ML20056G074
| ML20056G074 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/30/1993 |
| From: | Mckibben J, Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Weiss S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309010285 | |
| Download: ML20056G074 (98) | |
Text
{{#Wiki_filter:6 Research Reactor Facility
- Research Parn Columbia fAssouri 65211 Tetephone (314) 882-4211 UNIVERSITY OF MISSOURI-COLUMBIA FAX (314) 882-3443 August 27,1993 Seymour H. Weiss, Director U. S. Nuclear Regulatory Commission PDNP M.S.11-B-20 Washington, DC 20555
REFERENCE:
Docket 50-186 ! University of Missouri Research Reactor ; License R-103 Enclosed are two copies of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers 1 July 1992 through 30 June 1993. If you have any questions, please feel free to call. Sincerely, Oi
') Of Walt A. Meyer, Jr.
Reactor Manager WAM:bjb enclosure xc:t.Bos ient Control Desk, USNRC 3101J ~ u k'#m COLUMB!A KANSAS CITY ROLLA ST. LOUIS -
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i UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANh7JAL REPORT AUGUST 1993 ( Compiled by the Reactor Staff Submitted byn
\bg b Walt A. Meyer, Jr.
Reactor Manager Reviewed and Appr ed V
// M'mh .
W. L_ J.C. McKibben Associate Director
t TABLE OF CONTENTS Section Eage I. Reactor Operations Summary I-1 through 11 IA. Changes to the Technical Specifications IA-1
- 11. Changes to 31URR Procedures II-1 through 6 A. Standard Operating Procedures B. 31URR Site Emergency Procedures & Facility Emergency Procedures C. Health Physics Standard Operating Procedures III. Revisions to the Hazards Summary Report III-1 IV. Plant and System 31odifications IV-1 V. New Tests and Experiments V-1 ,
VI. Special Nuclear 31aterial Activities VI-1 through 2 VII. Reactor Physics Activities VII-1 through 2 VIII. Summary of Radioactive EfIluent Released to the Environment VIII-1 through 2 IX. Summary of Environmental Surveys IX-1 through 8 X. Summary of Radiation Exposures to Facility Staff, Experimenters and Visitors X-1 through 3
4 SECTION I REACTOR. OPERATIONS SU3131ARY 1 July 1992 through 30 June 1993 The following table and discussion summarize reactor operations in the period 1 July 1992 through 30 June 1993. Full Power Percent Date Full Power Hours Memwmt Devs of Total Tir e of Schedule
- July 1992 663.24 276.50 89.15 99.84 Aug. 1992 631.76 263.77 64.91 95.10 Sept. 1992 668.37 275.75 92.63 103.97 Oct. 1992 673.66 250.95 90.45 101.31 Nov 1992 638.82 267.14 88.73 99.37 Dec. 1992 680.16 283.59 91.42 102.39 Jan. 1993 6S6.70 286.25 92.30 103.37 Feb. 1993 600.63 250.35 89.38 100.11 Liar. 1993 663.77 276.55 89.22 99.92 Apr. 1993 642.58 267.92 89.37 100.10 May 1993 659.22 274.53 88.60 99.24 June 1993 644.99 26S.90 69.5S 100.3s Total fcr Year 7,554.10 3,275.53 89.06 % of 100.427c of Time for Yr. Sched. Time for at 10 MW Yr. et IO MW
- Mt'RR is scheduled to average at least 150 hours per week at 10 MW. Total time is the number cf hours in a month cr year.
There were 23 unscheduled shutdowns recorded during the year 1 July 1992 through 30 June 1993. This number is up slightly from the number of unscheduled shutdowns (IS) the previous reporting year. Of the unscheduled shutdowns,6 were Rod Run-Ins (PsRIs) and 17 were scrams. Fourteen of the unscheduled shutdowns were spurious in nature, with ten of the spurious shutdowns generated by the process indicatica and alarm circuitry associated with Reactor Loop B Flow. These spurious scrams were distributed throughout the year [ July 1992, Oct 1992, Dec 1992, Jan 1993, Feb 1993,31ay 1993] and resulted in extensive troubleshooting efforts that are described in the monthly summaries that follow. Two spurious scrams were associated with the Area Radiation 31onito:ing System. Two unscheduled shutdowns were due to personnel errors, two were due to loss of site electrical power, and four shutdowns were initiated by the duty operator in order to repair equipment. The remainder of the unscheduled shutdowns were from various sources f. shorted coil in control circuit for primary pump 501B, spurious scram from PT944A'B, and a spurious Rod Run-In of unknown origin). 1-1
Julv 1992 The reactor operated continuously in July with the following exceptions: five shutdowns for maintenance and refueling; two unscheduled shutdowns. On July 16, a manual rod run-in was initiated when the outer personnel airlock door gasket was found to have partially pulled out ofits seating groove. The gasket was reseated and tested satisfactorily. The reactor was refueled and returned to normal operation. On July 25, a spurious reactor scram occurred with reactorloop low flow indicated on the annunciator. Thore was no indication oflow flow on any other instrumentation. Flow transmitter 912E (primary loop B) was vented and subsequent investigation revealed that lightly tapping the K-3S relay could initiate a spurious reactor loop low Dow scram. Relay K-3S is in the green leg of the safety system and functions as the contact for reactor loop "B" low flow scram input from flow transmitter 912E. This relay was replaced and the scram test portion of the compliance procedure for flow transmitter 912E was performed satisfactorily. The reactor was then refueled and returned to normal operation. Major maintenance items for the month included: repairing a firemain leak ext.ernal to the facility; installing a new solenoid valve on the pressurizer charging pump cooling water inlet; dumping depleted pool DI bed "P"; loading new pool DI bed "F"; replacing the actuator and diaphragm on valve 527B (pressurizer water charging valve); replacing the sockets for relays K-25, K-26, K-2S; replacing the yellow leg trip actuator amplifier; repairing the sealing gasket on the outer personnel airlock door; replacing K-3S relay; replacing the meter for pool reflector pressure transmitter 917; rebuilding valves S-39, S-41 (secondary outlet of the primary heat exchange-s). Aucust 1992 The reactor operated continuously in August with the following exceptions: nine shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On August 14, a spurious reactorisolation occurred when the area radiation monitor module for air plenum (22) did not detect a threshold number ofinput pulses from its detector. This automatically initiated a scram trip and reactor containment isolation. The background radiation in the air plenum is normally very low, sometimes dropping below the radiation monitor detectable range of 0.1 mr/hr. The Eberline area radiation monitors in use at MURR are designed to initiate an automatic alarm or trip (a protective feature in the event of detector failure)if the background radiation drops below the detectable range for a specified period of time (approximately one minute between input pulses). After conferring with the Health Physics Manager, a small source was placed on the outside of the detector I-2
t assemblies in the air plenum to ensure that the background radiation at the detectors remained in the detectable range (these sources have since been moved to inside the monitor box). All personnel had exited the reactor containment building as required by the reactor isolation procedure when the scram occurred. The reactor was subsequently restarted and no further problems of this type have occurred. Major maintenance items for the month included: replacing (on two occasions) the detector for nuclear instrument channel #3, installing a new turning vane transition piece in the facility exhaust fan (#14) exhaust duct; replacing the millivolt transmitter GIV/I) for Mmary (inlet) te:nperature; changing the taps on the 13,S00/4S0 V substation transformer, increasing the voltage at the substation and at the 480/20S V distribution center; installing a new isokinetic probe and associated tubing on the stack monitor; replacing the disc O-rings on anti-siphon valves 543 A/B; repairing the air line to valve 565B (pool water make-up) solenoid; replacing the mechanical seal on pool demineralizer pump 513B; removing the air can in beamport A. Sentember 1992 The reactor operated continuously in September with the following exceptions: four scheduled shutdowns for maintenance and refueling; two unscheduled shutdowns. On September S, a manual rod run-in was initiated during a normal startup (with the reactor subcritical) due to erratic primary temperature (Te) indications generated by the temperature instrument channel connected to RTD 901A. The problem was traced to a faulty MV/I transmitter for the primary temperature (inlet) indication which had been replaced during September S maintenance activities. The MV/I 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 value (S-1) and an input signal to the digital power calorimetricindicator. This instrument does not provide any safety system scrams or technical specification required indication. The MV/I transmitter was replaced and tested satisfactorily and a normal startup was completed with no further problems. On September 9 a nuclear instrument channel #5 (nower range monitor) high power rod run-in was automatically initiated when the indication for this channel increased to approximately 114Cc. This occurred within seconds after a silicon sample position holder (the Red 3 position) was removed from the reflector during a normal sample handling evolution. The hourly nuclearinstrument log readings taken eighteen minutes prior to this incident reflected that channel #5 was indicating 108.57c. The rod run-in was reset and the channel #5 drawer gain potentiometer was I-3
lowered, decreasing the indicated power on that channel. The reactor was then returned to normal operating power. Nuclear instrument channel #4 (v,ide range monitor)is sensitive to the neutron flux change at the detector which occurs when silicon samples are removed from the red (J reflector) positions (which are closest to the channel #4 detector). Removal of these sample holders decreases the flux detected by the channel #4 detector, which then automatically calls for movement of the regulating blade out to compensate for the detected reduction in flux. This results in an increase in flux at the channel #5 detector and a concurrent increase in the channel #5 power indication. Usually, this increase is approximately 2-3Cc. As part of the August 31 startup (after maintenance activities), the drywells for nuclear instrument channels #4 and #6 detectors were repositioned. This repositioning was necessary due to the change in flux at the charmel 4 and 6 detectors after the removal of the beamport "A" aircan. Aner this drywell repositioning, the channel #4 sensitivity increased to a point where charmel 5 indication would change 5-7Cc depending on which sample position was involved. The change in sensitivity of channel 4 was not apparent to the operators because few red position samples had been handled after the repositioning of the drvwells. The operators recognized that they needed to pay closer attention to the I indication on channel #5 prior to sample handling evolutions and operate this channel at an indication le cel which would preclude this from recurring. Additionally, the drywells were repositioned again to try to minimize the effects of sample handling evolutions. Major maintenance items for the month included: replacing (on two occasions) the MWI transmitter for primary temperature (inlet) indication; replacing the outer personnel airlock door motor. October 1992 The reactor operated continuously during October with the following exceptions: four shutdowns for scheduled maintenance and refueling; one power reduction to allow investigation of equipment in the mechanical equipment room; and one unscheduled shutd own. On October 11, a reactor scram occurred with reactor loop low flow indicated on the annunciator. There were no low flow indications or abnormal indi:ations on any other instrumentation. The flow transmitter for primary loop B (912E) was vented and a detectable volume of air was vented from the flow transmitter and its instrument lines. After the transmitter was vented,it tested satisfactorily and was returned to service. The reactor was then refueled and returned to normal operation. 1-4
Major maintenance items for the month included: performing the biennial change-out of control blade offset "D"; installing an air can in beamport "A"-- perfonning radiographic mapping of the beam-then removing the air can; replacing the door spring on the inner personnel airlock door; removing the floodable center tube in beamport "F" and installing the center tube with silicon filters; removing from service a depleted pool deionization resin bed and loading a new pool sersice deionization resin bed. November 1992 The reactor operated continuously in November with the following exceptwne .- five shutdowns for scheduled maintenance and refueling; one shutdown for a samp. < change-out; two unscheduled shutdowns. l On November 4, a manual scram was initiated when the operators determined that the regulating control blade was inoperable in either the automatic or manual mode. The operators who investigated the regulating blade drive mechanism discovered that the set screw in the coupling between the motor and gear box had loosened, allowing the motor shaft to turn, but not drive the regulating blade. Electronics technicians removed the motor from the gear box and modified the drive shaft by f21ing a flat at the contact point for the set screw. The set screw was renewed and replaced v,ith Loctite. The regulating blade was tested satisfactorily and the reactor was refueled and returned to normal operation. Operation of the reactor while the regulating control blade is inoperable is a - violation of Technical Specification 3.2(a). A License Event Report describing the circumstances and corrective actions of this event was sent to the Nuclear Regulatory Commission on December 4,1992. On November 26, the reactor scrammed due to the loss of site electrical power. The emergency generator startea and assumed its assigned electrical loads. Site electrical power was restored in five minutes. The reactor was subsequently refueled and rett..ned to normal operation. Major maintenance items for the month included: modifying tS regulating blade drive mechanism motor shaft; removing the silicon filters from Be uport "A"; reconditioning Beamport "A" lead shield door; removing Beamport "A" monochromator; installing a new facility exhaust ventilation transition piece; replacing the control power fuse for primary pump 501A; replacing the mechanical seal, inboard and outboard bearings, and gaskets on primary demineralizer pump 513A. I-5
7-- b December 1992 The reactor operated continuously in December with the following exceptions: four shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns. On December 24, a spurious reactor scram occurred with reactor loop low flow indicated on the annunciator. No actuallow flow condition was indicated on any instrumentation. The " white rat" scram monitor indicated that the scram signal had originated from the reactor loop "B" Dow transmitter. The Dow transmitter for loop "B"(FT-912E) was vented and some air was purged. Additionally, the reactor loop
~B" low Dow scram input relay ('K-3S) was replaced after it was noted that minor manipulation of this plug-in type relay would initiate a spurious reactor loop low Dow scram. A hot startup was subsequently completed and the reactor was returned to normal operation.
