ML20114C675
| ML20114C675 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/30/1992 |
| From: | Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Weiss S NRC |
| References | |
| NUDOCS 9209030097 | |
| Download: ML20114C675 (113) | |
Text
_ _ _ _ _ _ - - _ _ _ _ _
I II Q v Research Reactor Facility UNIVERSITY OF MISSOURI .
Rosearch Park Columbia. Missouri 65211 1 Telephono (314) 082+4211 Fax (314)882 3443 August 27.1992 Scytnour II. iVelss, Director U. S. Nuclear Regulatory Cointnission PDNP M.S.11 B-20 Washington, D. C. 20555
REFERENCE:
Docket 50-18G University of Missouri Research Reactor License R-103 Dear Str; Enclosed are two copics of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers 1 July 1991 through 30 June 1992.
If you have any questions, please feel free to call.
C Qincerely, bks Walt A. Me) , J r.
Reactor Manager l Enclosure (2)
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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT AUGUST 1992 1
Compiled by the Reactor Staff
", Submitted by N$ 4r Walt A. Meyer, Jr.
Reactor Manager -
Reviewed and Approved
, ,/
/ .
. ~n
/r - J.C. McKibben Associate Director
TABLE OF CONTENTS Section Pace Number I. REACTOR OPERATIONS
SUMMARY
I 1 through I-13 II. CHANOES TO MURR PROCEDURES 111 through 117 A. STANDARD OPERATING PROCEDURES B. MURR SITE EMERGENCY PROCEDURES &
FACILITY EMERGENCY PROCEDURES C. HEALTH PHYSICS STANDARD OPERATINO PROCEDURES ';
R III. REVISIONS TO THE HAZARDS
SUMMARY
REPORT III 1 IV. PLANT AND SYSTEM MODIFICATIONS IV-1 V. NEWTESTS AND EXPERIMENTS V-1 VI 1 through VI 2
~
VI. SPECIAL NUCLEAR MATERIAL ACTIVITIES VII. REACTOR PHYSICS ACTIVITIES VII-1 through VII 3 VIII.E
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED TO THE ENVIRONMENT. VIII-1 through VIII 2-IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS IX-1 through IX-10 X.
SUMMARY
OF RADIATION EXPOSURES TO-
' FACILITY STAFF, EXPERIMENTERS & VISITORS X 1 through X 3 II
e I
SECTION I REACTOR OPERATIONS
SUMMARY
1 July 1991 through 30 June 1992 The following table and discussion summarize reactor operations in the period l 1 July 1991 through 30 June 1092. j i
Full Power Percent l Dtdo Full Power llours hieraw att jlny.A pf_ Total Time af Schedule
- July 19J1 665.75 277.73 92,17 103.23 Aug. IFJ1 669.03 278.91 89.92 100.71 Sept. 1991 623.99 260.27 86.67 97.07 0et. 1991 658.98 274.77 88.57 99.20 Nov. 1931 600.20 275.18 91.69 102.70 Dec. 1991 676.59 282.05 90.94 101.85 ,
Jan. 1992- 684.17 285.19 91.96 102.99 Feb. 1992 639.20 266.45 91.84 102.86 h1a r. 1992 666.34 27's. t 6 89.56 100.31 Apr. 1992 636.58 265.38 88.41 .99.02 '
hlay 1992 665.71 277.46 89.48 100.21 June IW2 626.98 261.42 87.08 97.53 Total for Year 7,873.52 - 3,282.57 89.63% of 100.39% of Time for Yr. Sched. Time for at 10 htW Yr. at 10 MW
- MUIUt 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 10 MW. Total time is the
- number of hours in a month or year.
There were eighteen (18) unscheduled shutdowns recorded during the year 1 July 1991 through 30 June 1992. This number is up slightly from the number of unscheduled shutdowns (15) the previous reporting year. Of the unscheduled
- shutdowns, four were Rod Run Ins (RRIs) und fourteen were scrams. ,
Eight of the unscheduled shutdowns were spurious in nature and from a variety of sources. Four spurious scrams were initiated by mechanical relay failures and two spurious scrams were initiated by falsely generated signals from meter relay trip units. Five of the unscheduled shutdowns were due to personnel errors, two -
were initiated by the duty operator in order to repair equipment, one was due to loss of facility electrical power, and two were the result of failure of the facility air compressor system which had provided air to the valve operating system for reactor and pool system valves.: A dedicated valve opeinting system air compressor was installed in February 1992 (backed up by the facility air compressor system) to increase the reliability of the valve operating system.
1- 1
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The reactor operated continuously in July with the following exceptions: five shutdowns for scheduled maintenance and refueling, and three unscheduled shutdowns.
On July 18, a pool loop low flow scram occurred due to the shutdown of pool pamp 508A, The shutdown occurred when an operator, while attempting to replace the
- 0N" indicating light on the breaker panel for pool pump 508A, caused a current surgo in the control power circuit which exceeded the interrupting capacity of the control power fuse. Th~ ffected fuse was replaced and the reactor was refueled and returned to norma' + con. The operations stairwas instructed that tasks of this type should be completed during reactor shutdown. -
On July 30, a " pool loop valve 509 off open screm" occurred t s a result of the shutdown of the main air compressor due to a breaker trip. T1.., shutdown of the main air compressorled to low air pressure in the valve operating air header which allowed tho valve 509 actuato spring to close the valve. (Wlve 500 is operated by an air-to-open, spring to-close actuator.)
When the pool recirculating system isolation valve (valve 509) left its full open seat the reactor was scrammed by a " pool loop valve 509 otf-open" scram. This scram provides a first line of protection for a loss of flow condition in the pool system (Technical Specifications 3.3 Bases). The safety system additionally provides a low pool enolant How scram and a reflector differential pressure scram to assure reactor shutdown if forced now cooling of the pool, reDector, control rods and the Gux trap is lost or reduced.
The shutdown of the reactor by the "poolloop valve 509 oft-open" scram does not present a safety concern, because natural convection flow through valve 547 into the lower plenum of the reDector tank and up through the reDector elements, control blade gaps and aux trap provides adequate enoling for these regions (Hazards Summary Report Addendum > Appendix A, Section A.3.3.14).
The men air compressor and its breakcr were examined and tested; both operated normally. The reactor was subsequently returned te normal operation, On July 31, approximately twenty four hourc after the previous shutdown, a " pool loop valve 509 off-open" scram occurred again as a result of the shutdown of the main air compressor on a breaker trip. Electronics technicians removed the hreaker and cleaned the contacts and renewed the control circuit toil.
The main air compressor motor breaker appeared to have tripped from high starting current when t.he main air compressor loaded too scou after the motor started. When the main air compressor runs in the " AUTOMATIC" mode its drive motor cycles on and off to maintain a desired pressure band. A load / unload-control regulator is designed to allow at least seven seconds between the time the breaker closes to start the air compressor motor and the time the compressor loads. This allows the motor to get to full running speed before the compressor k
12 I
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lor.ds. This control regulator was only allowing two to three seconds after the breaker closed before the compressor loaded.
The main air compressor was placed in the " MANUAL" mode which allows the motor to run continuously, with the compressor loading and unloading as necessary to maintain the desired pressure band. This mode of operation removes the susceptibility of the main air compressor to a breaker trip since the compressor motor does not have to start with the compressor in a load cycle.
The main air compressor was carefully examined in the " MANUAL" mode and tested satisfactorily. The reactor was then refueled and returned to normal operation. The main air compressor was scheduled for maintenance the following maintenance day (August 5,1991) to look at the load / unload control regulator and to replace the main air compressor breaker. This maintenance revealed that the load / unload control regulator was not functioning properly since its time delay could not be adjusted. New parts were ordered and on a subsequent maintenance day, the control regulator (which was found to have a punctured diaphragm) was repaired. This repair allows the proper timo delay between starting and loading so that the main nir compressor can run in the
" AUTOMATIC" mode without breaker trips on starting.
To increase the reliability of the source of compressed air for tha valve operating system, MURR staffinvestigated installing a new air compressor dedicated solely to the valve operating system, using the facility air system as a back up. This modification was completed February 17,1992.
A Nuclear Regulatory Commission (NRC) team conducted an announced, routine inspection of Reactor Operations activities on July 22,23, and 24. Ne violations ur deviations with NRC requirements were identified during this inspection.
On July 30 and 31, the NRC administered licensing examinutions to three prospective reactor operators.
Major maintenance items for tw month included: replacing the safety edge relays for personnel airlock doors 276 and 277; eplacing relay 2K 20 in preparation for installing new digital rod drop timer circuits; installing a new auxiliary annunciating alarm panel to accommodate Nuclopara and Alpha Laboraton alarms; replacing the control power fuse on the breaker for pool pump 508A; replacing the rod run in trip actuator amplifier; replacing the voltage )
regulator on intermediate range monitor channel #3; rewiring the control circuit l coil on the breaker for the main air compressor, thuDluill221 The reactor operated continuously in August with the following excaptions: four shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns.
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On August 11, while operating ut'10 MW steady-atale, the reactor scrammed when the safety system green leg trip actuator amplifier tTAA) tripped with no accompanying scram annunciation. The TAAe are bistable driver amplifiers which control two scris transistors to turn output current to the control rod magnets offin response to an input sigual from the green or yellow safety leg.
An electronics technician investigated the spuriour. trip, could find nn apparent
- problem with the green leg TAA or ita input, but replaced it with a spare TAA.
This TAA tested satisfee;o-ily and the reactor was restarted and resumed full- .
power operation.
Apprcxhnately one hour after reaching full power, the reactor scrammed when ty system yellow leg TAA tripped with no accompanying scram c.: = Vion. The niectronics technicians inspected both the green and yellow
-lc . u ir signs of deteriorated components er wiring. One resistor in the TAA and two resistors in the green leg TAA were found to be
> Ig the 10% colerance for reduced resistance and were replaced. The o iset points of the TAAs were tested and found to be satisfactory. The me reinstalled, the reactor was refueled and returned to operation.
e a result of further investigation of TAA problems e::perienced in September, ,
~ these particular spurious shutdowns are believed to have been caused by high rehistance in the series of closed contacts in the yellow and green legs. The 1K and 2K rolays were approaching the date when the semiannual preventive maintenance to check and clean contacts.was .due to be performed.
Majer maintenance itema for the month included: - replacing the 2K 21 relay-to accommodato the new tontrol blado drop timers; replacing resistor R 14 in the
- yellow safety leg trip actuator ampliller; replacing resistors R 14 and R-34 in the green safety leg trip actuator amplifier; installing new seals and bearings in primary pump 501B;-installing a supplemental fuel storage basket.
Sentembhr 1991 The reactor operated continuously in September with the following exceptions:
seven shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns.
.On September 3, the reactor scrammed aue to the loss of facility electrical power.
This scram occurred during a thunderstorm and the loss of electrical power was
> verified with the University power plant. The emergency generator nssumed its assigned electrical loads until normal power was restored after one hour and forty _two. minutes. The reactor was then returned to normal operation.
Qn September 10, a reactor loop low pressure scram was initiated by the meter ,
. relay trip unit for primary pressure transmitter 943. No_ actual low pressure condition waa indicated. Electronics techniciansiliscovered an intermittent open in the' lamp filament which provides the light source for the photo transistor switch in the meter relay trip unit for pressure transmitter 943. Low light I4
E.
intensity or an intermittent light source would cause the meter relay unit to provide a spurious trip signal to the safety system. The lamp assembly was i replaced and a scram verification check (part of Compliance test CP 22) was satisfactorily performed for the transmitter and meter relay trip unit.
While preparing to start up after replacing the lamp in the PT 943 meter trip unit, the Trip . Actuator Amplifiers (TAAs) for scram and RRI tripped with no annunciation No source of trip signal could be determined, although the spurious tny were similar to those that had occurred in August (TAA scram trip with no scram annunciation).
Electranics technicians, earlier on September 10 as part of routine maintenance activities, had performed preventive maintenance on the 1K and 2K relays, which included contact cleaning of these relays. Many of the 2K relays have contacts in series in the yellow and green leg input to the TAAs.
Electronics technicians had cleaned all contacts with a cleaner (GC Contact Kleen with Anti Oxidant) which contained a lubricant that leaves a residue on contacts.
This residue is believed to have caused high resistance in the string of closed relay contacts in the yellow and green leg inputs to the TAA, resulting in lower voltages at the input of the TAAs (approaching the trip voltage). Normully voltage at the input of the TAAs is almost twice the trip voltage setpoint and when an actual scram trip is called for a contact in the green or yellow leg opens, rtducing the innut voltage to the TAAs to zero. In this case, high resistance in the yellow and green leg relay string of closed contacts to the TAA input would place input voltage to the TAAs so close to the trip setpoint that small (spurious) variations in voltage could cause the TAAs to trip, when no actual scram condition existed.
Under these conditions the TAA could trip with no scram annunciation.
The electronics technicians recleaned all 2K and 1h relay contacts with a
. freon based cleaner to remove any lubricant residue from the previously used cleaner. The TAAs were tested and performed satisfactorily. The reactor was refueled and returned to normal operation. No further problems of this type have been experienced.
After a scheduled shutdown for maintenance activities, on September 30, while shuttin down the primary system pumps and valves, the shift supervisor noted from diflerential pressure indientions that one of the two primary coolant isolation valves had not seated properly. Subsequent investigation revealed that primary coolant outlet isolation valve 507A (a 12" diameter butterfly valve), was closing to within a few degrees ofits fully closed position, but would not consistently seat to hold a pressure difTerential as specified in the SOP (SOP IV.2.1 K.).
During disassembly of the 507A valve for problem evaluation, the upper valve stem packing was found to be extremely hard and embrittled which is most likely due to age and radiation effects. Once the packing was removed, the valve could be actuated with nominal torque to its fully seated position. The valve seat showed some signs of deterioration due to age, but the valve, when placed in its closed and 1-5 F
L seated position, was able to hold differential prescure of 40 psi for 30 minutes with no leakage. This testing indicated that the difliculty in consistently seating the 507A valve was, due to valve stem binding on pieces of the embrittled stem packing.
The basis for Technical Specification 3.9(a) states that " proper operation of these valves is not required for protection of fuel element integrity, however, their operation provides a means for isolation of the in pool portions of the reactor coolant sysi.em from the balance of the system."
Since valvo 507A was closing to within a few degrees ofits fully closed and seated position as determined by repeated testing, and was therefore capable of performing its intended function (ref: Original Hazards Summary Report, Section 13.2.6 and Hazardo Summary Report, Addendum 4),it was determined that the valve was operable but in a degraded condition. The valve was ultimately replaced and tested satisfactorily and the reactor was returned to normal operation.
- Operations staff subsequent to the 507A valve replacement, continued to test and evaluate the reactor inlet isolation valve (5078) and its actuator to verify that a generic problem did not exist. On October 14,1991, the actuator for the inlet isolation valve (507B) was removed so that its actuator could be tested and its closing / seat.ing torque could be measured. The seating torque for 507B (~ 15011 lbs) was greater than that of the new 507A vslve (~ 75 fllbs), but was less than the torque it took to seat the old 507A valve (> 300 ft lbs) and well within the minimum torque capacity ofits actuator.
Evaluation of these findings, along with the normal closing times for valve 507B, reinforced the engineering staff dcterminution that a similar problem with 507B was not indicated. On October 29,1991, a letter describing the circumstances of this event was sent ta the U. S. Nuclear Regulatory Commission, Director of Nuclear Reactor Regulation.
Major maintenance items for the month included: replacing the yellow leg trip actuator amplifier; replacing the 2K 5 relay block; rewiring the lamp assembly for pressure transmitter 943; replacing contacts 7 and 8 on relay 2K 28; replacing the yellow leg non-coincidence logic unit; replacing the oil seals on the main air compressor output shaft and replacing relay 2K-20.
October 1991 The reactor operated continuously in October with the follmving exceptions: four shutdowns for scheduled maintenance and refueling; and one unscheduled shutdown.
On October 2, a rod not in contact with magnet rod run-in occurred when an operator trainee accidentally bumped the offset mechanism counter balance arm for control blade "D" while performing a silicon sample handling evolution. A hot start-up was subsequently completed and the reactor was returned to normot I-G l
l operation. The person involved was instructed to exercise greater caution while handling silicon samples and to utilize a method of handling which minimizes the possibility of a recurrence.
Major maintenance items for the month included: replacing primary outlet isolation valve 507A; completing the biennial change.out of offset mechanism "C";
and testing the actuator and valve seating Srque on primary inlet isolation valve 507B.
November 1991 The reactor operated continuously in November with the following exceptions:
four shutdowns for scheduled maintenance and refueling; there were no unscheduled shutdowns.
The biennial requalification written examination was given to all operators during the week of November 10. Four of the operators were given NRC monitored requalification examinations and operating tests. These examinations were administered by the Reactor Manager and monitored by two NRC examiners as part of the 10 CFR 55 requirements that licensed operators have an NRC monitored requalification examination during the six year term of their license.
On November 11,1991, while shutting down the primary cooling system pumps and valves for scheduled maintenance day activities, the control room operator noted that difTerential prosaure indications showed that at least one of the two primary coolant isolation valves had not seated properly.
Investigation of the primary cooling system isolation valves revealed no problem with the primary coolant outlet isolation valve (507A), but the primary coolant inlet isolation valve (507B) was in the open position, while its valve actuator was in the closed position. A square steel key which serves to engage the air actuator to the 507B valve stem had fallen out, rendering the valve inoperable.
The primary coolant inlet valve (507B) is mounted such that its valve stem is vertical and below the coolant pipe. The valve actuator for 507B mounts under the valve such that the valve stem, with a keyway slot, goes through the actuator coupling. The steel key which engages the valve actuator to the valve stem must have fallen out of the valve stem keyway sometime during the week of November 4, 1991.
The bottom of the actuator keyway slot is crimped to prevent the key from falling out. In this case, the crimp failed to retain the key. The 507B keyway crimp may have been disturbed by maintenance activities that occurred on October 14,1991.
The valve actuator for 507B had been removed from the valve as part of the investigation of the 507B valve and actuator to ensure it did not have a generic problem similar to 507A, which failed on September 33,1991.
The immediate corrective action on November 11,1991, upon finding that the 507B actuator to valve stem engagement key had fallen out, was to test valve 502 on the reactor coolant inletline to ensure it was operable. After this test was I-7 1
i
. . .. - . . . . - - _ - - ~ - - - - - -.-- - - -- .
completed satisfactorily, the valve 5078 to actuator key was replaced, the bottom of
- its actuator keyway slot was recrimped and 507B was tested repeatedly to ensure it was operating properly. The two other valves of similar design (507A and 509) were also checked to ensure their keys were in place and that their keyway slots were sufficiently crimped to prevent their keys from falling out.
On November 18,1991, the primary coolant inlet valve (507B) was replaced and a new design for retaining the actuator to valve stem engage ent key was installed on 507A,507B and 509. This design attaches a part to the ' ve stems of 507A and 507B and to the actuator on V509 to physically block the k from dropping out of the keyway.
On December 10,1991, a letter describing the circumstances of this eveat was sent to the U. S. Nuclear Regulatory Commission, Director of Nuclear Reactor Regulation.
Major maintenance items for the month included: replacing valve 507B (primary inlet); replacing valve 507B actuator key and later modifying the actuator key retainers on valves 507A,507B,and 509 (pool isolation) to prevent the keys from dropping out of the keyway.
December 1991 The reactor operated continuously in December with the following exceptions:
five shutdowns for scheduled maintenance and refueling; there were no unscheduled shutdowns.
From December 9 through December 12,1991, NRC Region HI inspectors conducted an inspection of MURR Emergency Preparedness and Health Physics activities.
Major maintenance items for the month included: replacing the motor and gearbox on the outer personnel airlock door; replacing relay K-38 (reactor loop low flow); replacing the position indication switch for primary demineralizer isolation valve 527F; replacing the nitrogen banh 'B' regulator.
January 1992 The reactor operated continuously in January with the following exceptians: ' four shutdowns for scheduled maintenance and refueling; and three unscheduled -
shutdowns.
On January 6, a spurious reactor scram occurred while the reactor was 2t 50 KW-
- l. Eduring a normal startup following a scheduled maintenance period.
Investigation revealed poor contact between the K-37 relny plus and its socket which caused a pool loop low flow scram. The K-37 relay provides a pool loop low flow.' scram input from pool flow transmitter 912 D in the green leg of the safety system. The K 37 relay had been replaced with a shorted relay tarlier in the day
_during the performance of the pressurizer (level and pressure control) '
+
I-8
l compliance check, after which it was reinstalice and resumed its normal function. After the spurious scram, electronics technicians tightened the spring tension on the K 37 relay socket contacts. A scram check for pool Dow transmitter 912 D was then completed satisfactorily and the reactor was returned to normal operation.
