ML20076C669
| ML20076C669 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 08/19/1983 |
| From: | Brugger R, Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308230129 | |
| Download: ML20076C669 (67) | |
Text
m JNIVERSITY OF MISSOURI a :
masa Annua f.
Report N_
1982-83 E
((f?.l.'.-l lh!.
f, RESEARCH REACTOR FACILITY
- l l
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY
~.
REACTOR OPERATIONS ANNUAL REPORT August 1983 Compiled by the Reactor Staff Submitted by J. C. McKibben Reactor Manager Revfjewed nd Approv
<AJT s [ a F.obertM.brugger Director V e
- TABLE OF CONTENTS Section Page Number I. REACTOR OPERATIONS
SUMMARY
...................... 1-1/11 II. OPERATING PROCEDURE CHANGES ..................... II-1/7 III. 1983 REVISIONS TO THE HAZARDS
SUMMARY
REPORT ........................................ III-1 only IV. PLANT AND SYSTEM MODIFICATIONS .................. IV-1/2 V. NEW TESTS AND EXPERIMENTS ....................... V-1 only VI. SPECIAL NUCLEAR MATERIAL ACTIVITIES ............. VI-1/2 VII. REACTOR PHYSICS ACTIVITIES ...................... VII-1/4 VIII.
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT . . . . . . . . . . . . . . . . . . . VIII-1/2 IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS ................ IX-1/5 1
X.
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS .................................. X-1/2 11
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SECTION I REACTOR OPERATIONS
SUMMARY
Fiscal Year 1982-1983 The following table and discussion summarize reactor operations in the period July 1,1982 to June 30, 1983.
Full Power Percent
- Date Full Power Hours Megawatt Days of Total Time of Schedule July 82 673.4 280.74 90.51 101.37 Aug. 82 678.8 283.06 91.24 102.19 Sep. 82 672.6 280.40 93.42 104.63 Oct. 82 691.0 288.23 92.88 104.02 Nov. 82 612.3 255.43 85.04 95.25 Dec. 82 693.2 288.20 93.17 104.35 Jan. 83 618.3 269.48 83.10 93.08 Feb. 83 590.1 245.12 87.81 98.35 Mar. 83 692.5 288.57 93.08 104.25 Apr. 83 656.1 273.49 91.12 102.06 May 83 695.1 289.58 93.43 104.64 June 83 647.0 269.89 89.86 100.64 Total for Year 7,920.4 3,312.19 90.39% of 101.24% 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 month or year.
I-1
JULY 1982 The reactor operated continuously in July, with the following exceptionsi ten shutdowns for flux trap sample changes; two shutdcwns for maintenance; and six unscheduled shutdowns.
On July 7, the reactor was scrammed hy shifting the WRM switch too far down scale during a power reduction. All systems were verified normal and the reactor returned to operation.
Two unscheduled shutdowns on July 13 were by manual scram to repair and then replace an airlock door gasket.
The third unscheduled shutdown on July 13 was caused by the failure of the local pump control switch for P-5018, which caused a reactor loop low flow scram when P-5018 stopped. The reactor was re-turned to operation after the pump control switch was replaced.
The reactor was shutdown on July 18 by a momentary dip in electrical power, verified by the UMC Power Plant.
On July 31, the reactor was shutdown by a loss of valve operating air pressure which resulted in V509 leaving its full open seat, scramming the reactor.
The main air compressor had shutdown due to high temperature. Cooling water was increased to the compressor, all systems were verified normal and the reactor returned to normal operation.
Major maintenance items in July included the regeneration of DI-200 beds "0"
and "P"; the repair and replacement of the outer airlock door gasket and repair of the wet fire main.
AUGUST 1982 The reactor operated continuously in August, with the following excep-tions:
ten shutdowns for flux trap sample changes; three shutdowns for main-tenance; and three unscheduled shutdowns.
1-2
On August 15 and 26, the reactor was shutdown by a rod not in contact with magnet Rod Run-In. These Rod Run-Ins were both caused by control blade "D" falling off during startup with the reactor not critical. The reactor was re-turned to operation after checking the rod "D" alignment.
On August 31, the reactor was again shutdown by a rod not in contact with magnet Rod Run-In. Rod "D" disengaged from its magnet during a shimming evalu-ation at 10MW. The reactor returned to operation after the upper housing of Rod "D" was realigned.
Major maintenance items in August included the dumping of DI bed "0", the loading of new DI bed "R"; replacement of P-501A with a spare pump; and the in-stallation of air sparge lines on the secondary side of the primary heat ex-changers.
SEPTEMBER 1982 The reactor operated continuously in September, with the following excep-tions: seven shutdowns for flux trap sample changes; two shutdowns for main-tenance; and seven unscheduled shutdowns.
On September 5, the reactor was scrammed by a spurious reactor loop low flow signal. The primary flow detectors were inspected and found to be normal.
The next three unscheduled shutdowns occurred during the subsequent restoration of reactor power. Blade "D" fell off its magnet during each of three startups.
The reactor was returned to operation, after alignment of the blade "D" drive housing and the performance of a blade pull and drop test on blade "D".
On September 13, while the reactor was operating at low power for Physics testing, the reactor scrammed due to a static charge buildup in the WRM range switch. The switch was wiped and a reactor startup was commenced. A second I-3
scram was caused by an operator trainee shifting the WRM range switch improper-ly. The trainee was instructed in proper switch operation and a third startup was commented. A third scram occurred, caused by a voltage dip due to an elec-trical storm. The reactor systems were checked and the reactor was returned to operation.
Major maintenance items in September included regeneration of DI bed "R" and the alignment of offset drive housing "D".
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OCTOBER 1982 The reactor operated continuously in October with the following exceptions:
nine shutdowns for flux trap sample changes; two shutdowns for maintenance and three unscheduled shutdowns.
The three unscheduled shutdowns on October 12 and 13 were caused by reactor loop low flow scrams. These scrams were caused by spurious electronic signals generated in the Primary and Pool Flow Scram Trip Unit. In each case, the reactor flow recorder showed no actual loss or reduction of flow.
After both the first and second scrams, the primary system was inspected and flow detectors were inspected and vented. After the third flow scram, the Primary Loop A and Pool Loop B Flow Scram Trip Unit was replaced by the elec-tronics technician. The scram trip points for F. T. 912A (Primary Flow A) and F. T. 912F (Pool Flow B) were then checked, and the reactor was returned to operation.
Major maintenance items for October included: the replacement of the Primary and Pool Flow Scram Trip Unit, installation of new offset #8 in the "B" position; the regeneration of DI bed "P" and the performance of two reactivity measurement startups.
1-4
l NOVEMBER 1982 The reactor operated continuously in November with the following excep-tions: six shutdowns for flux trap sample changes; four shutdowns for mainte-nance and eigFt unscheduled shutdowns.
The unscheduled shutdowns on November 9 was due to a loss of site electri-cal power, verified by the UMC power plant.
One unscheduled shutdown on November 16 was caused by turning the Channel 4 Range switch incorrectly and the other by an electrical glitch in the annunci-ator. The reactor was returned to operation after each of the shutdowns.
On November 18, the reactor was shutdown by Manual Rod Run In to inspect and repair the regulating blade clutch mechanism. The reactor was refueled and returned to operation.
On November 22, the reactor was shutdown by Manual Rod Run In because the jog /stop switch had failed for the charging pump. The switch failed in the run mode causing an increase in pres'surizer level. The reactor was returned to op-eration after the pump control switch was replaced.
On November 29, the reactor was scrammed while decreasing reactor power during a reactivity measurement when the Channel 4 Range switch was turned too far down scale.
Major maintenance items for November included: dumping pool bed "Q" on November 13; installing reflector elements K-2, X-3, and N-2 as per Modification Packages 82-1 and 82-4 on November 15; the loading and regeneration of new DI bed "S" on November 17, and one reactivity measurement startup. Three reactor operator licensing examination startups were conducted November 8.
1-5
DECEMBER 1982 The reactor operated continuously in December with the following excep-tions: sixteen shutdowns for flux trap sample changes; two shutdowns for main-tenance and three unscheduled shutdowns.
On December 11, the reactor was shutdown twice by spurious pool loop low flow scrams. The pool systems were inspected and the reactor returned to oper-ation. On the next Maintenance Day, December 13, the pool loop B low flow scram set point was found to have drifted high causing low flow scrams when no low flow condition existed. The scram set point was adjusted to within the desired compliance check limits and Compliance Check CP-7B was performed.
The unscheduled shutdown on December 20 was caused by a rod not in contact with magnet rod run in when blade "0" was bumped while handling a laser experi-ment in the reflector region.
Major maintenance items for December included the regeneration of DI bed "R" and the performance of reactivity measurements for the Reactor Services group.
JANUARY 1983 The reactor operated continuously in January with the following excep-tions: nine shutdowns for flux trap sample changes; four shutdowns for main-temance and ten unscheduled shutdowns.
On January 3, after maintenance day, two anti-siphon high level Rod Run-Ins occurred. The anti-siphon system was blown down after the first Rod Run-In but the second Rod Run-In occurred a short time later. The reactor was shut down and the anti-siphon system values were cycled to reseat the valves. The reactor was returned to operation after the valves reseated.
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On January 13, the reactor scrammed for an unknown reason. The reactor instrumentation and systems were inspected and found normal and the reactor returned to operation.