On December 26, a manual rod run-in was initiated after the main breaker for motor control center (31CC-2A) and the local breaker for secondary pump #3 tripped when an operator attempted to start cooling tower fan #1. MCC-2A provides electrical power to iecondary cooling pump #1 and all three cooling tower fans. University electricians subsequently discovered that cooling tower fan #1 local breaker had shorted out causing the MCC-2A main breaker trip. The secondary pump :3 breaker trip apparently caused a line surge when the fan breaker shorted. The electricians removed the cooling tower fan el breaker, racked-out the secondary cooling pump =1 breaker; and MCC-2A was then reset. Cooling tower f:m #'s 2 and 3 were test run satisfactorily. The reactor was subsequently refueled and returned to operation. On the next maintenance day, January 4,1993, the breaker for cooling tower fan *1 was replaced. Major maintenance items for the month included: removing silicon and plastic spacers and loading a 24" lead collimator in beamport "F" center tube; replacing the 4" fare main connection to the facility with an S" connection; replacing the 3" irradiation hole wedge (#6) with a 6" irradiation hole wedge (*6D); repaiiing the outer personnel airlock door springs; replacing relay K-38; removing the silicon center tube from beamport "F" and installing a Doodable center tube. Januarv1993 The reactor operated continuously in January with the following exceptions: four shutdowns for scheduled maintenance and refueling; and three unscheduled shutdowns. On January 3, a nuclear instrument channel #5 (power range monitor) high power rod run-in was automatically initiated when the indication for this channel I-6
4 increased to approximately 1147c after a silicon sample was removed from the reflector J position during a normal sample handling evolution. The hourly nuclear instrument log readings taken sixty minutes prior to this rod run-in documented that channel #5 was indicating 107.5'~c. The rod run in was reset and the channel #5 drawer gain potentiometer was lowered, decreasing the indicated power on that channel. The operators had been instructed to pay particular attention to the indication on channel #5 prior to and during sample handling evolutions invohing the J (red) reDector poskions after a similar personnel error in September 1992. Operators were again reminded of the sensitivity to initial Nuclear Instrument indications befora handling the J reDector position samples. No additional personnel errors of this type have occurred. On January 5, a reactor loop low Dow scram occurred when primary pump 501B shutdown. Primary pump 501 A remained in operation continuously during the shutdown period. Electronics technicians subsequently discovered a shorted coilin the control circuit for the pump 501B breaker. The shorted coil was replaced and the pump was test run satisfactorily. The primary system was returned to the normal operating mode and a hot reactor start up was completed with no further problems of this type occurring. On January 30, a spurious reactor scram occurred with reactor loop low Dow indicated on the annunciator. No actuallow Dow condition was indicated on any instrumentation. The " white rat" scram monitor indicated that the scram signal had I originated from the reactor loop B Dow transmitter. The Dow transmitter for loop B (FT-912E) was vented and some air was purged. Primary loop B had been partially drained the previous maintenance day to replace a valve diaphragm and it was thought that the Dow transmitter may have been inadequately vented at that time. Subsequent spurious scrams of similar nature occurred in February. The source of these spurious scrams were traced to intermittent grounding of severalleads in the instrument chassis that houses the power supply and square root converter for the reactorloop B Dow transmitter. Details of these similar scrams and the troubleshooting efforts are included in the February monthly summary. Major maintenance items for the month included: replacing cooling tower fan #1 breaker; replacing secondary coolant pump (P-1) breaker; replacing the nitrogen bank "Y regulator; replacing coil in the control circuit for the P-501B breaker; replacing pressure transmitter 917 (pool reDector AP); replacing primary vent valve 552B (including solenoid); replacing the diaphragm for primary heat exchanger outlet valve 540B. I-7
February 1993 The reactor operated continuously in February with the following exceptions: three shutdowns for scheduled maintenance and refueling; three unscheduled shutdowns. Three spurious reactor loop low flow scrams occurred in February--one on Feb. 7, and two during normal startups on Feb. 8. The cause of these unscheduled shutdowns was eventually traced to an intermittent grounding of several leads in the instrument chassis that houses the power supply and square root converter for the reactor loop B flow transmitter. The intermittent nature of the cause of this problem made it diflicult to troubleshoot. Troubleshooting efforts included replacing the green scram leg dual flow alarm unit, and replacing (and calibrating) the primary loop B flow transmitter and square root converter. After isolating the problem to the power supply chassis, electronics technicians tightened the mounting screws on the cabinet assembly and rearranged the ribbon cables between the terminal blocks and the i module connector, eliminating the intermittent ground. A compliance check was performed on the Loop B Flow channel which verified proper operation and the reactor was returned to normal operation. Spurious scrams of this type occurred again in May 1993. Major maintenance items for the month included: replacing the 6" irradiation hole wedge (=6D) with the 3" irradiation hole wedge (#6); replacing the green scram leg dual flow alarm unit; replacing (and calibrating) the primary loop B flow transmitter and square root converter; discharging depleted pool deionization bed "v"into drying barrels--loading new pool deionization bed "w"; replacing the existing security alarm system with a new system. March 1993 The reactor operated continuously in March with the following exceptions: six shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On March 16, a reactor scram occurred as a result of what was determined to be a spurious trip from either PT-944A or PT-944B (reactor outlet pressure). One of these two channels was suspected because the scram was accompanied by the primary shutdown also initiated by these pressure transmitters. There was no actuallow pressure condition indicated on any instrumentation. As part of the normalinvestigation of the cause of the scram, compliance testing (Compliance Procedure, CP-22) of PT-944 A and PT-944B revealed that the PT-944B meter indication did not track input test pressures in a linear fashion with decreasing pressure increments. Numerous scram trip tests of PT-944B revealed a repeatable scram trip at 72.5 psia (57.8 psig) which is 2.5 psi below the LSSS for the low I-S
pressure scram. PT-944A was tested and found to be within specifications. The two other low pressure scrams which are initiated by PT-943 (Rertor Inlet Pressure) and by PS-938 (Pressurizer Low Pressure) were tested to be in compliance with Technical Specification requirements. The last compliance test of PT-944B (with PT-944A and PT-943) had been on October 26,1992. At that time the PT-944B scram setpoint was within compliance procedure limits. When the PT-944B meter relay trip unit did not respond properly, the meter movement for the unit was replaced. The pressure transmitter (PT-944B) was tested and found to be operating properly. After replacing the meter movement, compliance testing of the safety channel for PT-944B indicated it was operating within compliance procedure limits. As follow-up to this problem, the scram setpoints for PT-944B were retested on two occasions,31 arch 29 and April 12,1993, to ensure that there was no setpoint drift. The regularly scheduled compliance testing of the safety channels for PT-944A, PT-944B and PT-943 was completed in April 1993. As a result of fmding that the scram setpoint for pressure transmitter 944B was . below the Limiting Safety System Setpoint required by Technical Specifications, a license event report was sent to the Director of Nuclear Reactor Regulation, Washington, DC, on April 14,1993. hIajor maintenance items for the month included: reinstalling sample irradiation wedge 6D in position #6; replacing the meter movement for pressure transmitter 944B; replacing pressure transmitter 944A alarm lamp; replacing primary 501B pump assembly; replacing the flex gasket on the inlet side of primary loop discharge check valve; replacing the paraflex coupling on primary pump 501B. Anril 1993 The reactor operated continuouslyin April with the following exceptions: five shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On April 17, a spurious reactor isolation and reactor scram occurred which was caused by a disconnected circuit board in the high range detector module for the reactor bridge, a part cf the area radiation monitoring system (AR31S). There was no high airborne radioactivity level in containment. The disconnected circuit board caused a loss-of-signal to the AR31S module which automatically initiated a reactorisolation and scram. The typical vibration the module experiences in its mounted position may have caused the circuit board to become disconnected. The module had tested properly after its installation following calibration on Alarch 29,1993. The circuit board was properly rescated and the AR31S detector module was tested satisfactorily. The Electronics Technicians who assist in the compliance / calibration check have modified their procedure to add a check of this circuit board after future calibrations. I-9
Major maintenance items for the month included: replacing nucicarinstrument channel #3 detector; replacing prirnary 501B pump due to failed inboard bearing; rescating a disconnected circuit board in the reactor bridge high range ARMS detector module; completing biennial change-out of control blade offset "A"; repairing primary 501B pump due to failure of an oil seal. May 1993 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and refueling; one power reduction to allow a brief entry into the mechanical equipment room; four unscheduled shutdowns. Spurious reactor loop (B) low flow scrams occurred on May 7,8, and 20. The scram monitor indicated in each instance that primary loop B flow transmitter 912E, or its associated circuitry, was the source of the scrams. In each instance, there was no loss or reduction of primary flow. On May 7, the flow transmitter (912E) was vented and a compliance verification of the scram was performed satisfactorily. , On May S, investigation revealed that the scram trip adjust potentiometer for ' alarm unit 920C was so sensitive that merely touching the potentiometer knob would initiate a scram. The dual alarm trip unit 920 C/D was replaced with a spare and a comphance check was performed on both primary and pool trips, verifying the scrams. After the May 20 shutdown, investigation revealed similar scram trip potentiometer sensitivity on the unit that was installed on May 8. This dual alarm unit (920 C/D) was replaced with the unit removed on May 8 that had a new potentiometerinstalled. Compliance checks were completed on this trip unit. No further prob! ems of this type have occurred. On May 24, a rod run-in of unknown origin occurred shortly after a normal startup had been completed following a scheduled maintenance / refueling day. No annunciation or other indication of the rod run-in occurred. All other reactor indications were normal. The rod run-in was subsequently reset. Investigation of the reactor systems revealed that all reactor and auxiliary systems indicated normal. The reactor was returned to normal operation at 10 megawatts. Major maintenance items fbr the month included: replacing the inboard and outboard motor bearings in primary pump 501B; replacing the socket for relay K-26 fpressurizer high pressure); replacing the dual alarm unit 920 C/D (primary and pool flows); rebuilding valve 527F (primary demineralizer outlet insolation); replacing the sealing gasketin truck entry door (101); installing a new actuator in valve 527F. 1-10
June 1993 The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On June 11, a reactor scram occurred from loss of site electrical power caused by a switch problem at the South Providence electrical substation. Site power was restored approximately nine hours later, and the reactor was refueled and subsequently returned to normal operation. Major maintenance items for the month included: replacing a main facility exhaust fan (EF-14) time delay relay; replacing a depleted pool deionizing bed. l I-11
SECTION IA CHANGES TO THE TECHNICAL SPECIFICATIONS 1 July 1992 through 30 June 1993 i MURR TECHNICAL SPECIFICATIONS l (Manualissued 7/9/74) i Revision Number 7 Amendment Number 23 Amendment Date: 5/17/93 Section Page Number Number Amendment Update Sheet 6.1 1 of S I IA-1
. Rev. 5/17/93 MURR TECHNICAL SPECIFICATIONS Amendment Undate Sheet This book has been updated through Amendment No. 12(7-24-79). U.S. Nuclear Regulatory Commission issues the amendment number. NOTE: Not all amendments pertain to changes in the Technical Specifications. Amendment Nc. Amendment Date Revision No. Date Filed in Manual ] 13 3/6/51 1 ] 14 4/15/81 2 ) Tvping Correcticn n/a n'a ] 15 S/12/53 n/a (Physical Security Plan Change) ] 16 10.001S 3 ) 17 2/16/59 4 ) 15 5/E 59 5 _ ] 19 6'6/90 n'a (Facility License R-103 Change) ] 20 S/1/90 6 ) 21 5'S'91 n'a (Facility License R-103 Change) ] 22 E/17/92 n/a (Facility License R-103 Change) ] 23 5/17/93 7 )
< . TECHNICAL SPECIFICATION -
I - UNIVERSITY OF MISSOURI k " RESEARCH REACTOR FACILITY
\ .
QJ Number 6.1 Page 1 of 8 Date 5/17/93
SUBJECT:
Administration l Annlicability l l This specification applies to the administrative controls over operation of the l Research Reactor. 1 Obiective The objective of this specification is to assure proper and safe operation of the facility and experimental programs. Suecification
- a. The organization for the management and operation of the reactor shall be as indicated in figure 6.0.
- b. Written procedures shall be in effect for normal operations of the reactor, emergencies, radiological control and shipping of byproduct material ]
produced under the reactor license. Copies of these procedures shall be ] available in the reactor control room. The Reactor Manager shall review and approve Reactor Operating and Emergency Procedures annually. The Manager, Reactor Health Physics, shall review and approve radiological control procedures and byproduct matedal shipping procedures annually. ] Amendment No. 23
9 SECTION II 1 July 1992 through 30 June 1993 A. CHANGES TO THE STANDARD OPERATING PROCEDURES, 2nd Edition, Effective Date: 5/2/89 (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. 9, dated 8/27/92 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: Pevision No.10, dated 9/2S/92 Revision No.11, dated 10/16/92 Revision No.12, dated 2/4/93 NOTE: SEP-7, page 2: Social Security Numbers have been omitted per request by Nuclear Regulatory Commission, Al Adams,9/87. C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES NOTE: New manualissued 10/29/90 There were no revisions to the Health Physics Standard Operating Procedures 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 ()). II-1
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) Revision Number 9 Revision Date: 8/27/92 Pace Number Date Table of Contents, i - vii 8/27/92 Table of Contents, viii - Retyped only 2/28/92 SOPHII-1 10/18/90 SOPMII-2 8/27/92 SOP /III-3 8/27/92 SOP /III-4 8/27/92 SOP /III-5 8/27/92 SOP /III-6 8/27/92 SOPHII-7 5/2/89 SOPHII-8, New 8/27/92 SOPHII-9, Section renumbered only 8/27/92 SOPSII-10, Section renumbered only 8/27/92 SOPSII-11, Reset only 8/27/92 SOPSII-12, Reset only 8/27/92 SOP /VII-13 8/27/92 SOP /VII-14 8/27/92 SOP /VII-33 2/28/92 SOP /VII-34, New 8/27/92 SOP /VII-35, New 8/27/92 SOP /VIII-13 8/27/92 SOP /VIII-14, Reset 5/2/89 SOP /VIII-17 S/27/92 SOP /VIII-18, Reset 5/2/S9 SOP /VIII-37 8/14/89 SOP /VIII-38 8/27/92 II-2
