ML20151Q922

Univ of Missouri Research Reactor Operations Annual Rept 1987-1988

ML20151Q922
Person / Time
Site:	University of Missouri-Columbia
Issue date:	12/31/1988
From:	Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO
To:	Rubenstein L Office of Nuclear Reactor Regulation
References
NUDOCS 8808110333
Download: ML20151Q922 (111)

Text

- _. __ -- __ __ __ ---

l

! UNIVERSITY OF MISSOURI l l

UNIVERSITY OF MISSOURI RESEARCH REACTOR I

l I

l OPERATIONS ANNUAL REPORT l 1987-1988 i

i l

l Ri

• l -

gn"ni pq W N RESEARCH REACTOR FACILITY

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT AUGUST 1988 Compiled by the Reactor Staff Submitted by

'<k  ;

C. McKibben Reactor Manager

Reviewe and Appro  !

y l (3 ts' F. ober . rugger f l l

Director ,

i l

l s ,

TABLE OF CONTENTS

Section Page Number I. REACTOR OPERATIONS

SUMMARY

. . . . . . . . . . . . 1 I-11 II. CHANGES TO THE STANDARD OPERATING PROCEDURES . . . . . . . . . . . . . . . . . . . . 11 11-4 III. REVISIONS TO THE HAZARDS

SUMMARY

REPORT ..... III III-2 IV. PLANT AND SYSTEM MODIFICATIONS . . . . . . . . . . IV IV-3 V. NEW 1ESTS AND EXPERIMENTS ............ V-1 only VI. SPECIAL NUCLEAR MATERIAL ACTIVITIES ....... VI VI-2 VII. REACTOR PHYSICS ACTIVITIES . . . . . . . . . . . . VII VII-4 VIII.

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT . . . . . . . . . . . VI I I VI I I-2 IX.

SUMMARY

OF ENVIRONMENTAL SURVEYS . . . . . . . . . IX IX-10 X.

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS . . . . . . . . X X-2 i

i

?

ii

SECTION I REACTOR OPERATIONS

SUMMARY

1 July 1987 through 30 June 1988 The following table and discussion summarize reactor operations in the period 1 July 1987 through 30 June 1988.

i Full Power Percent

• Date Full Power Hours Megawatt Days of Total Time of Schedule _

July 1987 647.2 269.84 86.99 97.43 Aug. 1987 666.9 277.91 89.64 100.39 Sept.1987 670.5 279.49 93.12 104.30 Oct. 1987 657.5 274.26 88.26 98.84 Nov. 1987 620.9 259.26 86.24 96.58 Dec. 1987 655.7 273.07 88.13 98.71 Jan. 1988 669.7 279.13 90.01 100.82 l

Feb. 1988 601.8 250.81 86.47 96.84 Mar. 1988 676.8 282.07 90.97 101.88 Apr. 1988 661.4 275.66 91.99 103.03 May 1988 694.1 289.28 93.29 104.49 June 1988 669.3 278.93 92.56 104.11 l Total for Year 7891.8 3289.71 89.84% of 100,62% of time for sched, time i yr. at 10MW for yr, at 10 MW

• 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. i

Total time is the number of hours in a month or year. I There were 36 unscheduled shutdowns recorded during the year,1 July 1987 through 30 June, 1988. Of this number, there were ei 9 ht due to loss of electrical power (22%). This type of shutdown is usually characterized by only a momentary loss of electrical power to the safety system. The MURR is currently upgrading the

electrical supply system for reactor instrumentation. One feature will include an i

I

, I-1 j i - ~ _ _ _

f uninterruptible power supply which may reduce the scrams caused by a momentary loss of electrical power.

Six of the unscheduled shutdowns were due to NI drawer and/or detector failure. MURR is reviewing the past history of detector failures to try to deter-1 mine an optimal replacement frequency. The detector failures are, in most cases, failure of the detector cabling due to embrittlement or moisture in the drywell.

MURR is also evaluating the use of integrated cable NI detectors to alleviate the cable embrittlement problem.

Five of the unscheduled shutdowns were due to the Channel 4 range switch and/

or the relays the switch actuates in the picoammeter module. The Electronics Shop instituted a preventative maintenance procedure to clean the charnel 4 switch contacts on a periodic basis and over the last six months only one unscheduled shutdown has occurred due to this problem. l i

JULY 1987 The reactor operated continuously in July i the following exceptions: two i

4 shutdowns for scheduled maintenance; four shutdowns for refueling; and two unsched-uled shutdowns.

On July 25, a rod not in contact with magnet rod run-in occurred when control j blade "D" separated from its magnet during a routine shimming evolution. The j i

1 j magnet and anvil for this control blade were cleaned and the housing was realigned.

The reactor was subsequently refueled and returned to operation.

l On July 28, a rod not in contact with magnet rod run-in occurred when control blade "D" separated from its magnet while the reactor was operating in a steady 1

l s% ate condition. Subsequent electrical continuity checks of the magnet for blade l

"D" disclosed a cold solder connection. This was repaired and the reactor was

refueled and returned to normal operatio. with no further problems of this type. i This particular problem may have also caused the July 25 rod run-in.

I-2 l

Major maintenance items for July included: installing time delay circuits in the door-close/ gasket-inflation sequence 'of the motor operated isolation doors 504, 505, and 101; replacing the air regulator on the anti-siphon system; replacing the'OC power meter for control blade "0"; and performing oxide measurements on several MURR fuel elements.

AUGUST 1987 The reactor operated continuously in Augurt with the following exceptions:

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

On August 12, a rod not in contact with magnet rod run-in occurred when an operator accidentally bumped the drive housing for control blade "A", causing the blade to release from its magnet. This occurred during a routine sample handling evolution and the operator involved was instructed to be more careful. The reac-

, tor was subsequently refueled and returned to normal operation.  ;

1 On August 14, the reactor scrammed due to the loss of site power. This was l

verified by the power plant and a hot startup was completed when site power was I restored.

l On August 25, a pool loop valve 509 off open scram occurred. The cause was i found to be the failure of solenoid 529G which provides actuating air for pool isolation valve 509. The solenoid was replaced and the valve was tested satis-i factorily. The reactor was then refueled and returned to normal operation.

Major maintenance items for August included: replacing the source range detector; dumping depleted pool D. I. bed "K", loading new pool bed "B"; and replacing solenoid 529G (valve 509),

1 i SEPTEMBER 1987 The reactor operated continuously in September with the following exceptions: l two shutdowns for refueling; three shutdowns for maintenance; and five unsched-uled shutdowns.

1-3

k On September 13, the reactor was manually scrammed after an operator on rou-tine patrol reported noises that were later traced to the failure of the thrust bearing on primary pump 501A. The pump was replaced with a spare and tested sat-isfactorily. The reactor was refueled and returned to normal operation.

On September 14, a nuclear instrument channel #4 high power rod run-in occurred simultaneously with the clearing of the regulating blade 60% withdrawn annunciator alarm. No actual high power condition was indicated on any instru-mentation. The rod run-in was quickly reset and the reactor was returned to normal power. This particular electronic problem has occurred randomly in the past and an investigation by the electronic technicians led to replacement of the picoammeter module.

On September 15, a reactor scram and reactor containment isolation occurred as a result of a momentary ,ite electrical power interruptic1 All personnel 4

exited the containment building according to the containment isolation procedure.

Health physicists subsequently reentered the contairment building with monitoring

] equipment and discovered no abnormal readings. The electrical power interruption 2

was verified with the power plant and the reactor was refueled and returned to j operation.

. Later on September 15, the reactor again scrammed due to a momentary elec-trical power interruption. While a hot startup was being performed to recover from this incident, a channel #4 high power rod run-in occurred when an operator i failed to shift the wide range monitor switch at the proper time. The rod run-in was reset and the startup continued with no further problems. The operator in-volved was instructed to monitor the wide range monitor more closely during reac-tor startups.

Major maintenance items for September included: replacing primary pump 501A

t]ith a spare; replacing the oil bubbler on primary pump 501A; removing depleted pool D.I. bed "X" from service and placing new bed "B" on service.

1-4

-m ,- --- . ~ , - , - , - - , - - . - - , _ _ , _ _ . . - . _ . . - . . _ . _ . - , , e-.,. - , , . - , .. -i.,-=., ,,,,r-- -

- ,_y.- - .-..c -

__ _ .~ ___ ._ _

l OCTOBER 1987 The reactor operated ' continuously in October with the following exceptions: ;

four shutdowns for scheduled maintenance; three shutdowns for refueling and/or flux trap changes; and five unscheduled shutdowns.

On October 8, a nuclear instrument anomaly scram occurred when an operator opened the N. I. Channel #4 drawer to investigate an unusual chart recorder reading. Subsequently, a bad connection on the picoammeter for this channel was found and repaired.

On October 15, a reactor scram occurred while shifting the wide range switch upscale during a normal reactor startup. The cause was suspected to be a stick-ing relay contact in the feedback network of the picoammeter module for channel

1. 4 The channel #4 range switch was cycled through its full range and the picoammeter relays operated normally.

On October 18 and 24, the reactor scrammed due to momentary site electrical power interruptions. These were verified by the University power plant.

On October 28, a reactor loop high temperature scram occurred. No actual high temperature was indicated on any instrumentation and electronics technicians I subsequently found a defective lamp in the light activated switch section of the meter relay trip unit for primary heat exchanger temperature detector 980A. The lamp was replaced and the reactor was refueiad and returned to normal operation, i l

On October 15, an emergency preparedness drill involving the outside emer-  ;

gency support groups was conducted satisfactorily.

Major maintenance items for October included: replacing cams in motor operated doors 504, 505; replacing lamp in meter relay trip unit for 980A RTD; removing, inspecting and reinstalling Offset "C"; and shipping eight spent fuel j olements, i

I l-5

! NOVEMBER 1987 The reactor operated continuously in November with the following exceptions:

five shutdowns for scheduled maintcnance; two shutdowns for refueling and/or flux trap changes; and two unscheduled shutdowns.

On November 13, a channel #4 (wide range monitor) high power rod run in occurred wh11e shifting the wide ranga switch upscale during a normal reactor startup. No actual high power cordition was indicated on any instrumentation.

The cau n was suspected to be a sticking contact in the feedback network of the l picoammeter module for channel #4 The rod run-in was reset cnd the startup was completed with no further problems.

On November 21, a channel #5 (power range monitor) nuclear instrument anom-aly scram occurred. The cause was determined to be a failed detector. The detector was replaced and tested satisfactorily and the reactor was returned to

]

normal operation.

Major maintenance items for November included: shipping fif teen N.nc fuel elements; changing out beamport "C" crystal; rerouting the power cables for valves 543 A and B and control blade drives "C" and "D" to accommodate a new of f- j set mechanism design; replacing primary pump 501A with a spare; and replacing NI

\

channel #5 detector.

DECEMBER 1987 The reactor operated continuously in December with the following exceptions:

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

On December 7, a reactor scram and isolation was initiated by the contain-1 ment exhaust air plenum area radiation detector. The containment building was I i evacuated according to procedure. The remote radiation meter indicated a slightly elevated air plenum reading. The containment building was reontered and surveyed

)

i I-s .

! l l

4

j cith portable radiation monitors. No unusually high readings were noted. Elec-tronics technicians subsequently found and replaced a failed resistor in the high voltage circuit of the area radiation monitoring system. The reactor was then refueled and returned to normal operation.

i On December 10 and 17, a reactor scram occurred while shifting the wide range switch upscale during a normal reactor startup. The cause was suspected 4 to be a sticking relay contact in the feedback network of the picoammeter module for channel #4 In both cases, the switch was sub!.equently cycled through its full range and the relay operated normally.

1 On December 12, a manual scram was initiated when the outer personnel air-lock door drive motor shorted out. The motor was replaced and the reactor was returned to normal operation.

On December 20, a reactor scram occurred with no apparent cause. All reactor systems appeared to be operating non ally.

The "white rat" scram monitor-ing syitem was installed and a hot reactor startup was completed. Six minutes after gaining full power, the reactor again sci smmed. The "white rat" indicated  ;

a low core discharge pressure trip, but no actual loss was indicated on the meter.

Subsequent investigation revealed a defective lamp in the light activated switch section of the meter relay trip unit for core discharge pressure transmitter 944B. Electronics technicians replaced the meter and trip unit for 944B and the reactor was returned to normal operation.

On December 25, a nuclear instrument anomaly scram occurred. The power supply for channel #6 was replaced and the electronics technicians also found a l loose connection on the +24 volts 0.C. power supply. No high power conditions cere noted on any instrumentation and no similar problems have recurred.

i Major maintenance items for December included: replacing N.I. channel 45 detector; replacing resistor in HV circuit of ARMS; replacing meter relays for 960 A & B (Primary Heat Exchanger Temp.); replacing the outer airlock door drive I-7

motor; replacing the meter relay for PT 917 (Pool Reflector); replacing the meter and trip unit 'for PT 9448 (Core Discharge); replacing the cylinder heads on the emergency generator; replacing the starter relay in the emergency generator; and repairing a loose connection on +24 Volts D.C. power supply for N.I. channel #6.

JANUARY 1988 The reactor operated continuously in January with the following exceptions:

two shutdowns for maintenance; two brief power reductions for work on Beamport "C"; two shutdowns for refueling and flux trap changes; and three unscheduled shutdowns.

On January 10, a rod not in contact with magnet rod run-in occurred when an operator accidentally Dumped the c.ounter-weight for control blade "A" during a routine sample handling evolution. The operator involved was instructed to be more diligent in the future.

On January 19, a reactor scram and isolation occurred. All personnel exited the containment building according to the reactor isolation procedure.

After monitoring the building radiation levels from the remote station, opera-tions personnel reentered the containment building with a health physicist.

No abnormal radiation levels were detected and electronics technicians sub-sequently discovered a failed solder connection in the high voltage circuit of the area radiation monitoring system (ARMS). The connection was repaired and  :

the ARMS tested satisfactorily. The reactor was then refueled and returned to normal operation.

On January 31, the reactor scrammed due to the loss of site electrical power. This was confirmed by the power plant. After electrical power was re-stored, the reactor was refueled and returned to normal operation.

Major maintenance items for January included: replacing the 150 volt /high i

voltaje ARMS channel meter; replacing the drive motor on the inner personnel air lock door; replacing NI channel #3 voltage regulator and detector; repairing 1-8 1

i - , . .. .- - - - . _ - - _ _ _ . . - _ _ - _ _ . - = - .. , _ . - -

l a solder connection in the high voltage circuit of the ARMS; replacing the in-board and outboard motor bearings on primary pump 501B; repairing the mode switch on NI channel #4; replacing the drive sprockets on the personnel airlock doors.

FEBRUARY 1988 The reactor operated continuously in February with the following exceptions.

two shutdowns for maintenance; one shutdown for refueling; and four unscheduled shutdowns.

On February 1, a reactor loop low pressure scram occurred when the pressure switch (PS941) which operates the pressurizer nitrogen makeup valve (valve 526) failed to operata in its normal band width and thus failed to open the vilve at the desired time. This particular switch had operated satisfactorily during its most recent compliance check. The switch was readjusted and tested satisfac-torily. A hot startup was subsequently completed and the reactor was returned to normal operation with no further problems of this type.  ;

On February 25, a rod run-in occurred due to the failure of the rod run-in trip actuator amplifier. A manual scram was subsequently initiated by the duty ,

i operator. Electronics technicians replaced a burned resistor and a shorted '

transistor in the outout circuit and the amplifier was tested satisfactorily and returned to service.

l Later on February 25, a reactor scram occurred while shifting the wide range i

switch upscale during a normal reactor startup. The cause of this recurring j 1

problem is suspected to be a sticking relay contact in the feedback network of j l

the picoammeter module for channel #4, The switch was cycled through its full  !

range and the relay operated normally.

l On February 26, a reactor scram occurred for which a specific cause could l not be determined. From the annunciator indications and the primary system valve and pump actions in conjunction with the scram, it was believed that a spurious

electrical spike on one of the core discharge pressure transmitters (944 A/B)

! l-9

caused the scram. The "white rat" scram circuit monitoring system was installed on both the yellow and green legs of the safety system so if a similar scram occurred, what caused it could be specifically determined.

Major maintenance items for February included: replacing a broken spring and removing a link from the drive chain on the outer personnel airlock door; renewing the brushes, regulator rectifiers, field rectifiers, gas filter and rerouting the gas line on the emergency generator; dumping depleted pool DI bed "R"; loading new pool DI bed "T"; replacing a burned resistor and a shorted tran-sistor in the rod run-in trip actuator amplifier; installing new sample wedge "P" in tne reflector position 6; installing new offset "C ; and d

repairing broken connector on control rod "C" drive motor.

MARCH 1988 The reactor operated continuously in March with the following exceptions:

four shutdowns for maintenance; two shutdowns for refueling and flux trap changes; one shutdown for a flux trap inspection; and two unscheduled shutdowns.

On March 11, a nuclear instrument channel #5 high-power scram occurred when the detector failed. The detector was replaced and the detector and channel cir-cuitry were tested satisfactorily.

On March 24, the reactor scrammed due to the momentary loss of site electri-cal power which was confirmed by the University Power Plant. A hot reactor start-up was completed and the reactor was returned to normal operation. l Major maintenance items for March included: replacing the upper mounting bolt and repairing the bottom track springs on the inner personnel airlock door; J arid replacing channel #5 detector.

APRIL 1988 The reactor operated continuously in April with the following exceptions:

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

1-10 l

l I

On April 27, a nuclear instrument anomaly scram occurred when the power supply module for channel number four (wide range monitor) failed. The power supply module and the power supply output circuit card were replaced and the reactor was returned to normal operation. "

Major maintenance items for April included: replacing NI channel #4 power 4

i supply module and output circuit card; and replacing the D. C. power supply on NI channel #5.

1 MAY 1988 The reactor operated continuously in May with toe fallowing exceptions:

t

, two shutdowns for refueling and flux trap changes; two shutdowns for niaintenance; 4

and one unscheduled shutdown.  ;

On May 14, a manual scram was initiated by the duty operator when the o. .

4 personnel airlock door gear drive failed due to a broken weld on the gear driv, g sprocket. The sprocket was rewelded and tested satisfactorily. The reactor was then refueled and returned to normal operation.

