Text

Progress Rept for Univ of Missouri-Rolla Nuclear Reactor Facility Apr 1994-Mar 1995
	ML20082R786
Person / Time
Site:	University of Missouri-Rolla
Issue date:	03/31/1995
From:	Bolon A; MISSOURI, UNIV. OF, ROLLA, MO
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	NUDOCS 9505020205
	Download: ML20082R786 (145)
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3 Nuclear Reactor UNIVERSITY OF MISSOURI ROLLA noiie,Mo eNN4I Missouri's TechnologicalUniversity Telephone (314) 341-4236 FAX (314) 341-4237 April 27,1995 Document Control Room Attention: Director Oflice of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission hiail Stop 10-D-21 Washington, D.C. 20555

Dear Sir:

Please find enclosed the Annual Progress Report 1994-95 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, b

Albert E. Bolon Reactor Director lp Enclosurc xc: Manin Mendonca, Project Manager (NRC)

Jack Martin, Region til Administrator (NRC)

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 Senices (UMR)

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

Dr. John Fulton, Dean, College of Arts and Science (UMR)

Mr. Bruce Ernst, American Nuclear Insurers American Nuclear Insurers, clo Librarian Dr. Nord Gale, Chairman, Radiation Safety Committee (UMR)

Radiation Safety Committee University of Missouri-Columbia Research Reactor Reactor StafT 0

9505020205 950331 PDR ADOCK 05000160 t l }

R PDR an equal opportunity employer

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!- PROGRESS REPORT

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1994-95 UNIVERSITY OF MISSOURI-ROLLA i

NUCLEAR REACTOR FACILITY M O,,- fpM I S- OU S

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/. 1 PROGRESS REPORT.

I FOR THE ;

1 UNIVERSITY OF MISSOURI-ROLLA j NUCLEAR REACTOR FACILITY

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April 1,1994 to March 31,1995 Submitted to The U.S. Nuclear Regulatory Commission and

The University ofMissouri-Rolla l,

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Albert E. Bolon, Director F

David W. Freeman, Manager

, Nuclear Reactor Facility University of Missouri-Rolla Rolla, Missouri 65401 f

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SUMMARY

During the 1994-95 reporting period the University ofMissouri-Rolla Reactor (UMRR) l

.L was in use for 413 hours0.00478 days 0.115 hours 6.828704e-4 weeks 1.571465e-4 months . The major part of this time, about 97%, was used for class instruction, i i

research, and training purposes. j 1

The UMRR operated safely and efliciently over the past year. No significant safety- !

related incidents or personnel exposures occurred. j In July 1992 the reactor fuel was converted from the original high-enriched uranium I

(HEU,90% U-235) to new low-enriched uranium (LEU,19.8% U-235). The HEU is presently stored in the fuel storage area at the end of the reactor pool.

The reactor facility supported several UMR courses over the year for a total of 2,596 -

student-hours. The reactor was visited by about 3,600 visitors during the past year. There were 849 participants in the U.S. Depanment of Energy Reactor Sharing Program.

The reactor produced 4,588 kilowatt-hours of thermal energy using approximately 0.237 grams of uranium. A total of 206 samples were irradiated at the reactor with most of them being I analyzed in the Reactor Counting Laboratory.

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ee 11 Table of Contents 1.0 Introduction 1 1.1 Background Information . . I 1.2 Facility Status . .2 1.2.1 General . .2 2.0 Reactor Staff and Personnel .6 2.1 Reactor Staff. .6 2.2 Licensed Operators .6 2.3 Radiation Safety Committee . .7 2.4 Health Physics . .8 3.0 Reactor Operations .9 4.0 Public Relations 19 5.0 Educational Utilization . .21 6.0 Reactor Health Physics Activities .26 6.1. Routine Surveys .26 6.2. By-Product Material Release Surveys .26 6.3. Routine Monitoring . 27 6.4. Waste Disposal .28

. 6.5. I[istrument Calibrations . . 28 l

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, Table of Contents (cont.)

7.0 Plans . . . . . .29 7.1. Reactor Instrumentation Upgrade . 29 7.2. Shipment of HEU Fuel Offsite .30 7.3. LEU Fuel Characterization . .30 7.4. Expansion of Research Capabilities . . . .30 Appendix A. Standard Operating Procedures Changed During the Past Year 31 6

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- List of Tables Table 3-1. Core 10lW Technical Data .. . 10 Table 3-2. Scrams . . . . . 12 Table 3-3. Rundowns And Unplanned Shutdowns . . . 13 Table 3-4. Maintenance . . . . 14 Table 3-5. Facility Use Other Than The Reactor . . . . 18 Table 3-6. Reactor Utilization . .. . . I8 Table 4-1. Public Relations Program . 19 Table 5-1. UMR Classes at Reactor Facility 1993-94 Reporting Period . 22 Table 5-2. Reactor Sharing Program . . . . 24 List of Figures Figure 3-1. UMRR Core Configuration . . . . .. .. I1 a

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1.0 INTRODUCTION

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l This progress report covers activities at the University of Missouri-Rolla Reactor 'I (UMRR) Facility for the period April 1,1994 to March 31,1995.

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 !

universities, colleges, and high schools have made use of the facility during this reporting period. I The facility is also available for the training of reactor personnel from nuclear electric utilities.

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

facility.

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1.1 Background Information The University of Missouri-Rolla Reactor facility attained initial criticality on December 9th,1961. The UMRR was the first operating nuclear reactor in the state of Missouri. The reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. The initial licensed power was 10 kW. The licensed power was upgraded to 200 kW in 1966. During the summer of 1992, the reactor fuel was changed 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 natural convection flow.

The fuel is MTR plate-type 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,

2 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 spectmm analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment.

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

1.2.1 General The LEU conversion project is nearly complete. Several core characterization studies have been completed with the new core. A master thesis has been completed that involves the detailed measurement of dose rates associated with the HEU fuel. This information is being used to develop an ALARA procedure for transferring the fuel elements from the pool storage pit to the shipping cask.

We are continuing efforts to upgrade our console using grant awards from DOE combined with money directly from reactor funds. The total funds received from DOE combined with money committed from the reactor account totals to $167,000 available for the console upgrade.

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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

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. 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" We have installed a Yokogawa micro-R 1000 temperature stripchart recorder. The recorder replaces our old pool temperature recorder. We have also installed two test input jacks adjacent to the recorder to facilitate testing. The replacement was performed under the provisions of 10CFR50.59. The safety evaluation performed for the new temperature recorder and test jacks determined that no unreviewed safety questions were involved. l In January 1995, the Log N detector power supply (high voltage and compensating l 1

voltage) burned out while the reactor was shut down. We replaced the detector power supply with the detector power supply provided in one of our new Gamma Metrics drawers (the Wide l

Range Linear Drawer). Only the detector power seiy portion of the Gamma Metrics drawer is !

being used. The replacement of the detector power supply was performed under the provisions of 10CFR50.59 The safety evaluation performed for the replacement determined that no unreviewed safety questions were involved.

The Reactor Facility was audited in July of 1994 by an independent auditor from the University ofIllinois. We have entered into a new agreement with both the University ofIllinois and the University of Missouri-Columbia to rotate audits. We feel this will be very beneficial to all facilities involved.

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

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4 been continued in order to let both students and faculty in a number of departments across i

f campus know how the reactor could be used to enhance course work and research. As a result, additional classes have used the Reactor Facility as a part of their laboratory courses, including Physics 4 & 5, " Concepts in Physics"; Chemistry 8, " Qualitative Analysis Laboratory"; Physics 107, " Modern Physics"; Chemical Engineering 261, " Introduction to Environmental Engineering";

Chemistry 2, " General Chemistry Laboratory"; Mechanical Engineering 229, " Energy Conversion"; Life Science 352, " Biological Effects of Radiation"; Chemistry 251, " Intermediate (

Quantitative Analysis"; Chemistry 355, "Instmmental Methods Laboratory"; and Engineering Management 386, " Safety Engineering Management" I Much effort has been invested over the past year in revising SOPS to improve our j operations and efliciency. The following is a list of SOPS revised during the reporting period:

SOP 101 General Operational Procedures SOP 102 Pre-Stanup Checklist Procedures SOP 105 Reactor Shutdown & Reactor Securing Procedures SOP 208 Reactor Security SOP 501 Emergency Procedures for Reactor Building Evacuation SOP 502 Emergency Procedures for an Unusual Event SOP 503 Emergency Procedures for an Alert SOP 504 Emergency Procedures for a Site Area Emergency SOP 505 Enhanced Reactor Security SOP 506 Bomb Threat SOP 507 Emergency Procedures-Administrative Responsibilities SOP 508 Tornado Threat SOP 509 Fire SOP 510 Earthquake SOP 600 General Health Physics SOP 602 Entry Into a High Radiation Area SOP 604 Radioactive Waste Handling Criteria ,

SOP 620 Decontamination Procedures SOP 621 Guidelines for Emergency Exposures SOP 622 Handling Injured in Radiation Accidents SOP 650 Radiation Area Survey

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. SOP 651 Contamination 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 702 Irradiation Request Form SOP 800 Semi-Annual Checklist SOP 806 Temperature Channel SOP 810 Weekly Check The above listed SOPS are provided in Appendix A.

In addition, the Emergency Plan has been updated and revised (Rev. 6, December 30, 1994) under the provisions of 10CFR50.54q. Efforts are currently underway to submit to proposed revisions to the Emergency Plan that will reduce the number of emergency categories for NRC approval.

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.. 2.0 REACTOR STAFF AND PERSONNEL -

m 2.1 Reactor Staff Name lide Albert E. Bolon ' Director David Freeman Reactor Manager Linda Pierce Senior Secretary William Bonzer Senior Electronics Technician James Jackson Senior Lab Mechanic Hatem Khouaja Reactor Operator l 2.2 Licensed Ooerators Name License Albert E. Bolon Senior Operator David Freeman Senior Operator Hatem Khouaja Reactor Operator Matt McLaughlin" Senior Operator Shahla Keyvan" Reactor Operator

" Licensee placed on " Inactive" status by facility management.

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. 2.3 Radiation Safety Committee The Radiation Safety Committec meets quarterly. The committee met on 6/14/94,9/9/94, 10/25/94,1/24/95, and 2/7/95 during the reporting period. The committee members are listed below:

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

Mr. Randy Stoll Interim Vice Chancellor for Financial Services I

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8 2.4 Health Physics ,

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

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

Safety Services and Campus Health Physicist 2

Ms. Lisa Stiles ) HP Technician Mr. Chad Little HP Technician Mr. Justin Hillero HP Technician Mr. Paul Jason Dobson" HP Technician Mr. Darrell Liles HP Technician l Ms. Rebecca Steinman') HP Technician t Mr. Brian Richardson') HP Technician 1

' Terminated effective August 13,1994.

23 Terminated effective December 17,1994. .

3) Employed effective August 2,1994.

') Employed effective October 18,1994.

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-.; 3.0 REACTOR OPERATIONS 1'

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 thermal column) may be used for various experiments, including beam port and thermal column I

experiments.

Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of

, core 10lW. The excess reactivity, shutdown margin, and rod worths were measured in cold clean -

conditions.

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

Maintenance activities are listed in Table 3-4. Table 3-5 shows facility use other than the reactor and Table 3-6 shows reactor utilization.

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i 10 Table 3-1. Core 101W Technical Data ,

Parameter Value Rod 1 2.73% Ak/k l'

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 1

) Assumes Rod 3 (highest worth rod) and Reg Rod are fully withdrawn.

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. Fi Fure 3-1. UNIRR Core Configuration DATE Juiv 28.1992 LOADING NUMBER 101W i

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

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l-12 Table 3-2. Scrams ,

Daig Cause .

11/02/94 Period < 5 Sec Period Scram Cause: Spurious signals in Period Channel during a startup.

Corrective Action: Checked and cleaned connectors on Log N and Period drawer.

11/02/94 Period < 5 Sec Period Scram Cause: Spurious signals in Period Channel during a startup.

Corrective Action: Rerouted Log N and Period detector cables away from Fission Chamber cable. Checked connectors. Tapped on equipment to check for noise.

Rerouting of cables seemed to fix the problem. Cables had been previously rerouted for neatness.

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Table 3-3. Rundowns And Unplanned Shutdowns ~ j

i Date Cause ;

i 06/07/94 120% Demand Rundown. !

Cause. Trainee failed to properly upscale linear meter. [

Corrective Action: Trainee instructed on switching scales. SRO permission to l restart granted. .;

i 04/19/94 120% Demand Rundown.

Cause: Student failed to properly upscale linear meter. :

Corrective Action: Student instructed on switching scales. SRO on Duty I recovered rundown and granted permission to restart. ;

03/07/95 120% Demand Rundown :

Cause: Student failed to properly upscale linear meter.

Corrective Action: Student instructed on switching scales SRO on Duty l recovered rundown and granted permission to res+ art. '}

r 03/23/95 120% Demand Rundown. I Cause: A spike in the linear signal to the Linear Recorder occurred due to !

switching scales at 100%. This happened twice for the trainee and once for the i SRO in a 1 1/2 hour period. l Corrective Action: Trainee instructed on switching scales. SRO recovered rundown and granted permission to restart. Switches for changing scales on the i linear meter were cleaned. A channel test was performed.

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Table 3-4. Maintenance ,

Date Cause 04/11/94 Problem: Bridge High Area Radiation Alarm activated without high radiation present.

Corrective Action: Repositioned detector shield and tightened.

06/01/94 Problem: Semi-Annual Maintenance.

Corrective Action: Regularly scheduled calibration of all channels.

06/06/94 Problem: Installation of new Temperattce Recorder.

Corrective Action: Replace Temperaturc Recorder, #2 thermocouple, and #2 thermocouple wire. Calibrated Temperature Channel. Installation approved by Radiation Safety Committee under 10CFR50.59.

07/11/94 Problem: Conductivity Cell B had water dripping from cable entering the cell.

Corrective Action: Removed Cell B, sealed leak, and reinstalled Cell B. Replaced 1 temperature compensating resistors and vaternal power supply capacitor in the conductivity bridge. Calibrated conductivity bridge. Checked alarm action.

07/25/94 Problem: Safety Channel No. I reads 5% while Reactor is secured. t Corrective Action: Replaced vacuum tube in the Safety Channel pre-amp.

Calibrated Safety Channel.

07/25/94 Problem: Log N level was reading 1 decade high while Reactor was secured.

Corrective Action: Cleaned switches and connectors. Repositioned wiring at Period calibration switch in the Log N Drawer. Calibrated the Log N Drawer.

07/28/94 Problem: Log N signal was drining while Reactor was shut down.

Corrective Action: Cleaned connector and recalibrated drawer.

07/29/94 Problem: Log N Recorder was reading offlen edge of chart paper with Reactor shutdown.

Corrective Action: Mechanically adjusted the pen to proper position. Checked ,

120% full power trip point. Calibrated the Log N drawer. ,

07/29/94 Problem: Safety Channel No. I reads high.

Corrective Ac6 >n: Calibrated Safety Channel and repositioned the UICs. -

08/15/94 Problem: Safety Channel read 5% with Reactor secured.

Corrective Action: Recalibrated the Safety Channel drawer.

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Table 3-4. Maintenance (cont.)

D. ale Cause 08/29/94 Problem: Startup Channel was reading 100 CPS, a drop to 2 CPS occurred for a few seconds, then it returned to 100 CPS. t Corrective Action: Inspected Fission Chamber cable. Replaced a BNC barrel connector at the end of this cable. The problem was alleviated with replacement of 2 discriminator transistors on 11/22/94. ;

09/01/94 Problem: Demineralizer RAM meter reading had dropped to zero.

Corrective Action: Resoldered 5 volt regulator transistor. Performed a channel test.

t 09/21/94 Problem: Regulating rod would not stay in auto control Corrective Action: Replaced P.A.T. 60 relays and adjusted gain.

10/06/94 Problem: Startup Channel is noisy.

Corrective Action: Cleaned connectors on Startup Channel drawer. The problem was alleviated with replacement of 2 discriminator transistors on 11/22/94.

10/17/94 Problem: Startup Channel signal started to oscillate from 10 CPS to 100 CPS during a Pre-Startup check.

Corrective Action: Replaced cable from the pre-amp to the Fission Chamber cable. Checked connectors. The problem was alleviated with replacement of 2 :

discriminator transistors on 11/22/94.

10/18/94 Problem: Period Recorder stayed on an indicated 4 Sec Period after a pre-startup detector spike.

Corrective Action: Oiled recorder gears and pulleys.

i' 10/25/94 Problem: Startup Channel signal is oscillating.

Corrective Action: Replaced cable from the pre-amp to Fission Chamber cable as a troubleshooting technique. Recalibrated the Startup Channel. The problem was alleviated with replacement of 2 discriminator transistors on 11/22/94.

- i 10/26/94 Problem: Startup Channelis noisy.

Corrective Action: Removed the Fission Chamber from core for inspection of connector and cable. Installed new ground straps on pre-amp to bridge.

Recalibrated Startup drawer. The problem was alleviated with replacement of 2 discriminator transistors on 11/22/94.

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Table 3-4. Maintenance (cont.) , _.

i Dale Cause !

._ j 11/04/94 Problem: Startup Channel read low while Reactor is secured and source in source !

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l Corrective Action: Exchanged transistors in the discriminator circuit that were i identical to each othr. Cleaned ground wire to console. Calibrated Stanup .!'

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Channel. The problem was alleviated with replacement of 2 discriminator transistors on 11/22/94. i 11/22/94 Problem: Startup Channel drawer discriminator has reached its limit for ;

adjustment. !

Corrective Action: Replaced 2 transistors in the discriminator circuit. Performed !

a channel calibration. (This action finally corrects much of our previous Startup [

Channel problems.)

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11/22/94 Problem: Safety Channel No. I was reading 5% with Reactor shut down. :

Corrective Action: Recalibrated the Safety Channel Drawer No. I and No. 2 !

channels. .

t 12/20/94 Problem: Semi-Annual Maintenance ;

Corrective Action: Regular scheduled calibration of all channels. [

. .t 01/04/95 Problem: Preventative Maintenan e - Cable upgrade for Log N CIC detector.

Corrective Action: Replaced existing coax cables with new coax cables and connectors. ;

1 01/09/95 Problem: Log N Channel is not giving proper signals while Reactor is shut down.

Corrective Action: _ Removed CIC detector. Temporarily substituted another CIC detector. Checked cables and connectors. Calibrated channel. Removed the temporary CIC detector Refurbished a connector on the original CIC detector.

Installed the original CIC detector. Calibrated the Log N Channel.

i 01/10/95 Problem: Temperature Recorder not printing date. fi Correctivc Action: Readjusted plotter pen to specifications. -

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01/27/95 Problem: Log N detector power supply burned out with reactor shut down. t Corrective Action: Replaced the Log N power supply with another power supply. .

