ML19254B412

Annual Operating Rept for Jul 1978-June 1979

ML19254B412
Person / Time
Site:	University of Missouri-Columbia
Issue date:	08/31/1979
From:	Alger D, Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO
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ML19254B409	List: ML19254B408 ML19254B410 ML19254B412
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l UNIVERSITY OF MISSOURI l

i 70 s i :KESE 3

3 ANNUAL i REPORT

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2 1978'79 j

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b I I 3 m 8 289 t y'h

$ 1909g10 RESEARCH REACTOR FACILITY

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT August 1979 9

Compiled by the Reactor Staff Submitted by s'

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J. C. McKibben

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Reactor Manager Reviewed and Approved w -

Don M. Alger Associate Director 1048 290

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TABLE OF CONTENTS Section Page I. REACTOR OPERATIONS

SUMMARY

. . ............ 1 II. OPERATING PROCEDURE CHANGES . . . . . . . . . . . . . 15 III. REVISIONS TO THE HAZARDS

SUMMARY

REPORT ...... 16 IV. PLANT AND SYSTEM MODIFICATIONS. . . . . . . . . . . . 17 V. SPECIAL NUCLEAR MATERIAL ACTIVITIES . . . . . . . . . 19

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VI. REACT 0r. PHYSICS ACTIVITIES. . . . . . ....... 22 VII.

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT. . . . . . . . . . . . . . . ... 24 VIII.

SUMMARY

OF ENVIRONMENTAL SURVEYS. . . . . . . . . . . 26 IX.

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS. . . . ...... 30 4

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i SECTION I REACTOR OPERATIONS

SUMMARY

l The following table and discussion summarize reactor operations in the period 1 July 1978 to 30 June 1979.

Total Hours Operated 7965.6

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Total Hours at Full Power 7921.1 Total Integrated Power 3309.18 MWD 1 JULY 1978 The reactor was operated continuously during July with the following exceptions: three maintenance shutdowns on July 3,17, 31, fourteen sched-uled shutdowns for flux trap sample changes; and three unscheduled shutdowns whose dates and descriptions follsw.

i On July 3, a power level interlock scram occurred during the seven element pull for initial critical test on Core XX. The scram was caused by fluctuations in DPS 929 (Core Differential Pressure Transmittal) signal to the power level interlock circuitry. DPS 929 had to be reset to a different level for this portion of the initial critical test as per Reactor Test Procedure (RTP-3).

A Nuclear Instrumentation Channel 4 high power scram occurred on July 12, due to a spike on Channel 4 while switching ranges on its range selector switch.

On July 18, a Channel 4 high power scram occurred, due to operator error in switching Channel 4 range selector switch downscale during a reduction in power to 50 KW.

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The secondary low sump level cutout circuitry was upgraded in July by installing a flow shield around the low sump level cutout float switch and by installing a low sump cutout switch bypass to enable secondary pump operation if the cutout swicch fails.

The initial critical test of Core XX and the Containment Building Leak Rate Compliance Check were completed in July. The leak rate was checked by a new method this year where the building was held at a constant pressure while measuring the requirea makeup rate. The leak rate was determined to be 11.0 scfm, below the technical specification limit of 16.2 scfm.

AUGUST 1978 The reactor was operated continuously during August with the following exceptions: three maintenance shutdowns on August 7, 14, 28; fifteen sched-uled shutdowns for flux trap sample changes; and three unscheduled shutdowns whose dates and descriptions follow.

During the startun on August 1, following a maintenance shutdown, a rod not in contact with magnet rod run-in was received while pulling blade "A" due to mechanical drag caus<d b a blister as reported in a letter to the NRC Director of Nuclear Reactor Regulations on August 11, 1978. Control blade "B" was inspected on August 7 and control blade "C" was inspected on August 14, no blisters were found on either blade. Control blade "D" had previously beer, inspected on July 3,1978, and therefore was not reinspected.

On August 3, the reactor was shutdown by manual rod run-in to repair the personnel airlock door gasket. After the door was repaired, the reactor was started up and returned to normal 10 MW operations.

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On August 26, the reactor scrammed due to 'mentary loss of facility electrical power supply. No abnormalities were noted and recovery was commenced upon regaining facility power.

A new Solid State Servo Amplifier for regulating blade control ts installed during August. This unit was designed and manufacteced by the MURR Electronics Shop to provide a higher degree of stability and reliability than the tube type amplifier it replaced.

A new collimator was installed in Beamport "B" during August.

SEPTEMBER 1978 The reactor was operated continuously during September, with the following exceptions: fourteen scheduled shutdowns for flux trap sample changes and two shutdowns for maintenance on September 11 and September 25. There were no unscheduled shutdowns in September.

A new collimator was o de and installed in Beamport "D" during September and work continued on the SANS Experiment at Beamport "B".

OCTOBER 1978 The reactor was operated continuously during October, with the following exceptions: three maintenance shutdovns on October 9,16, and 30; fifteen scheduled shutdowns for flux trap sample changes; one scheduled shutdown for a facility evacuation drill, and six unscheduled shutdowns whose dates and descriptions follow.