a 9 TABLE OF CONTENIS,2ND EDIBON (Revisions #1 through #24 to the October 1981 printing have been incorporated.) SECTION NO. PAGE NO. I ADMINISTRATIVE OPERATING POLICIES SOP /I-I 1.1 Purpose SOP /I-I I.2 Scope SOP /I-1 1.3 Reactor Operating Parameters SOP /I-1 1.4 Administrative Policies SOP /I-2 II REACTOR OPERAUNG PROCEDURES SOP /II-1
- 11. 1 Routine Reacter Operation SOP /ll-1
- 11. 2 Fuel Handling Procedure SOP /II 9 1I.3 Control Blade Offset Mechanism Removal SOP /II-12 11.4 Waste Tank Analysis SOP /ll-15 III REACTOR CONTROL AND INSTRUMENTATION SYSTEM SOP /III-1 111. 1 Preparation of Reactor Instrumentation for Operation SOP /III-1 111. 2 Pre Start Up Check of Source Range Nuclear Instrument ]
Channel 1 SOP /DI-2 ] 111. 3 Pre-Start Up Check ofIntermediate Range Nuclear Instrument ] Channels 2 and 3 SOP /ID-3 ] 111. 4 Pre-Start Up Check of Wide Range Nuclear Instrument Channel 4 SOP /III-4 ) 111. 5 Pre-Start Up Check of Power Range Nuclear Instrument Channels ] 5 arid G SOP /IU-5 ) III.6 Procedure for Physically Adjusting NI Detectors at Power SOP /ID-7 III.7 Procedure for Adjusting Indicated Power on NI Channels 4, 5, 6 ) (While at Power) SOP /III-8 ) 111. 8 Check cf Process Radiation Monitors SOP /DI 9 ] 111. 9 Area Radiation Monitoring System SOP /III-10 ) IV PRIMARY COOLING SYSTEM SOP /IV-1 IV.1 Startup cf Reactor Cooling Loop SOP /IV-1 IV.2 Shutdown of Primary System SOP /IV-3 IV.3 Operation of the Antisiphon System SOP /IV-5 IV.4 Depressurization of Pressurizer SOP /IV-6 V POOL COOLING SYSTEM SOP /V- 1 V.1 Pool Cooling System Stanup SOP /V-1 V.2 Pool System Shutdown Procedure SOP /V-3 V.3 Partial Pool Fill!ng Procedures (Pool at Refuel Level or Above) SOP /V-3 1 Ib'. /gA1 kIrftA
TABLE OF COhTENTS. 2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) SECTION NO. PAGE NO. V.4 Pool Lowering Procedure SOP /V-4 V.5 Pool Cleanup System SOP /V-5 V.6 Single Pool Pump Operating Procedure SOP /V-6 ] VI SECONDARY COOLING SYSTEM SOP /VI-I VI.1 Startup of the Secondary System SOP /VI-1 VI.2 Procedure for Operation of Bypass Control Vah*es S-1 and S-2 SOP /VI-3 VI.3 Cooling Tower Operations SOP /VI-5 ] VI.4 Shutdown of the Secondary System SOP /VI-G VI.5 Draining and Filling the Secondary System Heat Exchanger and Piping SOP /VI-7 VI. 6 Secondary Water Treatment Procedures SOP /VI-7 VL7 Secondary System Operation on Maintenance / Refueling Days SOP /VI-9 ] VII AUXILIARY SYSTEMS SOP /VII-1 VII.1 Reactor Power Calculator SOP /VII-1 VII.2 Ventilation Exhaust System (EF-13/EF-14) SOP /VII-2 VII.3 Emergency Power System SOP /VII-3 VII.4 Reactor Demineralizer System SOP /VII-4 VII.5 Skimmer System SOP /VII-15 Vll.6 Primary / Pool Drain Collection System SOP /VII-17 VII.7 Primary and Pool Sample Station SOP /VII-19 VII.8 Liquid Waste Disposal System SOP /VII-20 Vll.9 Nitrogen System SOP /VII-30 ] V11.10 Compressed Air Systems SOP /Vll-30 ) VII.11 Sulphuric Acid System SOP /VII-34 ] VilI REACTOR EXPERJMENTS SOP /VIII-1 VIII.1 General Requirements SOP /VIII-1 V111.2 In-Pool Irradiations SOP /VIII-5 VIII.3 Pneumatic Tube (P-tube) System Irradiations SOP /VIII-S VIII.4 Beamport Experiments SOP /VIII-19 Vill.5 Handling and Release cfIrradiated Samples SOP /VIII-38 VIII.6 Response Procedures for the Nuclepore Irradiation Facility SOP /VIII-38 VIII.7 Thennal Column Door Operations SOP /VIII-40 VIII.8 Response Procedures for the Alpha Laboratory SOP /VIII-43 11 Ilv. / gid h. M
TABLE OF CONTENTS,2ND EDmON (Revisions #1 through #24 to the October 1981 printing have been incorporated.) SECTION NO PAGE NO. REACTOR EMERGENCY PROCEDURES: Table of Contents REP 1 REP-0 Introduction REP-0-2 REP- 1 Failure to Scram or Rod Run-In REP 1 REP 2 Reactcr Scram REP-2-1 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 REP 1 I REP-6 Area Radiation Monitoring System (ARMS) Failure to Actuate g Reactor Isolation REP 1 REP-7 Loss of Communications Between Reactor Control Room and Experimenters REP 1 REP-8 Control Rod Ddve Failure / Stuck Rod REP-8-1 REP-9 ElectMcal Anomalies REP-9-1:2:3;4 REP-10 Failure of Experimental Apparatus REP 1 REP-11 Low Fire Main Pressure REP 1 REP-12 1. css of Domestic Cold Water to Facility REP- 12-1:2 REP-13 Complete of Partial Loss of Secondary Flow REP-13-1:2 REP-14 Loss of Pool Flow Dunng Reactor Operation REP 1 REP-15 Loss of Pool Water Dunng Reactor Operation REP-15-1;2:3;4 REP- 16 Reactor Loop Isolation Valves (507A & 507B) Fall to Close Autcmatically REP 1 REP- 17 Pressurizer Valves Fail to Operate REP 1 REP-18 Both Ant! siphon Valves (543A & 543B) Fail to Open Automatically REP 1 REP-19 Emergency Core Cooling Va!ves (546 A/B) Fail to Open Automatically REP 1:2 REP-20 High ActMty Levels in the Primary Cooling System REP-20-1:2:3 REP-21 High Stack Monitor Indications REP-21-1;2 REP-22 Bomb or Other Oved Threats REP 1 111 k'. A;5 id _
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TABLE OF CONTENTS. 2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) SECTION NO. PAGE NO. APPENDIX A; SOP /A-1 Reactor Startup Checksheet-Full Power Operation SOP /A-la;b;c;d SOP /A-2 Deviation from Standard Operating Procedure SOP /A-2a;b l SOP /A-3 Reactor Shon-Form Pre-Critical Checksheet SOP /A-3a;b l SOP /A-4 Reactor Shutdown Checksheet SOP /A-4a;b SOP /A-S Nuclear Data / Process Data SOP /A-Sa:b;c;d SOP /A-6 Startup Nuclear Data SOP /A-6a;b SOP /A-7 Pneumatic Tube hTadiations SOP /A-7a:b SOP /A-8 Reactor Routine Patrol SOP /A-Sa:b;c;d SOP /A-9 Unscheduled Reductions in Power Repen No. SOP /A-9a;b SOP /A-10 Radiation Work Pennit SOP /A-10a;b SOP /A- 31 Waste Tank Sample Report SOP /A-11a;b SOP /A-12 Primary System Normal Operating Vahe Lineup Checksheet SOP /A-12a:b;c;d SOP /A-13 Secondary Water Activity Analysis SOP /A-13a;b SOP /A-14 Pool System Valve Lineup Checksheet SOP /A-14 a;b;c;d SOP /A-15 MURR Pool Water Analysis SOP /A-15a:b SOP /A- 16 D. I. 203 Series Resin Ihg For Bed SOP /A-16a;b SOP /A-17 TAG - DO NOT OPERATE SOP /A-17a;b SOP /A-18 D.1. Water Makeup Log (Fill in only if sending D. I. water.) SOP /A-18a;b SOP /A-19 MURR Operator Active Status log SOP /A-19a;b SOP /A-20 MURR Tag Out Sheet SOP /A-20a;b;c;d ] MURR Tag Out Inder Recorti ] APPENDIX B; SOP /B-1 Toxic Materials With Restricted Use in the Containment Building SOP /B-la;b iv Rv. 8/27/92 Md UltDi\
LIST OF EFFECTIVE PAGES,2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) Pare Numbq Date Revised Pace Number Date Revised Title Page 5/2S9 SOPMI 10 5/249 Assignment Sheet 5/247 SOPMI-11 5/2/89 Revision No. & Date Page 5/249 SOP /1112 5/2/89 Table of Contents: SOPM] 13 8/14/89 i 8/27/92 ] SOP 4114 1/1690 ii 8/27 S 2 ] SOPMI-15 1/1690 iii Reformatted Only 8/27S 2 ] SOPMI-16 10/1890 iv 8/27/92 ] SOPMll-1 10/18SO List cf Effective Pages: SOPMII 2 8/27S 2 ) v 8/27 S 2 1 SOPM]I-3 8/27S 2 ) vi 8/27/92 ] SOPall-4 8/27S 2 ] s ii 8/2792 ] SOPMll 5 8/27 S 2 ] viii 2/2892 SOP /111-6 8/27/92 ] SOPM1 5/249 SOPM11-7 5/259 SOP /1-2 10/1830 SOPall-S New 8/27/92 ] SOPM-3 10/1890 SOPall-9 Renumbered 8/27S 2 ] SOPM-4 10/18S 0 SOPMil-10 Renumbered 8/27S 2 ] SOPM-5 5/2/59 SOPall 11 Reset 8/27/92 ] SOPM-6 5/259 SOP /11112 Reset 8/27B2 ] SOPM-7 5/2S9 SOP /IV-1 10/0'81 SOPM-8 5/2S9 SOPSV-2 5/2/89 SOPM-9 8/14/E 9 SOPAV-3 10'0/81 SOPM-10 5/2S9 SOPMV-4 5/249 SOPM-11 10/1850 SOPM V-5 10/0/81 - SOPM-12 8/1449 SOP /lV 6 5/2/F9 SOPM-13 8/1449 SOP /V-1 5CS9 SOPM-14 8/14/t.9 SOP /V-2 5/249 SOP /I 15 8/14/59 SOP /V 3 8/1449 SOPM 16 10/1S/90 SOP /V-4 1/1690 SOPM-17 10/18SO SOP /V-5 5/2/S9 SOPM-18 10/1S9 0 SOP /V-6 1/16S 0 SOP /I-19 10/1890 SOP /V-7 1/16SO SOPM-20 10/ISG0 SOP /V-8 1/16SO SOPM 21 10/1850 SOP /VI-1 450/91 SOPM-22 10/1890 SOP /VI-2 1/16S 0 S OPM-23 10/18S 0 SOP /VI 3 5/2/89 SOP /1-24 10/1860 SOP /VI-4 5/2S9 SOPMI-1 5/259 SOP /V!-5 5/2'S9 SOPMI-2 5/259 SOP /V!-6 450S1 SOPMI-3 5/259 SOP /Vl-7 10/18SO SOPMI4 5/249 SOP /VI S 1/1690 SOPMI-5 10/0/81 SOP /VI-9 10/1890 SOP /116 5/249 SOP /VI-10 5/2/89 SOPMI-7 12/16S 9 SOP /VII-1 10/0S1 SOP /E8 8/14/89 sop /Vjl.2 4 SOS 1 SOP /11-9 10/18SO SOr/Vil-3 10/18SO _ v Rev- U2D2 App'd DM m__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ - - _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - - - - - - - " - - - -
y, ._ . - . _ _ . . _ LIST OF EFFECTIVE PAGES,2ND EDITION - l (Revisions 01 through #24 to the October 1981 printing have been incorporated.) ; P3ce Number Date Revised Pere Number Date Revised SOP /VII-4 10/1890 SOPNIll-14 5/2/89 - SOPNIl-5 5/2/89 SOPNI11-15 5/2/89 ! SOPNII-6 5/2/89 SOP /VIII-16 5/2/89 - SOPNII-7 5/2/89 SOPN111-17 8/2792 ] ! SOPNII-8 5/2/89 SOPNIll-18 5/2/89 .j SOPNII 9 5/2/89 SOP /VIII-19 10/1890 SOPNII-10 10/1890 SOP /VIII-20 5/2/89 : SOPNII-11 10/1SSO SOP /V111-21 5/2/89 .; SOP /VII-12 2/28S2 SOP /VIII-22 5/2/89 [ SOPNII 13 8/27B2 ] SOP / Vill-23 5/2/89 , SOPNII 14 8/27S 2 ] SOP /VIII-24 5/2/89 SOPN]I-15 5/2/89 SOP /VIII-25 5/1,o9 , SOPNII 16 S/2/89 SOPNIII-26 5/249 SOF/VII-17 5/2/S9 SOP /VIII-27 5/2/89 I SOPNII-18 5/2/89 ' SOP /VIII-28 5/2/89
- SOPNII-19 5/2/89 SOP /VIII-29 5/2/89 SOPNII-20 4/30S1 SOP /VIII-30 5/2/89 l
SOP /VII-21 5/249 SOP /V111-31 5/2S9 l 4 SOPNII-22 10/1860 SOP / Vill-32 5/2/89 l l SOP /VII-23 5/2/S9 SOPNIll-33 8/14/89 ; 50PNII-24 5/249 SOPNIII-34 5/249 i SOP /VII-25 1/2/92 SOP /VIII-35 8/14/89 ; j SOPNII-26 1/2/92 SOPNIII-36 5/2/89 ( l SOP /VII-27 5/249 SOP /VI11-37 8/14/89 l SOP /VII-28 5/2/89 SOP /V111-38 8/27S2 ] } COPNII-29 1/16/90 SOP / vill-39 2/28S2 : SOP /VII 30 2/28/92 SOP /VIII-40 2/28S 2 ! SOPNII 31 2/28/92 SOP /VIII.41 5/2/89 I SOP /VII-32 2/28/92 SOPN111-42 5/2/89 [ SOPNIl-33 2/28S2 SOPNIII-43 10/18SO SOPNII-34 New 8/27S 2 ] SOP /VIII-44 10/1890 4 SOP /VII-35 New 8/27/92 ] SOPN11145 10/18SO SOPNII-36 New 8/2792 ] SOPNIII-46 7/16S1 j SOP /V111-1 10/0/81 j SOPNIII-2 10/RSO REACTOR EMERGENCY PROCEDURES: - SOP /VIII-3 5/2/89 REP-9-1 (Table of Contents) 7/16S1 [ SOPNIII-4 5/2/89 REP-0-2 6/27B1 l SOPNIII-5 5/2/89 REP-1-1 6/27/91 i SOPNIII-6 5/2/89 REP-2-1 6/27S1 SOPNIII 7 10/18S 0 REP-3-1 6/27B1 ! SOP /VIII-8 5/2/89 REP-4-1 6/27/91 ! SOPNIII-9 5/2/89 ' 'P-5-1 6/27/91 : SOPNIII-10 ' 5/249 REP-61 6/27BI i SOPNIII-11 5/2/89 REP-7-1 6/27S 1 f SOPN111-12 10/18S 0 REP-8-1 6/27B1 i SOPN111-13 8/2782 ] REP-9-1 6/27/91 ! vi ! Rev. App'd h@ i 1
~
s LIST OF EFFECTIVE PAGES 2ND EDITION (Revisions #1 mrough #24 to the October 1981 printing have been incorporated.) Pace Number Date Revised Pace Number Date Revised REP 9-2 6/27S 1 SOP /A-Ba 2/28/92 ) REP-9-3 6/27S 1 SOP /A-Sb 2/28S 2
' REP-9-4 6/27SI SOP /A-Sc 2/28S2 REP-10-1 6/27/91 SOP /A-Sd 8/14S9 i
REP-11-1 6/27B1 SOP /A-9a 5/2/89 REP-12-1 6/27S ) SOP /A-9b ^ 6/0/80 REP-12-2 J2 SOP /A-10a 10/8/86 REP-13-1 CnS1 SOP /A-10b 10/8/86 REP-13-2 6/27S 1 SOP /A 11a 1/2S2 REP-14-1 6/27 S 1 SOP /A-11b 12/15/82 REP-15-1 6/27BI SOP /A-12a 5/2S9 REP-15-2 6/27S1 SOP /A-12b , 5/2/89
- REP-15-3 6/27S1 SOP /A-12c 8/14/89 REP-15-4 6/27S 1 SOP /A-12d 5/249 REP-16-1 6/27/91 SOP /A 13a 5/2/89 j REP-17-1 6/27S 1 SOP /A-135 5/2/89 1 REP-18-1 6/27BI SOP /A-14a 1/16SO REP-19-1 6/27 S 1 SOP /A-14b 1/16S 0 REP-19-2 6/27/91 SOP /A-14c 5/249 ;
j REP-20-1 6/27B1 SOP /A-14d 5/2/S9 REP-20-2 6/27/91 SOP /A-15a 5/2S9 i REP-20-3 6/27/91 SOP /A-15b 5/2/89 f REP-21 1 2/28/92 SOP /A-163 5/249 ; REP-21-2 2/2SS2 SOP /A-16b 5/2/89 ;
- REP-2 . -3 2/28/92 SOP /A-17a 5/2/89 j REP-22-1 6/27/91 SOP /A-17b 5/2/89 I
) S OP/A 18a 2/2562 9 APPENDIX A: SOP /A 1Sb 5/249 SOP /A la 2/2SS2 SOP /A-19a 5/2S9 l 3 SOP /A-lb 4/30S 1 SOP /A-19b 5/2S9 ! SOP /A-1c 2/2SS2 SOP /A-20a 10/IESO ! SOP /A-1d 2/ISS) SOP /A-205 l 10/18SO 4 SOP /A-2a 5/2/$9 SOP /A 20: 10/18/90 . SOP /A-2b 5/2/89 SOP /A-20d 10/1SB0 I SOP /A-3a 2/28S 2 ' SOP /A-3b 6/0/50 APPENDlX 3: SOP /A-43 5/2/S9 SOP /B-la 5/2/89 '; SOP /A-4b 5/2A9 SOP /B-lb 5/2/S9 ! SOP /A-Sa 7505> . SOP /A-5b 4SOSI !' SOP /A-Sc 6/0/50 SOP /A.5d 6/0$0 SOP /A-6a ' 3 S/83 l SOP /A-6b 5/2/S9 ! SOP /A-7a - 9/19/S3 ! SOP /A-7b 6/0/80
) vil 'I i
Rev. 8/27/O
^
App'd Nth 1
~
u'* - - w-
t J. On UPS-3 Panel:
- 1. Open breaker #1
- 2. Open breaker #2 1
- 3. Open breaker #3
- 4. Open breaker #4 {
- 5. Open breaker #5 l
t
- III.2 Pre-Start Up Check of Source Range Nuclear Instrument Channel 1 !
A. Verify power ON to recorder and alarms cleared. B. Check the internal drawer test functions (any order): l
- 1. STANDBY (Check the following indications) f
- a. Drawer Inoperative indicator light. !
Nuclear Instrument Anomaly. b. (
- 2. ZERO
- a. Recorder and Meters indicate 10-1 cps. ;
- b. Local and remote Period Meters indicate -30 sec. i
- c. < 1 cps light illuminates. !
- d. Channel 1 Lo Count Rate annunciation occurs. !
i- i
- 3. PERIOD -
Hold Ramp switch to fixed and check for +3 second period. { , Check local and remote Period Meters. , t
- 4. 10s
- a. Recorder, local and remote meters indicate S x 104 to 1.5 x 105 cps. .
- b. < 1 cps light is out. :
- c. Channel 1 Lo Count Rate s-. 'nciation is clear, j
- 5. 10 I Recorder, local, and remote meters indicate 8 to 15 cps. l
- 6. OPERATE f
Reset drawer and verify all indicator lights clear. . C. Energize SCALER for start up, if necessary. j
\
l Rev.18/27/92 App d hh h SOP /III-2 I Section IIL2 through IIL5 revised in its entirety I 3 [
t i IIL3 Pre-Start Up Check ofIntermediate Range Nuclear Instrument I
- Channels 2 and 3 A. Verify power ON to recorder and place console switch to drawer being tested. ;
- B. Check the internal drawer test functions (any order): ;
- 1. STANDRY (Check the following indications)
- a. Drawer Inoperative indicator light.
- b. Nuclear Instrument Anomaly. ;
- 2. ZEROJ !
- a. Recorder and Meters indicate 10-10 amps. !
1
- b. Local and remote Period Meters indicate -30 sec.
- 3. ZERO1 ;
- a. Recorder and Meters indicate 10-10 amps. [
, b. Local and remote Period Meters indicate -30 sec. t
- 4. PERIOD
- a. Hold Ramp switch to fixed and check for +3 sec. period. !
- b. Verify the 35 second indicator light illuminates.
- c. Local and remote Period Meters indicate +3 sec. period.
~ lt
- 5. 3.s I
Recorder, local, and remote meters indicate 8 x 10-9 to 1.2 x 10-8 amps.
- 6. E-4 Recorder, local, and remote nieters indicate 8 x 10-5 to 1.2 x 10-4 amps. .;
) '7. 1.5 x 10-3 ! Recorder, local, and remote meters indicate 1.2 x 10-3 to 1.8 x l 10-3 amps. 4 4
- 8. SHORTPERIOD CHECKS
- a. Rod Run-In occur, at 11 - 1 seconds on console meter. ;
- b. Rod Run-In light illuminates. l l
- c. SCRAM occurs at 9 i 1 seconds on console meter, j l d. SCRAM light illuminates. l
- 9. OPERATE ~
Reset drawer and verify all indicator lights clear. l C. Set compensating voltage so that indication is between 10-9 and 10-8 f amps. -t
- Rev. 8/27/92 3pp.d UANA SOP /III-3 !
Section III.2 through III.5 revised in its enthety l 1 d I
- _ - - . _ . , _ . . - - , , , . . . . - _ _ . _ , m...
~,
I I 111.4. Pre-Start Up Check of Wide Range Nuclear Instrument Channel 4 l 1 l A. Verify power ON to recorder. i j B. Verify drawer potentiometer setting with last recorded heat balance ! ] setting. ; i C. Check the internal drawer test functions (any order): , j 1. STANDBY (Check the following indications) !
! a. Drawer Inoperative indicator light.
f
- b. Nuclear Instrument Anomaly. !
- 2. ZERO 2 L 1
- a. Recorder and local and remote meters indicate 0 2%. ,
- b. Down Scale 95% light is illuminated. [
j
- 3. ZEROI i
- a. Recorder and local and remote meters indicate 0 2%. 5
- b. Down Scale 95% light is illuminated.
- 4. TRIP CHECK 9 i
- a. Rod Run-In occurs at 114 1% on console meter. ;
- b. Rod Run-In light illuminates. !
4 c. SCRAM occurs at 119 1% on console meter. ! , d. SCRAM light illuminates. ;
- 5. OPERATE !
3 Reset drawer and verify all indicator lights clear. ! ) 4 l D. Set WRM range switch to level necessary for start up. ' i 1 j- . 1 l ; l l Rev. 8/27/92 _ App'd Il e SOP /III-4 ! a Section IIL2 through III.5 revised in its entirety , l 1 i l
~
III.5 Pre-Start Up Check of Power Range Nuclear Instrument Channels 5 and 6 A. Verify power ON to recorder. i B. Setting potentiometer to the 103BV calibrated test setting.
- 1. Verify potentiometer setting to last recorded heat balance setting. ;
- 2. Adjust drawer potentiometer to the 10 3RV calibrated test setting.
