ML20134M929

Univ of Missouri Research Reactor Annual Rept,1984-85

ML20134M929
Person / Time
Site:	University of Missouri-Columbia
Issue date:	06/30/1985
From:	Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO
To:	Thomas C Office of Nuclear Reactor Regulation
References
NUDOCS 8509040350
Download: ML20134M929 (51)

Text

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fI ll UNIVERSITY OF MISSOURI i RESEARCH REACTOR l',

ANNUAL REPORT

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1984-85 I

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UNIVERSITY OF ti!SSOURI

l I RESEARCH REACTOR FACILITY 1

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REACTOR OPERATIONS l ANNUAL REPORT AUGUST 1985 I

I Compiled by the Reactor Staf f I

Submitted by

%o Walter A. Meyer, Jr. l Acting Reactor Manager  ;

I Reviewed and Approved j

' d j'c D'r.Roberkh.Urugger '/ j ) 7/ (/// [( ,

t Director ,j,j I

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TABLE OF CONTENTS I Section Page Number I. REACTOR OPERATIONS

SUMMARY

................. 1-1 through I-12 I II. CHANGES TO THE STANDARD OPERATING PROCEDURES AND THE OPERATOR REQUALIFICATION PROGRAM .................................... 11-1 through 11-3 III. REVISIONS TO THE HAZARDS

SUMMARY

REPORT .... III-1 only I IV. PLANT AND SYSTEM MODIFICATIONS ............. IV-1 through IV-4 V. NEW TESTS AND EXPERIMENTS .................. V-1 only VI. SPECI AL NUCLEAR MATERI AL ACTIVITIES . . . . . . . . VI-1 through VI-3 VII. REACTOR PHYSICS ACTIVITIES ................. VII-1 through VII-3 VIII.

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT .............. VIII-1 through VIII-2 IX.

SUMMARY

OF ENVIRONMENTAL SURVEYS ........... IX-1 through IX-6 X.

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS ............................. X-1 through X-2 I ii

I SECTION I REACTOR OPERATIONS

SUMMARY

1 July 1984 through 30 June 1985 The following table and discussicn summarize reactor operations in the period 1 July 1984 through 30 June 1985.

Full Power Percent

• Date Full Power Hours Megawatt Days of Total Time of Schedule July 1984 695.6 290.39 93.49 104.71 Aug. 1984 687.3 286.90 92.38 103.46 Sep. 1984 669.1 278.80 92.93 104.08 Oc t. 1984 634.1 264.44 85.11 95.33 Nov. 1984 671.7 279.88 93.29 104.49 Dec. 1984 636.8 265.59 85.59** 105.51 Jan. 1985 661.9 275.80 88.97** 103.90 Feb. 1985 610.4 254.33 90.83 101.73 Mar. 1985 683.8 284,93 91.91 102.94 Apr. 1985 653.8 272.44 90.93 101.84 May 1985 684,1 285.07 91.95 102.98 June 1985 667.7 278.22 92.74 103.87 I Total for Year 7,956.3 3,316.79 90.83% of time for yr.

102.88% of 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.

• • MURR scheduled shutdowns accounting for 109 hours0.00126 days <br />0.0303 hours <br />1.802249e-4 weeks <br />4.14745e-5 months <br /> over the Christmas and New Years holidays.

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I JULY 1984 The reactor operated continuously during July with the following excep-tions: three shutdowns for refueling and/or flux trap changes; two shutdowns for maintenance; and three unscheduled shutdowns.

On July 3, the reactor scrammed due to an electrical power dip that was verified with the Power Plant. All systems functioned normally and the reactor was refueled and returned to normal operation.

On July 7, spurious secondary low sump cut-out signals caused the second-ary pumps to cycle. Reactor power was lowered by manual rod run-in to reduce the necessary cooling load. The source of the spurious low sump signals was found to be an intermittent contact in the sump float switch. This switch was repaired and no further problems have been experienced.

On July 12, a channel 4 high power scram occurred during a startup when the range switch was inadvertently turned the wrong way. The operator trainee was counseled in the proper use of the range switch and the reactor was returned to normal operation.

Major maintenance items for July included installing Modification 84-4 on offset "A"; and installing topaz irradiation facility over beamport "E".

I AUGUST 1984 The reactor operated continuously in August with the following exceptions:

four shutdowns for refueling and/or flux trap changes; two shutdowns for main-tenance; and one unscheduled shutdown.

On August 31, a reactor scram and isolation occurred due to high radiation at the reactor bridge level ARMS detector which was set to trip at 50 mr/hr.

This occurred when a maintenance tool was being removed from the pool, without having the bridge Area Radiation Monttor turned upscale. The tool was immedi-tely put back in the pool and reactor personnel evacuated the containment l

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building as per the containment isolation procedure. Health Physicists subse-quently surveyed the containment building and checked the radiation level of the maintenance tool to ensure no personnel had received an unexpectedly high radia-tion dose. The tool had a contact radiation level of 150 mrem /hr. The reactor was returned to normal operation.

The major maintenance activity for August involved repairing a tear in the gasket of the truck entry door. A routine safety inspection was performed August 27-30, by Region Ill inspector, K. R. Ridgway and two subcontractors, J. E. Hyder and C. C. Thomas, Jr.

I SEPTEMBER 1984 The reactor operated continuously during September with the following excep-tions: two shutdowns for refueling and/or flux trap changes; three shutdowns for maintenance; and two unscheduled shutdowns.

On September 13, a rod-run-in occurred when control rod "D" disengaged from its magnet during a routine shimming evolution. The anvil and magnet were in-spected and the alignment of the rod drive housing was adjusted. The reactor was then returned to normal operation.

On September 27, a power level interlock scram occurred when the control air solenoid coil for valve 507B shorted out, causing the valve to nove from its normally open position. The coil was replaced and the reactor was returned to normal operation.

Major maintenance items for September included replacing the control relay coil for pool cleanup pump P513B; repairing and reinserting the Nuclepore irradiator case.

OCTOBER 1984 The reactor operated continuously during October with the following excep-tions : three shutdowns for refueling and/or flux trap changes; five shutdowns for maintenance; and five unscheduled shutdowns.

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On October 5, a reactor loop high temperature scram occurred while an electronics technician was checking the primary TH MV/I ribbon cable connection.

The cable connection was suspected as a cause of small deviations in the primary TH readings. Electronics technicians subsequently replaced the millivolt trans-mitter, the RTD, and the terminal board cable assembly for reactor loop Tg (901B).

Compliance checks were completed satisfactorily and the reactor was returned to operation with no further problems.

On October 16, two separate scrams occurred due to momentary dips in elec-trical power which were verified by the Power Plant. The reactor was returned to normal operation after each incident.

