ML20031D313
| ML20031D313 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 09/28/1981 |
| From: | Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8110130236 | |
| Download: ML20031D313 (1) | |
Text
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Research Reactor Facility UNIVERSITY OF MISSOURI Research Park September 28, 1981 f,T,"p"$;fj'3{""2!
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Director of Licensing u
U.S. liuclear Regulatory Commission
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Reference:
Docket 50-186 l' qT University of Missouri Research Reactor t.f cense R-103
Subject:
Annual Report as required by Technical Specification 6.1.h(4).
Dear Sir:
Enclosed are the additional twelve copies of the reactor operations annual report vor the University of Missouri Research Reactor as mentioned in my letter of August 28, 1981.
Sincerely, g
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J. C. McKibben Reactor Manacar JCMK:vs Enclosures 8Y<p
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Ea UNIVERSITY OF MISSOURI l
Annual i
Report l
1980-81 I
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. I UtilVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I
- I REACTOR OPEPATIONS ANNUAL REPORT Augus t, 1981 l
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Compiled by the Reactor Staff Submitted by 1
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J. C. McKibben Reactor Manager l
Reviewed and Approved g
D. M. Alger I
Associate Director lI
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TABLE OF CONTENTS g
Section Page I.
REACTOR OPERATIONS SUfEARY..
1 II.
OPERATING PROCEDURE CHANGES 13 111.
REv1510NS 10 1NE NAzAaDS
SUMMARY
REe0R1 24 y
IV.
PLANT AND SYSTEM MODIFICATIONS..........
25 V.
f4EW TESTS AND EXPERIMENTS 28 VI.
SPECIAL NUCLEAR MATERIAL ACTIVITIES 29 VII.
REACTOR PHYSICS ACTIVITIES............
32 VIII.
SU! NARY OF RADI0 ACTIVE EFFLUENTS RELEASED A
TO THE ENVIRONMENT.......
36 IX.
SUMMARY
OF ENVIRONMENTAL 3URVEYS.........
39 X.
SUMMARY
OF RADIATION EXPOSURES TO FACILITY l
STAFF, EXPERIMENTERS, AND VISITORS........
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I SECTION I REACTOR OPERATIONS
SUMMARY
The following table and discussion summarize reactor operations 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 I
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
- MURR 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.
I JULY 1980 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 power on July 2 and July 3.
The loss of electrical power was verified by the city power plant in both instances.
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I A reflectvr differential pressure scram occurred on July 6 and again on July 8.
Each time the breaker for pool pump P50SR 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 overheating in the breaker assembly and tripping of the breaker ~ s thermal overloads.
A rod not in contact with magnet rod run.r. 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 s#iicon sample unloader, the pool pump breaker (P508B) and the particulate off-gas recorder.
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 J00).
In accordance with technical specifications, T-300 must :ontain greater than 2000 gallons of primary grade make-up water to 5
operate in Mode I.
This occurrence was reported to the Nuclear Regulatory Com-lm missio-in a letter dated August 29, 1980.
J When the crimary systems were being shutdown following the manual rod run-in on August 3, the primary inlet isolation valve (V507B) failed to shut when operated remotely.
The valve was then shut by disconnecting the tubing to the solenoid valve and manually venting off the air pressure.
The failure of the isolation valve to shut was due to the installation of an improper (oversized)
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I 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 ibiversity 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 replacement of the source range detector.
SEPTEMBER 1980 The reactor operated continuously during September, with the following ex-I ceptions:
two maintenance shutdowns on September 8 and 22; nine scheduled shut-downs and three unscheduled shutdowns.
.\\ reactor scram occurred September 16 when the facility lost electrical power. The power outage was verified by the city power plant.
I A power level interlock scram occurred September 22 when the motor-to-pump 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 shutdown by rod run-in on September 30, when the Rod Run-In Trip Actuator Amplifier (TAA) failed. The electronics teconicians 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 P501A and the rod run-in trip actuator amplifier.
I OCTOBER 1980 The reactor operated continuously during October with the following exceptions:
two maintenance shutdowns on October 6 and 20; eight scheduled shutdowns 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.
After replacing the solenoid, V509 was tested and found to operate satisfactorily.
A reacter operations inspection was conducted by NRC Region III inspectors
!g K. Ridgeway and K. Connaughton from October 8 to October 10; no items of noncom-ll l
pliance were found.
l A letter dated October 20 was sent to the Nuclear Regulatory Commission I
detailing the events of September 22, 1980. While performing a semi-annual compliance 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 P501 A and the removal of the 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.-Si!% wns on November 3, 10, 16 and 23, eight scheduled shutdowns and two unscheduled shutdowns.
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A reactor lo 1 high temperature scram occurred November 6, after a reactor l
startup following a scheduled shutd w for flux trap sample change.
Secondary pumps P-2 and P-3 were found to be air-bound,resulting in low secondary flow.
The pumps were vented, secondary flow restored and the reactor returned to nor-mal operation.
A reactor scram occurred November 18, when the facility lost electrical 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 December 1,15 and 29; eight scheduled shutdowns and two unscheduled shutdowns.
j A rod not in contact with magnet rod run-in occurred December 7, when con-(
trol rod %" mechanism was bumped while handling a silicon sample.
On December 17, a reactor loop high temperature scram occurred when the bulb which actuates the photoelectric cell in meter relay 980B (HX 5038) burned out. The bulb was replaced and the scram function of the meter relay was tested and found to meet ompliance check specifications.
Major maintenance items for December included a spent fuel shipment, the replacement of DI-200 bed "M" with new bed "P" and the changeout of the offset mechanism for rod "B".
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I JANUARY 1981 The reactor operated continuously during January, with 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-I 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 P501A 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 stark radiation monitor due to the associ-ated air bl,
r being secured.
This blower had been inadvertently left secured by Electronic Shop personnel af ter perfonning a calibr tion of the iodine instru-ment during a reactor start-up check. This incident was reoorted to the Nuclear Regulatory Commission in 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.
FEBRUARY 1981 The rer"or operated continuously during February with the following excep-tions:
two maintenance shutdowns on February 9 and 23; eleven scheduled shutdowns and six unscheduled shutdowns.
I 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 roc not in contact with magnet od run-in occurred when rod "D" dropped from I
its magnet.
Rod "D" was inspected and debris was removed from the magnet seating surface.
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 briMc. After the dry-I well was repaired by the Machine Shop, channel 3 detector was reinstalled an.1 a reactor startup was commenced ring this startup, the reactor was manually scrammed when 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 Nuclear Regu-latory Commission in a letter dated March 13, 1981.
During 10 ff.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
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controlled at this point in manol control until the regulating blade circuitry could be inspected.
No abnormalities were discovered and the reactor returned to 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 fu'1y open or shut seats.
The parallel isolation valve functioned properly and so y analysis assumes only one of the parallel valves will function.
The valve was rebuilt and tested I -
I 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 on 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 dith magnet rod run-in occurred on February 24 when rod "D" fell off its magnet while shimming control blades. The rod "D" drive mechanism I
was pulled and the magnet and anvil were inspected and aligned.
Major activities in February included a reactor operator license examination on February 9, resear^ 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,nvective valve V546B.
MARCH 1931 The reactor operated co. ~ 'uously during March, with the following excep-tions:
two maintenance shutdowns on March 9 and 23 and nine schedule /, shutdowns.
There were no unscheduled shutdowns in March.
Major maintenance in March included the replacement of offset mechanism "D" (Modification Package 81-6); the installation 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 (Mcdification Package B1-3).
APRIL 1981 The reactor operated continuou '.y in April with the following exceptions:
three maintenance shutdowns on April 6, 20, 27; nine scheduled shutdowns and I
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 res' fond sufficiently to power level changas resulted in a manual rod rea-in.
The channel 6 detector was replaced and the reactor returned M operation.
Two scrams due to loss 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 ll, when a reactor loop hign emperature 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 was returned to operation with no further problem of this nature.
Later, on April ll, 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 repai, fire main leaks. This water scurce is required by technical specifications for reactor opera tion.
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 outer 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 cryer unit supplying con-I trol air to the Nuclepore experiment exploded due to overpressure. The control I
I 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 Determination).
