ML20095J549

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Progress Rept 1991-92 Univ of Missouri-Rolla Nuclear Reactor Facility
ML20095J549
Person / Time
Site: University of Missouri-Rolla
Issue date: 03/31/1992
From: Freeman D
MISSOURI, UNIV. OF, ROLLA, MO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9205040061
Download: ML20095J549 (63)
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Text

. . _ _____. _ _

t W D e Nuclear Reactor Facihty Nuclear Rea< tor E 3 Rob MO 65401-0249 Te + phone 1314)341-4236 UNIVERSITY OF MISSOURI-ROLLA April 29, 1993 Document Control Room Attention: Director Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Stop 10-D-21 Washington, D.C. 20555

Dear Sir:

Please find enclosed the Annual Progress Report 1990-91 for the University-of Missouri-Rolla Reactor Facility (License I 79) .

This report is being filed under the reporting requirements of

our Technical Specifications. A copy of this report is also being sent to our Regional Administrator and Project Manager.

Sincerely, lu -

h4 David W. Freeman Reactor Marager

-DWF/lp Enclosure xc: Marvin Mendonca, Project Manager (NRC)

A. Burt Davis, Region III Administrator-(NRC)

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

Dr. Don.L. Warner, Dean, School of Mines & Metallurgy (UMR)

Mr. Ray Bono, Director, Envir. Health / Risk Management (UMR)

Dr. Robert L. Davis, Dean, School of Engineering (UMR)

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

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

Dr. John Park, Chancellor (UMR)

-American Nuclear Insurers, c/o Librarian p

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1991-92 UNIVERSITY OF MISSOURI-ROLLA y .

,- 1: NUCLEAR REACTOR-FACILITY

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4 PROGRESS REPORT FOR Tile UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY --

APRIL 1, 1991 TO MARCH 31, 1992 Submitted to The U.S. Nuclsar Regulatory Commission and -

L Tne University of Missouri-Rolla Albert E. Bolon, Director David W. Freeman, Manager Nuclear Reactor Facility University of Micsouri-Rolla Rolla, Missouri 6S401

i i

SUMMARY

During the-1991-92 reporting period the University of Mis-souri-Rolla Peactor (UMRR) was in use for 420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />. Use hours are up 8.5% over last year. The major part of this tima, about 71%, was used for class instruction and training purposes.

The UMRR operated safely and efficiently over the past year.

tio significant safety related incidents or personnel exposures occurred.

The reactor facility supported 26 UMR courses over the year for a total of 3,799 student-hours. The reactor was visited by about 3,000 visitors during the past year. There were 600 participants in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced about 6,376 kilowatt hours of energy using'approximately 0.33 grams of uranium. A total of 171 samples were irradiated at the reactor with most of them being analyzed in the Reactor Counting Laboratory.

Two one-week training programs for reactor operator trainees of a Midwest utility were conducted during this reporting period.

The reimbursement helped to defray facility costs.

ii TABLE OF CONTENTS /

1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Background Information . . . . . . . . . . . . . . 1

- 1.2 Facility Status . . . . . . . . . . . . . . . . . 2 2.0 Reactor Staff and Personnel . . . . . . . . . . . . . . 5 4

2.1 Reactor Staff . . . . . . . . . . . . , . . . . . . 5 2.2 Licensed Operators . . . . . . . . . . . . . . . . 5 2.3 Radiation Safety Committae . . . . . . . . . . . . 6 2.4 Health Physics . . . . . . . . . . . . . . . . . . 7 3.0 ImprGyements . . . . . . . . . . . . . . . . . . . . . . 8 4.0 Reactor Operations . . . . . . . . . . . . . . . . . . . 12 5.0 Public Relations . . . . . . . . . . . . . . . . . . . . 23 6.0 Education Utilization . . . . . . . . . . . . . . . . . 25 7.0 Reactor Health Physics Activities . . . . . . . . . . . 30 ,

8.0 Plans . . . . . . . . . . . . . . . . . . . . . . . . . . 33 APPENDIX A. STANDARD OPERATING PROCEDURES CIIANGED DURING THE PAST YEAR . . . . . . . . . . . . . . 36

_i lii LIST OF TABLES Table'_3-1. Existing Nuclear Instrumentation System Characteristics . . . . . . . . . . . . . . . . . . . . 10 Table 3-2. Proposed Nuclear Instrumentation System Characteristics . . . . . . . . . . . . . . . . . . . . 11 Table 4-1. Core 74W Technical Data . . . . . . . . . . . . . 13 Table 4-2. SCRAMS . . . . . . . . . . . . . . . . . . . . . 16 Table 4-3. RUdDOWNS . . . . . . . . . . . . . . . . . . . . 16 Table 4-4. MAINTENANCE . . . . . . . . . . . . . . . . . . . 18 Table 4-5. Facility Use Other Than The Reactor . . . . . . . 21 Table 4-6. Reactor Utilization . . . . . . . . . . . . . . . 21 Table 4-7. Core Loading and Unloading . . . . . . . . . . . 22 Table 5-1. Public Relations Program . . . . . . . . . . . . 23 Table 6-1. UMR Classes at Rec.ctor Facility 1991-92 Reporting Period . . . . . . . . . . . . . . . . 26 Table 6-2. Reactor Sharing Program . . . . . . . . . . . . . 28 s

-s.

iv LIST OF FIGURES ~

Figure 4-1. UMRR Core Configuration and Rack Storage Form . 14 t

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1.0 1 Introduction This progress Missouri-Rolla Reactor (UMRR) report coversy ofactivities at th 1991 to March 31, 1992. Facility for the period April 1 ,

The reactor is operated as a unive to the faculty and students of th rsity facility, aval]able _

university for their educational and reseae various departments rch programs.

other universities, colleges, and high s h Several the facility during this reportin g period. c ools have made use of The facility is also made available for the purpole of traini ng reactor personnel of nuclear electric utilities.

activation is also provided at the y.

facilitTrace element n analy 1.1 BAck9I_qund _InfRIDAti9.n The University of Missouri-Rolla R l

constructed in 1960-1961 eactor (UMRR) Facility was k,

i 9th, 1961. and attained rc ti cality i on December I The UMRR was +10 the state of Missouri. first operating nuclear reactor in Shielding Reactor at Oak Ridge NatiThe reactor uk design is ba onal Laboratory.

licensed power was 10 kW. The initial The licensed kW in 1966. power was upgraded to 200 The reactor is a pool-type reacto convection flow. r cooled by natural The fuel is MTR plate-type fuel .

The standard fuel element consists of tene curv d enriched uranium. plates fueled with high-

_ - - ~ ' - ^ - ~ ~ --- --

2 rimental The facility is equipped with several expe thermal column, pneumatic facilities including a beam port, irradiation facilities.

rabbit system and several manual sampled with a counting laboratory Additionally, the facility is equippe The gamma bilities.

with gamma and alpha spectroscopy capa ity germanium, germanium-spectroscopy system includes a high pur ssociatea electronics, lithium, and two sodium-iodide detectors, a ftwarc.

The alpha i

and state-of-the-art spectrum analys s soface barrier detector and spectroscopy svstem consists of a cur data acquisition equipment.

1.2 Facility Status l over the past year.

The UMRR operated safely and efficient y ersonnel exposures No rignificant safety related incidents or p occurred. U conversion process.

Major progress has been made in the LEfety Analysis Report NRC concerns regarding our proposed LEU Sa On March 5, ddressed.

and Technical Specifications have been ar license to convert to 1991 NRC issued the order modifying ou LEU fuel.

h LEU, effective the date of receipt of t eelements for testing in We received " dummy" (unfueled) re We extensively tested the dummies to assu September, 1991. l rods and drives, dimensional compatibility with our controWe expect to receive the i

gridplate, and experimental facilit es.We plan to load the initial new core 11n the summer of 1992. itten procedures. A core carefully, in accordance with wr ting plan is being prepared detailed core loading and start-up tes

-  % ~  % _  %

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3 for the new fuel.