C. Check the internal drawer test functions (any order):
- 1. STANDBY (Check the following indications)
- a. Drawer Inoperative indicator light. [
- b. Nuclear Instrument Anomaly. ;
- 2. EERO
- a. Recorder and local and remote meters indicate 0 2c/c.
- b. Down Scale 95% light is illuminated. '
- 3. 110cc '
- a. Recorder and Console 31eters indicate 110 27c.
- b. Drawer meter indicates 110 57c. l
- 4. 75c'c !
- a. Recorder and Console Meters indicate 75 2%.
j b. Drawer meter indicates 75 57c.
- 5. 10"o i
- a. Recorder and Console Meters indicate 10 27o.
- b. Drawer meter indicates 10 + 57c.
- 6. TRIP CHECK 9 :
- a. Rod Run-In occurs at 114 17c on console meter. ,
- b. Rod Run-In light illuminates.
- c. SCRAM occurs at 119 1% on console meter. :'
- d. SCRAM light illuminates. ,
e i Rev. 8/27/92 App'd WMW SOP /III-5 . Section IIL2 through III.5 revised in its entirety l i
t
- 7. OPERATE Reset drawer and verify all indicator lights clear. .
D. Set drawer potentiometer to last recorded heat balance setting. a ! d l i 1 . a t i i r i I
?
2 4 1 1 1 4 j Rev. App'd Oh SOP /III- ' j Section IIL2 through III.5 revised in its entirety ! 4
?
t E. Increase power to original level. E Log final new pot setting. , III.7 Procedure for Adjusting Indicated Power on NI Channels 4, 5, 6 (While at ' Power) i NOTE: Shift Supervisor's approval is required before adjusting any power range monitor. ; Indicated power on NI Channels 4,5,6 may be adjusted while at power by manipulation of the drawer amplifier gain potentiometer. This may ' be done, at the Shift Supervisor's discretion, only after a determination of the power level by heat balance or during or shortly after a normal . reactor startup, when an accurate heat balance is not yet possible due to i changing temperatures. ! 111. 7 . 1 Adjusting Channel 4 NOTE: Adjusting the Channel 4 indication shall only be done with the reactor in manual control. Constant monitoring of Channels 5 & ' 6 is required while in this condition, particularly if the reactor is in a transient xenon condition. . A Determine the power level indication desired on Channel #4. B. Ensure regulating blade 60% withdrawn annunciation is energized. C Press " MAN" control switch (S-1) to place reactor in manual control (Reg. blade out of Auto annunciation will occur). D. Adjust the gain potentiometer to achieve the desired power level , 3 indication, referencing the power level indication meter on the console. E. Using the power level switch (IS-9), place the power level set indication approximately 3% below the Channel #4 indication. E Ensure all conditions are met for placing the reactor in Auto control (reference SOP 11.1.3) then press the " AUTO" control switch (S-2) to place the reactor in Auto Control. G. Describe the evolution in the console log, documenting the indicated - power level change. and document the new potentiometer setting on the Nuclear Startup Data log. I ~ 111.7.2. Adjusting Channels 5. 6 A Determine the power level indication desired. a Adjust the gain potentiometer to achieve the desired power level indication, referencing the power level indication meter 1 C Describe the evolution in the console log, documenting the indicated ' power level change, and documen't the new potentiometer setting on
; the Nuclear Startup Data log.
8/2 W 2 i Rev. App,d j p ^ SOP /III-8 Sections III.7 through III.7.2 - New
III.8 Check of Process Radiation Monitors ] 111.8.1 Operational Check of Secondary Coolant and Fission Product ] I Monitors respectively. ! A Lower alarm setpoint until annunciator alarms. l B Place level set switch up and adjust alarm setting to j 10k cpm + 10%. ; C Lower alarm setpoint until annunciator alarms. , D. Place level set switch up to and adjust alarm setting to 12k cpm + 10%. i 111.8.2 Operational Check of Stack Monitor l' A. The operator conducting the test in the West Tower shall establish communication with the control room via the intercom a Place the mode switch for the iodine detector in the 'T' (test) ( 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 i position. Reset the annunciator. .!
, E Place the mode switch for the particulate / gas monitor in the 3 "T" position.
G. Verify that the particulate recorder and gas recorder pens ; indicate 3600 cpm + 10% and that the stack monitor high ! l activity annunciation is received. Also verify that the local i meter reads 3600 cpm + 10%. H. Return the particulate mode switch to "OP" position.
- 1. 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. 7 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"
- alanns cleared. i Rev. App'd Ob SOP /III-9 ] i Sections renumbered only I
.I l
i III.9 Area Radiation Monitoring System ] i The area radiation monitoring system will be in operation continuously and is to be turned off only during maintenance on the system. When . handling samples or during maintenance place the Bridge Upscale Switch ! in the upscale position. Insure Bridge Upscale Switch is returned to ! normal position after handling samples. The 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 l Station 3 BP South Wall 2 X acceptable background l Station 4 Exhaust Plenum 1 mr/hr or 10 X normal operating i background Station 6 Bridge ALARA 300 mr/hr alert 10K mr/hr alarm / trip [ Station 7 Bridge 50 mr/hr or 10 X normal operating 3 background i Station 8 Nuclepore 2 X normal operating background - Station 9 Fuel Vault 2 X normal operating background , Station 10 Room 114 2 X normal operating background l Station 11 Exhaust Plenum #2 1 mr/hr or 10 X normal operating i background l l At least once a month for stations 4, 6, 7 and 11, and once a quarter for .l the remaining stations, the system will be checked according to the : following procedure: i NOTE: GREEN Lamp serves as Normal light and Check Source actuating ! switch (push to actuate source). l AMBER Lamp serves as Alert alarm (push to reset). ; RED Lamp serves as High alarm (push to reset). The alert has i been set up on all ARMS units except for both bridges. ; i A. At station 1, operate the check source pushbutton and verify that ! ivhen trip point is reached, the RED alarm lamp lights at the ' Electronic Channel, and the RED alarm lamp lights and the AUDIBLE i alarm sounds at the Remote Alarm Unit. ; B.. Repeat step A for Stations 2, 3, 8, 9 and 10. U2M2 Rev. App,d WMK SOP /III-10 ) [ Section renumbered only I l
! C The source check for Stations 4, 6, 7 and 11, while performing l the above-mentioned functions, also initiates a reactor scram and Containment building isolation. ;
i i NOTE: For normal startup checks, testing of the manually ! Initiated reactor isolation and facility evacuation trips will ; be performed in conjunction with the above checks with l the horns silenced and the isolation valves and doors i closed. l D. To conduct source checks of Stations 4, 6, 7 and 11: ; NOTE: For Station 6 (Bridge ALARA) and 7 (bridge), the alarm setpoints will have to be lowered to test operation, as the } check source will not provide enough deflection to actuate alarm. !
- 1. Reset scram and rod run-in trip actuators. !
- 2. Notify all persons within the facility of intentions to perform j the check. !
- 3. Operate check source push button, except Stations 6 & 7 and ,
i monitor point of trip, verifying the following has occurred: ; a Scram and rod run-in trip actuator ampliflers tripped. *
- b. Building Air Plenum and Bridge High Activity scram i alann indicated on annunciator. }
- c. Isolation scram alarm indicated on annunciator. [
, d. 16" isolation valves indicate closed, !
- e. Backup doors closed. !
j f. Containment isolation horns have sounded. ! i g. Isolation doors MO-504 and MO-505 indicate closed. l j h. Red flasher light outside outer containment door is j flashing.
- 4. If more than one check is required: '
a The horn cutout switch may be used to silence the j containment horns.
- b. The 16" isolation valves cutout switch, Nuclepore valve cutout switch and backup doors cut out switch may be turned to the off position, leaving the valves and doors !
closed. i
- c. The mVtor operated isolation doors may be left in the ;
closed position. Rev. U2W2 3pp,d Mk SOP /III-11 ] Reset only ' 1 e i _ _ _ , _ _ - ,,o . . - . .. .
l
- 5. When the checks have been performed as required, reset ,
the tripped Station 4. 6, 7 or 11. ; ' i NOTE: Reset alarm setpoints for stations 6 and 7.
- 6. Close the 16" isolation valve cutout switch, verify the valves e
indicate open, return the Nuclepore and back up doors cutout l , switches to nonnal. :
- 7. Open isolation doors MO-504 and MO-505 by depressing the open pushbutton until the doors are completely open and both fans have started. '
- 8. Perform a visual inspection of the ventilation system on the ;
fifth level. l
- 9. Insure isolation horn cutout switch turned ori.
- 10. Notify all persons within the facility that checks are completed and that they should regard all further alarms. ,
i i i
+
f 1 i I 1 1
)
4 i J Rev. ~8/27/92 App'd WA SOP /III-12 ] Reset Only
VII.4.3.1 Providing DI Water to T300 with Reverse Osmosis Makeup A Culligan (Polishing) bed is used to augment the R.0. unit. A. Open T-300 supply valve (RE-31). B. Place product water valve RO-10 to the DI water system position. ] ! i NOTE: The handle points in the direction of the open port. ] I C Check open the following R.O. unit valves: RO-1, RO-2, RO-5, ] ! RO-7, RO-8, RO-9 and RO-13. ! D. Open outlet valve (RO-11) from Culligan bottles. ] l E. Open DI-5. ] i F. Turn conductivity meter to "ON" and place auto valve switch to ] !'
" AUTO" (first auto valve should open).
G. Push the R.O. unit start button. ] H. Push reset button under conductivity meter (second auto valve ] ; should open). There should be a 3 to 6 second delay before R.O. , unit starts. (Pressure should come up to 190-200 psig.) CAUTION: If valves do not open, the conductivity is at or above alarm setpoint. Place normal / bypass switch to
" BYPASS".
l I. Flush R.0. unit through DI-5 until conductivity falls below alarm ] I setpoint. j l J. Open auto valve isolation valve (DI-17) and shut DI-5. ] [ K. Place normal / bypass switch to " NORMAL"if required. ] f L Fill out the DI water log. ; Normally, the water inlet temperature will not require adjust- f ment and is set at approximately 25 to 30 C. Allow at least 30 ] ! minutes of running time to stabilize temperature prior to , dhtermining if an adjustment is needed. j Rev. 8/2m2 App,d lJJ3A SOP /VII-13 i 1
h l [ i TO SECURE SENDING WATER ! A. Push the R.0. unit off button. , t I B. Place auto valve switch to "CLOSE." Turn conductivity meter to l "OFF" (both auto valves should be closed). ! i C. Shut auto valve isolation valve (DI-17). ! D. Shut Culligan bottles discharge valve (RO-11). ! i E. Place product water valve RO-10 to the flush or drain position. ] l
- F. Shut T-300 supply valve (RE-31). !
I CAUTION: The following valves should be left open while the i unit is OFF: i R O-2 > RO-5 i RO-1 RO-6 i RO-7 i RO-S RO-9 l 5 RO-13 l l G. Fill out the DI water log. ] l l
- When the unit is not in use, DO NOT UNPLUG, PLACE IN i STANDBY ONLY. DO NOT SECURE SUPPLY WATER. l NOTE: If for any reason the unit must be turned off or the !
supply water secured, this condition MUST NOT exist ! for more than 60 hours or damage will occur to the
- 3 filter membranes (see technical manual #476 for details). .
l l No regular maintenance is required to operate this unit. For any ; repair or maintenance, refer to the technical manual. ! VII.4.3.2 Providing DI Water to T300 Without Reverse Osmosis Unit Makeup i Transferred to SMP-22. ; i VII.4.3.3 Providing DI Water to DI200 Units Using R300 Bed Transferred to l' SMP-22 Rev. 27/92 App,d WEAN SOP /VII-14 t
. m.__ . . _ . _ . . .. _
i t VII.10.5 Instrument Air Compressor System (Johnson) l VII.10.5.1 Instrument Air Compressor System Operation ' The instrument air compressor is always valved for operation and I operates at a pressure of 70 5 psig. Should this compressor fail ; instrument air may be supplied from the main compressor by ; opening the cross-connect valve located near the compressor and : closing the cut out valve for the compressor. VII.10.5.2 Instrument Air Compressor System Startup l A. Close breaker #31 on LP11. [ , B. Check receiver outlet valve open. ! C. Check oillevel. D. Close local switch at the compressor. i VII.10.5.3 Instrument Air Compressor System Shutdown A. Open local switch at compressor. ! VII.11 Sulphuric Acid System VII.11.1 Receiving Bulk Acid i i CAUTION: This process is potentially very hazardous. Protective t equipment must be worn. Always have an available l supply of water and sodium bicarbonate. Bulk sulphuric acid is delivered by tank truck and is i , transferred to the storage tank by air pressure or j 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. Ensure that the tank pressure does not i exceed 15 psig and closely monitor tank levels. ! ( A. Obtain levelin the acid storage tank and record level on the Acid ; Storage Tank Log Sheet, j B. Check valve 1 shut and valve 2 open. . i C. Open valve 3. !
)
D. Remove the cap on the fillline and open the fill valve. i l Rev. 8/27/92 App'd {$1'\ SOP /VII-34 Sections VII.11.1.A through VII.11.2.K - New : l i
. t i
i E. Connect the acid transfer line from the truck to the fill valve. ' i CAUTION: Maintain a close watch on the acid tank level. If f the system is over filled, acid will spill into the I mixing tank. The heat generated at this point could result .% damage to the acid handling system. , F. Commence filling the acid storage tank. When the volume in : the storage tank reaches the desired level (approx. 34"), not to ! exceed 700 gallons, have the driver secure the transfer. ' G. Ensure the driver has vented all pressure off the system and ! disconnected the hose from the truck allowing the acid in the hose to drain into the storage tank. H. Shut the fill valve and replace the cap on the fill line. I. shut valve 3, check shut valve 1 and check open valve 2. i i J. Log the evolution on the Acid Storage Tank Log Sheet and in the I Reactor Console Log. 4 VII.11.2 Transferring Acid from the Storage Tank to the " Day Tank" When 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. Obtain levelin the acid storage tank and record level on the Acid l 2 Storage Tank Log Sheet. l 1 B. Ensure the acid fill valve is closed and the line is capped. C. Check valve 2 open and check valve 1 shut. i D. Open valve 3. l i E. Screw down on the air regulator (6) until a pressure of 15 psig is } i indicated on the pressure gauge. l F. Shut valve 2 and open valve 1. The indicated pressure will drop ; until the storage tank has been pressurized and the actual l 4 transfer begins. If the pressure rises above 15 psig, reduce it to l' 15 psig by adjusting the regulator. a G. During the transfer, monitor the levels in both the day tank and the storage tank. 8/27/92 ! Rev. App'd be SOPNII-35 i Sections VII.11.1.A through VII.11.2.K - New l 1 i
~. '. - --- _ . - ,
H. When the day tank is full, shut valves 3 and 1. I. Open valve 2 to depressurize the storage tank. J. Back off on the air regulator (6). K. Log the evolution on the Acid Storage Tank Log Sheet and in the Reactor Console Log. 1 Rev. App'd \)@k. SOPNII-36 Sections VII.11.1.A through VII.11.2.K - New
9 The weight limits above do not include the weight of the rabbit, i polyethylene vial, or packing, or the cadmium (or other metal) shields. l 4 The maximum irradiation time for most saniples will be 30 minutes ] ! for power levels > 5 MW. Hair, fibers, paint, air filters anc~ flux ]. ; monitors may be irradiated for a maximum of 2 hours at power levels ] ;
> 5 MW. The following additionallimitations shall apply for ] i irradiations > 10 minutes:
} [
i 1 Primary encapsulation will be heat-sealed high-density polyethylene vials (Holland vials). }
- 2. Liquid samples may be irradiated for up to 30 minutes ~provided pin i j
holes are punched in the top of the polythylene vial to relieve ! j pressure. I Deviations from the above weight and time limitations must be { j specifically authorized in the experimenter's RUR. i e VIII.3.3 Rabbit Limitations ! ?
)
1 A. The only type of rabbit which may be used in the p-tube system is the l high density rabbit. This type of rabbit will be used for all irradiations ! (see Section VIII.3.2.B). Each high density rabbit will be limited to six f insertions not to exceed a total irradiation time of one hour or a ! single insertion not to exceed a total of two hours. ! L ! j EXCEPTION: Each high density rabbit, used for 5 second irradiations l under RUR 254, is authorized to be run a total of 15 times. ! l To account for the irradiation history of high density rabbits, the [ i experimenter will place one mark with a marking pen on the high density ! i rabbit for each insertion up to and including 10 minutes. For irradiations l I longer than 10 minutes, a mark will be placed on the rabbit for each 10 i minute period or fraction there of. For example,if a rabbit is irradiated for l
- 25 minutes, it will receive 3 marks. When a rabbit has received 6 marks, it l
will be discarded. Each rabbit must be examined for cracks or other signs of l pot,ential failure before it is used. ! 8/27/92 i Rev. App'd h% SOP /VIII-13 } i
- l. l i f
\
i VIII.3.5.3 Rabbit Stuck in Tube Any time all or any part of a rabbit fails to return to the dispatch station, notify the control room immediately about the problem, stating the material contained in the sample, the weight of the j sample, the expected actMty and dose rate, and the approximate i time the rabbit can remain in the reactor without creating any hazard or melting. l A. After the control room is aware of the problem, press the
** i return" pushbutton. Observe the rabbit in reactor light and l
, check with the control room to see if the operators heard the , l rabbit leave the reflector region. Hearing the rabbit depart the t t reflector is the only sure way to know it has left. If the rabbit l was heard to depart the reflector region, check the other j connecting station to see if the rabbit was returned the e. , i j B. Depress the dispatch button.