During compliance check 22 (Primary Pressure Switch 944 A/B and Pressure 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 maicten-I This incident :as reported to the Nuclear Regulatory Commission in a letter ance.
dated May 18, 1981.
All similar meter relay uni s 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 exceptions:
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" disengaging from its magnet.
In both cases, the cause of the rod drop was due to misalignment of the upper housing.
Two unscheduled shutdowns occurred due to loss of facility electrical power.
I These occurred on May 18 and May 23.
Both power interruptions were verified ~by the University Power Plant.
Major maintenance items for May included completion of the building leak rate check, the replacement of P-4 check valve in the secondary-to-air-conditioning I
I units' oiping, and the dumping of DI-200 resin bed "N".
Two NRC 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.
JUNE 1981 The reactor operated continuously during June with the following exceptions:
four maintenance shutdowns on June 1, 8,15 and 29; eight scheduled shatdowns and seven unscheduled shutdowns.
A rod not in contact with magnet rod run-in occurred June 3 when rod "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 ccming out of its seat. The other shutdowns, on June 16 and 18, were due to failures in the electrical control relays for the open-close sequence of the airlock doors.
The reactor was shutdown by manual rod run-in due to fluctuations in indica-tions provided by channel 3.
The channel 3 detector, cables and connectors were 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" dropped from its magnet. The upper housing was realigned and the reactor returned to operation.
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I Major maintenance items included the installation of of fset #5 in rod "C" position, the installation of a new channel 3 detector and the installation of a new section of pipe in the fire main emergency pool fill line.
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SECTION II OPERATING PROCEDURE CHANGES As required by the MURR Technical Specifications, the Reactor Manager reviews and approves the Standard Operating and Emergency Procedures (S0P). Ten revisions have been made to the 50P during the past year. The revisions are contained il i
j this section with the part of each page that was revised marked on the right side l
i of the page by a vertical black line.
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- I REVISION NO. 1 8/05/80 i
SOP /VIII-ll Revised 8/80 SOP /VIII-12 Revised 8/80 I
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I water and biological fluids will be doubly encap-sulatc6 with the secondary encapsulation being a high density polyethylene rabbit.
3.
Powder samples will be sealed in a polyethylene vial and irradiated in a high density polyethylene rabbit.
Boron and boron compounds in powder form will be sealed in high density polyethylene within the rabbit.
I 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 insJre that the heat generated by the metal can be dissipated and will not cause damage to the sample or rabbit.
5.
The experinenter shall insure that the sample is adequately secured in the rabbit (by polyethylene I
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 exempted in D below may also be irradiated subject to the activity liinitations in A.
D.
Unless it is specifically authorized in the experimenter's l
RUR, tne 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 uranium enriched in isotope 233 or 235);
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Rev.
8/80 App'd I
SOP /VIII-11 e-
M 3.
Pure elements:
Lie Na, K, Rb, Cs, Ca Sr, Ba, Hgo o
l Os, H, 0, F, Ne, Ar, Kr, Xe, and P; 4.
Compounds:
NH NO, CaC, Ca0, perchlorates, per-4 3 2
manganates, Na 0, and Na 0 ;
2 22 5.
Materials which chemically react with water to pro-duce undesirable quantities of heat and pressure; 6.
Any explosive, flammable, combustible, or toxic materials.
E.
The controlling factor for determining the weight and time limits of a sample to be irradiated in the p-tube is the activity limitation of section A.
If the activity limits I
do not further restrict a sample's size, the following weight limits 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 I
measures to insure the heat generated can be dis-l sipated without causing damage to the rabbit or sample.
2.
For irradiation times of 30 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the maxi num weight of irradiated materials in one rabbit will be 1 gram with two exceptions:
a.
A maximum of 10 grams of water or dried feces; b.
Only 500 pg of chemical compounds in solution.
The weight limits above 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 l
levels > 5 MW.
Hair, fibers, paint, air filters and flux monitors 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 > 5 MW.
The following additional limitations shall apply for irradiations f
> 10 minutes:
l 1.
Primary encapsulation will be heat-sealed high-l density polyethylene vials (Holland vials).
Rev.
8/80 k.p' Ch_
SOP /VIII-12
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REVISION N0. 2 8/25/80 I
I SOP /I-14 Revised 8/80 SOP / III-6 Revised 8/80 SOP /VII-40 Revised 8/80 SOP /VIII-19 Revised 8/80 SOP /VIII-20 Revised 8/80 I
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i iI Table IV Values of Trip Settings for Alarm, Run-In and Scram Conditions I
Scram Run-In Alarm Units 1.
Short Period 9
11 sec
<l. 0 cps 2.
Low Count Rate j
3.
High Power 120 115
% full power l
4.
RC Inlet Temp 152 148 F
5.
RC Outlet Temp 173 165 F
1750 gpm I
6.
RC System Low Flow 1675 5 MW Operation 2
2 1750 gpm RC System Low Flow 1675 10 MW Operation 4
gpm
!g 7.
Heat Exchanger Low 1675
Rx System Low Press 61 Switch PS 944A/B 9.
4 Core Low AP, 10 MW 3300 gpm 10.
Low Pressurizer Level 14 below{
10-13below{
i r:ch 12-15above[
inch
- 11. Hi Pressurizer Wtr i'
Level 64 psig 12.
Low Pressurizer Press 61 i
13.
Hi Pressurizer Press 79 76 psig 480 gpm i
14.
Pool Low Flow, 5 MW 440 2
2 i
Pool Low Flow,10 MW 440 480 gpm 15.
Pool Loop Hi Temp 115 F
< 42.5 gpm 16.
Low Pri Denim Flow i
17.
Low Pool Demin Flow 42.5 gpm 18.
Bldg Air Plenum Hi 1.0 mr/hr Activity I Deleted l
2 For 10 MW operation, Alarm and Scram Received from Either Loop 3
Pressurizer Pressure with normal system flow 4
aP corresponding to this flow value
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8/80 App'd Cm SOP /I-14
e Set function switcn to operate".
verify tnct drawer E
m inoperative" lamp is extinguished.
F.
Verify tnat power level trip indicators are extinguished.
G.
Set function switch to " standby".
Verify that power level trip indicators are extinguished, that "d'awer inoperative" light (DS16A) is en'ergized, and that a nuclear instrument anomaly annunciation occurs.
H.
Set function switch to "zero".
Verify that both percent power.*ters (on the console and instrument cubicle) and the recorder ir.iicate 012%.
Verify that a downscale I
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% + LO.
l K.
Set function switch to 10%.
Verify that the console l
percent power meter and the recor<ier indicate 10% i 2%
and that the drawer meter indicates 10% 15%.
L.
Place function switch in " cal" position.
Rotate reset switch to left or right to clear rod run-in and scram trips.
Reset annunciator board.
Using the potentiameter provided on the front of the drawer, apply an input current equivalent to the desired trip point for rod run-in (114% 1 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.
I Rev.
8/80 App'd SOP /III-6
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Note: Rinse only long enough to obtain an increase in I
resistance.
If it stops, repeat VII.4.8.10; varying the flow rate may also help the rinse I
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 cpen the outlet valve on F301.
F.
The demineralizer is now ready for use.
l G.
Log regeneration complete.
V I I. 4.8.13 Providing DI Water to T300 DI water may be sent to T300 with or without the use of the reverse osmosis unit as a DI300 makeup supply.
Due to the fact that DCW, after passing through the R.0. Unit, is much I
more pure than raw DCW, the R.0. Unit is normally utilized to prolong the life of the DI300 resin regeneration.
How-I ever, there are provisions for bypassing the R.O. Unit when sending DI-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 Makeuo 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.
CAUTION: Auto valve should be open, if not or if reading is near set point, place normal, bypass switch 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.)
I I
Rev. 8/80 App'd, y A 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 the control room immediately about i
the problem, stating the material contained in the sample, the weight of the sample, the expected activity and dose rate, j
the approximate time the rabbit can remain in the reactor without creating any hazard or melting.
t A.
After the control room is aware of the problem, press the i
emergency return switch. Observe the rabbit in reactor j
light (CL-4) and check with the control room to see if the operators heard the rabbit leave the reflector region.
I Note:
CL-4 is not a true indication of rabbit location.