On October 29, a channel 4 high power rod-run-in occurred during a reactor

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I startup when the operator failed to move the channel 4 range switch upscale at the l proper time. The rod-run-in was reset ano the startup resumed with no further problems. Proper operating procedures were discussed with the operator involved.

On October 31, the reactor scrammed due to a momentary power dip which was veri fied by the Power Plant. The reactor was refueled and returned to normal j

operati on.

Major maintenance activities for October included installing new offset "B";

replacing the millivolt transmitter, RTD, and terminal board cable assembly for primary TH (901B); shipping the old beryllium reflector for disposal; and shipping 16 spent fuel elements. ,

The reactor operated continuously during November with the following exceptions: three shutdowns for refueling and/or flux trap changes; four shut-downs for maintenance; and five unscheduled shutdowns.

On November 4, the reactor scrammed due to a momentary power dip which was verified by the Power Plant.

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On November 9, a power level interlock scram occurred when the master control 1

switch was accidentally bumped. All systems functioned normally and the reactor I was returned to operation.

On November 19, the reactor scrammed upon failure of N.1. channel #3 (intermediate range monitor). Electronics technicians replaced the detector  ;

and the power supply for this channel. The detector was tested satisfactorily and the reactor was returned to normal operation.

On November 24, the reactor experienced a scram due to what was thought to be a momentary power dip. However, this could not be verified with the Power Plant. All safety systems functioned normally and no discrepancies were noted in any related system. The reactor was refueled and returned to normal opera-ti on.

On November 27, the reactor scrammed due to a momentary pcwer dip which was verified by the Power Plant.

Major maintenance activities for November included shipping eight spent fuel elements; and replacing power supply and detector for IRM channel #3, DECEMBER 1984 The reactor operated continuously in December with the following exceptions:

four shutdowns for flux trap sample changes and/or refueling; two shutdowns for maintenance day; and two reactor shutdowns with the building secured for the holiday periods on December 24, 25, and 31. There were no unscheduled shutdowns.

Major maintenance activities for December included installing 100 ohm RTD's for pool Tc and TH ; and inserting a nuclear powered fluorescent centertube in Beamport "F".

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JANUARY 1985 The reactor operated continuously in January with the following exceptions:

three shutdowns for flux trap sample changes and/or refueling; two shutdowns for maintenance day; and four unscheduled shutdowns.

On January 10, a rod not in contact with magnet rod-run-in occurred three separate times when control rod "D" disengaged from its magnet during normal ,

reactor start-ups. The control rod guide tube was realigned, the anvil surface was cleaned, and the magnet was re-centered. The reactor was then returned to j normal operation.

On January 17, a rod not in contact with magnet rod-run-in occurred when rod "D" disengaged from its magnet during a normal reactor start-up. The guide I tube was realigned and a rod pull and drop test were performed satisfactorily.

During the next maintenance day, January 24, the blade full-in switch for rod "D" was shortened to relieve its contact pressure with the anvil, which was 1

suspected to be causing a misalignment when the magnet made up with the anvil.

This particular problem is believed to have caused the misalignments and sub- l sequent rod-run-ins on January 10.

The Emergency Plan for MURR was implemented on January 8,1985. The plan had been reviewed and approved by the Nuclear Regulatory Commission on July 12, 1984.

Major maintenance activities for January were removal of beamport "F" nuclear powered fluorescent centertube and installation of a slit centertube.

FEBRUARY 1985 The reactor operated continuously in February with the following exceptions:

three shutdowns for flux trap sample changes and/or refueling; two shutdowns for maintenance day; and three unscheduled shutdowns.

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During the period February 5-7, three Nuclear Regulatory Commission (NRC) inspectors for emergency planning visited the facility to review the implementa-tion of our emergency plan.

On February 9, the reactor was scrammed by what was thought to be a momen-tary loss of site power but which could not be verified by the power plant. On the subsequent hot start-up, the reactor scrammed due to a low pressure trip from pressure transmitter 944 (core discharge). Investigation of this second scram revealed that the actual flow was greater than the flow indication for primary loop B. The higher than normal flow rate produced a lower reactor dis-charge pressure which caused the signal to the 944 trip units to be much closer than normal to the trip set points. It is felt that a low fluctuation of the 944 signal reached the trip point, initiating the scram. This is believed to have caused the first scram as well. Primary loop B flow was reduced and the reactor was returned to operation. During the following maintenance shutdown, the compliance check for loop B reactor flow (CP-48) determined the flow trip setpoints to be in compliance. The transmitter was replaced due to the low flow indication.

On. February 20, a 12% drop from pennal indication occurred on Nuclear Instrumentation channel 6 which lasted 17 minutes. This reduced indication was determined to provide a 126% full power scram for channel 6 which is less con-servative than the technical specification of 125% of full power. The scram setpoints for channel 4 and channel 5 would have provided a reactor scram at 120% of full power if a high power transient had occurred. A letter of expla-nation and the corrective measures taken was sent to the NRC Director of Nuclear Reactor Regulation dated March 18, 1985.

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On February 21, a rod not in contact with magnet rod-run-in occurred when control rod "D" separated from its magnet during a routine shimming. The anvil and magnet were cleaned and realigned and the reactor was returned to operation.

l Major maintenance items for the month included repairing primary flow trans-I mitter (712E) for loop B and replacing primary demineralizer flow transmitter and power supply.

MARCH 1985 The reactor operated continuously in March with the following exceptions:

two shutdowns for refueling and flux trap changes; one shutdown for maintenance; and five unscheduled shutdowns.

On March 6, the reactor scrammed due to an electrical power dip which was verified by the Power Plant. This snutdown occurred just prior to a scheduled f l

maintenance shutdown and the maintenance schedule was completed before the  !

1 reactor was returned to normal operation.

On March 8, March 22, and March 28, rod-run-ins occurred when control rod "D" disengaged from its magnet during shimming. In each case, the housing, bracket, and magnet were realigned before the reactor was returned to normal operation.

On March 29, the reactor scrammed due to an electrical power dip which was verified by the Power Plant. The reactor was subsequently returned to normal operati on.

Mr. Gary Pirtle, an NRC inspector, conducted a safeguards inspection on March 4,1985 of reactor security and special nuclear materials; no items of noncompliance were identified.

Major maintenance items for March included performing the annual containment building leak rate check (RTP-13); replacing the truck entry door gasket and performing a modified containment building leak rate check; replacing the trip relays for pressure transmitters 944 A and B, and 943; and replacing the trip relays for RTD's 980 A and B.

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APRIL 1985 The reactor operated continuously in April, with the following exceptions:

two shutdowns for refueling and flux trap changes; two shutdowns for mainte-nance; and five unscheduled shutdowns.