We received a second grant award from DOE to aid in purchasing new nuclear instrumentation (NI) for the UMRR console.

The cost of the upgrade is being shared directly from reactor funds. We plan to replace our existing five channel NI system with a three channel system. Gamma-Metrics has been selected as the supplier of our new contale equipment.

During the months of December, 1991 and January, 1992, the reactor facility was the subject of an internal review. A UMR Tasx Force was assigned to evaluate costs and benefits of continued operation of the reactor facility. The Task Force recommended "no further degradation in the status of the UMR Nuclear Reactor" and stated that "to maintain a strong Nuclear Engineering Program, UMR must continue to have an operating nuclear reactor".

The Reactor Facility was audited in April of 1991 by an independent audit team from the University of Missouri-Columbia research reactor. The audit team stated "We didn't have any significant areas of concern. The Facility appeared in good order," Several minor suggestions and comments were made by the audit team.

The reactor staff has continued to review the operation of the Reactor Facility in an effo.t to improve the safety and effi-ciency of its operation and t o provide conditions conducive to its utilization by students and faculty. An " outreach" program was implemented this year in crder to let both students and

4 faculty in a number of departments across campus know how the 3 reactor could be used to enhance course work and research. A number of special seminars were presented by Mr. Freeman. As a result, several classes went to the Reactor Facility for laboratories demonstrating variots nuclear concepts such as neutron activation and radioactive decay.

The following sections of this report are intended to _

provide a brief descript. ion of the various aspects of facility operations including the reactor's utilization for education and research.

i

5 2.0 Reactor Staff and Personnel 2.1 Reactor Staff Hang Title Albert E. Bolon Director David Freeman Reactor Manager C3rl Barton 3enior Electronic Technician __

Juls Williams Lab Mechanic Francis-Jones Reactor Maintenance Engineer Linda Pierce Senior Secretary Matt McLaughlin Student Operator 1

2.2 Licensed Operators HaEC L1RCDIin Albert E. Bolon Senior Operator Carl Barton Senior Operator David Freeman Senior Operator Francis Jones Senior Operator Matt McLaughlin Reactor Operator I

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2. 3 - Radiation Safety Committee i

1 The Radiation Safety Coumittee is~ required to meet q1:arterly. The committee met on 6/12/91, 9/17/91, 12/16/91 and 3/23/92 during the reporting. period. The committee members are listed below:

1 Name Q9partment Dr. Nord L~. Gale (chairman) Life Sciences Mr. Ray Bono (secretary, ex-officio, Environmental Health non-voting) and Risk Management 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

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Dr. Arvind Kumar Nuclear Engineering Mr.-David Freeman-(ex-officio, non-voting) Nuclear Reactor i

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

Hamp Title .

Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Director, Environmental k y)

Health and Risk Management , ;~

and Reactor Health Physicist Mr. Mark Sautman" Student Assistant (HP)

Mr. Charles Hooper Student Assistant (HP)

Mr. Cary Lieurance Student Assistant (HP)

Miss Lisa Stiles Student Assistant (HP)

1) terminated eEfective May, 1991
2) employed effective February, 1992 i

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3.0 Improvements A continicJ.D effort is made to enhance safety, availability g and reliability of the facility. In that effort the following improvements have been made at the facility during the reporting period:

1) Three new nuclear instrumentation drawers have been _

ordered from Gamma-Metrics. The three channel Gamma-

) ), Metrics system will replace our present five channel system. This is possible due to advanced technology that will allow a fission chamber based " wide range" channel to both serve as a start-up channel and an Intr.rmediate Log N and period channel. The other channel reduction is possible because advanced technology allows a linear high power scram trip to be set on each of the three channel drawers, thus the two existing Uncompensated Ion Chamber Safety Channels will not be needed.

We have purchased a Wide Range Logarithmic Drawer (fission chamber based), Wide Range Linear Drawer (CIC based),_and a Log / Linear Drawer (CIC based).

Table 3-1 presents characteristics of our existing NI system. Table 3-2 lists the characteristics.of our new proposed NI system. It should be noted that some details of the new proposed system may be revised in response to internal review comments. No equipmerit i

9 will be installed until proper reviews and approvals have been obtained.

2) A campus outreach program has been in progress over the past year. The program is designed to make UMR faculty and researchers outside of the Nuclear Engineering Department aware of reactor capabilities applicable to their specific disciplines. The program has been very 9? successful and has resulted in significant increased I

. reactor usage.

Table' 3-1. Existing truclear Instnrentation System Characteristics -

}DNITORED OUTPUT TRIP FUNCTION

. TYPE OF DETECTOR PAFJETERS .' PJEE ' DISPLAYS _(SET POINTL CHANNEL A. Starttp Fission Chamber .logCR 1 to 10E4 CPS 1. Meter WP (Fecorder off)

(MoveabletoCcver. 2. Fecorder h?'(CR(2 CPS)

FullPowerRangel B. Intemediate CIC 1. Iog N 0.2 W to 300 kW 1.' Meter B7 (Recorder Off)

Log NP 2. Recorder Rmdown(P)120%).

Rudown(Low (80%)

Detector HV).

Scram (NotOperate Mode)

2. Period -30 to +3 Sec 1. Heter MT(RecorGerOff)
2. Recorder h?(Period <30 Sec)

Rundo m (Period

<15Sec)

Scram (Period <5 Sec)

C. Linear CIC Linear Power 0 to 150% Scale 1. Meter n?(RecorderOff) w/Selectable 2. Recorder Rundo m (P)1201 Scales Scale)

Over 0.2W to 300kW Rundown (Low (80%)

Detector HV)

D. Safety #1 UIC Power Range 0 to 1501 Meter Scram (P)1501)

E fafety l2 UIC PowerRange O to 150t Heter Scram (P)1501)

WP = Rod Withdrawal Prohibit CPS = Cotets Per Second CIC = Ccepensated Ion Chamber HV = High Voltage l

llIC = Uncompensated Ion Cha.mber P = Power

R = Count Rate A-4 4

Table 3-2. Proposed Nuclear Instrunentation System Characteristics Cf7FUT TPS FUNCTION HONITOFE DISPLAYS (SET P.)niTL TYFE OF DETECTOR F1.EAMETEKi P14H CflgL 0.1 to 10 5cps Meter ET(crc 2 cps)

Fission Chanter 1. Log CR A. Wide Range 1. Meter W7 (Recorder Off)

2. Log N 10E-81 to 2001 Log NP 2. Recorder Rundown (P)1201)

Full Powar Scran (Not Operate Mode)

Meter Rundown

3. Power Fange 0 to 1251 (Power >120%)

Scram (Power

>?25)t

-30 to +3 Sec 1. Heter IW (Pecorder Off)

4. Period
2. Recorder B7(Period <30 Sec)

Rundown (Period (15Sec)

Scram (Feriod<5 Sec) 0 to 125% Scale 1. Meter n? (Eecorder Off)

B. Vidc Fange CIC Linear Power

2. Fecorder Fundown(P>l20%

w/Selectahle l Linear Scale)

Scales over i Scram (F>l20% Full 0.01 W to 250 kW Power)

Scram (NotOperate Mode)

Rundown (LcwCIC IN)

Meter Scram (Not Operate

1. Log N 1E-6 to 1101 C. Log ard Linear CIC Mode)

Rundown (Lcw CIC IN) 0 to 1251 Powar Meter ScIam(Ocwer

2. Linear (Power

>125%)

Iange)

-30 to +3 see Mcter Scram (Period <5

3. Period

!+r)

CIC = Ccopensated 10.1 Charler nT = Rod Withdrawal Prohibit CR = Count Eate CPS = Counts Fer Second XV = High Voltage

12 4.0 Reactor Operations Core designation 74W is presently in use. The "W" mode core is completely water reflected and is used for normal reactor operations. The "T" mode (core positioned near graphite thermal column) may be used for various experiments including beam port and thermal' column experiments.