Major maintenance items for May included:

performing the biennial replace-ment of the control blade offset in position "B"; and repairing the gear drive sprocket on the outer personnel airlock door.

JUNE lo*8

)

The reactor operated continuously in June with the following exceptions: '

three shutdowns for refueling and flux trap changes; and two shutdowns for i

scheduled maintenance. There were no unscheduled shutdowns in June.

Major maintenance items for June included

replacing the air diaphragm, a

valve diaphragm and the stem 0-ring for valve 527E (primary demineralizer inlet);

and replacing the shock absorber springs on the outer personnel airlock door

{-

drive chain. {,

1

) l 4 1 I  !

l I-11

i SECTION II CHANGES TO THE STANDARD OPERATING PROCEDURES Revised October 1981 1 July 1987 through 30 June 1988 As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the changes to the Standard Operating Procedures and the Emergency Procedures.

A. STANDARD OPERATING PROCEDURES There has been one revision (#24) made to the Revised October 1981 manual during the year.

B. EMERGENCY PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the changes to the Emergency Procedures.

1. Revision #6 to SEP Section dated October 2,1987

2. The Emergency Procedures dated January 1985 was revised May 13, 1988 and a new manual printed.

The revisions to the Standard Operating Procedure; and Emergency Procedures are contained in this section with the part of e'ach page that was revised marked on the right side of the page by a bracket (]).

11-1 l

w

. . - - . - . _ . .- _. _ . . - - _ . _ . . ..-_ _ ~ . . - . . . . . . . - - . ~ ... -

~

l REVISION NUMBER 24

! T0 l

0CTOBER 1981 MANUAL Pag _e_ Number _0_a_t_e_ Re v i s ed_

l SdP/II-11 7/29/87 SOP /VI!-49 7/29/87 S0P/VII-50 7/29/87 SOP /VIII-13 7/29/87 S0P/VIII-14 7/29/87 S0P/VIII 15 7/29/87 SOP /VIII-16 7/29/87 S0P/VIII-17 7/29/87 SOP /VIIl-18 7/29/87 SOP /A-12a 7/29/87 i  :

-l, II-2

._ ,- - , _ , , . . . . . . . . - _ . . . . . . , . ~ , . , . . . . . . - . . _ , - . _ , _ . . , _ . . _ _ . ...-,;-..,-.....__....-

1 l

l l

X. A Reactor Operator or Senior Reactor Operator shall initial the loading sequence sheet af ter each step.

L. Perform a post-refueling map check, verifying that the appropriate ]

positions in the "X", "Y" and "Z" baskets contain fuel elements as ];

indicated on the post fuel handling sequence drawing. ]

M. A Senior Reactor Operator will inspect the core prior to replacing ])

the pressure vessel head. I N. Install the pressure vessel head. (If the pressure vessel head is ]

to be lef t off at this point, install the aluminum protective head on tne pressure vessel.)

0. Record that the reactor has been defueled or refueled indicating ]

the identification numbers of the cores involved and the fact that the new core has been inspected.

P. Post the fuel element locations data sheet in the control room. ]

Q. Turn the bridge ARMS back downscale. 3.

R. Secure the SRM and pull the fission chamber to full out. ]'

1I.2.3 When starting up the reactor af ter any fuel change in the core, the predicted critical position shall be verified by the Reactor Physicist.

If the reactor has been loaded with a new mixed core, a 1/M plot shall be made on the subsequent start-up.

11.3 Control Blade Offset Mechanism Removal 11.3.1 Condi tions Prior to Removal A. The control rod offset mechanism will not be removed except by l l

authorization of the Reactor Manager. i B. The removal of the assembly will be supervised by the Shif t Supervisor or a Senior Operator.

C. When one offset mechanism is to be removed:

1. The core will be defueled of two fuel elements;

2. The balance of the other three rods will not be raised from their l fully lowered position without approval of the Reactor Manager.

D. When more than one offset mechanism is to be removed, the core will l

be defueled of at least two elements for each offset mechanism removed.l t Rev. 7/29/87 App'd Unik SOP /II-11

4. Start the waste cump (WP1) and verify flow through the bullseye.

5. Check the WT level frequently until the tank is empty.

6. When it is empty, shut W41 and secure the waste pump.

7. Close W5a, Sb, 10, 16, 17, - 18, 19, 28 and 30.

8. Turn on blowdown switch.

9. Record the volume remaining on the Waste Tank Sample Form and return it to the Health Physics Office.

10. Record pumping evolution completion in t.he Reactor Log.

8. Pumping WT3 to Sewer

1. Chack valves W5a, 5b closed.

2. Open W6a, 6b, 9, 10, 16, 17, 18, 19, 23 and 30.

3. Secure local blowdown switch by WT3.

4 Start the waste pump (WP1) and veri'y flow through the bullseye.

5. Check the WT level frequently until the tank is empty.

6. When it is empty, secure the waste tank pump.

7. Shut W6a, 6b, 10, 16, 17, 18, 19, 28 and 30.

8. Turn on blowdown switch.

9. Record the volume remaining on the Waste Tank Sample Form and return it to the Health Physics Of fice.

10. Record pumping evolution completion :n the Reactor Log.

VII.8.8 Pumping Waste System to Secondary Sy stem Note 1: Pumping from the Waste System to the Secondary System can only be done after having received permission from the' Reactor Manager.

Note 2: Any time a waste tank is pumped to the Seconday System it will be pumped through the Waste System filters.

Note 3: When possible, the cooling tower fans should be lef t in fast speed any time the secondary water activity level is above 10-" uci/mi tritium. ]

Note 4: The Secondary System Blowdown will remain secured until Tritium activity is less than 10-4 tci/ml and all other ]

activities are within 10 CFR 20 limits for discharge to the Rev. 7/29/87 App'd UMP SOP /VII-49

l l

l sanitary sewer. A Secondary Water Activity Analysis form will be filled out for each secondary water analysis performed.

Af ter the form (s) is(are) completely filled out, it will be sent to the Health Physics Office for filing with the appropri-ate waste tank analysis sheet.

Note 5: The following data will assist in determining when a water sample should be taken to check activities less than 10-" pCi/ml. Immediately af ter pumping a waste tank to ]

secondary, the secondary water activity level will be approxi-mately 1/6 of the concentration of the waste tank water. With the reactor at 10 MW and three cooling tower : fans in fast speed, the H 3 concentration decreases by a factor of 100 in about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A. Pumping WT2 to Secondary System

1. Secure and tag secondary system blowdown solenoid valve and isolation valve and log.

Caution: Will not shut off when pumping to sec. due to sec. system back pressure.

2. Check the following valves closeG: W1, 2, 3, 6a, 6b, 15, 22, 24, 25, 26, 27, 28, 38, 39.

3. Open valves W5a, Sb, W9 and 10 if using WP1 or W7 and W8 ff using WP2, W16, 17, 18, 19. Check open W14 and 21.

4. Start the waste pump (normally utilizing WP1) and open W23 and S169. Observe the bullseye to verify flow.

5. Check the waste tank level frequently until the tank is empty, also observe the Secondary Coolant Monitor in the Control Room.

6. When the tank is empty, secure the waste pump. f

7. Close the following valves: 5169, W23, Sa, 5b, 10, if WP1 was used, 8 ff WP2 was used, 16, 17, 18 and 19.

8. Record remaining tank volume on the Waste Tank Sample Form and return to the Health Physics Office. I 1

l l l l l

l l Rev. 7/29/87 App'd M$db- SOP /VII-50 1

l l i

l

each insertion up to and including 10 minutes. .or irradi-ations longer than 10 minutes, a mark will be placed on the rabbit for each 10 minute period or fraction thereof. For example, if a rabbit is irradiated for 25 minutes, it will receive 3 marks. When a rabbit has received 6 marks, it will be discarded. Each rabbit must be examined for cracks or other signs of potential failure before it is used.

VIII.3.4 Sample Irradiation Procedures VIII.3.4.1 When experimenters have met the requirements of VIII.3.3 and are ]

ready to run their experiment, they shall first make certain that ]

the P-tube system for the desired irradiation position is not in ]

use; i.e. , the system "in use light" should be of f, then they ]

shall :all the reactor control room giving their ]

A. Name

3. Laboratory room number C. Experiment file number ] l 1

0. Project number ]  !

E. Length of time the sample will be in reflector ]

F. Number of irradiations to be done under A - E ] l VIII.3.4.2 Af ter blowers are verified "0N" by the control room operator, the ]

system will be operated by the following procedure: (THE POSITION ]

0F ALL CONTROLS AND INDICATIONS ARE SHOWN ON ARE SHOWN ON FIGURE ]

VIII-1) ] )

l NOTE: THE "RETURN" PUSHBUTTON WILL RETURN RABBIT TO FUME ]

HOOD OURING ANY PORTION OF IRRADIATION CYCLE. ] .

1 A. Set timer to desired irradiation time. ]

1. Depress and hold pushbutton I. ]

2. Oepress numbered pushbutton until desired tiine is ]

indicated on display (HH.MM.SS). ]

3. Release pushbutton I. ]

4 Timer is now set, and need not be touched again until ]

a new irradiation time is required.

I Rev. 7/29/87 App'd kh-- SOP /VIII-13

f 1

l DISPLAY 655558 O O 1

l P.B. RABBIT l

lN REACTOR DISPATCH P.B.

RETURN ON SYSTEM IN USE O

OFF 8

Figure VIII-1 Control Station for Laboratories 216, 218, 227, 228 Rev. 7/29/87 App'd w%~

SOP /VIII-14

3. Place power switch to "0N" ("System in use, lamp lights). 3 C. Depress "Dispatch

• pushbutton (system is now lined up to 3 accept rabbit). ]

0. Insert rabbit, with cap down. ]

E. Observe "Rabbit in Reactor" lamp lights, and timer starts. ]

F. At end of pre-selected time, system will returr. rabbit to ]

"catcher" in fume hood. ]

G. If more then one rabbit is to be run, using same irradiation ]

time, depress "Dispatch" pushbutton and insert next rabbit. ]

H. Af ter last rabbit is run, place power switch to "0FF". ]

I. Call control room and give the irradiation time for the ]

rabbit ant: numter of rabbi:s irradiated. Verify numbers ]

consistent with those reported in section VIII.3.4.1.E. ]

If dif ferent, determine cause of discrepancy. ]

VIII.3.4.3 Af ter the rabbit has returned from the reactor, check the dose rate.

VIII.3.5 P-Tube Emergency Procedures VIII.3.5.1 The most common occurrences will be trouble with the station controls, the possibility of the rabbit sticking in the tube, and the rabbit coming apart in the pneumatic tube system.

VIII.3.5.2 Station Control Malfunction A. If the rabbit is in the reactor and is not automatically discharged, press the "return" pushbutton and notify the ]

centrol room immediately.

B. If the rabbit is not in the reactor and station controls do not work, call the control room. The reactor' operator will then get in touch with the electronic technician.

NOTE: THE EXPERIMENTER IS NOT AUTHORIZE 0 TO ATTEMPT REPAIR OF TffE SYSTEM.

Rev. 7/29/87 App'd \/MA- SOP /VIII-15

O C. Report to the control room the material contained in the sample, the expected activity and dose rate, and the ap-proximate time the rabbit can remain in the reactor without creating any hazard.

D. The reactor operator will get in touch with a health ] j physics technician to monitor as required. ]

VIII.3.5.3 Rabbit Stuck in Tube Any time all or any part of a rabbit fails to return to the

, dispatch station, notify the control room immediately about the problem, stating the material contained in the sample, the weight of tne sample, the expected activi ty and dose rate, and the approximate time the rabbit can remain in the reactor without creating any ha:ard or celting.

A. Af ter the control room is aware of the problem, press the "return" pushbutton. Observe the rabbit in reactor light ]

and check with the control room to see if the operators heard the rabbit leave the reflector region. Hearing the rabbit depart the reflector is the only sure way to know it has left. If the rabbit was heard to depart the reflector region, check the other connecting station to see if the ]

rabbit was returned there.

B. Depress the dispatch button. ]

C. Repeat steps A and B several times as directed by the ]

control room.

D. If the attempts fail, turn c.ontrol box off. Go to the other ]

connecting station, line it up for sarvice and repeat steps  ;

A and B. ]

E. If these procedures have failed, follow up action will be ]

handled by reactor operations and health physics personnel.

NOTE: IF THE RABBIT IS STUCK OUTSIDE THE REACTOR IT MAY BE FOUND BY SEARCHING THE GUIDE TUBES WITH A l RADIATION MONITOR. IF THE RABBIT IS STUCK IN THE l REFLECTOR, THE REACTOR MXY HAVE TO BE SHUTDOWN AND I

THE P-TUBE REMOVED.

Rev. 7/29 /g? App'd WA SOP /VIII-16

1 VIII.3.S.4 Wet Rabbi t If the outside of the rabbit is wet when it is returned from the reactor, notify the control room immediately.

VIII.3.6 Emergency Return of Rabbit with Malfunctioning P-Tube Control Box Dispatch and return of the rabbit is controlled by solenoids in cabinet located by the seal trench. All solenoids in use are labeled by letters in the solenoid cabinet. Procedure to be followed in case of a failure at the local station is as follows:

A. Remove cover to solenoid cabinet.

3. Turn solenoid power switch off (this de-energizes all solenoids).

NOTE: THIS CLOSES OFF ALL TUBES WHICH WILL RESULT IN A HIGH CONCENTRATION OF AR"1 IF THE REACTOR IS OPERATING.

Room 216 - R and J Dispatch solenoids Room 218 - Q and J Dispatch solenoids ]

Room 227 - 8 and M Dispatch solenoids Room 228 - A and N Dispatch solenoids ]

Refer to solenoid schedule.  ;

l C. Energize the P-tube blowers. I D. Then, "manually" depress following solenoids in solenoid cabinet, i

Room 216 - U and L Return solenoids .

Room 218 - V and L Return solenoids ]

Room 227 - G and 0 Return solenoids Room 228 - H and 0 Return solenoids ]

As an example, the solenoids for return to room 216 should be in the following positions: solenoids R and J "up";

solenoids U and L "down".

VIII.4 Beamport Experiments Rev. 7/29/@ App'd (VtTu_s ,

SOP /VIII-17

. _ ~ . . . . . . - _ - .--

l i

l l

THIS PAGE INTENTIONALLY LEFT BLANK i

i l

l l

l l

l l

l l

Rev. 7/29/87 App'd i t-))es SOP /VIII-18

l I

l NOTF. : PLEASE RETURN TO HEALTH PHYstCS OFFlCE AND ATTACH TO IN0!CATED ANALYSTS SHEET.

l SECONDARY WATER ACTIVITY ANALYSIS Date: Wt. Analysis Number:

(from Wt. sample sheet)

Time:

ini tial s:

Samole Taken from Tower Sumo Isotooe Half Life Ac ti vi ty H3 12.3 yr tCi/ml Analysis performed by:

Time Da te:

Tritium activity is less than 10-" 141/ml and all other activities are within ]

10 CFR 20 limits for discharge to the sanitary sewer. Approval is given to turn on the blow-down system.

Shif t Supervisor Blowdown on Time Date Initials I

Rev. 7/29/87 App'd 4 SOP /A-12a l

(_-.... . - - . - . - . . .. - . . _ - - . . . - . - . - . . ~ . . - . . - . - . . . . .

I e

i L

l i

REVISION NUM8ER-6 l Site Emergency Procedures Section > (SEP) to EMERGENCY PROCEDURES Issued January 8,1985 0-Section No. Page No. Date Revised SEP-8 1 10/2/88

. SEP-8 2 10/2/88 SEP-8 3 10/2/88 i

f I

4 1

4 1

D N

II-3

t Pa9e 1 of 3 SEP-8 EMERGENCY EQUIPMENT MAINTENANCE PROCEDURE t

Purpose:

l This procedure states how the operational readiness of emergency equipment l and supplies required by the Emrgency Procedures is to be maintained, calibrated, j tested, and periodically inventoried. <

HQalth Physics' Emergency Equipment:

Health Physics' Emergency Equipment and supplies required by the Site Emergency Procedures shall be maintained in two designated readily accessible ]

locations. The two locations are the MURR Emergency Equipment Cabinets in the copy machine room and the Backup Daergency Equipment Cabinet at RPDB in room 10. The inventory check lists for each location are attached to this procedure and shall be ]

used to verily quarterly that the contents of the cabinet meet a: least the ]

required levels. All maintenance and inventory records on emerger.;y equipment shall be maintained in the Health Physics Office. ]

The civil defense kits stored at each location contain a G-M survey meter, an ion chamber meter (500 R/hr range), and a set of self-reading pocket dosimeters.

These kits are exchanged routinely by Missouri SEMA for updated kits of instruments ]

which have been calibrated by SEMA. The self-contained breathing apparatus sets are inspected annually by the Columbia Fire Department. The emergency Health Physics' ]

equipment is supplemented by the Health Physics' instruments and equipment used for daily routine evaluations and is maintained and calibrated by the Operational Health Physics' Program.

Off-Gas Monitoring Equipment:

The off-gas stack monitor has three channels: gas, particulate, and iodine.

The three channels shall be calibrated semiannually by the Reactor Chemistry group ]

using Reactor Chemistry Standard Operating Procedures:

RC/III-2 Calibration of Stack Particulate Monitor RC/III-3 Calibration of Stack Iodine Monitor RC/III-4 Calibration of Stack Gas Monitor The operability of the off-gas monitor is checked as part of the start-up check-list for normal reactor start-ups.

Fire Fighting Equipment:

The fire hydrant in the reactor site is checked operable routinely by the ]

Columbia Fire Department. The fire extinguishers shall be checked annually by the University of Missouri Physical Plant. ]

Rev. 10/2/87 App'd /( -<

f

'- SE 8 (Cont'd) Page 2 of 3 1 EMERGENCY LOCKER INVENTORY MURR COPY ROOM Date \

By I l

Number Number I Required Desi red 1

0 () 3 self-contained breathing apparatus:

(1) Inspection Dates ID l (2) Inspection Dates ID L

(3) Inspection Dates ID 1 () 2 flashlights - new batteries installed 1 () 1 first aid kit 5 () 5 "D" cell batteries replaced with new batteries .