Following maintenance day on January 17 and 18, six unscheduled shutdowns occurred due to rod not in contact with magnet Rod-Run-Ins. After continued trouble shooting and fault isolation, the Rod Run-In Trip Actuator Amplifier was replaced and the reactor returned to operation.
On January 31, the reactor was shut down by a Pool Loop Low Flow Scram caused by a glitch from the Demineralizer Flow Chart Recorder. The pool flow recorder indicated no actual reduction of flow.
Major maintenance activities for January included the repair and replace-ment of the air sparge lines in waste tanks one and two; the overhaul of valves 543 A/B and installation of modified pins in the valve actuator linkages (Modification 83-1), and the dumping of DI bed "P".
FEBRUARY 1983 The reactor operated continuously in February with the following excep-tions: eight shutdowns for flux trap sample changes, three shutdowns for main-tenance and seven unscheduled shutdowns.
On February 1, while performing a startup, the reactor was shut down by a Pool Loop Low Flow scram. The scram was caused by an intermittent ground in a switch in the primary clean up flow recorder. The pool flow recorder indicated no actual reduction of flow. The reactor was returned to operation after the recorder switch mounting screws were tightened, removing the intermittent ground condition. This is believed to have also been the cause of the unscheduled shutdown on January 31, 1983.
I-7
The reactor had two rod not in contact with magnet Rod Run-Ins during February 3 startups on blades "C" and "B". After blade "C" dropped, its power supply was switched with the blade "B" power supply in an attempt to isolate the cause of dropping blade "C". Blade "B" fell off on the subscquent start-up. The power supplies for blades "C" and "B" were then returned to normal.
The power supply current meters for blade "C" and "D" were then switched in a further attempt to isolate the cause of the rod drops. Each time the entire power supply circuitry and connections were checked. The rod drops were being caused by an intermittent problem. The reactor was scrammed on the subsequent startup by a static charge on Channti #4 Range switch.
On February 6, a rod not in contact with magnet Rod Run-In occurred when blade "D" fell off during a startup. The magnet current meter for rod "D" was replaced and the reactor returned to operation. This current meter was the one that had been on rod "C". No further unexplained rod drops have occurred since the current meter was replaced.
After maintenance day on February 7, there was an unexplained reactor scram. The scram circuitry was inspected and no abnormalities were found. The white rat monitoring system was installed in the jumper boards and the reactor returned to operation. On February 8, a reflector High/ Low Differential Pres-sure Scram was received on the annunciator and the white rat. The electronics technicians replaced the meter and relay unit for PT-917 and the reactor re-turned to operation after a compliance check on PT-917.
Major maintenance activities for February included one spent fuel ship-ment; the replacement of blade "C" magnet current meter; the replacement of PT-917 meter and relay units; the replacement of the inner airlock door gasket and a change out of offset mechanism "D".
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MARCH 1983 The reactor operated continuously in March with the following exceptions:
nine shutdowns for flux trap sample changes; two shutdowns for maintenance; and two unscheduled shutdowns.
On March 21, a high power rod-run-in was received from Channel 5. The cause of the rod-run-in was vibration of a loose solder joint in the DC ampli-fier portion of the Channel 4 drawer. The loose DC amplifier lead caused Channel 4 indicated power to drop, which in turn caused the regulating blade to withdraw, resulting in an increase in power. The reactor was shutdown by manual scram, the lead was repaired and the reactor returned to operation.
On March 25, a rod-run-in was received for no apparent reason. All sys-tems were checked satisfactory and the reactor returned to operation.
Major maintenance activities included replacement of offset "D" with a new offset mechanism. This was done to replace an offset installed a week earlier, which had a problem with control blades falling off the magnet in the upper four inches of travel.
APRIL 1983 The reactor operated continuously in April with the following exceptions:
nine shutdowns for flux trap sample changes; four shutdowns for maintenance, and four unscheduled shutdowns.
On April 3, a loss of site power caused the reactor to scram. The power loss was due to a ground in an electrical substation adjacent to the reactor facility cooling tower. The reactor was refueled and returned to operation after electrical power was restored to the facility.
The reactor scrammed on April 6 by an electrical glitch from the Channel 4 Range switch. The reactor was being restored to power after a brief maintenance shutdown for electrically switching the source of site power.
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On April 11, after a maintenance shutdown, the reactor was scrammed by a Reactor Isolation. The isolation was initiated by the Area Radiation Bridge Monitor while handling a silicon sample. After evacuation of containment, the set point for the reactor bridge upscale meter was determined to have been set too low. The reactor returned to operation after setting the meter trip point properly. .
A momentary dip in electrical power caused by a thunderstorm initiated a scram on April 27. The reactor returned to operation after systems were in-spected.
Major maintenance in April included the repair of an in-pool leak in the primary vent system. A vent line was replaced from the pressure vessel to the in-pool heat exchange.
MAY 1983 The reactor operated continuously in May with the following exceptions:
ten shutdowns for flux trap sample changes and three shutdowns for naintenance.
There were no unscheduled shutdowns for the month.
Major maintenance activities in May included the completion of the annual containment leak test and the replacement of the pool system demineralizer bed.
The containment leak rate was 11.1 scfm, which is less than the Technical Speci-fication limit of 16.3 scfm.
JUNE 1983 The reactor operated continuously in June with the following exceptions:
ten shutdowns for flux trap sample changes; two shutdowns for maintenance and three unscheduled shutdowns.
On June 8, the rcactor was shutdown by a manual rod-run-in when the breakers supplying the secondary cooling pumps and fans tripped. The breaker 1-10
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i for cooling tower fan #2 was found to have shorted, causing a power surge that tripped the supply breakers for the secondary pumps and fans. The reactor re-turned to operation after the #2 fan breaker was racked out and the cooling tower switch gear was inspected and tested.
On June 18, the reactor was scrammed due to a loss of site power, verified by the UMC Power Plant.
On June 21, the reactor was scrammed during a reactor startup by a static charge buildup on the Channel #4 Range switch. The switch was wiped and the reactor returned to operation.
Major maintenance items for June included electronic ground isolation on June 6 and the replacement of cooling' tower fan #2 breaker on June 10.
1-11
SECTION II OPERATING PROCEDURE CHANGES TO REVISED OCTOBER 1981 MANUAL As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the Standard Operating and Emergency Procedures (S0P).
There have been six revisions (#7 through #12) made to the Revised October 1981 manual during the past year. The revisions are contained in this section with the part of each page that was revised marked on the right side of the page by a bracket (]).
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I REVISION NUMBER 7 TO REVISED OCTOBER 1981 MANUAL S0P/I-15 Revised 12/7/82 50P/I-16 Revised 12/7/82 S0P/I-17 Revised 12/7/82 SOP /I-18 Revised 12/7/82 SOP /VII-45 Revised 12/7/82 S0P/VII-53 Revised 12/7/82 S0P/A-la Revised 12/7/82 SOP /A-11 Revised 12/7/82 i
II-2
l Table IV Values of Trip Settings for Alarm, Run-In and Scram Conditions Scram Run-In Alarm Units
- 1. Short Period >8 >10 --
sec ]
- 2. Low Count Rate -- --
<1.0 cps
- 3. High Power (120 <115 --
% full power ]
- 4. RC Inlet Temp 150 -- 148 F ]
1
- 5. RC Outlet Temp 170 -- 165 *F ]
- 6. RC System Low Flow 1725 --
1800 gpm ]
5 MW Operation RC System Low flow 21725 --
1800 gpm ]
10 MW Operation
- 7. Heat Exchanger low 41675 -- -- gpm
- (DPS 928A/B)
- 8. Rx System Low Press 363 -- --
psig ]
Switch PS 944A/B 4
- 9. Core Low # , 5 MW 1650 -- --
gpm-Core Low # , 10 MW '*3300 -- --
gpm
- 10. Low Pressurizer Level 13-14 below C --
10-13 below C inch ]
- 11. High Pressurizer Water -- --
12-15 above C inch Level ZFor 10 MW operation, Alarm and Scram received from either loop 3 Pressurizer pressure with normal system flow 4# Corresponding to this flow value Rev. 12/7/82 f.< N App'dg_G SOP /I-15 l
TABLE IV (continued)
Units Scram Run-In Alarm
- 12. Low Pressurizer Press 63 -- 65 psig ]
l psig ]
- 13. Ili Pressurizer Press 78 -- 75
- 14. Pool Low flow, 5 MW 490 -- 530 gpm )
Pool Low Flow, 10 MW 490 -- 530 gpm ]
- 15. Pool Low Ili Te:np -- -- 115 *F
- 16. Low Pri Demin Flow -- -- <42.5 gpm
- 17. Low Pool Demin Flow -- -- <42.5 gpm
- 18. Bldg Air Plenum lli 1.0 -- --
mr/hr Activity
- 19. Reactor Bridge 50i.0 -- --
mr/hr
- 20. RC 111 Conductivity -- -- 2.0 unhos
- 21. PC lii Conductivity -- -- 2.0 unhos
-- -- psi ]
- 24. Low (12 System Press -- -- 115 psig
- 25. Low Seal Trench Level .-- -- 5.1' feet 6200/2500 gal
- 26. Fli/Lo Level in T-300 -- --
6000/<100 gal
- 27. Ili/Lo Levcl in T-301 -- --
m ano nnn'a / r4 4 .. , . . sqr /t jg
TABLE IV (continued)
Scram Run-In Alarm Units 40K cps
- 28. Fission Product -- --
Monitor Ili Activity s
-- see below cpm
- 29. Off-Gas ili Activity --
Secondary Coolant -- 10 cps l
- 30. --
)
Ili Activity 1
- 31. Anti-Siphon Line ili -- >6 -- inches !