On October 1, the reactor scranmed due to pool loop low flow as a result of the failure of V509 lag solenoid. This solenoid was replaced, the valve was tested and found to operate satisfactorily.

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. I A reactor scram occurrea on October 2, due to a temporary loss of facility electrical power. This power dip was confirmed by the University Power Plant.

On October 14, a truck entry door open rod run-in occurred due to RF interference from newly run electrical leads, which caused the door 101 control circuitry to open door 101. A key enable switch was added in series with the door 101 combination lock power supply to provide sufficient iso-

, lation of the door 101 control circuitry and prevent a reoccurrence of the RF induced opening of door 101.

On October 22, a rod not in contact with magnet rod run-in occurred, rod "B" having disengaged from its magnet. Investigation revealed that blade "B" was stuck approximately 7" from being fully inserted. The offset mechanism was pulled and it and blade "B" were inspected. The blade appeared to be in satisfactory condition, but the offset was suspected to have a broken center guide tube bearing, due to seeing pieces af bearing race in the bottom of the guide tube. The spare offset mechanism was rebuilt and aligned, a new blade was placed in service, and reactor operations were continued, with the I stipulation that the center guide tube bearings would be replaced with new bearings during each future offset mechanism alignment. This event was re-ported to the NRC Director of Naclear Reactor Regulation. in a letter dated October 31, 1978.

A rod not in cont.act with magnet rod run-in occurred on October 31, with all rods disengaged from their magnets. The cause of the rod run-in was g later determined to be due to intermittent contacts (5-6) on the manual scram switch.

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1048 295 i rod run-in due to high power on Channel 6 was received on October 31 due to operation error in control blade shimming.

A new 10 element upper Z basket was installed in October to expand our fuel storage capacity. Extensive effort was expended in support of the Nuclepore installation and testing of its irradiation facility.

NOVEMBER 1978 The reactor was operated continuously during November, with the following exceptions: two maintenance shutdowns on November 6 and November 20; fourteen scheduled shutdowns for flux trap sample changes; and five unscheduled shut-downs whose dates and descriptions follow.

On November 2, the reactor scrammed with no associated annunciation as to the reason the rods dropped. Investigation by the electronic technicians revealed that two contacts (5-6), on the manual scram cwitch input to the TAA's, were making intermittent contact. The switch was replaced and no further problems of this nature were experienced.

A manual rod run-in was initiated on November 2, in order to repair the inner airlock door limit switch chain.

On November 7, a Channel 5 high power rod run-in occurred due to operator error. The operator had not changed the power level set after changing the indication by pot setting of Channel 4, resulting in the indicated power in-crease which caused the rod run-in.

A manual scram was initiated on November E, shen pool pump 508B mechanical seal was found to be leaking excessively by an operator on routint patrol. The subsequent repair work revealed that the thrust bearing keeper nut had backed off the pump shaft, allowing the impeller to rub against the pump casing. The 1048 296

locking ring on the thrust bearing keeper nut, both bearings, the mechanical seal and the impeller were all replaced in the course of repairs.

A manual rod run-in was initiated on November 27, when the reg blade digital position indication did not respond to regulating blade movement; the regulating rod circuitry was in automatic at the time. While the reactor was shutdown, the regulating rod position indicator was corrected by tight-ening the drive sprocket and checking regulating rod function switches at the proper positions.

Work on Beamport "B" SANS Experiment continued in November with the installation of the vacuum chamber for SANS.

DECEMBER 1978 The reactor was operated continuously during December, with the following exceptions: two maintenance shutdowns on December 4 and 18; twelve scheduled shutdowns for flux trap sample changes; one scheduled shutdown to repair the outer airlock door bottom guide bearings; and three unscheduled shutdowns whose dates and descriptions follow.

On December 19, the reactor was shutdown by manual rod run-in during a

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reactor startup when the Nuclear Instrumentation indicated power was checked against a heat balance at 5 MW and N.I. Channel 6 was not indicating. This was reported to the NRC Director of Nuclear Reactor Regulations in a letter dated January 15, 1979. The inability to adjust the Channel 6 indication was found to be due to a loose amphenol connector.

On December 21, a rod not in conta'.c with magnet rod run-in occur.ed, due to bumping the counterweight of rod "D" sith a sample, during a sample handling evolution.

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s On December 24, the reactor was shutdown by manual rod run-in to repair a ruptured fire main on the north side of the Reactor Laboratory Building, which required isolating the emergency pool fill supply line to complete the repair.

The first two fuel elements from Atomics International arrived in December. These elements were loaded in the core on December 4 and have

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performed satisfactorily. Additionally, a significant improvement was made in the pool heat exchangers cooling capacity. The secondary chemist, Steve Hughes, was able to achieve this by injecting air into the secondary coolant line at the inlet to the heat exchangers. The air-caused turbulance in the secondary side of the heat exchangers and resulted in the removal of much of the deposited dirt that was fouling and restricting secondary flow. Efforts are in progress to permanently install an air line to the secondary inlet to the pool heat exchangers to permit a regularly scheduled air injection as

_ part of a preventive maintenance schedule to maintain as high a heat exchanger capacity as possible.