I 3 () 5 boxes swipes 0 () I box paper towels 0 () 1 box absorbent paper 2 () 4 bars face soap 3 () 6 "Radioactive Material" tags 0 () 2 rolls tape 0 () 1 roll "Radioactive Material" tape 2 () 2 full face respirators )

2 () 5 half face respirators l 8 () 10 spare filters for respirators 0 () Assorted plastic bags 2 () 4 NuCon permasigns

)

l 0 () NuCon permasign insets '

i 1 () I box rubber gloves 4 () 7 sets protective clothing i

0 () 20 ft, yellow and magenta rope l l

1 () 1 Civil Defense instrument kit -

date kit placed in cabinet . l REMARKS: I 1

l Re v. 10/ 2/ 6 / App'c s- w.v l

SEP-8 (Cont'd) Page 3 of 3 EMERGENCY LOCKER INVENTORY RESEARCH PARK DEVELOPMENT BUILDING (RPDB)

Da te By Number Number Reouired Desired 0 () I self contained breathing apparatus:

(1) Inspection Dates ID 1 () 2 flashlights - new batteries installed 1 () 1 first aid kit 5 () 5 "D" cell batteries replaced with new batteries j 3 () 5 boxes swipes 0 () 1 box paper towels 0 () 1 box absorbent paper 2 () 4 bars face soap 3 () 6 "Radioactive Material" tags 0 () 2 rolls tape 0 () 1 roll "Radioactive Material" tape I

2 () 2 full face respirators 2 () 3 half face respirators 8 () 10 spare filters for respirators 0 () Assorted plastic bags 2 () 4 NuCon permasigns 0 () NuCon permasign insets 1 () I box rubber gloves 2 () 2 sets protective clothing 0 () 20 ft. yellow and magenta rope 1 () 1 Civil Defense instrument kit -

date kit placed in cabinet .

REMARKS:

. /.

Rev. 10/2/6/ App'o J C, ras

EMERGENCY PR4CEDURES l

ISSUED JANUARY 8, 1985 l

REVISED AND REPRINTED MAY 13, 1988 Section No. Page No. Date Rev. Section No. Page No. Date Rev.

Assignment Sheet 5/13/88 FEP-1 1 of 5 5/13/88 FEP-1 2 of 5 5/13/88 Revision Posting Sheet 5/13/88 FEP-1 3 of 5 5/13/88 FEP-1 4 of 5 5/13/88 Table of Contents i 5/13/88 FEP-1 5 of 5 5/13/88 FEP-2 2 of 4 5/13/88 List of Effective Pages 11 5/13/88 FEP-2 3 of 4 5/13/88 FEP-2 4 of 4 5/13/88 SEP-1 2 of 5 5/13/88 FEP-3 1 of 1 5/13/88 SEP-2 3 of 5 5/13/88 FEP-4 2 of 5 5/13/88 SEP-2 5 of 5 5/13/88 FEP-4 3 of 5 5/13/88 SEP-3 2 of 6 5/13/88 FEP-4 4 of 5 5/13/88 SEP-3 3 of 6 5/13/88 FEP-4 5 of 5 5/13/88 SEP-3 4 of 6 5/13/88 SEP-3 6 of 6 5/13/88 UNIV. OF MISSOURI 5/13/88 SEP-4 2 of 6 5/13/88 HOSPITAL & CLINICS SEP-4 3 of 6 5/13/88 (Emergency Center Policy Manual)

SEP-4 4 of 6 5/13/88 SEP-4 6 of 6 5/13/88 SEP-7 1 of 4 5/13/88 SEP-7 2 of 4 5/13/88 SEP-8 1 of 3 5/13/88 SEP-9 1 of 2 5/13/88 SEP-11 1 of 3 5/13/88 SEP-11 2 of 3 5/13/88 SEP-11 3 of 3 5/13/88 EMERGENCY CALL LIST Table of Contents i 5/13/88 FACILITY EMERGENCY PROCEDURE 1 of 2 5/13/88 FEP - Description of 2 of 2 5/13/88 Radiation Alarms &

Personnel Response i II-4

EMERGENCY PR0CEDURES UNIYERSITY 0F MISS0URI RESEARCH REACTOR FACILITY - .

)

)

ISSUED JANUARY 1985 REVISED MAY 13, 1988 l

l ASSIGNMENT SHEE7 Numoer IS ASSIGNED AS FOLLOWS:

I t

I i

l I

_ _ . . . _ _ _ . . _ _ _ , _ . - , - - . _ - - - - . - - - - - . - . . - . - - - - - - - - - - - - - - - - ~ - - ~ - ~ ~ ~ ~ - - - - ~ - - - - - - - - - '

l l

, MURR l

SEP/FEP SECTIONS FOR EMERGE.9CY PROCEDURES Revision No. Date Filed Revi sion No. Date Filed 1

)

i

)

1 i

i Rev. 5/13/88 App'd ,j%n a' /

t/

l i

EMERGENCY PROCEDURES - SEP/FEP SECTIONS TABLE 0F CONTENTS l l

I. SITE EMERGENCY PROCEDURES (SEP)

SEP-1 Activation of Emergency Organization Procedure ....... 1-5 l SEP-2 Unusual Even t Procedure . . . . . . . . . . . . . . . . . . . 1-S SEP-3 Alert Procedure . . . . . . . . . . . . . . . . . . . . . . . 1-5 SEP-4 Site Area Emergency Drocedures ............... 1-6 1

! SEP-S Partial Site Area Evacuation Procedure ........... 1-2 SEP-6 Emergency Air Sampling Procedure . . . . . . . . . . . . . . . 1-2 SEP-7 Public Information Procedure ................ 1-4 SEP-8 Emergency Equipment Maintenance ?rocedure ......... 1-3 SEP-9 Training Procedure for Emergency Preparedness . . . . . . . . 1-2 SEP-10 Emergency Dosimeters for Offsite Personnel . . . . . . . . . Orig. 1 - 3 SEP-11 Monitoring Planned Exposures in Excess of Limits in 10CFR20 . 1-3 EMERGENCY CALL LIST .

........................ 1 only WORKSHEET * ...................... ....... 1 only WORKSHEET 3 ...................... ....... 1 only WORKSHEET C

............................. 1 only WORKSHEET 0

............................. 1 only WORKSHEET E

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . Orig. 1 only II. FACILITY EMERGENCY PROCEDURES (FEP)

FACILITY EMERGENCIES ........................ 1- 2 Classification of Facility Emergencies .......... 1 FEP-1 Facili ty Evacuation Procedure . . . . . . . . . . . . . . . 1- Sl FEP-2 Reactor Isolation Procedure ............... 1- 4I i

FEP-3 Fire Procedure ....... ............'... 1 only FEP-4 Medical Emergency Procedure . . . . . . . . . . . . . . . . 1-S UNH3C (Hosoital 1 Clinics) - RADIATION DISASTER PLAN i I Rev. 5/13/88 App'd 4 C,.e.

/

MURR EMERGENCY PROCEDURES - SE?lFEP SECTIONS LIST OF EFFECTIVE PAGES

' Section Page Section  ? age Number Number Date Revised Number Number Date Revised SEP-1 1 2/10/87 SEP-11 1 5/13/88 ] I 2 5/13/88 ] 2 5/13/88 ) i 3 2/10/87 3 5/13/88 ) l

• 2/10/87 5 6/24/85 EMERGENCY CALL LIST 1 5/13/88 ] l SEP-2 1 2/10/87 WORKSHEET A 1/08/85 2 6/24/85 3 5/13/88 ) WORKSHEET 8 1/08/85 1 4 1/08/85 I 5 5/13/88 ] WORKSHEET C 1/08/85 SEP-3 1 6/24/85 WORKSHEET 0 1/08/85 2 5/13/88 3 3 5/13/88 ] WORKSHEET E Orig. 6/24/85 4 5/13/88 l 3

l 5 1/08/85  !

6 5/13/88 ]  ;

FEP-Table of Contents i 5/13/88 1!

SEP-4 1 5/24/85  !

2 5/13/88 ] Facili ty Emergencies 1 5/13/88 ]

3 5/13/88 l 4

3 2 5/13/88 ]

1/08/85 5 1/08/85 FEP-1 1 5/13/88 ] '

6 5/13/88 3 2 5/13/88 ] '

SEP-5 3 5/13/88 ]

1 1/08/85 4 5/13/88 ]

2 2/13/87 5 5/13/88 ) l SEP-6 1 6/24/85 FEP-2 1 Orig. 7/03/85 2 2/13/87 2 5/13/88 ]  !

SEP-7 3 5/13/88 3 1 5/13/88 3 4 5/13/88 3 1 2 5/13/88 ] l 3 5/27/86 FEP-3 1 5/13/88 3 4 5/27/86 FEP-4 1 Orig. 7/03/85 SEP-8 1 10/02/87 2 5/13/88 ] l 2 10/02/87 3 5/13/88 ]  !

3 10/02/87 4 5/13/68 ]

SEP-9 5 5/13/88 ]

1 5/13/88 ) l 2 1/08/85 UNH&C (Hosoital & Clinics) imergency Center Raciation Disaster Plan ]

SEP-10 1 Orig. 6/24/85 2 Orig. 6/24/85 Rev. 5/13/88 App' r A.,

/

SE?-l (Cont'd) Page 2 of 5

2. The FE0 shall be activated by a paging system announcement, "ATTENTION, THIS IS REACTOR CONTROL - ASSEMBLE THE FACILITY EMERGENCY ORGANIZATION."

Repeat page.

3. The FE0 shall assemble outside the control room except when tne facility evacuation / reactor isolation horns sound, then the FE0 shall assemble

• 1 the facility front lobby.

4 The responsibility for EMERGENCY DIRECTOR shall be assumed.

Assumed by .

5. The EMERGENCY DIRECTOR shall assign an EMERGENCY COORDINATOR.

Assigned to .

6. IF sufficient on site personnel are available, assign a COMMUNICATOR ]

to call persons on the EMERGENCY CALL LIST. Emergency noti fication ]

rosters (EMERGENCY CALL LISTS) are posted at the Control Room console, ]

the lobby receptionist desk, and at the lobby phnne. EMERGdNCY CALL ]

LISTS are also included in each Emergency Procedures Manual. ]

Assigned to _ _ _ _

s

7. The Backup Emergency Command Center (RP08) may be activated by ]

calling 882-7221 during regular working hours. Af ter hours, contact ]

the Watch Office to open the RP00. This will be used as the exit point for all persons re-leased from site, so they can be monitored for contamination before release as per Procedure HP-20. A roster of all released persons will be maintained.

l Rev. 5/13/88 App'd 67

//

b

SEP-2 (Cont'd) Dage 3 of 5 TABLE II l EMERGENCY SUPPORT ORGANIZATIONS

a. WC HEALTH PHYSICS SERVICES In the event of a radiological emergency, the UMC Health Physics Services may be contacted to assist in checking facility personnel for con tami na tion. Af ter hours the Watch Office may be contacted to open  !

I the Research Park Development Building (backup emergency control center).

One of the persons listed below will man the backup control center.

CONTACT Office Home Dr. Philip Lee 882-7221 445-5275 j Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450

b. W C POLICE The WC Police may be called to restrict entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l to the facility. 882-7201 l

8

c. UN!YERSITY OF MISSOURI HOSPITAL AND Ambulance CLINICS (UMH&C) 882-6003 )

The WH&C should be contacted in the event Walk-in of personal injury. In the event of personal 882-8091 l

{ contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.

If three or more personnel are involved, ask the 3 Administrator-On-Duty to implement the Radiation l Di saster Plan. Refer to the MEDICAL EMERGENCY [

l PROCEDURES for details.

{

d. OFFICE OF UNIVERSITY 1: ELATIONS See SEP-7, PUBLIC This office will initially deal with questions INFORMATION from offsite. Direct any questions from media to PROCEDURE l

this office. They will release statements only by EMERGENCY DIRECTOR authorization.

e. COLUMBIA FIRE DEPARTMEill 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911

! The Columbia Fire Department shall be notified in the event of fire or need of emergency rescue capabili ty. Insure Office of University Relations i is also called.

Rev. 5/13/88 App'd bA k

l SEP-2 (Cont'd)  ? age 5 of 5 k

d. LABORATORIES

} (1) Cetermine which laboratory is the source of release, by checking radiation levels in quadrant exhaust ducting.

(a) Southwest Quadrant (b) Northwest Quadrant (c) Northeast Quadrant ACTIONS TO CONSICER (1) Throttle flow from laboratory quadrant to reduce release rate to less than Technical Specification's limits.

(2) Area Evacuations SUBSEQUQTACTIONS:

1. Change stack filters when chart reading exceeds 3 x 10 5 cpm. Reevalua te chart reading to determine if release rate is increasing / decreasing. Record time of filter changeout.

2. Evaluate results of. correction and subsequent actions to determine need to escalate /de-escalate the emergency classification.

l 3.

I Xeep record of actions and evaluations and time they were done for docu-menta tion. Use procedure worksheets.

l 4 Notify NRC, Region III, that an UNUSUAL EVENT has occurred within one hour 3 af ter event is classified er reclassified. (Use Worksheet C)

5. Notify American Nuclear Insurers (ANI) (203-677-7305] that an UNUSUAL EVENT  !

has occurred.

l 1

6. Notify State Emergency Management Agency (SEMA) [314-751-2748] that an UNUSUAL EVENT has occurred.

RECOVERY ACTIONS:

1. Evnluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by UNUSUAL EVENT emergency. I

2. Procedures snall be written and approved for handling significant recovery evolutions.

NOTE: Ouring recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits.

Rev 5/13/88 App'd Mym

SEP-3 (Cont'd) Page 2 of 5

5. Send operator to dest tower with radiation monitor to:

NOTE: Communicate with intercom, since stack monitor is affected by portable radio RF.

a. Verify radiation background at stack monitor,

b. Verify control room readings.

c. Mark initial needle position on analog display with time for future analysis if control room display becomes inaccessible. -

d. Verify flow rate through monitor to 7 + 1 SCFM.

~

If not, use Worksheet A, to determine stack monitor values.

6. Pull stack monitor filters and analyze. .

7. Af ter determining radionuclide responsible and verifying concentrations greater than 19,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, ]

RF1, SF1; (c) secure all individual vent fans. i

8. The EMERGENCY COORDINATOR shall evaluate the need for a partial or total evacuation of the facility. I NOTE: For facility evacuations or northeast quadrant evacuation, l have sample counting instrumentation removed to RP08. '

(Ge-Li detector and dewer; NUCLEAR DATA 66 computer)

9. The EMERGENCY COORDINATOR shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes.

NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 100 rem for life-  !

saving, up to 25 rem to prevent exposures to members of general 1 public in excess of 1 rem wnole body and S rem thyroid.)

10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE III, EMERGENCY SUPPORT ORGANIZATIONS.

Rev. 5/13/88 App'd MNe

SEP-3 (Cont'd) Page 3 of 6 TABLE III EMERGENCY Sl'PPORT ORGANIZATIONS

a. UMC HEALTH PHYSICS SERVICES In the event of an ALERT condition, the UMC Heal th Physics Services may be contacted to man the backup emergency control center.

Af ter hours, call the Watch Of fice to open RP08.

CONTACT Of fice Home Dr. Philip Lee 882-7221 445-5275 Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450

b. UMC POLICE The UNC Police may be called to restrict entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the research park and to assist in partial site 882-7201 area evacuation if deemed necessary.

c. UNIVERSITY OF MISSOURI HOSPITAL AND Ambulance CLINICS (UMH&C) 682-6003 3 The UNH&C should be contacted in the event Walk-in of personal injury. In the event of personal 882-8091 contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.

If three or more personnel are involved, ask the ]

Administrator-On-Duty to implement the Radiation Di saster Plan. Refer to the MEDICAL EMERGENCY PROCEDURES for details,

d. OFFICE OF UNIVERSITY RELATIONS See SEP-7, PUBLIC This office will initially deal with questions INFORMATION from offsite. Direct any questions from media to PROCEDURE this office. They will release statements only by EMERGENCY DIRECTOR authorization.

e. COLUMBIA FIRE DEPARTMENT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911 The Columbia Fire Department shall be notified in the event of fire or need of emergency rescue capabili ty. Insure Office of University Relations is also called.

Rev. 5/13/88 App'd_

l SEP-3 (Cont'd) Page 4 of 6 CORRECTIVE ACTIONS:

1. If the facility was evacuated in Step 8 of IMMEDIATE ACTIONS, continue. IF l NOT, go to step 2.

a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity.

b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE.

c. Evaluate results of surveys to determine pntsible reentry to parts of facility for further investigation, if necessary,

d. IF '.eakage concentrations exceed 19,000 MPC average-over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the UERGENCY DIRECTOR should consider evacuation of USDA, Science Instrument Shop, Oalton Research Center, and Blood Bank, as per SITE AREA EVAUCATION 3 PROCEDURE (SEP-5). ]

IF NOT, EMERGENCY 0! RECTOR should evaluate de> escalating to UNUSUAL ]

I7ETclassi fication.

2. Determine source of airborne radioactivity and try to reduce or eliminate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS.

(3) Check pool for gas releases.

ACTIONS TO CONSIDER (1) Sample primary (2) Procedure REP-20, Hioh Activity Levels in Primary (3) Reactor Isolation (FEP-2)

(4) Area Evacuations (5) Portable air monitor in room 114

\

Rev. 5/13/88 App'd I6n, l

b

\

l SEP-3 (Cont'd) ?aga 6 of 6 l

i SUBSEQUENT ACTIONS:

I

1. Evaluate results of correc*1ons and subsequent actions to determine j need to escalate /de-escalate emergency classification. '

2. Keep record of actions and evaluations for documentation. Use Procedures and worksheets.

3. Noti fy NRC, Region III, that ALERT condition has occurred within one hour af ter event has been classified or reclassified. (Use Work- ]

sheet C) 4 Notify American Nuclear Insurers (ANI) (203-677-7305] that ALERT condition has occurred. - -

5. Notify State Emergency Managemen*, Agency (SEMA) [314-751-2748] that ALERT condition has occurred.

RECOVERY ACTIONS:

1. Evaluate potential radiological effects to onsite and offsite -

personnel before returning access to specific areas effected by ALERT emergency.