Approved by the Radiation Safety Committee under 10CFR50.59.

t 03/03/95 Problem: Installation of the mocouple test jacks to facilitate testing. l Corrective Action: Installed 2 type K thermocouple jacks for routine testing ;

purposes during weekly checks. It has been reviewed and approved by the Radiation Safety Committee under 10CFR50.59. i

17 Table 3-4. Maintenance (cont.)

Dalt .Callic 03/03/95 Problem: Stanup Channel drawer reading wouldjump from 10 CPS to 20 CPS while doing the Pre-Stanup Checklist.

Corrective Action: Replaced the discriminator adjustment potentiometer. A channel test was performed.

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I 18 Table 3-5. Facility Use Other Than The Reactor ,

Exility Houc .

Bare Rabbit Tube 11.58 Cadmium Rabbit Tube 1.17 Beam Port 6.83 Other Core Positions 5.87 Total 25.45 Table 3-6. Reactor Utilization

1. Reactor use 413.0 hr

a. Research and irradiation runs 90.3 hr

b. Instruction runs (NE Classes) 273.4 hr

c. Maintenance runs (2) 14.0 hr

d. Training (3) 35.3 hr

2. Time at power 151.7 hr

3. Energy generated 4.588.0 kw-hr

4. Total number of samples 206

5. Sample hours 25.45 hr

6. U-235 Burned 0.200 g

7. U-235 Burned and Converted 0.237 g O

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19 4.0 PUBLIC RELATIONS The reactor staff continues to educate the public about applications of nuclear science.

Over 3,600 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 04/13/94 UMR Physics 4 & 5 Concepts in Physics, Dr. R. Bieniek 7 04/16/94 UMR Spring Open House 106 04/19/94 UMR Chemistry 8, Qualitative Analysis, Dr. T. Bone 34 05/03/94 Cub Scouts 19 05/06/94 UMR Physics 107, Modern Physics, Dr. A. Pringle 48 06/06/94 UMR Jackling Tours 45 06/13/94 UMR Jackling Tours 42 06/13/94 UMR Fundamennis of Engineering 25 06/14/94 UMR Fundamentals of Engineering 27 l

06/15/94 UMR Fundamentals of Engineering 23

, 06/20/94 UMR Jackling Tours 36 07/27/94 UMR ChemE 261, Intro to Environmental Eng. J Stevens 7 08/01/94 UMR Fundamentals of Engineering 37 I 08/02/94 UMR Fundamentals of Engineering 33 08/03/94 UMR Fundamentals of Engineering 20 08/04/94 UMR Fundamentals of Engineering 25

_08/08/94 UMR Fundamentals of Encineerina 24

20 Table 4-1. Public Relations Proargm DATE PARTICIPANTS NUMBER 08/9/94 UMR Fundamentals of Engineering 23 08/10/94 UMR Fundamentals of Engineering 55 09/19-22/94 UMR Chemistry 2, General Chemistry Laboratory, Dr. T. Bone 668 09/20/94 Cub Scouts, Waynesville Pack 154 19 10/15/94 UM-Rolla Day 251 10/22/94 UMR Parents Day 225 11/17/94 UMR NE 105 Fund of Nuclear Eng., Dr. N. Tsoulfanidis 8 11/28/94 UMR ME 229. Energy Conversion, Dr. J. Sheffield 16 11/30/94 UMR ChemE 261 Environmental Engineering. Dr. D. A. Sanders 30 12/02/94 UMR ChemE 261 Environmental Engineering, Dr. D. A. Sanders 25 12/05/94 UMR ChemE 261. Environmental Engineering. Dr. D. A. Sanders 30 12/07/94 UMR Physics 107, Modern Physics, Dr. A. Pringle 59 12/19/94 Offsite Emergency Training 5 12/22/94 Cub Scouts, Pack 145 17 01/30/95 UMR LSc 352, Biological Effects of Radiation, Dr. Roger Brown 15 02/01/95 UMR LSc 352, Biological Effects of Radiation, Dr. Roger Brown 13 02/13/95 UMR Chemistry 2, General Chemistry Laboratory, Dr. T. Bone 35 02/15/95 UMR Chemistry 2, General Chemistry Laboratory, Dr. T. Bone 32 02/16/95 UMR TEAMS Testing 45 02/18/95 Boy Scouts - Merit Badge University 38 -

03/25/95 Spring Open House 98

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. 1 21 l 5.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 2,596 ]:

student-hours. The munber of UMR students utilizing the facility was 1,068. This increased i usage is a direct result of an aggressive and continuing campus wide " outreach" program. The . 1 reactor facility provided financial support for three students with hourly wages and one PhD 1

candidate with a 0.5 FTE Graduate Research Assistantship. Additionally, students from several universities, colleges and high schools have used the facility.

Table 5-1 lists UMR classes taught at the facility along with associated reactor usage for j i

this reporting period.

The Reactor Sharing Program, which is funded by the U.S. Department of Energy, was established for colleges, universities, and high schools which do not have a nuclear reactor. This year,849 students and their instructors participated in this program. Table 5-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of our participants were high school students. We 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 Computer Integrated Manufacturing Lab, Mineral Museum, Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor Sharing Program serves as a strong campus-wide recruiting tool by getting high school students to the university and hopefully sparking some interest in our campus.

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Table 5-1. UMR Classes at Reactor Facility 1994-95 Reporting Period TIME AT ;

OF REACTOR STUDENT !

DATE CLASS NUMBERfflTLE STUDENTS (hrs) HOURS i 04/13/94 Physics 4 & 5 - Concepts in Physics 7 2.0 14.0 04/19/94 Chemistry 8 - Qualitative Analysis 34 1.0 34.0 05/06/94 Physics 107 - Modern Physics 48 0.5 24.0 07/27/94 ChemE 261 - Introduction to 7 0.5 3.5 Environmental Engineering Fall 1994 NE 304 - Reactor Laboratory 14 53.0 742.0 Fall 1994 hT 306 - Reactor Operations 6 36.0 216.0 Fall 1994 NT 490 - Research 1 10.0 10.0 09/19-22/94 Chemistiy 2 - General Chemistry 668 0.5 334.0 Laboratory 11/17/94 NT 105 - Fundamentals of Nuclear 8 0.5 4.0 Engineering 11/28/94 ME 229 - Energy Conversion 16 0.5 8.0 11/30/94 ChemE 261 - Environmental 30 1.0 30.0 Engineering 12/02/94 ChemE 261 - Environmental 25 1.0 25.0 Engineering 12/05/94 ChemE 261 - Environmental 30 1.0 30.0 Engineering 12/07/94 Physics 107 - Modern Physics 59 0.5 29.5 Winter 1995 NE 300 - Special Problems 2 28.0 56.0 i Winter 1995 NE 306 - Reactor Operations 6 36.0 216.0 -

Winter 1995 NE 308 - Reactor Laboratory II 11 55.0 715.0 Winter 1995 NE 400 - Special Problems 1 8.0 8.0 ;

01/30/95 LSc 352 - Biological Effects of 15 10 15.0 Radiation ,

I 23 Table 5-1. UMR Classes at Reactor Facility 1994-95 Reporting Period TIME AT

OF REACTOR STUDENT i DATE CLASS NUMBER / TITLE STUDENTS (hrs) HOURS 4

02/01/95 LSc 352 - Biological Effects of 13 1.0 13.0 Radiation 02/13/95 Chemistry 2 - Generai Chemistry 35 1.0 35.0 Laboratory 02/15/95 Chemistry 2 - General Chemistry 32 1.0 32.0 Laboratory ,

TOTAL 1068 239 2596 t

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i 24 Table 5-2. Reactor Sharing Program (1994-1995)

DATE PARTICIPANTS NUMBER 04/11/94 Rolla 5th Grade, Elaine Edgar 54 1 04/13/94 Southwest Missouri State University, Dr. Robert Mayanovic 5 04/14/94 Vienna High School, Geraldine Fritchey 11 04/21/94 East Central College, Debbie Schatz 19 04/21/94 Spring Bluff Middle School, Sullivan 19 04/25/94 North Callaway Middle School 12 04/28/94 St. James High School, Jim Jenkins 13 t 5/94 Michelle Darby, Malden High School 1 ,

05/03/94 Seckman Junior High School 15 05/05/94 Potosi 8th Grade Alan Ziegler 13 05/20/94 Steelville Middle School 62 06/20/94 Strafford 5th & 6th Grade 37

[

06/22/94 Houston High School 17 07/11/94 Teachers from Thailand, Dr. Sparlin 10 l

10/18/94 Conway High School, Phil Dasis 18 -

10/19/94 lloiman & Williams Middle School, Jackie Vandivort 62 10/25/94 Union High School, Linda Richardson 52 11/02/94 Dixon High School 38 l 11/08/94 Sullivan High School, Charles Holcomb 9 11/22/94 Crocker High School, Laura Jay 26 11/29/94 West Plains High School, Connie Henry 36 . !

12/06/94 Vo-Tech Radiology, Maggie Ogden 21 !

35 i 01/25/94 Washington High School, Richard Schwentker 02/01/95 Eminence High School, Shelley Williams 10 !

02/03/95 Rolla 5th Grade, Elaine Edgar 58 02/22/95 Potosi High School, Bill Nelson 8 7 02/22/95 Salem Science Club, John Hambacker 14

[

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25 Table 5-2. Reactor Sharing Program (1994-1995) ,.

DATE PARTICIPANTS NUMBER 03/08/95 Hazelwood West High School, Gail Haynes 25 03/14/95 West Plains Middle School, Barbara Alsup 91 03/20/95 Paul Middendorf, School of the Osage 2 03/21/95 East Central College. Debbie Schatz 17 03/21/95 Park Hill High School, Barbara Bnins 26 03/29/95 Vienna High School, Geraldine Fritchey 13 TOTAL 849 l

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t 6.0 REACTOR HEALTH PHYSICS ACTIVITIES ,

. i 1

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 ;

i and waste disposal. Releases of all by-product material to authorized, licensed recipients are' :

surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of j non-routine procedures.

6.1. Routine Surveys i

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 ;

i significant contamination outside of contained work areas was found.

i 6.2. Bv-Product Material Release Surveys ,

i There were no shipments of by-product material released off-campus from the reactor facility during this reporting period. j l

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~,: .- __ _ _ _ _ . . _ _

_ _ _ _ _ _ _ _ _ _ _ ___ _ __ _ _ _ _______.___ _ _ _ i

27 6.3. Routine Monitoring Thirty-nine reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Five are read twice per month (Reactor Staff) and thirty-four are read once per month. There are four area beta-gamma / neutron badges assigned.

Twenty-two 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 24 monitor and spare badges asugned on campus. In addition,8 direct-reading dosimeters are used for visitors and high radiation area work. There have been no significant personnel exposures during this reporting period.

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

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

Pool water activity is monitored monthly to ensure that no gross pool contamination or fuel cladding rupture has occurred. Gross counts and spectra oflong-lived gamma activity are compared to previous monthly counts. From April 1994 through March 1995 sample 4

concentrations averaged 14.3 x 10 Ci/ml.

l

_ _ . . _ _ _ 4 ._ . ___ ._ _- - .. - _ ._ _. _ __ __ _ .

1 Y .l 28 :

Waste Discosal

. 6.4.

l.

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

~

relating the operating times of the exhaust fans and reactor power during fan operation to i'

previously measured air activity at maximum reactor power. During this. period 60.041 millicuries were released into the air. The released isotope was identified as Ar-41.

.t Solid waste, including used water filters, used resins and contaminated paper is stored .j i

and/or transferred to the campus waste storage area for later shipment to a commercial burial site. I Water is analyzed for radioactive contamination and approval is required before the water is released. During this period one water release was discharged to the sanitary sewer totaling approximately 55 gallons of water with a total gross activity of 5.8x10'8 millicuries. j l

6.5. Instrument Calibrations I

During this period, ponable instruments and area monitors were calibrated at six month t

intervals.

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29

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

7.1. Reactor Instrumentation Uograde We have acquired three new NI channels from Gamma-Metrics which will ultimately ,

replace our existing five channel system. Additionally, we have recently purchased three Leeds >

and Northrop strip chart recorders. A total of $167,000 has been secured for the console upgrade. The U.S. DOE has provided $137,000 and $30,000 is being directly provided by the UMR Reactor.

As instruments are installed, extensive review documentation will be established and appropriate approvals will be obtained. Many changes will be made under the provisions of 10CFR50.59. Several changes will require NRC approval.

Detailed testing is now being performed on the equipment and extensive operational data is being collected. We feel that the funds we now have are sufficient for providing almost a complete console upgrade. As the new equipment is installed, the reliability and efficiency of console operations will be greatly increased.

J

i 30 7.2. Shioment of HEU Fuel Offsite ,

Efforts will continue during the next reporting period to ship our HEU fuel offsite. We hope to complete the project within the next year. Measurements and analyses have been completed that have characterized dose rates associated with each element.

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

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

We plan to continue the studies and to that end we have submitted a proposal to DOE for funding. In particular, we would like to do detailed gold wire flux mapping of the core, detailed energy spectrum characterization of our experimental facilities, and a precise measurement of reactor kinetics parameters.

7,4. Exoansion of Research Cacabilities Over the next year, efforts will continue to expand the facility's research capabilities. In particular, we are placing much emphasis on computer interfacing with the new console equipment. The new equipment has been specially designed to provide isolated signal outputs dedicated to interfacing with computer data acquisition stations. There is great faculty interest in this capability with planned research in the areas of artificial intelligence, neural networking and an .

l " operator advisory" system.

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5 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE PAST YEAR f

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

. SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES

. Revised: March 20, 1995 Page 1 of 3 A. PURPOSE:

To provide written general operational procedures for routine operations. Rev.

B. PROCEDURE

1. Reactor operations must at all times meet the requirements of the Facility License R-79, Technical Specifications, and the Physical Security Plan.

2. At least two persons, one of whom is a Senior Operator, shall be present in the Reactor Building when the reactor is operating.

3. a) A licensed operator who is responsible for reactor operation shall be present in the control room at all times wher. the reacter is operatin3-b) Students and trainees may operate the reactor controls subject to the following conditions. In such cases the licensed operator maintains complete and total responsibility for all aspects of reactor operations.

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

ii) Trainees may operate the reactor controls under the direct supervision of a Senior Reactor Operator when the excess reactivity is greater than 0.7% delta k/k and less than 1.5% delta k/k.

4. The reactor will be operated with the minimum amount of excess reactivity necessary to fulfill operational requirements as determined by the Reactor Director. Rev.

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

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

hev.

Revised By: David rpe Approved By: Albert Bolon pk n.c OuMJn l

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"* UMR REACTOR STANDARD OPERATING PROCEDURES *** f SOPi 101- TITLE: GENERAL OPERATIONAL PROCEDURES !

Revised: ' March 20, 1995- Page 2 of 3

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. 7. . Log books will be kept in the control room safe, except the one currently in use, . !

which may be kept on the console. If the books are removed from the control .

room, permission must be granted by the Reactor Manager. Any books removed ;

shall be returned as soon as possible. Rev.

.i

. 8. Only the Senior Operator on Duty may key bypass control channel automatic j functionsf The use of any interlock bypass key requires a permanent log entry for :

insertion and removal. This log entry shallinclude date and time. This j requirement does not apply when the reactor is shut down (e.g. performance of j the Weekly Checklist procedure). l i

9. Any abnormal behavior or abnormal change in core reactivity associated with ' l' reactor startup or operation should be reported to the Senior Operator on Duty .

immediately. If there is any doubt about reactor safety, the reactor shall be :

immediately shut down by the Operator-on-Duty. The cause should then be !

determined and corrective action taken. Rev. .

10. The Standard Operating Procedure (SOPS) should be followed to the extent practicable, especially whenever the Pre-Startup Checklist is being completed. [

when the reactor is being started, or when the reactor power is being changed. e i

11. The Senior Operator on Duty has the authority to instruct the reactor operator to j disregard certain SOPS provided that no safety requirements are violated. (For. ;

example, SOP 305 does not have to be performed every pre-startup checklist.)

12. All surveillance time intervals referred to in the SOPS are as defined in Section 1 of Rev. ,

the Technical Specifications. l i

13. The following procedures are to be performed by the Reactor Senior Electronics 1 Technician or other qualified individual as determined by the Reactor Manager. A ,

licensed operator will participate when reactor operation is involved (e.g. Rod '!

Drop Time Measurements). ,

Rev.

~ SOP 655, " Radiation Area Monitor (RAM) Calibrations" SOP 800, " Semi-Annual Checklist" .;

SOP 801, " Log N and Period Channel" ,

SOP 802, " Linear Channel" l

l Revised By: David Free Approved By: Albert Bolon !

i /!g:7&dil Q[Q$pfew .

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *" !

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES March 20,.1995

, Revised: Page 3 of 3 L- ,

' SOP 803, " Log Count Rate (LCR) Channel" SOP 804, " Safety Amplifier System" i SOP 805,'" Auto Control System" )

SOP 806, " Temperature Recorder" SOP 807, " Neutron RAM System" SOP 809, " Relay Test" 1 SOP 811, " Fire and Smoke Alarm System" SOP 813, " Rod Drop Time Measurement" SOP 818, " Functional Test of Building Security System" hev.

14. Only person (s) specifically approved by the Reactor Manager shall perform the !

follow'mg procedure:

SOP 204, "Demineralizer Regeneration" !

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Revised By: Davidf g Albert Bolon 7)..sf G' Approved By: & tt$cw

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

.- SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revision: June 6, 1994 Page 1 of 9 A. PURPOSE:

The purpose of the checklist is to verify that reactor systems are operating conectly prior to reactor start-up. '

E B. PRECAUTIONS. PREREOUISITES. OR l> IMITATIONS:

1. A licensed operator shall be responsible for performing the pre-startup checklist.

The operator may assign various steps to be completed by unlicensed personnel; however, the operator is still fully responsible for the proper performance of the checklist. ,

2. The checklist shall be completed prior to the first reactor start-up of the day. The !

checklist shall be completed prior to a reactor start-up after a " Secure" checklist has been completed.

3. After each step on the checklist is performed the operator will record the readings made, or in cases where no readings are required, will simply check the l appropriate blank on the form. ;

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

C. PROCEDURE ,

I Complete the checklist in accordance with the following steps: l

1. Date and Initials - Record the date using the rubber date stamp and record the Rev.

initials of the person performing the checklist. )

2. Time - Record the time shown on the console clock. -!

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

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

i Written By: David Freegan Approved By: Albert Bolon i e2 b'*N @@ 3b

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES -

Revision: June 6, 1994 Page 2 of 9 ,'

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5. RAM System Check: l h

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 AC7 ION

1. Bridge RAM 10 - 18 mR/hr High Radiation Alart i ,

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

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"

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

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

8. Beamport and Thermal Column Status: Record the status of the beamport and ,

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" Approved By: Albert Bolon Written By:)D iat WP";

9id Fre QQ{Q

i' *** UMR REACTOR STANDARD OPERATING PROCEDURES "*

. SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES

.. . Revision: June 6, 1994- Page 3 of 9

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.

