ML20030D419
| ML20030D419 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 08/31/1981 |
| From: | Alger D, Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | |
| Shared Package | |
| ML20030D415 | List: |
| References | |
| NUDOCS 8109010368 | |
| Download: ML20030D419 (79) | |
Text
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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I
I REACTOR OPERATIONS ANNUAL REPORT August, 1981 I
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Compiled by the Reactor Staff Submitted by
<dL$2' J. C. McKibben R..actar Manager I
Reviewed and Approved l
Q D. M. Alger I
Associate Director hD b0 ' O!b 6
p PDR
c TABLE OF CONTENTS Section Page I.
REACTOR OPEMTIONS
SUMMARY
1 II.
OPERATING PROCEDURE CHANGES 13 III.
REVISIONS TO THE HAZARDS SUMitARY REPORI 24 IV.
PLANT AND SYSTEM MODIFICATIONS.
25 V.
NEW TESTS AND EXPERIMENTS 28 VI.
SPECIAL NUCLEAR MATERIAL ACTIVITIES 29 VII.
REACTOR PHYSICS ACTIVITIES............
32 VIII.
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT.......
36 IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS.........
39 X.
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS........
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SECTION I REACTOR OPERATIONS
SUMMARY
The following table and discussion surr, arize reactor ope:ations in the period 1 July 1980 to 30 June 1981.
Full Power Percent
- Date Full Power Hours MWD Of Total Time Of Schedule July 80 704.9 293.54 94.74 106.1 Aug 80 697.9 290.95 93.80 105.1 Sep 80 675.9 281.06 93.88 105.1
]
Oct 80 707.7 308.97 95.12 106.5 Nov 80 655.2 273.18 91.00 101.9 Dec 80 683.1 284.72 91.81 102.8 Jan 81 704.5 293.61 94.69 106.1 Feb 81 597.4 248.31 88.90 99.6 Mar 81 700.1 291.77 94.10 105.4 Apr 81 619.1 258.30 85.99 96.3 May 81 692.9 288.83 93.13 104.3 June 81 620.2 258.70 86.14 96.6 Total For Year 8,058.9 3,371.94 92.00 103.3
- MURP, is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week at 10MW. Total time is the number of hours in a month or year.
JULY lE80 The reactor operated continuously during July, with the following exceptions:
two maintenance shutdowns on July 14 and 28; nine scheduled shutdowns for flux trap sample changes; and five unscheduled shutdowns.
The reactor was shutdown due to loss of facility electrical oower on July 2 and July 3.
The loss of electrical power was verified by the city power plant in both instances.
A reflector differential pressure scram occurred on July 9 and again on July 8.
Each time the breaker for pool pump P508B had tripped.
When the breaker was thoroughly checked on the maintenance shutdown on July 14, the electrician found a poor connection between the breaker contact and starting relay.
This caused everheating in the breaker assembly af.d tripping of the breaker's thermal overloads.
A rod not in contact with magnet rod run-in occurred July 14, when control rod mechanism "D" was bumped during a silicon sample handling evolution.
Major maintenance items for July included repairs to the silicon sample unloader, the pool pump breaker (P508B) and the particulate off-gas recorder.
I AUGUST 1980 The reactor operated continuously during August with the following exceptions:
one maintenance shutdown on August 25; a maintenance period following the unsched-uled shutdown on August 3; nine scheduled shutdowns for flux trap sample changes; and five unscheduled shutdowns.
The reactor was shutdown by manual rod run-in on August 3 when an improper valve line-up resulted in sending water not meeting primary grade specifications to the primary hold-up tank (T-300).
In accordance with technical specifications, T-300 must contain greater than 2000 gallons of primary grade make-up water to operate in Mode 1.
This occurrence was reported to the Nuclear Regulatory Com-mission in a letter dated August 29, 1980.
When the primary systems were being shutdown following the manual rod run-in on August 3, the primary inlet isolation valve (V5078) failed to shut when operated remotely.
The valve was then shut by disconnecting the tubing M t:ie solenoid valve and manually venting off the air pressure.
The failure cf the isolation valve to shut was due to the installation of an improper -(oversized) lower seal on the solenoid control valve actuating piston, preventing the valve from venting properly.
This incident was reported to the Nuclear Regulatory Commission in a letter dater August 29, 1980.
On August 4, a reactor startup was terminated by a manual rod run-in when the source range indication became erratic.
The source range detector was re-placed and no further problems were experienced with the source range.
Two scrams occurred on August 5, both due to temporary losses of electri-cal power to the facility.
The power losses were verified by the University Power Plant.
The reactor was shutdown by manual scram on August 21, when Reactor Services notified the Control Room that the wrong sample had been removed from flux trap tube "B" during the previous sample changeout.
This error resulted in tube "B"
holder being 1" short of samples and spacers. This occurrence was reported to the Nuclear Regulatory Commission in a letter dated September 18, 1980.
Major maintenance items for August included removal of the Nuclepore irradiator case, the rebuilding of three-way valves for V507A, V527C and V526, and replacemeat of the source range detector.
SEPTEMBFR 1980 The reactor operated continuously during September, with the following ex-ceptions:
two maintenance shutdowns on September 8 and 22; nine scheduled shut-l downs and three unscheduled shutdowns.
A reactor scram occurred sentember 16 when the f
-lity lost electrical j
power. The power outage was verified by the city power plant.
A power level interlock scram occurred September 22 when the motor-to-prip coupling failed on primary pump, P501A.
The Machine Shop repaired and aligned P501 A and the reactor returned to normal operation.
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The reactor was chutdown by rod run-in on September 30, when the Rod Run-In Trip Actuator Amplifier (TAA) failed. The electronics technicians replaced the TAA and associated relays,1K8 and 1K9.
The rod run-in circuitry was tested and the reactor returned to normal operation.
Major maintenance items for September included the calibration of nuclear instrument channels 2 and 4, the repair of P501 A and the rod run-in trip actuator amplifier.
OCTOBER 1980 The reactor operated continuously during October viith the following exceptions:
two maintenance shutdowns on October 6 and 20; eight scheduled shatdowns and one unscheduled shutdown on October 23.
The unscheduled shutdown was due to the failure of 529G, a solenoid which supplies operating air to the pool system isolation valve (V509).
The failure of this solenoid caused V509 to shut, causing a power level interlock scram.
Af ter replacing the solenoid, V509 was tested and found to operate satisfactorily.
A reactor operations inspection was conducted by NRC Region III inspectors K. Ridgeway and K. Connaughton from October 8 to October 10; no items of noncom-pliance were found.
A letter dated October 20 was sent to the Nuclear Regulatory Commission detailing '.he events of September 22, 1980. While performing a semi-annual complian e check on the reactor coolant high temperature scram unit 980A, the meter relay trip unit failed to activate in response to a scram signal. The relay unit was replaced and the compliance check completed satisfactorily.
Major maintenance items for October included the alignment of P501A and the removal of tSe Nuclepore irradiator case from containment to an anti-contamina-tion room outside the truck entry door.
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NOVEMBER 1980 The reactor operated continuously during November, with the following ex-ceptions:
four maintenance shutdowns on November 3, 10, 16 and 23, eight scheduled shutdowns and two unscheduled shutdowns.
A reactor loop high temperature scram occurred November 6, after a reactor startup following a scheduled shutdown for flux trap sample change.
Secondary pumps P-2 and P-3 were found to be air-bound,i e_uiting in low secondary flow.
The pumps were vented, secondary flow restored and the reactor returned to nor-mal operation.
A reactor scrrn occurred November 18, when the facility lost electrical I
power. The power outage was confirmed by the power plant.
Major maintenance for November consisted of two spent fuel shipments, preparations for a third fuel shipment, repair work on the Nuclepore irradiator case and the inspection of offset mechanism "D".
DECEMBER 1980 The reactor operated continuously during December with the following excep-tions:
three maintenance shutdowns on Daember 1,15 and 29; eight scheduled shutdowns and two unscheduled shutdowns.
A rod not in contact with magnet rod run-in occurred December 7, when con-trol rod "A" mechanism was bumped while handling a silicon sample.
Jn December 17, a reactor loop high temperature scram occurred when the bulb which actuates the photoelectric cell in meter relay 980B (HX 503B) burned out.
The bulb was replaced and the scram function of the meter relay was tested and found to meet compliance check specifications.
Major maintenance items for December included a spent fuel shipment, the replacement of DI-200 bid "M" with new bed "P", and the changeout of the offset mechanism for rod "B".
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JAfiUARY 1981 The reactor operated continuously during January, w:th the following excep-tions:
two maintenance shutdowns on January 9 and 15; ten scheduled shutdowns; four power reductions to work on the Nuclepore irradiator case; one power reduc-tion to enter the thermal column to remove a stuck radiography sample and one un-scheduled shutdown on January 28.
The unscheduled shutdown was an intermediate range channel 3 short period rod run-in. The short period signal was due to electronic drift in the instru-ment. The high voltage power supply and voltage regulator were replaced and the reactor returned to operation.
Major maintenance activities in January consisted of the replacement of a line bearing in primary pump P501 A and continued work on the Nuclepore irradiator case. The Nuclepore case was returned to service in January following an extended outage. Operational data and effluent analysis indicated that the new equipment was functioning very well.
On January 9 and 10, for a period of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, 40 minutes, the reactor was operated with low air flow through the stack radiation monitor due to the associ-ated air blower being secured.
This blower harl been inadvertently left secured by Electronic Shop personnel after performing a calibration of the iodine instru-ment during a reactor start-up check. This incident was reported to the Nuclear Regulatory Commise ;on ir. a letter dated February 5,1981.
The addition of a
" blower on" light in the control room to prevent a reoccurrence of this problem was completed March 23, 1981.
F_EBRUARY 1981 The reactor operated continuously during February with the following excep-tions:
two maintenance shutdowns on February 9 and 23; eleven scheduled shutdowns and six unscheduled shutdowns.
Two unscheduled shutdowns occurred on February 10. The first was caused by a short period scram from the failure of intermediate range detector channel 3.
The detector was replaced and a reactor startup was begun.
During this startup, a rod not in contact with magnet rod run-in occcrred when rod "D" dropped from its magnet.
Rod "D" was inspected and debris was removed from the magnet seating surface.
I On February 13, during a hot startup, a channel 3 short period scram occurred.
Channel 3 failed with meter indication upscale.
The drywell for channel 3 was found to be leaking at the support bracket on the refuel bridge.
Af ter the dry-well was repaired by the Machine Shop, channel 3 detector was reinstalled and a reactor startup was commenced.
During this startup, the reactor was manually e
scrammed whei, the reactor operator noticed a negative period on channel 3 while pulling control rods while still subcritical.
This was caused by reversal of leads when channel 3 detector was reconnected to the channel 3 drawer. The drawer connections were made properly, a front panel check was performed and the reactor returned to operation. This incident was reported to the fluclear Regu-latory Commission in a letter dated March 13, 1981.
During 10 !"1 operations on February 14, the regulating blade shifted out of automatic control resulting in a power reduction to about 2.5 MW's.
Power was controlled at this point in manual control until the regulating blade circuitry could be inspected.
tio abnormalities were discovered and the reactor returned to I
normal operation in automatic control.
While shutdown for regularly scheduled maintenance on February 23, the ac-tuator for one of the reactor convective cooling loop isolation valves was found to no longer be capable of moving the valve to the fully open or shut seats.
The parallel isolation valve functioned properly and safety analysis assumes only one of the parallel valves will function.
The valve was rebuilt and tested satisfactorily.