On January 20, a reactor loop low pressure scram occurred from what was determined to be an intermittent filament in the lamp for the meter relay trip unit monitoring core discharge pressure (transmitter 944A). The meter relay trip function is based on a light source, with photocell pickup, such that loss oflight to the photocell causes a trip. In this case, the bulb flickering due to an intermittent filament caused the spurious trip. No actual low pressure condition was indicated. The scram trip lamps for both pressure transmitters 944A and 944B were replaced and a satisfactory scram check of these transmitters was completed.
On January 21, a nuclear instrument channel #5 high power rod run in occurred when the channel five power indication rose to approximately 114% as the reactor was being placed in automatic control. Reactor control had bee- in manual so reactor operators could manually adjust the gain potentiometer on the vdde range monitor (nuclear instrument channel #4). This occurred shortly after reactor startup with two elements that were not Xenon free. With Xenon burning out, especially close monitoring of the nuclear instruments is required when shifting the reactor from manual to automatic control. The rod run in was acknowledged, reset, and the reactor was returned to automatic control. The operators involved were instructed to pay closer attention to all available instrumentation during evolutions of this type. This unscheduled shutdown lead to formalizing the procedure for adjusting NI channels at power. This procedure was incorporated as a standing order on March 18,1992.
Majcc maintenance items for the month included: tightening the spring tension on the K-37 relay socket contacts; replacing the K-38 relay socket; and replacing the PT944 A and B meter relay unit scram trip lamps.
February 1992 The reactor operated continuously in February with the following exceptions:
four shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns.
On February 3, a spurious reactor scram occurred during a normal startup, while the reactor was suberitical. The cause was traced to a faulty manual scram switch. The switch was replaced and a short form precritical checksheet was completed before continuing normal operation.
On February 19, a reactor loop low pressure scram occurred when an operator mistakenly opened the drain valve on the reactor loop demineralizer column, a
_p art of the reactor primary coolant cleanup system. The reactor cleanup system consists of three domineralizers operating through a 2" manifold piping system, I-9 . !
l
i with any two of three demineralizers on service at one time to provide independent cleanup capabilities for the primary system and the pool system at a flow rate of 50 gpm. The third demineralizer is isolated from both the pool and primary system and is considered in standby, capable of providing either primary or pool service if required.
The scram occurred as two operators were in the process of transferring a depleted deionization bed from the standby demineralize- column to the storage tank. The operator opened the drain valve on the operating demineralizer column instead of the standby column, resulting in a momentary reductien in primary system pressure causing the subsequent scram. The valve was immediately closed when the operator recognized his error. After determining that the scram initiated at a pressure well above the safety limit setting for pressure, the reactor was refueled and returned to normal operation. The operator involved was cautioned about the integrated nature of our demineralizer systems and of the need to be especially careful about valve identification when manipulating the demineralizer system valves.
The momentary reduction of primary pressure which resulted from opening this valve did not present a safety concern since a reactor scram was initiated prior to reaching a limiting safety system setting for pressure.
Limiting safety system settings are determined for those variables having significant safety functions. These setting are chosen so that (when reached) automatic protective action will correct the most severe anticipated transient before a safety limit is exceeded. The limiting safety system setting for reactor pressurizer pressure is 75 psia minimum (Ref: Tech. Spec. 2.2), Hazards Summary Addendum 4, Appendix H); a margin of 15 psi above the safety limit of 60 psia. The actual scram set-point for pressurizer low pressure is more conservative than this [77.2 psia at last compliance check, January 6,1992).
There are four independent pressure transmitters which are capable of causing a reactor scram in the event of a loss of pressure transient, thus insuring that the low pressure safety limit will not be violated (Ref: Hazards Summary Addendum 4, Appendix H),
Two reactor operator licensing examinations were administered by the Nuclear Regulatory Commission on February 24 and 25,1992.
Major maintenance items for the month included: installing, and placing on service, a new air compressor dedicated to the valve operating system.
March 1992 The reactor operated continuously in March with the following exceptions; five shutdowns for scheduled maintenance and refueling; and one unscheduled shutdown.
On March 17, a reactor scram and isolation was initiated by the reactor bridge ALARA nrea radiation monitor. This occurred during a silicon sample handling I-10
l evolution when a silicon sample was raised higher than normal while it was being transferred to its storage bin, resulting in a higher than normal radiation level at this detector.
The reactor bridge monitors that are part of the Area Radiation Monitoring System (ARMS) consist of two independent G. M. type detectors mounted near the pool surface level, each of which is capable ofinitiating a reactor scram and isolation. These detectors are designated " Bridge" and " Bridge ALARA" respectively.
The Bridge detector scram setpoint is 50 mR/hr while the Bridge ALARA scram setpoint is 10 R/hr - with an " Alert" alarm indication at 300 mR/hr. During periods of maintenance and sample hanciling, when temporary radiation readings greater than background can be expected, the Bridge ARMS detector scram function can be temporarily set upscale as per Technical Specification 3.4.a. note (2). This is accomplished by switching the scram function to the Bridge ALARA detector.
On March 16, the day prior to the reactor isolation, as part of the pre-startup checks done before returning the reactor to power after a scheduled maintcnance shutdown, the Bridge ALARA alarm and scram setpoints were tested. The reactor operator perfonning the pre-startup check mistakenly switched the slarm and scram setpoints on the Bridge ALARA ARMS module so that the scram / isolation was set at 300 mR/hr (a more conservative setpoint), and the alarm was set at 10 R/hr. On March 17, when the operator handling the silicon sample raised the sample to a point where a 300 mR/hr exposure rate was introduced at the detector, a reactor scram and isolation resulted. The evacuation of personnel from containraent was carried out according to the Reactor Isolation Procedure.
To eliminate alarm / alert setpoint errors in the future, a modification has been made to the small tool which is used to actuate the alarm / alert switches. This tool will prevent errors of this, type from recurring. All operators have been made aware of this type of error and of the importance of paying attention to detail when testing / resetting the alarm setpoints for the ARMS.
Major maintenance items for the month included: repairing a pinhole leak in the secondary water (shell) side of pool heat exchanger 521B and subsequently performing ultrasonic testing (UT) on all of the reactor and pool heat exchanger shells to determine wear characteristics; replacing the K-30 relay socket; shipping spent fuel elements from the facility; performing the biennial change out of control blade "B" otTset mechanism; and installing and testing a bulkhead electrical connector in the containment building penetration plate.
Anril 1992 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and refueling; and one unscheduled shutdown.
1-11 j
l On April 29, a spurious reactor power level interlock scram occurred from what was subsequently determined to be faulty relay contacts in relay 1K13. Relay 1K13 provides power levelinterlock scram input to the green leg of the safety system.
Electronics technicians replaced the 1K13 movable contact block and cleaned and burnished all contacts. The relay tested satisfactorily and the reactor was then refueled and returned to normal operation.
On April 27, the biennial emergency drill was conducted invoh*ing the following emergency support organizations: UMC Health Physics, UMC PCice, University Hospital and Clinics, MU News Bureau, and Columbia Fire Department, Major maintenance items for the month included: replacing the movable contact block for relay 1K13 and conducting spent fuel shipments.
May 1992 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and refueling; and one unscheduled shutdown, On May 17, a spurious scram of unknown cause occurred while the reactor was operating at a steady-state 10 MW The annunciator indications included reactor loop low pressure scram, rod not in contact with magnet, and regulating blade out of auto There were no pressure, temperature, or flow transients indicated on any instrumentation. Extensive investigation by the Chief Electronics Technician could dete'mine no specific cause, and the incident could not be repeated. The reactor was subsequently refueled and the maintenance scheduled to begin later in the day was commenced early.
Major maintenance items for the month included: conducting spent fuel shipments, June 1992 The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns, On June 23, a manual rod run in was initiated upon discovering that several loose pieces of sheet metal within the main exhaust plenum had become caught on the stack monitor isokinetic sampling probe, turning it 90 from its desired orientation. It was also determined that the sampling probe had become disconnected from the stack monitor sampling line and therefore affected the reliability of the monitor readings. The sheet metal pieces came from several flow turbulence suppressors (bending vanes) which had corroded. The sheet metal pieces were removed and the ischinetic sampling probe was inspected, repaired and reconnected to the sampling line. The stack monitor was then tested satisfactorily. The reactor was refueled and returned to normal operation. A I-12
i Licensco Event Report was sent July 23,1992 to the Director of Nuclear Reactor Regulations and the NRC Region Ill ofIice detailing the circumstances of this event and the corrective measures taken.
On June 28, a manual rod run in was initiated when an operator noted erratic primary temperature (Tc) indications provided by the temperature instrument channel connected to RTD 901A. The problem was traced to a faulty MVA transmitter for the primary temperature (inlet) indication. The MVS transmitter produces a direct current output proportional to a millivolt or variable resistance input from the RTD. This temperature instrument channel provides control room chart indication, a high temperature alarm, the driving signal to the primary heat exchanger bypass valve (S-1) and an input signal to the digital power calorimetric indicator. This instrument does not provide any safety system scrams or Technical Specification required indication.
- Electronics Technicians replaced the MVS transmitter, tested it satisfactorily, and the reactor was refueled and returned to normal operation.
Major maintenance items for the month included: replacing the socket for relay K-31 (pool loop low flow alarm - 920B); replacing valve 509 (pool outlet isolation valve); removing shcot metal pieces from the main exhaust air plenum; inspccting and repairing the stack monitor sampling probe; replacing the reactor Tc MVA transmitter (from RTD 901 A); replacing the magnet power coiled cord on control blade "B" drive mechanism; and replacing the control power fuse on primary pump 501A breaker.
I-13 l
l
~ .
h I
SECTION H I July 1991 through 30 June 1992 A. CHANGES TO THE STANDARD OPERATING PROCEDURES, 2nd Edition, Effective Date: 5/02/89 (Revisions #1 through #24 to the October 1981 printing were incorporated )
. As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:
Revision No. 6. dated 07/16/91 Revision No. 7, dated 01/02/92 Revision No. 8, dated 02/28/92 B. ' CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES (dated January 1985, and revised May 13,1988) {*
NOTE: New manual printed May 13,1988 As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:
Revision No. 8, dated 09/13/91 Revision No. 9, dated 01/23/92 "OTE: SEP-7, page 2: Social Secmity Numbers have been omitted per ,
request by Nuclear Regulatory Commission, Al Adams, U/87.
C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES NOTE: New manual iss ued 10/29/90
- HP 31, Revision No.1, dated 12/05/91 The revisions to the Standard Operating Procedures, MURR Site Emergency Procedures / Facility Emergency Procedures, and Health Physics Standard Operating Procedures are contained in this section with the part of each page that was revised marked on the right side of the page by a bracket G).
k 11-1
(
STANDARD CPERATING PROCEDURES 2nd Edition, Effective Date: 05/02/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.)
Revision Number G Revision Date: July 16,1991 fage..Jumber Revision Date SOP /VIII 46 Retyped Only 07/1691 K2P-01(Table of Contents) 07/16'91 __
1 k
e a
3 k
il i
II.2 a__a_-- - - - _ _ _ - - --__-----__a- - - - ---_.__---.--- _ _ _ _ _ _ - - - - _ . - - - - - . _ - - - - _ _ _ - - - . _ _ _ _ _ _ - - - - - _ _ _ . - - , - - - - - - - _ _ _ - - - - _ _ _ - _ -_w- -. - - -
_.,. Tills PAGE INTENTIONALLY LEFT T3IANK
,.y 1
'I g L
New 10/18/90 App'd RN SOP /VIII-46 1 Retyped Only;7/16/91
- . _ _ . _ . . - ~ _ _ . . _ _ . _
l REACTOR EMERGENCY PROCEDURES (REP SECTION)
TABLE OF CONTENTS L
SECTION NO. PAOE NQ.
REP-O Introduction REP-0-2 REP- 1 Failure to Scram or Rod Run-In REP 1 REP-2 Reactor Scram REP 1 REP-3 Reactor Scram from Loss of Primary System Pressure or Flow REP 1 REP-4 High Radiation Levels REP 1 REP-5 Nuclear Instrument Failure RE P 1 REP-6 Area Radiation Monitoring System (ARMS),
Failur: to Actuate Reactor Isolation RE P 1 REP-7 Loss of Communications Between Reactor Control Room and Experimenters REP 1 REP-8 Control Rod Drive Failure / Stuck Rod REP 1 REP-9 Electrical Anomalies RE P 1 REP- 10 Failure of Experimental Apparatus REP 1 REP-11 Low Fire Main Pressure REP 1 REP-12 Loos of Domestic Cold Water to the Facility REP 1 REP- 13 Con plete or Partial Loss of Secondary Flow REP 1 REP-14 Loss of Pool Flow During Reactor Operation REP 1 REP- 15 Loss of Pool Water During Reactor
~ deration REP 1 REP 16 actor Loop Isolation Valves (507A & 507B),
' ail to Clost Automatically r REP 1 REP- 17 Pressurizer Valves Fall to Operate REP 1 REP- 18 Both Antisiphon Valves (543A and 543B),
Fall to Open Automatically REP 1 REP-19 Emergency Core Cooling Valves (546 A/B),
Fall to Open Automatically REP 1 REP-20 High Activity Levels in the Primary Cooling System REP 1 REP-21 High Stack Monitor Indications REP 1 REP-22 Bomb or Other Overt Threats REP 1 Rev. 7/16/91 App'd M_ REP-0-1 ]
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 05/02/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.)
Revision Number 7 Revision Date: January 2,1992 SOP /III-2 SOP /III-3 SOP /III-4 SOP /III-5 SOP /III-6 SOP /III 8 _
SOP /VII-25 SOP /VII-26 SOP /VII-34 SOP /VII-35 SOP /VII 36 REP-12-2 SOP /A-11a II-3
J. On UPS-3 Panel:
l 1. Open breaker #1 l
- 2. Open breaker #2
- 3. Open breaker #3 I
- 4. Open breaker #4 l 5. Open breaker #5 111.2 Pre-startup Check of Source Range Nuclear Instrument Channel 1 NOTE: Internal drawer test functions may be done in any order.
A. Verify power to the recorder.
R Verify the drawer function switch is in " OPERATE" and all associated indicator lights are cleared.
C Place drawer function switch to " STANDBY". Verify the following indications occur:
- 1. " Drawer Inoperative" indicator light.
- 2. " Nuclear Instrument Anomaly" annunciator.
D. Place drawer function switch to "ZERO". Verify:
- 1. Recorder and local and remote level meters indicate 10-1 cps.
- 2. The local and remote period meters indicate -30 seconds
- 3. The "<1 cps" indicator light illuminates.
- 4. The " Channel 1 Lo Count Rate" annunciation occurs.
E. Place drawer function switch to "105 ". Verify:
- 1. The recorder and local and remote level meters indicate 8x104 to 1.5x105 cps.
- 2. The "<1 cps" indicator light extinguishes.
- 3. The " Channel 1 Im Count Rate" annunciation clears.
E Place drawer function switch to ".1H".
Verify that the recorder and local ar. remote level meters indicate 8 to 15 cps.
G. Place drawer function switch to " PERIOD". Hold the Ramp switch to " FIXED".
Verify that the local and remote period meters indicate +3 seconds then release the Ramp switch.
H. Place the drawer function switch to " OPERATE" and ensure all associated indicator lights are clear.
- 1. Turn on scaler for startup.
111. 3 Pre-startup Check of Intermediate Range Nuclear Instrument Channels 2 and 3 NOTE: Internal drawer trest functione may be done in any order.
A. Place the console IRM Channel Selector switch to the channel which is being tested.
a Verify power to the recorder.
C Verify the drawer function switch is in " OPERATE" and all associated indicator lights are cleared.
Rev. 1/02/92_ App'd M SOP /III-2 Section III.2 through III.5 revised in its entirety
D. Place the drawer function switch in " STANDBY". Verify the following indications occur:
- 1. " Drawer Inoperative" indicator light.
- 2. " Nuclear Instrument Anomaly" annunciator.
E. Place drawer function switch to "ZERO 2". Verify:
- 1. Recorder and local and remote level meters indicate 10-10 amps.
- 2. The local and remote period meters indicate -3n seconds
' F. Place drawer function switch to "ZERO 1". Verify;
+ 1. Recorder and local and remote level meters indicate 10-10 amps.
- 2. The local and remote period meters indicate -30 seconds G. Place drawer function switch to "_1_Q-8".
Verify that the recorder and local and remote level meters indicate 8x10-8lto 1.2x10"8_ amps.
H. Place drawer function switch to ".LQ-4".
Verify that the recorder and local and remote level meters indicate 8x10-5 to 1.2x10-4 amps.
-I. Place drawer function switch to "1.5x10-3".
Verify that the recorder and local and remote level meters indicate 1.2x10-3 to 1.8x10-3 amps.
'J. Place drawer function switch to " PERIOD". Hold the Ramp switch to " FIXED". Verify:
- 1. The local and remote period meters indicate +3 seconds.
- 2. The ."35 second" indicator light is received.
lK. Place Reset switch:
- 1. Momentarily to " TRIP".
- 2. To " RAMP" and hold until the recorder and local and remote level meters indicate 10-10
- 3. Release Reset switch.
, L ~ Jog Ramp switch to " VARIABLE". Verify:
- 1. The " Rod Run-In" trip indicator light illuminates.
- 2. The' " Channel 2 &-3 Short Period Rod Run-In" annunciation occurs at 11 1 seconds as indicated on the control console period meter.
- 3. The " Scram" trip indicator light illuminates.
Rev. 1/02/92 App'd MA SOP /III-3 Section III.2 through III.5 revised in its entirety i
- 4. The " Channel 2 & 3 Short Period Scram" annunciation occurs at 9 1 s .onds as indicated on the control console period meter.
M. Release the Ramp switch.
N. Place the drawer function switch to " OPERATE" and ensure all associated indicator lights are cleared.
O. Set compensating voltage so that indication is between 10 4 to 10-6 amps.
111.4 Pre-startup Check of Wide Range Nuclear Instrument Channel 4 NOTE: Internal drawer test functions may be done in any order.
A. Compare potentiometer setting with last recorded heat balance setting.
B. Verify power to the recorder.
C. Verify the drawer funcuon switch is in " OPERATE" and all applicable indicator lights are cleared.
D. Place'the drawer funcuon switch to " STANDBY". Verify the following indications occur:
- 1. " Drawer Inoperative" indicator light.
- 2. " Nuclear Instrument Anomaly" annunciator.
E. Place drawer function switch to "ZERO 2". Verify:
- 1. The recorder and local and remote level meters indicate 012%.
- 2. The "Downscale 95%" indicator light is illuminated.
F. Place drawer function switch to "ZERO 1". Verify:
- 1. The recorder and local and remote level meters indicate Oi2%.
- 2. The "Downscale 95%" indicator light is illuminated.
G. Place drawer function switch to ' TRIP TEST".
H. Clear any scram or rod nm-in indicator lights.
I. Using the drawer test signal pctendometer, raise the indicated power. Verify:
- 1. Rod Run-In Funcuon a The " Rod Run-In" trip indicator light, and
- b. The " Channel 4. 5 & 6 Hi Power Rod Run-In" annunciation occurs at 114 1% as indicated on control console power level meter.
Rev. 1/02/92 App'd M SOP /Ill-4 Section III.2 through III.5 revised in its entirety
l l
- 2. - Scram Funcuon l
a The " Scram" trip indicator light. and i
- b. The " Channel 4, 5 & 6 Hi Power Scram" annunciation occurs at 11911% as indicated on control console power level meter, J. Using the drawer test signal potentiometer, lower the indicated power to <100%.
K. Place the drawer function switch to " OPERATE" and ensure all applicable indicator lights are cleared.
111 5
. Pre-startup Check of Power Range Nuclear Instrument Channel 5 and 6 NOTE: Internal drawer test functions may be done in any order.
A Compare potentiometer setting with last recorded heat balance setting.
11 Adjust drawer potentiometer to the 10MW calibrated test setting.
C Verify ~ power to the recorder.
D. Verify the drawer function switch is in " OPERATE" and all applicable indicator lights are cleared.
E. Place the drawer function switch to " STANDBY". Verify the following indications occur:
- 1. " Drawer Inoperative" indicator light,
- 2. " Nuclear Instrument Anomaly" annunciator.