• JANUARY 1979 The reactor was operated continuously during January, with the following exceptions: three maintenance shutdowns on January 8, 15, and 29; thirteen scheduled shutdowns for flux trap sample changes, and six unscheduled shutdowns whose dates and descriptions follow.

E On January 4, the reactor scrammed due to pool loop low flow. The cause of the scram was attributed to bumping the pool flow Gemac unit, while re-placing the panel protective plastic cover where it is located.

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A Channel 4 high power rod run-in occurred on January 10, due to an operator failing to switch to a higher range on the Channel 4 switch when requi red.

On January 13, the reactor scrammed due to a loss of electrical power to the facility. This loss of electrical power was verified by the Uni-versity Power Plant.

On January 16, the reactor scrammed due to high power on Channel 6.

The scram was caused by a failure of the voltage regulator module in the Channel 6 drawer. 1he voltage regulator was replaced, the Channel 6 drawer was checked and operations were continued.

A pool loop low flow scram occurred on January 24. Th+ scram was due to the loss of a pool pump, P508B, which tripped while the electronic technicians were changing the open/ closed indicating light bulb on the P508B breaker at MCC No. 5.

On January 28, the reactor was manually scrammed when Channel 6 indi-cation dropped from 101.5% to 82%, with no cr .esponding change in power indications on any other channel. The decrease in Channel 6 indication was found to be due to a faulty DC amplifier. The DC amplifier was replaced, the Channel 6 drawer was checked and operations were continued.

Messrs. J. L. Belanger and G. M. Christoffer, N.R.C. Region III Inspectors,

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conducted a facility security inspection from January 22 to January 24.

FEBRUARY 1979 The reactor was operated continuously during February, with the following exceptions: two maintenance shutdowns on February 12 and 26; twelve scheduled shutdowns for flux trap sample changes; and one unscheduled shutdown.

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On February 8, the reactor was shutdown by manual rod run-in, due to a leak in the fire main supply to the reactor facility. Technical Speci-fications require that emergency pool fill capability be available when the reactor is operating and it is supplied by the fire main. This leak was repaired by the Physical Plant and the reactor returned to operation.

A new bouyant fuel handling tool developed by Jim Tunink was tested and used for performing a refueling in February. The tool performed well and will allow greater flexibility in refueling; since it permits refueling at normal pool levels, instead of at the refuel bridge level. This reduces radiation exposure during refueling significantly and eliminates the physical strain of handling 35 pounds at arm's length.

One maintenance day was devoted to performing reactivity verifications of shim blade "A" (RTP-11), the regulating rod (RTP-5), and various flux trap loadings (RTP-6).

Messrs. A. G. Finley and J. P. Patterson, N.R.C. Region III Inspectors, conducted a facility SNM Control and Accountability Inspection from February 21 to February 23.

MARCH 1979 The reactor was operated continuously during March, with the following exceptions: three maintenance shutdowns on March 5, 19, and 26; fourteen scheduled shutdowns for flux trap sample changes; and two unscheduled shut-dos.ns whose dates and descriptions follow.

II On March 9,1979, the reactor was shutdown by manual rod run-in, to repair the inner airlock door support bracket. The Machine Shop completed repairs to the airlock door and the reactor was started up af ter refueling.

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On March 27, a pool valve 509 (Pool Isolation Valve) off open scram occurred, due to valve 509 closing as a result of a solenoid failure in I the air supply to valve 509 actuator. The lead solenoid on 529V (three way solenoid valve) was replaced and V509 was tested and found to operate satisfactorily.

The "X" fuel storage basket was removed from the reactor pool in March for modification to accept a newly designed emergency fuel storage fixture.

After the modification was completed the "X" basket was reinstalled in the deep pool and a test fit of the new fuel fixture was completed.

A portion of the March 19 maintenance day was devoted to performing the Nuclepore Test Procedure (RTP-16). The results of this test are being evaluated by Nuclepore at this time, in preparation for the extended Nuclepore Test which will involve operating the film irradiator for a week.

APRIL 1979 The reactor was operated continuously during April, with the following exceptions: two maintenance shutdowns on April 9 and 23; thirteen scheduled shutdowns for flux trap sample changes; and three unscheduled shutdowns whose dates and descriptions follow.

On April 24, the reactor scrammed due to high power Channel 4, as a result of a short circuit across the Channel 4 power supply which occurred when electronic technicians were troubleshooting the regulating blade auto-matic control circuits. The electronic technicians found a broken solder lead in the regulating blade automatic control circuits, repaired the lead and a short form precritical checkoff was completed, with Channel 4 indi-cating satisfactory.

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During the ensuing startup, the reactor scrammed at approximately 15" while still subcritical, due to blown master fuse, 2F1, on the reactor console front panel. It is believed that this fuse may have been damaged during the previous unscheduled shutdown, when the 115V power supplied to Channel 4 was shorted. The blown 2F1 fusa was replaced, and clamp-on ammeter readings were taken on all affected circuits, with all readings found to be normal . After performing a short form precritical checkoff, a hot reactor startup was commenced.