It simply indicates the electronic control signal to the unit.
Hearing the rabbit depart the re-flector is the only sure way to know it has left.
l If the rabbit was heard to depart the reflector region, check the connecting station to see if the rabbit was returned there.
i B.
Check the station lineup, verify the circuit selector switch (CB-1) is selected to the proper station as 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.
I E.
Repeat steps A through D several times as directed by the control room.
F.
If the atterapts fail, go to the connecting station, line it up for service and repeat steps A through D.
I I
l l
50P/VIII-19 Rev.
8/80 App'd, M'
G.
If these procedures have failed, follow up action will be handled by reactor operations and Health Physics personnel.
Note:
If the rabbit is stuck outside the reactor it may be found by searching the guide tubes with a radiation monitor.
l jl If the rabbit is stuck in the reflector, the reactor must be shutdown and the p-tube removed.
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 cabiret 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 solenoid power switch off.
(This deenergizes all solenoids.)
(NOTE: This closes off all tubes which will result 4I in a high concentration of Ar if the reactor is operating.)
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""M"L[N
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L E
N REVISION fi0. 3 9/30/80 SOP /I-7 Revised 9/80 SOP /I-8 Revised 9/80 SOP /I-8b Revised 9/80 SOP /II-l Revised 9/80 3
50P/II-2 Revised 9/80 SOP /II-3 Revised 9/80 S0P/II-4 Revised 9/80 I
I I
I Table 11 j
ECP Acceptable Limits 11" - 16"
+ 0.40" 16" - 22"
+ 0.70" 22" - 26" 1.25" f
H.
Instrumentation I
Minimum nuclear instrumentation for startups shall be one f
~.;.hannel, two intermediate range channels each with s:
period trip, two power channels each with flux trips, and l
l one wide range channel with high flux trip.
l.
Use of the Public Address System j
L i
Immediately prior to actual movement of the control I
i rods, an announcement will be made over the public address system that a reactor startup has been commenced. A sec'nd announcement will be made when the desired power level is obtained.
If during the startup the determination is made l
that power will be held constant at any level for a period I
s ? greater than five minutes an additional announcement will be made to inform building personnel.
J.
Health Physics Monitoring of Reactor t
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 continuously monitor that experiment throughout the startup. Direct communications I
will bc maintained between the Control Room and the Health Physics Technician. The Control RJom will '.nform the Health Physics Technician at the follo,ving power level?
1.
During a Normal Reactor Startup a.
When the reactor reaches criticality.
b.
When roactor power reaches 50 KWs.
I
^""'"
I I
c.
When reactor power reaches 6 fGs.
(2.5 MWs if operating in Mode II) d.
When reactor power reaches 10 MWs. (5 MWs j
if operating in Mode II) j 2.
During a Reactor Hot Startup a.
When the reactor reaches criticality.
b.
When reactor power reaches 5 MWs. (2.5 MWs if operating in Mode II) c.
When Reactor power reaches 10 fMs.
If direct communications are lost or if one 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.4.4 Normal Operation 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 operator during steady state operation of the reactor and a second licensed operator will be in the Facility Building and at a location where communication with the control room 9
can be maintained.
C.
Prior to assuming control of the reactor, the oncoming operator ali read :ne cantrol room log book and shall be briefed on current ope-a ion.
D During shift 0;;eration, the shift supervisor for the new shift will review the log book and be briefed on current operations by the crew he 's to relieve. Upon completion of the log book review, the shift supervisor will note the same in the log book.
i A complete set of Nuclear data will be taken once an hour E.
during steady state operation.
F.
A complete set of Process data will be taken every two (2) l hours during steady state operation.
Rev. 9/3C App'd h SOP /I-8
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Section II Reactor Operating Procedures I
II.1 Routine Reactor Operation I
11.1.1 Procedure for Reactor Startup I
For full power, closed pressure vessel operation, the reactor will be brought to its scheduled operating power level according to the procedure outlined below.
A.
Take a complete set of full power process data.
B.
Ootain from the Shift Supervisor an estimate of the critical banked control blade position.
8 Take a complete set of nuclear data on the Startup Nuclear C.
Data Sheet.
J.
Complete the applicable startup checksheet required by Section I (I.?.3.F).
C.ai; fran the Shift Supervisor permission to commence a 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 A_
SOP /II-l
I K.
Bring the reactor critical at a steady state power level I
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 the fission chamber to full out.
M.
Verify that all nuclear instrumentation is responding
~
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 I
temperatures.
O.
Continue the startup, withdrawing only one blade at a time until the reat a power is increasing at no. less than a 30 second period.
At power levels greater than 100 KW, main-tain the centrol blades such that the maximum difference in positien between any two blades always remains less thar 1 inch.
P.
As the reacter power level approaches 1 MW, increase the period until a stable period remains that is n_o_ less than 100 seconds for all power increases greater than 1 MW.
i j
Q.
Bring the reactor critical at a steady state power level of l
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:
i I
1.
Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read I
out directly from the digital calorimetric meter.
Note the actual power level in the operations console log book.
In the case of the calorimetric 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 I
period at no less than 100 seconds.
I Rev.
9/80 App'd
&A S0P/II-2 V
I~
S.
As the scheduled power level is reached, adjust the control blades until the reactor is crh.ical at the desired steady state power in either the manual or automatic control mode.
T.
Switch IRM recorder from fast to slow speed and secure the SRM recorder and scaler.
U.
After the temperatures stabilize, take a complete set of I
nuclear and process data.
V.
Announce to experimenters the reactor power level, schedule and note arrival in the log book.
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.
'otain pernission from the shift supervisor to commence a
.eactor startup.
D.
Announce via the public address system that a hot reactor I
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 I
F.
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.
Stabilize reactor power at a power level of 2.5 MW in Mode II or 5 MW in Mode 1.
At this power level:
1.
Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read I
out directly from the digital calorimetric meter.
Note 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. A App' h SOP /II-3
I E
I.
Continue the reactor startup by withdrawing only one control blade I
at a time, maintaining the reactor period at no less_than 100 seconds.
J.
As the scheduled power icvel is reached, stabilize power in either manual or automatic control and complete the following:
1.
Switch the IRM recorder to slow speed and secure the SRM 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 enough to get a representative AT on the primary and pool.
4.
Announce to experimenters the reactor power level.
11.1.3 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 f
not less than 35 seconds.
2.
The WRM selector switch must be in the 5 KW red scale position or above.
3.
The power trace pointer (black) on the WRM recorder must be reading greater than the auto control prohibits set point (red).
I 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.
8 Rev. _9/80 ppp.d k
S0P/II-4 1
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{'
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REVISION NO. 4 12/19/80
.l SOP /II-9 Revised 12/80 l
SOP /II 'Od Revised 12/80 l
SOP /II-ll Revised 12/80 lI
!I s
f 18 l
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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 selector switch so as to keep channel WRM-4 on scale.
D.
Complete the Reactor Shutdown Checksheet.
I Ascertain that the reactor system is secured and enter same E.
in log book.
11.2.1 Fuel Handling Procedure A.
All fuel transfers will be authorized by the Reactor Manager or his designated representative.
B.
If a fuel assembly is determined by the Shif t Supervisor to be damaged, authorization must be obtained from the Reactor Manager prior to loading that element in the reactor.
The Special Nuclear Materials Custodian (Reactor Physicist)
C.
shall provide a step by step fuel movement procedure anytime fuel is handled.
D.
Fuel, new or irradiated, shall only be handled one element I
at a time.
E.
The reactor will be shutdown prior to handling fuel in the I
reactor.
Fuel may be handled in the weir area while the reactor is operating.
F.
Containment integrity is required anytime irradiated fuel is being handled.
G.
Pealth Physics coverage shall be necessary when the pool is below normal operating level, inspecting irradiated fuel, shipping irradiated fuel and handling suspected ruptured irradiated fuel.
H.
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 g
direct supervision of a senior reactor operator may handle 5
fuel.
The senior operator is in charge of the fuel handling evolution and is responsible for the proper conduct of the
(
evolution.
SOP /II-9 Rev. 12/80 App'd
I the element by pushing down and turning until it floats off.
Failing to release the element in this manner may result in accidentally lifting and leaving the element a few inches off of its I
seated pc-ition without realizing it.