1

2. Procedures shall be Sritten and approved fer handling significant recovery evolutions.

l NOTE: Ouring recovery operations, personnel exposures to radiation  !

should be maintained within 10CFR20 limi ts.

l l

Rev. 5/13/88 App'd,; N-

SEP-4 (Cont'd) Page 2 of 6

5. Send operator to west tower with radiation monitor to:

NOTE: Communicate by 11tercom, since the stack monitor is affacted by portable radio RF.

a. Verify radiation background at stack monitor.

b. Verify control room readings,

c. Mark initial needle position on analog display with time for future analysis if control room dfsplay becomes inaccessible.,

d. Verify flow rate through :nonitor to 7 + 1 SCFM. If not, use Worksheet A to determine stack monitor values.

6. Pull stack monitor filters and analyze.

7. Af ter determining radionuclide responsible and verifying cencentrations greater than 95,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, ]

RF1, SF1; (c) secure all individual vent fans.

8. The EMERGENCY COORDINATOR shall evaluate the need for a partial or total evacuation of the facility.

NOTE: For facility evacuations o northeast quadrant evacuation, have sample counting instrumentation removed to RP08. ,

(Ge-Li detector and dewer; NUCLEAR DATA 66 computer) j

9. The EMERGENCY COORDINATOR shall appoint and have a surveillani - team check areas evacuated clear of personnel within 30 minutes. j l

NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 100 rem for li fe-saving, up to 25 rem to prevent exposure to numbers of general public in excess of I rem whole body and 5 rem thyroid.) 1

10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE IV, EMERGENCY SUPPORT ORGANIZATIONS.

Rev. 5/13/88 App'd /k

[!n

l SEP-4 (Cont'd) Page 3 of 6 TABLE IV l

EMERGENCY SUPPORT ORGANIZATIONS I

a. UMC HEALTH PHYSICS SERVICES i

In the event of a SITE AREA EMERGENCY, the UMC Health Physics Services may be contacted to man the backup emergency control center.

Af ter hours, call the Patch Of fice to open RPDB.

CONTACT Office Home Dr. Philip Lee 882-7221 445-5275 Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450

b. UMC POLICE The UMC Police may be called to restrict entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the research park and to assist in partial site 882-7201 area evacuation if deemed necessary.

c. UNIVERSITY OF MISSOURI HOSPITAL AND Ambulance CLINICS (UMH&C) 882-o003 ]

The UMH&C should be cor tacted in the event Walk-in of personal injury. In the event of personal 882-8091 contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.

I 1

If three or more personnel are involved, ask the 3 l Administrator-On-Daty to implement the Radiation Disaster Plan. Refer to the MEDICAL EMERGENCY PROCEDURES for details, 1

d. OFFICE OF UNIVERSITY RELATIONS See SEP-7, PUBLIC This office will initially deal with questions INFORMATION from offsite. Direct any questions from media to PROCEDURE this office. They will release statements only by EMERGENCY DIRECTOR authorization.

e. COLUMBIA FIRE DEPARTMENT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911 l The Columbia Fire Department shall be notified .

1 in the event of fire or need of emergency rescue capabili ty. Insure Office of University Relations is also called.

Rev. 5/13/88 App'd __ /Ac f

e- , - , --

.n- ,

l SEP-4 (Cont'd)  ? age 4 of 6 CORRECTIVE ACTIONS:

1. If the facility was evacuated in Step 8 of IMMEDIATE ACTIONS, continue. IF NOT, go to step 2. ,

a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity.

b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE.

c. Evaluate results of surveys to determine possible reentry to parts of facility for further investigation, if necessary.

d. IF leakage concentrations exceed 95,000 MPC average over 24 hoars, the IUTERGENCY DIRECTOR shall commence evacuation of USDA, Science Instrument Shop, Oalton Research Center, and Blood Bank, as per SITE AREA EVACUATION ]

PROCEDURE (SEP-5). ]

IF NOT, EMERGENCY DIRECTOR should evaluate de-escalating to ALERT ]

Hassi fication. ]

2. Determine source of airborne radioactivity and try to reduce or eliminate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS.

(3) Check pool for gas releases.

ACTIONS TO CONSIDER (1) Sample primary (2) Procedure REP-20, High Activity Levels in Primary (3) Reactor Isolation (FEP-2)

(4) Area Evacuations (S) Portable air monitor in room 114 i

Rev. 5/13/88 App'd [ 'k

[ l l

SEP-4 (Cont'd) Page 6 of 6

$UBSE0 VENT ACTIONS:

1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.

2. Keep record of actions and evaluations for documentation. Use procedure and worksheets.

3. Notify NRC, Region III, that SITE AREA EMERGENCY condition has occurred within one hour af ter the event has been classified or reclassified.

(Use 'dorksheet C) ]

4. Notify American Nuclear Insurers (ANI) (203-677-7305] that a SITE AREA EMERGENCY has occurred.

S. Notify State Emergency Management Agency (SEMA) (314-751-2748] that SITE AREA EMERGENCY condition has occurred.

RECOVERY ACTIONS:

1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by the SITE AREA EMERGENCY.

2. Procedures shall be written and approved ect handling significant recovery evolutions.

NOTE: Ouring recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limi ts.

j l

i l

Rev. 5/13/88 App'd //1.I SS _,

/ 1 L

l

,, . _ - - - - . . . . ~ _- .. -

Page 1 of 4 SEP-7 PUBLIC INFORMATION PROCEDURE NOTE: The Office of University Relations (UR) shall be activated to handle the release of public information as required in the ALERT or SITE AREA EMERGENCY procedures; whenever offsite energency assistance is requested via 911; or whenever deemed appropriate by the EMERGENCY DIRECTOR.

A. INITIAL RELEASE OF PUBLIC INFORMATION

1. The Emergency Status Report shall be completed and approved by the EMERGENCY DIRECTOR.

2a. During normal University office hours, activate the Office of University Relations (UR) by calling 882-4591, 882-0600 (Bob Mussman), ]

or 882-0606 (Bud Carlson). 3 2b. At other times, call the following list of UR staff in order until one of the individuals listed is reached (gQl their spouse, children, etc.).

(1) Bob Mussman (314)-445-9852 (2) Phil Leslie (314)-474-6592 (3) Sud Carlson (314)-474-6334 (4) Larry Myers (314)-443-5325 (5) Bonita Eaton (314)-474-5629 (6) Frank Fillo 5314)-442-3269

3. Read the Emergency Status Report as approved by the EMERGENCY DIRECTOR to the UR staff member and answer any questions concerning definitions, terms, uni ts, etc.

4 Record other questions that the UR staff member may have. Enter the name of the UR staff memoer contacted and give the completed report to the EMERGENCY COORDINATOR to be kept with the records of the EMERGENCY.

4 Rev. 5/13/88 App'd - ..,}A'G-

~

l /

f

SEP-7 (Cont'd) Page 2 of 4 l

1 l l NOTE: Page two of SEP-7 is omitted from the Annual Report because it contains the verification procedure to sort out prangster calls.

l I

l pg Pa9e 1 of 3 1

1 EMERGENCY E0VIPMENT MAINTENANCE PROCEDURE

Purpose:

This procedure states how the operational readiness of emergency equipment and supplies required by the Emergency Procedures is to be maintained, calibrated, 3 2ested, and periodically inventoried.

Health Physics' Emergency Eauionent:

Health Physics' Emergency Equipment and supplies reouired by the Site Emergency Procedures shall be maintained in two designatea readily accessible j locations. The two locations are the MURR Emergency Equipe at Cabinets in the copy J machine room and the Backup Emergency Equipment Cabinet at RPDB in room 10. The inventory check lists for each location are attached to this procedure and shall be used to verify quarterly that the contents of the cabinet meet at least the required levels. All maintenance and inventory records on emergency equipment shall be maintained in the Health Physics Office.

, The civil defense kits stored at each location contain a G-M survey meter, an l icn chamber meter (500 R/hr range), and a set of self-reading pocket dosimeters.

These kits are exchanged routinely by Missouri SEMA for updated kits of instruments which have been calibrated by SEMA. The self-contained breathing apparatus sets are inspected annually oy the Columbia Fire Department. The emergency Health Physics' equipment is supplemented by the Health Physics' instruments and equipment used for i

daily routine evaluations and is maintained and calibrated by the Operational Health Physics' Program.

Off-Gas Monitoring Eouioment:

i The off gas stack monitor has three channels: gas, particulate, and iodine..

The three channels shall be calibrated semiannually by the Reactor Chemistry group using Reactor Chemistry Standard Operating Procedures:

RC/III-2 Calibration of Stack Particulate Monitor RC/III-3 Calibration of Stack Iodine Monitor RC/III-4 Calibration of Stack Gas Monitor The operability of the off-gas monitor is checked as part of the start-up check-l list for normal reactor start-ups.

1 Fire Fighting Equipment:

i The fire hydrant in the reactor site is checked operable routinely by the l Columbia Fire Department. The fire extinguishers shall be checked annually by l the University of Missouri Physical Plant.

1 Rev. S/13/88 App'd G O' -

Page 1 of 2 SEP-9 TRAINING PROCEDURE FOR EMERGENCY PREPARE 0 NESS 3

l I. TRAINING OF EMERGENCY ORGANIZATIONS A. FACILITY EMERGENCY ORGANIZATION (FE0) TRAINING l

This organization consists of MURR staff in the Director's Of fice, Operations, Health Physics and Reactor Chemistry groups. This organt-l zation will respond to botn GENERAL FACILITY EMERGENCIES (FACILITY ,

1 EVACUATION, REACTOR ISOCATTON, FIRE, MEDICAL AND SECURITY EMERGENCIES)  :

and EMERGENCIES WITH POSSIBLE OFFSITE CONSEQUENCES (UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, PARTIAL SITE AREA EVACUATION),

l. The members of the FE0 will train initially and annually thereaf ter, by emergency plan and procedure review of each member's role in emergency preparedness. This training will be documented by each member signing the EMERGENCY PLAN / PROCEDURES REVIEW DOCUMENTATION LIST.

2. Annual onsite emergency drills shall be conducted as action drills to test the training of FE0 members to carry out their roles under simulated emergency conditions.

3. TRAINING OF FACILITY STAFF OTHER THAN FE0 MEMBERS

1. The members of MURR staff not assigned to the FE0 shall initially and annually thereaf ter be trained as to their respective actions for each site and facility emergency classification. This training may be by seminar, lecture, or video tape sessions.

2. Annual onsite emergency drills will test these members' ability -3 to properly respond to simulated emergency conditions.

C. TRAINING OF EMERGENCY SUPPORT ORGANIZATIONS

1. The members of EMERGENCY SUPPORT ORGANIZATIONS shall be trained initially and biennially thereaf ter on their role in maintaining Emergency Preparedness. This will be performed by discussions between MURR staff and the members of each SUPPORT ORGANIZATION, j stressing familiarization with the facility or changes to the i emergency plan or procedures.

2. Biennial emergency drills shall be conducted to test, as a l

minimum, the communication link and notification procedures with these EMERGENCY SUPPORT ORGANIZATIONS.

l

}

Rev.5/13/88 App'd .-

A v

Page 1 of 3 3 SEP-11 MONITORING PLANNED EXPOSURES IN EXCESS OF LIMITS IN 10 CFR 20 NOTE: THE EMERGENCY DIRECTOR MUST APPROYE EACH VOLUNTEER TO EXCEED EXPOSURE LIMITS OF 10 CFR 20.

PURPOSE:

This procedure provides the guidelines for monitoring, dosimetry and

~

l records for persons who volunteer for life-saving and accident mit';ating activities which could result in planned radiation exposures in excess of 10 CFR 20 limits.

GUIDELINES:

A. Emergency Exoosure Guidelines f

1. A volunteer may be authorized to receive up to 100 Rem to save human l

t life.

2. A volunteer may be authorized to receive up to 25 Rem to save vital reactor equipment and/or to prevent radiation exposures to members of the general public in excess of the following Protection Action Guides (PAGs). i The Protective Actions for all claJsifications are based upon a PAG of 1 rem dose equivalent for whole body and S rem dose equivalent thyroid to members of the general public and MURR staff on site.

3. Personnel Selection Considerations

1. Individual is a volunteer (preferably 45 years or older).

)

l

2. Individual is familiar with the radiological consequences of emergency radiation exposures.

3. Women of childbearing age shall not take part (Reg. Guide 8.13).

Rev.5/13/88 App b' d M C

SEP-11 (Cont'd) Page 2 of 3 3 C. Self-reader Cosimeters and Locations Tyoe Range mr Loca tion PC 0 - 200 Receptionist Desk - Lobby PC 0 - 200 Health Physics Office PC 0 - 200 Film Badge Racks PC 0 - 200 Emergency 'ockers .

PC 0 - 200,000 Health Physics Office, (Instrument Cabinet in Health Physics Closet) 415A 0 - 9999 Health Physics Office, (Instrument Cabinet in Health Physics Closet)

NOTE: PC = Self-reader Pocket Chamber - -

415A = XETEX-415A Digi tal Dosimeter l PROCEDURE:

i NOTE: Although it is preferable to perform and document the steps presented below prior to emergency workers receiving the exposure, the situa- i tion (e.g., life saving measures) may require the EMERGENCY DIRECTOR  !

to verbally authorize the exposure and ensure completion of docu- )

mentation when time permi ts. '

l.

Ensure that the dose rate in the task area is known er measurable.

l 2. Ensure that volunteer has assigned film badge.

3. Complete Worksheet E giving careful attention to item C considerations.

4 A: sign the volunteer a self-reader pocket chamber or equivalent immediate readout monitor with a range double the anticipated total exposure for the (

assignment. l

5. The Emergency Director or a delegate shall obtain the exposure recorded by the readout device at a frequency that assures adequate control to prevent I l

exposures in excess of the planned limits for the volunteer,

a. The exposure received at each reading shall be recorded on Worksheet E.

FOLLOW-UP:

1. Expedite processing of volunteer's film badge to verify total exposure as indicated by self-reading dosimeters.

Rev. 5/13/88 App % m _.

! W

SEP-11 (Cont'd)  ? age 3 of 3 ]

2. If individual's dose equivalent exceeds any 10 CFR 20 limits, they should be examined by a physician to determine the need, extent and nature of medical surveillance or treatment.

REPORTING REQUIREMENTS:

Complete reporting requirements of 10 CFR 20.403.

I t

I Rev 5/13/88 App'd M/A V

- ~

EHERGENCY PROCEDURE EMERGENCY CALL LIST

_ _ _ _ _ lleel t!! P!!ysics Opera ti on s . __ _ _ ___ __ _ Emergengy Support Organjzations Phone No. _ Phone No.

S. Langhorst Phone N_o.

442-3534 ] H. Evans 698-2450 UNC Police B82-72DT R. Stevens 442-2539 K. Beamer 696-3540 J. Ernst 874-2710 R. Kitch 443-4273 Coluuela Fire Department R. Dobey 442-4043 C. Kribbs 9-911 ]

682-3980 UM llospital and Clinics T. Seeger 875-8656 Ambulance J. Baskett 882-6003 ]

874-0695 or 9-911 ]

Director'gi M flce___._.._.

Phone No. Walk-in 882-8091 R. H. Brugger 445-6580 D. H. Alger 445-4775 UNC llealth Physics (Office) t 882-7221 l Dr. Phil Lee (Home) 445-5275 Jamison Shotts (Home) 474-2194 UP erd dos!S _ _ ____-_.. _ _ _ _ _ Reac tor C;!e!!!f itrL __ _ _ __ David Spate (Home) 657-9450 Phone No. Phone No.

J. C. McKibben 442-6728 S. Morris 445-4217 Of fice of University Relations 882-4691, l W. A. Heyer 442-7675 V. Spate 657-9450 See Public Information C. Edwtrds 443-7529 J. Schuh 882-0600 ]

874-3086 ] Procedure for other or ]

R. Hultsch 442-6653 phone numbers. (SEP-7) 882-0606 ]

lC. Anderson 696-5506 State Emergency Mariagement B. Bezenek 445-5680 Agency (SEMA) 314-7S1-2/48 Y. Jones 445-2543 474-9388 NRC, Region III lN. Tritschler 312-790-5500 <

,B. Bsrker 449-2168 Americari Nuclear Isisurers i L. Fay to 446-0491 ] (ANI) 203-677-7305 G. Gu:n 875-1162 ,

R. Iludson 875-04S1 iH. Kilfoi1 474-6285 I lH. Randolph 474-4171 iT. Schoone 474-6416 lJ. Swallow 874-4049 lH. Wallis 443-E?64

'T. Warner 816-882-6740

'Hev. S/13/88 App'd - M/Alv V _ _ _ - - - - _ - - - _

l FACILITY EMERGENCY PROCEDURES (FEP)

TABLE OF CONTENTS Section No. Page No.

FACILITY EMERGENCIES ............ 1-2 3 f Classification of Facility Emergencies . . . 1 FEP-1 Facilt ty Evacuation Procedure . . . . . . . . 1-5 ]

FEP-2 Reactor Isolatien Procedure ......... 1-4 FEP-3 Fire Procedure

{ ................ 1 only FEP-4 Medical Emergency Procedure . . . . . . . . . . 1-5 UMH&C (Hosoital & Clinics) - RADIATION DISASTER PLAN

{ l l

l l

\

)

Rev. 5/13/88 App'd 7/A v/ _ _ _ _ _ _ _ _ _ _ _

Page 1 of 2 ]

FACILITY EMERGENCY PROCEDURE FACILITY OtERGENCIES FACILITY EMERGENCIES are classified as follows:

A. FACILITY EVACUATION - Emergencies of any type which require all personnel in the Facility to leave the premises, f

3. REACTOR ISOLATION - Emergencies limited to the reactor containment building which require all personnet in the -

containment to leave containment.

t L

C. FIRE - Emergencies which may or may not involve A or 3 and which may ruuire personnel to leave the premises.

D. MEDICAL - Emergencies involving injury to personnel but

• which may or may not involve situations A, 3 or C. These j injuries may but do not necessarily involve radiation j exposure or radioactivity contamination.