Level (above vivs)
Pool Level Low >23' 29'-1" -- inches 32.
- 33. Reg Blade -- <10% or <20% or >60% % withdrawn bottomed ]
- 34. Vent Tank Low Level -- 7-11 -- inches (below C)
<1800 gpm
- 35. Secondary Coolant -- --
Low Flow
- 36. Ch 4, 5, or 6 Downscale -- -- <75 % full-scale
- 37. Valve 546 A or B -- -- off closed
- 38. Valve 509 off open -- --
- 39. Valve 547 -- -- off open
- 40. Valves 507 A/B off open -- closed with p501 on
- 41. Valve S-1 -- -- 90% open or --
90% shut S
This setpoint is determined by the semiannual calibration.
Rev. 12/7/82 App'd 2g SOP /I-17
TABLE IV (continue <!)
Scram Run-In Alarm Units
- 42. Nuclear Instrument ' inoperative -- anomaly --
- 43. Anti-Siphon System -- --
30 psig Pressure Low Anti-Siphon System -- --
44 psig Pressure fligh
- 44. Thermal Column Door -- --
open --
- 45. Truck Entry --
door seal -- --
deflated
- 46. Evacuation or manual / auto --
manual / auto --
]
Isolation
- 47. Rx System Low 63 -- --
psig Pressure (PT-943) 3 Pressurizer Pressure with normal system flaw Any channel will scram on NI Inoperative except SRM e
Rev.12/7(82, App'd W SOP /I-18
sludge is dumped via a 3" drain line at the north end of WT1 or the south end of WT# into barrels. This sludge is dried and removed as dry active waste.
B. Cuno Filters The waste water will normally be pumped through the two Cuno filters. When the oP 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 renove this rsadioactive particulate. After filtering, the filters are shipped as dry radioactive waste (see Section VII.8.12).
VII.8.3 Dumping Criteria A. The liquid waste is collected and held until an analysis is made to determine that the specific activity of all radioactive isotopes in the waste is less than the limit specified in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20) for dumping liquid waste to the sani-tary sewer. If the 10 CFR 20 limits are not exceeded and the total activity of radionuclidee does not exceed 4 mci, the Shift Supervisor may authorize the water to be pumped to the sanitary sewer. Any tank containing water with an activity greater than 4 mci will be discharged only with the approval of the Reactor Manager. In addition to the dumping limit on each isotope, 10 CFR 20 also limits the total activity which the University can dump to the sani-tary sewer to 1 curie per year for carbon-14, 5 curies per ]
year for H-3 (tritium) and 1 curie per year of other radio- ]
active material, excluding C-14 and H-3. This latter limit ]
and a general desire to minimize the activity dumped to our environment, dictates that the waste be retained as long as possible to permit the activity to decay off prior to dis-Rev. 12/7/82 App o SOP /VII-45 r
- 5. Add sufficient acid (6 normal) to lower pH to between 5.0 amd 6.0.
- 6. Secure the acid pump and open the breaker.
- 7. Shut valves RES, RE57, RE58 and RE70.
- 8. Drain and flush the acid mixing tank.
- 9. Close the acid mixing tank valves.
C. Sparge and recirculate, bypassing the filters, for 30 minutes.
D. Add a special carrier solution which will be provided by the Laboratory Group.
E. Sparge and recirculate, bypassing the filters, for one hour.
F. Raise the pH.
- 1. Open the WT2 manhole cover.
- 2. Add sufficierit sodium hydroxide to raise the pH to 11.0-12.0.
Caut f ori: it is bett e to add too much than not encagh.
- 3. Replace the manhole caver.
G. Sparge and recitculate, bypassing the filter, fcr 30 minutes.
H. Secure W.T. recin:ulation Lnd let taak settle for 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Tnco pump (without air sparge) throacf stand pipe, from WT2 tc WT1.
I. WT1 should now be ready to sample.
J. Recirculate WT2 through filter until they no longer foul up.
VII.9 Nitrogen and Valve Operating Air Systems VII.9.1 Purpose The primary function of the nitrogen (N2) system is to provide pres-surized N2 to the pressurizer. The secondary function of the N2 system is to act as a backup to the air in the valve operating system, r
Rev. 12/7/82 App'd 50P/VII-53
REACTOR STARTUP CHECKSHEET DATE:
FULL POWER OPERATION TIME (Started)
( r Low Power Forced Circulation)
BUILDING AND MECHANICAL EQUIPMENT CHECKLIST
- 1. Run emergency generator for 30 minutes and check the governor oil level.
(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or after each maintenance day.)
- 2. a. Check operation of fan 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 />.)
- b. Test stack monitor per SDP wyhile 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. S1 and S2 hydraulic pumps on (oil level normal).
- c. Pump controllers unlocked to start (as required).
- d. Insure N2 backup system on per 50P.
- e. Open air valve for valve operating header (V0P 31).
- f. N2 backup valve open.
- g. Check valves 599A and 599B open.
- h. Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).
- 1. Add DI water to beamport and pool overflow loop-seals.
- 4. Visual check of CT equipment completed.
i a. Oil level in CT fans normal (Monday start-ups).
- 5. Becmport Floor
- a. Beamport radiation shielding (as required).
- 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
- 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 settinge 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 S0P.
- 6. Secondary system on line per S0P (as needed).
- 7. Primary system on line per SOP.
- 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 oP trips set per S0P.
- 9. Valves S1 and S2 cycled in manual mode and positioned as required.
- 10. Nuclear Instrumentation check completed per S0P.
- a. The following trip values were obtained during the check:
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 % Scram %
l 11. Channel 4, 5, and 6 pots returned to last heat balance position.
- 12. SRM-1 detector ponse checked and set to indicate > 1 cps.
O l RIv. 12/7/82 App' t 50P/A-la l
l ,N
RETURN ORIGINAL TO HEALTH PHYSICS OFFICE No.
WASTE TANK SAMPLE REPORT TANK NO. TANr. 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) ( uCi) a . H- 3 12.3Y b.
_ __ ____m pH TOTAL CONCENTRATION (b)
Analysis by TIME DATE Concentration (uCi/m) Total Volume (liters) Activity (mci)
(a) x =
l (b) x =
- 2. Approvals Required for:
Any Discharge ......................
Shift Supervisor Discharge of Total Activity >4 mci or to Secondary System Reactor Manager Discharge Limit Approved . . . . . . . . . . . . . . . . .
Health Physics
- 3. Action Taken l Date Discharged Time Discharged Volume Discharged (Liters)
Tank Discharged to (check one) Sanitary Sewer Secondary System Not Dischar<
REMARKS t , is Rev. 12/7/82 App'd # _ // p , SOP /A.
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REVISION NUMBER 8 TO REVISED OCTOBER 1981 MANUAL SOP /VII-53 Revised 12/15/82*
SOP /A-11a Revised 12/15/82**
S0P/A-11b Revised 12/15/82**
- 8 rackets added.
- 0nly page number changed .
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1 i.
II-3 I
r 44.,-, _, . . . . _ . . , _ , _ . ..,m_,. . - , , . , , , , , , . . , . , , , . . . _ . . _ . . . _ _ _ . , . , - - , - _ . . . . , _ , , _ _ , , , , _ , - - , _ _ , _ _ , .
- 5. Add sufficient acid (6 normal) to lower pH to between 5.0 and 6.0.
- 6. Secure the acid pump and open the brear.er.
- 7. Shut valves RES, RE57 RE58 and RE70.
I 8. Drain and flush the acid mixing tank.
i
- 9. Close the acid mixing tank valves.
C. Sparge and recirculate, bypassing the filters, for 30 minutes.
D. Add a special carrier sohtlon which will be provided by the Laboratory Group.
E. Sparge and. recirculate, bypassing the filters, for one hour.
F. Raise the pH.
- 1. Open the WT2 manhole cover.
4
- 2. Add sufficient sodium hydroxide to raise the pH to 11.0-14.0.
Caution: It is better to cdd too much than not enough.
- 3. Replace the manhole cover.
- G. Sparge and recirculate, bypassing the filter, for 30 minutes.
H. Secure W.T. recirculation and let tank settle for 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. ]
Then pump (without air sparge) through stand pipe, fro;n WT2 to ]
WT1. ]
I. WT1 should now be ready to sarnple. ]
- J. Recirculate WT2 through filter until they no longer foul up. ]
VII.9 Nitrogen and Valve Operating Air Systems
! VII.9.1 Purpose j The primary function of the nitrogen (N2 ) system is to provide pres-l surized N2 to the pressurizer. The secondary function of the Np system is to act as a backup to the air in the valve operating system.
Rev. 12/15/82 App'd M ga SOP /VII-53
RETURN 03.IGINAL TO HEALTH PHYSICS OFFICE No.