The reactor was started up, and at 10 MW, a Channel 4 high power rod run-in was received when attempting to place the reactor in automatic control at 10 MW, when the regulating rod drove out continuously. Reactor power of 10 MW was recovered and the reactor was operated in manual control while the electronic technicians investigated the regulating blade auto-matic control circuit. The problem in the regulating blade automatic control circuit was found to be a faulty component, and after checking the control system, the reactor was placed in automatic control at 10 MW.

Electronic technicians installed and calibrated a new console mounted digital indication for primary and pool flows, temperatures and DI system flows.

On April 23, the Containment Building Leak Rate Test (RTP-13) was conducted, the leak rate was 10.1 scfm less than the Technical Specification limit of 16.3 scfm.

MAY 1979 The reactor was operated continuously during May, with the following exceptions: two maintenance shutdowns on May 7 and May 21; sixteen 33 1048 302

scheduled shutdowns for flux trap sample changes; and four unscheduled shut-downs whose dates and descriptions follow.

The reactor scrammed due to high power Channel 4 during a reactor hot startup on May 3 when the reactor operator conducting the startup turned the Channel 4 range switch in the wrong direction.

The reactor scranmed due to a momentary dip in electrical power supplied to the facility on May 26. The University Power Plant was called and verified this electrical power transient.

On May 31, a Channel 5 high power rod run-in occurred when the regu-lating rod failed to  ; pond to an increasing power indication. Reactor power was restored to 10 MW in manual control while the electronic techni-cians were troubleshooting the regulating rod automatic control circuits.

The reason for the regulating rod not responding was traced to a faulty component in the servo amplifier circuit of the automatic control system.

Later the same day, May 31, while the reactor was at 10 MW in manual control with the electronic technicians returning the automatic control system to normal, Channel 4 indication failed down scale. A manual scram immediately initiated by the reactor operator and the electronic technicians found the Channel 4 picoammeter module defective. This module was replaced, the required precritical checkoff was performed and the reactor was returned to 10 MW in automatic control . No further problems have been experienced with the regulating roa automatic control system.

Modification 79-3 was completed by the electronic technicians in May.

This modification provides for splitting the electrical loads for nuclear instruments and rod position indications, so that the loss of fuse 2F1 or

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I 2F5 would not cause the loss of both indications, whicn are the two most direct indications that verify the reactor shutdown. The instrument panel fans were also removed from the Elgar line conditioner as part of this modification. Additionally, the electronic technicians replaced the molded retainers on all General Electric CR-120A relays with Valox re-tainers as specified in NRC Bulletin dated March 15, 1979. Control blade 5-3 was aligned on offset number 4 in May and installed in position "C".

Mr. N. E. Durby, N.R.C. Region III inspector, conducted a routine, unannounced inspection of the facility from May 14 to May 17.

JUNE 1979 The reactor was operated continuously during June, with the following exceptions: three maintenance shutdowns on June 4, 18, and 25; thirteen scheduled shutdowns for flux trap sample changes; and two unscheduled shutdowns whose dates and descriptions follow.

On June 29, the reactor was shutdown by manual scram due to failure of the personnel airlock doors. Electronic technicians found the breaker contacts on the outer airlock door highly pitted and corroded. The contacts were cleaned and the doors were placed back in service. During the sub-sequent startup, with the reactor critical but not yet at 10 MW, the outer airlock door failed again. This time the reactor was shutdown by manual rod run-in and the electronic technicians changed out the breaker for the airlock door, which was found to have an intermittent open in one phase.

Major maintenance items for June consisted of the replacement of cooling tower fan No.1 hub and blades; the continuation of RTP-16, Nuclepore Test Procedure, and the shipment of eight spent fuel elements to Savannah River

Processing Plant.

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Mr. C. H. Brown, N.R.C. Region III Inspector, conducted a routine unannounced inspection of Operating Records and Procedures from June 5 through June 8.

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SECTT.ON II I OPERATING PROCEDURE CHANGES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Standard Operating and Emergency Procedures during June 1979.

Throughout the year, minor changes were made via Standing Orders, These were incorporated into a Standard Operating Procedure revision that is now being reviewed before approval.

The Health Physics Manager conducted his annual review as required by the MURR Technical Specifications.

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g 1048 306 SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT Hazard Summary Report Addendum 4 Figure A.10 "Evar.uation/ Isolation System" was revised. The evacuation switch in room 269 was removed.

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I SECTION IV PLANT AND SYSTEM MODIFICATIONS August 1978 Modification 78-2: A deflector plate was atteched to offset mechanism "A" to prevent a sample holder striking the offset arm. Striking the off- '

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set arm will cause a reactor shutdown by dropping the control blade.

I Safety Analysis Summary: The deflecter plate does not affect the off-set method of operation in any way. ,

Modification 73-6: Due to bonding problems between blade cladding and edge cladding on control blades, the blade thickness was reduced from

.200 in. to .175 in. The edge cladding thickness remained at .250 in, which provides more material to weld the edge cladding to the blade.