On April 3, April 4, and April 8, rod-run-ins occurred when control rod "D" disengaged from its magnet. On April 3, this occurred spontaneously, with the cause suspected to be a bad solder joint on the amphenol connector (which was subsequently repaired). On April 4, and April 8, this occurred while shimming rod "D". Misalignment of the rod drive housing was the suspected cause. On April 18, the offset for rod "D" was replaced. The lower rod drive housing was aligned and shimmed and no further problems of this type have occurred.

On April 7, a rod not in contact with magnet rod-run-in occurred when the magnet current for rod "D" was inadvertently turned down. The magnet current adjusting switch for rod "D" was bumped while pushing a chair between the reactor console and the front panel. The auxiliary operator responsible was counseled on the need to exercise caution when passing equipment by the front panel. The reactor was subsequently refueled and returned to normal operation.

On April 23, a manual scram was initiated immediately upon discovery of the failure of the inner personnel airlock door. Both airlock doors remained closed with their sealing gaskets inflated until the reactor was shutdown. The door malfunctioned when the timing sequence chain jumped its sprocket during a door cycling event. This was repaired and tested satisfactorily. The reactor was refueled and returned to normal operation.

W. B. Grant, Region III NRC Inspector, conducted a routine safety inspection from April 16-18, in the areas of radiation protection and radwaste management.

No items of noncompliance were identified.

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Major maintenance items for April included changing out offset "D"; instal-ling new hold-down bolt insert on offset "D" (Modification Package 84-4); in- I stalling new photoelectric cells on control rod "D" for the rod drop timer and the blade full in indications (Modification Package 85-2); and repairing the timing sequence chain on the inner airlock door.

MAY 1985 The reactor operated continuously during May with the following exceptions:

three shutdowns for refueling and flux trap changes; three shutdowns for mainte-nance; and three unscheduled shutdowns.

'I On May 2, the reactor was scrammed during a reactor startup by a static charge buildup on the Channel 4 range switch. The switch was cycled to dis-charge any remaining static buildup and the reactor was returned to normal oper-ation.

On May 19, a manual rod-run-in was initiated when the drive chain for the l

regulating blade height indication failed. The chain was repaired and a compli-ance check was performed satisfactorily. The reactor was refueled and returned to normal operation. Reactor operation with the fai1ed position indicator, which actuates the regulating blade less than 10% withdrawn RRI, was a deviation from Technical Speci fication 3.4.c. This deviation was reported to the NRC by an LER dated May 31, 1985.

On May 23, a high power rod-run-in occurred when a reactor operator trainee failed to rotate the channel 4 range selector switch upscale at the proper time during a normal reactor startup. The rod-run-in was reset and the operator was counseled on the proper operating procedures. The startup then continued normal-ly with no further problems.

Kenneth Ridgway and Edward Schweibinz, Region III NRC Inspectors, conducted an Operations Audit from May 22 through May 24. No items of noncompliance were j i denti fi ed.

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I Major maintenance items for May included the change-out of offset "A"; re-placing the D. C. amplifier on N.1. channel 5; and repairing a broken wire on control rod "A" dri ve mechani sm.

JUNE 1985 The reactor operated continuously during June with the following exceptions:

two shutdowns for refueling and flux trap changes; two shutdowns for maintenance; three unscheduled shutdowns.

On June 8, the reactor scrammed due to the failure of the nuclear instrument detector for channel number two (intermediate range monitor). The D. C. ampli-fier, fuse F-2, and the detector were replaced and the channel was tested satis-factorily. The failure of channel two was caused by embrittlement of the cable insulation and subsequent current leakage in the detector leads. The reactor was refueled and returned to operation.

On June 17, a reactor scram and isolation occurred as a result of a momen-I tary loss of electrical power that was verified by the Power Plant. The reactor was refueled and retcrned to normal operation.

On June 25, a power level interlock scram occurred when the solenoid for valve 546( A) failed. Valve 546( A) is one of the two (redundant) in-pool con-vection cooling loop valves which open on loss of primary coolant. The failure of the solenoid caused the valve to fail open which permitted coolant bypass flow around the core. The resulting reduction in core flow was sensed by core AP pressure sensor 929, which immediately initiated the scram. The primary and pool coolant systems remained in operation, providing normal cooling after the shut-down. The solenoid was replaced and the reactor was refueled and returned to normal operation.

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I Major maintenance items for June included: repositioning of the dash pot piston on rod "D" down 1/8 inch; replacing the D. C. ampli fier, fuse F-2, and N. I. detector #2; installing new check sources in the north, south, and west beamport floor area radiation monitors; and replacing valve 546(A) solenoid.

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SECTION Il CHANGES TO THE STANDARD OPERATING PROCEDURES AND THE OPERATOR REQUALIFICATION PROGRAM A. Operating Procedure Changes To Revised October 1981 Manual.

As required by the MURR Technical Specifications, the Acting Reactor Manager reviewed and approved the Standard Operating and Emergency Procedures (50P).

There has been one revision (#18) made to the Revised October 1981 manual during the past year. This revision is contained in this section with the part of each page that was revised marked on the right side of the page by a bracket (]).

B. Operator Requalification Program Changes.

Two changes were made to the operator requalification program to clarify the use of the performance evaluation forms. The supervisor who should per-form the evaluation for each licensed operator is defined more clearly. The performance evaluation sheet was modified to allow evaluation of an operator's performance during reactivity manipulations and performance under emergency conditions at separate times. This will allow the supervisor to impose emer-gency scenarios to test an operator's responses to emergencies not limited to those associated with reactivity manipulations.

These changes are consistent with 10 CRF 50.54 (1-1) since they do not involve a change in the scope of the operator requalification program, the time allotted for completion of the program, or decrease the frequency in t

I conducting different parts of the program.

The changes to the operator requalification program are contained in this I

section with the part of each page that was changed marked on the right side of the page by a bracket (3). 77_y I

REVISION NUMBER 18 TO OCTOBER 1981 $ANUAL l

Page Number Date Revised SOP /VIII-11a 3/12/85 SOP /VIII-11b 3/12/85 SOP /VIII-51 3/12/85 SOP /VIII-52 3/12/85 SOP /A-8a 3/4/85 SOP /A-8b 3/4/85 SOP /A-16a 3/4/85 I

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I F. 1. Natural uranium;

2. Special nuclear materials as defined in Title 10, Part I 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, Kr. Xe, and P; 4 Compounds: NH4 NO 3 , CaC 2 , Ca0, perchlorates, perman-ganates, Na20 , and Na20 2;

5. Materials which chemically react with water to produce undesirable quantities of heat and pressure; I 6. Any explosive, flammable, combustible, or toxic materials.

E. Capsules may be run shielded with cadmium or boron (as ]

boron, BC, or BN) but weight and time are restricted due to the heat generated and their reactivity effect on 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 addition 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.

l 2. Cadmium shielded capsules: ]

l , a. 5 or less grams of cadmium may be run for up to ]

l 30 minutes.