11.2.2 Procedure for Handling Fuel in or out of the Core A.
Obtain a fuel handling sequence from the Reactor Physicist.
B.
Inspect the fuel handling tool.
I C.
Place the bridge ARMS to upscale position.
D.
Insure the pool is at the normal operating level or pump the pool to refuel level as necessary.
E.
Remove the pressure vessel head.
F.
Turn on the Source Range Monitor Scaler and Chart Recorder.
Drive in the fission chamber to = 1000 counts.
G.
Attach 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 I
supervising Senior Reactor Operator.
NOTE: A positive latch is achieved only whcn 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 element 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 I
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.
M.
Install the pressure vessel head.
(If the pressure vessel head is to be left off at this point, install the aluminum protective head on the pressure vessel.).
I I
Rev.12/80 App'd 644 S0P/II-10a I
'/
~
- I 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 element locations data sheet in the control room.
P.
Turn the bridge ARMS back downscale.
Q.
Secure the SRM and pull the fission chamber to full out.
11.2.3 When starting up the 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 the subsequent start-up.
11.3 Control Blade Offset Mechanism Removal II.3.1 Conditions Prior to Removal A.
The control rod offset mechanism 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 rce will not be raised from their fully lowered position 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 of fset mechanism removed.
E.
A ilealth Physicst or a 11ealth Physics Technician is to be present when the pool water is lowered and when the mechanism is brought out of the water.
I E
Rev. 12/80 App'd,[d1' SOP /II-ll n
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f 1
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4
\\
REVISION NO. 5 1/30/81 l
S0P/VII-63 Revised 1/81 4
j SOP /VII-64 Revised 1/81 1
SOP /A-4 Revised 1/81 l
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-l8-l,... -. - -. - _.
1 I
door 101 and the personnel air lock doors.
With the reactor operating the compressor for isolation valve 168 may only be electrically secured when the valves are placed in the closed position.
Should this be necessary, open the I
local switch only, because the main switch also provides power to the facility and reactor isolation systems.
I The instrument air compressor may be shutdown by opening its local breaker.
Its main supply may be secteed at I
breaker #3 of LP-ll.
If secured and air wnply is still required, the cross connect valve from the main compressor may be opened.
If any of the components or compressors above are secured or placed in a position other than normal, the component shall be tagged in accordance with the tag-out procedure.
VII.ll Beamport Water System See Section VIII.4 VII.12 Sulphuric Acid System I
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.
I' Bulk sulphuric acid is delivered by tank truck and is transferred I
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 be exercised. The tank truck can easily exceed the receiving capacity of the system.
Insure that the tank pressure does not exceed 15 psig. and closely monitor tank levels.
.I Rev. _1 '81 App'd.dIQ S0P/VII-63 I
]
i 1
A.
Check valve 1 closed and valves 2 and 3 open, i
B.
Crack open the Tank-0-Meter bubbler valve / ta give an l
air flow of 3-4 bubbies per second.
Note and record l
the tank level indicated on the Tank-0-Meter.
l C.
Remove the cap on the fill line to enable conr.ection af l
the transfer line from the truck.
Commence filling the tank.
O.
While the tank is filling, watch the Tank-0-Meter to l
insure that an air flow of 3-4 bubbles per second is maintained.
l CAUTICN:
If the system is over filled acid will spill into the mixing tank.
The heat generated at this point j
could result in damage to the acid handling system.
E.
When the tank volume reaches 750 gallons, secure the l
transfer.
I F.
Disconnect ti.
transfer hose into the storage tank.
i G.
Record the final volume of the tank and report to the j
truck driver the amount of acid received.
Close the l
bubbler valve.
lI i
VII.12.2 Transferring Acid from the Storage Tank to the " Day Tank" I
When the acid in the day tank has been used, the tank is refilled with acid from the storage tank by carrying out I
the following procedure.
A.
Check valves 2 and 3 open.
B.
Crack open the bubbler valve (7) to give an mir flow I
of 3-4 bubbles per second.
Rev.
1/81 App' hdM -
SOP /VII-64 I
I I
u
1 4
App'd u/ h Rev.
1/22781 ~ ~"
UNIVERSITY OF MISSOURI RESEARCH REACICR FACILITY REACTOR SHUTDOWN CHECKSHEET DATE____ _ _ _____
i 1.
Time of reactor shutdown.
2.
All biades bottomed and drive mechanism full in.
3.
Magnet current switcn off.
4.
SRM set to requi red pos i tion......
E Reactor primary system shutdown per 50P IV.
I 5.
6.
Pool system shutdown per 50P V.
7.
Secondary system shutdown per 50P VI..
l a.
Cooling tower fans off.
8.
Digital readout switch of f.
9.
Annunciator board on off 10.
Reverse osmosis unit secured..
11.
Sarple inventory satisfactory and data sheets updated..........
12.
Si integrators recorded.
13.
All bypass switches of f and keys in key box......
14.
Master switch off
. -. o n... _ ---.
15.
DCT system secured.
I 16.
Room 114 check:
a.
Cooling flow to P501 A/B secured....
l b.
Valves S1 and S2 hydraulic motor off.
Np system and air to valve header secured..
l c.
d.
Calgon units secured..................
e.
Room 114 pump controllers locked out.
17.
Completed and logged reactor shutdowa checksheet.
l 5
BUILDING SHUID04N CHlCKSHEET l
1.
Pool level normal..
2.
ARM trip levels set per 50P.
I 3.
Annunciator bom J off..
4.
TV ur.. secured.
5.
ARM and off-gas recorder paper supply okay, charts timed and dated.
6.
Primary / pool drain collection system s? cured per SOP.
7.
Routine patrol completed.
8.
SRM, IRM, WRM, PRM, ARM and process radiation moni tors in operate mode....._ _ _ _
9.
Master key swit ch of f and in key box..
I 10.
Test of containnent intrusion alarm completed.
System energized.
11.
All keys accounted for.
I 12.
Building shutonwn and reactor secured..
13.
control room doors locked......
14.
Complete ' ouilding shutdown checksheet.......
I 15.
logbook ntries complete, crews signed out.
- Teiifo~r Reactor Operator
~~~
I SOP /A-4
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REVISION f40. 6 I
l 4/23/81 SOP / A-l a Revised 4/81 l
SOP /A-4b Revised 4/81 l
(Page 2 of Reactor Shutdown Checksheet)
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1 REACTOR STARTUP CHECKSHEF.T DATE:
q FULL POWER OPERATION
~
April 1,1981
('r Low Power Forced Circulation) 1 o
il i e BUILDING AND MECHANICAL EQUIPMEt;T CHECKLIST Run emergency generator for 30 minutes anil check the governor oil level.
1.
(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.
l 2.
a.
l (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 50P while in west tower.
l c.
Test the stack monitor is floy a'.arn.
1 1
3.
Visual check of room 114 equipment ccmpleted.
j a.
P501A and P501B coolant water v&lves open.
b.
Sl and S2 hydraulic pumps on (oil level normal).
Pump controllers unlocked to start (as required).
c.
d.
Insure N2 backup system on per 50P.
Open air valve for valve operating header (V0P 31).
e.
l3 f.
H2 backup valve open.
jg g.
Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).
4.
Visual check 01 CT equipment completed.
a.
Oil level in CT fans normal (Monday startups).
l 5.
Beamport Floor l
a.
Beamport radiation shielding (as required) b.
Unused beamports checked flooded (Monday)
I
-'~~~ 6.
c.
Seal trench low level alarm tested (Monday)
Emergency a-ir compressor (load test for 30 minutes on Monday) 7.
Reactor pool a.
Reflector experimental loadings verified and secured for start-up.
l b.
Flux trap experimental leading verified and secured for start-up, or l
strainer in place.
I REACTOR CONTROL SYSTEM CHECKLIST 1.
All chart drives on; charts timed and dated.
IRM recorder to slow.
I 2.
Fan failure warning system cleared.
3.
Annunciator board energized; horn off.
I
~ 4.
Television receiver on.
5.
Primary / pool drain collection system in service per SOP.
6.
Secondary system on line per S0P (as needed).
., 7.
Primary system on line per 50P.
I a.
