ML20073G194
| ML20073G194 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 12/31/1990 |
| From: | Freeman D MISSOURI, UNIV. OF, ROLLA, MO |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9105030169 | |
| Download: ML20073G194 (80) | |
Text
&
l I *; '
Nuclear Reactor Facihty II UNIVERSITY OF MISSOURI ROLLA Nuclear Reactor Roha. MO 05401-0249 Telephone (314) 341 4236 I
April 30, 1991 Director Office of Nuclear Reactor Regulations l
U.S. Nuclear Regulatory Commission Mail Stop 10-D-21 l Washington, D.C. 20555 I l
Dear Sir:
1 Please find anclosed the Annual Progress Report 1990-91 for the University of Missouri-Rolla Reactor Facility (License R-79).
This report is being filed under- the reporting rerjuirements of our Technical Specifications. A copy of this report is also i being snnt to our Project Manager and Regional Administrator. l Sincerely, f;! Ab David W. Freeman Reactor Manager DWF/lp Enclosure xc: Alexander Adams, Jr., 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) l Mr. Ray Bono, Director,.Envir. Health / Risk Management (UMR)
Dr. Robert L. Davis, Dean, School of Engineering (UMR) i Mr. Bruce Ernst, American Nuclear Insurers Dr.-Nord Gale, Chairman, Radiation Safety Committee (UMR) ~
Dr. A. Glen Haddock, Interim Dean, College of Arts and Science-(UMR) l Dr. Martin'Jischke, Chancellor (UMR) '
i
-American Noclear Insurers, c/o Librarian lf l
l e i a~* cx oseeew[5' PDR
_ , _ _ o I l
Progress Report 1990-91 l
University of Missouri-Rolla Nuclear Reactor Facility l i
4 i
4,Of MISSoy4 4 ..
n 8 ,,
e, _h.a e >w N "
&O
&s k a - c(y
( 3 O. ,
O OO CDO 0000a0000 000000000 W J MEACTOB i l
1 l !
L a
J
.e
+
g 1 4
i.
I i
i PROGRESS REPORT
!- FOR THE ,
3-1 1 UNIVERSITY OF MISSOURI-ROLLA #
J NUCLEAR REACTOR = FACILITY ,
i
- ..i
~L I.
j- 3 4.
APRIL 1,>1990 TO MARCH 31,.1991 j
- 1 i
I i
Submitted to . .
The U.S'. Nuclear. Regulatory; Commission- '
and .
The UniversityLof Missouri-Rol~1a- <
j..
i 4 l
,- Albert E.: Bolonj Director David-W. Freaman,1 Manager- '
l Nuclear Reactor = Faci ~lity .
University ofLMissouri-Rolla. 1
].
Rolla,-l Missouri- .
.s
.65401 ?
l-g
- _ t t
i )
o
(. 2
- . 1
- l. ?
! s 4
', - , - . . ..a...... ...--,-;.:.,,.-
z..- . -, ; :. .~,...: . 2
l 1
SUMMARY
During the 1990-91 reporting period the University of Mis-
- 9 souri-Rolla Reactor (UMRR) was in use for 387 hours0.00448 days <br />0.108 hours <br />6.398809e-4 weeks <br />1.472535e-4 months <br />. The major part of this time, 71%, was used for class instruction and train-ing purposes. About 15% of the reactor time was used for research and irradiation service and 6% was needed for mainte-nance runs.
The UMRR operated safely and efficiently over the past year.
No significant safety related incidents or personnel exposures occurred.
There were 25 undergraduate and graduate students enrolled for course work at the reactor, not including the NE 105 students and the UMC graduate students. This committed the facility to 90 student credit-hours of classes. The reactor was visited by about 2641 visitors during the past year. There were 500 partic-ipants in the Reactor Sharing Program this year involved in vari-ous reactor projects. The facility is reimbursed for this pro-gram under a grant awarded by the U.S. Department of Energy.
The reactor produced about 11.6 MW hours of energy using approximately 0.5 gram of uranium. A total of 210 samples have been irradiated at the reactor with most of them being analyzed )
in the Reactor Counting Laboratory.
A one-week training program for reactor operator trainees of a Midwest utility was conducted during this reporting' period.
The reimbursement helped to defray facility costs and also helped to improve research and instructional capabilities.
l 11 TABLE OF CONTENTS Page Summary. . . . . . . . . . . . . . . . . . . . . . . . i List of Tables 1.0 Introduction . . . . . . . . . . .. . . . . . 1 1.1 Background. . . . . . . . . . . . . . . 1 0
1.2 Facility Status . . . . . . . . . . . . 2 2.0 Reactor Staff and Personnel. . . . . . . . . 4 2.1 Reactor Staff . . . . . . . = . . . . . . 4 2.2 Licensed operators. . . . . . .. . . . 4 2.3 Radiation Safety Committee, . .. . . . 5 2.4 Health Physics. . . . . . . . . . . . . 6 3.0 Improvements . . . . . . . . . . . . . . . . 7 4.0 Reactor Operations . . . . . . . . . . . . . 9 5.0 Public Relations . . . . . . . . . . . . . . 22 6.0 Educational Utilization. . . . - . . . . . . . 24 7.0 Reactor Health Physics Activities. . . . . .. 27 I
8.0 Plans . . . . . . . . .. . . . . . . . . . . 30 Appendix A. Standard Operating Procedures Changed During the Past Year. . . . . . . 32
[
t l
i h
111 LIST OF TABLES Page Table 1. UMRR Core Configuration and Rack Storage Form . . . 10 Table 2. Facility Use Other Than the Reactor . . . . . . . . 11 Table 3. Reactor Utilization . . . . . . . . . . . . . . . . 11 Table 4. Rundowns. . . . . . . . . . . . . . . . . . . . . . 12 Table 5. Scrams. . . . . . . . . . . . . . . . . . . . . .. . 14 Table 6. Maintenance . . . . . . . . . . . . . . . . . . . . . 15 Table 7. Core Loading and Unloading. . . . . . . . . . . . . 20 Table 8. Core Technical Data . . . . . . . . . . . . . . . . 21 Table 9. Public Relations Program. . . . . . . . . . . . . . 22 Table 10. Reactor Sharing Program . . . . . . . . . . . . . . 25 4
4 k
i
?
Y 1
1.0 Introduction I
j This progress report covers activities et the University of i
{. Missouri-Rolla Reactor (UMRR) Facility for the period April 1, ,
! 1990 to March 31, 1991. It is prepared in accordance with the-j requirements of 10 CFR Part 50.71 and Technical Specifications L
6.6.1 issued under License R-79.
i . ,
j The reactor is operated as a university.' facility available to the faculty and students of the various departments of the .i j university for their educationalfand research programs.- Several i t-other universities, colleges, and=high schools have madeiuse of the facility during this reporting; period. The= facility is.also
- made.available for the purpose of training. reactor personnel of l the nuclear industry and electric utilities. Trace element
~
f analysis using neutron activation is also provided'at the i
j facility.
s i
il - -1,1- Backcround Information c-
.The-University of Missouri-Rolla~ Reactors (UMRR) i . .
Facility wasLconstructed-in11960-1961 and attained--
criticality--on December 9th, 1961. The UMRR:was1the:first-
- -operating 1 nuclear reactorLin.the state
- of-Missouri.: The +
b reactorndesign is. based:on the Bulk 1 Shielding ReactorLat' Oak i Ridge National-LaboratoryL .The initialflicensed power 1wasl o
- 10-kW-which was-subsequently upgradedi to-2001kWfin;1966.
The.reactornis a-pool-typefreactor cooled;by natural I#
, ,,,.-4 4 - , - . ........;-., ...-;-- - , . , , _ -
4 f
a 2 ;
- convection flow. The fuel is MTR plate-type fuel. The' ,
1
- j. standard fuel element consists of ten curved plates = fueled ~
i
! with high-enriched uranium.
r
,_ The facility is equipped with several' experimental i
- facilities including a beam port,. thermal-column, pneumatic-i j rabbit system-and several sample irradiation facilities.
! Additionally,-the facility is equipped with a counting t i laboratory with gamma and alpha spectroscopy capabilities. .
! The gamma spectroscopy system includes a high purity =
! germanium, germanium-lithium,-and twoLsodium-iodide detectors, associated electronics,'and state-of-the-art I l spectrum analysis software. The' alpha-spectroscopy system i
consists of a surface barrier _ detector and data acquisition = ;
equipment.
i 1.2 Facility Status 4
) The UMRR operated safely-and efficiently.over:the past i
year. No significant safety relatedsincidents or personnel l
exposurec occurred.
j Major progress has~been made inlthe LEU conversionE d I .
l process. NRC concernsJregarding our proposed' LEU' Safety Analysis ReportJand Technical Specifications have'been-j addressed. On' March- 5,11991ENRC issued =thetorder modifying-i
- our;-license to-convert ?to
- LEU,. effective;the?dateiof..receiptL of thefLEU fuel.
i
~
(
Conversations with.the fuelisuppliers indicate.that we-may' receive " dummy"E('unfueled)1 elements-for testingzthis A i
J
> _ . - . . . _ - _ . . - . ~ . _ , . . _ . . . . . _ . ~ . . .. - _ . . . > . .. .-_- .
3 summer. We plan to extensively test the dummies to assure dimensional compatibility with our control rods and drives, gridplate, and experimental facilities.
We have received preliminary word that the new LEU fuel may be available in the Summer of 1991. We plan to prepare a detailed core loading and start-up testing plan for the new fuel.
We received a grant from DOE to aid in purchasing new i
nuclear instrumentation for the UMRR console. The cost of the upgrade is being shared directly from reactor funds. We plan to !
use these funds to upgrade our Start-up, Linear, and Intermediate Channel instrumentation.
The reactor staff has continued to review the operation of
-the Reactor Facility in an effort to improve th e safety and effi-ciency of its operation and to provide conditions conducive to its utilization by students and faculty from this and other uni-versities. The following sections of this report are intended to provide a brief description of the various aspects.of the oper-ation of this facility, including its utilization'for education and research, i
r
-v
1 i
4
, 2.0 Reactor Staff and-Personnel 2.1 Reactor Staff 1
i Hame Title 1 1 .
2 ..l i Albert E. Bolon Director l
- -t David Freeman" l Reactor Manager [
! Carl Barton Senior-Electronic Technician.
Juls' Williams Lab Mechanic-
! Francis Jones Reactor-Maintenance Engineer [
Linda' Pierce Senior Secretary 1
?
a 2.2 Licensed Operators Name License ;
l Albert E. Bolon Senior-Operator t
Carl Barton Senior Operator David Freeman *' Senior Operator -
f ' Francis Jones Senior Operator Matt McLaughlin Reactor Operator '
- 1) Effective-:Mayil, 1990:
L2 ) Effective February 21,:-1991 l
j i.
(. -
.i
5 20 3 Radiation Safety Committeo The Radiation Safety Committee is required to meet quarterly. The committee met on 6/5/90, 9/5/90, 12/7/90 and 2/20/91 during the reporting period. The committee members are listed below:
Name Department Dr. Nord L. Gale (chairman) Life Sciences Mr. Ray Bono.(secretary, ex officio) Environmental Health and Risk Management Dr. Ernst Bolter Geolcgy 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, non-voting) Nuclear Reactor
6 3.4 Health Physics Health Physics support is provided through the Environmental l Health and Risk Management Department and is organizationally independent of the Reactor Facility operations group. Health l Physics personnel are listed below:
Namn Title Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Director, Environmental Health and Risk Management Miss Kathy Stone') Student Assistant (HP)
Mr. Mark Sautman" Student Assistant (HP)
Mr. Charles Hooper" Student Assistant (HP)
Miss Danika Jackson" Student Assistant (HP) i Mr. Cary Lieurance Student Assistant (HP)
- 1) terminated effective May, 1990
- 2) terminated effective August, 1990
- 3) employed effective August, 1990
- 4) employed effective June, 1990
7 3.0 Improvements A continuous effort is made to enhance safety,_ availability and reliability of the facility. In that effort the following improvements have been made at the facility during the reporting period:
- 1) An emergency shower and eyewash station have been installed adjacent to the demineralizer system on the' intermediate level of the basement.
- 2) A fiber-optics cable has been installed linking the UMRR computers to the University network,-allowing.
access to several mainframe and workstation systems.
- 3) Several codes have been made operational on the facilities AT&T 6386 Workstation including 2DB-UM, LEOPARD, ONETRAN, ORIGEN2, QADCG,-and DSNP.
- 4) A database management code has been developed with l DBASE-III to track reactor usage and burnup by course number, run type, and experimental facility.. This code is being used to generate data for the annual report.
- 5) An IBM PS-2 and a riew copier have been purchased to support administrative wordprocessing and recordkeeping.
- 6) The beamport facility haslbeen reopened-for use and preliminary beam characterization studies and radiographic. imaging have been accomplished.:
F'
+
i 8
,1-l- 7) Totalizers have been installed on the basement sumpito j
track the water volume pumped from the' sump to the"
, -sewer system.
L -
4
- 8) A. security mirror has been: installed-in the front 1
- office to provide a better view of.the' entrance door
]
i area. :
i 9) New' nuclear instrumentation'to replace our.. Start-up,.