L E. SECURITY - Emergencies involving (1) the actual thef t of special nuclear material and/or the sabotage of the fccili-ty or (2) an attempt or threat of thef t or sabotage will be handled by the procedures outlined in the Reactor Security Procedures. [ SAFEGUARDS INFORMATION as per 10CFR50.34(c)]

Emergencies A and B are announced by a continuous sounding of I

the horns located aroughout the Facility. There is no dif-ference in the soutil of the horns for a Facility evacuation or

' for a reactor isolation, however, only those norns in the con-tainment sound when a reactor isolation occurs. Fires not associated with A or 3 above will De announced over the public

} address system with appropriate instructions for all personnel.

Security emergencies may result in the manual initiation of an i

. evacuation to clear all personnel from the building, j 1

I l

l Rev. 5/13/88 App'd d9a s 8

lil' - Ikscription of Aadiation Alarms and Personnel Response Facility Staff I'ersonnel ibn-Staff Personnel gesponse Resgense Incation of Sensors hallble location Type of Alarn

-}sg Responsible for Alarm llorn A 3 Execute reactor Isolation Esecute reactor isolation

a. eknual swissi in throu hout plan

p. Isslation Systen Control Room Conts tunent plan

b. Air plentse (AN!)

(flith level)

c. Reactor bridge (A#f)

J. Air pieruse 80 sentter Execute facility rzecute facility l

Control noom Throughout llorn a $ avecustion plan D. tvecu.tlon Ersten .a.

Facility evacuation plan I b. Front lobby Cause laneJtete area to Vacate contaltssient; D. G4s limitar (portable) Variable in Contslaunent local Bell Notify Reactor be vacated and pottfr Reactor Operations operations Bell and red light Cause inneJiste eres te vocate concelswat:

J. ras ticulate inmitor Variable in Contairement local be vacated and notify tetify Reactor Resctor Operations Operations

). Asec R.Jistion Ibnitor a. South wall-8P Floor locals Control the Burger sral red Ilght* Cause lasneJlste area to Yacate laceJiate eres (A30 be vacat&J and notify

b. West well-8P Floor llealth Thysics

c. Ihrth wall-BP Floor J. Fuel Storage Room

e. liest Eschanger acom

). Itand cnJ Foot Ibniters thin Corridor and Notify liestth Ftrysics

• Personnel Alttock (bor local tutter and red light tbtify liestth 11sysics e

) 8211 er busser and red light in Control Room '

) Fleshing red light near containment entrance

) Ccatral Boon annamclator butter and light

) Af ter normal working hours, notify Reactor Operations

'S

~ t o

av. ',/ t s/cu App'd gh. ,

~

/-- - - - ------------- -- - - -

. [g

Page 1 of 5 )

FEP-1 FACILITY EVACUATION PROCEDURE NOTE: An assessment of offsite radiological consequences shall be determined.

This assessment may require escalating emergency response to a site I

emergency procedure (UNUSUAL EVENT, ALERT or SITE AREA EMERGENCY).

( ENTRY CONDITIONS:

1. The Facility Evacuation alarm is actuated manually from two locations:

(a) the reactor control room, and (b) the lobby control center.

2. Situations that may warrant FACILITY EVACUATION include:

! (a) Security emergencies, such as a' bomb threat.

(b) A major facility fica. ,

(c) Whenever airborne radioactivity is expected to exceed 5 MPC throughout the facili ty.

(d) This procedure may be used as part of a Site Emergency Procedure (SEP).

(e) Other conditions occur that the Shif t Supervisor determines warrant personnel evacuation from the facility.

AUTOMATIC ACTIONS:

i The following events result from a Facility evacuation alarm: )

1. The reactor scrams.

2. The containment ventilation system isolation doors close.

3. The containment exhaust isolation valves close. j 4 The facility horns sound. )

5. The flashing red light exterior to the containment personnel l airlock uor is energized. l

? l

') Rev. 5/13/88 App'd fC t '

y  :

i

l FEP-1 (Cont'd) Page 2 of 5 3I I. PERSONNEL WITH PREASSIGNED TASKS (Facility Emergency Organization Members) i A. IMMEDIATE ACTIONS:

r The responsibility for the overall direction in the evene of an emergency i shall rest with the EMERGENCY DIRECTOR.

I In the event of a Facility evacuation during normal working nours, the L

following people shall report to the reactor lobby: the Facility Director, Associate Of rector, Reactor Manager, Manager of Reactor Health Physics, Machine and Electronics Shop Supervisors, Outy Shif t supervisor, 3 and a representative of Reactor Chemistry. - -

]

The responsibility for EMERGENCY DIRECTOR shall be assumed. The EMERGENCY DIRECTOR shall ascertain the availability of personnel required to execute the emergency plan and shall appoint an EMERGENCY COORDINATOR.

He shall investigate the cause of the alarm and the magnitude of the j incident, and shall direct those activt ties necessary to correct the

) emergency situation. Af ter the emergency is terminated, he shall direct the procedures necessary ta restore normal operation.

1 The EMERGENCY COORDINATOR shall ascertain that the reactor containment building, the Facility laboratories, and the mechanical equipment room, 3 l and below grade areas, have been vacated and secured. He will have the ]

t laboratory ventilation fans secured. He shall maintain a roster of all ]

persons released from the site by the EMERGENCY DIRECTOR. If the pneumatic t blower system was in use during the emergency, he shall insure that the

) samples being irradiated are returned to the laboratory and then have the blowers secured at the local lighting panel (f32). He shall insure a record of the events following the emergency is maintained.

The OUTY OPERATOR shall perform or have performed the following tasks ]

before leaving containment: (Do NOT attempt to correct any abnormalities at this time.)

A. Verify that the reactor has scrammed as indicated by the i ns trumen ta tion.

B. Verify that all shim rods have bottomed as indicated by the console lights.

h C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lignts, k

Rev. 5/13/88 App'd O ik-(/

L

(

FEP-1 (Cont'd) Page 3 of 5 ]

0. Ensure all personnel are cleared from al' levels of the contain- ]

ment building and exit via personnel airlock doors.

(

He shall report to the EMERGENCY COORDINATOR and advise him of the status p of the reactor.

MANAGER OF HEALTH PHYSICS shall proceed to the lobby control center

(

and establish the radiation-safe condition of the area. He shall estab-lish a hot-cold change area, assemble and prepare for use special Pealth Physics equipment, and perform radiation and contamination surveys. He shall evaluate the extent of radioactive contamination and/or radiation exposure received by personnel in the Facility at the time of the inci-dent. He shall advise the EMERGENCY DIRECTOR of measures to be taken to control and to clean up radioactive contamination which may have resulted from the incident.

The EMERGENCY DIRECTOR shall appoint a COMMUNICATOR to notify auxiliary organizations which have been made aware of these emergency procedures

[ and perform other communicative functions required. The following

) telephone numbers may be of assistance in the performance of these -

duties:

University Police / Watchman's Of fice, UMC 882-7201 1 Radiation Safety Office, UMC 882-7221 Dr. Philip Lee, 2 Research Park Dev. Bldg.

Emergency Room, UM Hospital & Clinics, UMC 882-8091 4

NOTE: When determined appropriate by the EMERGENCY DIRECTOR, the evacuation horns may be silenced by opening breaker 15 on the emergency lighting panel located in the north inner corridor next to the emergency power transfer swi tch.

Rev 5/13/88 App'd, 6A

[/

F2 P (Con t' d) Page 4 of 5 3 8!. PERSONNEL WITHOUT PREASSIGNED TASKS:

(Staf f otner than Facility Emergency Organization memoers)

A. IMMEDIATE ACTIONS:

1. Upon hearing the evacuation alarm, personnel shall proceed to points beyond the area bounded by the outer perimeter of the reactor labora-I tory building.

l 2. TOUR GUIDES shall be resp'nsible for the safe evacuation of visitors

, in their charge from the Facility in acc0rdance with the evacuation 1

routes in this plan. VISITORS shall be monitored by Health Physics Technicians as per HP-20 Defore being released to leave the site.

l

3. EXPERIMENTERS who are conducting experiments in the containment area shall render their experimental apparatas safe for unattended opera tion. They shall be responsible for the safe evacuation of visitors in their charge from the facility in accordance with the evacuation routes in this plan.

4 EVACUATION ROUTES (See the map of the routes on page 6.): ,

A. All personnel within the containment building will exit the containment building and proceed through the east door of the laboratory building and then go to the upwind parking 1.ot.

B. All laboratory personnel, support personnel, and guests exterior l to the containment building will leave the facility through the nearest exit (north, east, or south doors) and then proceed to the upwind parking lot, d

5. Once outside, personnel shall note the wind direction indicatcc at de top of the containment building east tower and proceed to the upwind parking lot.

3. SUBSE0tFNT_ ACTIONS:

3

1. All s'.a'f cersonnel shall remain on standby, unless released by the iMSGENCY DIRECTOR, to provide the special services that may be required to restore normal operation.

2. All staff Sersonnel shall be monitored by Health Physics Technicians as per proceaure rtP-20 before being released to leave the site.

3. A roster of all released personnel will be maintained by the EMERGENCY CO M INATOR.

I

-  ?

1 Rev. yl3/88 App'd Ao n/A^-.-

L .

FEP-1 (cont'd) '9' '

%s h y

- % e' '

1 PROCEED TO UPWlHD PARXING LOT f N /

J L

- I d

i .

9 '

o  :

E

% ~

f .

S

\ o g w g 1 3_

• E j $' -: g" o n- - -

o i

u

• O U A O

~ .

se

( U e

3

'l EVACUATION ROUTES, RESEARCH REACTOR FACILITY FIGURE FEP-1 i

Rev. 5/13/88 App'd (k/1__________ __

FEP-2 (Cont'd) Page 2 of 4

, I. PERSONNEL WITH PREASSIGNED TASKS:

(Facility Emergency Organi:ation members)

The following shall report to the lobby control center during normal working hours: Reactor Manager, Reactor Operations Engineer, Shif t Supervisor, Outy Operato', Reactor Services Engineer, Reactor Physicist, Plant Engineer, Manager of Health Physics, Machine and Electronics Shops Supervisors.

The responsibility for EMERGENCY DIRECTOR shall be assumed. The EMERGENCY DIRECTOR shall ascertain the availability of personnel required to execute the emergency plan. He shall investigate the cause of the alarm and the magnitude of the incident. He shall appoint an ENERGENC.Y COORDINATOR.

i If in the opinion of the EMERGENCY DIRECTOR the extent of the emergency is sufficient to warrant evacuation of tne facility, he shall actuate the alarm and the facility evacuation plan shall be executed. Af ter the emergency is i

I terminated, he shall direct the procedures necessary to restore normal operatier The EMERGENCY COORDINATOR shall establish that containment is vacated and secured. He shall maintain a roster of all persons released from the sita by the EMERGENCY DIRECTOR. If the pneumatic blower system was in use during the emergency, he shall insure that the samples being irradiated are returned '

to the laboratory and then have the blowers secured at the local lighting panel (132). He shall assist the EMERGENCY DIRECTOR as required and insure a record of the events following the emergency is maintained.

9 The OUTY OPERATOR shall perform or have performed the following tasks before leaving containment. (Do NOT attempt to correct any abnormalities at this ]

time.)

A. Verify that the reactor, has scrammed as indicated by the instrumentation, j' 9. Verify that all shim rods have bottomed as indicated by the console lights.

C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lights.

D. Ensure all personnel are cleared fron. all levels of the containment ]

building and exit via personnel airlock door.

Rev. 5/13/88 App'd 2 C,./b

FEP-2 (Cont'd) Page 3 of 4 He shall report to the EMERGENCY DIRECTOR and advise him of the status of the reactor. He shall then position himself at the outer personnel airlock door ]

and allow only authorized entry into the containment area. ]

The MANAGER OF HEALTH PHYSICS shall proceed to the lobby control center. He shall establish a hot-cold change area, assemble and prepare for use of special Health Physics equipment, and perform radiation and contamination surveys. He shall evaluate the extent of radioactivity contamination and/cr radiation exposure received by personnel in the containment at the time of the incident. He shall determine if the Radiation Safety Officer should be noti fied. He shall advise the EMERGENCY DIRECTOR of measures to be taken to control and to clean up radioactive contamination which may nave resulted

, from the incident. - .

A COMNUNICATOR appointed by the EMERGENCY OIRECTOR snall advise the laboratory personnel of the isolation emergency by means of the public address system. The following statements shall be read two (2) times:

"Your attention please ' Your attention please, j

A reactor isolation has occurred. All non-involved personnel shall keep clear of the main corridor and the lobby."

The COMNUNICATOR shall perform communicative functions for the EMERGENCY DIRECTOR. The following telephone numbers may be of assistance in the performance of these functions:

Traffic Safety and Security Office, UMC 882-7201

) Radiation Safety Office, UMC 882-7221 Emergency Room, UM Hospital & Clinics, UMC 882-8091

\

NOTE: To facilitate communication once reentry into the containment building has been made and proper radiation surveys are con-duc ted, the isolation horns may be silenced by means of a i switch on the back of the control console in the Control Room. l 1

i Rev. 5/13/88 App'd,.,hA ~

,// -

i

1 FEP-2 (Cont'd) Page 4 of 4

!!. PERSONNEL WITHOUT PREASSIGNED TASXS:

(5taff otner enan Facility Emergency Organi:ation memoers)

A. IMMEDIATE ACTIONS:

1. Upon hearing the REACTOR ISOLATION alarm, personnel in containment shall exit through the personnel airlock door to the front lobby,

2. TOUR GUIDES shall be responsible for the safe evacuation of visitors in their charge from the containment and exit via the east door.

VISITORS shall be monitored by Health Physics Technicians as per HP-20 before being released to leave the site.

3. EXPERD: ENTERS shall render their experimental apparatus safe for unattended operation. They shall be responsible for the safe evacuation of visitors in their charge to the lobby. They shall inform the EMERGENCY 0! RECTOR f f adjustments need to be made to their equipment upon reentry. l

3. SUBSEQUENT A_CTIONS: ,

1. All staff oersonnel shall remain on standby, unless released by tne EMERGENCY DIRECTOR, to provide the special services that may l be required to restore normal operation. '

2. All staff cersonnel who evacuated containment shall be 3 monitorao by Healtn Physics Technicians as per procedure HP-20 before being released to leave the site.

3. A roster of g released ?ersonnel who had evacuated containment ]

will be maintained by the EMERGENCY COORDINATOR.

1 t

T

) Rev. 5/13/88 App'd MM 0

Page 1 of 1 FEP-3 FIRE PROCEDURE

1. Any individual discovering fire shall notify reactor control (#13) of fire, ]

l giving nature and location of fire. The Shif t Supervisor will activate the FACILITY EMERGENCY ORGANIZATION by page system and provide warning to stay clear of fire location.

2. SHIFT SUPERVISOR will call (9-911) to notify Columbia Fire Departmanc.

3. EMERGENCY DIRECTOR will investigate the fire and determine steps to minimi:e hazard to both personnel and property.

NOTE: An assessment of offsite radiological consequences shall be de termi ned. This assessment may require escalating emergency response to a site emergency procedure (Unusual Event, Alert).

1 4 The EMERGENCY DIRECTOR may contact the OFFICE OF UN!YERSITY RELATIONS to handle public information, if appropriate.

5. If the fire cannot be put out immediately with local fire extinguisners - the reactor WILL be shutdown to focus on fire.

6. Secure EF-13 and EF-14.

7. Secure ventilation supply and exhaust fans and close all fire doors.

8. If the fire is in containment and cannot be immediately brought under control, initiate reactor isolation.

4 l

l 4

i

) Rev. S'13/88 App',d /A i i

FEP-4 (Cont'd) Page 2 of 5 See UMH&C RADIATION DISASTER PLAN (5 or more patients) to determine the plan they will need to implement:

1. Two or less patients (Emergency Room 1E17). ]

II. Greater than two patients (enter east side VA). ]

Upon discovery that an ateident has occurred, the following action is to be taken:

A. If the area in which the accident has occurred is a "high radiation area" with an exposure dose rate of 100 mR/hr or more, or is suspected to be such an area, move the victim quickly and carefully to a location l

at whien the exposure dose rate is 5 mR/hr or less if the victim can be moved without harm. Evacuate all personnel from the accident area and provide first aid to the victim.

l

3. Call the Health Physics Manager at 882-5227. If the Health Physics ]

Manager cannot be reached, call the UMC Health Physics at 382-7221. ]  !

C. Notify the Reactor Operator in the Control Room.

ACCIDENT INVOLVING PHYSICAL INJURY Upon arrival at the accident scene. Health Physics will take the following action:

l A. Assess the severity of the radiation injury and classify the injury.  !

)

l B. If necessary, close off and seal the accident area and turn off the ventilation to that area.

C. Notify the Emergency Room, UMH&C. at 882-8091, and arrange for medical 3 i care either at the Facility or at UMH&C.

l

0. If initial treatment is to be administered at the UMH&C arrange for transportation by the UMH&C ambulance, 882-6003, the Facility vehicle, )  !

or commercial amtulance service.

) Rev.5/13/88 App'd / M m > w 'v e

l l

, l l ,

FEP-4 (Cont'd) Page 3 of 5 l i l I

E. If initial treatment is to be administered at the Facility by a  !

representative of the LNH&C, attend the accident victim, keep him comfortable, and render first aid as required.

( I F. Survey all personnel who may have been contaminated in the accident,

[

Provide first aid as required.

G. Provide decontamination of the accident victim if possible, and all other persons founa to be contaminated.

H. Save all samples of clothes, jewelry, etc. Label the samples with name, time and date.

I. Notify the Facility Director and the Radiation Safety Officer.

J. Evaluate the radiation dose received by carefully reconstructing the accident. This assessment is more detailed than that required in item A

~

above and may be deferred until af ter the care of the accident victim is transferred to the attending physician.

Contamination and/or Radiation Exposure without Physical Injury ,

CONTAMINATION l If immediate emergency cleaning of contaminated person's skin cannot reduce i level to 1 mR/hr $Y or 1000 dpm alpha, they should be sent to the Research 3 4 Park Development Building for further health physics evaluation and/or 3 decontamina tion.

