ML20097F477
| ML20097F477 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 12/31/1984 |
| From: | Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409190010 | |
| Download: ML20097F477 (51) | |
Text
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I IUNIVERSITY OF MISS'OURI -
l L: UNIVERSITY OF MISSOURI L .
RESEARCH REACTOR i 1,
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ANNUAL REPORT 1983-84 lI.
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4-fl{Y 4[ $( h '~ .0t i]g RESEARCH REACTOR FACILITY
i UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT AUGUST 1984 Compiled by the Reactor Staff Submitted by n J' C_. .
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J. C. McKibben Reactor Manager Reviewed and Approved k.
Don M. Alger Acting Director
TABLE OF CONTENTS Section Page Number I.. REACTOR OFERATIONS
SUMMARY
............... I-1 through I-12 II. OPERATING PROCEDURE CHANGES .............. II-1 through II-6 III. 1983 REVISIONS TO THE HAZARDS
SUMMARY
REPORT ................................. III-1 enly IV. PLANT AND SYSTEM MODIFICATIONS ........... IV-1 through IV-2 V. NEW TESTS AND EXPERIMENTS ................ V-1 only VI. SPECIAL NUCLEAR MATERIAL ACTIVITIES ...... VI-1 through VI-3 VII. REACTOR PHYSICS ACTIVITIES ............... VII-1 through VII-3 ?
VIII.
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT ............ VIII-1 through VIII-2 IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS ......... IX-1 through IX-5 X.
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFP, EXPERIMENTERS, ,
AND VISITORS ........................... X-1 through X-3 O
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SECTION I REACTOR OPERATIONS
SUMMARY
s Fiscal Year 1983-198'4 The following table and discussion summarize reactor operations in the period July 1, 1983 through June 30, 1984.
Full Power Percent
- Date Full Power Hours + Megawatt Days of Total Time of Schedule July 1983 706.4 294.44 94.98 106.38 Aug. 1983 689.8 288.13 92.94 104.10 Sep. 1983 674.'0 281.02 93.67 104.91 Oct. 1983 666.6 277.79 89.61 100.36 Nov. 1983 668.3 278.43 92.81 103.95 Dec. 1983 692.7 288.66 93.12 104.29 Jan. 1984 706.1 294.33 94.94 106.34 Feb. 1984 638.1 266.30 91.83 102.85 Mar. 1984 690.6 288.13 92.94 104.10 Apr. 1984 639.4 267.20 89.07 99.76 May 1984 656.5 273.81 88.33 98.92 June 1984 666.4 285.68 95.23 106.65 Total for Year 8,094.9 3,383.92 92.46% of 103.55% of time for yr. sched. time at 10MW for yr. at 10MW
- 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 monin or year. ,
n I-1
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l JULY 1983 The reactor operated continuously in July, with the following excep-tions: ten shutdowns for flux trap sample changes; one shutdown for mainte-nance; and two unscheduled shutdowns.
On July 6, a dip in electrical power caused a reactor scram. The power dip was verified by the University Power Plant, systems were inspected and reactor power was restored. On July 17, a manual rod run-in was initiated when the secondary system make-up valve stuck shut. The make-up valve was in-spected and exercised and the reactor returned to operation.
Major maintenance for July included verification and inspection of fuel elements for the Nuclear Regulatory Commission SHM inspection.
AUGUST 1983 The reactor operated continuously in August, with the following excep-tions: three' shutdowns for maintenance; nine shutdowns for flux trap sample changes; and four unscheduled shutdowns.
On August 8, a rod not in contact with magnet rod run-in occurred when blade "D" disengaged from its magnet during routine shimming. The anvil was cleaned and its position with respect to the guide tube was checked. During the subsequent start-up, blade "D" fell off again. The offset guide tube was aligned and the reactor returned to operation.
On August 12, there were two reactor scrams caused by momentary loss of electrical power. The losses of power were verified by the University Power Plant. The reactor was refueled and returned to operation.
Major maintenance for August included regeneration of Pool D. I. bed "R" and the replacement of offset "C" with a new style offset.
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SEPTEMBER 1983 The reactor operated continuously in September, with the following exceptions: nine shutdowns for flux trap sample changes; two shutdowns for maintenance; and two unscheduled shutdowns.
On September 26, the reactor scrammed during a start-up by a static charge buildup on the Channel 4 range switch. The switch was cycled and the reactor was restored to power.
On September 29, a manual rod run-in was initiated during a start-up i due to .the failure of Channel 4. A broken solder connection on a gain potentiometer lead was found and repaired on Channel 4 and the reactor was returned to operation.
Major maintenance items for September included repair of the breaker for the primary demineralizer pump; replacement of the regulator on nitrogen bank "B"; and low power runs fcr reactivity and rod worth calculations.
OCTOBER 1983 The reactor operated continuously in October, with the following excep-tions: six shutdowns for flux trap sample changes; three shutdowns for main-tenance; and two unscheduled shutdowns.
On October 3, the reactor scrammed due to loss of site electrical power.
,The cause was found to be a tripped feeder breaker in the distribution system for Research Park. Site power was restored in approximately three hours. The emergency generator operated during this time, but in a degraded state due to problems with the fuel rixture. The emergency generator gas tank was drained, flushed and refilled and the emergency generator was load tested satisfactori-ly. On November 1, a letter was sent to the Director of Nuclear Reactor Regu-lation explaining the circumstances and the corrective action taken.
. I-3
On October 6, the reactor was manually scrammed because of a mechanical failure of the inner airlock door. A trolley hinge support pin sheared, which allowed one side of the door to slip from its normal position. The door was repaired and the reactor returned to operation.
Major maintenance items for October included the installation of two new four inch reflector irradiation positions; the replacement of the MV/I module in the temperature monitoring circuit for the primary outlet leg; the replace-ment of valve S-2 control motor; the regeneration of pool DI bed "T"; and the repair of the inner airlcck door.
1 NOVEMBER 1983 The reactor operated continuously in November, with the following excep-tions: five shutdowns for flux trap sample changes; three shutdowns for main-tenance and two unscheduled shutdowns.
On November 15, the reactor scrammed on low pool flow when an operator accidentally bumped the on/off switch for pool pump 508-B. All safety systems functioned normally and the reactor returned to operation.
On November 29, pressurizer pressure sensor 938 initiated a reactor loop low pressure scram. Tne reactor was being shutdown by manual rod run-in at the time of the scram, in response to a reactor system low pressure alarm.
The pressure loss had been caused by a separation in the pressurizer pressure gauge line in room #114. The gauge line was repaired and the reactor returned to operation.
Major maintenance items for November included replacement of the drive motor for the pool temperature recorder; the regeneration of-pool DI bed "V";
the installation of two sleeves in beamport "F" centertube; and the perfor-mance of the regulating blade calibration for a nuclear engineering class.
I-4
DECEMBER 1983 The reactor operated continuously in December, with the following excep-tions: six shutdowns for flux trap sample changes; two shutdowns for mainte-nance and five unscheduled shutdowns.
On December 14, loss of site electrical power resulted in a reactor scram and isolation. Site power was restored in approximately five hours.
The emergency generator, after operating satisfactcrily for two hours, tripped off due to high temperature. The thermostat was found stuck closed and was replaced. The generator was then restarted and it assumed its electrical load until site power was restored. The reactor was secured and a shutdown check-sheet had been completed prior to the emergency generator trip.