10. CIC Voltages: Record the high voltage (HV) and compensating voltage (CV) settings of the Linear and Log N Power supplies. Values should correspond -

approximately to ti,ose presented in the table below:

CIC HV CV Linear 480 2 to 8 Log N 540 6

11. a. Turn on and date the Startup, Linear, Period, and Log N recorders. Reset Rev.

the annunciator panel.

b. Observe the temperature recorder " RCD" is illuminated in the upper lefthand corner of the display.

12. Core Check: Turn the pool lights on.

. a. Check the water level in the pool.

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

i

c. Insert the source into the core source holder.

David 9 Written By: pa>,eem] < Approved By. Albert Bokonas w

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES

Revision. June 6, 1994 Page 4 of 9 ,

2 3

13. Start-Up Channel Test: Turn the Log Count Rate selector switch to 10,10, and 104 . Verify that the meter and recorder follow. Return the selector switch to the " OPERATE" position.

14. Verify Fission Chamber Response: Insert the fission chamber until the green Insert Limit light comes on. Observe the count rate. Raise the fission chamber until the count rate shows a definite decrease.

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

16. Log N Test: Check that the meter generally follows the recorder response for the

" LOW" and "HIGH" check.

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

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

c. Reset the annunciator panel.

17. Period Response Test:

a. Turn the period switch to "C ALIBRATE". Verify the receipt of the Log N/ Period Non-Operative Scram. Check that the Period recorder and meter read about 6 seconds.

b. Verify the annunciator panel for Log N and Period Nonoperative,30 sec period and 15 sec period lights. Resct the annunciator panel. (Note: The l -

5 second Period Scram may also be illuminated.)

18. Turn on the magnet power using the key switch. Push the Scram Reset button to ,

energize the magnets. Reset the annunciator panel. If a magnet contact light is out, notify the SRO on Duty.

Written By: David Fre Approved By: Albert Bolon Ja sma-su

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** !

w SOP: 102'- TITLE: PRE-STARTUP CHECKLIST PROCEDURES l A Revision: June 6~, 1994 Page 5 of 9 !

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

o. i

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

mamp.) j 4

e

21. 150% Power Scram Check: l

a. Withdraw shim rods to 3 inches. -I

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

f

c. Verify that the rods hwe dropped and that the audible and visual alarms f have actuated. .!

l

d. Reset the drawer and annunciator panel. :

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

i

a. Withdraw shim rods to 3 inches !

b. Turn the period test switch to " CALIBRATE" to provide a 6 second ;

period indication. Check for the Log N Inoperative Scram, Manual Scram, i 15 Second Rundown, and 30 Second Period lights on annunciator panel. ,

i

c. Try to stop the run down by lifting the shimjoy stick. !

d. Pop the rundown with the rundown reset button. j

e. Verify that the rods have dropped. l

. I

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

23. Period Trip Test: j r

i

a. Withdraw shim rods to 3 inches. l I

Davjid reen mn Approved By: Albert Bolon l Written By: f.wn 34 st' ) gQ

,, , , - - . -- -P

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" UMR REACTOR STANDARD OPERATING PROCEDURES "*

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES

l

' Revision: June 6, 1994 Page 6 of 9 ,

I i

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

l

c. Rotate the " Trip Test" knob slowly and observe that the 30 second rod l withdraw prohibit annunciator is actuated with a simulated period 2 30 i seconds. i

d. Continue to rotate the knob and observe that the 15 second period l rundown occurs with a simulated period 215 seconds. {

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

l t

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

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

24. Manual Scram: f

a. Raise shim rods to 3 inches. [

b. Push the manual scram button. Verify that the rods have dropped by l visually observing the video display and noting that the blue magnet !

contact lights are off. 1 i

c. Push the scram reset button and reset the annunciator panel, j i

i 25. Push the annunciator test button and check for burned out bulbs. Replace any ;

j burned out bulbs. Reset the annunciator panel. ;

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

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27. ~ Prepare hourly and permanent logs. ,

j i

I Written By: a an Approved By: Albert Bolon e

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" UMR REACTOR STANDARD OPERATING PROCEDURES *** :

. SOP: 102 TITLE: PRE-STARTUP CH ECKLIST PROCEDURES _

?e Revision: June 6, 1994 Page 7 of 9 i

28. Detector Response Check: !

a. Inspect the core. Make certain core coolingis clear and experiments are firmly secured. ,

t

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

c. . Insert the source into the holder. !

d. Observe the Log N, Period and Linear recorders to verify proper response t to the source spike. l 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. l i

f. Reset the annunciator panel. i l'

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

30. Announce,"THE REACTOR WILL BE STARTED AND TAKEN TO A ;

POWER OF WATTS"

31. Record the intended power level. i

32. Review the Pre-Startup Checklist. Verify that all of the steps have been 1 completed. The licensed operator responsible for performing the checklist will ;

initial the checklist thus verifying that it has been properly completed. )

i

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

. 1

34. Record the date using the rubber date stamp.

Written By: gg Approved By: Albert Bolon saw :

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- - Uh1K KbAC I UK 5 I ANUKKITUt'tKA rtNffPROC1:DURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES ':

June 6, 1994 Revision: Page 8 of 9 6' :

. j UMRR P.RE-STARTUP CHECKLIST (SOP 102) i l

t i

1. Date and trutials l Rev. '

2. Time (Console Clock)

3. Coreleading !

4 P. A., Intercom, Video Monitor On i

5. RAM System Check ,

6 Radiation Level Normal ,

7. Nitrogen Dt1Tuser Status No I No 2 +

8 Beam Port and Thermal Column Status ,

i

9. Linear Channel Zero ;

Meter Reading Scale

10. C.I.C. Voltages Linear IIV (~480)

Linear CV (~4)

Lon N HV (~540) f Log N CV (-6) >

11. Recorders On and Dated

12. Core Check (Lights On) Level Check !

I Inspect Core Source Inserted i I 3. Start-Up Channel Test

14. Verifv Fission Chamber Response f I

15. Fission Chamber Insted Count Rate > 2 CPS i

16 1.oc N Test avid Approved By: Albert Bogn :

Written By: I'd{MoDreemy &\%&% W

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

f, SOP: 102 TITLE: PRE-STARTUP CilECKLIST PROCEDURES Revision: June 6, 1994 Page 9 of 9 e

17. Period Response Test I8 Magnet Power On, Scram Reset, Board Reset I 9. Inlet Temperature (*F)

20. Magnet Currents (milliamps) No I No 2 No 3 I

21.150% Power Scram Test Raise Rods 3 in. Push

" Test" Button

22. Log N/Penod Non-Operative Scram Raise Rods 3 in. Select and I 5 See Penod Rundmm Test Switch to "Cahbrate" 23 Penod Tnp Test 1

Raise Rods 3 in. Push j 24 Manual Scram Test Manual Scram

25. Annunciator Test, All Lights On 26 Magnets On. Rods on Insert i.imit 1

27. Prepare llourly and Permanent Logs 28 Deteetcc Response Check Inspect Core Log N Spike Perie,d Spike k

Linear Spike Startup Channel

Response

29. Raise Rods to 6 in-, Record Time in Both Lees 30 Announce Intention to Stan

31. Intended Power Level

32. Pre-Stanup Check Properly Completed (Lie Op Initials) 33 Senior Operator's initials

34. Date Written By David F - Approved By: Alben Bolon

/ aD.# .

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

, SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR

, SECURING PROCEDURES ,

Revised: June 6, 1994 Page1 of4 A. PURPOSE r

To ensure a safe and consistent method to shutdown the Reactor from an operating l condition and, when advised by a Senior Operator on Duty, to secure the reactor. ;

B. _ PRECAUTIONS. PREREOUISITES. AND LIMITATIONS

1. The SRO on Duty will decide if the Reactor is to be " SHUTDOWN" or

" SECURED"

2. An operator assistant shall be present if the Reactor is not in " AUTO" before the f shutdown begins to take logs

3. The RO must be alert to the indication ofjamming of control rods during the r shutdown process. If this occurs, stop driving in the rods and inform the SRO on Duty.

4. The Reactor will be secured at the end of the work day.

f f

C. "SilUTDOWN" OF REACTOR r

1. Log time, initials, followed by " SHUTDOWN" in the hourly log.

2. Log time and " SHUTDOWN" in the permanent log. ;

3. Announce over the public address system, "The reactor will be shutdown"

4. Trip " AUTO /M ANUAL" switch to " MANUAL" (ifin " AUTO").

' i

5. Place the " OPERATE / SHUTDOWN" switch in " SHUTDOWN" position or insert :

safety rods and regulating rod with bothjoysticks.

6. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (I button to left) when the Linear Recorder decreases to 10% of the !

Written By: David Freeman Approved By: Albert Bolon fd hNhe.b l

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** -

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR !

L SECURING PROCEDURES i

I Revised: June 6, 1994 Page 2 of 4 i

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 insening fission chamber.

8. When the rods are fully inserted to their insen limits (green lights): J

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

9. Reactor is now " SHUTDOWN". ;

D. " SECURING" OF REACTOR ,

Refer to form SOP 105. .

i

1. Use date stamp.

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

3. All Shim Safety Magnet Contact (Blue) Lights on. .

4. Turn magnet key 90 degrees CCW and remove from console. Hand key to SRO on Duty.

5. Turn off the Log Count Rate, Linear, Period, and Log N recorders. Place date at Rev. ,

the top of each recorder chart (use date stamp).

i

6. Stamp the Log N Chart with the Log N Recorder Stamp and complete all requested information. (See example below.) .

l

7. Push Annunciator " RESET" The " MANUAL SCRAM", " RECORDERS OFF" :

- I and " MANUAL OPERATION" Annunciators will remain on.

Written By: David Freeman Approved By: Albert Bolon fu:7 hhh {;

I i

4 -

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

. SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR

. - SECURING PROCEDURES Revised: June 6, 1994 Page 3 of 4

8. Push Station #6 (REACTOR BRIDGE} intercom switch to return to the off position (button up). -l

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

10. Turn operation switch on Counter / Scaler to the off position. l l

11. Change CCTV monitor selector switch to the " DOOR" position.

12. Turn off the Nitrogen Diffusers, R.abbit System, Ventilation Fans, unless advised otherwise by the SRO on Duty.

l 13, Log time using a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock.

14. Your initials.

15. Senior Operator on Duty shall initial.

Any malfunctions or abnormal conditions noted during or after the Shutdown will be recorded in the Permanent Log and the SRO on Duty shall be notified. Return Operational Log Book and the Permanent Log Book to their proper storage location. Properly dispose of all trash, coffee cups, i soda cans, etc. and leave the Control Room in a clean and orderly appearance.

1 Log N Recorder Stamp Purpose NE 3C5 Loading No. 10I"/

Log Book No. 9

. Page No. 3h ad 3G l Operator's Signature 077 Wdtten By: David F man Approved By: Albert Bolon ladI AN &O bW

r

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES

Revised: June 6, 1994 Page 4 of 4 UMRR " SECURE" CHECKLIST

1. Date

2. All Rods on Insert Limit

3. All Magnet Contact Lights On

4. Magnet Power Off and Key to SRO

5. Recorders Off and Dated

6. Stamp and Record Data on Log N Recorder Chart

7. Reset Annunciator

8. Reactor Bridge Intercom OtT

9. Shutdown Switch to l Operate

10. Counter / Scaler Off

11. CCTV to Door

12. Nitrogen Diffusers, Vent l Fans, Rabbit System Off ,

13. Time Completed j

14. Operator's Initials

15. Senior Operator's Initials Revised 6/6/94 Written By: David Freeman Approved By: Albert Bolon

/ak & 6%&Bsk ;

k

1

" UMR REACTOR STANDARD OPERATING PROCEDURES *** ,

l SOP: 208

Title:

REACTOR SECURITY

. Resised: July 8, 1994 Page 1 of 2 A. Purnose To provide guidance for compliance with the Physical Security Plan.

B. Precaution. Prereauisites and Limitations

1. The door to the front office of the reactor building will be locked at all times with electrical access control at the secretary's desk.

2. Entry or exit to the building from other than the front office shall require the continuous presence of an authorized individual and permission of the Reactor i StafE

3. Individuals granted unesconed access will be issued identification badges. The ID badge will be worn while in the facility. ID badges are not to be worn outside of the building. The ID badges are to be returned to the badge rack when exiting the facility. 4 l

4. Authorized faculty and staff may escort visitors inside of the facility.

5. Authorized students may escon visitors inside of the facility only if they are l designated in writing as escorts.

6. Escorts shall be capable of maintaining visual contact and shall remain in the same general area as their visitors.

7. Visitors to the facility must sign the Visitors Log and be issued a radiation dosimeter.

3. The visitor-to-escort ratio shall not exceed 20-to-1 unless authorized in writing by the Reactor Director or Reactor Manager.

9. Packages leaving or entering the nuclear reactor facility (with the exception of the Rev.

office area) are subject to random search by the reactor stafE All suspicious packages should be searched.

J Written By: David Freg Approved By: Albert Bolon ,

' MW kkY n i

t

1

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 208

Title:

REACTOR SECURITY. ;

1 Revised: Ju1y 8, 1994 .

Page 2 of 2 I

^ ^

10. In the event of a situation which could affect the security of the facility, the reactor Rev.

will be shutdown and the magnet key secured.

I 1. - The reactor staff and students shall not enter into confrontation with any persons, l except to provide for their personal safety. j

' C. Procedure: ,

1 l

1. Three or less visitors seeking entry to the facility. !

I

a. If a visitor's identity is unknown, they shall be allowed access only by direct i action of the reactor staff. Access shall not be allowed by remote electric j control. .

b. Require identifi ation, from unknown individuals prior to allowing access to the restricted area unless the individual (s) are participating in a general . i tour of the facility. ;

i

c. Visitor should leave books, packages, etc. in the office area.

d. Issue the individual a dosimeter after recording its initial value and j identification number in the Visitors Log. !

e. The visitor is to complete the necessary information in the Visitors Log.

f. Prior to departure, retrieve the dosimeter and record the fmal reading and :

departure time in the Visitors Log. l

\

l

2. Four or more visitors seeking entry to the facility. ] !

a. All steps of SOP 208.C.1 above apply with the exception that three dosimeters may be placed in the bay area at suitable locations. The ,

maximum dosimeter radiation value obtained will be credited to all visitors ;

during their visit. , l

.. g Written By: David ma Approved By: Albert Bolon pW m- GWh~ l i

i i

l

- - UMR REACTOR STANDARD OPERATING PROCEDURES *** !

. SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR r

. BUILDING EVACUATION Revision: December 28, 1994 Page1of7 A. PURPOSE

To provide for the safe and orderly evacuation of the Reactor Building. ;

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

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

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

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

4. Upon sounding of the Building Evacuation Alarm, all personnel except for the Reactor Operator and the Senior Operator on Duty will proceed directly and calmly to the Physics Building basement area and remain in this area for further instructions.

5, Persons providing escort for visitors are responsible for the safe evacuation of their Rev.

visitors to the Physics Building basement and for obtaining the Visitor's Logbook from the front office upon exiting the facility. The escort will report the accountability status of the visitors to the SRO on Duty once in the Physics Building -

basement area.

6. All persons must remain calm and orderly.

. C. EVACUATION PROCEDURE Upon sounding of the Evacuation Alarm:

Written By: David Free Approved By: Albert Bolon f!N.d'iLpan g{Q(.W i

i i

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDLNG EVACUATION *

~ Revision: December 28, 1994 Page 2 of 7 i

I. REACTOR OPERATOR l

The Reactor Operator will obtain the " REACTOR OPERATOR EVACUATION CHECKLIST" and follow the steps therein. If the reactor is shut down at the time ,

of alarm, the REACTOR OPERATOR EVACUATION CHECKLIST need not be ,

completed. Proper actions for each step in the checklist are described below:

l. SCRAM REACTOR: The operator will promptly scram the reactor. ,

2. VERIFY ROD INSERTION: Verify that the shim rods have inserted !

(audibly, visually, or by observing the magnet contact lights and ' magnet currents). Verify power is decreasing appropriately.

3. SECURE MAGNET IGY; Remove the key from the console and maintain possession of the key.

4. ANNOUNCE FACILITY STATUS: Announce the status of the facility '

ever the building PA. State the cause of the alarm and areas of the building to avoid as necessary.

5. RECORD TIME: Record the console clock time. ,

6. WAIT IN CONTROL ROOM FOR SRO: Remain in the control room (or control room area) for the SRO on Duty, if possible. Report facility status to ,

the SRO on Duty upon his arrival. The SRO on Duty may instruct the '

- ~ operator to proceed differently from the items listed in the checklist.

7. OBTAIN PERMANENT LOGBOOK / METERS: Obtain the console permanent logbook. Obtain suney meters and pocket dosimeters, if :

convenient.

t

8. VENT FANS OFF: Verify that all three exhaust vent fans are off.

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

it.

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

$8N[/d*",' &&hk .

l

"* UMR REACTOR STANDARD OPERATING PROCEDURES *** -

, SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR

. BUILDING EVACUATION Revision: December 28, 1994 Page 3 of 7 e

10. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Leave the

facility and proceed directly to the designated Physics Building basement area. ,

i II. SENIOR OPERATOR ON DUTY j The Senior Operator on Duty will obtain the SRO EVACUATION CHECKLIST .

and follow the steps therein. Proper actions for each step are listed below:

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

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

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

l

4. VENT FANS OFF: Verify that all three exhaust vent fans are off.

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

6. EMERGENCY KEYS OBTAINED: Obtain emergency key box upon exiting the building. If the key box is not in its usual location, assume the key box has already been obtained.

7. PROCEED TO PilYSICS BUILDING BASEMENT AREA: Proceed directly to the Physics Building basement area.

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

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

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

Written By: David Freercan Approved By: Albert Bolon ft?Th!'? @(k{- (b&

I SOP: '501' T TLE ERG PROCEDURE R REACTOR -

BUILDING EVACUATION -

Revision: ' December 28, 1994 Page 4 of 7 l

3. Notify the Reactor Manager, Reactor Director, and Campus Health Physicist j as appropriate. Use the Emergency Phone List as needed.

l

4. If personal contamination is possible, fdsk each person evacuated for contamination. Isolate contammated person (s)in the emergency shower area. j

5. Evaluate the situation to determine if the potential for an emergency condition Rev.

exists. Implement the following procedures as necessary:

e SOP 502 " Emergency Procedure For An Unusual Event" e SOP 503 " Emergency Procedure For An Alert" e SOP 504 " Emergency Procedure For A Site Area Emergency" e SOP 507 " Administrative Responsibilities" e SOP 601 " Decontamination Procedure" e SOP 602 " Handling injured In Radiation Accidents" e SOP 603 " Guidelines For Emergency Exposure" e SOP 605 " Entry Into A High Radiation Area"

6. Take other actions as deemed appropriate.

D. END OF EMERGENCY. REENTRY. AND RECOVERY

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

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

3. Personnel approaching the facility for reentry will report to the Emergency Support --

Center if radiation levels in excess of 100 mrem /hr are encountered.

Written By: Da Approved By: Albert Bolon Q)pd Ereemart&N'h?' gQQQ

i i

l l

" UMR REACTOR STANDARD OPERATING PROCEDURES *** !

, SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR '

. BUILDING EVACUATION Revision: December 28, 1994 Page 5 of 7 i i

i l

- REACTOR OPERATOR -

EVACUATION CHECKLIST I

i

1. SCRAM REACTOR

2. VERIFY ROD INSERTION

3. SECURE MAGNET KEY

4. ANNOUNCE FACILITY STATUS

5. RECORD TIME . _ _ _

i

6. WAIT IN CONTROL ROOM FOR SRO

7. OBTAIN PERMANENT LOGBOOK / METERS ,

8. TURN VENT FANS OFF

9. OBTAIN EMERGENCY KEYS

10. PROCEED TO PHYSICS BUILDING BASEMENT AREA 1

i I

Written By: David _Freem Approved By: Albert Bolon T FI'.$. ' pn QQQW

~

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION

Revision: December 28, 1994 Page 6 of 7

- SRO -

EVACUATION CHECKLIST I. IMMEDIATE ACTION _S

1. PROCEED TO CONTROL ROOM

2. RECEIVE OPERATOR'S REPORT

3. OBTAIN SURVEY INSTRUMENTS

4. VENT FANS OFF

5. ALL PERSONNEL EVACUATED

6. EMERGENCY KEYS OBTAINED

7. PROCEED TO PHYSICS BUILDING II. SUPPLEMENTAL ACTIONS

1. PERSONNEL ACCOUNTABILITY:

A. Have all Personnel Evacuated Building?

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

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

1 Written By: Da Approved By: Albert Bolon Ti:rfi$ Freeman Y( ' QQ $am^-

i l

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 502 TITLE: EMERGENCY PROCEDURES FOR AN UNUSUAL EVENT

. Revised: December 28, 1994 Page1of2

- A. EMERGENCY ACTION LEVELS The Emergency Director (Reactor Director) shall determine if an Unusual Event condition exists and will respond to the emergency by implementing the appropriate procedures. An Unusual Event condition would exist if one of the conditions listed in the Action Levels in Table 1 of the UMR Reactor Emergency Plan exists. (See the attached.) Unusual Events conditions are not expected to warrant emergency notification of offsite organizations.

B. ASSESSMENT ACTIONS !

Reactor building and site boundary airborne radioactivity levels shall be determined from the area radiation monitors and portable monitoring equipment by members of the emergency organization. The Emergency Director shall use this information and Table I to determine that the emergency is appropriately classified.

C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactivity shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Further corrective actions shall be provided as needed for this emergency class.

D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of I rem whole body and 5 rem thyroid to members of the general public onsite and UMRR Staff.

Accountability of personnel following a building evacuation shall be done by the Senior Operator on Duty who will check that the facility is clear of personnel. Further protective actions shall be provided as needed for this emergency class.

l Written By: David Freeman Approved By: Albert Bolon

,P ,8K'? I Quf$5w .

=

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP:' 502 TITLE: EMERGENCY PROCEDURES FOR AN UNUSUAL EVENT Revised: December 28, 1994 Page 2 of 2 _,

l- .

SOP 502 Table I Emergency Class: Unusual Event Action Levels Purcose

1) Actual or projected radiological a) to assure that the first step in effluents at the site boundary any response later found to be calculated to produce a dose of necessary has been carried Rev.

15 mrem whole body accumulated out, in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2) Report or observation of b) to bring the operating staff -

severe natural phenomenon, to a state of readiness, and e.g. tornado, and earthquake.

3) Receipt of bomb threat. c) to provide for systematic

, handling of unusual events -

information and decision making.

Rev.

7.

Written By: D vi n Approved By: Albert Bolon o / l

(&kk $d*-

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

L.- SOP: 503 TITLE: EMERGENCY PROCEDURES FOR AN ALERT Revised: December 28, 1994 Page 1 of 2 A. EMERGENCY ACTION LEVELS The Emergency Director shall determine if an Alert condition exists and will respond to e the emergency by implementing the appropriate procedures. An Alert condition would exist if one of the conditions listed in the Action Levels in Table I exists. Alert conditions Rev.

may require providing emergency notification and status information to offsite ,

organizations. l B. ASSESS > LENT ACTIONS I Containment building and site boundary airborne radioactivity and radiation levels shall be determined from area radiation monitors and ponable monitoring equipment by members ,

of the emergency organization. The Emergency Director shall use this information and i Table I to determine that the emergency is appropriately classified.

l C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactive material shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Funher corrective actions shall be provided as needed for this emergency class.

D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of I rem whole body and 5 rem thyroid to members of the general public onsite. Accountability of personnel following a building evacuation shall be done by the Senior Operator on Duty who will check that the facility is clear of personnel. Funher protective actions shall be provided as needed for this emergency class.

t Written By: David Fre n Approved By: Albert Bolon paw au.ax

l t

" UMR REACTOR STANDARD OPERATING PROCEDURES *** $

~

SOP: 503 TITLE: EMERGENCY PROCEDURES FOR AN ALERT i Revised: ' December' 28, 1994 Page 2 of 2 -!

I t

SOP 503 Table I ' :i f

Emergency Class: Alert .j q

Action Levels Purcose

1) Actual or projected radiological a) to assure that emergency effluents at the site boundary personnel are readily available i calculated to produce a dose of to respond if situation becomes Rev. j 75 mrem whole body accumulated more serious or to perform j in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . confirmatoy radiation mon- !

itoring if required, and, !

2) Actual or projected radiation levels at the site bounday of b) to provide offsite authorities 20 mrem /hr for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months whole with current status information. .i body or 100 mrem thyroid dose. }

i i

I i

l t

Rev.

t

)

?

I Written By: a~ reema Approved By: Albert Bolon ln 3Y Qkb$nW h i

i

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

a

** UMR REACTOR STANDARD OPERATING PROCEDURES "*

. SOP: 504 TITLE: EMERGENCY PROCEDURES FOR A SITE AREA

- EMERGENCY Revised: December 28, 1994 Page 1 of 2 i*

A. ENIERGENCY ACTION LEVELS The Emergency Director shall determine if a Site Area Emergency condition exists and ;

will respond to the emergency by implementing the appropriate procedures. A Site Area i Emergency would exist if one of the conditions listed in the Action Levels in Table I Rev. ;

exists. i Site Area Emergency conditions may require evacuation of non-essential personnel to beyond the site boundary, and require providing emergency noti 6 cation and status )

l information to offsite organizations and the public.

B. ASSESSSIENT ACTIONS Containment building and site boundary airborne radioactivity and radiation levels shall be determined from area radiation monitors and portable monitoring equipment by members of the emergency organization. The Emergency Director shall use this information and Table I to determine that the emergency is appropriately classified. The Campus Health Physicist will determine release and contamination magnitudes and to estimate projected exposures to onsite and offsite population.

C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactive material shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Funher corrective actions shall be provided as needed for this emergency class.

I D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of 1 rem

. whole body and 5 rem thyroid to members of the general public onsite and UMRR staff.

Accountability of personnel following a building evacuation shall be done by the Senior Operator on Duty who will check that the facility is clear of personnel. Further protective actions shd! be provided as needed for this emergency class.

, m Written By: Davi Freempn Albert Bolon 7 4 Approved By: bbed bol ov~

,,/8

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 504 TITLE: EMERGENCY PROCEDURES FOR A SITE AREA EMERGENCY '

Revised: December 28,.1994 Page 2 of 2. l

.t :

d' SOP 504 Table 1 a

Emergency Class: Site Area Emergency ,

4 Action Levels Purcose ;

l) Actual or projected radiological a) to assure that response centers !

efDuents at site boundary calculated are manned, :'

to produce a dose of 375 mrem Rev.

whole body accumulated in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . b) to assure that monitoring teams !

are dispatched, ;

2) Actual or projected radiation levels at the site boundary of c) to assure that personnel required 100 mrem /hr for I bour whole body for evacuation of onsite areas .

or 500 mrem thyroid dose. are at duty stations, d) to provide consultation with .

offsite authorities, and f e) to provide information for the l' public through offsite authorities.

i

'i Rev.

i !

E i

Approved By: Albert Bolon ,

Written By: DavpWaam'n o e.<d mAm~ l t

I

e -

r ,

i

- - UMR REACTOR STANDARD' OPERATING PROCEDURES *** '

SOP: 505 TITLE: ENHANCED REACTOR SECURITY

\ Revised: December 28, .

1994 Page1of 1 In the event of any disorder on the campus of the University of Missouri-Rolla such as civil strife or demonstrations which could for any reason have an effect on the security of -

the Reactor Facility the following steps will be observed:

1. The reactor shall be shutdown and the magnet power key secured in its normal ,

storage location. [

2. All entrances to the building shall be locked 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day. Only persons who can be identified and have a need to be in the building will be admitted.

3. Access to the main office will be allowed only after visually observing the person- -

to ensure no unauthorized people are present. .

4. The Senior Operator on Duty shall lock the Reactor Confinement Security Door. !

5. The Senior Operator on Duty will notify the Highway Patrol, City Police, and

. Campus Police, respectively. The Fire Department should be notified, if necessary. .;

6. The reactor staff shall not enter into any confrontation with any persons, except to provide for personal safety.

7. If the civil disturbance is directed toward the reactor, the Director will evaluate the Rev.

situation to determine whether or not an Unusual Event should be declared per the {

Emergency Plan.

i

f. ;

I I

Written By: David Freemag Approved By: Albert Bolon

/ ,MCf','b $(Lu N o k ;

c- - - - . _- _

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

t p ;

- - UMR REACTOR STANDARD OPERATING PROCEDURES *** ;

. SOP: 506 .

TITLE: BOMB THREAT ;

A Revised: December 28, 1994 Page 1 of 2 [

i a Rev.

l'

' A. Attempt to obtain as much of the information on the attached Campus Bomb Threat Form as possible. ,

i B. If the reactor is in operation at the time of the call, the person receiving the call should Rev.. i inform the Senior Operator on Duty immediately and the Operator shall:- l

1. scram the reactor. _ l

2. secure the magnetic power key in its usual storage place, and j

3. initiate a building evacuation in accordance with SOP 501. !

C. If the reactor is not in operation at the time of the call, the person receiving the call should j notify the Reactor Manager (or Senior Operator in his absence). The Reactor Manager lRev. l (or his representative) shall initiate a building evacuation in accordance with SOP 501. l D. The incident shall be reported immediately to the University (campus) Police by the person l who received the call via a telephone in the Physics Building. ;

E. The Reactor Staff should not attempt to find an alleged bomb. The Senior Operator on Duty should be on the lookout for unusual packages as he checks that everyone has :

evacuated the building. l F. The University Police will assume the responsibility for the emergency from this point. j G. The Reactor Director and the Chief of University Police shall decide when the emergency no longer exists.

G. The receipt of a bomb threat initiates the Unusual Event emergency class as defined in Rev. ,

SOP 502. !

l t-I-

Written By: Davi an Approved By: Albert Bolon

,,Wfd 0Y$nW

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 506 TITLE: BOMB THREAT Revised: December 28, 1994 Page 2 of 2 e BOMB THREAT CHECKLIST Rev.

Exact time of call l Exact words of caller ,

QUESTIONS TO ASK ,

1. When is bomb going to explode?

2. Where is the bomb?

3. What does it look like?

4. What kind of bomb is it? .

5. What will cause it to explode?

6. Did you place the bomb?

7. Why?

8. Where are you calling from?

9. What is your address?

10. What is your name?

CALLER'S VOICE (circle)

Calm Disguised Nasal Angry Broken 1 Stutter Slow Sincere Lisp Rapid Giggling Deep Crying Squeaky Excited Stressed Accent Loud Slurred Normal :

If voice is familiar, whom did it sound like?

Were there any background noises?

Remarks: ,

Person receiving call:

Telephone number call received at:

(10/14/94) n Approved By: Albert Bo n Written By:fy au n

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

,, SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE

. RESPONSIBILITIES Complete Revision: December 28, 1994 Page 1 of 5 A. PURPOSE To establish responsibilities for administrative members responsible for coping with a reactor related emergency as set forth in the UMRR Emergency Plan.

B. PRECAUTIONS. PREREOUISITES. LIMITATIONS 4

1. The duties listed under each official are generalin description and are considered fundamental to the protective action to be taken in the event of a reactor-related Alen (see UMR Reactor SOP 503) or Site Area Emergency (see UMR Reactor SOP 504). T'

2. The specific duties of each office will be directed by the Emergency Support ,

Center (ESC) Director depending upon the nature of the radiological emergency.

The ESC Director may delegate any responsibilities to any individual who has sufficient experience and knowledge to handle such responsibilities.

3. The title "Vice Chancellor" used throughout refers to the Vice Chancellor of Administrative Services.

4. The title " Dean" used throughout refers to the Dean of the School of Mines and Metallurgy.

C. PROCEDURE

1. Chancellor - If offsite consequences are expected the Chancellor will be

. responsible for:

a. providing direction and coordination for the Control Group.

e

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES -

Complete Revision: December 28, 1994 Page 2 of 5 i

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:

(314) 751-2748

- Missouri Bureau of Environmental Epidemiology:

(314) 751-6160 or (314) 751-2748 (24 hrs)

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

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

(615) 576-3131; or (615) 481-1000 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ). n

- Rolla Emergency Management Agency: 364-1213

c. notifying the University of Missouri President and requesting University-Wide assistance, as needed.

d. acting as Administrative spokesman responsible for communications with the news media and city officials in the absence of both the Vice Chancellor and the Dean.

2. Vice Chancellor - If offsite consequences are expected the Vice Chancellor will be responsible for:

a. assuming the dut es of the Chancellor in his absence.

b. functioning as administrative spokesman responsible for communication with the news media and city officials.

c. assisting in the coordination of Control Group activities in the planning and preparation phase.

d. notifying American Nuclear Insurers (203) 561-3433 as soon as possible after declaration of an Alen or Site Area Emergency.

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

Written By: Da FrQ /IV Approved By: Albert Bolon Ok&W

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

. SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Complete Revision: December 28, 1994 Page 3 of 5 t

3. Dean of School of Mines and Metallurev

a. Assumes the duties of adminktrative spokesman responsible for communication with the news media and city officials in the absence of the Vice Chancellor.

b. Reports changes in federal and state agency policy with the respect to :

radiological emergency preparedness to the Reactor Director.

4. Radiation Safety Officer (RSO)

a. Implements the action needed to isolate the affected area. Establishes controlled access point and authorizes entnf.

b. Analyzes data collection on radiation levels and reports conditions (with recommend,3 actions) to the ESC Director.

c. Provides assessment of the situation at the site of the emergency to the l ESC director.

d. Authorizes emergency personnel exposures for volunteers in excess of !

normal exposure limits.

e. Reports to the Vice Chancellor if an off-campus evacuation is determined to be necessary after such an assessment has been made.

f. Establishes written procedures for data collection, (air, water, soil, etc.)

dose rate and contamination levels. These proceduro will provide for decontamination and monitoring equipment, their advisability and use.

5. Emergency Sucoort Center Director (i e. Reactor Director)

a. Initiates immediate action to isolate the affected area of campus.

b. Requests assistance from the following local emergency support

. oiganizations as necessary:

. UMR Police,341-4300

- Rolla City Police,9-911

- - Rolla Fire Department,9-911

- Phelps County Hospital,9-911 i

1 Written By: Dg Approved By: Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP:. 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES

Complete Revision: December 28, 1994 Page 4 of 5 I

c. Directs all assessment activities.

d. Authorizes voluntary radiation exposures up to 25 rem when immediate -

action is essential.

e. Reports to the Vice Chancellor if an off-campus evacuation is determined to be necessary, and advises him as to funher evacuation or possibility of 3 recovery from the emergency. f

f. Evaluates foreseeable hazards and determines corrective actions. ;

g. Coordinates all off-campus activities until relieved of this responsibility by supervisors. .

h. Reviews and approves proposed changes to the Emergency Plan. l

6. Emercency Suncort Center Manauer (i e. Reactor Manager)

a. Assumes the duties of the E.SC Director in his absence.

b. Evaluates the need for activating the ESC following any radiation [

emergency.

c. Informs (or delegates to infonn) necessary personnel that an emergency exists. j Coordinates and supervises the activities of the Emergency Squad in ;

d.

concurrence with ESC director. !

e. Supervises efforts to terminate a radiation release.

f. Promptly informs the UMR Campus Police to " rope off' or physically control a 100 m circle and post with radiation signs as necessary. l

g. Maintains a log of significant events. ;

I h. Euluates campus and facility surveys for protection of personnel.

l i. Ensures organization and training of reactor staff for emergency

! ccnditions.

l j. Reviews the Emergency Plan on an annual basis and makes needed !

l changes.

Ensures adequate procedures exist and are reviewed at periodic intervals to ;

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cope with emergency conditions. f l

I Approved By: l [

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' Written By7;a%s . w Ahbert Bo%o

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** y SOP: 507

Title:

EMERGENCY PROCEDURES-ADMINISTRATIVE !

' RESPONSIBILITIES I

_ Complete Revision: December 28, 1994 Page 5 of 5 !

1. !

l l L 7. Camous Health Physicist 1- t

a. Assumes the duties of the RSO in his absence. ;

b. Makes all measurements to assess activities in order to establish the extent i of the affected area. {

. c. Supervises and collects data on the radiological emergency. ;

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d. Establishes safety limits and an evacuation zone for emergency workers l l- and the general public. l l- e. Provides direction in the decontamination of personnel. j

f. Reviews changes in Federal and State Agency Policy with respect to l radiological emergencies and recommends to the Reactor Manager !

necessary changes for compliance. _ l L g. Inventories the emergency box on an annual basis and checks all equipment ,

I therein for proper operation.

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l Written By: David reema Approved By: Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *" '

SOP: 508 TITLE: TORNADO THREAT

. Revised: December 28, 1994 Page1 of 1 A. TORNADO IN ININlEDIATE VICINITY OF REACTOR BUILDING (i.e. a " Tornado Warning")

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1. SCRAM reactor.

2. Remove magnet power key and place in storage locker. ,

3. Close the security door.

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4. Go to the lowest level in the Reactor basement and wait for the tornado to pass. lRev.

5. Make certain physical security is re-established as soon as possible after tornado has passed.

6. The Reactor Director will evaluate the situation to determine whether or not an Rev. '

Unusual Event should be declared per the Emergency Plan.

1 B. TORNADO EXPECTED IN Tile REACTOR BUILDING AREA

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

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l Written By: David i Approved By: Albert Bolon ,

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" UMR REACTOR STANDARD OPERATING PROCEDURES *** i SOP: 509 TITLE: FIRE ,

Revised: December 28, 1994 Page1of 1 A. !

FIRE THREATENING REACTOR OPERATION I

1. SCRAM Reactor.

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2. Pull fire alarm station located to leR of personnel door. Rev.

3. Evacuate building per SOP 501.

4. Call Fire Department. '

5. Make sure physical security is re-established as soon as possible after fire is out. i

6. In the event of a prolonged fire, the Reactor Director will evaluate the situation to Rev.

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-determine whether or not an Unusual Event should be declared per the Emergency ,

Plan.