- Linear, and Intermedi~ ate Channels wil'1 soon be 1
l purchased.
- 10) The floors in the Reactor-bay, stairways, intermediate j j basement, and ground floor have all.been painted inian (j
. . 4 4
effort to maintain'high standards of' housekeeping.-
i t
)
e %
e i
l p -i i-
- r. ?
n u
n 4
l l
i: -
J. c
-l 1 t
u '
1 2 i
. . 4 -s,. . . . . . . ,_m . 4 --. . .~ s. .. ..a~ .._...w, - . , - ~ . . - _ , _ .,
. .. . _ _ . . . . _ - _. . - .. ~ . -..... ~ .. - . . _ - . . -
s i
I 9
i 4.0 Reactor Operations L
i Core designation 67:has been used'throughout this reporting t
~
!' .[
period. The "W" mode core (completely water, reflected).was used l
for normal reactor operations. The "T" mode (with the core f
._ positioned near the' graphite thermal column) is used for various - !
experiments including beam port and thermal column experiments.
- The excess reactivity was measured for the 67 W-core -
configuration in cold, clean conditions.- In day-to-day. operation-
- the excess' reactivity is quite often' lower duet.to' higher-pool- -
i temperatures.
Information about the-reactor operation during this ,
, reporting period'is presented in Tables'l'through 8. 4 a
i i
'I '
4 f
t f
(-
. , ,q l
a .
4 d
d
-1 i t h, i 4
- -r
- . , _ - . . . s , - . . .- . - - . . ,-_---_....._r. . . , , , + - . . , , , , - , . - ..,.
10 fable 1. UKERCoreConfigurationandRackStorageForn DATE 31 March, 1990 LOADING NUXBER 67T or 67W*
R1 R2 R3 R4 R5 R6 R7 R8 R9 R10 R11 R12 R13 R14 R15 l l ! l I I I ! ! IHF-1 l !F-13 IF-20 IF-22 l l RACK STORAGE FACILITY l I I I ! ! l ! ! I IF-2IF-5iF-3!F-18lF-21l R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 R29 R30 l
A KEY TO PREFIXES-B S F - Standard Elements C - Ontrol Elements C HR-1 R-14 F-1 C-4 HF - Half Front Element HR - Half Rear Element-D F-8 C-1 F-16 F-9 F-4 F-10 S - Source Holder l .
l E ___. F-6 C-2 F-19 C-3 F-12 F-11 F BE' F-17 F-15 F-7
- CRT l
1 2 3 4 5 6 7 8 9 BRIDGE SIDE CHRR CORE STATUS Other BRT - Bare Rabbit Tube CRT-CadmiumRabbitTube l .
- Tdesignatesthethermalcolumn-reflectedmode,-
andWdesignatesthewater-reflectednode.
l l
I l
l
11 Table 2. Facility Use Other-Than The Reactor Facility Hours Bare Rabbit Tube 24 Beam Port 2 l Thermal Column 1 Total 27 f
Table 3. Reactor Utilization
- 1. Reactor use 387 hr
- a. Research and irradiation runs 58 hr
- b. Instruction runs ~218 hr
- c. Maintenance runs 25 hr i d. Training 58 hr i 2. Time at power 180 hr f 3. Energy generated 11584 kw-hr l l l
- 4. Total number of samples 210 l
- 5. Sample hours 32 hr
\
l
-i
- 6. U-235 burned 0.5.g l l l l
! 7. U-235 burned and converted 0.6 g U l\
l l
l l
l l
L- l
12 Table 4. Rundowns Data Capse and Corrective Action 04/11/90 120% Demand - Range Switch button on Linear popped out while switching scales. Trainee given additional instructions.
04/11/90 120% Demand - Range switch button on Linear popped out. No corrective action necessary.
, 04/11/90 120% Demand - Cause and corrective action same as above.
I 04/25/90 120% Demand - Cause and corrective action same as above.
05/31/90 120% Demand - Operator down scaled on linear instead of up scale. Cautioned and instructed trainee about changing scales.
09/13/90 120% Demand - Button on Linear popped out. No corrective action necessary, f
09/25/90 120% Full Power - Set point on Log N recorder set too low. Readjusted set point.
09/26/90 120% Demand - Range switch on picoammeter-popped out. No corrective action necessary.
10/24/90 <15 see Period - Happened while moving Void Tube during experiment. Reactor was at 18" (subcritical). Experimenter cautioned and
! instructed on moving the Void Tube, 10/31/90 High Radiation - Slightly elevated radiation levels-at demineralizer caused by extended high power run. No corrective-action required.
11/08/90 120% Demand - Operator pushed button on Linear.
operator cautioned and instructed on changing scales.
11/27/90 High Radiation - Slightly elevated radiation levels at demineralizer caused by extended high power run. No corrective action required.
. 01/23/91 120% Demand - Range Switch on. Linear popped out.
l No corrective action necessary.
l I
13 Rundowns (cont.
02/19/91 120% Demand - Range Switch on Linear popped out.
Student given additional instruction.
03/27/91 120% Demand - Range Switch on Linear popped out while changing scales. No corrective action necessary.
i l
l i
l l
l i
l
_ . - _ . _ . _ _ . _ . _ . . - . . _ - _ _ _ _ . . . . . . _ _ _ . _ . _ _ . . _ . - .. _ . . ~ . . _ _ - _ _ . __ _ _ __ _ .____.
1' i
! 14 .
I j Table 5. Scrans 4
Dat;gt Cause i
04/09/90
- Manual Scram - Training.
t 04/17/90 Manual Scram - Intentional for experiment. !
04/17/90 Manual Scram- Intentional for experiment. l 04/20/90' Manual Scram - Intentional for experiment. -i i
04/20/90 Manual Scram - Intentional for experiment.
04/23/90 Manual Scram - Intentional-for experiment.
04/25/90 Manual' Scram - Intentional for-experiment.
04/26/90 Manual Scram - Intentional'for experiment.
04/26/90 Manual Scram - Intentional for experiment.
- 05/31/90 Manual Scram - Training.
12/7/90 150% Full Power Scram - Reactor was at 52% of i
- 2 W scale. Appeared to be spurious. trip.- System- 4 checked and returned to service.- 1 1
f 01/23/91 Manual Scram - Training.
02/14/91 150% Full Power Scram'--: Occurred at reactor-power-l of less.than 200 kW. ScramLthought_to be=
l_ spurious. -Reactor restarted.:
I 02/14/91- 150% Full Power Scram - Occurred at reactor power of less than 200 kW.- Scram Setpoint-was' --
inadvertently set-too low during_ maintenance.
j- Scram Setpoint--reset. '
!; -p l~
1
-}
i:
.J t
.. ; u ,_.;.. _. . __
i i
t l 15-Teble 6. Maintenance l' (Other than associated with Rundown, Scrams, and Semi-Annuals)-
t L Date: 4/27/90 t l Problem: Rod i dropping.-
- - Corrective Action
- Removed Magnet No. 1 and repaired.
1 4/28/90 Date:
, Problem: Continued from 4/27/90. _ _
]' Corrective Action: Replaced Magnet.No. 1. Completed Rod Drop t Time Test.
s Date: 4/30/90
- Problem: " Reactor On" Light in Foyer.not on when Reactor'is' -
operating. '
- Corrective Action: Replaced.both bulbs in "ReactorfOn" Light. _;
l
! Date: 5/3/90
[ -Problem: Start-up channel not indicating an increase:in-count
[ rate while pulling rods.
Checked all connections
- Corrective Action: Reactor shutdown.
- on Start-up channel ~. System check. good. Reactor i started up with no other problems indicated.
. Date: 5/27/90
!_ Problem: N/A t l Corrective Action: Semi-Annuals started- .
I Date: 5/29/90 Problem: Routine visual _ inspection-of_ rods.
l Corrective Action: -. Unloaded reactor core. Rodsfinspected.
l Date: 5/30/90
! Problem: Continued from 5/29/90., . .
Corrective Action:- Reinstalled magn'ets and completed Rod. Drop
[,
- . Times. ,,
l Date: -5/31/90 ..
i: Problem: ' Continued from 5/29/90.
-Corrective-Action: __ Reloaded reactor core.
! Date: 5/15/90 _ .
Problem:--' Cadmium Rabbit Tube removedLfrom_ core.to repairfwater leak.
l Corrective Action: None'- Rabbit hungLin pool for decay.1 9 l
3 l
l t
l'
.- -. - . . . . , , _ - ; ,- /- - - - .- ,, . ,,-
. - .a.,
J i.
1 1-j 16 f- Table 6. Maintenance (cont.)
l Date: 7/31/90 _ . .
Semi-Annual Power Calibration indicates Log N_ detector 1
Problem:
i position needs adjustment.
l Corrective Action: Adjusted Log N' detector-for proper power j indication.
\
l Date: 8/2/90 t Problem: . Vent Fan No. 1 previously removed for. maintenance by
} Physical Facilities. (Bearings) i Corrective Action: Vent Fan No. 1 replaced after bearings were replaced.1Mr Physical Facilities.
- Date: 8/13/90 ;
Checking temperature recorders as part of-scheduled .
j 4
Problem:
maintenance. 1
- Corrective Action
- None required. I
^
l c Date: 8/13/90 i Problem: N/A j Corrective Action: Semi-Annuals completed.
l l Date: 8/13/90 i Problem: Log N level meter sticking.
Corrective Action: Replaced meter.
I Date: 8/16/90 l Problem: Power-difficult to read'on new meter, j Corrective Action: Log N Amplifier adjusted for'easierireading
! on new meter.
8/23/90 Date: _
Problem: Water leak in Cadmium RabbitLTube. . . . . _ .
Corrective Action:- . Repaired'and; reinstalled Cadmium Rabbit Tube. .
in core. !
l- Date: 8/23/90:
l . Problem: Safety-Channel reading low.
Corrective = Action: UICs adjusted for proper output.
lf .Date: 8/31/90. _
i Problem: Magnet 1Contact Light on No. 2 notEoperating' . . .
[
E Corrective Action: Replaced pin-in. connector.-' Reinstalled l_ -
magnet and checked Rod Drop Times. .
l
.Date: 8/31/90 ._ . , . . _ -y Problem: Removed Bare. Rabbit: Tube-to' extend connectors above1 i water.toLpreclude potential future leaks.- --
d Corrective Action:' Maintenance delayed. R l
[
,- 'E[~ ve , -~~v v ,, ,r # , -n, A mi- v.--y , ' , . . e-., . -- y & w-
- .- . - - - . . _ . - _ . ~ . - - . - - . _ ~ . . . - - . ~ . - .. --. . . - _ - _ .
i i
'17; i
F TQble 6. Maintenance (cont.)
a l- Date: 9/4/90
$ Problem: Continued from 8/31/90.- -
3
{ Corrective Action: Repaired Bare' Rabbit Tube reinstalled'in l_ core. 4 Date: 9/7/90 b Problem: Water found in Cadmium Rabbit Tube. ^
j Corrective Action: ' Removed,-repaired and reinserted Bare Rabbit
].
after maintenance. j 1
l Date: . 9/19/90 .
cj l Problem: Water.found in Cadmium. Rabbit' Tube. _
i -Corrective Action: Removed Cadmium Rabbit Tube from-core'.
1 Date: 9/20/90 _ _
[ Problem: Safety Channels not indicating proper power.- i
[ Corrective Action: Adjusted UICs for-correctLreadings.
, Date: 9/24/90 _
Problem: Water ~found in Cadmium' Rabbit.. -
l Corrective: Action: Reinserted Cadmium Rabbit-Tube afterfrepair
- of lower swage lock.
Date: 10/10/90 r
-Problem: No Magnet' Contact Light on No. 1 Magnet. _
1 Corrective _ Action: Repaired Contact Light.and replaced Magnet: 4 i- No. 1. 4 Date: 10/16/90 l
[ Problem: PerformingLRod Drop Time._ _
i Corrective Action: Rod Drop Time Test, completed, h Date: 10/17/90.
Problem: Removed Magnet No. 3.
- Corrective Action
- - Replaced:No. 3 Magnet 1and performed' Rod (Drop 1 '
I Time: test. -'
4 Date: 10/19/90 '{
- Problem: . ' Removed. Magnet No.L3'. -i" Corrective Action: Replaced Magnet with spare.,,PerformedLRod:
Drop Time test..
l 'Date: 10/31/90 _ . ,
p Problem:. PowercChambers need-position adjustment. .
lCorrectiveuAction: Adjusted _ chambers =for correctJreading.1-i f
?
i
$ s l
_ . . _ _ - . _ _ _, . . _ . . ---._.. . .. _ _ . . . . - . m.
4
- I a
18 8
I Table 6. Maintenance (cont.)- _
l l Date: 11/6/90
{ Problem: Copper wire experiment stuck in Fuel Element F-8 in '
i Core Position D-3.-
i Corrective Action: Removed Fuel Element from Position-D-3.