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b. 50 or less grams of cadmium may be run for up to ]

l 10 seconds in row 1 or 20 seconds in row 2.

3. Boron shielded capsules:

I NOTE: The weight limit is only on the boron, i.e.,

the carbon weight in BC does count towards the

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weight limit.

3/12/85 App'd 50P/VIII-11a I Rev.

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D. 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) meters per minute.

F. Turn off drive motor. Leave speed set at running speed.

G. Turn of lamp.

I H. Log entry.

I 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 Room.

3. Disconnect air supply line on thermal column door at the I snap fitting.

4. Verify Neutron Radiograph rotating aperture drive shaft 3 pulled back and disconnected. ]

5. Preparation of Nuclepare Case:

A. Decouple Nuclepore take-up shaft.

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 lif ting rig and move to south side of the platform using the building crane.)

D. Decouple Nuclepore drive shaft.

l E. Decouple Nuclepore rabbit drive. (NOTE: Remove i

rubber grammet and store.)

F. Secure air to the Nuclepore equipment.

l G. Disconnect PVC air lines to the drive roll.

6. Unstack shielding as necessary to allow free movement of the door.

I 7. Plug in thermal column door drive motors (2).

Rev. 3/12/85 App'd SOP /VIII-51 r -

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8. Back out thermal column door approximately six (6) inches.

9. Disconnect four (4) PVC lines connected to the top of the Nuclepore Irradiator Case.

10. 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.

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 l cleared in the Control Room.

l S. Verify Neutron Radiograph rotating aperture drive shaft 3 will mate properly. 3 NOTE: DO NOT rotate aperture. 3

6. Unplug the thermal column door drive motors.

7. Restack shielding on the top of the thermal column.

8. Connect the Radiograph air supply line to the regulator assembly.

9. Install the platform deck plates.

10. Nuclepare 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.

Pin door fully shut.

E. Recouple take-up spline coupling.

F. Open Nuclepore air supply valve and reset all tension controls.

G. Test run film.

H. Place the experiment in its desired operational mode in accordance with approved procedures.

11. Inform operators of the system status.

Rev. 3/12/85 App'd ] SOP /VIII-52

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REACTOR ROUT 1NE PATROL Date:

1. Time of start of patrol.

2. Time and date all charts.

3. Check ARMS trip settings.

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4 Visual check of entire pool. l S. Anti-siphon tank pressure. 36 psig 2 3 psi

6. North iso coor seal press. 18-28 psig

7. South iso door seal press. 18-28 psig -

8. 5th level backup doors. Open -

9. 5th level detector reading. 0-3.5 mr/hr ,

10. 5th level trip point set. 3.5 mr/hr

11. 16" iso viv A air pressure. 45-55 psig

12. Emerg coinpress on standby. cg g open, 1

13. Containment hot sump pumps. Operable

14. Door 101 seal pressure. 18-28 psig

'15. 8P Floor Conditions normal. I

16. Fuel Vault Locked

17. Inner airlock door seal press, 18-28 psig

18. Outer airlock door seal press. 18-28 psig L 19. T-300 level. > 2000 gal.

20. T-301 level. < 6000 gal. I~

I 21. Labyrinth Sump Level < Alarm Pt.

22. R0 Unit Operate / Standby 3 Power ON

23. RO Unit Temp 24-28*C/ standby

24. RO Unit Pressure 190-200 psig/s tandby

25. EG Rm. (Batt. check Sun. mids.; Thermostat > 50'F (EG OP switch to Auto J Temp > 40*F (Gas j sight glass ) I,

( 26. T-300, 301 Room Thermostat > 55;F l i Thermostat > 40 F l On the first routine patrol of the day or the first patrol af ter a startup, crain all water from the anti-siphon system. If draining causes the pressure to drop significantly, return 7.0 the middle of the band (36 psig) and record the pressure here. If a condition or reading ]

is normal, enter a "/" (for conditions) or the reading in the applicable box. If the con- ]

dition is abnormal, enter the condition or reading and circle it. Explain all abnormal con- ]

ditions or readings in the remarks.

REMARKS:

l Rev. 3/a/85 App'd J /~M m 50P/A-8a

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27. Rm.114 Particulate filter & < 2.5" H 2O 1

28. External Daors Ibyn S $n dfdh '

29. CT basin water level. 5-10" ,

30. Acid day tank level. Visible '

31. CT sump pumps. Operable ,

32. P-pump (s) running.

33. Pump strainer d. -

0-7.0 psi 34 Discharge pressure. -

35. Pump strainer M. 0-7.0 psi .

36. Discharge pressure. ,

37. Tunnel sump pumps. Operable

38. WT booster fan. Running

39. Acid control and pH. fOy,j00g0 cc/ min p

40. Blowdown control /cond.

Q 7d . 2 b 2 . N

41. Fission Product Monitor Flow 95-105 cc/ min j

42. Viv control header pressure.90-120 psig ~l

43. Pressurizer N2supply press.90-100 psig 44 Check Rm. 114 from door.

45. gtg ilter "rea level" < 75% dark red

46. Seal trench. y~nhmpondays.

47. Full N2bottl es. Total > 3 I Ll

48. Bank A bottle press. > 250 psig l

49. Bank B bottle press. > 250 psig

50. Bank on service. A or B

51. N header pressure.

2 135-145 psi

52. Waste tank #3 level.

53. Waste tank #2 level.

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54. Waste tank fl level.

55. Doors to Ct, WT 's, Demin. l Lo:xed E Rm. 114 and CT Tunnel.

56. Time of Completion of Patrol.

57. Operator initials.

REMARKS: , . g Rev. 3/4/85 App'd (~/A SOP /A- S l

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Month Year D. I. WATER MAKEUP LOG (Fill in only if sending D.I. water.)

Time Conductivi ty Water Meter Pre- ]

Day S tart i Stoo R0 T-300 Start l Stop l Net Fil ter REMARKS ]

Uni t S tart i Stoo aP ]

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I I! lI Rev. 6/82 App'd #~ SOP /A-16b

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l REVISION NUMBER 1 TO ]

MURR REQUALIFICATION PROGRAM I SUBMITTED January 31, 1978 I Page Number Date Revised 5 3/20/85 APPENDIX A:

Performance Evaluation Form 3/20/85 I

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E Revised: 3/2f/85 Approved: ,M#f%

I 2.2 On-The-Job Training V

l This section of the program provides assurance that all operators will maintain competence in those major evolutions which can be performed by licensed operators only. The on-the-job requirements are outlined in the checklist in Appendix A.

i 2.3 Periodic Observation and Evaluation i I

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, Reactor Management will, on a continuing basis, observe and evaluate i the performance of all operators to maintain familiarity with the operator's i l

, competence in handling routine and emergency evolutions. This program i

implements the means of documenting the evaluations made by management.