F. Place drawer function switch to "ZERO". Verify:
- 1. The recorder and local and remote level meters indicate 0 2%.
- 2. The_"Downscale 95%" indicator light is illuminated.
G. Place drawer function switch to "110%". Verif3
- 1. The recorder and console power level meters indicate 110i2 %
- 2. The drawer power level meter indicates 11015%.
.Rev. 1/02/92 _ App'd ILvwA SOP /Ill-5 Section III.2 through IH.5 revised in its entirety
H. Place drawer function switch to "75%".- Verify:
- 1. The recorder and console power level meters indicate 7512%.
- 2. The drawer power level meter indicates 7515%.
- 1. Place drawer function switch to "10%". Verify:
- 1. The recorder and console power level meters indicate 1012%.
- 2. The drawer power level meter indicates 10iS%.
J. Place drawer function switch to " CAL".
It Clear any scram or rod run-in indicator lights.
L Using the drawer test s!gnal pote;ntiometer, raise the indicated power. Verify:
- 1. Rod Run-In Function a The " Rod Run-In" trip indicator light, and
- b. T1.e " Channel 4, 5 & 6 Hi Power Rod Run-In" annunciation occurs at 114 1% as indicated on control console power level meter.
- b. The " Channel 4. 5 & G H: Power Scram" annunciation occurs at 11911% as indicated on control console power level meter.
M. Using the drawer test signal potentiometer, lower indicated porier <100%.
N. Place the drawer function switch to " OPERATE" and ensure all applicable indicator lights are clear.
O. Return drawer potentiometer setting to the last recorded heat balance setting.
Rev. 1/02/92 App'd N SOP /111-6 Section m.2 through III.5 revised in its entirety
E. Increase power to original level.
l F. Log final new pot setting.
111.7 Check of Process Radiation Monitors 111. 7 . 1 Onerational Check of Seconday Coolant and Fission Product Monitors respectively.
A lower alarm setpoint until annunciator alarms.
B Place level set switch up and adjust alarm setting to 10k cpm + 10%.
C Lower alarm catpoi until anunciator alarms.
D. Place level set swnch up to and adjust alarm setting to 12k cpm + 10%.
111. 7 . 2 Operational Check of Stack Monitor A The operator conducting the test in the West Tower.
shall establish communication with the control room via the intercom.
B Place the mode switch for the iodine detector in the "T" ' st) position.
C Verify that the recorder pen indicates 3600 cpm + 10%, and that the stack monitor high activity annunciation is received.
Also verify that the local meter reads within 10% of the test reading marked on the meter face.
D. Return the iodine-mode switch to the "N" position.
E. Press the " reset" button until the iodine meter and recorder readings return to normal, do not drive them to the downscale position. Reset the annunciator.
F. Place the mode switch for the particulate / gas monitor in the "T" positjon.
G. Verify that the particulate recorder and gas recorder pens ]
Indicate 3600 cpm i 10% and that the stack monitor high ]
activity annunciation is received. Also verify that the ]
local meter reads 3600 cpm . 10%. ]
P Return the particulate mode switch to "OP" position. ]
L Press the " reset" button until the particulate meter and }
recorder readings return to normal; do not drive it to the ]
downscale position. Reset the annunciator. ]
J. Test the low flow alarm in the control room by securing the ]
blower. ]
K. Return the blower switch to "on", verify "high" and " low" ]
alarms cleared. ]
Note: Paragraphs G,H, I, J and K were inadvertently omitted when Revision No. 4, dated 4/30/91, was issued.
Rev. 1/02/92. App'd 'WWA SOP /Ill-8
Vll.8.5 Draining WT3 to Wl'2 g When WT31s nearly full, drain it to WT2 via the standpipe.
A. Check valves W1A,1B, 2A, 2B, 3A, 3B, 7, 9, 23, 38 shut.
B. Open valves W3A and W2B to start Wl'3 draining to WT2.
C. When WT3 is drained down to the level of the standpipe, shut WSA and W28.
D. Record the evolution !n the Reactor Log.
VII.8.6 Recirculating and Sampling of Waste Tanks __
NOTE 1: Notify Reactor Chemistry group before obtaining a sample.
NOTE 2: Always pump through the filters by opening valves W16 and W18, ensuring WS is closed.13Ne ecirculating any tank, check the following valves closed: W1 A, 1 B, 2A, 2B, 3A, SB, 5, 7, 8, 9, 22, 23, 24, 25, 26. 27, 38, WD1, WD2, WD3, WD4, WD5. -
If WP2 is used instead of WP1, open W7 and W8 instead of W9.
v A. Sampling WT2
- 1. Open W2A, 2B, 9,16,18, 24.
- 2. Start waste pump (WPI) and verify flow through the bullseye.
- 3. Commence a vigorous air sparge through W2C.
- 4. Recirculate for 10 minutes prior to sampling.
- 5. Draw off a sample thrcugh W22 and discard to liquid waste drain. '
- 6. Draw off a second sample through W22 for analysis.
- 7. Shut W22 and secure the waste pump. '
- 8. Close W2A, 2B, 20, 9,16,18, 24.
l 9 Deliver the sample and completed sample form to the Reactor Chemistry Group for analysis.
- 10. . Record taking of sample in the Reactor Log.
Rev. 1/02/92 App'd'h SOP /Vil-25 i
_ . . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . . . . . _ . . . . . . . . . .. .A
1 E
Sampling WT1
- 1. Open W1A, IB, 9,16,18, 26.
- 2. Start the waste pump (WPI) and verify flow through the bullseye.
- 3. Commence a vigorous air sparge through WIC, )
4.. Recirculate for 10 minutes prior to sampling.
- 5. ' Draw off a sample through W22 and discard to liquid waste.
G. Draw off a sample through W22 for analysis.
- 7. - Close W22 and secure the waste pump.
- 8. Close W1A, IB,1C, 9,16,18, 26. ]
- 9. Deliver the sample and completed form to the Reactor Chunistry Group for analysis.
- 10. Record talJng of sample in the Reactor Log.
VII.8.7 Pumping to Sanitary Sevier NOTE: CLn be done only with Shift Supervisor's or Reactor Manager's authorization. Check the following valves closed: W1A,1B, 2A. 2B, 3A, 3B, 5, 22, 23, 24, 25, 26.27, 38. If pumping with WP2, open W7 and 8 instead of W9.
A. -Pumping WT1 to Sewer
- 1. Open #1B, 9,16,18 -WD1, WD2.
- 2. Commence a vigorous air sparge through W1C.
- 3. Start the waste pump (WP1) and verify flow through the bullseye.
- 4. Check waste tank periodically until tank is empty.
4 When empty, secure waste pump.
Du 5. Shut W1B,1C, 9,16,18. WD1, WD2.
l, 6. Record the volume pumped on t 3 Waste Tank Sample Form and return it to Health Physics Office.
- 7. Record the pumping evolution in the Reactor Log.
Rev. J 102/92 App'd l#H~ SOP /VII-26 H
l- ,
'I
C Operability of the emergency air compressor is checked.
Should the facility lose DCW water, the main air compressor must be shut down as per REP-12. To shut down the compressor, the local auto /off/ manual switch is turned to "off'. The compressor may be electrically isolated by opening the main breaker on MCC3.
The emergency air compressor must always be operable whenever the reactor is operaung. It may be secured at its local breaker. Breaker #3 on the emergency power panel should not be secured because it supplies power to the isolation doors, door 101, and the personnel airlock doors.
With the reactor operating, the compressor for isolation valve 16B may only be electrically secured when the valves are placed in the closed position. Should this be necessary, open the local switch only, because the main switch also provides power to the facility and reactor isolation systems.
The instrument air compressor may be shut down by opening its local breaker. Its main supply may be secured at breaker #3 of LP11. When secured, if air supply is still required, the cross-connect valve from the main compressor may be opened.
If any of the components or compressors above are secured or placed in a postuon other than normal, the component shall be tagged in accordance with the tagout procedure.
VII.11 Sulphuric Acid System VII.11.1 ReceMng Bulk Acid CAUTION: This process is extremely dangerous.
Protective equipment must be worn. Always have an available supply of water and sodium bicarbonate.
Bulk sulphuric acid is delivered by tank truck and is transferred to the storage tank by air pressure or gravity drain. When possible, the gravity drain method should be used. In the event air pressure must be used, extreme caution should be exercised, The tank truck can easily exceed the receiving capacity of the system. Eusure that the tank pressure does not exceed 15 psig and closely monitor tank levels.
Rev. 1/02/92 App'd M SOP /VII-34 ]
Page reset
1
.= A L Remove the cap on the fill line and opsn fill lino vciva. ]
Manually obtain and record volume of bulk tank. -]
B. - Check valve 1 closed and valve 2 open.
C. _Open valve 3. -
D. Crack open the Tank O-Meter bubbler valve 7 to give an air flow of 3-4 bubbles per second. Note and record the tank level indicated on the Tank-O-Meter. Also note the level L in the Day Tank.
E. Connect the transfer line from the truck to the ] ,
tank fill valve and commence filling the tank. -]
1 F. While the tank is filling, watch the Tank-O-Meter to insure that an air flow of 3-4 bubbles per secc7d is maintained.
CAUTION: If the system is over filled, act I will spill into the mixing tank. The-heat generated at this point could >
result in damage to the add handling system.
4
- G.- When the tank volume reaches 700 gallons, have the driver secure the transfer.
-H._- Have the driver vent the pressure off the truck
-L---
Disconnect the hose from the truck and allow the acid in the hose to drain into the storage tank.
J. ; Close bubbler valve. ]
K. Disconnect transfer hose from the . storage tank. - Manually ]-
obtain and record new volume of bulk tank. Also ]
record level of day tank. ]
L. ' Report to driver the amount of acid received.-
M.' Verify that the bubbler valve (7), valve 1. and valve-3 are closed and valve 2 is open .
!N. Close fill line valve and recap.
O. Log evolution in console log.
_ Note: Letters A through O rearranged.
'Rev. 1/02/92 App'd -- bMA SOP /VII-35
+
m-- ,.--,
l .
Vll.11.2 Transferring Acid from the Storage Tank to the " Day Tank" When the acid in the day tank has been used, the tank is refilled with acid from the storage tank by carrying out the following procedure:
A Manually obtain and record volume of bulk tank. ]
B. Check valve 2 open and open valve 3.
C. Crack open the bubbler valve (7) to give an air flow of 3-4 bubbles per second.
D. Ensure fillline valve used and recapped. ]
E. Check valve 1 closed.
F. Screw down on the air regulator (6) until a pressure of 15 psig is indicated on the pressure gauge.
G. Close valve 2 and open valve 1. The indicated pressure will drop until the storage tank has been pressurized and the actual transfer begins. If the pressure rises above 15 l psig, reduce it to 15 psig by adjusting the regulator.
H. During the transfer, monitor the storage tank and day tank levels. Maintain a bubbler flow of 3-4 bubbles per second on the Tank-O-Meter. -
I. When the day tank is full, close valves 3 and 1.
J. Open valve 2 to depressurize the storage tank.
K. Back off on the air regulator (6).
L. Close the bubbler valve.
M. Manually obtain and record new volume of bulk tank. ]
N. Record evolution in console log.
Note: Letters A through N rearranged.
Rev. 1/02/92 App'd _ M SOP /VII-36
c Air conditioning units. !.10 all Secondary Ptunpa are secured.)
- d. Ilot water recirculat.tng plunp. ] >
- c. Room 212 (North counting room) air conditioner.
(Notify Resec.rch and Applications Group.)
- i. Room 232B (irrGRC Counttug room) air conditioner. ;
(Notify Research and Applic6cns Group.)
- g. Roont 260 air conditioning umt,
- b. Ice machine. I
- t. Control rcom water heater.
- j. RTAll recirculating pmnp (tag at motor controller at 1 DI-200 regeneration Station), )
" 6. Males console enby that the machinery above has been 'agged out, as per REP-12, and fill out UNSCHEDULED SIIUTDOWN REPORT.
ITCOVEl' ' AC110N'); ,
- 1. Upon restoration of water to the facility, return all systems to I norrnal status.
2 . . ounce to entire facility the restoration of domesue cold water service.
c Rev _1/02/93 App'd MA- REP-12-2
_ _ _ . - _ _ ___ .__.------__--_-u-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - - - - - - - - - - - "
_ . _ _ _ _ . ~ . . . _ _ . . . _ _ _ _ _ . ,
i' :
l RCTUlT1QAIGINAi. lQtf:/.LIUELD'SES.QEECE No. , '
WtSy.lNM eat.C'tE REPORT TANK NO._ TANK LEVEL _ (Luers)
- SAMPLE R __ ___,_ _ ___ TIME _ DATE -_.,,_. .
. ................. .............f.....,.................................. ,
- 1. Analysis Results lhit!!d.2 HMf Life NfCALfann Concentration N2Q Agity).ty
- e- th? _. 2E . , _
A _ -
2
, - m. --
pH ~ FRACTION OF MPC
- (Notot pH MUST DE JETWEEN 5.5 - 9.5 FOR RELEASE) )
! -Ar.alysis by ._m .- TIME DATE . , ,
Qnecntration ImCi/ mil TsjaL)lolume ditets) Activity (mC0 (a) _ _ _
( b ). _ . . _ _ - .
l
. 2. Approvals Required for:
- An y Dis cai g e . . . . . . . . . . . . . . . . . . . . , . . . . . . , . . . . . . .... .
Shift Supervisor
. . Disc:1arge of > 10 mei of H3, > 2 met of other activity, or to 86condary System . ~
Reactor Monager
. Discharge Limit Approved . . . . . . . . . . . . . .
Health Physics o 3. Acfon raken .
L Datel Dircharged _ Time Discharged . Votume Olscharged ,_ _(Utors) ,
Tank Discharged to (check one) Sanitary Sewer . _ Socondary Sysiern , Not Discharged REMARKS _ ,_, __
- Rev, 1!02M2 App'd NADL SOP /A.11 a r
e +- r -%7myr-+wy ,t+e- e e. m 4- --awm- w ,%c--n w e- .--*.r-
- r-T-w er r , e c --*r- *g-i n-ww-r 3 -w--
i STANDARD OPERATINO PROCEDUltES 2nd Edition. IMrective Date: 5/02/89 Olevisions #1 through #24 to the October 1981 printing were incorporatedJ Revision Number 8 Revision Date: February 28,1992 SOP /III 9 SOPNil 12 SOPNII 13 SOPNil 14 l'
SOPNil 30 SOPNil 31 SOP /VII 32 L SOPNil 33 -
I SOPNil 34 SOlWill 13 SOPNill 38 SOPNill 39 SOPNill-40 ,
REACTOR EMERGENCY PROCEDURES REP 12 2 REP 211 Retyped Only REP 212 REP-213 Deleted SOP /A la -
SO P/A 1c SOP /A 3a SOP /A 8a SOP /A 8b SOP /A-Sc SOP /A 18a 11 4
111.8 Area Radiation Monitoring System The area radiation monitoring system will be in operatJon continuously and is to be turned off only during maintenance on the system. When handling samples 'r during maintenance place the Bridge Upscale Switch in the upscale position, insure Bridge Upscale Switch is returned to nonnal position after handling samples.
'lhe station trip points shall be set as follows:
Station 1 BP North Wall 2 X acceptable background Station 2 BP West Wall 2 X acceptable background Station 3 BP South Wall 2 X acceptable background Station 4 Exhaust Plenum Imr/hr or 10 X normal operating background Station 0 Bridge ALARA 300mr/hr alert 10K mr/hr alarm / trip Station 7 Bridge 50 mr/hr or 10 X normal operating backgrou.1d Station 8 Nuclepore 2 X normal operating background Station 9 Fuel Vault 2 X normal operating background Station 10 Room 114 2 X nonnal operating background Station 11 Exhaust Plenum #2 1 mr/hr or 10 X normal operating background At least once a month for stations 4,6,7 and 11, and once a quarter ]
for the remaining stations, the system will be checked according ]
to the following procedure:
NOTE: GREEN Lamp serves as Normal light and Check Source actuating switch (push to actuate source).
AMBER Lamp serves as Alert alarm (posh to reset).
RED Lamp serves as High alann (push to reset). The alert has been set up on all ARMS units except for both bridges.
A. At station 1,' operate the check source pushbutton and verify .
that when trip point is reached, the RED alarm lamp lights at l the Electronic Channel, and the RED alarm lamp lights and the AUDIBLE alarm sounds at the Remote Alann Unit.
B Repeat step A for Stations 2, 3,8, 9 and 10.
Rev. .?/28/(2 App'd RM SOP /llI-9
_ - . . , . _ , . . - ~ _ . ~ . . . _ _- ___.- - , _
Vll.4.2.7 Transferring Tritiated (311) Water to the DCT A. Check the Di RESIN LOG for the status of the affected bed (s).
D. ENSURE all valves, including unused valves on adjoining systems are CLOSED.
C. ENSURE the operability of the DCT system by pumping down the collection tank prior to this operation.
D. ENSURE Ole flexible hose is connected to the DI water supply, then OPEN RE-89 and RE-18.
E. OPEN RE-25.
F. OPEN DI 9 AND DI 14.
G. OPEN DI 10 (DI-200) or DI-ll (DI-201) or DI-12 (Dl-202),
whichever is applicable to this operation, to start the water transfer,
- 11. When tank is empty, CLOSE DI-10 DI-ll or Dl-12 (whichever is applicable) and DI-9.
- 1. Of@1 Dl 8, R 2 and DI-3 to fill the tank with water.
J. When full, CLOSE DI-3 and Dl 8.
K. REPEAT steps F through J so that you have completed two ]
water transfers and fills. The bed will be left in a filled condition. Use CAUTION to assure that you do not overflli the DCT.
L _ When completed, CLOSE Dl-14. R-2, RE-25, RE-18 and RE-89 (T-300 to Dl-200 isolation valve).
M. OPEN RE 68 to vent pressure in the flexible hose, then CLOSE RE-68.
N. RECORD the transaction in both the DI RESIN LOO and the console log.
- 11. 4 . 3 Providing D1 Water to T300 DI water may be sent to T300 with or without the use of the reverse osmosis unit as a D1300 makeup supply Due to the fact that DCW, after passing through the R.O. Unit, is much more pure than raw DCW, the R.O. Unit is normally utilized to prolong the life of the D1300 resin regeneration. However, there are provisions for bypassing the R.O. Unit when sending D1300 water directly to D1200 (see Vll.4.3.3).
Rev. 2/?8/92 App'd WM SOP /Vil-12 1
l Vll.4.3.1 Providing DI WaLr to T300 with Reverse Osmosis Makeup I 1
A Culligan (Polishing) bed is used to augment the R. O. unit. ]
A. Open T-300 supply valve (RE-31). i B. Check open the following R. O, tmit valves;RO 1, RO 2, )
, RO 5, RO 7, RO 8, RO 0, RO-10 and RO 13. ]
C. Open outlet valve (RO 11) from Culligan bottles. ] i D. Open DI-5. ]
E. Turn conductivity meter to "ON" and place auto valve switch to "nUTO" (first auto valve should open).
F. Push the R. O. unit start button. ]
G. Push reset button under conductivity meter (second auto valve should open). There should be a 3 to a second delay ]
before RO unit starts. (Pressure should come up to )
100- 200 psig.) ]
CAUTION: If valves do not open, the conductivity is at or above alarm setpoint. Place normal / bypass switch to "DYPASS".
H. Flush R. O. unit through DI 5 until conductivity falls below ]
alatm setpoint.
I. Open auto valve isolation valve (DI-17) and shut DI-5. 1 J. Place normal / bypass switch to " NORMAL" if required.
TO SECURE SENDING WATER A. Push the R. O unit off button ]
B. Place auto valve switch to "CL.OSE." Turn conductivity meter to "OFF" (bout auto valves should be closed).
C. Shut auto valve isolation valys (DI- 17).
D. Shut Culligan bottles discharge valve (RO 11). }
E Place product water valve RO-10 to the Bush position (CW). ]
Rev. 2/74/99 App'd (M W SOP /Vil-13
, _ - . - - - - - - . _ - - - - - _.~-. .-
F. Shut T 300 supply valve (RE 31).
CAUTION: The following valves should be left open while the unit is in OFF. ]
RO 7 ]
RO 8 ]
RO9 )
RO 13 )
When the unit is not in use, DO NOT UNPLUG PLACE ]
IN STANDBY ONLY. DO NOT SECURE SUPPLY WATER.