On December 15, the day of its weekly automatic exercise, the emergency generator was found in a tripped condition, which would not have allowed it to operate automatically. The cause was felt to be a mispositioned electrical connection on the high temperature trip sensor. On January 13, 1984, a letter was sent to the Director of Nuclear Reactor Regulation explaining the circum-stances and corrective action taken.
On December 17, a high power rod run-in was initiated by electrical feedback through Channel 4, which was received while electronics technicians were investigating a problem with Channel 2 and 3 IRM chart drive. Full power was recovered in five minutes.
On December 19, the reactor scrammed with pool loop low flow annunciated.
No actual decrease in pool ficw was observed on any instrumentation. Whether the green or yellow leg of the pool loop low flow scram circuit had caused the scram could not be determined, so the " white rat" electronic surveillance unit was installed to determine the scram source, if any subsequent scrams occurred.
I-5
.Later on December 19, a rod run-in occurred with no associated annunci-a tion. An electronics technician had turned off the IRM chart recorder at the same instant. Electrical feedback was believed to have caused the rod run-in.
On December 20, the reactor scrammed on pool loop low flow. The source of the scrani was verified by the " white rat" to be from the yellow leg and again no indication of actual flow decrease was observed on the instrumenta-tion. The yellow leg reactor / pool dual trip circuit module for pool loop "B" and primary loop "A" flow was replaced. The reactor was returned to normal operation af ter compliance testing of pool and primary flows.
Major maintenance items for December included replacement of the dual
- trip unit for pool loop "B" and primary loop "A" flow; the replacement of
.Channe' 2 and 3 recorder selector switch; the regeneration of pool DI bed "R";
the performance of reactivity worth of a shim blade; and the replacement of the. emergency generator thermostat.
JANUARY 1984 The reactor operated continuously in January; with the following excep-tions: four shutdowns for flux trap sample cnanges; two shutdowns for main-tenance and two unscheduled shutdowns.
On January 16, and again on January 22, a rod not in contact with magnet rod run-in occurred when an operator bumped the drive housing for a control rod.. These occurred during routine sample handling evolutions.
The major maintenance item for January was the replacement of the MV/I module in the temperature monitoring circuit for the pool outlet leg.
I-6
2 FEBRUARY 1984 The reactor operated continuously in February, with the following excep-tions: three shutdowns for flux trap sample changes; two shutdowns for main-tenance; two scheduled reductions in power and two unscheduled shutdowns.
On February 4, the reactor scrammed due to an electrical power dip which was verified by the Power Plant. The reactor was refueled and returned to normal operation.
On February 7, the drain collection tank pump failed to start when its high level alarm was received. Reactor power was lowered for about fifteen minutes while electronics technicians jumpered the pump controls so it could be operated in manual.
On February 25, cooling tower fan #2 drive shaf t failed'as a result of mechanical wear. The drive shaf t was replaced and the fan was put back in operation. During this evolutinn, fan #1 failed to operate in fast speed and reactor power was lowered to decrease the necessary cooling load. Fan #1 controller was repaired and the reactor returned to operation.
On February 27, a reactor scram and isolation occurred when high radia-tion from an iridium sample in a transfer cask tripped the area radiation monitor. The cask was believed to be empty and the scram occurred when. the lid was removed, with Health Physics monitoring, prior to lowering the cask in the pool. The procedure for loading casks has since been revised to require cask lid removal under water. ' The reactor was refueled before returning to normal operation.
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1 Major maintenance for February included replacement of cooling tower fan
- 2 motor and drive shaft; the repair of cooling tower fan #1 fast speed con-troller; the replac~ement of the stack monitor drive motor; the removal of cooling tower cell #3 from service for rebuilding; the regeneration of DI bed "T"; and the performance of low power runs for flux trap and control rod reactivity worths.
MARCH 1984 i The reactor operated continuously in March, with the following excep-tions: four shutdowns for flux trap sample changes; two shutdowns for main-tenance; and one unscheduled shutdown.
On March 15, an antisiphon system'high level rod run-in occurred twenty minutes after a normal reactor start-up. The antisiphon line was believed to not have been blown completely dry prior to start-up. The line was blown dry and the rod run-in cleared in about two minutes. Full power was recovered in eight minutes.
Major maintenance items for March included placing cooling tower cell
- 3 back in service; removing cooling tower cell #1 from service for rebuild-ing; regenerating DI bed "V" and performing lower power runs for flux trap ar.d control rod reactivity worths.
APRIL 1984 The reactor operated continuously in April, with the following excep-tions: three shutdowns for flux trap sample changes; two shutdowns for main-tenance; nine unscheduled shutdowns.
I-8
On April 10, the reactor scrammed with reactor loop low flow annunci-ated. No actual decrease in reactor flow was observed on any instrumentation.
The specific leg of the reactor loop low flow scram circuit which caused the scram could not be determined. The "whi te rat" electronic surveillance unit was installed to determine the scram source on any subsequent scram.
On April 11, the reactor scrammed with reactor loop low flow annunci-ated. Again, no actual decrease in reactor flow was observed. The " white rat" indicated the scram source as primary loop A in the yellow leg. The yellow leg reactor / pool flow trip unit was replaced and after performing ,
compliance testing on the new unit, the reactor returned to operation.
On April 20, a rnd not in contact with magnet occurred three separate times when control red "A" disengaged from its magnet during normal reactor s tart-up s. The cause was believed to be the anvil contacting the upper housing due to slight movement of the offset base. A special C-clamp (Modi- >
fication Package 84-5) was attached to the back of offset "A" to eliminate movement of the base plate. The reactor returned to normal operation.
On April 21, the reactor scrammed on low pool flow when an operat6r accidentally bumped the on/off switch for pool pump 508-8. All safety systems functioned normally and the reacter returned to operation. This switch had been bumped, causing a scram, in November 1983 and has since 'been changed to prevent further unscheduled shutdowns of this nature.
On April 27, a rod not in contact with magnet rod run-in occurred when rod "D" disengaged from its magnet during routine shimming. While pulling the rods in gang on the subsequent start-up, rod "D" again disengaged resulting in a rod run-in. The control rod upper housing was realigned and the reactor I-9
1 s.
returned to operation. The rod housing was suspected to have become mis-aligned the previous day during maintenance activities.
On April 29, the reactor scrammed due to an electrical power dip verified by the Power Plant. The reactor was refueled and returned to opera tion. ,
Major maintenance items for April included replacement of meter relays for PT 944 A/B and PT 943; replacement of the yellow leg flow trip module; replacement of the meter and relay module for PT 943; replacement of the IRM recorder drive motor; dumping of DI bed "R" and loading of DI bed "U";
removal from" service of cooling tower cell #2 for rebuilding; placing cell
- 1 back in service; placing a special C-clamp on the back of offset "A"; and i renewing the time delay relay in cooling tower fan #1 controller.
MAY 1984 The reactor operated continuously in May, with the following exceptions:
three shutdowns for maintenance; two shutdowns for flux trap sample changes; and five unscheduled shutdowns.
On May 10, control blade "D" disengaged fron, its magnet during a normal reactor start-up, resulting in a rod run-in. The magnet current was increased from 90 MA to 120 ftA and the reactor returned to operation.
On May 11, a manual rod run-in was initiated when both personnel airlock doors opened simultaneously. The sealing gasket for the outer airlock door pulled free from its seat during the out-of-sequence operation of the doors.
The circumstrances of this occurrence was reported in a letter to the Director of Nuclear Reactor Regulation dated June 8,1984. The gasket was reseated and the airlock doors were tested before the reactor returned to operation.