This was reported to the Nuclear Regulatory Commission in a letter dated March 17, 1981.
Also on February 23, one of the air charging valves for the containment leak check system was found open.
This valve is un a 3/4" line leading directly from the facility basement to the containment building. A valve line-up was con-ducted and a pipe plug installed in the line. This was reported to the Nuclear Regulatory Commission in a letter dated March 17.
A rod not in contact with magnet rod run-in occurred on February 24 when rod "D" fell off its magnet while shimming control blades.
The rod "D" drive mechanism was pulled and the magnet and anvil were inspected and aligned.
Major activities in February included a reactor operator license examination on February 9, research into a secondary-to-primary calorimetric power indication mismatch (found to be due to secondary flow transmitter being out of calibration),
emergency repair of channel 3 drywell and repair of reactor convective valve V546B.
MARCH 1981 The reactor operated continuously during March, with the following excep-tions:
two maintenance shutdowns on March 9 and 23 and nine scheduled shutdowrs.
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There were no unscheduled shutdowns in March.
Major maintenance in March included the replacement of offset mechanism "D" I
l (Modification Package 81-6); the installaticn of a poly bushing in offset "B" (Modification Package 81-5); and the addition of a " motor on" light in the control room to monitor the off gas system blower (Modification Package 81-3).
APRIL 1981 The reactor operated continuously in April with the following exceptions:
three maintenance shutdowns on April 6, 20, 27; nine scheduled shutdowns and I -
eleven unscheduled shutdowns.
The reactor was shutdown by manual rod run-in on April 3 to replace a failed bearing on the inner airlock door.
During a normal reactor startup on April 6, the failure of channel 6 nuclear instrument detector to respond sufficiently to power level changes resulted in a menual rod run-in. The channel 6 detector was replaced and the reactor returned I
to operation.
Two scrams due to less of facility electrical power occurred in April (April 9 and April 16).
Both electrical power losses were verified by the University Power Plant.
The reactor was shutdown by manual rod run-in on April 11, when a reactor loop high temperature alarm was received.
The cold leg temperature indicated 172 on the chart recorder, but the digital indication from the same unit was normal and a separate cold leg recorder also indicated normal temperature.
The reactor Jas returned to operation with no further problem of this nature.
Later, on April 11, the reactor was shutdown by manual rod run-in when one of two operators had to leave the facility, resulting in only one licensed oper-ator available.
A second licensed operator was called in and operation resumed.
There were two manual scrams and one manual rod run-in to repair fire main leaks. This water source is required by technical specifications for reactor operation. These shutdowns occurred twice on April 12 and once April 18.
The reactor was shutdown by manual scram on April 16 to replace the drive sprocket on the cuter airlock door.
The reactor was shutdown by manual scram on April 25 when a loud explosion was heard on the beamport floor. The reactor was returned to normal operations after investigating the problem and discovering an air dryer unit supplying con-trol air to the Nuclepore experiment exploded due to overpressure.
The control
_g.
air system for the Nuclepore has no effect on reactor operations.
Major maintenance items for April included work on the fire main system, the replacement of channel 6 nuclear instrument detector and two reactor test procedures - RTP-4 (Control Rod Calibration) and RTP-17A (Flux Trap Sample Reac-tivity Detennination).
During compliance check 22 (Primary Pressure Switch 944 A/B and Pressure I
Transmitter 943) conducted April 20, the meter relay unit for pressure transmitter 943 failed to provide a scram.
The meter relay unit was replaced, the compliance check completed and the reactor started up upon completion of scheduled mainten-ance. This incident was reported to the Nuclear Regulatory Commission in a letter dated May 18, 1981.
All similar meter relay units used in the protection system were bench tested and verified operable on the April 27 maintenance day.
MAY 1981 The reactor operated continuously during May with the following exceptic,s:
nine scheduled shutdowns for flux trap sample changes; two shutdowns for main-tenance days on May 4 and May 18; and four unscheduled shutdowns.
Two shutdowns by rod not in contact with magnet rod run-in occurred in May, one May 4 and another on May 5.
Both were due to rod "D" disengag..ig from its magnet.
In both cases, the cause of the rcJ drop was due to misalignment of the upper housing.
Two unscheduled shutdowns occurred due to loss of facility electrical power.
These occurred on May 18 and May 23. Both power in'terruptions were verified by the University Power Plant.
Major maintenance items for f/ay included completion of the building leak rate check, the replacement of P-4 check valve in the secondary-to-air-conditioning units' piping, and the dumping of DI-200 resin bed "N".
Two iiRC inspections took place in May.
NRC Region III Inspector G. Christoffer performed a safeguards inspection on May 5 and 6 and NRC Region III Inspector Ken Ridgway completed a routine inspection extending from May 18 to May 22.
3 JUNE 1981 The reactor operated continuously during June with the following exceptions:
four maintenance shutdowns on June 1, 8,15 and 29; eight scheduled shutdowns and seven unscheduled shutdowns.
A rod not in contact w{r5 magnet rod run-in occurred June 3 when red "D" dropped from its magnet. Moisture was found in the pins of rod "D" power connec-tor. After drying the connector, the reactor was returned to operation.
The reactor was shut down on three separate occasions by manual rod run-in to work on the personnel airlock doors.
On June 5, the shutdown was due to the airlock door gasket coming out of its seat. The other shutdans, on June 16 and 18, were aue to failures in the electrical control relays for the open-close sequence of the airlock doors.
The reactor was shutdown by manual rod rur.-in d~e to fluctuations in indica-tions provided by channel 3.
The channel 3 detector, cables and cont.cctors were l
l replaced and the reactor returned to operation.
On June 9, the reactor was shutdown by a high power scram channel 4 during a reactor startup.
The scram was caused by a static charge buildup in the wide range selector switch and was not due to actual high power on channel 4.
I A rod not in contact with magnet rod run-in occurred June 16 when rod "C" j
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dropped from its magnet.
The upper housing was realigned and the reactor returned to operation.
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Major maintenance items included the installation of offset #5 in rod "C" position, the installation of a new channel 3 detector ano the installation of j
i a new section of pipe in the fire main eraergency pool fill line.
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SECTION II i
OPERATING PROCEDURE CHANGES 2
As required by the MURR Technical Spec', fications, the Reactor Manager reviews and approves the Standard Operating and Emergency Procedures (50P).
Ten revisions have been made to the 50P during the past year. The revisions are contained in this section with the part of each page that was revised marked on the right side of the page by a vertical black line.
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l REVISION NO. 1
,I 8/05/80 I
SOP /VIII-ll Revised 8/80 50P/ Vill-12 Revised 8/80 I
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water and biological fluids will be doubly encap-sulated with the recondary encapsulation b.:ing a high density polyethylene rabbit.
3.
Powder samples will be sealed in a polyethylene vial and irradiated in a higS density polyethylene rabbit.
Boron and boron compounds in powder form I
will be sealed in high density polyethylent. within the rabbit.
4.
A metal liner such as cadmium sheet may be used in the rabbit providing it is in one piece and covers at least 80 percent of the rabbit's interior sur-face.
The experimenter shall take measures to insure that the heat generated by the metal can be dissipated and will not cause damage to the sample or rabbit.
5.
The experimenter shall insure that the sample is adequately secured in the rabbit (by polyethylene packing, etc.) so that the motion within the rabbit is minimized.
C.
Material which may be irradiated in the p-tube system includes water, plant and animal tissue and fluids, bone, air filters, soils, rocks, soil extracts, coal, paper, meteorites, fibers, dried paint, safe insulation and glass.
Pure elements, alloys and compounds not I
exempted in D below may also be irradiated subject to the activity limitations in A.
D.
Unless it is specifically authcrized in the experimenter's RUR, the following materials will not be irradiated in the p-tube system:
1.
Natural uranium; 2.
Special nuclear materials as defined in Title 10, Part 70, Paragraph 70.4m of the Federal Code of Regulations (i.e., plutonium, uranium-233 or I
uranium enriched in isotope 233 or 235);
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Pure elements:
Lio Na, K, Rb, Cs, Ca, Sr, Ba, Hg, Os, H, 0, F, Ne, Ar, Kr, Xe, and P; 4.
Compounds:
N,1 N0, CaC, Ca0, perchlorates, per-4 3
2 2, and Na 0 I 0
manganates, N 22 5.
Materials which chemically react with water to pro-duce undesirable quantities of heat and pressure; 6.
Any explosive, flammable, combustible, or toxic mate rials.
E.
The controlling factor for determining the weight and time I
limits of a sample to be irradiated in the p-tube is the activity limitation of section A.
If the activity limits do not further restrict a sample's size, the following weight mits shall apply:
1.
For irradiation times up to 30 minutes, the maximum weight of irradiated materials in one rabbit will be 2 grams with three exceptions:
a.
A maximum of 10 grams of water or dried feces; b.
Only 1 mg of chemical compounds in solution; c.
A maximum of 10 grams of boron, BC, or BN in the form of powder. The experimenter shall take measures to insure the heat generated can be dis-sipated without causing damage to the rabbit or sample.
2.
For irradiation times of 30 minutes to I hour, the
.ximum weight of irradiated materials in one rabbit wi:' be 1 gram Hith two exceptions:
a.
A maximum of 10 grams of water or dried feces; b.
Only 500 pg of chemical compounds in solutic...
The weight limits a'ove do not include the weight of the I
rabbit, polyethylene vial, or packing, or the candmium (or other metal) shields.
The maximum irradiation time for most samples will be one hour at power levels <5 MW and 30 minutes for power levels > 5 MW.
Hair, fibers, paint, air filters and flux m;nitors may be irradiated for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at power levels <5 MW and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at power levels > 6 MW.
The I
following additional limitations shall apply for irradiations
> 10 minutes:
1.
Primary encapsulation will be heat-sealed high-density polyethylene vials (Holland vials).
SOP /VIII-12 Pev. 8/80 App'p
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l REVISION NO. 2 1
l 8/25/80 I
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SOP /I-14 Revised 8/80 S0P/ III-6 Revised 8/80 SOP /VII-40 Revised 8/80 SOP /VIII-19 Revised 8/80 SOP /VIII-20 Revised 8/80
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Table IV Values of Trip Settings for Alarm, Run-In and Scram Conditions "c ram Run-In Alarm Units 1.
Short Period 9
11 sec 2.
Low Count Rate
<l. 0 cps 3.
High Power 120 li5
% full power 4.
RC Inlet Temp 152 148 F
5.
RC Outlet Temp 173 165 F
6.
RC System Low Flow 1675 1750 gpm 5 MW Operation RC System Low Flow 1675 2
2 1750 gpm 10 MW Operation 7.
Heat E:-hanger Low 1675 gpm AP (DPS J28A/B) 3 psig 8.
Rx System Low Press 61 Switch PS 944A/B 4
gpm 9.
Co re '
gpm Core Low AP,10 MW 3300 10.
Low Pressurizer Level 14 below{
10-13 below [
inch
- 11. Hi Pressurizer Wtr 12-15above{
inch Level 12.
Low Pressurizer Press 61 64 psig 13.
Hi Pressurizer Press 79 76 psig 14 Pool Low Flow, 5 MW 440 480 gpm Pool Low Flow,10 MW 440 2
2 480 gpm 15.
Pool loop Hi Temp 115 F
16.
Low Pri Denim Flow
< 42. 5 gpm 17.
Low Pool Demin Flow
- 42.5 gpm 18.
Bldg Air Plenum Hi 1.0 mr/hr Activity I Deleted 2For 10 MW operation, Alarm and Scram Received from Either Loop I3Pressurizer Pressure with normal system flow 4aP corresponding to this flow value Rev.