NOTE: If for any reason the unit must be tumed off or the supply water sceured, this condition MUST NOT exist for more than 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> or damage will occur ]
to the filter membrancs (see technical manual for details).
Normally, the water inlet temperature will not require adjustment and is set at approximately 25 to 30*C. Allow ]
at least 30 minutes of running time to stabilize temperature prior to determining if an adjustment is needed.
No regular maintenance is required to operate this unit.
For any repair or maintenance, refer to +.he technical manual.
VII.4.3.2 Providing D1 Water to T300 Without Reverse Osmosis Unit MakeupTransferred to SMP-22
~
Vll.4.3.3 Providing DI Water to D1200 Units Using R300 Bed Transferred to SMP-22 E
.Rev. J 28/92 App'd (A%M. SOP /Vil-14
_ . . ~ . . . _ , . _ .-
Vll.0 Nitrogen System ]
Vll.0.1 Purpose The primary function of the Nitrogen System (N2 ) is to provide pressurized N2 to the pressurizer to maintain primary pressure. 1 Vll.0.2.1 N2 System Startup ]
Before the reactor is made operational, light off the N2 system by the following procedure: )
A. Verify that the regulator is set at 140 psig and the average ]
gauge pressure of the two N2 banks is at least 500 psig ]
before placing the system ht operation. 1 B. Close the switch which energizes the electrical controls 1 for the system. )
C. Open the N2 cut out valve 'N1tl in room 114. and verify )
a N2 pressure of 90 to 05 psig to the pressurizer. ]
The N2 system is now ready for operation. ]
Vll.9.2.2 N2 System Shutdown )
After the reactor has been secured the N2 system may be shutdown by shift supervisors pennission, as follows: )
A. Close the N2 cut out valve N15 in room 114. ]
B. Secure the N2 control system by opening the elect.rical switch at the bottle station, Vll.10 Compressed Air Systems VII.10.1 Valve Operation Air System ]
The valve operation air system provides air to the valve operation ]
header. The operation of the valve operation air system is fully ]
automatic. The operation of the system is monitored every four ]
hours during plant operation. The only manual evolution required is blowing down the Deltech filters every four hours. If moisture is detected in the air bled from the filter, the filter should be Rev. 2/28/92 App'd SYe SOP /Vil-30
l l
4 blown down until no further traces of moisture are seen. The ,
filter element turns a dark red color when it traps oil. The filter c!cment shall be changed when more tJmn 75% of its volume has turned dark red in color. '
VII.10.1.1 Valve Operation Air System Startup ]
Before the reactor is made operational the valve operation air ]
system is placed h1 operation and lined up to provide service to ]
the valve operation header. ] l I
A Close breaker on MCC 5. ]
R Check 0111cvel. ]
C Check shut VOP20, the receiver discharge valve, )
D. Place knife switch to on and place Off/ Auto switch on ]
controller to " Auto". ]
E. When compressor has pressttrized the receiver and ]
shutdown, open VOP20, the receiver discharge valve. ]
F. Open VOP33, the main air system cross connect valve. ]
G. Open VOP31, the air cut out valve, to pressurize the ]
valve operation header. ]
H. Verify valve operator header pressure of 115 i 10 psig. ]
VII.10.1.2 Valve Operation Air System Shutdown ]
A Place valve operation air compressor to "Off". ]
R Close VOP20, the receiver discharge valve . ]
C Close VOP33, the Main Ah system cross connect valve . ]
VII.10.2 Main Air Compressor System ]
VII.10.2.1 Main Air Compressor System Operation ]
The main air compressor operates contJnuously to supply air to the facility. -The pressure is maintained at approximately ]
100 20 psig. The desiccant dryer has a viewing window for ]
pellet level inspection: and the supply should be replenished when the level falls below the required level. The system requires that the after-cooler be in operation whenever the compressor is in operation. Should DCW to the af ter-cooler be secured, the main compressor must be secured to prevent damage.
Rev. 2/28/92 App'd b% SOP /Vil-31
VII.10.2.2 Main Air C mpr:sscr Sy0 tem Startup ]
A. Close breaker on MCC3.
D. Verify all valves in proper position for desired operation. ]
C Verify main air compressor after-cooler water supply operable with the chill water pump running.
D. Verify desiccant air dryer contains sufflcient desiccant ]
pellets.
E. Check DOTII head oil and crar.k all levels. ]
F. Place the local switch to " Auto" G. Verify receiver pressure of 100120 psig., ]
VII.10.2.3 Main Air Compressor System Shutdown ]
1hc main air compressor may be shut down for maintenance ]
during Reactor operation provided that: ]
A The operability of the emergency air compressor has been verified.
B The cross connect valve to the backup doors (supplied fro n the emergency compressor) is open to provide an alternate supply of air to keep the backup doors open.
C Large volumes of air are not required for a particular evolution (Topaz Counting System). ]
D IIoteellisointion valve has been switched to N2 bottle. ]
Place the compressor in "Off'. The compressor umy be electrically isolated by opening the main breaker on MCC3.
VII.10.3 Emergency Air Compressor System ]
VII.10.3.1 Emergency Air Compressor System Operation- ]
The emergency air compressor is always available as a backup for main air system loads within containment. It is checked for proper operation weekly. The compressor assumes the load at 65 i 10 psig and supplies sufficient air for all door gaskets and equipment within containment.
The stop button for the emergency air compressor will stop the ]
compressor, but if the pressure is below pressure switch low ]
limit when stop button is released the compressor will start ]
again. If the start button is pushed the compressor will run, ]
but if the pressure is above pressure switch Idgh Ihnit when the ]
start button is released the compressor will stop. ]
Rev. 2/28/92 App'd M SOP /VII-32
VU.10.3.2 Emcrgency Air Compr:suct Sy: tem Startup ]
i A. Close breaker #3 on the Emergency Power Panel.
R Verify all valves in proper position for desired operation. 1 C. Check 0111cvel in sight glass. ]
D. Close the local supply breaker (5th level). }
E. Verify compree** T starts as necessary. ]
VU.10.3.3 Emergency Air Compressor System Shutdown ]
The emergency air compressor must be operable when the reactor is operating or when mov!ng irradiated fuel. ]
A Open the local supply breaker. )
VU.10.4 10B Backup Air Compressor System )
VU.10.4.1 10D Backup Air Compressor System Operation ]
The backup air compressor for 1GB isolation valve will only ]
operate upon failure of both the main and emergency air j compressors. The ecmpressor assumes the load at 60 5 psig. ]
and provides air only for 10B. 1 VU.10.4.2 IGD Backup Air Compressor System Startup ]
A. Close breaker #18 on the Emergency Lighting Panel. ]
a Verify all valves in proper position for desired operation. ]
C. Close local toggle switch at the compressor. 1 D. Verify receiver pressure of 45 to 55 psig. ]
VU.10.4.3 10B Backup Air Compressor System Shutdown ]
The IGB air compressor must be operable or IGD must be shut ]
when the reactor is operating. ]
A Open the local toggle switch. ]
Rev._2/28/92 App'd bh SOP /Vil-33
. _ _ _ _ _ _ . . _ . _ _ _ _ . _ _ ~ . _ . _ . . _ _ _ .. _ .___ .-.__ _. _ .. _ .
. VII.10.5 In:tntmst.t Air Ccmpresser System (Johnson) )
I VII.10.5.1 Instrument Air Compressor System Operation ] l The instrument air compressor is always valved for operation and operates at a pressure of 70 i 5 psig. Should this com- :
pressor fall instrument air may be supplied from the main l compressor by opening the cross-connect valve located near the compressor and closing the cut ote tive for the compressor.
l VII.10.5.2 Instnunent Air Compressor System Startup ]
A _ Close breaker #31 on LP11. ]
B. Check receiver outlet valve open. ]
C Check ol11evel. ]
o D. Close local switch at the compressor. )
VII.10.5.3 Instrument Air Compressor System Shutdown i
A .Open local switch at compressor. }
VII.11 Sulphuric Acid System Vll.11.1 Receiving Bulk Acid CAUTION: This process is extremely dangerous.
Protective equipment must be worn. Always have an available supply of water and sodium
-bicarbonate. Bulk sulphuric acid is delivered by tank truck and is transferred to the storage tank by air
' pressure or gravity drLin When possible the -
gravity drain method should be used. In the -
event air pressure must be used, extreme caution should be exercised. The tank truck can easily exceed the receMng capacity of the system. Ensure that the tank pressure does not y exceed 15 psig and closely monitor tank levels, s
i l
l Rev. 2/28/92 App'd M SOP /VII-34 L
l >
The weight limits above do not include the weight of the rabbit. I polyethylene vial, or packing, or the cadmium (or other metal) shields, The maximttm irradiadon time for most samples will be one l hour at power levela <5 MW and 30 minutes for power levels j
> 5 MW. IIair, fibers, paint, air filters and flux monitors may be !
frradiated for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at power levels < 5 MW and '
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at power levels >5 MW The fodowing additional limitations shall apply for irradlauons >10 minutes: i
- 1. Primary encapsuladon will be heat-scaled high-<lensity j polyethylene vhls (Ifolland vials).
- 2. I.Jquid samples may be irradiated for up to 30 minutes provided pin holes are punched in 02e top of the polythylene vial to relieve pressure.
Deviations from the above weight and time limitntions must be specifically authorized in the experimenter's RUR.
VI!!.3.3 Rabbit Limitations A The only type of rabbit which may be used in the p-tube system is the high density rabbit. This type of rabbit will be used for all irradiations (see Section Vill 3.2.B). Each high density rabbit will be limited to six insertions not to exceed a l
totalirradiation time of one hour or a single insertjon not to exceed a total of two hours.
EXCEPTION: Esmh high density rabbit, used for 5 second 1 trradiations under RUR 254, is authorized to } ,
be run a total of 15 times, 1 To account for the irradiation history of high density rabbits, the experimenter will place one mark with a marking pen on the high ,
density rabbit for each insertion up to and including 10 minutes. For irradiations longer than.10 minutes, a mark will be placed on the rabbit fer each -10 minute period or fraction there of. 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.
Rev. .2 nn / o? App'd Mid SOP /Vlli-13 -
%
- g s-y *- ms--- pp r, ,av y -- -
w ,- y,-, , - g--
I Vill.5 Handling and Release ofIrradiated Samples c Vill. E l General Resp 0nsibilities I
^
)
The Reactor Services Engineer shall coordinate the handling and chipping of all samples irradiated in die in-pool facilities.
He shall ensure that die shipping container is in conformance with the applicable regulation and that all required shippirrg papers and documents are prepared in a timely manner.
The Senices Engineer shall also coordJnate use sample handling with Health Physics personnel.
' Die Shift Supersisor shall have the responsibility of ensuring that all irradiation reccrds are complete. He will immediately notify tSe Services Engineer or his designated ]
representative of any apparent discrepancies relating to the ]
in-pool irradiations.
VDi.5.2 Sample Handling Procedures Detailed procedures for the handling cf various samples are contained in the Health Physica Standard Operating Procedure
% . Response Piecedures for the Nuclopore Irradiation Facility The following procedures shall be used when responding to alarms for the Nuclepore Irradiation Facility.
V!II.6.1 Nuclear Erhaust System Alarms ]
A Nuclepore ARMS ]
. NOTE: If Nuclepore ATGiS is out of service for any reason ]
l (e.g. repair or calibration), the Nucleptue irradiator ]
system shall be red tagged off. ]
- 1. If the Nuclepore ARMS alarms, secure the Nuclepore ]
system. ]
- 2. Verify rabbit is fully retracted. ]
j 3. Notify the Shift Supervisor and Health Physics, 1 1
i Rev. 2/28L9.? App'd $$t,A_. SOP /VIII-38 l
l
9 R Reactor off-gas stack high activity
- 1. If the Nuclep re irradiation Facility is suspected to be the cause of the stack high activity alarm secure Ole system.
Verify rabbit is fully retracted.
- 2. NotJfy shift Supervisor and Health Physics. ]
I Vill.0.2 Automatic system shutdown trip alarms require the following 1 action:
A Verify the film drive motor has stopped.
H Verify the rabbit has retracted to die full out posidon.
C Time and date the film roll.
D. Notify the Nuclepore system technician.
Those alarms are as follows:
- 1. System failure alann
- 2. Large roll alarm
- 3. Take-up dancer alarm
- 4. Supply dancer alarm
- 5. Gas system alarm
- 6. Drive power alarm Vill.6.3 Alarms having no automatic function require that you either ]
remedy the cause of the alarm or shut the system down. The alarms are as follows:
A High oxygen concentrauon alarm
- 1. Increase the helium flow.
- 2. If you are unable to immediately reduce 02 concentration, shut down the system and withdraw the rabbit.- Contact the Nuclepore system technician, a Helium supply alarm 1 Place a new helium bank on supply.
- 2. If the alarm does not clear, shut down the system and 4 contact the Nuclepore system technician.
Rev. 2/?8/92 App'd DW\ SOP / Vill-39 L
L i
- . _.- ____ .-__ _ _ . _ - -__-. ._.-_ _.m_.____ _~.
I C. Alarm funcuan failure alann
- 1. Shut down the Nuclepore system and noufy the Nuclepore l system technician, j
- D. PISH-5 alarm
- 1. If the PISii-5 low alarm light is on at Cabinet B. shut '
down the system and notify the Nuclepore system technician.
E. Small roll alann
- 1. Note the time and prepare to shut down the system at the prearranged interval specilled by die Nuclepore system "
technician. ,
NOTE: A comprehensive systems procedure and systems description manual provided for the Nuclepore system )
is located at the system operating stauon for emergency reference.
Vill.7 Thennal Column Door Operations Vill.7.1 Opening The Thermal Column Door NOTE: Do ng1 open thermal eclumn door with the reactor critical.
- 1. Clear all obstrucuans from behind thermal column door.
- 2. Verify air off to Radiograph with Control Room.
- 3. Disconnect air supply line on thermal column door at the snap fliting.
- 4. Verify Neutron Radiograph rotating aperture drive shaft pulled back and disconnected.
- 5. - Preparntion of Nuclepore Case:
A Decouple Nuclepore take-up shaft.
B Remove alignment pins from shield box door.
C Roll shield box cover as far back along track as possible.
L (NOTE: If thermal column door must be backed out further than this attach shield box door lifting rig and move to south _ side of the r .atform using the building crane.)
l l Rev. 2/28/92 App'd M'\ _ SOP / Vill-40 e
, y v - -
,, y --- --g-- - ,-- y---y-* -, - , , - - - p
LOSS OF DOMESTIC COLD WATER TO FACILITY (cont'd)
- c. Alpha Lab, thermal wen (notify Alpha Lab. staff). }
4 Air conditioning Units. (if all Secondary Pumps are '
~
secured.)
- c. Ilot Water Recirculating Pump.
- f. Room 212 (North counting room) air conditiot ;r.
(Notify Nucicar Analysis Program) ]
g Room 232B (West Counting room) air conditioner.
(Notify Nuclear Analysis Program.) 1
- h. Room 200 air conditioning unit.
e
- 1. Ice Machine.
J. Control Room Water Heater.
- k. RTAH recirculating pump (tag at motor control!cr at DI-200 regeneration station).
G. Make console entry that the machinery above has been tagged out as per REP-12, and fill out UNSCHEDULED SHUTDOWN REPORT.
RECOVERY, ACTIONS:
- 1. Upon restorauon of water to the facility, return all systems to normal status.
- 2. Announce to entire facility the restoration of domestic cold water service.
Rev. 2/g8/92 .
App'd M REP-12-2
REPo 21 HIGH STACK MONITOR INDICATIONS IMMEDIATE ACTION 8;
- 1. Notify the Shift Supervisor.
- 2. Notify the Manager oflicalth Physics After working hours contact: IIEALTH . fYSICS CALL LIST.
SUBSEQUENT ACTIONS:
- 1. Evaluate the extent of lodine and particulate levels with overlay 1, and gas with overlay 11. If the extent of radioacuvity is great enough to enter event classifications, the highest category of event indicated by gns, lodine or particulate reading will be used to classify the event.
A. IODINE and PARTICULATE: (overlay I)
Check the stack monitor reading with overlay I, The ranges of values represented on the overlay are the threshold levels of concentrations corresponding to specific emergency events in excess of Technical Specification limits.
i The overlay thresholds assume the present release rates will be constant for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. They are conservative, since the l
present release rate may exist for less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the emergency action levels are:
UNUSUAL EVENTS - 3800 MPC averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ALERT EVENTS -
19,000 MPC averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SITE AREA EMERGENCY - 95,000 MPC averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
-(1.e., for UNUSUAL EVENT > could how 91,200 MPC for- 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> =
3800 MPC x 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; therefore still uave 3800 MPC averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) .
These overlays are to graphically as'sist the operator's judgement as to the extent of release. i Rev. '7/03/85 : App'd \MrA REP-21-1 j '
Retyped Only 2/28/92 O
r N <>ila n-- n rm,, ---a,w- S N --n +g w- ,.m- ,,m+ y p,-, .- e,., , - - y y- .m. e p-,3-y,-ar,,-,+,--,m-p---yps ymy-p , m y mn ,-,w-w<g---r
11101I STACK MONITOR INDICATIONS (cont'd)
D. QAS (Overlay 11)
NOTEI THE THRESHOLDS IN 1 TI! ROUGH 4 ARE BASED ON )- !
ONE (1) HOUR AVERAGE CONCENTRATIONS USED TO 1 !
PREDICT THE POTENTIAL EMERGENCY CLASSIFICATION. ] ;
THEY ARE MORE CONSERVATIVE ESTTMATES THAN ]
THE 24 HOUR AVERAGE THAT IS CALCULATED BY THE I FORMULA. ]
- 1. JE gas concentration exceeds 3.3. X 103 CPM (3800 MPC) but less than 1,66 X 104CPM (10,000 MPC), and remains betwcst diese levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with no evidence of declining, the event shall be classilled as an ])yUSUAL EVENT, 1
- 2. JE gas concentration exceeds 1.66 X 104 (10.000 MPC) but less dian 8.3 X 104 CPM (05,000 MPC) and remains between these levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with no evidence of declining, the event shall be ,
classified as an ALF2I.
- 3. E gas concentration exceeds 8.3 X 104 CPM (95.000 MPC) but less than.1 X 10 6-(FULL SCALE) and remains between these levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with no evidence.of declining, the event shall be classified
. as a SITE AREA EMERGENCY. .
- 4. E gas concentradon reaches full scale and remains there for 10 minutes without decline and cannot be attributed to electronic failure the event shall be classifled as SITE AREA EMERGENCY. ]
NOTE: A GENERAL FORMULA FOR DETERMINING 24 HOUR
- AVERAGE CONCENTRATIONS IS AS FOLLOWS ANY '
- APPROPRIATE TIME INTERVAL CAN BE USED BUT MUST BE EXPRESSED IN MINUTES.
Avis It(TERVAL RCADING (in CPM) X INTERVAL TIME DURATION (MIN)
G411flR A\En EMW/Hra -
241 LOURS Rev. _2/?R/92 _ App'd % REP-21-2
~ ~ . , ,nn-r--..
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I '
l l REACTOR STARTUP CllECKS11EET DATE: .
TULL POWER OPERA ~nON 'nME (Started):
BUILDING AND MECHANICAL EQU!PMEb7 CHECKl.lST
' 'l I 1. Emergency att compressor (load test for 30 minutes after maintenance day).
- 2. Beamport I'loor:
_ a . Deamport radlauon shielding (as required).
- b. Deamport status checked / updated,
- c. Seal trench low level alarm tested (after maintenance day).
- d. Check closed beamport floor access gates.
- 3. a. Check operauon of fan failure burzer and waming light. Notify Alpha lab of momentary
- ventilauon loss. (Reg'd if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
I b. Test stack monitor and low flow alann per SOP whde in w .t tower.
- c. Test UPS alarm panel.
- 4. Emergency generator availability checked as per Sect l.A. and 111. of D.G. checklist.
tif shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, run emergency generator for 30 minutes.) l I I 5. Emergency pool fill. (Check valves PIV 1 and PIV.2 locked open.)
O. Visual check of CT and secondary equipment:
- a. Od level in CT fans nonnal (after maintenance day).
- b. Secordary makeup isolauon valve power switch closed, val.e cycled to venfy operadon and placed in auto mode.
- 7. 'tisual check of room 114 equipment:
- a. Valve Op Air compressor oillevel normal and cutout switch in auto. )
- b. hialn air back up valve VOP 33 open. I
- c. Air valve for vah'c operating header (VOP31) open,
- d. P501A and P501B coolant water valves open
- c. Check vah es 599A and 5995 open.