I-10 1
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On May 18, a Channel 5 high power rod run-in was caused by an electrical glitch while changing the Channel 5 gain potentiometer setting. Electronics technicians investigated the problem on the next maintenance day.
On May 28, control rod "D" disengaged from its magnet during routine shimming causing a rod run-in. The anvil was found to have debris on its surface. The anvil was cleaned and 'the reactor returned to operation.
On May 29, a rod run-in occurred with no associated annunciation. The rod run-in occurred at the same time the 60% regulating blade withdrawn annunciation reset. The cause of, the rod run-in was believed to be electrical feedback. The rod run-in was reset and full power recovered within twelve minutes.
(
' Major maintenance items for May included the changeout of offset "A";
the performance of reactor startups for reactor operator examinations and the performance of the annual containment building leak rate check (RTP-13).
The leak rate was calculated to be 8.4 SCFM, significantly less than the Technical Specification limit of 16.3 SCFil.
JUNE 1984 -
The reactor operated continuously in June, with the following excep-tions: three shutdowns for flux trap sample changes; three shutdowns for maintenance; and three unscheduled shutdowns.
On June 1, a rod not in contact with magnet occurred when control blade "D" disengaged from its magnet during routine shimming. On the subsequent startup, this blade again disengaged causing a rod run-in. A broken pin was found in the amphenol connector, that provides drive and magnet current to the I-11
i rod mechanism. The connector was repaired and the reactor returned to operation. This faulty connector pin is believed to have contributed to the shutdowns in April and May where rod "D" disengaged from its magnet.
On June 8, the reactor scrammed due to an electrical power dip that was verified by the Power Plant. The reactor was refueled and returned'to operation.
Major maintenance items for June . included removing the Nuclepore irradiator case from the thermal column for future repair; the regeneration of DI bed "V"; and the performance of low power runs for a Nuclear Engineer-ing experiment.
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, SECTIch II
, OPERATING, PROCEDURE CHANGES TO-
- g. 2 REVISED OCTOBER' 1981 MA!!UAL
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' As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the' Standdd Operating and Emergency Procedures (SOP).
. . /
,,- There have been 5 revisions (#13 through #17) made to the Revised z' -
October #1981 manual during the past year. The revisions are contained in i
. this section with the. part of each pagef that was revised marked on the right
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side of the pag'ej by'a bracket ('])., .
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REVISION hut 1BER 13 TO OCTOBER 1981 f1ANUAL Page Number Date Revised 50P/VIII-13 7/12/83 SOP /VIII-15 7/12/83 II-2
m -
each insertion up to and including 10 minutes. For irradi-ations longer than 10 minutes, a mark will be placed on the l' rabbit for each 10 minute period or fraction thereof. For
' example, if a rabbit is irradiated for 25 minutes, it will receive 3 marks. When a rabbit has received six marks, it
'will be discarded. Each rabbit must be examined for cracks or other signs of potential failure before it is used.
VIII.3.4 Sample Irradiation Procedures VIII.3.4.1 ihen an e ;erimenter has met the requirements of VIII.3.3 and is ready to run his experiment, he shall call the reactor control room giving his A. Name B. Laboratory room number C. Experiment file number and project number. ]
D. Length of time the sample will be in reflector and how ]
many samples will be irradiated. ]
VIIIJ3.4.2 When the blowers are on, the system will be op~erated by the fol-lowing procedure.
Note: The position of each control button (CB) and control light (CL)-for the operation of the system from laboratories 216-228, 227-218 respectively are given on Figure VIII-1.
A. For laboratories (216-228, 227-218) which have switching or control stations, the circuit selector (CB-1) must be positioned to the control station of the experimenter's laboratory, i.e. 216.
B. . Set the " Automatic-manual" control switch (CB-2) to the type of control desired.
C. If automatic control of the system is used, set the timer
.to desired irradiation time. Irradiation time as short as 2 seconds can be used; maximum time in automatic control modes is not to exceed 20 minutes. Irradiations in manual control in excess of 20 minutes must be approved by the Reactor Manager in writing.
SOP /VIII-13 Rev. 7/12/83 App'd (3
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Note: In rooms 216 and 218, insure that the desired timer (2 1 seconds or 20 minutes) is selected and set for length of irradi-ation-time desired.
D. Press the -" reset" button (CB-3). The system is now ready for use; the control light'(CL-1) for " system in use" should be on.
E. Press the " rabbit dispatch" switch (CB-4).
F. Insert the rabbit. The air stream will carry rabbit through the system to the reactor.
G. Check that- the rabbit trips the " rabbit in reactor" indicator light -(CL-4).
H. Notify the reactor control room that the rabbit is in the reactor.
I. If the control (CB-2) is set on " automatic", the rabbit will be automatically discharged to the " catcher" located in the fume hood of the laboratory used as the operating site of the control station of the pneumatic tube system. The rabbit arrival at the control station will be indicated by the lights at either CL-2 or CL-3 and CL-5.
J. If the control is set on " manual", the rabbit is inserted as in steps A, B, D, E, F, G and H. However, the experimenter must depress the " rabbit return" switch (CB-5) to bring the rabbit back to the control station.
Note: The emergency return switch (CB-6) is not to be used for manual operations; its use is described in Section VIII.3.5, Emergency Procedures, below. .
K. Notify the control room when the rabbit returns to the labora-tory hood, t L. Place " station selector" switch to "off" position. l M. Press the " reset" button (see note below).
N. Place " auto-manual" switch to "off" position. (If buzzer ;
sounds, go through reset procedure again. If it still sounds, notify control room.)
- 0. Call the control room and give the actual irradiation time for the sample and number of samples irradiated, if different ]
from estimate given prior to irradiation. ]
Rev. 7/12/83 App' It
l REVISION flVMBER 14 TO OCTOBER 1981 MANUAL Page ilumber Date Revised 50P/A-8a 8/11/83 SOP /A-8b 8/11/83 II-3
REACTOR ROUTINE PATROL Date:
1.
~
Time. of start of patrol.
- 2. Time 'and date all charts.
- 3. . Check ARMS trip settings.
- 4. Visual check of entire pool.
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- 5. Anti-siphon tank pressure. 36 psig 3 psi
- 6. : North iso door seal press. 18-28 psig
- 7. South iso door seal press. 18-28 psig
- 8. . ' 5th level backup doors. Open
- 9. 5th level detector. reading. 0-3.5 mr/hr
- 10. 5th level trip point set. 3.5 mr/hr
- 11. 16" iso viv-A air pressure. 45-55 psig
', 12. Emerg compress on standby. cgsg open,
- 14. Door 101 seal pressure. 18-28 psig
'5. BP Floor Conditions normal.
- 16. , Fuel Vault Locked
- 17. Inner airlock door seal press. 18-28 psig
- 18. Outer airlock. door seal press. 18-28 psig
- 19. T-300 level. > 2000 gal.
- 20. T-301 1evel.
< 6000 gal.
- 21. Labyrinth Sump Level < Alarm Pt.
- 22. RO Unit (Run daily: ) UN (Run on 0700 routine for > 4 hrs.)