8/80 App'd _
SOP /I-14
E.
Set function switch to " operate".
Verify that " drawer
~
inoperative" lamp is extinguished.
F.
Verify that power level trip indicators are extinguished.
G.
Set function switch to " standby".
Verify that power level trip indicators are extinguished, that " drawer inoperative" light (DS16A) is energized, and that a nuclear instrument anomaly annunciation occurs.
H.
Set function switch to "zero".
Veri ff that both percent I
power meters (on the console and instrument cubicla) and the recorder indicate 012%.
Verify that a downscale light is received on the drawer and that a downscale alarm is received on the annunciator.
I.
Set function switch to 110%.
Verify that the console per-cent power meter and the recorder indicate 110% i 2% and the drawer meter indicates 110% 15%.
J.
Set function switch to 75%.
Verify that the console percent power meter and the recorder indicate 75% i 2%
and the drawer meter indicates 75% 1 5%.
K.
Set function switch to 10%.
Verify that the console percent power meter and the recorder indicate 10% i 2%
and that the drawer meter indicates 10% 15%.
L.
Place function switch in " cal" position.
Rotate reset switch tc left or ri;ht to clear rod run-in and scram trips.
Reset annunciator board.
Using the potentiometer provided on the front of the drawer, apply an input current equivalent to the desired trip point for rod run-in (114% i 1%).
Verify that rod run-in light (DS17A) is energized and that Channels 4-5-6 High Power Rod Run-In annunciation occurs.
M.
Apply an input current equivalent to the desired trip point for scram (120% i 1%).
Verify that scram light (DS16B) is energized and that Channels 4-5-6 high power scram annunciation occurs.
Rev. 8/80 App'd 50P/III-6
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I Note:
Rinse only long enough to obtain an increase in resistance.
If it stops, repeat VII.4.8.10; varying the flow rate may also help the rinse l
requirement.
Use minimum DCW for rinse.
D.
Let the water run to waste until the purity instru-ment shows a minimum resistivity of 500K ohms.
E.
Close all valves, then open the outlet valve on F301.
F.
The demineralizer is now ready for use.
I G.
Log regeneration complete.
VII.4.8.13 Providing DI Water to T300 DI water may be sent to T300 with or without the use of the I
reverse osmosis unit as a DI300 makeup supply.
Due to the fact that DCW, after passing through the R.0. Unit, is much more pure thar. raw DCW, the R.0. Unit is normally utilized to prolong the life of the DI300 resin regeneration.
Hew-ever, there are provisions for bypassing the R.0. Unit when sending 01-300 water directly to DI200.
(See VII.4.8.13a, b and c. )
VII.4.8.13a Providing DI Water to T300 with Reverse Osmosis Makeup 1.
Check shut valve 7 and open R0-8.
2.
Open T300 supply valve (Reach Rod).
3.
Open isolation valve for auto valve.
4.
Turn on conductivity meter and place auto valve in auto.
I Auto valve should be open, if nr i or if reading CAUTION:
is near set point, place normal, bypass switch j
to bypass.
(This is so. the R.0. Unit will not cycle on and off as the auto valve opens and closes. When the reading on the conductivity meter is low so the valves do not cycle, place normal, bypass switch to normal.)
5.
Place R.0. Unit in operate mode and push start / reset switch.
(Pressure should come up to 180-200 psig.)
e Rev. 8/80 App'd SOP /VII-40
C.
Report to the control room the material contained in the sample, the expected activity and dose rate, and the approximate time the rabbit can remain in the reactor without creating any hazard.
VIII.3.5.3 Rabbit Stuck in Tube Any time all or any part of the rabbit fails to return to the dispatch station, notify thc control room immediately about the problem, stating the material contained in the sample, the weight of the sample, the expected activity and dose rate, the approximate time the rabbit can remain in the reactor without crea:ing any ha; ard or melting.
A.
After the control room is aware of the problem, press the emergency return switch.
Observe the rabbi. in reactor light (CL-4) and check with the control room to see if the operators heard the rabbit leave the reflector region.
Note:
CL-4 is not a true indication of rabbit location.
It simply indicates the electronic control signal to the unit.
Hearing the rabbit dc art the re-r flector is the only sure way to know it has lef t.
If the rabbit was heard to depart the reflector region, check the connecting station to see if the rabbit uas returned there.
B.
Check the station lineup, verify the circuit selector switch (CB-1) is selected to the proper station as i
indicated by CL-2 or CL-3.
C.
Depress the reset switch (CB-3).
D.
Depress the dispatch button (CB-4) while observing CL-4.
E.
Repeat steps A through D several times as directed by the controi room.
F.
If the attempts fail, go to the connecting station, line it up for service and repeat steps A through D.
l 1
1 SOP /VIII-19 Rev. 8/80 Spp'd
/%
G.
If these procedures have failed, follow up action will be handled by reactor operations and Health
~
Physics personnel.
I Note:
If the rabbit is stuck outside the reactor it may be found by searching the guide tubes with a radiation monitor.
1 I
If the rabbit is stuck in the reflector, the rear. tor must be shutdown and the p-tube reno ved.
VIII.3.5.4 Wet Rabbit If the outside of the rabbit is wet when it is returned from the reactor, notify the control room immediately.
VIII.3.6 Emergency Return of Rabbit with Malfunctioning
^
P-Tube Control Box Dispatch and return of the rabbit is controlled by solenoids in cabinet located by the seal trench.
All solenoids in use are labeled by letters in the solenoid cabinet.
Pro-cedure to be followed in case of a failure at the local station is as follows:
A.
Remove cover to solenoid cabinet.
B.
Turn salenoid power switch off.
(This deenergizes all solenoids.)
(N0iE: This closes off all tubes which will result 4I in a high concentration of Ar if the reactor is operating.)
e
l REVISION f40. 3 9/30/80 I
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SOP /I-7 Revised 9/80 SOP /I-8 Revised 9/80 SOP / I-8b Revised 9/80 SOP /II-l Revised 9/80 SOP /II-2 Revised 9/80 SOP /II-3 Revised 9/80 l
SOP /II-4 Re-ised 9/80 l
'l l
l,
Table II I
ECP Acceptable Limits _
11" - 16" 1 0.40" 16" - 22" 1 0.70" 22" - 26" i 1.25" H.
Instrumentation Minimum nuclear instrumentation for startups shall be one source channel, two intermediate range channels each with period trip, two power channels each with flux trips, and one wide range channel with high flux trip.
I.
Use of the Public Address System Immediately prior to actual movement of the control rods, an announcement will be made over the public address system that a reactor startup has been commenced.
A second announcement will be made when the desired power level is obtained.
If during the startup the determination is made that power will be held constant at any level for a period of greater than five minutes an additional announcement will be made to inform building personnel.
J.
Health Physics Monitoring of Reactor Experiments During a Reactor Startup When a change is made to a beamport or other reactor experiment which could lead to significant alterations in area radiation levels as reactor power is increased, a Health Physics Technician will be assigned to continuoc?ly monitor that experiment throughout the startup.
Direct communications will be maintained between the Control Room and the Health Physics Technician. The Control Room will inform the Health Physics Technician at the following power levels.
1.
During a Normal Reactor Startup i
a.
When the reactor reaches criticality.
b.
When reactor power reaches 50 KWs.
O SCP/I-7 Rev. 9/80 App'd M
c.
When reactor power reaches 5 MWs.
(2.5 MWs
~
if operating in to.".a II) y d.
When reactor power reaches 10 MWs.
(5ffds f
if operating in Mode II) 2.
During a Reactor Hot Startup a.
When the reactor reaches crit 9 7.lity.
b.
When reactor power reaches 5 MWs.
(?.5 MWs if operating in Mode II) c.
When Reactor power reaches 10 ffds.
If direct communications are lost or if oree of the above reports is not acknowledged, reactor power will be maintained at a steady level until the problem is corrected. The Health Physics Techni-cian will make his final report to the Control Room after a complete survey is conducted at the desired power level.
I I.4.4 Normal Operation i
A.
Normal power level will be 9.90 to 10.00 MW as indicated by the total power meter.
B.
The control room shall be occupied by at least one licensed i
i operator during steady state operation of the reactor and a l
second licensed operator will be in the Facility Building i
and at a location where communication with the control room can be maintained.
y
'N C.
Prior to assuming control of the reactor, the oncoming operator will read the control room log book and shall be briefed on i
current operation.
4' D.
During shift operation, the shift supervisor for the new shift will review the log book and be briefed on current operations by the crew he is to relieve. Upon completion of the log book review, the shift supervisor will note the same in the log book.
E.
A complete set of Nuclear data will be taken once an hour during steady state operation.
y F.
A conplete set of Process data will be taken every two (2) hours during steady state operation.
Rev. 9/30 App'd SOP /I 8
l..
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1 SOP /I-8b Rev.
9/80 App'd @#m
Section II Reactor Operating Procedures 11.1 Routir.e Reactor Operation 11.1.1 Procedure for Reactor Startup For fe' power, closed pressure vessel operation, the reactor will be brought to its scheduled operating power le/el according to the procedure outlined below.
A.
Take a complete set of full power process data.
B.
Obhin from the Shift Supervisor an estimate of the critical banked contrnl blade position.
C.
Take a complete set of nuclear data on the Startup Nuclear Data Sheet.
D.
Complete the applicable startup checksheet required oy
(
Section I (I.4.3.F).
E.
Obtain from the Shift Supervisor permission to commence a 9
reactor startup.
F.
Announce via the public address system that a normal reactor startup has been commenced.
G.
Withdraw the four control blades in gang, stopping to take a set of startup nuclear data at five-inch increments.
Indicate in the console log book that startup has commenced.
H.
When the blades have reached a position within 2 inches of the estimated critical position, discontinue pulling in gang and take a set of startup nuclear data.
I.
Continue the startup, withdrawing only one blade at a time until the reactor power level is increasing on no less than a 30-second period.
J.
At the point where the reactor is indeed critical and on a positive period, a console log entry shall be made stating that fact.
Rev. 9/80 App'd
(
SOP /II-l
K.
Bring the reactor critical at a steady state oower level of approximately 50 KW unless a lower power level is de-sired for tests, calibration runs, etc.
The lowest steady state power level reached and any ensuing steady state power will be logged on the Startup Nuclear Data Sheet for a record of reactor operating time.
L.
Withdraw thL fission chamber to full out.
M.
Verify that all nuclear instrumentation is resnanding l
I normally.
N.
Take a complete set of nuclear data on the Startup Nuclear Data Sheet.
Indicate on this sheet the critical control and reg. blade positions and the primary and pool temperatures.
O.
Continue the sta tup, withdrawing only one blade at a time l
until the reactor power is increasing at no less than a 30 second period.
At power levels greater than 100 KW, main-tain the control blades such that the maximum difference in position between any two blades always remains less than 1 inch.
P.
As the reactor power level approaches 1 MW, increase the period until a stable period remains that is no less than 100 seconds for all power increases greater than 1 MW.
Q.
Bring the reactor critical at a steady state power level of 2.5 MW if in 5 MW mode of operation or 5.0 MW if in 10 MW mode of operation. At this power level:
1.
Verify that the nuclear instrume'ntation is in essential agreement with the at a a'. ;w.er level which can be read out directly t rom the digital calorimetric meter.
Note the actual power level in the coerations console log book.
In the case of the ca!orimetric meter being out of commission during a startup, the power level may be determined by manual calculation.
2.
Note the time of arrival and departure from this power level on the Nuclear Startup Data Sheet.