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Written By: David Free Albert Bo on, lalhxfit Approved( By: Nklyk 3

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'" UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 510 TITLE: EARTHQUAKE Revised: December 28, 1994 Page1 of 1 l

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EARTifOUAKE IN IMMEDIATE VICINITY OF REACTOR BUILDING

1. SCRAM the reactor and secure the magnet power key.

2. If danger is immediate, personnel should seek cover under tables, desks or in strong ,

doorways away from glass, heavy bookcases or shelves. l 1

3. If time permits, personnel should evacuate building to open area east of Reactor Building.

4. Prior to re-entering the building, conduct a radiation exposure rate survey to identify l

possible abnormal radiation levels.

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5. Re-establish physical security as soon as possible. j

6. Be prepared for "aftershocks" that may pose additional danger.

7. If an earthquake is felt in the facility, the Reactor Director will evaluate the situation to Rev.

determine whether or not an Unusual Event should be declared per the Emergency Plan.

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Written By: David.Freema Approved By: Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

.. SOP: 600 TITLE: GENERAL HEALTH PHYSICS Complete Revision: March 20, 1995 Page 1 of 2

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A. PURPOSE ;

r To establish general health physics guidelines which are intended to limit radiation exposures !

to as low as reasonably achievable (ALARA).

t B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. Personnel entering the restricted area of the reactor facility shall wear a film badge or ,

dosimeter. A group of four or more persons may be covered by three dosimeters i placed in the bay. !

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2. Personnel should immediately report any perceived unsafe situation including contamination incidents to either the Reactor Manager, Reactor Director, or Health i Physicist. l i

3. Do not eat, drink, or smoke in designated Radioactive Materials areas.

4. Protective apparel such as gloves, safety glasses, and lab coats should be worn as needed during lab operation. i

5. Latex gloves should be worn only in the bay area or lower level area while handling :

radioactive samples. Latex gloves should not be worn outside of these areas. '

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6. Do not transfer radioactive materials to unauthorized persons. Do not remove radioa:tive samples from the reactor facility, except under the provisions of SOP 603, l

" Release of By-Product Materials On Campus." l

7. Prior to using a survey meter check that the battery level is acceptable and that the >

calibration is current.

8. I Survey lab areas, equipment, and personnel during and aner experimental pro :edures involving radioisotopes. )

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9. Use the frisker station when leaving the bay area aner handling radioactive materials. )

, Keep the frisker probe pointed downward to avoid contamination of the frisker. l Immediately notify the reactor staffif any detectable personnel contamination is j identified.

Revised By: Ra Bono bdb Approved By: Albert Bolon

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

- SOP: 600 TITLE: GENERAL HEALTH PHYSICS Complete Revision: March 20, 1995 Page 2 of 2 ,

- 10. Use time, distance and shielding to reduce exposure to yourself and to others. .

11. Items to be removed from the reactor pool should be surveyed for unexpected -

radiation levels as they are being removed.

12. Radioactive wastes are to be disposed ofin accordance with the following criteria:

a. Radioactive waste reading greater than 5 mrem /hr at one foot are to be stored in the reactor bay safe or other storage location as approved by the Reactor Manager or Health Physicist.

b. Radioactive waste with detectable activity as identified by a hand-held frisker but reading 5 mrem /hr or less at I foot may be placed in the designated radwaste can.

c. Potentially radioactive wastes such as gloves, blotter paper, etc., that have come in contact with radioactive material but have no detectable activity when surveyed with a hand-held frisker are to be placed in the designated radwaste drum.

d. Do not place any of the following into the radwaste cans:

- sharp objects

- glass

- any other object that might cause injury when compacting.

. free-standing liquids

f. If a sample is not radioactive or potentially contaminated, it may be disposed ofin the designated clean waste can located in the reactor bay.

g. The contents of the reactor bay clean waste can are to be frisked to assure no l detectable activity is present prior to disposal.

13. Experimenters are to consult the reactor staff prior to bringing sample materials into ~

the reactor facility.

14. Prior to exiting the building, pause momentr.rily in the portal monitor. Immediately .

notify the reactor staffif any contamination is identified.

f' Revised By: Ray Bono J' hbhh Approved By: Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 602' TITLE: ENTRY INTO A HIGH RADIATION AREA j Q Complete Revision: March 20, 1995 Page1of2 ;

i A. PURPOSE i To ensure that personnel do not enter into a High Radiation Area by accident or without permission.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS i A High Radiation Area could exist in the lower level of the Reactor Building when the beam 'i port or thermal column is open dunng reactor operation or when an exposed source produces a radiation level at which an individual might receive a deep-dose equivalent of 100 mrem in I hour at a distance of I foot from the radiation source or from any surface that the radiation ,

penetrates. l t

C. PROCEDURE ;

The Senior Operator on Duty or Health Physicist shall be responsible for determining when a High Radiation Area exists and will follow the following procedures:

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1. Before the status of an area is changed to a High Radiation Area, the SRO on Duty, the Health Physicist, or their designee shall, by personal survey, ensure that no one is present in the area to become a High Radiation Area. An announcement to that ,

effect will be made over the building public address system.

2. The doors leading to the High Radiation Area shall be locked and access will be controlled by the SRO on Duty or Health Physicist.

3. The SRO on Duty or Health Physicist shall assure the proper "High Radiation" sign is on the doors.

The SRO on Duty or Health Physicist shall give permission for anyone to enter the 4.

High Radiation Area and shall be responsible for ensuring that each person is properly equipped with personnel monitoring devices. :

Revised By: Ra Bono bN Approved By Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** 1 SOP: 602 TITLE: ENTRY INTO A HIGH RADIATION AREA )

Complete Revision: March 20, 1995 Page 2 of 2 .)

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5. Persons entering a High Radiation Area established by opening the beamport or -

thermal column shall wear neutron and gamma sensitive dosimeters. The SRO on -

Duty will be responsible for entering the persons name and time in and out of the area ' l into the permanent log book.

6. When a door leading to a High Radiation Area is unlocked, the SRO on Duty or Health Physicist shall designate a member of the reactor staff to guard the door to assure that no one enters the area'without proper warning or protection.

7, After the High Radiation Area designation is rescinded, the SRO on Duty or Health Physicist or his designee shall ensure, by personally monitoring the area, that the. i radiation levels are less than 100 mrem / hour Then an announcement that the High Radiation Area has been rescinded will be made over the building public address system. r i ,

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Revised By: Ray Bono Nh Approved By: Albert Bolon ,

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'" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 604 TITLE: RADIOACTIVE WASTE HANDLING CRITERIA '

,. Complete Revision: March 20, 1995 Page1 of3 A. PURPOSE .

To ensure that the handling and disposal of radioactive waste is done in such a manner as to f maintain personnel exposures as low as reasonably achievable (ALARA) and to assure !

compliance with all applicable regulations.

i PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

^

B.

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

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

takes place.

2. The dose rate at a distance of I foot from any waste container shall be limited to 5 mrem /hr. If this dose rate limit is exceeded, the waste container shall be placed in a shielded location and the Health Physicist notifed. The Health Physics Staff should ,

then remove the waste from the facility as appepriate.

3. Health Physics approval must be obtained prior to the off-site release of any potentially contaminated solid waste. !

4. Contact the Occupational Health and Safety Services Office or Environmental ;

Management Services Office for guidance on handling hazardous or mixed waste.

5. All liquid and gaseous discharges shall meet 10 CFR 20 requirements. :

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6. Wastes containing plutonium or more than trace quantities of uranium and thorium, must be segregated as required by Nuclear Regulatory Commission accountability l requirements. !

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7. Certain wastes must be excluded from common containers due to the possibility of >

corrosion and/or explosion during storage or treatment. Such wastes must be collected separately and include: l

. a. Hydrochloric and/or hydrofluoric acids i

b. All organic liquids. p

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

l Revised By: Ra Bono Approved By: Albert Bolon i

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** j SOP: 604 TITLE: RADIOACTIVE WASTE HANDLING CRITERIA I Complete Revision: March 20, 1995 Page 2 of 3 [ .

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d. Explosives such as fulminates, picrates, etc.

e. Any other wastes which could cause a corrosion or explosion problem.

8. Health Physics shall keep permanent records of all liquid, solid, and gaseous waste i released from the facility.

9. Refer to SOP 605, " Waste Water Analysis and Discharge" for specific procedures on handling waste water.

10. Health Physics approval is required prior to the release of pool water to the environment. Pool water samples are taken monthly and at anytime pool water is released. Records are kept of each analysis.

C. PROCEDURE

1. Liquid wastes [

a. Monitoring and hold-up facilities shall be provided for liquid waste effluents .

where the level of activity constitutes a threat to meeting concentration ;

requirements of Appendix B of 10 CFR 20. ;

b. Health Physics shall have general responsibility for liquid waste hold-up, sampling, testing, and discharging in all areas. ;

c. Waste containers of adequate size and shielding that meet the requirements of Health Physics shall be used for radioactive liquid waste. Adequate space shall be made available for these containers in properly accessible locations. ;

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d. Radioactive liquid waste incidental to reactor operation will be surveyed by Health Physics. Isotopes having concentrations for. water greater than permitted by 10 CFR 20 must be placed in properly identified containers. ,

2. Solid Wastes .. ,

a. Wherever practical, non-radioactive wastes shall be segregated from i radioactive wastes in order to minimize the cost of waste disposal.

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Revised By: Ra ono Approved By: Albert Bolon b

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** !

SOP: 604 TITLE: RADIOACTIVE WASTE HANDLING CRITERIA !

1 Complete Revision: March 20, 1995 Page 3 of 3 ;

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b. Metal or plastic waste containers shall be provided for solid waste disposal.

L Containers for the disposal of radioactive waste shall contain non-porous f liners be painted yellow, and be labeled clearly, " RADIOACTIVE ;

MATERIALS." Containers for the disposal of non-radioactive wastes shall ,

be any color but yellow.

c. Solid wastes evolved from the use of alpha emitting materials shall be l considered radioactive waste and shall be segregated and transferred to the -

Health Physicists for disposal. ,

d. The handling of any special shielded waste containers of high activity or . .

l awkward shapes shall be the responsibility of the Reactor Manager. ;

e. It shall be the responsibility of the Reactor Manager to provide facilities adequate for the storage and handling of solid radioactive wastes.

f. Wastes contaminated with sufficiently long-lived material will be stored until :

enough has been accumulated to warrant shipping it off site to an NRC ,

licensed disposal site.

3. Airborne Wastes j

a. Wherever possible, design and operating conditions shall keep the amount of radioactivity discharged to the atmosphere to a minimum. All operations with :

radioactive materials shall be carried out as to minimize contamination of air j within the laboratory or building.

b. A record of fan operation times and the maximum reactor power for each run shall be maintained when the reactor is operating. ,

c. For operations likely to involve serious air contamination, such as machining ;

active metals or chemical processing of highly active materials, the use of !

facilities equipped with adequate ventilation and suitable filtration is l mandatory. In such instances, the Health Physicist shall be consulted in !

advance. The filters shall be changed when contamination becomes sufficient ]

. to constitute a health hazard. Maintenance activities will be carried out j according to special instructions furnished by Health Physics.

Revised By: Ra ono 4 Y0Y Approved By: Albert Bolon

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 620 TITLE: DECONTAMINATION PROCEDURES Complete Revision: March 20, 1995 Page1of5 l

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A. PURPOSE To provide for the safe and efficient decontamination of personnel, equipment and work areas.

B. PRECAUTIONS. PREREOUISITES. OR LINitTATIONS ,

1. Notify the reactor staff of any personnel contamination or unusual equipment or work j area contamination.

2. If personnel contamination is not easily controlled and removed, the Health Physicist must be notified.

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3. Contact the reactor staff or Health Physicist immediately with questions or concerns !

regarding contamination. ;

4. Undenake decontamination immediately. This will usually result in an increase in the degree of decontamination achieved and a reduction of required effort.

5. Protective clothing such as latex gloves should be worn for all decontamination work, and overshoes should be used if the material has been spilled on the floor.

6. For purposes of this SOP, Radiacwash refers to the Radiacwash decontamination solution or similar non-hazardous solution. ,

t C. PROCEDURE i

1. Personnel Decontamination l

a. A good scrub with soap and water usually removes most of the contar Ination ,

and this is usually sufficient. If repeated washing does not remove the remainder, the Health Physicist shall be notified and chemicals could be

, applied cautiously under the supervision of the Health Physics Staff. The use of organic solvents should be avoided because they increase the probability of

.yb Revised by: Ray Bono

%kW Approved by: Albert Bolon l

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** I SOP: 620 TITLE: DECONTAMINATION PROCEDURES l

~l Complete Revision. March 20, 1995 Page 2 of 5 ,

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radioactive materials penetrating through the pores of the ~ skin. The prolonged use of any one method of decontamination should be avoided. '

The efTect of repeated efforts will only result in skin irritation. ,

I b If the skin is broken by a contaminated object, take immediate action to '

remove the contamination which may have entered the wound. Wash the wounded area under large volumes ofmnning water; spread the edges of a cut to permit flushing action by the water, and stimulate bleeding. Speed and thoroughness are essential because some of what is not removed may enter ,

the blood stream.

c. If the contamination is localized, it may be practical to mask off the area and cleanse with swabs before risking the danger of spreading the contaminant by general washing.

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2. Procedures for Decontamination of Skin and Hands i

a. Wash hands thoroughly with soap and water. Cover the entire surface of the ,

contaminated area with a good lather then rinse off completely with water Pay attention to areas between the fingers and around the fingernails.

b. If the hand soap is not completely effective, use the liquid detergent mixture ;

found in the decontamination kit.

c. If the contaminants are fission products, wash the affected area using Radiacwash Spray Foam as provided by the Health Physics Staff paying l special attention to the skin around the fingernails. Rinse the area thoroughly l with water and recheck for contamination.

d. If the above methods fail to bring the contamination to almost negligible 2

levels, consult the Health Physicist for alternative methods.

3. Decontamination of Reactor Work Area

a. To decontaminate nonporous surfaces such as painted surfaces or linoleum, Revised by: Ray Bono "f' A hYW Approved by: Albert Bolon ,

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r'

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 620 TITLE: DECONTAMINATION PROCEDURES

, Complete Revision: March 20, 1995 Page 3 of 5 first use paper towels lightly wetted with water or ordinary cleaning solutions.

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

b. Decontamination of porous concrete floors should be attempted with strong concentrations of the commercial solution or detergent. If all attempts are unsuccessful, the surface concrete may have to be removed with a chisel.

c. When decontaminating linoleum, care must be taken to avoid driving the radioactive matenal into the cracks between the linoleum squares if sealer has not been used.

d. If a dry spill occurs on any surface, it should be wet misted with water, ;

Radiacwash, or similar non-hazardous solution prior to the decontamination ;

process.

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4. Cleaning Minor Radioactive Spills )

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

greater at a distance of I foot, if the contamination extends beyond a single room, or if the spill area resists all normal efforts for decontamination, Occupational Health and Safety Services or the Health Physicist must be ;

contacted immediately to supervise the decontamination effort.

b. Put on gloves and protective clothing such as a laboratory coat to avoid body and clothing contamination.

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c. Confine spills to as small an area as possible.

d. Absorb spilled liquid with absorbent paper-or cloth to limit the spread of contamination as necessary.

e. Define and mark off the contaminated area. Do not remove objects or allow people to leave the contaminated area until monitored.

I Revised by: Ra Bono 0SO $k Approved by: Albert Bolon

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 620. TITLE: DECONTAMINATION PROCEDURES Complete Revision: March 20, 1995 Page 4 of 5 -

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g. Decontaminate the area by cleaning with ordinary cleaning solutions. Start at the less contaminated area and proceed towards the area of greatest I contammation. ,

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h. Dispose of contaminated cleaning papers, cloths, and other materials in radiation waste receptacles. l l

i. Survey area and objects with survey meter and with swipe tests to insure !

contamination is removed. l I

j. Check personnel involved with spill and remove any contamination.

k. Notify the Health Physicist of the spill and remedial action.

5. Decontamination of Equipment ,

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a. All items which have been used with radioactive materials are to be '

considered contaminated unless a survey shows otherwise. Such material must be kept in the Reactor lab area and radiation hazard tape should be affixed to such material. Ifit is necessary to dismantle any equipment prior i to decontamination procedures, a careful survey must be made during the ,

operation.

b. If decontamina: ion ofequipment is needed, initial attempts are to be made by :

the experimenter using the equipment. Treatment will depend upon the nature of the contaminant and upon the surface which is contaminated. Ifinitial decontamination efforts are unsuccessful, aid should be sought from the Health Physicist.

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c. Glassware can be cleaned with a commercially available solution such as Radiacwash. If first efforts are unsuccessful it is usually easiest to discard glassware unless it is a specially manufactured apparatus.

d. Radiacwash Spray Foam, or similar non-hazardous product provided by the Health Physicist, can be used for removing fission products from metallic and plastic surfaces.

Revised by:- Ra Bono A $Y$hN Approved by: Albert Bolon l

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 620 TITLE: DECONTAMINATION PROCEDURES

Complete Revision: March 20, 1995 Page 5 of 5

e. If the above procedures fail, then alternate methods should be used after consulting with the Health Physicist.

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Revised by: Ra ono Approved by: Albert Bolon

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, SOP: 621 TITLE: GUIDELINES FOR EMERGENCY EXPOSURES

. Complete Revision: March 20, 1995 Page1of3 A. PURPOSE To give guidance to emergency personnel and radiation workers in the event of an emergency involving high radiation fields.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS !

1. When immediate action is essential, the Emergency Support Center Director may authorize voluntary exposures up to 25 rem. All other emergency exposures must be authorized by the Radiation Safety Officer.

2. Situations involving the saving oflife require separate criteria from that of actions required to recover deceased victims or records and equipment.

3. Accurate estimations of dose levels should be determined before entry is made into emergency areas. This includes both internal and external exposures. j l

4. All personnel entering a High Radiation Area during an emergency shall be equipped with personal monitoring devices to give a true account of exposures received.

5. Records will be taken on every person entering a High Radiation Area during an emergency including name, age, sex, and exposure received.

6. Individuals receiving greater than 1.25 rem per quaner shall be restricted from any further radiation work. This restriction shall remain in place until the Radiation Safety Officer determines a new limit.

l C. PROCEDURES - ACTIONS TAKEN IN SAVING A HUMAN LIFE This procedure applies to the search for and removal ofinjured persons, or entry to prevent conditions that would probably injure many people.

t . 1. Evaluation of the inherent risks should be based on the reliability of the prediction of radiation injury. This reliability cannot be any greater than reliability of the estimation Revised By, Ray Bono r/ Y 0kY Approved By: Albert Bolon W

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 621 TITLE: GUIDELINES FOR EMERGENCY EXPOSURES !

Complete Revision: March 20, 1995 Page 2 of 3 l

of the dose. Therefore, consideration should be given to limits of error associatec -

with the specific instruments and techniques used to estimate the dose rate. This is especially crucial when the estimated dose approximates 75 rem or more.

2. Planned whole body dose shall not exceed 75 rem.

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3. Planned dose to hands and forearms shall not exceed an additional dose of 200 rem.