J Assure that one of the following persons will be at the Research Park 3 Development Building to assist in evaluating the need to move the 3 person to tne UMH&C. (Health Physics Manager or UNC Health Physicist) 3 i RADIATION 4

If a person has an estimated 10 REM exposure to any part of the body or l

whole body, send te Research Park Development Building for further 3 medical / health physics evaluation.

l

) Rev. 5/13/89 App' NA

FEP-4 (Cont'd) Page 4 of 5 Transportation Routes to the UMC Hospital and Clinics '

A. Injuries which do not involve contamination of the surface of the body shall be taken directly to the emergency entrance of the UMH&C for treatment in the Emergency Room (see Figure FEP-2),

3, Injuries which involve three or more extensively contaminated persons 3 shall be taken to the East entrance of VA hospital. The patients will ]

be taken to rooms A-38, A-45, and/or A-18 in the VA Animal Research ]

l Area, 4

I i

I I  !

l I

l

-) Rey,5/13/88 App'd l' Y( A

/ ' l /; ,/ l r

,' l

~ l

}n g

ylg' . 4

^ ~

~

n g m.

s.

s Q (s o%

J J (t

' rlQu^eu  :-

W 7 a gg: ?lmh 4 f

'p ;k =

(,

i- .

)

~

/

1. /

%r ~

'R

~

,\ s

_~ 4 l

i.

~

/.' ' ' -

~

(  ?

%jw\{._s4 ,'.

Q c N

c, S ,

,c 8.h

& < ~

~ n ,_

y ar w r,ggr. gi i .

,m G

y, B"

i r

u o

6

/

S D

a i

/

/e ,

nn

. =

[.

+  %

m

~

P R

. g i

N,, -

f

~ ~ -

~ '

~ -,

( m -

i "u;'/ ' [~ Qo0

~

/ l/Iil 4

g?,  ?

)

~

h l

UNIVERSITY OF MISSOURI-COLUMBIA HOSPITAL AND CLINCS EMERGENCY CENTER POLICY MANUAL Policy No. 585, Ef fective Date: dev. 12/8S l

Subject:

Emergeacy Center Radiation Disaster Plan Section: Specific Emergency Treatments (3 pagos)

AUTHORITY TO IMPLEMENT RADIATION DISASTER RESPONSE PLAN Page 30 through 37 Y.A. ANIMAL RESEARCH AREA MAP Page 65 RADIOLOGICAL CONTACTS Page 66

) Rev. S/13/88 App'd k b

Subject pagicy g,

. ~ , , _ ,

z Fic>sm- EMERGENCY CENTER RADI ATION '95 l

4Ch.r.tmil nics otSASTrR ruN enecw. ooi.

. ~ ,

rev.

_ _ - _ _ . _ . - . . iS/gg l

ENERGENCY CENTER Sexbn Page 3 I POLICY MANUAL SPECIFIC EMERGENCT TREATMENTS I og i

1 l

POLICY: Emergency Center Personnel vill contain, decontaminate and render )

-.a<r.t_o.r _x, ~m-4.nre o4.s .na<aar.<v. rpne, 4nntdon.

PURPOS E: To provide for emergency care and decontamination of patients arriving unannounced with possibility of radioactive

' contamination. This plan vill also be used for one or two victims who may be delivered by ambulance or other means with prior notification. Groups of three or more patients vill be cared for under the guidelines of Operation RAIN-FAL (See Hospital Disaster Manual for details).

PROCEDURE:

Responsibi]1r.y: ~

l Emergency Center 1. Any emergency center staff member i Tersonnel who first comes in contact with a i patient claiming ec have radioactive contamination shoold direct that patient immediately to ro,m lE17. Any patients that may b already occupying that room I should be removed from that area I by the charge nurse before entry of the ce staminated patient. The patient vill be confined ir. lE17 and any necessary immediate medical care vill be given in that  ;

area. Further monitoring for j confirmation of radioactive i contamination vill be conducted  !

in that area. Entry of staff )

into that area vill be held j to a minimum and no contaminated  ;

clothing or other objects vill be l sent from that area.

Emergency Center 1. At the direction of the charge Unit C' ; 't nurse or emergency center attending physician, th a receptionist should notify the l f ollowing personnel or agencies l of the arrival or pacients with

). Suspected radioactive contamina-tion:

a. Health Physica Services l Director: Ph'11 Lee , Ph.D. I 882-7221 or calling Hospital Operator._.

e.- -

H2spRai

&Clirucs .. .

- -Subject - - - - O0cy-No. - Page . --

j EMERGENCY CENTER RADIATION DISASTER PLAN 585 2 g 3 ,

1 PROCEDUR E:

Emergency Center b. Housekeeping Receptionists Manager: Tom Carter

• R*-LLBR - _

c. Security Manager: Bill Ree; )

882-7147 j l d. Plant Engineering l l Manager: Bill Dcitenbeek -

1 382-7902

e. Administrator on Duty (AOD)  ;

[ rot > ting personnel]

Seeper #0540

f. Medical Director /Feergency Center Michael Metzler '

882-8157

g. Manager / Emergency Services Don Stamper 882-6003

h. Assistant Manager /Emergenty Center Joan Draka-Olsen 882-6003 EKT-Paramedic, Flight 1. Obtain survey meters (available in Staff IE27E, IE27C, and both ambulances) and prepare to survey for contamination.

Housekeeping 1. Cover floor aress with absorbent paper / plastic covering in areas directed by charge nurse.

2. Seal edges with masking tape.

3. Set up disposal hampers with double plastic bag.

4 Assist in delivery of radiation emergency equipment.

(

Security 1. Prepare to cordon off all areas through which contaminated l

T patients must travel prior to f decontamination.

Plant Engineering 1. Prepare to shut off air circula-tion system in the emergency ca're area as directed.

L

Jus =muur c W Hospital

& Clinics n

p - . Subject _.. -- -

__ felicy,No% _ Dage-- r- _

I l EMERGENCY CENTER RADIATION DISASTER PLAN 585 3 g, 3 PROCEDURE:

! Emergency Center . 1. Direct patient care (keeping A t r a 2' N Phyd M w-- p e rs onne L_who_co n t a ct_.p a tic _n t ___

prior to decontamination to a i

minimum). In general, life

, threatening situations should l be cared for and patients stabilized prior to full -

decontamination. Govns, gloves, I operative mask and hat should provide sufficient barriers for short term contact and prevention of staff contamination. Any perscnnel contacting patient prior to da. contamination should '

remain in the area uneiI radioactive monitoring is completed.

Health Physic Service 1. Supervise monitoring and -

Personnel decontamination of patients and I overall handling of contaminated  ;

materials. l l

2. It may be necessary to use the staff shower and bathroom in the Emergency Center for decontami-nation procedures. If this is I deemed advisable, the patient will l be vrapped in a protective sheet I and taken by gurney or wheelchair to the lounge entrance to the  !

shower. Following showering decontamination, the patient will egress via the office area

.ad be monitored at that point.

All contaminated clothing, shower materials and water vill be handled at the direction of the Health Physics personnel.

? - - -. - . .._ __ .. -_

s~ w w www www w w w. w% s%

AUTHORITY TO IMPLEMENT RADIATION DISASTER RESPONSE PLAN

- -AD M I N ! S TR AT O R - O N- D U-T-Y-tA O D-)-- -- - --

1 -

l It will be the responsibility of the Administrator-on-D uty to activate the Radiation Disaster Plan (three (3) or more victims) and assemble a command post (if needed).

TELECCNMUNICATIONS

. When notified b:' the AOD, operator will initiate Radiation disaster call list.

~

Other key departmental calls are assigned throughout tae pTen.

Call IIst should notify all departments , per page 09, so forewarned .

Housekeeping, Security , AOD, Maintenance , and House Manager-Nursing can '

be notified via 0500 beepers.

1

a. Beep 0500 (designate);

b. Contact Health Ph:' sics (3-7201 during the night cnd en weekends I contact the CONTREY 6 opet' tor);

c. Radiologist Cn Call (Resident and Attending);

d. Emergency Center (2-3001);

e. Admissions (2-8181);

f. Nursing Service Office (2-7183); and

g. Public Relations (2-1081).

3

d -

RADIATION EQUIPMENT AND SUPPLY LIST HOUSEKEEPIMG

~~

tte,3,i vivenwooning anninmant l

l SEC URITY

1. Equipment for raping off contaminated area.

VA HCSPITAL

1. Two large drums containing ' Radiation Cisaster supplies will be stored in -

the VA research area.

EMERGENCY SERVICES

1. Monitoring equipment: A. Survey meters

• 3. TLD Badges '

C. Pen Desimeters"

2. Large 6' x 2' pan to be placed on stretcher (optional)

Large scrub basins (various sizes)

Large drums to col'ect wash water Plastic floor covering or absorbent paper (sufficient to cover a large flcer and entrance area)

Labels marked "Radioactive - DO NOT DISCARD" 1 Soft brushes for scrubbing Disposable surgical drapes (saff-adhesive)

Long forceps l Gowns, masks, head and shoe covers, gloves, plastic aprons  !

Plastic (saran wrap) for wrapping probe of survey instrument l Tide, Cloro::

Irrigating solutions Cotton tipped applicators Glass and plastic containers (for hair, tissue samples) l Disposable hamper l l Large plastic trash bags l Twist ties Labels marked - Radioactive l T PMstic containers witn lids l ) "

Recalibrate survey meters arinu ly - check batteries frequently l l

l Page 31

l 2

DfERGENCY HANDLING OF RADIATION ACCIDENTS ViALK-IN RADIATION PATIENTS o e mp ganc, co-to- o-H e , e-a e-.ces c# ,-o. u ,-,,,i l

l l

l s

Page 32

?' , 1 f

T- -

- .- _ _ _ y EMERGENCY HANDLING OF RAv!ATIOt! ACCIDENTS T!!REE (3) OR MORE VICTIMS 1

l ADMINISTRATOR-Orl-DUTY ( AOD) l 1. Implement Radiation Disaster Plan by callin g Telecommunications (6). I

2. Call Veteran's Hospital, ask for Associate Hospital Director. If after 4 p.m. or weekends, ask for the  ?. edical Administrative Assistant (443-2511).

3. Inform person of impending arrival of radiation patients.

4. R ec.uost clearance of Animal Research area for immedia:e cccupancy by CMHC staff.

V.A. ASSOCIATE DIRECTOR OR MEDIC AL ADMINISTRATIVE ASSIST ANT -

1. Give approval for UMHC to use research area.

2. Call Animal Research Area and request evacuation of designated area.

3. Call V.A. Security -

request ancillary assistance as needed at east entrance to research area.

AOD (UMCHC)

1. Call Emergency Center -

inform them of V.A. approval to p roceed (2-8001).

2. Call IIospital Director.

3. Call Chief of Staff (2-4913) .

SENIOR E'.;ERGENCY SERVICE PERSONNEL Upon receipt of call announcing momentary arrival of radiation victims, j

1. Notify:

o Manager of Emergency o Health Physics Sve. (2-7221) h Service (2-809D

/ o Security (2-7147) o Housekeeping (2-0517)

Page 33

l l

~ E.'.15RGENCY HXNDLING CF RADIATION ACCIDENTS (continued) i THREE (3) OR MCRE VICTIMS 1

SENIOR EMERGENCY SERVICE PERSONNEL (continued)

2. Obtain survey meters.

3. Designate physician / nurse teams to staff patient receiving station (V.A.

Animal Research Area). Send to area.

4. Enter VA via east entrance to Research Area. - .

RESCUE SQUAD /ENT

1. Pick up radiation accident victims.

2. If known, give number of patients anc type of radiation accident.

3. Transport victims to designated V. A. Hospital entrance (East entrance to Animal Research Area).

HEALTH PHYSICS SERVICES

1. Call Reactor Health Physics Mgr. (2-4221) if campus reactor is involved.

2. Call University-%'ide Radiation Safety Officer (2-3"21).

SECURITY l

1. Dispatch Security officers to V.A. Hospital (East entrance to Animal l Research Area) to monitor entry and exit of personnel.

2. Work kvith V. A. Hospital Security to secure internal corridors.

V. A. ANIMAL RESEARCH AREA STAFF

1. Place UMCHC Disaster drums (2) within easy access of incoming staff.

2. Evacuate area. (Rooms A-38, A-45 and A-18 will be evacuated first.)

HOUSEKEEPING

} 1. When requested, and under the supervision of Health Physics Services personnel, proceed to Animal Research Area (V. A.  !!ospital) to perform necessary nousekeeping procedures.

Page 34

l ACTION TAKEN CPON ARRIVAL OF PATIENT (S)

HEALTH PHYSICIST, PARASTEDIC, EC PERSONMEL OR FLIGliT NL*RSE

. w hew.eMot-cotTtemmatior. -i t " ;urwat4cs-6prefera hh- r patient is removed from ambulance).

3. If seriously injured , give emergency lifesaving treatment immediately. l

3. Handle contaminated patient with wound as one would- a surgical procedure, i.e. , gown , mask, cap , double gloves , etc.

.i . If external contamination is involved, save all clothing and bedding : rom ambulance, bicod, urine, stcci, vomitus, and all metal objects (e.g. , with name, body Iccation, :ime and date. Save each in approorir.te containers:

mark containers cicarly, "P.adioactive - Do Not Discard." ':arking may be made with adhesive pasted to cloth bag or hamper inside of tyhich is a plastic disposable bag.

5. Decontamination should start , if medical status permits, with cleansing l and scrubbing (2-3 minutes of lathering to hair and intact skin) the area of highest concentration first. If an extremity alone is involved, clothing may serve as an effective barrier and the affected limb alone may be scrubbed and cleansed. Initial cleansing should. be done with soap and warm water . " Wash water waste , unless marked Radioactive , may be flushed into community seware system where dilution will obviate any ha:arcous eIfect. If tne c 'ocy as a whole is involved , or clothing generally permeated by contaminated material, showering and scrubbing v;ill be necessary. Pay special attention to hairy parts, body orifices, and body folds. Decontamination of eyes, ears, nose and mouth require irrigation with copious quantities of irrigation solution or water.

F.emeasure and record measurement after each washing or showe ring.

If a wound is involved, prepare and cover the wound with self-adhering disposable surgical drape. Cleanse neighboring surfaces of s! tin. Seal off cleansed areas with self-adhering disposable surgical drapes. Remove wound covering and irrigate wound with sterile salino , catching the irrigation fluid in a basin, and handle as described in item 4, above.

Each step in the decontamination process should be preceded and followed by monitoring and recording of the location and extent of contamination.

, 6. Save nurses', physicians' and attendants' scrub or protective clothing, as l described for patients (4). Nurses, doctors, and attendants must follow the same monitoring and decontamination routine as tne patients.

A paste of Tide detergent and water may be used.

l ~ ~ - -

Page 35

ACTION TAKEN UPON ARRIVAL OF PATIENT (continued )

flealth Physicist, Paramedic. EC Personnel or Flight Nurse (continued)

~

If-th e - p hysien Mn:.a t te n danca -ir - t h a- E me rga n ny._Can t a " -k - co n f:or. tad _ wit h -- -

a grossly centaminated wound with dirt particles and crushed tis sue ,

he/she should be prepared to do a preliminary simple wet deb ridement .

An emergency minor surgier.1 set would be used. Further measurements may necessitate sophisticated wound counting _ detection , instruments supplied by a consultant" who will advise if further definitive debridement s necessary.

=

Health Physics Personnel will serve as consultants in the event that ractation victims are treated at UMCHC. Their e.xpertise includes the area l of:

{

1. Use of radiation monitoring eouipment.

2. Logistical direction of patients treated and area to be utilized.

3. Directing disposal of radioactive waste.

4. Directing clean-up effort ter ensure radioactive-free environment. ,

1 l

l l

Page 36

\

l 7%  :

%  % ==.

} _=

OPERATION RAIN-FAL MUTUAL AGREEMENT - VA HOSPITAL /UMCHC

1. The UMCHC Administrator-On-Duty will have the authority to request use

_.- of th- "2 >_ Jmmuaser9 3.:e a ei heed- escomes-= evident -

2. The V.A. Associate Hospital Director-On-Call, or the V.A. Medical Administrative Assistant will be authori:ed to receive and act upon the above request.

3. When approval has been given to utilize the ARA, the V.A. re p re-sentative will alert that area to evacuate staff from the premises.

( 4. UMCHC physicians and nurses will staff the arria for initial r.reatment cr.d t-iage of the radiatten victims.

i

5. Radiology equipment and treatment room equipment in the AF.A will not be ,

l used (tables in each of these areas may be used).

6. The V.A. will store two UMCHC Radiation Disaster D rums , p roperly maintained and labeled, for easy access in the event of a disaster. These drums will hold supplies needed to treat radiation victims. Minimal quantities of V.A. supplies (4x4's, tape, etc.) may be used.

7. V.A. and UMCHC Security will coordinate both internal and external security requirements.

I S. After decontamination , patients requiring hospitali:ation will be transported via stretcher and V.A. Tunnel to UMCHC for admission .

l Patients requesting admission at V.A. and fulfilling their admission criteria will be admitted to the V. A. Hospital.

9. Decontamination of the ARA after victims have vacated the area will be

! supervised and directed by Health Physics Services personnel and l designated V. A. hospital personnel, and both UMCHC and V. A. house-i keeping personnel will be involved in the actual cleanup process.

10. The V. A. Radiation Safety Officer will officially declare the ARA safe for resumption of routine activities. I

11. Any victim that is dead on arrival or that expires during the treatment period will be transported to the V, A. morgue. i 1

i l

l Page 3" I

l

\

.'V. A Animal Research Area I

i h/ ** #***'*** *8'"

-~"

8/ usa a

~

s.ese f a.asa

'~

e*2a

{ '**~ . . g*f T A 60 A A 80.

p# h l

a. s . . .

E'''888'_

$. . .".'p' ' q (!"_Nc g tN!st . asoffi ental

. .~ , c ,. .u . -

w., .g , ,,

. (cCut45 **8 *"*a6 6 430 *=62C

...a. E shoo spaca ***"*M .*S 7 N 8 -

re er ""

M

.aS c 6ac a s.es I -

~<-  : A

-~sy g

4 p m g,Weh i  ::n" i _

g q". .s East *M *** ,

4

_ . ' . .~ _" . gh -

.... !, *'* *- ** l * .e , a es _

M __ L l *sa -s.

coyr p ..