- f. Pump controlhrs unlocked to start (as required),
- g. 51 and S2 hydraulic pumps on (oillevel normal).
- h. Valves 51 and S2 cycled in manual mode and postuoned as required.
- 1. Verit the pool hold up tank.
J. Vent the pool skimmer system pump,
- k. Check the pipe trench free of water. Check the four pipe annulus dratn valves for water leakage after maintenance days.
- 1. Add D! water te beamport and pool overflow loop seals,
- m. Check oil reservoir for pumps 501A. 501B and 533 for adequate supply. Add if necessary,
- n. Visually check room 114 and D1 area after all systems are in operation.
- 8. Renctor pool;
- a. Reflector experimental loadings venfled and secured for start up.
- b. Flux trap experimentalloading vertfled and secured for start up, or stratner in place.
- c. Check power on and reset, as necessary, silicon integrator, totalizer setting, silicon rotator an alann system.
Rev.212EloDpp'd .jiIrF SOP /A-1 a 1
l
REACTOR STARTUP CHECKSHECT FULL POWER OPERATION (cont'd; Page 3
]
- d. ARMS trip setpotnts checked and tripped, check bur 2er opemtioral locally fcr all
[~
channels and remotely for channels 6 and 7. ]
Channel 4 . E.xhaust Plenum Channel 6 Bridge A1 ARA Channel 7 Reactor Bridge Cnannel 11 Exhaust Plenum 82[B/U)
- e. Reactor tsolation horns switch in *lsolation Ho.ns On* postdon. Valves and d ors open,
- f. All ARMS trips set per SOP.
- g. Check ventilation fans, containment and backup doors,
- h. Armounce completion of test to factlity evacuation isolation system (Notify police)
- 20. Operate reg blade from full out to full in and set at 10" . 05".
- a. Chect; rod run in functjon at 10% withdrawn and annunciator at rod bottomed
- 21. Raise blade A to 2" and manually scram.
- 22. Rals.e blade B to 2' and trip manual rod run in.
- 23. Raise blade C to 2" and scram by WRM trip.
- 24. Raise blade D to 2" and senm by IRM trip
- 25. Annunciator board energt;zd: horn on.
- 26. J mper and taglog cleared or updated.
- 27. IRM recorder in fast speed.
- 28. Check magnet current for 90 ma on each magnet.
- 29. Cycle WRM range switch.
- 30. Resec
- white rat
- scram monitor.
- 31. Estimated critical blade position (corTected): inches.
- 32. Pre startup process data taken.
- 33. Routine patrol completed.
- 34. All reactor and license related systems upon which maintenance was perfonned ha"e been reviewed and are operable.
- 35. Reactor ready for stanup.
Time (Completed)
ShiR Supervisor / Lead Senior Operator Rev. 2/ 28/92 App'd WOh\ SOP /A le
I3 Date._
Time REACTOR SHORT FORM PRECRITICAL CIIECKSIIEET 1 Nuclear Instrument checks completed per SOP section 111
- n. The following trip values were obtained during the checks:
1RM-2 run-in sec(11 1 1) scram sec(9 1) 1RM 3 run in _ sec(11 1) scrain secl9 1)
Wrai-4 run in _ %(114 1) scram %(119 i 1)
_ PRM-5 rur. in %(114 i 1) scram %(119 1)
PRM 6 run in %(114 1 1) scram %(11911)
- 2. Channel 4, 5, and 6 pots retur. ed to the last heat balance position.
___ __ 3. SRM-1 detector response checked and set to indicate >l cps.
_ 4. ITG1 recorder in fast speed.
_ 5. Cycle WRM range switch.
- 6. Annunciator board energized: horn on.
- 7. Reset " white rat" scram monitor.
- 8. Estimated critical position (corrected): inches.
- 9. Reset scram and rod run-in circuits.
._, 10. Reflector and flux trap experiment loadings secured and ready for startup
- 11. Reactor ready for start up.
Shift Supenisor/ Lead Senior Operator NOTE: FORM REVISED IN ITS ENTIRETY ]
Rev, 2/28/92 App'd @41 SOP /A-3a
I i
REACTOR ROUTINE PATROL DATE'
- 1. Time of star 1 of patrol 5.. Time and dato all charts . .
- 3. Visual check of entiro pool
- 4. An11. siphon tank pressure 36 psig 13 psi North iso door seal pressuro 18 28 psig
,5.
- 6. South iso door seal pressuro 18 28 psig
- 7. 5th lovel backup doors open 8,10' iso viv A air pressure 45 55 psig 9.1G* Iso viv B air pressuro >80 psig }
~~
B cs vopen,
- 10. Ernerg air compress on standby g
- 12. Door 101 seal pressuro 18 28 psig
- 13. BP floor Conditions normal
- 14. Fuel vault Locked
- 15. Inner airlock door seal pressure 18 28 psig l6, Outer airlock door seal pressuro 18 28 psig
- 17. Cold deck temperaturo 45 65 deg F
- 18. Argon bank pressuto >200 psig
- 19. Full N2 bottles Total > 3
- 21. Bank on servico A or B
- 23. Bank A bottle pressure > 250 psig
> 250 psig
- 24. Bank B bottle pressuro
- 25. N2 header pressoro 135 1/5 psi
- 26. T 300 level >2000 gal On the first routt patrol of the day or the first patrol after a startup, drain all water from the anti siphon system. If draining causes the pressure to drop signifi-cantly, return to the middle of the band (36 psig) and record the pressure here. If a condition or reading is normal, enter a "/" (for conditions) or the reading in the applicable box. If the condition is abnormal, enter the condition or reading and circle it. Explain all abnormal conditions or readings in the REMARKS on page 3.
Rev 2m/o? App'd M SOP /A 8a
REACTOR ROUTINE PATROL DATE:
- 27. T.301 level <6000 gal ca.1.abyrinth sump Level < Alarm Pt.
- 29. RO unit Condition normal )
- 30. UPS room NO Alarms indigated Thermostat >55 F Temp > 40* F
- 31. T 300, T 301 Room Thermostat >55 F Tamo. 340 F _
- 32. Rm 114 particulate filter AP <3.5" water 33a. EG. Rm. (Perform complete F (checklist on Sunday) Thermostat Temp. >60,F
> F 0, ,_
33b. Battery charging current <1 amp -
33c. Battery Vo!tage >2BV All locked except east
- 34. External doors when sec on duty
- 35. CT basin water level 5 10" -
- 36. Automatic secondary makeup viv Auto or open 3'A Acid day tank level (Perform Visible
, weekly level check on Friday on storage tank)
- 38. Acid control and pH Range as posted
- 39. Blowdown control /cond. Range as posted
- 41. P pump (s) running
- 42. Pump strainer AP 0 7.0 psi
=
- 43. Discharge pressure
- 44. Pump strainer AP 0 7.0 psi
- 45. Discharge pressure
- 47. WT booster fan Running
- 48. Fission produr:t monitor flow 95 105 cc/ min
- 49. Viv control header pressure 90 125 psig )
- 50. Pressurizer N2 supply press 90 100 psig
- 51. Check rm 114 from door I
- 52. Deltech oil filters " red level *
< 75% dark red J and blow down Rev. 2/ 28/92 App'd turnw SOP /A-8b l
I
i 'R'EACTOR ROUTINE PATROL DATE:
- ! 53. Seal trench 61 66' Run pump on days
- 54. Wasto tank #3 level
- 55. Waste tank #2 lovel
- 06. Wasto tank #1 lovel
~
- 58. Time of completion of patrol
- 59. Operator initials REMARKS:
s- .
Rev. '/No? App'd (Milh SOP /A-8c 1 1
-. .-. _ - - _ - _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - _- _ _ -
l I
D. l. WATER MAKEUP LOG j Month Year Timo Conductivity Tomo Pressure Prod Flow ,
Water Meter Acadino )
Date Start Sion Start Sien 25 3,0 190 200 1 5 2.5 Start Sten
)
- t. -
ew 4,4 een L _. ;_ _
Remarks:
1 Rev. 2/28/92 App'd l#h\A SOP /A 18a
i MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 8
.<evision Date: September 13,1991 Section Page Number Number EMERGENCY CALL LIST FEP Table of Contents j FEP 3(a) 1 PEP 3(a) 2 l
8 6
P t
-r
. - 11 5 h
t M i , ** 4 ' - - e=- 't-' 'v -
'nt v - - - ' " * + ' *-*+--+*e <-e'--m-~~ e'er<--- --- r~'-~--' -+- -" --- *- " -
': .L . 3= .' -~ .' '~-
_- % . [:: ..:-. gg - . -
EMERGE!JCY PROCEDURE EMERGEtJCY CALL LIST Opstions Emergency Suroert Orcanizatie,s linth Ptws!cs EPmeE;
_EtxLnelt Phone f 6.
442-3534 P.t Evans 698-2450 UldCEcks 882-7201 S. Langhorst el Stavons 442-2539 K. Boamer S82-5499 ,
9-911 l J Ernst 445-5621 R. Kitch 696-3710 Columbia EkH Decartment.
l J. Ochbrs 443-4930 C. Kribbs 682.3980 '
J. Schuh 445-4985 ] 1lJd Hesnitaland Chmes T.Sorger 474-3891 } Emergency Services 882-6003 l J. Basantt 474-2046 Ambulance 882-6128 or 9-911 Wal?.-In (Emergency Center) 882-8091
_Dneciod_Qifice Phone (b.
UldQ Hullb Physics (Office) 882-7221 J. C. McKibben . 442-6728 Dn Phil Leo (Home) 445-5275
.Jamieson Shorts (Horr-e) 474-2?94 DavM Spate (Home) 657-9450 Operations RE10I_Clmmistry Phone Na, Phone fJo. MU News Bureau 882-6211 W. A. Meyer 442-7675 S Moms 445-4217 See Fi,tM informatbn 882-6214 C. Edwards 443-7529 V.Soa% 657-9450 Procedure for cinen- or T.Sctoorm 443-8862 phone numbers. (SEP 7) 382-9142 R. fluitsch 442-6653 Sla:e Ememency L'magement C. Anderson 696-5506 noency (SEMA) 314-751-2748 B.Bozonok 445-5680 G Gonn 875-1162 HRC. Washincton. D_C 301-951-0550 )
N. Tritschfor 474-9388 UflG,Hegicalli 708-790-5500 L. Foyto 446-0491 American Unfag.r insurers 203-677-7305 J. Fruits 474-0774 R. Hudson 875-0451 V. Jones 445-2543 M. Kilfoil 440 2524 P. Mu-an 473-0979 P. Noel 44," 9693 M. Rando!ph 4 7 4 - J58 9 R. Walkor 443-0970 }
M Wallis 696-1097 )
f Warner 81 G-8 8 2-6 74 0 nov 9/13/91 Aprid dm _ _
1 L
FACILITY EMERGENCY PROCEDURES (FEP)
TABLE OF CONTENTS Section No. Page No.
1 FACILrrY EMERGENCIES 1-2 Classification of Facility Eme.gendes FEP-1 Facility Evacuation Procedure 1-7 FEP-2 Reactor Isolation Protlura 1- 4 FEP-3 Fire Procedure 1 only FEP-3(a) Control Room Response to Alpha Laboatory Fire 1-2 ]
FEF-4 Medical Emergency Procedure 1-5
!!M&%C_{ Hospital & Cilnics) - nAD!ATION DISASTER PLAN i
Rev. 9/13/91 App'd bhhY
l f Page 1 of 2 ]
l FEP-3(a)
CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE NOTE: Throughout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (ALPHA-6) or Alpha Laboratory room monitor (ALPHA-3) for inoication of airborne radioactivity, as appropriate.
- 1. If a fire is detected by fire alarm or reported in the Alpha Laboratory, the shift supervisor (or senior licensed person in control) will call the Columbia Fire Department.
- 2. The shift st.pervisor will activate the Facility Emergency Organization by page system and provide warning to stay clear of facility basement.
- 3. The Emergency Director will determine nature and specific location of fire (i.e., if fire is in glove box or equipment exterior to glove box).
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will shut down to focus attention on the fire.
- 5. Ensure Alpha Laboratory doors are shitt and personnel are out of the laboratory.
If no experimenter is present, call the on call experimenter as soon as time permits.
- 6. Secure EF-13 and EF-14 at breaker on emergency distribution center im North ]
inner corridor) ONLY IF there is likelihood of fire spreading through ]
ventilation system.
- 7. Secure electrical power to Alpha Laboratory at following locations: ]
- a. Breaker #13 on UPS #2 -in control room (this secures power to the ]
Argon glove box.) ]
h Urcaker #17 on 120/208 V. distribution center - in North inner corridor ]
(this secures power to LP-34 which will secure Alpha Lab. supply and ]
exhaust fans). ]
- c. Breaker #2 on emergency power panel-in North inner corridor ]
(this secures power to ELP #2 outside Alpha Lab.). ]
S. Secure ventilation supply fan SF-1, north RTAH, South RTAH, at MCC-3 ]
and check closed all fire doors.
Rev. 9/13/91 App'd M l
l
4 Page 2 of 2 ]
FEP-3(a) (cont'd)
- 9. Isolate Alpha Laboratory by closing supply damper (above vial cleaning hot ]
cell), and exhaust damper (overhead, after last exhaust filter bank),if possible. ]
1.0. The EhERGENCY DIRECTOR (or his delegate) should entact Fire Department outside of facility to provide specific information.
- 11. The EMERGENCY DIRECTOR wul stay in contact with INCIDENT COMMANDER to coordinate fire fighting and life saving efforts.
- 12. Contact MU News Bureau to handle release of public information.
Rev. 9/13/91 App'd 1AMTN
I MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revisica Number 9 Revision Date: January 23,1992 Section Page Number Number SEP-1 2 SEP 2 3 SEP-3 2 _
SEP-3 3 SEP-4 2 SEP4 3 SEP-7 1 SEP-7 2 SEP-8 1 SEP-9 1 EMERGENCY CALL LIST WORKSIiEET C FEP1 2 I FEP-1 3 FEP-1 4 -
FEP-2 2 FEP-2 3 FEP-3(a)
FEP-4 2 II-6
- _ .y .. . . _ _ . ._ _ __ _ .__ _._._ -. . . - . . . . . .
h SEP 1 (Cont'd)'- Page 2 of S
- 2.1The FEO'shall be activated by a paging system announcement, " ATTENTION,-
-THIS IS REACTOR CONTROL - ASSEMBLE THE FACILITY EMERGENCY
- ORGANIZATION."'
Repeat page -
- 3. - The FEO shall assemble outside the control room except when the facility evacuation / reactor isolation horns sound, then the FEO shall assemble in the facility front lobby.
'4 ' The responsibility for EMERGENCY DIRECTOR shall be assumed Assumed by -
5.' The EMERGENCY DIRECTOR shall assign an EMERGENCY COOP.DINATOR.
~
Assigned to
& -IF sufficient on site personnel are available, assign a COMMUNICATOR ,.
to call persons on the EMERGENCY CALL LIST. - Emergency notification rosters (EMERGENCY CALL LISTS) are posted at the Control Room console, the lobby receptionist desk, and at the lobby phone._ EMERGENCY CALL LISTS are also included in each Emergency Procedures Manual.
- Assigned to_-
- 7. Th'e Backup Emergency Command Centet (RPDB) may' be activated by talling 882 7221 during regular working hours. After'nours, contact the UMC Police (882-7201) to.open the RPDB. This will be used as the exit point - r]-
for all persons released frcm site, so they can be monitored for contamination before release as per Procedure HP-20. A roster of ali released persons will be maintained.
Rev.1/ 23/92 App'd IM
_ ,,-y, -r%- r y .- --. . --w. -
es. -
, r*yg-i ,
SEP-2 iCont'd)- Page3 of 5 TABLE II EMERGENCY SUPPORT ORGANIZATIONS a.- UMC HEALTH PI-iYSICS SFRVICES In tne event of a radiological emergency, the UMC Health Physics Services may be contacted to assist in checking facility personnel for contamination. After hours the UMC Police may be contacted to open ]
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 Jamison Shotts 882-7221 474-2194
~ David Spate 882-7221 657-9450
- b. UMC POLIC'E 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 facility, 882-7201 l
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C) Emergency Services 882-6003 Ambulance 882-6128 or 9-911 Walk-In (Emerg.C.) 882-8091 The UMH&C shoud be contacted in the event
- of personalinjury. In the event of personal contamination or radiation exposure without l injury, see MEDICAL EMERGENCY PROCEDURES.
If three or more personnel are involved, ask the Administrator-On-Duty to implement the Radiation Disaster Plan. Refer to the MEDICAL EMERGENCY j_ PROCEDURES for details,
- d. MU NEWS BUREAU See SEP-7, PUBLIC This office will initially deal wi6h 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 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 L in the event of fire or need of emergency rescue l - capability. Ensure Office of University Relations ]
is also called.
Rev.1/ 23/92 App'd MM l
l L
SEP-3 (Cont'd) Page 2 of 6
- 5. Send operator to west 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. After determining radionuclide responsible and verifying concentration; greater than 19,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RFl, SFl; (c) secure all individual vent fans.
- 8. The EMERGENCY COORDLNATOR shall evaluate the need for a partial or total evacuation of the facility.
NOTE: . For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation removed to RPDB.
(Ge-Li detector and dewer; High Resolution Gamma Ray ]
Spectrometer) ]
- 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 75 rem for -
- life saving, up to 25 rem to prevent exposures to members of general public in excess of I rem whole body and 5 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. 1/ 2 3/ 9 2 App'd lwr (A l
l
SEP 3 (Cont'd) Page 3 of 6 TABLE III EMERGENCY SUPPORT ORGANIZATIONS
- a. 11MC HEALTH PHrSICS SERVICES In the event of a radiological emergency, the UMC Health Physics Services may be contacted to assist in checking facility personnel for contamination. After hours the UMC Police may be contacted to open ]
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 445-527S Jamison Shous 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 facility. 882-7201
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C) Emergency Services 882-6003 Ambulance 882-6128 or 9-911 Walk-In (Emerg.C.) 882-8091 The UMH&C should be contacted in the event of personalinjury. In the event of personal 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 ~
Disaster Plan. Refer to the MEDICAL EMERGENCY PROCEDURES for details.
- d. MU NEWS BUREAU 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 reJease statements only by EMERGENCY DIRECTOR authorization.
- e. COLUMBIA FIRE DEPARTMENT 24 horrs 9-911 The Columbia Fire Department shall be notified in the event of fire or need of emergency rescue ,
capability. Ensure Office of University Relations )
is also called.
Rev. 1/23/92 App'd D#h
e . - .- . - . ._ .. . . -
J SEP-4 (Cont'd) - Page 2 of 6 '
g 15.' Send operator to west tower with radiation monitor to:
- NOTE: Communicat'e by intercom, since the stack monitor is affected by portable radio RF.
a; ; Verify radiation background at stack momtor.
-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. Full stack monitor filters and analyze.
- 7. After determir.ing radionuclide responsible and verifying concentrations greater than 95,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RF1,'SFl; (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 or northeast quadrant evacuation, i have sample counting instrumentation removed to RPDB. ,
- . (Ge-Li detector and dewer; High Resolution Gamma Ray - ]
Spectrometer)_ ]
, 9. The EMERGENCY COORDINATOR shall appoint and have a surveillance team L , check areas evacuated clear of personnel within 30 minutes.
L l NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation-
L to 25 rem to prevent exposure to members of general public in excess of I
1 rem:whole body and 5 rem thyroid._)
- 10. I' mine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if
.sd, activate them or place them on standby. See TABLE IV, EMERGENCY
.- ew' PORT ORGANIZATIONS.
Rev.1/23/92 App'd jM l
SEP 4 (Cont'd) Page 3 of 6 TABLE IV EMERGENCY SUPPORT ORG ANIZATIONS
- a. UMC HEALTH PHYSICS SERVICES 3 In the event of a radiological emergency, the UMC Health Physics Services may be contacted to assist in checking facility personnel for contan.ination. After hours the UMC Police may be contacted to open ]
the Research Park Development Building (backup emergency control center).
One of the persons listed below will man the backup control center.
g CONTACT Office , Home Dr. Philip Lee 882-7221 445-5275 Jamison Shotts 882-7221 474-2194 Deid 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 facility. 882-7201
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C) Emergency Services 882-6003 Ambulance 882-6128 or 9-911 Walk-In (Emerg.C.) 882-8091 The UMH&C should be contacted in the event of personalinjury, in the event of personal 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 Disaster Plan. Refer to the MEDICAL EMERGENCY PROCEDURES for details.