4. Internal exposure shall be minimized by the use of the best available respiratory protection, and contamination should be controlled by the use of protective clothing. j 3

5. Rescue personnel shall be volunteers or professional rescue workers.

6. Rescue personnel should be broadly familiar with the consequences of exposure.

7. Women capable of reproduction shall not take part in these actions.

8. Other factors being equal, volunteers above the age of 45 should be selected.

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9. Generally, exposure under these conditions shall be limited to once in a lifetime.

10. In the event that any person exceeds any exposure limit, the Health Physicist shall be notified. Ifwhole body exposures greater than 25 rem are received, the person shall be placed under medical observation. The Physician will determine if medical treatment is required.

11. Persons receiving exposures as indicated above should avoid procreation for a period up to a few months.

i D. PROCEDURE - ACTIONS TAKEN IN LESS URGENT EMERGENCIES This procedure applies under less urgent circumstances where it is desirable to enter a ,

hazardous area to protect facilities, eliminate further escape of effluents, or to control fires.

1 Revised By: Ray Bono Approved By: Albert Bolon i

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" UMR REACTOR STANDARD OPERATING PROCEDURES *** 3 SOP: 621 TITLE: GUIDELINES FOR EMERGENCY EXPOSURES. ;

', Complete Revision: March 20, 1995 Page 3 of 3 e

1. Evaluation of the inherent risks should be based on the reliability of the prediction of -

radiation injury. This reliability cannot be any greater than that the reliability of the- l estimation of the dose. Therefore, consideration should be given to limits of error associated with the speciSc instmments and techniques used to estimate the dose rate.

2. Planned whole body dose shall not exceed 25 rem.-

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3. Planned dose of hands and forearms shall not exceed 100 rem. ;

4. Internal exposure shall be minimized by respiratory protection and contamination ;

i controlled by the use of protective clothing.

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5. Persons performing the planned actions should be volunteers and familiar with the consequences of exposure.

r

6. Women capable of reproduction shall not take part.

7. Normally, if the actual dose from these actions is a substantial fraction of the dose limits, such actions should be limited to once in a lifetime.

8. In the event that any person exceeds any exposure limit, the Health Physicist shall be ' i notified. Ifwhole body exposures greater than 25 rem are received, the person shall be placed under medical observation. The Physician will determine if medical :

treatment is required.

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 622 TITLE: HANDLING INJURED IN RADIATION ACCIDENTS

. Complete Revision. March 20, 1995 Page1of3 A. PURPOSE To provide for the proper handling ofinjured personnelin a radiation accident.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. If a person is injured and requires medical attention an ambulance should be summoned immediately (dial 9-911) as appropriate.

2. If a student sustains a minor injury that does not involve contamination, they may be .

referred to Student Health Services (call 4284). All injuries should be reported to the Reactor Manager.

3. If an injured person is contaminated internally or externally or has received a large exposure the Reactor Director, Reactor Manager, or the Health Physicist shall be immediately notified.

4. After ensuring that any injured persons are receiving proper medical care and depending upon the nature of the accident and the degree of contamination, the radiation dose should be estimated, and decontamination measures should be taken as soon as possible. Much depends upon the action taken within the first half hour following the contamination, whether external or internal, since within that time decontamination efforts can still be effective.

5. The reactor staff will from time to time be given detailed instructions on the following points by the Health Physicist:

a. The routine to follow in case of accidents involving radioactive material.

b. The first aid measures they should take pending the arrival of the physician or Health Physicist.

c. Actions to avoid in order not to interfere with the subsequent decontamination procedures.

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Revised By: Ray Bono d bb Approved By: Albert Bolon

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" UMR REACTOR STANDARD OPERATING PROCEDURES **

SOP: 622 TITLE: HANDLING INJURED IN RADIATION ACCIDENTS Complete Revision: March 20, 1995 Page 2 of 3 ,' '

i C. FIRST AID MEASURES

While awaiting the arrival of the paramedics and the Health Physicist, the following actions ;

may be taken:

a. In the event the radiation is from an external source the immediate action ;

should be to remove the victim outside the range of the radioactive source.

b. In the event ofingestion of radioactive substances, the mouth must be rinsed out immediately after the accident, care being taken not to let the injured person swallow the water. In cases ofinhalation of a radioactive aerosol, first aid can be given by inducing coughing and blowing the nose. ,

c. Radioactive substances should be removed as quickly as possible by washing [

or wiping. Any objects used to wipe will be considered contaminated. ;

D. ESTIMATION OF THE DOSE OR THE DEGREE OF CONTAMINATION Appropriate steps must be taken as quickly as possible for the decontamination of the !

respiratory and digestive tracts, and this must take precedence over determination of the .

exposure. Estimation of the amount of contamination in the urine, feces, and breath can be !

determined later at the hospital.

Evaluation of the radiation dose received by the accident victim is generally difficult and particularly so in the case ofinternal contamination. Prompt evaluation of the dose received from internal contamination is very important, whereas dose from external fields may be postponed to a more convenient time when a reconstruction of the conditions is possible.

I E. LIMITATION OF CONTAMINATION ,

i If there is danger of the radioactive substances spreading from the contaminated area of the .

I body, the local contamination should be removed by means of absorbent material. If possible the adjacent skin should be covered in order to avoid spreading the contamination. In all cases, uncontaminated open wounds must be suitably covered. When decontaminating the -

Revised By: Ray Bono d

Approved By: Albert Bolon bb kbb ;

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

L - SOP: 622 TITLE:' HANDLING INJURED IN RADIATION ACCIDENTS

"< March 20, 1995 Complete Revision: Page 3 of 3 face, care must be taken to prevent the entry of radioactive material into the nose, eyes, or ears. Decontamination material can be obtained from the decontamination kit located in the Reactor building.

Contaminated persons should not be allowed to come into contact with others if there is a danger of spreading the contamination.

Decontamination of injured persons should be performed as soon as possible on the spot or -

in adjoining premises to avoid spread of contamination. Only when immediate decontamination is impossible should the victim be removed from the Reactor building or the Physics building basement. Plastic sheets should be used under the contaminated person to avoid the spread of contamination. More decontamination materials are in the Emergency box located in room GMT-1 of the Physics Building.

F. DECONTAMINATION OF WOUNDS Except in cases where it would be harmful to the injured person, the wound should be washed as quickly as possible with mnning water and should be kept open to allow bleeding to take place.

Revised By: Ra/

y Bono

'A Approved By: Albert Bolon YW i

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 650 TITLE: RADIATION AREA SURVEY Complete Revision: March 20, 1995 Page1 ofI A. PURPOSE The purpose of a radiation area survey is to evaluate radiation levels throughout the Reactor facility.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. A radiation survey of the Reactor Building will be performed monthly by the Health Physics staff, or in their absence a designated member of the reactor staff. The reactor should be operating at high power (20 kW or above).

2. Make certain that the survey meters used are in good working order. Check the battery and calibration sticker. Do not use a meter if the battery is low or if the calibration date has expired.

3. Equipment required:

a. portable beta-gamma detector.

b. ponable neutron detector.

C. PROCEDURE

1. Survey beta-gamma radiation at random locations throughout the Reactor building, including the outer office, the bay, and the lower levels.

2, Survey neutron radiation at random locations in the lower basement including near the neutron sources, beam port, and thermal column.

3. Record the radiation level and location of each reading on a Reactor Radiation Area Survey Form.

.- 4. If unusual radiation levels are detected, the Reactor Manager and Health Physicist are to be contacted immediately.

'- If any unsafe radiation levels are identified, the appropriate action, as determined by 5.

Health Physics, shall be taken.

/ M-8 b}b b Revised By: Ray Bono Approved By: Albert Bolon l

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"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 651 TITLE: CONTAMINATION SURVEY

'. Complete Revision: March 20, 1995 Page 1 of 2 i

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A. PURPOSE )

The purpose of a swipe survey is to determine the presence and amount of removable 1 contamination. This procedure is not intended to determine fixed contamination. I B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. Swipe swveys will be performed monthly by a member of the Health Physics Staff, or by a designated member of the reactor staff, at random locations throughout the Reactor Building. J

2. A swipe survey should also be conducted when contamination of a surface is suspected.

3. Avoid cross-contaminating swipe samples. !

4. Make certain swipes are properly labeled.

5. The following equipment is required:

a. Suitable swipe paper

b. Swipe counting instmment suitable for potential contaminants C. PROCEDURE

1. Perfonn a swipe survey at several locations throughout the reactor building.

2. For each swipe, wipe an approximate 100 cm2 area with the swipe paper.

3. Frisk the swipes with an open window G-M probe. If any detectable activity is observed above background, contact the Reactor Health Physicist for j appropriate approvals before removing the swipes from the facility. If no detectable activity is identified, the swipes may be removed from the facility 1 for counting at the Health Physics office.

4. Count the swipe for contamination.

I Revised By: Ray Bono bW 00 Approved By: Albert Bolon Y

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

~

SOP: 651 TITLE: CONTAMINATION SURVEY

. Complete Revision: March 20, 1995 Page 2 of 2 a

5. . If the count indicates removable contamination greater than 100 pCi/100 cm2 .

2 beta-gamma (222 dpm/100 cm ) or is considered above background for alpha >

contaminants, the area is to be considered contaminated.

6. If unusual or unforeseen contamination is determined to be present, the area shall be roped off and the Health Physicist notified immediately.

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Revised By: R Bono Approved By: Albert Bolon ;

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

' SOP: 652 TITLE: POOL WATER TRITIUM ANALYSIS

,. C,mplete Revision: March 20, 1995 Page1of2 A. PURPOSE To provide a routine check for tritium (H-3) concentrations in the reactor pool water.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

1. This test is to be performed semi-annually by the Health Physics staff.

2. Equipment required I

a. Liquid scintillation counter (LSC)

b. Clean 20 ml sample container

c. 20 ml H-3 standard

d. 2 LSC counting uals ,

f. Scintillation cocktail

3. 10 CFR 20 limit is lx10microcuries/ml.

C. PROCEDURE

1. Use an empty sample container to collect reactor pool water.

2. Place equal volumes of scintillation cocktailinto two clean LSC counting vials. If using mini-vials, place about 3 ml of cocktail into each vial. If using a standard vial, place about 10 mi into each vial.

3. Place 1 ml of deionized water in one of the vials and label it as background.

4. Place 1 ml of the pool water sample in the other vial and label it as the sample.

5. Place the background and the sample in the LSC.

6. Select the program on the Beckman LSC (with automatic calibration) which is

. preprogrammed for H-3.

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't Revised By: Ray Bono 8

awkw Approved By: Albert Bolon I

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***. -)

SOP: 652 TITLE: POOL WATER TRITIUM ANALYSIS

( Complete Revision: March 20, 1995' Page 2 of 2, o

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7. Calculate the H-3 activie, as follows:

Activity (dpm/ml) = Samole com - Background com Detector efficiency ;i Activity (microcuries/ml) = Activity (dom /ml) 2.22x10'dpm/microcurrie Always report the values in microcuries/ml. i i

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Revised By: Ray Bono k

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 653 TITLE: SEALED SOURCE LEAK TEST

. Complete Revision: March 20, 1995 Page 1 of 2 A. PURPOSE To ensure the integrity and encapsulation of sealed sources and to guard against contamination of personnel.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS

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

2. The following sources located at the reactor facility are to be leak tested semi-annually: PuBe S/N M-1092 (Reactor Stanup Source), PuBe S/N M-169 (RAM Calibration Source), Cs-137 S/N 5049 (RAM Calibration Source).

3. Leak test requirer.ents are listed in item 14 (A through F) of NRC Materials License number 24-00513-40.

C. PROCEDURE

1. The leak test should be performed with filter-paper discs or with cotton-tipped applicators depending upon the source activity, configuration, and containment.

2. The source, source holder, and immediately surrounding area should be rubbed firmly with the swipes held with tongs or forceps or with cotton-tipped applicators in order to remove any surface contamination that may be present. If access to the sealed source is prevented by the construction of the device, the swipes should be taken as near the source as possible.

3. Each swipe or applicator should be placed in a separate envelope appropriately labeled for identification.

4. Frisk the swipes with an open window G-M probe. If any detectable activity is observed above background, contact the Reactor Health Physicist for appropriate

- approvals before removing the swipe from the facility. If no detectable activity is identified, the swipes may be removed from the facility for counting at the Health Phv ics office.

1 Revised By: Ray ono

, J L b5b Approved By: Alben Bolon

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 653 . TITLE: SEALED SOURCE LEAK TEST Complete Revision: March 20, 1995 Page 2 of 2 a

5. Evaluation of swipes taken from sealed sources containing a beta-gamma emitter.

should be made with shielded, end-window, Geiger-Mueller counter or equivalent. l Evaluation of swipes taken from' sealed sources containing an alpha emitter should be i made with a gas-flow proportional counter or equivalent. ..

6. 'If the results of the test indicate a removable contamination in excess of 0.005 microcuries, the following steps shall be taken:

a. The source is to be taken from' service imm.dately and held in secured .;

storage until it can be decontaminated. !

b. Notify the Reactor Manager.

I

. c. File a report with the NRC that contains the information required by section 14.E of the Materials License. ,

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" U51R REACTOR STANDARD OPERATING PROCEDURES *** ;

SOP: 654 TITLE: MEASUREMENT OFAr CONCENTRATION IN THE

, REACTOR BUILDING AIR .

Complete Revision: March 20, 1995 Page 1 of 3 !

1 A. PURPOSE To test the activity concentration of *'Ar in the Reactor building air. l B. PRECAUTIONS OR LIMITATIQ3.S

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

2. Ifother 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. Samole oreparation Evacuate the aluminum sample tank to 60 torr. The tank is of j Marinelli design and has a volume of 6842 ml. ,

t

2. Bgkground Count After evacuating the tank, take a 600 second count with the Nal detector in the Health Physics counting room (114 Fulton Hall) and print out the spectnim to include the area where the ' Ar peak will occur.

Note: 2Wa 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. :

f

3. Samoling

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.

Revised By: Ray Bono Approved By: Albert Bolon :

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

b. Position the air sample tank and open the valve. Allow the tank to completely

_ 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 be 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 shielded,

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 d

which the peak of the 'Ar sample occurred. The background count should be done prior to the sample and enough channels 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 of counts in the 1.294 MeV peak ofAr as determined in the integration of the printed spectrum (counts) .

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

'" UMR REACTOR STANDARD OPERATING PROCEDURES ***

. SOP: 654 TITLE: MEASUREMENT OFAr CONCENTRATION IN THE

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REACTOR BUILDING AIR Complete Revision: March 20, 1995 Page 3 of 3

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

R = N/t where, R= Count rate in 1.294 MeV peak ofAr (cps) t= Count time (3econds)

d. Determine the concentration of activity ofAr 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 NaI ,

detector and 6842 ml sample can for Ar) (cps /(pCi/ml))

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

Fe4 l Revised By: Ray Bono f Approved By: Albert Bolon l

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- - UMR REACTOR STANDARD OPERATING PROCEDURES "* d SOP:- ' 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS l

. Complete Revision: March 20, 1995 Page1of6

/ .. PURPOSE !

To provide for the efficient calibration of the fixed Radiation Area Monitors and to minimize ,

personnel exposure during the calibration. ,

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B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS ,

1. The RAMS are calibrated semi-annually.

2. A minimum of two personnel are needed to perform the calibration. One person will be i located in the control room to take readings and record values and the other will handle the sources near the monitors. i

3. The person who handles the sources must wear a minimum of a pocket dosimeter and ;

a film badge. Ring badges are optional but advisable.

4. The person who bndles the source should minimize their exposure time in close proximity to the source.

5 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, then high radiation area j posting and area control are required. j 6 I Notify the Reactor Manager prior to performing this procedure.

C. PROCEDURE - GAMM A RAM CALIBRATION

+

1. Calculate Source to Detector Distances: Calculate source to detector distances to provide target dose rates of to mrem /hr,30 mrem /hr,100 mrem /hr, and 200 mrem /hr. ~

Use the inverse square law (DR,/DR2" d 2/d,2) 2 and the exponential decay law (DR, =

DRy e*).

i The Cs-137 source (SN5049) was certified to read 114 mrem /hr at a distance of 1.64 fi (19.68 inches) on July 23,1979. The halflife of Cs-137 is 30.17 years.

Revised By: David Freeman b

Approved By: Albert Bolon 7 uI?!hi/S +

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SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Complete Revision: March 20, 1995 Page 2 of 6 " <

Using the above information the source to detector distances are calculated as' follows:

114. 4 ,-o.o2 d (19,68)

DR d = source to detector distance (inches). ..

DR = target dose rate (i.e.,10 mrem /hr,30 mrem /hr,100 mrem /hr, and 200 [

mrem /hr. .

t = source decay time since 7/23/79 (years). j Record th :alculated soa.c: to detector distances in Column 1 of the table on the l I

Gamma RAM Calibration Form.

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

i

3. The person handling the source should handle it remotely by using the extension handle !

provided with . tie source. !

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4. Place the source at the calculated distances from the RAM, then stand away from the i source to minimize exposure during the calibration. [

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5. Exposure levels in the immadiate area shall be determined with hand-held instruments -

when the source is first exposed and again when it is put back in its shield to ensure the radiation levels are ALARA.

i

6. The person in the control room should verify that the RAM reading is within 20% of the target dose rate. If the RAM reading is not within 20%, adjust the RAM calibration ;

according to the equipment technical manual. -

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

8. Repeat the above procedure for all three RAM's. I 1- l r

Revised By: David F an Approved By: Albert Bolon l ld5 $0

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

, SOP: 655- TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS

.. Complete Revision: March 20, 1995 Page 3 of 6 I

9. Reset the alarm setpoints as follows:

Location Set Point Function Reactor 5 20 mrem /hr Ruradown Bridge 5 30 mrem /hr Bldg. Evacuation Deuuneralizer 5 20 mrem /hr Rundown Experiment Room 5 20 mrem /hr Rundown

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

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

l

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

Physicist. i i

D. PROCEDURE - NEUTRON RAM CALIBRATION: ,

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

i

2. Fillin the " calculated kepm" column on the " Neutron RAM Calibration Form" based on the year using the following table (Note: Values presented below are from UMRR ,

1, R. Steinman)-

)

I DISTANCE YEAR l 1995 to 1999 2000 to 2004 2005 to 2014 2015 to 2025 12 132 kepm 135 kepm 138 kepm 139 kepm 24 45 kepm 45 kepm 46 kepm 46 kepm 36 28 kepm 29 kepm 29 kepm 30 kepm A

Da Approved By: Albert Bolon Revised By: IhWLf,Gjd Ereeman QQQ

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** ;

LSOP; 655. TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS - l Complete Revision: March 20,'1995 Page 4 of 6 i

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

4. Place the source at the calculated distances from the RAM, then stand away from the source to minimize exposure during the calibration.

5. 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. l 1

6. Record the values displayed in the control room in units of kilocounts per minute (kepm) !

on the " Neutron RAM Calibration Form" !

i

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

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8. If the Neutron RAM fails to meet the calibration specifications, perform the alignment procedure in SOP 807 " Neutron RAM System"; then repeat the neutrom RAM i

- calibration.