I The minimum weight of Borcq-10 per unit area was incraased from

.0414 to .0418 gm/cm2 ar.d the neutron attenuation performance was improved due to more effective particle sizes of boron carbide.

Safety Analysis Summary: The new control blade meets the reactivity requirements of Technical Specification, therefore there is no change to the MURR safety analysis. The thicker cladding and better edge cladding weld make the blade less susceptible to blistering.

I Modification 76-12: The Regulating Blade Servo Amplifier was replaced with a solid state amplifier to eliminate the old amplifier tubes and to ,

make other circuit improvements.

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Safety Analysis Summary: This unit is designed to be more reliable in auto control of the reactor than the tube amplifier model. The con-sequences of an auto control failure are the same, i.e. a reactivity in-sertion of no more than 0.003 AK/K which can be safely tolerated.

r February 1979 Modification 79-2: The air operated fuel handling tool head was re-placed by one identical to the manual fuel tool and air cylinders added to increase buoyancy. These changes resulted in a lower man-rem exposure during refuelings.

Safety Analysis Summary: The modification does not involve an un-reviewed safety question as described ir. 10CFR50.59. The desigr. int upo-rates designs used in the two MURR fuel handling tools for over ten years.

May 1979 Modification 79-3: The neutron monitoring systaa and control rod indication were changed from being supplied through a common fuse 2F1 to being supplied by parallel fused power supplies. This eliminated the situation where a single fuse failure would secure power to both primary indications of a reactor shutdown.

_ Instrument panel fan - pewer supply was moved from Elgar line con-ditioner output to reduce conditioned loads.

Safety Analysis Summary: The modification does not involve an un-reviewed safety question as described in 10CFR50.59.

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SECTION V SPECIAL NUCLEAR MATERIAL ACTIVITIES

1. SNM Receipts: During the year, the MURR received fuel from Rockwell Int'l.

Energy Systems Group (Atomics International). A total of 18 elements were received. A natural U02 sphere was received from Battelle, 4/30/79, for use in the Engineering Department.

Grams Grams Date Shipper Elements U U-235 Remarks 11/30/78 Atomics Int'l. M01, M02 1,660.93 1,546.95 (a) 12,'It '78 Atomics Int'l . M03, M04, 3,322.03 3,094.16 (a)

M05, M06 1/26/79 Atomics Int'l. M07, M08, 3,322.47 3,094.52 (a)

M09, M010 4/18/79 Atomics Int'1. M0ll, M012, 3,322.73 3,094 74 (a)

M013, M014 6/22/79 Atomics Int'l. M015, M016, 3,321.33 3,093.45 (a)

M017, M018 (a) Receipt of new fuel elements.

2. SNM Shipments: One shipment of three fuel elements (350 gms each) to Atomics International for temporary storage. One shipment of eight spent fuel elements was sent to U.S.D.0.E. Savannah River Plant.

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Grams Grams Date Shipper Elements V U-235 Remarks 5/07/79 MURR 350F1, 3ECF3 1,112.39 1,036.19 (b) 350F4 6/25/79 MURR 775F49, 775F51, 5,414.56 4,725.53 (c) 775F67, 775F68, 775F72, 775F80, 775F81, 775F83 (b) femporary storage.

(c) Spent fuel for reprocessing.

3. Inspections: On January 22-24, 1979, a Physical Protection Inspection was conducted by Mr. J. L. Belanger and Ms. G. M. Christoffer of Region III, USNRC. No items of noncompliance were identified during the course of their inspection.

On February 21 23, 1979, a Special Nuclear Material Control and Accountability Inspection was conducted by Messrs. A. G. Finley and J. P. Patterson of Region III, USNRC. No items of noncompliance was identified as a result of this inspection.

4. SNM Inventory: As of 30 June 1979, the MURR financially responsible inventory was as follows:

Total U = 44,460.78 grams Total U-235 = 39,497.27 grams I

All of this material is physically located at the MURR. In addition, MURR has three 350 gram elements stored at Atomics International.

Total U = 1,112.39 grams Total U-235 = 1,036.19 grams Also MURR owns a total of 116 grams U and 37 grams U-235.

Fuel elements on hand have accumulated the following burnup as of 30 June 1979:

Fuel Element Accumulated Fuel Element Accumul ted Number MWD Number MWD 350F2 4.92 M01 107.14 775F55 146.89 M02 107.14 775F60 147.36 M03 75.38 775F62 146.26 M04 75.96 775F64 146.49 M05 75.38 775F65 146.71 M06 75.96 775F70 144.95 M07 69.80 775F71 144.95 M.08 54.68 775F73 147.92 M09 65.33 775F71 141.99 M010 54.68 775F75 146.40 M0ll 29.34 775F76 146.40 M012 29.03 775F77 146.89 M013 34.22 775F78 141.98 M014 23.99 775F79 139.06 M015 0 775F82 148.12 M016 0 775F84 148.12 M017 0 775F85 149.24 M018 0 775F86 139.42 775F87 145.42 775F88 146.12 775F89 129.41 775F90 144.01 775F91 146.55 775F92 147.80 775F93 129.41 775F94 144.01 775F95 148.54 775F96 148.38 775F97 148.95 775F98 120.50 775F99 148.12 775F100 143.98 775F101 148.85 775F102 142.87 775F103 142.87 775F104 143.98 775F105 139.62 775F106 139.62 775F107 123.78 775F108 123.78 775F109 123.46 775F110 112.08 775F111 l'2.18 775F112 108.03