WASTE TANK SAMPLE REPORT TANK NO. TANK LEVEL (Liter:
Completed adding water to this tank. TIME DATE SAMPLER TIME DATE
- 1. Analysis Results Nuclide Half Life Physical Form Concentration MPC Activit;
( uCi/ml ) (uCi)
- a. H.3 12.3Y b.
pH
.. TOTAL CONCENTRATION (b)
Analysis by TIME DATE Concentration (uti/m) Total Volume (liters) Activity ,(me)
(a) x =
(b) x =
i
- 2. Approvals Required for:
Any Discharge ...................... __
Shift Supervisor Discharge of Total Activity >4 mci or to Secondary System Reactor Manager l Discharge Limit Approved . . . . . . . . . . . . . . . . .
l Healtn Physics
, 3. Action Taken 1
Date Discharged Time Discharged Volume Discharged (Liters)
Tank Discharged to (check one) Sanitary Sewer Secondary System Not Dischar l
l REMARKS i
Rev. 12/15/82 App'd ,e 34S>n _ S0P/A-112 ici '
NOTE: THIS PAGE INTENTIONALLY LEFT BLANK-R:v. 12/15/82 App'd, _ S0P/A-11b ]
u '
REVISION NUMBER 9 TO REVISED OCTOBER 1981 MANUAL SOP /A-4a Revised 1/3/83 II-4
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY App'd M $'4 '
DateRft 1/3/83 REACTOR SHUTDOWN CHECKSHEET DATE
- 1. Time of reactor shutdown: .
- 2. All blades bottomed and drive mechanism full in.
- 3. Magnet current switch off.
- 4. SRM set to required position (= 1000 counts if refueling).
- 5. Reactor primary system shutdown per 50P IV.
- 6. Pool system shutdown per S0P V.
- 7. Secor.dary system shutdown per SOP VI.
- 8. Cooling tower fans off.
- 9. Digital readout switch off.
- 10. Annunciator board on off __.
- 11. Reverse osmosis unit to standby.
- 12. Sample inventory satisfactory and data sheets updated.
- 13. Si integrators recorded.
- 14. All bypass switches off and keys in key box.
- 15. Master switch off on .
- 16. DCT system secured.
- 17. Room 114 check:
- a. Cooling flow to P501 A/B secured.
- b. Valves S1 and S2 hydraulic motor off.
- c. N2 system and air to valve header secured,
- d. Calgon units secured.
- e. Room 114 pump controllers locked out.
- 18. Completed and logged reactor shutdown checksheet.
BUILDfNG SHUTDOWN CHECKSHEET
- 1. Pool level normal.
- 2. ARM trip levels set per 50P.
- 3. Annunciator board off.
4 TV unit secured.
- 5. ARM and off-gas recorder paper supply okay, charts timed and dated.
- 6. Primary / pool drain collection system secured per 50P.
- 7. Routine patrol completed.
- 9. Master key switch off and in key box.
- 10. Test of containment intrusion alarm completed. System energized.
s 11. All keys accounted for.
- 12. Building shutdown and reactor secured.
- 13. Control room doors locked.
- 14. Completed building shutdown checksheet.
- 15. Logbook entries complete, crews signed out.
Senior Reactor Operator 50P/A-4a
REVISION NUMBER 10 TO REVISED OCTOBER 1981 MANUAL 50P/A-la Revised 1/17/83 SOP /A-lb Revised 1/17/83*
l
- 0nly page number changed.
i l
l II-5
REACTOR STARTUP CHECKSHEET DATE:
FULL POWER OPERATION TIME (Started)
(or Low Power Forced Circulation)
BUILDING AND MECHANICAL EQUIPMENT CHECKLIST
- 1. Run emergency generator for 3Ginutes 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 fan 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 />.)
- b. Test stack monitor per S0P 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 50P.
- e. Open air valve for valve operating header (V0P 31),
- f. N2 backup valve open.
9 Check valves 599A and 5998 open,
- h. Pipe trench free of water (or. Monday *,tartups, check the four-pipe annulus drain valves for water leakaSe).
- 1. Add D1 water to beamport and pool overflow loop-seels.
- 4. Visual check of CT equipment completed.
- a. 011 level in CT fans normal (Mcaday start-ups).
- 5. Beamport Floor
- a. Beamport radiation shielding (as required).
- b. Unused beamports checked flooded (Monday).
- c. Seal trench low level alarm tested (Monday).
- 6. Emergency air con' pressor (load test for 30 minutes on Monday).
- 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.
l S. Primary / pool drain collection system in service per SOP.
- 6. Secondary system on line per SDP (as needed).
l 7. Primary system on line per S0P.
[
- a. Primary cleanup system on line.
- 8. Pool system on line per SOP.
- a. Pool cleanup system on line.
- b. Pool skinsner system vented.
- c. Pool reflector oP trips set per 50P.
- 9. Valves Si and S2 cycled in manual mode and positioned as required.
- 10. Nuclear Instrumentation check completed per S0P.
- a. The following trip values were obtained during the check:
b 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 %
- 11. Channel 4, 5, and 6 pots returned to last heat balance position.
- 12. SRM-1 detector response checked and set to indicate > 1 cps.
Rev. 1/17/83 App'd /k SOP /A-la y
REACTOR STARTUP 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. a. Bypass switches 2S40 and 2S41 in position required,
- b. All keys removed from bypass switches.
- 18. Master switch 151 in "cn" position.
- 19. Magnet current switch on, check " Reactor On" lights.
- 20. Reactor isolation, facility evacuation and ARMS checks. (Monday start-up).
These items are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verity that the TAA's do trip.
- a. Reactor isolation switch (lease valves and doors closed). (Monday start
- b. Facility evacuation switch (check outer containment horns),(Monday start
- c. ARM 5 trip setpoints checked and tripped, check buz:er operational locall 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 6 - Cooling Equipment Room 114 Channel 7 - Building Exhaust Air Plenum (Monday Start-up)
Channel 8 - Reactor Bridge (switch in " Normal") (Monday Start-up)
Channel 9 - Reactor Bridge backup (switch in " upscale") (Monday Start-up
- d. Check HV readings: volts.
- e. Check 150V reading: volts.
- f. Selector switch on ARMS in position 5.
- g. Trip backup monitor with attached source.
- h. Reactor isolation horns switch in " Isolation Horns On" position. Valves doors open.
- i. All ARMS trips set per SOP.
- j. Check ventilation fans, containment and backup doors.
t 21. Operate reg blade from full-out to full-in and set at 10" + .05".
l a. Check rod run-in function at 10% withdrawn and annunciator at rod bottom
- 27. Raise blade A to 2" and manually scram.
l 23. Raise blade B to 2" and trip manual rod run-in.
l 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 after all systems are in operation.
l
- a. Check oil reservoir for pump P501A, P5018, and P533 for adequate supply.'
Add if necessary. Vent the 6000 gallon pool hold up tank.
- 34. Routine patrol completed.
- 35. Reactor ready for startup.
Time (Completed) l 5enior Reactor Operator Rev. 1/17/83 App'd SOP /A-lb
i i
REVISION NUMBER 11 TO REVISED OCTOBER 1981 MANUAL S0P/VIII-7 Revised t/7/83 S0P/VIII-11a Revised 4/7/83
, SOP /VIII-11b Revised 4/7/83 50P/VIII-12a Revised 4/7/83*
SOP /VIII-12b Revised 4/7/83*
S0P/VIII-43a Revised 4/7/83 SOP /VIII-43b Revised 4/7/83*
SOP /VIII-44a Revised 4/7/83*
S0P/VIII-44b Revised 4/7/83*
S0P/A-lb Revised 2/8/82 j S0P/A-6a Revised 3/9/83 f SOP /A-7a Revised 3/25/83 l
I i
- Page number changed only.
II-6 f
threaded) or a sealed quartz vial . The quartz vials have a very low rupture pressure so precautions must be taken to eliminate possible pressure build-up when quartz vials are used.
Sample cans will be weighted if necessary to insure that the sample has negative buoyancy.
VIII.2.3 Flux Trap Irradiations Since the flux trap region has a positive temperature and void coefficient of reactivity, additional limitations are placed on all samples to be irradiated in the flux trap.
All flux trap samples will be seal-welded, leak e.heckea and will have a negative buoyancy.
The fiux trap sample holder will be loaded or removed from the reactor only when the reactor is shutdown. The flux trcp sample holder must be securely latched in olace while it is in the reactor. 00 NOT under any circunstances unlatch the flux trap until the control blades are full in.
For verification that the flux trap is properly latched, an operator other than the operator inserting the flux trap will visually observe its proper latching.
All flux trap irradiations will be shown on a flux trap loading sheet (Appendix A) which must be signed by the Reactor Service Engineer. If the sample loading is unique the Reactor Physicist will check the Service Engineer's calculations of the total reactivity worth and will also sign the loading sheet.
If there are insufficient samples to fully load the flux trap sample holder, the holder will be loaded with aluminum
! spacers to insure that the samples cannot move during reactor operation. The sample hold-down rod must be securely pinned or wired to the sample holder to satisfy the Technical Specification requirement of a secured experiment. When the loading of each ]
tube in the flux trap is completed, the operator shall verify ]
that the proper sample height loading has been achieved by lift- ]
q ing the unloading rod to the mark and observing that the top of ]
the highest sample is in line with'the unloading door. ]
Rev. 4/7/83 App'd [0G SOP /VIII-7 l j' I,
F. 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);
- 3. Pure elements: Li , Na , K Rb , Cs , Ca , Sr. Ba , Hg , Os ,
H, 0, F, Ne, Ar, Xr, Xe, and P; 4 Compounds: NH4 N0 3 , CaC2 , Ca0, perch 1 crates, perman-ganates, Na20 , and Na202;
- 5. Materisi s which chemically react with wate* to prod +,ce undesirable quantities of heat and pressure;
- 6. Any explosive, flammble, combustible, or toxic materials, E. Capsules may be run shielded with cadium nr boron (.*s baron, BC, or BN) but weight and time are restricted due to the neat generated and their reactivity effect ca the reactor. The experimenter shall take measures to insure the heat generated can be dissipated without causing damage to the rabbit or sample. The following limitations apply to shielded capsules in 3ddition to the activity limits of Section VIII.3.2.A:
- 1. The authorized p-tube user will inform the control room he is going to run shielded capsules and will insert the rabbit so that the cap is on top when the rabbit is in the reactor.