Primary cleanup system on line.
_ _ 8.
Pool system on line per SOP.
~
a.
Pool cleanup system on line.
1.]~,
b.
Pool skinmer system vented.
I c.
Pool reflector op trips set per SOP.
__,,9.
Valves S1 and S2 cycled in manual mode and positioned as required.
Nuclear instrumentation check completed per 50P.
I
_ _ 10.
the following trip values were obtained during the check.
a.
IRM-2, run-in seconds Scram seconds IRM-3, run-in __ _ seconds Scram seconds l
WRM-4, run-in ~ ~ '
Scram ~ ~ ~ ~ %
PRM-5, run-in Scram PRM-6, run-in ~
~'%
- 11. Channel 4, 5, and '6 Vots returned to last heat balance position.
__ _ __12. SRM-1 detector response checked and set to indicate > 1 cps.
I 1
s.
Repl.
8/76 App'd
/ S /25 I
Rev. 4/1/81 SOP /A-la
~~
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-;I f I i
f REVISION NO. 7 i
5/14/81 SOP /IV-2 Revised 5/81 4
)
SOP /IV-3 Revised 5/81 i
SOP /IV-4 Revised 5/81 l
l S0P/IV-5 Revised 5/81 SOP /V-2 Revised 5/81 50P/V-3 Revised 5/81 i
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I d.
Primary system flow recorder and temperature recorders are energized and the primary demineralizer flow recorder is energized. Time and date the recorders.
Place heat exchanger bypass switch 2S41 in the position c.
required for the heat exchanger combination to be used.
B.
Verify antisiphon vent valve closed.
C.
Close antisiphon system manual drain valve.
D.
Set the anti-siphon system air regulator to 35 psig and open the air inlet valve.
I E.
Place master switch 1S1 to test.
F.
Open valves 527 E and F.
G.
Place valve 545 switch to auto /cl. sed.
H.
Place valve 527A switch to auto / closed.
I.
Place valve 527B switch to auto / closed.
J.
Place pump P-Ei3 switch to on, P-533 may or may not start, depending upon demand.
K.
After P-533 has completed charging, place valve 526 switch to auto / closed.
L.
Place valve 507A/B switch to manual /open. Valves 543A/B will automatically close at this time.
I M.
Immediately place valve 527C switch to open. 'Ihe primary system is now pressurized.
N.
Cycle valves 546A/B switches 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 verify the increase and then decrease in primary system flow as each valve is cycled.
Q.
Start the remaining pump 501 A or B.
Verify proper primary system flows.
I R.
Start pump 513A and verify proper flow.
S.
Open the antisiphon system drain valve and blow the system dry.
Close the valve, wait 10 seconds and repeat. This may have to be done three or four times to insure that all the water is drained.
T.
Close the antisiphon system drain valve.
U.
Insure that the antisiphon system pressure is set at 36 psig; I
tnen close the air inlet valve.
Rev.
5/81 App'd 1'fik SOP / IV-2 y
I V.- Place the following valve controls in the indicated positions.
Valve Mode Position I
V507A/S Auto Closed V546A/B Auto Open Open V543A/B I
V545 Auto Closed V526 Auto Closed V527A Auto Closed V5278 Auto Closed I
Open V527C W.
Verify that all the valve position indicating lights are operating l
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-I eration by a visual examination of the actuator linkage during op-eration.
In the case of V5433 or B indication failure, perform CP-24 Compliz.nce Check.
(NOTE:
If the malfunction is determined to be an electrical indication problem not used in the safety system, the re-actor may be operated with repairs being made at the next maintenance shutdown.)
l X.
For 10 MW, 2 pump operation, balance loop flows as follows:
I 1.
Check the flow in the two heat exchanger loops and adjust the 540 valves to balance the flow.
2.
Check the t.P ccr".is each of the pumps and adjust the bypass valves to balance the flow delivered by each pump.
IV.2 St Jtdcwn of Primary System NOTE: The primary system should remain in operation for fif teen 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.
D.
Secure P513A E.
If both pun.ps P501 A and/or P501B are running, secure them simulta-neously to reduce check valve slam.
F.
Verify that valves 546A/B open on the loss of flow.
G.
Place the 507A/B mode switch to manual.
H.
Verify that V507A/B close and that valves 543A/B open.
I Rev.
S/81 App'd [J -n SOP / IV-3
' I
1.
Open the drain valve on the antisiphon system and then slowly open the vent valve and M eed 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 Cosed V527A Manual Closed I
V546A Manual Caen V527B Manual Closed V546B Manual Open V545 Manual Closed V543A/B
Open V526 Manual Closed K.
Verify that valves 507A and B have operated and sealed closed by I
cycling V507A/B while noting the system pressure drop.
There will always be some pressure drop due to prec.sure 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.
(NOTE:
If the mal-function 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 maintenance 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 P501 A/B, P513A, 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 The anti-siphon system is designated to provide sufficient aire (u,' der 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 valves must be less than six inches.
The procedures below will be followed to insure that the anti-siphon system is op-erated within the above limitations.
IV.3.2 Decreasing Pressure in the Anti-Siphon System The system contains a pressure switch which will initiate an annunciator alarm when the system pressure falls below 30 psig upon receipt of the Rev.
S g App d g
sop /Iy_4 i
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 27 psig, the reactor shall be shutdown until the problem is corrected.
IV.3.3 Increasing Pressure in the Anti-Siphon System I
After the primary coolant system has been placed in service, open the system drain valve and check that the system is drained of all water. The system's pressure will then be returned to the middle of the operating band (~36 psig) and I
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-leakage 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 flowing 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 water drained is significant, record this fact on the reutine patrol sheet and in the console log.
D.
Return the system pressure to noiral (~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 through E above.
l Rev.
S/31 App'd / A --
50P/IV-5
i I
j 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 appears normal and the j
tes' 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.
F.
Verify that the local pump stop switches in room 114 are unlocked.
NOTE:
If the breaker is closed, the selector switcn 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 appropriate by turning the control switches to on.
Veri fy proper flow.
K.
Start cleanup pump P513B and verify flow.
L.
Adjust pool flow if required by throttling the HX outlet valves (522A and 5220) as necessary.
I 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 system 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 ead make repairs prior to any start up.)
i I
0.
If not required for other evolutions, turn master control switch 151 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.
S/81 App'd A A n SOP /V-2
_ _ _ _.. _ _ _ _. _ _ _ _ - _ ~ _ _ _ _ _
I D.
Verify that valve V509 closes automatically.
(
j I
l E.
Place V509 in the manual / closed position.
F.
Verify that all the valve position indicating lights are operating.
If I
not, replace the appropriate light bulb.
If this does not clear the j
malfunction, determine the cause and make repairs prior to any reactor start-up.
f G.
Turn 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 water in T301 should be used first.
l l
A.
Filling may be accomplished with the skimmer system (Section VII.S.1) with or without the skimmer pump operating and the reactor either operating or shutdown.
Required operational pool makeup will be accomplished in this manner.
1.
Check capacities of tanks T300 and T301 and check proper valve lineup.
l 2.
Jbserve the pool level and check that the skimmer pump is secured.
3.
Remotely open valve 565B from the primary / pool drain collection system control panel.
Insure valve does indicate open.
4.
The skimmer pump may be started at this point, however, it will lg fill by gravity if desired.
=
t 5.
When proper pool level is obtained, secure the skimmer pump and remotely close valve 565B.
Insure it does indicate closed.
B.
The second approved method of filling the pool is via the 4" line from tank T300/301 to the pool pump suction 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, fi'. ling the pool
)
through a pool pump can be avoided by opening valve V522C and per-mitting T301 or T300 to drain by gravity feed alone.
3.
Close valve V522C when the filling operation is completed.
i
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Rev. 5/31 App'd [ m SOP /V-3
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l 8
lI II 1
5 1
REVIS10f4 f40. 8 5/20/81 l
S0P/A-la Revised 5/81 I
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REACTOR STARTUP CHECKSHEET DA l t. :
B FULL POWER OPERATION (or Low Power Forced Circulation)
BUILDING AND MECHANICAL EQJIPMENT CHECKLIST
___1.
Run t~ergency 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.)
2.
a.