- C. Repeat steps A and B several times as directed by the control l room.
D. If the attempts fail, turn control box off. Go to the other j connecting station, line it up for service and repeat steps A l l and B. ' j E. If rabbit still has not returned, a chaser rabbit may be inserted ] l d in an attempt to dislodge the stuck rabbit. Before the chaser ] t rabbit is dispatched it will be marked so that it can be readily ] l identified, thus preventing confusion with the stuck rabbit ] ! should it return. CHASER RABBIT ID MARK SHOULD GO ] ; ACROSS ONE END CAP, ALONG THE SIDE AND ACROSS THE ] ! ) OTHER END CAP. ] l j F. If these procedures have failed, follow up action will be ] 4 handled by reacter operations and health physics personnel. ' i t 1 NOTE: If the rabbit is stuck tutside the reactor it may be found i l by searching the guide tubes with a radiation monitor. !
- If the rabbit is stuck in the reflector, the reactor may l
- have to be shutdown md the p-tube removed. l Vill.3.5.4 Wet Rabbit !
l If the outside of the rabbit is wet when it is returned from the l l reactor, notify the control room immediatelv. j j ' [ , I 8/27/92
- Rev. App'd (t%\ SOP /VIII-17 i
! i ) i l _ . . . . . . - . - ~ _ ,___ _ _ - - - . - _.
VIII.5 Handling and Release of Inadiated Samples V111.5.1 General Responsibilities 1 The Reactor Services Engineer shall coordinate the handling and shipping of all samples irradiated in the in-pool facilities. He shall ; ensure that the shipping container is'in conformance with the I applicable regulation and that all required shipping papers and l documents are prepared in a timely manner. I
- The Sen' ices Engineer shall also coordinate the sample handling 4
with Health Physics personnel. ' l j The Shift Supervisor shall have the responsibility of ensuring that all irradiation records are complete. He will immediately notify the Services Engineer or his designated representative of any apparent discrepancies relating to the in-pool irradiations. ' i VIII.5.2 Sample Handling Procedures Detailed procedures for the handling of various samples are I contained in the Health Physics Standard Operating Procedure VIII.6 Response Procedures for the Nuclepore Irradiation Facility 4 The following procedures shall be used when responding to alarms [
- . for the Nuclepore Irradiation Facility. I i !
VIII.6.1 Nuclepore Exhaust System Alarms ] ' ] 4 A. Nuclepore ARMS l i NOTE: If Nuclepore ARMS is out of senice for any reason (e.g. repair or calibration), the Nuclepore Irradiator system shall be red tagged off. ; i ;
- 1. If the Nuclepore ARMS alarms, secure the Nuclepore !
system. i , 2. Verify rabbit is fully retracted. 3
- 3. Notify the Shift Supervisor and Health Physics.
2 i Rev. 8/27/92 g p p,d R Nt M . SOP /VIII-38
MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 10 Revision Date: 9/28/92 l Section Page l Number Number ' t List of Effective Pages ii I SEP-2 2 of 5 l SEP-2 5 of 5 SEP-3 2 of 6 SEP-3 3 of 6 - SEP-3 6 of 6 i SEP-4 2 of 6 SEP-4 3 of 6 j SEP-4 6 of 6 : l SEP-7 2cf4 SEP-8 2 of 3 i SEP-8 3 of 3 l Emergency Call List Worksheet A FEP-1 4 of 7 i FEP-2 4 of 4 {' FEP-3 1 of1 FEP-4 2 of 5 l a 11-3 i e
. MURR EMERGENCY PROCEDURES - SEP/FEP SECTIONS LIST OF EFFECTIVE PAGES Page i Section Section Page Fumkr Number Dnta Raviv d Number Numbar Date Revicad SEP/FEP T-C 1 7/11/90 SEP-1 1 2/10/87 SEP- 11 4/08/91 2
1 . f 1/23/92 2 5/13/88 l 3 2/10/87 3 5/13/88- l 4 2/10/87 ! 5 6/24/85 EMERGENCY CALL LIST 1 9/2S/92 ] j SEP-2 1 12/8/89 ' 2 9/28/92 ] WORKSHEETA 9/28/92 ] 3 1/23/92 WORKSHEET B 1/08/85 ; 4 1/08/85 WORKSHEET C 1/23/92 1 5 9/2S T ] WORKSHEET D 1/OS/85 SEP.3 1 12/8/89 WORKSHEET E 0:1g. 6/24/85 l 2 9/28/92 ] 3 9/28/92 ] FEP Table of Contents ! 9/13/91 4 5/13/8S 5 1/09/85 Facility Emergencies 1 5/13/88 6 9/2S/92 ] SEP-4 1 12/8/89 FEP-1 1 3/22/90 2 9/28/92 ] 2 1/23/92 l 3 9/28/92 ] 3 1/23/92 ( 4 5/13/88 4 9/28/92 ] ; 5 1/09/85 5 4/OS/9.' : 6 9/28/92 ] G 7/11/9C SEP-5 1 1/OS/S5 7 7/11/90 2 2/10/87 i SEP 6 1 6/24/85 FEP-2 1 7/03/85 2 2/10/87 2 1/23/92 3 1/23/92 S EP-7 1 1/23/92 4 9/28/92 ] i 2 9/28/92 ] , 3 9/18/89 FEP-3 1 9/28/92 ] 4 9/18/89 , F EP-3(a) 1 1/23/92 j SEP-8 1 1/23/92 2 9/13/91 2 9/28/92 ] 3 9/28/92 ] FEP-4 1 7/03/85 2 9/28/92 ] SEP-9 1 1/23/92 3 5/13/88 2 1/09/85 4 5/13/88 > 5 5/13/88 l SEP-IO 1 Or:g. 6/24/85 2 Orig. 6/24/85 UMH&C (Hospital & Clinics) j Emergency Center Radiation Disaster Plan '
- 11 !
Rev. 9/28/92 App'd UJ% 1
SEP-2 (Cont'd) Page 2 of 5
- 5. Send operator to west tower with radiation monitor to:
NOTE: Communicate by 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 positions on analog display with the time for future analysis if the control room display becomes inaccessible.
- d. Verify flow rate through monitor is 5 + 1 SCFM. If not, use Worksheet A to ]
determine stack monitor values. .
- 6. If nuclides which are being released are in doubt, pull stack filters and analyze.
- 7. The EMERGENCY COORDINATOR shall evaluate the need to evacuate specific portions of the facility.
- 8. The EMERGENCY COORDINATOR shall appoint and have a surveillance team check any areas evacuated in step 7, clear of personnel within 30
. minutes. i NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of10CFR20 limits. (Up to 75 rem for life-saving, up to 25 rem to prevent exposure to members of general public in excess of 1 rem whole body and 5 rem thyroid.)
- 9. The EMERGENCY DIRECTOR shall determine the need for EMERGENCY i SUPPORT ORGANIZATIONS and,if needed, activate them or place them on i standby. See Table II, EMERGENCY SUPPORT ORGANIZATIONS.
~
NOTE: If 9-911 is called daring any emergency, contact MU News Bureau. I i k i i l 1
- Rev. 9/28/92 App'd (LCtA
1 SEP-2 (Cont'd) Page 5 of 5 1
- d. LABORATORIES e (1) Determine which laboratory is the source of release, by checking radiation levels in quadrant exhaust ducting.
(a) Southwest Quadrant ! (b) Northwest Quadrant ! (c) Northeast Quadrant l ACTIONS TO CONSIDER ! (1) Throttle flow from laboratory quadrant to reduce release rate to less than Technical Specifications limits. (2) Area Evacuations SUBSEOUENT ACTIONS:
- 1. Change stack filters when chart reading exceeds 3 x 105 cpm.
Reevaluate chart reading to determine if release rate is increasing / ~ , decreasing. Record time of filter changeout. ;
- 2. Evaluate results of correction and subsequent actions to determine need ;
to escalate /de-escalate the emergency classification. l l
- 3. Keep record of actions and evaluations and time they were done for !
documentation. Use procedure worksheets. .
- 4. Notify NRC, Region III, that an UNUSUAL EVENT has occurred ;
within one hour after event is classified or reclassified. (Use Worksheet C) !
- 5. Notify American Nuclear Insurers (ANI)[203 561-3433] that an ] !
UNUSUAL EVENT has occurred. (Use information in Worksheet C) ! t
- 6. Notify State Emergency Management Agency (SEMA)[314-751-9770] that ] l an UNUSUAL EVENT has occurred. (Use information in Worksheet C) !
RECOVERY ACTIONS: l i
- 1. Evaluate potential radiological effects to onsite and offsite personnel before :
returning access to specific areas effected by UNUSUAL EVENT emergency.
- 2. Procedures shall be written and approved for handling significant recovery evolutions, j NOTE: During recovery operations, personnel exposures to radiation should be !
maintained within 10CFR20 limits. l f Rev. 9/28/92 App'd ljNhW
'i i
. ~ . =. --
- - ' ^
SEP-3 (Cont'd) Page 2 of 6
- 5. Send operator to west tower with radiation monitor to:
NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.
- a. Verify radiation background at stack monitor.
l
- 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 5 1 SCFM. If not, use Worksheet A to ] :
determine stack monitor values. *
- 6. Full stack monitor filters and analyze.
- 7. After determining radionuclide responsible and verifying concentrations greater i than 95,000 MFC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RF1, SFI; (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, have sample i 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. i NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation i exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up ; to 25 rem to prevent exposure to members of general public in excess of ! I rem whole body and 5 rem thyroid.) l
- 10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if !
needed, activate them or place them on standby. See TABLE IV, EMERGENCY l SUPPORT ORGANIZATIONS. ; 1 i l Rev. 9/28/92 App'd WMA !
- . , .,c -
1
. 1 SEP-3 (Cont'd) Page 3 of 6 TABLEIII EMERGENCY SUPPORT ORGANIZATIONS l
- a. UMC HEALTH PHYSICS SERVICES In the event of an ALERT condition, the UMC Health Physics Services may ]
be contacted to man the backup emergency control center. After hours, call ] the UMC Police to open RPDB. ] , CONTACT Office Home ' Dr. Philip Lee SS2-7221 445-5275 , , Jamison Shotts 882-7221 474-2194 l David Spate 882-7221 657-9450
- b. UMC POLICE I The UMC Police may be called to restrict entry 24 hours to the facility. 882-7201
- c. UNIVERSITY OF MISSOURI HOSPITAL i AND CLINICS (UMH&C) Emergency Services SS2-6003 l Ambulance 882-6128 or 9-911 -
Walk-In (Emerg.C.) SS2-8091 l
; The UMH&C should be contacted in the event I
] of personal injury. In the event of personal , contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES. l 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. f i
- d. MU NEWS BUREAU See SEP-7, !
PUBLIC ! This office will initially deal with questions INFORMATION l from offsite. Direct any questions from media to PROCEDURE i this office. They will release statements only by EMERGENCY DIRECTOR authorization.
- e. COLUMBIA FIRE DEPARTMENT 24 hours !
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. i Rev. 9/28/92 App'd M4%\
l SEP-3 (Cont'd) Page 6 of 6 i SUBSEOUENT ACTIONS: l
- 1. Evaluate results of corrections and subsequent actions to determineneed to ,
escalate /de-escalate emergency classification. :
- 2. Keep record of actions and evaluations for documentation. Use procedures i and worksheets. j
- 3. Notify NRC, Region III, that ALERT condition has occurred within one hour [
after event has been classified or reclassified. (Use Worksheet C) ! Notify American Nuclear Insurers (ANI) [203-561-3433] that ALERT condition
- 4. ] ;
has occurred. (Use information in Worksheet C) l
- 5. Notify State Emergency Management Agency (SEMA) [311-751-9770] that ]
ALERT condition has occurred. (Use information in Worksheet C) [ RECOVERY ACTIONS: ! B
- 1. Evaluate potential radiological effects to onsite and offsite personnel before l returning access to specific areas effected by ALERT emergency.
4
- 2. Procedures shall be written and approved for handling significant recovery f
- evolutions.
i NOTE: During recovery operations, personnel exposures to radiation { should be maintained within 10CFR20 limits. j i l I i , l l l W i Rev. 9/28/92 App'd 1)JMi\ l l
, I
i SEP-4 (Cont'd) Page 2 of 6
- 5. Send operator to west tower with radiation monitor to:
l NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.
- a. Verify radiation background at stack monitor. )
i
- b. Verify control room readings. )
- c. Mark initial needle position on analog display with time for future analysis i if control room display becomes inaccessible. ,
l
- d. Verify flow rate through monitor to 5 1 SCFM. If not, use Worksheet A to ] I determine stack monitor values. !
- 6. Pull stack monitor filters and analyze.
- 7. After determining radionuclide responsible and verifying concentrations greater j than 95,000 MPC (a) secure EF-13 and EF-14; (b) secure FF2, SF2, RF1, SF1; j (c) secure all individual vent fans. 1 l
- 8. The EMERGENCY COORDINATOR shall evaluate the need for a partial or total i evacuation of the facility. .
t l NOTE: For facility evacuations or northeast quadrant evacuation, have sample ; counting instrumentation removed to RPDB. (Ge-Li detector and dewer; i High Resolution Gamma Ray Spectrometer)
]
I
- 9. The EMERGENCY COORDINATOR shall appoint and have a surveillance team l check areas evacuated clear of personnel within 30 minutes. !
NOTE: EMERGENCY DIRECTOR approval required for any vo. . ntary radiation exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to prevent exposure 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 IV, EMERGENCY SUPPORT ORGANIZATIONS.
Rev. 9/28/92 App'd b)hTA i l
)
i SEP-4 (Cont'd) Page 3 of 6 l 2 TABLE IV l EMERGENCY SUPPORT ORGANIZATIONS
- a. UMC HEALTH PHYSICS SERVICES s In the event of a SITE AREA EMERGENCY, the UMC Health Physics Services ] i may be contacted to man the backup emergency control center. After hours, ]
call the UMC Police to open RPDB. ] j CONTACT Home Office :
; Dr. Philip Lee SS2-7221 445-5275 j Jamison Shotts 8S2-7221 474-2194 ;
David Spate 882-7221 657-9450 i
- b. UMC POLICE The UMC Police may be called to restrict entry 24 hours ,
to the facility. 882-7201 t
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C) Emergency Services 882-6003 I Ambulance 882-6128 or 9-911 ,
i 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. ! i 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 release statements only by l 4 EMERGENCY DIRECTOR authorization. i e 1 e. COLUMBIA FIRE DEPARTMENT 24 hours j 9-911 i j The Columbia Fire Department shall be notified in the
- i event of fire or need of emergency rescue capability.
Ensure Office of University Relations is also called. Rev. 9/28/92 App'd NMil
SEP-4 (Cont'd) Page 6 of 6 SUBSEOUENT ACTIONS:
- 1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use procedures and worksheets.
- 3. Notify NRC, Region III, that ALERT condition has occurred within one hour after event has been classified or reclassified. (Use Worksheet C)
- 4. Notify American Nuclear Insurers (ANI) [203-561-3433] that ALERT condition ]
has occurred. (Use information in Worksheet C)
- 5. Notify State Emergency Management Agency (SEMA) {314-751-9770) that ]
ALERT condition has occurred. (Use information in Worksheet C) RECOVERY ACTIONS-
- 1. Evaluate potential radio?ogical effects to onsite and offsite personnel before returning access to specific areas effected by ALERT emergency.
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits. ! l l l l j 1 Rev. 9/28/92 App'd V/W
- . - . . - - . . - . ~ ~ . . - . ~ . . - . ~ . - . _ - .
SEP-7 (Cont'd) Page 2 of 4 l 2 I 5. The MU News Bureau staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling j 882-4211 or 874-4119 and asking to speak to a member of the Facility Emergency ' l Organization (FEO). If the person answering the phone does not know who is
- in the FEO, then ask for anyone from the Director's Office, Operations, Health Physics / Reactor Chemistry groups. The individuals in these groups are listed j below in alphabetical order. After verifying the person's identity by asking for
] his social security number, the emergency call can be verified. VERIFICATION LIST FOR MURR EMERGENCIES , J Name Soc. Sec. No. Name Soc. Sec. No. l Chuck Anderson Walt Meyer ! Rex Ayers ] Steve Morris ! i Joe Baskett Paul Muren i' 1 Rita Bonney Phil Neel ! Kenneth Beamer Willy Oldham Barry Bezenek Dave Peeler ] ; i Chester Edwards Derek Pickett ] 1 John Ernst l Leslie Powell 4 Christine Errante ! Mike Randolph i Les Foyto l Bill Reilly John Fruits ! Tony Schoone Greg Gunn l ] l Jim Schuh Robert Hudson i Tom Seeger i
- Rolly Hultsch i Andrea Shipp ] !
j Brenda Johnson ( Vickie Spate j Vernon Jones Ray Stevens ; Mike Kilfoil Nolan Tritsch!er : I Ron Kitch Robert Walker l
, Sue Langhorst Mike Wallis i Charlie McKibben Tim Warner i j 6. MU News Bureau personnel contacted will determine the need for staffing and
- l equipping an emergency information center and will call in the required staff i j and arrange for necessary facilities. I
- 7. MU News Bureau personnel will inform news media and others of the public, l l as necessary, of the emergency. j
- 8. If possible, a MU News Bureau staff member will be sent on site to assist the
{ t EMERGENCY DIRECTOR with the release of information. i Rev 9/28/92 App'd OM
6 i
't SEP-8 (Cont'd) Page 2 of 3 ,
EMERGENCY LOCKER INVENTORY ! MURR COPY ROOM i Date By Number Number { it Requ_i e_d Desired i 0 () 3 self-contained breathing apparatus: (1) Inspection Dates _ _ ID ! (2) Inspection Dates _ ID ! (3) Inspection Dates ID 1 () 2 flashlights - new batteries h stalled every 6 months. Date ] batteries when installing in flashlights. ] 1 () I first aid kit
- 5 () 5 "D" cell batteries replaced with new batteries every 6 ] .
months. Date batteries when placing in locker.