Table 4-1 presents pertinent core data and Figure 4-1 shows the core. configuratior: of core 74W.. The excess reactivity, shutdown margin, and rod worths were measured in cold clean conditions.

Tables 4-2 and 4-3_present a listing of unscheduled shutdowns along with their.causes and corrective actions.

Maintenance activities are listed'in Table 4-4.

Table 4-5'shows facility use other than the reactor and Table 4-6 shows reactor utilization. Table 4-7 presents core loadings and unloadings over-the.past year.

13 Tabic 4-1. Core 74W Technical Data

. Rod Worths:

Rod 1: 2.40% Ak/k (3/23/92)

Rod 2: 2.40% Ak/k (3/23/92)

Rod 3: 3.38% Ak/k (3/23/92)

Reg Rod: 0.35% Ak/k (3/23/92) _

Excess Reactivity: 0.37% Ak/k Shutdown Margin *: 4.43% Ak/k

" Rod 3 and Reg Rod are assumed to be fully withdrawn.

1 1

., s i 14 l Figure 4-1. URICoreConfigurationandRackStorageFora DATE 23 March, 1902 LOADINO EMBER 2R R1 R2 R3 14 R$ R6 R7 R8 R9 R10 R11 -R12 113 R14 R15 t I- 1 l l 1 1 l l l IP l  ! lF-22 l l l RACK STORAGE FACILITY

!  !  ! I I i l i F-21F-151 ER-il F-191 F-16l F-3 lF-1% 'iT-21 l R16 R17 118 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 R29 R30 I

.A KEY TO FRETIXES B S F - Standard Elements C - Control Elements C F-12 F-14 F-1 C-4 HF - Half Front Element l HR - Half Rear Element D F-8 C-1 F-5 F-9 F-13 F-20 S - Source Holder E F-6 C-2 F-11 C-3 F-17 HF-1 F BRT F-10 F-4 F-7 CRT 1- 2 3 4 5 6 7 8 9 BRIDGE SIDE-- C HR CORE STATUS Other BRT - Bare Rabbit Tube CRT-CadmiumRabbitTube l

"t 15 Table 4-2. SCRAMS Dg_tg Cause 07/03/91 -< 5 second Reactor Period Scram Cause: Received Scram during adjustment of Log N CIC detector. Reactor was at steady state power.

Transient was indicated from detector movement - not from actual transient.

Corrective Action: Cautioned staff involved in adjustments to move detector very slowly.

11/22/91 <5 second Period Scram Cause: Passed by Log N CIC too closely with a fuel element while loading the core. Core loading was subcritical.

Corrective Action: Cautioned SRO handling fuel.

02/13/92 Lost power indication on Log N channel during reactor operations.

Cause: Modulator board failed.

Corrective Action: Failure was immediately identified.

Reactor shut down immediately by operator via normal reactor-shutdown. Repaired modulator board and realigned unit.

03/16/92 < 5 second Reactor Period Scram Cause: Movement of void tube during experime-t. Void Tube moved too close to Log N detector causiLj an indicated (not actual) period transient. Reactor was subcritical.

Corrective Action: Cautioned personnel on proper _

movement of void tube.

03/23/92. 150% full power and < 5 second period Scran Cause: Spurious signal fron'cafety amp. Rods were being inserted et the time of Scram and reactor was subcritical.

Corrective Action: Checked connectors and safety amp.

16 Table 4-3. RUNDOWNS o Note: Most of the rundowns listed below were due to switching probleras in the Linear instrument while manually changing scales.

A new Linear instrument has been purchased from Gamma-Metrics that, when installed,will eliminate the spurious rundown trips.

Date Cmisn 04/16/91 120% demand Cause: Button on Linear picoameter popped out.

Corrective Action: Rundown terminated by Senior L Operator on duty. Student Operator given additional instruction.

05/06/91 120% demand Cause: Student operator changed Linear picoameter down scale rather than upscale.

Corrective Action: Rundown terminated by Senie Operator on duty. Student operator cautioned tut operation of picoameter.

08/07/91 120% demand .

Causc: Auto controller witndrew reg rod instead of inserting and did not reverse. Reactor rundown occurred at 24 watts.

Corrective Action: Rundown was terminated by Senior Operator and Reactor returned to power. Checked for insert action upon returning to auto position.

08/12/91 120% demand -

Cause: Operator did not change scales on Linear picoameter before increasing power.

Corrective Action: Senior Operator terminated rundown.

Operator cautioned.

09/11/91 120% demand Cause: Linear picoameter noise spike as range button was nressed.

Corructive Action: Rundown terminated by Senior Operator on duty. Operator trainee cautioned.

09/11/91 120% demand Cause: Button on Linear pico.teter popped out after changing scales.

Corrective Action: Senior Operator terminated rundown and cautioned operator trainee.

A

's 17 Table 4-3. RUNDOWNS (cont.)

Data Cause 09/25/91 120% demand Cause: Button on Linear "icoameter pc 7 ped out.

Corrective Action: Rundown terminated by SRO and operator cautioned.

10/07/91 120% demand Cause: Student operator pressed wrong button on Linear picoameter.

Corrective Action: Rundown terminated by Senior __

Operator on duty. Student operator instructed on changing scales.

11/07/91 < 15 Second Period Cause: Moving void tube for experiment. Tube moved too close to Log N detector and caused indicated (not actual) period transient. Reactor was subcritical at the time.

Corrective Action: Rundown terminated by Senior Operator on duty. Cautioned student moving void tube on proper movement of void tube, 11/25/91 120% demand Cause: Switch popped out on Linear picoameter while switching scales.

Corrective Action: Rundown terminated by Senior Operator on duty. Cautioned Student Operator.

02/13/92 120% demand _

Cause: Switch on Linear picoameter not operating correctly.

Corrective Action: benior Operator terminated rundown.

03/16/92 120% demand Cause: Student operator did not switch scales on Linear picoameter.

Corrective Action: Rundown terminated by Senior Operator and further instructions given to Student Operator.

18 Table 4-4. MAINTENANCE i

Data Cause 04/01/91 Problem: Need to measure dimension of control rod. ,

Cause: None Corrective Action: Removed shroud and Control Rod Nc:

1. . Reassembl.ed Control Rod No. 1, replaced shroud and performed Rod Drop tests on Rod No. 1.

06/04/91 Problem: Annual Control Rod inspection.

Cause: Routine maintenance.

Corrective Action: Control Rod Inspection completed and reassembled. Rod Drop Time test completed.

06/07/91 Problem: Routine Semi-Annuals.

Cause: Routine maintenance.

Corrective Action: Completed Semi-Annuals on 6/14/91.

06/24/91 Probl~em: Magnet currents not normal.

Cause: Magnet tubes in Safety Amplifier bad.

Corrective Action: Replaced V 3, V., V, and R-50 in Safety Amplifier.

n6/27/91 Problem: 150% full power test not operating.

Cause: Safety Amplifier power supply voltage low.

Corrective Action: Replaced V-9, V-10, V-11 and V-12 in Safety Amplifier.

07/01/92 Problem: Magnet No. 1 not picking up Rod No. 1.

Cause: Magnet current low.

Corrective Action: _ Replaced V 3, V., and V. in Safety Amplifier.

08/12/91, Problem: -Rod drive-motor for Shim Rod No. 3 would not insert during normal shutdown.

Cause: No voltage to rod drive motor. Failure of relay.

Corrective Action: Reactor-was shut down by normal rod insertion of Rods 1 and 2. Rod 3 was then inserted by dropping magnet current. Replaced relay K-13.

08/13/91 Problem: Fission chamber response not adequate.