- 2. Cadium shielded capsules:
- a. 5 or less grams of cadium may be run for up to 30 minutes.
- b. 50 or less grams of cadium may be run for up to 10 seconds in row I or 20 seconds in row 2.
- 3. Roron shielded capsules:
N0fE: The weight limit is only on the boron, i.e. , y the carbon weight in BC does count towards the weight limit, i r
Rev. 4/7/83 App'd ( % SOP /VIII-lla
/
4
- a. 10 or less grams of boron may be run for up to ]
10 seconds in row 1 or 20 seconds in row 2. ]
- b. Between 10 to 15 grams of boron may be run up to ]
10 seconds in row 1 or 20 seconds in row 2, but ]
must be approved by Director of NAP and Reactor ]
Manager prior to running. ]
F. Except for the boron or cadium shielded samples, the con- ]
trolling 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 do not ]
further restrict a sample's size, the following weight limits shall apply:
1, For irradiation times up to 30 minutes, the mix. mum weight of irradiated eaterials in one rabnit will be 2 grams with two exceptiots:
- a. A maximum cf 10 grami of water or dried feces;
- b. Only 1 my of chemical compounds in tointion.
- 2. For irradiation times of 30 minutes to 1 nour, the maximum 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 rabbit, polyethylene vial, or packing, or the cadmium (or other metal) shields.
Rev. 4/7/83 App'd / d24, SOP /VIII-11b I'
-- _ _ . . r
The maximum irradiation time for most samples will be one hour at power levels f 5 MW and 30 minutes for power 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 f 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 > 10 minutes:
- 1. Primary encapsulation will be heat-sealed high-density polyethylene vials (Holland vials).
- 2. Liquid samples may be irradiated fer up to 30 minutes pro-virad pin holes are punched in the top of tne polyethylene vial to relieve pressure.
Deviations frein the above weight and time limitatier.s must be
~
specifically authorized D: the exnerimenter's EdR.
V I I ": .1. 3 Rabbit Limitations A. Two types of rabbits are p.etently authorized for use in the p-tube systen. Tr:e mo:.t com .only Jhed rabbit is the low density polyethylene rabbit. The rainimal cost of this rabbit makes it ideally suited for- short irradiations in which the sample is a solid and the weight is small. These rabbits are very susceptible to radiation damage and have led to rabbit failure when they were used a number of times. Low density rabbits will therefore be used only once in the p-tube system and will not be used for irradi-ations greater than 10 minutes.
B. The second type of rabbit which may be used in the p-tube system is the high density rabbit. This type of rabbit will be used for all irradiations greater than ten minutes and for most liquid and powder irradiations (see Section VIII.3.2.B). Each high density rabbit will be limited to six insertions or two hours of total irradiation, which-
^
ever occurs first. To account for the irradiation history of high density rabbits, the experimenter will place one mark with a marking pen on the high density rabbit for Rev. 4/7/83 App'd SOP /VIII-12a
- . , . . - , , - . - , _. _, , , , _ .,__-.m
s N
NOTE: THIS PAGE INTENTIONALLY LEFT BLANK l
l l Rev. 4/7/83 App'd )b L SOP /VIII-12b ]
U
VIII.6.7 Renove Irradiated Roll from Rewind Stand To remove irradiated film from the shield box one of the i
following two conditions must be met:
- 1. Eight hours decay time from completion of irradiation, or
- 2. a. Two hours decay time from completion of irradiation,
- b. Roll heading <500 mR/hr.
- c. Health Physics Technician present.
- d. Roll storage to be in the shielded iteel box.
If an irradiated roll is to be stored outside toc shieic=1 i
box the cad 6.aticn reading at the roll must be <100 9 /h .
General: Consider all itens insIde the shiefi box as contamirated. Expertence has sho e .sn minatien to be smearable but fixed sufficiently 50 that f t does not blow around. The contamination levels or, the towed :nt'er (light colored rubber) and the lay-on roller (biack rolf ar) will be quite high. The pinch roll (black rubber) will also be contaminated but it is relatively keccessiole.
A. Make sure the splined shaft coupling is disconnecteo from the rewind roll shaf t.
- 8. Raise LAY-0N.
C. Cut the film near the roll.
D. Secure the end of the film on the roll with scotch tape.
! E. Wrap a layer of plastic around the roll and secure it l with tape.
l i F. Open the bearing caps.
I G. Depending on roll size, follow procedure below.
l 1. Fifty pound roll l a. Lift the roll off the unwind stand and lay the roll on a piece of sponge rubber.
- b. Deflate the unwind shaft and remove it and the ,
j adapter from the roll.
- c. Set the shaft and adapter on paper.
7
- d. Tuck the ends of the plastic roll wrap inside the core tube.
I r
Rev. 4/7/83 App'd hhu SOP /VIII 43a L ___
I
- e. Lif t the roll and place it in the box It cane out of.
- f. Inset core tube shipping adapter in the end of the core tube,
- g. Close the box with duct tape.
- h. Write roll I.D. number on box,
- i. Have Health Physics survey the box and record apprcoriate r3diation level en the box.
Move the box to storage, j.
e s
b
- I ',
1 g
./
d a
y ?
lev. 4/7/33 1 0 0 ' 1- (_. I'!"-- SOP /VIII llb e
- 2. Greater than fif ty pound roll (up to 300 lbs)
- a. Have either a shipping container or a roll support stand available to hold the roll, f b. Place the large sling around the roll and lif t it off the unwind stand with the MURR crine,
- c. Deflate the unwind shaf t and renove it and the core tube adapter from the roll. It is convenient to store the adapter and rewind shaft back an the rewind stand.
- d. Place the filra coli on the cantilevered shaft of the shipping container or the cell support stard.
- e. Remove the sling.
- f. If the snipoing coatainer is used, place ne re-tainer ring on the shaf t to hold the core tube i-clace and install the srioning r.ontainer cover, i g. Mark the t:entainer or roll witn the radiation level and move the roll or container to stcrage.
VIII.6.8 Install New Core Tube on Rewind Stand A. Put core tube adapter and rewind shaft inside core tube.
NOTE: Make sure core tube is wide enough for the next roll.
B. Center the adapter and shaft in the core tube.
C. Inflate the unwind shaft.
D. Put the assenoly on the bearings and close and latch the bearing caps.
E. Paint the north end of the core tube black.
F. With measuring tape, mark the center of the core tube.
G. Measure from inside of left bearing block to the center of the core tube. The center should be 12" t 1/8" from the inside edge of the left bearing block.
H. If necessary, deflate the rewind shaft, relocate the core tube and re-inflate the shaft.
I. Pull the film end from the raised lay-on roll to the core tube and lay it smoothly over the core tube.
Rev. 4/7/83 App'd- !!v SOP /'/III ada V
l NOTE: THIS Pt.GE INT!hil0NALU LEFT BLANK I
i Rev. 4/7/83 App' '
~ S0?/VIII-44b ]
REACTOR STARTUP 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 inmediately 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. a. Bypass switches 2S40 and 2S41 in position required,
- b. All keys removed from bypass switches.
- 18. Master switch IS1 in "on" position.
~__
~ 19. Magnet current switch on, check " Reactor On" lights.
~
- 20. Reactor isolation, facility evacuation and ARMS checks. (Mcnday start-up).
These items are to be checked with scrcms and rod run-ins reset, and wher-appropriate items are actuated, verify that the TAA's do trip,
- a. R3 actor isolation switch (leave valves and doors closed). (Monday start.
- b. Facility evacuation switch (check outer containment borns).(Morday start
- c. ARMS trip sotpoints checked and tri.pped, check buzzer operational locall for all thennels and remotely for channels 1 throug'r 4 and 9.
Chacnel 1 . fa n Room South Wil Cunrel 2 - Beam Room West Wall Channel 3 - B0an Poom North Wall Channel 4 - Fuel Stcrage Vault Channel 6 - Cooling Equipment Room 114 Chant.el 7 - Puilding Exhaust Air Plenum (Ponday stort-up)
~
CFanne? 8 - Peactor Bridge (switch in " Normal') (Monday Start-un)
{ Chennel 9 - Reactor Bridge backup (switch in "apscale") (Mon (13y 3. art-up
- d. Check HV readings: volts.
- e. Check 150V reading: volts.
- f. Selector switch on ARMS in position 5.
- g. Trip backup monitor with attached source.
- h. Reactor isolation horns switch in " Isolation Horns On" position. Valves doors open.
- i. All ARMS trips set per SOP.
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 107, withdrawn and annunciator at rod bottom
- 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 scran 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 after all systems are in operation,
- a. Check oil reservoir for pump P501A, P501B, and P533 for adequate supply.
Add if necessary. Vent the 6000 gallon pool hold up tank.
- 34. Routine patrol completed.
- 35. Reactor ready for startup.