Power ON- (to T-300 or drain) 23... R0 Unit Temp 24-28*C/ standby
.,' 24. R0 Unit Pressure 190-200 psig/ standby 25 *-- EG Rm. - @a LL. did 3un. niius.) Inermostat > 50*F (EG OP switch to Auto r Temp > 40*F (Gas > sight glass )
- 26. T-300, 301 Room Thermostat > 55 Thermostat > 40;FF
'On the -first routine patrol of the day or the first patrol after a startup, drain all water from the anti-siphon system. If draining causes the pressure to drop significantly, return
- to the middle of the band (36 psig) and record the pressure here. If a condition is normal, enter an "N" or a check "/" in the applicable box. If the condition or reading is abnormal, enter 'AN" for the condition and circle it. Explain all abnormal readings or conditions in the remarks.
REMARKS: ,
Rsv. 8/llic3 App' h 50P/A-8a
- 27. Rm. .114 Particulate filter AP -
< 2.5" H 20 -
- 28. External Doors All locked except east when set on duty. ,
- 29. CT basin water level. j5-10" p 30. Acid day tank level. Visible ,
- 32. P-pump (s) running. ,,
- 33. Pump strainer AP. 0-7.0 psi..
34.. Discharge pressure. ,
- 35. -Pump strainer AP. 0-7.0 psi -
)
- 36. Discharge pressure.
1
- 37. Tunnel sump pumps. 0perable
- 38. WT booster fan. Running
- 39. Acid control and pH. F-low 400-800 cc/ min pH 7.2-7.7
- 40. Biowdown control /cond. g5g0 / min
- 41. Fission Product Monitor Flow 95-105 cc/ min
- 43. Pressurizer N2 supply press.90-100 psig
- 44. Check Rm. 114 from door.
- 45. Deltech oil filter " red level" < 757. dark red and blowdown. -
1
- 46. Seal trench. N % mp on days.
- 47. . Full N2 bottles. Total > 3 i
- 48. Bank A bottle press. > 250 psig )
- 49. Bank B bottle press. > 250 psig i
[- 1
- 50. Bank on service.. A or B l
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- 51. N header pressure. 135-145 psi 2
- 52. Waste tank #3 level, i
- 53. Waste tank #2 level.
54.: Waste tank #1 level. )
- 56. T' Completion of Patrol.
- 57. Operator initials.
REMARK 5: , . j Rev. 8/11/83 App uh SOP /A,8
REVISI0tl HL11BER 15 TO OCTOBER 1981 ttAllVAL l
I Page Number Date Revised SOP /VII-45 9/19/83 S0P/A-7a 9/19/83 SOP /A-11a 9/19/83 II-4
T L
L sludge is dumped via a 3" drain line at the north end of WT3 or ]
the south end of WT1 into barrels. This sludge is dried and ]
m removed as dry active waste.
B. Cuno Filters ,
The waste water will normally be pumped through the two Cuno filters. When the AP is high across them, they are replaced with new filters, and the old ones are disposed of as dry active waste. See Section VII.8.11.
C. Chemical Precipitant Treatment Radioactive particulates will attach themselves to carriers which can then be readily filtered out of the WT water. Without these carriers, even the most efficient filters could not remove this radioactive particulate. After filtering, the filters are shipped as dry radioactive waste. See Section VII.8.12.
VII.8.3 Oumping Criteria A. The liquid waste is collected and held until an analysis is made to determine that the specific activity of all radioactive iso-topes in the waste is less than the limit specified in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20) for dump-ing liquid waste to the sanitary sewer. In addition to the dumping limit on each isotope, 10 CFR 20 also limits the total activity which the University can dump to the sanitary sewer to I curie per year for carbon-14, 5 curies per year for H-3 (tritium) and 1 curie per year of other radioactive material, excluding C-14 and H-3. MURR is allocated 80% of. the Univer-
]
sity's limit, i.e. 800 millicurie per year for carbon-14, 4 ]
curies per year for H-3 (tritium) and 800 millicuries per year ]
of other radioactive material. This latter limit and a general ]
desire to minimize the activity dumped to our environment, dic-tates that the waste be retained as long as possible to permit the activity to decay off prior to discharge. If the 10 CFR 20 limits are not exceedad and .the total activity of radionuclides does not exceed 10 mci of tritium or 2 mci of other nuclides, ]
the Shift Supervisor may authorize the water to be pumped to the sanitary sewer. Any tank containing water with an activity greater than 2 mci of other nuclides will be discharged only ]
with the approval of the Reactor Manager.
Rev. - 9/19/83 App'd C SOP /VII-45
Sheet No: Date:
PNEUMATIC TUBE IRRADIATIONS Run Glock Time Total Project Room Irraajation No. In Out Name No. Runs No. No. Mi n . Sec. File No.
1 2
3
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5
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- - 7 8
1 9 ;
10
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! 12 13 14 15 16 17
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18 19 l
, 20 21
- 22 23
. 24 l 25 26 3 27 28 i 29 i
30 31' 32
- 33 i
34 i Rev. 9/19/83 App'd - , 50P/A-7a' V'
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Y RETURN ORfGINAL TO HEALTH PHYSICS OFFfCE No.
j l
WASTE TANK SAMPLE REPORT .
l TANK NO. TANK LEVEL (Liters)
Completed adding water to this tank. TIME DATE SAMPLER TIME DATE
- 1. Analysis Results Nuclide Half Life Physical Form Concentration MPC Activity
( uCi /ml I ( uCi )
- a. H_3 12.3Y b.
I l
pH TOTAL CONCENTRATION (b)
Analysis by TIME DATE Concentration (uci /m) Total Volume (liters) Activity (mci )
x =
(a) x =
(b)
- 2. Approvals Required for:
Any Discharge ......................
Shif t Supervisor Discharge of > 10 mci of H 3 , > 2 mci of other activity, or ]
to Secondary System .................. ]
Reactor Manager Discharge Limit Approved . . . . . . . . . . . . . . . . .
Health Enysics
- 3. Action Taken Date Discharged Time Discharged' Volume Discharged (liters)
Tank Discharged to (check one) Sanitary Sewer Secondary System Not Discharged REMARKS Rev. 9/19/83 Appojdhs,i SOP /A-11a f/
I I
l j
i REVISI0fl NUMBER 16 TO OCTOBER 1981 f1AtlUAL Page ilumber Date Revised
. EP-I-3 12/30/83 l
l II-5
. EP-I.O.2 IMPORTANT TELEPHONE NUMBERS O f fice Home Director, R. M. Brugger ,
882-4211, Ext. 230 445-6580 ]
Associate Director, D., M. Alger 882-4211, Ext. 229 445-4775 ]
Reactor Manager, J. C. McKibben 882-4211, Ext. 204 442-6728 Reactor Operations Engineer, W. A. Meyer, Jr. 882-4211, Ext. 203 474-7368 Reactor Shift Supervisor, N. Tritschler 882-4211, Ext. 214 474-6214 Reactor Shif t Supervisor, B. Bezenek 882-4211, Ext. 214 445-5680 Reactor Shif t Supervisor, C. Anderson 882-4211, Ext. 214 696-5506 Reactor Shif t Supervisor, Y. Jones 882-4211, Ext. 214 445-2543 ]
- k. Health Physics Manager, MURR, 0. Olson 882-4211, Ext. 227 874-8167 Health Physics Technician, A. Deralius 882-4211, Ext. 226 449-1655 ]
{ Health Physics Technician, R. Stevens 882-4211, Ext. 225 442-2539 ]
University Police / Watchman's Office, UMC 882-7201 Medical Center Health Physicist, P. Lee , 882-7221 445-5275 2 Research Park Dev. Bldg.