! Removed copper wire 1 experiment and reinserted-element.
i Date:. 11/12/90 i Problem: Bridge RAM not showing proper indication.
l Corrective Action: Removed Bridge RAM module-for maintenance.. i i
l Date: 11/12/90
- Problem: Demineralizer RAM not indicating correctly..
l _ Corrective Action: Removed--Demineralizer RAM module for-maintenance.
! Date: 11/20/90 .
Continued _from 11/12/90.
Problem: _
{ Corrective Action: Repaired and reinstalled ~ Bridge RAM module.
[ Date: 11/20/90 i Problem: Continued from 11/12/90 Corrective Action: Repaired and reinstalled Demineralizer module. <
f a
! Date: 11/20/90
! Problem: N/A . ,
Corrective Action:--- Recalibrated. Bridge'and_Demineralizer- ')
! modules.-
i Date: 12/14/90.
- Problem
- N/A
, Corrective Action: Semi-Annuals started. '
i l'
Date: 12/20/90-Problem: N/A- '
Corrective Action: Semi-Annuals completed.
- Date
- 1/14/91 L Problem: Semi'-Annual Power 1 Calibration-
[ Corrective' Action: Adjusted-Linear Channel CIC for proper- ,!
, indication.' i g
Date: _ -
1/28/91' '
[
L Problem: - Routine 1rodsdrop-time 1 test.1 -]
l CorrectiveLAction:-_ Completed rod drop time test. .i Date: _ 2/21/91. .
- Problem:- Safety Channel indicated high.-
Corrective Action:'JSafety. Channel repaired.
\
l h
. , , , . . . . - , ,.x,- , _ -, .. , . , . _ . . . 1., - i...._ - (
19 TQble 6. Maintenance (cont.)
Date: 2/22/91
, Problem: Continuation from 2/21/91.
Corrective Action: Repaired Safety Channel and adjusted SCRAM point.
Date: 2/25/91 Problem: <5 Second Period.
Corrective Action: Re-Adjusted Trip Point to 7 seconds for extra margin of safety.
Date: 3/20/91 Problem: Basement experiment room RAM meter sticking.
Corrective Action: Removed meter, checked and reinstalled meter.
Recalibrated RAM.
1 i
-20 Table 7. Core Loading and Unloading i'
I Date l l
05/29/90 Unload (67W to suberit) for control rod 4 inspection. I 05/31/90 Reload (subcrit to 67W) to return to previous con-figuration.
l 11/06/90 Removed Fuel Element F-8 to unload copper wire experiment.
6 4
e
l 21 ;
Table 8. Core Technical Data 4 l l
Average Therral Flux 1. 6X10" n/cm*-sec at 200 kW Maximum Thermal Flux 2. 8X10" n/cm*-sec at 200 kW
- 1. 6X10" n/cm*-sec at 200 kW Average Epithermal Flux Worth of Thermal Column 0.46% A k/k Worth of Bear Port not detectable Rod Worths (in "T" mode):
' Rod 1: 2.63% Ak/k (4/16/79)
Rod 2: 2.65% Ak/k (4/16/79)
Rod 3: 3.36% Ak/k (4/16/79)
Reg Rod: 0.34% Ak/k (9/14/89)
Excess Reactivity (in "W" mode): 0.6% Ak/k Shutdown Margin (in "W" mode)*: 4.7% Ak/k l
r i
i i
l
" Rod 3 and Reg Rod not taken into account.
l 22 5.0 Public Relations The reactor staff continues to help educate the public about applications of nuclear science. Over 2640 persons toured the facility during this reporting period. Tour groups are usually given a brief orientation and/or demonstration by a member of the reactor staff.
Table 9 lists some of the major occasions or groups and number of visitors for each event.
Table 9. Public Relations Program DATE PARTICIPANTS NUMBER _
04/28/90 Spring Open House 92 05/01/90 Cub Scouts, Ron Olson 6 04/04/90 UMR Physics 107, Dr. Sparlin 62 05/15/90 Cuba 6th Grade 60 05/17/90 UMR Registrar and Admission Offices 13 05/22/90 Rolla Vo-Tech Business Class 16 06/08/90 Freshman Orientation Parents 8 06/11/90 Jackling Institute 41 06/15/90 Fundamentals of Engineering 77 l 06/18/90 Jackling Institute 37 06/10/90 Doe Run Company 34 06/22/90 Freshman Engineering 9-06/22/90 Beaumont High School 8
! 06/25/90 Jackling Institute 46 07/06/90 Boys Town of St. James 13 07/12/90 First Baptist Church Youth 'Rolla 7
l 23 DATE PARTICIPANTS NUMBER 07/13/90 Summer Open House 66 07/17/90 Concordia Lutheran Church -
56 08/09/90 Fundamentals of Engineering 97 09/25/90 UMR Introduction to Physics, Dr. Peacher 25 10/19/90 Florissant Senior Citizens 31 ,
10/20/90 UM Rolla Day open House 254 10/25/30 Society of Women Engineers 8 11/01/90 St. Louis Public Schools - 8th Grade 23
- 11/03/90 UMR Parents Day Tours 244 11/16/90 UMR ME 229 24 12/04/90 UMR NE 105, Dr. Mueller 15 12/07/90 UMR Physics 107 62 02/14/91 Raymondville 7 and 8 Grade 30 02/15/91 Rolla Middle School 42 02/19/91 St. Louis 8th Grade 12 02/23/91 Math Counts 8 03/28/91 Freshman Engineering 90 i TOTAL 1606 i
l
.__ _ _ _ _ _ - . . . _ _ _ _ _ _ . . _ - _ . . - _ _ _ . _ . _ . _ . . ~ . _ . . _ . . - . . . _ _ _ . _ . _ . _ .
1 i
s
.d 1 i 1 24 1
j 6.0 Education Utilization '
i 4
l l
Twenty-five UMR students, graduates and undergraduates, have l participated in classes at the facility, utilizing 40 stu-j dent-semester hours of allocated time. Additionally, students i
from several universities, colleges and high schools have used l the facility.
4 The following~is a list of scheduled classes at-the facility i along with associated reactor usage for this reporting period. ;
i
- ' Credit Reactor l Course Semester Title Hours Students Hours i
4 NE 105 Fall, 90 Funaamentals of Nuclear 2 14 13.7 [
Engineering i
NE 300 Fall, 90- Special Problems- 1 2 1.9
& Winter, 91 r l
NE 304 Fall, 90 Reactor Laboratory I 2. 8 60.2 i
l NE 306 Fall, 90 Reactor Operations 1- 8' .115 i & Winter, 91 f
l NE 308 Winter, 91 Reactor Laboratory II -2 7 26.8 l
NE 404 Winter, 91 UMC 2 11- .4: .;
{ The Reactor Sharing Program, funded by-the Department of !
- Energy, was established for colleges and universities which do -
not own a nuclear reactor. Additionally, high-schools are.
, - allowed to. participate. About 500 students and their' instructors- l l -. participated in this1 program. Table 10. lists those' schools;or~ t I
- similar groups;that were involved in this year's program.
i- 3 9 . .
1 me, e n p ,, e, .n 4,s a - Me
- w.ee.,,++ - ,,,-g< e-,,g +vv-- -ng r-yv-, w--,e- g e, , ~~ e we s w - e .e n- s e n- + , r+-n,--m< -
~
t 1
25 Table 10. Reactor Sharing Program 1 ._
DATE PARTICIPARTS NUMBER 04/04/90 Hollister High School 25 04/05/90 Eminence High School 21 04/17/90 Rolla Vo-Tech Radiography, Rita Montgomery, 11 Instructor 04/18/90 Benton County High School, Cole Camp, John 39 Scde, Instructor 04/20/90 Potosi Gifted 8th Grade, Alan Ziegler, 10 Instructor 04/23/90 John F. Hodge High School, St. James, Jim 16 Jenkins, Instructor 04/24/90 Sullivan High School, Marcene Abel, Instructor 15 04/25/90 Vienna High School, Harvey Richards, Instructor 30 04/26/90 East Central College, Vera Luedde/Leroy Alt, 22
, Instructors 05/02/90 Rolla Vo-Tech Radiography, Rita Montgomery, 12 Instructor 05/14/90 West Plains High School, Jack Dillard, 44 Instructor 11/00/90 Kyle Mitchell, John F. Hodge High School, St. 1 James i 11/14/90 Whitfield High School, Tom Rodgers, Instructor 19 12/04/90 Parkway North High School, Jenny Shubert, 28 Instructor 12,'04/90 Van Buren High School, Daniel Freeman, 22 Instructor 12/06/90 SMSU, Springfield, Howard Petefish, Instructor 4 01/18/91 Sasha Scott, Eldon High School, Individual 1 Travis Thomason, Houston High School, 1 01/25/91 Individual 01/28/91 St. Charles Science Teachers 10-Angie Nicholson, Potosi High School, Individual 1 02/01/91 Stockton High School 6 02/14/91 02/14/91 Eureka High School 11 l
26 DATE PARTICIPANTS NUMBER 02/14/91 Springfield High Schools, Jon Feeney, 17 Coordinator 02/20/91 Linn Technical College, Jack Light, Instructor 20 02/22/91 Therese Luna, St. James High School, Individual 1
- 02/25/91 UMC Nuclear Engineering, Jay Kunze, Instructor 12 03/04/91 St. Charles West High School, Rebecca Teague, 18 Instructor 03/07/91 Hazelwood West High School, Gail Haynes, 14 Instructor 03/11/91 Washington High School, Rick Swentker, 43 Instructor 03/22/91 Stacy Dronnon, Potosi High School, Individual 1 03/25/91 Crocker High School, Donna Burrow, Instructor 25 TOTAL 500 i
l l
l l
. _ _ _ _ _ . _ _ _ . ~ . _ . . - . _ _ _ . . _ . . _ . _ _ _ _ _ . _ _ _ _ _ . . -__
1 l
l 27 7.0 Reactor Health Physics Activities
! The health physics activities at the UMR Reactor racility i
! consist primarily of radiation and contamination surveys, moni-i toring of personnel exposures, airborne activity, pool water
]
$ activity and waste disposal. Releases of all by-product material i ,
to authorized, licensed recipients are surveyed and recorded. In i l
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.
5 A. Routine Surveys Monthly radiction exposure surveys.of the facility. consist 4-l of direct-gamma and neutron measurements with the reactor at ,
i power. No unusual exposure rates were identified. Monthlyf i-surface contamination surveys consist of120 to 30: swipes. counted l separately for alpha, and beta / gamma activity. In 12 monthly l
l surveys, no significant contamination outside of contained work l
areas was found.
l l
B. 'By-Product Material Rel' ease Surveys l
There were no shipments of by-product material released.off-campus from the reactor. facility'during'this-reporting period.
?
- i. !
l 28 l
C. Routine Monitoring Twenty-eight reactor facility personnel and students involved with operations in the reactor facility are currently assigned film badges which are read twice each month for reactor
, staff and once a month for students. There are 4 area i
j beta-gamma / neutron badges assigned. Twenty-two campus personnel and students are assigned beta-gamma film badges, and frequently l
l TLD ring badges for materials and X-ray work-on campus. There are 21 monitor 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, i Visitors-are monitored with direct reading dosimeters. No f visitor received in excess of 5 mrem.
Airborne activity in the reactor facility is: monitored by a i ;
- fixed-filter. particulate continuous air monitor (CAM) located in l the reactor bay. Argon-41 is routinely detected.during
, operations. '
l .
l Pool water activity'is monitored monthly to ensure ~that'no.
l gross pool contamination nor fuel cladding rupture has occurred.
i Gross counts and spectra of long-lived gamma activity-are.com-pared'to1 previous-monthly counts. From April 1990fthrough March.
1991 sample concentrations averaged 1.05X10* pCi/ml.
?
4 8
, w, p-w -+ y--- r-v, ,,,,--...e ,.n, ,m.,,,m.-..,.,,rme e,,..++. nnw,. ,.nr , u , , . ,, : - y .w.~.w ,.a ,w,-,,c
i i i-
}
! 29 1
D. Magte 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 measured air activity at maximum reactor power. Dur-
- j. ing this period 171.06 millicuries were released into the air.
The released isotope was identified as Ar-41.
3 l Solid waste, including used' water filters, used resins and i
[ . contaminated paper is stored and/or transferred to the campus 1 1
l waste storage area for later shipment to a commercial _ burial I
site. Radioactive waste released to the sanitary sewer is pri-i i marily from regeneration of the ion-exchange column. During this i
i period 9 releases associated with resin. regeneration were 4
discharged to the sanitary sewer' totaling approximately 37,570 '
I gallons of water with a total gross activity of less than11.413L i
i mil 11 curies.
I 1
l
! E. Instrument Calibrations During this period, portable instruments'and area monitors 4 were calibrated twice.
m i i
5
$ 52' i F
~?
A
- 7
____:. ____.-__c.2._... _ ; -. ._ . . , . , , _ ...-,--_e. , _ _ , . d
9 30 8.0 Plans The reactor staff will be heavily involved in 4 major projects during the next reporting periodt 1) preparing for receipt of the LEU fuel, 2) procuring, testing and bringing on-i line the new reactor nuclear instrumentation, 3) preparing to ship HEU fuel offsite, and 4) solicitation of new reactor users to increase reactor utilization.