Check operation of f an failure buzzer and warning light. Shift fans.
(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 />.)
~
L.
Test stack' monitor per 50P while in west tower.
c.
Test the stack monitor low flow alarm.
3.
Visual check of room 114 equipment completed.
l a.
P501A and P501B coolant water valves open.
b.
51 and 52 hydraulic pumps on (oil level normal).
c.
Pump controllers unlocked to start (as required).
d.
Insure N backup system on per 50P.
2 e.
Open air valve for valve operating header (V0P 31).
I f.
N backup valve open.
7 g.
Cneck 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 le/el in CT fans normal (Monday startups).
5.
Beamport Floor Beamport radiation shielding (as required).
l d.
I b.
Unused beamports checked flooded (Monday).
c.
Seal trench low level alarm tested (Monday).
6.
Emergency air compressor (load test for 30 minutes on Monday).
7.
Reactor Pool I
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.
lW REACTOR CONTROL SYSTEM CHECKLIST 1.
All chart drives on; charts timed and dated.
IRM recorder to slow.
'T 2.
Fan failure warning system cleared.
,I 3.
Annunciator board energized; born off.
~
4.
Television receiver on.
5.
Primary / pool drain collection system in service per SOP.
I 6.
Secondary system on line per SOP (as needed).
7.
Primary system on line per SOP.
a.
Primery cleanup system on line.
8.
Pool system on line per 50P.
I b.
Pool skimmer systen vented.
Pool cleanur system on line.
a.
Pool reflector Ap trips set per 50P.
c.
I
__ 10.
Nuclear instrumentation check completed per 50P.
9.
Valves Sl and S2 cycled in manual mode and positioned as required.
The following trip values were obtained during the check.
a.
IRM-2, run-in seconds Scram seconds I
WRM-4, run-in ~ ~ ~ - seconds Scram seconds IRM-3, run-in PRM-5, run-in -
Scram -
~ %
I
_ 11.
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 a d5._.
SOP /A-la Rev.
5/81 App'dl' 4
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I REVISION N0. 9 5/29/81 50P/A-8a Revised 5/81 B
E l
8 1
5 1
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7
~
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5 1l I l
Date J'
Reactor Routine Patrol 1.
Tu.e of start of patrol 2.
Time and date all charts
- 5 3.
Check ARMS trip settings
'i 4.
Visual check of entire pool 5.
Anti-siphon tank pressure
+3.0 psig E 6.
North iso door seal press 18-28 psig j
7.
South iso door seal press 18-28 psig 1
8.
5th level backup doors Open j
)
9.
5th level detector iing 0-3.5 mr/hr W10.
5th level trip point s c 3.5 mr/hr j
f 11.
16" iso vlv A air pressure 45-55 psig i
~
r
- open, 12.
Emerg compress on standby ge p g 13.
Containment hot sump pumps Operable 14.
Door 101 seal pressure 18-28 psig 15, BP floor Conditions normal i
16 Lockea I.Fuelvault 17.
Inner airlock door seal press 18-28 psig a
i 18.
Outer airlock door seal press 18-28 psig j
19.
T-300 level
> 2000 gal 20.
T-301 level
< 6000 gal 21.
1.abyrinth sump level < Alarm Pt.
RO UNIT IRundaily:
)
ON[Run on 0700 routine]
2 ', ~
i POWE_R_0N \\to T-300 or drain./
tfor 1 4 hrs.
/
23 24-28 C / standby I
R0 Unit Temp 24.
RO Unit Pressure 190-200 psig / standby 3
1
~~
lE 25 EG rm.IEdL6p 90hcN"Yo huf8l-c Thermostat > 50"F (Gas > sicht glass.)
Temo
> 40 F lg Thermostat > 55 F 26.
T-300, 301 room l herinos tat > 40 F L
Rm 114 particulate fil ter t.P
< 2.5" Hp0 77, t
j On the first routine patrol of the day or the first patrol af ter a startup, drain all water fr the anti-siphon system.
If draining causes the pressure to drop significantly, return to the
! middle of thn band (36 osig) and record the pressure here.
Rev. 5/81 App'd
[/b SOP /U3a ^
i
l
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REVISION NO. 10 5/30/81 4
50P/A-ll Revised 5/81 t
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b -
. - ~.
RETURN ORIGIriAL TO HEALTH PHYSICS OFFICE NO.
I WASTE TANK SAMPLE REPORT l
TANK NO.
TANK LEVEL (Li te, i
TIME DATE Completed adding water to this tank.
i
'~
TIME DATE 4PLER 1.
Analysis Results Nuclide Half Life Physical Form Concentration MPC Ac tivi ty
.___[p Ci /ml )
__[p Ci )_
a.
H-3 12.3Y I
b.
4I II j
lI I
a 1
)
pH TOTAL CONCENTRATION (b)
Analysis by Date Time j
Concentratio.jg/,ml Total Volume (liters.).
gti_vi ty_,(mcM (a) x
=
(b) x
=
IAnyDischarge Shift Supervisor 2.
Approvals Required For I Discharge of Total Activity s 4 mci or to Secondary System Reactor Manager DiI scharge Limit Approved Health Pnysics 3.
Action Taken Date Discharged Time Discharged Volume Discharged (Liter-ITr Discharged to (check one)
Sanitary Sewer _ Secondary System f;ot Discharged RelGrks l l _...._
y...._...-....-......
Rev. _5/81 App'd
[
50P/A-11
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SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT i.
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-i gas system plenum that supplies sample air to a filter paper monitored I
by a beta scintillation detector followed by a charcoai filter moni-1 tored by a gamna scintillation detector followed by a shielded gas i
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 each detector.
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}
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an,-,----.,-,--.-,--,-,--,-,--..--.-,-,n,n,,,,--,--..~.,.n n,-
,_----_.n,
1 I
I SECTION IV PLANT AND SYSTEM MODIFICATIONS August 1980 PSdification 80-4: Moves the air supply for the containment back-up doors to the emergency 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.
I 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 metal to metal contact between the anvil and offset tube and reduces friction in the system.
Safety Analysis: The installed bushing presents no unreviewed safety hazard. The modification should help minimize problems with misalignment of the y
anvil and magnet.
I I -
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II l'jg Modification 81-6:
Improves the mechanical stability and reduces the amount 13 of stainless steel which can be activated in an offset mechanism.
The concept is identical to existing Type II offset mechanism.
i Safety Analysis Summary:
The new materials and increased mechanical stability present no unresolved safety questions. The reduction in stainless steel will i
help to decrease operator dose during maintenance on the offset.
I l
l Modification 81-8:
Replaces the waste tank system two steel filter horsings with one non-corrosive plastic filter housing.
i Safety Analysis Summary: The modified system components propose no unreviewed i
l5 g
safety hazard.
All components are being replaced with materials of superior 1
I quality than presently installed, increasing ease of operation of the waste tank filter system.
April 1981 i
1m Modification 81-4:
Installs a means for filling the loop seal for the pool ig l
averflow in Room 114 pipe tunnel with DI water.
Safety Analysis Summary: The modification to the pool overflow line pre-l sents no unresolved safety question. The installation allows easier operation and use of DI water versus pool water for filling the pipe.
ig Modification 81-9: This modification installed a pump from T-300 discharging j
to DI - 200 regeneration station.
The T-300 pump provides an alternate means of supplying DI water to DI - 200 regeneration station, minimizing depleting 01-300 during a 01-700 regeneration. The use of the T-300 pump will greatly increase DI-300 resin life and decrease the cost in making DI water.
I
-2e-g
I Safety Analysis: Modification 81-9 presents no unresolved safety questions.
The installed alarms insure proper level is maintained in T-300.
Modification 81-10: This modific& tion was the replacement of the carbon steel tank and some waste tank system piping modifications. This modification reduces maintenance required for the tank pks provides additional or alterna-tive tanks for pool water storage.
Safety Analysis Summary: Modificatlor, 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.
l Modification 81-13:
Replaces the unitized fan cross piping for cooling tower cails #1 and #2 with new pipes of identical design. The replacement is
(
due to corrosion over the years.