Radiation Safety Officer, (Rica, J. Tolan 882-3721 445-7787 l
413 Clark Hall Physical Plant Emergency -
882-8211 (Day)
Physical Plant Emergency 882-3333 (Night) , ]
Univ. of Mo. Hosp. & Clinics Emergency Center 882-8091 ]
Univ. of Mo. Hosp. & Clinics Ambulance Serv. 911 (Will be dispatched by ]
Ci ty of Columbia. )
Boone Hospital Center 875-4545 ]
Boone Hospital Center, Admissions 875-3237 ]
Boone Hospital Center, Emergency Room 875-3501 ]
Boone Hospital Center, Ambulance Service 449-0937 ]
Missouri State Highway Patrol, Jefferson City 314-751-3313 FBI, Jefferson City 314-636-8814 NOTE: For any emergency involving the City of Columbia, dial 911.
) Rev. 12/30/83 App'd a C ,
EP-I-3 V'
REVISION NUf1BER 17 TO OCTGGEP, 1981 11ANUAL
.m Page Number Date Revised SOP /A-la 1/24/84 l '. SOP /A-lb 1/24/84 I
I II-6
, , .c REACTOR STARTUP CHECKSHEET DATE:
FULL POWEL OPERATION TIME (Started)
(or Low Power Forced Circulation) dVILDING AND MECHANICAL EQUIPMENT CHECKLIST
- 1. Run emergency generator for 30 minutes and check the governor oil level.
(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or af ter each maintenance day.)
- 2. a. Check operation of fan failure buzzer and warning light. Shif t 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 />.)
- b. 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.
- a. P501A and P501B coolant water valves open,
- b. Si and S2 hydraulic pumps on (oil level normal).
_ c~ Pump controllers unlocked to start-(as required).
- d. Insure N2 backup system on per SOP. .
- e. CJen air valve for valve operating header (V0P 31). '
- f. N2 backup valve open.
- g. Check valves 599A and 5998 open.
- h. Pipe trench free of water (af ter maintenance day, check the four pipe annulus drain valves for water leakage).
- 1. Add DI water to beamport and pool overflow loop-seals.
~~
- j. Vent the 6000 gallon pool hold up tank.
- 4. Visual check of CT equipment completed.
- a. Oil level in CT fans normal (af ter maintenance day).
- 5. Beamport Floor
- a. Beamport radiation shielding (as required).
- b. Unused beamports checked flooded (af ter maintenance day),
- c. Seal trench low level alarm tested (af ter maintenance day).
- 6. Emergency air compressor (load test for 30 minutes af ter maintenance day).
- 7. Reactor Pool
- a. Reflector experimental loadings verified and secured for start-up.
- b. Flux trap experimental loading verified and secured for start-up, or strainer in place.
- c. Check power on and reset, as necessary, silicon integrator, totalizer setting, silicon rotator and alarm system.
REACTOR CONTROL SYSTEM CHECKLIST
- 1. All chart drives on; charts timed and dated. IRM recorder to slow.
- 2. Fan failure warning system cleared.
- 3. Annunciator board energized; horn off. '
- 4. Television receiver on.
- 5. Primary / pool drain collection system in service per 50P.
- 6. Secondary system on line per SOP (as needed).
- 7. Primary system on line pe'r 50P.
- a. Primary cleanup system on line.
8 Pool system on line per SOP.
- a. Pool cleanup system on line,
- b. Pool skimmer system vented.
- c. Pool reflector AP trips set per 50P.
- 9. Valves 51 and 52 cycled in manual mode and positioned as required.
- 10. Nuclear Instrumentation check completed per SOP.
- a. The following trip values were obtained during the check:
IRM-2, run-in seconds Scram seconds IRM-3, run-in seconds Scram seconds .
WRM-4, run-in % Scram %
PRM-5, run-in % Scram :
PRM-6, run-in % Scram i
- 11. Channel 4, 5, and 6 pots returned to las,t heat balance post tion.
- 12. SRM-1 detector response checked and set to indicate > 1 cps.
Rev. 1/24/84 App'd
/
, d 50P/A-11
EACTOE STA , TUP CHECKSHEET, FULL POWER OPERATION (Cont'd)
- 13. Check of process radiation monitors (front panel checks). (
- a. Fission product monitor,
- b. Secondary coolant monitor.
NOTE: Items 14 through 35 are to be completed in sequence immediately prior to pulling rods for a reactor startup.
14 Annunciator tested.
- 15. Annunciator alarm cleared or noted.
- 16. Power selector switch 158 in position required.
- 17. 3. Bypass switches 2540 and 2541 in position required.
- b. All keys removed from bypass switches.
- 18. Master switch 151 in "on" position.
, 19 . Magnet current switch on, check " Reactor On" lights. _
- 20. Reactor isolation, facility evacuation and ARMS checks (af ter maintenance day).
These items are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip,
- a. Reactor isolation switch (leave valves and doors closed) (af ter maint. day).
- b. Facility evacuation switch (check outer containment horns) (af ter maint. day)
- c. ARMS trip setpoints checked and tripped, check buzzer operational locally for all channels and remotely for channels 1 through 4 and 9.
Channel 1 - Beam Room South Wall -
Channel 2 - Beam Room West Wall Channel 3 - Beam Room North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipment Room 114 Channel 7 - Building Exhaust Air Plenum (af ter maintenance day).
Channel 8 - Reactor Bridge (switch in " Normal") (af ter maintenance day).
Channel 9 - Reactor Bridge backup (switch in " upscale") (af ter maint day).
- d. Check HV readings: volts.
- e. Check 150V reading: vol ts.
- f. Selector switch on ARMS in position 5.
- g. Trip backup monitor with attached source (af ter maintenance day).
- h. Reactor isolation horns switch in " Isolation Horns On" position. Yalves and doors open,
- i. All ARMS trips set per 50P.
- j. Check ventilation fans, containment and backup' doors.
- 21. Operate reg blade from full-out to full-in and set at 10" + .05".
- a. Check rod run-in function at 10% withdrawn and annunciator at rod bottomed.
- 22. Raise blade A to 2" and manually scram.
- 23. Raise blade B to 2" and trip manual rod run-in.
- 24. Raise blade C to 2" and scram by WRM trip.
- 26. Annunciator board energized; horn on.
- 27. Jumper and tag log cleared or updated.
- 28. IRM recorder in fast speed.
- 29. Check magnet current for 90 ma on each magnet.
- 30. Cycle WRM range switch.
- 31. Predicted critical blade position ( inches).
- 32. Pre-startup process data taken.
- 33. Visually check room 114 and D.I. area af ter all systems are in operation.
- a. Check oil reservoir for pump P501A, P501B, and P533 for adequate supply.
Add if necessary.
- 34. Routine patrol completed.
- 35. Reactor ready for startup.
Time (Completed)
Senior Reactor Operator R v. 1/24/84 App'd b '
% SOP /A-lb
, / '
/
SECTION III 1984 REVISI0flS TO THE HAZARDS SUfttfARY There were no revisions to the Hazards Summary between July 1,1983 and June 30, 1984 t
A U*
D
SECTION IV PLANT AND SYSTEM MODIFICATIONS i
NOVEMBER 1983 Modification 83-3: This modification was designed to expand the irradi-ation spaces in the bulk pool (adjacent to the reflector tank). This modiff-cation provides two spaces for the irradiation of 4" diameter samples. Each irradiation space has its own self powered neutron detector.
The ' irradiation element is constructed of aluminum canned reactor grade graphite and is similar in design to other irradiation elements presently in use. The. element is consistent with existing irradiation facilities and does not interfere'with other components or operation of the reactor.