A. LEU Fuel ConversioD on March 5, 1991 we received the NRC order to modify our license to convert from HEU to LEU effective upon the date of receipt of the LEU fuel. Currently, we plan to receive " dummy" elements this summer and receive the LEU fuel sometime next summer.
When the dummy elements are received they will be rigorously tested to assure dimensional compatibility with our gridplate, control rods, and experimental facilities.
A detailed start-up testing plan will be prepared to cover loading and testing of the new LEU core.
B. Reactor Instrumentation voorade Efforts are currently underway to procure new nuclear instrumentation to replace our current Start-up, Linear, and i Intermediate instruments. This upgrade is partially i 1 supported under a grant from DOE.
l i
1 j 31 As instruments are procured, extensive review documentation will be established and appropriate approvals
- obtained. NRC will be notified of our intended changes in a timely fashion.
Detailed testing will be performed and extensive operational data will be collected prior to actually replacing the equipment.
I C. Shion_ent of HEU Puel Offsite Efforts will continue during the next reporting period to prepare for offsite shipment of our HEU fuel. We hope to maintain the HEU fuel for a period of about 1 year after discharge to allow for radioactive decay. Studies are currently underway to project the dose rates that will be associated with each element.
i 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. Reactor Utilization Increasing reactor utilization is a high priority at
, UMRR. Plans to increase our efforts in soliciting more on-
- campus and off-campus users are underway.- These plans include seminar presentations to-various departments on the UMR campus and to area universities an'd colleges.
Additionally, certain service oriented organizations will be solicited.
4
32
)
i s
1 i
! t J
1 4
4 4
1 APPENDIX A.
1 STANDARD OPERATING PROCEDURES i
CHANGED DURING THE PAST YEAR s
4 i.
d-E 1
1 1
i
, - , a
T' M 7,*,f i"!O$2"']i.'"?
) 0 )h
- U.4R REACTOR STAbDARD OPERATING PROCEDi2ES **w SOP: 100 TITLE: PREAMBLE Total Revision: September 12, 1990 Pap 1 of 1 l
A. Purpose The nurpose of this document is to set forth the procedures for --outine and emergency operations of the University of Mist u .. < slle. Reactor. The goal of these procedures is to asst:m m : the UMRR will be operated safely, presenting no ha zn "c' ta :. t public or to the operating staff, and second- l ari , f.r ', reactor equipment will be safeguarded. It is l
mandh % that all personnel involved with reactor operations be completely familiar with these procedures and that these ;
procedures be followed.
B. Precautions, Prerecuisites, or Limitations
- 1. These procedures are intended to reflect and implement Facility License Number R-79, as amended, and Title 10 ;
of the Code of Federal Regulations.
- 2. Only two copies of the SOPS are to be considered con- !
trolled copies. The controlled copies shall contain all of the approved procedures and will incorporate new or revised procedures as they are approved. The controlled copies should be retained in the office reception arca (Reactor Manager's Copy) and in the Control Room (Con-trol Room Copy). l.11 other copies of SOPS are to be considered complimentary only and shall not be used for facility evolutions.
, 3. The SOPS shall be reviewed annually by either the Reac- !
, tor Manager, Reactor Director, or a licensed operator. !
Identified weaknesses, inadequacies, or recommendations i for improvements should be discussed with the Reactor '
Manager to determine if revision to the SOPS is ;
required, j 1 i
- 4. Changes that do not change the original intent of the procedures may be made with the approval of'the racility 4 Director.
1
- 5. Substantive changes to the approved procedures shall be made only with the additional approval of the Radiation Safety Committee.
t
.i oktllfY Written By: / David Freeman Approved By: Albert Bolon l
-m-+ ,
a n9;*mq 4 m .m
- y,9 Y LY $
- UMR REACTOR STANDARD OPEPATING PROCEDURES ***
SOP: 101 TITLE: CENERAL OPERATIONAL PROCEDURES Revised: September 12, 1990 Page 1 of 3 A. Purcose:
To provide written procedures for routine reactor operation.
4 B. Precautions. Prerequisites, or Limitations 1
- 1. Reactor operations must at all times meet the require- I ments of the Facility License R-79, Technical Specifica-tions, and the Physical Security Plan. i
- 2. At least two persons, one of whom is a Senior Operator, shall be present in the Reactor Building when the reac .
tor is operating, j
- 3. A licensed operator responsible for reactor operation i shall be present in the control room at all times when the reactor is operating. '
a) Students 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.
b) Trainees may operate the reactor controls under the direct supervision of a Senior operator provided the excess reactivity is less than 1.5% delta k/k.
l
- 4. The reactor will be operated with the minimum amount of excess reactivity necessary to fulfill operational requirements, and those requirements will be at the :
t direction of the Senior Operator on Duty. l
- 5. personnel in the Reactor Building should be informed l over the public address system about changes made to the ~
reactor status.
- 6. 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.
- 7. All personnel are responsible for notifying the Senior operator on Duty of any work being done that could Rev.
either directly or indirectly affect reactor operations.
i i
b.*:5 NC5 Written By: -David Freeman Approved By:
hY W Albert Bolon
\'
pp 31& M9 a -a m .n +. '*
1m En b j
- UMR REACTCR STANDARD OPERATING PROCEDURES ***
SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: September 12, 1990 Page 2 of 3
- 8. Radioactive samples or sources will be removed from the Rev.
core or thermal column only under the direction of a Senior Operator, or the Campus Health Physicist (or his designated representative).
- 9. Log books will be kept in the control room safe, except the one currently in use, which may be kept on the con-sole. 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.
- 10. Completed recorder chart paper will be dated and filed in designated areas, and kept on file for at least the minimum required time. Loa N charts are to be kent as a permanent record.
- 11. Changes in Core Mode (T or W) will be noted in the per- Rev.
manent log book, including date and time.
- 12. Only the Senicr Operator on Duty may key bypass control channel automatic functions. The use of any interlock bypass key requires a permanent log entry for insertion and removal. This log entry shall include date and time.
- 13. Handwritten revisions to the Controlled SOPS may be made provided the following conditions are satisfied:
a) Handwritten revisions are clearly legible and neatly made in ngtd ink in both Control SOPS.
b) Handwritten revisions'are reviewed and approved by ,
both a Senior Operator and the Reactor Director. l Review and approval shall be documented by initial-ing and dating the revision, c) Handwritten revisions should be listed on the revision form located in the front of the Reactor Manager's controlled copy of SOPS in red ink.
In the absence of the Reactor Director, the Reactor Man-ager may review and temporarily approve handwritten l revisions provided the Reactor Director reviews the revision as soon as practical upon his return.
Written By:
St Q dav/ id Freeman Approved By:
0 iY Albert Bolon l
l i-l
I L .I
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 101 TITLE: CENERAL OPERATIONAL PROCEDURES Revised: September 12, 1990 Page 3 of 3 e
- 14. Any abnormal behavior associated with reactor startup or pey, operation should be reported to the Senior Operator on Duty immediately. If there is any doubt about reactor safety, the reactor shall be shut down. Then the cause should be determined and corrective action taken.
- 15. Only a Senior Operator can give permission to restart the reactor after a scram or rundown.
- 16. The Standard Operating Procedures (SOP's) should be fol-lowed to the extent practicable, especially whenever the pre-startup checklist is being completed, when the reac -
tor is being started, or when the reactor power is being changed.
- 17. The Senior Operator on Duty has the authority to instruct the reactor operator to disregard certain SOP's provided that no safety requirements are violated. (For example SOP 305 does not have to be performed every pre-startup checklist.)
- 18. All scrams and rundowns shall be noted with explanation Rev' of the cause and corrective action in the permanent log book.
e j Written By: / Dav d Freeraa Approved By: Albert Bolon '
l l
_ _ _ =
b ab 3
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES
- Revised
- August 14, 1990 Page 1 of 8 A.
Purpose:
, The purpose of the checklist is to give assurance that sys-tems are operating correctly. The checklist shall be comp- Rev.
leted any time the reactor is to be started up from a com-plete shutdown, that is if a shutdown checklist has been com-pleted, unless otherwise specified by the Senior Operator on Duty.
B. Precautions. Prerecuisites, or Limitations:
- 1. It shall be the responsibility of the licensed operator checking the reactor out to make sure that all steps in the checkout list have been properly completed. In the event a student checks out the reactor as part of his or her training, the licensed operator must still accept the responsibility. The operator may assign various steps to be completed by unlicensed personnel, in which case, the responsibility still lies with the operator performing or supervising the checkout.
- 2. Immediately before the reactor is started up a startup cncck list must be completed.
- 3. After each step on the check list is completed the oper-ator will record the readings made, or in cases where no readings are required, will simply check the appropriate blank on the form.
- 4. Any malfunctioning or abnormality of the reactor or com-ponents shall be immediately reported to the Senior Operator on Duty, and corrected before continuing with the checkout form.
- 5. After the check list is completed the Senior Operator on Duty must give final approval of the check list by ini-tialing the completed form.
C. Procedure i
Refer to the pre-startup check list.
l l 1. Use the rubber date stamp.
l l
j Written Byr David Freeman Approved By:
0 Albert Bolon l
UU$)dTD LC.i Fl'i l'NO3 Y d ilV[;i VMi
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 102 TITLE: PRE STARTUP CllECKLIST PROCEDURES Revised: August 14, 1990 Page 2 of 8
- 2. Record the time that is shown on the reactor console clock translated into military time.
- 3. Your initials.
- 4. Enter core loading number and mode.
- 5. Check or turn on these units. Number 6 is the bridge intercom.
. 6. Announce, "The building alarm will sound. This is a test. Do not evacuate the building."
- 7. Check the #1 Radiation Area Monitor (RAM) at its respec-tive setpoint, i.e. ~13 mr/hr "High Radiation Alarm" and lRev.
~20 mr/hr " Building Evacuation Alarm." Depress the but-ton on #1 RAM Amplifier and hold until the board annun-clator and building alarm sound. Push scram reset, acknowledge, and reset buttons in that order. Repeat for #2, and #3 RAM, except there will be no building evacuation alarm. Push acknowledge, and board reset.
Announce, " Test complete, acknowledge all further alarms."
- 8. See that all monitors read approximately 3 to 6 mrem /hr.
- 9. Ask the Senior Operator if the nitrogen diffuser pumps need to be turned on.
- 10. See that the beam port and thermal column lights aro off. Check status of experiments.
This completes the preliminaries.
Now a " static test" of the instrumentation will begin.
- 11. Depress the zero check button. If the digital readout is not ".0000", notify the S.O. Depress the zero check button again to release the check function. If the lin-ear reading is not between 0.02 to 0.05, ask the Senior Operator on Duty to adjust the compensating voltage.
Record the meter reading. Record the scale.
ff , ;jfN. A Written By:' David Freeman hO p
%^~
Approved By: Albert Bolon
- w* UMP. REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 102 TITLE: PRE STARTUP CHECKLIST PROCEDURES Revised: August 14, 1990 Page 3 of 8 1,
j 12. These are the compensated ion chamber voltages. Record
- 1 (Linear) power voltage. Hold meter range switch down for negative (compensating) voltage and record. Then do the same for #2 (Log N). (Normal reading should be approximately 510, 5, 580, 6.)
- 13. Open the recorders. Turn them on. Leave the glass doors open. Date each recorder chart. Close doors and push the reset button. The " Recorder OFF" light should be off.
- 14. Turn the pool lights on. Check the water level in the pool. " Spike" the Log N and period CIC and the Linear ROV-CIC by positioning the neutron source next to the detec-tors. Check that the period, Log N and linear recorders have responded p operly. Reset the board. Insert the source in holder. Look at the core and pool for foreign objects that may have fallen in. Check the in-core experimente. If you received < 5 sec signal, reset the period light on the amplifier.
- 15. Turn selector switch on Log Count Rate meter to 102, 103, 104 See if meter and recorder follow. Return to the " OPERATE" position.
- 16. Depress fission chamber insert switch and hold down until the green insert limit light comes on.
- 17. Turn on scaler, reset the timer, make sure it is count-ing.
- 18. Depress fission chamber withdraw switch. Hold down until the counts start to decrease.
- 19. Reinsert fission chamber to insert limit. Make sure the recorder is reading greater than 2 counts /sec.
- 20. Turn switch on Log N meter to " LOW". (The Log N recorder should read about 0.01.) Quickly turn switch to "HIGH'. (The recorder should read about 8 kW.) Fush acknowledge and board reset.
I b o%
Written By: ' David Freeman Approved By: Albert Bolon I
j .
i i
a-10NTR0iiED COPY 1 ,
! *** UMR REACTOR STANDARD OPERATING PROCEDCXES ***
! SOP: 102 TITLE: PRE STARTUP CHECKLIST PROCEDURES Revised: August 14. 1990 Page 4 of 8 i i
! I l-I 21. Turn period " CALIBRATE" switch. Hold until period
! recorder reads 6 seconds. Check the annunciator panel
{ for Log N and Period Honoperative, 30 sec and 15 sec j periods lights. Push acknowledge and board reset.
This completes the " static test" of the instruments.
) The next section of the checklist tests the' console under
! actual operating conditions.