Time (Completed) enior eac or .pera or Rev. 2/8/83 App'd / M k_ SOP /A-lb
CORE: 51ARTUP NUCLEAL DtTA Date:
AkP. b4NK xk hKP i {
TIME P05. P05. P05. SRM-1 l 1RM-? ! IRM-3 WRM 4 PROCEEDINGS I
l Critical RodTdsition A '~ ~
B C D RR EC F Power at Critical Position Pri . ' Temp. / Pooi Temp. /
Operator / Remarks:
3 C0ki: Date: __
lAPDT ETR T 'Ot 5RM l d TIME '20 s . PDS. POS. ! SRM-1 IRM-2 IRM-3 WRM a PROCEEDINES 1
Critical Rod Position A B C D RR EC F Power at Critical Position Pri . Temp. / Pool Temp. /
Operator / Remarks:
CORE: Date: _
APP. BANK kR SRM TIME P05. P0S. POS. SRM-1 IRM-2 IRM-3 WRM 4 PROCEEDING Critical kod Position A B C D RR LLP Power at Critical Position Pri . Temp. / Pool Temp. /
Operator / Remarks: e Rev. 3/9/83 App'Q-o/~
I sneet No: _
Date:
PNEUMATIC TUBE IRRADIATIONS 70li" CTo13 6 Tiisi- TF6TedTT6orii TfFadiatT6ir No. In Out Name No. No. Min. Sec.
I 2 l 3
_ ___.l____ _
4 5 l 6 l l 7I l l l l ._
8 l l ,_
9 i l JL I - . -_a _.,
11 l l l l l 12l l l ! h 13 l l l ! j la l- !._- ! l. J ___
'15 l l l l_
l !
16 l l _,
j_ l l ,
17 I I l 1 3 8_L_____L____ L_____1___L_ _
19l l l E- _
n_ \ _
n_ _
23 2t _m 25 _ A__
n_ _ _
22_ i n_ ____L___ __
29 l 30 _,
I l l31 l 32 l l 33 34 Rev.3/25/83 App'd.l[/.s 50P/A-7 c
REVISION NUMBER 12 TO REVISED OCTOBER 1981 MANUAL t
et r; A
~."
50P/VIII-51 Revised S/23/83 s 4*
SOP /V!II-Si. Revised 5/23/83 .,,
,4,4
,y
, Ihg l t . "), .
- s P '
u .
i h
s v
(
II-7
- 0. Turn on drive motor.
NOTE: Ensure take-up reel is turning. If not, immediately stop machine.
E. Run film approximately five (5) meters at four (4) to five (5) neters per minute.
F. Turn off drive motor. Leave speed set at running speed.
G. Turn off lamp.
H. Log entry.
VIII.7 Thermal Column Door Operations ]
VIII.7.1 Opening The Thermal Column Door ]
NOTE: Do not open thermal column door ]
with the reactor critical. ]
- 1. Clear all obstructions from behind thermal column door. ]
- 2. Verify air off to Radiograph with Control Roon. ]
- 3. Disconnect air supply line on thermal column door at the ]
snap fitting. ]
- 4. Preparation of Nuclepare Case: ]
A. Decouple Nuclepore take-up shaf t. ]
B. Remove alignment pins from shield box door. ]
C. Roll shield box cover as far back along track as ]
possible. (NOTE: If thermal column door must be ]
backed out further than this, attach shield box door ]
lifting rig and move to south side of the platform ]
using the building crane.) ]
- 0. Decouple Nuclepore drive shaft. ]
E. Decouple Nuclepore rabbit drive. (NOTE: Remove ]
rubber grommet and store.) ]
F. Secure air to the Nuclepare equipment. ]
G. Disconnect PVC air lines to the drive roll. ]
- 5. Unstack shielding as necessary to allow free movement of ]
the door. ]
- 6. Plug in thermal column door drive motors (2). ]
Rev. 5/23/83 App'd A SOP /VIII-51
- 7. Back out thermal column door approximately six (6) inches. ]
- 8. Disconnect four (4) PVC lines connected to the top of the ]
Nuclepore Irradiator Case. ]
- 9. With Health Physics coverage, open the thermal column door ]
to the desired position. ]
VIII.7.2 Shutting The Thermal Column Door ]:
- 1. Shut the thermal column door far enough to allow the four ],
(4) PVC lines to be reconnected to the Nuclepore Irradiator]:
Case. ]f
- 2. Reconnect the four (4) PVC lines. ]'
- 3. Completely shut the thermal column door while monitoring ]:
to insure that the four (4) PVC lines do not become ]
pinched off. ]
4 Verify the thermal column door open limit switch has ]
cleared in the Control Room. ]:
- 5. Unplug the thermal column door drive motors. ]'
- 6. Restack shielding on the top of the thermal column. ]'
- 7. Connect the Radiograph air supply line to the regulator ]
assembly. ];
- 8. Install the platform deck plates. ]'
- 9. Nuclepore Experiment: ]
A. Recouple and lock Nuclepore drive roll. ]
B. Attach PVC air lines to the drive roll. ]'
! C. Install rubber grommet and attach rabbit drive ]
mechanism. ]
D. Place shield box door back on rails and shut it. ].
I Pin door fully shut. ]
l E. Recouple take-up spline coupling. ]:
F. Open Nuclepore air supply valve and reset all ]
( tension controls. ]
l G. Test run film. ]
H. Place the experiment in its desired operational mode ]
[ in accordance with approved procedures. ]'
l 10. Inform operators of the system status. ]
l
-1
- Rev. 5/23/83 App'd g#u SOP /VIII-52
4 SECTION III 1983 REVISIONS TO THE HAZARDS
SUMMARY
The third paragraph of section 8.4 is deleted and replaced by the following two paragraphs.
A plenum plate adaptor (plenum, design duplicates the reflector plenum plate between Beamports A and D) was inserted occupying the two large graphite element positions on both sides of the reg. blade and new irradiation baskets inserted.
This includes one 15 solid aluminum element with a two inch and a three inch irradiation basket; one 30 graphite element; a two inch row two irradiation element and two small graphite elements. All the wedge irradiation baskets and each of the three inch baskets have self powered neutron detectors monitor-ing the irradiation spaces.
All samples that are irradiated are verified to be covered by an approved RUR, prepared, and scheduled for irradiation by the Reactor Services group. A record is kept of all irradiations. Various forms are now utilized. The type of form is determined by the type of sample and position required for irradi-ation.
III-1
SECTION IV PLANT AND SYSTEM MODIFICATIONS
~
~
AUGUST 1982 Modification 81-23: This modification installed phonojacks in the power supply leads for the valve 552A and 5528 solenoids (primary vent valves). The jacks are of the normally closed type and require the insertion of a plug for compliance testing. This modification provides a safer and more reliable method for i terrupting power to these valves than the old method which involved the lifting of electrical leads. The continuity of the power supply to the valves is checked in the last steps of compliance testing.
Modification 81-23 presents no unresolved safety questions. It increases operator safety while working with electrical control systems.
NOVEMBER 1982 Modification 82-1: This modification installed an adaptor fixture in the reflector tank to accommodate small 15* graphite irradiation elements replacing two existing graphite elements on either side of the regulating blade.
Modification 82-4: This modification placed a 15* solid aluminum reflec-tor element in the south position adjacent to offset "B", created by Modifi-cation 82-1. This element has a 2" diameter sample position and a 3" diameter sample position. These sample positions are instrumented with self powered neutron detectors. The north position created by 82-1, adjacent to offset "C",
currently uses previously installed H-1, H-2, and H-3 elements.
Modifications 82-1 and 82-4 present no unresolved safety questions. These modifications increase the sample irradiation facilities in the reflector region consistent with existing installed assemblies.
IV-1 l
JANUARY 1983 Modification 83-1: This modification installed 1/4" 0.D. x 3" long stain-less steel pins, with ring clips threaded through the eyelet at each end, in the valve operating linkage for valves 543A and 543B. The installation of these pins with ring clips, in the valve operator linkage coupling, prevents the pins from falling out.
Modification 83-1 presents no unresolved safety questions. This modifi-cation increases the reliability of the operation of the 543 valves.
IV-2
SECTION V NEW TESTS AND EXPERIMENTS New experimental programs during the period of July 1982 through June 1983 are as follows.
RUR264 Experimenter: Don Alger/ John Lindsay
Description:
Installation of a new neutron radiography facility was completed in July 1982 with the capability to do real-time neutron radiography or conventional film radio-graphy. The facility was designed to allow radiography of larger objects and to have a lower radiation level next to the unit compared to the old neutron radiography facility.
V-1
SECTION VI j SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1982 through 30 June 1983
- 1. SNM Receipts: During the year, the MURR received fuel from Rockwell Inter-national Energy Systems Group -(Atomics Internatice al). In December of 1982, the fuel fabrication facility at Atomics International was closed and fabri-cation ~ equipment was transferred to Babcock & Wilcox (B & W) at Lynchburg, i
Virginia. Fuel elements that were stored at Atomics International were also transferred to B & W for storage and eventual shipment to MURR when required
.for entry into the reactor fuel cycle. A total of 27 new fuel elements were received.
?