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SECTION VI REACTOR PHYSICS ACTIVITIES

1. Fuel Utilization: During this period, the following elements reached their licensed burnup and were retired.

775F73 776F88 775F97 775F77 775F90 775F99 775F81 775F91 775F100 775F82 775F92 775F101 775F83 775F94 775F102 775F84 775F95 775F103 775F85 775F96 775F104 There was one initial critical experiment conducted during the past fiscal year for a core of eight new elements.

Core XX was initially tested on 3 July 1978. Due to requirements of having less than 5 kg of unirrediated fuel on hand at any one time, initial criti-calities are now conducted with six new elements or less as conditions dicticate.

Core XXI M01, 2 4 December 1978 M03, 4, 5, 6 8 January 1979 M07 9 March 1979 MO 9 19 March 1979 Core XXII M08, 10 26 March 1979 M0ll, 13 3 May 1979 M012 7 May 1979 M014 4 June 1979 M015, 16 (12 July 1979) Fiscal Year 1980

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2. Fuel Shipping: One spent fuel shipment of 8 elements departed the facility on 25 June 1979. The shipnent contained the following elements.

775F49 775F72 775F51 775F80 775F67 775F81 775F68 775F83

3. Fuel Procurement: At the present time, MURR fuel is being fabricated by Rockwell Int'l . Energy Systems Group of Canoga Park, California. This work is contracted with USD0E and administered by the Idaho Operations Office. Future plans include building up a 2-year inventory of fuel or greater with possible storage in Idaho.

4. Licensing Activities: The proposal submitted last year to increase the allowable Facility Gaseous and Particulate Release to levels allowed by 10 CFR is still pending. A license was granted for using G.E. Model 700 Shipping Cask for MURR spent fuel shipments. Amendment No. 9 was issued 23 March 1978 changing the inspection time interval for control blades such that every control blade is inspected every two years. Amendment No.10 was issued 13 July 1978 allowing MURR containnent building leak test to be performed at 1 psig using the makeup flow technique. Amendment No. 11 was issued 26 January 1979 incorporating a revision to the University of Misnouri Research Reactor (MURR) security plan.

5. Continuing Studies:

a. Incrersed loading of fuel elements.

b. Quality Assurance Programs for Shipping Casks.

c. Licensing National Lead Shipping Cask.

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1048 M4

SECTION VII

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Liquid Effluent 1-78 to 6-30-79*

Nuclide Amount (Ci)

H-3 via cooling tower drain 0.00167 H-3 0.124131 Na-24 0.000788 Sc-46 0.000908 Cr-51 0.001831

__ Mn-54 0.001174 Co-58 0.000319 Co-60 0.002583 Cu-64 0.000041 Zn-65 0.003303 Tc-99m 0.0000E0 In-113m 0.000694 Sn-113 0.000350 Sb-124 0.007468

• Except as noted material was released directly to sanitary sewer via waste tank system.

Stack Effluent 1. ; to 6-30-79 Nuclide 4 mount (Ci)

H-3 .8*

Na-24 .000009 Cl-38 .000321 Ar-41 2122.1 Cr-51 .000003 Mn-54 < .000001 Mn-56 .000005 Co-57 < .000001 Co-60 .000007 Cu-64 .000002 As-77 .000004 Br-82 .000151 1048 315

Stack Effluent 1-78 to 6:30-79 N_uclide Amount (Ci)

Sr-85 .000001 3 Kr-85m .000001 Kr-87 .000001 Kr-88 .000001 Y-92 .000147 Nb-95 .000001 Rh-106 .000023 Sn-ll3 .000001 In 113m .000001 In-114m .000001 Cd-115 .000063 .

1-128 .000026 I-130 .000003 I-1 31 .000788 Xe-131m .000024 Te-132 .000047 I-132 .000265 Xe-133 .000031 I-133 .001550 I-134 .000846 Xe-135 .000048 Xe-135m .000088 .

1-135 .001291 Cs-138 .000008 .

, Ba-139 .000022 Ba-140 < .000001 La-140 < .000001 Ce-144 .000054 Hz-181 < .000001 Au-198 < .000001 Hg-203 .000003  :

Bi-214 .000001 Pb-214 < .000001 Ra-226 .000002

• 0.30299 Ci H-3 evaporated to atmosphere via cooling tower in addition to H-3 release via exhaust stack. 104lB 316

SECTI0ft VIII

SUMMARY

OF Ef1VIR0fiMEf1TAL SURVEYS Environmental samples are collected twice yearly at nine '.ocations and i

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. The results are given in tne following tables.