,ay*=f to st.s (,.,,t tree as ees.rgc.a e . sg e

n , ..

[;.s... . _ g~g 1s.

ymQw . w.-

i8

~, I " " a [.,4*****"l l AocM a**

a.

\' i a Araz --

y Q - --

e _ce*, .ee es .o a.2 Qs fa: 4-.s

., ~.

.r

• - l 4

l.== -

a

. ,.,[.~p

.., 3

. ., 3 t

4

, . .w-a **.au 6s oL i

""" 4 4.%.

.-.esaus -

4. n es. ,a was

.. l .. s., ~~ n2 .!,, 7 '** - 6'*

3o.  ;

pg g. .' nm *

' ggggggg SICa.gA

• • es.ej ee.e. and

'" ,8 6&E f e9-.nst as & -8*" hNID I.

6 l 5 '#--o'<* E'1 d  : .s.. L4aceAror

• B " S

• -

• I ** * * :g.....,..'**---S-y 3 I

< =

%*-* * **,%"L" a' ' '-*

• ***l*

p,;'*=* *, ' g' **- **=

"* j a

, l = a'm.e i. en-we

^ "'"* Q*

• • '**4-

• ,~,Q~ =d w I

j

~ - - '

, ,. .a=* .;._ '****^*"' * .

• tS t.

• • ""~ pg ( j

[,j ass . T. 4.ca oen a i.. '

a .

m ,' d I v, ,..-u -.-_ s 3 ,..

- =4 .r-*=

-" A . . _

. G.' .. .'c........

- ~ k%1..a . .. _

gg,

,.. --- ~

1.. 384 848 6 4 lg -,.. H . . . t - .- - .

-n s:.,,;

8 44 P gp sed e eggg , .4 gg. ,,

, ** **'*a". 4 .M a a.g e.e e "I"P""""'%

) "T"8 M l $ EE891 i ,II19 4.mg 4 a TITIVO g et b *m .

MUI.MOA/AN'I 8 I # 84 %

53 i e -j .3 Palme* D '

A s r . . %.

l Ti L A 8 sa $

g i

@ @ @ b O '

h h -

4

se

.)

Radiological Contacts ASSISTANCE may be secured from the U.S. Department of Energy's REGIONAL CO-ORDINATING OFFICES FOR RADIOLOGICAL EMERGENCY ASSISTANCE.

l Telephone and personal contacts with trained physic:aa, specialist, technicians, labora-tories, health physicists, public relations and information officer specialists are available in the following areas:

l Brookhaven Area Ofnce Chicago Operations Office Upeon, L.I., New York 11973 9800 South Cass Avenue (516) 345-2200 Argonne, Illinois 60439 .

(312) 972-4800 dutv hours

} (312).972-5731 off-duty hours Oak Ridge Operations Ofnce Idaho Operations Office P.O. Box E P.O. Box 2108 Oak Ridge, Tennessee 37830 Idaho Falls, Idaho S3401 (615) 576-1005 or

} (208) 526-1515 (615) 525-7885 Savannah River Operations Office San Francisco Operations Office P.O. Box A 1333 Broadway Aiken, South Carolina 29801 Oakland, California 94612 (803) 725-3333 (415) 273-4237 Albuquerque Operations Office Richland Operations Office P.O. Box 5400 P.O. Box 550 Albuquerque, New Mexico 87115 Richland, Washington 99352 (505) 264-4667 (509) 942-7381 Rekrences

1. U.S. Department of Energy. Emergency Handling of Radiation Accident Cases: Physicians (Prepared in cooperanon with the American Medical Assoc:ation) Washington. D.C. U.S. Covernment Printing Office.

1979.

2. Carol B. Jankowski. Radiation Emergencv. Amencan fournal of Nursing. Jan.1982, pp. 90 C.

SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT 1 July 1987 through 30 June 1988 HAZARDS

SUMMARY

REPORT (original July 1,1965)

1. Section 8.4:

Delete Section 8.4 of Hazards Summary, including two revisions reported in the 1981-82 and 1982-83 Annual Reports, and replace with the following paragraphs:

8.4 IRRADIATION BASKETS i Irradiation baskets are hoesed in various elements in the graphite reflector region. There were originally 12 removable graphite elements between Beamports "A" and "F" which could be replaced with irradiation baskets (modified graphite elements to house samples during irradiation at relatively high thermal neutron flux).

This graphite region has been modified. A large wedge shaped irradiation basket occupies two rows (30 ) of the original four row (60*) design. This wedge is an aluminum helium filled structure with six irradiation positions. Two solid aluminum elements, one with a 3 l

inch 0.0, and the other with a 1 inch 0.D. irradiation basket, occupy one of the original rows (15 ). Two pneumatic tubes terminating in solid aluminum elements and a solid small graphite element occupy the remaining row (15 ).

The remainder of the graphite reflect region (300 ) originally consisted of ten (10) 30 wedges (designated elements 1, 2, 3, 4, SA, 5B 6, 7, 8, 9) comprised of graphite canned in aluminum. Four of these 30* graphite wedges have been modified to provide irradiation baskets (positions) between Beamport "C" and Beamport "D". The graphite IIl-1

L element at position 4 has been replaced with a graphite wedge accom-f L

modating both a 2 inch 0.0. and a 3 inch 0.0. irradiation basket. The graphite elements at positions 5A, 58 and 6 have been replaced with

[

elements that each accommodate a 5-1/2 inch 0.0. irradiation basket.

{ All samples that are irradiated are verified to be covered by an approved Reactor Utilization Request (RUR), prepared and scheduled for

[ irradiation by the Reactor Services group. A record is kept of all irradiations. Various forms are utilized based on the type of sample and position required for irradiation.

2. Section 8.3:

Change the last sentence of the third paragraph from: "These installed radiation monitors report to a recorder read-out in the control room." to

( "These installed radiation monitors report to an analog readout in the control room".

The change to Section 8.3 removes reference to the multipoint recorder that was removed by Modification Package 85-6 and reported in the Hazards Summary Section of the 1985-86 Operations Annual Report.

3. Section 9.5:

Change the title of the Section from "Startup Interlocks" to "Rod Withdrawal Prohibit Circuits". Change reference to "startup interlock" to "rod withdrawal prohibit circuits" in last paragraph of Section 9.5.

4. Section 7.1.8:

Delete the following sentence in the eighth paragraph: "Either all new elements will be loaded or all elements will be turned upside down and reloaded."

!!1-2

W 6

[ SECTION IV PLANT AND SYSTEM MODIFICATIONS

[ 1 July 1987 through 30 June 1988 L

_SEP_TE_MBER 19_8_7_

Modification 87-3: This modification adds a time delay of approximately

( two seconds to the gasket inflation sequence initiated by the motor driven closing of containment isolation doors 504, 505 and 101.

This modification ensures that these motor driven containment isolation doors are fully closed and stationary before the gaskets are inflated. This time delay is designed to reduce the potential for door movement during gasket infla-tion, which might result in rolling the inflating gasket from its seat.

OCTOBER 1987 Modification 87-5: This modification replaced the cams previously used to actuate the "inflate" microswitch for the gas'Kets on doors 504 and 505 (ventila-tion doors) after their closing sequence. The replaced cams had a sharp point to actuate the gasket "inflate" microswitch. The potential existed when the venti-lation doors were driven closed that overdriving the cam would allow the gasket to "inflate" and then "deflate" even though the door was closed. This arrange-ment required that the door rest position after closing be in a narrow band of location. That is, the gasket inflation point was very sensitive to door rest pjsition after closing.

The new cams were designed with a long lead lobe to provide continuous mie.roswitch actuation. This design mechanically ensures that the "inflate" microswitch remains actuated for a broader band width of door rest positions after closing.

IV-1

FEBRUARY 1988 L

Modification 87-1: This modification replaced the original 30' reflector element number six, which was solid graphite canned in aluminum, with a wedge that accommodates a 5-1/2" diameter irradiation position. Because Beamport "D" tube penetrates the lower section of the element, the usable element space is limited to twenty inches depth in the irradiation position.

The lower hook section of the reflector element that previously encircled Beamport "0" is also removed in the new element. This permits removal of this reflector element without withdrawing the beam tube.

( The outer envelope dimensions of the new reflector element (with the exception of the lower hook) are identical to the element it replaces. The side and wall thicknesses of the aluminum cladding remain .125 inches. In an effort to obtain a specific neutron flux spectrum, shielding material is added around the irradiation hole. This shielding consists of tantalum sheets, cadmium sheets and indium. The graphite log of the original element is replaced by a titanium log in the new wedge design.

Modification 87-2: The modification added design changes to the existing

)

offset mechanism that is used to position the boron carbide control blades adjacent to the pressure vessel.

The offset arm assembly was changed to allow the pull block and guide tube to be placed 5-1/2" further from the pressure vessel than previous offsets. In addition, the offset arm was dog legged to allow access to the reflector irradia-tion elemerits directly below the offset mechanism arm. The pull block, pull rod, blade arm and centerbalance ann weights were designed so that the change in the I magnet pull weight and the static balance is changed insignificantly from pre-vious offsets.

IV-2 ,

Y A shield plate attached to the gelde tube is added to form a protective L cover around the offset arm to prevent inadvertent contact with the blade arm and prevent any object fre- f alling onto the arm and causing it to wedge.

The offset uses the same blade, meets the same drop time requirements, uses the same alignment stand mounts to the reflector tank in the same way and is constructed of the same materials as existing.

{

l l

l l

4 IV-3

L I

)

SECTION V NEW TESTS AND EXPERIMENTS 1 July 1987 through 30 June 1988 There were no new tests or experiments initiated during this period under the conditions of 10 CFR 50.59.

J t

V-1

l 1

SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1987 through 30 June 1988

1. SNM Receipts: A total of 23 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.

Grams Grams

( Shipper Elements U U-235 B&W M0249, M0250, M0251, M0252, M0253, 19,055 17,750 M0254, M0255, M0256, M0257, M0258, M0259, M0260, M0261, M0262, M0263, M0264, M0265, M0266, M0267, M0268, M0269, M0270, M0271

2. SNM Shipments: A total of 23 spent fuel elements were shipped to Savannah River Plant, Aiken, South Carolina, for reprocessing.

Grams , Grams Shipper _ Element _s

__ __ _ _U _ _

__ U _2 3 5 _

MURR M0133, M0135, M0141, M0142, M0145, M0146, 15,479 13,492 M0147, M0148, M0149, M0200, M0201, M0202, M0203, M0204, M0206, M0207, M0208, M0209, M0210, M0212, M0214, M0219, M0221 One unirradiated fuel element (M0241, 828 g U, 772 g U-235) was returned to Babcock and Wilcox on 8/7/87 for salvage.

3. Inspections: There were no routine safeguards inspections conducted by the Nuclear Regulatory Commission (NRC), Region III office during the time period 1 July 1987 to 30 June 1988. The MURR Special Nuclear Material Control Pro-cedures were reviewed by the Procedures Review Subcommittee (of the Reactor Advisory Committee) as per the annual requirement.

4 SNM Inventory: As of 30 June 1988, MURR was financially responsible for the following 00E owned amounts:

Total U = 42,067 grams Total U-235 = 37,639 grams VI-1

Included in these totals are 36 grams of U and 34 grams of U-235 non-fuel, 00E owned. In addition to these totals, MURR owns 156 grams of U and 74 grams of U-235 All of this material is physically located at the i"JRR -

Fuel elements on hand have accumulated the following burnup as of 30 June 1988:

MWD MWD MWD M0143 139.62 M0233 144.15 M0254 77.62 M0205 128.57 M0234 104.00 M0255 75.90 M0211 148.38 M0235 104.95 M0256 77.62 M0213 148.38 M0236 112.29 M0257 75.90 M0215 147.55 M0237 104.95 M0258 84.15 M0216 147.71 M0238 112.29 M0259 58.89 M0217 128.57 M0239 101.91 M0260 84.15 M0218 147.71 M0240 101.91 M0261 58.89 M0220 147.69 M0242 96.80 M0262 69.08 M0222 147.69 M0243 96.94 M0263 50.44 M0223 147.55 M0244 96.80 M0264 69.08 M0224 146.95 M0245 96.94 M0265 50.44 M0225 146.95 M0246 98.22 M0266 9.49 M0226 139.62 M0247 78.22 M0267 0.50 M0227 140.26 M0248 98.22 M0268 9.49 M0228 138.41 M0249 78.22 M0269 0.50 M0229 140.26 M0250 93.20 M0270 0 M0230 138.41 M0251 99.04 M0271 0 M0231 144.15 M0252 93.20 M0232 104.00 M0253 99.04 Avg. Burnup 97.96 MWD

, VI-2

SECTION VII

(

REACTOR PHYSICS ACTIVITIES 1 July 1987 through 30 June 1988

1. Fuel Utilization: Ouring this period, the following elements reached licensed or feasible burnup and were retired.

Serial Number Final Core Date Last Used MWDs M0143 88-14 3-24-88 139.62 M0211 87-54 10-22-87 148.38 M0213 87-54 10-22-87 148.38 l M0215 87-74 1-07-88 147.55 M0216 87-73 12-31-87 147.71 M0218 87-73 12-31-87 147.71 M0220 87-51 10-08-87 147.69 M0222 87-51 10-08-87 147.69 M0223 87-74 1-07-88 147.55 M0224 88-7 2-11-88 146.95 M0225 88-7 2-11-88 146.95

\

M0226 88-14 3-24-88 139.62 M0227 88-11 3-10-88 140.26 M0228 88-25 5-26-88 138.41 M0229 88-11 3-10-88 140.26 M0230 88-25 5-26-88 138.41 M0231 88-21 5-05-88 144.15 M0233 88-21 5-05-88 144.15 Due to the requirement of having less than 5 kg of unieradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel VII-1

1 elements of which only the initial critical fuel element serial numbers are listed in the following table. To increase operating efficiency, fuel ele-

[ ments are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.

Fabrication Serial Initial Core initial Core No. No. Load Number Operating Date 46 M0246 87-31 7-02-87 46 M0247 87-43 8-25-87 47 M0248 87-31 7-02-87 47 M0249 87-43 8-25-87 47 M0250 87-45 9-03-87 47 M0251 87-60 11-02-87 47 M0252 87-45 9-03-87 47 M0253 87-60 11-02-87 47 M0254 87-61 11-05-87 47 M0255 87-74 12-31-87 48 M0256 87-61 11-05-87 48 M0257 87-74 12-31-87 48 M0258 87-74 12-31-87 48 M0259 88-11 3-03-88 48 M0260 88-74 12-31-87 48 M0261 88-11 3-03-88 48 M0262 88-12 3-10-88 48 M0263 88-21 4-28-88 49 M0264 88-12 3-10-88 49 M0265 88-21 4-28-88 VII-2

w e

L

2. Fuel Shipping: Twenty-three spent fuel elements were shipped from MURR to i

L Savannah River Plant, Aiken, South Carolina. The identification numbers of these elements are:

M0133 M0147 M0203 M0210 M0135 M0148 M0204 M0212 M0141 M0149 M0206 M0214 M0142 M0200 M0207 M0219 M0145 M0201 M0208 M0221 M0146 M0202 M0209

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 1988, seventy two fuel assemblies fabricated by B & W t.ad been received and sixty five used in cores at 10 MW. One element was returned to Babcock and Wilcox for salvage.

4. Licensing Activities: A request for an increase in Special Nuclear Material Inventory under our Facility License submitted in December,1982 was withdrawn. A revision to Technical Specifications 4.4.d requiring two operating parallel pool pumps submitted in February,1982 is pending. A revision to Technical Specifications which involves changes which are editorial in nature was submitted November 22, 1985 and is pending. A sub-mittal was made September 12, 1986 pertaining to the new MURR fuel design and associated revisions to the Technical Specifications. The fuel design is currently being evaluated by Nuclear Regulatory Commission's subcontract-or, Therefore, this submittal is also pending. A request for a unique purpose exemption as defined in 10 CFR 50.2 was submitted September 26, 1986 and is pending.

VII-3

N

?

L

5. Reactor Characteristic Measurements: Seventy five refueling evolutions r

L were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 2.1%. MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.

Reactivity measurements were performed for 70 evolutions to verify reactivity parameters for the flux trap. Four shim and regulating blade calibrations were performed.

A physical inspection of the following fuel element was performed to verify the operational parameters.

M0216 from Core 43 during November 1987 All measurements were within operational requirements.

l P

VII-4

L I

SECTION VIII L

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT

( Sanitary Sewer Effluent k

1 July 1987 through 30 June 1988 Descending Order of Activity Released Nuclide_ _Am_ount (Ci) Nuclide_ _ Amount _ JCi_)

H-3 7.70E-02 Sc-46 1.23E-04 S-35 5.19E-03 Zn-65 1.09E-04 Te-125M 5.91E-04 Na-24 1.03E-04 As-77 4.05E-04 Ag-110M 7.27E-05 Eu-152 3.90E-04 Rh-105 4.49E-05 Sb-124 1.61E-04 Eu-152M 3.02E-05 f Ru-105 1.20E-04 Sb-122 2.72E-05 Cc-51 1.19E-04 Sb-125 2.44E-05 Co-60 1.64E-04 Se-75 2.29E-05 Cd-109 1.22E-04 Gd-159 1.22E-05 Re-186 1.19E-04 VI!!-1

?

Stack Effluent I 1 July 1987 through 30 June 1988 Descending Order of Activity Released for Nuclide Levels Greater than 10-4 Ci flu c l_ide_

Amount _(Ci)

Ar-41 8.134E+02 H-3 1.450E+01 Xe-135M 1.405E-02 I-134 7.332E-03 C1-38 6.445E-03 I-128 4.782E-03 I-135 2.311E-03 I-132 1.812E-03 J I-133 9.246E-04 Cs-138 8.517E-04 Xe-138 6.794E-04 Rb-88 6.531E-04 As-77 6.148E-04 Ba-139 1.441E-04 I-131 1.341E-04 Stack Flow Rates:

7/01/87 to 5/25/88 16,200 cfm 7/26/88 to 6/30/88 17,100 cfm NOTE: Beginning July 1,1987, calculations were made utilizing a Nuclear Data program for air filter analysis which in-cludes the correction for decay of isotopes during filter collection, assuming constant release rate. This cor-rection has the greatest effect on the estimated release for isotopes with short half-lives, making them appear to have had a higher release than last year. The difference is due to use of this new method of decay correction, and not to an increase in release.