- d. MU NEWS BUREA_Il See SEP-7, FUBLIC 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 Col .mbia Fire Department shall be notified in the event of fire or need of emergency rescue capability. Ensure Office of University Relations ]
is also called.
Rev.1/23/92 App'd MA
Page1 of 4 SEP-7 PUBLIC INFORMATION PROCEDURE NOTE: The MU News Bureau shall be activated to handle the release of public information as required in the ALERT or SITE AREA EMERGENCY procedures; whenever offsite em<: gency assistance is requested via 911; or whenever deemed appropriate by the EMERGENCY DIRECTOR.
A. INITIAL RELEASE OF PUBLIC INFORMATION
- 1. Tne Emergency Status Report shall be completed and approved by the EMERGENCY DIFECTOR.
2a. During normal University office hours, activate the MU News Bureau by p calling 882-6211,882-6214 (Mary Still) or d82-6217 (Jim Muench). ]
2b. . At other times, call the following list of MU News Bureau staff in order until one of the individuals listed is reached (NOT their spouse, children, etc.).
- 1) Mary Still 875-4730 1
- 2) . Ken Brogdon 442-5260 1
- 3) Jim Muench 443 0879 ]
- 3. Read the Emergency Status Report as approwd by the EMERGENCY DIRECTCR to the MU News Bureau staff member and answer any questions concerning definitions, terms, units. etc.
- 4. Record other questions that the MU News Bureau staff member may have.
_ Enter the name of the MU ' Taws Bureau staff member contacted a'nd give the completed report to the EMERGENCY COORDINATOR to be kept with the records of the EhE RCENCY.
l C
~ Rev.1/ 23/ 9 2 App'd \@\
-w- -
g e , -w w
l SEP-7 (Cont'd) . Page 2 of 4 l
- 15. The hRJ News Bureau staff member contacted should verify a call concerning '
an emergency at the University of Missouri Research Reactor by calling- ;
882-4211 or 874-4119,and asking to speak to a member of the Facility
.~ }
Emergency Organintion-(FEO). If the person answering the phone does
-1 not know who is hi the FEO, then ask for anyone from the Director's Office, Operations, Health Physics / Reactor Chemistry groups. The }
individuals in these groups are listed below in alphabetical order.
L After verifying the person's identity by asking for his social security
. number, the emergency call can be verified.
VERIFICATION LIST FOR KRIRR EMERGEI4CIES Name Soc. Sec. No. _ Name- - Soc. Sec. Noa Chuck Anderson Sue Langhorst
. Joe Baskett . Charlie McKibben Rita Bonney- Walt Meyer .
S Kenneth Beamer - Steve Morris s Barry Bezenek Paul Muren Chester Edwards Phil Nael John Ernst . Willy Oldham ] t Christine Errante Leslie Powell Mac Evans Mike Randolph Les Foyto Bill Reilly
- John Fruits . Tony Schoone Greg Gunn Jim Schuh ,
Roberc Hudson Tom Feeger Rolly Hultsch. Vickie spate Brenda Johnson Ray Stevens ,
Vernon Jones Nolan Tritschler Mike Kilfoil- ~ Robert Walker
. Ron Kitch -Mike Wallis
- Tim Warner
- 6. MU News Bureau personnel contacted will determine the need for staffing end equipping an emergency information center and will callin the required _
staff and arrange for necessary facilities.
7.' MU_ News Bureau personnel will inform news media and.others of the public, '
- as necessary, of the emergency.
'8.' If possible, a MU News Bureau staff member will be sent on site to assist the EMERGENCY DIRECTOR with the release of information. ,
~ Rev.1/ 23/9 2_ App'd Wh
> ~ _ . ., , _
t Page l of 3 SEP-S i'
EMERGENCY EOUIPMENT MAINTENANCE PROCEDURE
~y LERM j'6 This procedure states how the operational readiness of emergency equipment and '
suppiks required by the Emergency Procedures is to be maintained, calibrated, o : tested, and periodically inventoried, 1* lliutt) Physics' Emergency Falu_lpment:
4 y[ :3Heahh Proudufes shall Physics' Emergency be maintained Equipment in Mvo designated and supplies readily accessible locations.required The two by the S locations'are the'MURR Emergency Equipment Cabinets in the copy machine room .
and th'e 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 L quartuly that the contents of the cabinet meet at least the required levels. All W , maktenance and inventory records on emergency equipment shall be maintained in
+ Lthe Hedth Physics Office.
!# ?The avil defense kits stored at each locatien contain a G-M survey meter, an ion .
3 Tchamber meter (500 R/hr rangd, and a set of self-reading pocket dosimeters.
' TThese kits are exchanged routinely by Missouri SEMA for updated kits of instruments >
Jwhich have beer. calibrated by SEMA. The self-cornained breathing apparatus sets are
- 'lasputed annually by the Columbia Fire Department. The emergency Health Physics' L
, iequipmsnt is supplemented by the Health Physics' inst uments and equipment used
% for daily routine evaluations and is maintained and calibrated by the Operational iHealth Physics' Program, c
~ Off-Gas M.g.citming EoulpmeJ1t1 3The offgas stack monitor has three channels: gas, particulate, and iodine. The three ichantiels shall be calibrated semiannually by the Health Physics / Reactor Chemistry .)
[ group using Reactor Chemistry Standard Operating Pro edures:
- RC/fli 2 Calibration of Stack Particulate Monitor iRC/III;3 Calibration of Stack Iodine Monitor RC/III4 Calibration of stack Gas Monitor f r
iThe operability of the off-gas monitor la checked as part of the start-up check-
- ; list for normal reactor start-ups.
(Fitelghting Eauipment:
L ' CThe fire hydrant ir. the reactor site is checked operable rot.tinely by the Columbia Fire i;- Department._ The fire extinguishers shall be checked annually by the University of Missouri _ Physical Plant, i
. .Rev.1/ 2 3 / 9 2 App'd rom s ,
,, ,. . y v < . - -
Page1 of 2
! EE,P. -9
.s TRAINING PROCEDURE FOP EMERGENCY PREPAREDNESS
- 1. TRAINING OF EMERGENCY ORGANI7.ATIONS I
l A. FACILITY EMERGENCY ORGA1El.ATION (FEO) TRAINING t
This organization consists of MURR staff in the Director's Office, Operations, and )
Health Physics / Reactor Chemistry groups. Th s organization will resporid to }
both GENERAL FACILITY EMERGENCIES (FACRITY EVACUATION, REACTOR ISOLATION, FIRE, MEDICAL AND SECURITY EMERGENCIES) and EMERGENCIES WITH POSSIBLE CFFSITE CONSEQUENCES (UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, PARTIAL SITE AREA EVACUATION).
- 1. The members of the FEO will train initially and annually thereafter, '
by emergency plan and procedure review of each member's role in emergency preparednes3. This training will be documented by each member signing the EMERGENCY PLAN /PROCED~JRES REVIEW DOCUMENTATION LIST. ,
- 2. Annual onsite emergency drills shall be conducted as action drills to test the trair.ing of FEO members to carry out their roles under ,
simulated emergency conditions.
B. TRAINI: G OF FACILITY STAFF OTHER THAN FEO MEMBERS
- 1. The members of MURR staff not assigned to the FEO shall initially and annually thereafter 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. Aimual onsite emergency drills will test these members' ability to properly respond to simulated emergency cariditions.
C. TRAINING OF EMERGENCY SUPPORT ORGANIZATIONS
- 1. The members of EMERGENCY SUI". ORT ORGANIZATIONS shall be trained initially and biennially thereafter on their role in maintaining Emergency Preparedness. This will be performed by diMussions between MURR staff anc! the members of each SUPPORT ORG ANIZATION, stressing familiarization with the facility or changes to the emergency plan or procedures. This training will be scheduled prior to each biennial drill and willinclude drill planning and scenario development.
- 2. biennial emergency drills shall be conducted to test, as a minimum, the communier. tion link and notification procedures with these EMERGENCY SUPPORT ORGANIZATIONS. ,
Rev.1/ 2 3/ 9 2 App'd \tM@ ,
EMERGEtJCY PROCEDURE EMERGEtJCY CALL LIST Health Physics /RL Chemierv ] ; acilities Ooerations ] 6emency Support Organizatiens Phone No. Phors No. Phone No.
S. Larv; horst 442-3534 ( . Edwards 443-7529 UMC Police ,882-7201 R. Stevens 442-2539 M. Evans 698-2450 445-5621 '< Beamer 682-5499 Co!umbia Fire Deoartment 9-911 J. Ernst
'.Schuh 445-4985 R. Kitch 474-6117 ] ;
C. Krib*os 499-0221 ] UM Hosoitat and Clinics Emergency Services 887-6003 l T. Seeger 474-3691 Ambutance 882-6128 or 9-911 Di ector's Office J. Baskett 474-2046 Waik-in (Emergency Center) 882-8091 Phono No.
J. C. McKiboon 442-C .'28 UMC Health Physics (Office) E82-7221 Dr. Phil Lee Olcmc) 445-5275 Reactor Ooorations Staff Resourco Personnel ] Jamieson Shotts (Home) 474-2194
, ]
I Phono No. Phone No. David Spate (Home) 657-9450 W Moyer 442-7675 S Morris 445-4217 1.3chcono 44'3-8862 V. Spsto 657-9450 fAU News Bureau 882-6211 R. Hu!tsch 442 6653 C. Baskett 474-2046 ] See Public Information 882-6214 C. Anderson 696-:.506 M. Glascock 443-4172 ] Procedure for other or B.Bozonek 445-5630 B. McCracken 449-7731 ] phono numbers. (SEP-7) e 8 2 -6217 ]
G Gum 875-1162 W. O!adiran 443-5G58 ]
State Emeroency Manaaement N. Tritschlor 474-9388 D. Nickclaus 443-0502 ]
446-0491 G. Ehrhardt 445-3570 ] Agency (SEMA) 314-751-2748 L Foyto J. Fruits 474-0774 A. Kotring 657-9614 ]
D. Poo!or 816-848-2471] NRC Washinaton. DC 301-951-0550 Ft Hudson 445-6769 ]
V. Jones 445-2543 B. Yelon 445-8147 ]
449-2524 S.Gunn 443-2125] TJHC Reaion !!! 708-790-:>500 M. Kilfoil P. Muren 474-0d79 P. Miller 449-7237 ]
442-8693 L Krueger 442-0740 ] American Nuclear iniplma 203-677-7305 P. Neel W. Oldham 474-0987 ] T. Storvick 445-4038 ]
M. Randolph 474-0500 R. Walker 443-0970 i
M. Wallis 696-1097 l T. Warner 816-882-6740 Rev- ]/ 2 3 / 9 2 ^'P'd W I\
,c . ,
vs i 4
WORKSHEll C CONTENTS OF INITI AL/ FOLLOWUP EMERGENCY MESSAGES TO THE NRC REGION 111 s 703-790-5500 i
NORMAL WORKING HOURS: AFTER HOURS / WEEKENDS;
" REGIONAL D1'TV OFFICER'- 'HE ADQUARTERS OPERATIONS OFFICER" REGION lll 703-790 5500 WASHINGTON, D.C. 30' )51-0550
- 1. Provide Name, tit'e, telephone number of caller.
- 2. Location of eme.gency event.
UNIVERSITY OF MISSOURI RESEARCH REACTOR AT COLUMBIA, MISSOURI
- 3. Description of emergency event and emergency class:
NOTIFICATION OF UNUSUAL EVENT, ALERT, or SITE AREA EMERGENCY Time of event classification ]
The cause or initiating event, if known.
- 4. Date and time event started: 5
- 5. Status d reactor: e.g. shutdown, fuel damage.
- 6. Was there actual releese of radioactive material? (estimate quantity)
Has the release been terminated?
?
- 7. What protective actions taken? e.g. evacuation of facility, site area evacuation S. What outside assistance is required? e.g. SEMA, Fire Department, Medical Facilities
- 9. Are there any injuries? Are the injured contaminated?
- 10. Esumate impact of release? c.g.,is general public expected to be affected?
EMERGENCY DIRECIOR-ALTTHORIZATION TO CALI Rev.1/ 2 3 / 9 2 App'd bM
EEEd (Cont'd) Page 2 of 7
[
?. PERSONNEL WITH PR'dASSIGNED TASKS (Facility Emergency Organization Members)
A IMMEDI ATE AC"IION_S The responsibility for the overall directicn in the event of an emergency shall rest with the EMERGENCY DIRECTOR.
In the event of a Facility evacuation during normal working hours, the following people shall report to the reactor lobby: the Facility Director, Associate Director, Reactor Manager, Manager of Reactor Health Physics / )
Reactor Chemistry, Machine and Electronics Shop Supervisors, and Duty ]
Shift Servisor.
The respobsibility for EMERGENCY DIRECTOR shall be assumed. The ?
EMERGENCY DIFECTOR snall 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 incident, and shall direct those activities necessary to correct the emergency situation. After the emergency is terminated, he shall direct the procedures necessary to restore normal operation.
The EMERGENCY COORDINATOR shall ascertain all that the reactor containment building, the Facility laboratories, and the mechanical equipment room, and below grade areas, have been vacated and secured.
He will have the laboratory ventilation fans secured. He shall maintain a roster of all persons released from the site by the EMERGENCY DIRECTOR. If the pnemnatic blower system was in use during the _
emergency, he shall insure that the samples bung irradiated are returned to the laboratory and then have the blowers secured at the locallightirg panel (#32). He shall ensure a record of the events following the ]
emergency is maintained.
The DUTY 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.
S. Verify that all shim rods have bottonied as indicated by the console lights.
C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lights.
Rev.1/ 2 3/9 2 App'd _lM
_.__._.___-__.____m__._____m_ _ _ . _ _ _ _ . _ _ _ . _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ , _ _ _ _ __
l l
L EEP-1 (Cont'd) Page 3 of 7 D. Ensure all personnel are cleared from all levels of the containment building and exit via personnel airlock doors.
He shall report to the EMERGENCY COORDINATOR and advise him of the status of the reactor.
MANAGER OF HEALTH PHYSICS / REACTOR CHEMISTRY shall proceed ]
to the lobby control center and establish the radiation safe condition of the area.
Immediate actions may require the Manager of H.P./R.C. to: )
- 1) establish a hc,t-cold change area; 1
- 2) assemble and prepare f or use, special Health Physics equipment; ]
- 3) perform radiation and contamination surveys; )
- 4) evaluate the extent of radioactive cantamination and/or radiation i exposure received by personnel at the time of the incident; and/or ]
- 5) advise the EMERGENCY DIRECTOR of measures to be taken to ]
control radioactive contamination which may have resulted from ]
the incident. }
The EMERGENCY DIRECTCR 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 Office, UMC 882-7201 Radiation Safety Office, UMC 882-7221 Dr. Philip Lee,2 Research Park Dev. Bldg.
Emergency Room, UM Hospital & Clinics, UMC 882-8091 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 nortis inner corridor next to the emergency power transfer switch.
Rev.1/ 23/92 App'd M
c FEP-1 (Cont'd) . Page 4 of 7 II. -PERSONNEL WITHOUT PRE ASSIGhTED TASKS:
(Staff other than Facility Emergency Organization members)
A.lMMEDIATE ACTIONS:
1.. Upon hearing the evacuation alarm, personnel shall proceed to points beyond the area bounded by the outer perimeter of the reactor labora-tory building.
- 2. TOUR GUIDES shall be responsible for the safe evacuation of visitors in 'their charge from the Facility in accordance with the evacuation routes in this plan. VISITORS shall be monitored by Health Physics Technicians as per HP-20 before being released to leave the site.
- 3. EXPERIMENTERS who are conducting experiments in the containment area shall render their experimental apparatus safe for unattended operation. 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 5): ]
g A. All personnel ivithin the containment building will exit the-containment buildhlg and proceed through the east door of the laboratory building and then go to the upwind parking lot.
~ B. All laboratory personnel, support personnel, and guests exterior
- to the containment building will leaw: the facility through the nearest exit (north, east, or south doors) and then proceed to the upwind parking lot.
! 5. -'Once outside, personnel shall note the wind direction indicator at the top of the containment building east tower and proceed to the-upwind parking lot.
B.f SUBSEOUENT - ACTIONS:
- 1. All staff personnel shall remain on standby, unless released by the EMERGENCY DIRECTOR, to provide special services that may be required to restore normal operation.
.2.- All staff p.ctsonnel shall be monitored by Health Physics Technicians as per procedure HP-20 before being released to leave the site.
- 3. A roster of all released personnel will be maintained by the l EMERGENCY. COORDINATOR.
Rev,1/ 2 3/ 9 2 App'd VR.
a
i FTP-2 (Cont'd) Page 2 of 4
\
I. PERSONNEI, WITH PRE-ASSIGNED TASKS:
(Facility Emergency Organization members)
The following shall report to the lobby control center during ncrmal working hours: Reactor Manager, Reactor Operations Engineer, Shift Supervisor, Duty Operator. Plant Engineer, Manager of Health Physics, Machine and Electronict ]
Shop Supervisors.
The responsibilities of 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 EMERGENCY COORDINATOR.
If in the opinion of the EMERGENCY DIRECTOR the extent of the emergency is suft'icient to wstrant evacuation of the facility, he shall actuate the alarm and the facility evacuation plan shall be executed. After the emergency is terminated, he shall direct the procedures necessary to restore normal operation.
The EMERGENCY COORDINATOR shall establish that containment is vacated and secured. He shall maintain a roster of all persons released from the site 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 (#32). He shall assist the EMERGENCY DIRECTOR as required and insure a record of the events following the emergency is maintained.
The DUT / 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.
B. 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 from til levels of the containment building and exit via personnel airlock door.
Rev.1/ 23/92 App'd \pch l
F_El-2 (Cont'd) Page 3 d i 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 HEAPH PHYSICS / REACTOR CHEMISTRY shall ]
_ proceed to the lobby control tenter.
Immediate actions may require the Manager of H.PJR.C. to: }
- 1) establish a hot-cold change area; ]
- 2) assemble and prepire for use, special Health Physics equipment; )
- 3) perform radiation and contamination surveys; }
- 4) evaloate the extent of radioactive contamination and/or radiation ]
exposure received by personnel at the time of the incident; and/or ]
5)_ advise the EMERGENCY DIRECTOR of measures to be taken to -]
control radioactive contamination which may have resulted from ]
the incident. ]
- A COMMUNICATOR appointed by the EMERGENCY DIRCCTOR shall 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. A reactor isolation has occurred. All non-involved personnel shall keep _ clear of the main corridor and the lobby."
The COMMUNICATOR 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 re-entry into the containment building has been made and proper radiation surveys are con-ducted, the isolation horns may be silenced by means of a switch on the back of the control console in the Control Room.
Rev.1/ 23/ 92 App'd h
_ -_ _._ __ __ ~ .-. _ __ _ _ _ . _ . _ _ - . _ . . _ . . _ _ _ . . _ . _ _
d Page 1 of 2 FEP-3(a) v CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE NOTE: -Throughout this procedure continue to monitor stack exhaust monitor,
- Alpha Laboratory exhaust monitor (ALPHA-6) or Alpha Laboratory room monitor (ALPHA-3) for indication of airborne radioactivity, as appropriate. '
- 1. If a fire is detected by fire alarm or reported in the Alpha Laboratery, the shift supervisor _(or senior licensed person in control) will call the Columbia Fire Department. .
- 2. We shift supervisor will activate the Facility Emergency Organization by page system and provide warning to stay clear of facility basement.
- 3. The Emergency Director will determine nature and specific location of fire (i.e.,if fire is in glove box or equipment exterior to glove box).
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will shut down to focus attention on the fire.
- 5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.
- If no experimenter is present, call the on-call experimenter as soon as time permits.
- 6. . Secure EF-13 and EF-14 at breaker on emergency distribution center (in North inner corridor) ONLY IF there is likelihood of fire spreading through ventilation system.
- 7. Secure electrical power to Alpha Laboratory at following locations:
- a. Breaker #13 on UPS #2i-in control room (this secures power to the
. Argon glove box.)
bi Breaker #17 on 120/208 V. distribution center - in North inner corridor
.(this secures power to LP-34 which will secure lights and receptacles). ] *
~
- c. - Breaker #2:on emergency power panel -in North inner corridor
- (this secures power to ELP #2 outside Alpha Lab,, which will secure ']
Alpha Lab, supply and exhaust fans). ]
- 8. Secure ventilation supply fan SF-1, north RTAH, South RTAH, at MCC-3 and check closed all fire doors.