_, Detection Limits Matrix Alpha Beta Gamma Tritius Water 0.2 pCi/l 2.5 pCi/l 0.04 pCi/l 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g vegetation

1. Sampling Date: 10/18/78 Determined Activity Concentration Sample Alpha Beta Gamma Tritium 1 V 14 <0.2 pCi/g 47.4 pC1/g <0.04 pCi/g <9.1 pCi/g 2 V 14 0.6 pCi/g 33.8 pCi/g <0.04 pCi/g <9.1 pCi/g 3 V 14 0.7 pCi/g 31.6 pCi/g <0.04 pCi/g <9.1 pCi/g 4 V 14 0.5 pCi/g 33.5 pCi/g <0.04 pCi/g <9.1 pCi/g 5 V 14 0.2 pCi/g 31.3 pCi/g <0.04 pCi/g <9.1 pCi/g

-m 6 V 14 <0.2 pCi/g 42.1 pCi/g <0.04 pCi/g <9.1 pCi/g 7 V 14 0.3 pCi/g 38.5 pCi/g <0.04 pCi/g <9.1 pCi/g 8 V 14 0.5 pCi/g 27.9 pCi/g <0.04 pCi/ g <9.1 pCi/g 9 V 14 <0.2 pCi/g 38.3 pCi/g <0.04 pCi/g <9.1 pCi/g

A Determinea Activity Concentration - continued Sample Alpha Beta Gama Tri tium 1 S 14 0.7 pCi/g 5.5 pCi/g <0.04 pCi/g <9.1 pCi/g 2 S 14 0.9 pCi/g 5.5 pCi/g <0.04 pCi/g <9.1 pCi/g 3 S 14 0.8 pCi/g 5.3 pCi/g <0.04 pCi/g <9.1 pCi/g 4 S 14 0.5 pCi/g 3.2 pCi/g 4.04 pCi/g <9.1 pCi/g 5 S 14 1.1 pCi/g 1.9 pCi/g <0.04 pCi/g <9.1 pCi/g 6 S 14 0.7 pCi/g 3.2 pCi/g <0.04 pCi/g <9.1 pCi/g 7514 0.7 pCi/g 5.0 pCi/g <0.04 pCi/g <9.1 pCi/g 8 S 14 3.2 pCi/g 9.7 pCi/g <0.04 pCi/g <9.1 pCi/g 9 S 14 0.4 pCi/g 41.2 pCi/g <0.04 pCi/g <9.1 pCi/g 4 W 14 0.6 pCi/l 6.7 pCi/l 4.04 pCi/1 <9.1 pCi/ml 6 W 14 <0.2 pCi/l 5.3 pCi/l <0.04 pCi/1 <9.1 pCi/ml 3

8 W 14 1.2 pCi/l 28.5 pC1/1 *l.03x10 pCi/l <9.1 pCi/ml 3

9 W 14 3.4 pCi/l 96.7 pCi/l *3.04c10 pCi/l <9.1 pCi/ml Gamma photo peak was observed and identified as I-131.

Verification letter from Health Physics Services relative to release of I-131 to sanitary sewer from University Medical Center, 10/16/78 through 10/18/78, in file.

Detection Limits Ma tri x Al pha Beta Gamma Tritium Water 0.2 pCi/l 2.5 pCi/l 0.04 pCi/l 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g vegetation

-2,. 1048 318 y _ . , _ _ _

2. Sampling Date: 4/30/79 Determined /ctivity Cencentration Sample Alpha Beta Gamma Tritium 1 V 15 <0.2 pCi/g 30.0 pCi/g <0.04 pCi/g <9.1 pCi/g 2 V 15 <0.2 pCi/g 23.7 pCi/g 4.04 pCi/g <9.1 pCi/g 3 V 15 <0.2 pCi/g 22.8 pCi/g <0.04 pCi/g <9.1 pCi/g 4 V 15 <0.2 pCi/g 25.9 pCi/g <0.04 pCi/g <9.1 pCi/g 5 V 15 <0.2 pCi/g 25.3 pCi/g <0.04 pCi/g <9.1 pCi/g 6 V 15 <0.2 pCi/g 32.4 pCi/g <0.04 pCi/g <9.1 pCi/g 7 V 15 <0.2 pCi/g 27.9 pCi/g <0.04 pCi/g <9.1 pCi/g 8 V 15 <0.2 pCi/g 18.0 pCi/g 4.04 pCi/g <9.1 pCi/g 9 V 15 <0.2 pCi/g 22.2 pCi/g <0.04 pCi/g <9.1 pCi/g 1 S 15 0.6 pCi/g 15.7 pCi/g <0.04 pCi/g 2 S 15 0.6 pCi/g 14.8 pCi/g <0.04 pCi/g 3 S 15 1.0 pCi/g 13.7 pCi/g <0.04 pCi/g 4 S 15 0.8 pCi/g 10.6 pCi/g <0.04 pCi/g 5 S 15 0.5 pCi/g 7.1 pCi/g <0.04 pCi/g 6 S 15 0.2 pCi/g 10.7 pCi/g <0.04 pCi/g 7 S 15 0.6 pCi/g 10.2 pCi/g <0.04 pCi/g 8 S 15 0.3 pCi/g 12.9 pCi/g <0.04 pCi/g 9 S15 0.2 pCi/g 11.6 pCi/g <0.04 pCi/g 4 W 15 <0.2 pCi/g 2.7 pCi/1 <0.04 pCi/l <9.1 pCi/ml 6 W 15 <0.2 pCi/g 3.7 pCi/l <0.04 pCi/l <9.1 pCi/ml 8 W 15 0.4 pCi/g 4.1 pCi/l <0.04 pCi/l <9.1 pCi/mi 9 W 15 <0.2 pCi/g 1.4 pCi/l <0.04 pCi/l <9.1 pCi/ml I