R.
Continue the reactor power increase by withdrawing only one control blade at' a time, maintaining the reactor period at no less than 100 seconds.
Rev.
9/86 App'd 6h SOP /II-2
g E
S.
As the scheduled power level is reached, adjust the control blades until the reactar is critical at the zesired steady
.3g state power in either the manual or automatic control mode.
~
T.
Switch IRM recorder from fast to slow speed and secure the z
}
SRM recorder and scaler.
U<
After the temperatures stabilize, take a complete set of nuclear and process data.
V.
Annour.ce to experimenters the reactor power level, schedule and note arrival in '.he log book.
I 11.1.2 Procedure for Hot Startup A hot startup shall only be made by a senior reactor operator, or a licensed reactor operator under the direct supervision of a senior reactor operator, Gang control of the rod drives may be used for the entire approach to critical and to override Xenon buildup if required.
A.
Take a set of startup nuclear data.
B.
Obtain an estimate of the critical banked control blade position from the shift supervisor.
C.
Obtain permission from the shift supervisor to commence a reactor startup.
D.
Announce via the public address system that a hot reactor startup has been commenced.
E.
Withdraw the four (4) control blades in gang, stopping to take a set of startup nuclear data at five inch increments.
Insure the stable period is no less than 30 seconds.
+5 E.
At 50 KW or when channel 1 indication is greater than 10 withdraw the fission chamber to full out position.
G.
Continue the startup, insuring that the maximum difference in position between any two (2) blades always remains less than one (1) inch.
H.
5tabilize reactor power at a power level of 2.5 MW in Mode II or 5 MW in Mode 1.
At this power 1m i:
1.
Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read out directly from the digital calorimetric meter.
Note I
the actual power level and the time of arrival in the console log book.
2.
Note the critical rod heights, power level, primary and pool temperatures, and arrival / departure times on the Startup Nuclear Data Sheet.
Rev.
9/80 App' SOP /II-3
l I.
Continue the reactor startup by withdrawing only one control blade at a time, maintaining the reactor period at no less than 100 seconds.
J.
As the scheduled power level is reached, stabilize power in either manual ok automatic control and complete hie following:
st 1
Switch the IRM recorder to slow speed and secure the EdM re-corder and scaler.
2.
Note the time of arrival in the console log book and in the Start-up Nuclear Data Sheet.
3.
Take a complete set of nuclear and process data as soon as the temperatures stabilize enouoh to get a representative AT on the primary and pool.
4.
Announce
, experimenters the reactor power level.
II.l.3 Assuming Automatic Reactor Control A.
Conditions to be met prior to " auto" operation.
Prior to assuming automatic control for reactor operation, the following conditions must be met:
1.
The period as indicated by both IRM-2 and IRM-3 must indicate not less than 35 seconds.
2.
The WRM selector switch must be in !..e 5 KW red scale ;;sition s
or above.
3.
The power trace pointer (black) on the WRM recorder must be reading greater than the auto control prohibits set point (red).
4.
The reg blade position must be greater than 60% withdrawn, such that 60% annunciator alarm is energized.
B.
Procedure To place the reactor into the automatic control mode.
1.
Set the low level trip (red pointer) in the wide range recorder so that the auto-control prohibit trip is at 75% of the desired operating power.
2.
Using the power schedule switch (159), bring the setpoint indicator to approximately 3% bel'ow a desired power level of >1000 watts as would be indicated on the black scale of the wide range monitor.
Rev. _9/80 ppp.d b
SOP /II '4
~,
REVISION NO. 4 12/19/80 SOP /II-9 Revised 12/80 50P/ II-10a Revised 12/80 SCP/II-11 Revised 12/80 I
\\
-l7-
I B.
Depress the manual rod run-in button on the control console.
Enter the time of shutdown in the. log book.
c.
Follow the reactor power decrease by changing the range I
selector switch so as to keep channel WRM-4 on scale.
D.
Complete the Reactor Shutdown Checksheet.
E.
Ascertain that the reactor system is secured and enter same in log book.
II.2.1 fuel llandling Procedure A.
All fuel transfers will be authorized by the Reactor Manager or his designated representative.
3.
If a fuel assembly is determined by the Shif t Supervisor to l
be damaged, authorization must be obtained from the Reactor Manager prior to ' ading that element in the reactor.
C.
The Special fluclear Materials Custodian (Reactor Physicist) shall provide a step by step fuel movement procedure anytime I
fuel is handled.
. D.
fuel, new or irradiated, shall only be handled one element E
at a time.
E.
The reactor will be shutdown prior to handling fuel in the reactor.
fuel may be handled in the weir area while the reactor is operating.
f.
Containment integrity is required anytime irradiated fuel is be ng handled.
i G.
Itealth Physics coverage shall be necessary when the pool is below normal operating level, inspecting irradiated fuel, shipping irradiated fuel and handling suspected ruptured I
irradiated fuel.
II.
One senior reactor operator and one reactor operator must be present to handle fuel.
Only a senior reactor operator, a reactor operator, or a reactor operator trainee under the direct supervision of a senior reactor operator may handle fuel.
The senior operator is in charge of the fuel handling evolution and is responsible for the puper conduct of the
(
evolution.
+
SOP / II-9 Rev. I2/80 App'd 1
(
the element by pushing down and turning until it floats off.
Failing to release the element in
... E
~
g this manner may res/t in accidentally lifting and leaving the element a few inches off of its seated position without realizing it.
11.2.2 Procedure for Handling Fuel in or out of the Core A.
Obtain a fuel handling secuence from the Reactor Phyticist.
B.
Inspect the fuel handling tool.
C.
Place the bridge ARMS to upscale po-ition.
, ump the D.
Insure the pool is at the normal Operating level or pool to refuel level as necessary.
E.
Remove the pressure vessel head.
F.
Turn on the Source Range Monitor Scaler and Chart Recorder.
I Drive in the fission chamber to = 1000 counts.
G.-
At tach a fuel element to the handling tool.
H.
The operator handling the fuel element tool shall verify that the element 'is fully latched and verbally report this to the supervising Senior Reactor Operator.
NOTE: A positive latch is achieved only when the red plunger on the air-handling tool is fully re-tracted and flush with the cylinder. Any pro-trusion of the plunger means the fuel ele.aent I
is not latched.
I.
Remove and visually identify the fuel element and place it in the position specified on the loading sheet.
J.
Verify the element is seated in its new position.
If in the reactor, utilize board and reference mark.
K.
A reactor operator or senior reactor operator shall initial the loading sequence sheet after each step.
L.
A senior reactor operator will inspect the core prior to replacing the pressure vessel head.
I M.
Install the pressure vessel head.
(If the pressure vessel head is to be left off at this point, install the aluminum l
protective head on the pressure vessel.).
l Rev.12/80 App'd _ N Ac, SOP /II-10a
,n,
.~p.-n.,
4
-N.
Record that the reactor has been defueled or refueled indicating the identification numbers of the cores involved and the ~ fact that the new core has been in-spected.
O.
Post the fuel elemen' locations data sheet in the control room.
.P.
Turn the bridge ARMS back downscale.
0.
Secure the SRM and pull the fission chamber to full out.
II.2.3 When starting up th.! reactor after any fuel change in the core, the predicted critical position shall be verified by the Reactor Physicist.
If the reactor has been loaded with a new mixed core, a 1/M plot shall be made on tiie subsequent start-up.
II.3 Control Blade Offset Mechanism Removal 11.3.1 Conditions Prior to Removal A.
The control rod offset mechdsm will not be removed except by authorization of the Reactor Manager.
B.
The removal of the assembly will be supervised by the shift supervisor or a senior operator.
C.
When one offset mechanism is to be removed:
1.
The core will be defueled of two fuel elements; 2.
The balance of the other three rods will not be l
raised from their fully lowered pcsition without approval of the Reactor Manager.
D.
When more than one offset mechanism is to be removed, the core will be defueled of at least two elements for each offset mechanism removed.
E.
A Health Physicst or a Health Physics Technician is to be present when tb pool water is lowered and when the mechanism is brought out of the water.
Rev. 12/80 App'd _Ry y 50P/II-11
.a.__,=....
__.. ~,
n- :-,
~c-
i
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,I l
SOP /VII-63 Revised 1/81 SOP /VII-64 Revised 1/81 SOP /A-4 Revised 1/81 l
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I,
door 101 and the personnel air lock doors.
With the reactor operating the compressor for isolation valve lob ma, only be electrically secured when the valves are placed in the closed position.
Snould this be necessary, open the local switch only, because the main switch also provides power to the facility and reactor isolation systems.
The instrument air compressor may be shutdown by opening its local breaker.
Its main supply may be secured at breaker #3 of LP-ll.
If secured and air supply is still required, the cross connect valve from the main compressor may be opened.
If any of the components or compressors above are secured I
or placed in a position other than normal, Lne component shall be tagged in accordance with the tag-out procedure.
VII.ll Beamport Water System See Section VIII.4
'!TI.12 Sulphuric Acid System VII.12.1 Receiving Bulk (concentrated) Acid CAUTION:
This process is extremely dangerous.
Protective equipment must be worn.
Always have an available supply of water and sodium bicarbonate.
Bulk sulphuric acid is delivered by tank truck and is transferred to the storage tank by air pressure or gravity drain.
When possible the gravity drain method should be used.
In the event air pressure must be used, extreme caution should he exercised.
The tank truck can easily exceed the receiving capacity of the system.
Insure that the taak pressure does not exceed 15 psig. and closely nonitor tank levels.
Rev.
1/81 App'd (Oh SOP /VII-63 t /
s-
A.
Check valve 1 closed and valves 2 and 3 open.
B.
Crack open the Tank-O-Meter bubbler valve 7 to give an air flow of 3-4 bubbles per second.
Note and record the tank level indicated on the Tank-0-Meter.
C.
Remove the cap on the fill line to enable connection of the transfer line from the truck.
Commence filling the tank.
D.
While the tank is filling, watch the Tank-O-Meter to insure that an air flow of 3-4 bubbles per second is maintained.
CAUTION:
If the system is over filled acid will spill into the mixing tank.
The heat generated at this point could res"It in damage tu the acid handling system.
E.
When the tank volume rea:hes 750 gallons, secure the transfer.
F.
Disconnect the transftr hose into the strrage tank.
G.
Record the final volum2 of the tank and report to the truck driver the amour.t of acid received.
Close the bubbler valve.
VII.12.2 Transferring Ac.id from the Storage Tank t-the " Day Tank" When the acid in the day tank has been used, the tank is refilled with acid from the storage tank by carryino out l
the following procedure.
l l
A.
Check valves 2 and 3 open.
B.
Crack open the bubbler valve (7) to give an air flow l
of 3-4 bubbics per second.
Rev.
1/81 App'd A
SOP /VII-64
'C-) b App'd UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Rev.
~1/22/81 ~
REACTOR SHUTOOWN CHECKSHEET DATE 1.
Time of reactor shutdown..........................
2.
All blades bottomed and drive mechanism full in.....
3.
Magnet current switch off..........................
I 4.
S RM s e t to req u i re d po s i t i o n...............................................
5.
Reactor primary system shutd: ~n per 50P IV................................._
6.
Pool system shutdown per S0P V....................................
7.
Secondar" system shutdown per 50P VI......................................._
a.
Cor t i n g towe r fa n s o f f...............................................
I 8.
Digital readout switch off.................................................
9.
Annunciator board on off 10.
Reverse osmosis unit secured...............................................
11.
Sample inventcry satisfactory and data sheets updated......................
12.