Cause: Fission chamber drive cable broken.

Corrective Action: Reclamped drive cable to fission chamber extension tube.

08/30/91 Problem: Log Count Rate recorder not operating.

Cause: Recorder not getting power. Switch bad.

Corrective Action: Replaced power switch.

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'e 19 Table 4-4. MAINTENANCE (cont.)

Data C.anac 08/30/91 Problem: Testing dummy control rod element.

Cause: Routine. Disassembled and removed rods for testing.

Corrective Action: Rods reassembled, Rod Drop Time test completed and core reloaded.

09/30/91 Problem: Start-Up Channel not operating proverly.

Cause No signal to Start-Up Channel equipment.

Corrective Action: Replaced DNC connector on high voltage cabic.

10/13/91 Problem:- Temperature _ Recorder going full scale.

Causer Contact on switch broken.

Corrective Action: Repaired switch.

10/26/91 Problem: Testing dummy control element.

Cause -Routine. Disassembled and reme,2d eac;1 Control and Reg Rod for testing.

Corrective Action: Reassembled rods and performed Rod Drop Time tests.

12/02/91 Problem: Linear Recorder indicating wrong power while Re& tor was suberitical.

Ccuse: Recorder inoperativo due to had capacitor.

- Corrective-Action: Replaced capacitor unit.

01/06/92 Problem: Semi-Annual started.

Routine.

Cause:

Cerrec?ive Action: Completed Semi-Annuals on 1/14/92.

01/15/92 Problem: Inspection and measurement of Control Rods 1, 2, and 3.

Cause:- Routine.

Corrective Action: Completed measurements and reassembled units and completed Rod Drop Time test.

01/27/92 Problem: Magnet current not normal o. Magnet No. 1.

Cause: Magnet No. 1 bad.  ;

Corrective Action: Repaired and replaced Magnet No. 1 and performed Rod Drop Time test.

01/31/92 Problem: Start-Up Channel noisy.

Cause: Orcamplifier bad.

Corrective Act . ion: Repaired Pre-amplifier and reinstalled it.

x.-_.

i 20 i Table 4. MAINTENANCE (con.t.)

Dahn CAMEQ l 02/14/92 Problem: Difficulty in aligning Log H amplifier.

Cause L3 on modulator board defec+.ive.

Corrective Action: Replaced L; on nodulator boa.d.

02/21/92 Probler - Start-t!p Chansiel not operating correctly.

Cause Low high voltage.

Corrective Action: Reent high voltage to proper value.

03/25/92 Problem: Stact-1)p Channel not operating properly.

Causes Pre-amplifier noisy. ,

Corrective Action: . Changed Pre-amplifiers. .

l 4

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21 Table 4-5. Facility Use Other Than The Reactor Facility ligita Bare Rabbit Tube 9

Beam Port 5.4 Total 14.4 Table 4-6. Reactor Utilization

.s ..

1. Roactor use 419 hr

.a. Research and irradiation %dns 10.4 hr b.. . Instruction runs 231 hr

c. Maintenance runs 35.5 hr i
d. Training 67.6 hr
2. Time at power 197 hr
3. Energy _ generated 6376 kw-hr
4. Total. number of samples 171
5. Sample hours 21.5 hr 6.. U-135 burned 0.28 g
7. U-235 burned and.. converted O.33 g

-.-.--7..

l 22 Table 4-7. Coro Loading and Unloading Daig Action 06/04/91 -Unload-(67W to Subcrit) Annual Control Rod Inspection 06/06/91 Reload (Suberit to 67W) Return to previous configuration 06/28/91 Unload different elements to fuel storage area'for dose j rate measurements '

07/08/91 Unload different elements to fuel storage area for dose rete measurements Unload ~(67W to Subcrit) Core for LEU dummy trial l 09/16/91 09/17/91 Test fit-of LEU dummy element 109/18/91 . Reload to previous configuration j 11/19/91- Unload (67W to subcrlt) Core for LEU dummy trial 11/24/91 Test fit of dummy element q Reload to previous configuration I 11/22/91 01/15/92 . Unload (67W to subcrit) Core for Babcock and Wilcox

- measurement of control rods 01/17/92 Movement-for Rod Drop test in dummy control element 01/21/92 . Roload to previous-configuration 03/12/92 Change core 67W to 73W-03/20/92 Unload 73W-to subcrit 3 03/20/92 Load subcrit to core 74W R

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23 5.0 Public Relations The reactor staff continues to educate the public about applications of nuclear science. Over 3,000 persons toured 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 5-1 lists some of the major occasions or groups and number of visitors for each event.

Tablo 5-1. Public Relations Program DATE PARTICIPANTS NUMBER 04/12/91 Rolla Middle School 57 04/23/91 Rolla High School Science Club 4 01/27/91 UMR Spring Open House 212 _

05/10/91 Salem 5 & 6 Grade 75 06/10/91 Jackling Institute, UMR 44 06/10/91 Fundamentale of Engineering, UMR 18 06/11/91 Fundamentals of Engineering, UMR 12 06/12/91 Fundamentals of Engineering, UMR 17 06/13/91 Fundamentals of Engineering, UMR 27 06/17/91 Jackling Institute, UMR 41 06/24/91 Jackling Institute, UMR 44 07/29/91 Minority-Engineering, UMR 39 08/05-23/91 Jackling-2, UMR 3 l

08/05/91 Fundamentals of Engineering, UMR 17

( 08/06/91 Fundamentals of Engineering, UMR 30 Fundamentals of Engineering, UMR 19

24 Tablo 5-1. Public Relations Program ,_ ___

DATE PARTICIPANTS NUMBER 08/08/91 Fundamentals of Engineeri6g, UMR 17 08/12/91 Fundamentals of Engineering, UMR 20 08/13/91 Fundamentals of Engineering, UMR 17 08/14/91 Fundamentals of Engineering, UMR 10 08/15/91 Fundamentals of Engineering, UMR 23 10/17/91 TJ 4 South, UMR 16 10/18/91 Rolla Review, Prospective Students, UMR 9 10/18/91 UM-Rolla Dny 348 10/30/91 TJ 7 South, UMR 7 11/02/91 UMR Parents Day 123 11/04/91 Cub Scouts ___ ,

5 11/25/91 TJ 4 tiorth, UMR 11 12/06/91 TJ South, UMR 7 12/16/91 Nuclear Reactor Task Force, UMR 7 02/11/92 TEAMS Testing (Basic Engineering) UMR 33 02/25/92 St. Louis County 8th Grade 62 02/28/92 Rolla Emergency Services Training 7 03/10/92 Rolla Fire Department 6 03/11/92 Rolla Fire Department 5 _

03/12/92 Rolla Fire Department 5 03/17/92 Rolla Middle School 55 03/24/92 Freshman Engineering, UMR 18 03/25/92 Freshman Engineering, UMR 19 03/26/92 Freshman Engineering, UMR 4

s 25 6.0 Education Utilization The reactor facility supported 26 Ul4R courses over the past year for a total of 3,799 student-hours. The reactor facility provided financial support for six students witt. hourly wages and one PhD candidate with a partial GRA. Additionally, students from several universities, colleges and high schools have used _

the facility.

Table 6-1 lists UMR classes taught at the facility along with associated reactor usage for 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. About 600 students and their instructors participated in this program.

Table 6-2 lists those schools and groups that were involved in this year's Reactor Sharing program.