]
3 () 5 boxes swipes
- O () Ibox paper towe!-
0 () Ibox absorbent paper i 2' () 4 bars face soap 3 () 6 " Radioactive Material" tags j 0 () 2 rolls tape l l 0 () Iroll " Radioactive Material" tape l 2 () 2 full face respirators ; 2 () 5 half face respirators 8 () 10 spare filters for respirators ! 0 () assorted plastic bags 2 () 4 NuCon permas:gns f t 0 () NuCon permasign insets j 1 () Ibox rubber gloves 4 () 7 sets protective clothmg j 0 () 20 ft. yellow and magenta rope 1 () 1 Civil Defense instrument kit - l date kit placed in cabinet { REMARKS: Rev. 9/28/92 App'd UNTh'l l
\
i l
SEP-8 (Cont'd) Page 3 of 3 , EMERGENCY LOCKERINVENTORY RESEARCH PARK DEVELOPMENT BUE NG (RFDB)
- Date By .
. Number Number Recuired
~
Desired I 0 () 1 self-contained breathing apparatus: (1) Inspection Dates ID ! 1 () 2 flashlights - new batteries installed every 6 months. Date ] . batteries when installing in flashlight. ] l 1 () 1 first aid kit 5 () 5 "D" cell batteries replaced with new batteries every 6 ] ; q months. Date batteries when placing in locker. ] - 3 () 5 boxes swipes l 0 () Ibox paper towels l l 0 () Ibox absorbent paper ! 2 () 4 bars face soap 3 () 6 " Radioactive Material" tags 0 () 2 rolls tape [ 0 () I roll " Radioactive Material" tape ! 2 () 2 full face respirators ( 2 () 3 half face respirators 8 () 10 spare filters for respirators l 0 () assorted plastic bags 2 () 4 NuCon permasigns ; O () NuCon permasign insets t I () 1 box rubber gloves i 2 () 2 sets protective clothing h 0 () zu ft. yellow and magenta rope 1 () 1 Civil Defense instrument kit - i date kit placed in cabinet . 1 REMARKS. ! i Rev. 9/28/92 App'd [J M N_ i
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- WORKSHEET A i i
CALCULATION OF STACK MONITOR READINGS YvTTH NON-NORMAL FLOW RATES THROUGH STACK MOhTTOR , t i This worksheet is to be used only if stack monitor flow as indicated by the flow gauge is outside j the band 5 1 SCFM. The formula permits the calculation of the reading that would be indicated ] ! if the flow were in the proper range. f i 5 SCFM ' STACK MONITOR READING (in CPM)cnc = STACK MONITOR READING (in CPM)co. x ] FLOW (in SCFM) y for example: flow at monitoris 4 SCFM ] i Stack monitor reading is 1 x 105 CPM ! i i i i ! 5 5 ! CPMcuc = 1 x 10 CPM x 5 SCFM = 1.25 x 10 CPM ! 3 ' SCFM i i
~
t i l i l ! I i i t i ; 1 I i I I ! i I I Rev. 9/28/92 App'd Md I t i i i i >
- .. .-. -- _ ~ . . -
. i FEP-1 (Cont'd) Page 4 of 7 {
i II. PERSONNEL WITHOUT PREASSIGNED TASKS: l (Staff other than Facility Emergency Organization members) l A. IMMEDIATE ACTIONS: !
- 1. Upon hearing the evacuation alarm, personnel shall proceed to points beyond the area bounded by the outer perimeter of the reactor laboratory building.
t
- 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. j i
- 3. EXPERIMENTERS who are conducting experiments in containment !
(including pneumatic tube users) shall render their experimental ] l 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):
A. All personnel within the containment building will exit the ! containment building and proceed through the east door of the laboratory building and then go to the upwind parking lot. j , B. All laboratory personnel, support personnel, and guests exterior to ! the containment building will leave the facility through the nearest exit (north, east, or south doors) and then proceed to the upwind 4 parking lot. l I 2
- 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 :
l B. SUBSEQUEN'I' ACTIONS: , J
- 1. All staff nersonnel 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 persennel shall be monitored by Health Physics Technicians j as per procedure HP-20 before being released to leave the site. i
- 3. A roster of g released personnel will be maintained by the EMERGENCY COORDINATOR.
Rev. 9/28/92 App'd (Jt;n)
. . .. . --- ~ . . . . ~ . -.
= _ , . ,
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^
l FEP-2 (Cont'd) Page 4 of 4 II. PERSONNEL WITHOUT PREASSIGNED TASKS- ! (Staff other than Facility Emergency Organization members) i A. IMMEDIATE ACTIONS: l
- 1. Upon hearing the REACTOR ISOLATION alarm, personnel in f containment shall exit through the personnel airlock door to the front !
i lobby. l l
- 2. TOUR GUIDES shall be responsible for the safe evacuation of visitors m j their charge from the containment and exit via the east door. VISITORS '
shall be monitored by Health Physics Technicians as per HP-20 before being released to leave the site. I r
- 3. EXPERD ENTERS (including pneumatic tube users) shall render ]
their experimental apparatus safe for unattended operation. They shall f be responsible for the safe evacuation of visitors in their charge to the ' lobby. They shallinform the EMERGENCY DIRECTOR if adjustments ! need to be made to their equipment upon re-entry. j B. SUBSEQUENT ACTIONS: i
- 1. All staff nersonnel shall remain on standby, unless released by the [
EMERGENCY DIRECTOR, to provide the special services that may be j required to restore normal operations. ;
- 2. All staffnersonnel who evacuated containment shall be monitored by ,
Health Physics Technicians as per procedure HP-20 before being released to leave the site. , f
- 3. A roster of_all. released personnel who had evacuated containment will be l maintained by the EMERGENCY COORDINATOR. +
t i i i l j i Rev 9/28/92 App'd \t h .
Page1of1. < FEP-3 ; FIRE PROCEDURE f i IMMEDIATE ACTIONS: i
- 1. Any individual discovering a Dre shall notify the Reactor Control Room (#13 or ,
2-5213) of the Ere ! l If the fire cannot be extinguished with local fire extinguishers: [ i NOTE: This procedure is meant to serve as a guide to the EMERGENCY DIRECTOR. At his ; discretion any step may be altered or omitted as necessary. p
- 2. The SHIFT SUPERVISOR will call 911 on the outside line (black phone) to notify the !
. Columbia Fire Department. !
I 3. The SHIFT SUPERVISOR will initiate a Facility Evacuation.
- 4. The EMERGENCY DIRECTOR willinvestigate the source of the fire and determine' !
the steps to minimize hazards until the Fire Department arrives.
- 5. Secure EF-13 and EF-14 if there is a potential for the Ere spreading through the j ventilation system. i
- 6. Secure the ventilation supply fan SF-1, the north RTAH, the south RTAH, and close '
I all fire doors. NOTE: The assessment cfof-site radiological consequences shall be determined.This l assessment may res7uire escala:ing emergency response to a site emergency procedure . (Unusual Event, Alert). SUPPLEMENTAL ACTIONS:
- 1. The EMERGENCY DIRECTOR or EMERGENCY COORDINATOR should meet the l l Fire Department in the upwind parking lot. l 2.- The EMERGENCY DIRECTOR will maintain contact with the INCIDENT COMMANDER at the Command Post. ,
- 3. The EMERGENCY DIRECTOR should contact the MU News Bureau to handle public ;
, information. } 4 The EMERGENCY DIRECTOR will assist the INCIDENT COMMANDER in ! j ccordinating fire fighting and lifesaving measures. l
- 5. The EMERGENCY DIRECTOR will advise the INCIDENT COMMANDER of any j proposed action that may violate the Facility NRC bcense.. ;
i Rev. 9/28/92 App'd 5YMN Revised in its entirety j i 1
_ . . .- - . . . .= .- - - . _ . _- . .. FEP.#. (Cont'd) Page 2 of 5 , See UMH&C RADIATION DISASTER PLAN (5 or more patients) to determine the ! plan they will need to implement: ! I. Two or less patients (Emergency R.oom 1E17). . II. Greater than two patients (enter east side VA). I i ; Upon discovery that an accident has occurred, the following action is to be taken: , . A. If the area in which the accident has occurred is a "high radiation ' area" with an exposure dose rate of 100 mR/hr or more, or is suspected to be such an area, move the victim quickly and carefully to , a location at which the exposure dose rate is 5 mR/hr or less if the ! victim can be moved without harm. Evacuate all personnel from the - accident area and provide first aid to the victim. ! 4 B. Notify the Reactor Operatorin the Control Room (2-5213). ! C. Control Room Operator will call Health Physics Manager at (2-5227) i or by page. If the Health Physics Manager or health physics ] , representative cannot be reached, call the UMC Health Physics ] at 882-7221. ACCIDENT INVOLVING PHYSICAL INJURY Upon arrival u 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 i to that area. ! C. Notify the Emergency Room, UMH&C at 882-8091, and arrange for medical care either at the Facility or at UMH&C. D. Ifinitial treatment is to be administered at the UMH&C arrange for i transportation by the UMH&C ambulance,882-6003, the Facility vehicle, or i commercial ambulance service. l r i f b Rev. 9/28/92 App'd WR __ l
MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 11 Revision Date: 10/16/92 Section Page Number Number List of Effective Pages i SEP-2 2 of 5 SEP-2 5 of 5 SEP-3 2 of 6 SEP-4 6 of 6 II-4
l MURR EMERGENCY PROCEDURES - SEP/FEP SECTIONS -l LIST OF EFFECTIVE PAGES Sec6cn Page Seedon Page pum9r Nu rler Dete Reed Numkr Number Date Revind l SEP/FEP T--C i 7/11/90
' SEP- 1 1 2/10/87 SEP-11 1 4/08/91 !
2 1/23/92 2 5/13/88 1 3 2/10/87 3 5/13/88 l 4 2/10/87 ) 5 6/24/85 EMERGENCY CALL LIST 1 9/28/92 ; SEP-2 1 12/8/89 2 10/16/92 1 WORKSHEET A 9/28/92 3 1/23/92 WORKSHEET B - 1/08/85 ! 4 1/03/85 WORKSHEET C 1/23/92 ! 5 10/16,m i WORKSHEET D 1/08/85 ; i SEP-3 1 12/8/89 WORKSHEET E 0:1g. 6/24/85 2 10/16/92 ] i 3 9/28/92 FEP Table of Contents i 9/13/91 f 4 5/13/68 l 5 1/03/65 Facility Emergencies 1 5/13/88 6 9/28/92 ; SEP-4 1 12/8/89 FEP-1 1 3/22/93 2 9/28/92 2 1/23/92 i 3 9/28/92 3 1/23/92 4 5/13/88 4 9/28/92 5 1/03/65 5 4/08/91 ! 6 10/16/92 ] 6 7/11/90 l SEP-5 1 1/OS/S5 7 7/11/90 , 2 2/10/87 SEP-G 1 6/24/85 FEP-2 1 7/03/85 2 2/10/87 2 1/23/92 3 1/23/92. ; SEP-7 1 1/23/92 4 9/28/92 2 9/28/92 y 3 9/18/89 FEP 3 1 9/28/92 ; 4 9/18/89 l FEP-3(a) 1 1/23/92- ; SEP-8 1 1/23/92 2 9/13/91 2 9/28/92 l 3 9/28/92 FEP-4 1 7/03/85 1 2 9/28/92 SEP-9 1 1/23/92 3 5/13/88 2 1/03/85 4 5/13/88 j 5 5/13/88 l SEP-10 1 Ong. 6/24/85 2 O dg. G/24/85 UMH&C (Hospital & Clinics) Emergency Center Radiation Disaster Plan i 11 Rev. 10/16/92 App'd UMDb
.x.- a .. = =. .: - : :..: ==: x - . = = := .. : ,
SEP-2 (Cont'd) Page 2 of 5 ,
- 5. Send operator to west tower with radiation monitor to: ):
NOTE: Communicate by intercom, since stack monitor is affected by portable ! radio RF. i
- a. Verify radiation background at stack monitor.
- b. Verify control room readings. '
- c. Mark initial needle positions on analog display with the time for future analysis if the control room display becomes inaccessible. ,
- d. Verify flow rate through monitor is 5 1 SCFM. If not, use Worksheet A to ] .
determine stack monitor values.
- 6. If nuclides which are being released are in doubt, pull stack filters and analyze.
- 7. The EMERGENCY COORDINATOR shall evaluate the need to evacuate specific portions of the facility.
- 8. The EMERGENCY COORDINATOR shall appoint and have a surveillance team check any areas evacuated in step 7, clear of personnel within 30 minutes.
NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of10CFR20 limits. (Up to 75 rem for life- ! saving, up to 25 rem to prevent exposure to members of general ' public in excess of I rem whole body and 5 rem thyroid.)
- 9. The EMERGENCY DIRECTOR shall determine the need for EMERGENCY l SUPPORT ORGANIZATIONS and,if needed, activate them or place them on :
e standby. See Table II, EMERGENCY SUPPORT ORGANIZATIONS. ; NOTE: If 9-911 is called during any emergency, contact MU News Bureau. ; i t l l Rev. 10/16/92 App'd #\_
NEP-2 (Cont'd) Page 5 of 5
- d. LABORATORIEE (1) Determine which laboratory is the source of release, by checking .
radiation levels in quadrant exhaust ducting. : Ca) Southwest Quadrant , (b) Northwest Quadrant i (c) Northeast Quadrant i I ACTIONS TO CONSIDER ' ( }} Throttle flow from laboratory quadrant to reduce release rate to less ; than Technical Specifications limits. ; (2) Area Evacuations SUBSEQUENT ACTIONS:
- 1. Change stack filters when chart reading exceeds 3 x 10' cpm. ] -
Reevaluate chart reading to determine if release rate is increasing / decreasing. Record time of filter changeout.
- 2. Evaluate results of correction and subsequent actions to determine need to escalate /de-escalate the emergency classification. !
- 3. Keep record of actions and evaluations and time they were done for !
documentation. Use procedure worksheets. l
- 4. Notify NRC, Region III, that an UNUSUAL EVENT has occurred within one hour after event is classified or reclassified. (Use Worksheet C) :
- 5. Notify American Nuclear Insurers (ANI) [203-561-3433] that an UNUSUAL EVENT has occurred. (Use information in 'Worksheet C)
- 6. Notify State Emergency Management Agency (SEMA) [314-751-9770] that an UNUSUAL EVENT has occurred. (Use information in Worksheet C) i B_ECOVERY ACTIONS: l
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by UNUSUAL EVENT emergency. ;
- 2. Procedures shall be written and approved for handling significant recovery l evolutions.
NOTE: During recovery operations, personnel exposures to radia* ion should be maintained within 10CFR20 limits. ] l l l Rev. 10/16/92 App'd W '\
SEP-3 (Cont'd) Page 2 of 6 ' ,
- 5. Send operator to west tower with radiation monitor to: '
i NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF. l
- a. Verify radiation background at stack monitor. :
, b. Verify control room readings. +
- c. afark initial needle position on analog display with time for future analysis if control room display becomes inaccessible.
- d. Verify flow rate through monitor to 5 1 SCFM. If not, use Worksheet A ;
to determine stack monitor values. '
- 6. Full stack monitor filters and analyze. !
- 7. After determining radionuclide responsible and verifying concentrations greater than 95,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RF1, SF1; (c) secure all individual vent fans. ,
- 8. The EMERGENCY COORDINATOR shall evaluate the need for a partial or total evacuation of the facility. :
NOTE: For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation remcved to RPDB. (Ge-Li detector and dewer; High Resolution Gamma Ray 3pectrometer) i
- 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 ; I radiation exposure in excess of10CFR20 limits. (Up to 75 rem for i i lifesaving, up to 25 rem to prevent exposure to members of general public in excess ofI rem whole body and 5 rem thyroid.) L
- 10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE III, ]
EMERGENCY SUPPORT ORGANIZATIONS. i l l 4 l Rev. 10/16/92 App'd4M W\ l
SEP-4 (Cont'd) Page 6 of 6 SUBSEOUENT ACTIONS:
- 1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use procedures and worksheets.