. FEBRUARY 1984 Modification 84-1: This modification installed an antomatically oper-ated isolation valve in the 4" diameter secondary sump makeup water supply line. The valve is operated by a pneumatic actuator which allows the valve to close upon loss of site electrical power or when all three secondary pumps are secured. This modification was needed to prevent secondary sump overflow, particularly in the event of loss of site electrical power, when the cooling tower basement sump pump becomes inoperable and the cooling tower basement floods.
APRIL 1984 Modification 84-5: This modification was installed on offset mechanisms "A" and "C", to attach each mechanism to its reflector tank base pedestal.
There were needed to more securely hold the offset mechanisms in place when IV-1
their normal method of hold-down, stainless steel 7/8" -9 bolts threaded into stainless steel guide sockets, galled when attempting to remove offsets "A" and "C", during maintenance activities, April 19, 1984.
This modification installed a "C" clamp with tightening stainless steel bolts to span across tne reflector tank pedestal base and the hold-down block at the rear of the offset mechanism. A "C" clamp will be used until tooling and procedures are developed for a permanent repair of the hold-down mechanism.
L IV-2
SECTION V NEW TESTS AND EXPERIf1ENTS 4
New experimental programs during the period of 1 July 1983 through 30 June 1984 are as follows:
RUR150 Experimenter: Sue Langhorst/C. Park
Description:
An addendum was added to the RUR to include neutron activation analysis of water samples for small amounts of thorium.
RUR210 Experimenter: Gary Ehrhardt
Description:
An addendum was added to the RUR to include irradiation of small quantities of potassium iridic chloride.
RUR265 Experimenter: Mark Prelas
Description:
The experiment is to measure vacuum ultra violet fluorescence production efficiencies. The fluorescence is generated from neutron absorp' tion in the Boron-10 coating of the experiment tube inserted in beamport F.
V-1
. _ _ . _ . . . _ . . _ _ _ _ _ . _ , _ . _ . ._- _ _ _ _ . - - . _ ~ . , . _ - .
SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1983 through 30 June 1984
- 1. SNM Receipts: A total of 26 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia. These had been fabricated by Atomics International, Canoga Park, California, and shipped to B & W after December, 1982. B & W is holding 17 elements, serial numbers M0132 through M0149 except M0139 which was not made. Shipment of these to MURR will begin in late 1984.
Grams Grams Shipper Elements U U-235 8&W M058, M0102, M0103, M0104, M0105, M0106, 21,554 20,074 M0107, M0108, M0109, M0111, M0112, M0113, M0114, M0115, M0116, M0117, M0122, M0123, M0124, M0125, M0126, M0127, M0128, M0129, M0130, M0131
- 2. SNM Shipments: A total of 24 spent fuel elements were shipped to Exxon Nuclear Company, Inc., Idaho Falls, Idaho, for reprocessing.
Grams Grams Shipper Elements U U-235 MURR M041, M055, M056, M057, M059. M060, 16,183 14,122 M061, M062, M064, M066, M067, M068, M069, M071, M072,'M074, M078, M080, M081, M083, M084, M085, M087, M089
- 3. Inspections: A routine safeguards inspection was conducted by the Nuclear Regulatory Commission (NRC), Region III office, on 13-15 July 1983. MURR Special Nuclear Material Control Procedures were reviewed and found adequate to enable MURR to comply with 10CFR70.51(c) requirements -(accounting proce-dures for SNM in possession). Uranium burnup calculations were found in agreement with HRC 742 Material Balance Reports. Shipping and receiving procedures and records were found adequate and NRC 741 Nuclear Material
\
VI-1
t Transaction Reports were found adequately documented and properly filed with NRC. Internal fuel transfers and storage records were reviewed. Inventory of fuel and non-fuel material was physically identified and no discrepancies
'in inventory records were noted. By letter from NRC, Region III, dated 29 July 1983, no items of noncompliance with NRC requirements were identi-fied during the course of this inspection.
- 4. SNM Inventory: As of 30 June 1984, MURR was financially responsible for the following DOE owned amounts:
s Total U = 47,112 grams >
Total U-235 = 42,124 grams Included in these totals are 36 grams of U and 34 grams of U-235 non-fuel, DOE owned. In addition to these totals, MURR owns 134 grams of U and 54 grams of U-235. All of this material is physically located at the MURR.
1 I
VI-2
Fuel elements on hand have accumulated the following burnup as of 30 June 1984:
L Fuel Element Accumulated Fuel Element Accumulated Fuel Element Accumulated Humber Megawatt Days Number fiegawatt Days Number Megawatt Days M058 27.39 M0103 27.39 M0126 89.96 f1070 119.84 M0104 67.59 M0127 89.96 M073 142.73 M0105 47.41 M0128 66.64 f1075 143.81 M0106 49.01 M0129 89.74 M076 135.00 M0107 47.41 M0130 66.64 M077 129.94 M0108 49.01 M0131 89.74 M079 143. 8' M0109 23.91 f10150 124.49 M082 145.72 M0111 23.91 M0151 144.51 M088 106.39 M0112 0 M0152 124.49 M090 145.76 M0113 0 M0153 144.51 f1091 148.48 M0114 0 M0154 119.82 M092 145.76 M0115 0 M0155 137.89 M093 148.48 M0116 0 M0156 128.84 11094 147.60 M0117 0 M0157 137.89 M095 143.74 M0118 144.99 M0158 144.60 M096 147.60 M0119 144.83 110159 144.60
'l M097 143.74 M0120 144.99 M0160 95.09 M098 145.96 M0121 144.83 M0161 97.96 M099 143.82 M0122 57.42 M0162 95.09 M0100 145.96 M0123 77.18 M0164 97.96 M0101 143.82 M0124 74.38 M0165 106.39 M0102 67.59 M0125 60.22 l Average Burnup = 98.98 MWD VI-3
r 1 SECTI0tl VII REACTOR PHYSICS ACTIVITIES 1 July 1983 through 30 June 1984
- 1. Fuel Utilization: During this period, the following elements reached their licensed burnup and were retired.
Serial Number Core Designation Date Last Used NWDs M091 AP-46 11-14-83 148.48 M093 AP-46 11-14-83 148.48
- M090 AP-50 12-14-83 145.76
, MG92 AP-50 12-14-83 145.76 M073 AP-52 12-20-83 142.73 M075 AP-52 12-20-83 143.81 M095 AP-52 12-20-83 143.74 M097 AP-52 12-20-83 143.74 M094 A-5 2-02-84 147.60 M096 A-5 2-02-84 147.60 M099 A-10 2-27-84 143.82 M0101 A-10 2-27-84 143.82 M0151 A-15 3-29-84 144.51 M0153 A-15 3-29-84 144.51 M0118 A-16 4-05-84 144.99 M0120 A-16 4-05-84 144.99 M079 A-23 5-17-84 143.08 M082 A-23 5-17-84 145.72 M098 A-23 5-17-84 145.96 M0100 A-2? 5-17-84 145.96 M0119 A-24 5-24-84 144.83 M0121 A-24 5-24-84 144.83 M0158 A-24 5-24-84 144.60 M0159 A-24 5-24-84 144.60 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel elements of which only the initial critical fuel element serial numbers are listed in the following table. To increase operating efficiency, fuel ele-ments are 'used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.