}
i 22. The magnet power key is normally kept.in the locked j safe. When the key is given to you insert it into the-i console and turn on the magnet power. Push scram and i board reset buttons to clear the annunciator: panel'and- "
energize the magnets.
- 23. Record magnet readings using the current-gauges located j above the safety amp. (Typical readings should.be bet- Rev. i.
j ween 35 and 85.)
J
- 24. Withdraw shim / safety rods.3 inches using the gang' joy i '
stick. Depress test button on safety. amp and hold until the 4 red lights come on. Push acknowledge, reset'the l safety amp and reset button. . Check that the blue magnet >
contact lights are out indicating the: rods have dropped.
! (Note. If a magnet contact light is not' out: ask the 50 on Duty whether you.should refer to sop 305,) Run the j rod drives back down.
1 25a. Again withdraw shim / safety rods-3 inches. -Turn period:
test switch on Log N-meter clockwise to " CALIBRATE".
, Hold and wait for the period recorder.to indicate a 6 j second period. Push acknowledge'. button. Check for Log i
N-Inoperative Scram, Manual. Scram, 15 second rundown, -
and 30,second period lights on annunciator panel.- Try-
! to stop the run down by lifting the shim / safety' joy
- 1. stick.- Then stop the rundown with the rundown reset i- button. . Check that all-magnet contact lights are out-
'1 l and; then run: rod drives- back down. Push scram. reset, and board reset buttons.
25b. Periodt< .5: Seconds Test Rev..
l
- a. Withdraw' rods;to 3 inches.
b Written By: ~ David Freeman-Y F
Approved By: ' Albert Boloni
,t I
-- ,,.m.,.,~-, - _ , , ~ , , - - , , , _ , _ - . - _ . _ , - _ . , . . _ . . . _ . _ ,
COUR)LLED COPY l
- UMR REACTOR STANDARD OPERATINC PROCCDURES ***
SOP: 102 TITLE: PRE.STARTUP CHECKIIST PROCEDUPJS Revised: August 14 1990 Page 5 of 8
- b. Push in and turn trip test knob on the period sec- p'V' tion of the Log N Amplifier.
- c. Rotate the trip switch slowly and observe that the 30 second rod withdraw prohibit annunciator is actuated with a simulated period s 30 seconds.
Continue to rotate the trip switch.and observe that '
the 15 second period rundown occurs with a simu-lated period 2 15 seconds. Continue with trip test button rotation until the period' light is illumi-nated.on the Log N Amplifier..
- d. Acknowledge the annunciator alarm and observe j period < 5 second scram occurs at a value 2 5 sec .-
onds. Also observe the 150% Full Power. Scram and that the safety rods.have dropped. Reset the 1 period trip test light-on the Log N Amplifier and ,
push the rundown reset buttons. Insert rod drives !
and reset annunciators.
l
- 26. Rasse shim / safety rods 3 inches and push the manual' .
setam button. Check to-see.if rods have dropped by 1 observing the video display and' noting whether the blue j magnet contact lights are off.- push acknowledge,' scram reset and board reset' buttons, and run down the rod ;
drives. !
- 27. Push annunciator test button. Check for burned out l bulbs. Acknowledge-.and reset.
- 28. All blue magnet contact-lights should be on and the regulating rod on insert limit.
- 29. Prepare' hourly and permanent logs.
- 30. Raise shim / safety rods to 6 inches. Record the time in both locs.
- 31. Inspect.the core. Make certain core cooling is clear:
o and experiments are firmly secured.:
- 32. Announce, "The' reactor'will be' started and taken to a.-
watts (or= _ kilowatts)".
power'of
- - 33. Record the intended power level, including W or kW.
)
Written.By: ' David ' E reeman - ' Approved'By: Albert Bolon r
i
1 i
i CONTR0Li.ED COPY 1
l *** UMR REACTOR STANDARD OPERATING PROCEDURES ***
- SOP
- 102 TITLE: PRE STARTUP CHECKLIST PROCEDURES 1 Revised: August 14, 1990 Page 6 of'8 1
l i
1
} 34. Review the pre-startup checklist to make certain that i all the steps have been completed.
- 35. The Senior Operator must initial the check list. This I
completes the check list.
- 36. Use the rubber date stamp, in case'page 2 of the check-
- list should be separated from page 1.
l 2
l 1
l i
j i
i 1 -!
}
l t 1
l l
1 i
I j
1
-)
i ,
- i-j j
3' 1
I?
?- +
i i
'l
, Written By: . David Freemani-4 Approved By:
k bb Albert Bolon
pf N 04 $/
Ud h {W j hU., QiLLfi {l0 bi i
- w* UMR REACTC'R STANDARD OPEPATING FROCEDURES * **
SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURES Revised: August it., 1990 Page 7 of 8 UW R ER!.5IARf0P C-E:K '. ! S T (500 102)
- 1. Cate
- 2. Time (Console Clock, Military Time)
- 3. Operator's initials
- 4. Core Leading and Mode (W or T)
- 5. Intercos, P.A., T.V. Camera & Monitor Oa
- 6. Announce RAM Check
- 7. Check PAM Syster
- 8. Padiation Level hortal
- 9. Nitroger. Ettfuser On, List. Lit No. 1 (Peautre: w r e n P > 2 0x 'a' ) No . 2
- 10. Beam Pcoe Bear Tate and Trerr.a1 Column Experimer.ts Set for Run l 11 Lirear Zero the Meter l Level leter Eeacars W.ast Sensitive Scalei Scale
- 12. C.I.C. ho, 1 -
Linear Rev.
Peadtrgs No.1 -(Hold meter range s=ttch down)
No. 2 - Log N Rev.
No. 2 - (Hold meter range switch down)
- 13. Pecorders: On, Ink, Paper, Date 14 Pool Lignts on, Level Creek, Loq N ed Perted 50tke Rev.
(Inca
- Sotke Source Inserted Insce:t Core (Ex;ts. , e tc. )
1$. Test L:q Count Rate (Use Pecorder)
- 16. Insert Fission Chamoer to Insert Lir.it
~
REV. 3/14/90
/',i b'#.'/[ . bN 9A Written By: David Freeman Approved By: Albert Bolon
. .f, l p '" .0 0 i. 'l f.,e.17.,AlI,1.L; V J 12 3 ;J 5 i=
- e Ddi_ s. j
- CME REACTOR STANDARD OPERATING PROCEDURES ***
SDP: 102 TITLE: PRE STARTUP CHECKLIST PROCEDURES l Revised: August 14, 1990 Page 8 of 8 peo p a r.;; Ap;;p ;HE:< LI5*
Pn6' 2 17 Maier c a. Count ana ; hrting
- n ?;ssi
- a Cr.a-te* Pes: ante 16 ll l I i. . F;sst:n :nanter an Insert L 1 ?.i t one : aunt Pite
- rester tnan 2 CPS 2: Tes: Mg N Pe::r:er PespOnse ll 2' test Pertod Pe : acer Respo*se l L .
I
- 22. Magaet Po.er On, Jeram Paset, Boari Peset
- 23. Magnet No. 1 Carrerts (Fead N: 2 l l Va Les) NJ. 3 l l l 4 -
24 Creu 150% Raise Ects 3 in. l P:.or P.sn " Test" Batten 5: ar On Safety Anp Parel
- 25. One u Leg N/ Pa;ae Reas 3 in.
Per13d Non. Select S itch tc Userative 3 ram Ca ll ts e n t e an! 15 se:
Pe tad Rans:wn l 250. 5 se Period s:; ram ll l } l Rev.
l
- 26. Iest Manual Raise R:ds 3 in. l Scram Push Marual Scrat l 2' Test Annun: tatar, All Lignts On
- 23. All Magnet Contacts Mace, Peg. Rod on Inser: Limit
- 29. Prepara Hourly and Permanent Logs
- 30. Paise Rods to 6 in. , Record ilme
- 31. Inspe:t Core
- 32. Announce Int'ent ton to Start f
- 33. Irtended Po.er Level 3k. Pre-3tartup Che:w Completed
- 35. se uce 0;erator's Intetals l
36 Date 4M sh) ' d' Mb(,,d kw k'ritten By: David Freeman Approved By: Albert Bolon
[$, $(d k OC 7I
. ;aaJ.G U L LL.a (L;C f lf
- UKR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: August 10. 1990 Page 1 OF 7 A. PURPOSE The purpose of this procedure is to provide guidance for pgy*
performing the resin regeneration and associated sample
- collection.
B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS Inform the Reactor Manager that the regeneration
~
- 1. p,y' is being started.
- 2. Two personnel should be present dressed in lab coats and eye protection for all caustic and acid transfers.
T
- 3. The Reactor Manager should be informed when the Rey, system is returned to service.
- 4. Ensure water flow to the make-up sump is maintained to prevent draining of make-up sump which would cause air to be sucked into the demineralizer.
- 5. WATCH LEVEL WHEN USING ACID AND CAUSTIC TANKS TO ENSURE THAT NO AIR IS DRAWN INTO THE SYSTEM WHEN THE LEVEL IS LOW.
- 6. Each step must be performed in a timely manner to pre-vant a faulty regeneration.
- 7. SOP 205 must be used in conjunction with this procedure.
- 8. The numbers referred to in this procedure are the valve numbers found on the valve tags.
- 9. Sampling of liquids sent to the retention tank should Rev.
consist of three grab samples collected at the beginning, middle, and end of each process (i.e.
backwash, caustic rinse, and acid rinse). Sampling of liquids discharged to the sewer system may consist of
. either grab sampling as described above or " trickle" sampling using a continuous draw sample collection i technique during discharge.
I Written By: David Freeman Approved By: Albert Bolon lJhb hr
l l
, 00NTR0!. LED00M
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: August 10, 1990 Page 2 OF 7 C. PROCEDURES
- 1. Check that the following valves are closed: 30, 31, 32, 33, 34, 35, 36, 37, 39, and 40,
- 2. STOP PUMP. Isolate purification system from pool by:
closing 19, 22, 25, 3, and 1.
- 3. Open 13. Fill make-up sump to lower overflow hole.
Adjust 13 to maintain level.
- 4. Open 17 Check 18 is shut.
- 5. Isolate demineralizer: Close 2, 9, 5, 7, 11, and 4.
- 6. Align retention tank #2 to accept backwash water. Open valves 31, 35, and 30,
- 7. Backwashing resind:
a) Open 5 and 4 b) Start pump c) Open 1 to maintain flow 0 10 gpm d) Close 30 until pressure increases or flow decreases e) Maintain full sump level with 13 f) Obtain a backwash sample from 38 at the beginning, gg*
middle, and end of the backwash to the retention tank g) Leave 38 open to check for no resin beads present h) Backwash for minimum of twenty minutes to separate beads
- 8. Prepare caustic while backwashing, a) 45 pounds (7 inches) of NaOH placed in caustic tank (tank on pump side of demineralizer).
- 9. To stop backwash:
a) Close 30, 1, 38, 4, and 5 b) STOP PUMP c) Wait for resins to completely settle d) Open plug (below valve 10) to drain resin from spreader Written By: D id -eman Approved By: Albert Bolon l ' '(7"b k&(6Y
,, 6 3
- UKR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: August 10, 1990 Page 3 OF 7
- 10. a) Record the volume (gallons) of backwash sent to the retention tank. Rev.
b) The backwash sample collected in Step 7f) must be analyzed and the appropriate release authorization signature must be obtained (per SOP 205) prior to discharging backwash water from the retention tank.
c) After release authorization has been obtained for the backwash water in the retention tank, additional backwash water may be discharged directly to the drain, provided it is sampled and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the release. If additional backwash is discharged, record the volume (gallons), date, and time of release, d) Discharge to sump by: closing 31, and 35; opening 33, and 37
- 11. Regenerating anion bed (watch tank level):
a) Open 34 (to retention tank #1) b) Open 9, 11, and 30 c) Start pump d) Open 1 to obtain 34 psig on bottom gage
- 1. Adjust 4 to lower pressure to 20 psig
- 2. Adjust 1 to raise pressure to 34 psig
- 3. Close 30 until pressure starts to increase c) Open 10 to siphon caustic
- 1. Regulate siphon rate to approximately 1 to 1.5 in/ min
- 2. Should be completed in approximately 30 min.
- 3. Obtain samples at 5, 10, and 20 min. lRev .
f) When caustic tank is empty, close valve 10
- 12. Anion Slow Rinse a) Rinse for 30 min. at approximately 34 psig on bottom gage b) Ensure valve 4 is cracked open
- 13. Anion Fast Rinse (Caution: make-up sump level will drop) a) Close 9 while opening 2 b) Adjust i to approximately 30% (top gage) c) Rinse for 30 min.
d) To start fast rinse:
- 1. Close 35
- 2. Open 32 Written By: Dggi Pfe mhn Approved By: Albert Bolon iil'1 ,-l5?
Q
. 1 CYTRELED COPY
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: August 10, 1990 Page 4 OF 7
- 3. Adjust 30 for 25 psig )
e) Prepare acid while fast rinsing
- 1. Fill acid tank with hcl to within 4 in, of top f) TO STOP FAST RINSE:
- 1. Close 1, 4, 2, and 11 g) Record the volume (gallons) of anion rinse sent to Rev.
the retention tank.
h) In the event that retention tank #1 is full and {
additional anion rinse is required, the additional anion rinse water may be discharged to the drain, provided it is sampled and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the release. If additional rinse water is discharged, record the volume (gallons), date, and time of the release.