Si integrators recorded....................................................
13.
All bypass switches off and keys en key box................................,_
14.
Master switch off on 15.
DCT system secured.........................................................
16.
Room 114 check:
I Cooling flow to P501A/B secured.......................................
a.
b.
Va l ve s S1 a n d S2 hyd ra ul i c mo to r o f f..................................
c.
N2 sys tem a nd air to val ve header secured.............................
d.
Calgon units secured..................................................
e.
Room 114 pump control l ers l ocked out..................................
17.
Completed and logged reactor shutdown checksheet...........................
I BUILDING SHUTDOWN CHECKSHEET 1.
Pool level normal............................................
2.
ARM trip levelt set per S0P................................................
3.
Annunciator board off.....................................................
4.
TV unit secured............................................................
5.
ARM and ( ff-gas recorder paper supply okay, charts timed and dated.........
I 6.
Primary / pool drain collection system secured per S0P.......................
7.
Ro u t i n e p a t rol c ompl e t e d...................................................
I SRM, IRM, WRM, PRM, ARM and process radiation monitors in operate mode.....
8.
9.
Mastr key switch off and in key box.......................................
10.
Test of containment intrusion alarm completed.
System energized...........
11.
A l l k ey s a c c o u n t e d fo r......................................
12.
Buil di ng sh utdown a nd rea ctor sec ured......................................
13.
Control room doors locked.................................................
14.
C,mpleted building shutdown checksheet.....................................
15.
Logbouk er tries c^mlete, crews signed out......
SeTior Reactor Op'erator S0P/A-4
I
.l
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REVISI0il fiO. 6 I
4/23/81 i
l SOP /A-la Revised 4/81 SOP /A-4b Revised 4/81 (Page 2 of Reactor Shutdown Checksheet)
I -
RLACTOR STAfdUP CHLLKSHELT DAll:
April 1, 1981 FULL PO'.lER OPER/ CON
' (' r Low Power forced Circulation) o BUILDING AND T1ECHAtlICAL E_QUIPMENT CHECKLIST Hun emergency generator for 30 minutes and check the governor oil level.
I
~ 1 (Ree: ired if shutdohn for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or after each maintenance day.)
Check operation of fan failure buzzer and warning light.
Shift fans.
2.
a.
I (required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) b.
Test stack monitor per S0P while in west tower.
Test the stack monitor low floy alarn.
c.
__ 3.
Visual check of, com 114 equipment completed.
a.
P501A and P501B coolant water valves open.
b.
51 and S2 hydraulic pumps on (oil level normal).
Pump controllers unlocked to start (as required).
c.
d.
Insure fl2 backup system on per SOP.
I_
Open air valve for valve operating header (V0P 31).
e.
f.
Il2 backup valve open.
g.
Pipe trench free of water (on ihnday startups, check the four-pipe I ___ 4.
annulus drain valves for water leakage).
Visual check of CT equipment completed.
a.
Oil level in CT fans nnrmal (Monday startups).
I 5.
Beamport Floor Beamport radiation shielding (as required) a.
b.
Unused beamports checked flooded (Monday)
Seal trench low level alarm tested (11onday)
I Emergency air compressor (load test for 30 minutes on Monday) c.
6.
7.
Reactor pool
(
Reflector experimental loadings verified and secured for start-up.
a.
F.
Flux trap experimental loading verified and secured for start-up, or strainer in place.
REACTOR CONTROL SYSTE_11 CHECKLIST 1.
All chart drives on; charts timed and dated.
IRM r_ corder to slow.
I 2.
Fan failure warning system cleared.
3.
Annunciator board energized; born off.
4.
Television receiver on.
~
_ 5.
Primary / pool drain collection system in servicc per 50P.
6.
Se cndary system on line per 50P (as needed).
7.
Primary system on line per SOP.
Primary cleanup system on line.
a.
__ 8.
Pool system on line per SOP.
a.
Pool cleanup system on line.
b.
Pool skinmer system vented.
I_
Pool reflector Ap trips set per SOP.
c.
9.
Valves S1 and S2 cycled in manual mode and positioned as required, 10.
t!uclear instrumentation check completed per SOP.
the following trip values were obtained during the check.
a.
IRM-2, run-in seconds Scram seconds IRM-3, run-in seconds Scram seconds WRM-4, run-in Scram
~
PRM-5, run-in Scram k
PRM-6, run-in Scram
- 11. Channel 4, 5, and 6 pots returned to last heat balance position.
- 12. SRM-1 detector response checked and set to indicate > 1 cps.
5
. 4/1/81 _
dRev Repl.
8/76 App'd CM,._
50P/ A-la
a
- a. - _ _
m ms 2
2 s
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..g 1I E
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. NN SOP /A-4b
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l REVISION NO. 7 5/14/81 SOP /IV-2 Revised 5/81 SOP /IV-3 Revised 5/81 l
SOP /IV-4 Revised 5/81 i
SOP /IV-5 Revised 5/81 50P/V-2 Revised 5/81 SOP /V-3 Revised 5/81 i
I l l
d.
Primary system flow recorder and temperature recorders are energized and the primary demineralizer flow recorder is energized. Time and date the recorders.
c.
Place heat exchanger byp-switch 2S41 in the position required for the heat exchanger combination to be used.
I B.
Verify antisi, hon vent valve closed.
C.
Close antisiphon system manual drain valve.
D.
Set the enti-siphon system air regulator to 35 psig and open the air inlet valve.
E.
Place master switch 1S1 Tc test.
F.
Open valves 527 E and F.
G.
Place valve 545 switch to auto / closed.
H.
Place valve 527A switch to auto / closed.
I.
Place valve 527B switch to auto / closed.
J.
Place ptrp P-533 switch to on, P-533 may or may not start, depending upon demand.
I K.
After P-533 has completed charging, place valve 526 switch to auto / closed.
L.
Place valve 507A/B swi+ch to manual /open. Valves 543A/B will automatically close at this time.
M.
Immediately place valve 527C switch to open. The primary system is now pressurized.
N.
Cycle valves 546A/B sv ;tches to manual / closed.
l 0.
Immediately start pump 501A or B.
Verify proper flow.
P.
Cycle valves 546A and B open and then closed one at a time and I
verify the increase and then decrease in primary system flow as i
cach valve is cycled.
Q.
Start the remaining pump 501A or B.
Verify proper primary l
system flows.
R.
Start pump 513A and verify proper flow.
l S.
Open the antisiphon system drain valve and blow the system dry.
I Close the valve, wait 10 seconds and repeat.
This may have to l
be done three or four times to insure that all the water is 1
drained.
I T.
Close the antisiphon system drain valve.
U.
Insure that the antisiphon system pressure is set at 36 psig; then close the air inlet valve.
l t
Rev.
5/81 App'd Jf T %
SOP / IV-2 17
V.
Place the following valve controls in the indicated positions.
Valve Mode Position V507A/B Auto Closed
__g V546A/B Auto Open 3
V543A/B Open V545 Auto Closed V526 Auto Closed V527A Auto Closed V527B Auto Closed V527C Open W.
Verify that all the valve position indicating lights are operating with the valves in the positions listed in Step V.
If not, replace the appropriate light bulb.
If this does not clear the malfunction, shutdown the primary system as per IV.2 and verify proper valve op-eration by a visual examination of the actuator linkage during op-eration.
In the case of V543A or B indication failure, perform CP-24 Compli ace Check.
(NbTE:
If the malfunction is determined to be an electrical indication probl'_m not used in the safety system, the re-actor may be operated with repairs being made at the next maintenance shutdown.)
X.
For 10 MW, 2 pump operation, balance loop. flows as follows:
1.
Check the flow in the two heat exchar.ger loops and adjust the 540 valves to balance the flow.
2.
Check the AP across each of the pumps and adjust the bypass valves to balance the flow delivered by each pump.
IV.2 Shutdown of Primary System NOTE: The primary system should remain in operation for fifteen minutes after reactor shutdown to remove decay heat.
IV.2.1 Procedure A.
Place master switch 151 in test.
B.
Close valve 527C.
C.
Secure pump P533.
I D.
Secure P513A.
E.
If both pumps P501A and/or P501B are running, secure them simulta-neously to reduce check v lve slam.
F.
Verify that valves 546A/B open on the loss of fiow.
G.
Place the 507A/B mode switch to manual.
H.
Verify that V507A/B close and tha; valves 543A/B open.
Rev.
5/81 App'd,jd4}>vt SOP / IV-3
/
O -
B B
1.
Open the drain vaive on the antisiphon system and then slowly open the vent valve and bleed the pressure to zero.
Reclose the valves
~
when depressurized.
J.
Place the following valve controls ~in the indicated positions.
Valve Mode Position Valve Mode Position V507A/B Manual Closed V527A Manual Closed V546A Manuai Open V527B Manual Closed I
V546B Manual Open V545 Manual Closed Open V526 Manual Closed V543A/B K.
Verify tnat valves 507A and B have operated and sealed closed by cycling V507A/B while noting the system pressure drop.
There will always be some pressure drop due to pressure trapped on the pump side of V507A/B, if not, repair of V507A or B actuator or valve is required prior to any reactor start-up.
L.
Close valves 527E/F.
M.
Verify that all the valve position indicating lights are operating with the valves in the positions listed in Step J.
If not, replace the appropriate light bulb.
If this does not clear the malfunction, determine the cause and make repairs prior to any reactor start-up.
For V543A or B, perform CP 24 Compliance Check.
(N0TE:
If the mal-tunction is determined to be an electrical indication problem not used in the safety system, the reactor may be operated with repairs being made at the next mair.tenance shutdown.)
N.
Secure the primary flow and temperature recorders and the primary demineralizer flow recorder.
Time and date the recorders.
O.
Secure power to pumps P501A/B, PS13A, and P533.
P.
Secure shaft cooling water supply to pumps P501 A/B.
IV.3.
Operation of the Anti-Siphon System IV.3.1 General Operating Philosophy i
The anti-siphon system is designated to provide sufficient aire (under pressure) to break a siphon of the primary coolant system in the event of a pipe rupture.
To perform its function, this system must be main-tained at a pressure greater than 27 psig, and the water level above the anti-siphon valver must be less than six inches.
The procedures l
below will be fcllowed to insure that the anti-siphon system is op-i erated within the above limitations.
IV.3.2 Decreasing Pressure in the Anti-Siphon System l
The system contains a pressure switch which will initiate an annunciator alarm when the system pressure falls below 30 ps.g.
Upon receipt of the Rev.
5/81 App'd k7A SOP /IV-4 e
I low pressure alarm an attempt shall be made to establish normal system pressure by admitting air through the valve and regulator on the bridge.
If system pressure cannot be maintained above I
27 psig, the reactor shall be shutdown until the problem is corrected.
I IV.3.3
. Increasing Pressure in the Anti-Siphon System After the primary coolant system has been placed in service, open the system drain valve and check that the system is I
drained of all water. The system's pressure will then be returned to the middle of the operating band (-36 psig) and this pressure will be recorded on the routine patrol sheet.
On each subsequent routine patrol, read the system pressure and compare it to the base pressure recorded after the startup.
If the pressure has increased by more than 4 psi, action must be taken to insure that the pressure increase is not due to in-Icakage of primary coolant water.
If the pressure has increased by more than 4 psi, carry out the following procedures:
A.
Open the drain valve and observe the water ficwing from the drain line.
B.
Drain until you no longer receive a solid stream of water, then close the drain valve.
C.
If the amount of w ter drainri is significant, record this fact en the reutine patrol sheet and in the console log.
D.