Grams Grams Shipper Elements V U-235 Atomics Int 'l . 22,388 20,853 94, 95, 96, 97, 98, 99, 100, 101, 118, 119, 120, i 121 B&W 150, 151, 152, 153, 154, 155, 156, 157, 158, 159, 160, 161, 162, 164, 165 i
- 2. SNM Shipments: Spent fuel elements were shipped to Exxon Nuclear Company, Inc., Idaho Falls. Idaho, for reprocessing.
l Grams Grams Shipper Elements U U-235 MURR 17, 21, 26, 31, 33, 43, 10,766 9,387 46, 48, 15, 22, 27, 29, 53, 54, 63, 65
- 3. Inspections: No Special Nuclear Material Inspection .was performed during this fiscal year.
i 4. SNM Inventory: As of 30 June 1983, the MURR financially responsible in-ventory was as follows:
Total U = 45,327 Total U-235 e 40,436 4
All of this material is physically located at the MURR.
VI-1
Fuel elements on hand have accumulated the following burnup as of 30 June 1983:
Fusl Element Accumulated Fuel Element Accumulated Fuel- Element Accumul-ated Number Megawatt Days Number Megawatt Days Number Megawatt Days M041 146.45 M078 146.52 M0100 88.53 M055 149.31 M079 115.35 M0101 86.17 M056 147.83 M080 146.15 M0118 94.61 M057 149.31 M081 144.46 M0119 87.84 M059 146.10 M082 114.98 M0120 94.61 M060 146.10 M083 144.46 M0121 87.84 M061 145.43 M084 142.87 M0150 73.47 M062 145.43 M085 142.87 M0151 96.16 M064 141.60 M087 147.57 M0152 73.47 M066 141.60 M088 10.69 M0153 96.16 M067 146.75 M089 147.57 M0154 67.21 M068 134.99 M090 116.69 M0155 33.56 M069 146.75 M091 112.31 M0156 67.21 M070 106.65 M092 116.69 M0157 33.56 M071 147.83 M093 112.31 M0158 15.13 M072 143.86 M094 115.13 M0159 15.13 M073 109.09 M095 128.94 M0160 0 M074 143.86 M096 115.13 ,
M0161 0 M075 110.17 M097 128.94 M0162 0 l M076 134.99 M098 88.53 M0164 0 i M077 107.72 M099 86.17 M0165 10.69 l
Average Burnup = 102.15 MWD Also MURR owns a total of 134 grams V and 54 grams U-235.
I VI-2
SECTION VII REACTOR PHYSICS ACTIVITIES
~
July 1,1982 through June 30, 1983
- 1. Fuel Utilization: During this period, the following elements reached their licensed burnup and were retired.
Serial Number Core Designation Date Last Used MWDs M067 A0-23 8-22-82 146.75 M069 A0-23 8-22-82 146.75 M059 A0-29 10-10-82 146.10 M060 A0-29 10-10-82 146.10 M064 A0-40 12-20-82 141.60 M066 A0-40 12-20-82 141.60 M081 A0-41 1-03-83 144.46 M083 A0-41 1-03-83 144.46 M072 AP-7 2-28-83 143.86 M074 AP-7 2-28-83 143.86 M061 AP-9 3-20-83 145.44
, M062 AP-9 3-20-83 145.44 M078 AP-8 3-07-83 146.52 M080 AP-8 3-07-83 146.15 M056 AP-10 3-28-83 147.83 M071 AP-10 3-28-83 147.83 M087 AP-15 5-08-83 147.58 M089 AP-15 5-08-83 147.58 M084 AP-19 6-06-83 142.87 M085 AP-19 6-06-83 142.87 M068 AP-20 6-12-83 135.00 M076 AP-20 6-12-83 135.00 Normally 24 fuel elements are listed as retired, but due to increased shipping costs for new and irradiated fuel, fuel elements that cannot be utilized during a normal fuel cycle (previous definition for retirement) 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 four new elements or fewer as conditions dictate. A core designation consists VII-1
of eight fuel elements of which only initial critical fuel element serial numbers are listed in the following table. To increase operating effi-ciency, fuel elements are used in mixed core loading, therefore, a fuel .
element fabrication core number is different from its core load number.
Fabrication Serial Core Load Initial Core No. No. Designation Operating Date 32 M094 A0-23 8-09-82 32 M096 A0-23 8-09-82 32 M095 A0-25 8-30-82 32 M097 A0-25 8-30-82 32 M098 A0-29 10-04-82 32 M099 A0-29 10-04-82 32 M0100 A0-29 10-04-82 33 M0101 A0-29 10-04-82 35 M0119 A0-36 11-19-82 35 M0121 A0-36 11-19-82 35 M0118 A0-40 12-13-82 35 M0120 A0-40 12-13-82 39 M0150 AP-7 2-14-83 39 M0151 AP-7 2-14-83 39 M0152 AP-7 2-14-83 39 M0153 AP-7 2-14-83 39 M0154 AP-10 3-20-83 39 M0156 AP-10 3-20-83 39 M0155 AP-15 4-26-83 39 M0157 AP-15 4-26-83 31 M088 AP-20 6-07-83 40 M0165 AP-20 6-07-83 40 M0158 AP-23 6-19-83 1
40 M0159 AP-23 6-19-83
- 2. Fuel Shipping: Sixteen spent fuel elements were shipped f rom our facility during the fiscal year. The following list contains the serial numbers of the fuel elements that were shipped.
M015 M026 M033 M053 M017 M027 M043 M054 M021 M029 M046 M063 M022 M031 M048 M065 VII-2
- , , - - . , ,,.m --
g-- a--- ---- - - - -. , --- -- ---
- 3. Fuel Procurement: At the present time, the Babcock & Wilcox Company is es-tablishing facilities to fabricate MURR fuel at Lynchburg, Virginia. This work is contracted with U.S.D.0.E. and administered by t.he Idaho Operatio,ns Office.
- 4. Licensing Activities: A physical security plan (10CFR70:67) that was sub-mitted May,1980 was reviewed by the NRC and our staff in May 1983. A re-vised physical security plan was submitted in June 1983 and final approval is still pending. A reactor emergency plan was submitted in September of 1982 and approval is pending. A request for an increase in Special Nuclear Material Inventory under our Facility License was submitted in December of 1982. A revision to Technical Specifications 4.4.d requiring two pool pumps operating submitted in February 1982 is still pending.
No changes were made to our Facility License No. R-103 (Docket No.
50-186) during this fiscal year. The latest amendment to our license is Amendment 14 which was issued April 14, 1981.
- 5. Reactor Characteristic Measurements: During the fiscal year, 47 reactor refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 3.06%.
MURR Technical Specification requires an excess reactivity value of less than 9.8%.
Reactivity measurements were performed for 31 evolutions to verify reactivity parameters for the flux trap. Shim blade calibrations were performed at selected rod heights in support of reactivity measurements.
A physical inspection of the following fuel elements was performed to verify the operational parameters:
VII-3
M056 from Core 27 during April 1983 M061 from Core 28 during April 1983 -
M062 from Core 28 during April 1983 M071 from Core 29 during April 1983 M078 from Core 30 during April 1983 M087 from Core 31 during April 1983 All measurements were within operational requirements.
Computer analysis of the reactor core is being accomplished using Citation Computer Code. A master's degree will be awarded to Larry Livingston for his work in this area.
1 1
i i
I i
l' l
VII-4
SECTION VIII
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Sanitary Sewer Effluent From 7-1-82 through 6-30-83 Descending Order of Activity Released Nuclide Amount (C1) Nuclide Amount (Ci ) Nuclide Amount (Ci)
H-3 8.594E-01 AG-110M 1.652E-04 AU-198 1.113E-05 S-35 5.510E-01 LA-140 1.630E-04 C0-57 8.715E-06 ZN-65 3.203E-02 SN-113 1.363E-04 I-133 5.867E-06 C0-60 2.303E-02 RE-188 1.351E-04 NI-65 5.531E-06 CR-51 1.446E-02 RB-86 1.128E-04 NA-22 4.943E-06 SB-124 7.492E-03 CD-109 1.058E-04 CD-115 4.058E-06 TA-182 2.638E-03 RU-103 9.503E-05 CO-56 3.108E-06 MN-54 1.816E-03 TC-99M 9.077E-05 SC-46 1.602E-03 NB-95 8.866E-05 NA-24 1.191E-03 ZR-95 5.946E-05 C0-58 1.033E-03 MO-99 5.843E-05 RE-186 8.715E-04 I-131 5.803E-05 CU-64 9.420E-04 BA-133 4.653E-05 AS-77 5.861E-04 BA-139 4.515E-05 TE-125M 5.474E-04 TA-183 4.199E-05 SB-125 5.428E-04 SB-122 3.865E-05 FE-59 3.382E-04 MN-56 3.100E-05 BA-140 2.473E-04 HG-203 2.987E-05 CS-137 2.332E-04 ZN-69M 2.651E-05 CS-134 2.230E-04 K-42 1.658E-05 SE-75 2.041E-04 GA-72 1.490E-05 VIII-1
Stack Effluent From 7-1-82 through 6-30-83 Descending Order of Activity Released Nuclide Amount (Ci) Nuclide Amount (Ci) Nuclide Amount (Ci) .