- 14. STOP PUMP
- 15. Regenerating Cation Resins:
a) Lineup retention tank #2 by:
- 1. Closing 34 and 32
- 2. Opening 35 b) Open 6 and 8 c) Start pump d) Adjust 1 to 20 psig (bottom gage) e) Open 7 _
f) Close 30 until pressure increases g) Adjust 7 for a 1 to 1.5 in/ min siphon rate of acid tank h) Obtain samples from valve 38 at 5, 10, and 20 min. Rev.
intervals
- 1) When acid tank is empty:
- 1. Close 7
- 16. Catiori Slow Rinse:
a) Rinse 15 min, at 20 psig i
- 17. Cation Fast Rinse .
a) STOP PUMP b) Close 1, 8, and 6 c) Open 4, 11, and 1 d) Rinse 15 min, at 30% flow e) Record the volume (ga21ons) of cation rinse sent to Rey, the retention tank.
Written By: D Approved By: Albert Bolon C64
/gyip-freman %d. 0e(2 k _
-- - -mminummme
lCONIELLD COPY
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DD4INERALIZER REGENERATION Revised: August 10, 1990 Page 5 OF 7 f) In the event that retention tank #1 is full and pg*
additional cation rinse is required, the additional cation rinse may be discharged to the drain, provided it is sampled and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the release. If additional rinse water is discharged, record the volume, date, and time of the release.
- 18. Full Bed Rinse:
a) Close 4, 11, and 1 b) Open 2, 8, and 1 c) Rinse 15 min. at 30% flow d) Start air compressor
- 19. STOP PUMP
- 20. Close 2, 8, 1, and 11
- 21. Close 13 (to makeup sump)
- 22. Draining Resin Bed (level drops quickly with air) a) Open 2 and 8 b) Drain to 1/2 inch of top of resin
- 1. Valves 12 and 12A can be used to allow air pressure to enter c) Close 12A, 8, and 2 d) Open 5 (release air pressure)
- 23. Start pump
- 24. Open 4
- 25. Slowly open 1
- 26. Refill resin 1 inch above top of resin bed
- 27. STOP PUMP
^
- 28. Close valve 1
- 29. Remixing Resin:
a) Slowly open 4, 5, and 12 b) Mix resin beads thoroughly Written By: Davi1 Er6e? n Approved By: Albert Bolon l'&'V' $Luk @k
l s 30hiR011ED COPY
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 204 TITLE: DEMINERALIZER REGENERATION Revised: August 10, 1990 Page 6 OF 7 i
- 30. Close all valves
- 31. Allow beads to settle
- 32. Refill of Demineralizer:
a) Open 9 b) Start pump c) Crack open valve 1
- 1. Obtain 30 psig (lower gage)
- 2. Continue for 15 minutes d) Open 2
- 1. Pump at 40% flow until demineralizer is full
- 2. Remove air at regular intervals while filling by:
- a. Closing i
- b. Opening 5 e) Close 9
- 33. Final Rinse:
a) Open 2 and 8 b) Open 1 to 60% flow c) Rinse resin until 500,000 ohm-cm is obtained d) If not obtained in 45 minutes:
- 1. Close 1, 8, and 2
- 2. Open 4 and 5
- 3. Open 1 to approximately 5% flow for 2 min.
- 4. Close 1, 4, and 5
- 5. Allow resin to settle
- 6. Repeat step 33.a.
e) Rinse water may be discharged to the drain, provided Rev.
it is sampled and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the release. If final rinse is discharged, record the volume (gallons), date, and time of release, f) Close 2 and 13 g) STOP PUMP h) Close 8
- 34. Restart Recirculation to Pool a) Close 13 b) Open 19 while closing 17 Written By: Dpuid Ftanmaq Approved By: Albert Bolon fnl' WE;/ hbh h*8
l l
i ss ~ ' CONTROLLED COPY
- ***UMR REACTOR STANDARD OPERATING PROCEDURES *** ,
I SOP: 204 TITLE: DEMINERALIZER REGENERATION !
- Revised: August 10, 1990 ,
Page 7 OF 7 I i
} 35. Discharging to-Basement Sump:
l a) Samples must be analyzed and release approval. Rey, j obtained per SOP 205 4 b) Close 30 and 35 j c) Open.32, 33, and 37
- d) Observe sump levels .
i 1. Adjust.33 to prevent overflow condition
- e) When tanks are empty
l 1. Open 30, 31, 32, and 33 3
- 2. Close 36 and 37
- f) Record the volume (gallons), date, and. time of each Rev.
i release i
4 i
i i
s f
! .L j-.
a f
.i 4
2 Written By: : David Free an ApprovedlBy: Albert _.Boloni t'{j' - 5
~
ltl (i
- i. .1
+.-.. ,. . - - . . - . . ~. , ,.n,
. . __ _ = . _ _ _ - _ _ _ . . - . ._
l J
i
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
t SOP: 205 TITLE: DEMINERALIZER REGENERATION WASTE WATER <
3- '
. ANALYSIS AND RELEASE-Complete Revision: August 10,-1990 Page 1 of 4 l A. PURPOSE i
To provide instruction on the analysis and discharge of demineralizer regeneration waste water. !
! B. EOUIPMENT 15 ml plastic vials -
1 15.5 nl Co-60 standard (UMR-1, #11) '
i 15.ml vial of Reactor-Facility tap water (background) j Multichannel analyzer with Germanium or !
! Sodium Iodide detector.
C. ANALYSIS PROCEDURE l 1. Obtain er.ch sample.as required in SOP 204.
- 2. Label and date each vial. (e.g. Acid,-Caustic, Backwash,-Dilution, etc. and-Month / Day / Year.)
- 3. Samples of liquids stored in holdup tanks should be
[ analyzed within-one week of collection. iTtus results of this analysis may be used'for reporting purposes when~
the tanks are discharged; however, credit for decay'may
- be taken by reporting the results of a re-analysis
l performed on tho sample.on or.before.the day of release.-
l l 4. Samples.should be retained for.a period of 6 months.
- 5. Count the Co-60l standard-(UMR-1, #11) for'at.least 300, -
i ~ seconds, 600 seconds (live. time).or longer ~isfpreferred.
- Print'out the gross . integral counts ~between 0
- and 2:MeV: i
.and.the net integrals for-theLisotope-peaks. Record:the 6 error in the grossiccunt integral-between 0 and 2.MeVJon -
[
the printout.- -
- 6. Count the tap waterL(background) in the same' geometry-l and for the same : length of L time as thelstandard. . The -;
background determination should be made at least once. n
! every four hours'during analysis'.- Print;out~the-gross ,
- i. ~ integral between 0-2 MeV. Record.the' error'on the !
l printout.
c . ,
l ..
ApprovedLBy:
bbA . vYM Albert"Bolon i
Written By:- Davi.d Freeman FAY
.- .. .- - -.-~. . . = _ _ . _ _ . -- --. - , - . . - - ~ .- -.
'00NTROLLE COPY l'
SOP: 205*** UMR REACTOR STANDARD OPERATING PROCEDURES ***
TITLE: DEMINERALIZER REGENERATION WASTE WATER Comp 10te Revision: August 10,ANALYSIS 1990 AND RELEASE ~
Page.2 of 4 i 7. Count the sample (s) in the same geometry and for the 1
same length of time as the standard. (The standard,-
' background and sample (s) should be counted in succession with no excessive delays between counts.)
gross integral between 0-2 MeV. Record thePrint-out the error _on the i printout.
If any isotopes are identified in the sample,
- print out the net integral for each peak. If,no peaks
< are present, note 3: on the print out.
j 8. If isotope peaks a)e identified in the sample,:
- re-analyze the back 7round spectrum (previously collected) and determine if. peaks exist.in the background at the same energies, if so, subtract-the-background net integral peak counts from the-sample net-integral peak counts to determine if the sample. peak is' significantly above background. If sample peaks-are determined to exist above background,-list their
' energies and try to identify the isotope (s) on the
' " Regeneration Waste Water Analysis and Release-1 Authorization Form".
9.
Complete the " Regeneration Waste Water-Analysis and-Release Authorization Form".1 Use the gross integralt count rates between Otto 2 MeV for the efficiency land sample a "ivity determinations.. Attach-all_ supporting-i documentation (clearly _ labeled)1to the " Regeneration-i Waste Water Analysis and-Release'_ Form".
D. DISCHARGE PROCEDURE' F
- 1. Obtain the appropriate authorization signature for-L re]oase using the criteria below:- '
- a. The Reactor Manager or-_the Health Physicist (or his 1 designee) may authorize the release (by-signature) if no radioisotopes are-identified above '!
background and the gross activity.is'less than-1 5 x 10-5 pCi/ml above background.
t' i
- b. LIf any radioisotopes'are identified'above background or-if'the gross activity of the-sample' is. greater thanEl.5 x 10-5 pCi/ml_above 3 i
background',1the Health. Physicist.(or his-j designee) must authorize-(by signature)'=the release.
1 Written By: YCu 6 u-D vi Fr,eeman Approved By:
l Albert Bolon hpf .i!4f _ ',
l i' _ _ _ . -
4 s
O bOh;11ULL U bO3iO'O[
%IDOI l L(D 4
- UMR REACTOR STANDARD OPERATING PROCEDURES *** -
SOP: 205 TITLE: DEMINERALIZER REGENERATION' WASTE WATER
- ANALYSIS AND RELEASE Complete Revision: August 10, 1990 Page 3 of 4 i
i c. The release authorization signature must be l obtained prior to discharge with the exception of i dilution wash and rinse water. The authorization signature for dilution wash and rinse water should
- be obtained within 3 working _ days after the !
< release,
- s. Dilution wash and rinse water has been shown to meet the
! release criteria above and may be released without; prior:
l analysis on the condition that this water is sampled per SOP 204 and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the release. In the unlikely event that the. average activity of the
. dilution wash and rinse water. exceeds 1.5x10-5 pCi/ml',
the Reactor Manager and Reactor Director should be j 4 -
notified.
-2. Release the liquid. Record the date, time, and volume-of the release. If discharging dilution wash and~ rinse <
water, sample the discharge per SOP 204.
- 3. Attach a copy of the spectral7 analysis-printouts;to the -
i completed " Regeneration 4 Waste Water. Analysis and Release
{ Authorization Form". -Forward'a copy of the: completed-form to the Health Physicist. File the original-form "
with-attached printouts in the Reactor Facility files.
i l
! r i=
) ' b.A r .;y A L Written'By: avid F man. : Approved-;By: Albert Bolon ' ,
hhd'bYW(
_ _ ~ . - _ _ _- . . . , ,,
- . - . - - . _ - - . . . _ - . . . . _ . . . - . . . - - . - . ~ . . - .-. -- - _ .
T 4
4 gy yn m ll ?; c',1 Q
,(;d di1L5d bbI:I ,{D7 !
i
- UMR REACTOR STANDARD OPERATING PROCEDURES ***-
j SOP: 205 TITLE: DEMINERALIZER REGENERATION-WASTE WATER 1 ANALYSIS AND RELEASE Complete Revision: August 10, 1990 Page 4 of 4.
Regeneration Waste Water Analysis and Release Authorization Form.
l Sample
Description:
j Sample' Collection Date:
i Sample Volume (ml):
Analysis Date:
! I. Efficiency Determination ,
j i Source Identification Co-60, UMR-1, #11 Initial Source Activity (Ao): 1.88x10-2 pCi on 10/1/78 Decayed Source Activity A(t): 4Ci !
1 Fixed Geometry Description ,
l Source et rate i cpm 1 - Backaround et rate 1 cpm i Differential et rate- cpm
. Efficiency (eff) = Differential CR- = 1 gp31 (OT/ dis)(A(4) pCi) 4Ci II. Sample Activity Determination j
4 Sample ct rate opm
- - Backcround et rate Li cpm Differential ct rate i. cpm-
) Sample Activity =-Differehtial-ct' rate =' .yCi l (eff) x sample' volume (ml)- ml.
l III. Peak Identification t
CPM ;
-Enerav (above backcround) Nuclide-i i
! l l
jr IV. Approval for Release: .
i j Signature Date & Time l
Actual Release Date~&. Time '
4 Volume of Release Written By: Da d Freeman-N b d.o w
-Approved By: _ Albert Bolon
[
Ja/t M l
d) 0,:,W C D *7?;3 5 3 t 'i w ;n i u)
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 505 TITLE: ENHANCED REACTOR SECURITY Revised: November 12, 1990 Page 1 of 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 Rev.
the Reactor Facility the following steps will be observed:
- 1. The reactor shall be shutdown and the magnet power key lRev.
secured in its normal storage location.
, 2. All entrances to the building shall be locked 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 Con-finement Security Door. N Del.
- 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, i
l
(
l l
l
./?.ht Written By:' David Freesan Approved By:
YY Albert Bolon-l
CONTROLLEE C07l
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 510 TITLE: EARTHQUAKE Revised: September 12, 1990 Page 1 of 1 EARTHOUAKE 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.