Return the system pressure to normal (~36 psig) by vent-ing or adding air.
E.
Record the new base pressure on the routine patrol.
sheet.
A new base pressure will be established during the first routine patrol of every day that the reactor is operating.
To establish the new base pressure, carry out steps A l
through E above.
l l
l r
l Rev.
5/31 App'd
$m 50P/IV-5 L
F
D.
Visually check for proper in-pool loadings:
1.
Make certain experiments are securely loaded and are seated within their proper loading facilities.
2.
Make certain the flux trap facility apper ; normal and the test hole guard web is properly in place, or the test hole sample holder is correctly and securely positioned.
E.
Turn on the pool flow and temperature recorders and time and date.
I Verify that the local pump stop switches in room 114 are unlocked.
F.
NOTE:
If the breaker is closed, the selector switch is in the auto mode and the stop switch is unlocked, the off indicator in the control room for P508A/B will be lighted.
G.
Place HX bypass switch 2S40 in the position required for the HX lineup intended.
H.
Master control switch 151 should be in the test position.
I.
Place valve V509 switch to the manual /open position.
J.
Turn on pool pump P508A/B as appropi iate by turning the control switches I
to :n.
Veri fy proper flow.
K.
Start cleanup pump P513B and verify flow.
Eg L.
Adjust pool flow if required by throttling the HX outlet valves (522A and 522D) as necessary.
M.
With normal flow and pressure, place V509 switch to auto / closed.
N.
Verify that all the valve position indicating lights are operating.
If not, replace the appropriate light bulb.
If this does not clear the malfunction, shutdown the pool syWm as per V.2 and verify proper valve operation by a visual examination of the actuator linkage during operation. (NOTE:
Determine the cause of the failure and make repairs prior to any start 9p.)
0.
If not required for other '.volutions, turn master control switch 1S1 to the on position.
V.2 Pool System Shutdown Procedure V.2.1 The pool cooling system should remain in operation for a short period of time (5 minutes minimum) after a normal reactor shutdown in order to remove core decay heat from the reflector and experimental facility.
The procedure for attaining a normal pool system shutdown mode is as follows:
A.
Place master switch 151 in test.
B.
Turn off cleanup pump P513B.
C.
Turn off P508A/B using the control switches in the control room.
To minimize check valve slam, secure both pumps simultaneously.
Rev.
5/81 App'd Om SOP /V-2
D.
Verify that valve V509.'oses automatica1'y.
E.
Place V509 in the manual / closed position.
F.
Verify that all the valve position indicating lights are operating.
If not, replace the appropriate light bulb.
If this does not clear the malfunction, determine the cause and make repairs prior to any reactor start-up.
G.
Tur; off the pool flow and temperature recorders.
I H.
Secure power to P508A/B.
V.3 Partial Pool Filling Procedures (pool at refuel level or above)
V.3.1 To increase the water level in the pool with demineralized water from T301 or T300, one of the two following procedures can be used, however, all I
water in T301 should be used first.
A.
Filling may be accomplished with the skimmer system (Section VII.5.1)
I with or without the skimmer pump operating and the reactor either operati g or shutdown.
Required operational pool makeup will be n
accomplished in this manner.
1.
Check capacities of tanks T300 and T301 and check proper valve lineup l
2.
Observe the pool level and check that the skimmer pump is secured.
3.
R.'motely open valve 565B from the primary / pool drain collection system control panel.
Insure valve does indicate open.
I 4.
The skimmer pump may be started at this point, however, it will fill by gravity if desired.
5.
When proper pool level is obtained, secure the skimmer pump and remotely close valve 565B.
Insure it does indicate closed.
t B.
The second appi oved method of filli,q the pool is via the 4" line from tank T300/301 to the pool pump suctioc and discharge line.
1.
Check capacities of tanks T300 and T301 and check proper valve lineup.
2.
With the pool system in the normal shutdown mode, filling the pool through a pool pump can be avoided by opening valv2 V522C and per-mitting T301 or 1300 to drain by gravity feed alone.
3.
Close valve V522C when the filling operation is completed.
/
I SOP /V-3 Rev. 5/81 App'dO (A e
= _ -
I REVISION N0. 8 5/20/81 SOP /A-la Revised 5/81 i
t e
I l
l t
I
' I l
l i
1 l
l l
.---,----- _ r--_
a.,n-e--
-.ve-mn,,
~, - ~ -
REACTOR STARTUP CHECKSHEET DATE:
I FULL POWER OPERATION (or Low Power Forced Circulation)
BUILDING AND MECHANICAL EQUIPMENT CHECKLIST 1.
Run emergency generator for 30 minutes and check the governor oil level.
(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or after each maintenance day.)
Check operation of fan failure buzzer and warning light.
Shift fans.
2.
a.
I (Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
b.
Test stack' monitor per SDP while in west tower.
c.
Test the stack monitor low flow alarm.
3 I
3.
Visual check of rocm 114 equipment conpleted.
I a.
P501 A and P501B coolant water valves open.
b.
S1 and S? hydraulic pumps on (oil level normal).
I Pump controllers unlocked to start (as required).
c.
d.
Insure N backup system on per SOP.
^
2 Open air valve for valve operating header (V0P 31).
e.
f.
N backup valve open.
7 g.
Check valves 599A and 5998 open.
h.
Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).
4.
Visual check of CT equipment completed.
i a.
Oil level in CT fans normal (Monday startups).
I Beamport Floor 5.
Beamport radiation shielding (as required).
a.
b.
Unused beamports checked flooded (Monday).
c.
Seal trench low level alann tested (Monday).
Emergency air compressor (load test for 30 minutes on Monday).
6.
7.
Reactor Pool a.
Reflector experimental loadings verified and secured for start-up.
b.
Flux trap experimental loading verified and secured for start-up, or strainer in place.
REACTOR CONTROL SYSTEM CHECKLIST 1.
All chart drives on; charts timed and dated.
IRM recorder to slow.
2.
Fan failure warning system cleared.
I 4.
Television receiver on.
3.
Annunciator board energized; horn off.
5.
Primary / pool drain collection system in service per S0P.
6.
Secondary system on line per S0P (as needed).
7.
Primary system on line per S0P.
a.
Primary cleanup system on line.
8.
Pool system on line per SOP.
I Pool cleanup system on line.
a.
b.
Pool skimmer system vented.
c.
Pool reflector Ap trips set per S0P.
9.
Valves S! and S2 cycled in manual mode and positioned as required.
)
10.
Nuclear instrumentation check completed per 50P.
The following trip values were obtained during the check.
a.
IRM-2, run-in seconds Scram seconds I
IRM-3, run-in seconds Scram seconds WRM-4, run-in Scram PhM-5, run-in Scram PRM-6, run-in Scram ll.
Channel 4, 5, and 6 pots returned to last heat balance position.
12 SRM-1 detector response checked and set to indicate >l cps.
I Rev. 5/81 App'd _
/4_
SOP /A-la
l 1
I REVISION NO. 9 5/29/81 SOP /A-8a Revised 5/81 l
l l
l l
l
~.
f Date Reactor Routine Patrol 1.
Time of start of patrol h
Time anc. date all charts 3
Check ARMS trip settings 4.
Visual check of entire pool l
5.
Anti-siphon tank pressure
+3.0 psig
?
6.
North iso door seal press 18-28 psig 7.
Sa th iso door seal press 18-28 psig 8.
5th level backup doors Open
[
9.
5th level detector reading 0-3.5 mr/hr O.
5th level trip point set 3.5 mr/hr 1.
16" iso ylv A air pressure 45-55 psig B
$d P "'
2 Emerg compress on standby age
- 20 g
3 Containment hot sump pumps Operable Door 101 seal pressure 18-28 psig 3P floor Conditions nonnt i 16.
Fuel vault Locked Lg i7 5 Intrr airlock door seal press 15-28 psig 4
18 Outer airlock door seal press 18-28 psig b
4 19 T-300 level
> 2000 gal
.T-301 level
< 6000 gal 21.
Labyrinth sump Level < Alarm Pt.
f k'Run daily:
ON[Run on 0700 routine R0 UNIT f
POWER ON te J-300 or drain./
t for - 4 hrs
)3 R0 Unit Temp 24-28*C / standby H
24 R0 Unit Pressure = =
190-200 psig / standby 1
k5 G rm. E8L6p M Hch"90 Au Bj-Themostat > 50*F C
Temo
> 40*F Gas > sight glass.
Thermostat > 55 F h
T-300, 301 room Thennostat > 40 F i
HE
< 2.5" H 0 p73 Rm 114 particulate filter AP 2
I e first routine patrol of the day or the first patrol after a startup, drain all water from nti-siphon system.
If draining causes the pressure to drop significantly, return to the e of_the band (36._psig) and record the pressure here.
5/81 App'd_
k< [
SQP/A-8a Se I
/ _
L
I REVISION NO. 10 5/30/81 I
SOP /A-ll Revised 5/81 I
I I
' I _ _ - _ _ _ _ - _
KLiuGi Udui!.ist ~ iU iiEtslui hu biCd ui i lCE I40.
WASTE TANK SAMPLE REPORT IK NO.
TANK LEVEL (Liters) !
TIME DATE Completed adding water to this tank.
-1 iPLER TIME DATE
~
1.
Analysis Results Nuclide Half Life Physical Form Concentration MPC Activity
_(pCi/ml L _
(pCi)__
H-3 12.3Y
- l I
I p
TOTAL CONCENTRATION (b)
A lysis by Date _
Time l
Concentration bCi/m)
Total Voluine (_ liters)
Activity (mci) l (a) x
=
(b) x
=
2.
Approvals Required For Ar Discharge.
Shift Supervisor
- Di harge of Total Activity > 4 mci or to Secondary System Reactor Manager l
l Discharge Limit Approved Health Physics 3.
Action Taken 1
Date Discharged Time Discharged Volune Discharged (Liters)
Ta Discharged to (check one)
Sanitary Sewer Secondary System Not Discharged Remarks
~~
Re 5/81 App'd..
tc_.;
SOP /A-ll
SECTION III REVISIONS TO THE HAZARDS SUf41ARY REPORT Hazards Summary Report, Section 9.7.3, changed to read:
9.7.3 Off-Gas Radiation Monitoring System The off-gas monitoring system has an isokinetic probe in the off-gas system plenum that supplies sample air to a filter paper monitored by a beta scintillation detector followed by a charcoal filter moni-tored by a gamma scintillation detector followed by a shielded gas chamber monitored by a Geiger-Miller tube. Output from each detector is shown on a log scale count rate meter on the instrument cabinet and on continuous chart recorders in the reactor control room.
Audio alarms sound in the control room for low air flow, and for high radiation above a manually set limit for eaci, detector.
I
SECTION IV PLANT AND SYSTEM MODIFICATIONS August '980 Modification 80-4: Moves the air supply for the containment back-up doors to the amergency air supply side of the air system.
This change provides increased reliability for the system.
Safety Analysis Summary: Modification 80-4 presents no unresolved safety question.
It adds the capacity to operate the ventilation back-up doors in the event of loss of the main air compressor.
March 1981 Modification 81-3:
Purpose is to separate the power supplies for the stack monitoring system and its associated alarm function. This allows testing of the low flow alarm.
Safety Analysis Summary:
Modification 81-3 has no effect on safety related equipment.
It provides an additional power supply for the low flow alarm improving the capability to monitor the system's functions.
I Modification 81-5:
Installs a poly bushing beneath the anvil on offset "C".
The bushing prevents netal to metal contact between the anvil and offset tube and reduces friction in the system.