Safety Analysis Summary: The parts installed in CT #1 and #2 are identical to those originally installed and pose no new or unresolved safety question.
l l
June 1981 l
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 1
with 6", 300 psig, CPVC increasing the pressure rating and pipe diameter. The flow path is the same and,due to the larger diameter, pipe will allow better flow.
Safety Analysis Summary: Modification 81-12 presents no unresolved or new l
safety c,
':ns.
The larger diameter pipe helps increase the total fle-delivered for emergency pool make-up.
I 1l l l
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4 I
SECTION V NEW TESTS AND EXPERIMENTS New experimental programs dt; ring the period of July 1980 through June 1981 l
are as follows.
t f
RUR 262 Experimenter:
Guy Schupp
Purpose:
To use gamma rays from 2n intense radioactive source to investigate crystal properties and l
structures by inelastic ard elastic scattering measurements.
==
Description:==
Intense gamma ray sources will be produced by activating in the flux trap sources foils i
welded in aluminum cans. The source is then transferred to the experiment station on the
{I l
north end of the beamport floor where the experiment is performed.
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I SECTION VI SPECIAL NUCLEAR MATERIAL ACTlVITIES I
l.
SNM Receipts: Juring the year, the MURR received fuel from Rockwell Interr.ational 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 i
2.
SNM Shipments: Three shipments of spent fuel elements were sent to U.S.D.O.E. Savannah River Plant for reprocessing.
Grams Grams Shipper Elements U
U-235 MURR 775F79, 86, 89, 93, 98, 17,126.28 15,016.98
.I 105, 106, 107, 108, 109, 110, 111, 112, M01, M02, 4, 6, 7, 8, 9, 10, 11, 12, 13 3.
Inspections:
On May 5-6, 1981, a Physical Protection Inspection was I
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 cf 30 June 1981, the MURR financially responsible inventory was as follows:
Total U
= 41,894 grams i
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.
lI -
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Fuel elements on hand have accumulated the following burnup as of i
30 June 1980:
)
Fuel Element Accumulated Fuel Element Accumulated Number MWD Number MWD
,I M03 149.33 M042 145.49 1
MOS 149.33 M043 125.12
,I 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 i
M022 108.94 M056 0.0 M023 147.69 M057 82.05 I
M024 146.79 M059 56.68 M025 147.69 M060 67.81
}
M026 135.98 M061 56.68 M027 120.41 M062 67.81 l
M028 148.00 M063 54.81 M029 120.41 M064 66.99 M030 148.00 M065 54.81 l
M031 107.98 M066 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 i
M037 131.76 M074 0.0 i
M038 120.44 M075 0.0 i
M039 142.66 M077 0.0 P
i M040 120.44 M041 125.12 M049, 50, 51, 52 not issued and M058 returned June 23, 1981.
lI
i 4
Total U
= 1,112.39 grams i
f Total U-235 = 1,036.19 grams Also MURR owns a total of 128 grams U and 49 grams U-235.
The 12 gram increase in U and U-235 from last year is due to acquiring two sets of plates l
for Nuclepore for use in the thermal column.
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SECTION VII REACTOR PHYSICS ACTIVITIES I
1.
Fuel utilization:
During this period, the following elements reached I
their licensed burnup and were retired.
M018 M028 M019 4030 M023 M032 I
M024 M03a M025 M035 Normally 24 fue' elements are listed as retired,but due to increased shipping costs for new and ir radiated fuei, 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 on 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)
M045, 47 25 August 1980 M046, 48 11 November 1980 I
Nc s:
Serial #'s 49 thru 52 were.'ot issued.
Core XXVII M053, 54 1 December 1980 I
M055, 57 29 December 1980 M056, 58*
(initial criticality will
.I be next fiscal year)
M059, 60 9 February 1981
- As of June 30, M058 was returned to Atomics International for adjustment of end fitting.
- I -
l i
Core XXVIII M061, 62 9 February 1981 M063, 64, 65, 66 9 March 1981 M067, 68 4 May 1981 ii Core XXIX M069, 76 4 May 1981 M070, 71, 73 (Save not been received for use) l M072, 74, 7; (initial criticality will be j
next fiscal year)
Core XXX "377 (initial criticality will be next fiscal year) f M078-84 (have not been received for use)
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2.
Fuel Shipping: Three spent fuel shipments departed the facility ijg during the tiscai year. The shipments contained the following g
i elements:
775F79 775F108 M006 775F86 775F109 M007 i
j 775F89 775F110 M008 775F93 775 Fill M009
)
)
775F98 775Fll2 M010 1
775F105 M001 M0ll 1
775F106 M002 M012 775F107 M004 M013 3.
Fuel Procurement: At the present time, MURR fuel is being fabricated by Rockweli International Energy Systems Group of Canoga Park, Cali-fornia. This work is contracted with U.S.D.0.E. and administered by l
the Idaho Operations Office.
i j
4.
Licensing Activities: A revised physical security plan as per 10CFR70:67 i
that was submitted May 16, 1980 is still pending. Amendment #13 to l
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 Specificction 6.1 to reflect the current admini-r strative organization for our facility. Amendment No.14 to Facility Operating License No. R-103 was issued April 14, 1981. This amendmen';
l changed the definition of " Reactor Secured," item 1.20. Appendix A, l
of the Technical Specifications of our facility license.
I I
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,I I
S.
Reactor Characteristic Measurements:
Shim Blade "D" Reactivity calibration measurements were performed in April on Core A0-2 at 605 MWDs.
A series of five (5) reactivity measurements for various flux trap sample loadings were performed during April, May and June.
A ph.vsical inspection of the following fuel elements was performed at approximately 130 MWDs to verify the operational parameters:
M028 from Core 24 on 4/14/81 M035 from Core 25 on 6/04/81 M042 from Core 26 on 4/14/81 All measurements were within operational requirements.
!I I
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lI w--
1 1
1!I l
SECTION VIII
SUMMARY
OF RADIOACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT fg Liquid Effluent 1-80 to 6-30-81 i3 l
Nuclide Amount (Ci)
H-3 via cooling tower drain
<.001 i
.434*
Na-24
.001 l
K-42
.001 i
Sc-46
.007 Cr-51
.029 Mn-54
.005 Mn-56
<.001 I
<.001 Co-58
.001 Fe-59
.001 f
.032 I
Zn-65
.110 Ni-65
<.001 I
.001 Se-75 As-76
<.001 l
As-77
.005 l
Ag-110*
.002 Sn-ll3
<.001 l
Sb-122
<.001 Sb-124
.006
.001 Sb-125 1-131
.001 l
I-133
.001
{
Ba-133
.001 j
Cs-134
.001 Cs-137 1
Ba-140
.001 i
i l I
i HF -181
<.001 i
Au-196
<.001 1
Au-198
<.001 l
Hg-203
.001 l
<.001 i
- 0.334 Ci of the H-3 released after 3-11-81.
Stack Effluent 1-80 to 6-30-81 1
Nuclide Amount (Ci)
)
H-3 10.42*
I Na-24
.000003 l
Cl-38
.000117 Ar-41 1733.48 Sc-46
.000001 l
Cr-51
.000001 Mn-54
<.000001 Mn-56
.000001 Co-57
<.000001
.000001 Co-58 Co-60
.000002 Cu-64
.000020 Zn-65
.000003 j
Se-75
.v00003
{
As-76
<.000001 As-77
.000332 Br-82
.000048 I
.000001 Kr-85;a
.000001 Kr-87
.000001 Rb-89
.000001 Sr-92
<.000001 Nb-97
<.000001 Zr-97
.000001 Mo-99 -
Tc-99m
<.000001 l
Tc-101
.000005 In-113m
<.000001
- g
- m In-ll4m
<.000001
.000001 In-ll5m Cd-115
.000003 Sb-122
<.000001 1-128
.000023 I-131
.000603 I-132
.000223 Te-132
.000001
.000001 Ba-133 I
I-133
.001082 Xe-133
.000026 Xe-133m
.000003 I-134
.000440 I-135
.000885 Xe-135
.000100 Xe-135m
.000410
.000001 Cs-137 Cs-138
.000006 Ba-139
.000053 l
Ce-139
.000002 Ba-140
.000001 l
l La-140
.000001 Ce-144
.000001
.000001 Hf-181m Ta-182
.000001 Ta-183
.000004
<.000001 Ir-192
.000001 Au -196 l
Hg-203
.000068 l
Bi-214
.000007 l
Pb-214
.000005
- Less than 0.001 Ci H-1 released to air by evaporation from cooling tower.
lE,
.------n,._.-
,.,. _. _. - -,... ~. - -. _. - -. -
SECTION IX
SUMMARY
OF ENVIORNMENTAL SURVEYS I
Environmental samples are colleci.ed yearly at nine locations and analyzed for radioactivity.