P

26 Table 6-1. UMR Claesen at Reactor Facility 1991-92 Reporting Period TIME AT .-

  1. OF REACTOR STUDENT DATE CLASS NUMBER / TITLE STUDENTS (hrs) HOURS Fall 91 NE 300, Nuclear 2 60 120 Winter 92 Special Problems 4 Fall 91 NE 304, Reactor 14 53 742 Laboratory I Fall 91 NE 306, Reactor 14 153 2142 Winter 92 Operations Winter 92 NE 308, Reactor 9 25 225 Laboratory II , _ ,

Winter 92 NE 404, UMC, Nuclear 28 8 112 Laboratory (twice) 04/09/91- NE 204, Nuclear 8 1 8 Radiation Measurement 04/11/91 NE 204, Nuclear 7 1 7 Radiation Heasurement I 04/16/91 NE 204, Nuclear 9 1 9 Radiation Measurement 04/18/91 NE 204, Nuclear 14 1 14 Radiation Measurement 04/22/91 NE 204, Nuclear 8 1 8 .

Radiation Measurement f 04/25/91 NE 204, Nuclear 7 1 7 Radiation Heasurement 09/25/91 NE 205, Fundamentals 15 1 15 of Nuclear Ergineering 10/02/91 NE 105, Introduction 17 1 17 to Nuclear Engineering 11/25/91 NE 205, Fundamentals 13 1 13 of Nuclear Engineering 03/17/92 NE 204, Nuclear 7 2 14 Radiation Measurement 04/09/91 Life Science 251, 17 1 l' Ecology l

s 27  ;

Table 6 1, UMR Classes at Reartor Facility 1991-92 Reporting Period TIME AT

/ OF REACTOR STUDENT DATE CLASS NUMBER /T1TLE STUDENTS (hrs) HOURG 04/12/91 Eng. Mgmt. 334, 33 1 33 Robotics 05/01/91 ME 229, Energy 13 1 13 Conversion ,

05/03/91 Physics 107, 70 1 70 Introduction to Physics 05/03/91 ME 229, Energy 11 1 11 Conversion 10/01/91 Physics 107, 9 1 9 Introduction to Physics 12/13/91 Physics 107, 101 1 101 Intrac;uction to Physics _

01/23/92 Life Science 301, 16 1 16 Biological Effects of Radiation 01/28/92 Life Science 301, 17 3 51 Biological Effects of Radiation 03/04/92 ME 229, Energy- 25 1 25 Conversion >

TOTAL 484 378 3799 i

i

)

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

e 28 Table 6-2. Henctor Sharing Program DATE PARTICIPANTS NUMBER 04/16/91 East Central College, Leroy Alt /Vera Luedde, 29 Instructors 04/17/91 Potosi Gifted 8th Grade Alan Ziegler, 12 Instructor 04/22/91 John F. Hodes High School, Jim Jenkins, 19 Instructor 04/02/91 Vienna High School, Ms. Fritchey, Instructor 16 04/24/91 Park College of Nursing, Christiane Dornhoefer, 14 Instructor 04/25/91 Park College of Nureing, Christiane Dornhoefer, 13 Instructor 05/92/91 Northwest High School, Paul Oldeg, Instructor 25 05/08/91 Vo-Tech Radiography, Rita Montgomery, 9 InstrLly or 05/15/91 Sullivan High School, Marcene Abel, Instructor 11 05/22/91 Rolla High School, Gayle Lucien, Instructor 43  ;

07/09- University of Arkansas, Dr. Leon West, 7 11/91 Instructor 07/30/91 Eldon High School Science Club, Connie Wyrick, 11 Instructor 10/17/91 Rolla High School, Gayle Lucien, Instructor 10 11/01/01 ' Park College of Nursing, Christiane Dornhoefer, 22 Instructor 11/08/91 Rolla Vo-Tech School, Jeff Dalton, Instructor 13 11/13/91 Roxana High School, Gerald Uhe, Instructor 50 11/13/91 West Plains High School, Jack Dillar'd, 14 Instructor 12/09/91 St. Dominic High School, Dorothea Bean, 26 Instructor _

12/10/91 Linn Technical College, Jack Light, Instructor 31

-12/11f 91 Benton County High School (Cole Camp), Todd 26 Rusk, Instructor

29 Tablo 6-2. Reactor Sharing Program DATE PARTICIPANTS NUMBER Licking High School, Jonnie Kirkland, 9 01/24/92 Instructor Licking High School, Jonnie Kirkland, 9 02/06/92 I

Instructor 02/10/92 Poplar Bluff High School, Bill Reeves, 17 Instructor 02/17/92 UMC NE 404, Robert Thompson, InstruItor 14 -

02/27/92 Cabool High School, Gary Maggard, Instructor 28 02/28/92 Westminster Christian Academy, Andrew Shaw, 18 Instructor Newburg Science Club, Peggy Brown, Instructor 16 .

_03/03/92 St. Louis Community College, Delwin Johnson, 4 03/09/92 Instructor 03/16/92 UMC NE 404, Robert Thompson, Instructor 14 03/19/92 Van Buren High School, Daniel Freeman, 31 Instructor 03/20/92 John F. Hodge High School, Jim Jenkins, 7 Instructor 03/24/92 Hazelwood West High School, Gail Haynes, 22 Instructor ,

03/25/92 Viburnum High School, Judy McGee, Instructor 10 TOTAL 600

30 7.0 Reactor Health Physics Activities The health physics activities at the UMR Reactor Facility -

consist primarily of radiation and contamination surveys, moni-toring of personnel exposures, airborne activity, pool water activity and waste disposal. Releases of all'by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of por-table and stationary radiation detection instruments, personnel training, special-surveys and monitoring of non-routine proce-dures.

A. Boat;1n.o surveys Monthly radiation exposure surveys of the facility consist of direct gamma and neutron measurements with the reactor at power. No unusual exposure rates were identified. Monthly surface contamination surveys consist of 20 to 40 swipes counted separately for alpha, and beta / gamma activity. No significant contamination outside of contained work areas was found.

B. Dy-Product Material Release Surveys There were no shipments of by-product material released off-campus froin the reactor f acility during this reporting period.

s ___

s 31 C. Equtine Mgnitoring Twenty-four reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges. Five are read twice per month and twenty-nine are read once per montr.. There arc four area beta-gamma / neutron badges assigned. Eighteen 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 22 moni'.or and spare badges assigned on campus. In addition, 4-7 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 ..ading dosimeters. No visitor received in excess of an indicated 8 milliren.

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 nor fuel cladding rupture has occurred.

Gross counts and spectra of long-lived gamma activity are com-pared to previous monthly counts. Frcm April 1991 through March 1992 sample concentrations averaged 5.58 x 10-' #Ci/ml.

s 32 D. Hante Disposal Release of gaseous and particulate activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously-mnasured air activity at maximam reactor power. Dur-ing this period 138.72 millicuries were released into the air.

The released isotope was identified as Ar-41. _

Solid waste, including used water filters, used resins and contaminated paper is stored and/or transferred to the campus waste stcruge area for later shipment to a commercial burial site. Radioactive waste released to the canitary sewer is pri-marily from regeneration of tne ion-exchange column. During this period four releases associated with resin regeneration were discharged to the sanitary sewer totaling approximately 10,598 gallons of water with a total gross activity of less than 257 microcuries..  ;

E. Instrument Calibrations During this period, portable instruments and area monitors were calibrated twice.

-_.-s -.w--------_-- - - - - - - - - - - - - _ - _ - . _ - - - - , _ . - --------.___---_--.---____---.--,_------_-----_------x - - - - - - ,

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s3 8.0 Plsns The reactor staff will be heavily involved in four major projects during the next reporting period; 1) preparing for receipt of the LEU fuel, 2) procuring, testing and bringing on-line the new reactor nuclear instrumentation, 3) preparing to ship !!EU fuel of fsite, and 4) managing staff turnover. _

A. LEU Fuel ConversioD on March 5, 1991 we received the NRC order to modify our license to convert from HEU to LEU efrective upon the date of We received " dummy" elements this past receipt of the LEU fuel.

year for fit tests and will rece've the LEU fuel sometime this summer.

The dummy elements have been received and were rigorously tested to assure dimer:Jional compatibility with our gridplate, control rods, and experimental facilities.