Safety Analysis:
The installed bushing presents no unrevies.cd safety hazard. The modification should help minimize problems with misalignment of the anvil and magnet.
I I
Modification 81-6:
Improves the mechanical stability and reduces the amount of stainless steel which can be activated in an offset mechanism.
The concept is identical to exist;ng Type II offset mechanism.
Safety Analysis Summary:
The new materials and increased mechanical stability present no unresolved safety questions.
The reduction in stainless steel will help to decrease operator dose during maintenance on the offset.
I Modification 81-8:
Replaces the waste tank system two steel filter housings with one non-corrosive plastic filter housing.
Safety Analysis Summary: The modified system components propose no unreviewed safety hazard. All components are being replaced with materials of superior quality than presently installed, increasing ease of operation of the waste tank filter system.
April 1981 Modification 81-4:
Installs a means for filling the loop seal for the pool overflow in Room 114 pipe tunnel with DI water.
Safety Analysis Summary: The madification to the pool overflow We pre-l l
sents no unresolved safety question.
The installation allows easier operation l
l and use of DI water versus pool water for fillirg the pipe.
l l
Modification 81-9: This modification installed a pump from T-300 discharging l
l to DI - 200 regeneration station.
The T-300 pump provides an alternate means of supplying DI water to DI - 200 regeneration station, minimizing depleting DI-300 during a 01-200 regeneration.
The use of the T-300 pump will greatly l
increase DI-300 resin life and. decrease the cost in making DI water.
l.
Safety Analysis:
Modification 81-9 presents no unresolved safety questions.
The installed alarms insure prope-level is maintained in T-300.
Modification 81-10:
This modification was the replacement of the carbon steel tank and some waste tank system piping modifications.
This modification reduces maintenance required for the tank plus pravides additional or alterr.a-I tive tanks for pool water storage.
Safety Analysis Suunary:
Modification 81-10 presents no unresolved safety questions.
The new tank is essentially the same as the tank it replaces with the water management and operation as before.
Modification 81-13:
Replaces the unitized fan cross piping for cooling tower cells #1 and #2 with new pipes of identical design.
The replacement is due to corrosion over the years.
Safety Analysis Summary:
The par'.s installed in CT #1 and #2 are identical to those originally installed and pose no new or unresolved safety question.
June 1981 Modification 81-12:
Replaced the wet firemain pipe in the seal trench with 6" CPVC pipe. The piping replaced was 4", 150 psig carbon steel and is replaced l
with 6", 300 psig, CPVC increasing the pressure rcting and pipe diameter.
The i
l flow path is the same and,due to the larger diameter, pipe will allow better flow.
l l
Safety Analysis Summary:
Modification 81-12 presents no unresolved or new safety questions.
The larger diameter pipe helps increase the total flow delivered for emergency 5 col make-up, i
W SECTION V
[
NEW TESTS AND EXPERIMENTS New experimental programs during the period of July 1980 through June 1981 are as follows.
RUR 262 Experimenter:
Guy Schupp
[
Purpose:
To use gamma rays from an intense radioactive source to investigate crystal properties and structures by inelastic and elastic scattering measurements.
~
==
Description:==
Intense gamma ray sources will be produced by
{
activating in the flux trap sources foils welded in aluminum cans.
The source is then transferred to the experiment station on the north end of the beamport floor where the
[
experiment is performed.
[
[
[
Y
[
-22
i 7
I SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1.
SNM Receipts: During the year, the ;iURR received fuel from Rockwell International Energy Systems Group (Atomics International). A total of 24 new fuel elements were received.
Grams Grams Shipper Elements U
U-235 Atomics Int'l.
47, 48 and 53 thru 69 19,869.88 18,507.61 and 72, 74 thru 77 2.
SNM Shipments: Three shipment of spent fuel elements wcre sent to U.S.D.0.E. Savannah River Plant for reprocessing.
Grams Grams Shipper Elements U
U-235 MURR 775F79, 86, 89, 93, 98, 17,126.z8 15,016.98 I
105, 106, 107, 108, 109, 110, 111, 112, M01, M02, 4, 6, 7, 8, 9, 10, 11, I
12, 13 3.
Inspections: On May 5-6, 1981, a Physical Protection Inspection was conducted by Ms. G. M. Christoffer of Region III, USNRC.
No items of noncompliance were identified during the course of their inspection.
4.
SNM Inventory: As of 30 June 1981, the MURR financially responsible inventory was as follows:
Total U
= 41,894 grams Total U-235 = 37,426 grams All of this material is physically located at the MURR.
In addition, MURR has three 350 gram elements stored at Atomics International.
I l
-;9-
M4m Fuel elenents on hand have accumulated the following burnup as of 30 June 1980:
Fuel El; ment Accumulated Fuci Element Accumulated Number MWD
_ Number MWD M03 149.33 M042 145.49 h05 149.33 M043 125.12 M014 145.47 M044 145.49 M016 144.01 M045 148.08 M015 98.75 M046 73.23 M017 135.98 M047 148.08 M018 148.15 M048 73.23 M019 147.73 M053 92.16 M020 143.14 M054 92.16 M021 125.64 M055 82.05 M022 108.94 M056 0.0 M023 147.69 M057 82.05 M024 146.79 9039 56.68 M025 147.69 M060 67.81 M02<
135.98 M061 56.68 M027 120.41 M062 67.81 M028 148.00 M063 54.81 M029 120.41 M064 66.99 M030 148.00 M065 54.81 I
M031 107.98 M056 66.99 M032 145.33 M067 19.40 M033 115.37 M068 26.57 M034 145.33 M069 19.40 M035 147.14 M076 26.57 l
M036 142.66 M072 0.0 1
M037 131.76 M074 0.0 M038 120.44 M075 0.0 Mo39 142.66 M077 0.0 l
- MQM, 120.44 M041 125.12 l
M049, 50, 51, 52 not issued and M358 returned June 23, 1981. _~
I Total U
= 1,112.39 grams Total U-235 = 1,036.19 grams Also MURR owns a total of 128 grams U and 49 grams U-235.
The 12 gram increa',e in U and U-235 from iast year is due to acquiring two sets of plates f or fluclepore for use in the thermal column.
I R
l. ---
~
SECTION VII REACTOR PHYSICS ACTIVITIES 1.
Fuel utilization:
During this period, the following elements reached their licensed burnup and were retired.
M018 M028 I
M019 M030 M023 M032 M024 M034 M025 h035 Normally 24 fuel elements are listed as retired, but due to increased shipping costs for new and irradiated fuel, fuel elements that cannot be utilized during a normal fuel cycle (previous definition for retire-ment) are retained in the active fuel cycle structure for possible use in an abbreviated fuel cycle.
Due to requirements of having less than 5 kg of unirradiated fuel ori hand at one time, initial criticalities are normally conducted with 4 new elements or fewer as conditions dictate.
Core XXVI M041, 42, 43, 44 (initial criticality was last fiscal year)
M0G, 47 25 August 1980 M046, 48 11 November 1980 Note:
Serial #'s 49 thru 52 were not issued.
Core XXVII M053, 54 1 December 1980 M055, 57 29 December 1980 l
M056, 58*
(initial criticality will be next fiscal year) i M059, 60 9 February 1981 i
- As of June 30, M058 was returned to Atomics International for adjustment of end fitting.
l
I Core XXVIII M061, 62 9 February 1981 M063, 64, 65, 66 9 March 1981 M067, 68 4 May 1981 Core XXIX M069, 76 4 May 1981 M070, 71, 73 (have not been received for use)
M072. 74, 75 (initial criticality will be next fiscal year)
Core XXX M077 (initial criticality will be next fiscal year)
M078-84 (have not been received for use)
I I
I I
)
I I
I I
I g
33
I 2.
Fuel Shipping:
Three spent fuel shipments departed the facility
~
during the fiscal year. The shipments contained the following elements:
775F79 775F108 M006 775F86 775F109 M007 775F89 775F110 MJ08 775F93 775 Fill M009 775F98 775rll2 M010 775F105 M001 M0ll 775F106 M002 M012 775F107 M004 M013 3.
Fuel Procurement: At the present time, MURR fuel is being fabricated by Rockwell International Energy Systems Group of Can.ga Park, Cali-fornia.
This work is contracteJ with U.S.D.0.E. and administered i:y the Idaho Operations Office.
4.
Licensing Activities: A revised physical security pia.. as per 10CFR70:67 that was submitted May 16, 1980 is still pending. Amendment #13 to Facility Operating License No. R-103 was issued March 5, 1981.
This amendment changes the organizational structure as outlined in Figure 6.0 of the Technical Specification 6.1 to reflect tne current admini-strative organization for our facility. Amendment No. 14 to Facility l
Operating License No. R-103 was issued April 14, 1981.
This amendment i
l l
changed the definition of " Reactor Secured," item 1.20, Appendix A, 1
i of the Technical Specifications of ot r facility license.
l I
{
5.
Reactor Characteristic Measurements:
Shim Blade "D" Reactivity calibration measureaents were performed in April on Core A0-2 at 605 mids.
A series of five (L) reactivity measurements for various i
flux trap sample loadings were performed during April, May and June.
1 A physical inspection of the followirg fuel elements was performed at approximately 130 MWDs to veriff the operational parsioeters:
M028 from Core 24 on 4/14/81 M035 from Core 25 on 6/04/81 M042 frem Core 26 on 4/14/81 All measurements were within operational requirements.
i I
1 l
l P.
i 1
SECTION VIII
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Liquid Effluent - /-1-80 to 6-30-81 Nuclide Amount (Ci)
H-3 via cooling iswer drain
<.001 H-3
.434*
Na-24
.001 K-42
<.001 Sc-46
.0Cl C.-51
.029 Mn-54
.005
.001 Mn-56
.001 Co-57 I
Co-58
.001 Fe-59
.001 Co-60
.032 Zn-65
.110 Ni-65
<.001 Se-75
<.001
.001 As-76 As-77
.005 Ag-110*
.002 l
Sn-ll3
<.0G1
<.001 Sb-122 Sb-124
.006 Sb-125
.001
<.001 I-131 1-133
.001 Ba-133 001 Cs-134
.001 Cs-137
.001 Ba-140
.001 g
H F -181
<.001
.001
~
Au-196
.001 Au-198
,001 Hg-2r
.001 Ra-226
- 0.33a Ci of the H-3 released af ter 3-11-81.
Stack Effluent 1-80 to 6-30-81 Nuclide Amount (Ci)
H-3 10.42*
Na-24
.000003 Cl-38
.000117 Ar-41 1733.48 Sc-46
.000001 Cr-51
.000001 Mn-54
<.000001 Mn-56
.000001 l
.000001
.000001 Cc-58 s
.000002 u-64
.000020
^
Zn-65
.000003 Se-75
.000003 As-76
<.000001 I
As-77
.000332 Br-82
.000048
.000001 Kr-85m
.000001 Kr-87
.000001 Rb-89
<.000001 Sr-92
<.000001 Nb-97
<.000001 Zr-97
.000001 Mo-99 I
Tc-99m
<.000001 l
~~
Tc-101
.000005 In-ll3m
<.000001 In-ll4m
<.000001 In-ll 5ra
<.000001 Cd-ll5
.000003 Sb-122
<.000001 1-128
.000023 I-131
.000603 I-132
.000?.23 Te-132
.000001
.000001 Ba-133 1-133
.001082 Xe-133
.000026 Xe-133m
.000003 I-134
.000440 1-135
.000885 Xe-135
.000100 Xe-135m
.0004i0 I
.000001 Cs-137 Cs-138
.000006 Ba-139
.000053 Ce-139
.000002 Ba-140
.000001 La-140
.000001 Ce -144
.000001
.000001 Hf-181m Ta-182
.000001 Ta-183
.000004
.000001 Ir-192
<.000001 Au-196 Hg-203
.000068 Bi-214
.000007 Pb-214
.000005
- Less than 0.001 Ci H-3 released to air by evaporation from cooling tower.