9. The completed fomt is to be approved by both the Reactor Manager and the Health Physicist.

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS E Complete Revision: March 20, 1995 Page 5 of 6 Gamma RAM Calibration Form i

Source (SN 5049) Decay Time (since July,1979): (years)

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

(mrem /hr) (mrem /hr) (mrem /hr) 10 2 30 6 100 20 200 40 Alarm setpoints reset verified (Initials)

All readings are within 20% of Target Dose Rates. (Initials) l Calibration Performed By: Date / /

Approved By: Date / /

Reactor Manager Approved By: Date / / !

Health Physicist Revised By: David Freeman Approved By: Albert Bolo

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- - UMR REACTOR STANDARD OPERATING PROCEDURES *** l SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS i I

Complete Revision: March 20, 1995 Page 6 of 6 s Neutron RAM Calibration Form a

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

i Distance Calculated Meter Reading -

(inches) (kcom) (kepm) 12 f

i 24 36 i

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

Calibration Performed By: Date / /

Approved By: Date / /

Reactor Manager ,

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Approved By: Date / / "

Health Physicist Revised By: avid n Approved By: Albert Bolon

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"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 702 TITLE: IRRADIATION REQUEST FORMS

?, Completely Revised: April 10, 1995 Page 1 of 8

.- A. PURPOSE- i To provide for the thorough Reactor Staff review of all experiments to be irradiated by !

neutrons from the UMRR. The review evaluates potential 1) reactivity effects,2) dose hazards to the experimenter, and 3) hazards to the reactor. >

B. PRECAUTIONS. PREREOUISITES OR LIMITATIONS :

I'

1. All sample irradiations must be performed under an approved Irradiation Request Form (IRF) with two approval signatures.

2. All materials to be irradiated are to either be corrosion resistant or encapsulated in l corrosion resistant conta:ners. '

3. Approved IRFs remain valid for future irradiations. j

4. IRFs will be numbered sequentially following the last two digits of the current year :

(e.g. 95-1, 95-2, etc.).

{

5. Radiation Safety Committee approvalis required for

a. experiments worth more than 0.4% Ak/k,

b. explosive materials, :

c. fueled experiments, or l

d. untried experiments. 1

6. The total reactivity worth of all experiments is limited to 1.2% Ak/k.

7. Experiments having moving parts shall not have an insertion rate greater than 0.05%

Ak/k per second. ;

8. Cooling is to be provided as ne ded to prevent the surface temperature of an j

experiment being irradiated from ex eeding the boiling point of the pool. I i

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I l Writted By: David reeman '

Approved By: Albert Bolon TI 8/A' @lN bDN

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 702 TITLE: IRRADIATION REQUEST FORMS ' i Completely Revised: Apri1 10, 1995 Page 2 of 8- y 1' l C. PROCEDURE - IRRADIATION REOUEST FORM The IRF should be completed according to the following steps:

1. IRRADIATION REQUEST- This section of the IRF should be completed by the experimenter.

a. Sample Description - Describe the sample material to be irradiated (e.g.

dried tobacco leaves, powdered milk, gold foil, etc.)

b. Physical Form - Specify the physical form of the sample material (e.g, powder, ash, liquid, etc). ,

c. ~ Encapsulation - Check the box marked " Poly-vial" or check "other" and describe.

d. Irradiation Location - Specify the irradiation facility to be used. More than 'I one facility may be authorized on a single IRF. If "Other" is specified, describe the irradiation location (for example: " wire stringer in Grid Position C-3 ").

i

e. Irradiation Limits - Specify the irradiation limits as follows: .

1) Power - Specify the maximum reactor power for irradiation. Samples may NOT be irradiated at powers higher than specified.

2) Time - Specify the irradiation time for the sample (s) at the maximum power. Samples may be irradiated at lower powers for times longer than the specified irradiation time as long as the total fluence (i.e. kW- L hrs) does not exceed the product of the specified maximum power and irradiation time.

3) Mass - Specify the maximum sample mass (grams) to be irradiated in -

any single irradiation. -

Handwritten revisions to the limits are allowed based on the measured dose rate from the initial irradiation (s). Assume dose rate is a linear function of r

?

Written By: David F Approved By: Albert Bolon f5h,rpeman"b fkb L&

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP:-- 702 TITLE: IRRADIATION REQUEST FORMS -

f3 , Completely Revised; April 10, 1995 Page 3 of 8

, power, irradiation time, and sample mass. Revised irradiation limits require the review and approval of either the SRO on Duty, Reactor Manager, or Reactor Director as signified by their initials with dates.

f. Expected Dose Rate - Specify the expected I foot dose rate when the sample comes out of the reactor based on one of the categories below:

Experience - The expected dose rate may be based on measurements made during previous similar irradiations. In such instances, record the IRF number of the previous similar irradiation.

Calculations - The expected dose rate may be calculated using the l DR=6CE mle (or other appropriate method) where DR is the 1 foot l dose rate in mrem /hr C is the expected activity in mci, and E is the gamma energy in MeV. The expected activity can be calculated using A - Ncr$ (1-e **a) where N is the number of target atoms, o is the cross section, & is the neutron flux, A is the decay constant andwt is the irradiation time.

Completely Unknown - A trial irradiation is required if the expected dose rate is completely unknown. The irradiation limits for a trial irradiation are normally reactor power 5 2 kW, irradiation time 51 minute, and sample mass 51 gram. The reviewers may approve different trial irradiation limits at their discretion. Dose rates for higher powers, masses and times can then be linearly extrapolated based on the measured dose rate resulting from the trial irradiation.

g. Reactivity Worth - Estimate the reactivity worth of the sample based on one of the categories below:

Default - A default reactivity worth of<0.05% Ak/k may be used for the rabbit facilities if the sample mass is less than 7 grams. A default reactivity worth for core periphery stringers of <0.1% Ak/k may be used for holders with a volume of 35 cm' or less and a sample mass ,

of 7 grams or less. (Note: The default mass and location values are

- based on a report by Wagner,1992.) Beamport and thermal column irradiations have a default reactivity of 0.0%.

Written By: David Fr man Approved By: Albert Bolon iL;/' E W h

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 702 TITLE: IRRADIATION REQUEST FORMS -

Completely Revised: Apri1 10, 1995 Page 4 of 8 ,

Experience - The estimated reactivity wonh based on previous .

" experience" may be specified along with the applicable IRF number.

If no previous experience exits, estimate the reactivity worth using SOP 306.

Completely Unknown - If reactivity worth is completely unknown and not easily calculated, it must be experimentally determined.

h. Comments - Provide additional comments, if any.

i. Request Completed By - The person completing items a through h above should sign their name in the blank provided.

2 REVIEW AND APPROVAL - This portion of the IRF is to be completed by one of the reviewers and approved by both of the reviewers.

a. Analysis of Potential llazards - Reviewers shall analyze potential hazards associated with the experiment with regard to following:

1. Reactivity - Review the expected reactivity worth information.

Assure that the Technical Specification Section 3.7 requirements are met. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

2. Dose Rate - Review the expected dose rate information and assess potential dose rate hazards. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

3. Reactor Equipment - Verify that no corrosion problems exist.

Verify that no explosive materials or fueled experiments are to be irradiated without Radiation Safety Committee approval. Verify that proper provisions for cooling have been made. Evaluate the experiment with respect to potential hazards to the reactor or reactor operations (for example, detector " shadowing"). Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain. .

Written By: David Freeman Approved By: Albert Bolon p.. wha \ %%W

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP; 702- TITLE: IRRADIATION REQUEST FORMS F, Completely Revised: April 10. 1995 Page 5 of 8

, 4. Other - Evaluate the experiment for any other types of conceivable hazards to personnel or equipment,

b. Additional Restrictions / Requirements - The reviewers are to specify any additional restrictions or requirements deemed appropriate.

c. Approvals - Reviewers shall signify approval of the experiment by signing and dating in the appropriate blank. Two signatures are required from either the Director, Manager, SROs, or the Health Physicist.

D. PROCEDURE - SAMPLE IRRADIATION LOG A Sample Irradiation Log will accompany each IRF to document sample irradiation information. An entry shall be made on the Sample Irradiation Log for each sample irradiated.

1. Date - Specify the date of the sample irradiation.

2. Sample ID - Specify the sample identification number or name.

3. Experimenter's Name - Provide the name of the experimenter responsible for the ,

sample. l

4. Location - Specify the irradiation location.

5. Power - Specify the power level at which the irradiation is performed.

6. Time In - Specify the console time at which the irradiation began.

7. Time Out - Specify the console time at which the irradiation ended.

8. Total Time - Specify the total time of the irradiation.

9. Dose Rate @ l' foot - Record the I foot dose rate from the sample at the time of

. initial sample handling.

Written By. Davi _ eman Approved By: Albert Bolon fa.'I"ut4', a G Q &ck n i

l

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

~ ' SOP:'702 TITLE: IRRADIATION REQUEST FORMS

- Completely Revised: Apri1 10, 1995 Page 6 of 8 ,'

10. Decay Time - Specify the approximate decay time between the end of the irradiation .

and the time of the dose rate measurement.

11. Initials - Either the console operator (licensed operator, student, or trainee) or the experimenter will provide their initials signifying that sample irradiation information is complete.

Written By: Davi freeman, Approved By: Albert Bolon TeEld//k, @}@hb

/

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 702 TITLE: IRRADIATION REQUEST FORMS Completely Revised: Apri1 10, 1995 Page 7 of 8

?

IRRADIATION REOUEST FORM IRF#_____-

1. IRRADIATION REQUEST l

a. Sample

Description:

b. Phy sical Form: c. Encapsulation ( ) Poly-Vlal () Other

d. Irradiation Location: () Bare Rabbit () Cad Rabbit () Beam Port () Thermal Column i

( ) Other i I

c. Irradiation Limits: 1) Power: 2) Time: 3) Mass: em l l )

i

f. Expected i Foot Dose Rate: mrem /hr Based on: () experience (IRF# ) i J

() calculations (attached)

() completely unknown

g. Espected Reacthity Worth: % k/k Based on: () default

() experience (IRF# )

() SOP 306 calculations (attached) {

() completely unknown

h. Comments:

l. Request Completed By:

l

2. REVIEW AND APPROVAL

e. Analysis of Potential Hazards:

1. Reactivity () None () Other

2. Dose Rate () None () Other

3. Reactor Equipment () None () Other j

1. Other ()None () Other I

h. Additional Restrictions / Requirements

c. Irradiation Request Resiewed and Approved (two signatures required): !

Director Date , Manager Date SRO Date ,SRO Date Health Physicist Date J

Written By: Dad Approved By: Albert Bol

'I/. lll . lllQ Qh k

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 702 TITLE: IRRADIATION REQUEST FOR31S Completely Revised: April 10, 1995 Page 8 of 8

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Written By: Davi& fEah Approved By. Albert Bolo

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"* UMR REACTOR STAhT)ARD OPERATING PROCEDUFIS ***

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST F Complete Revision: March 20, 1995 Page 1 of 7

, Date Commenced Date Completed Total Hours on Hour Meter

1. Log N and Period Channel Initial Rate

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

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

c. Log N Detector Resistance (ohms)

(1) Signal to ground (approximately 10'" ohms)

(2) Positive to ground (approximately 10" ohms)

(3) Negative to ground (approximately 10* ohms)

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

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

PicoAmpere True Expected Generator Readines Recorder Meter Imtial Rain 5.0x10 ' A 100 kW 5.0x104 A 10 kW 5.0x10"A 1 kW 5.0x104 A 0.1kW 5.0x10*A O.01 kW 5.0x10'"A '.'301 kW 5 0x1 l'" A 0.0001 kW Revised By: William Bonzer Approved By. Albert Bolon GUbuim 0nyt h& hh ~~

l

- - UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Complete Revision: March 20, 1995 Page 2 of 7 ,

1. Log N and Period Channel (cont.) Initial Dats

c. Reconnect all cables Reconnection of cables verified

f. Period Recorder (1) Cleaned chassis as needed

2. Linear Pow er Channel

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

b. Linear Recorder (1) Cleaned Chassis

c. Linear Calibration (cont.)

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

From 10* to 10" the overall accuracy should be better than 4%. Any.

instmment found to be out of calibration should be realigned in accordance with procedures.)

.----.---METER-------- ------RECORDER-----

PicoAmp Acceptable Actual Acceptable Actual Generator Reading Reading Reading Reading Initial Dat.c 6.0x10~5A (57pA-63 A) (57%-63%)

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

6 0x10*A (570nA-630nA) (57%-63%)

6.0x10A (57nA-63nA) (57%-63%) ,

6.0x10*A (5.3 nA-6.6nA) (53%-66%)

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

2.0x10"A (130pA-260pA) - (13%-26%)

Revised By: William Bonzer Approved By: Albert Bolon k;44Lc. , d~p 6hL(L~

"* UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST

~

Complete Revision: March 20, 1995 Page 3 of 7

, 2. Linear Power Channel (cont.)

d. Linear CIC Detector Resistance (ohms) Initial Rau:

t (1) Signal to ground (approximately 10 ' ohms)

(2) Positive to ground (approximately 10' ohms) 2 (3) Negative to ground (approximately 10 ohms)

e. Reconnect all cables 1

Reconnection of cables verified

3. Log Count Rate Channel

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

b Fission Chamber Preamp l l

(1) Cleaned chassis as needed ,I (2) Additional Comments

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

Pulse Generator Meter Recorder IQ l

1.000 1 10.000

d. Reconnect all cables Reconnection of cables verified i

Revised By: William Bonzer Approved By: Albert Bolon !

lOdba v, . d.m, Mbb kbh

s-j

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP:: 800 . .

Title:

SEMI-ANNUAL CHECKLIST-Complete Revision: March 20, 1995 Page 4 of 7 q t

l 4 Safety Channels Initial Rats !

a. Safety Preamp j Cleaned chassis as needed j (1) i

b. Safety Detector #1 :

1 Resistance (1) Signal to ground (approximately 10' ohms)

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

i (3) Additional Comments l t

c. Safety Detector #2 l Resistance j t

(1) Signal to ground (approximately 10 " ohms) ;

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

(3) Additional comments

d. Safety Amplifier ,

(1) Cleaned chassis as needed !

r

e. Safety Amplifier Adjustments ;

i f, Reconnect all cables j Reconnection of cables verified f

5. PAT 60 Controller

a. PAT 60 {

(1) Cleaned chassis as needed i

I

b. Check dial settings and record the following (1) Approach _

(2) Proponional Bank _

l (3) Rate Time [

(4) Reset ;

(5) Gain (if applicable) l Revised By: William Bonzer Approved By: Albert Bolon i LU1.i., k cwy [d.Ib u_ W E h Y .----.-e - - , , . . - - -,n - , _

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SE.TII-ANNUAL CHECKLIST I, - Complete Revision: March 20, 1995 Page 5 of 7

. 6. Temperature Channel (Note: All readings should be 2 F.)

a. Verification of Temperature Readings Date

)

I m m i m L M M M L s N

y )

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.a I c c H Q c M M

g a u 5 m 4 e C

4 O CL H O c. C o C C E

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L 3 g O W O O u U O U C U c Temperature Range g g g g g 8 (Take one reading from each, g g $ {

temperature range) E E p 60* F-70

F l 70

F-80* F 80

F-90

F 90

F-125

F 125"F-135 *F 135

F-145

F

b. Temperature > 135" Rod Withdrawal Prohibit Test l

l Thermocouple #1 Thermocouple #3 dl35'F Trip Temperature I >135*F Annunciator Audible Alarm Rod Prohibit Withdrawal gInitials Revised By: William Bonzer Approved By: Albert Bolon

( vi(('s. s., h~. p Mllo N

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI ~ ANNUAL CHECKLIST Complete Revision: March 20, 1995 Page 6 of 7

7. Regulated Power Supply Initial Daig -

a. Cleaned chassis as needed

b. Additional comments

8. Conductivity Bridge

a. Cleaned chassis as needed

b. Additional comments

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

6" 12" 18" 24"

10. Fire Alarm Check

a. Cleaned system containers as needed

b. Checked batteries

c. Checked pull stations

d. Checked heat detectors

e. Checked smoke detectors

f. All indicator lamps operate

11. Security System Check

~

a. Door Sensors

b. Motion Detectors Tamper Switch c.

d. Duress Alarm ,_ _

e. Battery

f. Additional Comments Revised By: William Bonzer Approved By: Alben Bolon L LsO, ; s., 13cqq $IN bdM

"* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800'

Title:

SEMI-ANNUAL CHECKLIST Complete Revision: March 20, 1995 Page 7 of 7

12. Public Address System Irutial Data

a. Cleaned chassis as needed

b. Additional Comments

13. Area Radiation Monitor

a. Cleaned chassis as needed I

b. Additional Comments

14. Portal Detector

a. Cleaned chassis as needed

b. Perform Source Check l 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)

I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

Director (Date) or Reactor Manager (Date)

Revised By: William Bonzer Approved By: Albert Bolon ,

LUEdbu '., . 0ot}q NO

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 806 TITLE: TEMPERATURE CHANNEL

, Complete Revision: Apri1 4, 1994 Page 2 of 2 f

c. Record the results on the Semi-Annual Checklist.

I 3. Temperature >135* F Rod Withdrawal Prohibit Test a Place inlet thermocouple #1 into the water bath.

b. Adjust the temperature of the water bath to below about 125*F.

c. Have a Licensed Operator energize the console and clear the rod withdrawal prohibits.

d. Verify that rods can be withdrawn. Do not raise rods above 3 inches.

e. Slowly raise the temperature of the bath until the Temperature >l 35 F trip is received. Verify that the trip occurred at a temperature less than or equal to 135*F.

f. Log the temperature displayed on the recorder for thermocouple #1 on the semi-annual checklist.

g. Verify that the Temperature >l35*F audible alarm is activated.

h. Verify that the Temperature >135'F annunciator is illuminated.

i. Attempt to withdraw rods.

j. Verify that rods do not withdraw.

k. Remove inlet thermocouple #1 from the water bath.

1. Reset the annunciator.

m. Repeat steps a-1 for inlet thermocouple #3.

l l 4. FINAL ASSEMBLY l

a. Install #1, #2, and #3 thermocouples into the pool.

b. Check all wiring connections at the bridge thermocouple connector box.

Verify that each thermocouple is reading a reasonable value.

c. A second knowledgeable person will verify each connection to ensure that the Temperature Channel is properly connected and on line.

l .

e P" AAA 1

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 806 TITLE: TE31PERATURE CHANNEL Complete Revision: April 4, 1994 Page1 of2 -

4 A. PURFOSE To provide for the consistent method of checking the calibration of the Temperature Recorder.

B. PRECAUTIONS. PREREOUISITES AND LIMITATIONS

1. Prior to removing or installing reactor thermocouples, permission must be obtained from the SRO on Duty.

l

2. Record removal or installation of reactor thermocouples in the permanent logbook.

C. PROCEDURE

1. Document each of the following steps in Section 6, " Temperature Channel" of the Semi-Annual Checklist (SOP 800). As each equipment is checked or calibrated, it shall be checked otron the check list to serve as a record of the date that the item was completed.