A detailed start-up testing plan is being prepared to cover fuel receiving, inspection, loading and testing of the new LEU Core.

B. Reactor Instrumentatiorl_Ungrade We have recently contracted with Gamma-Metrics to provide three new NI channels which will replace our exicting f've channel system..

As instruments are procured, extensive review documentation

7.____

34

~

will be established and appropriate approvals will be obtained.

NRC will be notified of our intended changes in a timely fashion.

Detailed testing will be performed and extensive operational data will be cvilected prior to actually-replacing the equipment.

l l

C. Shionent_ of IIEU Fuel Of fnite i Efforts will continue during the next reporting period to

_ prepare for offsite shipmont of our HEU fuel. We 14 ope to l 1

maintain the HEU fuel for a period of about one year after discharge to allow. fur radioactive decay. Studies have been completed to help project the dose rates that will be associated with each element.

l

. Additionally, we plan.to submit a revised Security Plan for NRC. review and approval to relax our current security requirements _ associated with the HEU fuel.

-D.- fL.cLL W .DQ1CI A- ra *sptember 1, 1992,-two staff personnel will retire and a third' position will be eliminated. Carl Barton (senfor Electronics Technician and SRO) and Juls Williams (Reactor Lab Hechanic)1 plan-to retire on September 1,-1992. Both employees are planning on working at the facility on a part-time basis

'(about 1/3 time each) over the'next-few years. The-third technical position, the Reactor Maintenance Engineer (3/4 time) will be eliminated. .Bocause_the Reactor Maintenance Engineer-is referred to.in Chapter 6 of the Technical Specifications, we plan

o l J l 35 to either apply for a Technical Specification change or to classify one of the new hires an " Reactor Facility Maintenance Engineer".

Presently, we plan to hire a replacement for the Senior Electronics Technician in September, 1992 ano a replacement for the Reactor Lab Mechanic in September, 1993. Both new hires will be trained for SROs. Efforts are underway to begin training of additional personnel to serve as licensed operatorn. Both faculty and students are being considered as operator candidates.

The above staffing changes will not impair the facility's ability to operate safely and within compliance of procedures and regulations.

I I

i

      • UMR REACTOR STANDARD OPERATION PROCEDURES ***

SOP: 610 TITLE: RADIATION AREA SURVEY Revised: September 12, 1991 Page 2 of 2 and Health Physicist notified. Rev.

7. If an abnormal radiation level is detected in a restricted area. The Reactor Manager and the Health Physic'.st are to bo inmediately notified. The appropriate action, as determined by Health Physics shall be taken.

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Written By: Davi ,reena Approved By: Albert Bolon

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Ray Bono

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      • UMR REACTOR STANDARD OPEUATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CilECK Revised: March 20, 1992 Page 1 of 13 A. PURPOSE To ensure the proper operation of the control and safety- ,

related instruments of the actor and to functionally test the Physical Security Alarm Efstem. ,

D. ERECAUTIONS. PREREOUISITES. OR LIMITAT7:e;1S

1. The Weekly Check should be completed on the first Rey, 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 F Select the Reactor Bridge Station on the Building Intercom, check the PA system, install-the neutron source, turn on all 5 primary recorders (date the recorders), turn on core camera and select core on the monitor selector. Obtaj, Magnet Power Key and turn on magnet power.

1. ' ROD WITHDRAW PROHIBIT'(vel'ow liohts): -7 A. Re. orders off ... the-rods will not withdraw if
  • any one of.5 primary recorders is turned off.
1. ' Turn off LCR recorder.
2. Attempt to withdraw rods.
3. Turn on LCR recorder, reset alarm.
4. Turn off linear level recorder.
5. Attempt to withdraw rods. ,

!)h.x Albert Bolon' h

Written By: Carl Barton Approved By:

a_

r,......

      • =UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CllECK Revised: March 20, 1992 Page 2 of 13

6. Turn on linear level recorder, reset alarm.
7. Turn off period recorder.
8. Attempt to withdraw roda.
9. Turn on period recorder, reret alarm.
10. Turn off log N recorder.
11. 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 fission chamber to the insert limit. Reset annunciator.

C. Period < 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 g" on the recorder.

j

2. Attempt to withdraw rods.- -
3. Release test switch, reset alarm.

D. Inlet Temperature Above 135 Degrees

1. With recorder on, remove back cover and manu-ally rotate potentiometer arm until alarm occurs, record trip point.

2.: Acknowledge alarm and attempt to withdrew rods.

3. Reset alarm on temp. recorder, reset alarm on console.

E. Shim Rods Below Shim Range h c-Approved By:

$Y Albert Bolon.

W Written By: .arl.Barton-

t i

A w

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK

' Revised: March 20, 1992 Page 3 of 13

1. With all-Shim / Safety rods below shim range attempt to withdraw the regulating rod. Note that the regulating rod will withdraw just 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. RUEIOWN CHECK (blue liohts):

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.

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 Rundown Reset and Annunciator Reset. Record value of alarms.

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 further alarms,"

.on the building PA system.

B. 120% Demand

1. Withdraw rods to 3 inches.
2. De-energize (Linear, Period or Log N) recorder. .(Switch to off.)
3. Remove Linear Channel potentiometer cover and manually rotate potentiometer arm, note _

i recorder reading when trip point-is reached.

4. When inward motion of rods is verified, lower .

recorder below reset point, reset the_ rundown .i ut and'all alarms, turn recorder on and replace  ;

cover, compare actual and specified trip points. ~

5.- Record trip point value.

I OCAh OW L Written By: Carl Bartoo Approved By: Albert Bolon p

. -_ _ m _ . . _ . _ -

_ _ _ . - _ _ . .- __ _ __--=____ ._ . _ _ _

', t f <

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

, SOP: 810 TITLE: WEEKLY CHECK Revised: March 20, 1992 Page 4 of 13 C. Period < 15 Seconds

1. Repeat steps 1 through 5 of 2.B for the Period recorder.  !

1 D. 120% Full Power

1. Repeat steps 1 through 5 of 2.B for the Log N Recorder.

E. Low CIC Voltage Linear Power Supply

1. Withdraw rods to 3 inches, l
2. Push and hold alarm test button on Linear CIC Power Supply. Observe High Voltage meter and

-record the value when the under voltage alarm light comes on. Release the test button.

3. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown in pro-gress). _
4. Uhen the High Voltage on the Linear CIC Power Supply has increased to approximately 500 volts push alarm reset. The under voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and' the annunciator.
5. Record value of the trip point.

F. Low CIC Voltage Log N. Power Supply

~

1. Withdraw the rods to 3 inches.
2. Push and hold alarm test button on-the Log N CIC powe? aupply. Observe the high voltage meter and record the value when the under voltage alarm-light comes on. Release the test button. -

3.- Acknowledge the annunciator alarm and observe '

the Low CIC Voltage annunciator light (also check for 5 ? sec. period, s 15 sec. period,-

~

<.12 sec. period, and-150% full power).

Reset the period _ trip light on the Log N-&

Period Amplifier. This_ allows for reset of all annunciator lights except low CIC Written.By: Carl Barton Approved By:

bb Albert Bolon t

3

o

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: March 20, 1992 Page 5 of 13 voltage.

4. When the High Voltage on the Log H CIC power supply has increased to approximately 500V, push alarm reset. The voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and reset the annunciator.
5. Record value of trip point. _

G. Regulating Rod on Insert Limit on Auto

1. Withdraw the Shim / Safety rods to 3 inches and Reg Rod to 0.5 inches (use the shim range bypass).
2. Adjust Linear recorder setpoint so that " auto permit" comes on.
3. With egulating 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 insert on the Reg Rod will result.
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 annunciators. -
7. Record results.
3. SCRAM fred lichts):

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.

obtst--

Written By: Carl Barton Approved By: Albert Bolon

O

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: March 20, 1992 Page 6 of 13 B. Period < 5 Seconds

1. Withdraw rods to 3 1
2. Push in and t ;rn tri tch on the Period Section of the Log N ,_.,..ifier.
3. Observe Period Meter for, s 30 second and 5 j 15 second annunciators. Continue with trip test button operation until the period light is illuminated on-the Log N Amplifier.