- 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 possible abnormal radiation levels.
- 5. Re-establish physical security as soon as possible.
- 6. Be prepared for "aftershocks" that may pose additional danger.
Written By:
lb
/ avid D
(N!
Freeman Approved By:
(W Albert Bolon y
i
- CONTELE CDM i-1 i *** UMR REACTOR STANDARD OPERATING-PROCEDURES ***
l SOP: 604 TITLE: RELEASE OF BY-PRODUCT MATERIALS ON CAMPUS Revised: July 31, 1990 Page 1 of-3 i
N i
i i A. PURPOSE To ensure that proper transport, handling, and shielding requirements and regulations are observed in thershippingfor~
releasing of radioactive materials to licensees on camous.
B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS i-
- 1. All shipments or releases of by-product material:from the
' Reactor Building shall-be handled as " limited quantity"
-- if possible.= Any_ amounts greater than " limited-4 quantity" require special attention as deemed.;by: Health Physics,
- 2. The person receiving radioactive material must-show that he/she is licensed to possess--it. Radioactive materialss can not be . released to someone who is: not licensed.
- 3. -If there are any questions pertaining to-lthe release of a material, or whether a substance is considered to be' i " limited quantity", the campus = Health Physicist should-be
, notified.
C. PROCEDURES i - -
i 1. Check D.O.T.1173.423 and 173.421 to ensureithat-the. _
radioactive material. meets 1the requirements off" limited- --
quantity".
\ . .
i 2. Package the radioactive material in doubl'e. containers._.
Check the package to ensure:that the materials =are pack-=
' aged.in strong, tight containers such that there will-bec p no leakage' of radioactive ~ materials under conditions-nor-
- mally. incident to-transportation.
i i
- 3. Check the'outside~of the inner container to be sure-that- -
[
it-bears the. marking " Radioactive Material".-
4., check the1 radiation levels to ensureLthat the.doseLrate ,
at any point on the external"surfaceLof the outer: package i does nottexceed'0.5 mr/hr.
J h h fce h.
Albert-Bolon:
Nritten By: Ray Bono Approved By: ,
A i
.q
, , . , , ,. .-- ~i
- . - - - . - . . . _ _ - - . - - - . . - . _ . - . - - . _ . ~ _ - . - - . - .
I CElKLLED COPY
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 604 TITLE: RELEASE OF BY-PRODUCT MATERIALS ON CAMPUS-Revised: July 31, 1990 Page 2.of 3- ;
- i i
i 5. Swipe the outside of the outer package for contamination I and count the swipes. The swipes must-not'be >220 i dpm/cm 2 for beta / gamma.or >22 dpm/cm 2 alpha (if pey, applicable).
y
- 6. Fill out a Material Transfer Form (see the attached).
1 Make two1 additional copies. One goes with the carrier,
! one goes to the Health Physicist and'one goes.into the -
- Reactor files. ,
l 7. Check the cosignees license.before releasing the z radioactive material to be sure they are authorized to l receive it, i
i
)
i J
i-i h
~
J -
Ek i j Writte.n By: Ray Bono. . Approved.By,: . Albert Bolon'-
.-. , .. .4-. .. . , . _ _ . .-
k CONTRCLLED COPY ,
1
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 604 TITLE: RELEASE OF BY-PRODUCT MATERIALS ON CAMPUS _
Revised: July 31, 1990 Page 3 of 3 1
l MATERIAL TRANSFER FORM j i i
{ Ship To Consignee By-Product License [
3
- Number Exp Date' I
4 i TARGET MATERIAL WEIGHT PHYSICAL RADIONUCLIDE ACTIVITY TRANSPORT l FORM- (IN CURIES) GROUP i
GAMMA DOSE RATE DATE IRRADIATION i ,
' TYPE SHIPMENT _
i i
l SHIPPING CONTAINER LABELS :
4 i
l TRANSPORT ROUTING -l i
DOSE RATE SURFACE _ CONTAMINATION' - i
- AT SURFACE mr/hr BETA / GAMMA dpm/cm2hgi AT 3 FEET mr/hr ALPHA dpm/cm2 he.
(If applicable):
INSTRUMENT USED .
I HEALTH PHYSICS APPROVAL INSTRUMENT USED' ,
! DATE i
~
"This package conforms to the conditions'and_ limitations specified ing; 49CFR173.421 for excepted' radioactive material, limited quantity, N.O.S. UN2910."
CERTIFIED BY DATE:
_ ACCEPTED BY CARRIER DATE 4
dy' bMO B Written By: Ray Bono Approved By: Albert BolonE l
q i -j
_ .__ _ _.- _ _ _ ., _._ . - _ . _ . _ _ _ . _ . . _ _ - _ _ . - _ . - . - _ . . . _ _ . . _ _ . . . ~ _ .
- J l- **Y h LQ a su/
U e% *N i ma} y . .p. 3%3/ i 4 i
- UMR REACTOR STANDARD OPERATING PROCEDURES ***-
j SOP: 810 TITLE: WEEKLY CHECK e
! Revised: September 12, 1990 Page 1 of 14 s e
i I A. PURPOSE ,
i To ensure the proper operation of the control and safety- Rev*
i related instruments of the reactor and to functionally. test- ;
i the Physical Security Alarm. System.. 1 1
B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS
- 1. The Weekly Check should be completed on the first. working l day of each week the reactor is to be. operated. -The. 4 Physical Security.' Alarm _ System =shall-be checked regard -
i less of reactor status. !
4 l'
- 2. The Physical Security Alarm System should be functionally tested for proper operation _(per Section C.11) ion the-l first work day of each week'.' The interval between tests 4- is not to exceed'10 days, i .
- 3. The weekly check should be_ performed'by a licensed opera- -
- tor, or a student under-the-direct supervision.of a' l licensed operator, o i ;
I l
- 4. Complete lthe Weekly Surveillance Checklist form:(Form SOP
- 810), and forwarditLto the Reactor Manager."(or Director)
I for-review and signature.;iAny abnormalities,' problems,- ~
or out of s'ervice equipmentfshould:be brought-to the. j l attention of-the Reactor. Manager'(or-Director). ,
C. PROCEDURE
' Select:the-Reactor. Bridge Station on'theEBuil_ ding Inter-4 com, check the PALsystem,Linstall' the neutronisource, L turn on all 5-primarytrecorders1(date the; recorders)l,___
turn on' core camera.and.selectLcore on'the. monitor'selec- -
, tor..Obtain. Magnet Power Key;anditurn'on r.agnetipower.-
, at
.1. . ROD ~ WITHDRAW PROHIBIT (vellow'lichts): j
?
A. Recorders off ... thel';ods willinot:withdrawLif.any .!
-one:of 5 primary recordersLisfturned'off. ,
i si i
! -Written,By: 'CYr1 Bai' ton capproved By: . Albert,Bolon
( ,
j
.2 -
- . . _ _ __. 1 - .. .
i q .S *'.
t BA-, ff,9 T. , ',')
w
, x ,.
dqN' IdOh
' &.W,
'd D.
[ '. )
r -
i !
1 . .
!' *** UMR REACTOR STANDARD'0PERATING PROCEDURES ***
- SOP
- 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Pago 2 of 14 4
i i
- i l 1. Turn off LCR recorder.
4
- 2. Attempt to withdraw. rods.
l"
- 3. . Turn on LCR: recorder, reset. alarm.
- 4. Turn off linear level recorder. -
! 5. Attempt to withdraw'rodst
- 6.- Turn on linear D ievel recorder,-reset alarm.
- 7. Turn off period-recorder. 1 i 8. Attempt to withdraw rods. !
] 9. Turn on period recorder, reset: alarm. 1 j
! 10. Turn off log N-recorder. -
e 11. ' Attempt to withdraw'_ rods. -
1
- 12. Turn on Log-N-recorder,_ reset alarm J
- 13. Turn.off temperature recorder.
! 14. Attempt _to withdraw rods..
- 15. Turn.on temperature recorder, reset 1 alarm.-
1 B. Log Count Rate <'2 CPS. i
- 1. Remove source from. holder _and/or withdraw 1fis-sion chamber until LCR-reads <2 CPS. Record' value-at which: alarm occurs:from recorder.
i
- 2. Attempt to withdraw rods.
- 3. Insert source and/or insert the' fission' chamber- >
l i
to the. insert limit..' Reset > annunciator.- ;
C. Period < 30' Seconds i
.j i . - . .
- 1. Depress _" Test' Trip"n switch on-Log'Nr& Period-i l l Amplifier and adjust for=a; period =< 30~ seconds.:- i Record-value-at;which~ alarm occurs 1on-the- j recor' der.. -
! 2. 1 Attempt toLWithdraw? rods. j j 13. Releats:-test: switch,-reset alarm.. d' h -i
[ D. Inlet TemperatureiAbove 135'_ Degrees I, i .
l '. :With,recorderDon, remove back cover.andimanu '
'al'ly? rotate' potentiometer: arm until alarm occurs, record trip point'.
j, 2. Acknowledge l alarm and_ attempt;to-withdraw rods.. '
- q L :3 . Reset =alarmionLtemp.. recorder, reset-alarm on- 1
~
console. -- !
l 1 j ._ Written By:
LisbW Carl Barton
$k.kdx k Approved.Byl : Albert Bolon
.1 im- - r r e . , -e d -
r ..w -.r
- 4 i
t_
I j *** UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE; WEEKLY CHECK _
! Revisedi September 12, 1990 Page 3)of 14:
1 i
E. Shim Rods Below Shim Range ;
! 1. With all Shim / Safety rods below shim range j . attempt to withdraw the regulating _ rod.- . Note <
f that the regulating rod.Will_ withdraw-just far l L enough to clear-the insert limit light. _
y l Attempt to-withdraw the Shim / Safety rods.- Notex
'that further withdrawal-cannot be made.1 . Insert all control rods to the insert limit and recordL .)
1
{ these results.
[ 2. . RUNDOWN CHECK (blue-lights): j q
j 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-l Building'PALSystem. .. _ . _ _
l 3. Using RAM' check-source switch #1. = Note the i value at which alarm (s) occurs.. Check the
-ciator Rundown Reset and Annunciator Reset. J
!! Record value of alarms.- _ . . 4
- 4. Repeat step =3 for RAMS #2.and_#3. >
j 5. All alarms, values shall be d 20Lmr/hr.
l 6. Upon completion of_. testing-announce " Test Com- .
l plete. Acknowledge..all furtherHalarms,'" on the building PA' system.-- ~
i B. 120%-Demand-l .
y 1-1.: Withdraw rods to 3: inches. ;
- 2. 'De-energize --( Linear ,L Period or: Log:N): recorder. }
l
.'(Switch <to:off.)T -!
! 3.-
Remove: Linear Channel potentiometer _; cover and ]Rev; :.l '
l ' manually.rotatel. potentiometer arm,- note' -
I recorder / reading.~wh'en trip; point is reached., ..
4 '. - When inward motionLof-rods is_verifled, lowerL l, recorder'below reset. point,' reset the-rundown
. d l and.all alarms, turn: recorder.'on'and replace- --
'q cover,' compare actual'and_specified trip, ,
.. O
- Written By: Ca'r1 Barton ; Approved By: Albert.Bolon.
}
! i Tj ,
%e . 3, --- n-v Q, I s s ; .1 'li 1 '
., l , ; .J '
gDUNN5'db]ndud,;- 3 YJ.I
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 4 of 14 points.
- 5. Record trip point value.
C. Period < 15 Seconds l'. 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.
E. Low CIC Voltage Linear Power Supply
- 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 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. When the High Voltage on the Linear CIC Power Supply has increased _to approximately_500 volts push alarm reset. The under voltage alarm light will ga off allowing the operator to reset the rendown (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 power supply. Observe the high voltage meter and record the value when the.under vol-tage alarm light comes on. Release the test button.
- 3. Ackt:owledge the annunciator alarm and observe the Low CIC Voltage annunciator light.(also check for 5 5 sec. period, s 15 sec. period, <
e 6 e GKA. .
Written By: Carl Barton Approved By: Albert Bolon l
l . .
I 9;O,0 i 3
.Oh
- . D'ufi i i U d. L E ij. [O j j h. ] -
} *** UMR REACTOR STANDARD OPERATING PROCEDURES ***
i SOP: 810 TITLE: WEEKLY CHECK Revised: September 12,- 1990 Page 5 of 14
. 2.Q sec. period, and 150% full. power). Reset- -l l the period. trip light-on the Log N &-Period >
l Amplifier._ This allows for reset of_allLannun- ;
} clator lights except low CIC-voltage. l 4
-4. When the High1 Voltage on.the Log N:CIC power -
supply has. increased to-approximately-500V,. t
, . push alarm reset. The voltage alarm: light will- i go off_ allowing the' operator to reset the rundown-(push rundown reset)_and resetrthe 4 annunciator. i
! 5. Record'value of trip point.