VII-1
m ,
l 1
l 1
Fabrication Serial Cors Load Initial Core No. No. Designation Operatino Date 39 f10160 AP-26 7-18-83 39 M0162 AP-26 7-18-83 39 f10161 AP-29 8-07-83 40 M0164 AP-29 8-07-83 35 M0123 AP-37 9-26-83 35 f10125 AP-37 9-26-83 35 M0122 AP-38 9-29-83 35 M0124 AP-38 9-29-83 35 M0126 AP-46 11-07-83 35 M0127 AP-46 11-07-83 35 M0128 AP-50 12-01-83 35 M,129 AP-50 12-01-83
. 36 M0130 AP-50 12-01-83 36 M0131 AP-50 12-01-83 32 M0102 A-3 1-16-84 32 M0104 A-3 1-16-84 33 F0105 A-9 2-16-84 33 .'10107 .\-9 2-16-84 33 M0106 A-17 4-05-84 33 M0108 A-17 4-05-84 27 M058 A-18 4-12-84 32 M0103 A-18 4-12-84 32 M098 A-23 5-10-84 33 M0111 A-23 5-10-84
- 2. Fuel Shipping: Twenty-four spent fuel elements were shipped from MURR to Exxon Nuclear Company, Idaho Falls, Idaho. The identification numbers of these elements are:
M041 M061 l1069 MO81 M055 M062 M071 M083 M056 M064 M072 M084 M057 M066 M074 f1085 M059 M067 M078 M087 M060 M068 M080 M089
- 3. Fuel Procurement: Babcock and Wihox, Lynchburg, Virginia is MURR's current fuel assembly fabricator. 1his work is contracted with the U. S. Department of Energy and administered by E G & G Idaho, Idaho Falls, Idaho. EG&G
- notified us 13 June 1984 that B & W will be rolling 12 MURR fuel assemblies by October,1984 and plans to roll 36 assemblies in Fiscal Year 1985.
VII-2
- 4. Licensing Activities: A revised physical security plan (10CFR70.67) was approved by the NRC on 12 August 1983. This is Amendment 15, the latest amendment to our Facility License No. R-103 (Docket No. 50-186). A reactor emergency plan was approved by the NRC on 27 June 1984. A request for an increase in Special Nuclear Material Inventory under our Facility License submitted in December,1982 is pending. A revision to Technical Specifica-tions 4.4.di requiring two operating parallel pool pumps submitted in February,1982 is pending.
- 5. Reactor Characteristic Measurements: Sixty-four refueling evolutions were completed. Aa excess reactivity verification was performed for each refuel-ing and the average excess reactivity was 3.24%. MURR Technical Specifica-ation 3.1(f) requires that the excess reactivity be less than 9.87,.
Reactivity' measurements were performed for 11 evolutions to verify reactivity parameters' for the flux trap. Shim blade calibrations were per-formed at selected rod heights in support of reactivity measurements.
A physical inspection of the following fuel elements was performed to verify the operational parameters.
M096 form Core A-32 during March 1984 M0120 from Core A-35 during March 1984 All measurements were within operational requirements.
\
\
VII-3
SECTION VIII SUf1 MARY OF RADI0 ACTIVE EFFLUEllTS RELEASED TO THE ENVIRONMENT Sanitary Sewer Effluent From 1 July 1983 through 30 June 1984 Descending Order of Activity Released !
Nuclide Amount (C1) Nuclide Amount (Ci) Nuclide Amount (CT)
S35 5.51E-01 TA183 4.39E-04 TC99M 4.23E-05 H3 1.06E-01 SM153 4.34E-04 HG203 4.09E-05 C060 9.95E-02 CS137 3.73E-04 AU198 4.00E-05 ZN65 8.05E-02 CE144 3.42E-04 AS76 3.40E-05 l l
CR51 8.41E-03 IR192 3.15E-04 RE188 3.33E-05 MN54 5.80E-03 CS134 2.88E-04 SN113 2.94E-05 TA182 5.25E-D3 MN56 2.45E-04 PA233 2.26E-05 SC46 4.76E-03 C057 2.33E-04 K42 2.26E-05 NA24 2.66E-03 SE75 1.98E-04 TE123M 2.04E-05 58124 1.88E-03 NB95 1.56E-04 1133 1.79E-05 AG110M 1.72E-03 ZR95 1.07E-04 GA72 1.50E-05 AS77 1.27E-03 BA140 1.05E-04 W187 9.77E-06 CU64 1.16E-03 CD109 8.96E-05 BR82 8.12E-06 C058 9.90E-04 C0115 8.82E-05 1132 7.24E-06 58125 6.08E-04 SB122 7.16E-05 HF181 5.86E-06 LA140 6.04E-04 RB86 7.09E-05 1131 5.21E-06 FES9 5.83E-04 NA22 6.27E-05 EU152 5.12E-06 RE186 5.59E-04 ZN69M 4.60E-05 AU196 2.35E-06 TE125!1 5.08E-04 BA133 4.55E-05 VIII-1
,t Stack Effluent From 1 July 1983 through 30 June 1984 Descending ,0rder of. Activity Released i
Nuclidjt Amount (C1)
AR41 1.25E+03 H3 1.25E+01 l-U 1133 2.33E-03
, I135 1.795-03 1131 1.52E-03 1134 1.47E-03 AS77 6.49E-04 K40 S.47E-04 1132 4.21E-04 XE135M 4.12E-04 TA182 2.53E-04 CL38 2.20E-04 VIII-2
SECTION IX
SUMMARY
OF ENVIRONMENTAL SURVEYS !
Environmental samples are collected two times per year at nine locations and analyzed for radioactivity. These locations are shown in Figure 1. Soil and vegetation samples are taken at each location. Water samples are taken at four !
of the eight locations. Results of the samples are shown in the following tables.
Detection Limits Matrix Alpha Beta Gamma Tritium Water 0.2 pC1/1 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 pC1/g vegetation
- 1. Sampled during November 1983.
Determined Radioactivity Levels Vegetation Samples Sample Alpha pC1/g Beta pCf /g Gamma pCi/g Tritium pCf /g 1-V-24 < .2 12.6 < 0.04 < 9.1 2-V-24 < .2 16.2 < 0.04 < 9.1 3-V-24 <.2 15.1 < 0.04 < 9.1 4-V-24 <.2 14.6 < 0.04 < 9.1 5-V-24 < .2 15.6 < 0.04 < 9.1 6-V-24 <.2 10.2 < 0.04 < 9.1 7-V-24 < .2 16.1 < 0.04 < 9.1 10-V-24 < .2 27.8 < 0.04 < 9.1 IX-1
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. Figure i- tWRR Environmental Program SampTe Stations tt0TE: September 1983 City sewerage plants at stations 8 and 9 closed. All waste water now processed at Cf ty Waste Treatment Facility at station 10.
Determined Radioactivity Levels
-5o11 Samples Sample Alpha DCi/g Beta pCi/g Gamma pCi/g
, 1-S-24 0.5 10.0 < 0.04 2-S-24 0.5 7.1 < 0.04 3-S-24 0.3 6.3 < 0.04 4-S-24 0.6 9.1 < 0.04 5-S-24 0.4 8.2 < 0.04 6-S-24 0.3 6.5 < 0.04 7-S-24 0.4 10.2 < 0.04 Determined Radioactivity Levels Water Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g 4-W-24 < 0.2 10.1 < 9.1 6-W-24. < 0.2 5.2 < 9.1
- 2. Sampled during May 1984.