Record the meter value when this occurs.

4. Acknowledge annunciator alarm and observe period < 5 second scram, 150% Full Power Scram and Loss of Magnet Contact Lights. ,

-Reset the per(od trip test light on the Log N~ )

Amplifier and push. reset buttons for rundown. j Insert magnets and reset annunciators. 1

5. Record value.- ,

j C. Log N & Period Non-Operative Scram  :

\

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.

Roset 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 off.

3. Push reset on the Safety Amp., ackncwledge the annunciator and observe the 180% Full Power Scram annunciator and Magnet Contact lights are off.
4. Reset annunciator and insert the magnets.
5. Record results.

Approved By:

hh Albert Bolon Nw Written By:- Carl.Barton

[

- _ m - _ _ __.

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: March 20, 1992 Page 7 of 13 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 cur-rent using current adjustment #1, until the
  1. 1 magnet contact light goes out (you should also hear an audible " click" from the Reactor Bridge Intercom Station). Record this drop current value.
3. Repeat Steps 1 and 2 for Shim Rod No. 2 and No. 3.
4. Insert all Shim Rods to insert limit.
5. Set all Magnet Currents to " normal" (i.e.

Drop Current plus 10 ma).

5. TEST 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 alarm and annunciator.
3. Record results.

B. Interlock Bypass

1. Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights.

' 2 I. h Written By: Carl Barton Approved By: Albert Bolon

4

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***  !

SOP: 810 TITLE: WEEKLY CllECK Revised: March 20, 1992 Page 8 of 13 C. Servo Limits

1. Note linear level recorder reading. l
2. Change the automatic set point for auto  !

permit by adjusting the star wheel. Note  ;

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

3. ' Reset automatic set point to the 100% level. j
4. Record results.

D. Pool Demineralizer Effluent Conductivity High l Record pool and demin effluent readings. Rev.

.. Check the alarm secpoint by dialing setpoint knob on the resistivity meter

  • to match the needle reading. The local L, arm (red alarm light) on the resistivity meter should come cn1 and the console annunciator should' alarm.

'3. Reset the alarm to a setpoint of 0.5 MD-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 (1) above console (2)'at reactor entrance and (3) basement level.

7. BUILDING EVACUATION ALARM:

A. Announce over the PA, "The Buildina Alarm will sound. This is a test. Do not evacuate the building."

B. Pitsh the Building Evacuation Alarm (center) of reactor console) and note the audible alarm. 3 C. Reset Building Evacuation Alarm by pushing scram >

Reset.

l D. Announce.over building PA " Test alarms complete.

D ' Acknowledge al] further alarms."

be

, Written By: . Carl.Barton Approved By: Albert Bolon 1

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      • UV7:-REACTOR STANDARD OPERATING PROCEDURUS ***

9?h: 810 TITLE: WEEKLY CHECK

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'visig;

. _ Mar . n 20, %92 - Page 9 of 13 15w

8. NITROGEN DIFFUSERS:

gf)

  • With the bridge intercom station selected, start diffuser #1.- The green operation light sriuld ,

'luminate. Note the sound level of the } ump and-unusual noise.

.. tutdown the-#1 pump and repeat step 1 for the #2 altrogen diffuser, Secord results on form SOP 810.

9. FEAL ' ort AND THERMAL COLUMN WARNING LIGHTS:

A. -Announce over the building PA. " Attention person-nel, stanr: ? lear of the Eaam Port". j s .B. .

Open the Beam Port by holding the beam port con-trol switch in the open position until thU " Red"

.(cpen) light comes on.

C. Acknowledge the annunciator alarm and check the Baser'a e L o l Warning Light (Flashing Red).

IL Close t'; a Laam Port by b 71 ding the Beam Port Switch until the Green (:losed) light comes on.

Reset te-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-Therma.' Column Key. Select the '

Basement Level Station on the Duilding Intercom.

Address the operator over the intercom to open the  ;

G.

Thermal Column until the warning light comes on _('

.(approximately 1-inch)

I H. The Control' Room Operator should observe and acknowledge the annunciator alarr Inform the Thermal Column Operator - to - shut the Thern.al Column andJensure the warning light goes off. {

- 1 Written By:

EL Carl Barton s

Approved By:

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      • UMR REACTOR STANDARD OPERATING PROCEDURES ***
- SOP
810 '"ITLE : WEEKLY CHECK

- Revised: March 20, 1992 Page lo of 13 e I. Reset the annunciator and have the Thermal Column '

Operator return the key to the locker, Complete form SOP 810.

10. SHUTDOWN CHECK:

A. Complete a S.lutdown Check- List form 103 to ensure that all console equipment is secured. ,

11. SECURITY SYSTEM:

Inform the campus police (4300) that the security systen 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 .,wtem.
d. Open dead bolt 6.. itch by releasing or opening dead bolt and ensure alarm occurs in campus police dispatch station.
2. Ultrasonics
a. Hold or close dead bolt on securiby 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 F -ultra sonic detector should be tested o each week.

' "c . Allow the ultrasonic to reset by moving

. clear of the detector or stani still.

3; Duress

a. .nform the campus police that the duress alarm will be tested.
b. Momentarily depress the alarm button.

b tr Written.By: Carl Barton Approved By: Albert Bolon r

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      • 'UMF-REACTOR STANDARD OPERATING PROCEDURES ***

-SOP:'~810 .

TITLE: WEEKLY CHECK-Revised: Marctr 20, J 1992 Page 11 of 13 b

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 an intrusion alarm. A different door should be tested each week.

c.. Have the campus police acknowledge the e 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 different door should be tested each week. l
e. When all. intrusion channels have been l

-tested, ask campus _ police to check the battery circuit. This completes the security check.

f. Wran al~. channels of the security system have been functionally tested and operate _ properly, initial the weekly l checklist, Fort. SOP 810.

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Written-Dy: 1 Carl Barton

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Approved By:

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      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP:- 810 TITLE: WEEKLY CHECK Revised: Apri1 27. 1992 Page 12 of 13 WEEKLY SURVEILLANCE CEECKLIST FORX S0P 810

- Date Performed 1, R0D PROEIBIT- hnunciator Prohibit Inithl A. Recorder Off

-l1) Log count rate recorder (2) Linearrecorder _

(3) Periodrecorder-(4) Log N recorder

-(5) - Temperaturerecorder

- B. Log count rate <2 CPS Initial ActualTrioPoint Anngghin Enhibli O. Period 00 seconds 0

D. Inlet Temperature >135 F

- E. ShimRodsbelowshinrange

2. RUE 0WN CEECK --

A. RAM Systen Remote and Station 311 L 11g n ' Local Alarm Annunciator Rundown Trio reint Initial 1.

1.

-2.

J 3.

B. 1201 Demand' rundown Rev.

C. ' Period 15 seconds rundown D. '1201 Full Power Rundown

~ E. LowCICLinearP.S. __.

F.: Low CIC Log N P.S.

G. RegulatingRodonInsert-Linit on Auto- l

3. SCRAM CEECK .ActualTrioPoint- Innunciator Sgg Initial A. Bridge !;21on Scram B. Period <5 Seconds Scram j C. Log N Period Non-operative L v Olbca_b No b Written By:- CarrBarbon Approved By: Albert Bolon

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      • UMR REACTOR STANDARD OPERATING PROCEDURES *** '

SOP: 810 TITLE: WEEKl.Y CIIECK Revised: Apri1'27. 1992 Page 13 of 13 Date Actual Trio Point Anrmchtgr EgIn initial

- D. 1501 full Power Scran E. Manual Scram

4. RODDPOP. CURRENTS Droe Cuaent ContactLigh1Mi Initial A .- -Rodil B. Rod #2 C. Rod #3
5. TEST OF AMElllQRS A. Beam Room High Neutron flux it 111ari licht Annunciator Initial B. Interlock B'ypass Annunciator Initial (1) Shinrange .