VI!!-2

b

(

SECTION IX

SUMMARY

OF ENVIRONMENTAL SURVEYS 1 July 1987 theough 30 June 1988

, Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. Those locatfors 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.

10 Sampled during October 'i98~.

Det_ection_ _L_imi ts*

Matrix Alpha Beta Gamma Tritium Water 0.5 pCi/l 1.6 pCi/l 188.2 pCi/l 12.7 pCi/ml of sample So i'i 0.9 pCi/g 2.5 pCi/g 2.1 pCi/g N/A Vegetation 1.8 pCi/g 5.3 pCi/g 2.8 pCi/g 12.7 pCi/g of distillate

• Gamma and tritium analyses are based on wet weights while alpha and beta analysis are based on dry weights.

Determi_n_ed __Ra_dioac_tivity Lev _els le_getation samp1es Sample Alpha Beta Gamma Tritium (DCi/g) (pCi/g) (pCi/g) (pCi/g) 1-V-32 < 1.8 13.8 < 2.7 < 12.7 2-V-32 < 1.8 11.1 < 2.7 < 12.7 3- -32 < 1.8 30.0 < 2.7 < 12.7 4-V-32 < 1.8 12.2 < 2.7 < 12.7 5-V-32 < 1.8 12.0 < 2.7 < 12.7

( 6-V-32 < 1.8 20.9 < 2.7 < 12.7 7-V-32 < 1.8 22.6 < 2.7 < 12.7 4

10-V-32 < 1.8 24.3 < 2.7 < 12.7 k IX-1

- - - _ - wu

~

D g .

1 u. ',

j ' ,'i fg-

~~.

W _____j_

- if D ' . ,'o ,

s '

- .i Y

i sm 5

i(  ; -.

5~ -L, ,. N-4

~ . j-V 1 1 -

~Y b 1

hit <

% / A [}_____l %jJb T 4

d

% e , .

_-g ~~

w ~

_e.

gr y

i

~

s r [,,,g!

I j a'i f

~ .... &T n -

-=11 T '

. ..e A &

, a I. O ee .

.e

\

' L '

< 0 ' "\

, .i .- ',,

l ,, '

MORR'1 .

s I

~ i w **\*g d p t 1 ,

\

i I a 5,

.\ /: 'q """'" g = , __ -g- -

=

m T~ .. c'\ / ..

i  :

[--t -s w g x _r--,y' ,

, < . = = ____.1l.s i

\ y 1 i

_ _ - - gl n- ?- -

Figure i- MORR Environmenta1 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.

l J

Dete_rmined _Radi_oa_ctivity Levels 5011 5amples _

s Sample Alpha Beta Gamma (pCi/q)_ (DC1/g) (pCi/g) 1-S-32 < 0.9 11.5 8.9 2-S-32 0.9 18.3 9.9 3-5-32 < 0.9 11.4 8.8 4-S-32 1.0 12.0 4.0 5-S-32 0.9 13.6 9.4 l

l 6-S-32 < 0.0 11.1 6.7 7-5-32 1.7 20.7 7.9 10-S-32 < 0.9 11.0 9.1 4

_Det_ ermined Radioactiv_ity Levels Xater_ _5 amp 1_es Sample Alpha Beta Gamma Tritium (pCi/1) (pCi/1) (pCi/1) (pCi/ml) 4-W-32 < 0.6 3.9 < 188.2 < 12.7 6-W-32 < 0.6 4.8 < 188.2 < 12.7 10-W-32 < 0.6 17.9 < 188.2 < 12.7

2. Sampled during April 1988.

_D_et_ection Limit _s*

Ma_tr i x __ Al_p h a_ _ _, __Be_ta_ _ __ _ Gamma _T_ri t ium Water 0.5 pCi/l 2.0 pCi/l 214.7 pCi/l 14.5 pCi/ml l of sample Soil 0.5 pCi/g 2.0 pCi/g 1.6 pCi/g N/A Vegetation 1.4 pCi/g 5.4 pCi/g 3.2 pCi/g 14.5 pCi/g I

of distillate i

• Gamma and tritium analyses are based on wet weights l

while alpha and beta analysis are based on dry weights.

I 1

l l I

IX-3 j I

l

, _ _ , ,_ .~- __ _

u I

O_etermined Ra_d_i_oact_iv_ity Lev _els.

vegetation samples ___

l Sample Alpha Beta Gamma Tritium (p

_ _ C_1/_9 )_ (pCi/g)__ (pCi/g) (pCf/g)__

1-V-33 < 1.4 12.0 < 3.2 < 14.5 2-V-33 < 1.4 20.9 < 3.2 < 14.5

( [

3-V-33 < 1.4 20.2 < 3.2 < 14.5 4-V-33 < 1.4 26.1 < 3.2 < 14.5 5-V-33 < 1.4 21.0 < 3.2 < 14.5 6-V-33 < 1.4 20.5 < 3.2 < 14.5 7-V-33 < 1.4 23.2 < 3.2 < 14.5

{

10-V-33 < 1.4 30.6 < 3.2 < 14.5 Determined Radi_oa_c_tivity Levels

_5o11 Samples Sample Alpha Beta Gamma (pCi/g)_ (0C1/g) (pC i/_g )_

1-S-33 1.0 13.1 5.2 2-S-33 0.6 12.4 4.5 3-S-33 < 0.5 9.7 5.1 4-S-33 < 0.5 6.6 2.6 5-S-33 < 0.5 14.7 4.4 6-S-33 < 0.5 8.6 3.7 7-S 33 < 0.5 9.5 4.9 10-S-33 0.8 13.4 6.3 i

d IX-4

I 1

I Determined Radioactivity Levels Water Samples L

Sample Alpha Beta Gamma Tritium ,

s (pCi/1) (pCi/1) (pCi/1) (pC1/ml) I 4-W-33 < 0.5 6.4 < 214.7 < 14.5 1 6-W-33 < 0.5 5.1 < 214.7 < 14.5 10-W-33 < 0.5 3.1 < 214.7 < 14.5 l Environmental samples were also collected around Sinclair RAD WASTE Facility 1

at four locations. Soil and vegetation samples were taken at each location.

Results of these samples are shown in the following tables, i

1. Sampled during October 1987 Detection Limits

• Matrix Alpha Beta Gamma Tritium Soil 0.6 pCi/g 1.7 pCi/g 2.1 pCi/g N/A Vegetation 1.4 pCi/g 3.9 pCi/g 3.6 pC1/g 12.7 pCi/g

• Gamma and tritium analyses are based on wet weights i while alpha and beta are based on dry weights.

Determined Radioactivity Levels Vegetation Samples Sample Alpha Beta Gamma Tritium (pCi/g) (pC1/g) (pCi/g) (pCi/g) l SF-1-V6 < 1.4 21.3 < 3.7 < 12.7 I l

l SF-2-V6 < 1.4 13.5 < 3.7 < 12.7 l

l SF-3-V6 < 1.4 14.3 < 3.7 < 12.7 SF-4-V6 < 1.4 10.5 < 3.7 < 12.7 l

l I

1 1

IX-5 l

Determined Radioactivity Levels Soil Samples Sample Alpha Beta Gamma (pCi/g) (pCi/g) (pCi/g)

SF-1-S6 < 0.6 18.0 10.7 SF-2-S6 0.7 15.6 10.2 SF-3-S6 < 0.6 19.2 8.5 SF-4-S6 0.7 13.3 8.7 1

2. Sampled during April 19C8.

Detection Limits

• l Matrix Alpha _

Beta ,

Gamma Tritium Soil 0.5 pCi/g 2.0 pCi/g 1.7 pCi/g N/A

, Vegetation 1.4 pCi/g 5.6 pC1/g 3.0 pCi/g 14.5 pCi/g

( *Gauma and tritium analyses are based on wet weights '

while alpha and beta are based on dry weights.

Determined Radioactivity levels vegetation damples 1

Sample Alpha Beta Gamma Tritium  !

(pCi/g) (pCi/g) (pCi/g) (pCi/g) j 1

SF-1-V7 < 1.4 15.9 < 3.0 < 14.5 l 1

SF-2-V7 < 1.4 31.4 < 3.0 < 14.5 SF-3-V7 < 1.4 23.5 < 3.0 < 14.5 SF-4-V7 < 1.4 21.7 < 3.0 < 14.5 i

IX-6

._ -_ ._ _ - _ ~ . , . _ - - - . . . _ _ , . - _ . _ _ . _ _ - - . ~ . - _ - _ - - _ . . --

.) '

s

, _De_termi_n_e_d Ra_dioactivi_ty levels sol _L sam _ples Sample Alpha Beta Gamma (pCi/g) (pCi/g)_ (pCUg)__

SF1-S7 < 0.5 15.7 5.6 s

SF2-S7 < 0.5 4.0 < 1.7 SF3-S7 < 0.5 15.8 5.4 SF4-S7 1.1 17.1 6.5

( _ Radiation and Cont _ amin _ation Surveys The following table gives the number of surveys performed during FY 87-88.

Radiation Surface Contamination Air Samples 2

July 45 40 24 August 25 22 21

! September 52 48 22 October 52 46 22 November 47 37 21 December 62 58 23 January 21 18 21 February 36 18 21 March 57 42 23 April 35 29 21  !

May 37 37 22 l

June 62 53 22 TOTALS 531 448 263  ;

184 Radiation Work Permits were issued during the year.

l l

IX-7 l

m _ ._. _ _

Miscellaneous Items As of December 1,1987, John Ernst was promoted from Health Physics Technician to Health Physicist. Jim Schuh, who is assigned full responsibilities associated with Reactor Chemistry, was promoted from Research Specialist to Senior

.Research Specialist as of Maren 1, 1988. A new Health Physics Technician position was created and job interviewing to fill this position is currently underway.

Health Physics Procedure #3, "Receiving and Opening Packages of Radioactive Material," was revised to provide an additional check to verify authorization to receive the quantity of radioactive material. Health Physics Procedure #16, l "Surveying Containers of Radioactive Material for Transport by Common Carrier,"

was revised to remove the list of persons qualified to perforrr this procedure and eliminate the need to continually revise this procedure whenever people are added or deleted from the list.

ADC0 Services, Inc. has continued to act as our institutional waste broker.

Through ADC0, MURR made nine shipments and disposed of 599.1 cubic feet of LSA material generated at MURR.

A hand exposure exceeding 10 CFR 20 limits (see Summary of Radiation l

Exposures, Permanent Issue, TLD Finger Ring, July) occurred under our Byproduct Material License 24-00513-32. To prevent recurrence of the violations cited due to this exposure, subsequent processing of radioactive materials greater than 100 mci were performed under RWPs until written approved procedures were established for these processes. The number of RWPs issued for 87/88 were therefore signifi-cantly higher due to this requirement.

The MURR production and processing of radioisotopes used in radiopharmaceu-ticals has increased in number of samples and total activity handled over the past two years. The effort to improve ALARA in the handling of these isotopes has also increased. This isotope work is performed either totally under the reactor IX-8

a.

r s

license if no separation of the radioisotope is needed, or is transferred to our byproduct materials license if further processing of the radioisotope at MURR is needed. The isotopes chosen for this purpose are primarily beta emitters with some also emitting gamma radiation. Procedures for handling these isotopes include shielding the hands from the source for as much of the time as possible.

Because the TLD ring badges may require a correction factor to be applied to known beta dose readings and cannot differentiate between beta and gamma doses, Landauer's 'L" or "K" badges have been used as wrist badges to provide a qualitative measure of the radiation dose type, i.e., beta, bremsstrahlung, and gamma. Ring badges are worn on each hand to determine the extremity dose. Use of the wrist badges have confirmed no beta doses associated with most of these isotope procedures. The processing of these isotopes is performed in gloveboxes, making it difficult to obtain dose rate measurements to the hands. An Eberline R0-7 Ion Chamber with a Mid-Range Detector (full scale reading of 199.9 R/h) was installed in one of the processing gloveboxes which now provides more precise dose rate measurements to assess possible exposure to the hands and help in 1 developing movements and shielding to maintain ALARA dose to the hands.

Formal training for members of the Health Physics Group include the following:

J

1. S. Langhorst attended the Health Physics Society Summer School entitled, "Practical Statistics for Operational Health Physics", which l

was held July 13 -17, 1987 in Pocatello, Idaho. This course covered l l

1 l how to effectively apply various types of problems encountered in '

health physics measurement programs.

2. R. Stevens attended FEMA Course Number 9 (FY-87) entitled, "Radiological Emergency Response Course for Radiological Emergency

, Response Teams", wnich was held July 15 -24, 1987 in las Vegas, Nevada.

l l

t IX-9

The course included such topics as basic concepts, dosimetry, emergency b team organizations, instruments, and SCBAs. The course also included participation in exercises designed to simulate possible accident situations.

3. J. Ernst and seven other MURR staff attended a day long class provided

[

by the Columbia Fire Department on "Emergency Breath)ng Apparatus .

Training" held July 29, 1987. The training included classroom instruc-tion, donning and removal of SCBAs, an exercise in a burning building and an exercise in controlling contamination and protecting personnel l 1

from a hazardous chemical spill.

4. S. Langhorst and three other M'JRR staff attended a Federal Express l Seminar on "Transportation of Dangerous Goods", which was held March l

8-9, 1988 in Xansas City, Missou-i. The seminar included review of l regulations from Title 49 Code of Federal Regulations and the International Air Transport Association, as well as Federal Express I requirements for shipping these materials, i

{

IX-10

SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS l 1 July 1987 through 30 June 1988 l 1. Largest single exposure and average exposure are expressed in millirem.

l 2. Minimal exposure is defined to be gamma < 10 mrem; beta < 40 mrem; neutron < 20 mrem.

! 3. ME = Number of monthly units reported with minimal exposure.

( 4 AME = Number of monthly units reported with exposure above minimal.

5. AE = Average mrem reported for all units above minimal.

6 IIE = liighest mrem reported for a single unit for the month.

PERMANENT ISSUE FILM-BADGES E.e.t,a2fr p,ha Neutron _(D_e,eg)_Who1ebody_Badqes:

JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE ME 106 98 121 99 111 115 109 113 142 101 110 108 AME 69 76 55 ";6 48 42 45 55 51 58 49 50 AE 61 63 62 62 71 84 88 73 54 46 70 63 ilE 160 230 150 250 220 480 290 190 210 150 200 220 Beta and Gamma (Deep) Wholebcdy B_adges_:

JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. HARCH APRIL MAY JUNE ME 64 64 68 69 56 54 47 71 58 56 58 57 AME 4 4 1 2 2 3 3 5 3 5 1 3 AE 25 17 10 15 15 17 27 25 45 18 30 17 IIE 40 20 10 20 20 20 60 60

~

50 40 30 20 TLD Finqer Rings *:

JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE i

l NE 51 63 83 129 124 119 118 73 119 100 142 78 i AME 62 49 67 89 51 91 84 72 101 83 145 72 AE 792 191 137 166 155 237 208 183 168 134 149 125 llE 35600** 830 570 890 550 2690 1550 1260 1770 890 2950 540

• Includes monthly and bi-weekly issued ring badges.

• • See Miscellaneous Items

( X-1

SPARE ISSUE FILM-BADGES Beta. Gamma. Neutron (Deep) Wholebody Badges:

j JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE ME 38 38 43 45 44 42 46 25 44 45 40 24 AME 7 5 2 0 0 3 4 9 1 0 AE 39 20 50 5 6 0 0 307 110 80 10 0 42 87 HE 70 30 90 0 0 450 200 160 10 0 140 150 Beta and_ Gamma (Deep) Wholebody Badges:

JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE ME 30 29 29 31 31 29 46 29 29 30 30 20 AME 2 0 2 0 0 0 1 2 2 0 1 2 l AE 30 0 SS 0 0 10 0 15

, HE 20 0 10 20 40 0 70 0 0 10 0 20 20 0 10 20 l

l l TLD Finger Rings:

JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE

ME 38 18 18 27 39 31 28 24 39 37 33 34 lAME 2 18 12 2 1 11 11 8 1 3 6 6 AE 40 148 90 45 80 696 493 280 30 S3 210 227

!!E 50 470 190 60 80 2390 1200 620 30 100 450 640 SELF READING 00SIMETERS l JULY AUG. SEP. OCT. NOV. DEC. JAN. FEB. MARCH APRIL MAY JUNE ME 2 4 4 6 1 3 4 0 6

1. 8 6 lAME 77 63 63 68 73 70 68 75 74 71 71 74 l AE S4 59 59 43 59 77 61 62 39 40 60 49

'HE 247 180 180 195 235 560 404 245 171 181 208 205 X-2 x

Research Reactor Facility UNIVERSITY OF MISSOURI Resea en Pan Columbia. M ssoun 65211 August 8, 1988 Teiepnone (314> es2-4211 l

l l

U.S. Nuclear Regulatory Commission Standardization & Non-Power Reactor Project Directorate Office of Nuclear Reactor Regulation Washington, DC 20555 ATTENT10h: Lester S. Rubenstein, Director

REFERENCE:

Docket 50-186 )

University of Missouri Research Reactor

!_icense R-103

SUBJECT:

Annual Report as required by Technical Specification 6.1.h(4).

Dear Sir:

1 Enclosed are two copies of the Operations Annual Report for l the University of Missouri Research Reactor. The reporting period covers 1 July 1987 through 30 June 1988.

Sincerely, l wy J. C. FtKibben Reactor Manager Enclosures (2) xc w/ report: s U.S. N.R.C.

c/o Document Control Desk Washington, DC ge1 <

Yo

&.yG g R

m 4,@'n.jg COLUPS A K ANS AS CIT' RD LA ST LOUIS M an ena n: w, .ntm s

/