- 3. Notify NRC, Region III, that a SITE AREA EMERGENCY condition has ]
occurred within one hour after event has been ciassified or reclassified. (Use Worksheet C)
- 4. Notify American Nuclear Insurers (ANI) [203-561-3433] that a SITE AREA ]
EMERGENCY condition has occurred. (Use information in Worksheet C) ]
- 5. Notify State Emergency Management Agency (SEMA) [314-751-9770] that a ]
SITE AREA EMERGENCY condition has occurred. (Use information in Worksheet C) l RECOVERY ACTIONS:
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by the SITE AREA EMERGENCY. ]
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits. 1 l l Rev. 10/16/92 App'd _ NING 1 l
~ -s,
- . - 2 ... , . ,
\
.i MURR SITE EMERGENCY PROCEDURES AND !
FACILITY EMERGENCY PROCEDURES 1 Revision Number 12 - Revision Date: 2/4/93 l Section Page , Number Number List of Effective Pages i i SEP-2 5 of 5 I l SEP-3 6 of 6 l' SEP-4 6 of 6 t Emergency Call List , FEP-4 2 of 5 i i d'
+
I i i l i i i I t l l 11-5
-. MURR EMERGENCY PROCEDURES SEP/FEP SECTIONS {
, LIST OF EFFECTIVE PAGES j l
Secdon Page Seedon Page j mmkr Wmkr ns hiW Wmkr Numkr D& hised j SEP/FEP T-C i 7/11/5X) SEP- 1 1 2/10/87 SEP 1 4/08/91 l j 2 1/23/92 2 5/13/88 3 2/10/87 3 5/13/88 ' 4 2/10/87 5 6/24/85 EMERGENCY CALL LIST I 2/4/93 ] ; SEP-2 1 12/8/89 : 2 10/16/92 WORKSHEETA 9/28/92 ! 3 1/23/92 WORKSHEET B 1/08/85 l 4 1/08/85 WORKSHEET C 1/23/92 { 5 2/4/93 ] WORKSHEET D 1/08/85 l SEP-3 1 12/8/89 WORKSHEET E Orig. 6/24/85 ! 2 10/16/92 L 3 9/28/92 FEP Table of Contents 1 9/13/91 ; 4 5/13/88 5 1/03/65 Facility Emergencies 1 J/13/88 6 2/4/93 ] ! SEP-4 1 12/8/89 FEP-1 1 3/22/93 l 2 9/28/92 2 1/23/92 l 3 9/2S/92 3 1/23/92 j 4 5/13/68 4 9/28/92 5 1/09/85 5 4/09/91 6 2/4/93 ) 6 7/11/93 ' SEP-5 1 1/OS/85 7 7/11/90 2 2/10/87 SEP-6 1 6/24/S5 FEP-2 1 7/03/85 2 2/10/87 2 1/23/92 3 1/23/92 SEP-7 1 1/23/92 4 9/28/92 2 9/28/92 3 9/18/89 FEP-3 1 9/28/92 4 9/18/89 FEP-3(a) 1 1/23/92 S EP-8 1 1/23/92 2 9/13/91 2 9/28/92 3 9/28/92 FEP-4 1 7/03/85 , 2 2/4/93 ] S EP-9 1 1/23/92 3 5/13/88 l 2 1/09/85 4 5/13/SS J 5 5/13/88 l SEP- 10 1 Ong. 6/24/85 2 Orig. 6/24/85 UMH&C (Hospital & Clinies) Emergency Center Radiation Disaster Plan 11 Rev. 2/4/93 App'd V@%
SEP-2 (Cont'd) Page 5 of 5 *
- d. LABORATORIES '
(1) Determine which laboratory is the source of release, by checking radiation levels in quadrant exhaust ducting. (a) Southwest Quadrant (b) Northwest Quadrant ! (c) Northeast Quadrant l
- ACTIONS TO CONSIDER i (1) Throttle flow from laboratory quadrant to reduce release rate to less ;
than Technical Specifications limits. , I (2) Area Evacuations i SUBSEQUENT ACTIONS: , . 1. Change stack filters when chart reading exceeds 3 x 10' cpm, i Reevaluate chart reading to determine if release rate is increasing / ; decreasing. Record time of filter changeout. l
- 2. Evaluate results of correction and subsequent actions to determine need i
- to escalate /de-escalate the emergency classification. !
- 3. Keep record of actions and evaluations and time they were done for ,
documentation. Use procedure worksheets. -
- 4. Notify NRC, Region III, that an UNUSUAL EVENT has occurred within one hour after event is classified or reclassified. (Use Worksheet C)
- 5. Notify American Nuclear Insurers (ANI) [203-561-3433] that an UNUSUAL
! EVENT has occurred. (Use information in Worksheet C) i
~
) Notify State Emergency Management Agency (SEMA) [314-751-2748] that an ]
- 6. '
UNUSUAL EVENT has occurred. (Use information in Worksheet C) ; , RECOVERY ACTIONS: ! ! 1. Evaluate potential radiological effects to ensite and offsite personnel before z ] returning access to specific areas effected by UNUSUAL EVENT emergency. ;
- 2. Procedures shall be written and approved for handling significant recovery :
evolutions. NOTE: During recovery operations, personnel exposures to radiation should be . i maintained within 10CFR20 limits. : t a Rev. 2/4/93 App'd UMP \ l
~ _ _ _
'SEP-3 (Cont'd) Page 6 of 6 SUBSEQUENT ACTIONS:
- 1. Evaluate results of corrections and subsequent actions to determine need to '
escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use procedures and worksheets. i
- 3. Notify NRC, Region III, that ALERT condition has occurred within one hour after event has been classified or reclassified. (Use Worksheet C)
- 4. Notify American Nuclear Insurers (AND [203-561-3433] that ALERT condition has occurred. (Use information in Worksheet C) i
- 5. Notify State Emergency Management Agency (SEMA) [314-751-2748] that ]
ALERT condicion has occurred. (Use information in Worksheet C) RECOVERY ACTIONS:
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by ALERT emergency.
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
NOTE: Dm-ing recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits. i 1 1 l
- I 4
1 b l j s Rev. 2/4/93 App'd VhD\ l wr-
, I 4
SEP-4 (Cont'd) Page 6 of 6 SUBSEQUENT ACTIONS: 1
- 1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use i procedures and worksheets.
- 3. Notify NRC, Region III, that a SITE AREA EMERGENCY condition has occurred within one hour after event has been classified or reclassified.
(Use Worksheet C)
- 4. Notify American Nuclear Insurers (ANI) [203-561-3433] that a SITE AREA EMERGENCY condition has occurred. (Use information in Worksheet C) -
- 5. Notify State Emergency Management Agency (SEMA)[314-751-2748] that ]
a SITE AREA EMERGENCY condition has occurred. (Use information in Worksheet C) RECOVERY ACTIONS:
- 1. Evaluate potential radiological effects to onsite and offsite personnel before [
returmng access to specific areas effected by the SITE AREA ' EMERGENCY. t i
- 2. Procedures shall be written and approved for handling significant recovery evolutions. 4 NOTE: During recovery operations, personnel exposures to radiation i should be maintained within 10CFR20 limits.
i 1 l Rev. 2/4/93 App'd \ff8TV\
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4 FEP-4 (Cont'd) Page 2 of 5 , See UMH&C RADIATION DISASTER PLAN (5 or more patients) to determine the plan they will need to implement: I. Two or less patients (Emergency Room 1E17). II. Greater than two patients (enter east side VA). h Upon discovery that an accident has occurred, the following action is to be taken: A. If the area in which the accident has occurred is a "high radiation area" with an exposure dose rate of 100 mR/hr or more, or is suspected to be such an area, move the victim quickly and carefully to a location at which the exposure dose rate is 5 mR/hr or less if the victim can be moved without harm. Evacuate all personnel from the accident area and provide ' first aid to the victim. B. Notify the Reactor Operator in the Control Room (2-5213). C. Control Room Operator will call Health Physics Manager at (2-5227) or by ! page. If the Health Physics Manager or health physics representative { cannot be reached, call the UMC Health Physics at 882-7221. 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, recommend to the Emergency Director (or Shift Supervis.or) ] to seal off the accident area and secure ventilation to that area. ] C. Notify the Emergency R.oom, UMH&C at 882-8091, and arrange for ' medical care either at the Facility or at UMH&C. l D. Ifinitial 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. - 1 f t i L i i
]
i Rev. 2/4/93 App'd _ \MTD\
. _ - . - ._- . .. . . - . . - . - -.. ~
e . I j HEALTH PHYSICS STANDARD OPERATING PROCEDURES . (New manual issued 10/29/90)
)
l There were no revisions to the Health Physics Standard Operating Procedures. , i 1 1 i t 1 II-6 e . _ _ _ _ - , ,- _ _ , . , . , - , . . ., --
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l I i l d SECTION III j REVISIONS TO THE HAZARDS
SUMMARY
REPORT l 1 July 1992 through 30 June 1993 i i HAZARDS
SUMMARY
REPORT (Original July 1,1965) i ; l- l No Hazard Summary Report changes were made from 1 July 1992 through 30 June 1993. I i ! 1 l i ! 1 l i i I I 8 i i r l l l l l l l l l l i l l l l l 111-1 i d
. . . - - , , _ _ _ . _ . _ _ _ _ _ _ _ . _ . . . . . . . . , _ _ _ . . _ . _ , . . _ _ _ . _ , .,...m_. - ., , , ,-.__ _ _ . - . _ . . . _ ,__ _ . .
l l l SECTION IV ; PLANT AND SYSTEM MODIFICATIONS l 1 July 1992 through 30 June 1993 Modification 92-3: Renlacement of 4"line with 8"line in the firemain main loop ! svstem . I This modification removes the old 4"line and post indicating valve (PIV) and replaces it with a 8"line and new PIV. This was done to replace the leak prone - old line and valve and to upgrade the system. The system upgrade will allow a ! flooded firemain system in the reactor and laboratory buildings and still provide ! a sufficient supply of water to the emergency pool fill system. l i The safety evaluation for 'his modification documents thatit does not present an unreviewed safety question as per 10 CFR 50.59. . l l I J -! i t ) 5 i 4 l i t l i l l l l
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4 A IV-1
, - -,e -.
SECTION V l NEW TESTS AND EXPERIMENTS - 1 July 1992 through 30 June 1993 j l New experimental programs during this period are as follows: RUR-219, Request 125: Experimenter: S. Gunn
Description:
This RUR authorized irradiation of a thallium metal j i calibration source.
\
j RUR-269: -l l Experimenter: S. Gunn i
Description:
This RUR authorized irradiation of a platinum metal for medical use. ; RUR-292: Experimenter: S. Gunn ;
Description:
This RUR authorized irradiation of barium carbonate to - generate Cesium-131 for medical use. The process is proprietary to the customer, j I RUR-293: Experimenter: S. Gunn '
Description:
This RUR authorized irradiation of ammonium bromide for biomedical research. : RUR-301: i I Experimenter: S. Gunn '
Description:
This RUR authorized upgrade irradiation of chromium metal from 20 mg target mass to 100 mg. RUR-302: Experimenter: S. Gunn l
Description:
This RUR authorized irradiation of terbium oxide for biomedical distribution studies. ! l RUR-307: Experimenter: S. Gunn l
Description:
This RUR authorized irradiation of zirconium oxide and 1 circonium metal enriched to 99?c Zr-94 for calibration l source use. ! Each of these experiments 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. l V-1
SECTION VI SPECIAL NUCLEAR MATERLtL ACTIVITIES 1 July 1992 through 30 June 1993
- 1. SNM Receipts: A total of 24 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.
Grams Grams Shipper Elements U U-235 B&W MO-361, MO-362, MO-363, MO-364, MO-365, MO-366, 19,936 18,561 MO-367, MO-368, MO-369, MO-370, MO-371, MO-372, MO-373, MO-374, MO 375, MO-376, MO-377, MO-378, MO-379, MO-380, MO-361, MO-382, MO-353, MO-384 a
- 2. SNM Shipments: No shipments.
- 3. Inspections: There were no Physical Security and Special Nucln.r M@ rial Accountability inspections conducted by the Nuclear Regulatory Commission for the period 1 July 1992 through 30 June 1993.
- 4. SNM Inventory: As of 30 June 1993, MURR was fmancially responsible for the following DOE-owned amounts:
Total U = 48,820 grams Total U-235 = 43,503 grams Inch:ded in these totals are 36 grams of U and 34 grams of U-235 in DOE-owned non-fuel. In addition to these totals, MURR owns 177 grams of U and 96 grams of U-235. All of this materialis physically located at the MURR. VI-1
The fuel elements on hand have accumulated the following burn-ups as of 30 June 1993: Burned-un Elements (32) Element No. MWD Element No. MWD Element No. MWD M O-316 144.20 MO-330 145.21 MO-341 144.99 MO-318 144.20 MO-331 148.59 M O-342 138.03 MO-319 146.54 MO-332 149.92 MO-343 146.30 M O-320 146.54 MO-333 148.59 MO-344 146.07 MO-323 349.98 MO-334 149.92 MO-345 146.30 MO-324 147.08 MO-335 145.59 MO-346 146.07 MO-325 149.9S MO-336 149.42 M O-348 145.31 MO-326 147.05 MO-337 145.59 MO-350 145.31 MO-327 146.26 MO-33S 149.42 M O-351 147.50 MO-328 145.11 MO-339 144.99 MO-353 147.50 MO-329 146.26 M O-340 138.03 Elements in Service (36) MO-321 107.51 MO-361 95.14 MO-373 61.56 MO-322 107.51 MO-362 50.73 M O-374 62.90 MO-347 130.68 MO-363 95.14 MO-375 61.86 MO-349 130.6S MO-364 60.73 MO-376 62.90 MO-352 121.78 MO-365 55.94 M O-377 34.41 MO-354 121.78 MO-366 51.52 MO-378 25.97 M O-355 94.26 MO-367 55.94 MO-379 34.41 MO-356 94.26 MO-368 51.52 M O-3SO 25.97 MO-357 69.74 MO-369 59.77 MO-381 0.00 MO-358 69.74 MO-370 67.24 MO-382 0.00 MO-359 91.40 MO-371 59.77 MO-383 0.00 MO-360 91.40 MO-372 67.24 MO-384 0.00 Average Burn-up (all elements): 106.23 ARVD VI-2
4 __.7 4 SECTION VII REACTOR PHYSICS ACTIVITIES 1 July 1992 through 30 June 1993
- 1. Fuel Utilization: During the period 1 July 1992 through 30 June 1993, the /
following elements reached licensed or feasible burn-up and were retired: Serial Number Final Core Ds'a Lmt 19ed MWD MO-327 92-33 07-06-92 146.26 MO-329 92-33 07-06 92 146.26 MO-331 92-39 05-03-92 148.59 MO-333 92-39 OS-03-92 148.59 MO-335 92-32 07-03-92 145,59 MO 336 92-46 09-08-92 149.42 N O-337 92-32 07-03-92 145.59 MO-338 92-46 09-08-92 149.42 M O-339 92-49 09-28-92 144.99 M O-34 0 92-54 11-02-92 139.03 NO-341 92-49 09-25-92 144.99 MO 342 92-54 11-02-92 138.03 MO-343 93-04 01-30-93 146.30 MO-344 92-61 12-07-92 146.07 MO-345 93-04 01-30-93 146.30 MO-34 6 92-61 12-07-92 146.07 M O-348 93-13 03-16-93 145.31 MO-350 93-13 03-16-93 145.31 l MO-351 93-31 06-01-93 147.50 l MO-353 93-31 06-01-93 147.50 . 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 dict. ate. 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 1993. To increase operating efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number. Fabrication Initial Core Initial Ser;sl Number Core Number Lead Number Operatinc Date MO 361 61 92-39 07-27-92 MO-362 61 92-40 03 03-92 MO-363 61 92-39 07-27-92 M O-364 61 92-40 OS-03-92 MO-365 61 92-44 08-24-92 MO-366 61 92-54 10-26-92 MO-367 62 92-44 OS-24-92 MO-36S 62 92-54 10-26-92 MO-369 62 92-55 11-02-92 MO-370 62 92-59 11-20-92 MO-371 62 92-55 11-02-92 MO-372 62 92-59 11-20-92 MO 373 62 93-2 01-11-93 , VII-I
Fabrication Initial Core Initial Serial Number Cere Number Izad Number Ooeratinc Date 310-374 62 93-3 01-19-93 L10-375 63 93-2 01-11-93 510-376 63 93 3 01-19-93 510-377 63 93-23 04-26-93 510 378 63 93-30 05-24-93 510-379 63 93-23 04-26-93 510-350 63 93-30 05-24 93
- 2. Fuel Shipments: No shipments were made between 1 July 1992 and 30 June 1993.
- 3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia,is MURR's fuel assembly fabricator. This work is contracted with the U. S. Department of Energy and administered by EG&G Idaho Inc., Idaho Falls, Idaho. As of 30 June 1993,185 fuel assemblies fabricated by B & W had been received and 181 used in cores at 10 MW.