Determined Radioactivity Levels Vegetation Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g Tritium pCi/g 1-V-25 < .2 14.9 < 0.04 < 9.1 2-V-25 < .2 11.9 < 0.04 < 9.1 3-V-25 < .2 13.3 < 0.04 < 9.1 4-V-25 <.2 18.4 < 0.04 < 9.1 5-V-25 < .2 17.3 < 0.04 < 9.1 6-V-25 < .2 18.3 < 0.04 < 9.1 7-V-25 < .2 14.8 < 0.04 < 9.1 10-V-25 < .2 13.5 < 0.04 < 9.1 IX-3
Determined Radioactivity Levels
_5_ oil Samples Sample Alpha pCi/g Beta pCi/c Gamma pCi/g 1-S-25 0.3 9.4 < 0.04 2-S-25 0.3 10.7 < 0.04 3-S-25 < 0.2 9.7 < 0.04 4-S-25 0.3 8.7 < 0.04 5-S-25 0.5 9.5 < 0.04 6-S-25 0.4 5.5 < 0.04 7-S-25 0.5 9.7 < 0.04 10-S-25 0.4 10.3 < 0.04 Determined Radioactivity Levels Water Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g 3H (pCf/ml) 4-W-25 < 0.2 6.2 < 0.04 < 9.1 6-W-25 0.3 5.2 < 0.04 < 9.1 10-W-25 < 0.2 7.5 < 0.04 < 9.1 Radiation and Contamination Surveys The following table gives the number of surveys performed during FY 83-84.
Radiation Surface Contamination Air Samples 401 278 272 Twenty-nine (29) Radiation Work Permits were issued during the year.
Miscellaneous Items Effective October 1,1983, responsibility for routine knitoring of exhaust stack Ar-41 emission, Ar-41 in containment- building air, and analyzing person-nel urine for tritium was transferred E cm Reactor Chemistry to Reactor Health Physics.
IX-4 k... ..
i i
Four procedures in the 10MW Standard Operating Procedures, Volume 5, Health Physics, were updated.
It was decided to produce bdo sets of procedures for Health Physics controls. The 10MW Standard Operating Procedure, Volume 5, Health Physics, will contain material needed by personnel not in the Health Physics group. A new set of procedures called " Internal Procedures and Guides" (IP's) is being written. This set is to ,contain detailed procedures that Health Physics person-nel are to use which are not of interest to other personnel, e.g. calibration and use of swipe counters; changing filters on the stack monitor. This set contains six procedures at this time.
June 8,1984, nine 55 gallon drums of reactor water system filters and resins were shipped to the Richland, Washington disposal site.
During the year, Reactor Health Physics built a counting well with a HaI detector attached to a M.CA to analyze collected samples and radwaste.
During the year, three technicians were hired to replace previous staff members. All are experienced in Health Physics procedures.
Initiated a radwaste program which reduces the volume of waste generated at the work stations and uses engineered procedures to reduce the volume af ter waste is collected. Fif ty to sixty percent reduction of final waste volume is anticipated.
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IX-5
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SECTION X-
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS .
1 July 1983-through 30 June 1984
- 1. Largest. single exposure and average exposure-are expressed in millirem.
- 2. Minimal exposure is defined to be gamma < 10 mrem; beta, < 40 mrem; neutron < 20 mrem.
- 3. 'M. E. = Number of monthly units reported with minimal exposure.
- 4. A. M. E. = Number of m6nthly units reported with exposure above minimal.
- 5. A. E. = Average mrem reported for all units above minimal. i
- 6. H. E. = Highest mrem reported for a single unit for the month. I PERMANENT ISSUE FILM-BADGES Beta, Gamma, Neutron Wholebody Badges: (Six badges ari area monitors.)
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER. DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE l i ME 50 37 37 49 55 56 78 59 67 58 62 64 AME 50 61 65 48 42 48 49 56 68 60 54 65 l AE 67 80 52 76 79 81 92 95 109 99 136 97 i HE 290 350 260 330 430 510 720 700 1060 930 1200 990 Beta and Gamma Wholebody Badges: (Six badges are area _ monitors.)
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEt1BER JANUARY FEBRUARY MARCH APRIL MAY JUNE ;
1 ME 41 47 47 39 41 56 51 47 51 48 46 50 AME 3 7 4 3 3 2 5 8 8 7 8 7 ,
AE 27 43 23 57 20 45 38 20 34 46 45 36 HE 40 100 40 100 40 50 120 80 120 130 120 110 l TLD Finger Rings:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 35 30 34 32 35 35 41 32 37 31 38 40 AME 29 33 31 29 31 24 33 34 37 35 31 36 AE 695 220 247 257 235 297 309 285 308 483 365 406 HE 15080 1870 1720 -
1340 2590 1470 1660 1750 2210 4210 2260 3830 X-1 .
I 1
SPARE ISSUE FILM-BADGES Beta, Gamma, Neutron Wholebody Badges:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 24 21 21 24 27 17 10 34 45 41 36 41 AME 6- 4 18 8 7 2 3 10 1 6 9 7)
AE 43 32 22 46 27 165 140 72 260 58 54 40 HE 130 70 90 110- 60 230 200 170 260 190 150 140 Beta and Gamma Wholebody Badges:
1
! JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL HAY JUNE ME 18 17 29 24 16 14 19 31 27 32 31 30' AME O 2 1 1 2 0 2 0 7 0 2 1 AE O 45 10 10 10 .0 10 0 17 0 5 100 HE O 60 10 10 10 0 20 0 40 0 10 100 l
TLD Finger Rings:
I JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 14 12 16 15 16 15 17 17 17 18 14 18 AME 9 10 4 4 7 10 3 4 5 4 8 4 AE 209 386 58 190 274 213 187 123 192 145 126 63 ,
llE 390 1300 130 550 110 360 290 210 370 350 410 150 l DOSIMETERS JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 14 11 11 11 10 10 12 12 10 5 2 1 AME 28 30 30 27 27 27 26 29 36 41 44 44 '
AE 62 63 63 85 64 64 70 72 64 69 54 88 HE 235 195 195 215 485 485 365 260 288 247 240 240 l l
X-2 l
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i COMMENTS CN SUMt1ARY OF RADIATION EXPOSURES During July 1983, it was necessary to open an irradiated sample can with hand tools. A supervisor was chosen to perform the operation because higher than normal hand exposure was anticipated. The operation was monitored by a Senior Health Physics Technician. A TLD finger ring was worn on the tool hand, f 1 An exposure of 15080 mrem was received by the supervisor's hand. Total beta-gamma exposure for the supervisor for the month was 740 mrem.
During May 1984, an area monitor for the north beamport floor recorded gamma 139% higher than normal (1200 mrem compared to 865 mrem monthly average) because of work performed on beamport "D" during the month which temporarily f raised exposure levels in the area. No unusual personnel exposures occurred as a result of the work.
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N, Research Reactor Facility UNIVERSITY OF MISSOURI Research Park Columbia. Missouri 65211 Telephone (314) 882-4211 September 6, 1984 Director of Huclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Cecil 0. Thomas, Chief Standardization & Special Projects Branch Division of Licensing )
Reference:
Docket 50-186 University of i;issouri Research Reactor License R-103
Subject:
Annual Report as required by Technical Specification 6.1.h(4).
Dear Sir:
Enclosed are the additional twelve (12) copies of the reactor operations annual report for the University of Missouri Research Reactor as mentioned in my letter of August 24, 1984.
Sincerely, gA 4
/.
J. C. McKibben Reactor Manager JCMK:vs Enclosures (12) g,Oy
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COLUMBIA KANSAS CITY ROLLA ST. LOUIS OM an equal opportunity institution l[ l3-