I - -
SECT 10ri IX
SUMMARY
OF ENVIORNMENTAL SURVEYS Environmental samples are collected yearly at nine locations and analyzed for radioactivity.
These locations are shown in figure 1.
Soil ard vegetation samples are taken at each location.
Water samples are taken at four of the nine locations.
Results of the samples are shown in the following tables.
Detection Limits Matrix Alpha Beta Gamma Tritium Water 0.E pCi/l 2.5 pCi/l 0.04 pCi/l 9.1 pCi/ml I
foil and 0.2 pCi/g 2.5 pCi/g 0.04 pCf/g 9.1 pCi/g vegetation 1.
Sampling Date:
11-5-80 Determined Radioactivity Levels Sample Alpha Beta Gamma Tritium 1 v 18
<0.2 pCi/g 18.00 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 2 v 18 0.8 pCi/g 11.85 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 3 v18 0.3 pCi/g 10.25 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 4 v 18
< 0.2 pCi/g 17.72 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g l
5 v18
< 0.2 pCi/g 21.55 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 6 v18 0.2 pCi/g 19.51 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 7 v 18
< 0.2 pCi/g 21.43 pCi/g
<0.04 pCi/g
< 9.1 pCi/g j
8.v 18 0.2 pCi/g 18.48 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 9 v18 0.2 pCi/g 15.29 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g i
l 1 S 18 0.7 pCi/g 11.93 pCi/g
< 0.04 pCi/g l
2518 0.3 pCi/g 8.06 pCi/g
< 0.04 pCi/g 3 S 18 0.6 pCi/g 12.4 pCi/g
< 0.04 pCi/g 4 S 18
< 0.2 pCi/g 7.41 pCi/g
<0.04 pC1/g 5518
< 0.2 pCi/g 11.91 pCi/g
< 0.04 pCi/g 6 S 18
< 0.2 pCl/g 8.26 pCi/g
<9.04 pCi/g 7 S 18 0.3 pCi/g 7.22 pCi/g
< 0.04 pCi/g 8 S 18 0.3 pCi/g 7.53 pCi/g
< 0.04 pCi/g 9 S 18 0.3 pCi/g 10.60 pCi/g
< 0.C4 pCi/g 4 W 18 0.5 pCi/1 7.32 pCi/1
'0.04 pCi/l
< 9.1 pCi/ml 6 W 18 0.5 pCi/1 5.14 pCi/1
< 0.04 pCi/l
< 9.1 pCi/ml 8 W.18
< 0.2 pCi/1 13.05 pCi/1
< 0.04 pCi/l
< 9.1 pCi/ml 9 W 18
< 0.2 pCi/l 6.33 pCi/l
< 0.04 pCi/1
< 9.1 pCi/ml I
_ Detection Limits Matrix Alpha Beta Ganma Tritium _
Water 0.2 pCi/l 2.5 pCi/l 0.04 pCi/l 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/p 9.1 pCi/g vegetation 2.
Sampling Date:
4-24-81 Det. ermined Radioactivity Levels Sample.
A_lph a.
- Beta, Gamma Tritium 1 V 19
< 0.2 pCi/g 39.1 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 2 V 19 0.71 nCi/g 32.6 pCi/g
<0.04 pCi/g
<9.1 pCi/g 2 V 19
< 0.2 pCi/g 18.6 pCi/g
< 0.04 pCi/g
< 9.1 pCi/,
4 V 19
< 0.2 pCi/g 22.1 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 5 V 19
< 0.2 pCi/g 25.2 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 6 / 19 0.23 pCi/g 29.0 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g _.
7 V 19
< 0.2 pCi/g 15.8 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g I
8 V 19
< 0.2 pCi/g 25.8 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 9 V 19 0.85 pCi/g 19.5 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 1519 0.34 pCi/9 4.6 pCi/g
< 0.04 pCi/g 2 S 19 0.52 pCi/g 10.2 pCi/a
< 0.04 pCi/g 3 S 19 0.92 pCi/g 11.1 pCi/g
< 0 J4 pCi/g 4 S 19 0.49 pCi/g 11.4 pCi/g
< 0.04 pCi/g 5 S 19 0.77 pCi/g 8.5 pCi/g
< 0.04 pCi/g 6 S 19 0 46 pCi/g 7.5 pCi/g
< 0.04 pCi/g 7519
< 0.20 pCi/g 11.6 pCi/g
< 0.04 pCi/g 8 S 19
.54 pCi/g 11.8 pCi/g
< 0.04 pCi/g 9 S 19 1.34 pCi/g 13.7 pCi/g
< 0.04 pCi/g 4 W 19 0.52 pCi/l 8.9 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml 6 W 19
< 0.2 pCi/l 10.0 pCi/1
< 0.04 pCi/1
< 9.1 pCi/ml 8 W 19 0.25 pCi/l 8.3 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml 9 W 19
< 0.2 pCi/1 10.4 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml i i
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R ESE ARCH RE ACTOR FACILITY lI UNIVERSITY OF MISSOURI t
I Figure 1 I..
e M
M M
M M
M i
i SECTION X SutARY OF RADIATION EXP05t'RES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS
]
Personnel Monitoring (?xpcsure in neeg 1
1980 July August Septecter Octcher November December r
El8 lB lB C
D E
B C
D E
[
A B
C D
E lB C
D C
D E
C 7
E G
! 33 5 4/
Boi 35 4
25 40 i 51 2
45 70 1 51 4
23 Zi 35 41 21 9'
43 11 ~22 60 l
U(G) i 14 5 626 iB10 8 6
75 19a 11 4
177 3301 11 4
97 12*d 10
% 73 4710 13 4
29Q73 l
G-S c a re
- i8 1
10 104 1 0
0 0 l 9 0
0 0
12 2 15 20 0
9 19 301 10 6 63 473 UI G pare *! 4 1
40 4F2 0
0 0 L2 0
0 0))
O O
O 1
0 0
I 2 3
16HO I
O_f 81 i
N i 35 78 43 230 6s 50 53 26a 75 32 70 150i 52 e4 54 27; 74 47 112 3?
37 112 TTU U(n) i il 36 153 F5d7 2 33 13Mai 14 21 18I600M 7 26 281 743' TO 23 155 6d 20 21 231 79]
I l
N-S p a re
- i3 8
18 53D2 2
30 35 5
1 2370T6 18 175 6! M O 12 31 195 18 5 98 250 '
f U(h) Spare
- i i 3
142 530 0 0
0 0
2 2
70 lid 4 3
193 27} 4 3
2C8 32' 4
3 3:6 93]
i D
!O 54 62 J3a 6 48 48 15Q 0 50 73 225l 0 49 67
- 19) 0 45 84 I?? O 45 190 370 t
4 Y
r Janua ry February March April May June G
I 46 2
20 304 48 2 10 10 6 46 7
45 222O2 2
25JW2 1 10 ICWS 4 32 100 U(G)
( 15 2
270 4? D 4 3
43 60 i 14 3
1653 4710 11 6
145JR 14 2
90 13;J 3 4 13, 5I5 i
i G-5p a re
- 16 1
10 ld i 15 1
10 10 i 15 2 10 10 L16 1
110 11; 6 0
0 0! i2 7___31N I
UtG) Spare
- 3 i
175 7 G 3 1
30 30 L 2 1
280 7P01_2 1
100 10; O 2
45 5?t 0 4
F7570 t
l H
68 COMSG 65 48 81 290i 51 63 105 310! 49 6e 66 27; 67 55 70 2ft 52 63 91 792 l
U(M) i i6 21 175 750__18 27 39 11]Q_14 31
?LL JZt(L15 39 1P; 1s1n if vi 1on 17M 11 u
777 2iOO i
H-Scare
- i 16 7
52 lid 22 8 65 13?! 13 16 51 7%! 13 8 10 1?*
10 11 99
??t ??
7 67 130 U(h) Spare *i 2 5
136 220 2 6
159 250 3 2
100 150l 1 1
32__12! 1 2
Sc A 0 4
ic7 170 D
10 48 78 170~D IS 84 225i 0 51 108 3601 0 53 81 230 0 50 100 240 0 50 114 400
.l Note:
G = mently beta-ga ra film badge Colu-n Headings: A = Type of desi eter U(G) = montnly finger TLD B = Nu-ber reported as minimun l
H = biweekly Sta-ga-r.a-neutron film badge C = Nu-ber reported with exposures ab0ve minismm U(H) = biweekly finger TLD D = Average of exposures above minirum I
D = self-reacer desirreters E = Single hit, nest dosi.-eter repcrtec
- dsed for temporary workers, rew workers prior to issue of permanent. and replacenent for Icst badges.
i i
i l
4 E
Radiati_ n and Contamination Surveys _
~
The following table gives the number of surveys performed during Fy 80-81.
I Radiation Contamination 331 333 Fi 'ty (50) Radiation Work Pennits were issued during the year.
Miscellaneous Items July 1980 Reactor Health Physics accomplished the first step in a program to refine personnel neutron monitoring.
Landauer H type dosimeter badges were replaced with C-1 dosimeter badges.
The C-1 badges use a polycarbonate foil for fast neutron monitoring.
In addition, a graduate student began neutron monitoring studies with a neutron spectrometer.
This study will contribute to improved personnel neutron monitoring.
The duty of ALARA Coordinator was assigned to the Manager, Reactor Health Phy:,i cs.
This is a new duty at MURR.
It is anticipated that the assignment will be rotated to other individuals at apsropriate times.
Reactor Health Physics added two new continuous, recording, beta sensitive, air monitors and a neutron spectrometer (Bonner Spheres type) to the equipment inventory.
Equipment to enable Health Physics t-do alpha, beta and gamma spec-troscopy has been ordered.
Radiation worker training was increased during the year. All new employees and temporary workers are now given an indoctrination which covers radiation safety, emergency procedures, and plant physical security.
In addition, 155 attendees received training on specific topics of radiation safety. One Health Physics Technician attended c TLD Work Shop at the University of Wisconsin.
A personnel exposure that occurred in November,1979 was resolved with NRC Region III to be a quarterly total of 2400 mrem wholebody. -
Two Health Physics proce&res were revised and two new procedures were added during the year.
A Hcalth Physics Technician was hired to replace one who terminated.
In addition, a student working half-time has been added to the Health Physics j
l organization for this year.
A student from Northeast Missouri State University 1
at Kirskville served a 5-week Health 9hysics trial internship at MURR.
All
)
concerned considered the trial a good learning experience.
Laboratory room surveys were increased significantly and a daily " walk j
through" by Health Physics was added to routine duties to increase Health Physics knowledge of laboratory work.
Increased surveillance of personnel was accomplishect by limiting general entry and exit to the main entrance only.
Disposal of radioactive waste to commercial sites has not been possible since a shipment July 10, 1980.
The situation is too complex and irrational to discuss briefly, but the problem is being actir ly worked-on by Reactor 3
Health Physics.
k A local reporter who had accused MURR of storing radioactive waste gener-ated by the UM Columbia Campus was invited to a Health Physics group meeting.
As a result, the reporter became enthused about the value of research performed lI at MURR and published an informative article on that subject in a local paper.
r I
I l ---
- - - - - -..