amplifier. Hold button until both power j range meters read full scale and 4 red test lights are on, and Magnet power light is o1T.

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.

l Revised By: William Bonzer Approved By eman 7"

w:a&

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Page Revision: May 21, 1997 Page 7 of 11

6. Test of Annunciators 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. Servo Limits

a. Note linear level recorder reading.

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

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 Effluent 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 leading. The local alarm (red alann light) on the resistivity meter should come on and the console annunciator should alarm.

c. Reset the alarm to a setpoint of 8% (0.4 MO-cm) and switch the selector Rev.

switch to display Demin effluent 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.

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Revised By: Approved By: David reeman Lusk Bonzer %

William pg

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APPENDIX B.

REVISED SA.R PAGE FOR THE 1997-98 REPORTING YEAR l

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in air, and sends a remote signal to the recorder in the control room. Rey, 4/28/97 l

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