- 4. Licensing Activities: On April 30,1993, MURR requested an amendment to the license R-103 allov,ing a temporary (until May 31,1994) increase in the U-235 possession to 60 kilograms.
A request for a tmique purpose exemption as defined in 10CFR50.2 was submitted September 26,19S6, and is pending.
- 5. Reactor Characteristic Measurements: Seventy refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 2.28Fc. The largest excess reactivity was 3.337c. MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.87c.
Reactivity measurements were performed for eleven evolutions to verify reactivity parameters for the flux trap. Differential worth measurements were made on blades A (once), B (once), C (cnce), and D (three times). The entire bank differential worth was measured once at two poiuts. The total bank worth (separate total worths of all four blades) was meesured twice. The reactivity worth due to a reflector wedge change was measured once. The primary coolant temperature coeflicient was verified. VII-2
SECTION VIII
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED TO THE ENVIRONMENT Sanitary Sewer EfIluent 1 July 1992 through 30 June 1993 Descending Order of Activity Released for Isotope Totals > 1.00 E-5 Ci: Npelide Amount (Ci) Nuclide Amount (Ci) H-3 1.711E-01 W-188 1.501E-04 Eu-154 3.001E-02 Ba-131 7.571E-05 As-77 4.971E-03 Sc-46 6.703E-05 S-35 4.920E-03 Cd-109 5.192E-05 Re-186 S.930E-04 Eu-152 5.094E-05 Te-125m 8.220E-04 Co-58 5.064E-05 Ca-45 5.094E-04 Cr-51 4.291E-05 Co-60 3.924E-04 Pd-109 2.S65E-05 Na-24 2.545E-04 Ce-144 2.433E-05 Zn-65 2.554E-04 Co-57 1.692E-05 Se-75 1.967E-04 Sb-125 1.526E-05 l Total H-3 1.711E-01 Ci Total Other 4.3SOE-02 Ci l l l l VIII-1 l
Stack Efiluent . I July 1992 through 30 June 1993 Ordered by % Tecimical Specification (TS) Limit Average Total Release 3 Concentration FY 92-93 TS Limit 1 Isotone (uCi/ml) (Ci) (x MPC) % TS* Ar-41 9.30E 07 4.7 E+ 02 350 6.6769 I-131 7.57 E-13 1.6E-04 1 0.7567 K-40 2.03 E-13 { 1.9E-06 1 0.2032 i Pd-103 5.02E-11 1.0E-03 1 0.1673 Ce-144 5.52E-14 6.0E-07 1 0.0276 Ce-139 1.52E 14 6.5E-07 1 0.0152 Cs-134 6.10E-14 7.5E-07 1 0.0152 H-3 1.03E-08 5.1E + 00 350 0.0147 Ba-140 1.46E-13 3.4 E-06 1 0.0146 Co-60 4.20E-14 1.5E-06 1 0.0140 Cd-109 2.68E-13 2.7 E-05 1 0.0134 Cd-115 S.19E-14 8.0E-07 1 0.0082 Cs-137 2.81 E-14 7.S E-07 1 0.0056 Se-75 1.92E-13 3.2E-05 1 0.0048 Xe-135m 5.01E-10 1.1E-02 350 0.0048 1-133 6.31 E-12 1.5E-03 350 0.0045 I135 1.55E-11 3.6E-03 350 0.0044 Zr-95 3.40E-14 3.6E-07 1 0.0034 Hg-203 9.16E-14 2.1E-05 1 0.0023 I-134 4.86E-11 1.1E-02 350 0.0023 Zn-65 2.90E-14 6.4 E-07 1 0.0015 I-132 1.39 E-11 3.2 E-03 350 0.0013 Nb-95 2.39 E-14 5.4 E-07 1 0.0008 I-128 7.57E-11 3.3E-03 350 0.0007 Sn-113 1.42E-14 4.1E-07 1 0.0007 Pa-233 3.16E-14 5.6E-07 1 0.0005 Sr-55 2.00 E- 14 1.6 E-07 1 0.0005 Ru-103 1.31 E- 14 2.6E-07 1 0.0004 Ba-133m 1.16E-13 1.1E-06 350 0.0003 l Kr-67 2.38E 11 5.2 E-04 350 0.0003 Os-191 2.60 E- 14 1.9 E-06 1 0.0003 As-77 6.76E-12 1.4 E-03 350 0.0002 Cr-51 1.83 E-13 4.2E-06 1 0.0002 Cu 67 6.67 E-14 5.2E-06 350 0.0002 Gd-153 1. 74 E-14 3.5 E-07 1 0.0002 Ba-139 6.53 E-12 4.5E-04 350 0.0001 Co-57 5.66E-15 5.6E-08 1 0.0001 Pt-193m 4.07E-12 8.9E-05 350 0.0001 Total 7.9673
- Isotopes observed at <0.001'~c TS limit net listed.
Stack flow rate 33,500 ft 3/ min l 1 VIII-2 l
SECTION IX
SUMMARY
OF ENVIRONMENTAL SURVEYS 1 July 1992 through 30 June 1993 Emironmental 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 three of the eight locations. Results of the samples are shown in the following tables.
- 1. Sampled during December 1992.
i Detection Limits
- Matrix Alnha Beta Gamma Tritium Water 0.9 pCill 2.7 pCiil 215.3 pCill 7.6 pCi/ml of sample Soil 0.9 pCi/g 2.6 pCi/g 1.4 pCi/g N/A Vegetation 1.8 pCi/g 5.2 pCi/g 2.0 pCi/g 7.6 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 Samples Alpha Beta Gamma H-3 Samnie (nCi/g) (nCi/c) (nCi/c) (nCi/c) 1-V-42 < 1.8 14.8 < 1.4 < 7.6 2-V-4 2 < 1.8 22.1 < 1.4 < 7.6 3-V-42 < 1.8 28.2 < 1.4 < 7.6 4-V-4 2 < 1.8 24.5 < 1.4 < 7.6 5-V-4 2 < 1.8 21.3 < 1.4 < 7.6 6-V-4 2 < 1.8 22.6 < 1.4 < 7.6 7-V-4 2 < 1.8 26.8 < 1.4 < 7.6 10-V-42 < 1.8 17.5 < 1.4 < 7.6 IX-1
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Determined Radioactivity Levels Soil Samules Alpha Beta Gamma Sample (nCi/c) (oCi/c) (nCi/c) 1-S-42 < 0.9 15.2 7.7 2-S-42 < 0.9 17.9 10.8 3-S-42 1.0 12.1 9.4 4-S-42 < 0.9 9.9 5.2 5-S-42 < 0.9 14.4 7.9 6-S-42 < 0.9 14.5 7.9 7-S-42 1.0 11.9 12.9 10-S-42 1.4 16.5 12.0 Determined Radioactivity Levels Water Samnles l l Alpha Beta Gamma H-3 i famp!e (pCidl. (nCill) (pCiO (nCi/ml) ' 4-W-4 2 < 0.9 < 2.7 < 215.3 < 7.6 6-W-4 2 < 0.9 < 2.7 < 215.3 < 7.6 10-W-4 2 < 0.9 < 2.7 < 215.3 < 7.6 l
- 2. Sampled duringJune 1993 l
Detection Limits
- Matrix Alpha Beta Gamma Tritium Water 1.1 pCia 2.7 pCi/l 213.4 pCill 13.8 pCi/ml of sample Soil 1.1 pCi'g 2.7 pCi/g 0.4 pCi/g N/A Vegetation 2.1 pCi/g 5.3 pCilg 1.3 pCi/g 13.8 pCi/ml ofdistillate
- Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
IX-3
Determined Radioactivity Levels Vecet.ation Samoles Alpha Beta Gamma H-3 Samnle (nCi/c) (nCi/c) (nCi/c) _(nCi/gl 1-V-4 3 < 2.1 30.3 < 1.3 < 13.8 2-V-4 3 < 2.1 22.1 < 1.3 < 13.8 3-V-4 3 < 2.1 32.6 < 1.3 < 13.8 4-V-43 < 2.1 23.1 < 1.3 < 13.8 5-V-4 3 < 2.1 19.0 1.4 < 13.8 6-V-4 3 < 2.1 35.6 < 1.3 < 13.8 7-V-4 3 < 2.1 27.2 1.4 < 13.8 10-V-43 < 2.1 26.8 < 1.3 < 13.8 Determined Radioactivitv Ixvels Soil Samnles l Alpha Beta Gamma l Samole (nCi/c) (nCi/ci (nCi/g) 1-S-43 2.0 22.0 6.4 2-S-43 1.7 15.2 7.7 3-S-43 1.8 15.2 5.9 4-S-43 < 1.1 8.4 5.2 5-S-43 < 1.1 15.2 7.2 6-S-43 < 1.1 8.4 5.6 7-S-43 < 1.1 14.4 6.6 10-S-43 < 1.1 16.4 7.5 Determined Radioactivity Levels Water Samules Alpha Beta Gamma H-3 Sample (nCil) (nCill) (nCill) (nCi/ml) 4-W-4 3 < 1.1 7.5 < 213.4 < 13.8 6-W-43 < 1.1 5.2 < 213.4 < 13.8 10-W-43 < 1.1 9.5 < 213.4 < 13.8 IX-4
ENVIRONMENTAL TLDs The MURR Health Physics staff have continued to work with Landauer, Inc. in the development of a TLD monitoring program to monitor external doses around the MURR Facility. The table on the following page lists the results of monitors as they were deployed in 1992. A design for the monitors has been determined, but their placement is still under development. All totals remained below 100 mrem / year, except monitor number 9. This monitor is located on the side of the MURR building near the loading dock where radioactive shipments are made. This monitor, along with the other five monitors that had readings greater than 25 mrem / year, were alllocated on the brick exterior of the building. A test during the first quarter in 1993 showed that a monitor mounted on a brick structure 65 meters from the reactor building recorded 15.1 mrem where its counterpart equidistant, but deployed in a tree, was 4.6 mrem. Shipping and deployment controls are carried with each set and stored at a distant site. These are used to determine background which is subtrated from each of the monitors. This normalizes all of the monitors and compensates for any exposure they may experience in transit. Negative numbers on some of the monitors indicate that dose levels at the deployment site are not significantly different than bachground. l IX-5
Environmental TLD Annual Summary January 1992 through December 1992 Eadge Direction Map Distance from Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr- Total Number fmm MURR MURR Stack Net mR Net mR Net mR Net mR Net mR (meters) 1 Discretionarv N/Al -0.6 -0.5 -8.4 -1 -10.5 2 Discretionarv N/AI 0.2 -0.6 -7.4 -1.1 -8.9 3 Discretionary N/Al -0.6 -1.1 -7.4 -0.2 -9.3 4 Discretionarv N'A l -0.7 -0.9 -3.6 -0.2 -5.4 5 Discretionarv N/AI 1.8 -0.1 -5.5 -1 -4.5 6 NNE S4 6.9 4 7 8.6 26.7 7 ESE 57 14 11.4 13 20.7 59.1 5 WSW 27j 18.1 13 12 28.9 72 9 SSE 27- 42.2 49.7 85.4 58.3 265.6 10 NE 149 -4.1 -1.5 -5.3 0.9 -10 11 N 149 2.3 -0.2 -0.1 4.3 6.3 12 ENE 301i -0.4 0.9 -1.3 4.5 4 13 NNE 3161 -0.2 -0.4 0.5 2.7 2.9 14 S 156! -1.2 i 22 -2.3 5.5 4.2 15 S 651 13.1 11.9 12.5 17.8 55.3 16 SE 1071 -2.5 -1.1 -2.3 3.3 -2.6 17 E 293I - 0.9 0 -3 3.3 -0.6 15 NE 476 0 -1.3 -4.3 0.2 -5.4 19 NNE 606 4 -1.1 -2.4 3 3.5 20 NE 9071 0.2 -0.5 -2.5 2.4 -0.7 21 SE 236l 2.3 -1.4 -0.5 3.3 3.4 22 ESE 165! -3.4 -4.5 -6.7 -1.9 -16.5 23 NW 1101 <2 -2.6 -1.7 0.9 -5.6 24 SSW 3251 -0.4 lost -3.7 0.4 -3.7 25 SSW 450i 0.5 -1.5 0.6 3.2 3 26 SW 301! 1.3 -0.8 1.5 4.5 C.5 27 WSW 1411 -1.7 -5.3i -5 -0.5 -12.5 251 WNW 2101 9.5 -0.9 1.2 4.7 14.5 29! NW 255l 0.1 -
-0.6 1.6 4 5.1 30' NNW 3251 -0.5! -2.2 2.4 1.9 -3.2 31 NNE 6711 1.3 -0.4 0.6 5.4 6.9 32 NNW 724I 2.9 -0.7 0.8 4.2 7.2 30 7 6711 -1.5 -3.9 -3.6 -0.1 -9.1 l 34 ENE 557 -1.9 -4.9 -4.9 -0.6 -12.3 35 SSE 499 2.3 -1 0.9 4 6.2 36 SE 419 1.5 -0.3 -0.5 3.4 4.1 37 NE 690 -3.1 -5.5 -4.4 -1.E -15.1 3F NW 556 3.2 0.2 1.2 5.1 9.7 39 W 491i 51 -06 1 4.3 9.5 40 N 514l 2.6 -1.5 0.1 3.7 4.9 41 ENE 137 3 0 -1.6 5.2 6.6 42 In building N/A 4.6 1.2 2.5 6.6 14.9 43 In building N/A 4.6 3.9 -0.1 8.6 17 44 Distant site N/A -3.7 -5.6 -4.6 -0.4 -14.3 45 Distant site N/A 1.7 -1.4 -1.6 5.6 4.3 IX-6 l
t
NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS Surface Air Radiation Contamination
- Samples ILWVP_
1992 July 53 49 33 8 August 50 39 26 25 September 36 36 27 18 October 31 30 32 21 November 47 40 30 25 December 33 22 32 14 1993 January 38 37 28 9 February 38 40 29 7 Alarch 37 34 33 11 Apnl 29 29 34 11 May 40 38 29 7 June 17 23 30 3 TOTALS 449 417 363 159
- Note In addition, general building contamination surveys are conducted each normal work day.
Miscellaneous Items In 1992 Ms. Leslie M. Powell was promoted from Secretary to Senior Secretary in the Health Physics group. Ms. Powell had been with the HP Group for two years and dunng that time has assumed many office management responsibilities. December 20,1992, Mr. Ray W. Stevens and Rex G. Ayers met the requirements to be added to the National Registry of Radiation Protection Technologists (NRRPT). In December 1992, Mr. John P. Ernst, Assistant Manager Reactor Health Physics, completed a Masters degree in Nuclear Engineering / Health Physics. In January 1993, Dr. Susan M. Langhorst, Manager Reactor Health Physics, began a one year sabbatical with the Committee on Interagency Radiation Research and Policy Coordination (CIRRPEC)in Washington, DC. CIRRPEC is a research committee responsible for advising federal agencies on Health Physics policy. Dr. Langhorst will return to MURR at the end of 1993. Mr. Ernst is Acting Health Physics Manager in her absence. Mr. Ayers was promoted from Health Physics Technician to Senior He ..u. Physics Technician in March of1993. Mr. Stevens graduated with a Bachelor o; Science degree in Mechanical Engineering in May of 1993. An additional Health Physics Technician position was established and the hiring process is underway. The University made application to the NRC for renewal ofits Broad Scope Materials License on February 27,1992. The renewal application asked for separate licenses for each of the four campuses and for MURR. The NRC has issued licenses IX-7
for the Rolla, Kansas City, and St Louis campuses, but continues to review the license requests for the AIURR and the Columbia campus. ADCO Services continues to function as radioactive waste broker for 31URR. Through ADCO we disposed of 210 cubic feet of LSA matedal during the 1992/1993 fiscal year. In addition,157.5 cubic feet oflow level wasta was shipped in a shielded cask through Chem Nuclear. The ALARA program implemented to document efforts to reduce personnel exposure continues to function. During 1992 the research groups were reorganized and renamed. The ALARA review program was reorganized as well. The average monthly whole body deep dose to individuals in each group are shown in the following table: Groun Name Averace Afonthlv Dose Actinide Chemistry 10 mrem Analytic Epidemiology and Nutrition minimal Computer Development minimal Electronic and 31echanical Properties 10 mrem Director's Omce minimal Facilities Operations 10 mrem Gamma Ray Scattering 10 mrem Health Physics 40 mrem Instrument Development minimal 31agnetic and Crystal Structure 20 mrem Nanostructures and Excitations 20 mrem Neutron Optics 20 mrem Nuclear Archaeology and Geochemistry minimal Nuclear Engineering minimal Operations 70 mrem Radiopharnaceutical 10 mrem Services Applications 20 mrem The A1URR continues its ehorts to improve radiation safety training for radiation workers. In 1992 Health Physics Group deeloped a new six part training program. The program consists of formal classroom instruction and hands-on demonstrations in the following categories: Basic AIath and Science Review, Radiation Safety Calculations and Decontamination, Ratiioactive Waste Disposal and 31aterials Transfer, Dosimetry and Radiation Effects, Radiation Detection Instrument Theory and Operation, and Air 31onitoring and Bioassay. Training in these areas is offered through the Health Physics group as needed by 31URR personnel. The training material is also available as a document for individual study. IX-8
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