~
a Rev.f1/23/92 App'd M 4
- _ _ , , _ , . ~ , _ _ . . - . _
y 4
EEE-4. _ (Cont'd)? Page 2 of 5 i
- See UMH&C RADIATION DISASTER PLAN (5 or more patients) to determine the 3 .. .
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 accident has occurred, the following action is to be taken: i
- 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 at which the exposure dose rate is 5 mR/hr or less if the victim can be g moved without harm. Evacuate all personnel from the accident area and provide first aid to the victim.
B. Notify the Reactor Operator in the Control Room (2 5213). ')
f C. Control Room Operator will call Health Physics Manager at (2-5227) or ]
-by page. If the Health Physics Manager cannot be reached, call the UMC 1
-Health Physics at 882-7221.
L
\:
ACCIDENT INVOLVING PHYSICAL INJURY '
<Upon arrival at the accident scene, Health Physics will take the following action:
A. Assess the severity of the radiation injury and classify the injury.
B. -If necessary, close off and seal the accident area and turn off the ventilation to that area.
L- C. Notify the Emergency Room, UMH&C at 882-8091, and arrange for
- medical' care either at the Facility or at .UMH&C.
p
} D.- 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 ambulance' service.
Rev.1/23/92 App'd- I)#nn L
r.
- -,-. __ s - , , 4 , - , . -_c,
HEALTH PHYSICS STANDARD OPERATING PROCEDURES (New manual issued 10/29/90)
Section Page No. Revision No. Revision Date HP-31 1,2,3,4 1 12'05/91 m
II-7
---suum ll (Revised in its entirety) i SOP MP-31 Rev. 1 Page 1 Appr' d k 1M Date C\
December-L 1991 Personnel Indoctrination at MURR
- 1. Policv All personnel with unescorted access to 1GRR shall have completed the indoctrination program to provide them with basic information concerning their responsibility with regard to the security, health physics, and emergency programs at MURR commensurate tc their level of access.
II. PLpNg Th( ou nose of this procedure is to define the indoctrination progic and the associated recordkeeping.
III. Definitions, A. Sponsor Guidelines:
- 1. Students - MURR supervisor
-2. MURR personnel - Im:nediate supervisor
- 3. Campus Facilities /Other contractors - Manager or Engineer, Facilities Operations
- 4. Collaborators - MURR liaison B. Levels of Security Access and Approval Signatures:
Level of Indoctrination Final Security Completed Approval Accessi Signature Lab / Limited HP HP Manager Lab HP HP Manager Containment w/o combination HP Reactor Manager Containment w/ combination HP Reactor Manager 2 Receptionist 3 Reindoctrination for any access or HP 1 Health Physics training levels include Non-Containment Limited, Non-Containment, Containment, and Beamport Area Access (see HP-35) 2 Normally upgraded following a period of time at Access Level ' Containment w/o ecmbination" 3 Same as final approval for access level being renewed
l SOP MP-31 Rev. 1 Pagc. 2, App r ' d I M . ~~ s 2 C\
Date December 55 1991 III. Definitionn (continuedi C. Temporary worker - individual not issued ID Badge with picture (see HP-24) due to work assignments being temporary at MURR.
Permanent worker - ' n dividu a.1 issued ID Badge with picture (see HP-34). -
IV. Procedure for Indoctrinatien A. Sponsors can consult the Health Physics' bulletin board to sign up individuals for scheduled indoctrination times. Request for indoctrination must include individual's name, sponsor and level of access requested.
D. A member of the Health Physics staff will present the current indoctrination program.
m C. The following pictures will be obtained:
- 1. Temporary workers:
- a. Containment - one picture required f or cont rol room photo file
- b. Laboratory - none required
- 2. Permanent workers:
- s. Containment - two pictures (one required for control room photo file and one required for I.D. Badge)
- b. Laboratory - two pictures (one required for I.D. Badge and one requested for receptionist photo file)
D. After indoctrination is complete, appropriate signatures will be secured on the indoctrination form and the person's access will be added to the appropriate access list.
E. The Rear 7r Manager will add the names of the new containment indoctrinees to the containment list maintained by the control room.
F. The receptionist will complete the section on the indoctrination form concerniag: where the indoctrination form is on file, if a picture was taken and when the ID badge was issued.
Rev. 1 Page 3 Appr'd [ k . b A .
Date December 3 1991 IV; Procedure for Indoct r i n a t ion (centinued)
G. The receptionist will add names of all new indoctrinees to.the appropriate access list maintained by the receptionist. These access lists will be updated monthly or more often as necessary and copies distributed to:
- 1. Health Physics, Manager (3 copies)
- 2. Reactor Control Room (1 copy)
H. The receptionist will keep the file of the active -
indoctrination forms.
V. Procedura for Ra-Tndoctrination At :the beginning _ of each month the receptionist will generate a list of all persons on current access lists for whom it has been one. year since their indoctrination or reindoctrination.
A. The receptionist will contact sponsors to determine need for.reindoctrination and any change in security access level (See Item VI for procedure for termination of access)..
B. All-persons needing reindoctrination will complete an R
. annual reindoctrination with the HPs or be sent:
- 1. Cover letter from Reactor Manager
- 2. Indoctxination form
-3. MURR indoctrination packet C. When_the completed reindoctrination packet is returned to the receptionist, the required signatures will.be secured.
D. The receptior.ist will file the new indoctrination form and update the appropriate access list. The old indoctrination forms will be marked with the reindoctrination date and returned to Health Physics.
E.- .Reindoctrination must-be completed and approved by an HP if:
- 1. Access is' changed from Lab / Limited to Lab or to Containment.
- 2. Access is changed from Lab to Containment
SCP MP-91 Rev. 1 Page 4 Appr'd_ > N ->
+I .es/ [
< s Date r enerher 5."1991
- v. Eyc;; min nt fo r .E,e _ln *
- d e *+ d r n < c en*.J,nnn:1L
- 3. Reindoctrination is not ccmpleted before 14 menths fellowing individual's last indoctrinatien er reindc:trination F. The Mealth Physics secretary will enter the reindoctrinatico inform 0 tion on the appropriate trainin, fcxms. The updated indoctrination forms will be f i .' e d .
in the active personnel files.
"i. Ihrn:,nmilen r f.101t1.2 A. Personn not requiring centinued F ess to MURR will not be rcindoctrinated after one u, Access may be terminatec or limited at any time at the request of the Sponoor, Heslth Physics Manager or Reactor Manager.
Accecs shall be terminated after 14 months folicwing the date oi' the individual's last indoctrination or reindoctrinatica.
E. The recept $onist wi l 2. , with the help of the person's sponsor, attep.pt to retrieve outstanding ID badges.
"Ihouc badges not retrieved will be added to the list, maintained by the receptienist, of badges
" Lost / Stolen /Not Returned". This 1.ist will be distributed on a men dly basia to:
- 1. Reatter Manager
~
2, Health Physics Manager
- 3. Reactor Physicist C. The reception;st will mark the terminateu ,
indoctrination er reindoctrination form " inactive",
date e and 'ter. urn it to Health Physics along with individual's permanent ID badge. Healt' Physics will retrieve individual's photo from the Centrol Rcom photo file and place the form a:id photos in the individual's inactive personnel flie,
SECTIOU. ill REVISIONS TO THE hZARDS
SUMMARY
llEPORT 1 July 1991 through 30 June 1992 HAZARDS
SUMMARY
REPOllT (Original July 1,1965) i l-- 1. IISR, ADDENDUM 5, SF.CTION .L? (page 21)
Ddete from the last narneraph. third sentence: "and as . backup to the air operating air for all of the air-operated valves."
The third sentence should now rend: "The nitrogen pressure from the bottles is reduced to a pressure of 140 psig and is thea piped to the equipment room where .',is used for the pressurizer."
. 111-1
SECTION IV PLANT AND SYSTEM MODIFICATIONS 1 July 1991 through 30 June 1992 Modification 911: Digital ILqd_Dmp Timers This modification replaced mechanical clutch timers, which were 1960 vintage, with digital timers. The timers are started by pressing the manual scrum button and stopped when the rod anvil passes through a fiber optic light. The fiber optic light and switch is located at the 20% withdrawn p%ition. This modification has increased the reliability of the rod 'zop timer circuit.
Tne safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10 CFR 50.59.
Modification 913: Temporn-v Additional In Pool Fuel Storage Baskets 1 This modification increased MURR's in pool fuel storage capability.
Temporary storage was nceded for MURR fuel while waiting on the availability of the DOE spent fuel shipping cask. The temporary storage baskets are capabic cf storing an additional 32 fuel elements. Fuel basket holders were built and installed on existing in pool storage baskets.
The safety evaluation for this modification documents that it does not present an unreviewed safety quetta as per 10 CFR 50.59. These evaluations included criticality analysis of the new, plus existing storage positions and analysis of the direct radiation effect on the biological shielding.
Mmllfication 921: Valve Operation Air,Comoressor This modification increases the reliability of the air supply to the reactor valve operation header. A 25 to 30 CFM air compressor was installed to provide dedicated compressed air to the valve operation header. The facility's main air compressor, which is original equipment, is valved in to supply back up compressed siir for the valve operation system. The nitrogen banx system has been removed as a back up to the valve operation system and is now dedicated to providing a compressed nitrogen source for the pressurizer. This enhanced the reliability of the nitrogen supply to the pressurizer.
The safety evaluation for this modification documents (l'at it doc. >t present an unreviewed safety question as per 10 CFR 50.50.
IV 1
___A__._ _ . _ _ _ _ . . . _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ - ~ _ _ _ _ _ _--_--__-___----__---__.----.__-_.--__m_____
l l
l SECTION Y I
NEW TESTS AND EXPEltlMENTS 1 July 1991 through 30 June 1992 New experimental progr:enu du-wg this period are as follows:
11U11219, Request 11GA:
Experimenter: S.Gunn
Description:
This RUit authorized irradiation of a Thulium Oxide source for a portable blood irradiator.
RUll 219, Request 123:
Erperimenter: K. Zinn
Description:
This RUlt authorized the development and use of a boron thermal shielded can to irradiate samples in the flux trap.
RUR 219, Request 121:
Experimenter: S.Gunn
Description:
This itUR authorized the irradiation of aluminum clad Li Al pic:es as requested by Argonne National Laboratories.
Each of these experirr<ents has a written safety evaluation on file which provides the basis for the determination that it does not involve an unreviewed safety question as per 10 CFR 50.59.
V-1
SECTION VI SPECIAL NUCLEAlt MATERIAL ACTIVITIES 1 July 1991 through 30 June 1992
- 1. SNM Receipts: A total of 22 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia, Grama Oratna Jft,m D rue U U M5 l 11 & W MO 339, MO-340, MO 341, MO 342, MO 343, MO-344, 18,255 17,008 MO 345, MO 340, MO 347, MO-348, MO 349, MO 350 MO 351, MO-352, MO-353, MO-354, MO 355, MO-356, MO 357,MO 358,MO 359,MO 300.
! Facilities at Savannah River Plant, Aiken, South Carolina, Grams Grains
_Fhim r , Dsme U U 35 MURR MO-232, MO 231, MO 239, MO 240, MO-241, MO 246, e,587 42Aal MO 247,MO 248, MO 249, MO 254, MO 255, MO 256, MO 257, MO 258, MO 259, MO 200, MO 261, MO-202, MO-203, MO 264, MO 265, MO 266, MO-267, MO 268, MO 269, MO-270, MO 271, MO-272, MO 273, MO 274, MO 275, MO 270, MO 277, MO 278, MO 279, MO 280, MO-291, MO 282, MO 283, MO 284, MO 285, MO.286, MO 287, MO 288, MO 289, MO 290, MO 291, MO-292, MO 293,MO-294,MO 295,MO 296,MO 297,MO 298, MO 299, MO-300, MO 301, MO 302, MO 303, MO 304, MO 305, MO-306, MO-307, MO 308, MO 309, MO-310, MO-311, MO-312, MO 313, MO-314, MO 315, MO 317.
- 3. Inspections: There were no Physical Security and Special Nuclear Material accountability inspections conducted by the Nuclear Regulatory Commission in the period 1 July 1991 to 30 June 1992. The NRC performed a routine, announced inspection of an irradiated reactor fuel shipment at the point of origin March 24,1992, with followup questions by telephone on March 31,1992.
The MURR Special Nuclear Material Control Procedures were reviewed in June 1992 by the Procedures Review Subcommittee (of the Reactor Advisory Committee) as per the annual requirement,
- 4. SNM Inventory: As of 30 June 1992, MURR was financially responsible for the following DOE owned amounts:
Totai U = 32,357 grams Total U 235 = 29,070 grams Vl 1
included in these totals are 30 grams of U and 34 grams of U 235 in DOE-owned non fuel. In addition to these totals, MUltll owns 177 grams of U and 90 grams of U 235. All of this materialis physically located at the MUltII.
The fuel elements on hand have accumulated the following burn ups as of 30 June 1992.
Burned-un Elemulls EluntnLNn. MED Element No. M Wil Elcut/11 h1W D MO-316 144.20 MO 321 147.08 MO-329 144.11 MO 318 144 20 MO325 149.98 MO 330 145.11 MO 319 146.54 M O.320 147.03 MO-332 149.92 MO 320 146.51 MO 327 144.11 MO-334 149.02 MO-323 149.99 MO 328 145.11 Elements inlen'itt MO-321 12.19 M 0 411 99.34 MO-351 37.75 MO422 12.19 MO-M2 84.56 MO-352 34.77 MO331 141.36 M0443 72.30 MO453 37.75 MO-333 141.36 NOJ44 85.06 MO-351 34.77 M0035 142.23 M 0 415 72.30 MO 355 15.20 M O-336 116 21 MO-346 85.06 MO-356 15.20 MO-337 142.23 MO-347 39.05 MO 357 9.22 MO-338 116.21 M0 4tB 48.83 MO-358 9.22 M0439 99.34 MO-319 39.05 N O.359 8.96 MO-340 84.56 MO-350 48.83 M O-300 8.96 Average Burn-up (all elements): 89.73 MWD VI-2
1 l SECTION VII ltEACTOlt I'llYSICS ACTIVITIES 1 July 1991 through 30 June 1992
- 1. Fuel Utilization: During the period 1 July 1991 through 30 June 1992, the following elements reached licensed or feasible burn up and were retired:
Serial Numbn EianLCarr Date Ln=t Used hili'D MO-315 91-13 (f> 23-91 149.89 MO 310 91 48 10 28-91 144.20 MO-317 91-43 09-23-91 149.89 MO-318 91-2 10-28 91 144.20 MO 319 91 50 11 11 91 146.54 MO 320 91-50 11 11 91 146.54 MO 323 91-57 12 30-91 149.98 M O-324 92-01 01 06 92 147.08 MO 325 91-57 12 30-91 149.98 MO 326 92 01 01-06-92 147.08 MO 327 92 29 06 23 92 144.11 MO-328 92 27 0429-92 145.11 MO-329 92 29 00 23 92 144.11 MO 330 92 27 OG-29 92 145.11 MO 332 92 21 05 03 92 149.92 MO-334 92-21 05-03 92 149.92 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate A core designation consists of eight fuel elements of which only the initial critical fuel element serial numbers are listed in the following table of elements in service 30 June 1992. To increase operating efliciency, fuel elements are used in mixed core loadings Therefore, a fuel element fabrication core number is different frem its core load number, l'al rication Initial Core initial Serial Number fore Number kad Number Oncrnting Date MO-321 T4 92 26 OG'01/92 MO-322 76 92 26 OG'01/92 MO 331 57 91-17 04/15/91 MO 333 57 91 17 04/15.91 MO-335 ra 9125 06'10/91 MO 336 to 91 27 06/24/91 MO-337 ra 91 25 Om10/91 MO 338 re 91 27 06'24/91 MO 339 rd 91-40 09/09/91 MO-340 rd 91-40 09/09/91 MO 341 rd 91 40 09/09/91 MO-342 58 91 40 09/09/91 MO 343 59 91-46 10/07/91 Vll 1
Fabrication Initial Core Initial Serin 1 Numbu Cut.H.tunbu Lond Number Qtwrnting Dnte MO 344 to 9147 IW1U91 MO 345 TD 91-46 IWO7/91 MO 316 U) 91-47 10/14/91 MO.347 fo 91 53 12'3W91 MO-348 fo 92-01 01/0&D2 MO 349 !O 91-53 12/3W91 MO-350 fr3 92-01 01/0G'92 MO 351 00 92,09 02/24/92 MO-352 60 92 17 04/06/92 MO 353 00 92 09 02/24/92 MO 354 00 92 17 OV06/92 MO 355 00 92 22 . Ordo 4/92 _
MO 356 60 92/a OWO4/92 MO-357 00 92 25 05/26/92 MO-358 60 92 25 05'26/92 MO-359 61 92 28 OW15/92 MO 360 61 92 28 OW15/92
- 2. Fuel Shipping: Sever.ty two spent fuel elements were shipped from MURR to Savannah River Plant, Aiken, South Carolina. The identification numbers of these elements are:
MO 232 MO 256 MO 267 MO 277 MO 287 MO297 MO-307 MO 234 MO 257 MO 268 MO 278 M0488 MO 298 MO 308 MO 239 MO 256 MO 269 MO 279 MO-289 MO 299 MO 3C9 MO-240 MO 259 MO 270 MO 280 MO-290 MO 300 MO-310 MO 241 MO260 M O 271 MO 281 MO-291 MO 301 MO-311 MO 246 MO-261 MO 272 MO 282 MO 292 MO 302 MO-312 MO 247 MO462 MO 273 MO 283 MO 293 MO 303 MO-313 MO 248 MO 263 MO 274 MO 284 MO 294 MO-304 MO 314 MO-249 M O 264 MO-275 MO-285 MO 295 M O-305 MO 315 MO-254 MO-265 MO 276 MO-286 MO-296 MO 306 MO-317 MO 255 MO-266
' embly fabricator, This work is contracted with the U. S.
Energy and administered by EC&G Idaho h.:., Idaho Idaho. Falls,< AsDepartment of 30 of June 1992,161 fuel assemblics fabricated by B & W had been received and all used in cores at 10 MW.
- 4. Licensing Activities: On May 8,1991, MURR receival Amendment No. 21 to the facility license No, R 103 allowing a temporary (until December 31,1992) increase in U 235 possession to 75 kilograms. In March, April and May of 1992, MURR completed nine spent fuel shipments. By letter of July 2,1992, MURR requested an amendment to the license R-103 to return to a U 235 possession limit of 45 kg.
A request for a unique purpose exemption as defined in 10CFR50.2 was submitted September 26,1986, and is pending.
. V11-2
___.____...-_m__ . . . _ _ _ _ _ _ _ _ _ _ _ _ . _ - . _ _ _ _____.__________m_ _ _ . .-- _._ _ --- -
- 5. Reactor Characteristic Measurements: Sixty-two refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 2.32'"c. The largest excess reactivity was 3.07'7c. MURR Technical Specification 3.1(0 requires that the excess reactivity be less than 9.8'7c.
Reactivity measurements were performed for eight evolutions to verify reactivity parameters for the fiux trap. Dirrerential worth measurements were made on blades C and 13 (twice). The primary coolant temperature coeflicient was verified by measurement.
Physical inspection of the following fuel elements were perfortr?d to verify operational parameters:
MO-295 12/11/91 MO 303 12/11/91 MO 311 12/13/91 All measurements were within operational requirements.