). G. . Regulating Rod on. Insert Limit on Auto
!- 1. Withdraw the-Shim /Safet'f rods to'3 inches and Reg Rod to 0.5 inches'(use the-shim ~ range bypass). . '
l 2. Adjust Linear recorder.setpoint'so that " auto i
permit" comes on.1 l 3. -With regulating rod'at approximately 0.5 inches l a
- withdrawn, : switch the c Reg Rod control- to Auto"
- and reset-the
- annunciator. _
L 4. Adjust the red-pointer (auto-.setpoint)uto:be i slightly below black pointer,(LinearE. signal) so?
that an insert on the. Reg" Rod 4will" result.
- 5. When_the Reg Rod reachessinsertil'imit! observe i- Manual Operation"and1" Reg:Rodfinsert 1imitLon_
l Auto" annunciators. ~ ~
- 6. Acknowledge and reset' rundown and-annunciators.
- 7. Record results.
- 3. SCRAM fred lichts):
A. Bridge Motion scram I
1.- Withdraw, rods to 3-inches. . .
I
'2. Release bridgetlock:and move the. bridge:a small distance;.
L 3.. Observe a' Bridge Motion k. Manual Scram and' Mag-L net contact' lights off.? Acknowledge the annun- '
r.
~
clator. alarm.
-4.- Return bridge to.originalLpositio~nfandireset
- all annunciators.- Re-insert theimagnets.
k
,j ?
Written By: Carl Barton : Approved;By: Albert _ Bolon -- ,;
l l- . , , - . . , - - - , - - . .
,, g a : J
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 6 of 14 i
S. Record results. l B. Period < 5 Seconds
- 1. Withdraw rods to 3 inches.
- 2. Push in and turn trip switch on the Period Sec-tion of the Log N Amplifier.
- 3. Observe Period Meter for, s 30 second and 5 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 period trip test light on the Log N Amplifier and push reset buttons for rundown. Insert magnets and reset annunciators.
- 5. Record value.
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 Rev.
lights go out. Acknowledge annunciators.
Reset Manual Scram and reset annunciator.
Insert the magnets.
- 4. Record results.
l D. 150% Full Power Scram I
- 1. Withdraw rods to 3 inches.
, 2. Push Scram test button on Safety Amplifier.
I Hold button until both power range meters read l full scale and 4 red test lights are on, and ;
Magnet power light is off. T
- 3. Push reset on the Safety Amp., acknowledge the !
i annunciator and observe the 150% Full Power Scram annunciator and Magnet Contact lights are off.
k E Written By: $$1Barton Approved By: Albert Bolon l
I
-. , _ _ .. . _ . _ ~ _ _ _ . ~ _ . . . _ - _ . . _ _ _ _ . . . __ __. . _ . . _ _- _ . _ _ . . _ .
1 Ob $: ) J '
- I .Jh-j J5v kaakl.) bd3 i
i *** UMR REACTOR STANDARD OPERATING PROCEDURES ***
' SOP: 810- TITLE: WEEKLY CHECK Revised: September 12,=1990 Page. 7 - of 14 1
- 4. Reset annunciator and insert the magnets.
- 5. Record results.
T l E. Manual Scram i r
l 1. Withdraw rods to 3 inches.
- 2. -Push-Manual Scram button, i j 3._ Acknowledge the
- annunciator, observe-Manual
{ Scram light-and all. magnet contact lights are.
4 off. Push Scram Reset, Annunciator. Reset and.
)' insert the magnets.
- 4. Record results, i
- 4. ROD DROP CURRENTS:
- 1. Withdraw:rodsIto-3 inches.
3 .2. Using a screwdriver slowly reduce magnet cur-- Rev.
j rent using current' adjustment #1, until the #1
! magnet' contact light,goes out-(you_should-also-hear an audible " click" from,the-Reactor Bridge I Intercom Station). : Record this' drop current- 4 value.
i 3. Repeat Steps l'and 2-for Shim Rod No. 2. and :No . "
l 3.
- 4. Insert alliShim~ Rods to insert limit.- i
- 5. ' Set all.. Magnet Currents.to " normal"1(i.e.- Drop; Current plus 10 ma). .,
- 5. TEST OF ANNUNCIATORS: I
. -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.- ui
- 2. Check for local red alarm' light and/for white [
annunciator light on! control panel. _ Return redi 7 needleto normal'(10K)1 set point, . reset' alarm. J and annunciator.
~
- 73. Record results.. .
i f'.
i !
I l-
- l t -
b -
i tiritten'By: Carl Barton- Approved By: , Albert Bolon- .
N
.h m - -+=>.tr - g-r- - e-/ WF y W $
. . . _ . _ , ._ m . . _ . _ _ ._ .. .
j- i h[Wma.;;
L& MW g203 5 70 OCTf i
j *** UMR REACTOR STANDARD OPERATIN
C. PROCEDURE
S ~***
i SOP: 810 TITLE: WEEKLY CHECK l Revised: September 12, 1990 _Page 8 of 14 B. Interlock Bypass ,
1
-1. Bypass-each interlock one-at time to ensure that each individual bypass operates the annun-j- clator and the bypass lights.
C. Servo Limits 4 i
- 1. Note linear level recorder reading. _ _
i
- 2. Change the automatic set: point-for' auto permit-i .by adjusting the star wheel. Note linear level-4
-at which light comes oni(<+2%). : Continue-to-
- lower and note-reading-untilEthe auto. permit ,
L light goes off-(> -2%). _
- 3. Reset automatic--set _pointLto the3100%-level.-
- 4. Record-results.
1 D. Pool Demineralizer Effluent-Conductivity High-Have an individual station himi(her)fself at
~
i 1.
! the conductivity = monitor'and.-s' elect-thel l intermediate, level- station on the~' building-intercom.
- 2. Have the individual'. select " Meas B" (Demineral--
I izer Effluent) Land then_ reduce'the setpoint.
value until'the red._(low): alarm light-comes on.:
l At this time the annunciator,should also alarm.
[ 3. The' Control-Room-Operator;should then~ inform the individual stationed at the demineral-izer ;
lC to-return the-setpoint to;thec0.'5 Megachm value
- (green light should come;on'). 1
-4.
~
! -With this step complete return'buil'ingiinter- d
!- com to normal status,' reset the-' annunciator.
5.- Record results. !
" REACTOR ON" LIGHTS:
6.
! A. ~With Magnet = key inserted and;all.. scrams? reset check._
~
the " reactor on" 1ights-(1) above console(2) at' j : reactor entranceland;(3l)~ basement-level.
- - Written?By
- Carl Barton 1 < .
. W Approved By: -Albert Boloni o
. .~, -~-.44, , , - -
. .. . . . . . - _ . - . . - - . - - . . . .. _ , . . . . - _ - ~ .-. . . . .
3
[ J b
- UMR REACTOR STANDARD OPERATING PROCEDURES ***-
SOP: 810 TITLE: WEEKLY-CHECK-i Revised: September 12, 1990 Page 9 of'14 i
i i j i i "
- 7. BUILDING EVACUATION ALARfd:
- A. Announce over the PA, "The' Building Alarm will=
j sound,.. 'This is a-test. Do'not evacuate the build-
~
ing." _
)
B.
~
i Push the Building' Evacuation Alarm:(center),of-reactor console) and. note the audible' alarm. -
, C. Reset Building Evacuation Alarm by-pushing Scram '
i Reset.
D. Announce over building PA " Test-alarms complete.
- Acknowledge all further alarms.". 1 d 8. NITROGEN DIFFUSERS
- f
- l 4
A. With the bridge. intercom station selected,-start diffuser _#1._ The green. operation-light sho'uld illu ~ l minate. Note 4the: sound.-level of the pump _and no. l j unusual = noise. r i B. Shutdown the--#1 pumpLand repeat step lifor the=#2L !
nitrogen diffuser.
~
'i i C. Record results Lon : form -SOP . 810.
4
- 9. BEAM PORT AND THERMAL COLUMN WARNING LIGHTS
- =
s .
A. - Announce~over.the building:PA. "
.Attenti'on! person- 1 l
l .
nel, stand- clear - of = the c Beam Port'! .,
L B. Open the Beam Port lby1 holding theibeam port con-i trol switch in thefopen position'untillthec" Red"'
- j. (open) light.comes.on. '
l . C. Acknowledge the annunciator alarm:and1 check the
- Basement Level; Warning-Light-(Flashing Red).
L D. Close,the Beam! Port by. holding.the Beam Port-Switch until'the Green,(closed) light,comes on._. .
- Reset the annunciator;andtobserveLthat;the light
~
- . goes out. . .
i
. Building PA'" Beam Port secured".
!- E; -Announce.over1the: .
l- Complete SOP.810.
Dispatch a knowledgeable individualLto the Thermall 'E i F. .
- Column with the Thermal.: Column Key.:; Select the:
, - Basement LeveltStation.on-the: Building Intercom. .. ,
J G. - Address - the ; operator'. cverj the intercom: to open thee .
Thermal Column until the. warning _l-ight comes on' l
'('approximatelyfliinch) . .
!. . Written.By:" Carl-Ifarton. ' Approved By: -Albert'Bolon 1
i
.y .-y -
$ ea i r , ,.- - - - ,*,--e.- ,e.
h?R Ori *'
74 WNbh&s pm' '
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 10 of 14 H. The Control Room Operator should observe and ac-knowledge the annunciator alarm. Inform the Thermal Column Operator to shut the Thermal Column and ensure the warning light goes off.
I. Reset the annunciator and have the Thermal Column Operator return the key to the locker. Complete lRev.
form SOP 810.
- 10. SHUTDOWN CHECK:
A. Complete a Shutdown Check List form 103 to ensure that all console equipment is secured.
- 11. SECURITY SYSTEM: ,
y' Inform the campus police (4300) that the 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 bclt switch by releasing or opening dead bolt 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.
EYE Written By: Carl Barton Approved By:
$N dW Albert Bolon
.. 6 I ,
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 11 of 14
- b. Momentarily depress the alarm button. The campus police should indicate the satis-factory 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 Rev.
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.
- e. When all intrusion channels have been tested, ask campus police to check the battery circuit. This completes the Rev.
security check.
- f. When all channels of the security system have been functionally tested and operate properly, initial the weekly checklist, Form SOP 810.
el.
l l
l Written By: Carl Barton Approved By: Albert Bolon l
l i.
JI E Od
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 12 of 14 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 (5) Temperature recorder B. Log count rate <2 CPS Actual Trio Point Annunciator Prohibit Initial C. Period <30 seconds D. Inlet Temperature >1350F E. Shim Rods below shim range
- 2. RUNDOWN CHECK A. RAM System Remote and Station Bldg. Alarm Local Alarm Annunciator Rundown Trio coint Initial i 1.
1.
2.
3.
B. 120% Demand rundown Actual Trio Point Annunciator Rundown laitial C. Period 15 seconds rundown 4L v s Written By: Carl Barton Approved By: Albert Bolon I
%f 7[1
, UU54 l 7 !L;d.
d M'JdLd OO177
'j
- UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WFEKLY CHECK Revised: September 12, 1990 Page 13 of 14 Date D. 120% Full Power Rundown Actaal Trio Point Annunciator Bundown Initial E. Low CIC Linear P S.
F. Low CIC Log N P.S.
C. Regulating Rod on Insert Limit on Auto
- 3. SCPRf CHECK Actual Trio Point Annunciator Scram Initial A. Bridge Motion Scram B. Period <5 Seconds scram C. Log N Period Non-operative Sccam D. 150% Full Power Scram E. Manual Scram 4 ROD DROP CURRENTS Dron Current Contact Licht off Initial A, Rod #1 B. Rod #2 C. Rod #3
- 5. TEST OF ANNUNCIATORS A. Beam Room High Neutron Flux i i
I Local Alarm Licht Annunciator Initial i
i
/l : 0 Written By:
.A Carl Barton
- f w Approved By:
bb Albert Bolon 4%
m PGMTan.';Cd uunanULL (e buff nn 3 L *** UMR REACTOR STANDARD OPERATING PROCEDURES ***
SOP: 810 TITLE: WEEKLY CHECK Revised: September 12, 1990 Page 14 of 14 l
Date B. Interlock Bypass Annunciator Initial (1) Shim range (2) 30 second period (3) Radiation area high (4) <2 CPS j C. Servo Limits Lin. Rec. Reading Permit on at Permit off at Initial D. Pool Demineralizer Effluent Conductivity High Local Alarm Annunciator Initial
- 6. " REACTOR ON" LIGHTS Overational Initial A. Main Entrance B. Control Room C. Beam Room
- 7. BUILDING EVACUATION Alarm Ocerational Initial
- 8. NITROCEN DIFFUSER Pume Orerational Indicator Light On Initial A. #1 B, #2
- 9. BEAM PORT AL THEPBAL COLUMN WARNING LIGHT Annunciator Flashing Light Initial A. Beam Port B. Thermal Column
- 10. SHUT DOWN CHECK LIST Comoleted Initial
- 11. SECURITY SYSTEM Batterv Check
- 12. APPROVED AND REVIEWED Manager or Director (Rev. 8/90)
Written By:
Carl Barton 8
Approved By:
h D Albert Bolon l
- . _ _ . _ .. . . . . . - - _ _ _ _ - _ - _ - _ _ - A