These locations are shown in Figure 1.
Soil and vegetation samples are taxen 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 Tri tium 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/g 9.1 pCi/g vegetation 1.
Sampling Date:
11-5-80 Determined Radioactivity Levels Samole Alpha Beta Gamma _
Tritium 1 y 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 v 18 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 5 v :8
< 0.2 pCi/g 21.55 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 6 v 18 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 8 v 18 0.2 pCi/g 18.48 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 9 v 18 0.2 pCi/g 15.29 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g l
1 S 18 0.7 pCi/g 11.93 pCi/g
< 0.04 pCi/g I __
I 2 S 18 0.3 pCi/g 8.06 pCi/g
< 0.04 pCi/g 3 S18 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 pCi/g 5 S 18
<0.2 pCi/g 11.91 pCi/g
< 0.04 pCi/g 6 S 18
<0.2 pCi/g 8.26 pCi/g
< 0.04 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
< 0.04 pCi/g 4 W 18 0.5 pCi/1 7.32 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml 6 W 18 0.5 pCi/l 5.14 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml 8 W 18
< 0.2 pCi/l 13.05 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml 9 W 18
< 0.2 pCi/l 6.33 pCi/l
< 0.04 pCi/l
< 9.1 pCi/ml I
Detection Limits Matrix Alpha Beta Gamma Tritium Water 0.2 pCi/l 2.5 pCi/l 0.04 pCi/1 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g vegetaticc.
2.
Sampling Date:
4-24-81 Determined Radioactivity Levels Sanple Alpha 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 pCi/g 32.6 pCi/g
- 0.04 pCi/g
< 9.1 pCi/g I
3 V 19
< 0.2 pCi/g 18.6 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 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 V 19 0.23 pCi/g 29.0 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g
-40 g
I 7 V 19
< 0.2 pCi/g 15.8 pCi/g
< 0.04 pCi/g
< 9.1 pCi/g 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 1 S 19 0.34 pCi/g 4.6 pCi/g
< 0.04 pCi/g 2 S 19 0.52 pCi/g 10.2 pCi/g
< 0.04 pCi/g 3 S 19 0.92 pCi/g 11.1 pCi/g
<0.04 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 7 S 19
< 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/1
< 0.04 pCi/l
< 9.1 pCi/ml 6 W 19
< 0.2 pCi/l 10.0 pCi/l
< 0.04 pCi/l
< 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/l 10.4 pCi/l
< 0.04 pCi/1
< 9.1 pCi/mi l
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[
LOCATION OF SAMPLE STATIONS RESE ARCH REACTOR FACILITY g
UNIVERSl!Y OF MISSOURI I
n>
g.
M M
M M
M M
M g
g 4
4 l
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,I SECTION X i
SUMMARY
OF RADI ATION EXPOSURES TO FACILITY STAFF, i
EXPERIMENTERS AND VISITORS I
personnel Monitoring (exposure in rrrem},
1980 f
July August Septenber October N o>embe r December 1
A B
C D
E B
C D
E B
C D
E B
C D
E B
C D
E B
C D
E l'
60 j
G 38 5 42 80 35 4 25 49 51 2
45 70 51 4
23 30 35 4]__.21 90 43 11 22 _ 7 76 g
M 14 5
626 18]O 8 6
75 190 11 4
177 330 11 4
97 12n _l)_1.0 1 Q))_4 7A]3 4 230_ 2D 63 2 G-5 pare
- 8 1
10 10 1
0 0
0 9
0 0
0 12 2 15 20 0
9 19 30 10 6 l
'OTQSpa re
- 4 1
40 40 2
0 0
0 2
0 0
0 0
0 0
0 1
0 0
0 2
3 180-370 4
fi '
33 78 4T-23iP61 30 50 26a 75 32 70 150 52 84 54 270 74 47 112 330 81 37 112 4TO l
UTHL ll 7 o R 5~3 R5f lF33 13T 4hd TF2T~ 181 666 17 26 281 740 10 23 155 640 20 21 2 31 790
{
ii-Spare
- 3 8
18 56^ 12 7 30 46-5 1
20 20-6 T8 T75 OT T6 12 31 199 18 5 98 24C UTd5 pare
- 1 3
1 C 33C~0 0
D-D~
22 70 lTU~4 3
1G1 270 4 3
208 37) 4 3
346 ' 30 e
{
U 5T-- W 33i 6 48 45 T60 0
50 73 225 0
4T-67 1G0 0 45 84 lQ_0 43 W3J 4
Y lanua ry February March April May June 10 10 _ 42 4
32 100 9QJ 3{a_,j } J _J gg_54U 46 2 20 30 48 2 10 10 46 7 45 220_h?
2 25 3Q}_5L_1 G[G)
U 15 2 270 47C 14 3 43 60 14 3 1653 4710 11 6 146 62$ 14 2 G-Sp a re
- 16 1
10 10 15 1
10 10 15 2 10 10 16 1
110 Ll$ _b 0
0 0_ ]2 7
51 T70 3
1 3D 30 _ 2 1
280_ 280_2 1
100 101 _ 0 2
45__5Q _0 4
1E01_ SILO
{Q5pa re*
3 1
12D-~12C]35-4B 81 2f01 51 63 105__310 49 68 66 27Q 67 56 70 26L _ 12__ b3__ 23 220 H
TB 47-10C3M_18__2 7__J B2 _lllD_li__._3 L__211_126 cJ 5 30
_1Ei._.li1IL16 in 19n 17 (LJLJ4 777 2ik)
UlH) 18 21 175 75C H-Spare
- 16 7
52 11C 22 8 65 130l_13 Ik _._5L _ 200d3_8 10__120 JO 11 sa 37 _ 21.
7 67 130 170
]UHSpare*
2 5
136 22C 2
6 158 75 3
2 100 160 1
1 30 _ _3Q1 1 2
55__._101__0 4
10L_450 D -
0 45-- 7B-~ 17C 0--'~48 84 22.~
0 51 108 360 0
53 81 23e 0
_.50 100 24L 0 50 114 i
Note:
G = mon tly beta-gamma film badge Column Headings: A = Type of dosimeter U(G) = monthly finger TLD B = Number reported as minimum H = biweekly beta-gama-neutron film badge C = Number reported with exposures above minimurr U(H) = biweekly finger TLD D = Average of exposures above minimum D = self-reader dosimeters E = Single highest dosimeter reported
- Used for temporary workers, new workers prior to issue of penr.anent, and replacement for lost badges.
^
I Radiation and Contamination Surveys The following table gives the number of surveys performed during Fy 80-81.
Radiation Contamination 331 333 Fif ty (50) Radiation Work Permits 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 leutron 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 Physics.
This is a new duty at MURR.
It is anticipated that the assignment will be rotated to other individuals at appropriate times.
Reactor Health Physics added two new continuous, recording, beta sensitive, air monitors and a neutron spectrometer (Sonner Spheres type) to the equipment inventory.
Equipment to enable Health Physics to 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 a 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. I l
l Two Health Physics procedures were revised and two new procedures were added during the year.
A Health Physics Technician was hired to replace one who terminated.
In addition, a student working half-time has been added to the Health Physics organization for this year.
A student from Northeast Missouri State University at Kirskville served a 5-week Health Physics trial internship at MURR. All concerned considered the trial a good learning experience.
Laboratory room surveys ware increased significantly and a daily " walk th: tugh" by Health Physics.vas added to routine duties to increase Health Physics k.nowledge of laboratory work.
Increased surveillance of personnel was accomplished by limiting general entry,..d 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 i
to discuss briefly, but the problem is being actively worked-on by Reactor Health Physics.
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 iesult, the reporter became enthused about the value of research performed at MURR and published an informative article on that subject in a local paper.
I I
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-