AR-41 1.714E+03 CE-144 7.965E-06 C0-57 2.625E-07 H-3 1.270E+01 XE-131M 7.477E-06 MN-54 2.615E-07 I-133 1.627E-03 NA-24 3.929E-06 ZN-69M 2.535E-07 I-135 1.131E-03 CS-138 3.742E-06 AG-110M 2.107E-07 I-131 1.109E-03 SN-113 3.736E-06 BA-131 1.864E-07 I-134 5.717E-04 RB-86 3.342E-06 LA-140 1.754E-07 AS-77 5.001E-04 CE-139 2.548E-06 CS-137 1.726E-07 K-40 4.487E-04 C0-60 2.362E-06 NB-95 1.501E-07 XE-135M 3.759E-04 TC-101 2.144E-06 TE-123M 1.353E-07 I-132 3.092E-04 BA-140 1.591E-06 TE-123 1.073E-07 CL-38 2.602E-04 TE-132 1.556E-06 NA-22 1.048E-07 BR-82 1.057E-04 CR-51 1.182E-06 AU-198 9.716E-08 SE-75 4.260E-05 ZN-65 9.978E-07 AU-196 7.239E-08 XE-133 3.663E-05 KR-87 9.550E-07 TC-99M 6.308E-08 HG-203 3.422E-05 IN-114M 8.270E-07 HF-181 2.975E-08 BA-139 3.337E-05 CE-134 7.233E-07 RE-188 3.124E-05 NI-65 7.158E-07 XE-135 2.963E-05 C0-58 7.108E-07 BI-214 2.955E-05 FE-59 5.916E-07 AS-76 2.885E-05 KR-85M 5.849E-07 PB-214 1.947E-05 EU-152 5.664E-07 I-128 1.365E-05 GA-72 4.670E-07 RE-186 1.355E-06 CD-115 2.660E-07 VIII-2
, . . . - . _ . . ,n. , ,,,w., ~ . - - . , , , ,- ., , ,
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 nine locations. Results of the samples are shown in the following tables.
Detection Limits Matrix Alpha Beta Gamma Tritium Water 0.2 pCi/1 2.5 pCi/l 0.04 pC1/1 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: 10-27-82 Determined Radioactivity Levels vegetation Samples Sample Beta pCi/g Alpha pCi/g 3H pCi/mi Ganma pCi/g 1-V-22 15.2 <.2 < 9.1 < 0.04 2-V-22 13.0 <.2 < 9.1 < 0.04 3-V-22 12.1 <.2 < 9.1 < 0.04 l
4-V-22 15.2 <.2 < 9.1 < 0.04 5-V-22 18.1 .5 < 9.1 < 0.04 6-V-22 10.9 .3 < 9.1 < 0.04 7-V-22 12.7 <.2 < 9.1 < 0.04 8-V-22 8.4 <.2 < 9.1 < 0.04 9-V-22 12.2 <.2 < 9.1 < 0.04 IX-1 i
Determined Radioactivity Levels Water Samples -
Sample Beta pC1/1 Alpha pCi/l 3H pCi/ml Gamma pCi/l 4-W-22 < 2.5 .2 < 9.1 < 0.04 6-W-22 3.6 <.2 < 9.1 < 0.04 8-W-22 7.2 <.2 < 9.1 < 0.04 9-W-22 13.3 .4 < 9.1 < 0.04 Determined Radioactivity Levels Vegetation Samples Sample Beta pCi/g Alpha pCi/g Gamma pCi/g 1-S-22 6.9 <.2 < 0.04 2-S-22 6.2 .5 < 0.04 3-S-22 6.2 .5 < 0.04 4-S-22 5.9 < .2 < 0.04 5-S-22 7.3 .3 < 0.04 6-S-22 6.7 <.2 < 0.04 7-S-22 3.9 <.2 < 0.04 8-S-22 5.2 <.2 < 0.04 9-S-22 7.9 .5 < 0.04 l
l IX-2 l
(
- 2. Sampling Date: 4-28-83 Determined Radioactivity Levels Vegetation Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g Tritium (pCi/ml) 1-V-23 0.3 18.3 < 0.04 < 9.1 2-V-23 < 0.2 29.8 < 0.04 < 9.1 3-V-23 < 0.2 20.9 < 0.04 < 9.1 4-V-23 < 0.2 29.1 < 0.04 < 9.1 1 5-V-23 < 0.2 28.1 < 0.04 < 9.1 1
6-V-23 < 0.2 27.2 < 0.04 < 9.1 7-V-23 < 0.2 16.9 < 0.04 < 9.1 9-V-23 < 0.2 25.2 < 0.04 < 9.1 Determined Radioactivity Levels Soil Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g
, 1-S-23 0.24 4.0 < 0.04
! 2-S-23 0.37 9.0 < 0.04 3-S-23 0.33 5.7 < 0.04 4-S-23 0.27 8.4 < 0.04 5-S-23 0.46 8.2 < 0.04 6-S-23 0.25 6.9 < 0.04 l 7-S-23 0.31 12.3 < 0.04 9-S-23 0.37 11.0 < 0.04
[ 10-S-23 0.29 12.4 < 0.04 IX-3 l
Determined Radioactivity Levels Water Samples Sample Alpha pCi/l Beta pCi/l Gamma pCi/l Triti u_m (pCi /ml ).
4-W-23 0.4 5.0 < 0.04 < 9.1 6-W-23 < 0.2 4.7 < 0.04 < 9.1 9-W-23 < 0.2 38.4 371 pCi/1 of I-131 < 9.1 10-W-23 < 0.2 6.7 < 0.04 < 9.1 Radiation and Contamination Surveys The following table gives the number of surveys performed during FY 82-83.
Radiation Contamination 406 305 Sixty-eight (68) Radiation Work Permits were issued during the year.
Miscellaneous Items A program has been initiated for training new Health Physics Technicians to assure they receive a thorough knowledge of Reactor Health Physics procedures.
An analysis of radiation exposure to all monitored personnel except visitors and one day service persons, indicates the ALARA effort resulted in a reduction of 8.8 manRem during the year.
A real reduction of 25 manRem occurred from the 81-82 year, however,14 manRem was used to replace the beryllium reflector in October 1981 and exposure time in badge-months was only 80% that of the 81-82 year.
Following the development of neutron spectra analysis procedures by a Nuclear Engineering student, Reactor Health Physics began neutron spectra surveys in the beamport areas. Lower neutron exposure levies are determined with the neutron spectrometer than indicated by the neutron survey meters.
IX-4
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IX-5
SECTION X
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS July 1,1982 through June 30, 1983
- 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 monthly units reported with exposure above minimal.
- 5. A. E. = Average mrem reported for all units above minimal.
4
- 6. H. E. = Highest mrem reported for a single unit for the month,
- 7. N. E. = No exposure registered.
PERMANENT ISSUE FILM-BADGES Beta, Gamma, Neutron Wholebody Badges:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 72 81 65 34 71 50 55 60 68 57 45 58 AME 40 41 60 80 42 57 52 47 39 45 59 46 AE 71 42 40 39 72 52 75 73 57 65 54 65 HE 230 110 120 190 210 180 240 170 190 190 230 260 Beta and Gamma Wholebody Badges:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE i ME 43 33 44 49 37 36 21 41 29 36 39 40 AME 8 3 6 2 2 4 4 4 3 8 4 5 AE 50 20 17 25 75 48 40 30 30 39 45 22 HE 110 20 30 40 120 110 100 40 70 90 70 40 TLD Finger Rings:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 34 52 56 45 35 37 33 33 33 40 46 40 AME 38 31 31 34 30 34 40 42 35 31 28 28 AE 494 194 149 429 306 243 191 282 291 232 205 197 HE 3770 1470 750 6170 3580 2680 1480 2240 5500 2750 910 1010 X-1
SPARE ISSUE FILM-BADGES Beta, Ganwna, Neutron Wholebody Badges:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 17 30 23 33 18 10 23 14 20 18 20 14 AME 12 6 14 3 5 0 3 2 3 8 8 28 AE 204 105 50 60 66 0 23 35 60 33 28 36 HE 230 180 130 110 180 0 30 50 90 130 90 80 Beta and Gamma Wholebody Badges:
i JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE i ME 4 1 6 6 1 1 4 14 26 26 26 18 AME 3 1 0 0 0 0 0 0 1 3 1 0 AE 37 70 0 0 0 0 0 0 10 13 30 0 HE 70 70 0 0 0 0 0 0 10 0 30 0 TLD Finger Rings:
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ItE 14 13 11 17 16 18 17 19 14 16 19 15 AME 6 5 8 5 5 1 3 0 7 3 2 5 AE 212 170 173 84 136 140 377 0 249 453 105 144 HE 620 350 670 160 200 140 850 0 1100 900 170 350 DOSIMETERS JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE NE 16 13 17 17 17 14 17 20 16 19 16 17 AME 24 28 22 24 24 28 25 23 26 23 28 24 AE 24 28 22 24 24 28 25 23 26 23 28 76 HE 270 260 270 130 225 155 305 180 155 205 175 220 X-2
r- x Research Reactor Facility UNIVERSITY OF MISSOURI Research Park Columbia Missouri 65211 Telephone (314) 882-4211 August 19, 1983 Director of Nuclear Reactor Regulation U. 3. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Cecil 0. Thomas
Reference:
Docket 50-186 University of Missouri Research Reactor License R-103
Subject:
Annual Report as required by Technical Specification 6.1.h(4).
Dear Sir:
Enclosed are two copies of the reactor operations annual report for the University of Missouri Research Reactor. The reporting period covers July 1,1982 through June 30, 1983. The remaining twelve copies will be sent in the near future.
Sincerely, s ', y J. C. McKibben Reactor Manager JCMK:vs I
Enclosures (2) cc w/ report: U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 A"// /
g- y at u COLUMBIA KANSAS CITY ROLLA ST. LOUIS 4
an equal Opportunity institutton