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SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS Personnel Monitoring (exposure in mrem) 1978 July August September October November December A B C D E B C D E B C D E B C D E B C D E B C D E G 46 6 42 110 49 1 20 20 42 1 80 80 42 1 43 43 42 3 23 30 35 2 15 20 U G) 13 7 309 920 12 6 192 490 15 5 160 290 14 4 310 760 15 6 135 350 10 5 76 110 G-Spare + 10 1 20 20 14 1 40 40 5 1 50 50 14 1 20 20 4 0 NA NA 14 1 20 20 0 G Spare + 4 2 40 50 2 3 100 130 0 4 375 1230 3 2 175 320 NA NA NA NA 0 2 120 130 H 59 49 89 340 57 43 117 230 59 42 113 340 65 36 139 570 56 39 96 430 i 54 42 112 280 U H 10 22 284 1030 5 24 467 2470 2 26 262 790 4 27 166 750 7 23 240 960 4 6 24 213 810 H-Spare + 8 1 10 10 7 1 50 50 12 1 20 20 5 3 90 130 6 0 NA NA 6 2 225 370 U H -Spare + 1 1 40 40 1 1 220 200 0 3 260 530 2 0 NA NA 0 2 80 120 0 1 240 240 D 2 59 87 448 5 54 78 467 9 49 47 160 4 51 80 282 3 56 77 230 5 54 69 235 GVIS* 1 1 10 10 1 1 70 70 0 0 NA NA 0 0 NA NA 0 0 NA NA 1 1 30 30 1979 January February March April May June G 45 2 55 80 47 1 40 40 47 1 20 20 52 2 25 30 51 1 20 20 48 0 NA NA U(G) 11 4 210 470 15 3 283 720 11 4 62 80 15 5 314 800 12 6 243 950 14 3 400 1110 G-Spare + 8 0 NA NA 4 0 NA NA 2 3 NA NA 16 0 NA NA 5 4 35 50 15 1 30 30 U (G )S pare + 2 2 60 90 2 0 NA NA 3 0 NA NA 0 0 NA NA 0 1 130 130 1 1 40 40 H 65 28 74 130 51 46 130 620 39 55 71 340 70 25 59 160 59 38 125 420 67 32 85 260 U(H) 9 21 136 490 3 29 310 1310 7 27 160 600 7 28 148 560 8 28 419 2280 12 25 186 560 H-Scare + 9 0 NA NA 7 1 60 60 1 4 60 70 3 0 NA NA 11 2 60 70 7 5 60 90 U(H)-Spare + 0 0 NA NA 0 2 130 210 0 2 90 110 0 1 40 40 0 0 NA NA 0 0 NA NA D 54 5 77 415 4 56 53 225 1 49 66 230 4 48 48 180 3 53 86 320 2 53 63 245 GVIS* 0 0 NA NA 0 0 NA NA 0 0 NA NA 0 0 NA NA 2 2 60 60 0 0 NA NA

~

c$pte: G = monthly beta-gama film badge Column Headings

.c: U(G) = monthly finger TLD A. Type of dosimeter Co H = biweekly beta-gama-neutron film badge B. Number reported as minimum U(H) = biweekly finger TLD C. Number reported with exposures above minimum u D = self-reader dosimeters D. Average of exposures above minimum N GVIS = G badge worn by visitor E. Single highest dosimeter reported c

• Measurable Exposures Recorded Only i

+Used for temporary workers, new workers w prior to issue of permanent, and replacement for lost badges

m Radiation and Contamination Surveys The followins table gives the number of surveys performed during Fy 78-79.

Radiation Contamination 272 193 Sixteen (16) Radiation Work Permits were issued during the year.

Miscellaneous Items Reactor Health Physics has added a full-time technician position and a half-time technician trainee position.

Approximately $20,000 in new monitoring equipmer:t has been added to the Reactor Health Physics inventory.

The facility effluent stack monitor was moved to a location more accessible for observation and service. The new location also has a more stable radiation background. An isokinetic sample probe was designed and installed in the effluent plenum to assure more accurate sampling of airborn particulates.

Formal surveys of laboratories were changed from monthly to quarterly because actual monitoring in laboratories increased due to the increase in work involving Health Physics on a daily basis. Daily swipe surveys of the facility floors continue to indicate cood control of radioactive materials.

k0h0 b -

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