I The Training Coordinator, Reactor Manager, Reactor Operations Engineer, j

i or Shift Supervisor will annually conduct a performance evaluation of all operators during one of their reactivity manipulations. The supervisor conducting the evaluation will complete an Operator Performance Evaluation Sheet (Appendix A). The evaluator will also discuss or simulate abnormal ]

or emergency conditions and grade the operator on his response to these conditions. Each operator's present supervisor fills out the final section ]

of the evaluation sheet as an overall appraisal of the operator's perfor- 3 mance during the time on the supervisor's shift. If the present supervisor 3 feels there has been insufficient time on his shift to make such an evalua- ]

tion, the previous supervisor will fill out the final section of the evalua- 3 tion sheet based- on performance -on the previous-shif t. 3 I s

Revised: 3/20/85 Approved: JM4, , "

MURR OPERATOR REQUALIFICATION PROGRAM PERFORMANCE EVALUATION FORM Operator's Name: Date:

i Evolution Performed:

Excel- Good Aver- Poor U n sa ti s-lent age factory l PERFORMANCE DURING REACTIVITY MANIPULATION: 3

1. Procedures - knowledge and understanding of

2. Console Log Entries - adequacy, completeness and legibility of entries.

3. Checksheets and Data Sheets - thoroughness in completing checklist, accuracy of and interpre-tation of data on data sheets.

4 Manipulation of Controls - proficiency in handling controls and positive approach to bandling the plant.

5. Use of Instrumentation - used all available instrumentation and properly interpreted same.

6. Awareness of Reactor Conditions - knowledge of plant conditions, understanding trends or abnormal indi-cations, response to changing conditions.

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VER~ALL P[~RFORMANCE : _ . . - - - - - - - _ . - - . _ _ _ _ - - _

]

hERFORMANCE UNDER ABNORMAL OR EMERGENCY CONDITIONS: ]

Immediate actions - recognized condition and took "l 1. immediate steps to put plant in safe condition.

2. Communications - communicated problem, took charge, initiated or directed corrective action.

l 3. Follow-up Actions - ability to recover plant.

OVERALL PERFORMANCE:

Abnormal or Emergency Cisndftions Imposed or Observed:

Comments and Recommendations:

Evaluator:

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~~~~~ ~~

~P FRATOR Oh SHIFT FiRFORMA~NC~E APMAI$~AL: ]

, Appraisal Period: From To

~ - ~ ~

" OVERALL PERFORMANCE: __F___~ J--~ l l

{ _

1 --

m

E Supervisor's Signature

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SECTION Ill I 1985 REVISIONS TO THE HAZARDS

SUMMARY

1 July 1984 through 30 June 1985 I There were no revisions to the Hazards Summary between July 1,1984 and June 30, 1985.

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SECTION IV I PLANT AND SYSTEM MODIFICATIONS 1 July 1984 through 30 June 1985 SEPTEMBER 1984 l l

Modi fication 84-7: This modification adds a manual blowdown valve to the i nitrogen bank system which allows the nitrogen bank to be bled down, creating a '

l l demand on the system and allowing the banks to switch from bank "A" to bank  !

I "B" manually.

This does not downgrade the system, but provides a simple way to switch t

from one bank to the other and test the switch-over pressure point for pre-ventive maintenance. l 0CTOBER 1984 Modi fication 84-4: This modification changes th: technique used to secure the offset mechanisms to the reflector tank pedestal. An aluminum insert is bolted into the reflector pedestal and then the offset holddown bolt is screwed into the insert to secure the offset mechanism.

This eliminates stainless-on-stainless threads which gall and cause op-erational maintenance problems. It does not change the final positioning and alignment of the offset. The strength of the aluminum insert is many times greater than the maximum stress that could be exerted during operation.

Modi fication 84-3: This modification changes the control room indica-tion for charging pump P533 and the conditions for the indication. The "0N" indication was changed to "AUT0" and will enable only if the following condi-tions are met:

I 1) Main power breaker at MCC5 is closed.

2) Room 114 lockout switch is unlocked.

3) Control power switch on MCC5 is in ' AUT0", and

4) Control room switch is in ' AUT0".

IV-1

This prevents a green light from being indicated for P533 when either the control room switch or control power switch on MCC5 is out of ' AUT0".

During charging, both the red "RUN" light and the green "AUT0" light will be on. When any of the four switches are out of position, both lights will be off.

This change enables the operator to more quickly determine that the charging pump control system is lined up for proper operation. It does not affect the operation of the primary water makeup system.

DECEMBER 1984 Modi fication 84-14: This modification replaced the 10 ohm RTD's in Pool Tc and Pool Th with 100 ohm RTD's. The 100 ohm RTD's provide a .227 ohm / F change over the temperature range of 0*F to 200 F, where the 10 ohm RTD's provided a .0218 ohm / F change over this range. The increased ohm /*F obtained by using the 100 ohm RTD's makes the temperature indications less susceptible to variations due to small resistance changes, i.e. terminal board connections, wire connectors, etc. in the temperature indicating current loop.

This modification in no way affects the operation of the safety system.

The change is designed to enhance the accuracy of the temperature signal and its transmission to temperature indicating circuitry.

APRIL 1985 Modi fication 85-1: This modification to the exhaust fan system ensures that the axhaust fan running prior to a loss of site power is the fan that re-starts when the emergency generator picks up the emergency load. This takes advantage of the fan coast down and reduces the starting current on the emergency generator.

IV-2

Modi fication 85-2: This modification, installed first on the Rod "D" housing, replaced both the " blade full in" and rod drop reed switch with photo-electric activated switches and circuitry.

The " blade full in" indication had been actuated by a spring arm style microswitch being moved by the offset pull rod anvil. This was suspected to have created an alignment problem between the anvil and magnet which resulted in unscheduled reactor shutdowns when the anvil would contact the upper guide l

tube.

Each control blade travel drop time is measured from full out to 80%

full in. A magnetic reed switch had been used as the disconnect to stop the timers. Alignment of the magnet located in the pull rod and the reed switch located on the outside of the upper guide tube was critical and any misalign-ment greater than 1/4" would require a realignment before the drop time could be obtained.

The reliability of this modification has been proven by prior testing.

Rod "A" will have this modification installed in May 1985. Rods "B" and "C" will have this modification installed when their offset mechanisms are changed out on their regular schedule.

MAY 1985 Modification 85-4: This modification changes the offset "A" blade arm design, giving a 3/4" step in the arm. The change to the blade arm will allow for clearance of the relocated pneumatic tubes. This was done in an effort to maximize and create reflector sample irradiation facilities. To do this, the pneumatic tube ends will be relocated from the G-1 and G-2 positions (north side of pool) to a special graphite element adjacent to Beamport "A" (south side of pool).