VII 3
SECTION VIII
SUMMARY
OF ItAD10 \CTIVE EFFLUENT RELEASED TO THE ENVIRONMENT Sanitary Sewer Emuent 1 July 1991 through 30 June 1992 Descending Order of Activity Released for Isotope Totals > 1.00 E 5 Ci:
Nuclide Amount (Ci) Nuclide Amount (Ci)
H3 2.091E-01 Se-75 4.84GE-04 As-77 1.390E-02 Eu 154 3.127E4)4 S-35 8.055E-03 Na 24 2.393E-04 Pd-109 G.503E-03 Rb-8G 2.248E-04 Pd 103 6.419E-03 Cd 109 2.219E-04 Re-186 5.090E-03 Cr-51 2.201E-04 C -C! 1.GG9E-03 Eu-152 1.303E-04 Ca-45 1.630E-03 Sc46 1.225E-04 Te-125m 1.189E-03 Fe 59 4.407E-05 W-188 9.569E-04 Gd-159 3.50GE-05 Zn 65 6.779E-01 Tm-170 2.179E-05 Co-60 6.259E-04 Ru 105 1.791E-05 Total h -J 2.094E.01 Ci Total Other 4.879E-02 Ci VIII-1
Stack Ellluent 1 July 1991 through 30 June 1992 Ordered by % Technical Specification (TS) Limit Average Total Release Concentration FY 9192 TS Limit Isotope (itCibnl) . (Ci) (x MPC) % TS+
Ar-41 8.SE 07 4.4E4 02 350 6.286 W.188 3.8E.12 6.0E 05 1 3.819 1131 1.3E 12 7,3E 01 1 1.263 Xe 135m 2.1E-10 7.8E-03 350 0.591 Pd 103 1.0E-10 2.0E-03 1 0.344 Eu 154 2.2E 13 1.9E-06 1 0.220 Eu 152 2.9E-13 7.5E-06 1 0.072 V 52 6 OE 09 d.7E 01 350 0.058 Te 125m . 1.8E 12 6.9E-05 1 0.016 1.3E 13 '
Co-60 1.3E 05 1 0.013 lin-133 3.9E-14 4.9E 07 1 0.039 Co 139 3.1E-14 4.4 E-06 1 0.031 Cd 115 3.0E-13 1.3 E-05 1 0.030 Cc-144 5.9E 14 1.8E-06 1 0.030 Cd 109 4.3E 13 1.5E.04 1 0 021 Ilg 203 S.4E 13 4.7E 01 1 0.016 13a 140 1.4 E-13 8.4 E-06 1 0.014 =
Se 75 4.8E 13 3.3E 04 1 0.012 Tb 100 9.68 14 1.7 E-06 1 0.010 Rb 89 8.7E 10 7.5E-03 350 0.008 Sc-46 6.3E 14 4.0E 06 1 0.008 Gd 153 5.6E-13 3.7E-05 1 0.007 Zr-95 6.7 E-14 8.5E-07 1 0.007 Mn 54 6.5E 14 6.5E 07 1 0.007 Cs-137 3.2E 14 4.1E 06 1 0.000 Zn-65 1.2 E-13 1.1E-06 1 0.006 I135 2.0E-11 1.0E-02 3'O 0.006 Rb-86 5.1E-13 4.6E-06 1 0.005 -
1133 6.8E 12 4.0E-03 350 0.J05 Xe-138 4.9E-10 1.4 E-02 350 0.005 Ir-192 2.9E-14 2.1E-07 1 0.003 lif 181 3.2E 14 6.7 E-07 1 C.003 1134 6.2E-11 3.2E-02 350 0.003 11 3 1.5E-09 7.3E-01 350 0.002 1132 1.6E 11 8.9E-03 350 0.001 ,
Sb 125 2.8E-13 1.2 E-05 1 0.001 Cs-138 1.4E-10 3.6E-02 350 0.001
- Rb-88 1.3 C-10 3.4 E-04 350 0.001 Cu 64 1.7 E-10 1.8E 03 350 0.001 Pd 109 3.9E 11 9.9 E-03 350 0.001 Pa 233 6.1E 14 9.6E-07 1 0.001 Ru 103 2.9E 14 8.3E-07 1 0.001 Total 13.035
- Isotopes observed at <0.001% TS limit not listed.
Stack flow rate 33,500 ft.a/ min VIII-2
SECTION IX
SUMMARY
OF ENVIRONMENTAL SURVEY 9 1 July 1991 through 30 June 1992 Environmental samples are collected two times per year at eight locations (HP-11: " Environmental Sampling") and analyzed for radioactivity. These locations are shown in Figure 1. Soil and vegetation samples are taken at each location. Water samples are taken at thice of the eight locations. Results of the samples are shown in the following tables.
- 1. Sampled during October 1991.
lktection Limits
- Matrix _ Alpha Beta Gamma Tritium ___
Water 0.8 pCi/l 2.8 pCi/l 229.3 pCi/l 16.3 pCi/ml of sample Soil 0.8 pClig 2.7 pCi/g 1.4 pCi/g N/A Vegetation 1.5 pCi/g 5.5 pCi/g 3.4 pCi/g 16.3 pCi/ml ofdistillate
- Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
Determined Radioactivity Levels -
Vecetation Samnles Alpha Beta Gamma Tritium Samnle .InCilg)_ (nCi/g) (nCi/c) (nCi/c) 1-V-40 < 1.5 28.8 <3.4 < 16.3 2-V-40 < 1.5 21.3 < 3.4 < 16.3 3 V-40 < 1.5 19.2 < 3.4 < 16.3 4-V 40 < 1.5 16.2 <3.4 < 16.3 5 V-40 < 1.5 18.8 < 3.4 < 16.3 6-V-40 < 1.5 19.0 3.7 < 16.3 7-V-40 < 1.5 19.3 < 3.4 < 16.3 10-V-40 < 1.5 21.2 < 3.4 < 16.3 1X-1 i
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t Delrmined_lktdinac1hity Levels Soil Samples Alpha Beta Gamma Samnle .Ipli/g) (pCi/g) (pCi/d 1&%0 < 0.8 18.1 6.4 2&%0 < 0.8 19.3 6.3 3-S-40 < 0.8 18.4 6.8 4-S-40 < 0.8 10.6 4.4 5&t0 < 0.8 19.0 7.1 G-S40 < 0.8 14.3 6.3 7-S-40 < 0.8 15.2 7.9 10-S 40 <0.8 18.4 8.2 D.21RnDIACJ1 Radionctivitv Levels Water Samules Alpha Beta Gamma
- Tritiu ra Sample (oCi/l) 11GL (nCUl) .
(nCi/ml) ,
4--W-10 < 0.8 11.2 355.2 < 16.3 G-W-10 < 0.8 11.0 400.4 < 16.3 10-W -40 1.2 14.0 397.6 < 16.3
- The gross gamma activity was greater than the minimum detectable activity.
No unusuel gamma peaks were observed in the spectra on the analyzer screen. Before 'the gross gamma MDA and activity calculations were made, ~
the water samples were evaporated to dryness in preparation for the gross alpha and beta analyses. The procedure was modified to assure that the grosa gamma MDA and activity of the water samples are calculated so that f ther gamme, analysis can be made before water samples are taken to dryness. ._
- 2. Sampled during April 1992 Detection ldmi1E*
llatri:L. .Alph a ;-- Beta Gammn Tritium Water 0.8 pCi!1 2.5 pCi/i 227.0 pCi/l 13.4 pCUml of sample Soil 0.8 pCilg 2.8 pCilg 1.2 pCi/g N/A Vegetation . 1.6 pCi/g 5.6 pCi/g 2.6 pCl/g . 13A pCi/mi ofdistillate
- Gamma and tritium analyses are based on wet veights while alpha and beta are based on dry weights.
IX-3 1
l x- , -- .. .
l lht:IminedlludlDElirily Lrrrla yrgelqtian Sampleg Alpha Beta Ganuna Tritium
. Sample. lDLilfi (DCilgt .Lnfi/E L lRCi/c) 1-V-41 < 1.6 19.0 < 2.6 < 13.4 2.V-11 < 1.6 15.7 < 2.6 < 13.4 3V41 < 1.6 21.9 < 2.6 < 13.4 J 4.V 41 < 1.0 22.5 < 2.6 < 13.4 5 V 41 < 1.C 17.9 < 2.6 < 13.4 6 V 41 < 1.6 22.8 < 2.6 < 13.4 7 V-41 < 1.6 21.1 < 2.6 < 13.4 10-V-41 < 1.6 27.:4 2.8 < 13.4 e Determined Iladicaciirjty Levels Soil Samples Alpha Beta Gumma Samnlc. (pCtM. (nCi/gl tpCi/ci 1-S-11 1.2 19.7 6.8 2-S-41 < 0.8 16.6 7.8 3 & 11 < 0.8 11.0 5.7 4-S-41 < 0.8 11.4 5.5 GS 41 < 0.8 13.8 7.0 6-S-41 < 0.8 15.0 5.9 7-S-11 < 0,8 15.4 6.2 10-S-11 < 0.8 15.8 7.5 Detennined Radistelivity Levels Water Samnles Alpha Iketa Gamma Tritium
.Esunnic_ JnCidL .InCi/D .(pci/l)_ lDfilmlL 4 W-41 <08 < 2.8 < 227.0 < 13.4 G-W-41 < 0.8 5.5 < 227.0 < 13.4 10.W-41 < 0.8 12.2 < 227.0 < 13.4 IX-4
l ENVIRONMENTAL TLDs ,
! The MURR Health Physics sta!T have continued to work with Landauer.
l Inc. in the development of a TLD monitoring program to monitor external doses around the MURR Facility. This development has included both establishing of appropr. ate placement of the TLDs around University property and Landauer's instituting Lacir new environmental mP.itoring services. As such, the program has continued to be in its testing phase.
Based on their testing, Landauer chose aluminum oxide (Al 2Oa:C) as the TLD material for use in their environmental monitors. They finalized their packaging design for the first quarter 1992 moniters deployed by MURR.
Landruer is now marketing their environmental monitoring services ("X9" Dosimeters). Utilizing the guidance of ANSI N5451975:" Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications)," Landauer is offering accurate reporting to .
0.1 mrem precision. 1 The table on the following page lists inting results of monitors deployed in 1991 to provide indication of this development procesr. Clumge:: in the monitor design and placement during this time frame were made er we and Landauer learned more about the process. Precision of the meanurements improved (see fourth quarter results) as Landauer was able to perfect their monitors and procedures.
All totals remained below 100 mrem / year except monitor number 9. This monitor is placed on the side of MURR building (brick) near the loading dock from where radioactive shipments are rnade. This monitor placement was made to sF e that dose rates averaged for a quarter meet requirements for on
) .tricted arca. Monitor number 15 is located on the wall (brick) of the MURR
< c.. .ng Tower. Dose directly from the brick building material is suspected to v .ribute to this reading and continues to be evaluated.
We feel the results for the calendar year 1992 will begin to provide the consistent environmental monitoring data needed to establish the base of data needed to evaluate meaningful environmental impact assessments.
IX-5
Environmental TLD Annual Summary January 1991 through December 1991 13adge Direction Map Distance frt.rn i t,t Q tr. 2nd Qir. 3rd ytr. 4th ytr. Total Nurnbcr h;m MUlt!t MUIllt Stack Net mit Net mit Net mit Net mit Net mit (meters) 1 Control N/A 1 4 1 0.3 6.3 2 Control N/A 0 2 2 0.2 4.2 3 Control N/A 2 5 -4 0.6 -10.4 4 Deploy Control N/A -4 1 0 1.0 6.0 5 Deploy Control ,- -4 -2 0 -0.1 6.1 6 NNE '
34 6 3 8 5.9 10.9 7 ESE 57 -10 4 18 15.3 27.3 8 WSW 27 -13 7 2P 12.3 20.3 9 SSE 27 27 12 43 45 '4 127.3 10 NE 149 6 6 0 -0. '. ' 14.7 11 N 149 -2 11 6 1.9 -5.1 12 ENE 301 1 4 5 -0.4 9.6 13 NNE --
316 2 6 4 3.3 15.3 14 S 156 2 6 4 25 1.5 15 S 65 10 16 20 11.4 57.4 16 SE 107 1 7 1 0.5 6.2 17 E 293l 2 10 3 1.1 16.1 18 NE 47t> -1 lost -7 -0.6 8.6 19 NNE 606 0 0 2 0.6 2.6 20 NE 907 0 2 1 0.5 1.5 21 SE 236 2 2 6 1.6 11.6 22 ESE 168 -6 12 -6 3.0 27.0 23 NW 110 10 2 3 1."' 10.6 24 SSW 328 6 -5 6 5.5 22.5 25 SSW 480 1 4 2 0.3 7.3 26 SW 301 3 2 2 3.6 10.0
~
27 WSW 141 0 0 lost -3.5 3.5 28 WNW 210 4 0 4 1.8 9.8 29 NW 255 3 2 4 2.9 11.9 30 NNW 328 2 5 1 0.5 8.5 31 NNE 671 2 1 6 0.7 9.7 32 NNW 724 4 lost 3 2.0 9.0 33 E 671 0 1 -1 3.6 5.6 34 ENE 587 0 0 3 -5.0 -8.0
~
' 35 SSE 499 2 4 2 0.4 8.4 36 SE 419 4 -3 2 -0.9 5.9 37 NE 690 -2 -3 -2 -4.9 11.9 38 NW 556 4 3 6 3.1 16.1 39 W 491 4 4 2 -0.3 9.7 40 N 514 2 0 lost -0.3 1.7 41 ENE 137 ,
4 4 5 0.9 13.9 j2 in building N/Al 2 5 4 0.5 11.6 4'l in building N/A 4 4 5 1.7 14.7 44 Distant site N/A -3 2 0 -5.3 6.3 45 Distant site N/A -3 -3 -3 0.8 - 8.2 IX-G
NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS Surface Air Radiation C.ent amination
- Samples RWP M
July fB CG 23 9 August EG 76 22 8 September 41 43 21 9 October m m 23 11 November m m 21 6 December TD 53 22 7 M
January 47 41 Z3 10 February 29 27 20 6 March a (0 22 9 April m 49 22 5 May 53 53 21 6 June M d2 % 3 TOTALS GGG G24 2G2 EO Taic: In addition, general building contamination surveys are conducted each normal work day, Miscellaneous items In August 1991, Mr. Rex G. Ayers was hired into the MURE Health Physics Group as a Health Physics Technician. This was a new position created within -
the group to meet the radiation protection needs of the growing programs at MURR. Mr. Ayers received his health physics training in the Nuclear Navy Power Program. He was a Master Engineering Laboratory Technician, a Reactor Laboratory Dosimetry Supervisor and Reactor Labontory Division Leading Petty Omcer at the time of his honorabic discharge. In January 1992, Mr. William D.
Pickett was hired into the MURR Health Physics Group as a Health Physics Technician. This was an open position made available due to the resignation of one of the MURR Health Physics Technicians. As with Mr. Ayers, Mr. Pickett received his health physics training in the Nuclear Navy Power Program. He served as a Leading Engineering Laboratory Technician, a Reactor Laboratory Dosimetry Supervisor and Reactor Laboratory Division Leading Petty Ollicer at the time of his honorable discharge. In April 1992, Ms. Andrea J. Shipp was upgraded from a Health Physics Technician Trainee to a Health Physics Technician.
IX-7
The Univeruity of Missouri's current Br.,ad Scope License (License Nc. 24-00513 32) establishes the administrative structure required fer this Type A matericis license. This structure has consisted of a Central Radiation Safet.y Committee (CitSC) and one Radiation Safety Officer (RSO). The CHSC and RSO are responsible for reviewing and approving the use of radioactive materials at the four campuses under all the University's materials licenses (except the Exempt Release License). In additkn to the Broad Scope License, these materials licenses consist of the following: Source and Special Nuclear Materials License (License No. SNM 247); Cobalt Irradiator at MU campus (License K 24 00513 33); MURR Cobalt-60 Irradiation Facility (License No. 24 00513 34); MU Hospital Co 60 Teletherapy Unit (License No. 24 00513 35); and MURR Exempt Release License (License No. 24 00513 3GE). Each campus and MURR have been responsible for the operational function of these licenses at their respective sites.
For MURR, this operational responsibility has resided with the Isotope Use Subcommittee and with the MURR Health Physics Group. The University applied for renewal ofits Broad Scope License on February 27,1992. As a result of the University wanting to improve the effectiveness ofits radiation safety programs in light of the diversification of the University's Central Administration, the University requested in its license renewal that licensing and operational responsibilities be combined within the respective committee and health physic s.mits by issuance of separate radioactive materials licenses for each campus and for MURR In recent years, the NRC has been focusing on improving and strengthening administrative controls defined for materiala licensees. As part of this defining, the University feels that establishing administrative controls consistent and compatible with those already established under the MURR reactor license provides the most effective and logical control of radioactive materials at MURR The NBC is currently reviewing the University's application for renewal. We are in the process of answering some of their questions concerning our reorganization and how we plan to conduct our radiation safety programs.
ADCO Servicm, Inc. has continued to act as our institutional waste broker.
Through ADCO, MURR disposed of 472.5 cubic feet of LSA material generated at MURR.
The ALARA Program implemented to improve the review and documentation of these efTorts has continued to develop. As stated in last year's annual report, the challenge of establishing a meaningful ALARA Program at MURR has been the organizing of appropriate ALARA review levels which initiate such review and documentation for a wide range of reasonable persor qe1 doses. The following investigational levels have been established:
IX-S
_h . __.____-______m._--_-.-_______.__________-__-______-__--__.__-__________._..__M _m____-_-____-..
_________.____________._._._._m
INVESTIGATIONAL LEVELS Investigational Levels (mrem per month)
Level 1+ L evel 11'
- 1. Whole body; head and > 30 above > 50 above trtmk; active blood and 337c of and 507c of forming organs; lens average monthly average monthly of eyes; or gonads doset doset, or > 180 (deep dose)
- 2. Hands and forearms; > 1003 > 3000 (shallow dose)
- 3. Skin of whole body * > 300 > 600 (shallow dose)
+ Personnel dose noted Report required assessing personnel dose t Average monthly dose based upon previous four quarters
- Applicable for significant quantities of beta emitters The average monthly whole body deep doses in each groupt have typically been:
minimal for Computer Development, Director's Office, Nuclear Engineering, and Itadiation Effects; 10 mrem for Facilities Operations (formally Facilities Management), Instrument Development, Nuclear Analysis Program, Neutron and Gamma Ray Scattering, and Radioisotope Applications; 30 mrem for Reactor Services; 50 mrem for Health Physics; and 80 mrem for Operations.
Increased etTorts in provit'ing additional training for individuals working at MURR have resulted in the development and/or presentation of the following special lectures and videos: Radiation Fundamentals; HP Instrument Training; General Safety video; Chemical Safety videos; History of Radioactivity; Personnel Monitoring; Radiobiology; special subjects for Custodial Support; Biological EITects; Radioactive Material Shipping; and Radioactive Decay.
1 Reorganization of research groups and renaming of other support groups did occur during the report year, but the ALARA review prog an was not reorganized. The reorganization for ALARA review was not completed during this report year because the renewal of the contract for personnel dosimetry services was still being completed, IX-9
Work has continued to make operational a new stack inonitoring systern (Nuclear Measurements Corporation Model ItAK 22ABIB P/0, Continuous Air Monitor System). Equipment and progrtunming problems have delayed final testing and MUltlt's acceptance of the system to perform as the primary stack monitoring system at Multlt. In December 1991, a new access to the MURll containment httilding roof was made in the North tower. This new necess port allows easier entrance to that area for inspection of the roof and of the systems and instrumentation located in thu. area. Previous access we.s either through the facility stock exhaust systee , wh'ch was normally limited to times of reactor shutdown, or by portable ladder access from the laboratory roof.
o t
IX-10
SECTION X
SUMMARY
OF RADIATION EXPOSURESTO FACILITY STAFF, EXPERIMENTERS AND VISITORS 1 July 1931 through 30 June 1992
- 1. Largest single exposure and average exposure are expressed in millirem.
- 2. Minimal exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.
- 3. ME = Number of monthly units reported with minimal exposure.
- 4. AME = Number of monthly units reported with exposure above mini cal.
- 5. AE = Average mrem reported for ali units above minimal.
- 6. HE = Highest mrem reported for a single unit for the month.
- 7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co.
Dosimeter Types: 'C' - X, Gamma Beta, Fast N:.utron (Neutrak 144), Thermal Neutron;"G"- X, Gamma, Beta;"U" TLD (1 Chip Ring).
PERMANENTISSUE BADGES "C" Whole Body Badges (Deep Dose):
AUG SEP OCT NOV DEC JAN FEB MAR l APR MAY JUN JUL 137 137 122 131 115 119 125 129 ME 99 131 112 12'3 55 57.. 62 54 68 62 66 64 AMI 63 48 65 67 63 68 68' 60 65 64 46 62 57 AE 60 68 53 250 220 170 ISO 190 140l 250 170 HE 270 269 240 300 "G"Whole Body Badges Weep Dose):
OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP 69 73 78 76 75 81 84 83 77 ME 31 69 66 7 2 7 5 5 5 2 3 0
, AMI 37 5 8 20 10 17 22 18 18 20 13 0 AE 19 14 16 50 10 30 30 20 30l 30 20 0 HE 60 20 20 X-1
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