2. Verification of temperature readings

a. Remove inlet thermocouple #1, outlet thermocouple #2, and inlet thermocouple #3 from the pool. Check the dose rate of each thermocouple as it is removed from the pool.

b. Place thermocouple (s) in a water bath with a thermometer that meets NIST specifications. This step may be performed with more than one thermocouple at a time. Adjust the temperature of the water bath from about 60"F to about 145*F. Record one simultaneous reading of the thermometer and the thermocouple for each of the following temperature groups:

60* F-70* F 70

F-80* F 80

F-90

F ,

90 F-125 F 125

F-135

F 13 5

F-145

F Written By: Davi n Approved By: Albert Bolon 94 wi ouLw

_ _ - - - 3

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 6, 1994 Page1of14 A. PURPOSE To ensure the proper operation of the control and safety-related instruments of the reactor and to functionally test the Physical Security Alarm System.

B. PRECAUTIONS. PREREOUISITES. OR LIMIT ATIONS

1. The Weekly Check should be completed on the first working day of each week the reactor is to be operated.

2. The security system and pool conductivity must be checked weekly. The remaining portion of the checklist may be omitted if the reactor will not be operated that week.

3. The weekly check should be performed by a licensed operator, or a student under the direct supervision of a licensed operator 4 Complete the Weekly Surveillance Checklist form (Form SOP 810), and forward it to the Reactor Manager (or Director) for review and signature. Any abnormalities, problems, or out of service equipment should be brought to the attention of the Reactor Manager (or Director).

C. PROCEDURE Select the Reactor Bridge Station on the Building Intercom, check the PA system, install the neutron source, turn on and date the Startup, Linear, Period, and Log N recorders. Rev.

Turn on the core camera and select core on the monitor selector. Obtain Magnet Power Key and turn on magnet power.

1. ROD WITHDRAW PROHIBIT (vellow lightst A. Recorders Off- Verify that the rods will not withdraw if any one of 5 Rev.

primary recorders is turned off.

1. Turn off LCR recorder.

. 2. Attempt to withdraw rods.

3. Turn on LCR recorder, reset alarm.

f 1

Written By: Davi r man Approved By: Albert Bolon w ageu~

\

l i

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CllECK Revised: June 6, 1994 Page 2 of 14

4. Turn offlinear level recorder.

5. Attempt to withdraw rods.

6. Turn on linear level recorder, reset alarm.

7. Turn off period recorder.

8. Attempt to withdraw rods.

9. Turn on period recorder, reset alarm.

10. Turn ofTiog N recorder.

I 1. Attempt to withdraw rods

12. Turn on Log N recorder, reset alarm

13. Turn off temperature recorder.

14. Attempt to withdraw rods.

15. Turn on temperature recorder, reset alarm.

B. Log Count Rate < 2 CPS

1. Remove source from holder and/or withdraw fission chamber until LCR reads <2 CPS. Record value at which alarm occurs from recorder.

2. Attempt to withdraw rods.

3. Insert source and/or insert the tission chamber to the insert limit.

Reset annunciator.

C. Penod < 30 Seconds

1. Depress " Test Trip" switch on Log N & Period Amplifier and adjust for a period < 30 seconds. Record value at which alarm occurs on the recorder.

2. Attempt to withdraw rods.

3. Release test switch, reset alarm.

l l

Written By: David Freep)an Approved By: Albert Bolon f* "'T

&lQk%W

- - UMR REACTOR STANDARD OPERATING PROCEDURES *"

SOP: 810 TITLE: WEEKLY CHECK

, Revised: March 6. 1995 Page 3 of 14 D. Inlet Temperature Above 135 Degrees

1. Plug the thennocouple simulator into the tcst input jack for one of Rev.

the inlet thermocouples (thermocouple #1 or #3). (Randomly alternate which 'mlet thermocouple is checked from week to week.) 4

2. Slowly adjust the simulator from about 120*F to a higher setting, until the " Inlet Temperature Above 135'F" annunciator and audible alarm are energized.

3. Attempt to withdraw rods. Verify rods do not withdraw.

4. Record the temperature displayed on the recorder when the " Inlet Temperature Above 135'F' td.p occurs.

5. Disconnect the thermocouple simulator from the thermocouple test input jack.

6. Reset annunciator.

E. Shim Rods Below Shim Range

1. With all Shim / Safety rods b elow shim range attempt to withdraw the regulating rod. Note that the regulating rod will withdrawjust far enough to clear the insert limit light. Attempt to withdraw the Shim / Safety rods. Note that further withdrawal cannot be made.

Insert all control rods to the insert limit and record these results.

2. RUNDOWN CHECK (blue lichts):

A. Radiation Area Monitoring (RAM) System

1. Withdraw rods to 3 inches.

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

1 Written By: David Fry Approved By: Albert Bolon i IN hb%k

- A

i i

i

*" UMR REACTOR STANDARD OPERATING PROCEDURES *** ;

SOP: 810 .

TITLE: WEEKLY CHECK j Revised; -June.6, 1994' Page 4'of 14 j

-t

3. Using RAM check source switch #1. Note the value at which' !

alarm (s) occurs. Check the automatic reset'of the RAM, reset the !

. Building Alarm, (Scram Reset Button), acknowledge annunciator i Rundown Reset and Annunciator Reset. Record value of alarms. .j

'4 Repeat step 3 for RAMS #2 and #3. .

5. All alarms values shall be 5 20 mr/hr.- .!

6. Upon completion of testing announce " Test Complete.

Acknowledge all funher alarms," on the building PA system. j i

B. 120% Demand i

1. Withdraw rods to 3 inches. ;

2. ' De-energize (Linear, Period or Log N) recorder. (Switch to off.) l

3. Remove Linear Channel potentiometer cover and manually rotate

~

l potentiometer arm, note recorder reading when trip point is j reached. t

4. When inward motion of rods is verified, lower recorder below reset- j point, reset the nmdown and all alarms, turn recorder on and .!

replace cover, compare actual and specified trip points. [

5. Record trip point value. ;

C. Period < 15 Seconds .l

1. Repeat steps 1 through 5 of 2.B for the Period recorder.

D. 120% Full Power ;

1. Repeat steps 1 through 5 of 2.B for the Log N Recorder. j i

E. Low CIC Voltage Linear Power Supply I

1. Withdraw rods to 3 inches.

2.- Push and hold alarm test button on Linear CIC Power Supply. .

Observe High Voltage meter and record the value when the under j voltage alarm light comes on. Release the test button. j L -

}

Written By: David Freeman Approved By: Albert Bolon h L

f4 h ;

I i

f i

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: January 27, 1995 Page 5 of14 Q

3. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown m j progress). i

4. When the High Voltage on the Linear CIC Power Supply has !

increased to approximately 500 volts push alarm reset. Tk ader voltage alarm light will go off allowing the operato, to reu.ti :ne i l

rundown (push rundown reset) and the annunciator.

5. Record value of the trip point.

F. Low CIC Voltage Log N Detector Power Supply Rev.

1. Withdraw the rods to 3 inches.

! 2. Push upward the period test switch to simulate an approximate infmite period and hold.

3. Slowly adjust the Wide Range Linear high voltage potentiometer, A7-R4, to a lower voltage. Observe the vohage on the High Voltage meter located on the front of the Wide Range Linear drawer.

4. Stop adjusting when the Low CIC Voltage annunciator trips.

5. Acknowledge the annunciator alarm and observe that the Low CIC Voltage annunciator light, audible alarm and rundown have been actuated.

6. Record value of HV when the rundown occurred.

7. Reset the high voltage to 540 VDC using potentiometer A7-R4.

8. Release the period test switch.

9. Reset the rundown (push rundown reset) and reset the annunciator.

G. Regulating Rod on Insen Limit on Auto l

l 1. Withdraw the Shim / Safety rods to 3 inches and Reg Rod to 0.5 l inches (use the shim range bypass).

l 2. Adjust Linear recorder setpoint so that " auto permit" comes on.

~

3. With regulating rod at approximately 0.5 inches withdrawn, switch the Reg Rod control to " Auto" and reset the annunciator.

. 4. Adjust the red pointer (auto setpoint) to be slightly below black pointer (Linear signal) so that an insen on the Reg Rod will result.

Written By: DavidI-reem n Approved By: Albert Bolon d 'A

&& $$Ar" i

r

- - UMR REACTOR STANDARD OPERATING PROCED11RES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 6, 1994 Page 6 of 14

~

5. When the Reg Rod reaches insert limit observe Manual Operation and " Reg Rod insert limit on Auto" annunciators.

6. Acknowledge and reset rundown and ann.aciators.

7. Record results.

3. SCRAM (red lightsk A. Bridge Motion scram

1. Withdraw rods to 3 inches.

2. Release bridge lock and move the bridge a small distance.

3. Observe a Bridge Motion, Manual Scram and Magnet contact lights off Acknowledge the annunciator alarm.

4. Return bridge to original position and reset all annunciators. Re-insert the magnets.

5. Record results.

B. Period Trip Test

1. Withdraw shim rods to 3 inches.

2. Hold the trip test toggle switch in the " Test" position.

3. Rotate the " Trip Test" knob slowly and observe that the 30 second rod withdraw prohibit annunciator is actuated with a simulated period 2 30 seconds.

4. Continue to rotate the knob and observe that the 15 second period rundown occurs with a sirr.alated period 215 seconds.

5. Continue to rotate the knob until the period scram is received.

Verify that the Period scram occurs at a value > 5 seconds and that the shim rods have dropped. Record the scram setpoint value.

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

7. Reset the Period trip on the Log N drawer. Reset the rundown.

Reset the annunciator panel. -

C. Log N & Period Non-Operative Scram .

Approved By: Albert Bolon Written By: David Fregan

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" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 6, 1994 Page 7 of 14

1. Withdraw rods to 3 inches

2. Turn Log N test from the operate to high or low position.

3. Observe Log N Period Amp Non-Operative Scram, Manual Scram, and that the Magnet contact lights go out. Acknowledge annunciators. Reset Manual Scram and reset annunciator. Insert the magnets.

4. Record results.

D. 150% Full Power Scram

1. Withdraw rods to 3 inches. .

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

3. Push reset on the Safety Amp., acknowledge the annunciator and observe the 150% Full Power Scram annunciator and Magnet Contact lights are ofE ,

4. Reset annunciator and insert the magnets.

5. Record resul ts.

E. Manual Scram

1. Withdraw rods to 3 inches.

2. Push Manual Scram button.

3. Acknowledge the annunciator, observe Manual Scram light and all magnet contact lights are off Push Scram Reset, Annunciator Reset and insert the magnets.

4. Record results.

4. ROD DROP CURRENTS:

1. Withdraw rods to 3 inches.

~

2. Using a screwdriver slowly reduce magnet current using current adjustment #1, until the #1 magnet contact light goes out (you should also hear an audible " click" from the Reauor Bridge Intercom Station). Record this drop current val ie.

Written By: Davi -

an Approved By: Albert Bolon

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,- *** UMR REACTOR STANDARD OPERATING PROCEDURES ***

o LSOPi 810 TITLE:. WEEKLY CHECK !

. Revised: June 6, 1994 Page 8 of 14 -

3.

4.

Repeat Steps 1 and 2 for Shim Rod No. 2 and No. 3.

Insert all Shim Rods to insert limit.

'f I

. 5. Set all Magnet Currents to " normal" (i.e. Drop Current plus 10 ma). j

5. IEST OF ANNUNCIATORS:

A. Beam Room High Neutron Flux :

1. Lower alarm set point by turning red needle on log rate meter to ;

the left. Alarm occurs when black needle is hard against the red ;

- needle. ;

2. Check for local red alarm light and for white annunciator light on ;

control panel. Return red needle to normal (10K) set point, reset l alarm and annunciator. .

3. Record results. 'l B. Interlock Bypass

1. Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights. j C. Servo timits 1

1. Note linear level recorder reading.

2. - Change the automatic set point for auto permit by adjusting the star j

wheel. Note linear level at which light comes on (<+2%). ;

Continue to lower and note reading until the auto permit light goes off(> -2%). !

t

3. Reset automatic set point to the 100%1evel. ~

4. Record results.

D. Pool Demineralizer Efiluent Conductivity High - ;

i

1. Record pool and demin effluent readings. ,

j j

Written By: David Ereeman Approved By: Albert Bolon !

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- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK

, Revised: June 6, 1994 Page 9 of 14

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

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

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

l l

7. BUILDING EVACUATION ALARM:

A. Announce over the PA, "The Building Alarm will sound. This is a test. Do not evacuate the building."

l B. Push the Building Evacuation Alarm (center) of reactor console) and note the audible alarm.

C. Reset Building Evacuation Alarm by pushing Scram Reset.

D. Announce over building PA " Test alarms complete. Acknowledge all further alarms."

8. NITROGEN DIFFUSERS:

l A. With the bridge intercom station selected, start diffuser #1. The green )

operation light should illuminate. Note the sound level of the pump and no unusual noise.

l B Shutdown the #1 ma and "reat step 1 for the #2 nitrogen diffuser.

C. Record results on form SOP 810.

I Written By: David Freegan Albert Bolon fisk;4V2 Approved By: h &w i 1

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK June 6, 1994 Page 10 of 14 Revised: .

9. BEAM PORT AND THERMAL COLUMN WARNING LIGHTS:

A. Announce over the building PA. " Attention personnel, stand clear of the Beam Port" B. Open the Beam Port by holding the beam port control switch in the open position until the " Red" (open) light comes on.

C. Acknowledge the annunciator alarm and check the Basement Level Warning Light (Flashing Red).

D. Close the Beam Port by holding the Beam Port Switch until the Green (closed) light comes on. Reset the annunciator and observe that the light goes out.

E. Announce over the Building PA " Beam Port secured" Complete SOP 810.

F. Dispatch a knowledgeable individual to the Thermal Column with the Thermal Column Key. Select the Basement Level Station on the Building Intercom.

G. Address the operator over the intercom to open the Thermal Column until the warning light comes on (approximately 1 inch).

H. The Control Room Operator should observe and acknowledge the annunchtor alarm. Inform the Thermal Column Operator te shut the Thermal Column and ensure the warning light goes off.

1.

Reset the annuncit. tor and have the Thermal Column Operator return the key to the locker. Complete form SOP 810.

10. SHUTDOWN CHECK:

A. Complete a Shutdown Check List form 103 to ensure that all console -

equipment is secured.

Written By: David Freeman Approved By: Albert Bolon

,3 6 hh 6 1

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

- SOP: 810 TITLE: WEEKLY CHECK

, Revised: June 6, 1994' Page11of14 v...

11. SECURITY SYSTEM:

Inform the campus police (4300) that the security system will be checked.

1. Security Door

a. Have police remain on line for the security checks.

b. Hold in or close dead bolt on the security door.

c. Reset the alarm system.

d. Open dead bolt switch by releasing or opening dead bolt l and ensure alarm occurs in campus police dispatch station.

2. - Ultrasonics

a. Hold or close dead bolt on security door. Reset alarm system.

b. While holding the dead bolt switch, move around or have someone walk toward one of the UT's. Have campus police notify you when the alarm occurs. A different ultra sonic detector should be tested each week.

c. Allow the ultrasonic to reset by moving clear of the detector or stand still.

3. Duress

a. Inform the campus police that the duress alarm will be tested.

b. Momentarily depress the alarm button. The campus police should indicate the satisfactory operation of this alarm.

4. Doors

~

a. While holding the dead bolt switch closed, reset the alarm.

b. Open one of the exterior doors equipped with r,n intrusion a alarm. A different door should be tested each week, 4

Da fi Fr ian Approved By: Albert Bolon Written By:f"'tAKt QQhk

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK June 6, 1994 Page 12 of 14

! Revised: .

~

c. Have the campus police acknowledge the alarm when the door is opened.

d. Repeat steps a, b, and c for one of the interior doors equipped with an intrusion alarm. A ditTerent door should be tested each week.

e. When all intrusion channels have been tested, ask campus police to check the battery circuit. This completes the security check.

f. When all channels of the security system have been functionally tested and operate properly, initial the weekly checklist, Form SOP 810.

Written By: David r an Approved By. Albert Bolon

'" # k}N hb

" UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 6, 1994 Page 13 of 14 g . . ..

FORM SOP 810

- Date Performed

1. ROD PROHIBIT Annunciator Prohibit initial A. Recorder Off (1) Log count rate recorder (2) Linear recorder (3) Period recorder

(4) Log N recorder f (5) Temperature recorder B Log count rate <2 CPS f

Actual Trio Point Annunciator Prohibit Indial I

C. Period <30 seconds D Inlet Temperature >l 35'F E. Shim Rods below shim range 2- RUNDOWN CIFCK !

A. RAM System Remote and !

Ststion Bide Alarm I oeal Alarm Annunciator Rundown Trin noint initial j 1.

l.

2.

I 3 l

Actual Trin Point Annunciator Rundown Initial B 120% Demand rundown C. Penod 15 seconds rundoun D. 120% Full Power Rundown ,

i I

E. Iow CIC Linear P.S.

F. I.ow CIC Log N P S.

G. Regulating Rod on Insert j

I.imit on Auto I

3 SCRAM CIECK Actual Trin Pnint Annunciator N; ram Inidal A. Bridge Motion Scram l

. B Period <5 Seconds Scram C 1og N Period Non-operatise Scram David n Approved By: Albert Bolon Written By: a A gaen

l l

l

- - UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 6, 1994 Date Page 14 of 14 ,

Actual Trin Point Annunciator Scram Ind.inl D 150% Full Power Scram E. Manual Scram ,

Dron Cunent Contact Licht Off j. nidal

4. ROD DROP ClIRRENTS A. Rod # I B Rod #2 C. Rod #3

5. TEST OF ANNiiNCI ATORS A. Beam Room High Neutron Flux Lncal Almn 1.icht Anminciator lai'ial B Interkxk Bypass Annunciator Inidal (1) Shtm range (2) 30 second period (3) Radiation area high (4) <2 CPS C. Servo Limits Iin Rec Readine Permit on at Permit off at Inidal D. Pool /Deminerali/er Resistivity Demm Ineal Alarm Annunciator Inidal Eel M O-cm M O-cm Operatiomil Indial

6. "RFACTOR ON' I.lGiiTN A. Main Entrance B Control Room C. Beam Room Alann Operational Inidal

7. Bt iII. DING EVACII ATION

8. N1TROGFN DIFFIiSER Pumn Operational Indicatnr Licht On Inidal A. #1 B #2

9. REAM PORT AND THFRMAI Col tIMN WARNING LIGHT Annunciator FlashineLicht IDidal A. Beam Pon B. Thennal Column Comnleted Inidal ~

10. SH1JT DOWN CHECK I.lST Batterv Check

11. SECtIRITY SYSTEM ,

12. APPROVED AND REVIEWFD Manager or Director (Rev. 6/6/94)

Written By: David Free n Approved By: Albert Bolon a A4 YD 1

_. ____ - _-_____

ML20082R786

Text

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