IV-3 I

I Two new blade arms were constructed and will be cycled in service for offset A" at the biennial preventive maintenance. Since the load created by the control blade is vertical, the side load created by the stepped arm will have negligible effect on rod drop times. Operation of the offset and control blade remain as existing.

I flodification 85-5: This modification installed a 1/8" aluminum shim plate between the reflector tank pedestal and of fset "A" base. This was neces-sary due to one of the offset "A" locating pins being galled. The offset lacked approximately 1/8" from setting full down on the pedestal.

The shim plate was drilled with 2-1/8" holes to permit adequate pin clearance. The shim plate gives a flat surface on which the off set is mcunted so that the blade will not tilt in its groove or come in contact with the pressure vessel.

Operation of the offset assembly does not change and this change does not effect the drop times or compliance requirements.

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I SECTION V NEW TESTS AND EXPERIMENTS 1 July 1984 through 30 June 1985 I New experimental programs during this period are as follows:

RUR-243 Experimenter: J. Steven Morris / Jim Carni Description : An addenum was added to the RUR to include neutron activation analysis of small arms propellant samples.

RUR-247 Experimenter: W. Yelon/H. Kaiser

Description:

An addendum was added to the RUR to include the use of U-235 and Pu-239 samples as phase shifters on Beamport B.

RUR-264 Experimenter: Don Alger

Description:

The RUR was revised to broaden the scope of the applications of neutron radiographic techniques in research, education and service.

RUR-265 Experimenter: Mark Prelas

Description:

An addendum was added to the RUR to include the measurement of ultraviolet fluorescence production efficiencies of Xenon gas at low power levels.

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I V-1

I SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1984 through 30 June 1985

1. SNM Receipts: A total of 16 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia. These had been fabricated by Atomics International, Canoga Park, California, and shipped to B & W after December, 1982. B & W is holding 5 elements, serial numbers M0145 through M0149. Shipment of these to MURR will be completed in 1985.

Grams Grams Shipper Elements V U-235 B&W M0132, M0133, M0134, M0135, M0136, M0137, 13,272 12,363 M0138, M0140, M0141, M0142, M0143, M0144, M0200, M0201, M0202, M0203

2. SNM Shipments: A total of 24 spent fuel elements were shipped to Westinghouse Idaho Nuclear Company, Inc., Idaho Falls, Idaho for reprocess-ing.

I Shipper Elements Grans U

Grams U-235 MURR M073, M075, M076, M079, M082, M090, M091, 16,221 14,162 M092, M093, M094, M095, M096, M097, M098, M099, M0101, M0118, M0119, M0120, M0121, M0151, M0153, M0158, M0159

3. Inspections : A routine safeguards inspection was conducted by the Nuclear Regulatory Commission (NRC), Region III office, on 4-7 and 11 March 1985.

MURR Special Nuclear Material Control Procedures were reviewed and found ade-equate to enable MURR to comply with 10CFR70.51(c) requirements (accounting procedures for SNM in possession). Uranium ; .1up calculations were found in agreement with NRC 742 Material Balan w %or s . Shipping and receiving procedures and records were found adequate and NRC 741 Nuclear Material I

VI-1 I .

I Transaction Reports were found adequately documented and properly filed with NRC. Internal fuel transfers and storage records were reviewed. Inventory of fuel and non-fuel material was physically identified and no discrepancies in inventory records were noted. By letters from NRC, Region III, dated 26 March 1985, no items of noncompliance with NRC requirements were identi-fied during the course of these inspections.

4. SNM Inventory: As of 30 June 1985, MURR was financially responsible for the I following DOE owned amounts:

Total U = 40,647 grams Total U-235 = 36,147 grams I Included in these totals are 36 grams of U and 34 grams of U-235 non-fuel, j 00E owned. In addition to these totals, MURR owns 162 grams of U and 79 I

grams of U-235. All of this material is physically located at the MURR.

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VI-2 I

Fuel elements on hand have accumulated the following burnup as of 30 June 1985: l Fuel Element Accumulated Fuel Element Accumulated Fuel Element Accumulated Number Megawatt Days Nunber Megawatt Days Number Megawatt Days 122.78 M0117 98.27 M0141 0 M058 M070 149.03 M0122 133.10 M0142 40.41 l 147.86 M0123 147.64 M0143 0 M077 M088 146.99 M0124 144.84 M0144 40.41 M0100 145.96 M0125 135.90 M0150 147.82 M0102 145.82 M0126 148.53 M0152 147.82 M0103 122.78 M0127 148.53 M0154 149.01 M0104 145.82 M0128 145.17 M0155 148.59 M0105 138.04 M0129 149.28 M0156 146.76 M0106 129.27 M0130 145.17 M0157 148.59 I M0107 138.04 129.27 M0131 f10132 149.28 107.73 M0160 M0161 147.64 148.36 M0108 M0109 107.90 M0133 59.50 M0162 147.64 M0111 107.90 M0134 107.73 M0164 148.36 M0112 99.38 M0135 59.50 M0165 146.99 M0113 95.82 110136 87.35 M0200 9.61 M0114 99.38 M0137 57.84 M0201 6.56 M0115 95.82 M0138 87.35 M0202 9.61 M0116 98.27 M0140 57.84 M0203 6.56 Average 8urnup = 110.13 t1WD I

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I SECTION VII

( REACTOR PHYSICS ACTIVITIES 1 July 1984 through 30 June 1985

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

I Serial Number Core Designation Date Last Used MWDs I M070 M077 M088 A-51 A-52 A-63 10-22-84 10-25-84 12-31-84 149.03 147.86 146.99 I M0102 M0104 M0123 85-20 85-20 85-15 4-25-85 4-25-85 4-07-85 145.82 145.82 147.64 I M0124 M0126 M0127 85-15 85-1 85-1 4-07-85 1 17-85 1-17-85 144.84 148.53 148.53 M0128 85-20 4-25-85 145.17 I M0129 M0130 85-6 85-20 85-6 2-14-85 4-25-85 149.28 145.17 M0131 2-14-85 149.28 I M0150 M0152 M0154 A-61 A-61 A-51 12-13-84 12-13-84 10-22-84 147.82 147.82 149.01 I M0155 M0156 M0157 A-37 A-52 A-37 7-26-84 10-25-84 7-26-84 148.59 146.76 148.59 M0160 A-59 11-29-84 147.64 M0161 A-60 12-06-84 148.36 M0162 A-59 11-29-84 147.64 M0164 A-60 12-06-84 148.36 M0165 A-63 12-31-84 146.99 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel elements of which only the initial critical fuel element serial numbers are listed in the following table. To increase operating efficiency, fuel ele-ments are used in mixed core loadings. Therefore, a fuel element fabrication core number it different from its core load number.