(2) 30secondperiod (3) Padiationareahigh (4) <2 CPS C. .ServoLimits Lin. Rec (R> ding Perz:it on at Permitoffat Initial t _ t  % Fug 27AN 92 D.' . Pool /Deninerali:erResistivity- .

Eggl Dgh . Local Alaru Annunciator Initial MD-cm K0-cm

. 6. " REACTOR Ci? LICHTS Operational Initial A. Main Entrance B. Control Room C. Bean Room' ____

7: BUILDING EVACUAT10il AlenOrerational Initial

8. NITROGEN DIFFUSER EurpOperationil IndiratorLichton Initial A .' il B. l2

^ 9. BEAM PORT AND TEIFyJ1 COLUMN MNING LIGHT

'JJampiltpr flashina Licht Initial A. LBeam Port B. Thermal Column i

10. SiiUT DWN CHECK LIST Co:oleted Initial  ;

Battery Check  ;

11. SECURITY SYSTEM __

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12. APPPOVED AND REVL%TD

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ManagerorDirector(Rev., 3/92'

'AP A 4-- ' (hy w Written By: Carl Barton Approved By: bert Bo dn

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      • UMR' REACTOR STANDARD OPERATING PROCEDURES ***

SOP: -812 TITLE: CONFINEMENT AND VENTIL?. TION SYSTEM CHECK Revised: February 27,7 1992 Page 1 of 1 A. PURPOSE To check ventilation fans and closure equipment (bay door, Rev.

ventilation inlet and exhaust duct louvers, and the personnel-security door).

B. PRECAUTIONS. PREREOUISITES, OR LIMITATIONS 1.- Ventilat' ion fans and closure equipment shall be checked monthly.

2. Two people ~are needed - one to operate fans and the other to observe the fans and louvers.
3. One stopwatch is-needed.

C. PROCEDURE

1. Fans;and_ Louvers
a. Start one fan.

-b. Observer will position himself to get a view of the fan to be turned off with stopwatch in hand.

c. ' Inform operator to turn fan off.
d. When the fan is turned off,11 click will be heard.

Start stopwatch at this point.

e. Record the time it takes for louver to close completely.
f. Compare this time to previous readings.- A major change could indicate a: malfunctioning of the louvers.
g. Visually check physical condition of fans and louvers.
n. Log observations on Confinement and Ventilation System Check Form.
1. ' peat a. through h.'for each exhaust and intake louver.
2. Confinement'
a. ~ Check operation of doors and louvers to ensure the ability to maintain confinement.
b. Log observations on Confinement and Ventilation L -System Check Form.

Lb2M 3C% b h(bertBolon Al Written By: Francis Jones Approved By:

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      • UMR' REACTOR STANDARD OPERATING PROCEDURES ***

SOP : - 813 TITLE: ROD DROP TIME MEASUREMENT Complete Revision: March 20, 1992 Page 1 of 4 A.: PURPOSE To provide instructions.for determining accurate and consistent control rod drop times.

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS 1.. Complete a Pre-Startup Checklist prior to withdrawing rods _unless the. core loading is below 50% of critical mass.

2 .1 Rods shall'only_be withdrawn one at a time for the purpose of these' tests. .

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3. -The drop time for each rod-must be less than 600 msec.

If resd drop times exceed 600 msec, the rods shall be

. visually inspected for pitting and cracking. (Toch.

Spec.-3.2.3.)-

4. Rod drop times must be measured a) semiannually, b) when a-centrol assembly is moved to a new core position, c)-when a magnet assembly has been removed, and_d) after_ rod visual inspections. (Tech. Spec.

4.2.1.)

C. PROCEDlTRE Ecuinment Needed: . ,

Tektronix Model 2221 (nr_ equivalent) oscilloscope  ;

1. '

-2.  : Microphone

3. Auxiliary scram test trigger 4~..- Duct tape  ;
5. Interconnecting wiring Steps: l
1. _ Tape microphone onto one of the rod shrouds.

w h {hJ h Writteri~By. arl Ba: 'n Approved By: Albert Bolon

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      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 813 TITLE: ROD DROP TIME MEASUREMENT Complete Revision: March 20, 1992 Page 2 of 4

2. Connect microphone to Channel 1 input jack of the scope.
3. Remove the auxiliary scram circuit jumper wire connecting TBS-31 and TB5-32 (located on back panet af console).
4. Connect the auxiliary scram test trigger between TB5- -

31, TB5-32 and the external trigger jack of the scope.

5. Perform reactor Pre-Startup Checklist as required.

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6. Determine the drop current for each rod by slowing reducing magnet current until rod drops. Record the drop currents on the Rod Drop Measurement Form.

Insert all rod drives to 0.0 inches.

8. Set the magnet current for each magnet about 20 mamps above drop current (not to exceed 80 namps).
9. Recommended scope control set;ings are as follows:
a. Store Display Controls:

(1) Press " STORE /NON-STORE" button in to put scope in store mode. Make sure " SAVED is n,Qt displayed on upper right hand carner of screen. If it is, push SAVE/ COUNT button.

(2) Press the SGLSWP to activate the green

" ready" light.

b. Input Controls:

(1) Volts /Div to 50 mV-(2) DC-GND-AC Switch to DC (4) Ch 1/BOTH/Ch 2 switch to Ch 1 position

c. SEC/DIV Settings:

(1) X 10/ CAL in-ar knob in and fully c]ockwise (2) Time /Div (outer knob) to 50 ms

d. Trigger Level Operation: Press button on auxiliary scram test unit. Single shot should fire and cause a trace across oscilloscope.

M (, % bW Written By: Carl Barton Approved By: Albert Bolon 3

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      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

sop: 813. . _ _

TITLE: ROD DROP TIME MEASUREMENT

' Complete Revision: March 20, 1992 Page 3 of 4

10. Measure _the rod drop times as follows:

a .; -Fully withdraw (24 inches) one rod. Verify that the oscilloscope is in the store tode (STORE /NON-STORE button depressed and green " ready" light is on).

b. Firmly press _the auxiliary scram switch. (Sweep

-should start and the sound of rod hitting bottom should be-heard.

c. Press "Save" button on oscilloscope, d; Adjust urser to beginning of. sweep (left hand side) 3 high point of blip on trace.
e. Recorc .he drop tinc displayed in upper right hand corner,af-screen.
f. Clear data by. depressing the "SAVE" button on the oscilloscope.

11'. Repeat step 10 for other rods as necessary.

- 12 . Shut down or secure the reactor and remove all rod drop equipment.

, 13. Complete a Reactor Secured Checklist, if appropriate.

14. 1 Reconnect the jumper wire between TBS-31 and TB5-32.
15. List all data Eon the Rod Time Measurement Form alad

' forward to the-Reactor Manager for review.

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x A k0 i WrittenLBy: Carl Barton Approved By: Alber". Bolon ll L

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      • -UMR REACTOR STANDARD OPERATING PROCEDURES ***

-SOP: 813 .

TITLE: ROD DROP TIME MEASUREMENT Complete Revision: March 20, 1992 Page 4 of 4 ROD DROP TIME MEASUREMENT FORM DESCRIPTION ROD 1 ROD 2 ROD 3

1. Drop Current _
2. Current Used for. Drop Time Measurement
3. Rod Drop Time _ _ _ _

Performed By: Date:

Comments:

P Reactor Manager Review:

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Written By: Carl Barton Approved By: Albert Bolon

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