VII-1 I

Fabrication Seri al Core Load Ini ti al Core No. No. Desi gnati on Operating Date 34 M0112 A-37 7-19-84 7-19-84 I 34 34 34 M0114 M0113 M0115 A-37 A-42 A-42 8-23-84 8-23-84 34 M0116 A-54 10-29-84 34 M0117 A-54 10-29-84 36 M0132 A-55 10-31-84 36 M0134 A-55 10-31-84 36 M0133 A-63 12-20-84 37 M0135 A-63 12-20-84 37 M0136 85-1 1-10-85 37 M0138 85-1 1-10-85 37 M0137 85-11 3-14-85 37 M0140 85-11 3-14-85 37 M0142 85-20 4-23-85 38 M0144 85-20 4-23-85 41 M0200 85-30 6-13-85 41 M0202 85-30 6-13-85 41 M0201 85-32 6-20-85 41 M0203 85-32 6-20-85

2. Fuel Shipping: Twenty-four spent fuel elements were shipped from MURR to Westinghouse Idaho Nuclear Company, Inc., Idaho Falls, Idaho. The identi-fication numbers of these elements are:

M073 M091 M097 M0120 M075 M092 M098 M0121 M076 M093 M099 M0151 M079 M094 M0101 M0153 M082 M095 M0118 M0158 M090 M096 M0119 M0159

3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia is MURR's current fuel assembly fabricator. This work is contracted with the U. S. Department of Energy and administered by E G & G Idaho, Idaho Falls, Idaho. As of 30 June 1985, four fuel assemblies fabricated by B & W had been received and used in cores at 10 MW.

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4. Licensing Activities: Changes to the MURR Physical Security Plan were submitted 30 May 1985; reviewed and found acceptable 17 June 1985. A re-quest for an increase in Special Nuclear Material Inventory under our Facility License submitted in December,1982 is pending. A revision to Technical Specifications 4.4.d requiring two operating parallel pool pumps submitted in February,1982 is pending.

5. Reactor Characteristic Measurements: Sixty-six refueling evolutions were completed. An excess reactivity verification was performed for each refuel-ing and the average excess reactivity was 2.7%. MURR Technical Specifica-ation 3.1(f) requires that the excess reactivity be less than 9.8%.

Reactivity measurements were performed for 19 evolutions to verify reactivity parameters for the flux trap. Shim blade calibrations were per-I formed at selected rod heights in support of reactivity measurements.

l A physical inspection of the following fuel elenents was performed to l

verify the operational parameters.

M0156 from Core A-39 during August 1984 M0150 from Core A-38 during October 1984 M0165 from Core A-40 during December 1984 All measurements were within operational requirements.

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SECTION VIII

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT l Sanitary Sewer Effluent l 1 July 1984 through 30 June 1985 Descending Order of Activity Released Nuclide Amount (Ci) Nucli de Amount (Ci) Nuclide Amount (Ci)

S35 1.33E-1 Sm153 1.51E-4 Re188 2.16E-5 H3 1.21E-1 Fe59 1.23E-4 Re186 1.91E-5 Co60 3.87E-2 Ag110M 1.91E-4 Au196 1.83E-5 Zn65 2.95E-2 Rb86 8.64E-5 Nb95 1.76E-5 Cs137 7.44E-3 CoS7 7.80E-5 Zr95 1.14E-5 Na24 3.70E-3 Sb122 7.26E-5 Au198 1.09E-5 Cr51 2.49E-3 Mn56 6.96E-5 I131 1.03E-5 Mn54 1.54E-3 Ba139 6.63E-5 Na22 1.01E-5 Sc46 1.10E-3 W187 6.45E-5 Se75 7.93E-6 Sb124 5.90E-4 Ni 65 6.16E-5 Sn113 7.35E-6 Sb125 5.89E-4 Zn69M 5.02E-5 Hg203 5.79E-6 As77 4.49E-4 Ba140 4.67E-5 Cs134 3.74E-6 1134 3.52E-4 Cel44 4.66E-5 La140 3.34E-6 Cd109 2.41E-4 Pa233 4.42E-5 Re188 3.12E-6 Ta182 2.36E-4 Ir192 4.39E-5 Hf181 2.88E-6 CoS8 2.05E-4 Ba133 3.21E-5 Tc99M 1.64E-6 VIII-1 I

l Stack Effluent 1 July 1984 through 30 June 1985 Descending Order of Activity Released i

Nuclide Amount (Ci)

Ar41 1.39E+3 I H3 1.01E+1 1133 2.48E-3 l 1135 1.91E-3 1131 1.51E-3 1134 1.13E-3 As77 5.20E-4 K40 4.91E-4

( 1132 4.64E-4 Xe135M 3.53E-4 C138 1.66E-4 l

I Ta182 1.21E-4 l

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i SECTION IX

SUMMARY

OF ENVIRONMENTAL SURVEYS I 1 July 1984 through 30 June 1985 I Environmental samples are collected two times per year at eight 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 three of the eight locations. Results of the samples are shown in the following tables.

Detection Limits Matri x Alpha Beta Gamma Tri ti um Water 0.2 pCi/1 2.5 pCi/1 0.04 pCi/1 9.1 pCi /ml I Soi1 and vegetation 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g

1. Sampled during October 1984.

Determined Radicactivity Levels Vegetation Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g Tri ti um pCi /g 1-V-26 <0.2 13.7 < 0.04 < 9.1 2-V-26 <0.2 18.0 < 0.04 < 9.1 3-V-26 <0.2 26.7 < 0.04 < 9.1 4-V-26 0.3 13.0 < 0.04 < 9.1 5-V-26 <0.2 13.5 < 0.04 < 9.1 6-V-26 <0.2 9.9 < 0.04 < 9.1 7-V-26 <0.2 17.8 < 0.04 ( 9.1 10-V-26 <0.2 24.2 < 0.04 < 9.1 I

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-[cw.>f Figure 1. MURR Environmental Program Sample Stations NOTE: September 1983 City sewerage plants at stations 8 and 9 closed. All waste water now processed at City Waste Treatment Facility at station 10.

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I I Determined Radicactivity Levels Soi l Samples Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 1-S-26 0.3 3.0 < 0.04 2-S-26 0.2 13.7 < 0.04 3-S-26 0.3 5.7 < 0.04 4-S-26 0.4 8.0 < 0.04 5-S-26 0.5 10.6 < 0.04 6-S-26 0.6 8.1 < 0.04 7-S-26 1.3 18.9 < 0.04 10-S-26 0.6 9.9 < 0.04 Determined Radicactivity Levels Water Samples Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 3 H (DCi /ml )

4-W-26 < 0.2 3.7 < 0.04 < 9.1 6-W-26 < 0.2 3.8 < 0.04 < 9.1 10-W-26 < 0.2 9.3 < 0.04 < 9.1

2. Samples during April 1985.

Detection Limits I Matrix Alpha Beta Gamma Tri ti um 1

Water 0.5 pCi/l 1.6 pct /l 150 pCi/l 11 pCi/ml Soi1* 0.3 pCi/g 0.9 pCi/g 3.2 pCi/g ----

l Vegetati on* 1.5 pCi /g 4.3 pCi/g 8.4 pCi /g 11 pCi/g

• Gamma and tritium analyses are based on wet weight; a and 8 analyses are based on dried weight.

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l Determined Radioactivity Levels I Vegetation Samples I Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) Tritium (pCi/g) )

1-V-27 < 1.5 20.4 < 8.4 < 11 l

2-V-27 < 1.5 25.3 9.6 < 11 l

3-V-27 < 1.5 22.9 < 8.4 < 11 4-V-27 < 1.5 19.3 < 8.4 < 11 5-V-27 < 1.5 14.0 < 8.4 < 11 6-V-27 < 1.5 29.7 < 8.4 < 11 7-V-27 < 1.5 21.8 < 8.4 < 11 10-V-27 < 1.5 19.9 < 8.4 < 11 I Determined Radioactivity Levels Soil Samples Sample Alpha (DCi/g) Beta (pCi/g) Gamma (pCi/g) 1-S-27 0.3 9.4 8.4 2-S-27 0.8 11.7 10.8 3-S-27 0.6 10.2 8.4 4-5-27 < 0.5 6.6 7.8

. 5-S-27 < 0.5 10.4 5.8 6-S-27 0.4 6.6 6.6 7-S-27 0.7 8.3 6.2 10-S-27 0.4 9.5 11.8 Determined Radioactivity Levels Water Samples Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) 3 H (pCi /ml )

4-W-27 < 0.5 3.9 < 150 < 11 6-W-27 < 0.5 3.8 < 150 < 11 10-W-27 < 0.5 7.2 < 150 < 11 No gamma peaks above background were observed in any of the gamma analyses.

IX-4

I Radiation and Contamination Surveys I The following table gives the number of surveys performed during FY 84-85.

Radi ati on Surface Contamination Ai r Sampies 366 277 253 Forty-four (44) Radiation Work Permits were issued during the year.

Miscellaneous items Eight revisions were made to Health Physics standard operating procedures.

A new procedure was added to provide for formal review of unusual unplanned radiation exposure. A second new Health Physics procedure was written to improve use of Radiation Work Permits for better exposure control.

Several actions were taken which contributed to the ALARA effort.

I a. A radwaste shipment in May reduced exposure to personnel who work in the basement an estimated 5 manrem per year.

b. A plexiglass beta shield was put in service to reduce exposure in a laboratory when handling low energy gamma emitters which decay by beta decay. An estimated manrem per year to upper body is saved by this unit.

c. A lead shield was installed on a glove box to reduce exposure to females processing low energy gamma emitters used for medical studi es. A quantitative value for exposure reduction is not available.

d. Smaller waste containers have been put in use in radiochemistry laboratories to reduce background both for personnel exposure reduction and a more accurate record of isotopes collected for disposal.

IX-5

i The radiation exposure rate in the reactor pool was reduced by e.

several hundred mrem /hr (dependent on location) when a used beryllium reflector and much activated metal, which had been stored in the pool, were shipped to a radwaste disposal site.

This reduces the potential exposure level should it be necessary to perform repair operations in the reactor pool.

Gross gamma analysis of environmental samples was improved by Reactor Chemistry to the extent that gamma analyses can be calculated for samples that do not exhibit distinct gamma peaks.

Environmental samples were collected around the University radwaste incinerator and analyzed to establish background data for the area.

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I IX-6

SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS 1 July 1984 through 30 June 1985

1. Largest single exposure and average exposure are expressed in millfrem.

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.

6. H. E. = Highest mrem reported for a single unit for the month.

l PERMANENT ISSUE FILM-BADGES Beta, Gamma, Neutron Wholebody Badges: (Six badges are area nonitors.)

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 63 66 70 51 60 81 73 80 64 74 67 69 AME 58 56 52 68 67 45 57 52 65 59 69 60 AE 108 91 103 423 101 117 125 139 116 130 123 106 l HE 210 240 320 680 320 190 260 260 330 350 410 360 Beta and Gamma Wholebody Badges: (Six badges are area monitors.) l JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 47 48 48 51 56 57 59 52 52 53 54 55 AME 4 5 2 5 9 6 7 7 8 5 8 6 AE 50 34 85 66 101 52 34 46 30 60 618 183 HE 80 90 150 140 450 90 60 110 70 200 4470 740 TLD Finger Rings:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 38 42 38 40 48 47 52 45 48 52 48 51 AME 35 32 35 44 44 38 40 42 37 34 38 37 AE 313 213 233 457 325 486 308 301 253 226 215 269 HE 1640 1250 1310 3160 4010 8170 2830 2390 1720 1670 1740 3470 X-1

(

m m m m m m m m m m m M SPARE ISSUE FILM-DADGES Beta, Gamma, Neutron Wholebody Badges:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 39 31 25 36 37 38 44 40 36 33 39 38 AME 5 17 18 13 9 6 3 6 10 12 7 10 AE 76 46 56 158 73 70 147 75 90 60 41 47 HE 200 140 280 560 160 120 380 140 300 130 150 140 Beta and Gamma Wholebody Badges:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 30 30 29 30 33 32 32 30 30 29 29 32 AME 3 3 3 1 0 0 0 4 1 3 3 1 AE 33 47 27 10 0 0 0 68 420 213 53 30 HE 40 80 40 10 0 0 0 120 420 510 130 30 TLD Finger Rings:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 16 11 20 12 18 17 19 14 11 13 18 19 AME 6 9 12 9 2 4 1 6 7 7 2 7 AE 195 210 167 338 170 88 30 198 229 217 785 263 HE 570 1030 610 1020 210 130 30 510 560 620 1490 540 00SIMETERS JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME O 3 2 6 2 2 8 6 5 6 4 4 AME 47 42 44 49 52 52 53 55 57 49 58 55 AE 77 57 64 114 87 87 72 80 79 79 79 02 HE 260 265 270 620 295 295 295 275 325 335 320 380 X-2

e .

Research Reactor Facility UNIVERSITY OF MISSOURI Research Park Columbia Missouri 65211 Mephone Q14) 882-42M August 26, 1985 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Cecil 0. Thomas, Chief Standardization & Special Projects Branch Division of Licensing

Reference:

Docket 50-186 University of 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 1 July 1984 through 30 June 1985. The The remaining twelve copies will be cent in the near future.

Sincerely,

{ ,

Wal t A. Meyer, r.

Acting Reactor Manager JCMK:vs Enclosures (2) cc w/ report: U.S. N.R.C. jj) .A c/o Document Mgmt. Br.

Washington, DC [ '# s f

9 COLUMBIA KANSAS CITY ROLLA ST. LOUIS an equal Opportunity institution